36
United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 | 05000286 Exhibit #: Identified: Admitted: Withdrawn: Rejected: Stricken: Other: RIV00053A-00-BD01 10/15/2012 10/15/2012 ... . ... , DSR #./K J. tlOFPAGE$ ANALYTICAL REPOllT " FOI DfDlAN POINT REACTOR. VESSEL - UNIT NO. 3 ... . " Cockrell / Lowry

#./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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Page 1: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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United States Nuclear Regulatory Commission Official Hearing Exhibit

In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 | 05000286 Exhibit #: Identified: Admitted: Withdrawn: Rejected: Stricken:

Other:

RIV00053A-00-BD01 10/15/201210/15/2012

... . ... ,

DSR #./K J. f'~'----I tlOFPAGE$

ANALYTICAL REPOllT "FOI

DfDlAN POINT REACTOR. VESSEL - UNIT NO. 3

... . " Cockrell/

Lowry

Page 2: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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REPORT NUMBER ll22 SUBJECT CATEGO&Y 11ANALYTICAL REPORT"

... -

COMBUSTION ENGINEERING• INC. NUCLEAR COMPONENTS ENGINEERING DEPARTMENT

C.E. CONTRACT NO. 3366

ANALYTICAL REPORT

-FOR

INDIAN POINT REACTOR VESSEL UNIT NO. 3

C. R.. COCKRELL AND J. C. LOWRY

JUNE, 1969

RIV000053A Submitted: December 27, 2011

' ..... :

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REPORT NUMBER 1122 SUBJECT CATEGO&Y "ANALYTICAL REPORT"

... -

COMBUSTION ENGINEERING. INC. NUCLEAR COMPONENTS ENGINEERING DEPARTMENT

C.E. CONTRACT NO. 3366

ANALYTICAL REPORT

- FOR

INDLAN POINT REACTOR VESSEL UNIT NO. 3

c. R. COCKRELL AND J. C. LOWRY

JUNE. 1969

Page 3: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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THIS DOCUMENT IS TilE PROPERTY. OF

COMBUSTION ENGINEERING, INC., WINDSOR, CONN.

AND IS NOT TO BE REPRODUCED, OR USED TO FURNISH ANY IN­

FORMATION FOR MAKING OF DRAWINGS OR APPARATUS EXCEPT

WHERE PROVIDED FOR BY AGREEMENT WITH SAID COMPANY.

RIV000053A Submitted: December 27, 2011

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TH IS DOCUMENT IS nu; PROPERTY OF

COMBUSTION ENGINEERING, INC., WINDSOR t CONN.

AND IS NOT TO BE REPRODUCED, OR USED TO FURNISH ANY tN­

. FORMATION FOR MAKING OF DRAWINGS OR APPARATUS EXCEPT

WHERE PROVIDED FOR BY AGREEMENT WITH SAID COMPANY.

..

Page 4: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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l1W S!t"H~l.ttral itliC~ri..l'V of the 173 in. l.JJ. lndinn Poiut Rt·uctor vcssL•l - Unit: N~. 1 desi.gnc,J and Latn·L:<ILc:d un<lc:r con.t.nt<.·t ro tht· Atomtc .Po\o;t•r Di·:i.::iou or llll' \!t'SlinJ.;h•H.I1'H.' El••ctric Corporation is ('Sttll'li!o\h!..••l hy tlw l'VS\tlU; uf the dt.>tailt•d !ilrtl~·ltW<tl <1lhi tlwnaal. mwl.•sis ''l)tlf.:titwd in Lhis n•p(n·t.

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Page 5: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

TABLE OF . COHTENIS

.......................................... 1

·.':":". · : .-:.. : ~z . 000 IN'rR.Q:DUCTION .•••••••••••• - ................ .- •••. • ... . 4 .. ~ . ... . . . ·:··· .. ·, ..

<:f.;''> ·.· .·~ ::j.':t,·

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2.010 Subject ...•.•••. , ............................. . 4

2. 020 Pu:rpose •• ~ •• ~ ••••••• , ........................ . 4

2.030 Scope ••••••••••••••••••••••••••.••••••.•.. ~. 4

DES lt:N C~ ITER IA •• .;. •••• · ...................... - •.••• 5

GEOMETRY AND GENERAL CONFIGURATION .•••••••••••••.. 6

SUMMARY OF RESULTS •••••••••••••••••••••••••••••••• 7

;.010 Control Rod Housings •.•••••.•.•••••••••.•. 7-8

5.020 Closure Head Flange and Shell ••••.•••••••••. 9

).030 Vf:'ssel Flange and Shell ••••.•••••••••••••••• lO

5. 040 Main Closure studs. • • • • • . • • . • • • • . • • • • • • • . • • . 11

~.0~0 Inlet Nozzle and Vessel Support .••••••••.••. 12

~.060 Outlet Nozzle and Vessel Support •••.•••.••. 13

,.070 Ve~sel Wall Transition ••••••••.•••••••••••• 14

~.080 Core Barrel Support Pads •.••••••••••••••••• 15

5.0q0 Bnttom Head to Shell Juncture •••••••••••.•• 16

I S.lOO 1\otte'm\ Head Instrumentation Penetra.tions ••• 17

·:1 b .000 OISCUSSlON OF RESULTS ANt> HEntOD OF ANALYSIS ••••• 16

6,010 Control Rod Houslngs ••••••••••••••••••••••. 18-20

6.020 Closure Head Flange and Shell ••H•••••••••. 20

thn ttl \''"""''l F'lan~t«.' a.,d Sholl • , • , ·• •• •., •••••••••• 21 .

b .Cll.O Main Closurt.• Studs ••••••••••••••••••••••••• Zl•2l

6.()')0 Inlet Nozzlt' and \'est~el Support •••.•••••••.• 22·23

...

••

••

RIV000053A Submitted: December 27, 2011

TABLE OF' COHTENIS

............................................ 1

"':":" .. :.,:-' : ~2 .000 IN'rRQ:DUCTION .•••.•••••••• _ It •••••••• II • It ......... _ ... . 4 .. ~ ... ". . .: ..... " "

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2.010 Subject ...•.•••. , ...................... . ,_ .... . 4

2.020 Pu:rpose •• ~ •• ~ • " ••••• , ........................ . 4

2.030 Scope ••••••••••••••••••••••••••.••••••.•.. ~. 4

DES IGN C~ ITER IA •• .;. •••• ' ................. « ... ,. • _ ••••• 5

GEOMETRY AND GENERAL CONFIGURATION .•••••••••••••.. 6

SUMMARY OF RESULTS •••••••••••••••••••••••••••••••• 7

;.010 Control Rod Housings •.•••••.•.•••••••••.•. 7-8

5.020 Closure Head Flange and Shell ••••.•••••••••. 9

C).030 V('ssel Flange and Shell ••••.•••••••••••••••• 10

5.040 Ma in Closure Studs...................... . • •. 11

~.o~o Inlet Nozzle and Vessel Support .••••••••.••. 12

~.060 Outlet Nozzle and Velsel Support •••.•••.••. 13

'.010 Ve~sel Wall Tran.ition ••••••••.•••••••••••• 14

~.080 Core Barrel Support Pads •.••••••••••••••••• 15

5.0QO Bottom Head to Shell Juncture •••••••••••.•• 16

1 S.IOO 8ottC'm\ Head Instrumentation Penetl"a,tions ••• 17

':1 b .000 DISCUSSION OF RESULTS ANt> HEntOD OF ANALYSIS ••••• 16

6.010 Control Rod Houslngs •••••••••••••.•.•••.... 18-20

6.020 Closure Head Flange and Shell •• H •••••••••• 20

n.n 'Il "fO ... t-t rlanJ\4.' a.,d shvll •••• ' •••••••••••••••• 21 '

b • ()I. 0 MIl in C}osurt.' Studs .......................... 21"2:l

6.()I)O tnl~t Nozz\(' and \'esfa~l Support ............. 22-23

...

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Page 6: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

;·.·'

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I

TABLE Of CONTENTS (CQnt 1 d~

6.060 Outlet Nozzle and Vessel Support •••••••••• 23-24

6.070 Vessel Wall Transition •••••••••••.••.•••.. 24-2 5

6.080 Core Barrel Support Pads •••••••••••••••.•• 25-.26

6.090 Bottom Head to Shell Juncture ....•...•.••. 26

6.100 BottomHead Instrumentation Penetrations .• 27

7.00ll ••• * .......................................... .. 28-.::9

H.OOU APPENDICES

A. Ot>tnllcc.l Structural Analysis Calculations •••••• Al - A3')''

B. l1u.•rmal .Ann 1 ys is • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • B l ~ 912.4

C. Drawings - Combustion Engineering, Inc .••.••.• Cl - Cl3

RIV000053A Submitted: December 27, 2011

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TAILI QPCOHlENTS "2Dt1d)

6.060 Outlet Nozzle and VesseL Support ........... 23-24

6.070 Vessel Walt Transition ••••••••••••••••••.• 24-:::;

6.080 Core Barrel Support Pads •••••••••••••••.•• 25-.26

6.090 Bottom Head to Shell Juncture •••••..••.••. 26

6.100 Bottom.Head Instrumentatlon Penetratiuns .• 27

. 7.000 •••••••••••• If. ................. III ........ I • ...

siono APPENDICES

A. Ot·taUeu Structural Analysis Calculations •••••• Ai - A3')',

B. nl~rmal Analysis •••••••••••••••••••••••••••••• 81 - 6124

C. Dr.to.rtngs - Combustion Engineering, Inc •••.•••• Cl - C13

Page 7: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

INIKQOOCTIOti

2. 010 Subject

The Indian Point Reaccor Vessel - Unit No. ~ is a 173 in. I.D •. pressu~ized water reactor. Ihe vessel is of cylindrical shape terminating in a hemispherical head at the bottom and a bolted flange at the top. Four inlet and four outlet nozzles are located in the cylindrical wall section. n,e vess~l is supported by four weld built·up pads located on the unde~sidfO of two inlet nozzles and two outlet nozzles. The closure head is of th~ hemlspht.>rlcal type. The closure seal is of the O·r in~ t )!Pl'.

2 • 020 ~.u:pos.r.

This report contains the detailed structure l and ther~l analysis required to substantiate the adequacy of the design of the 173 in. I.D. Indian

.foint Reactor Vessel.

2.0)0 ~~

l'he detaUed analytical 'WOrk necessary to justify the reactor vessel and its associated ~arts included in the contract at"f!' contalned in this report. All equations used are shown and intermediate answers and final ans'Wt>rs au• usually presented in tabular f,.,rm.

4

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RIV000053A Submitted: December 27, 2011

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INIRQDUCT ION

2.010 Subject

2.020

The Indian Point Reaceor Vessel - Unit No. :: is a 173 In. 1.0., pressurized water reactor. The vesael La of cylindrical shape termina~ing in 8 hemispherIcal head at the bottom and a bolted flange at the eop. Four inlet and four outlet nozzles are located in the cylindrical ~a11 section. n,. vess~l is supported by four weld built-up pads located on the under81d~ of two inlet nozzles and two outlet nozzles. The closure head is of tht! hemispherical t~pe. The closure SE?sl is of the O-rinA tYpt'.

furpose

11119 report contains the detailed structural and ther~l analys1s required to substantiate the adequacy of the design of the 173 in. I.D. Indian

,Point Reactor Vesael.

2.0)0 SCQRI

lbe detalled analytical ~rk necessary to justify the reactor vessel and its associated parts included in th~ contract ... e contained 1n this r('port. All ~quatlons used are shown and lnte~edlate answers and final an&'Were are usually presented 1n tabular f,"rm •

4

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Page 8: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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. APPENDIX A

Ul~Ti\ I Ll.m STRUCl'UH.AL ANAL YS lS

TABYE Of CONI;NTS

Coot t·ol H.od Housing Stress Analysis and r'lltiguc t::valuat!.on

Stl'th'::urat ..'malysi.s tlf thu Glosur"' llcacl a~d :~~$~l AM~~~~l~

3. !•'l\!.\.!'~11' t..:,,ahMth:m or rtl"t'l.! l•'tnngt~, Vt!NSl'l.

l·'l.nn,",l..' :!til: <.:l,J~urt.• Studs

•;. '11~t•r:o,::tl ~.tn·!~~ Am1lysis and l·'nti,;\1(' ~,;,.,d,tat i1,11 ,,f lnh'l Nu;~:d~._•

6. ·nH.'t"':Oll St r~·~:-; 1\n••lys i.s am\ r<u i!;,ltl'

t·:va bta l itHI \l r \.hat lt•t N\l7.7. h·

1. :itnl!..'tttn'll .r\r'll~tysis ~~r lnh•t and Outl<.•L Nt)•~:~ l~·=- anu Vcssc: l :;upports ttn!h•r PiJW

Cl ..

81'~'111< l."-Mdfi

atru(·tua•al an'l 1-'atig,uc Anal.ysh of th(' 'b .. •s::.,·t Hall l't·ansitlon

1\ l. -) - It\. I }

,\ I 0 '.\ • All';

All/, - Al il

lL Strlll'~m·,,t Analvsis or V~ssel and Bott<:trn rl1:~n ... AJ:P..

H1 ''" J11n~·• \1\"(.'

12. l-':n .. i,:th' t:.:alu•~tfon t'lf Sottorn Head to Slu:•ll t\332- t\3.:..: • ..iu~'' tun!

13. St nt.;:tm·al .anu l•at h~ue Analvsis of So~tom A)', S - t\ 1"' 'i lk'-\ ... \ t 11!'.t rument.nt io;.t PenelT,;.t ions

RIV000053A Submitted: December 27, 2011

. APl'ENDIX A

OI~TI\IL.~D STRUCTlU~L ANA1.YSIS

TAB w: Qf CONTeNTS

·.1. Cont t'ol l{odUo\lsing Stress Analysis and lo'lll i guc ~\la l.u4tion

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2. StnH'::ural Analysi.s t.')f th~ (:losurl-' Head and !v"$~l A~~~~~l~

,. J.

I"n~\.!-,ih' t:.!Clhl.ll:i.on or rh.-a.! l:tnngl~1 Vc,;s~l. 1.'1.lIu:,I..' nt\~: cllj~ur(' Studs

'11"' .. :",al ~,ll·t·~~ Ancllysis null I~nli,~u(' !,;vnlllar ;"'1"1' lnh·f Nu;~:dl'

'nh.'\""::d SIt',," s:-; An"l y~ Ls lUBt rOll i!;,u\." 1·;,,~dH"l hm ,,1' llnt l('l N,,~.d(·

·.··'~·'.·:·,l.'·.·:. .;:.' ' ... ' .. 1. Stnll'tUl'al ~'".'lysis ur Inh·t and OutlC.·l

N(~~~:~ l".~ anu Ve~S~ l :;lIpporls und,',. Pip(.· " '.~. ·1':' .

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1t.

81''''/11< l .... m,,1,. .

~.h rudul'. I an,1 1-~8t 19,uc Ana lys t~ of the' 'h':H.,·t \:all l'l'",nsltlon

Strm't;m'''\ Analvsis or Vessel and Bott<)fti

III .',d J\\n~" m'e

12 •• 'llt.i,:lh' 1:~Cllu'ltJon or Bottom Ut"ac to Slu:·ll .. hm .. t.m"\!

1.3. St n';;'l,ut'a\ OInu I'at h~lIe Analvsis of &octotn lka .. \ 1 "l't Tumentnt Ion P~l\elT'';'t ions

.t\ :1:W .. A3:n

Page 9: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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Page 10: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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ACl(NQWJ.EDGEMENT

Acknowledgement is hereby made of the important contributions rendered by the following individuals:

Protect ~ngineer

J. S. Meek

Structural Analysis

M. W. Alexander R. J. C&udle W. R. Ferguson W. J. Heilker F. P. Hill

Therm1! Awaln is

J. K. Allison

B. R. Moss

RIV000053A Submitted: December 27, 2011

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ACKtiOWJ.EPGEKENT

Acknowledgement is hereby made of the impo~tant contributions rendered by the following i~dividuals~

Proiect gnglneer

J. S. Meek

Structural Analysis

M. W. Alexander R. J. Caudle W. R. Ferguson .w. J. Hel1ke~ F. P. Hill

J. K. Allison

B. R. Moss

Page 11: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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F. P. Hill

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J. K. ALU.son

c. R. Cockrt•ll

w. J. MeUker

J. c. Lowry

Westinghouse•APD

Hartford Inspector

NCD Library

Mel l.ab Library

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Page 16: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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Page 17: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

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,,' . ':,< '.:' .. :,. configu.ration:and~·:rel •. tive··locations ., .... . .' :"" , of component' parts.' The'nomtOnclature

C';,:·""'" i,-:, shown.is used consistently .through •. "~'/~') ':~~;t'''''''''': out ',this' report~·,;' For'detaill-d , \ .. ' . . drawings of component 'parts. see . \' q _14.~ '. . . Appendix C. .:,',. .

\ .• : 1 ,.c:J._. .

Tbl, .,' ~ .~. ~.:.~,:~,

) .f , \

..

,llfIEID'. ~IKLD&I' ··,lltll, , . DrI!UDi' N!;2.

1. ,Control Rod ' . ~:-2]4-r)lH M~chanism Housing Details

J ;

«:~i : , I

2. Control Rod 1-;-234-0 ";2 Penetration Details

r- .• __ .. ", ...... . ; (,..... '.

.\ ' ,-'!iJ. I I .. \ ........ .. I .

, 3 • Closur. Head Form-' .:-234-046 ing &. Welding

4. Closure Head £-234-047 Machining ••

s. Studt Nut 6t £-234 -049 Waaher DetaU

6. Pre.sur. Ve .... l £-234 -042 Forming & ~ldtng

7. Pressure V ..... l £-234-044 Final Machining

8. Nozzle o.talla E"2]?-045

9. Miscellaneous. £"23.'..-050 Attachment.

to. Misce itaneous £"2J:.-OC;~ Detail. '

11. 8Ottona Head £-234-043 Form' ••• W.ldlftl •

12. Ins trumeftta tloft. . 'E-2~-OC;6 . '.net. A •• eillbly,& e· Detall. - Botto. R.ad

. "

Page 18: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

;,, ... _.

; ( . \

...... .,• '

..... ;· '' '

,,·. ·,;,·.

_ . Results of the detailed structurai:·a~lysis·.presented ·.·in Appendix A are .su-..r1zed,on~Pages·.7 through 1.7

·for locations. of_ ~j~r. interest~-- · · · · · ·. ·

- '

Stresses Due to Operating Pressure of 2.2S.KS1

SA· me IF s:,~,s'!. .S~!.' £'!.> lltl"fJ:()::if"J''J'

.... ---...--..-a; 69

/~lt.IE .::'.'27 ./.;()

tAJ1t:.fDE .3.76 -=~25

The maxlmum stress intensity_for operating pressure is oo • a • 6.45 KSI on the inside surface. r ·

The overall usage factor for fatigue was U ""' o.

lQ;ation - ~.

Stresses Due. to Operating Pressure of 2.5 KS! and Design Temperature of 650°F

,;• ~'A-162 T,.Ar .JP~SS rut4A.~ ... ~- l §t;~:J"AI.'I · . S:,<ISS · -~~',[-·$ ~-~~_:_~_J

c;. . &; r.. ""'-If._ .1'~-r~:.-:q 1/tkiM)t:: .J.:/1 -l't).-11 -2. ~ ~.;~~--- .£'__!!___ - 9_'f_1_ i a"!.t!.~~- ....!.:.JL -11.01 o ;;..s~ _!_J"7_ __ - "~~J

;:;;~ s-e•/6':' /.w"....-'- rV<!E __ ~ -J.II -· 2J.I./.. '· -~.~ -lf.f3 .!'.1l ~~64 1.,1"' ' _!1.1- ,' tJ ., ,,., ...... ~~., ' l_t-~t,

The maxim\'m stt'ess intensity for design pressure of 2.5 KSI and the design temperature of 650°F i.s ~a ... · "r .. 25.6 .KSI and was locatet\ on the lnside surfac:e of the inc:onel tube material.

Th@ over a l 'l usa~e factor for fat lgue was U · • 0.

RIV000053A Submitted: December 27, 2011

..... . ' ,

.! ~ :'.~' :.(,'

.-.,' ,\ ..

.--'~ -." :i>" .~. " .~ ,,< •

"< .. ~,' ",' , ~< /S ',~

/- ~:,/:~"' I.· .. ,~""" ,

- . ~~, .. " ....

" ,. , "! Stresses Due ,to OperatlngPr.essure of 2.2;,KSI

s;.'r«iI" ~71(~tS'!. S~:!!.-~ /Ill'? i ():i I 7Y ---0; &; ''''( .. "t:-~.,- ..;;~r,. .r. .-~ ~ :.,::.:o~""':.~'.:'':o. -,~:.~~~

1~/ue . P.27 ttl. ;p -2.;~ -3'13 :'.!:'2 6 4 $ ---a",fjlM 3.76 .;1':.';5 I) /,4.:'1 S.7b, :;-:25

The maxlmum stress intensity ,for operating pressure, is 00 ... or- 6.45 KSI on the inside· surface.

The' overallusaRe factor for fatigue was U • o.

'1.QS;ltion - ~,

Stre8S~S Due':,to Operating" Pressure of 2.5' KSI 'and Design Temperature of 650°,

J.2/· 2.J~i. ""'I.~ ";'/"*.5 ~ 'J/ ;_~U

'1-,,'" 11M ";" -I, "" '/.I'!"I "16-, I . _ t"'fC"'!' '. __ ~~.~~

, ' . ' .. !:.' '" ' . ' ~::::::":.,,!"The mAxinmm stress intensity for'design pressure of 2.5 KSI and

-"'-':-::.(\1: the. design temperature of 6S0oF ,is ~Q ... , ~r''', 2S.6 .KSI and was ;, lacatell on the lnside lurface of the inconel tube uterial. ,. '. I: :. . '. '. ,., .., .

.. ,I The overall usa~e reetor forfatlluewa."u:.'o. ,. ',1.

" 'j -":,

Page 19: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

. . ~ ~' ; • . ,• ~ ; ,·. I '~ •

l. · •

.. - .. ,p~Wt·::;~~:>:r ·,;<~?:Xi:~_:,;-· _. _ s-Due to Operating Pressure o£.2.25-KSI.and Maximum

·-'J,;._,. __ Interference Pit. with:. Closure· Rea~:;:~<-:. . : -- . . .... ·. ' . ·~ . .: ~ '~ : .. ~

and

·.:•.

()

. ~' ,, ... !) ;;,~' t) () -:1-l:

,;) v ;) () ()

... :- .-;!J:. ' . ' .

•..• :t:··)i:i)?~.-~·imum stress _intensity. is ,...x .:. I"\' a:~· .. -46.7 KSI and occurs the condition of maximum interference and zero fnternal

This stress intensity is on the inside surface.

of stress is. 55.3 KSI and occurs on the

usage factor for fatigue was U"" 0.0003.

' ' : :>'~:l:d,;!~\<::': ; -:·_'l'he __ maximum stress intensity for the J·weld is ax- c 9 • 42.2

'~;,~-. XS 1 ;~and occurs on the ins ide surface. The maximum range of :._ -~ ..... , ··. I :~.,.

·<;},.::stress intensity i~ 42.8 at the same location. /'. , I -. . . --;;~·;,: ·n,e ·overall usage factor for fatigue was U • 0.06 and occurred i.:;-;,. an _the outside surface.

- '· •' ..

. :~

;~' ...

... ·\ . . •.:.·'

RIV000053A Submitted: December 27, 2011

,.' . ~ ... ' :' ... ,' ~,

' .. . .

. '';

~' ", '. ! • . .! ..... . '. ,: ' ...• :; ..•• I.'.

'. " .' . . : .. ~ '.;:. :: ,\;~i~;;~~}i~:; ; :~f :: :~':;,:::~;?;;~!;(> >. • ". '.". '. .'

·Due to Operating ,Pre .•• \lre;.·of.2.25·.~I.iand ~x~ and Interference' Pit .. with:. Clo.ur~; .. H~a~ .. ::;;:; .. :::;" ;'. '! .. }:- .... ' , .: ....

, .• '. • ~, "i"" ~ .•. ~ '..... . • • • ; ••

• • '. • .....: '. ' •• I • . 'r::,' ~.:: '. : " , ~

".:'.

" '. t.) v " () .- .. ' ,'.~') ,;) v {) f)

; )t{~·~./,· ".: . ·t' 1,,'; ".

'~a'~'imum stress .inten·sity,.is .... x ;;'I"t.:l'" 46.7 KSl and occurs the condition of maxim\Ul\·· int;erferenceand zero fnternaL

Thls stress intensity is on the . inside surface.

of stress ls. S5.3 KSland occurs on the

usage factor forfatlgue was' U .... 0.0003.

' ..

I·' .

. . , ~ ·:,m8.~1mum stress lntensityfor the J-we:Ld, is ox-as &; 42.2 ;\'~;:~;,:1CSti~andoccurs on the inside surface. The maxiuium range of \ ~ .. -:, .. I .l..,

H:i:,;:stress intensity i~ 42 .Sat the .ame location. :;'\:'<f·····, ," ;;~~,:;-·:Th·e "overall usage' factor for fatigue' was U - 0.06 and occurred ~::::;:"'on . 'the outside surface.

i1;«,; i~~~~" ..... .

:':: .. ~:;\/;'" ..... , / ..

. . :~'. . . .

" I· .. l

-, ; .) .: > :<:~.::.~ .... . ". i

, . .' ~ ,

, ;':'. :.:-. .... :'" ! :: ..... ., -'t.,':"

".' '.

, .. ;.~/ . ,.~~~ . ..... ., . :--', .' '., -: ....

'';'"

:"'(

.' · ... 8;, .. :·· ..... : .. <.

••.• '\0

. .....

Page 20: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

.. . · ...... , ~ . .

' . •• • . • • .i :._ ~ .•••

•.. ;!.' ···: ::.;:;::\•'''•::.~;1;~:;~~fii,t~~,{~_·· ;~:_;~ ;;:;\~:,,., ~ ·.· ~.·: ~. ~ . . . . .. . . .

. ·:·:-::··-.{ ... :·. _;,_· ...

· · Jolt: UD Coadf.ti.Ot(: -.s;...s.s·> ·:- .· ·. ·s-1int ·A~T#Ifllkw

-~

I

I I I I I

I I I I I

-· I

2

I

2

·,·:,; _.

-' ;.;f..,

.1.1.tf.

-q.z

45-tl

.-11(; :; :.t~~; 4;..(/j ·,;..,r,

:-J'.S. :·:(, -1?.2. -z;..,. 4'1 '() 9.5" iz~..-..

~tor-tAr. .li~ ~.,4e.;s . .;. :l.,fKfl

'~.i ~;.s .;./Y.J ... .,_.

-~.<:> tf) //,~ $S

-',··~\;~ighest range of stress f.nten~ity for the head flange to -.-.r.;.·i!':P.tl'J:! loaure head juncture -was located on_ the inside surface

· tion - 1). The value of this range of stress intensity

..,. -:-2.5.

~/,J.'f

..~.

;.,~

· 50~4 ICSl and compares favorably witb the allowable of 80 KSl .

. ' •.

:following overall usage factors were .. calculated at the two ,,·-~···~··-'-...,··-· • .,,~ ... -... -.-locations:

1 u & 0.004

- 2 u • 0.015

. ·~ . ,_,. . .. ~ ~ ' .. ·.j.·

.,._ . . ~ '.•.

i-_·,

. . ~ '

. 1:

. _·.·.

. . . . .

....

RIV000053A Submitted: December 27, 2011

.. " .... '., ~ . .

, .••• . .' .i :..~ .• ' •

• ,,;!,' .":::'\;;:\:';··::.~;1:~:;~~fiift~~'{~.··;~:.;~i;;:;\~:i;'. ~ ' .. ~.': ~ . ~ . . .. " '. .

. ,:.:.: :"-.~ ..... :', .; ..... .

''101t: lID CoRdlt una": .6i-.-s.s ,;-': -.' ' . -S"1ins -AlT#llllkw

. ~

I

I I I I I

I I I I I

-' I

2

I

2

',-:,,; -'

- , ;,.;/. ., .1.1.tf.

-q.. 45.(1

_.11(; :; :·rr 4;..(Ij ',;..,r,

:-J'.S· :':0 -Hoi. -2;'''1'

4'1 '0 9.S" iz~'" .. ~t.7-tAr. .Ii~

~.,4e.;s.';' :I,,r,k"fl

. ~.i ~;''$ ';'/Y.J ... ,,-. -~.<:> tf) I/'~ $9

-""~\;~ighe8t range of atre •• lnteri~lty for the head flange to ',;r.;.'i!'.'P.'I'J:! lasure head juncture,wa. located Oft _ the inaide surface

6.,r,-

':'"2·5

~/$.'

,.j. ;.,,~

. tion - 1). The value ofthia range of stress intenaity .50~4 lCSl and comparel favorably witbthe allowable of 80 KSI.

" "

:fo110w1ng overall usage factors were .. calculated at the two If.··~' •• ~.,._,-I'.!.'., -.,,~ ... -... -,'locat ionl:

1 U & 0.004

- 2 u. 0.015

'.-'; .

:.(: .. ' .... : '

. :~ . ;:.

Page 21: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

_- .. ". ~ ...

.:r:· .-.. IO:ft:' u.t · CoDditiO..- .. -· ..

" ': ,,;. .~~. ·:

. ' . .- .s;.uss .. s.n.s ht'IUIIfr' 4Jclf-

·.- , .. •

.d; 4# .r,. 1;-tfit /1;-11. ,;~r,..

I .

'·-- j . , .. I -2Ae -<1.7 ,? -/(,../ -P •. r --<#."/

·2 ZA£' ~& (J /~.o '2"·' -7,~

&-r-tlp· ·..4us ~N ~-r·zs~sl

1 -1!').2 /tl..l ·P.S ·2</J -7.7 1'-• 2 2&6 ;se " J.D J!1.S J5.1

~~·; .. :- Range of Strr•• Intrnoity t. > ~ ~.. . . ~:~~-.·~~i~~-~:.. . . . . ·:~;;;;-,·.:::The highest. range of stress intensity for the vessel flange to :~~-i{ii._ ·vessel shell juncture was located on _the. inside surface :·$M:.:· (Location .. l ) • · The value of this range of stz::-eas intensity ··~·/{?:';. is 45.4 KSl and compares favorably with the allowable of 80 KSI.

:~~~;;,~ Fttiqc EuWition

·~.:f.:·': >·The following overall usage factors were calculated at the two · above · locations: ·

Location - l u - o .. oos Location- 2- u - 0.00002

The max~um allowable usage factor is 1.0 •

.., .. •'•:

. . ... ( ., :.

•'· . '

RIV000053A Submitted: December 27, 2011

:;, , ..... f;· ..... .'.": '101'::' UILCoDditJ' nt' \ . . ,' . ' , ." .. , ,'s.w.ss· .,' ' " 's.ns IMrutSlTr'

4Ic4-'.

.4; lG . ,r,. . 1;-6 '4;.,/; . ,;~r,. I • .. -_.J . "

I -as -~.7 'p -/601 -ZlJ ....,."1 2 lA' ~. " /.$~D '211., .' 7.8

.&k."7' ·vp . , .4~s : , "

, ",

~AI Iift:£.". 'Z5~s I 1 -A!'J.Z 14.1 -2.s -2"'" -7.7 "'-" 2 2&6 ~SIJ tP J.D .1];.5 .15.1

ofSCr." Int,n.1ty

•. ' The higheat. range of .tr~aa intensity for t.he ve •• el flange to ':', ve •• el shell juncture was located on ,the . inside surface' ,:: . (Location .. 1 ). . The value of tb 18 rana' of 8tr.ea. intensity .' i. 45.4 lCSI and compares favorably with the 'allowable of 80 lCSI.

'. ,.:,';:The following oVer-all usage factors were calculated at the two ,::;,~,(~;,:';< above . locations: . :~:.~;': 1::

. Location - 1 U - 0.005

Location - 2, U - 0.00002·

The maxtmumallowable' u8ag. factor i8 1.0.

. .

,'.' :i, . , : ;:~ ~".;'" ~ . .... .'

'., .'

. '. ~

.' .. '

Page 22: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

\ \

\ \

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I I ,--

\

\ I

) I I I I I t..._ .................... _:

Evaluatign

I I I I I I

I

I

I ' I

' ,··.·· .: ;..·

The' -~~~~--~ii li:r~s•· reeu.lting ··•_ froin the:: design ·pressure floW :off · . load "plus o-ring seatin& l•d ,was.-.· .. • ··. ·~::: =~: ~~;cj~~ble otreaa. ia

Maxiwm Avlrau Bpl,t-sea;:xi;s Strci•

· ·The_ maxiMum average bolt service . stress for the bolt-up condition was 36:8KSI.compared to.the allawable of 86.6 KSI •. For the bolt-up plus­operating pressure condition, this _stress was 39.6 lCSI compared to the allowable of· 73~ 5 KSL

Mlximym Bolt Scryice Stress . .

the-maximum.bolt service stress was 95.9 KSI and occurred at Location - 3. This stress occurred during the heat-

. up cycle of the 2500 psi hydrostatic teat. This stress compares fa-.orably with the allowable of 116 .4 KSI.

. , .... '.·:The maximum overall usage factor for the closure studs was U • 0. 313 ::::. :. :;: -~/.:_:'and occurred at the point where it enters the vease 1 flange

:: . .-:·.·: · __ ;;(Location ... 3). · This usage factor compares favorably with the · "-·:;; :'\:·-;allowable of 1.0 •.

- . . !. . . . . .

<. ----<MI~iplum •••a::~n, __ st~··· . ·:., .... ___ .. ;,-;_;;>_:---... ·\~:.'·:.:~· ·:~.·;.;. __ : :·.--: .

'nle maximum bearing·- atrea~---b~twen .the:-:e:ioaijr.{':ltud;~··h;r;- .. nd'. cloaure head flanse waa 39.8 KSt and compare a with: the alloWable.-·-. of 40 KS I for the flange mater lal. '1b is va lu~ oecurred during · -the heatup cycle of the 2500 psi hydroatatie .. teat.·

~ .. , .. ·..,.·

-. .· r:·

RIV000053A Submitted: December 27, 2011

:: .::.- t,'.:

• :.r,:',·:: .... .~·;/.:·t,: . ., ....... ~ .. /.- .; .... . ,'..' ,." .. ' ' ..

. ; ..... ·"~.;:'~:';·i';;::Mi;'.1§0~t~~l~~;;'B:";;';>':" .,,':-;:', .. ":" '1'h.' averaie:bOlt·'i:re •• · reliultiDa , .. ~., '.

\ \ ,

\ I

Evalu.tlgn

I I

I .

I I

. . .

I

, I

• I

" frain tb.::deililll '.pressurefloW, :off':·.' .' ~ .... . :," ".load"plus .. O-r.:1na I.atina· l .. d.,w ••.. · Z.,· ... :'34·;.4:UI.·.:Tbe"'.11owable:stre8 •. , 1.... '.

:.>:1 . :··.34~8·ICS~(:::·:: ,;:t:.;.::::,::~:.~: .. ;:.':;:··, . '.' '.

Ma~'" i."r~'i·:IRJ,t: ktJ:iIi' s",·j • . ·-·Th •. maxiiium'average bolt service;"

. streaa for the bolt";upcondit:lon·. wa •. 36;8' KSI .. coaaparedto· tbe' allOwable of 86.6 KSI.,,· For the bolt-up plus' operatini .preaaure condition, this .streaa wa. 39.6 lSI compared' to the·

, .. allowable . of ;73~5 KSI~' .'

",xyPwa Bolt S.ryise·Stre.s·

The· ·maximum. bolt service Itres. wa. 95.9 KSI and occurred at Location - 3 •

. 'l'his atre'ss occurred during the heat-. up cycle'~ of the· 2500:,P8i hydrostatic .teat •.. This atre88ccoaaparea f.~rably w:1th . the allowable of, 116.4 1CS1. .

. <'The maximum oVerall u.ase factor for the cl08ure studs waa U - .0.313 . .-::' and occurred at the point where it enter. thevelsel flange

. '. ··.7f:·i: '.> (Location .. 3).' Thi. u8age factor cOlilpare. favorably with the '. "';·::;:,:'''.;allowable of l.0. . . '.' . < .: t ' ; . ~".:: ' • .

. :.;-','<.:::): Maxiplum BeIEingStr •• '· . , .. ,:'.>;.I .... :.::::~:·;t,'.:.y ,,<! .... ;>.<.~:. ,,; ~. ,.;, .... , ... ". '\"': . !, . '. -... : .. :". . .. :. ':" '::,':!.' ......... ; :'.1:.'.;, ";'> < ;~, ;:..:. :_.:;:: ..... ,;,;" ... ;;.:" .. )";::' .. ;":::' . .':":",.,

The maximum bearintf stre •• · between··.the:·:clos\inratUch"asher;.and:;;' . clo.ure head flanse "aa 39.8 KSt and coapare. with;.theallaWable·,>.,· of 40 KSI for the flange materlal. 'lbiaval.ue' oeeul"red dUring· .. the heatup cycle of the 2500 psl hydrottatic> teat.· .

\', ....

. \~~;~.~i<·· -;' ,

... '>'.; .. :.. . . ..•.. . .... , .. :.,: ~ ' .. ~. , '.' "" .:'

Page 23: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

.. , .,'

. :. . ~ ~- . .• ··, .... '""' < '

·. ;.•

·., .··.The same location gave the highest value of average primary :'plus local pr tmary stress. The value of this stress intensity ·.was 32.3 KSI and compares favorably with the allowable of

I ;1. 5 Sm &: 40 KSI. . . .

·.·. :):'Ramu: gf Stre§§. IntensitY .

. ·.: TI1e highest range of stress intensity occurred at the juncture '~m:~r·,fm-:.~·.·, :'of the nozzle to vessel wall on the outside surface in the

; .Ylongitudi.nat direction. ·The value of this range of stress ~:intensity was 45.5 KSl and compares favorably with the allow-

·;· able of 80 KSI. ~··. '· '

"BjariD& Stre§S on ~upport Pad

._ .. , .•. __ ,.,·-~···'The bearing stress on the underside of the support pad.for dead ,.,weight. and thermal pipe reactions only was 3 .. 0 KSI. This· stress

••

.~:was not to exceed 5.0 KSI for this condition... . . . t . . ·- . '· · •.

; :. : :· .

.· ;,~-~ . : . . '.' .. • . : ~ ' ' ' . . . :: : .;;. . . • ~ . ~·. ·, . ; • 1 • : ... '

,_ •: .. _."'.•

The maximum overall usage factor for th~ .int'et~ n~-~zl~ ~as ·'. . ..

· fatigue Evat~ation

U • 0.042 and occurred at 'the nozzle•vessel wall junctureon .:the nuts lde surface tn the circumferent la1 direction'. n, is value·

':cc,,miMrrs favorably with the allowable o( t.O. .....

> •••• '. ~. • • •• ' ••

RIV000053A Submitted: December 27, 2011

.'. " :"

maximum average prilnarymembrane stress intensity for the . inlet nozzle was at. the juncture of the, nozzles to the vessel

"11 on the longitudinal axis. " 'I'he value of this stress tensity was 21. l K51 and comi;ares favorably w~th the. allow­le of 26.7 KSI.

gave the highest value of: average primary [us local primary stress', . The value of. this stress intensity

. :was32. 3 KSI and compares favorably with the allowable of . ,;,1.5 Sm 0: 40 KSl. .

Ranse Gtf SU'el§ Intensity.

::'TIlc highest.range of stress intensi.ty oceurred at the.·juncture ~of'the nozzle to vessel wall on the outside surface in the '-longitudinaL direction •. nte value of this range of stress . intens'ity was 45.5 KSl and compares favorably with the . allow­.. bie of 80 KSI.

~UPPQIt. Pad : ~~~;', f..: .. ~.' ;"' '. '.,

,.Y::t':"N':t"?· ,'rhe'bearing stress on theunderslde' of the support pad.for dead' . 'weight and thermal pipe reactionsonly'was l.OKSt. Thi.s· stress','

was not to exceed·S.O KSI for thls.condltion .... · . . .~. : .

,,':' ...... -.:;' . ,', .

. :~, ;.::::. ".':'. . '.: . :. . .: .. ,:: - .'. ~:' .. ' . , '.... ......,' 1'·'-· ...... .

. ' ", ~.t: .. . <~ .~. "'~.' ... ~:~l-'/.:. ·~.-) .. T:l;·(.f !':!.:":::,,.:.:.)'.~' . :: .. ~ : .. '~'::"

'nU! maximum overaU usage' f"~tor for 'th~:j,ni~{~:~~:~'zi~:~~~ "<: t·' .. U - 0.042 and occurred at 'the nozz'te-vessel. wall juncture on .~ ,:th~ llut5lde surface!' 1n the c:i.rcwnferent lal direction'. TIlis value

. '.,:cuhlJulrr5 favorably with the allowable or 1.0. ..' . . ": .

,.'

.!.\:,;.<. <:~:)i' " ; .. ,- .

.' . , ', . .'. .:~;:. "

. .' :,-. ':

'" >"

..,.", ~., ..

Page 24: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

: ::<·'--:~:-~;.;' __ :::r:·:/?:::;r,:·i·:;_;\"~.·;ft'; :~.: ._·_ ·,.··'·

',1: { ·:.~_: .. <~~\' .. ;.~.:· . OUTLET NQZZLE :'NiP \•jsgL: $YnORT- ~:- ':: · ·.. · · ·. -. .:'·:· . •'

. . ·' • ·· .. >·H'• :, r: ~:~>;;J:'f; :;;: ;.: :? .. \\!:!::;} :~( .: . -~ ;, . ·;·: .... ,. .• • ;_ , :: !i'~_f,;.: .· • .. , : . . . :·-

...

. ·· .. _The maximum .average· primary membrane stress intensity for the .· ~.".outlet nozzle was at the juncture of the nozzle- to the vessel .L walt on the longitudinal axis. The ·value. of this stress !::-·intensity was 21.1 KSl and compares· favorably with the allow· · able of 26 • 7. KS 1 . - . · .. ,. · _, .. · ,, .. _- · · ·

· .. :·;.·:The same location g~ve the highest value of average .primary ·-·,plus local primary stress. The value of this stress intensity

was 32.3 KSl and-compares favorably with the allowable of ,_ ...• .,,_,__..., .• -,._,,_..":.·1. 5 Sm • 40 KSt.

.. , ·.· ... . ·:

Range of Stress intenSity --··

:The highest range of. stress intensity occurred at the juncture. of the nozzle to vessel wall·.on the outside _surface· in the ·

.... , . longitudinal direction.· 'lbe value of. this. range of stress . · ..•• < _intensity wa·s 45~ 5 KSI .and compares favorably with. the allow-

·.:.-·.· ·able of 80 KSt·. · . . ~ ·.

Bearing Streas on Support Pad

....... , The bearing stress on· the underside of the support pad· for de•d . · ·. :_'-. weight and _thermal pipe reactions only was 3.6 KSI. -'ntis stress

· i'<(f.'': ... ,was not to· exceed ;.o· KSI for this condition. : . . .. '

Faticue Eya1uation ._., .. · · · .·-· ,:..'~ ;<_.: ':_:. . · · ... ..: .... ,··

The maximum overall uaage factor for~ ~h~·:~u-:ti"~{-~~~·~~--;~~~-·.·_ .. '· .· U • 0.022 and OCCUJ'l"ed It the nozzle~VCS&el Juncture on the inalde R\lrface ln the longl.tudtnaL .direction. :This value· ...

. . ·':'··."

··.· .. ··.··

. compares favorably with the allowable of U ··•1.0~ ;:, __ .... '··;: :--': .. ··- ::- :-:.:.-._:_:·{:.:~_t.-~_:._~-~::::_·>.;~_·~s -·:.;-.:: -·. · .· ·· -· .·:·,: :::::

. ~ '• . . '·· ... · . . . .. . . :~_:;- ':: ~- ... . · .. ~>~- : ~; ;. ··.. . ._ : .. · .. ,, . (J"

. ~-·. . ·.

. .. . . . : _:}:;;L:::., .. ::;;~'-::,_}-~.~:>:.~;( __ ·

RIV000053A Submitted: December 27, 2011

; :: <': .. :~:. ~;';'·.:::r:·:/?:;:;r\: 'i·:;.;\"~.';ftl; :~.: .... . , .....

',1: {.:.~.:.,<~~\' .. ;.~.: .. OUTLEr NOZZLE :'NiP ".SUL: $YnORT ·r· '::' .... . .... .:":. .,'

. ',' •. '. '>,H'i:ii:~:~,!;j:'F;:};': h,,;j;;i::Y}:i(,:,·~;' "';': .... ,' ·..;.')!i,~.f,;,: " ',": . . ~ :"

...

.' .'; .....

··· ... The maximum average' primary membrane stress intensity for the .' ~'''' outlet nozzle was at the juncture of the nozzle· to the vessel o{:walt on the longitudinal axis. The 'value, of this stress :::"intensity was2!. 1 KSt and compares' favorably with the allow" . ab 1e 0 f 26. 7. KS 1. . ..,' .. . .' .. ' ,; .' .' . . .

' .. :';.'; The same location g~ve the highest value of average . primary .. ' ,plus local primary stress. The value of this stress intensity

was 32.3 KSt and'comparesfavorably with the allowable of ".,o, ... ,.".y .•. , .. ":,,,:.· 1. 5 Sm - 40 KS 1.

", ....... ":

Range of Stress intenlity ....

;'n\e highest range of. stress intensity occurred at the -juncture. of the nozzle to vessel wall'.on the outside .surface . in the .

. ' '" . longitudinal direction.· 'lbe value of. this. range of stress ... "'< .intensity was 45~ 5 1<51.and compares favorably with. the allow-

.: c···· able of 80 KSI·. . . . ~',

Bearing Strels on Support Pad

. '.. .... The bearing stress on' the underside of the support pad . for de.d .' .. :.' .. weight and. thermal pipe reactions only was 3.6 KSI..'nais stress

. j;<;f,.:;; ... :wasnot to' exceed ;.0' KSI for thiscondltion. ~

'.~ . . '"" ",' : .... ', ,:.: '.

".

Page 25: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

• 0 ., 2

I. I

l t-·4

.. ~ .

. · . ..... ~ ~ . : ... ·~

. . . . .. I' : : . . . . ~ ~. ·: ... :. ·-. ~·~:.. . ; .- . ,.

0 0 :: 0::001Q1ili~; .. ~.;~: •;~!~f~iot:ena''x : . . - ·~:.- -·~ ·: . _..: . : ... ·< .... ~·r · .. ~'. : .. : ! .·;·:> ·, .:· . . ....... .

. 'l'be · •xfawa :averaae primary membrane atreaa intensity for the.· vessel -wall. · transition occura in ·tbe thin portion of the vesael wall. 'lbe value of this stress intenaicy-waa 26.3 lSI "'and compares: fawrably-_with the allowable. atreea intensity of 26.7 KSI.

occurredoat Location - 1 as range of stress intensity was 37.9 the allowable of 800 lSI.

~~.r~·~/.. . · ·im\.an overall usage factor for the vessel wall ·transition was

0.002 and oceurndat Location - 2 aa shown above. This value :COI:nPilr favorably with the allowable of U .. 1.0.

, ...

) ;

... ;·~:,": ..... - ~.'· .....

RIV000053A Submitted: December 27, 2011

'/',

, . "

2 I' I

l r-4

.. ~ .

" ':... ~ ~. :... .~

" .' '. I' : :'.' ' ~ ~' ':, .. :' '_, ~.~: .. , .. ,- . "

'.;:.::";J,;~;:~';~: .;~!~{~iot:enlitY ,', .- '~: .. _.~.: .... :.: ,' .. < ,," ~'r ' .. ~'. : .. :! ,';':>" .:" ........ .

,'l'be '_xfawD:,averase primary membrane .tr ••• intensity for the" vessel ,wall, ' tran.ition occur. 1n'thethin portion of the vesaelwall. 'lbe value of this acresaintenaity- ••• 26.3 lSI ..... nd compare.: favorably ',with the allowable, .tre •• lntensity of 26.7 lSI.

occurred.at Location - 1 as range of atreaa intensity was 37.9 the allowable of 80. lSI.

~~l"~'~/. . . "imian overall usage factor for the ve •• el wall 'transition ••

0.002 and oceurndat Location - 2 a. ahown above. This value :COl:nPllr favorably with the allowable of U .. 1.0.

I". _".: I

f .•• ,::_. ' ..... ~.'

," .

,,'.

, .'. . '~:. ~ ' ..

• :,. . : . ~ . . ':

. : ... :.~, , ~. " ' .' .. ~~>: ::~-;

Page 26: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

) )., ). ) . . r r r..· 2.. •

"·' .. ;. ,·

. ' . ' DYI to Steady L9ad1

: ·· .. :~ ' .. -~~ · .. · .

. ,;,..-, .

·.('

. -~ -·

. . . ~ ' . ·· .. · D.e ~xbw. :sc~e~s .·inten*i.;;·: · · .:. ty ·dux in& insertion of· the ·

. core ·.occunecl at Location .. .. · , .. · 1 /· "lbe value of · th ia .',

a·tTe88 intensity WAS 10~ 7 ICSI and compares · faVOTab 1 y · with the allowable of 35 ICSI. 'nle ,maximum shear stress occurs at Location 2 and is 10~4 lSI which . compares favorably with the allowable of 18.6 KSI.

critical streis intensity for the steady 125 KIP side steady 125 KIP vertical load (due to thermal growth) at the vessel wall (Location· Y as shown above). The

ue of this streas intensity was 31.1 K&l and compares favorably ith the allowable of 35 KSI.

"

Bange o; st,cas Intensity

·· : .. 'lbe highest range of stress intensity occured at Location • C ;\).as shown above. .The value of this range of stress intensity was ::::40.8 .ICSl and compares favorably with the allowable of 69.9 ICSI .

. ·· ',:;: ,:; ,;":-~.' . .

· ·:,Fatiauc iyaluatMlJ:l

· The fatigue evaluation disclosed that the highest overall usage '"'·~., ... ",~· factor for the pads was 0.02 and occurred at the upper corner

\of the pad at the pad•to·vessel juncture Location - A. 'nl is , : .. value compares favorably with the allowable of U • 1.0. ' ' .....

RIV000053A Submitted: December 27, 2011

.:~. :~-,":~'~'; {y~' :~::\ ;··-~?Jt:f':~~.l·~?~f!:7:~f;~~~~::E~~~~:';:·i;?~"~~: :?;)'?;.t:,'\.;: ,', . 'J .... ,.,. .1: " .... ),.. . ~. >.' ~(:; ".:- ' , r, ~ ..•

:.:.': .. "{':'~"«~ ,~:; ... ::':'.':;:~'.: ... 1IalL...IIId .. UIlll ......... i&.&._A-.. 1P ".:'·::·~e::I;; :.' i ~ 1.;"" , .

,',; "" ,.:<.;{,t' T;',~/ '.;.';':~;;;~~~';~!::\;::"i ;,," ) )t J. / , .' roO

r r..: 2 •

,. /",

. ': -:::.' ,,' 'lbe: .xiliua :stre •• ', iDeenat-', J ).)) , · .. :,.· .. ,;:ey,:,d.iD&:·ln.e~tioft of:~ •. . . . r,,: . eore·.oeeurred at Location' '.-

'. , .' .: ,-'< .. ' ... ··1/· lbe "alueof'thl •. ~ '. ::,:' . '; ·.:treesintenslty vas 10~ 7 " ,'~'

( i • teSt and comparee' favorably' ':; .r with the allowable of 35'. , . . ,r . DI. 'lbe ,maximumabear .. '-r' . stre •• oecurs at LOcation'';' r

".... 2 al'ld 'ia 10.;4' lSI .which .

..... "

cO-pare a favorably with the allowable of 18.6 KiI •

criticalstre.s intenaity for the steady 125 KIP side steady 125 KIP vertical load (due to thermal growth) at the vea •• l w.ll.(Location • Y asahown above). The

lue of this streaa intensity was 31.1 al and compares favorably th the allowable Of.' 3S.ICSI.

", . ' ... '''.;~''ii,>,·r._,.·._·.Bln8' At Stl:," lutep,ity

'''lbe highest 'range of stresa intenslty occured at Location - C '. '.' aa ahown above. .'lbe value of this range of stress intensity was

~O.8,KSI and compares favorably with the allowable of 69.9151. '. \ ~. .' .

t',::", ';.'

.~."T.,:.,.".,.·, "tiauc lyalyatWl

..... The fatigue evaluation disclosed that the hiltlest overall usage . factor for the pads was 0.02 and oceurred It the upper corner

,.of the pad at the. pad .. to-vesael juncture Location - A. "ntis ;:;.::'.i,value compares favorably with the allowable of U II! 1.0.

Page 27: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

. f .. ~ .

:; ,.·· ... · . . . ·· •'. ·.·· .

:, · .... ' ·.· •.· ' ~-··. : ~ .· . . . . . .. . : ~ .. ·. .. . .. : ~. ; ~ . . . . . . -,.~: ~-:-:i~-·-· .... ·~:;. ":' :~- .' .. · .. · · ... · . . .. "• .

•. ·. • . . .'. •. h''•ry ttllllttAIJi! : sen··· Ioccu a_c;y .' .. ··-: ·.. ·.··~ .-~-- :·~·:. ·,.~/·~~: . ,.' ·,". ~ . .;.·~: ·".;: -~.-.-.:· .... · ~. ·. ·. ~.-. ·.· .. · ..

.. :.· ·. Die. ·•xtmuaa ·average·: primary. m.inabrane · screas. intenaf.ty _for the.'bOttom: head .

. to ebell. juncture occurs ·10. · i:be cylindrical shell portion' of the juncture.-: The value·of this stress intensity was: 26.3 KSI and compares favorably with. the allowable of 26.7 ICSI •. :

·_}highest range of· stress intensity occurred at Location .. 3. · ·t,ahown above. The. value of thia'.range of. stress intenai.ty was

., .. ., .... "·'···· Z-l=,.XSI. and compares favorably to the allowable range of stress . nslty of 80 KSI. ·

-~<>··~··--·· 'l.'""'':.lf'if<.~··-.·~,~ :·",, ' I

· ; fatigue evaluation disclosed that the highest overall usage tor, for the bottom head to shell juncture· vas 0.003 and

,,...,_ .. r ...... urred at Location • 3 as ahown. above. · 'fhia value c:oaparea 'ltr.!:b~MI!.•, ably with the allowable of U • ·1.0.

. . / .~-~ . ( ·i ·••·· -.-.

. · .. ·

'.· ··.·.·. .·.,

16 ,._·'

,,.·.,.

?·-~ ·. ~--, ~. : ~.-... ·.'i:- .. -

-: .· , .. .

. ·:·

. -., :;,

.. ,;~ ' ..

...•.. ·':,:··';·{ .:-

. '

RIV000053A Submitted: December 27, 2011

· f .. ~ .

. '.':

:; ,,"

'.' ." .... , ". ".-, .

:, " ... , '.' '.' .. ~.' .. ,' ~.'. .. .....: ~. ". .. ' , .: ~. .. ~ ,

, '. .' ':~: ~·:':t~··.· ,.', '~::-. ,,:' :~ . .' ., .,.'" .. ' . ." ", . •. ..•.. .' .. , IT'·EY ttIIIIttAIJi!: Seql" Ipt.pI "1.' '.

",: ".' •..• ~ ,-~.' :.~ • ." ''''~/'~~: . ,,' .... ~, .;,'~: i".;: ·~i,'.:· .' . " ~.','. ~,' ...... -, .

. ' :,' '. 'lbe. '.ximuaa . average .: primary. m.lnabrane· scr ••• · intenslty .for the.'bOttolll: head'

, to ebell, juncture occurs ,tn.' tbe cylindrical sbel1portlon' of the juncture • .; The value'of tbis streas intensity was: 26.3 KSI and compares favorably with' the allowable of 26.7 1CS1.·:

· .}h1ghest range of' stress intensity occurred at Location .. 3, 't,abownabove. The,value of thi •. range of,stress intenatty was

Z-l'iXSI. and compares favorably to the allowable range of stress · nslty of 80 KSI.'

.~""';';';' ...... "".,.,.';."'~.";.~, ~ :.... . '

'; fatigue evaluation disclosed that tbe highest overall us.ge tor, for tbe bottom head to ahell juncture' vas 0.003 and

,,"" ... r ...... urred at Location - 3 a •• hown, above •. 'Ibis value c:oaparea 'l1"!:l\o~MI!.·, ably with the allowable of U .. '1.0.

. . / .~.~ . ( .j .• '" -.-.

. . ,'. . ",'

','

. ~'.'.'

16 "," .

. ,.'.,.

?,-~ '. ~." ~.: ~; •. ,·.'it ,,-

., " , .. '

. ,:'

. -', :;,

. ; ',.: .~.'

"." .:,~;', . .' .':', , ,

Page 28: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

,•·,,'·

. ~ ·:;;1 ;ii!f :;;·:;<,:. \, .~, ''''· ·.... . . ) .....••. , . ; ,.,y. :'( :~ · ·: Prfmerx · ""'"'•' -sttu• ·Jnc•n•f.ty .

og §tEI'I Jgtenaity

-'lb;,:-~~~- aver~~e >prhaary'; ·:·::·~·: ,_ ..1abrane atress intensity occurs -in --the ; bOttom· head when · taking : into conaideration the ligame~t efficiency. The value_ of the atreee intensity is.26.S KSl and compares favorably with .

·the allowable of 26.7 _KSI.

- · -- -'lbe highest range of stress intensity occurred on the inslde surface of the tube • Location - 1 as shown above~ The value

.. ,,_, .. , .. ","''···"·""'of this range of- stress intensity is 55.2 :KSI and compares favorably th the allowable of 69.9 KSI.

fatigue evaluation disclosed that the highest overall usage factot" for the bottom head instrumentation was 0.14 and occurred on the outside surface of the tube - Location - 2 as shown above.

, -~- 'lbe value compares favorably with the. allowable of U ... 1.0. •.- -

1

·•;; .,

RIV000053A Submitted: December 27, 2011

.- .

.• ' '·1'l1~i:··~~~.:':~.~~~e ::Priii.ar)/:"~~':'~:~~·:'·" .; .......... tre •• lfttensityoccurs

. ; In· the.' bOttom' head 'when' takinl :. 'loto consideration the 11..-e~t efficiency. · .. ·Thev.lue. of the' stre •• :inten.ity.is.26~5 lSt

. aod cOIlparesfavorably with. ·.tbeallowable of 26.7 .KSI •

. "

higheat r.nge of atress intensity occurred on the inslde . surface 0 f the tube - Location - 1 .s shown' above ~ 'lbe value

this ranle of·8tres8 intenaity. is 5,.2:ICSI and compares . favorably ith the allowable of 69.9:1t81 •.

... '. 'Itl1"e hlluatlon' ..

.. · ... ;Th~·f.tigue ev.luation dlsc'losed that the higheat' overall usage' '. "i': facto't for the bottom he.d instrUllWintation was 0.14 and occurred

. < Jett: on' the outside surface of the tube - Location - 2 as shown above.· ./~,); The value compares favorably with' the. allowable of t.r .. LO. ">'~.;>:~/ . . ' .. ;~, .. ~~' ;.... '"

1 . :. -.!

..

.. < .".:~:.,~:~;:/~.;~:::/.:; ,;';':}.;;\: .'.,~/.: ,:;;~;:.:~ ... .; .. ::.~;>~>,; /;~,,?:. 'j' <1':" >~ , ' , , -.. ;:-'" '" "" • '.. '~.

Page 29: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

of Stretl Jgtensi,tt

• • ''~. >: ;~ ', .

'lbe max1Dn:im .average. prtMry · . . meaabraae · .. stress .in tens tty occurs . in.· the. bottom ti'ead vben : taking ·.into. considerattoa· the •tigaa.ent :efficiency •. 'lbe ... value: of. the· · .

: · ·stress. intensity is 26. 5 lCSl· . and compares favorably with. ·the allowable of 26.7 KSI •

...

_The highest range of stress ·intensity. occurred on the ins.lde

''• · . .-.:· .'--' ~.;

surface of the tube - Location • 1 as shown above. The value .· .. 'of this range of stress intensity 1.s 55.2 ;JCSI and compares favorably

with .the allowable of 69.9 ICSI.

'"'· .. ··"··"·., .. i!t;i&lll tivaluatism · ··:.

'._,_·:

···:The .fatigue evaluation disclosed. that the higtu!st o\Terall usage factor for the bottom head instl'\ll'Dentatton was 0.14 and occurred

. . on the outside surface of the tube - Location - 2 as sbown above. ·:...:·.:·The value compares favorably with the allowable. of u .. t.O • . _}·:_. ... ~<.

.. \ ·~ ~ ; . '

: . . ' .;.

RIV000053A Submitted: December 27, 2011

.. : .,,\{',~~( /:":C?J;;:j-;!"~;:~};~1;'1~~~i' %if;J:';:':X;·;.,· .. !~;;~"tl;i" ' >,',:; ?', ··:-."':J,'.:·'rt'ME1(lfjjebrai'ae"Stre.j' IDCep',C!" ,::.

·~'~j'~::,.~e~~p.:·pr~r)/· . ....,1' •• 1'. .trea. ,intensity occur. '. : 1a:, the .. boctOm b'Nd .. en: taking . .,:' into, COD.lderation' die.' U.gaaenc... :} ·.:·eff1c1ency. , 'l'he""value: Df th., ': . ,:;~,}-:

"tre'., intensity is 26. 5ICSI: .'. <' '.:and cOmpare, favorably with. . ~.\ . tbe allowable ,of 26.1,tan •.

9f Stre •• Jotcn.U,X

"The bighest ranse 'of atr ••• ·tntenaity: occurred on tbe inl.ide· 'iurfece of the tube -' Loc.tion ~ 1 aa .howri above . The value

. of this range of stre" inten.ity l.s ".2;KSI and compare. favorably : with. the allowable of 69.9 lSI •

. :',', .',; ,:", . ~".\::' . .~. . .

Thefat:l.gue evaluatlondl.cloeed, that the' highest overall usase· for the bottom head:l.n.trumentetion was 0.14 and occurred

. 00' the outside lurface of tbetube -Location - 2a, shown above. , . )',>'11\. value compare. favorably with.the allowable .. ofU.· 1.0.

': .:!~~;' ..

.' ~ .'

. " .~

. "

, "

Page 30: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

:; ..... ,~~,~ ~~! ;~:r~~ :;::~~:-~~'?/''Yf: ~ :~;:~::-: . . ~ .. f ' • .

... ' ' ~ .·. ·.

. '. ! ••

For the 304 stainless steel at the· bi-metallic weld, the max~um pr~ry plul secondary 1trea1· intensity was 13.7 XSI on the inside 1urface. Thil stress intensity occurred

. . for the de1ign temperature and·.preaaure'. :For the .operating. · ... conditions, the max!mwtt:ranae of ·atreas ·t.tltensity ,waa lL l ·

·KSl and compares favorably with the ,allowable· of 3 Sm • . .:·4s.9 ICSl.

··. For the inconel portion of the tube, the maximum atress ::o',:~:·j'j;i'.-,,~···· :.intenat.ty for the de1ip. coitditl:ons occurred on the inside

:surface. The value of thia ·stress itltenllty was 2.5.6 KSI. ·.:For the operating transients,.· the MXim'-D range of stress

... , ... ,,,,.,_.~ ... · · . intensity was 21.8 K.Sl and· compares favorably with the · allowable of l Sm • 69.9 ICSI •.

At the point where the CIJM·houain&. enters the closure · bead, stresses are induced ·in the tube· at zero preis\lre

due to the i~terference fit. The stress intensity at the ·maximum interference and zero .pressure ia 46.7 ICSI. For

· .. ·>.':·(~:·.~ .. ·the operating transients, the maxU:aum range of stress ,,:.:,:·; ·· · intenalty was 55.3 KSl and· compares favorably with the

.:~:':',., .. allowable of 3 Sm •· 69.9 ICSl. ·

. : .· The fattgue evaluation revealed that the hllheat cUmulative usage factor vas 0.0003 for the inaicle •urface•· . This com-pare• favorably with th• allowabl• of 1.0... · ·

. ·. 'J- ..

. . ~

····, _.,.•.

RIV000053A Submitted: December 27, 2011

:; "f";~~'~ ~~! ;~t~ :;:~~~:.~~,?/:;y~;; :.~ :~.:~:} . . ~ .. f '

,"' " ~.' . " . ~ . '" ", ~', , . :.~ " ~ ':

~~IUiI:!dI.!e..I!!:e.....!!:t.....IA!WIrIA...LJaUJ"~ __ !Yf.IiUL'·: " ::~::«',~> , .. "

................ ton of "~~t}'~rw~~·ri;;-.~~?i~~,.·.ty;ffi~~ .. :;./.; .. :;; .. ":!.';' ......•.. . :. ", :. ~\: ':.;:: ~'. . ~ ..... .

, '., " ,·'::: .. ::~·~i.:>.: >:,.,: ... ,.::.~':·,::~·",~i~{t(~:,;,.:\.'... ..:;' , ,:' : the juncture,.of'the ClU.Cflanee co·:tube,the;-.x1a.aa ,

,ltr.11 int.naity for .Iila Pre •• ure' 1ii ·7~2 ,al,and ' , on the inside surface. ,!be al10altle for' the '304 atainl.ls ateel attbe d.at.p temperatUre 1a .1.S San • 23, lSI.

, '. ! ••

For the 304 atalnle •• ateel at the, bi-me tal lie weld, the max~um pr~ry p1uI lecondary Itre.l· lntenaity was 13.7 XSI on the in. ide .urface. Thil atrelaintenalty occurred

, ,for the de.ign temperature and', prellure'. : Fortbe,operating . '",conditions, the maxlmUlILranae of 'atreal'intenaity :wa. it. 1 '

'151 and comparel favorably witb the ,allowable' of 35m -,-:'45.9 ICSI •

. ' . For tbe inconel portion of tbetube, the maximum atre.s :,1ntenat.ty for the del lan' coitditl:oll8 occurred on the inaide iaurface. The value of thil'ltre •• inten.lty was 2.5.6 1tS1.

, ': Fortbe operatlngeransienta," the Mxm .... range of stress ""~"""'i,'~ •. ", intensity was 21.8 61 and' compares favorably with the

'allowable of 1 Sm • 69.9 teSi •.

,: ':: 19"t10» .. 3

At the point where tbe CR1M' houainl, enterathe closure 'bead. strelses are induced 'in the tube,at zero preisUre

due to tbe 1~terference flt. Thestres. intensity at the 'maximum interference and zero,preslure ia 46.7 1CS1. For

... ' ;',;':'(~:',~." the operating transients. the maxUaum range of stre •• ,,:!;:';.', t.ntenalty was 55.3 KSl and'comparel f.vo .... bly with the .:~\.', -,allowable of 3 Sm .' 69.9 lSI. '

The fattgue evaluation reve.led thatthehlBhest cUmulative us.se faCtor " •• 0.0003 for the lnlide Burf.ce., . This com-pares favorably with th .. allow.bi .. of·l.O., . .\,'

-·.t

'. ;:"r',:

. . ~

",y .. ...• ::. : ... '

". ".

Page 31: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

Lgeatioo • lt .. . . . , ·.. . · .:.·. ;, . ·. ·-:· .. ~-~_:_<--;~·; .. ?j;~.J~ .-·:-~,_:: -.. _~~ ~~--~:-~;~---,~ ·.:-~-: .. :·,.:;,::_::-... :-~~.~----~.-.-_,·_.·~ ... : .... :_. .. ;_ .··; ~ '

At the location· ·w~s•~~-~ di• • CIUII: houataa t. 11\, &ttachect·. to· the closure head ·by:·t:be'·.J-1.eld;l 'theYclaUil~'.range·,:of · stress intensity'· is ''42.8~1Sl,·and coiaiParea~:fawrably· with the allowable of.3 Sm •.69.9 lSI. This range of stress intensity occurs on the inside surface.

From the standpoint of· f~tipe·, the 110~t .critical location will.be'on the outaideporcion of'the·tu'be \mere a atreaa concentration' f-=t:Dr of fwr was used. The cumulative· usage· factor at tbis. locatiOn waa 0.06 and compares favorably with the alLowable of 1.0.

···B. Method of Analysis.

Lqcation - l ·

An interaction analysis was performed-at cut one assuming the CRDM housing flange to be a ring and the tube a long cylindeT.

L9catipp • 2

An interaction analysis was performed at cut two taking into. consideration that elements Z and 3 are long cylinders having different valuea of Youn.g•a Modulua of Elasticity and coefficients of thermal expansion.

lQcttion .. 3 ·

An interaction analysis was performed at cut three by taking the housing as a cylinder and setting its deflection equal to the deflection of the radius of the head pene­tration and conservatively assuming its rotation equal to the local flexibility as if it were solidly attached. lt was assumed that the forces exerted on the head by the tube have negligible effect on the head.

LQctJ;iDQ - 4 . . .

An interaction analyata waa perfot'aled by dividing· the actu.l structure. into the followina analytical model: thit cla1ure head waa tl'aatad aa a pel'fol'ated apharical aha11· with modified elaattc.conatants and the CRDM housing aa a long cylinder. 'ftte effects of the roedundants on the cloaure head were aesumed to be local only. It waa aaaumed that

.· -~·

RIV000053A Submitted: December 27, 2011 '.

. .';'. '. ' .

. . '. .. .. . . . ; ...... , " ...

ieSltwa •. It, . .' .... ." ...;:;..:,...... . >~.;:. '. .. '. .' ... " ":-':' .. :'~::":'.~·i:/~; .. }: .:':.~~.:: ..... ~: ... ~~.:~.~;~ .. ,:\ ... :.,.> .. ::~,:'~.~.~,:~.,., .. ,~: .. :>' .. ; .. : .... :; ~.' . ,~,~,: .... r •• !>.::~.:: .'.

';':, .. Ai: the loc.ti_'·*ft.·~.th.::emr~houlait:U;.:.ttacb~~.to:~·;,~,,:,,:' ._ .;:.:;:/:, the closure h.ad .. by,:·tbie'.:J' __ lcI;l·:th.;-... la_;":r_.~::of.. . ..... ;: .. ' ..... ;' .. ,'.' .' acreas intena1t,.:·i. ;:42.8~DI:'aad coiilPares;-favorably" . '. with the allowable of.3 Sat -.69.9 al.· 'l'biara"ge'

of atre •• int.na1ty occur. Oft·theiftslde·surface. . .

From the .tandpo1ftt of ·.f~t1&Ue:itbe . ..o~t .critical location vill, be ':on the oUtside' portion of' the' tube.

". itaere a .tre •• · c:oncentracicm' f..ct:ar of" fOur '. was . used.· . ..... The CWIlulaciveuaapfactot" at tbia,locattOnwaa 0.06 . . '. and compares favorably with the allowable' of 1.0.

B. Method of Analysis.

. ' ..

lQs.tipn - 1 .

An interaction analysis was perfcmaed'at cut one assuming the CRDK housing flange to be a ring and the tube 1 long cylindn •

LoGlcipp • 2·

An interaction analysis was performed at cut two taking . into. consideration. that elements t and 3 .re long cylinders havlng different valuea of Youngta Modulus of Elasticity and coefficients of thermal expansion.

Lgcation .. ,) .

An interaction analysis vas performed at cut three by taking the housing as a cylinder and setting its deflection equa 1 to the deflection of the· radius of the. head pene­tration and con8ervatively •• suming its. rotation equal to the local flexibility· a8 it: it were SOlidly attached. It was assumed that the forces exerted on the head by the tube have negligible effect on the b.ad.

LgcltiPD - 4

An interaction ana~Y'i8'~" ~rfoned.by dividing' the actu.l structure. into the follawinca ... lYtlcal 1tO.1: the clolure h.ad "al treated a •• ,.I'fol'ated 1",11'1011 ah.ll' with mOdified elaatic.conatanta and the CRDM houl1na ••• long cyU.nder. 'lbe effecta of the redun.dante Oft the clolur •. head were a •• umed to be local only. It was allumed 'that

.' ' ..

:,~

Page 32: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

• ' ,! ' . ~ .; .... '• -~ ...

•'. ····· .. · ..

. ' ~

· C,LOSUU HEAD [LANq£ NIP SIIELL

Di1cussion of Results

. ·,.; •,: .•·:.'

,· I

'!'·'

.·The madJDum primary stress intensity at the closure bead .-'.:flange to shell juncture was 35.8 KSI for the bolt•up ·

l'f{<·,,.~.,"' .•::• plua design pressure condition. This stress occura on • ,~: ... the outside surface of the juncture of the bead to flange

· .. and compares favorably with the allowable of 1. 5 Sm ... . ·40 KSI.

' .,- ..... ·

,::<<:The highest range of ltresa intensity for thia juncture was ·.:: ·• : · 50.4 KSI on the inside surface and compares favorably with

:( '-,~'(:, · .• the allowable of 3 Sm • 80 KSI • . ••• t,. •. ........

t·· 'nle fatigue evaluation revealed that the highest cumulative :; usage factor was 0.015 and occurred for the outside surface. ·. · 'ntis value compares favorably with the allowable of 1.0 •

• Method of Analysis

:·:.The closure head, closure head flange, vessel flange, '··~ vessel shell, and closure studs were all evaluated in the

same analysts. The actual structure was divided into the following elements: the closure bead dome was treated as

· a long sphere, the closure bead flange was treated as a ring,· the vessel flange and studs were· cc:abined as one element with the flange tt'eated as a ring and the studs as cantilever beams fixed to .the flange, and the vessel shell was tt"eat.ed as a long· cylinder·.

Using the above described analytical model, an interaction analysis was performed to detemine the atreaaes due to the mechanical and thermal load in&&. for the heatup .and cooldown cycle. For. the remainiq tranatenta, the eon-· ••rvat 1ve akin atr••• aet:hod waa u1ecl .loa- dal:entlnina. thermal stresaea. These stre••••· were evaluated -itr light of the strength and fatiaue requir•enta of the ASHE- · Boller and Pre1aure VeiHl· Code, Seetion ttl.

••

···.,;. ... ~ .· .· . •?·:. . · ..

. _} _· ..

RIV000053A Submitted: December 27, 2011

" ,,. ,'. "

.',J."t

'. 'j'"

, , -'. :.:, .. -.'; .. ~ ... ,' '\.; .. (.:J."<~;.':':./:- .'

" f' ":' • : .. ,:'" ,.' •••• : • '~"',;::' ':

"for .ny condition ".r~·.)hU:e. _l.lnt~~fer.~e' ... ~ttn .the·tube and h •• d •. fto.: .. ad:l.n& .• t: .. th ..... ld.caft-.xi •. t •. ' .. Usina _chanical·alid· 'd..mal iter ••• .-s:, tram:.thi. ::analY':l.s, . . f.tlgue evaluatiOD" •• :.defor the:'J-veld.:'/·,:: : .. , .. ,

, . '~~.': .... : '~,:' : ... :;<'.~' .. ' <';~:,~:: ,: ,,: .' .... ,; ., .,: .. , " .... -~. , -

Dtaculsion of Results _ .

·.·The .... ximum primary' .tre •• intensity .-'tthe clo.ure bead .' flange to shell juncture wa. 35.8 lCSI for the bolt-up'

.wI"H·'<:'· ... -' .. ' .. ;~·:,::plu. design pre.sure condition. 'l'h1e atre.s occurs on .' .. " :;', the outside surface' of the juncture ,of the head to. flange

··.:·.and compares favorably with the .lloveble of 1. S Sa. .. . ' :,::::.-40 lSI •

• " .... ,.:'1': •.• ':, ...•.

;·.:'-The highest range of atress intensity for chi. juncture was . ;:,:~: ·50.4 KSI on the inside surf.ce and eOmpares favorably with

. ;N,~'i'" . the allowable of 3 San • 80 UI.· . . .' "\,.f .. :

,The fatigue evaluation revealed that the highest cumulative , •. usage factor was 0.015' and occurred for the outside surface. >. "nais value compares favorably with the allowable of 1.0.

• Method of Analysi.

':\'.~: 'lbe closure head. closure head fLanje. vessel flange, .. ~:.~ vessel shell t and cl08ure' stud. were all evaluated in the , . sa .. analysis. 'lbe actual structure was divided into the·

following elements: tbe elo.ure bead doaae wa. treated .a . . ···.a long sphere I the closure head f1anle va. tr.ated as a

ring,' the vessel flange and studs were'combined a. one .element with the flanptreated as a ring and the studs a. cantilever beams fixed to .the flanee. and tbe ve •• el shell was treated aaa lona' cylindel'-•

. U.i.." the above described analytical model, an interaction analy.is was performed to determine the .tre •••• due to the mechani.cal. and the1:mAl loadings., for the b_tup .and cooldown cycle. For. the l' ... inlq·· tra"atents, .theeon- ' . • aryatift ski.n .tr ••••• thod .1 ..... 41 ·.IO&- d ••• Ni"..... . thermal st1'e..... 1h •• e sCre.ses,were evaluated:in'lilh't of the strength and. fatl.ue requlr.ents of the ASHE" . . Boller and Pr ••• ure V .... l· Cod.~ Section Ill·.

. ..... "

'~., .' ·,?~:t '.. ';.'. ;'~ .;

,~:

. ,,~ -'

••

... . .- ..•..... . . . . . .

, )":,,,

Page 33: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

A.

YIJSEL f'L!IIjE MP $HIU.. :, . ; . ' ..

Diseusslo~: ~talt•~lfl ·,· : .. : :.- · .. · ·. : ~- :

' •• < '· "'~ •• ~ ' .• '; .I • •, . ~ "'

The maxiana prfmary. I tress btensity at. the ve'sse 1 . flange to vessel shell juncture val 28.8 151 for the boltup plus design presaure condition: This stress occurred on . tbe outside surface of the juncture flange to. vessel shell. and COIDp&re8 favorably r:o r:he allowable of -l.S St.· • 40· XSI.

lbe higbesr: range of iatresa intensity for this juncture. vas 45-4 kSI on the inside surface and compares favorably vith the allowable of 3 Sm • 80 XSI.

The fatigue evaluation revealed that the highest cumula~ tiveuaage factor was O.OOS and occurred for the inside surface. This value compares favorably with the allowable of 1..0.

s. Method of Analysis

See Section 6.020-B, Method of Analysis, Closure Head Flange and Shell.. ...

6 I 0&0 MAJN . CI.Q§YBE §IUDS

A. Discussion of. Results

The maximum average bolt service stress foT the cold bol.tup condition was 36.8 KSl and compares favorably vith the allowable of 2 Sm • 86.6 lCSI. For the boltup plus opeTating pressure, the average bolt service stress is 39.6 KSI and compares favorably with the allowable of 2 Sat "" 73.5 JCSI at temperature. ·

The max~um bolt service stress was 95.9 KSl and occurred on tbe inside surface of the stud where it enters the vessel flange. This stress occurred during the heatup cycle of the 2500 PSI hydrostatic. teat aftd compares favorably with the allowable of 3 Sm • 116~4 KSI.

~ . . . . ..

A fatipe eval.U.tion vas performed on:.the• atuda using the method outlined in. Para. N•416~2.of the·ASMI Boiler and Preaaure Vessel Code, Section 111. The max~m cumulative uaaae factor for the &tude was 0.313 on the inside eurface of the stud ~ere it enter• the vessel fl.ange • The alloWable ·UI81e: factor b 1.0.

'• ':._.. ' ... ~

RIV000053A Submitted: December 27, 2011

A.

. ';'i

'." ....... .

USIIL f'MIIiE' MP SHIUe:,:,"" .... :\ .

• ' 1 'r" .... :.,:...' ~ .. ~.~~: .' .....

Dileu~.~·~.~f'~ .. ~~~~~ :::::::»>·:·:,;.;:f~,::.::;.:;( ',>' '::. \ '.' .. ', :>. The .xiai. primary: .tr... iDttinaity' '~~\:the vesse 1 . flange to " ••• el Ibell, juncture .s 28.8 Ulfor the. boltup plul delian pre • .ure coDdltioD~1bis 8tres. occurred on, the out.f.de lurface of. the juncture ..' . flaDp to. vessel shell.andC!Ollp8resfawrably ,co t:he' allowable of ,1.5 Sm'· 4O'kSI. , .. .

lbe highelt ran .. of atresl intensity for this juncture, wa. 45.4 KSI on the In. ide surface and· compares favorably with the allowable of 3 Sm • 80 lSI.'

The fatleue,evaluation'revealed that. the highest cumula 4

tlve.u.a&efactorwaa 0.005 and occurred for the inside surface. 'lbi8 value compare I favorably with the ai.lowable of 1.0.

B. Method of Analysis.

Se. Sectlon6.020';'1, Method of Analysil, Cloaure Head Flange and Shell. ...

6 .040 MAli' CkOlWBI stups'

A. Discussion of, Relults

The aax~ average bolt service stre8S for the cold boltup condition was 36.8 'ltSl and cOIlpares favorably' with t~e allowable of 2 Sm • 86.6 lCSI. For the boltup pluI operating prellure. the averase bolt service stress is 39.6KSland compare. favOrably with the allowable of 2 Sat "" 73.5 . lSI at, temperature. '.' '.

The max~ bolt service atre •• ·wa. 95.9 181 and occurred on the inside surface of the stud where it enters the velsel flange. Thil atres8 OCCUlTed during the heatup cycle of the 2500 PSI hydroscatic, teat aftd coarpares favorably vith the allowable.'of 3' Sm • 116 ~4 lSI. . . : . . . .

A fatipe ev.lu.tlon ".'~ perfon.e~~~·~·d.~: 'tud •... ~.~1ng . the method outltfted in "'r •• ·N·416~2:ol the 'AIMS Ioiler and Pressure Yes.el Cod., Section Ill. The 'tnaxbtwn cumulatlv. u ••• e factor .for the studs v •• 0.313 on the lns1d. lurf.ce of the stud where it enterl the veliel nanle. The alieNable ,uaa •• : factor 11·1.0.· .

. . ..... ':""."' . ,:':: " '.' '. ~:"; '" .. ~. , '. . ': :' '" . ' :. :;. .' ~ : . ,'.. . ... .•.....

Page 34: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

.' • ~ : -: i ~ • J .-

' ... ·, .... ' ~ ... .'t"•'···:.;; ~ . . .. . . .:.:.);··. ·.~·,<·; ..

_,··The auuclmum bearins -~t~eea between. th··-~l.Osu~~. st~d. ··-:washers and closure head· flange was .39.8 .KSI •. This'. ·stress occurred• during.: the heac·up;,cycle:.·of .. the_~asoo: PSI hydrostatic·. test.>aad<'eoaapares;.:_f~vora~ly_·.w,ith· t~e ... -... ·

llowable of -l.S· Sm. forSthe, fl~nae~:•tetial~:..:::~ (;. :::' .. ;· ·:·. · .. ~.-~ ~ . '_<_..~ ' . -~ .. · ., ~ \·:'::.·:/(_·~ .':>: ,.'< • ." :·:···.···~ .... ·-~· .. • ••. ' ~ . .:·.·· .,· . . · ... ~' '. : :. '-Method of Analysts.· :: ".· ' .. :. ·, .· · · · · · ,: ·; .. · .:

. ' ..

. Se~ Section 6 .020-a, Method. of Analysis, Closure Head Flange and Shell.

of Results

.:. The maximum average primary membrane stress lntensity for .,·.the inlet nozd.e occurred at the juncture of the nozzle . to the vessel wall on the longitudinal axis. The value

·".,., ... ,.,, ...... _ .. ,.·-~.;of this stress intensi,tywas 21.1 KSI and compares favor->.;:: ably with the allowable of 26.7 KSI. ·

. ~""'. ' .

.·._The same location 'gave the highest value of average primary plus local primary stress. The value of this stress inten• sity was 32.3 KSI and compares favorably with _tbe allowable of 1.5 Sm r. 40 KSl.

The highest range of stress intensity for the operating transients occurred at the juncture of the nozzle co vessel wall on the outside surface in the longitudinal direction. The value of this range of stress intensity was.45.5 KSI and compares favorably with the allowable of 80 KSI.

The bearing stress on the underside of the support pad for dead weight anu the thermal pipe reactions only was 3.0 KSI. This stress was to be l imite.d to S. 0 K.Sl under thiS condition.

The fatigue evaluation revealed that the highest cumulative usage factor was 0.042 and occurred at the nozzle to vessel

. wall juncture on the. outside surface in the circumferential direction. This value compares favorably with the allow­able of t.o. The cumulative usage factor through the · nozzle watt and weld built·up support pad was found to be 0.007 on the outside surface of the pad.

B. Method of Analysis

For the analysis of the nozzle and nozzle to shell juncture, the toads considered were i.nternal pressure, operating tran• sicnts, thermally induced and seismic pipe reactions, static

--·· ·.• ''

RIV000053A Submitted: December 27, 2011 ,'~\~;':tt;r')~;I',rt'1:;~~f~:~!~~/~f7f" '

maximum bearing_tre.s between. the clo8ure,stud. w.l.nl.-,;8 and clo8ure· h •• d, flanse . vas ··.39~8 :KSI •.. :·:1hiS'. str •• s occurred: during::: the he.t·up r, cycl. ::of :~th •. ;...2. saO:. ,'. '51 hydroseatLc·. test:';aDd::.com.,.re.;~f.Yor.bly.:,.with'·the:: :.: -,;.

llowable of ·.1 .. S·'Sm'-forttbe~:,fl.nae~:_terla.1:~:,.:\(;·~>·:. ',:, ,'-.;.

,~thOd of AnalY~:~~ :::<:::?:'~'<"~:'~: ~~~(.·J~j..::~!~>:r,':~~::L··,:":r~·;<.·:?·· ,':- . See Section 6.020-1. Method.ofAn.1Y~is, Closure ,Head'

. Flange and Shell.. . .... ....

of Results

,,,,.,,,.;.;,,.~ .. ,,:. lbe maximum average primary membrane' Itress intensity for .. ', theo inlet nozd,eoccurred at the· juncture of the nozzle

·:·to the vessel wall on the longitudinal axis. 'lbe value ·I()f th1s streSs intensi;ty~as 21.1 KSI and compares favor­'.'. ably with the allowable, of 26.7 KSI. '

:,..,

: C':'<',:}:' The same location 'gave the highest value of average primary .. ':::/ .. :: plus local prlmary stress. The value of this stress incen­

,.-..;' sit)' was 32.3 KSI.and compares favorably with .tbe allowable ':';/' of 1.5 Sm .. 40 KSI •.

Tho highest range of streiB intensity for the. 'operating' . transients occurred at. the juncture of the nozzle to. ·velsel .... <./. wall on the outside surface in the longitudinal direction •

. 'The value of this range·ofstresI.lntensity was,45.5 lSI and compares favorably with the allowable of 80 KSI.

The bearing scress on the underside of the support pad for dead weight and the thermal pi~ reactions only was 3.0 ItSI. 'nlis str.ess was to be U.mite.d to S.O lSI under this' condition.

The fat l&ue evaluation revealed that the highest cumulative usage factor was 0.042. and occurred at the nOzzle to .vessel

... wall juncture on the ,out'side'csurface in the circumferential

'·~:<I' .. " 'j'

direction. This value compares faVorably "ltb :the allow­able of 1.0. The cumulative usase factor thTOUgh the '. nozzl.e wall and weld built-up support'pad wasfound,'to be

8.

.. , . 'r'

...... , ..

0.007 on the outside sur,face.of .the pad. " .. .. . ' .'

Method of Analysis

Fot' the analysls of the nozzle and nozzle. to shell juncture, the loads conSidered were· Internal pressure, operating tran­sients. thermally lndueed and 'seismic pipe reactlons t static

••

, •. '. " . ,.';

Page 35: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

'· I Jo;· ! I I : i i

•••

6.060

A.

-~ • ~\:~·:::' '·~::":·:; :t~-.~-~'':::.·:·'":•= ,. -:·;'::-::r.;'.~·d;t~::;:',:!.~·:F~sr~;:x~::.;/··:::··· . · . . . ..

-weight of veaael, .. earthquake >loading,. and expansion and eontracti~n. :~';: _. ·· ... ~~ .. _ , ;· .•..

n.e stresses '·re~~l~ing fro~·· ali ~xternai .. io~ds were determined in ·the nozzle by the use of the standard formula for direct stress plus bending stress in ·a beam. At the juncture of the.nozzle to vessel walL. these stresses were determined by the methods presented in references 19, 20, and 21. ·

'·:,.

The pressure stresses were determined in .the nozzle by performing an interaction analysis •. · 'lbe actual structure \ofas divided. into the· following elements: · the thin portion-~ of the nozzle was treated as a cylinder, the tapered portion ·' ·\ofas treated as a tapered cylinder, the reinforcement portion was treated as a cylinder. _and the vessel was treated by id~alizing it as a spherical segment of the same thickness as the vess~l and w.ith a rnid•radius 1. 5 times the actual radius of the· vessel.

The thermal stresses for the operating transients were determined by performing an interaction with t:he above analytical model.

For the fatigue evaluation, pressure stre$ses were determin­ed by the stress index method sec forth in Article l-6 of the ASME Boiler and Pressure Vessel Code, Section III. Peak stresses resulting from the external.loads and the thermal transients were determined by concentrating the

·stresses as determined by the above described methods. Combining these stresses enabled the fatigue ~valuation to be per formed. ·

OUTLET NOZZLE AND VESSEL §UPPQBI

Discussion of Results

The maximum average primary membrane stress int:ensity for the outlet nozzle occurred at the juncture of the nozzle to the vessel wall on the longitudinal axis. The value of this stress intensity was 21.1 ,KSl ·and compares favor· ably with t:he allowable, of 26.7 KSI. · '. · . ·. · ·· ··

The same location· gavtt ·the hipeat value ot. awrage primary plus local primary streu. The value of this stress intensity was 32~3 KSt and compares f•vo~ably with th~ allowable of 1.5 Sm • 40 KSI.

RIV000053A Submitted: December 27, 2011

';,

, '~··"\~j·1;:j:~r::~~}·:~~~~/·::t::~;'::7't~ .:;~,:,::::r.iA·~fN?:!:!:~'r'~~~t;Z~:~·.:~·ii.:-;,:<~;"::: :· .. :i;~~ ,:" . ' .. ' " . ,~,

.::;. weight of veaa.l,.,earthquake .. 1oadlna"· aadexpaiaai.on ' ).:'~: .. ~'. , and contraction. 'l~,::·.;/:· ._~ .. ':, .~:. , .:, ' .' '.' : . .' ~

The st~ea.es '·~.~~'i~~~~:·· ~~~'·~~i'~~~~~ai···:io~ds.were " ":: ... ,.

determined in ·the oo&&le by the us. of the standard formula for direct atre.a plus bendi.ng stress in"a beam. At the juncture of the. nozzle toveasel wall t

these stresses were determined by the. methods'presented 1n re ferences 19, 20 ~ . and 21.' , . '

The pressure stresses were determined in .thenoz~le by performing an interaction analysi •• : .. The actual structure,.; "as divided into the' followin& elements:.:' the tbin poi-tion :'. of the nozzle was treated as a cylinder, ,the tapered'portion 'was treated as a tapered cylinder, thereinf(,.,:'cernent pOrtion "as treated as aeylinder J ,and. the vessel was treated by id~alizingitas a spherical'segment of'the same thickness a s the vesse 1 and w.i.th a mid-radius 1.5 times the ac tua 1 radius of the"vessel.

The thermal· stresses for the' operating transients were determined by' performing an interaction with the above analytical model.

For the fatigue evaluation, pressure stresses were determin­ed by the stress ,lndex method set forth in Article 1-6 of the ASMEBoi1er and Pressure Vessel Code, Section III. Peak stresses resultina:·from the external· loads and the thermal transients were determined by ~oncentrating the

. stresses as determined by the above described methods. Combining these stresses enabled the fatigue .valuation to be per formed.' '

6.060 OUTLET NOZZLE ANP'YESSEL SUPpglT

A. Discussion of Results

The max~m average primary membrane stres. intensity for the outlet nozzleoecurred at thejuncture of the nozzle to the vessel wall on the lonaltudinal axis. ' The value of this stress intensity v.s 21.1 ,lCSl 'and compares favor-ably with the allowable,of:26.'.KSI.· ',':.: ... ," ' .•

, ' ,

The •• me location' save' the hip.at valu.of.· awrase ' prlmary plus local primary stre... The value of this stress int4!'nsity was 32~3 KSt and compares favorably with th~ allowable of t.5 Sm - 40 KSI •

.....

.. ,~. '. '. ·.:",t·, .. ",

.' '~',

, r, , ';

. ....

Page 36: #./K J. f'~'----I · ˘ ˇˇ United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating

. . .. · .•• • •. ·.· ······:. ;· ~• .~f'•· ·t·~ :,\-·r::~r1.~~~?-~:~s;;f ii .· '-~-'!/ · ; h-ighest range of stress intenait)•;~fo~~~~the-~.oJie~at,irig .· ·" · ,_< . · -., ....... ~--'"··.-..

r ........ •ients occurred at the -juncture:_of:the· noz~le _to .. -vessel. 11 on the outside. surface.: in the· _lonaltudinal direction•> · value of this ranae_ of. stress· 1ntelui:l.ty".'was· .. S4--.l-~ KSI' :·- _.': :_

. compares favorably __ with.: ~e··•llowabl~ ~f~~~.O.:·.KSl;: _ "_-,_. :-- · -·-. . .·.· ···.·:.:~ .··-.· -~.~--~·.·.-i·.··.-.·.-:~· .. ~-~~-.:{·. ,_. ... .

. bearing stress on the 'underside_ of :the-:_sup~rt~ pad for _­:ti,><~!::'.r."r.· '"'',,the dead weight and the- thermal- pipe reactions -.only. was

··' - :3.6 -ItS I. This stress, was to be llmlted_· to 5.0 KSt,·under is condition. . _ _ ..

' - ·, . · .. = .~ . . .

. _·fatigue evaluatio~ 'revealed': that the hlgbe'at' cumulative · factor was 0~022 and occurred_ at the .nozzle·· to·. vessel

juncture on the instd~ ·surface in· -the ·longitudinal . ireetion. This value compares. favorably with the ·allowable f ·1.0. The cumulative usage factor through.the ·nozzle ll and the weld bullt·up support pad was found to be

0.011 on the outside surface of the pad.

·,·-''.See Section 6.050, Method of Analysis, Inlet Nozzle _and ·;-:~essel Supports for the metho-d of analysis.·

~-~:t·: ~ : . . · ···\

; XESSEL WALL tRANS lTION .

'·:Discussion of Results

-: ::f~he maKimum average- primary stress intensity for the vessel ./{wall transition occurs in the thin portion of_ the vessel

, ·:_?:,'wall. The value of tbia stress -intensity ·is Z6.) KSI and · ··. -·:· ~·· compares favorably with the Sm. value of· 26 .• 7 ·Ksl •

. :)\.· .

-·_:\(·,The highest range of stre~s 'intensity for -the operating J.:;. transients occurred on inside surface at the large end of

... . ;~·-\;the taper. The value of this_ range of stress intensity · -,:: :-__ . :;·_/:was 37.9 KSI and compares favorably with the allowable of . -.·.:,_; . >:,:3 Sm • 80 KSt.. . · - _ ...

_ . The fatigue evaluation revealed that the highest ~~lative. ·:: .• :usage factor was 0.00.2 and. occurred on .the outside- surface

· :_'!;·.:·at the large end of the · tap.-r • . n. is value· is we 11 be low · · ·• .. ;:.the allowable of 1.0. -· .. ,·:. . . . ....... '. ·._;i':·.· .,·

·IB. Method of Analysis ....... ·' .. !

Stre-&&t'S due- to internal pre"uure were determined by means _,.of a standard lnteraction analyal.a. For the purpose of · · - thla analysls. the actual atruct\1re waa divided lnto .

. ', .. ·.,

,· ..

• •

RIV000053A Submitted: December 27, 2011 . . ....••••. '.' ......... ;·~.,~f'.· :t,~ ;;;-'r;i~r1.~~~?o~:~S;;fii.' ',~' '!/ .

;h'ighest range of .tr ••• inten.it)";~fo~~I~the'~,oPe~.t,lrig.· 'J' ',~,' " '.,.:, ... ~.,'".'.-.. r ..... .,,-lents occurred at the, juncture:,of: the' noz~le ,to.,vessel.

11 on the outside, surface.: 1n the',lonaltud1na1 direction ...... . v.lue of th 1& r.n&e, of· stre •• , lntelui:l.tt .. w •• · .. S4' .. l-~ KSI ':' ',' ': :, .

. compares favOrably"vith,:~e·'.11owabl~~f~~~,o.:'.KSI;:, ".': .. :." ' ". . •..• "'.':.:~ .' •••. ·~·~··~·.· .. i· .. ·:·· .. :~·.,~·~~,.:;.·. '.'." .

. bearing stress on tbe 'underside. of :the·:.lup~rt~ pad for " :t",>'~I::';."r., '''i/ .. the dead we igh t and the, thermal, pipe reactions ',only. was

'.·':3.6 ,ItSI. This stress. va. to be Ilmited.' to 5.0 KSI.'under 18 condition. . " ..

, - " . '. ,:.~ '. .

. ,'fatigue evaluatio~' revealed': that the hlgbe'.t' cumulative . factor was 0~022 and occurred. at the,noz.zle·· to'. vessel

juncture on the in.id~ 'surface in"the 'longitudinal . irection. This value compares. favorably with the 'allowable f'l.O. The cumulative usage factor through ,the 'nozzle II and the weld bullt-up support pad was found to be

0.011 on the outside surface of the pad •

. . ·,l'.See Section 6.050, Method of Analysis, Inlet Nozzle .and ';':~essel Supports for the metho'd of analysis.·

~.~:t·: ~ : . . ' '.'\

; XESSEL WALL tRANS IlION '

;,: Discussion of ResuLts

,:::r~he maKimum average· primary stress intensity for the vessel ,/Xwall transition occurs 1n the thin portion of, the vessel

,':?:'wall. The value of this strel. ,tntensity ,is 26.) KSI and "'., ':'~"compares favorably with the Sm, value of· 26'. 7 ·KSI •

. : .. ,i\.. .

,·.;\(·:The highest range of stre~s tntensity for ,the operating J,:;. transients occurred on inside surface at the large end of

.,.. ;~',\;the taper. The value of this. range of stress intensity ,'; :::,,,,:;'/:was 37.9 KSI and compares favorably with the allowable of .. ,',:,,;.>':':3 Sm- 80 1(51. . . " , ...

, . The fatigue evaluation revealed that the highest~~lative, ';:,.: usage factor was 0.00.2 and. occurred on . the outside'surface

·:,'!;'·:·at the largl! end of the' tap"r •. n.ts value i. well below'· .• ,';:. the allowable of 1.0.

. i 8. Me,thod of AnalY8is .. 1

;", . ,':'

" .. ' ,

'. ~ • .'. I" • • .:~ .

... ," .";!:\',:,\,~.::., ': ........ ~.

Stre8SCS due to internal pr.uure were determined 'by means .• ,of a standard lnteractlon .na1),8l.. For the purpose of .. , thls analYNLs. the actual 8truct\lre ,,&. divided into

.' .. ' ",

,' ..

• •