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Official Transcript of Proceedings
NUCLEAR REGULATORY COMMISSION
Title 10 CFR 2206 Petition Review Board RE BraidwoodByron
Docket Number (na)
Location teleconference
Date Wednesday May 162012
Work Order No NRC-1624 Pages 1-31
IORIGINALI
NEAL R GROSS AND CO INC Court Reporters and Transcribers 1323 Rhode Island Avenue NW _ Washington DC 20005w)
(202) 234-4433
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UNITED STATES OF AMERICA
NUCLEAR REGULATORY COMMISSION
+ + + + +
10 CFR 2206 PETITION REVIEW BOARD (PRB)
CONFERENCE CALL
RE
BRAIDWOODBYRON
+ + + + +
WEDNESDAY
MAY 16 1 2012
+ + + + +
The conference call was held Bill
Ruland Chairman of the Petition Review Board
l
ll
presiding
PETITIONER BARRY QUIGLEY
PETITION REVIEW BOARD MEMBERS
BILL RULAND I PRB Chairman and Director
NRRDSS
JOEL S WIEBE Petition Manager for 2206
Petition
LEE BANIC I PRB Coordinator NRRDPR
ERIC DUNCAN Region 1111 Branch Chief
Division of Reactor Projects
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ED SMITH NRRDSS Balance of Plant Branch
PREM SAHAY NRRDE ectrical Engineering
Branch
AHSAN SALLMAN NRRDSS Containment and
Ventilation Branch
ALEXANDER TSIRIGOTIS NRRDE Mechanical and
Structural Engineering Branch
NRC HEADQUARTERS STAFF
MICHELLE ALBERT Office of General Counsel
LAUREN CASEY Office of Enforcement
NICOLE COLEMAN Office of Enforcement
KIMYATA MORGAN BUTLER NRRDPRGeneric
Communications Branch
JAKE ZIMMERMAN NRRDORL
NRC REGION III STAFF
BRUCE BARTLETT Senior Resident Inspector
Byron Generating Station
TRAVIS DAUN Resident Inspectors Office
Byron Generating Station
RAYMOND NG Project Engineer
JOHN ROBBINS Resident Inspector Byron
Generating Station
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JAMIE BENJAMIN Senior Resident Inspector
Braidwood Generating Station
ALEX GARMOE Resident Inspector Braidwood
Generating Station
ALSO PRESENT
TOM COLE Braidwood Generating Station
Engineering Staff
DAN ENRIGHT Braidwood Generating Station
Site Vice President
AMY FERKO Braidwood Generating Station Site
Engineering Director
MARK KANAVOS Braidwood Generating Station
ant Manager
CHRIS VANDENBURGH Braidwood Generat
Station Regulatory Assurance Manager
DAVE GUDGER Byron Generating Station
Regulatory Assurance Manager
TRACY HULBERT Byron Generating Station
Regulatory Assurance
CHUCK KELLER Byron Generating Station Acting
Design Manager
DAVE GULLOTT Exelon Corporate censing
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MIKE
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(202) 234-4433
PERRY Illinois Management
Agency Resident Inspector for Braidwood
Generating Station
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P-R-O-C-E-E D-I-N G S
(1005 am)
MR WIEBE My name is Joel Wiebe I am
the Braidwood and Byron Stations Project Manager
This is the Petition Review Board
discussion with the Petitioner of the 2206 petition
dated April 20 2012
The Petition Manager for the petition shy
the Petition Review Board Chairman is 11 Ruland
And one thing could I ask the ones who
arent talking to go on mute and then go off mute
when you want to say something
As part of the Petition Review Boards
review of this petition the Petitioner Barry
Quigley has requested this opportunity to address the
PRB The meeting is scheduled from 1000 to 1100
Eastern Time The meeting is being recorded by the
NRC Operations Center and is also being transcribed by
a Court Reporter
The transcript itself will become a
supplement to the petition and the transcript will be
made publicly available
I would like to open this meeting with
introductions and we will go around the room in
headquarters first I would 1 ike to ask you to
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clearly state your name your posi tion and the office
you work for within the NRC
I will start off My name again is Joel
Wiebe I am a Project Manager with NRR
MR SALLMAN My name is Sallman I work
with the Containment - my position is Reactor Systems
Engineer and I work for the Division of Safety
Systems in the Containment and Ventilation Branch
MS BUTLER Kimyata Morgan Butler in the
Division of Policy and Rulemaking in NRR Im the
Acting Branch Chief of the Generic Communications
Branch
MS COLEMAN Im Nicole Coleman an
Enforcement Specialist in the Office of Enforcement
MS CASEY Im Lauren Casey an
Enforcement Specialist in the Office of Enforcement
MR SAHAY 11m Prem Sahay P-R-E-M S-Ashy
H-A-Y Im an Electrical Engineer work for NRR
Electrical Engineering Branch
MR TSIRIGOTIS Alexander Tsirigotis
Division of Engineering l Mechanical and Structural
Engineering Branch
MR DUNCAN And in Region III my name is
Eric Duncan I am the Branch Chief for Branch III BRP
for Byron and Braidwood And also Raymond Ng is
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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UNITED STATES OF AMERICA
NUCLEAR REGULATORY COMMISSION
+ + + + +
10 CFR 2206 PETITION REVIEW BOARD (PRB)
CONFERENCE CALL
RE
BRAIDWOODBYRON
+ + + + +
WEDNESDAY
MAY 16 1 2012
+ + + + +
The conference call was held Bill
Ruland Chairman of the Petition Review Board
l
ll
presiding
PETITIONER BARRY QUIGLEY
PETITION REVIEW BOARD MEMBERS
BILL RULAND I PRB Chairman and Director
NRRDSS
JOEL S WIEBE Petition Manager for 2206
Petition
LEE BANIC I PRB Coordinator NRRDPR
ERIC DUNCAN Region 1111 Branch Chief
Division of Reactor Projects
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ED SMITH NRRDSS Balance of Plant Branch
PREM SAHAY NRRDE ectrical Engineering
Branch
AHSAN SALLMAN NRRDSS Containment and
Ventilation Branch
ALEXANDER TSIRIGOTIS NRRDE Mechanical and
Structural Engineering Branch
NRC HEADQUARTERS STAFF
MICHELLE ALBERT Office of General Counsel
LAUREN CASEY Office of Enforcement
NICOLE COLEMAN Office of Enforcement
KIMYATA MORGAN BUTLER NRRDPRGeneric
Communications Branch
JAKE ZIMMERMAN NRRDORL
NRC REGION III STAFF
BRUCE BARTLETT Senior Resident Inspector
Byron Generating Station
TRAVIS DAUN Resident Inspectors Office
Byron Generating Station
RAYMOND NG Project Engineer
JOHN ROBBINS Resident Inspector Byron
Generating Station
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JAMIE BENJAMIN Senior Resident Inspector
Braidwood Generating Station
ALEX GARMOE Resident Inspector Braidwood
Generating Station
ALSO PRESENT
TOM COLE Braidwood Generating Station
Engineering Staff
DAN ENRIGHT Braidwood Generating Station
Site Vice President
AMY FERKO Braidwood Generating Station Site
Engineering Director
MARK KANAVOS Braidwood Generating Station
ant Manager
CHRIS VANDENBURGH Braidwood Generat
Station Regulatory Assurance Manager
DAVE GUDGER Byron Generating Station
Regulatory Assurance Manager
TRACY HULBERT Byron Generating Station
Regulatory Assurance
CHUCK KELLER Byron Generating Station Acting
Design Manager
DAVE GULLOTT Exelon Corporate censing
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MIKE
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(202) 234-4433
PERRY Illinois Management
Agency Resident Inspector for Braidwood
Generating Station
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P-R-O-C-E-E D-I-N G S
(1005 am)
MR WIEBE My name is Joel Wiebe I am
the Braidwood and Byron Stations Project Manager
This is the Petition Review Board
discussion with the Petitioner of the 2206 petition
dated April 20 2012
The Petition Manager for the petition shy
the Petition Review Board Chairman is 11 Ruland
And one thing could I ask the ones who
arent talking to go on mute and then go off mute
when you want to say something
As part of the Petition Review Boards
review of this petition the Petitioner Barry
Quigley has requested this opportunity to address the
PRB The meeting is scheduled from 1000 to 1100
Eastern Time The meeting is being recorded by the
NRC Operations Center and is also being transcribed by
a Court Reporter
The transcript itself will become a
supplement to the petition and the transcript will be
made publicly available
I would like to open this meeting with
introductions and we will go around the room in
headquarters first I would 1 ike to ask you to
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clearly state your name your posi tion and the office
you work for within the NRC
I will start off My name again is Joel
Wiebe I am a Project Manager with NRR
MR SALLMAN My name is Sallman I work
with the Containment - my position is Reactor Systems
Engineer and I work for the Division of Safety
Systems in the Containment and Ventilation Branch
MS BUTLER Kimyata Morgan Butler in the
Division of Policy and Rulemaking in NRR Im the
Acting Branch Chief of the Generic Communications
Branch
MS COLEMAN Im Nicole Coleman an
Enforcement Specialist in the Office of Enforcement
MS CASEY Im Lauren Casey an
Enforcement Specialist in the Office of Enforcement
MR SAHAY 11m Prem Sahay P-R-E-M S-Ashy
H-A-Y Im an Electrical Engineer work for NRR
Electrical Engineering Branch
MR TSIRIGOTIS Alexander Tsirigotis
Division of Engineering l Mechanical and Structural
Engineering Branch
MR DUNCAN And in Region III my name is
Eric Duncan I am the Branch Chief for Branch III BRP
for Byron and Braidwood And also Raymond Ng is
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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ED SMITH NRRDSS Balance of Plant Branch
PREM SAHAY NRRDE ectrical Engineering
Branch
AHSAN SALLMAN NRRDSS Containment and
Ventilation Branch
ALEXANDER TSIRIGOTIS NRRDE Mechanical and
Structural Engineering Branch
NRC HEADQUARTERS STAFF
MICHELLE ALBERT Office of General Counsel
LAUREN CASEY Office of Enforcement
NICOLE COLEMAN Office of Enforcement
KIMYATA MORGAN BUTLER NRRDPRGeneric
Communications Branch
JAKE ZIMMERMAN NRRDORL
NRC REGION III STAFF
BRUCE BARTLETT Senior Resident Inspector
Byron Generating Station
TRAVIS DAUN Resident Inspectors Office
Byron Generating Station
RAYMOND NG Project Engineer
JOHN ROBBINS Resident Inspector Byron
Generating Station
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JAMIE BENJAMIN Senior Resident Inspector
Braidwood Generating Station
ALEX GARMOE Resident Inspector Braidwood
Generating Station
ALSO PRESENT
TOM COLE Braidwood Generating Station
Engineering Staff
DAN ENRIGHT Braidwood Generating Station
Site Vice President
AMY FERKO Braidwood Generating Station Site
Engineering Director
MARK KANAVOS Braidwood Generating Station
ant Manager
CHRIS VANDENBURGH Braidwood Generat
Station Regulatory Assurance Manager
DAVE GUDGER Byron Generating Station
Regulatory Assurance Manager
TRACY HULBERT Byron Generating Station
Regulatory Assurance
CHUCK KELLER Byron Generating Station Acting
Design Manager
DAVE GULLOTT Exelon Corporate censing
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(202) 234-4433
PERRY Illinois Management
Agency Resident Inspector for Braidwood
Generating Station
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P-R-O-C-E-E D-I-N G S
(1005 am)
MR WIEBE My name is Joel Wiebe I am
the Braidwood and Byron Stations Project Manager
This is the Petition Review Board
discussion with the Petitioner of the 2206 petition
dated April 20 2012
The Petition Manager for the petition shy
the Petition Review Board Chairman is 11 Ruland
And one thing could I ask the ones who
arent talking to go on mute and then go off mute
when you want to say something
As part of the Petition Review Boards
review of this petition the Petitioner Barry
Quigley has requested this opportunity to address the
PRB The meeting is scheduled from 1000 to 1100
Eastern Time The meeting is being recorded by the
NRC Operations Center and is also being transcribed by
a Court Reporter
The transcript itself will become a
supplement to the petition and the transcript will be
made publicly available
I would like to open this meeting with
introductions and we will go around the room in
headquarters first I would 1 ike to ask you to
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clearly state your name your posi tion and the office
you work for within the NRC
I will start off My name again is Joel
Wiebe I am a Project Manager with NRR
MR SALLMAN My name is Sallman I work
with the Containment - my position is Reactor Systems
Engineer and I work for the Division of Safety
Systems in the Containment and Ventilation Branch
MS BUTLER Kimyata Morgan Butler in the
Division of Policy and Rulemaking in NRR Im the
Acting Branch Chief of the Generic Communications
Branch
MS COLEMAN Im Nicole Coleman an
Enforcement Specialist in the Office of Enforcement
MS CASEY Im Lauren Casey an
Enforcement Specialist in the Office of Enforcement
MR SAHAY 11m Prem Sahay P-R-E-M S-Ashy
H-A-Y Im an Electrical Engineer work for NRR
Electrical Engineering Branch
MR TSIRIGOTIS Alexander Tsirigotis
Division of Engineering l Mechanical and Structural
Engineering Branch
MR DUNCAN And in Region III my name is
Eric Duncan I am the Branch Chief for Branch III BRP
for Byron and Braidwood And also Raymond Ng is
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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JAMIE BENJAMIN Senior Resident Inspector
Braidwood Generating Station
ALEX GARMOE Resident Inspector Braidwood
Generating Station
ALSO PRESENT
TOM COLE Braidwood Generating Station
Engineering Staff
DAN ENRIGHT Braidwood Generating Station
Site Vice President
AMY FERKO Braidwood Generating Station Site
Engineering Director
MARK KANAVOS Braidwood Generating Station
ant Manager
CHRIS VANDENBURGH Braidwood Generat
Station Regulatory Assurance Manager
DAVE GUDGER Byron Generating Station
Regulatory Assurance Manager
TRACY HULBERT Byron Generating Station
Regulatory Assurance
CHUCK KELLER Byron Generating Station Acting
Design Manager
DAVE GULLOTT Exelon Corporate censing
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MIKE
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(202) 234-4433
PERRY Illinois Management
Agency Resident Inspector for Braidwood
Generating Station
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P-R-O-C-E-E D-I-N G S
(1005 am)
MR WIEBE My name is Joel Wiebe I am
the Braidwood and Byron Stations Project Manager
This is the Petition Review Board
discussion with the Petitioner of the 2206 petition
dated April 20 2012
The Petition Manager for the petition shy
the Petition Review Board Chairman is 11 Ruland
And one thing could I ask the ones who
arent talking to go on mute and then go off mute
when you want to say something
As part of the Petition Review Boards
review of this petition the Petitioner Barry
Quigley has requested this opportunity to address the
PRB The meeting is scheduled from 1000 to 1100
Eastern Time The meeting is being recorded by the
NRC Operations Center and is also being transcribed by
a Court Reporter
The transcript itself will become a
supplement to the petition and the transcript will be
made publicly available
I would like to open this meeting with
introductions and we will go around the room in
headquarters first I would 1 ike to ask you to
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clearly state your name your posi tion and the office
you work for within the NRC
I will start off My name again is Joel
Wiebe I am a Project Manager with NRR
MR SALLMAN My name is Sallman I work
with the Containment - my position is Reactor Systems
Engineer and I work for the Division of Safety
Systems in the Containment and Ventilation Branch
MS BUTLER Kimyata Morgan Butler in the
Division of Policy and Rulemaking in NRR Im the
Acting Branch Chief of the Generic Communications
Branch
MS COLEMAN Im Nicole Coleman an
Enforcement Specialist in the Office of Enforcement
MS CASEY Im Lauren Casey an
Enforcement Specialist in the Office of Enforcement
MR SAHAY 11m Prem Sahay P-R-E-M S-Ashy
H-A-Y Im an Electrical Engineer work for NRR
Electrical Engineering Branch
MR TSIRIGOTIS Alexander Tsirigotis
Division of Engineering l Mechanical and Structural
Engineering Branch
MR DUNCAN And in Region III my name is
Eric Duncan I am the Branch Chief for Branch III BRP
for Byron and Braidwood And also Raymond Ng is
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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MIKE
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(202) 234-4433
PERRY Illinois Management
Agency Resident Inspector for Braidwood
Generating Station
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P-R-O-C-E-E D-I-N G S
(1005 am)
MR WIEBE My name is Joel Wiebe I am
the Braidwood and Byron Stations Project Manager
This is the Petition Review Board
discussion with the Petitioner of the 2206 petition
dated April 20 2012
The Petition Manager for the petition shy
the Petition Review Board Chairman is 11 Ruland
And one thing could I ask the ones who
arent talking to go on mute and then go off mute
when you want to say something
As part of the Petition Review Boards
review of this petition the Petitioner Barry
Quigley has requested this opportunity to address the
PRB The meeting is scheduled from 1000 to 1100
Eastern Time The meeting is being recorded by the
NRC Operations Center and is also being transcribed by
a Court Reporter
The transcript itself will become a
supplement to the petition and the transcript will be
made publicly available
I would like to open this meeting with
introductions and we will go around the room in
headquarters first I would 1 ike to ask you to
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clearly state your name your posi tion and the office
you work for within the NRC
I will start off My name again is Joel
Wiebe I am a Project Manager with NRR
MR SALLMAN My name is Sallman I work
with the Containment - my position is Reactor Systems
Engineer and I work for the Division of Safety
Systems in the Containment and Ventilation Branch
MS BUTLER Kimyata Morgan Butler in the
Division of Policy and Rulemaking in NRR Im the
Acting Branch Chief of the Generic Communications
Branch
MS COLEMAN Im Nicole Coleman an
Enforcement Specialist in the Office of Enforcement
MS CASEY Im Lauren Casey an
Enforcement Specialist in the Office of Enforcement
MR SAHAY 11m Prem Sahay P-R-E-M S-Ashy
H-A-Y Im an Electrical Engineer work for NRR
Electrical Engineering Branch
MR TSIRIGOTIS Alexander Tsirigotis
Division of Engineering l Mechanical and Structural
Engineering Branch
MR DUNCAN And in Region III my name is
Eric Duncan I am the Branch Chief for Branch III BRP
for Byron and Braidwood And also Raymond Ng is
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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P-R-O-C-E-E D-I-N G S
(1005 am)
MR WIEBE My name is Joel Wiebe I am
the Braidwood and Byron Stations Project Manager
This is the Petition Review Board
discussion with the Petitioner of the 2206 petition
dated April 20 2012
The Petition Manager for the petition shy
the Petition Review Board Chairman is 11 Ruland
And one thing could I ask the ones who
arent talking to go on mute and then go off mute
when you want to say something
As part of the Petition Review Boards
review of this petition the Petitioner Barry
Quigley has requested this opportunity to address the
PRB The meeting is scheduled from 1000 to 1100
Eastern Time The meeting is being recorded by the
NRC Operations Center and is also being transcribed by
a Court Reporter
The transcript itself will become a
supplement to the petition and the transcript will be
made publicly available
I would like to open this meeting with
introductions and we will go around the room in
headquarters first I would 1 ike to ask you to
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clearly state your name your posi tion and the office
you work for within the NRC
I will start off My name again is Joel
Wiebe I am a Project Manager with NRR
MR SALLMAN My name is Sallman I work
with the Containment - my position is Reactor Systems
Engineer and I work for the Division of Safety
Systems in the Containment and Ventilation Branch
MS BUTLER Kimyata Morgan Butler in the
Division of Policy and Rulemaking in NRR Im the
Acting Branch Chief of the Generic Communications
Branch
MS COLEMAN Im Nicole Coleman an
Enforcement Specialist in the Office of Enforcement
MS CASEY Im Lauren Casey an
Enforcement Specialist in the Office of Enforcement
MR SAHAY 11m Prem Sahay P-R-E-M S-Ashy
H-A-Y Im an Electrical Engineer work for NRR
Electrical Engineering Branch
MR TSIRIGOTIS Alexander Tsirigotis
Division of Engineering l Mechanical and Structural
Engineering Branch
MR DUNCAN And in Region III my name is
Eric Duncan I am the Branch Chief for Branch III BRP
for Byron and Braidwood And also Raymond Ng is
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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18
this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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clearly state your name your posi tion and the office
you work for within the NRC
I will start off My name again is Joel
Wiebe I am a Project Manager with NRR
MR SALLMAN My name is Sallman I work
with the Containment - my position is Reactor Systems
Engineer and I work for the Division of Safety
Systems in the Containment and Ventilation Branch
MS BUTLER Kimyata Morgan Butler in the
Division of Policy and Rulemaking in NRR Im the
Acting Branch Chief of the Generic Communications
Branch
MS COLEMAN Im Nicole Coleman an
Enforcement Specialist in the Office of Enforcement
MS CASEY Im Lauren Casey an
Enforcement Specialist in the Office of Enforcement
MR SAHAY 11m Prem Sahay P-R-E-M S-Ashy
H-A-Y Im an Electrical Engineer work for NRR
Electrical Engineering Branch
MR TSIRIGOTIS Alexander Tsirigotis
Division of Engineering l Mechanical and Structural
Engineering Branch
MR DUNCAN And in Region III my name is
Eric Duncan I am the Branch Chief for Branch III BRP
for Byron and Braidwood And also Raymond Ng is
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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here and he is the Project Engineer for Branch III
MR BARTLETT This is Byron Resident
fice Weve got Bruce Bartlett Im the Senior
Resident Weve got John Robbins he is the Resident
And we have Travis Daun
MR BENJAMIN At the Braidwood resident
inspector office we have Jamie Benjamin the Senior
Residenti Alex Garmoe the Resident Inspector and we
also have Mike Perry with the Illinois Emergency
Management Agency He is the Resident Inspector of
Braidwood
MR SMITH Here at headquarters this is
Ed Smith DSS Balance of plant Branch
MR ZIMMERMAN Jake Zimmerman Branch
Chief Division of Operating Reactor Licensing
MS ALBERT Michelle Albert At torney in
the Office of General Counsel
MS BANIC Lee Banic 2206 Petition
Coordinator NRR
MR RULAND 11 Ruland Director of the
Division of Safety Systems in NRR and the PRB Chair
MR WIEBE Okay That completes the
introductions at NRC headquarters and the other NRC
participants Is there any other NRC participants
that have not introduced themselves
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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(No response)
Okay Are there any representatives from
the licensee on the phone
MR ENRIGHT Yes This is Dan Enright at
Braidwood Station Im the site Vice President With
me are Mark Kanavos Plant Manager i Chris Vandenburgh
Regulatory Assurance Manager i Amy Ferko Site
Engineering rectorj and Tom Cole of our engineering
organization
MR GUDGER This is Dave Gudger at the
Byron Nuclear Station Im the Regulatory Assurance
Manager I have with me Chuck Keller Acting Design
Manager and Tracy Hulbert Regulatory Assurance
MR GULLOTT This is Dave Gullott Exelon
Corporate Licensing
MR WIEBE Okay Mr Quigley would you
introduce yourself for the record
MR QUI GLEY Yes My name is Barry
Quigley Q U-I G-L-E Y
MR WIEBE Okay Thanks It is not
required for members of the public who may be on the
phone to introduce themselves for the call However
if there are any members of the public on the phone
who do wish to introduce themselves please do so at
this time
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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(No response)
Okay Hearing none t I would like to
emphasize that we each need to speak clearly and
loudly to make sure the Court Reporter can hear you
and accurat y transcribe the meeting Also t first
state your name before you say something That way
the Court Reporter knows who to attribute the comment
to
For those who are dialing into the
meeting please remember to mute your phones tot
minimize the background noise If you do not have a
mute button t you can mute by pressing the keys star
and then six To unmute t you can press the star six
key again Thanks
At this timet I will turn it over to the
PRB Chairman t Bill Ruland
MR RULAND Thank you t Joel Good
morning Welcome to this meeting regarding the 2206
petition submitted by Mr Quigley
I would like to first share some
background for our process Section 2206 Title X
of the Code Federal Regulations describes the
petition process tithe primary mechanism for the public
to request enforcement action by the NRC II It is a
public process
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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18
this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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This process permits anyone to petition
NRC to take enforcement type action related to NRC
licensees or licensed activities Depending on the
results of this evaluation NRC could modify suspend
or revoke an NRC-issued license or take any other
appropriate enforcement action to resolve a problem
The NRC staffs guidance for the
disposition of a 2206 petition request is in
Management Directive 811 which is publicly
available
The purpose of todays meeting is to give
the Petitioner an opportunity to provide any
additional explanation or support for the petition
before the Petition Review Boards initial
consideration and recommendation This meeting is not
a hearing nor is it an opportunity for the Petitioner
to question or examine the PRB on the merits of the
issues presented in the petition request
No decisions regarding the merits of this
petition will be made at this meeting Following this
meeting the Petition Review Board will conduct its
internal deliberations The outcome of this internal
meeting will be discussed with the Petitioner
subsequently
The Petition Review Board typically
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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consists of a Chairman l usually a manager at the
senior executive level at the NRC It has a Petition
Manager and a PRB Coordinator I who already have
introduced themselves Other members of the Board are
determined by the NRC staff based on the content of
the information in the petition request
First l I would like to introduce the
Board Of course I myself I Bill Ruland l I am the
Peti tion Review Board Chairman Joel Wiebe I who is
who gave us the introduction l is the Petition Manager
the petition under discussion today Lee Banic is
the fices PRB Coordinator
Our technical staff includes l but is not
limited tOI Ed Smith who is in the Balance of ant
Branch in the Division of Safety Systems in NRRi Prem
Sahay who is in the Division of Engineering in
Electrical Engineering Branch exander Tsirigotis
who is in theDivision Engineering Mechanical and
Civil Engineering Branch Ahsan Sallman who is in the
Containment and ventilation Branch in NRR and Eric
Duncan who is a Branch Chief in Region III in the
Division of Reactor Projects
We also obtained advice from the Office of
General Counsel represented by Michelle Alberti and
the Office of Enforcement I represented by Nicole
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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12
Coleman
As described in our process the NRC staff
may ask clarifying questions to better understand the
Peti tioner s presentation and to reach a reasoned
decision whether to accept or reject the Petitioners
request for review under the 2206 process
Now I would like to summarize the scope
of the petition under consideration and the NRCs
activities to date On April 20 2012 Mr Quigley
submitted to the NRC a petition under 2206 regarding
Braidwood Units 1 and 2 and Byron Units 1 and 2
In this petition Mr Quigley identified
the following areas of concern He requested that the
NRC require Braidwood Uni ts 1 and 2 and Byron Uni ts 1
and 2 to be immediately shut down until all turbine
building high energy line break concerns are
identified and those important to safety are
corrected
As the basis for this request Mr Quigley
states that the physical layout of the Byron and
Braidwood plants exposed both trains of emergency
electric power generation alternating current
distribution ESF batteries and a direct current -shy
and direct current distribution to the effects of non-
safety-related piping failures
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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Mr Quigley states that the design flaw
was missed during initial licensing and the potential
to disable mul tiple trains of safety related equipment
was first identified in 1991 He states that some
analysis was performed but work stopped short
of a comprehensive review of the HELB or high-energy
line break regulatory requirements
Mr Quigley identified the following major
issues One the emergency diesel generators are
affected by H-E L-B - Ill use those initi s from
now on or HELB because steam can enter the
emergency diesel generator rooms the emergency diesel
generator room ventilation and the emergency diesel
generator air intakes
Engineered safety features or ESF
switchgear rooms - this is the second item - are
af ed because of the potential of high temperature
to alter protective relay set points
Three the current method of analysis for
turbine building HELB uses a lumped volume approach
which substantially reduces energy effects and does
not always give conservative results Preliminary
assessment using GOTHIC subdivided volume features
shows structural limits substantially exceeded on the
block wall between the ESF switchgear rooms
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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18
this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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Four there has been no structured and
detailed review of the licensing requirements
regarding impacts on equipment operability for turbine
building high energy line break or HELB
Next I will discuss NRC activi ties to
date On April 26 2012 the Petition Manager
contacted the Petitioner to discuss the 10 CFR 2206
process and to offer him an opportunity to address the
PRB by phone or in person The Petitioner requested
to address the PRB by phone prior to its internal
meeting to make the initial recommendation to accept
or reject the petition for review
On May 4th also of this year the PRB met
internally to discuss the request for immediate
action The PRB denied the request for immediate
action of shutdown - excuse me The PRB denied the
request for immediate shutdown of the fected plants
because the licensee had completed an operability
determination finding the equipment was operable but
degraded
Instead based on the potential hazardous
conditions presented in the petition we determined
that a 10 CFR Section 2204 demand for information
would be initiated for the purposes of determining
whether an order under 2202 should be issued or
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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whether other action should be taken
The PRB may stop or continue the
processing of the Section 2204 demand for information
based on further internal meetings accordance with
the 2206 process
On May 14 2012 the Petitioner was
informed of the PRBs decision to deny the request for
immediate action
As a reminder for the phone participants
please identify yourself if you make any remarks as
this will help us in the preparation of the meeting
transcript that will be made publicly available
Thank you
Mr Quigley I will ask you now to provide
any information that you believe the PRB should
consider as part of its petition Mr Quigley
MR QUIGLEY Thank you I will be
pausing as I go through to allow for questions first
talking a little bit about the physical layout At
Byron and Braidwood the turbine building shares a
wall with the safety-related aux building The diesel
generators and ectrical equipment rooms are located
the aux building but they have ventilation and
personal access openings in a shared wall with the
turbine building
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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The ventilation for these areas is
relatively simple consisting of using fans to blow
outside air through areas Al though the source of
the air is a safety-related intake air shaft the
exhaust openings are simply holes in the turbine
building wall
As far as the history of HELB the NRC
asked several questions related to HELB outside
containment during initial licensing Additional
analyses were done but nei ther the NRC or
Commonwealth Edison noticed the large openings
approximately five foot by five foot between the
turbine building and the dies generator and
switchgear rooms
In 1991 the NRC partially noted the
potential for a turbine building HELB to effect the
diesel generator switchgear and diesel generator
However the NRC only allowed Commonwealth Edison 90
days to reply Therefore the analysis done was
limited
Basical the analysis took credit for
fire dampers in the turbine building exhaust openings
to drop and isolate the areas from the fects of the
high energy line break Credit was also taken
turbine building siding to blow off and relieve the
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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pressure In the turbine building
Additional work was done in 1996 related
to piping break locations Stress calculations were
done to eliminate some locations In 2011 it was
noted that the assumed fire damper drop time was
substantially in error An operability evaluation was
completed which showed acceptable temperatures based
on more thermal hydraulic analyses that were done
I note that Mr Ruland stated that the
immediate request was denied in part on the presence
of the op eval I did not have that information prior
to today BasicallYt I wrote the op eval The only
thing that the Byron op eval addresses is fire dampers
taking too long to drop
MR RULAND Mr Quigley Ive got a
question for you
MR QUIGLEY Certainly
MR RULAND Since you wrote the original
operabilityevaluation t and apparently determined that
the equipment was operable but degraded what has
changed from the time you wrote and signed off on that
operability evaluation and the present time
MR QUIGLEY The operability evaluation
only dealt with the fact that the fire dampers take
too long to drop Thats all it deals with I had
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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this information at the time but I could not show
operabil
MR RULAND So you didnt include this
other information in the op eval nor did you write a
non-conformance or a condition report whatever you
call it at those stations at that time
MR QUIGLEY I made my management aware
of - - my engineering management aware of the technical
concerns I had
MR RULAND Okay Thanks
MR QUIGLEY Yep Talk a little more of
the history and a little bit more the structural
layout So the basic high energy line break concern
is that we have a non-safety-related steam or feedline
rupture in the turbine building pressurized within
the turbine building And since these diesel rooms
and switchgear rooms are connected the adverse
environment for the turbine building can propagate
into the safety-related areas
So we had recognized that at some point
However as I looked at it more detail thats
where these additional issues under the basis
request come from
Well the first one I want to t k about
is the combustion air for the diesel generator As I
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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said the ventilation for this system is relativelyl
simple For temperature control I it relies on a
recirculation mode BasicallYI when it is hot air
outside or hot in the diesel room l it draws air in
through the intake sha through a fan l and out
through a hole in the turbine building wall
If the temperatures are cooler there is
a recirculation damper that opens up And what that
recirculation damper does is allows the fan to
basically isolate the outside air path and just
recirculate air through the room It is that
recirculation path that is of concern for combustion
air
When the turbine building pressuri zes and
then the pressure comes in and steam comes into the
diesel generator room l the damper configuration can be
such that steam flows back into the intake air shaft
The diesel generator combustion air supply is located
approximately eight feet from that point So the
concern would be that the diesel l when it is either
trying to start or already running l could draw in some
steam that is coming through this other path
Now that is very difficult to visualize
perhaps So if there is any questions on how that is
laid out I will take them right now
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
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CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
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(No response)
Okay Hearing none I will move on So
potentially instead of having 100 percent air the
diesel generator could be trying to run or start on a
steam air mixture And we have not undertaken to find
out the capability of the engine to do so nor have we
undertaken to find out how much steam will actually
get to that location
Also as I was thinking further about
this the turbocharger on the diesel engine could also
be at risk because now we have a pressurized air
intake if you will So that could raise concerns
with the ability of the turbocharger to carry that
additional bus load
The next item I had was that the effects
of high temperature in the switchgear rooms on the
protected relay has not been evaluated
We did look at motor control centers
However the four kv switchgear was not rigorously
looked at So the concern would be that the
temperature effects could cause the relays to fail to
actuate when desired or the relays could actuate
earlier than desired
We have not fully considered the
environment in the switchgear room including the
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
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ssurization effects These reI have glass
covers on them If the pres zation breaks the
glass it follows the relay We not considered
any of that
The next item is reI to the modeling
The way that a high energy I break outside
containment has been modeled the past both at
Byron and other utilities is wi a lumped volume
approach I paused when I d because there is
no NRC approved methodology for culating pressures
and temperatures for HELBs fsite containment
So as I was looking at the lumped volume
approach I created a side model if you will and
started looking at the effects of subdivided volumes
where the area is divided up 0 a much finer mesh
When I did that I got results were contrary to
those in the model currently progress
What I was focusing on was the switchgear
rooms Our switchgear rooms Alpha and Bravo
Divisions -- are located adjacent to each other and
are separated by a block wall on in the HELB
reconstitution we noted that block wall had very
little margin in it and there were concerns that we
could exceed the structural limits on the wall
We resolved that in the rna part of the
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
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1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
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proj ect separately However when I looked at it
under a subdivided approach we would exceed the
structural capability on that wall by about a factor
of three So the subdivided approach yields more
accurate results and unacceptable results
MR RULAND Just hold on a second Mr
Quigley
MR QUIGLEY Yep
MR SALLMAN This is Ahsan Sallman from
the Containment and Ventilation Branch I understand
that you did a subdivided approach Could you explain
more about this How many divisions for the lumped
model and what was the outcome of that
MR QUIGLEY For the model that Exelon is
currently working on the 426 elevation is about 13
million cubic feet I divided that up into six
smaller lumped volumes and then the area in front of
the switchgear rooms is approximately 110 feet by 45
feet I divided that up into about 800 sub-volumes
And then I also modeled the switchgear rooms as
subdivided volumes with connections into the turbine
building
So what I saw there was if I put a break
outside of that subdivided volume as the pressure -shy
as the whole model pressurizes the pressure moves
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234middot4433 WASHINGTON DC 20005middot3701 wwwnealrgrosscom
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW (202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
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into the subdivided volume I and it reaches one of the
switchgear rooms before it reaches the other and thenI
it starts to pressurize that room
And then l several milliseconds later l the
other room starts to pressurize And then l after a
period of timel the pressures in the rooms
switchgear rooms stabilized And then I when the
turbine building siding blows off I and the model
depressurizes l the rooms do not depressurize at the
same rate
SOl againl there is depressurization of
the building We get another excessive differential
pressure across the switchgear room wall
MR SALLMAN You said there were six
smaller lumped volumes for - which building was that
MR QUIGLEY For the 426 elevation of the
turbine building
MR BARTLETT HeYI BarrYI this is Bruce
Bartlett
MR QUIGLEY Yes
MR BARTLETT Wouldnt that so work if
the dampers in one of the switchgear rooms worked and
the dampers in the other swi tchgear room had your
single failure and didnt work You can generate a
differential pressure across the wall that way also
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234middot4433 WASHINGTON DC 20005middot3701 wwwnealrgrosscom
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
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MR QUIGLEY Yes With that -- those
other dampers that we are considering putting in
MR BARTLETT Thank you
MR QUIGLEY Right That is one of the
problems that we are trying to work through on the
dampers were putting in The scenario that I am
talking about right now exists today independent
any damper installation
Now again this is the first thing I
looked at with the subdivided model So I would
anticipate that a further subdivided model would
uncover further non-conservatisms I have looked at
this particular one enough to be confident that
modeling-wise there is not a whole lot that can be
done to make it better
Were there any other questions on the
modeling aspects
MR BARTLETT No not from here from
headquarters
MR QUIGLEY Thank you
MR RULAND Mr Quigley why dont we
because I you know we - I would like to see if we
can finish this meeting today on time And if we need
further time we will have to just reschedule and have
another phone call
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234middot4433 WASHINGTON DC 20005middot3701 wwwnealrgrosscom
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW (202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
5
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But so why dont you just kind of go
through your entire list right now and then we will
come back and ask questions How does that sound
MR QUIGLEY Well thats fine But Ive
only got one more item on the list
MR RULAND Oh Then I guess thats
easy
MR QUIGLEY Right The next one is that
there has been no structured and detailed review of
the licensing requirements for HELB As I said
earlier HELB got missed during initial licensing
When the issue was identified by the NRC
in 1991 the company responded The NRCs followup
inspection was not a licensing type of review It
just looked at the response and accepted the response
So in 1991 we had a chance and didnt get there
In 96 it was looked at a little bit
further but only for piping stresses In 2001 we
looked at the HELB issue again and that is when we
found out that the fire damper assumption the fire
damper drop time assumption was in error
We did a lot of work but we have still
not done a structured review of HELB We have not
picked up the standard review plan gone through it
line by line and found all of the problems
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW (202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
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MR RULAND Mr Quigl could you
would it be possible since it might help us expedite
our actions on this to provide those references You
talked about 91 and shy
MR QUIGLEY Yes
MR RULAND 96 and you know
several inspection reports I f you could provide
those references to us it would be helpful
MR QUIGLEY I can do that
MR RULAND And he would provide them
through to you Joel
MR WIEBE Yes right
MR RULAND Okay Okay Continue
MR QUIGLEY I would also note that the
licensee has entered the items of my petition into the
corrective action process So basically the four
bullets of the petition were entered into CAP
I would note that the rationale for
acceptability is weak and at times I that the
rationale is dismissive In particular when it talks
about the GOTHIC analysis it refers to the work I
have done as preliminary informal which is true but
Exelon is making no effort to resolve it So I feel
that by saying it is informal it is preliminary that
is dismiss
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW (202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
5
10
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27
1
2
3
4
6
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8
9
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24
Also the IR alludes to a HELB resolution
team and a HELB resolution effort I dont see that
What I see is an organization trying to resolve the
minimum amount of possible with high energy line
break so that we can get our MUR approval
So does anybody have any followup
questions before I conclude
MR RULAND Hold on a second Ive just
got a question for the - - youre the Petition Manager
right Joel Could you tell us what the status of
those MUR approvals are
MR WIEBE We are in the latter stages of
our review We have about three safety evaluation
inputs left from the tech staff
MR RULAND Okay And they have been inshy
house about - what about a year or so or
MR WIEBE For the application
MR RULAND Yes
MR WIEBE Yes the year is up in June
MR RULAND Okay I just wanted to get
a perspective on where they were Hold on a second
Im going to go on mute for a minute
(Pause)
Yes We were just trying to understand
how this fit into MUR issue and you know at this
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW (202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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25
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point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
10
15
20
25
29
1
2
3
4
6
7
8
9
11
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14
16
17
18
19
21
22
23
24
to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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8
9
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21
22
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24
question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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31
1
2
3
4
6
7
8
9
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
5
10
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25
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28
point it is uncertain But we understand your point
MR QUIGLEY Thank you
MR RULAND So any more questions for Mr
Quigley from this room
(No response)
We have no more questions
Any other NRC participants
MR QUIGLEY Well I wasnt quite done
yet
MR RULAND Oh Im sorry Go ahead
MR QUIGLEY Thats fine I have been
involved with the turbine building HELB analysis for
22 years now I have struggled to get Exelon to
resolve it I have not been successful
I performed the operability evaluation
last year in the hope that that would move us along
I focused the op eval solely on the fire damper delay
times Then when I was challenged by management to
add additional information I told them that I
couldnt because I didnt know that it would support
operability
Based on what I know now -- I was an SRO
for 15 years I have been involved in this analysis
for 21 years I I have been doing operability
evaluations for eight years - I see no rational basis
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
10
15
20
25
29
1
2
3
4
6
7
8
9
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14
16
17
18
19
21
22
23
24
to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
10
15
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30
1
2
3
4
6
7
8
9
11
12
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18
19
21
22
23
24
question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
10
15
20
25
31
1
2
3
4
6
7
8
9
11
12
13
14
16
17
18
19
21
22
23
24
participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
5
10
15
20
25
29
1
2
3
4
6
7
8
9
11
12
13
14
16
17
18
19
21
22
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24
to conclude that the diesel generators and the ESF
switchgear rooms are operable
That concludes my remarks
MR RULAND Thank you Mr Quigl Now
let me ask again is there any other questions in the
room here
(No response)
Any other NRC participants have a
question
(No response)
Does the licensee have any questions
(No response)
Hearing none did we ever establish
whether or not there was a member of the public
listening in
MR WIEBE No No member of the public
spoke up
MR RULAND Spoke up So I will just
assume that there was and I will are there -shy
before I conclude this meeting members of the public
may provide comments regarding the petition and ask
questions about the 2206 process
However as stated in the opening the
purpose of this meeting is not to provide an
opportunity for the Petitioner or the public to
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
10
15
20
25
30
1
2
3
4
6
7
8
9
11
12
13
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16
17
18
19
21
22
23
24
question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
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question or examine the PRB regarding the members
regarding the merits of the petition request
So are there any members of the publ ic
that have a question or comment about the petition
process
(No response)
Having heard none let me just ask a
process question So anything else before we close
the meeting Counsel do we have anything else
(No response)
Okay Mr Quigley I thank you for taking
the time to provide the NRC staff with clarifying
information on the petition you have submitted
Before we close does the Court Reporter
need any additional information the meeting
transcript
THE COURT REPORTER Hello This is the
Court Reporter and I am going to email Mr Wiebe if
that is okay with him to confirm the names of some
the participants
MR WIEBE Yes thats good
THE COURT REPORTER Thank you
MR RULAND Okay With that this
meeting is concluded and we will be terminating the
phone connection Again thank you everyone for
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTON DC 20005-3701 wwwnealrgrosscom
5
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31
1
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7
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participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
5
10
15
20
25
31
1
2
3
4
6
7
8
9
11
12
13
14
16
17
18
19
21
22
23
24
participating
(Whereupon at 1047 a m the
proceedings in the foregoing matter were
conc1uded )
(202) 234-4433
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW WASHINGTON DC 20005-3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom
CERTIFICATE
This is to certify that the attached proceedings
before the United States Nuclear Regul
Commission
Proceeding 10 CFR 2206 Petition of BraidwoodByron by Barry Quigley
Docket Number n a
Location teleconference
were held as herein appears and that this is the
original transcript thereof for the file of the
United States Nuclear Regulatory Commission taken
and thereafter reduced to typewrit under my
direction and that said transcript is a true and
accurate record of the proceedings
Official er Neal R Gross amp Co Inc
NEAL R GROSS COURT REPORTERS AND TRANSCRIBERS
1323 RHODE ISLAND AVE NW
(202) 234-4433 WASHINGTONDC 20005middot3701 wwwnealrgrosscom