ML20079L637
| ML20079L637 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/28/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20079L639 | List: |
| References | |
| DPR-71-A-063 NUDOCS 8401260255 | |
| Download: ML20079L637 (16) | |
Text
'
- jan arcg'o UNITED STATES E y) g,( [,h NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 gw g CAROLINA P00ER & LIGHT COMPANY l
DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.63 License No. OPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated June 16, 1983, as supplemented fpril 28 and August 10, 1983, complies with the standards and reauirements' of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and reaulations set forth in 10 CFR Chapter I:
R.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and reaulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that ~such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this anendment will not be ininical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
P.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
l 8401260255 831228 PDR ADOCK 05000325 p
(2) Technical Specifications The Technical Specifications contained in Appendices' A and B, as revised through Amendment No. 63, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,!,).,Ybcvs~u-.
\\_*-sDomenic B. Vassallo, Chief cJ Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 28, 1983 i
+
,=
~
..e,.
ATTACHMENT TO LICENSE AMENDMENT N0. 63 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Remove Insert 2-4 2-4 3/4 3-3 3/4 3-3 3/4 3-6a 3/4 3-6a 3/4 3-8 3/4 3-8 3/4 3-48 3/4 3-48 3/4 3-49 3/4 3-49 3/4 3-50 3/4 3-50 3/4 3-51 3/4 3-51 3/4 3-51a 3/4 3-51a 3/4 3-52 3/4 3-52 3/4 3-52a 3/4 3-52a 3/4 6-30 3/4 6-30 3/4 7-12 3/4 7-12 be e
.O e
1 tu TAllLE 2.2.1-1 Q
REACTOR PROTECTION SYSTEll INSTRll!!ENTATION SETPOINTS H
e ALLOWAlil.E
- )
FilNGTIOflAL llNIT. AtlD IllSTRilHENT NUHiiER TRIP SETPOIllT VAI.llES s
l.
Intermediatu Range Monitor, Neut ron Flux - Iligli(I)
< 120 divisions of full scale
< 120 divisions (CS I-I RM-Kiiol A, B.C. D,E,F G,il) of full scale 2.
Average Power Range Monitor
'(CS I-A PRM-Cll. A,B,C, D, E, F)
~
a.
Neutron Flux - liigli, 15%(2)
< 15% of RATED TilERHAI. POWER
< 13% of RATED TilERHAL POWER h.
Flow-liiased Neutron Flux - liigb(3)(4)
< (0.66 W + 54%)
< (0.66 W + 54%)
[
Fixed Neutron Flux - liigli(4)
< 120% of RATED TilERHAL POWER
< 120% of RATED c.
TilERNAL POWER 1
Reactor Vessel Steam Dome Pressure - liigh
< 1045 psig
< 1045 psig
( ll 21 -PTH -1102 3A-1, 5-1, C-1,1)- 1 )
4.
Reactor Vessel Water level - Low, Level I
> +162.5 inches *
( H 21 -1.Til-fl017 A-I, B-1, C- !, D - 1 )
> +162.5 inches
- 5.
Itain Steam Line Isolation Valve - ClosureIS)
< 10% closed
< 10% closed
(!!21 -F022 A, B.C. D ;
H 21 -F028 A, II,C, b) 6.
!!ain Steam I.ine Radiation - liigh
< 3 x full power background
< 3.5 x full power g
( D 12-Ril-K603 A,II C. D) background t3 7.
licywe l l Pressure - liigh
< 2 psig
< 2 psig
( C / l -PTil-N002 A-l.11-1, C-1, D-1 )
~~
3 8.
Sc r.iin Discharge valiime llater level - liigh
< 109 gallons
< 109 gallons g
( C I I -1.Sil-N011 A,11, C. D)
(C I I -1.sil-4 51 tu, n,C, D) l
_~
tu TAlli.8 3.3.1-1 (Cont i nnett )
i REACTOR PROTECTIOti SYSTi'.fi ItlSTRUMENTATION O
APPL.ICAlli.E HINIMUM NLIMBER d
OPRIMTIONAI.
OPERAHl.E CliANNEI.S "3
l'llt!CflONAl. IINif AND lilSTRllMENT THlHilER C0tlHITIO!1S PER TRIP SYSTEM (a)
ACTIOrl l
- 7. ' llryyell Pressure - liigh 1, 2(")
2 6
( C71 -PT-N002A, B,C, D)
(C 71 -PT!!-NOO2 A-1,11-1, C-1, D-1 )
- 8. Scrain Discluirge Voluine Water Invel -
liigh 1,
2, 5( f )
2 5
( C l l -l.Sil-N013 A, H,C,1))
( C i l -l.Sil-4 516 A, lI, C, U) l N
IU) 9.
Tut hine Stop Valve - Closure I
4 8
(EllC-S VOS-I X. 2 X,3 X,4 X) lll. Turblue Control Valve Fast Closure.
I8)
Cont rol Oi l Pressure - 1.ow I
2 8
( EllC-PSI.- 17 5 6,17 5 7,17 58,17 59 )
I I. 1 cact or Moile Switch in Shutilown Position I,
2, 3,4,5 I
9
-(C71A-51)
- 12. Ilinual Sc rata 1, 2, 3, 4, 5 1
10
' ( G7 l - A-S'l A,15)
. o
- 3 t
~ b
. g r,
i *
.w
k.
i 1
tcw w
'A l
E I
"J
- me u
'A 3
3 2
4 :
C m:
Q Z U C
CC E
- C
- J
- m C.
C.
- J tt3 v t O
C
- J
=
4 l
ar*
=c
- E'
- . =
m l Z Z
Vl Vl Z
Z
=
"2 M U G/3 5
I
' 2 0 WJ 6'
u 0
- 9..=
e 4z u
Z M
D O
O O
- m Cf3 "J
-s
.a
-a t
%1 c:
1%
O '!
Z l' M E O
v,l C C e
4, he xv Nl
- m. '
..V i, m
=
. i.
_. =
M. 6.O.l' 1
6 w w Mi b6 au u?
- J g
c; a
.4
.J
=6 0
o
- C f 2w bl
-T
&a w
=
2 t0 Cw C
e 6
=
C
'A e
- g Y
M O2 l
.=
0w tz:
a
'J)
W
==
"J O
Ow Ml
- J U
==
'A l
^
J m
^
9w Z
==
.J
=
3
.O e
3 0 :
e u a Z
Q 6
- J u3N w.O a
y u.q==.
u L
.=
w eJ i2:
1 1
UI 2
T 1 *J tr.I u.
'3 0^
c I n G/3 E.:
Z 4
^^
-= X
- a.
N J w
=
J: n==
- J C O u<
"J.=
=
x
=
-O 1
3
=
c6.
.=
G E 6.
=
- T.
- u. u.
1 X N
m:'
l u M
.-s ae
- J u
Z a==
Q22 O *
' 7) N
'J Lw a
a
>3 2 1
- J
=
u 3
= <C
<C
- f'
-N w
a 6
u'J
=
em
.v e c
>n
-:e m o
=-
me X
e o
m u
=C' 2CO 6Ce k-N
=
3 w 2CZ eZ4
- c. i
.3 - -
e s
a be VZ t 6 f O t/3
- C 1
^
u m"f J
U L
-e u s=
u==
a c c
ou Z: : s s=
zmm m>-
u-m
= m um u :-
=;
m oc i
m i o=
- l,
_.. I
_I.
C 1.
1
- J t
U k i L *
- u ua
."3
-u
- ss s--
=
- : =
w~
- s
=,
auu
- co 2.a
- ca
- u
- u
- w ce uvu v
-em v
J
.=
a v wi =
m
?-
=
=
l y;
2,.
=.
-=t
=
=
i mi s
=
m i,
3RC!S*i!C - C;IT '.
1/1 2-Aa 1.nend=en: "o.
63 1
i
l l
D i E CR l l l
i i
l WQ
?
I i
ANH J0t I 5
5 E
SC 1
TNN A O A.
'4 4
RI l.
ETl 5
3 3
PI l
ODE l
r V 2
22 2
OR 2
2 l
S.
Cl T
S I
I I 1 I
{
1 1
I N
E 1
tE R
)
I_
d U.
I
)
E-.
N
(
O R
ET I'
L II l I
)
)
)
)
E NA I
(
(
A A
C NR R
R gH R
R R
N N
N Al l
A.
i I.
)
l d
l.
Cl e
l A
u i
C n_
H i
V-t R
n U
o S
C 0.-
N
(
l 1
1-A T
A-l.N
)
E OT 1
I r.
NI S I
g 3
f_
NTE H
H gil Q
H 1
K Q
t 1
s-R.- LACT 1
H 4
1 i
I Cl i
E.
R F
i T
l l
S A
l Ir.
T l
EK A
S
)
A A
A a
A n
t.
t NC N
k i N
N N
N l
E NE l
(
T _-
Al A
i S
liC_
N Y
C S
N-O-
I-T-
C E
18
)
r o_
e R-v 1
1 e
)
n l
1 r
9 w
P.
1 u
5 o
a r
e s
7 l
R-V D,
e r
s 1
t e
O-C.-
1 t
u t e T
n n
a s
s r 8
l i
u o
o i
C, H
o) aP 5
S A.
i i
lg)
) )
l X F
7 E.
t l
i t) 1 D, D, e
C4 R
a n
n l
1 a H, i D, I m
i ei i
l a
s C, C,
- X vO 7
a i
l o
)
d C, C,1 3,
l l
5 i
D, D, s
a o
e al
/
le l
l R
I V
i, l, RI I
vX V o I
e l, A aA r
F 1
t C, C, n3 u20 gli l 6 i 2, ii e
i eA rA2 e
a l t
(
u TH n
B, B, 1 1 VX on 5
S
)
I u i.
- i. 0 s 0
)i r g05 1
r o 7
l NN, AA 6
s0N aiN4 p-t C 1
i, I
l 1
e n
28 K
eN I
.l i i-l l
I f m
22 n -
r -
c l
oS n
l.
)
urM
.f i !
i i t O o
l l ae00 a!
PTT s -
S. S.
SV C e S
lonI I
AE erFF eR PP
.i oS cS f
1 l S
r l'
Nl t u-t -
l Dl - -
e -
eu rl A A
.l S -
f 0liH i
S s1 1 S2 l 1 1 eI nC ns C
oi 1
1 1
l l 22 l
e77 mv1 e
l l
l i
l oull t s7 a/
T nl s i nO wCC a e. C C lC{r l
l>E hl o.
l t
a P (C in(
c o oC C(
l i
i (
y( (
ri( (
- (
rCl (
t i.
a c
o o
t i
{
t l
D S
T T
R f
f F
1_
I 4
'A4 5
13
/
i t
b 0
1 1
1 1
1 s#du'h n:p,
n
.No **
2
)
u 6
'{0 g$:[j g n v.c g 8
.- 1 j
2 l
l ;
os TABLE 3.3.5.2-1 w
v>
REMOTE SilDTDOWN HONITORING INSTRUMENTATION M
E3 MINIM UM i
READO UT CHANNELS g
FUNCTIONAL UNIT AND INSTRUMENT NUMBER LOCATION OPERABLE
- 1. Reactor Vessel Pressure RSP*
1 (C32-PI-3332 and C32-PT-3332)
- 2. Reactor Vessel Water Level RSP*
1 (821-LI-3331, B21-LI-R504AX, B21-LT-3331, B21-LT-N026A, B21-LT-N017 D-3, and B21-LSil-N017 D-3)
- 3. Suppression Chamber Water Level RSP*
1 (CAC-LI-3342 and CAC-LT-3342)
- 4. Suppression Chamber Water Temperature RSP*
1
{h (CAC-TR-778-7)
Y
- 5. Drywell Pressure RSP*
I (CAC-PI-3341 and CAC-PT-3341)
- 6. Drywell Temperature RSP*
1 (CAC-TR-778-1,3,4)
- 7. Residual Heat Removal Head Spray Flow RSP*
1 (Ell-FT-3339 and Ell-FI-3339)
- 8. Residual Heat Removal System Flow RSP*
1 l
'O (Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338)
1 l
Discharge Differential Pressure f
(Ell-EDT-N002BK and Ell-PDI-3344)
O
- Remote Shutdown Panel, Reactor Building 20' Elevation
=. -
_ =. - _. _.
to gj TABLE 4.3.5.2-1 ai REMOTE SillTFDOWN MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS O
CHANNEL CIIANNEL FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK CALIBRATION c:
3
-3
- 1. Reactor Vessel Pressure M
Q (C32-PI-3332 and C32-PT-3332)
Q (B21-LI-3331, B21-LI-R604 AX, B21-LT-3331, B21-LT-N026A, B21-N017D-3, and l
B21-LSH-N017 D-3) l
- 3. Suppression Chamber Water Level M
R (CAC-LI-3342 and CAC-LT-3342) l
- 4. Suppression Chamber Water Temperature M
R (CAC-TR-778-7) w l
3:
l
- 5. Drywell Pressure M
Q m.
L (CAC-PI-3341 and CAC-PT-3341) e
- 6. Drywell. Temperature M
R (CAC-TR-778-1,3,4) t
- 7. Residual Heat Removal ifead Spray Flow M
Q (Ell-FT-3339 and Ell-FI-3339) l l
- 8. Residual Heat Removal System Flow M
Q l
l (Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338) 1 g
- 9. Residual IIeat Removal Service Water Discharge M
Q l
Differential Pressure l
(Ell-PDT-NOO2BX and Ell-PDI-3344) 8.
L
.- -=...
e INSTRLNENTATION POST-ACCIDENT MONITORING INSTRUMENTATION 1
LIMITING CONDITION FOR OPERATION 3.3.5.3 The post-accident monitoring instrumentation channels shown in Table 3.3.5.3-1 shall be OPERABIE.
i APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
l ACTION:
a.
With the number of OPERABLE post-accident mon'itoring channels less than required by Table 3.3.5.3-1, either restore the inoperable channels to OPERABLE status within 31 days or be in at least HOT SHITrDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
The provisions of Specification 3.0.4 are not applicable.
1 SURVEILLANCE REQUIREMENTS 1
i 4.3.5.3 Each of the above required post-accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK q
and CHANNEL CALIBRATION operations at the frequencies shown in Table i
4.3.5.3-1.
i 4
i 1
1
)
1 BRUNSWICK - UNIT 1
'.3/4 3-50 Amendment No. 63-
1 TABLE 3.3.5.3-1 I,
POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.
OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER HpNELS 1.
Reactor Vessel Pressure 2
(B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 4 2.
(B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37 ; and B21-LTM-NO37-1) 3.
Suppression Chamber Water Level 2
t (CAC-LT-2601; CAC-LI-2601-1)
(CAC-LT-2602; CAC-LR-2602) l
}
4.
Suppression Chamber Water Temperature 2
(CAC-TR-1258-14, 21; and C91-P602) 1 5.
Suppression Chatber Atmosphere Temperature 2
(CAC-TR-1258-17 thru 20; and C91-P602) 6.
Lrywell Pressure 2
(CAC-PI-4176; CAC-FT-4176; i
CAC-PR-1257-1; and CAC-PT-4175) 7.
Drywell Temperature 2
(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.
Drywell Radiation 2
(CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262; and CAC-AQH-1262-1, 2, 3) 1 9.
Drywell Oxygen Concentration 2(a)
L (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; 4'
CAC-AR-4409-41)
(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2; CAC-X-KY-4363-2;.
CAC-AR-4410-41)
H BRUNSWICK - UNIT 1 3/4 3-51 Amendment No.
63
k TABLE 3.3.5.3-1 (Continued)
POST-ACCIDENT MONfTORING INSTRUMENTATION MINIMUM NO.
OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 10.
Drywell Hydrogen Concentration Analyzer and Monitor 2(a)
(CAC-AT-4409-38; CAC-AI-4409-32; CAC-X-XY-4348-1; CAC-X-XY-4349-1; CAC-AR-4409-42)
(CAC-AT-4410-38; CAC-AI-4410-32; CAC-X-XY-4362-1; CAC-X-XY-4363-1; CAC-AR-4410-42) 11.
Safety Relief Valve Position Indication:
1/ valve Primary - Sonic (B21-FY-4157 thru 4167) a.
b.
Secondary - Temp. (B21-TR-R614, points 1-11)
)
i 1
(a) An OPERABLE instrument' channel shall consist of the AT instrument and either the AI instrument or the XY-XY-AR instruments.
BRUNSWICK - UNIT 1 3/4 3-51a Amendment No. 63 i
o a,
_ TABLE 4.3.5.3-1 x
POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5
Q CHANNEL CHANNEL e
INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION C
1.
Reactor Vessel Pressure M
R (B21-Pl-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.
. Reactor Vessel Water Level M
R
( B21-LITS-N026 A, B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1) 3.
Suppression Chamber Water Level M
R (CAC-LT-2601; CAC-LI-2601-1; CAC-LT-2602; CAC-LR-2602) l 4.
Suppression Chamber Water Temperature M
R (CAC-TR-1258-14, 21; and C91-P602) 5.
Suppression Chamber Atmosphere Temperature H
R (CAC-TR-1258-17 thru 20; and C91-P602) w 6.
Drywell Pressure M
R Y
(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.
Drywell Temperature M
R
( CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.
'Drywell Radiation H
R (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262; and CAC-AQH-1262-1,2,3) 9.
Drywell Oxygen Concentration H
R (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-AR-4409-41)
(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2;
{
CAC-X-XY-4363-2; CAC-AR-4410-41)
E. '
10.
Drywell Hydrogen Concentration Analyzer and Monitor M
R (CAC-AT-4409.-38; CAC-Al-4409-32; CAC-X-XY-4348-1; 5
CAC-X-XY-434 9-1 ; CAC-AR-4409-42) z.
( CAC-AT-4410-38; CAC-AI-4410-32; CAC-X-XY-4362-1; CAC-X-XY-4363-1; CAC-AR-4410-42)
N TABLE 4.3.5.3-1 (Continued)
E M
POST-ACCIDENT MONITORINC INSTRUMENTt. TION SURVEILLANCE REQUIREMENTS M
CIIANNEL CIIANNEL E
INSTRUMENT AND INSTRUMENT NUMBER CliECK CALIBRATION 4
11.
Safety Relief Valve Position Indication a.
Primary - Sonic (B21-FY-4157 thru 4167)
M R
b.
Secondary - Temp. (B21-TR-R614, points 1-11)
M R
c.
R u
I a
e s,
CONTAINMENT SYSTEMS CAS ANALYZER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6.4 Two independent gas analyzer systems for the drywell and suppression chamber shall be OPERABLE with each system consisting of an oxygen analyzer and a hydrogen analyzer.
APPLICABILITY: OPERATIONAL CONDITION 1.
l ACTION:
With one oxygen and/or one hydrogen analyzer inoperable, restore at a.
least two oxygen and two hydrogen analyzers to OPERABLE status within 31 days or be in at lee 3t STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The provisions of Specification 3.0.4 are not applicable.
~
b.
With no gas analyzer OPERABLE for oxygen and/or hydrogen, be in at least STARTUP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.6.4 Each gas analyzer system (CAC-AT-4409, Division I and CAC-AT-4410, Division II) shall be demonstrated OPERABLE at least once per 92 days by performing a CHANNEL CALIBRATION using standard gas samples containing a nominal:
Zero volume percent hydrogen, balance nitrogen.
l a.
b.
Seven to ten volume percent hydrogen, balance nitrogen.
c.
Twenty-five to thirty volume percent hydrogen, balance nitrogen.
d.
Zero volume percent oxygen, balance nitrogen.
e.
Seven to ten volume percent oxygen, balance nitrogen.
f.
Twenty to twenty-five volume percent oxygen, balance nitrogen.
1 l
BRUNSWICK - UNIT 1 3/4 6-30 Amendment No. 63
to h
TABLE 3.7.5-1 (Continued)
M M
SAFETY-RELATED HYDRAULIC SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE, ZONE **
TO REMOVE Condensate Drain System IB21-51SS103 Drywell 29' I
No No SISS105
- 29' I
No No 51SS106 26' I
No No 50SS109 18' I
No No 50SSI11 31' I
No No 51SSil3 28' I
No No 51SS115 23' I
No No SISSil8 24' I
No No Control Rod Drive Systee y
ICIl-16SS10 Drywell 72' I
No No 16SSI1 72' I
No No
'y-16SS12 72' I
No No C
High Pressure Coolant Injection System lE41-4SS44 Drywell 40' I
No No 4SS45 35' I
No No 4SS47 40' I
No No 4SS49 37' I
No No
.4SS50 50' I
No No 4SSSI 30' I
No No 60SS9 Reactor Building 4'
A No No 6SS27
-5' A
No No 6SS28 l'
A No No
.,k 6SS30
-l' A
No No g,
6SS32
-5' A
No No g
6SS33 l'
A No No S
6SS35
-l'~
A No No 6SS36
-5' A
No No 2
.