ML20083P501
| ML20083P501 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/28/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20083P504 | List: |
| References | |
| DPR-62-A-095, DPR-71-A-069 NUDOCS 8404200035 | |
| Download: ML20083P501 (35) | |
Text
[o na,'#o u
UNITED STATES i
[ [ v.,
NUCLEAR REGULATORY COMMISSION l
- .;y.-
/,C
- WASHINGTON, D. C. 20555 Nf...,
,1 I
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated March 16, 1982, as supplemented June 23 and September 6, 1983 and February 28, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations 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 Comission's regulations; D.
The issuance of this amendment will not be inimical 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.
2.
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:
8404200035 840328 PDR ADOCK 05000324 P
2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, 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
=
,. /,5
,,.,a.
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 28, 1984 4
e I
i i
4
ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. DPR-71 t
DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-14a 3/4 3-15 3/4 3-15 i
3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24 3/4 3-24a 3/4 3-24a.
3/4 3-24b 3/4 3-24b j
3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 i
3/4 3-29a 3/4 3-29a
]
3/4 3-29b l
1 4
i l
4
___.____.___________._..__..__..._.-.___.__.m.____
l i
(BSEP-1-18)
E-e TABLE 3.3.2-1 (Continued) c
~
O ISOLATION ACTUATION INSTRIMENTATION e
VALVE CROUPS MINIMUM NtMBER APPLICABLE j
OPERATED BY OPERABLE CilANNELS OPERATIONAL TRIP FUNCTION AND INSTRtMENT NIMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION d
4.
CORE STANDHY COOLING SYSTEMS ISOLATION t
a.
High Pressure Coolant Injection System Isolation 1.
HPCI Steam Line Flow - High 4
1 1,2,3 25 (E41-PI)T-NOM ;
(E41-PDTS-NOO4-2;
-i i
E41-PDTS-NooS-2)
(
1' 2.
IIPCI Steam Line liigh Flow t'
i Time iblay Relay NA 1
1,2,3 25 d
(E41-TDR-K33; i
'i' E41-Tun-K43) 3.
IIPCI Steam Supply Pressure - Low 4
2 j
(E41-PSL-N001A,B,C,D) 1,2,3 25 j
4.
HPCI Steam Line Tunnel Temperature - liigh 4
2 (E41-TS-3314; 1, 2, 3 25 I
I E41-TS-3315; E41-TS-3316; E41-TS-3317; i
E4I-TS-3318; a
i E41-TS-3354;
{
E41-TS-3488; s
E41-TS-3489) i n.
5.
Bus Power Honitor NA(h) 1/ bus 1, 2, 3 26
[
(E41-K55 and E41-K56)
E 6.
HPCI Turbine Exhaust i
Diaphragm Pressure - I!!gh 4
2
} $
(E41-PSit-N012A,B,C,D) 1,2,3 25 h
4 l
l (BSEP-1-18)
E c
U TABLE 3.3.2-1 (Continued)
~
O ISOLATION ACTUATION INSTRINENTATION VALVE CROUPS MININUM NLMBER APPLICABLE S
OPERATED BY OPERABLE CllANNELS OPERATIONAL g
TRIP FUNCTION AND INSTRillENT NtHBER SIGNAL.(a) ~
_PER TRIP SYSTEM (b)(c) CONDITION ACTION 7.
IIPCI Steam Line Ambient Temperature - !!! gh 4
1 1, 2, 3 25 (E51-TS-N603C,D) 8.
litt I St cam Li ne Ar ea A Te up. -
Ili gh 4
1
( E51,fTS-N604C.D) 1, 2, 3 25 e
9.
Emergency Area Cooler Temperature - liigh 4
1 1, 2, 3 25
( E41 -IS-NuO2A, B) i_,
8 D
b.
Reactor Cire Isolation Cooling System Isolation S'
,i, 1.
RCic Si cam Li ne FIou - 111 gh 5
1 o
(E5 I-PDT-Nul 7; 1, 2, 3 25 t
l E51-l*DT-N018)
(E51-PDTS-N017-2; E51 -PDTS-N018-2) i 2.
RCJC Steam Line liigh Flow l
' lime tulay Relay NA i
1, 2, 3 25 I
(E51-TDR-K32; E51-T Dl;-K I 2) 3.
RCIC Steam Simpply Pressure - Iow 5
2 g
( E51 -PS-N019.\\, B, C, D) 1, 2, 3 25 l'
ag 4.
RCIC St eam Line Tannel Temperature t
g
- Iligh
~,
2 g
(E51-TS-3319; 1, 2, 3 25 E51-TS-3 320; y
E51-TS-3321; E51-TS-3322;
.m ESI-TS-3323; t
E51-TS-3 355; E51-TS-3487) f
.- ~
w..
-~
4
..,m
_ -. -.. _. - _... -. _... -. - ~. - - _. - ~.
_~
(BSEP-1-18)
E e
TABLE 3.3.2-1 (Continued) c
~
O ISOLATION ACTUATION INSTRUMENTATION VALVE CROUPS MINIMUN NUMBER APPLICABLE g
OPERATED BY OPERABLE CHANNELS OPERATIONAL I
TRIP FUNCTION AND INSTRtDIENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION H
5.
Bus Power !!anitor NA (h) r 1/ bus 1, 2, 3 26 (E51-K42 and E51-K43) 6.
RCIC Turbine Exhaust Diaphragm Pressure - liigh 5
2 (E51-PS-Nol2A,B.C.D) 1, 2, 3 25 7.
RCIC Steam Line Ambient Temp -
Iligh 5
1 1,2,3 25 (E51-TS-N603A,8) 8.
RCIC Stean Line Area A Temp - High p
1 M
(E51-JTS-N604A,8) 1, 2, 3 25 l
e u
9.
RCIC Equipment Room Ambient Temp - Iligli 5
1 l
1, 2, 3 25 l
i l
(E51-TS-N602A,8) 10.
RCic Equipment Room A Temp - Iligh 5
1 l
(ESI-dTS-N60lA,B) 1, 2, 3 25 l
5.
SHUTDOWN C001.ING SYSTEM ISOLATION l
a.
Low, Level 1 2,6,7,8 2
l (821-LT-N017A-1.B-1,C-1,D-1) 1,2,3 27 (B21-LT1-Nol7A-1,B-1.C-1,D-l) g b.
Reactor Steam Dome Pressure-7, 8 1
5 High 1, 2, 3 27 l
E.
(B32-PS-N018A,B) m I
\\
4D l
1
(BSEP-1-18)
E 6
TABLE 3.3.2-2 (Continued)
EN ISOLATION ACTUATION INSTRIPIENTATION SETPOINTS 7:
TRIP FUNCTION AND INSTRlRIENT NUMBER ALLOWABLE
-2 TRIP SETPOINT VALUE U
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - liigli 1 53 gal / min 1 53 gal / min (C 31,lFS-N603-I A, I B) b.
Area Temperature - IIIgh
< 150*F
< 150*F (C31-TS-N600A,H,C,D.E.F)
Area Ventilation Temperature A Temp - High
< 50*F
< 50*F c.
(C 31-TS-N 602A, B, C, D. E. F) d.
SLCS Initiation NA NA (C41A-SI) ug e.
I Low, tevel 2
> + 112 inches *
> + 112 inches
- 4 (B21-LT 1-NO24 A-I,B-l and o
B21-LTH-NO25A-I,8-1) e 4.
CORE STAND 5Y COOLING SYSTEMS ISOLATION a.
Iligh Pressure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow - Iligh
< 300% of rated flow
< 300% of rated flow (E41-PDTS-No04-2; E41-PDTS-Noo$-2) 2.
IIPCI Steam Line fligh Flow Time Delay Relay 3 < t < 7 seconds 3 < t < 12 seconds f
(E41-TDR-K33;
[
E41-TDR-K43) 3.
HPCI, Steam Supply Pressure - Low
> 100 psig
> 100 psig l
a (E41-PSL-NootA,B,C,D)
.u O
ee
(BSEP-1-18) g TABLE 3.3.2-2 (Continued)
Og ISOLATION ACTUATION INSTRIMENTATION SETPOINTS E
M ALLOWABLE s
TRIP FUNCTION AND INSTRtNENT NiblBER TRIP SETPOINT VALUE Ey 4.
11101 St eam Line Tunnel Temperature - liigh
< 200* F
< 2 00* F l
( E41 -TS-3314 ;
y E41 -T S-3315 ;
E41 -TS-3316 ;
E41-T S-3317 ;
E4I-TS-3318; E41-T S-3354 ;
E41-TS-3488; E4 I-T S-34 89) 5.
Bus l' owe r ib n i t or
.NA NA l
(E41-K55 an.1 E41-K56)
R 6.
11101 Turbine Exhaust Diaphragm l
l'ressure - lii gh f 10 psig I'10psig y
( E41 -PSil-N012A, B, C, D) o 7.
IllCI Steam Li ne Ambient Temp - High
' 200* F
< 200*F
( E51 -TS-N603C, D) l 8.
11101 St eam Line Area a Temp - High I 50*F f 50*F l
(E51-d TS-N6 0!C,D) 9.
Emergency Area Cooler Temp - liigh
< 175'F
< 175'F l
(E41-TS-1;602A B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC St eam I.i ne Flow - Ili gh
< 300% of rated flow I 300% of rated flow i
g (E51-PUTS-tm17-2; i
E5 I-l'DTS-N o! 8-2) a g
2.
RCIC Steam Line High Flow Time lu lay Relay 3 < t < 7 seconds 3 < t < 12 seconds y
(E51-TDR-K12; E51-T UR-K I 2) 3.
RCIC Steam Supply Pressure - low
)_50 psig
)_50 psig l
( E51 -PS-N019A, B, C, D)
- -. - - - - ~ - - -
(BSEP-1-18)
E TABLE 3.3.2-2 (Continued) roc i
E ISOIATION ACTUATION INSTRIMENTATION SETPOINTS r.
4 8
{
TRIP FUNCTION AND INSTRINENT NIDfBER ALLOWABLE TRIP SETPOINT I
E VALUE
-j y
4.
RCIC St eas Line Tunnel Temp - High
< 175'F
< 175*F (E51-TS-3319; f
l r
}
E51-TS-3 320;
}
ESI-TS-3321;
]
E51-T S-3322; E51-TS-3123; E51-rS-3355;
{
E51-TS-3'.87) 5.
Bus Power Monitor NA NA s
(E51-K42 and E51-K43) l i
]
u 6.
RCIC Turbine Exhaust Diaphragm l
j 2
Pressure - Illgh
< 10 psig i 10 psig I
(E51-PS-Nol 2A,B,C D) u e
1 0
7.
RCIC St e.ma Line Ambient Temp - liigh
- < 200* F
< 200* F
( E51 -TS-N60M, B) 4 8.
RCIC St ema Line Area A Temp - High
< 50* F
< 50* F j
(E51 slTS-N6O!A,B) j 9.
RCIC Equipment Roon Ambient Temp - High
< 175* F
< 175*F
( E51 -TS-N602A, B) l f
10.
RCIC Equipnent Room A Temp - High
< $0*F
' < 50* F (E51 SITS-N6OIA,b) 1 i
5.
SilUTDOWN COOLING SYSTEM IS01.ATION k
N.
s a.
f{
low, level I 1 + 162.5 inches
- 1 + 162.5 inches
- l 2
(BZl-LTM-NOI 7A-1,B-1 C-1,D-1) r j
1 y
b.
Reactor Steam lume Pressure - IIIgh 1140 psig i 140 psig (B12-PS-Nultn,B) iI #
i
- Vessel water levels refer to REFERENCE LEVEL ZERO.
i
_ _.. ~ -, -. _
(BSEP-1-18)
TABLE 3. 3. 2 -3 ISOLATION SYSTEM INSTRDiENTATION RESPONSE TDIE TRIP FUNCTION AND INSTRDIENT NDiBER RESPONSE TIME (Seconds)#
1.
PRIMARY CONTAINMENT ISOLATION
~~
a.
Beactor Vessel Water Level -
1.
Iow, level 1 (B21-LT-N017A-1, B-1, C-1, D-1 ),
113 (B21-L n!-N017A-1, B-1, C-1, D-1) 2.
Low, level 2 (B21-LT-N024A-1, B-1 and 11.0*
B21-LT-N02 5A-1, B-1)
(B21-LDi-N024A-1, B-1 and
~
B21-LTM-N025A-1,B-1) b.
Drywell Pressure - liigh
<13 (C71-PT-N002A, B, C, D)
~
(C 71-P n!-N 002A-1, B-1, C-1, D-1) c.
Radiation - liigh(b)
<1.0*
(D12-RM-K603A,B,C D) 2.
Pressure - lov
<13
( B21-PT-N015A, B, C, D)
~
(B21-P r!-N015A-1, B-1, C-1, D-1) 3.
Flow - High.
<0.5*
(B21-P DT-N 006A,B,C,D ;
~
B21-PDT-N00 7A, B, C,D ;
B21-P DT-N008A, B, C,D ;
B21-PD T-N009A, B, C, D)
(B 21 -P Dnt-N006A-1, B-1, C-1, D-1 ;
B21 -PDTM-N00 7A-1, B-1, C-1, D-1 ;
B21-P Dnt-N008A-1, B-1, C-1. D-1 ;
B21 -PDT:1-N009A-1. B-1, C-1. D-1 )
d.
Main St eam Line Tunnel Temperature - High (B21-TS-N010\\,3,C,0;
<13
~
B21-T S-N 011A, B, C,D ;
B21 -TS-N012A, B, C,0 ;
B21-T S-N011\\, B, C,0) e.
Condensor Vacum - Low
( B21 -P T-N05 M, B, C. D)
(13
~
( B 21 -P T:H105 M-1. B-1 C-1 D-1)
BRUNSWICK - UNIT 1 3/4 3-22 knendnent No.
69
(BSEP-1-18)
TABLE 3.3.2-3 (Co ntinued)
ISOLATION SYSTEM INSTRDtENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NDtBER RESPONSE TIME (Seconds) #
PRIMARY CONTAINMENT ISOLATION (Continued)
~ '
f.
'Ibrbine Building Area Temperature - High NA (B21-TS-3225A,B,C,D; B21-T S-3 22 fA, B, C,D ;
B21 -TS-322 7A, B, C,D ;
B21-T S-3 2285, B, C,D ;
B21-TS-322 9A, B, C,D ;
B21-T S-3 2305, B, C,D ;
B21-TS-3231A,B,C,D; B21-T S-3 232A, B, C,D) 2.
SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - High(b) gg 3 a.
(D 12-RM-N010A, B) b.
Drywell Pressure - liigh
<13 (C71-PT-N00 2A, B, C, D)
(C 71-P T!!-N 002A-1, B-1, C-1, D-1)
Reactor Vessel Water lovel '- Low, lovel 2
<1.0*
c.
(B21-L T-N024\\-1, B-1 and B21-LT-N025A-1,B-1)
(B21-LT:1-N0241-1, B-1 and B21-LTM-N025A-1,B-1) 3.
REACTOR WATER CLEANUP SYSTE!! ISOLATION a.
A Flow - lii gh
<13 (G 31-d F S-N6 03-1A,1 B )
~
b.
Ar ea Temp e rature - liigh
<13 (G31-TS-N60 G\\, B, C, D, E, F) c.
Area Ventilation Temperature C - lii gh
<13 (G 31-T S-N6 02A, B, C.D. E, F) d.
SLCS Initiation NA (C41A-SI) e.
Pa nctor Vessel Water Level - Low, la vel 2
<1.04 (821-LT-N024 A-1, B-1 and B21-L T-N 02 5 A-1. B-1)
( B21-LT t-N02 4 A-1. B-1 and B21-L "Cl-N 02 5 A-l, B-1)
BRUNSWICK - UNIT 1 3/4 3-23 knendment No. 69
1 (BSEP-1-18)
TABLE 3.3.2-3 (Co ntinued)
ISOLATION SYSTEM INSTRlMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRINENT NINBER RESPONSE TIME (Seconds) #
4.
CORE STANDBY COOLING SYSTEMS ISOLATION High Pressure Coolant Injection System Isolation a.
1.
HPCI Steam Line Flow - High
<13(a)##
(E41-PDT-N004; E41-PDT-N005)
(E41-PDTS-N004-2; E41-PDTS-N005-2) 2.
nNI Steam Line High Flow Time Delay Relay NA (E41-TDR-K33 ;
E41-T DR-K43) 3.
HPCI St eam Supply Pressure - Low
<13 l
(E41-PS L-N001A, B, C, D) 4.
HPCI Steam Line Tunnel Temperature - High (E41-TS-3314 ;
<13 E41-IS-3315 ;
E41-TS-3316 ;
E41-T G-3317 ;
E41-TS-3318 ;
E41-T S-3 354 ;
E41-TS-3A88; E41-T S-3489) 5.
Bus Power Monitor NA l
(E41-K55 and E41-K56) t 6.
HPCI Turbine Exhaust Diaphragm Pressure - High (E41-PSil-N012A, B, C, D) l NA 7.
HPCI St eam Line Ambient Temperature - 111gh NA l
( E51-TS-N60 3C, D) 8.
HPCI St eam Line Area (E51-dTS-N604C D)
NA 9.
Emergency Area Cooler Temperature - liigh NA (E41-TS-602A,3) b.
Mactor Co re Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - 111gh
<13(a)H1
( E51-P DT-N017 ;
E51-PDT-N018)
(E51-P DTS-N017-2 ;
E51-PDTS-N018-2 )
BRUNS'*1CK - 1[ nit I 3/4 3-24 Amendment No.
69
~,.
~
(BSEP-1-18) r TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRth!ENTATION RESPONSE TIME t
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
I 2.
RCIC Steam Line High Flow l
Time Delay Relay NA r
}
(E51-TDR-K32; E51-TDR-K12) i 3.
RCIC Steam Supply Pressure - Low NA l
I (E51-PS-N019A,B,C,D) l 4.
RCIC Steam Line Tunnel Temp - High NA l
jl (E51-TS-3319; E51-TS-3320; 1
E51-TS-3321; l
E51-TS-3322; j
E51-TS-3323; E51-TS-3355; i
j E51-TS-3487)
J 1
5.
Bus Power Monitor NA l9 (E51-K42 and E51-K43)
Pressure - High l
6.
RCIC Turbine Exhaust Diaphragm NA
{
(E51-PS-N012A,B,C,D) l 7.
RCIC Steam.Line Ambient Temperature - High NA j
(E51-TS-N603A,B) 1 8.
RCIC Steam Line Area a Temp - High NA (E51-dTS-N604A,B) j 9.
Emergency Area Cooler Temperature - High NA k
(E51-TS-N602A,B) 3 1
l 10.
RCIC Equipment Room a Temp - liigh NA i
(E51-dTS-N601A,B) l 5.
SHUTDONN COOLING SYSTEM ISOLATION i
1 a.
Reactor Vossel Water Level - Low, Level 1 NA (B21-LT-N017A-1,B-1,C-1,0-1) i
( B 21 -LTil-N017A-1, B-1, C-1, D-1 )
1 l
l b.
Reactor Steam Dome Pressure - liigh NA j
( B 32-PS-N018A, B) i I
BRUNSWICK - UNIT 1 3/4 3-24a Amendment No.
69 i
(BSEP-1-18) i i
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME i
NOTES (a)
The isolation system instrumentation response time shall be measured and I
recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Isolation
)
system instrumentation response time specified includes the delay for i
diesel generator starting assumed in the accident analysis.
l (b)
Radiation monitors are exempt from response time testing.
Response time l i
shall be measured from detector output or the input of the first
]
electronic component in the channel.
J t
Isolation actuation instrumentation response time only.
l i
l Isolation system instrumentation response time specified for the Trip
]
Function actuating each valve group shall be added to isolstion time shown in Table 3.6.3-1 and Table 3.6.5.2-1 for valves in each valve
}
group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
j Includes time delay added by the time delay relay (E41-TDR-K33 and E41-TDR-K43).
i Includes time delay added by the time delay relay i
(E51-TDR-K32 and E51-TDR-K12).
1 i
=
1 I
I i
i i'
r 1
i J
l l
i l
\\
l t
- BRUNSWICK - UNIT 1 3/4 3-24b Amendment No.
69
(BSEP-1-18)
N TABLE 4.3.?-l (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3
CHANNEL OPERATIONAL j
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
]
y TRIP FUNCTION AND INSTRtDIENT NIE1BER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
Ifigh Pressure Coolant Injection System Isola, tion 1.
IIPCI Steam Line Flow - liigh (E41-PDT-N004; NA(a)
NA R(b) 1, 2, 3 4
E41-Pl>T-NOOS)
(E41-PDTS-Noo4-2; D
H H
1, 2, 3 E41-PDTS-N005-2)
I R
2.
IIPCI Steam Line Illgh Flow l
Time Delay Relay NA R
R 1, 2, 3 y
(E41-TDR-K33; y
E41 -Ti>R-K4 3 )
l 3.
HPCI Steam Supply Pressure -
Iow NA H
R 1, 2, 3 l
(E41-PSL-NOOIA,B,C,D) 4.
IIPCI Steam Line Tunnel
]
Temperature - lilgh NA M
Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; l
E41-TS-3316; E41-TS-3317; E41-TS-3318; ik E41-TS-3354;
! E, E41-TS-3488; 2
E41-TS-3489) n 5.
Bus Power Monitor NA R
NA 1, 2, 3
',y
'(E41-K55 and E41-K56) 6.
HPCI Turbine Exhaust l$
Diaphragm Pressure - High NA H
Q 1, 2, 3 lg (E41 -PSil-N012A, B,C, D) i.
~
i
, s, (BSEPhl-18) g top TABLE 4.3.2-1 (Continued) i' S
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL h
TRIP FUNCTION AND INSTRI4!ENT NilMBER CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN IJHICH CllECK TEST CALIBRATION SURVEILLANCE REQUIRED H
H
- 7. ' t!!'CT Steats Line Asnblent i
Temp - liigh NA M
R 1, 2, 3 (E51-TS-N603C,D)
S.
IIPCI Steam Linh Area 4
A Temp - liigh NA M
R 1, 2, 3 (E51-dTS-N604C,D) 9.
Emergency Area Cooler 1
l Temp - Iligh.
NA H
Q 1, 2, 3 (E41-TS-N602A,B) m D
b.
Re.ici.br Core Isolatihn Cooling S'ystem Isolation M
- 1.
RCIC Steam Line Flow - liigh (E51-PI)T-N017; NA(a)
ID}
NA R
E51-PDT-Nol8) 1, 2, 3 (E51-PDTS-Nol7-2; D
H M
1, 2, 3
'{E51-PDTS-Nol8-2) 2.
RCIC Steam Line liigh Flow Time Delay Relay NA R
R 1, 2, 3
,s
, (E51-TDR-K32; ESI-TDR-Kil) 3.
RCIC Steam Supply y
Pressure - I.ow NA H
Q 1, 2, 3
( E51 -PS-No l 'JA,8, C, D) c.
a
s (BSEP-1-18)
E E
TABLE 4.3.2-1 (Continued)
U ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS S
CHANNEL OPERATIONAL c:
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
$ TRIP FUNCTION AND INSTRIRIENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED j
H 4.
RCIC Steam Line Tunnel liigh Temperature NA H
R 1, 2, 3 (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355;
)
E51-TS-3487)
Si 5.
Bus Power !bnitor NA i
R NA y
(E51-K42 and E51-K43) 1, 2, 3 w
f, 6.
RCIC Turbine Exhaust l
y Diaphragm Pressure - High NA M
R-(E51-PS-N012A,B,C,D) 1, 2, 3 7.
RCIC Steam Line Ambient Temp - Iligh NA M
R 1, 2, 3 (E51-TS-N603A,B) 8.
RCIC Steam 1.ine Area a Temp - liigh NA M
R 1, 2, '
(E51-dTS-N604A,B) 9.
RCIC Equipment Room Ambient Temp - liigh NA M
Q 1, 2, 3 j[
(E51-TS-N602A,B) a j
10.
RCIC Equipment Room A a
Temp - liigh NA M
Q 1, 2, 3 (E51-JTS-N601A,B)
s (BSEP-1-18) en g
TABLE 4.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CilANNEL OPERATIONAL CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED H
5.
SHUTDOWN COOLING SYSTEM ISOLATION Reactor Vessel Water Level -
a.
Low, Level 1 (B21-LT-N017A-1,B-1,C-1,D-1)
NA(a)
NA R(b)
(li21 -LTM-N017A-1, B-1, C-1, D-1)
D M
M 1, 2, 3 1, 2, 3 b.
Reactor Steam Dome Pressure -
liigh NA S/U(c),M R
(1132-PS-No l aA, B) 1, 2, 3 u,
's-i LJ h
- When handling irradiated fuel in the secondary containment.
- When reactor steam pressure > 500 psig.
(a) The transmitter channel check is satisfied by the trip unit channel check, A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
(c) If not performed within.the previous 31 days.
, g-lP
~
t
p stro,
u I
]
gi 70,,
UNITED STATES y
g NUCLEAR REGULATORY COMMISSION
[
3
..E WASHINGTON D. C. 20555
,o
+....
CAROLINA POWER & LIGHT COMPANY J
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 3
License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company 1
(the licensee) dated March 16, 1982, as supplemented June 23 and September 6, 1983 and February 28, 1984, complies with the standards 4
)
and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the CommissLn's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
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-62 is -
hereby amended to read as follows:
2-I (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, 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 tiis date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
?:
, u.':_
y,,,
?
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 28, 1984 e
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 95 l
FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-14a 3/4 3-15 3/4 3-15 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 i
3/4 3-24 3/4 3-24 3/4 3-24a 3/4 3-24a 3/4 3-24b 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 3/4 3-29a 3/4 3-29a r -
(BSEP-2-18) a, Ed TABLE 3.3.2-1 (Continued) c s
ISOLATION ACTUATION INSTRM1ENTATION VALVE GROUPS HINIMUM NUMBER APPLICABLE c:
OPERATED BY OPERABLE CllANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
_PER TRIP SYSTEM (b)(c) CONDITION ACTION
- -1 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow - High 4
1 1, 2, 3 25 (E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Line liigh Flow Time Delay Relay NA 1
1,2,3 25 (E41-TI)R-K33 ;
E41-TDR-K43)
I 3.
IIPCI Steam Supply Pressure - Low 4 2
t' (E41-PSL-N001A,B,C,D) 1, 2, 3 25 l
4-u, 4.
IIPCI Steam Line Tunnel 4
Temperature - liigh 4
2 l
(E41-TS-3314; 1, 2, 3 25 E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 5.
Bus Power Monitor NA
-1/ bus 1, 2, 3 26 l
I)
(E41-K55 and E41-K56) a 6.
IIPCI Turbine Exhaust Diaphragm Pressure - liigh 4
2 l
g (E41-PSil-No l 2A, B,C, D) 1, 2, 3 25 m:
7.
IIPCI Steam Line Ambient P
l Temperature - liigh 4
1 (E51-TS-N603C,D) 1, 2, 3 25 m
u,
(BSEP-2-18) b3 E
TABLE 3.3.2-1 (Continued) a s
O
_1 SOLATION ACTUATION INSTRUMENTATION VALVE CROUPS MINIMUM NUMBER APPLICABLE c:
OPERATED BY OPERABLE CilANNELS OPERATIONAL 3
TRIP FUNCTION AND INSTRUMENT NUMBER 4
SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION N
8.
IIPCI Steam Line Area A Temp. -
liigh l
4 1
(E51-dTS-N604C,D) 1, 2, 3 25 9.
Emergency Area Cooler Temperature - liigh 4
1 1, 2, 3 25 (E41-TS-N602A,B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - liigh 5
1 1, 2, 3 25 (E51-dPIS-N017 and E51-dPIS-N018)
. y I
)
2.
RCIC Steam Line liigh Flow y
Time Delay Relay NA 1
g (E51-TDR-K32; 1,2,3 25 m
e E51-TDR-K12) 3.
RCIC Steam Supply Pressure - Low 5
2 1, 2, 3 25 l
(E51-PS-N019A,B,C,D) 4.
RCIC Steam Line Tunnel Temperature l
- Ifigh 5
2 1, 2, 3 25 (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; J
g E51-TS-3323; y
E51-TS-3355; a-S E51-TS-3487)
S 5.
Bus Power Monitor NA (h) 1/ bus 1, 2, 3 26 l
4 (E51-K42 and E51-K43) u 6.
RCIC Turbine Exhaust Diaphragm Pressure - liigh 5
2 1,2,3 25 e*
(E51-PS-N012A,B,C,D) s
(BSEP-2-18) en
]-
TABLE 3.3.2-1 (Continued) h 9
ISOLATION ACTUATION INSTRUMENTATION VALVE CROUPS MINIMUM NUMBER APPLICABLE g
OPERATED BY OPERABLE CllANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER g
SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION H
7.
RCIC Steam Line Ambient Temp -
liigh 5
1 1, 2, 3 25 (E51-TS-N603A,B) 8.
RCIC Steam Line Area A Temp - liigh 5
1 (E51-dTS-N604A,B) 1, 2, 3 25 l
9.
RCIC Equipment Room Ambient Temp - !!!gh 5
1 1, 2, 3 25 l
(E51-TS-N602A,B) t,'
10 RCIC Equipment Room A Temp - liigh
'5 1
(E51-dTS-N601A,8) 1, 2, 3 25 j
Y G
5.
SiluTDONN COOLING SYSTEM ISOLATION E
a.
1.ow, level 1 2,6,7,8 2
(B21-LT-N017A-1,B-1,C-1,D-1) 1,2,3 27
( B 21 -I.Tri-NO l 7A-1, B-1, C-1, D-1 )
b.
Reactor Steam Dome Pressure-7, 8 1
1, 2, 3 27 liigh (B32-PS-N018A,B) i a
i Gn
(BSEP-2-18)
Ee M
TABLE 3.3.2-2 (Continued)
A ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION AND INSTRUMENT NUMBER ALLOWABLE
_ TRIP SETPOINT VALUE U
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION w
a.
A Flow - liigh 1 53 gal / min 1 53 gal / min (C31-dFS-N603-1A,IB) b.
Area Temperature - liigh
< 150*F (C31-TS-N600A,B,C,D,E,F)
< 150*F Area Ventilation Temperature A Temp - liigh
< 50*F
< 50*F c.
(G31-TS-N602A,B,C,D,E,F) d.
SLCS Initiation NA NA y
(C41A-SI)
I s~
g 4
I.ow, Level 2
> + 112 inches *
> + 112 inches *
(ll21-LTM-N(124A-1,ll-1 and
'i 1121 -LTM-NO2 SA-1,ll-1 )
4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow - Ifigh
< 300% of rated flow
< 300% t - rated flow (E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Line liigh Flow Time Delay Relay 3 < t < 7 seconds 3 < t < 12 seconds (E41-TDR-K33; E41-TDR-K43) g, 3.
IIPCI Steam Supply Pressure - Low
)_ 100 psig
> 100 psig l
,q (E41-PSL-N001A,B,C,D)
?
4 -
\\
(BSEP-2-18)
E TABLE 3.3.2-2 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SETPOINTS R
ALLOWABLE TRIP FUNCTION AND INSTRUtlENT NUMBER TRIP SETPOINT VALUE i
U 4.
IIPCI Steam Line Tunnel Temperature - liigh
< 200*F
< 200*F N
(E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 5.
Bus Power Monitor
' NA NA R
(E41-K55 and E41-K56)
I s~
6.
IIPCI Turbine Exhaust Diaphragm u
j' L
Pressure - Iligh 1 10 psig i 10 psig o
(E41 -PSil-N012A, B, C, D) l 7.
IIPCI Steam Line Ambient Temp - liigh
< 200*F
< 200*F (E51-TS-N603C D) l 1
8.
IIPCI Steam Line Area A Temp - liigh
< 50*F
< 50*F (E51-dTL-N604C,D) 9.
Emergency Area Cooler Temp - liigh
< 175'F
< 175'F (E41-TS-N602A,B) l b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Ste m Line Flow - liigh
< 300% of rated flow
< 300% of rated flow k
(E51-dPIS-N017 and E51-dPIS-N018) n 2.
RCIC Steam Line liigh Flow h
Time Delay Relay 3 < t < 7 seconds 3 < t < 12 seconds (E51-TDR-K32;
'j E51-TDR-K12) 3.
RCIC Steam Supply Pressure - Low 1 50 psig 1 50 psig l
(E51-PS-N019A,B,C,D)
(BSEP-2-18) en m
0 TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS R
ALLOWABLE TRIP FtINCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE' sH 4.
RCIC Steam Line Tunnel Temp - High
< 175*F
< 175'F (E51-TS-3319; l
u E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-33S5; E51-TS-3437) 5.
Bus Power Monitor NA NA (E51-K42 ant! E51-K43) l i
ug 6.
RCIC Turbine Exhaust Diaphragm l
l're s s u re - liigh 1 10 psig i 10 psig 4
(E51-PS-No12A,B,C,D) w 7.
RCIC Steam Line Ambient Temp - Iligh
< 200*F
< 200*F
( E 51 -TS-tJ603 A, B) 8.
RCIC Steam Line Area A Temp - Ilfgh
< 50*F
< 50*F l
(E51-dTS-N604A,B) 9.
RCIC Equipment Room Ambient Temp - liigh
< 175*F
< 175'F (E51-TS-N602A,B) 10.
RCIC Equipment Room A Temp - High
-< 50*F
< 50*F l
(E51-JTS-N601A,B) 5.
SHUTDOWN COOLING SYSTEM ISOLATION n.
a.
l Low, Level I
> + 162.5 inches *
> + 162.5 inchea*
(ll21 -LTri-N017 A-1, B-1, C-1, D-1 )
a
's
,o b.
Reactor Steam Dome Pressure - Iligh 1 140 psig i 140 psig
( H 32-PS-No I BA,11) u, a Vessel water levels refer to REFERENCE LEVEL ZERO.
(BSEP-2-18)
TABLE 3.3.2-3 ISOLATION SYSTDI INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
1.
_ PRIMARY CONTAINMENT ISOLATION Reactor Vessel Water Level -
a.
1.
Low, Level 1
, _13 (B21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) 2.
Low, Level 2 (B21-LT-N024A-1,B-1 and j:1.0*
i B21-LT-N025A-1,B-1)
(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) b.
Drywell Pressure - High (C72-PS-N002A,B,C,D) j:13 c.
Radiation - High(b)
<1.0*
I 4
1 (D12-RM-K603A,B,C,D) 2.
Pressure - Low (B21-PT-N015A,3,C,D)
<13
~~
j (B21-PTM-N015A-1,B-1,C-1,D-1)
I i
3 '.
Flow - High
<0.5*
1 (B21-PDT-N006A,B,C,D;
~~
B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C,D)
.(B21-PDTM-N006A-1,B-1,C-1,D-1; B 21-PDTM-N007A-1, B-1, C-1, D-1 ;
B21-PDTM-N008A-1,B-1,C-1,D-1; B 21-PDTM-N009A-1, B-1, C-1, D-1 )
4.
Flow - High-(B21-PDTS-N006A-2;
. <0.5*
B21-PDTS-N007B-2; B21-PDTS-5008C-2; B21-PDTS-N009D-2) d.
Main Steam Line Tunnel Iamperatura - High (B21-TS-N010A,B,C,D;
<13
~~
B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.
Condenser Vacuum - Low (B21-PS-N056A,B,C,D)
<13
~~
BRUNSWICK-UNIT 2 3/4 3-22 Amendment No. 95
(BSEP-2-18) l TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRif!ENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
f.
Turbine Building Area Temperature - High NA
~
(B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A, B, C, D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D) 2.
SECONDARY CONTAINMENT ISOLATION Reactor Building Exhaust Radiation - Higb(b)
~~gg3 a.
(D12-RM-N010A,B) b.
Drywell Pressure - High (13 (C72-PS-N002A,B,C,D)
~~
Reactor Vessel Water Level _ Low, Level 2
<l.0*
c.
(B21-LT-N024A-1,B-1 and
~~
B21-LT-N025A-1,B-1)
(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High 4
(13 i
(G31-dFS-N603-1A,1B)
~~
b.
Area Temperature - High (13 (C31-TS-N600A,B,C,D,E,F)
~~
Area Ventilation Temperature AT - High c.
<13 (G31-TS-N602A,B,C,D,E,F)
~~
d.
Reactor Vessel Rater Level - Low, Level 2 e.
<l.0*
l (B21-LT-N024 A-1,B-1 and B21-LT-N025 A-1,3-l)-
1 (B21-LTM-N024 A-1,3-1 and B21-LTM-N025 A-1,3-1) i
.I:
BRUNSWICK - UNIT 2 3/4-3-23 Amendment No.
95 1
,c.
y
_,,r
(BSEP-2-18)
TABLE 3.3.2-3 (Continued) i ISOLATION SYSTEM INSTFDIENTATION RESPONSE TI'1E TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 1.
HPCI Steam Line Flow - High 113(8)##
l (E41-dPIS-N004 and E41-dPIS-N005) 2.
HPCI Steam Line High Flow Time Delay Relay NA (E41-TDR-K33; E41-TDR-K43) 3.
HPCI Steam Supply Pressure - Low 113 l
(E41-PSL-N001A,B,C,D) 4.
HPCI Steam Line Tunnel Temperature - High 113 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 5.
Bus Power Monitor NA l
(E41-K55 and E41-K56) 6.
HPCI Turbine Exhaust Diaphragm Pressure - High NA l
(E41-PSH-N012A,B,C,D) 7.
HPCI Steam Line Ambient Temperature - High NA l
(E51-TS-N603C,D) 8.
HPCI Steam Line Area NA l
(E51-dTS-N604C,D) 9.
Emergency Area Cooler Temperature - High NA l
(E41-TS-602A,B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - High
<13(*) #
l (E51-dPIS-N017 and
~
E51-dPIS-N018) 2.
RCIC Steam Line High Flow Time Delay Relay NA (E51-TDR-K32; E51-TDR-K12)
]
3.
RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D) l r
BRUNSWICK - UNIT 2 3/4 3-24 Amendment No.
95
)
.. ~ -.. _. -.. _
... ~
(BSEP-2-18) t TABLE 3.3.2-3 (Continued) f ISOLATION'SYSTE'1 IESTRL71ENTATION RESPONSE TIME
(
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
4.
RCIC Steam Line' Tunnel Temp - High NA (E51-TS-3319; l
E51-TS-3320; i
E51-TS-3321;
~
E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) l l
S.
Bus Power Monitor l
NA j
(E51-K42 and E51-K43) l 6.
i RCIC Turbine Exhaust Diaphram I
Pressure - High l
NA (E51-PS-N012A,B,C,D) i i
j 7.
1 RCIC Steam Line Ambient Temperature - High NA l
(E51-TS-N603A,B) 1 j
8.
RCIC Steam Line Area a Temp - High l
NA l
(E51-dTS-N604A,B) t 9.
Emergency Area Cooler Temperature - High NA l
(E51-TS-N602A,B) 10.
RCIC Equipment Room A-Temp - High l
NA (E51-d,TS-N601A, B) 5.
SHUTDOWN COOLING SYSTEM ISOLATION L
Reactor Vessel Water Level - Low, Level 1 a.
]
(B21-LT-N017A-1,B-1,C-1,D-1)
NA (B21-LTM-N017A-1,B-1,C-1,D-1) i b.
Reactor Steam Dome Pressure - High NA (B32-PS-N018A,B) 4 I
4 i
i j
4 i
i BRUNSWICK - UNIT 2 3/4 3-24A Amendment No.
95
m..
(BSEP-2-18)
I l
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTDi INSTRUMENTATION RESPONSE TIME j
I NOTES (a)
The isolation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Isolation system instrumentation response time specified includes the delay for j
diesel generator starting assumed in the accident analysis.
(b)
Radiation monitors are exempt from response time testing. Response time
,l shall be measured from detector output or the input of the first electronic component in the channel.
Isolation actuation instrumentation ~ response time only.
1 Isolation system instrumentation response time specified for the. Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and Table 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
Includes time delay added by the time delay relay I
(E41-TDR-K33 and E41-TDR-K43).
?
Includes time delay added by the time delay relay
~
I (E51-TDR-K32 and E51-TDR-K12).
t 1
4 d
I t
e i
t i
BRUNS'JICK - UNIT 2 3/4 3-24B Amendment No. 95 i
. _ _ _ _. _.... = _ _ _ _ _ _
(BSEP-2-18) as g
TABLE 4.3.2-1 (Continued) di g
ISOLATION ACTUATION INSTRG1ENTATION SURVEILLANCE REQUIREMENTS 1
N t
CilANNEL OPERATIONAL i
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH h
TRIP FUNCTION AND INSTRIMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED H
e4 4.
CORE STANDBY C001.ING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow - High D
M Q
1, 2, 3 (E41-dPIS-NOO4; E41-dPIS-N005) 2.
IIPCI Steam Line liigh Flow Time Delay Relay NA R
R 1, 2, 3 (E41-TDR-K33; i
[
E41-TDR-K43) y 3.
IIPCI Steam Supply Pressure -
l g
Low NA M
,.R 1, 2, 3 (E41-PSL-N001A,B,C,D) 4.
IIPCI Steam Line Tunnel Temperature - liigh NA H
Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) l li l
5.
Bus Power Monitor NA R
NA 1, 2, 3 g.
(E41-K55 and E41-K56) g 6.
IIPCI Turbine Exhaust l
Diaphragm Pressure - liigh NA H
Q 1, 2, 3 g
P (E41 -PSil-N012A, B, C, D) uf
(BSEP-2-18)
Ng TABLE 4.3.2-1 (Continued)
Eg ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 7:
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH y
TRIP FUNCTION AND INSTRil!!ENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED to 7.
IIPCI Steam Line Ambient l
'remp - liigh NA M
R 1, 2, 3 (E51-TS-N603C,D) 8.
IIPCI Steam Line Area l
A Temp - liigh NA M
R 1, 2, 3 (E51-dTS-N604C,D) 9.
Emergency Area Cooler Temp - Iligli NA M
Q 1, 2, 3 (E41-TS-N602A,B) l R
b.
Reactor Core Isolation Cooling System Isolation
/,
1.
RCIC Steam Line Flow - liigh NA M
- Q 1, 2, 3 (E51-dPIS-N017 and E51-dPIS-NOIB) 2.
RCIC Steam Line High Flow Time Delay Relay NA R
R 1, 2, 3 (E51-TDR-K32; E51-TDR-K12) 3.
RCIC Steam Supply l
Pressure - Low NA M
Q 1, 2, 3 (E51-PS-No19A,B,C,D)
J l
4.
RCIC Steam Line Tunnel E,
liigli Temperature NA M
R 1, 2, 3 4
(E51-TS-3319; l
5 E51-TS-3320; z
E51-TS-3321;
. P ESI-TS-3322; E51-TS-3323; u?
E51-TS-3355; E51-TS-3487)
= - _ _ _.
(BSEP-2-18)
_ TABLE 4.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
[G
$li CilANNEL OPERATIONAL CIIANNEL FUNCTIONAI.
CHANNEL CONDITIONS IN WHICH
[j TRIP FIINCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED e
g 5.
Bus Power Honitor NA R
NA 1, 2, 3 l
(E51-K42 and E51-K43) w H
w 6.
RCIC Turbine Exhaust l
Diaphragm Pressure - High NA M
R 1, 2, 3 (E51-PS-Nol2A,B,C,D) 7.
RCIC Steam Line Ambient l
Temp - Iligh NA M
R 1, 2, 3 (E51-TS-N603A,B) 8.
RCIC Steam Line Area l
A Temp - Iligh NA M
R 1, 2, 3 (E51-dTS-N604A,B) v.
I w
9.
RCIC Equipment Room Ambient
/,
l Temp - liigh NA H
(E51-TS-N602A,B)
Q 1, 2, 3 10.
RCIC Equipment Room A Temp - Iligh NA H
Q 1, 2, 3 (C51-dTS-N601A,B) 5.
SilllTDOWN C001.ING SYSTEM IS01.ATION Reactor Vessel Water Level -
a.
Low, I.e vel I (li21 -LT-N017A-1, B-1, C-1, D-1 )
NA(a)
NA R(b) 1 2, 3
( li21 -1.Til-N017A-1, B-1, C-1, D-1 )
D H
H 1, 2, 3 g
b.
Reactor Steam Dome Pressure -
Iligh NA S/U(c),H R
o E.
(li32-PS-N018A,B)
~
1, 2, 3 E
- When handling irradiated fuel in the secondary containment.
i
- When reactor steam pressure > 500 psig.
2:
F (a) The transmitter channel check is satisfied by the trip unit channel check.
'1 A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
(c) If not performed within the previous 31 days.