ML20151B420
| ML20151B420 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/01/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151B423 | List: |
| References | |
| NUDOCS 8804080222 | |
| Download: ML20151B420 (15) | |
Text
'o, UNITED STATES
'n NUCLE AR REGULATORY COMMISSION g
a WASHINGTON, D. C. 206b5
%.....}
CAROLINA POWER & LIGHT COMPANY, et al, DOCKET N0. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendmant No.146 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for uendment by Carolina Power & Light Company (the licensee), dated September 29, 1987, as supplemented November 24, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth.in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisionc of the Act, and the rules and regulacicas of the Comission; C.
Thcre is reasonable assurance (i) that the activities authoriad by this amendment can he conducted without endangering the health and safety of the public, and (ii) that such activitfes will be conducted in compliance with the Comission's regulations; D.
The issuanca of this amendrdat will not be inimical to the I
comon defense and security or to tLa health and safety of the pu'.Jic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable require.ments have been satisfied.
2.
Accordingly, the license is smended by 6tanges to the Technical Specifications, as indicated it the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. OPR-62 is tereby amended to read as follows:
G804080222 880401 PDR AT>OCK 05000324 A
.,. ~... -...-... -..
~
. ]
l (2) Technical Specifications 1
The Technical Specifications contained in Appendices A and 8, as
~;
revised through Amendment No.
, are hereby incorporated in the license.
Carolina Power & Light Company shall operate the facility in 6ccordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance'and shall be implemented within 60 days o ' issuance.
F0P. THE NUCLEAR REGULATORY COMMISSION h(AA.d - bu-Cbg pfL Elinor G. Adensam. Director Project Directorate 11-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDHENT N0.146 FACILITY OPERATING LICENSE N0. DPR-62 DOCKET h0. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3/4 3-11 3/4 3-11 3/4 3-11a 3/4 3-11a 3/4 3-13 3/4 3-13 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 3-22 3/4 3-22 3/4 3-22a 3/4 3-22a 3/4 3-23 3/4 3-23 3/4 3-25 3/4 3-25 3/4 3-25a 3/4 3-25a 3/4 3-27 3/4 3-27
Ye an TABl.E 3.3.2-1 Pc 8
ISOLATION ACTUATION INSTRUMENTATION N
[j VALVE CROUPS MININUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL i
y TRIP FUNCTION AND INSTRUNENT NUMBER SICNAL(a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION I
1.
PRIMARY CONTAINMENT ISOLATION a.
1.
Low, Level 1 2,6,7,8 2
1, 2, 3 20 (821-LT-M017A-1,8-1 C-1,D-1)
(B21-LTH-W017A-1,5-1,C-1,D-1) 2.
Low, Level 2 3
2 1, 2, 3 20 (821-LT-NO24A-1,8-1, and 821-LT-NO25A-1,8-1) 10 (821-LTM-NO24A-1-1,B-1-1 and B21-LTM-NO25A-1-1,B-1-1) s.,
J, 3.
Low, Level 3 1
2 1, 2, 3 20 (821-LT-N024A-1,B-1 and r
821-LT-W025A-1,B-1)
(B21-LTS-N024A-1-2,8-1-2 and 821-LTS-N025A-1-2,8-1-2) 3-b.
Drywell Pressure - High 2, 6, 1 2
1,2,3 20 g
(C72-PT-N002A,B,C,D) g (C72-PTM-N002A-1,8-1,C-1,D-1)
<D S
c.
pf 1.
Radiation - High (d) 1 2
1, 2, 3(h) 21 (D12-RM-K603A,B,C,D) ww 2.
Pressure - Low 1
2 1
22 (B21-PT-NO15A,B,C,D) ya (821-PTH-NO15A-1,B-1,C-1,D-1) mM
~
. ~.
~.
un i
Ej TABLE 3.3.2-1 (Continued)
!N ISOLATION ACTUATION INSTRUMENTATION 9
VALVE CROUPS HINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL c.
TRIP FUNCTION AND INSTRUMENT NUMBEk SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION os 3.
Flow - liigh 1
2/line 1
22 (821-PDT-NOO6A,B,C,D; B21-PDT-NOO7A,B,C D; B21-PDT-NOO8A,B,C,D; 821-PDT-NOO9A,B,C,D)
(821-PDTM-NOO6A-1,B-1,C-1,D-1; B21-PDTM-NOO7A-1,8-1,C-1,D-1; B21-PDTM-NOG 3A-1,B-1,C-1,D-1; B21-PDTM-NOO9A-1,B-1,C-1,D-1)
M u
r u
d a
Et 3o On 1
E E
E Ei TABLE 3.3.2-1 rt
~
(Continued) 8 ISOLATION ACTUATION INSTRUMENTATION N
gj VALVE CROUPS HINIMUH NUMBER APPLI CABLE y
OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION 2.
SECOLT)ARY CONTAllttENT ISOLATION a.
Reactor Building Exhaust Radiation - High 6
1 1, 2, 3, 5, and*
23 (D12-RM-N010A,B) b.
Drywell Pressure - High 2,6,7 2
1, 2, 3 23 (C72-PT-N002A,B,C,D)
(C72-PTM-NOO2A-1,B-1,C-1,D-1) c.
Low, Level 2 3
2 1,2,3 23 l
(821-LT-NO24A-1,B-1 and
's 0-B21-LT-NO25A-1,8-1) l
[
(821-LTH-NO24A-1-1,B-1-1 and 821-LTM-N025A-1-1,8-1-1)
'a 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION ff a.
A Flow - High 3
1 1,2,3 24 g
(C31-dFS-N603-1A,lB) hf b.
Area Temperature - High 3
2 1, 2, 3 24 S
(C31-TS-N600A,B,C,D,E,F) jf c.
Area Ventilation A Temp. - High 3
2 1, ?, 3 24 (C31-TS-N602A,B,C,D,E,F) de SLCS Initiation 3 (f)
NA 1, 2, 3 24 (C41A-SI) vo e.
R$
Low, Level 2 3
2 1,2,3 24 l
(B21-LT-NO24A-1,B-1 and
- [
B21-LT-NO25A-1,8-1) ma (B21-LTM-N024A-I-1,B-1-1 and I
IC B21-LTH-N025A-1-1,8-1-1)
)
+
to E
TABLE 3.3.2-2 v,
ISOLATION ACTUATION INSTRUMENTATION SE7 POINTS O
ALLOWABLE TRIP FU'dCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE q
-.s
- 8 1.
PRIMARY CONTAINHENT ISOLATION ea a.
3 + 162.5 inches (*)
3 + 162.5 inches *)
I 1.
Low, Level 1 (821rLTH-NOl?A-1,B-1,C-1,D-1)
I a) 3 + 112 inches *)
3 + 112 inches 2.
Low, I.evel 2 (B21-LTM-NO24A-1-1,B-1-1 and B21-i.TH-NO25A-1-1.B-1-1)
I 3 + 2.5 inches *)
3 + 2.5 inches (a) 3.
Low, Level J (821-LTS-N024A-1-2,B-1-2 and B21-LTS-N025A-1-2,B-1-2)
I b.
Drywell Pressure - High 1 2 psig
$ 2 psig y>
(C72-PTH-NOO2A-1,B-1 C-1,D-1) e c.
Radiation - liigh 5 3 x full power background (b) $ 3.5 x full power (b)
(D12-MM-K603A.8,C,D) background 2.
Pressure - Low 3 825 psig
- 825 psig (821-PTH-NO15A-1,B-1,C-1,D-1) 3.
Flow - liigh
$ 140% of rated flow
,,140% of rated flow g
(B21-PDTM-DOO6A-1,8-),C-1,D-1; y'
B21-PDTH-NOO7A-1,B-1,C-1,D-1; Q
B21-PDTM-NOO8A-1,8-1,C-1,D-1:
g B21-PDTH-NOO9A-1,8-1,C-1,D-1) 4.
Flow - Iligh
$ 40% of rated flow
$ 40% of rated flow
?
(B21-P:TrS-NOO6A-2; B21-PDTS-NOO78-2; go B21-PDTS-NOO8C-2; e
w B21-PDTS-NOO9D-2) no e
e
~
e
-d g
$m J
w%
on PU TABLE 3.3.2-2 (Continued)
EE ISOLATION ACTUATION INSTRIMENTATION SETPOINTS 7e ALLOWABLE
[j TRIP FUNCTION AND INSTRUMEKr NUMBER TRIP SETPOINT VALUE e-.
H PRIMARY CONTAINHENT ISOLATION (Continued) o, d.
Main Steam Line Tunnel Temperature - High
< 200*F
$ 200*F (B21-TS-N010A,B,C,D; M21-TS-40llA,B,C,D; B21-TS N012A,B,C,D;
~
B21-TS-N013A,B,C,D) c.
Condenser Vacuum - Low 3 7 inches Hg vacuum 3 7 inches Hg vacuum (B21-PTH-NO$6A-1,B-1,C-1,D-1) f.
Turbine Building Area Temp - High
$ 200*F
< 200*F t*
(821-TS-3225A,B,C,D; a
B21-TS-3226A,B,C,D; i*
B21-TS-3227A,B,C,D;'
((
521-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; l
821-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; 521-TS-3232A,B,C,D) 2.
SECONDARY COWTAINHENT ISOLATION f
Reactor Building Exhaust a.
2 (D12-BM-N010A,B)
~< 11 mr/hr
~ 11 mr/hr
[L Badiation - High o*
b.
Drywell Pressure - High y 2 p3ig
< 2 peig Ei (C72-P1N-NOO2A-1,B-1,C-1,D-1) t
==
c.
I 3 + 112 inches *)
3 + 112 inches (a) j Low, Level 2 Tu (B21-LTH-NO24A-1-1,8-1-1 and B21-LTH-NO25A-1-1,5-1-1)
~
D l
os 4
i A
Y Q
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 9
ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE i
U 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION u
a.
A Flow - liigh
< 53 gal / min 5 53 gal / min (C31-dFS-N603-1A,lB) b.
Area Temperature - liigh
~< 150*F
~< 150*F (C31-TS-N600A,B,C,D,E,F) c.
Area Ventilation Temperature a Temp - liigh 5 50*F
$ 50*F (C31-TS-N602A,B,C,D,E,F) d.
SLCS Initiation NA NA (C41A-SI) e.
3 + 112 inches (*}
3 + 112 inches (*}
tf Low, Level 2 (821-LTH-NO24A-1-1,B-1-1 and i*
B21-LTM-N025A-1-1,B-1-1) 5 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Isolation 1.
I!PCI Steam Line Flow - liigh
$ 300% of rated flow
$ 300% of rated flow (E41-PDTS-NOO4-2; E41-PDTS-N005-2) x M
2.
IIPCI Steam Line liigh 1/ low 1
Time Delay Relay 3 < t < 7 seconds
~
2 (E41-TDR-K33;
~
~
3<t ~< 12 seconds 5
E41-TOR-K43) 5i 3.
IIPCI Steam Supply Pressure - Low 3 100 psig 3 100 psig
( E41-PS L-NOOI A, B, C, D)
D 5
1 0
t TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME i
TRIP FUNCTION AND INSTRUMENT NUMBER PESPONSE TIME (Seconds)#
f 1.
PRIMARY CONTAINMENT ISOLATION a.
[
1.
Low, Level 1 113 (821-LT-N017A-1,B-1,C-1,D-1)
[
(B21-LTM-N017A-1,8-1,C-1,0-1) l 2.
Low, Level 2
<l.0*
(B21-LT-N024A-1,B-1 and B21-LT-N025A-1,8-1)
(B21-LTM-NO24A-1-1,B-1-1 and B21-LTM-NO25A-1-1,B-1-1) 3.
Low, Level 3
<l.0*
(821-LT-N024A-1,8-1 and B21-LT-N025A-1,B-1) l (B21-LTS-N024A-1-2,B-1-2 and f
821-LTS-N025A-1-2,B-1-2) b.
Dryvell Pressure - High
<13 (C72-PT-N002A,B,C,D)
(C72-PTM-N002A-1,B-1,C-1,D-1) f c.
<1.o*
1.
Radiation - High(D)
(D12-RM-K603A,B,C,D) l 2.
Pressure - Low
<13 i
(B21-PT-N015A,B,C,D)
~
(B21-PTM-N015A-1,B-1,C-1,0-1) l 3.
Flow - High
<0,5*
(B21-PDT-N006A,B,C,D; B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,Di i
B 21-PDT-N009 A, B, C, D ) --
f (821-PDTM-N006A-1,B-1,C-1,D-1, B21-PDTM-N007A-1,B-1,C-1,D-li B21-PDTM-N008A-1,B-1,C-1,D-1; i
321-PDTM-N009A-1,B-1,C-1,D-1) 4 Flow - High
<0.5*
(B21-PDTS-N006A-2; B21-PDTS-F0078-2; B 21-PDT3-!!CO8C-2 ;
B21-PDTS-N0090-2) l BRUNSWICX - UNIT 2 3/4 3-22 Amendment flo. 7/.146
-+ --
g,..
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)$
d.
Main Steam Line Tunnel Temperature - High
<13 (S21-TS-N010A,B,C,D;
~
B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,Di l
B21-TS-N013A,B,C,0) e.
Condenser Vacuum - Low
-<13 (B21-PT-N056A,B,C,D) 4 (B21-PTM-NOS6A-1,B-1,C-1,D-1) h i
e i
t f
i I
L i
1 4
I i
i i
BRUNSWICX - UNIT 2 3/4 3-224 Amendment No. 146 l[
i
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds M PRIMARY CONTAINMENT ISOLATION (Continued) f.
Turbine Building Area Temperature - High NA (821-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; j
i B'.1-TS-3 2 2 7A, B, C, D ;
i B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; t
B21-TS-3230A,B,C,D; i
B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)
L 2.
SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(D}
113 i
a.
(D12-R.M-N010 A, B )
b.
Drywell Pressure - High 113 (C72-PT-N002A,B,C,D)
(C72-P h-N002A-1,B-1,C-1,D-1) l Reactor Vessel Water Level - Low, Level 2
<l.0*
c.
(B21-LT-NO24A-1,B-1 and B21-LT-N025A-1,8-1)
(B21-LTM-N024A-1-1,3-1-1 and B21-LTM-N025A-1-1,3-1-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION A Flow - High
<t3 l
a (C31-dFS-N603-1A,lB) b.
Area Temperature - High 113 (C31-TS-N600A,B,C,D,E,F)
Area Ventilation Temperature a T - High
$13 c.
(C31-TS-N602A,B,C,D,E,F) 4 d.
SLCS Initiation NA 1
(CalA-SI)
{
Reactor Vessel Water Level - Low, Level 2 11.0<
e.
(B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
I (B21-LTM-NO24A-1-1,B-1-1 and 321-LTM-N025A-1-1,B-1-1) i BRUNSWICK - UNIT 2 3/4 3-23 en ent M. 9,7. W l
E E$
TABLE 4.3.2-1 M
ISOLATION ACTUATION INSTRtMENTATION SURVEILLANCE REQUIREMENTS y
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CilANNEL CONDITIONS IN WHICH y
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST _
CALI BRATION SURVEILLANCE REQUIRED 1.
PRIMARY CONTAINHENT ISOLATION a.
1.
Low, Level 1 (821-LT-N017A-1,B-1,C-1,D-1)
NA(*}
NA R(b) 1 2, 3 (B21-LTM-NOl7A-1,B-1,C-1,D-1)
D SA SA 1, 2, 3 l
2.
Low, Level 2 (B21-LT-N024A-1,8-1 and 821-LT-NO25A-1,B-1)
NA(a)
NA R(b) 1 2, 3 (B21-L1N-NO24A-1,8-1 and w
821-LTM-NO25A-1,B-1)
D SA SA 1, 2, 3 l
u 4
b.
Drywell Pressure - High (C72-PT-N002A,B,C,D)
NA NA R
1, 2, 3 j
u (C72-PTM-NOO2A-1,B-1,C-1,D-1)
D SA SA 1, 2, 3 l
c.
Radiation - High D
W R(d) 1 2, 3 (D12-RM-K603A,B,C,D) 2.
Pressure - Lov k
(821-PT-N015A,B,C,D)
NA ")
NA R(D) 1 I
SA SA 1
l i
(B21-PTM-NO15A-1,B-1,C-1,D-1)
D 3*
3.
Flow - High 5
(821-PDT-NOO6A,B,C,D; NA(a)
NA R(b) g g
821-PDT-NOO7A,B,C,D; B21-PDT-NOO8A,B,C,D; O
B21-PDT-NOO9A,B,C,D) n l
(B21-PDTM-N006A-1,B-1,C-1,D-1; D
SA SA 1
y C
B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTM-WOO 8A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1)
TABLE 4.3.2-1 (Contir.ued) r-is Id ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIRdHENTS fl a.
a CilANNEL OPERATIONAL CllANNEL FUNCTIONAL.
CllANNEL CONDITIONS IN WillCil i
'i TRIP FUNCTION ANr> INSTRUMENT NUMBER CIIECK TEST CALI BRATION SURVEILLANCE REQUIRED e.s 3.
Flow - liigh (B21-PDT-NOOoA,B,C,D; NA(a)
NA R(b) g B21-PDT-NOO7A,B,C,D; B21-PDT-NOO8A,B,C,D; B21-PDT-NOO9A,B,C,D)
(B21-PDTM-NOO6A-1,B-1,C-1,D-1; D
H H
I B21-PDTM-NOO7A-1,B-1,C-1,D-1; 321-PDTM-NOO8A-1,B-1,C-1,D-1;
}
B21-PDTM-NOO9A-1,B-1,C-1,D-1)
Y::
s.
l l
2 i
an D
t b
m
TABLE 4.3.2-1 (Continued) s M
ISOIATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS El
~
OPERATIONAL CllANNEL CIfANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil c
~~
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CAI.I BR ATION SURVEILLANCE REQUIRED 2.
SECONDARY CONTAINHENT ISOLATION a.
Reactor Building Exhaust Radiation - Higli D
H R
1,2,3,5, and *
(D12-RM-N010A,5) b.
lirywell Pressure - High NA *)
NA R(b) 1 2, 3 I
(C72-PT-N002A,B,C,D)
( C't 2-PTM-N002 A-1, B-1, C-1, D-1 )
D H
H 1, 2, 3 c.
Henctor Vessel Water Level -
Low, Level 2 (B21-LT-N024A-1,B-1 and NA(*}
'NA R(b) g, 2, 3 mp B21-1.T-N025A-1,B-1) y (821-I.TH-N024A-1-1,B-1-1 and D
H H
1, 2, 3 84 B21-LTH-NO25 A 1, B-1-1 )
l 3.
REACTOR WATER Cl.EANUP SYSTEM ISOLATION a.
A Flow - lii gh D
H R
1, 2, 3 (C31-dFS-N603-1A,lB) b.
Area Temperature - High NA H
R 1, 2, 3 (C31-TS-N600A,B,C,D,E,F) c.
Area VentiIation A Temp - High NA H
R 1, 2, 3 (C31-TS-N602A,B,C,D,E,F)
- g k
d.
SLCS Initiation NA R
NA 1, 2, 3 3
(C41A-SI) e.
g Low, i.evel 2 g
(B21-1.T-H024A-1,B-1 and NA(a)
NA R(b) 1, 2, 3 B21-I.T-NO25A-1,B-1) w7 (B21-l.TH-N024A-1-1,B-1-1 and D
M H
1, 2, 3-I B21-1.TH-NO25A-1-1,B-1-1)
I m
-