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McGuire Nuclear Station UFSAR Appendix 3A. Tables
Appendix 3A. Tables
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-1
(P
ag
e 1 o
f 4
)
(09
OC
T 2
01
5)
T
ab
le 3
-1.
Su
mm
ary
of
Cri
teri
a -
Str
uct
ure
s
L
oa
din
g
S
eis
mic
T
orn
ad
o
Rem
ark
s In
clu
din
g A
ny E
nvir
on
-
men
tal
Req
uir
em
en
ts
Str
uctu
re
Q.A
.
Req
’d
Cate
gory
Norm
al
Win
d
Dea
d a
nd
Eq
uip
men
t L
ive
Co
nta
inm
en
t
Accid
en
t
Press
ure
OB
E
SS
E
Win
d
Mis
sile
²
Co
nta
inm
ent
X
I -
X
X
X
X
X
- -
Ther
mal
Str
esse
s an
d P
arti
al
Vac
uum
in
Annulu
s. E
quip
ment
Mis
sile
Pro
tect
ed
Co
nta
inm
ent
and
Rea
cto
r B
uil
din
g
Fo
und
atio
n S
lab
X
I X
X
X
X
X
X
X
Ther
mal
Str
esse
s
Co
nta
inm
ent
Inte
rio
r
Co
ncre
te
X
I -
X
X
- X
X
-
- D
iffe
renti
al
Acc
ident
Pre
ssure
; P
ipe
Rup
ture
Load
s T
herm
al
Str
esse
s.
Eq
uip
ment
Mis
sile
Pro
tect
ed
Co
nta
inm
ent
Penet
rati
ons
X
I -
X
X
X
X
X
- -
Chec
ked
fo
r P
ote
nti
al
Pip
e W
hip
pin
g
Co
nta
inm
ent
Str
uct
ura
l S
teel
X
I -
X
X
- X
X
-
- T
her
mal
Str
esse
s
Nucle
ar
Ser
vic
e
Wat
er P
ipe
X
I X
X
X
-
X
X
X
X
So
il a
nd W
ater
Pre
ssure
s o
n B
uri
ed
Port
ion.
Hyd
rauli
c P
ress
ure
s.
Movin
g
Eq
uip
ment
Load
s. S
tati
c S
eis
mic
Analy
sis.
Sp
ec.
By M
ech.
Sec
tio
n.
Nucle
ar
Ser
vic
e
Wat
er
Inta
ke/
Dis
char
ge/
Overf
low
Str
uct
ure
s
X
I X
X
X
-
X
X
X
X
So
il a
nd W
ater
Pre
ssure
s.
Sta
ndb
y N
ucle
ar
Ser
vic
e W
ater
Po
nd
Dam
X
I X
X
X
-
X
X
X
X
New
mark
's M
ethod
fo
r S
eis
mic
Analy
sis
of
Dam
s; H
urr
icane
Win
ds
Au
xil
iary
Bu
ild
ing,
Inclu
din
g
Die
sel
Bld
g
Fu
el
Po
ol
(Co
ncr
ete
Wal
ls,
Lin
er
Pla
te)
X
I X
X
X
-
X
X
X
X
So
il a
nd W
ater
Pre
ssure
s o
n
Sub
stru
cture
; T
orn
ado P
ress
ure
Dro
p;
D/G
Fly
whee
l R
eact
or
Mis
sile
Ther
mal
Str
esse
s an
d C
ask D
rop
New
Fuel
Sto
rage
Vau
lt
X
I -
X
X
- X
X
X
X
Fu
el
Sto
rage
Rac
ks
X
I -
X
X
- X
X
-
- T
her
mal
Str
esse
s
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-1
(P
ag
e 2 o
f 4
)
(09
OC
T 2
01
5)
L
oa
din
g
S
eis
mic
T
orn
ad
o
Rem
ark
s In
clu
din
g A
ny E
nvir
on
-
men
tal
Req
uir
em
en
ts
Str
uctu
re
Q.A
.
Req
’d
Cate
gory
Norm
al
Win
d
Dea
d a
nd
Eq
uip
men
t L
ive
Co
nta
inm
en
t
Accid
en
t
Press
ure
OB
E
SS
E
Win
d
Mis
sile
²
Mai
n S
team
and
Fee
dw
ater
Sup
po
rts,
Thro
ug
h I
sola
tio
n
Val
ve
and
Fir
st
Sup
po
rt O
uts
ide
Rea
cto
r B
uil
din
g
X
I X
X
X
-
X
X
X
X
Pip
e L
oad
s, P
ipe
Rup
ture
Load
s
Rea
cto
r B
uil
din
g
X
I X
X
X
-
X
X
X
X
Torn
ado P
ress
ure
Dro
p.
So
il a
nd W
ater
Pre
ssure
on S
ub
stru
ctu
re
Sta
tio
n V
ent
(No
te 1
) -
I X
X
X
-
X
X
X
-
Ref
ueli
ng
Wat
er
Sto
rage
Tan
k
Fo
und
atio
ns
X
I X
X
X
-
X
X
X
-
Ref
ueli
ng
Wat
er
Sto
rage
Tan
k
Pip
e T
rench
I
X
X
X
- X
X
X
X
Rea
cto
r R
efueli
ng
Wat
er S
tora
ge
Tan
k
Mis
sile
Wall
X
I X
X
X
-
X
X
X
X
Sec
ondar
y C
onta
inm
ent
for
Tank
Rel
ay H
ouse
III
X
X
X
- -
- -
-
23
0 K
v S
wit
ch
Sta
tio
n S
teel
and
Fd
ts.
II
I X
X
X
-
- -
- -
Ste
p-U
p a
nd
Au
xil
iary
Tra
nsf
orm
er
Fo
und
atio
ns
- II
I X
X
-
- -
- -
-
Acc
ess
Rai
lro
ad,
Inclu
din
g S
tructu
res
- II
I X
X
-
- -
- -
-
Ad
min
istr
atio
n
Bu
ild
ing
- II
I X
X
-
- -
- -
-
Hea
tin
g B
oil
er V
ent
- II
I X
X
-
- -
- -
-
Co
nd
ense
r C
oo
lin
g
Wat
er P
ipe
- II
I X
X
-
- -
- -
- S
oil
and W
ater
Pre
ssure
s.
Movin
g
Eq
uip
ment
Load
s
Co
nd
ense
r C
oo
lin
g
Wat
er I
nta
ke
Str
uct
ure
- II
I X
X
-
- -
- -
- S
oil
and W
ater
Pre
ssure
s.
Movin
g
Eq
uip
ment
Load
s
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-1
(P
ag
e 3 o
f 4
)
(09
OC
T 2
01
5)
L
oa
din
g
S
eis
mic
T
orn
ad
o
Rem
ark
s In
clu
din
g A
ny E
nvir
on
-
men
tal
Req
uir
em
en
ts
Str
uctu
re
Q.A
.
Req
’d
Cate
gory
Norm
al
Win
d
Dea
d a
nd
Eq
uip
men
t L
ive
Co
nta
inm
en
t
Accid
en
t
Press
ure
OB
E
SS
E
Win
d
Mis
sile
²
Co
nd
ense
r D
ischarg
e
Str
uct
ure
- II
I X
X
-
- -
- -
- S
oil
and W
ater
Pre
ssure
s.
Movin
g
Eq
uip
ment
Load
s
Dis
char
ge
Canal,
Dik
e an
d R
ipra
p
- II
I X
X
-
- -
- -
-
Hyd
rogen a
nd
Nit
rogen H
ouse
s
- II
I X
X
-
- -
- -
-
Mai
n S
team
Lin
e
Sup
po
rts,
Exclu
din
g
Fir
st S
up
po
rt O
uts
ide
Rea
cto
r B
uil
din
g
- II
I X
X
-
- -
- -
-
Ser
vic
e B
uil
din
g
- II
I X
X
-
- -
- -
-
Turb
ine
Bu
ild
ing
Eq
uip
ment
Sup
po
rts
- II
I -
X
X
- -
- -
-
Turb
ine
Bu
ild
ing
Sub
stru
ctu
re
- II
I X
X
X
-
- -
- -
Turb
ine
Bu
ild
ing
Sup
erst
ruct
ure
- II
I X
X
X
-
- -
- -
So
il a
nd W
ater
Pre
ssure
s
Turb
ine-
Genera
tor
Fo
und
atio
n
- II
I -
X
X
- -
- -
-
Yar
d D
rain
age
- II
I -
X
X
- -
- -
- P
er M
anufa
cture
r's
Rec
om
mendati
ons
So
ll a
nd W
ater
Pre
ssure
s, M
ovin
g
Eq
uip
ment
Load
s
Ho
t M
ach
ine
Sh
op
,
Dec
onta
min
atio
n
Ro
om
s, S
hip
pin
g a
nd
Rec
eiv
ing A
reas
- II
I X
X
X
-
- -
- -
So
il a
nd W
ater
Pre
ssure
s, M
ovin
g
Eq
uip
ment
Load
s
Was
te W
ater
Co
llec
tio
n B
asin
Dam
(N
on-
(Nu
cle
ar
Was
te)
- II
I X
X
X
-
- -
- -
Un
its
1 a
nd
2
Mak
eup
Wat
er
Sto
rage
Tan
k
Fo
und
atio
n
X
I X
X
X
-
X
X
X
-
Co
wan
s F
ord
Au
xil
iary
Inta
ke
Str
uct
ure
- II
I X
X
X
-
- -
- -
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-1
(P
ag
e 4 o
f 4
)
(09
OC
T 2
01
5)
L
oa
din
g
S
eis
mic
T
orn
ad
o
Rem
ark
s In
clu
din
g A
ny E
nvir
on
-
men
tal
Req
uir
em
en
ts
Str
uctu
re
Q.A
.
Req
’d
Cate
gory
Norm
al
Win
d
Dea
d a
nd
Eq
uip
men
t L
ive
Co
nta
inm
en
t
Accid
en
t
Press
ure
OB
E
SS
E
Win
d
Mis
sile
²
52
5 K
v S
wit
ch
Sta
tio
n S
teel
and
Fo
und
atio
ns
- II
I X
X
X
-
- -
- -
Rad
was
te B
uil
din
g
X
III
X
X
X
- -
- -
- M
eets
the
req
uir
e-
ments
of
Reg
. G
uid
e
1.1
43
Sy
mb
ols
:
OB
E
= O
per
atin
g B
asis
Ear
thq
uak
e
SS
E
= S
afe
Shutd
ow
n E
arth
quak
e
X
= D
esig
ned
For
- =
No
t D
esig
ned
Fo
r
No
te 1
: T
he
Sta
tio
n V
ent
is n
ot
des
igned
fo
r to
rnad
o m
isil
es.
No
te 2
: T
urb
ine
mis
sile
s ar
e in
clu
ded p
er s
ecti
on 3
.5.1
.2
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
(P
ag
e 1 o
f 2
)
(09
OC
T 2
01
5)
Ta
ble
3-2
. S
um
mary
of
Cri
teri
a -
Eq
uip
men
t
Eq
uip
men
t S
cop
e
Qu
ali
ty
Ass
ura
nce
Req
uir
ed
Cate
gory
3
Cod
e L
oca
tion
Rad
2
Sou
rce
Sei
smic
T
orn
ad
o
Rem
ark
s
Incl
ud
ing
An
y
En
vir
on
men
tal
Req
uir
emen
ts
OB
E
SS
E
Win
d
Mis
sile
4
Co
nta
inm
ent
Po
lar
Cra
ne
D
X
11
ITT
T,
NE
MA
,
NE
C
C
- X
X
-
- C
on
tain
men
t
Acc
iden
t
Pre
ssu
re, D
ead
and
Eq
uip
men
t,
Liv
e L
oad
s, H
old
Do
wn
Dev
ice1
Fu
el H
andli
ng
Bri
dge
Cra
ne
D
X
11
ITT
T,
NE
MA
,
NE
C
AB
-
X
X
- -
Dea
d a
nd
Eq
uip
men
t, L
ive
Lo
ads,
Hold
Do
wn
Dev
ice1
Sy
mb
ols
:
AB
=
Au
xil
iary
Bu
ildin
g
C
= C
on
tain
men
t
D
= D
uke
X
= D
esig
ned
For
- =
No
t D
esig
ned
Fo
r
OB
E
= O
per
atin
g B
asis
Ear
thq
uak
e
SS
E
= S
afe
Sh
utd
ow
n E
arth
qu
ake
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
(P
ag
e 2 o
f 2
)
(09
OC
T 2
01
5)
Eq
uip
men
t S
cop
e
Qu
ali
ty
Ass
ura
nce
Req
uir
ed
Cate
gory
3
Cod
e L
oca
tion
Rad
2
Sou
rce
Sei
smic
T
orn
ad
o
Rem
ark
s
Incl
ud
ing
An
y
En
vir
on
men
tal
Req
uir
emen
ts
OB
E
SS
E
Win
d
Mis
sile
4
No
tes:
1.
Po
lar
cran
e an
d c
ask c
rane
des
ign
ed f
or
seis
mic
load
s in
unlo
aded
condit
ion o
nly
.
2.
X =
Sou
rce
of
radia
tio
n
- =
No s
ou
rce
of
radia
tio
n
P =
Poss
ible
sou
rce
of
radia
tio
n
3.
Cat
egory
II
& I
II S
tru
ctu
res
are
no
t sa
fety
rel
ated
.
4.
Turb
ine
mis
sile
s ar
e in
cluded
per
sec
tion 3
.5.1
.2
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-3
(P
ag
e 1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-3
. S
um
mary
of
Co
des
an
d S
tan
dard
s fo
r C
om
pon
ents
of
Wate
r-C
oole
d N
ucl
ear
Pow
er U
nit
s B
y N
RC
Qu
ali
ty G
rou
p C
lass
an
d
AN
S S
afe
ty C
lass
Q
ua
lity
Gro
up
Cla
ss A
AN
S
Safe
ty C
lass
1, S
C-1
Qu
ali
ty G
rou
p C
lass
B A
NS
Safe
ty C
lass
2,
SC
-2
Qu
ali
ty G
rou
p C
lass
C A
NS
Safe
ty C
lass
3, S
C-3
Qu
ali
ty G
rou
p C
lass
D A
NS
No
n N
ucl
ear
Safe
ty,
NN
S
Co
mp
on
ent
Cod
es a
nd
Sta
nd
ard
s
Pre
ssure
Ves
sels
AS
ME
Bo
iler
& P
ress
ure
Ves
sel
Co
de,
Sec
tio
n I
II,
Cla
ss 1
AS
ME
Boil
er &
Pre
ssure
Ves
sel
Cod
e, S
ecti
on
III
,
Cla
ss 2
AS
ME
Boil
er &
Pre
ssu
re
Ves
sel
Code,
Sec
tion
III
,
Cla
ss 3
AS
ME
Bo
iler
& P
ress
ure
Ves
sel
Co
de,
Sec
tio
n V
III,
Div
isio
n 1
0-1
5 p
sig
Sto
rage
Tan
ks
–
AS
ME
Boil
er &
Pre
ssure
Ves
sel
Cod
e, S
ecti
on
III
,
Cla
ss 2
AS
ME
Boil
er &
Pre
ssu
re
Ves
sel
Code,
Sec
tion
III
,
Cla
ss 3
AP
I-6
20
Atm
osp
her
ic
Sto
rage
Tan
ks
–
AS
ME
Boil
er &
Pre
ssure
Ves
sel
Cod
e, S
ecti
on
III
,
Cla
ss 2
AS
ME
Boil
er &
Pre
ssu
re
Ves
sel
Code,
Sec
tion
III
,
Cla
ss 3
AP
I-6
50
, A
WW
A D
10
0 o
r
AN
SI
B9
6.1
Pip
ing
AS
ME
Bo
iler
& P
ress
ure
Ves
sel
Co
de,
Sec
tio
n I
II,
Cla
ss 1
AS
ME
Boil
er &
Pre
ssure
Ves
sel
Cod
e, S
ecti
on
III
,
Cla
ss 2
AS
ME
Boil
er &
Pre
ssu
re
Ves
sel
Code,
Sec
tion
III
,
Cla
ss 3
AN
SI
B3
1.1
.0 P
ow
er P
ipin
g
Pu
mp
s
and
Val
ves
AS
ME
Bo
iler
& P
ress
ure
Ves
sel
Co
de,
Sec
tio
n I
II,
Cla
ss 1
AS
ME
Boil
er &
Pre
ssure
Ves
sel
Cod
e, S
ecti
on
III
,
Cla
ss 2
AS
ME
Boil
er &
Pre
ssu
re
Ves
sel
Code,
Sec
tion
III
,
Cla
ss 3
Val
ves
- A
NS
I B
31
.1.0
Pu
mp
s
- M
anu
fact
ure
r's
Sta
nd
ard
s
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 1 o
f 2
6)
(24
AP
R 2
01
4)
Ta
ble
3-4
. S
um
mary
of
Cri
teri
a -
Mec
han
ica
l S
yst
em C
om
pon
ents
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Rea
ctor
Coola
nt
Syst
em
Rea
ctor
Ves
sel
W
1
III-
1
X
C
X
X
X
X
X
Rea
ctor
Coola
nt
Pu
mp
s W
1
II
I-1
X
C
X
X
X
X
X
Ste
am G
ener
ato
rs (
Tub
e)
B
1
III-
1
X
C
X
X
X
X
X
(Sh
ell)
B
2
II
I-2
X
C
X
X
X
X
X
Pre
ssuri
zer
W
1
III-
1
X
C
X
X
X
X
X
Pre
ssuri
zer
Rel
ief
Val
ves
D
1
II
I-1
X
C
X
X
X
X
X
Pre
ssuri
zer
Saf
ety V
alves
W
1
II
I-1
X
C
X
X
X
X
X
Pre
ssuri
zer
Rel
ief
Tan
k
W
NN
S
VII
I X
C
X
X
X
X
X
RC
Pum
p M
oto
r D
rain
Tan
ks
D
NN
S
AP
I-620
-
C
P
- -
X
X
RC
Pum
p M
oto
r D
rain
Tan
k
Pu
mp
D
NN
S
- -
C
P
- -
X
X
Val
ves
D
1,2
,3,
NN
S
III-
1,-
2,-
3
B31.1
.0
X
C,A
B
X
X
X
X
X
Saf
ety I
nje
ctio
n S
yst
em
Saf
ety I
nje
ctio
n P
um
ps
W
2
P&
V-I
I X
A
B
P
X
X
X
X
Acc
um
ula
tors
W
2
II
I-C
X
C
P
X
X
X
X
Val
ves
D
&W
1,2
,3
III-
1,2
,3
X
C,A
B
P
X
X
X
X
UH
I W
ater
Acc
um
ula
tors
W
2
II
I-2
X
A
B
P
X
X
X
X
UH
I N
itro
gen
Acc
um
ula
tor
W
2
P&
V-I
I X
A
B
P
X
X
X
X
UH
I S
urg
e T
ank
W
2
P&
V-I
I -
AB
P
X
X
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 2 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Gas
/Wat
er I
nte
r. M
emb
rane
W
2
P&
V-I
I X
A
B
P
X
X
X
X
Res
idual
Hea
t R
emo
val
Syst
em
RH
R P
um
ps
W
2
P&
V-I
I X
A
B
P
X
X
X
X
RH
R H
eat
Exch
anger
s (T
ub
e)
W
2
III-
C
X
AB
P
X
X
X
X
(Sh
ell)
W
3
V
III
X
AB
P
X
X
X
X
Val
ves
D
1
,2
III-
1,I
II-2
X
C
,AB
P
X
X
X
X
Co
nta
inm
ent
Sp
ray S
yst
em
CS
Pum
ps
D
2
III-
2
X
AB
X
X
X
X
X
CS
Hea
t E
xch
anger
s (T
ube)
20
D
2
III-
-C
X
AB
X
X
X
X
X
(Sh
ell)
20
D
3
VII
I X
A
B
P
X
X
X
X
CS
No
zzle
s D
2
-
X
C
P
X
X
X
X
Val
ves
D
2
II
I-2
X
C
P
X
X
X
X
Ch
emic
al &
Vo
lum
e C
on
tro
l
Syst
em
Pu
mp
s
Ch
argin
g,
Rec
ipro
cati
ng
W
2
P&
V-I
I X
A
B
X
X
X
X
X
Ch
argin
g,
Cen
trif
ugal
W
2
P
&V
-II
X
AB
X
X
X
X
X
Bo
ric
Aci
d T
ransf
er
W
3
P&
V-I
II
X
AB
X
X
X
X
X
Hea
t E
xch
anger
s
Reg
ener
ativ
e W
2
II
I-C
X
C
X
X
X
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 3 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Let
dow
n (
Tub
e)
W
2
III-
C
X
AB
X
X
X
X
X
(Sh
ell)
W
3
V
III
X
AB
P
X
X
X
X
Ex
cess
Let
dow
n (
Tub
e)
W
2
III-
C
X
C
X
X
X
X
X
(Sh
ell)
W
2
II
I-C
X
C
P
X
X
X
X
Sea
l W
ater
(T
ube)
W
2
II
I-C
X
A
B
X
X
X
X
X
(Sh
ell)
W
3
V
III
X
AB
X
X
X
X
X
Tan
ks
Volu
me
Co
ntr
ol
W
2
III-
C
X
AB
X
X
X
X
X
Bo
ric
Aci
d
D
3
VII
I X
A
B
P
X
X
X
X
Bo
ric
Aci
d B
atch
ing
W
NA
V
III
- A
B
- -
- X
X
Ch
emic
al M
ixin
g
W
NA
V
III
- A
B
- -
- X
X
Res
in F
ill
D
NA
V
III
- A
B
- -
- X
X
Su
ctio
n S
tabil
izer
on
Rec
ip.
Ch
argin
g P
um
p
D
2
III-
2
X
AB
X
X
X
X
X
Dem
iner
aliz
ers
Mix
ed B
ed
W
3
VII
I X
A
B
X
X
X
X
X
Cat
ion
W
3
VII
I X
A
B
X
X
X
X
X
Fil
ters
Rea
ctor
Coola
nt
W
2
III-
C
X
AB
X
X
X
X
X
Sea
l W
ater
Ret
urn
W
2
II
I-C
X
A
B
X
X
X
X
X
Sea
l W
ater
Inje
ctio
n
W
2
III-
C
X
AB
X
X
X
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 4 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Bo
ric
Aci
d
W
3
III-
C
X
AB
-
X
X
X
X
Mis
cell
aneo
us
Let
dow
n O
rifi
ces
W
2
III-
2
X
C
X
X
X
X
X
Bo
ric
Aci
d B
len
der
W
3
II
I-3
X
A
B
- X
X
X
X
Val
ves
D
1,2
,3
III-
1,I
II-2
III-
3
X
C,A
B
X
X
X
X
X
Rec
ip.
Char
gin
g P
um
p A
ccu
m.
D
2
III-
2
X
AB
X
X
X
X
X
Bo
ron R
ecycl
e S
yst
em
Pu
mp
s
Evap
ora
tor
Fee
d
W
NN
S
B31.1
-
AB
-
- X
X
X
Rea
ctor
Mak
eup
Wat
er
W
NN
S
- -
AB
-
- -
X
X
Rec
ycl
e E
vap
. C
on
cen
. P
um
p
D
3
III-
3
- A
B
X
X
X
X
X
Sea
l C
ooli
ng W
ater
Pu
mp
D
N
NS
-
- A
B
P
- -
X
Tan
ks
Ho
ldup
(11
) D
3
D
100
X
AB
X
X
X
X
X
Rea
ctor
Mak
eup
Wat
er
Sto
rage
(11
)
D
NN
S
D100
- O
-
X
X
X
-
Rea
gen
t W
N
NS
V
111
- A
B
- -
- X
X
Sea
l C
ooli
ng W
ater
Tan
k
D
NN
S
- -
AB
P
-
- X
X
Dem
iner
aliz
ers
Evap
ora
tor
Fee
d
W
3
VII
I X
A
B
X
X
X
X
X
Evap
ora
tor
Co
nd
ensa
te
W
NN
S
VII
I -
AB
P
-
- X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 5 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Fil
ters
Evap
ora
tor
Fee
d
W
3
VII
I X
A
B
X
X
X
X
X
Evap
ora
tor
Co
nd
ensa
te
W
NN
S
VII
I -
AB
P
-
- X
X
Evap
ora
tor
Co
nce
ntr
ates
W
N
NS
V
III
- A
B
P
- -
X
X
Sea
l C
ooli
ng W
ater
Fil
ter
D
NN
S
VII
I -
AB
X
X
X
X
X
Mis
cell
aneo
us
Evap
ora
tor
- G
as S
trip
per
Pk
g
W
NN
S
B31.1
-
AB
X
-
- X
X
Evap
ora
tor
Co
nd
ensa
te R
etu
rn
Un
it
D
NA
-
- A
B
- -
- -
-
Val
ves
D
2
,3
III-
2,I
II-3
X
C
,AB
X
X
X
X
X
Sea
l C
ooli
ng W
ater
HX
(T
ub
e)
D
NN
S
VII
I -
AB
P
-
- X
X
(
Sh
ell)
D
N
NS
V
III
- A
B
- -
- X
X
Bo
ron T
her
mal
Reg
ener
atio
n
Syst
em
Hea
t E
xch
anger
s
Mod
erat
ing (
Tub
e)
W
3
VII
I X
A
B
X
X
X
X
X
(Sh
ell)
W
3
V
III
X
AB
X
X
X
X
X
Let
dow
n C
hil
ler
(Tube)
W
3
V
III
X
AB
X
X
X
X
X
(Sh
ell)
W
N
A
VII
I -
AB
-
X
X
X
X
Let
dow
n R
ehea
t (T
ub
e)
W
2
III-
C
X
AB
X
X
X
X
X
(Sh
ell)
W
3
V
III
X
AB
X
X
X
X
X
Mis
cell
aneo
us
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 6 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Ch
ille
r U
nit
s W
N
A
- -
AB
-
- -
X
X
Val
ves
D
2
,3
III-
C,I
II-3
X
A
B
X
X
X
X
X
Ch
ille
r S
urg
e T
ank
W
NA
V
III
- A
B
- -
- X
X
Bo
ron C
hil
ler
Pu
mp
s W
N
A
P&
V-I
II
- A
B
- -
- X
X
NR
Dem
in.
W
3
III-
3
X
AB
X
X
X
X
X
An
nulu
s V
enti
lati
on
Syst
em
Fan
s D
3
A
MC
A(1
2)
X
AB
P
X
X
X
X
Fil
ters
D
3
-(1
3)
X
AB
P
X
X
X
X
Mois
ture
Sep
arat
or
D
3
-(13
) X
A
B
P
X
X
X
X
Val
ves
D
3
II
I-3
X
A
B
P
X
X
X
X
Ice
Con
den
ser
Ref
riger
atio
n
Syst
em
Ice
Bas
ket
s W
2
A
s
App
lica
ble
X
C
P
X
X
X
X
Ice
Bed
Doo
rs
W
2
As
App
lica
ble
X
C
P
X
X
X
X
NF
Ref
riger
atio
n U
nit
s W
N
A
- -
AB
-
- -
X
X
Ice
Mac
hin
e W
N
A
- -
AB
-
- -
X
X
Ice
Con
den
ser
Bri
dge
Cra
ne
W
NA
-
- C
-
- -
X
X
Air
Han
dli
ng U
nit
s W
N
A
As
App
lica
ble
C
-
- X
X
Val
ves
D
2
II
I-2
X
C
,AB
P
X
X
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 7 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
NF
Gly
col
Pu
mp
s W
N
NS
-
- A
B
- -
- X
X
NF
Gly
col
Mix
ing &
Sto
rage
Pu
mp
D
NN
S
- -
AB
-
- -
X
X
Ice
Mak
ing S
olu
tio
n F
eed
Pu
mp
D
NN
S
- -
AB
-
- -
X
X
NF
Flo
or
Co
oli
ng P
um
ps
W
NN
S
- -
C
X
X
X
X
X
NF
Gly
col
Mix
ing &
Sto
rage
Tan
k
D
NN
S
VII
I -
AB
-
- -
X
X
Ice
Mak
ing S
olu
tio
n M
ix T
ank
D
NN
S
- -
AB
-
- -
X
X
NF
Gly
col
Exp
ansi
on T
ank
W
NN
S
- -
C
- -
- X
X
Ice
Bin
& A
nn
ex C
on
d. U
nit
s W
N
A
- -
AB
-
- -
X
X
Ice
Bin
W
N
A
- -
AB
-
- -
X
X
Ice
An
nex
W
N
A
- -
AB
-
- -
X
X
Ice
Bin
& A
nn
ex A
ir H
and
lers
W
N
A
- -
AB
-
- -
X
X
Ice
Blo
wer
Pac
kag
e W
N
A
- -
AB
-
- -
X
X
Ice
Con
d.
Cycl
on
e R
ecei
ver
W
N
A
- -
C
- -
- X
X
Ro
tary
Val
ve
Ass
emb
ly
W
NA
-
- A
B
- -
- X
X
NF
Flo
or
Co
oli
ng D
efro
st
Hea
ter
W
NA
-
- C
-
- -
X
X
NF
Sla
b C
ooli
ng
W
NA
B
31.1
-
C
- -
- X
X
NF
Gly
col
Byp
ass
Str
ain
er
W
NA
B
31.1
-
AB
-
- -
X
X
Lo
wer
Supp
ort
Co
ole
rs
W
NA
-
- C
-
- -
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 8 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Co
nta
inm
ent
Iso
lati
on
Syst
em
Val
ves
D
2
II
I-2
X
C
,AB
X
,P
X
X
X
X
Co
nta
inm
ent
Air
Ret
urn
&
Hyd
rogen
-Skim
mer
Syst
em
Air
Ret
urn
Fan
s D
2
A
MC
A(1
3)
X
C
- X
X
X
X
Hyd
rogen
Skim
mer
Fan
s D
2
A
MC
A(1
3)
X
C
- X
X
X
X
Val
ves
D
2
II
I-2
X
C
-
X
X
X
X
Co
mp
onen
t C
oo
lin
g S
yst
em
Pu
mp
s
Co
oli
ng W
ater
B
3
II
I-3
X
A
B
P
X
X
X
X
Dra
in T
ank
D
NA
-
- A
B
P
- -
X
X
Hea
t E
xch
anger
s (T
ube)
D
3
V
III
X
AB
-
X
X
X
X
(Sh
ell)
D
3
V
III
X
AB
P
X
X
X
X
Tan
ks
Su
rge
D
3
III-
3
X
AB
P
X
X
X
X
Dra
in
D
NA
-
- A
B
P
- -
X
X
Val
ves
D
2,3
,NN
S
III-
2
X
AB
P
X
X
X
X
III-
3
X
C
P
X
X
X
X
NA
AB
P
X
X
X
X
Liq
uid
Was
te D
ispo
sal
Syst
em
Was
te C
oll
ecti
on
Sec
tio
n
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 9 o
f 2
6)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
1.
Tan
ks
Was
te E
vap
. F
eed
D
NN
S
III-
3
- A
B
X
- -
X
X
Was
te D
rain
D
N
NS
B
31.1
-
AB
P
-
- X
X
Lau
nd
ry &
Ho
t S
ho
wer
D
N
NS
V
III
- A
B
P
- -
X
X
Rea
ctor
Co
ola
nt
Dra
in
W
NN
S
VII
I -
C
X
- -
X
X
Flo
or
Dra
in
D
NN
S
VII
I -
AB
X
-
- X
X
Aux
. F
loor
Dra
in T
ank
D
NN
S
D100
- R
F
X
X
X
X
X
Aux
. W
aste
Evap
. F
eed
Tan
k
D
NN
S
D100
- R
F
X
X
X
X
X
2.
Pu
mp
s
Was
te E
vap
. F
eed
Tan
k
D
NN
S
VII
I -
AB
X
-
- X
X
Was
te D
rain
Tan
k
W&
D
NN
S
B31.1
-
AB
X
-
- X
X
Lau
ndry
& H
ot
Sh
ow
er
Tan
k
W
NN
S
P&
V-I
II
- A
B
P
- -
X
X
Flo
or
Dra
in T
ank
W
NN
S
P&
V-I
II
- A
B
P
- -
X
X
Rea
ctor
Co
ola
nt
Dra
in
Tan
k
W
NN
S
P&
V-I
II
- C
X
-
- X
X
RH
R &
CS
Pu
mp
Ro
om
Su
mp
D
NN
S
- -
AB
P
-
- X
X
Gro
un
dw
ater
Dra
inag
e
Su
mp
D
3
III-
3
X
AB
-
X
X
X
X
Was
te E
vap
. F
eed
Tan
k
Su
mp
D
NN
S
- -
AB
P
-
- X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 10
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Flo
or
Dra
in T
ank S
um
p
D
NN
S
- -
AB
P
-
- X
X
Co
nta
inm
ent
Flo
or
&
Eq
uip
men
t S
um
p
D
NN
S
- -
C
P
X
X
X
X
Inco
re I
nst
. S
um
p
D
NN
S
- -
C
P
X
X
X
X
Au
x.
FD
T P
um
p
D
NN
S
VII
I -
RF
X
-
- X
X
Au
x.
WE
FT
Pu
mp
D
N
NS
V
III
- R
F
X
- -
X
X
IRF
Su
mp
Pu
mp
D
N
NS
-
- R
F
P
- -
X
X
IRF
Pip
e T
rench
Su
mp
Pu
mp
s
D
NN
S
- -
RF
P
-
- X
X
Lau
ndry
Mac
hin
e S
um
p
Pu
mp
s
D
NN
S
- -
CW
X
-
- X
X
Dec
on E
quip
men
t S
um
p
Pu
mp
s
D
NN
S
- -
CW
X
-
- X
X
3.
Str
ain
ers
Lau
ndry
& H
ot
Sh
ow
er
Tan
k
W
NN
S
VII
I -
AB
P
-
- X
X
Flo
or
Dra
in T
ank
W
NN
S
VII
I -
AB
P
-
- X
X
4.
Fil
ters
Lau
ndry
& H
ot
Sh
ow
er
Tan
k P
rim
ary
W
N
NS
V
III
- A
B
P
- -
X
X
Tan
k S
eco
nd
ary
W
NN
S
VII
I -
AB
P
-
- X
X
Flo
or
Dra
in T
ank
W
NN
S
VII
I -
AB
P
-
- X
X
5.
Mis
cell
aneo
us
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 11
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Rea
ctor
Co
ola
nt
Dra
in
Tan
k
Hea
t E
xch
anger
(Tub
e)
W
NN
S
VII
I -
C
P
X
X
X
X
(Sh
ell)
W
3
V
III
X
C
P
X
X
X
X
Val
ves
W
2
,3
III-
3
X
AB
X
X
X
X
X
Gas
Sam
ple
Ves
sel
D
3
III-
3
X
AB
X
X
X
X
X
Was
te P
roce
ssin
g S
yst
em
1.
Tan
ks
Mix
ing a
nd
Set
tlin
g
D
NN
S
VII
I -
AB
P
-
- X
X
Mix
ing a
nd
Set
tlin
g T
ank
Rea
gen
t T
ank
D
NA
-
- A
B
- -
- X
X
Evap
ora
tor
Co
nc.
Lin
es
Flu
sh
D
NN
S
VII
I -
AB
X
-
- X
X
Sea
l C
ooli
ng W
ater
Tan
k
D
NA
-
- A
B
P
- -
X
X
2.
Pu
mp
s
Mix
ing a
nd
Set
tlin
g T
ank
D
NN
S
VII
I -
AB
P
-
- X
X
Mix
ing a
nd
Set
tlin
g T
ank
Slu
dge
D
NN
S
VII
I -
AB
P
-
- X
X
Was
te E
vap
or.
Con
cen.
Pu
mp
D
3
III-
3
X
AB
X
X
X
X
X
Sea
l C
ooli
ng W
ater
Pu
mp
D
N
NS
-
- A
B
P
- -
X
X
Sea
l C
ooli
ng W
ater
Fil
ter
D
NN
S
VII
I -
AB
P
-
- X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 12
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Sea
l C
ooli
ng W
ater
HX
(Tub
e)
D
NN
S
VII
I -
AB
P
-
- X
X
(Sh
ell)
D
N
NS
V
III
- A
B
P
- -
X
X
3.
Mis
cell
aneo
us
Was
te E
vap
. C
on
den
sate
Ret
urn
D
NA
-
- A
B
- -
- X
X
Was
te E
vap
ora
tor
W
NN
S
B31.1
-
AB
X
-
- X
X
Was
te E
vap
. C
on
d. D
emin
. W
N
NS
V
III
- A
B
P
- -
X
X
Was
te E
vap
. C
on
d. F
ilte
r W
N
NS
V
III
- A
B
P
- -
X
X
Was
te E
vap
. R
eagen
t T
ank
W
NN
S
VII
I -
AB
P
-
- X
X
Was
te E
vap
. F
eed
Fil
ter
W&
D
NN
S
III-
C,V
III
- A
B
X
- -
X
X
Lau
ndry
& H
ot
Sh
ow
er
Car
bo
n F
ilte
r
D
NN
S
VII
I -
AB
P
-
- X
X
Lau
ndry
& H
ot
Sh
ow
er
Dem
iner
aliz
er
D
NN
S
VII
I -
AB
P
-
- X
X
Lau
ndry
& H
ot
Sh
ow
er
Dem
in.
Fil
ter
D
NN
S
VII
I -
AB
P
-
- X
X
Val
ves
D
3,N
NS
II
I-3,B
31.1
.0
X
AB
X
X
X
X
X
Was
te M
on
itor
& D
isp
.
Sec
tion
1.
Tan
ks
Was
te M
on
itor
D
NN
S
VII
I -
AB
P
-
- X
X
Rec
ycl
e M
on
ito
r T
ank
D
NN
S
VII
I -
AB
P
-
- X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 13
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Ven
t. U
nit
Co
nd
. D
r. T
ank
D
NN
S
VII
I -
AB
P
-
- X
X
2.
Pu
mp
s
Ven
t. U
nit
Co
nd
. D
r. T
ank
D
NN
S
- -
AB
P
-
- X
X
Was
te M
on
itor
Tan
k
W
NN
S
VII
I -
AB
P
-
- X
X
Rec
ycl
e M
on
ito
r T
ank
W&
D
NN
S
VII
I -
AB
P
-
- X
X
3.
Mis
cell
aneo
us
Was
te M
on
itor
Dem
iner
aliz
er F
ilte
r
D
NN
S
VII
I -
AB
P
-
- X
X
Val
ves
D
N
NS
B
31.1
.0
- A
B
X
- -
X
X
Gas
eou
s W
aste
Dis
posa
l
Syst
em
Was
te G
as C
om
pre
sso
r P
kg
W
N
NS
B
31.1
.0
- A
B
X
- -
X
X
Was
te G
as T
anks
D
3
VII
I X
A
B
X
X
X
X
X
Hyd
rogen
Rec
om
bin
ers
W
3
- -
AB
X
X
X
X
X
Au
to G
as A
nal
yze
r D
N
NS
-
- A
B
X
X
X
X
X
Gas
Dec
ay T
ank D
rain
Pum
p
W
NN
S
- -
AB
P
-
- X
X
Gas
Tra
p
W
NN
S
- -
AB
P
-
- X
X
Val
ves
D
2
,3
III-
2,I
II-3
X
C
,AB
X
X
X
X
X
So
lid
Was
te D
isp
osa
l S
yst
em
1.
Tan
ks
Sp
ent
Res
in S
tora
ge
Tan
k
D
3
III-
3
X
AB
X
X
X
X
X
Ch
emic
al D
rain
Tan
k
D
NN
S
VII
I -
AB
X
-
- X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 14
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Evap
ora
tor
Co
nce
ntr
ates
Sto
rage
Tan
k
D
NN
S
VII
I -
AB
X
-
- X
X
Res
in B
atch
ing T
ank
D
NN
S
VII
I -
AB
X
-
- X
X
Evap
. C
on
cen
. B
atch
Tan
k
D
NN
S
VII
I -
AB
X
-
- X
X
Bin
der
Sto
rage
Tan
k
D
NA
-
- B
-
- -
- -
2.
Pu
mp
s
Sp
ent
Res
in S
luic
ing
W
NN
S
- -
AB
X
-
- X
X
Ch
emic
al D
rain
Tan
k
W
-
- A
B
X
- -
X
X
Res
in D
ewat
erin
g P
um
p
D
NN
S
- -
AB
X
-
- X
X
Bin
der
Tra
nsf
er P
um
p
D
NA
-
- O
-
- -
- -
3.
Mis
cell
aneo
us
Hydra
uli
c C
om
pac
tor
D
NN
S
- -
AB
P
-
- X
X
Sp
ent
Res
in S
luic
ing F
ilte
r W
N
NS
V
III
- A
B
X
- X
X
X
Val
ves
D
3,N
NS
II
I-3,B
31.1
X
A
B
X
X
X
X
X
Rad
was
te P
um
p S
kid
Unit
D
NN
S
B31.1
-
AB
X
-
- X
X
Fu
el P
ool
Cooli
ng &
Cle
anup
Syst
em
Co
oli
ng P
um
ps
B
3
III-
3
X
AB
X
X
X
X
X
Co
oli
ng H
eat
Ex
chan
ger
D
3
V
III
X
AB
X
X
X
X
X
Co
oli
ng S
trai
ner
s D
3
V
III
X
AB
X
X
X
X
X
Dem
iner
aliz
er
D
NN
S
VII
I -
AB
X
-
- X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 15
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Fil
ter
D
NN
S
VII
I -
AB
X
-
- X
X
Skim
mer
Pu
mp
D
N
NS
-
- A
B
X
- -
X
X
Skim
mer
Fil
ter
D
NN
S
- -
AB
X
-
- X
X
Val
ves
D
3,N
NS
II
I-3,B
31.1
.0
X,-
A
B
X
X
X
X
X
Die
sel
Gen
erat
or
Fu
el O
il
Syst
em
Day
Tan
ks
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Bo
ost
er P
um
ps
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Dri
p T
anks,
Pu
mp
s, &
Fil
ters
D
N
NS
-
- A
B
- -
- X
X
Rec
ircu
lati
on
Pu
mp
D
N
NS
-
- O
-
- -
- -
Rec
ircu
lati
on
Fil
ter
D
NN
S
- -
O
- -
- -
-
Tra
nsf
er F
ilte
rs
D
3
III-
3
X
AB
-
X
X
X
X
Tra
nsf
er P
um
ps
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Fu
el O
il T
anks
(17)
D
3
AP
I-620
X
B
-
X
X
X
X
Rel
ief
Val
ves
D
3,N
NS
(1
8)
X,
- A
B,
o
- (1
8) ,
- (1
8) ,
- X
, -
X,
-
Val
ves
(In
-lin
e &
Oth
ers)
D
3,N
NS
II
I-3,(1
8) ,
- X
, -
DB
,B
- X
X
X
X
Die
sel
Gen
erat
or
Co
oli
ng
Wat
er S
yst
em
Co
oli
ng W
ater
Hea
t
Ex
chan
ger
s
D
3
VII
I X
A
B
- X
X
X
X
Inte
rco
ole
r P
um
ps
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 16
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Jack
et W
ater
Cir
cula
tin
g
Pu
mp
s
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Jack
et W
ater
Hea
ters
D
3
(1
8)
X
AB
-
(18)
(18)
X
X
Su
rge
Tan
ks
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Tem
per
ature
Reg
ula
tin
g
Val
ves
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Val
ves
(In
-lin
e &
Oth
ers)
D
3
II
I-3,(1
8)
X
AB
-
(18)
(18)
X
X
Die
sel
Gen
erat
or
Lub
e O
il
Syst
em
Dir
ty L
ub
e O
il T
anks
D
NN
S
- -
TB
-
- -
- -
Hea
ter
Pu
mp
s D
3
(1
8)
X
AB
-
(18)
(18)
X
X
Oil
Hea
ters
D
3
(1
8)
X
AB
-
(18)
(18)
X
X
Fu
ll F
low
Fil
ters
D
3
V
III,
(18
) X
A
B
- (1
8)
(18)
X
X
Lub
e O
il C
oole
rs
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
B &
A L
ub
e O
il P
um
ps
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Inta
ke
Str
ain
ers
D
3
VII
I X
A
B
- X
X
X
X
Tem
per
ature
Reg
ula
tin
g
Val
ves
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Rel
ief
Val
ves
D
3
(1
8)
X
AB
-
(18)
(18)
X
X
Val
ves
(In
-lin
e &
Oth
ers)
D
3,N
NS
II
I-3,(1
8) ,-
X
,-
AB
,B
- X
X
X
X
Die
sel
Gen
erat
or
Sta
rtin
g A
ir
Syst
em
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 17
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Air
Co
mp
ress
ors
D
N
NS
-
X
AB
-
(18)
(18)
X
X
Sta
rtin
g A
ir T
anks
D
3
VII
I,(1
8)
X
AB
-
(18)
(18)
X
X
Lin
e F
ilte
rs
D
3
III-
3
X
AB
-
X
X
X
X
Co
ntr
ol
Air
Fil
ters
D
3
(1
8)
X
AB
-
(18)
(18)
X
X
Fil
ter
- M
ois
ture
Tra
ps
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Rel
ief
Val
ves
D
3 N
NS
II
I-3,(1
8)
X
AB
-
X,(1
8)
X,(1
8)
X
X
Val
ves
(In
-lin
e &
Oth
ers)
D
3
II
I-3
X
A
B
- X
X
X
X
Die
sel
Gen
erat
or
Inta
ke
and
Ex
hau
st S
yst
em
Inta
ke
Sil
ence
rs
D
3
(18
) X
A
B
- (1
8)
(18)
X
X
Ex
hau
st S
ilen
cers
D
3
(1
8)
X
AB
-
(18)
(18)
X
X
Val
ves
D
3,N
NS
II
I-3,-
X
A
B
- X
X
X
X
Die
sel
Gen
erat
or
Cra
nkca
se
Vac
uum
Syst
em
Vac
uum
Blo
wer
s D
N
NS
-
X
AB
-
(18)
(18)
X
X
Die
sel
Gen
erat
or
Ro
om
Su
mp
Pu
mp
Syst
em
Gen
erat
or
Pit
Su
mp
Pu
mp
s
D
NN
S
- -
AB
-
- -
X
X
Gen
erat
or
Roo
m H
igh
Cap
acit
y S
um
p P
um
ps
D
3
(15
) X
A
B
- X
X
X
X
Gen
erat
or
Roo
m L
ow
Cap
acit
y
Su
mp
Pu
mp
s
D
NN
S
- -
AB
-
- -
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 18
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Val
ves
D
3,N
NS
II
I-3,-
X
,-
AB
,AB
-
X
X
X
X
Nu
clea
r S
ervic
e W
ater
Syst
em
Pu
mp
s D
3
II
I-3
X
A
B
- X
X
X
X
Str
ainer
s D
3
V
III
X
AB
-
X
X
X
X
Val
ves
D
2
,3
III-
2,I
II-3
X
A
B,O
-
X
X
X
X
Co
nven
tional
Ser
vic
e W
ater
Syst
em
Pu
mp
s D
N
A
- -
SB
-
- -
- -
Str
ainer
s D
N
A
- -
SB
-
- -
- -
Val
ves
D
N
A
- -
SB
-
- -
- -
Fu
el H
andli
ng S
yst
em
Rea
ctor
Man
ipu
lato
r C
ran
e W
N
NS
-
X
C
- -
X
X
X
Fu
el T
ran
sfer
Tub
e W
2
II
I-2
X
C
,AB
-
X
X
X
X
Un
der
wat
er F
uel
Co
nvey
or
W
NN
S
- X
C
,AB
-
- -
X
X
Sp
ent
Fuel
Man
ipula
tor
Cra
ne
W
NN
S
- X
A
B
- -
X
X
X
Fu
el H
andli
ng T
ools
W
N
NS
-
X
C,A
B
- -
- X
X
Sam
pli
ng S
yst
em
Sam
ple
Hea
t E
xch
anger
D
N
NS
V
III
- A
B
X
- -
X
X
Sam
ple
Ves
sel
D
NN
S
VII
I -
AB
X
-
- X
X
Val
ves
D
2
,3
III-
2,I
II-3
X
C
,AB
X
X
X
X
X
Ref
uel
ing W
ater
Syst
em
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 19
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Ref
uel
ing W
ater
Pu
mp
D
N
NS
-
- A
B
P
- -
X
X
Ref
uel
ing W
ater
Rec
irc.
Pu
mp
s
D
NN
S
- -
AB
P
-
- X
X
Ref
uel
ing W
ater
Pu
mp
Str
ainer
D
NN
S
- -
AB
P
-
- X
X
Sto
rage
Tan
k
D
2
D100
X
O
P
X
X
X
19
FW
Pip
e T
ren
ch S
um
p P
um
p
D
NA
-
- O
-
- -
- -
Val
ves
D
2
II
I-2,
B31.1
.0
X
C,A
B
P
X
X
X
X
Eq
uip
men
t D
econ
tam
inat
ion
Syst
em
Pu
mp
D
N
NS
-
- A
B
- -
- X
X
Tan
k
D
NN
S
D100
- A
B
- -
- X
X
Val
ves
D
N
NS
(1
8)
X
C,A
B
- X
X
X
X
Fir
e P
rote
ctio
n S
yst
em
Fir
e P
um
ps
D
NA
(1
4)
- O
-
- -
- -
Val
ves
D
N
A
- -
TB
,SB
,O
B,A
B
- -
- -
-
Sta
tion
Ven
tila
tio
n S
yst
ems
Co
nta
inm
ent
Ven
tila
tio
n
1.
Co
nta
inm
ent
Pu
rge
Fan
s D
N
NS
-
- A
B
P
- -
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 20
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Fil
ters
D
N
NS
-
- A
B
P
- -
X
X
2.
Oth
er S
yst
ems(1
6)
Fan
/Coil
Unit
s D
N
NS
-
- C
P
-
- X
X
Fil
ters
D
N
NS
-
- C
P
-
- X
X
CR
DM
Fan
s D
N
NS
-
- C
P
-
- X
X
3.
Au
xil
iary
Bld
g.
Ven
tila
tion
Fan
/Coil
Unit
s D
N
A
- -
AB
-
- -
X
X
Fil
ters
(C
har
coal
) D
3
-
X
AB
P
X
X
X
X
ES
Air
Han
dli
ng U
nit
s D
3
-
X
AB
P
X
X
X
X
4.
Co
ntr
ol
Bld
g. V
enti
lati
on
Fan
D
3
-
X
AB
P
X
X
X
X
Fil
ters
D
3
-
X
AB
P
X
X
X
X
Air
Con
dit
ionin
g U
nit
D
3
-
X
AB
-
X
X
X
X
5.
Die
sel
Bld
g. V
enti
lati
on
Fan
s D
3
-
X
AB
P
X
X
X
X
Fil
ters
D
3
-
X
AB
P
X
X
X
X
Mai
n S
team
Syst
em
Iso
lati
on V
alves
D
2
II
I-2
X
D
H
- X
X
X
X
Fee
dw
ater
Syst
em
Iso
lati
on V
alves
D
2
II
I-2
X
D
H
- X
X
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 21
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Au
xil
iary
Fee
dw
ater
Syst
em
Moto
r D
riven
Pu
mp
s D
3
II
I-3
X
A
B
- X
X
X
X
Ste
am T
urb
ine
Dri
ven
Pu
mp
s D
3
II
I-3
X
A
B
- X
X
X
X
Val
ves
D
2
,3
III-
2,I
II-3
X
A
B,D
H
- X
X
X
X
Sto
rage
Tan
k
D
D-1
00
- O
-
- -
- -
-
Ste
am D
um
p S
yst
ems
Turb
ine
Byp
ass
D
NA
-
- T
B
- -
- -
-
Rel
ief
Val
ves
D
2
II
I-2
X
D
H
- X
X
X
X
Saf
ety V
alves
D
2
II
I-2
X
D
H
- X
X
X
X
Ste
am G
ener
ato
r B
low
do
wn
Rec
ycl
e S
yst
em
No
te:
Ste
am G
ener
ator
Blo
wd
ow
n R
ecycl
e S
yst
em i
s no
longer
in
ser
vic
e. F
low
pat
h h
as b
een p
erm
anen
tly i
sola
ted
per
NS
M M
G-1
/2-2
43
0.
SG
Blo
wdo
wn
HX
D
N
NS
V
III
- A
B
P
- -
X
X
SG
Blo
wdo
wn
Tan
k
D
NN
S
VII
I -
AB
P
-
- X
X
SG
Blo
wdo
wn
Pu
mp
s D
N
NS
-
- A
B
P
- -
X
X
SG
Blo
wdo
wn
Rec
ycl
e D
emin
. D
N
NS
V
III
- A
B
P
- -
X
X
Blo
wo
ff T
ank
D
NN
S
VII
I -
TB
-
- -
- -
Blo
wo
ff T
ank P
um
ps
D
NN
S
- -
TB
-
- -
- -
Val
ves
D
2
II
I-2
X
C
,AB
P
X
X
X
X
Co
nd
ense
r C
ircu
lati
ng W
ater
Syst
em
Co
nd
ense
r C
ircu
lati
ng P
um
ps
D
NA
-
- O
-
- -
- -
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 22
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tion
(6
)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
Val
ves
D
N
A
- -
TB
,O
- -
- -
-
Inst
rum
ent
Air
Syst
em
Co
mp
ress
ors
D
N
A
- -
SB
,O
- -
- -
-
Aft
er C
oo
lers
D
N
A
- -
SB
-
- -
- -
Air
Tan
ks
(1A
, 1
B,
2A
, 2
B)
D
NA
II
I-3
-
AB
-
X
X
X
X
Air
Rec
eiver
s (A
, B
, C
) D
N
A
VII
I -
SB
-
- -
- -
Air
Dry
ers
D
2
VII
I -
SB
-
- -
- -
Val
ves
D
2
II
I-2
X
C
,AB
P
X
X
X
X
Mai
n S
team
Iso
lati
on
Val
ve
Air
Tan
ks
D
3
III-
3
- D
H
- -
- X
X
Hyd
rogen
Syst
em
Hyd
rogen
Ves
sels
D
N
A
VII
I -
O
- -
- -
-
Val
ves
D
N
A
-
AB
-
- -
- -
Nit
rogen
Syst
em
Nit
rogen
Ves
sels
D
N
A
VII
I -
O
- -
- -
-
Val
ves
D
N
A
VII
I -
AT
,TB
-
- -
- -
Co
nta
inm
ent
Air
Rel
ease
an
d
Ad
dit
ion S
yst
em
Fil
ters
D
N
NS
-
- A
B
P
- -
X
X
Val
ves
D
2
II
I-2
X
A
B,C
P
X
X
X
X
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 23
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tio
n
(6)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
No
tes:
1.
Eq
uip
men
t lo
cate
d i
n t
he
Co
nta
inm
ent
and A
uxil
iary
Bu
ildin
g n
ot
des
ign
ed f
or
seis
mic
load
ing w
ill
be
chec
ked
to
ver
ify t
hat
fau
lt o
f su
ch
equip
men
t w
ill
no
t re
sult
in t
he
loss
of
fun
ctio
n o
f sa
fety
cla
ss e
qu
ipm
ent.
2.
D
=
Du
ke
B
=
B
abco
ck &
Wil
cox
W
=
W
esti
ngh
ou
se
3.
1
=
Saf
ety C
lass
1
2
=
S
afet
y C
lass
2
3
=
S
afet
y C
las
3
N
NS
=
N
on
-Nu
clea
r S
afet
y
N
A
=
No
t A
pp
lica
ble
4.
III-
1
=
AS
ME
Bo
iler
and P
ress
ure
Ves
sel
Code
– S
ecti
on
III
, C
lass
1
II
I-2
=
A
SM
E B
oil
er a
nd P
ress
ure
Ves
sel
Code
– S
ecti
on
III
, C
lass
2
II
I-3
=
A
SM
E B
oil
er a
nd P
ress
ure
Ves
sel
Code
– S
ecti
on
III
, C
lass
3
V
III
=
AS
ME
Bo
iler
an
d P
ress
ure
Ves
sel
Code
– S
ecti
on
VII
I
B
31
.1.0
=
A
NS
I B
31
.1.0
(1
967)
D10
0
=
Am
eric
an W
ater
work
s A
ssoci
atio
n,
Sta
ndar
d f
or
Ste
el T
anks,
Sta
ndp
ipes
, R
eser
vo
irs,
an
d E
levat
ed T
anks
for
Wat
er
Sto
rage,
AW
WA
, D
100
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 24
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tio
n
(6)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
AP
I-6
20
=
A
mer
ican
Pet
role
um
Inst
itute
Rec
om
men
ded
Rule
s fo
r D
esig
n a
nd C
onst
ruct
ion o
f L
arge
Wel
ded
Lo
w P
ress
ure
Sto
rage
Tan
ks
A
CI
=
Am
eric
an C
on
cret
e In
stit
ute
A
MC
A
=
Air
Mo
vin
g a
nd C
on
dit
ionin
g A
ssoci
atio
n
N
FU
L
=
Nat
ional
Fir
e U
nder
wri
tes
Lab
ora
tory
P
&V
-1
=
AS
ME
Co
de
for
Pum
ps
and V
alves
for
Nucl
ear
Po
wer
, C
lass
I
P
&V
-11
=
A
SM
E C
od
e fo
r P
um
ps
and V
alves
for
Nucl
ear
Po
wer
, C
lass
II
P
&V
-III
=
A
SM
E C
od
e fo
r P
um
ps
and V
alves
for
Nucl
ear
Po
wer
, C
lass
III
II
I-A
=
A
SM
E B
oil
er a
nd P
ress
ure
Ves
sel
Code,
Sec
tion I
II,
Cla
ss A
II
I-B
=
A
SM
E B
oil
er a
nd P
ress
ure
Ves
sel
Code,
Sec
tion I
II,
Cla
ss B
II
I-C
=
A
SM
E B
oil
er a
nd P
ress
ure
Ves
sel
Code,
Sec
tion I
II,
Cla
ss C
S
ee T
able
3-5
7 f
or
HV
AC
des
ign c
odes
5.
Saf
ety r
elat
ed q
ual
ity a
ssura
nce
req
uir
ed:
X =
Yes
; -
= N
o
6.
C
=
Co
nta
inm
ent
R
B
=
Rea
ctor
Buil
din
g
A
B
=
Au
xil
iary
Bu
ildin
g
T
B
=
Turb
ine
Bu
ildin
g
S
B
=
Ser
vic
e B
uil
din
g
D
B
=
Die
sel
Bu
ildin
g
D
H
=
Do
g H
ou
se
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 25
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tio
n
(6)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
O
=
O
utd
oo
rs a
bo
ve
gro
und
B
=
B
uri
ed i
n g
rou
nd
C
W
=
Co
nta
min
ated
war
eho
use
R
F
=
Rad
was
te f
acil
ity
7.
X
=
So
urc
e o
f ra
dia
tion
-
=
No
so
urc
e of
rad
iati
on
P
=
P
oss
ible
so
urc
e of
rad
iait
on
8.
X
=
Des
ign
ed f
or
-
=
No
t d
esig
ned
for
9.
X
=
Pro
tect
ed b
y v
irtu
e o
f lo
cati
on i
n a
str
uct
ure
des
igned
for
torn
ado w
ind a
nd
mis
sile
s
-
=
No
pro
tect
ion
req
uir
ed
10
.
Red
un
dan
t el
ectr
ical
hea
ters
are
suppli
ed
11
.
Tan
k i
s p
rovid
ed w
ith
dia
ph
ragm
mem
bra
ne
for
oxygen e
xcl
usi
on
12
.
AM
CA
Cla
ss I
II a
nd
per
form
ance
tes
ted i
n a
ccord
ance
wit
h A
MC
A S
tandar
d T
est
Code
for
air
mo
vin
g d
evic
es.
13
.
Per
form
ance
tes
t re
qu
ired
.
14
.
Nat
ional
Fir
e P
rote
ctio
n A
ssoci
atio
n N
o.
20
.
15
.
Pu
mp
fo
r th
is s
ervic
e d
esig
ned
an
d m
anufa
cture
d i
n a
ccord
ance
wit
h S
ecti
on I
II o
f A
SM
E B
oil
er a
nd
Pre
ssure
Ves
sel
Co
de
is
eith
er u
nav
aila
ble
or
not
as s
uit
able
for
this
ser
vic
e as
conven
tional
pum
p n
ot
in c
onfo
rman
ce t
o t
he
AS
ME
Co
de.
Co
nven
tio
nal
,
no
n-c
od
e p
um
p w
ill
be
furn
ished
.
16
.
This
ref
ers
to U
pper
an
d L
ow
er C
onta
inm
ent
Ven
tila
tion S
yst
ems.
17
.
Tan
ks
are
des
ign
ed f
or
all
exte
rnal
forc
es d
ue
to s
oil
and w
ater
, in
lcudin
g b
uoyan
cy.
18
.
Th
ese
com
po
nen
ts w
ere
not
buil
t to
appli
cab
le c
odes
and s
tand
ards,
but
hav
e b
een q
ual
ifie
d s
eism
ical
ly.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
(P
ag
e 26
of
26
)
(24
AP
R 2
01
4)
Co
mp
on
ent
Sco
pe
(2
)
Safe
ty
Cla
ss
(3)
Cod
e
(4)
QA
Req
'd
(5)
Loca
tio
n
(6)
Ra
d
Sou
rce
(7)
Sei
smic
(1)
Win
d
(9)
To
rna
do
Mis
sile
(2
2)
OB
E
(8)
SS
E
(8)
19
.
Th
e st
ora
ge
tan
k, it
self
, is
not
des
igned
to r
esis
t a
torn
ado g
ener
ated
mis
sile
; in
stea
d,
a w
all
has
bee
n i
nst
alle
d a
rou
nd t
he
tan
k t
o
elev
atio
n 7
73
+1
to
res
ist
any t
orn
ado g
ener
ated
mis
sile
. T
his
wal
l as
sure
s th
at a
min
imu
m q
uan
tity
of
wat
er i
s av
aila
ble
to
mit
igat
e an
y p
ost
ula
ted
acc
iden
t ca
use
d b
y a
torn
ado
.
20
.
CS
HX
was
rep
lace
d a
t E
OC
-8.
The
confi
gura
tion w
as c
han
ged
to r
ever
se f
low
pat
tern
s; t
he
shel
l has
co
nta
inm
ent
spra
y,
III-
B,
and
tub
es h
ave
raw
lak
e w
ater
, II
I-C
.
21
.
L
ow
er S
up
port
Co
ole
rs –
Funct
ion a
ban
don
ed p
rior
to s
tart
up
. N
ow
air
-coole
d d
ue
to r
adia
tio
n.
22
.
T
urb
ine
mis
sile
s ar
e in
cluded
per
sec
tion 3
.5.1
.2
McGuire Nuclear Station UFSAR Table 3-5 (Page 1 of 1)
(05 APR 2011)
Table 3-5. System Piping Classification
Duke
System
Piping
Class
NRC
Quality
Class
ANS
Safety
Class Code Design Criteria
Designed For Seismic
Loading
A A 1 Class 1, ASME Section III, 1971 Yes
B B 2 Class 2, ASME Section III, 1971 Yes
C C 3 Class 3, ASME Section III, 19711 Yes
D B 2 Class 2, ASME Section III, 1971 No
E D NNS ANSI B31.1.0 (1967) No
F D NNS ANSI B31.1.0 (1967) Yes
G - - ANSI B31.1.0 (1967) No
H - - Duke Power Company
Specifications
No
Note:
Code Applicability: Due to the numerous code references located throughout this SAR, no attempt is
made to revise these references as Codes are amended, superseded or substituted. The code references
specified above are the basis for design and materials. Duke establishes an “effective code date” for
the station in accordance with 10 CFR 50.55a, reviews and may elect to comply with portions of or all
the latest versions of the above Codes unless material and/or design commitments have progressed to a
stage of completion such that it is not practical to make a change. When only portions of Code
Addenda are utilized, the appropriate engineering review of the entire addenda assures that the overall
intent of the Code is still maintained.
1. The Nuclear Service Water System meets the requirements of ANSIB31.7, Class III, which was
the required code at the time of initial design, procurement and installation.
McGuire Nuclear Station UFSAR Table 3-6 (Page 1 of 1)
(05 APR 2011)
Table 3-6. System Valve Classification
Duke
System
Piping
Class
NRC
Quality
Class
ANS
Safety
Class Code Design Criteria
Designed For Seismic
Loading
A A 1 Class 1, ASME Section III, 1971 Yes
B B 2 Class 2, ASME Section III, 1971 Yes
C C 3 Class 3, ASME Section III, 1971 Yes
D B 2 Class 2, ASME Section III, 1971 No
E D NNS ANSI B31.1.0 (1967) No
F D NNS ANSI B31.1.0 (1967) Yes
G - - ANSI B31.1.0 (1967) No
H - - Duke Energy Specifications No
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-7
(P
ag
e 1 o
f 7
)
(09
OC
T 2
01
5)
Ta
ble
3-7
. E
lect
rica
l S
yst
ems
an
d C
om
pon
ents
Su
mm
ary
of
Cri
teri
a
Eq
uip
men
t
Safe
ty
Cla
ss
QA
Req
'd
Loca
tion
Rad
.
En
vir
on
.
Sei
smic
SS
E
To
rna
do
Win
d
Mis
sile
S
cop
e
Air
Co
ndit
ionin
g S
yst
em (
Co
ntr
ol,
Eq
uip
men
t, a
nd
Cab
le R
oom
)
Co
mp
ress
or
Mo
tors
1E
X
A
B
- X
X
X
D
Ven
t F
an M
oto
rs
1E
X
A
B
- X
X
X
D
Ch
ill
Wat
er P
um
p M
oto
rs
1E
X
A
B
- X
X
X
D
Co
ntr
ol
Ro
om
Mak
eup
Fan
Mo
tor
1E
X
A
B
- X
X
X
D
Eq
uip
men
t &
Cab
le R
oo
m M
akeu
p F
an M
oto
r 1E
X
A
B
- X
X
X
D
Ann
ulu
s V
ent
Syst
em
Fan
Moto
rs
1E
X
A
B
X
X
X
X
D
Mo
istu
re S
epar
ator
Ele
ctri
c H
eate
rs
1E
X
A
B
X
- -
- D
Air
Op
erat
ed V
alves
(S
ole
no
ids)
1E
X
A
B
- X
X
X
D
Aux
ilia
ry B
uil
din
g V
ent
Syst
em
ES
F A
ir H
andli
ng U
nit
Moto
rs
1E
X
A
B
- X
X
X
D
Cab
lin
g E
qu
ipm
ent
(Ess
enti
al A
ux
ilia
ries
)
Cab
le S
up
po
rt S
yst
em
1E
X
A
B,C
,RB
X
(Insi
de
Cont.
)
X
X
X
D
Cab
le
1E
X
A
B,C
,RB
X
(Insi
de
Cont.
)
- X
X
D
Chem
ical
an
d V
olu
me
Co
ntr
ol
Syst
em
Ch
g.
Pu
mp
Mo
tor
(Cen
trif
ugal
) 1E
X
A
B
X
X
X
X
W
Bo
ric
Aci
d T
ransf
er P
um
p M
oto
r 1E
X
A
B
- X
X
X
W
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-7
(P
ag
e 2 o
f 7
)
(09
OC
T 2
01
5)
Eq
uip
men
t
Safe
ty
Cla
ss
QA
Req
'd
Loca
tion
Rad
.
En
vir
on
.
Sei
smic
SS
E
To
rna
do
Win
d
Mis
sile
S
cop
e
Sel
ecte
d M
O V
alve
Mo
tors
1E
X
A
B,C
X
X
X
X
D
Con
tain
men
t A
ir R
eturn
Syst
ems
Air
Ret
urn
Fan
Mo
tors
1E
X
C
X
X
X
X
D
H2 S
kim
mer
Fan
Mo
tors
& M
O V
alve
Moto
rs
1E
X
C
X
X
X
X
D
Con
tain
men
t S
pra
y S
yst
em
Co
nta
inm
ent
Sp
ray P
um
p M
oto
rs
1E
X
A
B
X
X
X
X
D
Sel
ecte
d M
O V
alve
Mo
tors
1E
X
A
B
X
X
X
X
D
Con
tain
men
t Is
ola
tio
n S
yst
ems
Co
nta
inm
ent
Iso
lati
on
Val
ve
Moto
rs
1E
X
R
B,C
,AB
X
X
X
X
D
Com
po
nen
t C
oo
lin
g W
ater
Syst
em
Co
mp
onen
t C
oo
lin
g P
um
p M
oto
rs
1E
X
A
B
- X
X
X
D
Sel
ecte
d M
.O. V
alve
Mo
tors
1E
X
A
B
- X
X
X
D
Die
sel
Bu
ildin
g V
enti
lati
on S
yst
em
Die
sel
Ro
om
Sup
ply
Fan
Mo
tors
1E
X
A
B
- X
X
X
D
Pro
po
rtio
nin
g D
amp
ers
1E
X
A
B
- X
X
X
D
Em
ergen
cy D
isel
Au
xil
iary
Syst
ems
Em
ergen
cy D
iese
l G
ener
ato
r 1E
X
A
B
- X
X
X
D
Die
sel
Cra
nk C
ase
VA
C P
um
p M
oto
r 1E
X
A
B
- X
X
X
D
Die
sel
F.O
. T
ran
sfer
Pu
mp
Mo
tor
1E
X
A
B
- X
X
X
D
Die
sel
Gen
. F
.O. B
oo
ster
Pu
mp
Mo
tors
1E
X
A
B
- X
X
X
D
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-7
(P
ag
e 3 o
f 7
)
(09
OC
T 2
01
5)
Eq
uip
men
t
Safe
ty
Cla
ss
QA
Req
'd
Loca
tion
Rad
.
En
vir
on
.
Sei
smic
SS
E
To
rna
do
Win
d
Mis
sile
S
cop
e
Die
sel
L.O
. F
ilte
r P
um
p M
oto
r 1E
X
A
B
- X
X
X
D
Die
sel
600/1
20V
Pan
elb
oar
d
1E
X
A
B
- X
X
X
D
Die
sel
Lube
Oil
Pu
mp
Mo
tors
1E
X
A
B
- X
X
X
D
Die
sel
Jack
et &
In
terc
oole
r P
um
p M
tr
1E
X
A
B
- X
X
X
D
Die
sel
Air
Co
mp
ress
or
Moto
rs
1E
X
A
B
- X
X
X
D
Die
sel
Gen
erat
or
Bat
tery
& C
har
ger
1E
X
A
B
- X
X
X
D
Aux
ilia
ry F
eed
wat
er S
yst
em
Au
xil
iary
Fee
dw
ater
Pu
mp
Mo
tor
1E
X
A
B
- X
X
X
D
Sp
ent
Fuel
Coo
lin
g S
yst
em
Co
oli
ng P
um
p M
oto
rs
1E
X
A
B
X
- -
- D
Del
eted
Per
20
08
Up
dat
e
Nucl
ear
Inst
rum
enta
tio
n S
yst
em
Det
ecto
rs
1E
X
C
X
X
X
X
W
/D
Am
pli
fier
Ass
emb
ly
1E
X
C
X
X
X
X
D
Nu
clea
r In
stru
men
tati
on R
acks
1.
So
urc
e R
ange
Eq
uip
men
t 1E
X
A
B
- X
X
X
D
2.
Inte
rmed
iate
Ran
ge
Eq
uip
men
t 1E
X
A
B
- X
X
X
D
3.
Po
wer
Ran
ge
Eq
uip
. 1E
X
A
B
- X
X
X
W
Pen
etra
tions
1E
X
C
,RB
X
X
X
X
D
4 K
V E
S A
ux
Po
wer
Syst
em
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-7
(P
ag
e 4 o
f 7
)
(09
OC
T 2
01
5)
Eq
uip
men
t
Safe
ty
Cla
ss
QA
Req
'd
Loca
tion
Rad
.
En
vir
on
.
Sei
smic
SS
E
To
rna
do
Win
d
Mis
sile
S
cop
e
4 K
V M
etal
clad
Bu
s 1E
X
A
B
- X
X
X
D
4 K
V M
etal
clad
ES
Sw
itch
gea
r 1E
X
A
B
- X
X
X
D
41
60
/60
0V
Tra
nsf
orm
ers
1E
X
A
B
- X
X
X
D
60
0V
Ess
enti
al A
ux
Po
wer
Syst
em
60
0V
ES
Aux
Po
wer
syst
em
1E
X
A
B
- X
X
X
D
60
0V
ES
Moto
r C
on
tro
l C
ente
rs
1E
X
A
B
- X
X
X
D
60
0/2
08
V E
ssen
tial
Tra
nsf
orm
ers
1E
X
A
B
- X
X
X
D
12
5V
DC
Vit
al I
nst
rum
enta
tio
n &
Co
ntr
ol
Pow
er
Syst
em
12
5V
DC
Bat
tery
Ch
arger
s 1E
X
A
B
- X
X
X
D
12
5V
DC
Bat
teri
es
1E
X
A
B
- X
X
X
D
12
5V
DC
Dis
trib
uti
on
Cen
ters
1E
X
A
B
- X
X
X
D
12
5V
DC
Pan
elb
oar
ds
1E
X
A
B
- X
X
X
D
12
0V
AC
Vit
al P
ow
er S
yst
em
12
5V
DC
/12
0V
AC
Sta
tic
Inver
ters
1E
X
A
B
- X
X
X
D
12
0 A
C V
ital
Po
wer
Pan
elb
oar
ds
1E
X
A
B
- X
X
X
D
Pro
cess
Inst
. &
Co
ntr
ol
Syst
em
Pro
cess
I &
C R
acks
(Pro
tect
ion
) 1E
X
A
B
- X
X
X
W
Pri
Sys
Det
ecto
rs (
Pro
tect
ive)
1E
X
C
,AB
X
X
X
X
W
Sec
Sys
Det
ecto
rs (
Pro
tect
ive)
1E
X
A
B
X
X
X
X
W
Au
x S
ys
Det
ecto
rs (
Pro
tect
ion
) 1E
X
C
,AB
X
X
X
X
W
/D
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-7
(P
ag
e 5 o
f 7
)
(09
OC
T 2
01
5)
Eq
uip
men
t
Safe
ty
Cla
ss
QA
Req
'd
Loca
tion
Rad
.
En
vir
on
.
Sei
smic
SS
E
To
rna
do
Win
d
Mis
sile
S
cop
e
Con
trol
Pan
els
(Cla
ss 1
E C
ircu
its)
Mai
n C
on
tro
l B
oar
d
1E
X
A
B
- X
X
X
D
RC
P V
olt
/Fre
q M
onit
or
Pan
el
1E
X
A
B
- X
X
X
D
Au
x F
eed
wat
er P
anel
s 1E
X
A
B
- X
X
X
D
Au
x S
hutd
ow
n P
anel
s 1E
X
A
B
- X
X
X
D
Die
sel
Gen
erat
or
Co
ntr
ol
Pan
els
1E
X
A
B
- X
X
X
D
HV
AC
Co
ntr
ol
Pan
els
1E
X
A
B
- X
X
X
D
Mis
c T
erm
inat
ion
Cab
inet
s 1E
X
A
B
- X
X
X
D
Rad
ioac
tive
Was
te S
yst
ems
RH
R &
CS
Pu
mp
Ro
om
Su
mp
Pu
mp
Moto
r 1E
X
A
B
X
X
X
X
D
Res
idual
Hea
t R
emo
val
Syst
em
RH
R P
um
p M
oto
rs
1E
X
A
B
X
X
X
X
W
Sel
ecte
d M
.O. V
alve
Mo
tors
1E
X
C
,AB
X
X
X
X
D
Rod
Co
ntr
ol
Syst
em
Rea
ctor
Tri
p S
wit
chgea
r 1E
X
A
B
- X
X
X
W
Saf
ety I
nje
ctio
n S
yst
em
Saf
ety I
nje
ctio
n P
um
p M
oto
rs
1E
X
A
B
X
X
X
X
W
Sel
ecte
d S
ole
no
id V
alves
1E
X
A
B
X
X
X
X
D
Sel
ecte
d M
.O. V
alve
Mo
tors
1E
X
A
B
X
X
X
X
D
Ser
vic
e W
ater
Syst
em (
Nu
clea
r)
Ser
vic
e W
ater
Pu
mp
Mo
tors
1E
X
A
B
- X
X
X
D
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-7
(P
ag
e 6 o
f 7
)
(09
OC
T 2
01
5)
Eq
uip
men
t
Safe
ty
Cla
ss
QA
Req
'd
Loca
tion
Rad
.
En
vir
on
.
Sei
smic
SS
E
To
rna
do
Win
d
Mis
sile
S
cop
e
Mo
tor
Op
erat
ed V
alve
Mo
tors
1E
X
A
B
- X
X
X
D
Rea
ctor
Pro
tect
ion
Syst
em &
En
gin
eere
d S
afet
y
Fea
ture
Act
uat
ion
Syst
em
So
lid
Sta
te P
rote
ctio
n S
ys
Rac
ks
1E
X
A
B
- X
X
X
W
ES
F T
est
Cab
inet
1E
X
A
B
- X
X
X
W
Au
xil
iary
Saf
egu
ard
Cab
inet
s 1E
X
A
B
- X
X
X
W
Ste
am S
upp
ly S
yst
em
Mai
n S
team
Iso
lati
on
Val
ve
So
len
oid
s 1E
X
A
B
- X
X
X
D
Note
:
Th
e in
stru
men
tati
on
des
crib
ed i
n S
ecti
on
s 7.2
thro
ugh 7
.6 i
s su
bje
ct t
o t
he
per
tinen
t re
quir
emen
ts o
f th
e Q
ual
ity A
ssu
ran
ce P
rogra
m.
EX
PL
AN
AT
ION
OF
SY
MB
OL
S
Tab
le H
eadin
gs
Sym
bols
Sco
pe
W
= W
esti
nghouse
D
= D
uke
Saf
ety C
lass
1E
=
Ele
ctri
cal
Saf
ety C
lass
1E
(R
ef. 3.2
.4.1
)
2E
=
Ele
ctri
cal
Saf
ety C
lass
2E
(R
ef. 3.2
.4.1
)
3E
=
Ele
ctri
cal
Saf
ety C
lass
3E
(R
ef. 3.2
.4.1
)
4E
=
Ele
ctri
cal
Saf
ety C
lass
4E
(R
ef. 3.2
.4.1
)
- =
No S
afet
y C
lass
Q.A
. R
eq'd
X
=
Yes
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-7
(P
ag
e 7 o
f 7
)
(09
OC
T 2
01
5)
Eq
uip
men
t
Safe
ty
Cla
ss
QA
Req
'd
Loca
tion
Rad
.
En
vir
on
.
Sei
smic
SS
E
To
rna
do
Win
d
Mis
sile
S
cop
e
- =
No
Lo
cati
on
C
= C
onta
inm
ent
RB
=
Rea
ctor
Buil
din
g
AB
=
Aux.
Bu
ildin
g
TB
=
Turb
ine
Buil
din
g
S
B
= S
ervic
e B
uil
din
g
O
= O
utd
oors
Ab
ove
Gro
und
Rad
En
vir
on
X
= D
esig
ned
for
Rad
. E
nvir
onm
ent
-
= N
ot
Des
igned
For
Sei
smic
S
.S.E
. =
Saf
e S
hu
tdow
n E
arth
quak
e
X
= D
esig
ned
For
- =
Not
Des
igned
For
Torn
ado
X
= P
rote
ctio
n R
equir
ed (
Pro
tect
ed b
y v
irtu
e o
f lo
cati
on
in
a s
tru
cture
des
ign
ed
for
torn
ado
win
d a
nd
mis
sile
s)
- =
No P
rote
ctio
n R
equir
ed
Eq
uip
men
t E
SF
=
Engin
eere
d S
afet
y F
eatu
res
McGuire Nuclear Station UFSAR Table 3-8 (Page 1 of 1)
(14 OCT 2000)
Table 3-8. Tornado Generated Missiles
Tornado Missiles are as defined below:
1. A 2 in. by 4 in. by 12 ft board weighing 40 pounds per cubic foot, end on at a speed of 300 mph.
2. A cross-tie, 7 in. by 9 in. by 8.5 ft weighing 50 pounds per cubic foot at a speed of 300 mph.
3. An automobile weighing 2,000 pounds with an impact area of 20 sq. ft. at 20 ft. above grade at a
speed of 100 mph.
4. A steel pipe 2 in. in diameter by 7 ft. long end on at 100 mph.
McGuire Nuclear Station UFSAR Table 3-9 (Page 1 of 1)
(14 OCT 2000)
Table 3-9. Category 1 Structures and Missiles Protected Against
Structure Types of Missiles Protected Against
Reactor Building Tornado Missiles and Turbine-Generator Missiles
Containment Interior Structures Internal Missiles
Diesel Generator Building Tornado Missiles and Turbine-Generator Missiles
Block Dividing Wall D/G Flywheel Missiles
Auxiliary Building (outside
walls, roof, floors and some
internal walls)
Tornado Missiles, Turbine-Generator Missiles and Selected Internal
Missiles
Spent Fuel Pool Tornado Missiles and Selected Internal Missiles, Turbine-Generator
Missiles
Control Room (outside walls
and roof)
Tornado Missiles and Turbine-Generator Missiles
McGuire Nuclear Station UFSAR Table 3-10 (Page 1 of 1)
(14 OCT 2000)
Table 3-10. CRDM Housing Plug Ejection
Plug Weight: 11 lbs
Plug O.D.: 2.75 in.
Travel, x
(ft)
Velocity, v
(ft/sec)
Kinetic Energy
(ft/lb)
1 240 9,750
2 335 19,900
.
3 370 23,300
4 415 29,200
5 440 33,000
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-1
1 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-1
1.
Dri
ve
Sh
aft
Eje
ctio
n
Dia
met
er =
1.7
5 i
n.
Len
gth
= 3
00
in
.
Wei
gh
t =
12
0 l
bs.
Dri
ve
Sh
aft
Tra
vel
Ou
tsid
e H
ou
sin
g1 (
ft)
Dri
ve
Sh
aft
Vel
oci
ty
(ft/
sec)
Dri
ve
Sh
aft
Kin
etic
En
ergy
(ft
-lb
)
Mis
sile
Sh
ield
2 S
teel
Pla
te T
hic
kn
ess
(in
.)
Mis
sile
Sh
ield
2
Ad
dit
ion
al
Co
ncr
ete
Sla
b
Th
ick
nes
s (i
n.)
1
151
42,9
00
1
---
2
162
49,0
00
1
2.5
3
171
55,0
00
1
10
4
179
60,2
00
1
16
5
189
66,5
00
1
25
10
2
69
134,7
00
No
tes:
1.
Dis
tance
fro
m t
op
of
rod
tra
vel
ho
usi
ng t
o b
ott
om
of
mis
sile
sh
ield
.
2.
Th
ese
thic
kn
esse
s ar
e in
dic
ativ
e o
nly
, an
d s
hie
ld d
esig
n c
an o
pti
miz
e b
etw
een s
teel
and c
oncr
ete
thic
kn
esse
s.
McGuire Nuclear Station UFSAR Table 3-12 (Page 1 of 1)
(14 OCT 2000)
Table 3-12. Drive Shaft and Mechanism Ejection
Missile Weight: 1500 lbs
Impact O.D.: 3.75 in.
Travel, x
(ft)
Velocity
(ft/sec)
Kinetic Energy
(ft-lb)
1 14.3 4,600
2 20.2 9,200
3 24.8 13,800
4 28.6 18,400
5 32.0 23,000
McGuire Nuclear Station UFSAR Table 3-13 (Page 1 of 1)
(14 OCT 2000)
Table 3-13. Temperature Element Assembly Characteristics
1. For a tear around the weld between the boss and the pipe:
Characteristics “without well” “with well”
Flow Discharge Area 0.11 in.2 0.60 in.
2
Thrust Area 7.1 in.2 9.6 in.
2
Missile Weight 11.0 lb 15.2 lb
Area of Impact 3.14 in.2 3.14 in.
2
Missile Weight divided by
Impact Area
3.5 psi 4.84 psi
Velocity 20 ft/sec 120 ft/sec
2. For a tear at the junction between the temperature element assembly and the boss for the “without
well” element and at the junction between the boss and the well for the “with well” element.
Flow Discharge Area 0.11 in2
0.60 in2
Thrust Area 3.14 in2
3.14 in2
Missile Weight 4.0 lb 6.1 lb
Area of Impact 3.14 in2
3.14 in2
Missile Weight divided by
Impact Area
1.27 psi 1.94 psi
Velocity 72 ft/sec 120 ft/sec
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-1
4 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-1
4. P
ress
uri
zer
Sp
ace
Va
lve
Mis
sile
s
W
eigh
t
Flo
w
Dis
charg
e
Are
a
Th
rust
Are
a
Imp
act
Are
a
Wei
gh
t to
Imp
act
Are
a
Ra
tio
Vel
oci
ty
1.
Saf
ety R
elie
f V
alve
Bo
nn
et (
3"
x 6
")
350 l
b
2.8
6 i
n.2
80 i
n.2
24
in
.2
14
.6 p
si
11
0 f
ps
2.
3"
Moto
r O
per
ated
Iso
lati
on
Val
ve
Bo
nn
et (
plu
s M
oto
r an
d S
tem
)
400 l
b
5.5
in.2
113
in.2
28
.3 i
n.2
1
4.1
psi
1
35
fps
3.
2"
Air
Op
erat
ed R
elie
f V
alve
Bo
nn
et
(plu
s st
em)
75 l
b
1.8
in.2
20.7
in.2
20
in
.2
3.7
5 p
si
11
5 f
ps
4.
3"
Air
Op
erat
ed S
pra
y V
alve
Bo
nn
et (
plu
s
stem
)
120 l
b
5.5
in.2
50.3
in.2
50
in
.2
2.4
psi
1
90
fps
5.
4"
Air
Op
erat
ed S
pra
y V
alve
200 l
b
9.3
in.2
50.3
in.2
50
in
.2
4 p
si
19
0 f
ps
McGuire Nuclear Station UFSAR Table 3-15 (Page 1 of 1)
(14 OCT 2000)
Table 3-15. Properties of Credible Turbine Missiles
Missile
Weight
(lb)
Initial
Velocity
fps
Exit
Velocity
fps
Energy (ft-lb)
106
Missile Area ft2(1)
A1 A2 A3
Disc No. 1 3521 Missile
Contained
Disc No. 2 3611 665 341 6.5 4.77 2.55 3.28
Disc No. 3 2741 Missile
Contained
Disc No. 4 3194 629 312 4.8 2.4 1.96 3.60
Disc No. 5 3961 574 345 7.3 3.03 2.52 4.00
Notes:
1. See Figure 3-4.
2. Disc No. 5 controls the thickness of the barrier.
3. or more details on the turbine missile properties, see Section 3.5, Reference No. 4.
McGuire Nuclear Station UFSAR Table 3-16 (Page 1 of 2)
(14 OCT 2000)
Table 3-16. Internal Missiles. (1)(4)
Missile
Penetration
Depth "t"
Inches
Minimum Barrier Thickness
Required, D=3t Inches
CRDM Housing Plug Ejection (FSAR Table 3-10) 2.1 6.3
Drive Shaft Ejection (FSAR Table 3-11) 1.1 3.3
Drive Shaft and Mechanism Ejection (FSAR
Table 3-11)
1.112 3.336
Temperature Element Assembly Missiles (FSAR
Table 3-13)
0.54 1.62
Safety Relief Valve Bonnet (Table 3-14) 1.96 5.88
3" Motor Operated Isolation Valve Bonnet Plus
Motor and Stem (Table 3-14)
1.81 5.43
2" Air Operated Relief Valve Bonnet Plus Stem
(Table 3-14)
0.38 1.14
3" Air Operated Spray Valve Bonnet plus Stem
(Table 3-14)
0.65 1.95
4" Air Operated Spray Valve (Table 3-14) 1.04 3.12
Turbine Missiles (2) (4 )
Disc No. 5 of the Turbine 8.29 24.9
Diesel Generator Missiles(5 )
A 10# Section of the D/G Flywheel 1.7 5.1
Tornado Generated Missiles (3) (4)
A 2" x 4" wooden board @300 mph 3.50 10.50
A Cross Tie 6" x 9" x 8.5' @ 300 mph 3.13 9.39
An Automobile 2000 lbs at speed of 100 mph 0.109 0.327
A steel pipe 2" diamter, 7' long @ 100 mph 2.03 6.09
McGuire Nuclear Station UFSAR Table 3-16 (Page 2 of 2)
(14 OCT 2000)
Missile
Penetration
Depth "t"
Inches
Minimum Barrier Thickness
Required, D=3t Inches
Notes:
1. Barriers for internal missiles include reinforced concrete walls, slabs and other components of the
interior structure subjected to the paths of these missiles. Whenever a steel barrier is encountered
by the missile, the required thickness of this barrier becomes 1/12 of the thickness required for a
reinforced concrete barrier (see Reference 2).
2. Barriers are 1) Reactor Building dome and 2) Auxiliary Building roof.
3. Barriers are reinforced concrete slabs and walls, e.g.,: a) Reactor Building dome, b) Reactor
Building shell, and c) Auxiliary Building roof and appropriate side walls.
4. The penetration depths of the reinforced concrete missile barriers are based on a concrete strength
of 5000 psi.
5. Barrier is the reinforced block wall separating Diesel Generator Rooms A from B.
McGuire Nuclear Station UFSAR Table 3-17 (Page 1 of 1)
(09 OCT 2015)
Table 3-17. Minimum Barrier Thicknesses for all Category 1 Structures For Which Missile
Protection Is Provided
Structure
Minimum Reinforced Concrete
Missile Barriers Thickness Inches
Reactor Building Cylindrical Shell 36
Reactor Building Dome 27
Reactor Building Interior Structure
1. Walls 24
2. Slabs 24
Auxiliary Building
1. Main Building
Roof 28(1)
Walls 12
2. Diesel Generator Building
Roof 28
Walls 36
Dividing Wall 12(2)
3. Spent Fuel Storage Area
Roof 28
Walls 24
4. New Fuel Storage Vault
Roof 30
Walls 24
5. RN Manway Missile Barrier 12
Notes:
1. The thickness provided is considered as one independent thickness or the accumulation of several
successive slabs.
2. Thickness is for grout filled, reinforced concrete masonry wall.
McGuire Nuclear Station UFSAR Table 3-18 (Page 1 of 1)
(14 OCT 2000)
Table 3-18. High Energy Mechanical Piping Systems Analyzed for Consequences of Postulated
Piping Breaks
System or Portion Thereof Operating During
Normal Reactor Operation
System
Identification
Pipe Break
Protection Method
High Energy Safety Related Systems
Steam Generator Blowdown Recycle System BB (a) (b)
Auxiliary Feedwater System (Motor Driven
Pump Portion)
CA (a) (b)
Nitrogen System GN (a)(b)
Reactor Coolant System NC (a) (b)
Residual Heat Removal System ND (a) (b)
Safety Injection System NI (a) (b)
Nuclear Sampling System NM (a) (b)
Boron Thermal Regeneration System NR (a)
Chemical and Volume Control System
(Letdown Portion and Sealwater Injection)
NV (a) (b)
Other High Energy Systems
Feedwater System CF (a) (b) (c)
Main Steam Supply to Auxiliary Equipment SA (a)
Main Steam System SM (a) (b) (c)
Main Steam Vent to Atmosphere System SV (a)
Pipe Whip Protection Methods Legend:
(a) Physical Separation
(b) Piping Restraints
(c) Enclosures, structural, guard pipes, etc., (designed specifically for pipe break).
Note:
1. High Energy Systems may contain moderate energy portions; however, for brevity, high energy
systems are only listed in this table.
McGuire Nuclear Station UFSAR Table 3-19 (Page 1 of 2)
(09 OCT 2015)
Table 3-19. Moderate Energy Mechanical Piping Systems Analyzed for Consequences of Postulated
Piping Breaks
System or Portion Thereof Operating During
Normal Reactor Operation
System
Identification Pipe Break Protection Method
Moderate Energy Safety Related Systems
Auxiliary Feedwater System (Turbine Driven
Portion)
CA (a)
Diesel Fuel Oil System FD (a)
Refueling Water system FW (a)
Component Cooling System KC (a)
Diesel Generator Cooling Water System KD (a)
Spent Fuel Cooling System KF (a)
Diesel Generator Lube Oil System LD (a)
Boron Recycle System NB (a)
Residual Heat Removal System ND (a)
Containment Spray System NS (a)
Nuclear Service Water System RN (a)
Containment Ventilation Cooling Water
System
RV (a)
Main Steam Supply to Aux. Equipment SA (a)
FWP Turbine Exhaust TE (a)
Diesel Generator Starting Air System VG (a)
Gaseous Waste Recycle System WG (a)
Liquid Waste Recycle System WL (a)
Solid Waste Disposal System WS (a)
Deleted Per 2015 Update
Other Moderate Energy Systems
Auxiliary Steam System AS (a)
Recirculated Cooling Water System KR (a)
Ice Condenser Refrigeration System NF (a)
Fire Protection System RF (a)
Equipment Decontamination System WE (a)
Liquid Waste Monitor & Disposal System WM (a)
Chemical Addition System YA (a)
McGuire Nuclear Station UFSAR Table 3-19 (Page 2 of 2)
(09 OCT 2015)
System or Portion Thereof Operating During
Normal Reactor Operation
System
Identification Pipe Break Protection Method
Control Area Chilled Water System YC (a)
Plant Heating System YH (a)
Make-up Demineralizer System YM (a)
Pipe Whip Protection Methods Legends:
(a) Physical Separation
(b) Piping Restraints
(c) Enclosures, structural, guard pipes, etc., (Designed specifically for pipe break)
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
0 (
Pa
ge
1 o
f 6
)
(06
OC
T 2
00
3)
Ta
ble
3-2
0.
Com
pa
riso
n o
f D
uk
e P
ipe
Ru
ptu
re C
rite
ria A
nd
NR
C R
equ
irem
ents
Of
Bra
nch
Tec
hn
ical
Po
siti
on
s A
PC
SB
3-1
(N
ov
emb
er
19
75
), M
EB
3-1
(J
uly
19
81
), a
nd
NR
C R
egu
lato
ry G
uid
e 1.4
6 (
May 1
97
3)
NR
C C
rite
ria
Du
ke
Cri
teri
a
AP
CS
B 3
-1,
Sec
tion
B.2
.c
SA
R S
ecti
on
3.6
.2.2
Sec
tion
B.2
.c. re
qu
ires
that
pip
ing b
etw
een c
onta
inm
ent
isola
tion
val
ves
be
pro
vid
ed w
ith
pip
e w
hip
res
trai
nts
cap
able
of
resi
stin
g
ben
din
g a
nd
tors
ion
al m
om
ents
pro
du
ced
by a
post
ula
ted
fai
lure
eit
her
up
stre
am o
r d
ow
nst
ream
of
the
val
ves
. A
lso, th
e re
stra
ints
should
be
des
igned
to w
ith
stan
d t
he
load
ings
fro
m p
ost
ula
ted f
ailu
res
so t
hat
nei
ther
iso
lati
on
val
ve
op
erab
ilit
y n
or
the
leak
tight
inte
gri
ty o
f th
e
conta
inm
ent
wil
l b
e im
pai
red
.
Ter
min
al e
nds
sho
uld
be
con
sid
ered
to
ori
gin
ate
at a
poin
t ad
jace
nt
to
the
req
uir
ed p
ipe
wh
ip r
estr
aints
.
Du
ke
crit
eria
is
rough
ly e
qu
ival
ent
to N
RC
cri
teri
a as
cla
rifi
ed b
elo
w:
Th
e co
nta
inm
ent
stru
ctura
l in
tegri
ty i
s p
rovid
ed f
or
all
po
stula
ted
pip
e
rup
ture
s. I
n a
ddit
ion, fo
r an
y p
ost
ula
ted r
uptu
re c
lass
ifie
d a
s a
loss
of
coola
nt
acci
den
t, t
he
des
ign l
eakti
gh
tnes
s o
f th
e co
nta
inm
ent
fiss
ion
pro
duct
bar
rier
wil
l be
mai
nta
ined
.
Pen
etra
tion d
esig
n i
s dis
cuss
ed i
n S
AR
Sec
tio
n 3
.9.2
.8. T
his
sec
tion
also
dis
cuss
ed p
enet
rati
on g
uar
d p
ipe
des
ign
cri
teri
a.
Ter
min
al e
nds
are
def
ined
as
pip
ing o
rigin
atin
g a
t st
ruct
ure
or
com
ponen
t th
at a
ct a
s ri
gid
co
nst
rain
t to
th
e p
ipin
g t
her
mal
exp
ansi
on
.
AP
CS
B 3
-1,
Sec
tion
B.2
.d
1.
Th
e p
rote
ctiv
e m
easu
res,
str
uct
ure
s, a
nd g
uar
d p
ipes
should
no
t
pre
ven
t th
e ac
cess
req
uir
ed t
o c
ond
uct
inse
rvic
e in
spec
tion
exam
inat
ion
.
2.
Fo
r p
ort
ion
s of
pip
ing b
etw
een
con
tain
men
t is
ola
tion
val
ves
, th
e
exte
nt
of
inse
rvic
e ex
amin
atio
ns
com
ple
ted
duri
ng e
ach i
nsp
ecti
on
inte
rval
sh
ou
ld p
rovid
e 1
00 p
erce
nt
vo
lum
etri
c ex
amin
atio
n o
f
circ
um
fere
nti
al a
nd
lo
ngit
ud
inal
pip
e w
eld
s.
3.
Insp
ecti
on
po
rts
sho
uld
be
pro
vid
ed i
n g
uar
d p
ipes
to
per
mit
the
req
uir
ed e
xam
inat
ion
of
circ
um
fere
nti
al w
elds.
Insp
ecti
on p
ort
s
sho
uld
not
be
loca
ted
in
th
at p
ort
ion
of
guar
d p
ipe
pas
sing t
hro
ugh
the
annu
lus.
4.
Th
e ar
eas
subje
ct t
o e
xam
inat
ion
sh
ou
ld b
e def
ined
in a
ccord
ance
wit
h E
xam
inat
ion
Cat
ego
ries
C-F
an
d C
-G f
or
Cla
ss 2
pip
ing
wel
ds
in T
able
s IW
C-2
52
0.
SA
R S
ecti
on
5.2
.8
Du
ke
crit
eria
is
dif
fere
nt
than
the
NR
C c
rite
ria
du
e to
th
e co
de
effe
ctiv
e dat
e as
des
crib
ed b
elo
w:
AS
ME
Cla
ss 2
pip
ing w
elds
wil
l b
e in
spec
ted
in
acc
ord
ance
wit
h
Tab
les
ISC
-251 o
f S
ecti
on X
I (1
97
1),
th
rou
gh
Win
ter
19
71
Ad
den
da,
of
the
AS
ME
Code,
as
acce
ssib
ilit
y p
erm
its.
In
serv
ice
insp
ecti
on
pro
gra
m r
equir
emen
ts a
re g
iven
in
SA
R S
ecti
on
5.2
.8.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
0 (
Pa
ge
2 o
f 6
)
(06
OC
T 2
00
3)
NR
C C
rite
ria
Du
ke
Cri
teri
a
AP
CS
B 3
-1,
Ap
pen
dix
A
Hig
h E
ner
gy f
luid
syst
ems
are
def
ined
as
those
syst
ems
that
, duri
ng
no
rmal
pla
nt
con
dit
ion
s, a
re e
ith
er i
n o
per
atio
n o
r m
ainta
ined
pre
ssuri
zed u
nd
er c
on
dit
ions
wh
ere
eith
er o
r b
oth
of
the
foll
ow
ing a
re
met
:
1.
max
imu
m o
per
atin
g t
emp
erat
ure
exce
eds
200°F
, or
2.
max
imu
m o
per
atin
g p
ress
ure
exce
eds
275 p
sig.
SA
R S
ecti
on
3.6
.1.2
Du
ke
crit
eria
is
the
sam
e as
NR
C c
rite
ria
wit
h e
xp
ansi
on
of
def
init
ion
as c
lari
fied
bel
ow
:
1.
Non-l
iquid
syst
ems
wit
h a
max
imu
m n
orm
al p
ress
ure
les
s th
an
275 p
sig a
re n
ot
consi
der
ed h
igh
en
ergy r
egar
dle
ss o
f th
e
tem
per
ature
. S
uch
low
pre
ssu
re s
yst
em (
i.e.
, A
ux
ilia
ry S
team
, 5
0
psi
g,
34
0°F
) do n
ot
con
tain
su
ffic
ient
sen
sib
le e
ner
gy t
o d
evel
op
sudden
, ca
tast
rop
hic
fai
lure
s. P
ropag
atio
n o
f a
crac
k t
o a
full
fail
ure
is
extr
emel
y u
nli
kel
y.
2.
Exce
pti
on t
o t
he
200°F
th
resh
old
for
hig
h e
ner
gy s
yst
ems
is t
aken
for
non-w
ater
syst
ems
such
as
eth
yle
ne
gly
col.
Su
ch s
yst
ems
that
op
erat
e at
les
s th
an t
hei
r b
oil
ing t
emp
erat
ure
are
co
nsi
der
ed
moder
ate
ener
gy.
AP
CS
B 3
-1,
Ap
pen
dix
A
In p
ipin
g r
uns
wh
ich
are
mai
nta
ined
pre
ssuri
zed d
uri
ng n
orm
al p
lant
cond
itio
ns
for
on
ly a
port
ion
of
the
run
(i.
e., up
to t
he
firs
t norm
ally
shut
val
ve)
a t
erm
inal
en
d o
f su
ch r
uns
is t
he
pip
ing c
onn
ecti
on t
o t
his
close
d v
alve.
SA
R S
ecti
on
3.6
.2.2
.1
Du
ke
crit
eria
is
dif
fere
nt
fro
m N
RC
cri
teri
a as
des
crib
ed a
nd
ju
stif
ied
bel
ow
:
Ter
min
al e
nds
are
con
sider
ed a
t p
ipin
g o
rigin
atin
g a
t st
ruct
ure
or
com
ponen
ts t
hat
act
as
rigid
co
nst
rain
t to
the
pip
ing t
her
mal
exp
ansi
on. T
yp
ical
ly,
the
anch
ors
ass
um
ed f
or
the
code
stre
ss a
nal
ysi
s
wo
uld
be
term
inal
end
s. S
tres
ses
in t
he
syst
em e
ither
sid
e o
f th
e cl
ose
d
val
ve
wil
l be
about
the
sam
e; t
her
efore
, te
rmin
al e
nd
cla
ssif
icat
ion
bas
ed o
n c
onst
rain
t an
d h
igh
str
esse
s ar
e n
ot
appli
cab
le.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
0 (
Pa
ge
3 o
f 6
)
(06
OC
T 2
00
3)
NR
C C
rite
ria
Du
ke
Cri
teri
a
ME
B 3
-1,
Sec
tio
n B
.1.b
(6)
Sec
tion
B.1
.b(6
) re
qu
ires
that
gu
ard
pip
e as
sem
bli
es b
etw
een
conta
inm
ent
iso
lati
on
val
ves
mee
t th
e fo
llow
ing r
equir
emen
ts:
1.
Th
e d
esig
n p
ress
ure
and
tem
per
atu
re s
hould
not
be
less
than
the
max
imu
m o
per
atin
g t
emp
erat
ure
and
pre
ssure
of
the
encl
ose
d p
ipe
und
er n
orm
al p
lan
t co
ndit
ion
s.
2.
Th
e d
esig
n s
tres
s li
mit
s of
Par
agra
ph
NE
-3131(c
) sh
ould
not
be
exce
eded
und
er t
he
load
ing a
ssoci
ated
wit
h d
esig
n p
ress
ure
an
d
tem
per
ature
in
co
mb
inat
ion w
ith
th
e sa
fe s
hutd
ow
n e
arth
quak
es.
3.
Gu
ard p
ipe
asse
mb
lies
sh
ou
ld b
e su
bje
cted
to a
sin
gle
pre
ssure
tes
t
at a
pre
ssure
equ
al t
o d
esig
n p
ress
ure
.
SA
R S
ecti
on
3.9
.2.8
Du
ke
crit
eria
is
dif
fere
nt
fro
m N
RC
cri
teri
a as
des
crib
ed a
nd
ju
stif
ied
bel
ow
:
Gu
ard p
ipes
pro
vid
ed b
etw
een
con
tain
men
t is
ola
tio
n v
alves
is
des
igned
in a
ccord
ance
wit
h S
AR
Sec
tio
n 3
.9.2
.8.
Gu
ardp
ipe
thic
knes
ses
wer
e dev
eloped
usi
ng t
he
crit
eria
of
AS
ME
Co
de
Cas
e
16
06 a
nd t
he
appro
pri
ate
load
ing c
om
bin
atio
n a
nd
str
ess
lim
its
of
Tab
le 3
-48
. G
uar
d p
ipes
are
subje
cted
to
a p
ress
ure
tes
t as
req
uir
ed b
y
the
mat
eria
l sp
ecif
icat
ion b
efo
re w
eld
ing t
o t
he
pen
etra
tio
n a
ssem
bly
.
It i
s im
pra
ctic
al t
o t
est
guar
d p
ipes
in
the
fin
ish
ed p
enet
rati
on
asse
mb
ly d
ue
to t
he
confi
gu
rati
on
an
d p
ote
nti
al d
amag
e to
inte
rnal
pro
cess
pip
e an
d a
ssoci
ated
in
sula
tio
n.
Ind
epen
den
t d
esig
n a
nal
ysi
s
hav
e b
een c
onduct
ed t
o p
rovid
e as
sura
nce
th
at D
uke
pen
etra
tio
n
des
igns
are
acce
pta
ble
. In
ad
dit
ion
, th
e ex
ten
t o
f N
DT
co
nd
uct
ed o
n
gu
ard p
ipes
to f
lued
hea
d b
utt
wel
d i
s su
ch t
o a
ssure
inte
gri
ty o
f
des
ign.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
0 (
Pa
ge
4 o
f 6
)
(06
OC
T 2
00
3)
NR
C C
rite
ria
Du
ke
Cri
teri
a
ME
B 3
-1,
Sec
tio
ns
B.1
.c(3
)
Bre
aks
in n
on
-nu
clea
r p
ipin
g s
ho
uld
be
post
ula
ted a
t th
e fo
llow
ing
loca
tio
n:
1.
Ter
min
al e
nd
s,
2.
At
each
inte
rmed
iate
pip
e fi
ttin
g, w
eld
ed a
ttac
hm
ent,
and v
alve.
No
te:
PE
R G
EN
ER
IC L
ET
TE
R 8
7-1
1,
AR
BIT
RA
RY
INT
ER
ME
DIA
TE
BR
EA
KS
AR
E N
OT
RE
QU
IRE
D T
O B
E
PO
ST
UL
AT
ED
.
SA
R S
ecti
on
3.6
.2.2
.1
Du
ke
crit
eria
is
rough
ly e
qu
ival
ent
to N
RC
cri
teri
a as
des
crib
ed a
nd
just
ifie
d b
elow
:
Bre
aks
in D
uke
Cla
ss F
pip
ing (
no
n-n
ucl
ear,
sei
smic
) ar
e p
ost
ula
ted
at
term
inal
ends
and a
t in
term
edia
te l
oca
tio
ns
bas
ed o
n t
he
use
of
AS
ME
Sec
tion I
II a
nal
ysi
s te
chniq
ues
, th
e sa
me
as D
uke
Cla
ss B
an
d C
pip
ing.
Duke
Cla
ss F
pip
ing i
s co
nst
ruct
ed i
n a
cco
rdan
ce w
ith
AN
SI
B3
1.1
and i
s dynam
ical
ly a
nal
yze
d a
nd
res
trai
ned
for
seis
mic
load
ings
sim
ilar
to A
SM
E S
ecti
on I
II p
ipin
g.
Mat
eria
ls a
re s
pec
ifie
d, pro
cure
d,
rece
ived
, st
ore
d,
and i
ssued
un
der
Du
ke'
s Q
A p
rogra
m s
imil
ar t
o
AS
ME
Sec
tion I
II m
ater
ials
ex
cep
t th
at c
erti
fica
te o
f co
mp
lian
ce i
n
lieu
of
mil
l te
st r
eport
s ar
e ac
cepta
ble
on
min
or
com
po
nen
ts,
and
const
ruct
ion
docu
men
tati
on f
or
erec
ted
mat
eria
ls i
s n
ot
un
iqu
ely
mai
nta
ined
. C
onst
ruct
ion d
ocu
men
tati
on
fo
r er
ecte
d m
ater
ials
is
gen
eric
ally
mai
nta
ined
. M
TR
are
req
uir
ed f
or
the
bulk
of
pip
ing
mat
eria
ls.
ME
B 3
-1,
Sec
tio
n B
.2.e
Thru
-wal
l cr
acks
may
be
po
stula
ted
in
stea
d o
f bre
aks
in t
hose
flu
id
syst
ems
that
qu
alif
y a
s h
igh e
ner
gy f
luid
syst
ems
for
sho
rt o
per
atio
nal
per
iods.
This
op
erat
ional
per
iod
is
def
ined
as
about
2 p
erce
nt
of
the
tim
e th
at t
he
syst
em o
per
ates
as
a m
od
erat
e en
ergy f
luid
syst
em.
SA
R S
ecti
on
3.6
.1.2
Du
ke
crit
eria
is
rough
ly e
qu
ival
ent
to N
RC
cri
teri
a as
cla
rifi
ed b
elo
w:
Th
e op
erat
ional
per
iod t
hat
cla
ssif
ies
such
syst
ems
as m
od
erat
e en
ergy
in e
ither
:
1.
One
per
cent
of
the
norm
al o
per
atin
g l
ifes
pan
of
the
pla
nt,
or
2.
Tw
o p
erce
nt
of
the
tim
e p
erio
d r
equir
ed t
o a
cco
mp
lish
its
syst
em
des
ign f
unct
ion.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
0 (
Pa
ge
5 o
f 6
)
(06
OC
T 2
00
3)
NR
C C
rite
ria
Du
ke
Cri
teri
a
Reg
ula
tory
Gu
ide
1.4
6
Lo
ngit
ud
inal
bre
aks
are
po
stu
late
d i
n p
ipin
g r
uns
4 i
nch
es n
om
inal
pip
e si
ze a
nd l
arger
. C
ircu
mfe
ren
tial
bre
aks
are
post
ula
ted i
n p
ipin
g
runs
exce
edin
g 1
in
ch n
om
inal
pip
e si
ze.
SA
R S
ecti
on
3.6
.2.2
.1
Du
ke
crit
eria
is
the
sam
e as
NR
C B
ran
ch T
ech
nic
al P
osi
tio
n A
PC
SB
3-1
and r
oughly
equiv
alen
t to
Reg
ula
tory
Gu
ide
1.4
6 w
ith
exp
ansi
on
of
def
init
ion
as
des
crib
ed b
elo
w:
Lo
ngit
udin
al b
reak
s ar
e p
ost
ula
ted
in
pip
ing r
un
s 4
inch
es n
om
inal
pip
e si
ze a
nd l
arger
exce
pt
that
lo
ngit
udin
al b
reak
s ar
e n
ot
post
ula
ted
at t
erm
inal
ends
wher
e th
e p
ipin
g h
as n
o l
on
git
udin
al w
eld
s.
Reg
ula
tory
Gu
ide
1.4
6
A w
hip
pin
g p
ipe
sho
uld
be
con
sid
ered
cap
able
of
rup
turi
ng a
n
imp
acte
d p
ipe
of
smal
ler
nom
inal
pip
e si
ze a
nd
lig
hte
r w
all
thic
kn
ess.
SA
R S
ecti
on
3.6
.2.2
Ite
m 1
0
Du
ke
crit
eria
is
the
sam
e as
NR
C B
ran
ch T
ech
nic
al P
osi
tio
n A
PC
SB
3-1
and r
oughly
equiv
alen
t to
Reg
ula
tory
Gu
ide
1.4
6 w
ith
exp
ansi
on
of
def
init
ion
as
des
crib
ed b
elo
w:
Th
e en
ergy a
ssoci
ated
wit
h a
wh
ippin
g p
ipe
is c
on
sid
ered
cap
able
of
(a)
ruptu
ring i
mp
acte
d p
ipes
of
smal
ler
no
min
al p
ipe
size
s, a
nd
(b)
dev
elop
ing t
hru
-wal
l cr
acks
in l
arger
no
min
al p
ipe
size
s w
ith t
hin
ner
wal
l th
icknes
ses.
Reg
ula
tory
Gu
ide
1.4
6
Mea
sure
s fo
r re
stra
int
agai
nst
pip
e w
hip
pin
g n
eed n
ot
be
pro
vid
ed f
or
pip
ing w
her
e:
1.
the
des
ign
tem
per
ature
is
20
0°F
or
less
, an
d
2.
the
des
ign
pre
ssu
re i
s 2
75
psi
g o
r le
ss.
SA
R S
ecti
on
3.6
.1.2
Du
ke
crit
eria
is
rough
ly e
qu
ival
ent
to N
RC
Bra
nch
Tec
hn
ical
Po
siti
on
AP
CS
B 3
-1 a
nd d
iffe
rs f
rom
Regu
lato
ry G
uid
e 1
.46
wit
h e
xp
ansi
on
of
def
init
ion a
s des
crib
ed b
elow
:
Hig
h e
ner
gy p
ipin
g i
s re
vie
wed
fo
r p
ipe
wh
ipp
ing a
nd
is
def
ined
as
tho
se s
yst
ems
that
duri
ng n
orm
al p
lant
con
dit
ion
s ar
e ei
ther
in
op
erat
ion o
r m
ainta
ined
pre
ssu
rize
d u
nd
er c
on
dit
ion
s w
her
e ei
ther
or
bo
th o
f th
e fo
llow
ing a
re m
et:
1.
max
imu
m t
emp
erat
ure
ex
ceed
s 2
00
°F,
or
2.
max
imu
m p
ress
ure
exce
eds
27
5 p
sig,
exce
pt
that
(1)
no
n-l
iqu
id
pip
ing s
yst
em w
ith a
max
imu
m p
ress
ure
les
s th
an o
r eq
ual
to
275
psi
g a
re n
ot
consi
der
ed h
igh
en
ergy r
egar
dle
ss o
f th
e te
mp
erat
ure
,
and (
2)
for
liquid
syst
ems
oth
er t
han
wat
er, th
e at
mo
sph
eric
boil
ing t
emp
erat
ure
can
be
app
lied
.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
0 (
Pa
ge
6 o
f 6
)
(06
OC
T 2
00
3)
NR
C C
rite
ria
Du
ke
Cri
teri
a
S
yst
ems
are
clas
sifi
ed a
s m
od
erat
e en
ergy i
f th
e to
tal
tim
e th
at e
ither
of
the
above
condit
ion
s ar
e m
et i
s le
ss t
han
eit
her
:
1.
one
(1)
per
cent
of
the
oper
atin
g l
ifes
pan
of
the
pla
nt,
or
2.
two (
2)
per
cent
of
the
tim
e p
erio
d r
equir
ed t
o a
cco
mp
lish
its
syst
em d
esig
n f
un
ctio
n.
No
te:
1.
Pip
e bre
aks
in t
he
RC
S p
rim
ary l
oop
are
not
consi
der
ed i
n c
erta
in a
spec
ts o
f p
lant
des
ign,
as d
efin
ed i
n R
efer
ence
3 o
f S
ecti
on
3.6
.6.
McGuire Nuclear Station UFSAR Table 3-21 (Page 1 of 1)
(06 OCT 2003)
Table 3-21. Postulated Break Locations in Reactor Coolant Loops
Location of Postulated Rupture Type
1. Reactor Vessel Inlet Nozzle1 Circumferential
2. Reactor Vessel Outlet Nozzle1 Circumferential
3. Steam Generator Inlet Nozzle1 Circumferential
4. Steam Generator Outlet Nozzle1 Circumferential
5. Reactor Coolant Pump Inlet Nozzle1 Circumferential
6. Reactor Coolant Pump Outlet Nozzle1 Circumferential
7. 50° Elbow on the Intrados1 Longitudinal
8. Loop Closure Weld in Crossover Leg1 Circumferential
9. Residual Heat Removal (RHR) Line/Primary
Coolant Loop Connection
Circumferential (Viewed from the RHR line)
10. Accumulator (ACC) Line/Primary Coolant
Loop Connection
Circumferential (Viewed from ACC line)
11. Pressurizer Surge (PS) Line/Primary Coolant
Loop Connection
Circumferential (Viewed from the PS line)
Note:
1. Reference 1 of Section 3.6.6 defines the original basis for postulating pipe breaks in the Reactor
Coolant System Primary Loop. References 3 and 4 of Section 3.6.6 provide the basis for
eliminating the previously postulated reactor coolant system pipe breaks with the exception of
those breaks at branch connections from certain aspects of design considerations.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
2 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-2
2.
Com
pa
riso
n o
f A
ctu
al
Mo
men
ts T
o R
efer
ence
Fati
gu
e A
naly
sis
Mom
ents
No
de
No
.1
Fati
gu
e A
na
lysi
s L
oad
ings
Use
d I
n F
ati
gu
e A
naly
sis
McG
uir
e L
oa
din
gs
Cu
mu
lati
ve
Usa
ge
Fa
cto
r S
I (p
si)2
S
I/S
m1
Mi (
in-l
bs)
(O
BE
Mom
ents
)
Mi (
in-l
bs)
(Th
erm
al
Exp
an
sion
Mom
ents
)
Mi (
in-l
bs)
(O
BE
Mo
men
ts)
Mi (
in-l
bs)
(Th
erm
al
Exp
an
sio
n
Mo
men
ts)
40
4
.63
2
94
,77
2
5.2
6
.341 x
10
8
.243 x
10
8
.01
64
x 1
08
.19
9 x
10
8
41
3
.00
93
65
,50
9
3.6
4
.243 x
10
8
.163 x
10
8
.01
13
x 1
08
.12
2 x
10
8
41
5
.26
56
75
,52
8
4.1
9
.243 x
10
8
.203 x
10
8
.02
00
x 1
08
.15
3 x
10
8
43
8
.03
82
70
,74
4
3.9
4
.266 x
10
8
.536 x
10
7
.05
38
x 1
08
.04
7 x
10
8
45
9
.00
0
33
,40
6
1.8
5
.211 x
10
8
.837 x
10
8
.13
63
x 1
07
.07
3 x
10
8
46
8
.00
60
61
,10
0
3.3
9
.29 x
10
8
.729 x
10
7
.08
49
x 1
08
.05
0 x
10
8
48
4
.09
59
81
,82
0
4.5
4
.29 x
10
8
.811 x
10
7
.11
50
x 1
08
.05
7 x
10
8
No
tes:
1.
Th
e lo
op
clo
sure
wel
d, R
HR
lin
e co
nnec
tio
n, ac
cum
ula
tor
line
connec
tion a
nd s
urg
e li
ne
connec
tio
n l
oca
tio
ns
hav
e
not
bee
n i
ncl
ud
ed i
n t
his
tab
le s
ince
sel
ecti
on o
f th
ese
loca
tion
s fo
r post
ula
ted b
reak
s is
ind
epen
den
t of
det
aile
d s
tres
s
and
fat
igu
e an
alyse
s. A
lso
, n
od
e n
um
ber
s ar
e def
ined
in W
CA
P-8
172.
2.
SI
= m
axim
um
pri
mar
y p
lus
seco
nd
ary s
tres
s in
tensi
ty r
ange
com
pute
d u
sing E
qu
atio
n 1
0 o
f p
arag
rap
h N
B3
65
3 o
f
AS
ME
, S
ecti
on I
II. W
hen
3S
m, th
e li
mit
of
Equat
ion
10,
is e
xce
eded
, th
e re
quir
emen
ts i
s N
B3653
.6 a
re u
sed
.
Sp
ecif
ical
ly, E
qu
atio
ns
12
an
d 1
3 a
re s
atis
fied
and a
fac
tor
Ke
is u
sed i
n t
he
fati
gue
anal
ysi
s (E
qu
atio
n 1
4).
McGuire Nuclear Station UFSAR Table 3-23 (Page 1 of 1)
(27 MAR 2002)
Table 3-23. Deleted Per 2002 Update
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
4 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-2
4.
Exce
pti
on
s to
Cri
teri
a.
Pre
sente
d i
n F
SA
R S
ecti
on 3
.6 f
or
the
Per
form
ance
of
the
Pip
e B
reak
An
alysi
s
Sy
stem
E
xce
pti
on
R
easo
n f
or
Exce
pti
on
A
lter
na
tiv
e to
Cri
teri
a
Saf
ety
Inje
ctio
n
(10"
accu
mu
lato
r
lines
)
Pip
e bre
ak r
estr
ain
ts a
re n
ot
pro
vid
ed
for
po
stu
late
d b
reak
s at
eig
ht
loca
tions
in t
he
10"
accu
mu
lato
r li
nes
insi
de
con
tain
men
t.
Const
ruct
ion o
f re
stra
ints
would
tra
nsf
er
larg
e lo
ads
to t
he
shie
ld w
all
requir
ing a
num
ber
of
larg
e an
chor
bolt
s. S
ince
the
shie
ld w
all
is h
eavil
y r
einfo
rced
,
inst
alla
tion o
f hig
h t
ensi
on
anch
or
bolt
s
is i
mp
oss
ible
. E
xtr
eme
conges
tion i
n t
he
area
furt
her
pro
hib
its
an a
deq
uat
e
rest
rain
t des
ign.
Inse
rvic
e in
spec
tio
n w
ith t
he
addit
ion
of
mo
nit
ori
ng u
nid
enti
fied
RC
S L
eakag
e
uti
lizi
ng t
he
RC
S L
eakag
e D
etec
tion
Syst
em i
s p
rovid
ed f
or
the
po
stula
ted
bre
ak l
oca
tio
ns.
Th
ese
mea
sure
s ar
e
con
sid
ered
equ
ival
ent
to a
rup
ture
rest
rain
t, a
nd t
her
efo
re,
adeq
uat
e
pro
tect
ion
is
pro
vid
ed f
or
the
po
stu
late
d
bre
aks.
McGuire Nuclear Station UFSAR Table 3-25 (Page 1 of 1)
(14 OCT 2000)
Table 3-25. Damping Values for Westinghouse Supplied Equipment(6)
Item
Damping (Percent of Critical)
Normal / Upset
Conditions Faulted Condition
OBE SSE/DBA
Primary Coolant Loop System - Components 2 4(3)
Primary Coolant Loop System - Large Piping1 2
(7) 4
(7)
Small Piping ½, 1(2)
2
Welded Steel Structures 2 4(5)
Bolted and/or Riveted Steel Structures 4 7(4)
Control Rod Drive, Mechanisms & Support
System
5(5)
5(3)
Fuel Assemblies 7(5)
9(3)
Note:
1. Generally applicable to 12" or larger piping
2. For multiple hanger supported piping
3. Damping of 3% used for steam generator replacement analysis
4. Damping of 5% used for steam generator replacement analysis
5. Damping of 2% used for steam generator replacement analysis
6. Also includes the BWI supplied replacement steam generators
7. N-411 damping used for OBE & SSE steam generator replacement analyses
McGuire Nuclear Station UFSAR Table 3-26 (Page 1 of 1)
(14 OCT 2000)
Table 3-26. Reactor Building and Interior Structure Comparison of Peak Responses
Mass Location
Peak Acceleration on the Response
Spectrum(G's)
Percent
Increase Fixed Base Combined Interaction
Reactor Vessel Support 0.498 0.493 -0.1
Steam Generator Support 1.724 1.692 -1.85
Penetration Support 1.074 1.176 +9.5
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-2
7 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-2
7.
Com
pa
riso
n o
f R
esp
on
se S
pec
tru
m A
nd
Tim
e-H
isto
ry R
esp
on
ses(1
)(2
)
Mass
Poin
t
Acc
eler
ati
on
s
(G's
)
M
om
ents
(X
10
4 F
t-K
)
Sh
ears
(X
10
3 K
ips)
Res
po
nse
Sp
ectr
um
Tim
e-
His
tory
R
esp
on
se S
pec
tru
m
Tim
e-
His
tory
R
esp
on
se S
pec
tru
m
Tim
e-
His
tory
1
.04
67
.1174
27.2
6
30.9
7
4.7
2
6.2
8
2
.06
38
.1278
23.2
1
25.8
6
4.4
7
5.6
0
3
.08
72
.1434
18.6
3
20.2
1
4.3
5
5.3
1
4
.11
25
.1601
14.4
3
15.1
6
4.1
6
4.9
4
5
.13
44
.1766
11.8
1
12.1
3
3.7
9
4.3
2
6
.14
07
.1811
10.9
4
11.1
4
3.7
0
4.1
8
7
.18
18
.2138
7.5
1
7.5
7
2.9
1
3.0
0
8
.22
47
.2458
4.6
0
4.6
4
2.4
3
2.4
5
9
.26
45
.2750
2.3
5
2.3
7
1.8
8
1.8
9
10
.2
78
5
.2848
1.7
3
1.7
5
1.3
8
1.3
9
11
.3
02
8
.3002
0.9
1
0.9
2
1.1
3
1.1
4
12
.3
28
4
.3153
0.3
2
0.3
2
0.7
4
0.7
5
13
.3
52
8
.3301
0.0
0.0
0
.37
0.3
7
No
tes:
1.
Ref
er t
o F
igu
re 3
-20
fo
r m
ath
emat
ical
mod
el
2.
Val
ues
for
Res
po
nse
Sp
ectr
um
Tec
hn
ique
are
bas
ed o
n t
he
ori
gin
al a
nal
ysi
s (M
CC
-1134.0
2-0
0-0
00
3),
bef
ore
Ste
am G
ener
ato
r re
pla
cem
ent
and
Ice
Co
nd
ense
r m
ass
adju
stm
ents
.
McGuire Nuclear Station UFSAR Table 3-28 (Page 1 of 1)
(14 OCT 2000)
Table 3-28. Maximum Blowdown LOCA Load Resultants for the Containment Interior Structure
Loading Maximum Value Break Location Time
OVERTURNING
MOMENT
280,950 FT-K ELEMENT NO. 1(1)
0.312 SEC.
HORIZONTAL
SHEAR
3,977 KIPS ELEMENT NO. 1(1)
0.312 SEC.
UPLIFT 6,354 KIPS ELEMENT NO. 2(1)
0.222 SEC
Note:
1. The blowdown history and structural geometry for Elements No. 1 and No. 6, No. 2 and No. 5 are
the same, therefore, the maximums for No. 1 apply to No. 6 and the maximums for No. 2 apply to
No. 5.
Refer to Table 6-1 through Table 6-6 for Containment Interior Structure blowdown model
McG
uir
e N
ucl
ear
Sta
tio
n
UF
SA
R T
ab
le 3
-29
(P
ag
e 1
of
12
)
(1
3 A
PR
20
08)
Ta
ble
3-2
9 M
cGu
ire
Nu
clea
r S
tati
on
- C
on
tain
men
t S
ub
com
part
men
t P
ress
ure
s C
alc
ula
ted
Valu
es o
f d
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ren
tia
l P
ress
ure
(p
si)-
Acr
oss
Co
mp
art
men
ts
MC
GU
IRE
NU
CL
EA
R S
TA
TIO
N C
ON
TA
INM
EN
T S
UB
CO
MP
AR
TM
EN
T P
RE
SS
UR
ES
CA
LC
UL
AT
ED
VA
LU
ES
OF
DIF
FE
RE
NT
IAL
PR
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SU
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(P
SI)
– A
CR
OS
S C
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PA
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ME
NT
S
D
esi
gn
Dif
f P
ress
ure
(= 1
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Dif
f P
res
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CO
MP
BE
TW
EE
N
AN
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CO
MP
MA
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UM
DIF
F P
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C)
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EM
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UM
M
INIM
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1
2
0.7
158
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190
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51
7E
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190
H.L
. 2
0.1
002
E+
02
-0.7
72
3E
+0
1
1
6
0.1
099
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02
0.0
640
H.L
. 1
-0.1
08
6E
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H.L
. 6
0.1
539
E+
02
-0.1
52
0E
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2
1
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02
0.2
700
C.L
. 1
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. 6
0
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0
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****
***
***
***
***
***
*
2
1
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517
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01
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190
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. 2
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2
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350
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280
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0.8
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2
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0.7
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8E
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1
McG
uir
e N
ucl
ear
Sta
tio
n
UF
SA
R T
ab
le 3
-29
(P
ag
e 2
of
12
)
(1
3 A
PR
20
08)
MC
GU
IRE
NU
CL
EA
R S
TA
TIO
N C
ON
TA
INM
EN
T S
UB
CO
MP
AR
TM
EN
T P
RE
SS
UR
ES
CA
LC
UL
AT
ED
VA
LU
ES
OF
DIF
FE
RE
NT
IAL
PR
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SU
RE
(P
SI)
– A
CR
OS
S C
OM
PA
RT
ME
NT
S
D
esi
gn
Dif
f P
ress
ure
(= 1
.4 x
Dif
f P
res
sure)
CO
MP
BE
TW
EE
N
AN
D
CO
MP
MA
XIM
UM
DIF
F P
RE
SS
UR
E
TIM
E (
SE
C)
EL
EM
EN
T
MIN
IMU
M
DIF
F P
RE
SS
UR
E
TIM
E (
SE
C)
EL
EM
EN
T
MA
XIM
UM
M
INIM
UM
****
***
***
***
***
***
*
3
2
0.4
767
E+
01
0.0
280
H.L
. 3
-0.6
35
0E
+0
1
0.0
640
H.L
. 1
0.6
673
E+
01
-0.8
89
0E
+0
1
3
4
0.4
675
E+
01
0.0
280
H.L
. 3
-0.5
72
5E
+0
1
0.0
190
H.L
. 4
0.6
545
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01
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01
5E
+0
1
3
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0.5
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0.2
880
C.L
. 3
-0
.333
3E
-01
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C.L
. 3
0
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01
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7E
-01
3
14
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C.L
. 3
-0
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3E
-01
0.0
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. 3
0
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01
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. 3
0
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01
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. 3
0
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01
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H.L
. 3
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C.L
. 1
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01
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3
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C.L
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01
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0.7
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0.2
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C.L
. 3
-0
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3E
+0
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C.L
. 6
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02
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H.L
. 3
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C.L
. 6
0
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01
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0.5
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H.L
. 3
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3E
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H.L
. 6
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01
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C.L
. 6
0
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01
-0.5
60
0E
+0
0
****
***
***
***
***
***
*
4
3
0.5
725
E+
01
0.0
190
H.L
. 4
-0.4
67
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0.0
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H.L
. 3
0.8
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. 5
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01
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C.L
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01
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McG
uir
e N
ucl
ear
Sta
tio
n
UF
SA
R T
ab
le 3
-29
(P
ag
e 3
of
12
)
(1
3 A
PR
20
08)
MC
GU
IRE
NU
CL
EA
R S
TA
TIO
N C
ON
TA
INM
EN
T S
UB
CO
MP
AR
TM
EN
T P
RE
SS
UR
ES
CA
LC
UL
AT
ED
VA
LU
ES
OF
DIF
FE
RE
NT
IAL
PR
ES
SU
RE
(P
SI)
– A
CR
OS
S C
OM
PA
RT
ME
NT
S
D
esi
gn
Dif
f P
ress
ure
(= 1
.4 x
Dif
f P
res
sure)
CO
MP
BE
TW
EE
N
AN
D
CO
MP
MA
XIM
UM
DIF
F P
RE
SS
UR
E
TIM
E (
SE
C)
EL
EM
EN
T
MIN
IMU
M
DIF
F P
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SS
UR
E
TIM
E (
SE
C)
EL
EM
EN
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MA
XIM
UM
M
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UM
4
36
0.6
950
E+
01
0.2
520
C.L
. 4
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0E
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0
2.5
200
C.L
. 1
0
.9730
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01
-0.6
65
0E
+0
0
****
***
***
***
***
***
***
5
4
0.5
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0.0
190
H.L
. 5
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C.L
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C.L
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0.8
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H.L
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H.L
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C.L
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H.L
. 6
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24
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0.2
583
E+
01
1.2
780
C.L
. 2
-0
.552
5E
+0
1
0.0
820
H.L
. 3
0.3
617
E+
01
-0.7
73
5E
+0
1
35
27
0.2
750
E+
00
2.6
460
C.L
. 6
-0
.447
5E
+0
1
0.2
700
C.L
. 1
0
.3850
E+
00
-0.6
26
5E
+0
1
35
28
0.2
417
E+
00
0.2
340
H.L
. 1
-0.5
50
0E
+0
0
0.5
940
C.L
. 5
0
.3383
E+
00
-0.7
70
0E
+0
0
35
29
0.1
542
E+
01
0.5
940
C.L
. 1
-0
.333
3E
-01
2.5
920
C.L
. 6
0
.2158
E+
01
-0.4
66
7E
-01
****
***
***
***
***
***
*
36
4
0.4
750
E+
00
2.5
200
C.L
. 1
-0
.695
0E
+0
1
0.2
520
C.L
. 4
0
.6650
E+
00
-0.9
73
0E
+0
1
36
16
0.2
558
E+
01
1.2
600
C.L
. 6
-0
.566
7E
+0
1
0.0
730
H.L
. 4
0.3
582
E+
01
-0.7
93
3E
+0
1
36
29
0.1
483
E+
01
0.5
580
C.L
. 6
-0
.416
7E
-01
2.9
160
C.L
. 1
0
.2077
E+
01
-0.5
83
3E
-01
36
30
0.2
667
E+
00
0.2
340
C.L
. 6
-0
.575
0E
+0
0
0.5
760
C.L
. 1
0
.3733
E+
00
-0.8
05
0E
+0
0
36
31
0.3
500
E+
00
2.5
560
C.L
. 1
-0
.442
5E
+0
1
0.2
160
C.L
. 6
0
.4900
E+
00
-0.6
19
5E
+0
1
****
***
***
***
***
***
*
37
6
0.3
833
E+
00
2.4
660
C.L
. 1
-0
.119
9E
+0
2
0.0
730
H.L
. 6
0.5
367
E+
00
-0.1
67
9E
+0
2
37
22
0.3
217
E+
01
1.7
280
C.L
. 5
-0
.803
3E
+0
1
0.0
820
H.L
. 6
0.4
503
E+
01
-0.1
12
5E
+0
2
37
25
0.2
842
E+
01
1.6
380
C.L
. 4
-0
.875
0E
+0
0
0.3
060
H.L
. 4
0.3
978
E+
01
-0.1
22
5E
+0
1
37
31
0.2
167
E+
00
2.7
900
C.L
. 1
-0
.440
8E
+0
1
0.2
340
C.L
. 6
0
.3033
E+
00
-0.6
17
2E
+0
1
37
32
0.4
833
E+
00
0.6
120
C.L
. 4
-0
.150
0E
+0
0
0.5
760
C.L
. 3
0
.6767
E+
00
-0.2
10
0E
+0
0
****
***
***
***
***
***
*
McGuire Nuclear Station UFSAR Table 3-30 (Page 1 of 1)
(14 OCT 2000)
Table 3-30. Design Loading Conditions
The operating condition categories are defined as follows from ASME III, NB 3113.
Normal Conditions - Normal conditions are any conditions in the course of system startup, operation in
the design power range, hot standby and system shutdown, other than Upset, Emergency, Faulted or
Testing Conditions.
Upset Conditions (Incidents of Moderate Frequency) - Any deviations from Normal Conditions
anticipated to occur often enough that design should include a capability to withstand the conditions
without operational impairment. The Upset Conditions include those transients which result from any
single operator error or control malfunction, transients caused by a fault in a system component
requiring its isolation from the system and transients due to loss of load or power. Upset Conditions
include any abnormal incidents not resulting in a forced outage and also forced outages for which the
corrective action does not include any repair of mechanical damage. The estimated duration of an
Upset Condition shall be included in the Design Specifications.
Emergency Conditions (Infrequent Incidents) - Those deviations from Normal Conditions which
require shutdown for correction of the conditions or repair of damage in the system. These conditions
have a low probability of occurrence but are included to provide assurance that no gross loss of
structural integrity will result as a concomitant effect of any damage developed in the system. The total
number of postulated occurrences for such events shall not cause more than 25 stress cycles having an
Sa value greater than that for 106 cycles from the applicable fatigue design curves of Figures 1-9.0.
Faulted Conditions (limiting Faults) - Those combinations of conditions associated with extremely-
low-probability, postulated events whose consequences are such that the integrity and operability of the
nuclear energy system may be impaired to the extent that considerations of public health and safety are
involved. Such considerations require compliance with safety criteria as may be specified by
jurisdictional authorities.
Note:
Definition of Terms from the ASME Boiler and Pressure Vessel Code, Section III, 1971
McGuire Nuclear Station UFSAR Table 3-31 (Page 1 of 1)
(14 OCT 2000)
Table 3-31. Codes and Specifications for Design of Category 1 Structures and Equipment Supports
Structural Component Design Codes and Specifications
Concrete ACI 318-63
ACI 307-69(1)
Regulatory Guide 1.15
Concrete Reinforcement ASTM A615, Grades 40 and 60
Cadwelds Regulatory Guide 1.10(2)
Structural Steel and Plates ASTM A-36
AISC, 7th Edition(3)
Containment Vessel Shell Subsection B Section III of the ASME
Code 1968 Edition Including all the
addenda through the Summer of 1970.
(The high strength embedded anchor bolts
for the steam generator enclosure walls
meet the requirements of Section A for
normal operation and 1986 Code,
Appendix 'F', for faulted condition.)
Steel Pipes USS T-1
Note:
1. For the design of the Reactor Building for Temperature effects.
2. Valid test results are used. A test is not considered valid if a failure occurs in the bar or near testing
machine grips. Test samples for B Series Splices are sister splices only.
3. For visual inspection of structural welds, reference the “Visual Weld Acceptance Criteria For
Structural Welding at Nuclear Power Plants”, NCIG-01, Rev. 2 dated 5/7/85.
McGuire Nuclear Station UFSAR Table 3-32 (Page 1 of 1)
(14 OCT 2000)
Table 3-32. Reactor Building Loading Combinations and Code Requirements
Loading Combination Code or Stress Requirements
1. DL + CL
2. DL + OL + OBE
3. DL + OL + DBA
4. DL + OL + W
WSD, stresses in reinforcement and concrete are
in accordance with Chapter 10, ACI 318 - 1963
Code. AISC with allowable stresses of Fs.
5. DL + OL + SSE
6. DL + OL + Wt
7. DL + OL + SSE + DBA + Y
ACI-318, USD with no factors applied to
loadings. AISC with allowable stress of 1.5 Fs or
0.9 Fy whichever is less.
DL = Dead Load, including weight of permanent equipments attached to the Reactor Building.
CL = Construction Loads.
OL = Normal Loads on the Reactor Building due to plant operation such as thermal loads and
normal penetration loads due to pipe reactions on the building. OL also includes Live Loads
during plant operation.
OBE = Operating Basis Earthquake Load, inertia forces due to base excitation of 8 percent G.
SSE = Safe Shutdown Earthquake Load, inertia forces due to base excitation of 15 percent G.
DBA = Design Basis Accident, includes the differential pressures on the Reactor Building and the
associated thermal loads.
W = Normal wind loads.
Y = Loading on structure due to pipe rupture.
Wt = Tornado Loading as defined in Section 3.3.2.2.
ACI-
318
= “Building Code Requirements for Reinforced Concrete,” June 1963.
AISC = “Specification for the Design, Fabrication and Erection of Structural Steel Buildings,” 1969.
Fs = Steel allowable stresses as specified in AISC, Part 1.
WSD = “Working Stress Design” Method.
Fy = Steel specified yield stress.
USD = “Ultimate Strength Design” method.
As a minimum, the margin of safety as specified in the above codes and specifications is met in the
design of the Reactor Building.
AISC is used for the design of structural steel embedments and pipe sleeves through the Reactor
Building wall.
In addition to the Design conditions defined above, the roof has been investigated, spot checked, and
found structurally adequate for the following loading condition: SLOLDLU ++=
where SL = Severe snow and ice loads and is defined in Section 2.4.10.
McGuire Nuclear Station UFSAR Table 3-33 (Page 1 of 1)
(14 OCT 2000)
Table 3-33. Containment Vessel Loading Combination and Code Requirements
Loading Combination Code Reference
DL + CL ASME - Normal Condition
DL + OL + DBA ASME - Normal Condition
DL + OL + OBE ASME - Normal Condition
DL + OL + OBE + P' ASME - Normal Condition
DL + OL + SSE ASME - Emergency Condition
DL + OL + SSE + DBA ASME - Emergency Condition
DL + OL + SSE + P' ASME - Emergency Condition
ASME = ASME Boiler and Pressure Vessel Code, Section III, Subsection B, 1968, including all
addenda through Summer of 1970.
DL = Own weight of the Containment Vessel and all the permanent attachments to the
Containment.
CL = Construction Loads.
DBA = Design Basis Accident which includes temperature and pressure effects.
OBE = Operating Basis Earthquake, 8 percent G.
SSE = Safe Shutdown Earthquake, 15 percent G.
OL = Normal Operating Loads of the Containment Vessel, including Live Loads, thermal
loads and operating pipe reactions.
P' = External pressure due to the internal vacuum created by accidental trip of the
Containment Spray System.
Stress limits of the Containment Vessel are as prescribed in Figure N-414 of the ASME, Section III,
Nuclear Vessels, 1968, including all the addenda up to the Summer of 1970. Buckling is considered in
all loading combinations.
McGuire Nuclear Station UFSAR Table 3-34 (Page 1 of 1)
(14 OCT 2000)
Table 3-34. Containment Materials
Material Location Material Specification
Base Liners SA-516, Grade 60 or 70
Base Liner Embedments SA-516, Grade 60 and/or
ASTM A36
Knuckle Plate SA-516, Grade 60 or 70
Shell and Dome Plate SA-516, Grade 60 or 70
Penetrations (Piping and Electrical) SA-106, Grade B and/or
SA-516, Grade 60
Personnel Locks SA-516, Grade 60 and/or
Grade 70
Stiffeners SA-516, Grade 60 or 70
Equipment Hatch SA-516, Grade 60 and/or
Grade 70
Anchor Bolts SA 320-L43
Anchor Bolt Anchor Plates SA-516, Grade 60
McGuire Nuclear Station UFSAR Table 3-35 (Page 1 of 1)
(14 OCT 2000)
Table 3-35. Deleted Per 1998 Update
McG
uir
e N
ucl
ear
Sta
tio
n
UF
SA
R T
ab
le 3
-36
(P
ag
e 1
of
1)
(1
3 A
PR
20
08)
Ta
ble
3-3
6 F
act
ors
of
Safe
ty A
ga
inst
Bu
ckli
ng o
f S
hel
l P
an
els
for
the
McG
uir
e C
on
tain
men
t V
esse
l
Po
int*
Axia
l
kip
s/in
ch
Shea
ring
Lo
ad
kip
s/in
ch
Saf
ety F
acto
r A
gai
nst
Buck
lin
g
Shel
l P
anel
s T
reat
ed a
s F
lat
Pla
tes
Shel
l P
anel
s T
reat
ed a
s
Curv
ed P
late
s
1
-5.7
0
5.2
8
6.0
0
3.2
7
2
-3.9
9
5.3
1
8.6
0
4.4
3
3
-3.0
2
4.4
7
11
.42
5.9
3
4
-4.4
9
1.7
5
8.3
6
4.9
3
5
-4.5
3
1.0
8
8.3
3
4.9
7
6
-4.1
3
1.2
2
9.1
3
5.4
3
* S
ee F
igure
3-1
32
McGuire Nuclear Station UFSAR Table 3-37 (Page 1 of 1)
(14 OCT 2000)
Table 3-37. Comparison Between the Actual Design Differential Pressures and the Latest Design
Differential Pressures For the Major Structural Barriers of the Interior Structure
Structural Barrier
Actual Design Diff.
Pressures (psi) (= 1.4
X Diff. Press.)
Latest Calculated
Diff. Pressures (psi)
Pressure Values Used
for Design
Ice Condenser Floor 11.37 8.12 12.74
6.80 5.67 12.74
6.74 4.60 7.84
6.74 4.52 7.84
7.88 6.52 12.74
8.05 6.79 12.74
7.93 7.15 12.74
6.86 6.40 7.84
6.63 4.44 7.84
9.11 4.55 12.74
11.25 7.97 12.74
Operating Floor 17.43 14.13 15.51
12.28 11.35 15.51
9.38 9.19 15.51
9.49 9.53 15.51
12.06 11.25 15.51
16.94 13.57 15.51
Wingwalls 6.71 5.74 10.00
6.27 7.36 10.00
2.16 5.16 10.00
2.08 5.20 10.00
6.19 7.17 10.00
6.17 5.55 10.00
Crane Wall See Note 1.
Note:
1. The Crane Wall is designed to sustain several critical loading combinations. The differential
pressures comprise part of these combinations, hence it is not practical to single out these
differential pressures on the crane wall for comparison purposes.
McGuire Nuclear Station UFSAR Table 3-38 (Page 1 of 1)
(14 OCT 2000)
Table 3-38. Comparison Between Kalnin's Program Results and Finite Elements Results w (cps)
Mode Kalnin's Finite Elements
Reactor Building
N = 1 1 4.964768 4.9748
2 13.66 13.729
Containment Vessel
N = 0 1 24.9259 24.97
N = 1 1 9.284 9.3234
2 25.69 25.660
McGuire Nuclear Station UFSAR Table 3-39 (Page 1 of 1)
(14 OCT 2000)
Table 3-39. Containment Interior Structures Loading Combinations and Code Requirements
Loading Combination Code or Stress Requirements
1. DL + CL
2. DL + OL + Pa
3. Deleted
4. DL + OL + OBE
WSD, stresses in reinforcement and concrete are
in accordance with Chapter 10, ACI-318 - 1963
Code. AISC with allowable stresses of Fs.
5. DL + OL + SSE
6. DL + OL + SSE + Ta
7. DL + OL + SSE + Pa + Y
ACI-318, USD with no factors applied to
loadings, AISC with allowable stress of 1.5 Fs or
0.90 Fy whichever is less.
DL = Dead Load, including weight of permanent equipment.
CL = Construction Loads.
OL = Normal Operating Loads, these loads are associated with the plant operation,
including Live Loads.
Pa = Differential Pressure across the individual Internal Structures due to a Loss-of-
Coolant Accident.
Y = Loading on structure due to pipe rupture.
Ta = Thermal loads on the Internal Structures Components due to a Loss-of Coolant
Accident.
OBE = Operating Basis Earthquake Load, inertia forces due to base excitation of 8 percent
G.
SSE = Safe Shutdown Earthquake Load, inertia forces due to base excitation of 15 percent
G.
ACI-318 = “Building Code Requirements for Reinforced Concrete,” June 1963.
AISC = “Specification for the Design, Fabrication and Erection of Structural Steel
Buildings,” 1969.
WSD = “Working Stress Design” Method.
USD = “Ultimate Strength Design” method.
Fy = Yield stress of steel.
Fs = Allowable stresses in steel as specified in AISC, Part 1.
Note:
Pa and Ta do not act simultaneously on the structure
McGuire Nuclear Station UFSAR Table 3-40 (Page 1 of 1)
(14 OCT 2000)
Table 3-40. Design Properties of Seals
Durometer Tensile Elongation Compression Set
1. Membrane Seals:
Initial 65 (approx.) 2260 psi 470% 14.1%
2. Compressible Seals:
Initial 40 1400 psi 800% 12.88%
Note:
1. All tests are in accordance with ASTM D-2000-XX. XX = The current ASTM D-2000 revision at
the time of procurement.
McGuire Nuclear Station UFSAR Table 3-41 (Page 1 of 1)
(14 OCT 2000)
Table 3-41. Divider Barrier Seals Minimum Acceptable Physical Properties
Membrane Type Seals Tensile Strength
Mk 10 39.7 lbs.
Mk 11 39.7 lbs.
Mk 12 10.6 lbs.
Mk 13 288 lbs.
Mk 20 42.4 lbs.
Compression Type
Seals Tensile Strength Elongation Durometer
40 Duro 575 psi 350% +5 pts. from initial
60 Duro 1333 psi 387% +5 pts. from initial
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
2 (
Pa
ge
1 o
f 2
)
(10
OC
T 2
00
9)
Ta
ble
3-4
2.
Au
xil
iary
Bu
ild
ing
Lo
ad
ing
Con
dit
ion
s
Are
a
Lo
ad
ing C
on
dit
ion
s R
emark
s
Co
mp
artm
ents
at
El.
69
5
A,
G,
H
Soil
an
d w
ater
pre
ssure
. S
ee N
ote
1.
Co
mp
artm
ents
at
El.
71
6
A,
G,
H
Soil
an
d w
ater
pre
ssure
. S
ee N
ote
1.
Co
mp
artm
ents
at
El.
73
3 a
nd
Eq
uip
men
t
Ro
om
s an
d S
wit
chgea
r R
oo
ms
A,
G,
H
Soil
an
d w
ater
pre
ssure
. S
ee N
ote
1.
Die
sel
Gen
erat
or
Ro
om
s A
, B
, C
, F
, G
, H
S
oil
an
d w
ater
pre
ssure
.
Fu
el P
ool
A,
B,
C,
G,
H.
*S
ee N
ote
2.
Fu
el P
ool
Rac
ks
A,
G,
H
See
No
te 1
.
Co
ntr
ol
Roo
m
A,
B,
C,
F,
G,
H
Ho
t M
ach
ine
Sh
op
A
Lab
ora
tory
Are
a A
Per
sonnel
Dec
onta
min
atio
n
A
Was
te S
hip
pin
g A
rea
A
Fu
el S
hip
pin
g A
rea
A
Iso
lati
on V
alve
Are
a A
, B
, C
, F
, G
, H
, I
Soil
an
d w
ater
pre
ssure
.
New
Fuel
Rac
ks
A,
G,
H
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-4
2 (
Pa
ge
2 o
f 2
)
(10
OC
T 2
00
9)
Are
a
Lo
ad
ing C
on
dit
ion
s R
emark
s
No
te:
1.
En
clo
sed
by e
nvel
opin
g s
tru
cture
des
igned
for
win
d, to
rnad
o w
ind, to
rnad
o m
issi
les
and t
urb
ine
mis
sile
, as
ap
pli
cable
.
2.
Des
igned
for
ther
mal
str
esse
s an
d c
ask d
rop
acc
iden
t.
A =
All
norm
al d
ead
, eq
uip
men
t, l
ive
and
win
d l
oad
s.
B =
No
rmal
dea
d a
nd
eq
uip
men
t lo
ads
plu
s to
rnad
o l
oad
ings
C =
Torn
ado m
issi
les.
F =
Tu
rbin
e-G
ener
ato
r m
issi
le (
or
Die
sel-
Gen
erat
or
mis
sile
).
G =
No
rmal
dea
d a
nd
eq
uip
men
t lo
ads
plu
s op
erat
ing s
eism
ic l
oad
s.
H =
No
rmal
dea
d a
nd
eq
uip
men
t lo
ads
plu
s des
ign s
eism
ic l
oad
s.
I =
Norm
al d
ead
and
eq
uip
men
t lo
ads
plu
s des
ign s
eism
ic l
oad
s plu
s p
ipe
ruptu
re a
nd
pre
ssure
load
s.
* =
Soil
and
wat
er p
ress
ure
, p
ress
ure
du
e to
eq
uip
men
t o
r ra
ilro
ad r
amp
.
McGuire Nuclear Station UFSAR Table 3-43 (Page 1 of 2)
(14 OCT 2000)
Table 3-43. Auxiliary Building Loading Combinations
Loading Conditions5
Load Combination
A,G U = 1.5D + 1.8L
U = 1.25 (D + L + W)
U = 0.9D + R +1.1E
U = 1.25 (D + R + E)
B,H U = 1.25 (D + R) + E'
U = 1.25D + Wt
C,F Analyzed on bases of "Design of Protective
Structures," Amirikian, A., Bureau of Yards and
Docks, Department of the Navy, NAVDOCKS
P-51, 1950.
I U = 1.25 (D + R) + P + E' + Y
U = Required Ultimate Load Capacity of Section
D = Dead Load (including equipment load and normal operating pipe loads)
L = Operating Live Load
W = Wind Load
Wt = Tornado Loading
E = Operating Basis Earthquake Load
E' = Safe Shutdown Earthquake Load
R = Piping Seismic Reactions
P = Peak compartment pressure generated by a postulated pipe break
Y = Equivalent static load on structure from pipe break (including a dynamic load factor of 2.0)
Fs = Allowable stresses in steel in accordance to AISC, Part 1.
Fy = Allowable yield stress in steel
McGuire Nuclear Station UFSAR Table 3-43 (Page 2 of 2)
(14 OCT 2000)
Loading Conditions5
Load Combination
1. Design Strengths are in accordance with ACI 318-63, Sections 1504 and 1505 for concrete and
reinforcing steel.
2. Concrete design is based on the Ultimate Strength Method in accordance with the June 1963
version of ACI 318. For design of those structural elements not covered in ACI 318-63, the ACI
Standard 318-71 is used.
3. Structural Steel design is based on Part 1 of the February, 1969 version of the AISC Specification
except that for those loading conditions including Wt, E', P and Y, the maximum allowable steel
stress is permitted to be 1.5 Fs or 0.9 Fy, whichever is less.
4. In addition to the Design conditions as defined above, the roof has been investigated, spot checked,
and found structurally adequate for the following loading condition: SLLDU ++=
where SL = severe snow and ice loads and is defined in Section 2.4.10.
5. See UFSAR Table 3-42, (Page 2 of 2) for the explanation of the Symbols (A thru I) used in
Loading Conditions.
McGuire Nuclear Station UFSAR Table 3-44 (Page 1 of 1)
(14 OCT 2000)
Table 3-44. New Fuel Storage Vault Loading Combinations
Loading Conditions4 Load Combination
A, G U=1.5D + 1.8L
U=1.25 (D + L + W)
U=0.9D + R + 1.1E
U=1.25 (D + R + E)
B, H U=1.25 (D + R) + E'
U=1.25D + Wt
C Analyzed on bases of "Design of Protective
Structures," Amirikian, A., Bureau of Yards and
Docks, Depart of the Navy, NAVDOCKS P-51,
1950.
I U=1.25 (D + R) + P + E' + Y
U = Required Ultimate Load Capacity of Section
D = Dead Load (including equipment load and normal operating pipe loads)
L = Live Load
W = Wind Load
Wt = Tornado Loading
E = Operating Basis Earthquake Load
E' = Safe Shutdown Earthquake Load
R = Piping Seismic Reactions
P = Peak compartment pressure generated by a postulated pipe break
Y = Equivalent static load on structure from pipe break (including a dynamic load factor of 2.0)
1. Design Strengths are in accordance with ACI 318-63, Sections 1504 and 1505 for concrete and
reinforcing steel.
2. Concrete design is based on the Ultimate Strength Method in accordance with the June 1963
version of ACI 318. For design of those structural elements not covered in ACI 318-63, the ACI
Standard 318-71 is used.
3. Structural Steel design is based on Part 1 of the February, 1969 version of the AISC Specification
except that for those loading conditions including Wt, E', P and Y, the maximum allowable steel
stress is permitted to be 1.5 Fs or 0.9 Fy.
4. See UFSAR Table 3-42 (Page 2 of 2) for the explanation of the Symbols (A through I) used in
Loading Conditions.
McGuire Nuclear Station UFSAR Table 3-45 (Page 1 of 1)
(14 OCT 2000)
Table 3-45. Factors of Safety for Category 1 Structures Against Overturning and Sliding
Structure
Factor of Safety
Overturning Sliding
Reactor Building Complex 2.3 2.24
Main Auxiliary Building 9.23 2.82
Diesel Generator Building 8.2 3.7
Main Steam Line Isolation Valve Enclosure 1.10 1.22
New Fuel Vault 1.23 1.15
SNSW Intake 2.44 1.18
SNSW Discharge 2.72 1.24
SNSW Overflow Spillway 1.05 1.28
McGuire Nuclear Station UFSAR Table 3-46 (Page 1 of 2)
(14 OCT 2000)
Table 3-46. Piping Systems Included in Vibration Test Program
System
Reactor Coolant System
Safety Injection System
Residual Heat Removal System
Containment Spray System
Chemical and Volume Control System
Boron Recycle System
Boron Thermal Regeneration System
Component Cooling System
Liquid Waste Disposal System
Fuel Pool Cooling and Cleanup System
Diesel Generator Fuel Oil System
Diesel Generator Cooling Water System
McGuire Nuclear Station UFSAR Table 3-46 (Page 2 of 2)
(14 OCT 2000)
System
Diesel Generator Lube Oil System
Nuclear Service Water System
Refueling Water System
Main Steam System
Feedwater System
Auxiliary Feedwater System
Steam Dump System
Containment Ventilation Cooling Water System
Control Area Chilled Water System
Steam Generator Blowdown Recycle System
Recirculated Cooling Water System
McGuire Nuclear Station UFSAR Table 3-47 (Page 1 of 2)
(14 OCT 2000)
Table 3-47. Design Conditions, Load Combinations, and Code Compliance Criteria for Duke
Classes B, C, and F Piping
Condition Loads Code Compliance Criteria
1. Sustained Loads5 Pressure
Weight
Other Sustained
Mechanical loads
Σ Primary stresses ≤ Sh 3,
7,
8
2. Thermal Expansion Thermal Expansion
Thermal Anchor
Movements
Maximum Secondary Stress Envelope 3,
7,
8
3. Upset Loads Pressure
Weight
OBE (Inertia)
OBE (Anchor
Movements)1
DFL 2
Wind4
Σ (Primary Stresses) ≤ 1.2 Sh 7,
8
4.
a. Faulted Loads Pressure
Weight
SSE (Inertia)
DFL 2
Tornado 4
Σ (Primary Stresses) ≤ 2.4 Sh 7,
8
b. Faulted Loads Pressure
Weight
Pipe Rupture 6
Σ (Primary Stresses) ≤ 2.4 Sh 7,
8
McGuire Nuclear Station UFSAR Table 3-47 (Page 2 of 2)
(14 OCT 2000)
Condition Loads Code Compliance Criteria
Notes:
1. Stresses due to seismic displacements such as anchor movements may alternatively be considered as
secondary stresses and combined with thermal expansion.
2. Dynamic Internal Fluid Loads are occasional loads such as relief valve thrust, steamhammer,
waterhammer or loads associated with Plant Upset or Faulted Condition where appropriate.
3. The allowable stress, SA, may be increased when primary stresses due to sustained loads are less than
Sh per ASME Section III, Subsection NC-3611.1(b)4(a).
4. Wind as defined in UFSAR Section 3.3.1.1 is applicable to the Upset Condition, but not concurrent
with seismic loads inertia or anchor movement loadings per ASME III 1971, Subsection NC-3622.
Tornado as defined in UFSAR Section 3.3.2.1 is applicable to the Faulted Condition, but not
concurrent with seismic loads inertia or anchor movement loadings per ASME III 1971, Subsection
NC-3622.
5. If, during operation, the system normally carries a medium other than water (air, gas, steam),
sustained loads should be checked for weight loads during hydrotest as well as normal operation
weight loads.
6. Pipe rupture loadings include LOCA and MSLB as applicable.
7. ASME Code Case N-318-4, "Procedure for Evaluation of the Design of Rectangular Cross Section
Attachments on Class 2 or 3 Piping, Section III, Division 1", may be used in case of pipe welded
attachment qualification. It should be documented in appropriate calculations.
8. ASME Code Case N-392-1, "Procedure for Evaluation of the Design of Hollow Circular Cross
Section Welded Attachments on Class 2 or 3 Piping, Section III, Division 1", may be used in case of
pipe welded attachment qualification. It should be documented in appropriate calculations
McGuire Nuclear Station UFSAR Table 3-48 (Page 1 of 1)
(14 OCT 2000)
Table 3-48. Stress Criteria For Reactor Containment Mechanical Penetrations Duke Class B
Condition Piping Loads Criteria
1. Normal Thermal Displacement
Pressure Weight
ASME III, Class 2
2. Upset Thermal Displacement
OBE (Displacement)
Pressure Weight OBE
(Inertia)
(Secondary Stresses) ≤SA
(Primary Stresses) ≤ 1.2 Sh
3. Faulted Thermal Displacement1
SSE (Displacement)1
Pressure Weight SSE
(Inertia) Pipe Rupture
(Primary Stresses) ≤2.4 Sh
Note:
1. For the faulted condition, the displacement induced stresses are considered primary stresses.
McGuire Nuclear Station UFSAR Table 3-49 (Page 1 of 1)
(14 OCT 2000)
Table 3-49. Stress Criteria For Supports, Restraints, and Anchors Duke Class A
Condition Piping Loads Criteria
1. Normal Thermal Displacement
Pressure (As Applicable)
Weight
ASME III, Class 1
2. Upset Thermal Displacement
OBE (Displacement)
Pressure (As Applicable)
Weight OBE (Inertia)
ASME III, Class 1
3. Faulted Thermal Displacement SSE
(Displacement) Pressure
(As Applicable) Weight
SSE (Inertia) Pipe Rupture
(Primary Stresses) ≤ Yield Stress At
Operating Temperature
or ASME III, Class 11
4. Faulted Thermal Displacement SSE
(Displacement) Pressure
(As Applicable) Weight
SSE (Inertia) Pipe Rupture
(Primary Stresses) ≤ Yield Stress At
Operating Temperature
or ASME III, Class 11
Note:
1. ASME III, Class 1 allowables (i.e. Level D) may be used for standard vendor supplied pipe support
components provided a certified Design Report Summary (DRS) or Load Capacity Data Sheet
(LCDS) is available for the component.
McGuire Nuclear Station UFSAR Table 3-50 (Page 1 of 1)
(14 OCT 2000)
Table 3-50. Stress Criteria For Supports, Restraints, and Anchors Duke Classes B, C, and F
Condition Piping Loads Criteria
1. Normal Thermal Displacement
Pressure (As Applicable)
Weight
ASME III, Class 2
2. Upset Thermal Displacement
OBE (Displacement)
Pressure (As Applicable)
Weight OBE (Inertia)
wind1
ASME III, Class 2
3. Faulted Thermal Displacement SSE
(Displacement) Pressure
(As Applicable) Weight
SSE (Inertia) tornado1
(Primary Stresses) ≤ Yield Stress At
Operating Temperature or ASME III,
Class 22
4. Faulted Thermal Displacement SSE
(Displacement) Pressure
(As Applicable) Weight
SSE (Inertia) Pipe Rupture
Tornado1
(Primary Stresses) ≤ Yield Stress At
Operating Temperature or ASME III,
Class 22
Note:
1. Wind as defined in UFSAR Section 3.3.1.1 is applicable to the Upset Condition, but not concurrent
with seismic loads inertia or anchor movement loadings per ASME III 1971, Subsection NC-3622.
Tornado as defined in UFSAR Section 3.3.2.1 is applicable to the Faulted Condition, but not
concurrent with seismic loads inertia or anchor movement loadings per ASME III 1971, Subsection
NC-3622.
2. ASME III, Class 2 allowables (i.e. Level D) may be used for standard vendor supplied components
provided a certified Design Report Summary (DRS) or Load Capacity Data Sheet (LCDS) is
available for the component.
McGuire Nuclear Station UFSAR Table 3-51 (Page 1 of 1)
(14 OCT 2000)
Table 3-51. Stress Criteria For Safety Class 2 and 3 Cylindrical Shell Type Equipment and
Components And Their Supports
Condition Loads Criteria
1. Normal & Upset
(includes Normal
Operating Effects Plus
OBE Effects)
Nozzle Loads
Pressure
Weight
Support Reactions
ASME Section III Class 2 or 3 (See Table
3-4)
2. Faulted (includes
Normal Operating
Effects Plus SSE
Effects)
Nozzle Loads
Pressure
Weight
Support Reactions
Pressure Boundary - ASME Section III,
Class 2 and 3 and Par. NB-3225
Supports - (Primary Stresses) ≤ Yield
Stress At Operating Temperature
McGuire Nuclear Station UFSAR Table 3-52 (Page 1 of 1)
(14 OCT 2000)
Table 3-52. Westinghouse Design Criteria for ASME Class 2 and 3 Components
Condition Vessels/Tanks Pumps
Normal S0.1Pm ≤ ASME Section III Subsection NC-3400 and ND-
3400
S0.3PP bm ≤+
Upset S0.1Pm ≤ S0.1Pm ≤
S0.3PP bm ≤+ S5.1PP bm ≤+
Faulted S5.1Pm ≤ S2.1Pm ≤
S0.3PP bm ≤+ S8.1PP bm ≤
S = Allowable stress for the material at temperature as given in ASME Section III
Pm = Membrane stress, i.e., the component of normal stress which is uniformly distributed across the
thickness of the solid section under consideration.
Pb = Bending stress, i.e., the linearly variable component of normal stress across the thickness of the
solid section under consideration.
ASME
CLASS LOADING COMBINATION CONDITION CLASSIFICATION
2 1. Pressure + Deadweight +
Thermal (Nozzle loads only)
Normal
2. Pressure + Deadweight +
OBE
Upset
3. Pressure + Deadweight +
SSE
Faulted
3 1. Pressure + Deadweight +
Thermal (Nozzle loads only)
Normal
2. Pressure + Deadweight +
SSE
Faulted
McGuire Nuclear Station UFSAR Table 3-53 (Page 1 of 1)
(14 OCT 2000)
Table 3-53. Guard Pipe Designs Relying on ASME Code Case 1606
Penetration
Mk. No.
Process
Pipe
Size
(NPS) System
Energy Classification of
Process Pipe
Ratio:
Design Pressure
Pressure Rating
Note 1
154 34" SM - Main Steam - A High Energy 1.22
261 34" SM - Main Steam - B High Energy 1.22
393 34" SM - Main Steam - C High Energy 1.22
441 34" SM - Main Steam - D High Energy 1.22
329 3" NV - Charging Pumps
to Regenerative Hx.
High Energy 1.55
339 2" NV - Sealwater
Injection
High Energy 1.56
343 2" NV - Sealwater
Injection
High Energy 1.56
344 2" NV - Sealwater
Injection
High Energy 1.56
350 2" NV - Sealwater
Injection
High Energy 1.56
316 4" NI - Safety Injection -
A
Moderate Energy 1.56
319 4" NI - Safety Injection -
B
Moderate Energy 1.56
348 2" NI - UHI Check Valve
Flush
Moderate Energy 1.56
351 3" NI - From Boron
Injection Tank
Moderate Energy 1.56
352 4" NI - Safety Injection -
A & B
Moderate Energy 1.56
N/A Note 2 34" SM - Main Steam High Energy 1.43
N/A Note 2 18" CF - Feedwater High Energy 1.39
Note:
1. Design Pressure refers to the maximum operating pressure during normal plant conditions. Pressure
rating refers to allowable pressure utilizing Eq (3) of Paragraph NC-3641-1 of ASME Section III,
1971 Edition through Winter 1971 Add.
2. This guard pipe encloses process pipe in areas other than penetrations.
McGuire Nuclear Station UFSAR Table 3-54 (Page 1 of 1)
(14 OCT 2000)
Table 3-54. Comparison of Predicted PWHIP Response - Inelastic Pipe Element. (Example Problem:
Figure 3-117)
Response Theoretical Prediction 1 PWHIP Prediction
2 Conclusion
Maximum
Displacement
ymax @ tm
0.8041" @ 0.0668 sec. 0.8038" @ 0.067 sec. Predicted ymax
and tm are “exact”
within three
significant
figures of
accuracy.
Peak-to-Peak
Elastic
Displacement
Range
ymax - ymin
0.3669" 0.3679" Predicted
response is
within 0.3% of
theoretical.
Elastic Natural
Period of Free
Vibration
Tn
0.1107 sec. 0.112 sec. Predicted
response is
within 1.2% of
theoretical.
Note:
1. Theoretical response based on the solution by Biggs, Introduction to Structural Dynamics, McGraw-
Hill, 1964, recomputed with intermediate calculations to 5 significant figures.
2. PWHIP response calculated using a numerical integration time step of 0.001 seconds and output at
that time interval.
[HISTORICAL INFORMATION – NOT REQUIRED TO BE REVISED]
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-5
5 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-5
5.
Com
pa
riso
n o
f P
red
icte
d P
WH
IP R
esp
on
se -
In
ela
stic
Yie
ld E
lem
ent.
(E
xam
ple
Pro
ble
m:
Fig
ure
3-1
18
)
Res
pon
se
Th
eore
tica
l P
red
icti
on
1
PW
HIP
Pre
dic
tion
2
Con
clu
sio
n
Max
imum
Dis
pla
cem
ent
ym
ax @
tm
0.8
04
1"
@ 0
.06
68
sec
. 0
.8051"
@ 0
.067 s
ec. (0
.8043"
when
corr
ecte
d f
or
init
ial
gap
3
PW
HIP
res
po
nse
ex
act
wit
hin
3 s
ign
ific
ant
figu
res
of
accu
racy
.
Pea
k-t
o-P
eak
Ela
stic
Dis
pla
cem
ent
Ran
ge
ym
ax -
ym
in
0.3
66
9"
0.3
670"
PW
HIP
res
po
nse
ex
act
wit
hin
3 s
ign
ific
ant
figu
res
of
accu
racy
.
Ela
stic
Nat
ura
l
Per
iod o
f F
ree
Vib
rati
on
Tn
0.1
10
7 s
ec.
0.1
105 s
ec.
PW
HIP
res
po
nse
ex
act
wit
hin
3 s
ign
ific
ant
figu
res
of
accu
racy
.
No
te:
1.
Th
eore
tica
l re
spo
nse
bas
ed o
n t
he
solu
tion
by B
iggs,
Intr
oduct
ion t
o S
truct
ura
l D
ynam
ics,
McG
raw
-Hil
l, 1
964
, re
com
pu
ted
wit
h
inte
rmed
iate
cal
cula
tio
ns
to 5
sig
nif
ican
t fi
gure
s.
2.
PW
HIP
res
po
nse
cal
cula
ted u
sin
g a
num
eric
al i
nte
gra
tion t
ime
step
of
0.0
005 s
econds
3.
PW
HIP
mo
del
in
clud
ed a
n i
nit
ial
gap
of
0.0
005".
It
is c
alcu
late
d t
hat
init
ial
kin
etic
ener
gy a
t th
e ti
me
of
imp
act
(0.0
015
sec
on
ds)
in
crea
ses
max
imu
m d
isp
lace
men
t b
y 0
.00
03
". T
her
efore
, th
e in
itia
l gap
res
ult
ed i
n a
max
imum
dis
pla
cem
ent
0.0
00
8"
gre
ater
th
an t
hat
of
a ze
ro g
ap
mo
del
.
[HIS
TO
RIC
AL
IN
FO
RM
AT
ION
– N
OT
RE
QU
IRE
D T
O B
E R
EV
ISE
D]
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-5
6 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-5
6.
Com
pa
riso
n o
f P
red
icte
d P
WH
IP R
esp
on
se -
In
ela
stic
Yie
ld E
lem
ent.
(E
xam
ple
Pro
ble
m:
Fig
ure
3-1
20
)
Res
pon
se
Th
eore
tica
l P
red
icti
on
1
PW
HIP
Pre
dic
tion
2
Co
ncl
usi
on
Tim
e o
f in
itia
l
imp
act
(y =
h)
to
0.0
71
98
sec
. y =
.9867"
@ t
= 0
.072 s
ec.
y =
1.0
145"
@ t
= 0
.073 s
ec.
PW
HIP
res
po
nse
is
wit
hin
on
e in
tegra
tion
tim
e
step
of
theo
reti
cal.
Vel
oci
ty a
t
init
ial
imp
act
yo
27
.78
5 i
n/s
ec.
in/s
ec
27
.70
.se
c0
01
.
.98
67
" -
"0
14
5.
1=
PW
HIP
res
po
nse
is
exac
t w
ithin
th
ree
sign
ific
ant
figure
s o
f ac
cura
cy.
Tim
e to
zer
o
vel
oci
ty
tm
0.1
00
37
sec
. 0
.101 s
ec.
PW
HIP
res
po
nse
is
wit
hin
on
e in
tegra
tion
tim
e
step
of
theo
reti
cal.
Max
imum
dis
pla
cem
ent
ym
1.5
50
6 i
n.
1.5
514 i
n.
PW
HIP
res
po
nse
is
exac
t w
ithin
th
ree
sign
ific
ant
figure
s o
f ac
cura
cy.
No
tes:
1.
Th
eore
tica
l re
spo
nse
bas
ed o
n t
he
solu
tion
by T
hom
ason,
Vib
rati
on T
heo
ry a
nd A
pp
lica
tion,
Pre
nti
ce-H
all,
19
65
.
2.
PW
HIP
res
po
nse
cal
cula
ted u
sin
g a
num
eric
al i
nte
gra
tion t
ime
step
of
0.0
01 s
eco
nds.
[HIS
TO
RIC
AL
IN
FO
RM
AT
ION
– N
OT
RE
QU
IRE
D T
O B
E R
EV
ISE
D]
McGuire Nuclear Station UFSAR Table 3-57 (Page 1 of 1)
(27 MAR 2002)
Table 3-57. HVAC Design Codes
Component Design Code
1. Standard for Installation of Air Cond'g. & Ventilation Systems NFPA 90A
2. Central Station Air Handling Units ARI 430-66
3. Chillers: ASHRAE 30-60
ARI 555-63
ARI 550-66
4. Coils: ARI 410-64
ASHRAE 33-64
5. Fans: AMCA 99
AMCA 210-67
6. Fire Dampers UL 555-1968
7. Electric Coils: UL 499-1968
NEMA HE-1-1966
8. Carbon Filters ANSI/ASME N509-
1976
9. Dampers Refer to system
purchase specification
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-5
8 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-5
8. M
axim
um
Def
lect
ion
s fo
r R
eact
or
Inte
rnals
Un
der
Blo
wd
ow
n a
nd
Sei
smic
Exci
tati
on
(1-M
illi
seco
nd
Do
ub
le-E
nd
ed B
rea
k)
[HIS
TO
RIC
AL
IN
FO
RM
AT
ION
– N
OT
RE
QU
IRE
D T
O B
E R
EV
ISE
D]
Co
mp
on
ent
Blo
wd
ow
n D
efle
ctio
n (
Inch
es)
Sei
smic
Def
lect
ion
,
(In
ches
) D
irec
tion
Ma
xim
um
To
tal
Def
lect
ion
,
(In
ches
)
All
ow
ab
le
Def
lect
ion
,
(In
ches
)
Def
lect
ion
fo
r
No
Lo
ss o
f
Fu
nct
ion
,
(In
ches
) C
old
Leg
H
ot
Leg
Upp
er B
arre
l
Rad
ial
Inw
ard
0
.0
0.0
57
0.0
02
Hori
zon
tal
0.0
59
4.1
8
.2
Rad
ial
Outw
ard
0.4
31
0.0
29
0.0
02
Hori
zon
tal
0.4
60
0.5
1
.0
Upp
er C
ore
Pla
te
0.0
16
0.0
15
0
Ver
tica
l 0
.01
6
0.1
00
1
0.1
50
Rod
Clu
ster
Co
ntr
ol
Guid
e T
ubes
(def
lect
ion a
s a
bea
m)
(54
)
<A
llow
able
0.0
10
Hori
zon
tal
<A
llo
wab
le
1.0
1
.60
to
1.7
5
(2)
<
N.L
.F
>A
llow
able
0.0
10
Hori
zon
tal
<N
.L.F
>A
llo
wab
le
1.0
1
.60
to
1.7
5
(5)
>
N.L
.F.
0.0
10
Hori
zon
tal
>N
.L.F
1
.0
1.6
0 t
o 1
.75
Fu
el A
ssem
bly
~
0
~0
~0
Hori
zon
tal
~0
0.0
36
0.0
72
Thim
ble
(C
ross
sec
tio
n d
isto
rtio
n)
Note
:
1.
On
ly t
o a
ssu
re t
hat
th
e pla
te w
ill
not
touch
a g
uid
e tu
be.
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-5
9 (
Pa
ge
1 o
f 1
)
(14
OC
T 2
00
0)
Ta
ble
3-5
9. M
axim
um
Str
ess
Inte
nsi
ties
for
Rea
ctor
Inte
rnals
(1-M
illi
seco
nd
Pip
e B
reak
an
d S
eism
ics)
[H
IST
OR
ICA
L I
NF
OR
MA
TIO
N –
NO
T R
EQ
UIR
ED
TO
BE
RE
VIS
ED
]
Co
mp
on
ent
BL
OW
DO
WN
ST
RE
SS
ES
, P
SI
H
ot
Leg
Bre
ak
C
old
Leg
Bre
ak
Maxim
um
Mem
bra
ne
Maxim
um
Tota
l
Maxim
um
Mem
bra
ne
Maxim
um
Tota
l
Dir
ect
Sei
smic
1
S
tres
s, p
si
Ver
tica
l/h
ori
z
Ma
xim
um
To
tal
Blo
wd
ow
n P
lus
Sei
smic
psi
Bar
rel
(Gri
th W
eld
) 21
,440
31,3
40
38
,900
46,2
00
10
0/4
00
46
,70
0
Bar
rel
(Fla
nge
Wel
d)
19
,820
29,7
20
18
,430
47,4
00
41
0/6
00
48
,71
0
Up
per
Suppo
rt C
olu
mn
s (1
) 6,2
00
39,2
00
---
---
---/
---
39
,20
0
(55
) 6,2
00
<20,3
00
---
---
---/
---
<2
0,3
00
Fu
el A
ssem
bly
- T
op
No
zzle
Pla
te
---
28,7
00
---
8,0
00
0/0
2
8,7
00
Fu
el A
ssem
bly
- B
ott
om
No
zzle
Pla
te
---
38,7
00
---
40,8
00
40
0/-
--
41
,20
0
Fu
el A
ssem
bly
Th
imb
les
6,6
00
6,6
00
2,3
00
2,3
00
---/
---
6,6
00
All
ow
able
Str
ess
Max
imum
Mem
bra
ne
Pm +
2.4
Sm +
39,8
00
psi
Max
imum
To
tal
Pm +
Pb =
3.0
Sm =
48
,000 p
si
S (
eval
uat
ed a
t 5
88
°F)
= 1
6,6
00
psi
(per
Win
ter
Adden
da
AS
ME
Sec
tion I
II C
ode)
No
te:
1.
Val
ues
are
for
hig
h l
evel
sei
smic
pla
nt.
McGuire Nuclear Station UFSAR Table 3-60 (Page 1 of 3)
(14 OCT 2000)
Table 3-60. Electrical Systems & Components Seismic Criteria [HISTORICAL INFORMATION –
NOT REQUIRED TO BE REVISED]
Equipment4
Base Load
Levels3
Freq. Range
(Hz)1
Air Conditioning System (Control, Equipment & Cable
Room)
Compressor Motors Note 2 -
Vent Fan Motors Note 2 -
Chill Water Pump Motors Note 2 -
Control Room Makeup Fan Motor Note 2 -
Equipment & Cable Room Makeup Fan Motor Note 2 -
Annulus Vent System
Fan Motors Note 2 -
Air Operated Valves (Solenoids) 0.5g 1 to 33
Aux. Bldg. Vent System
EFS Air Handling Unit Motors Note 2 -
Chemical & Volume Control System
Selected M.O. Valve Motors 0.5g 5 to 200
Containment Air Return System
Air Return Fan Motors Note 2 -
H2 Skimmer Fan Motors Note 2 -
Containment Spray System
Containment Spray Pump Motors Note 2 -
Selected M.O. Valve Motors 0.5g 5 to 200
Containment Isolation System
Containment Isolation Valve Motors 0.5g 5 to 200
Component Cooling Water System
Comp. Cooling Pump Motors Note 2 -
Selected M.O. Valve Motors 0.5g 5 to 200
Deisel Bldg. Vent. System
Diesel Room Supply Fan Motors
Emergency diesel Aux. Systems
Emerg. Diesel Generator Note 2 -
Dsl. Crank Case Vac. Pump Motor 0.25g 0.5 to 40
McGuire Nuclear Station UFSAR Table 3-60 (Page 2 of 3)
(14 OCT 2000)
Equipment4
Base Load
Levels3
Freq. Range
(Hz)1
Dsl. F.O. Transfer Pump Motor 0.25g 0.5 to 30
Dsl. L.O. Filter 0.25g 0.5 to 40
Dsl. 600/120V Pnl. Board 0.25g 0.5 to 40
Dsl. Lube Oil Pump Motors 0.25g 0.5 to 40
Dsl. Jacket & Intercoolant Pump Motor 0.25g 0.5 to 40
Dsl. Air Compressor Motors 0.25g 0.5 to 40
Auxiliary Feedwater System
Aux. Feedwater Pump Motor Note 2 -
Penetrations 0.25, 2.1 or 3.75g
depending on
location
0.5 to 40
4KV ES Aux. Power System
4KV Metalclad ES Switchgear 0.8g 0.5 to 50
4160/600V Transformers 0.8g 0.5 to 50
600V Essential Aux. Power System
600V ES Motor Control Centers 1.2g 1 to 40
600/208V Essential Transformers 0.4g 0.5 to 40
125V DC Vital Inst. & Cont. Power System
125V DC Battery Chargers 0.4g 0.5 to 40
125V DC Batteries 0.4g 0.5 to 40
125V DC Distribution Centers 1.2g 1 to 40
125V DC Panelboards 1.2g 1 to 40
120V AC Vital Power System
125VDC/120V AC Static Inverters 0.4g 0.5 to 40
120VAC Vital Pwr Panelboards 1.2g 1 to 40
Radioactive Waste Systems
RHR & CS Pump Room Sump Pump Motor Note 2 -
Residual Heat Removal System
Selected M.O. Valve Motors 0.5g 5 to 200
Safety Injection System
Motor Operated Valve Motors 0.5g 5 to 200
Steam Supply System
McGuire Nuclear Station UFSAR Table 3-60 (Page 3 of 3)
(14 OCT 2000)
Equipment4
Base Load
Levels3
Freq. Range
(Hz)1
Main Steam Iso. Valve Solenoids Note 2 -
Notes:
1. Hertz
2. Seismic qualification being accomplished by analyses
3. Meaning maximum horizontal ground or floor acceleration level for SSE
4. For other equipment see references sited in Section 3.1
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-6
1 (
Pa
ge
1 o
f 2
)
(13
AP
R 2
00
8)
Ta
ble
3-6
1. P
ost
-Acc
iden
t E
qu
ipm
ent
(In
sid
e C
on
tain
men
t) O
per
ati
on
al
Req
uir
emen
ts
Eq
uip
men
t N
am
e O
per
ati
ng
Mod
e R
equ
ired
Du
rati
on
of
Op
era
tio
n
INS
TR
UM
EN
TA
TIO
N
Pre
ssuri
zer
pre
ssu
re c
han
nel
s (4
) C
onti
nuou
s S
I In
itia
tio
n
Pre
ssuri
zer
level
ch
ann
els
(3)
Conti
nuou
s T
wo
wee
ks
Ste
am g
ener
ator
level
chan
nel
s N
/R (
16)
Conti
nuou
s F
ou
r m
on
ths
Rea
ctor
Coola
nt
syst
em p
ress
ure
W/R
(2)1
C
onti
nuou
s T
wo
wee
ks
Rea
ctor
Coola
nt
RT
D N
/R
Conti
nuou
s R
eact
or
Tri
p
Rea
ctor
Coola
nt
Syst
em R
TD
W/R
C
onti
nuou
s T
wo
wee
ks
Co
nta
inm
ent
Su
mp
Lev
el1
Conti
nuou
s F
ou
r m
on
ths
Co
nta
inm
ent
Pre
ssure
1
Conti
nuou
s T
hre
e m
on
ths
VA
LV
ES
& O
PE
RA
TO
RS
SIS
mo
tor
op
erat
ed v
alves
, h
igh
hea
d i
nje
ctio
n l
ine
(4)
Conti
nuou
s F
ive
min
ute
s
Co
nta
inm
ent
iso
lati
on
val
ves
, m
oto
r oper
ated
& s
ole
noid
op
erat
ed
Op
erat
e on
sig
nal
F
ive
min
ute
s
Co
nta
inm
ent
air
retu
rn &
H2 s
kim
mer
syst
em v
alves
O
pen
on s
ignal
F
ive
min
ute
s
OT
HE
R E
QU
IPM
EN
T
Del
eted
Per
20
08
Up
dat
e
Saf
egu
ard
eq
uip
men
t p
ow
er, co
ntr
ol
and
inst
rum
ent
cab
le
Conti
nuou
s 4 m
o.
Co
nta
inm
ent
Air
Ret
urn
and
H2 S
kim
mer
Fan
s an
d M
oto
rs
Conti
nuou
s 2 m
o.
Pen
etra
tio
ns
As
indic
ated
for
abo
ve
list
ed
equip
men
t
As
indic
ated
fo
r ab
ove
list
ed e
qu
ipm
ent
Co
nta
inm
ent
Hig
h R
ange
Rad
iati
on
Mon
itor
Det
ecti
ons
Conti
nuou
s T
wo
wee
ks
Aco
ust
ical
Val
ve
Po
siti
on
Mo
nit
or
Sen
sors
& A
mp
s C
onti
nuou
s T
wo
wee
ks
McG
uir
e N
ucl
ear
Sta
tio
n
U
FS
AR
Ta
ble
3-6
1 (
Pa
ge
2 o
f 2
)
(13
AP
R 2
00
8)
Eq
uip
men
t N
am
e O
per
ati
ng
Mod
e R
equ
ired
Du
rati
on
of
Op
era
tio
n
Lim
it S
wit
ches
C
onti
nuou
s F
ive
min
ute
s
Pre
ssure
Sw
itch
es
Conti
nuou
s F
ive
min
ute
s
No
te:
1.
Tra
nsm
itte
rs f
or
thes
e si
gn
als
are
loca
ted o
uts
ide
of
the
Conta
inm
ent.
2.
See
FS
AR
Fig
ure
1-9
th
rough
Fig
ure
1-1
6 f
or
loca
tio
n o
f E
quip
men
t.
McGuire Nuclear Station UFSAR Table 3-62 (Page 1 of 1)
(30 NOV 2012)
Table 3-62. Control Complex Areas Ventilation Systems Analysis Results
Control Complex Area Temperature1
Relative
Humidity1
Control Room 75°F 45%
Cable Room 85°F 30%
Battery and Equipment Room 80°F 50%
Switchgear Rooms 85°F 30%
Motor Control Center Rooms 85°F 30%
Ventilation Equipment Rooms 100°F 30%
Electrical Penetration Rooms (EL 767) 85°F 30%
Note:
1. The temperature and relative humidity values are nominal and may vary by ±5°F and ±10% RH
respectively.
