ML20067E102
| ML20067E102 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/20/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20067E104 | List: |
| References | |
| DPR-62-A-078, DPR-71-A-053 NUDOCS 8301030314 | |
| Download: ML20067E102 (95) | |
Text
.
[
UNITED STATES 3*
t NUCLEAR REGULATORY' COMMISSION 3
j I*
WASHINGTON, D. C. 20585
\\*..../
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company dated November 12, 1982, complies with the standards and require-ments 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 Commission'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 Spec-ifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is L'
hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 53,'are hereby incorporated in the licenpe. The licensee shall operate the facility in accordance with the Technical Specifications.
8301030314 821220 PDR ADOCK 05000324 P
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COPEISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 20, 1982
ATTACHMENT TO LICENSE AMENDMENT NO. 53 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:
Remove Insert 2-4 2-4 2-6 2-6 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-6 3/4 3-6 3/4 3-6A 3/4 3-6a 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-8A 3/4 3-8a 3/4 3-11 3/4 3-11 3/4 3-11A 3/4 3-12 3/4 3-12 3/4 3/13 3/4 313 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-15 3/4 3-15 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 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-22A 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24 3/4 3-24a 3/4 3-25 3/4 3-25 3/4 3-25A 3/4 3-26 3/4 3-26 3/4 3-26A 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 l
3/4 3-29a 3/4 3-31 3/4 3-31 l
3/4 3-31A l
3/4 3-32 3/4 3-32 3/4 3-32A 3/4 3-32a l
l I
4..
Remove Insert 3/4 3-34 3/4 3-34 3/4 3-34A 3/4 3-35 3/4 3-35 d
3/4 3-35A 3/4 3-35a 3/4 3-37 3/4 3-37 3/4 3-37A 3/4 3-38 3/4 3-38 3/4 3-38A 3/4 3-38a 3/4 3-38B 3/4 3-38b 3/4 3-51 3/4 3-51 3/4 3-52 3/4 3-52 3/4 3-63 3/4 3-63 3/4 3-64 3/4 3-64 l
3/4 3-65 3/4 3-65
=
6 j
TABLE 2.2.1-1 M
REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS nn t
M ALLOWABLE 8
FUNCTIONAL UNIT AND INSTRUMENT NUMBER TRIP SETPOINT VALUES 5
l h
1.
Intermediate Range Monitor, Neutron Flux - liighfI)
< 120 divisions of full scale
< 120 divisions (C51-IRM-K601A,B,C,D,E,F,G,ll) of full scale l-2.
Average Power Range Monitor (C S I-APRM-Cil. A, B,C, D, E, F) a.
Neutron Flux - liigh, 15%(2)
< 15'% of RATED TilERMAL POWER
< 15% of RATED l
1 THERMAI. POWER l
b.
Flow-Biased Neutron Flux - liigh(3)(4)
__< (0.66 W + 54%)
__< (0.66 W + 54%)
l y
c.
Fixed Neutron Flux - liigh(4)
< 120% of RATED TilERMAL POWER
< 120% of RATED TilERNAL POWER j
3.
Reactor Vessel Steam Dome Pressure - Iligh
< 1045 psig
< 1045 psig i
( B 21-PTM-N02 3 A-1, B-1, C-1, D-1) 4.
Reactor Vessel IJacer Level - Low, Level 1
> +162.5 inches *
> +162.5 inches *
(ll21-1.TM-N017 A-1, B-1, C-1, D-1)
~~
~~
l 5.
Main Steam Line Isolation Valve - Closure (5)
< 10% closed
< 10% closed (B21-F022A,B,C,D; B 21-F028A, B,C, D) 6.
Main Steam Line Radiation - liigh
~~< 3 x full power background
< 3.5 x full power k
( D 12-R'l-K603A,B,C, D)
~~
background a
Q 7.
Drywell Pressure - liigh
< 2 psig
< 2 psig g
(C71-PS-N002A,B,C,D) z
.o 8.
Scram Discharge Volume llater Level - liigh
-< 109 gallons
< 109 gallons (C l 2-LSil-N013A, B, C, D) ym
O TABLE 2.2.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS TABLE NOTATION
- Vessel water levels refer to REFERENCE LEVEL ZERO.
l (1) The Intermediate Range Monitor scram functions are automatically bypassed when the reactor mode switch is placed in the Run position and the Average Power Range Monitors are on scale.
(2) This Average Power Range Monitor scram function is a fixed point and is increased when the reactor mode switch is placed in the Run position.
(3) The Average Power Range Monitor scram function is varied, Figure 2.2.1-1, as a function of recirculation loop flow (W).
The trip setting of this function must be maintained in accordance with Specification 3.2.2.
(4) The APRM flow-biased high neutron flux signal is fed through a time constant circuit of approximately 6 seconds. The APRM fixed high neutron flux signal does not incorporate the time constant, but responds directly to instantaneous neutron flux.
(5) The Main Steam Line Isolation Valve-Closure scram function is automatically bypassed when the reactor mode switch is in other than the Run position.
(6) These scram functions are bypassed when THERMAL PCRER is less than 30% of RATED THERMAL POWER.
i
(
l BRUNSWICK - UNIT 1 2-6 Amendment No.
53
~
h TABLE 3.3.1-1
=
E!
REACTOR PROTECTION SYSTEM INSTRUMENTATION N*
APPLICABLE MINIHUN NUMBER OPERATIONAL OPERABLE CilANNELS E
FUNCTIONAL UNIT AND INSTRUMEKr NUMBER CONDITIONS PER TRIP SYSTE4 (a)
ACTION 4
1.
Intermediate Range !!onitors:
j (C 51-IRM-K601 A, B,C, D, E,F.C.II) a.
Neutron Flux - liigh 2, 5(b) 3 g
l 1
3, 4 2
2 b.
Inoperative 2, 5 3
1 3, 4 2
2 2.
Average Power Range Monitor (C S I-A PRM-Cll. A, B,C, D, E, F)
{h a.
Neutron Flux - Iligh, 15%
2, 5(b) 2 3
l b.
Flow Biased Neutron Flux - High 1
2 4
y, l
c.
Fixed Neutron Flux - liigh, 120%
1 2
4 j
d.
Inoperative 1, 2, 5 2
5 4
e.
Downscale 1
2 4
i i
f.
LPRM 1, 2, 5 (c)
NA 3.
Reactor Vessel Steam Dome Pressure - liigh 1, 2(d) 2 6
l (B21-PT-N023A,B,C,D)
]
(B21-PTM-N023A-1,B-1,C-1,D-1) l 4.
1, 2 2
6 Low, level 1
( B 21-LT-N017A-1, B-1, C-1, D-1)
(B21-LTri-N017A-1,B-1,C-1,D-1) o E
5.
Itain Steam Isolation Valve - Closure 1
4 4
=
(B21-F022A,B,C,D and j
B21-F028A,B,C,D) f 6.
Main Steam Line Radiation - liigh 1, 2(d) 2 7
l (D12-RM-K603A,B C.D) ou i
em
o g;
TABLE 3.3.1-1 (Continued)
E!y REACTOR PROTECTION SYSTEM INSTRUMENTATION l
5 7:
8 APPLICABLE MINIMUM NUMBER l
5 OPERATIONAL OPERABLE CllANNELS l
FUNCTIONAL UNIT AND INSTRUMENT NUMBER CONDITIONS PER TRIP SYSTEH (a)
ACTION
- 7. Drywell Pressure - liigh 1, 2(*)
2 6
(C71-PS-N002A,B,C,D)
- 8. Scram Discharge Volume Water Level -
3 3.
liigh 1, 2, 5(f) 2 5
(C l l-LSil-N013A, B,C,D)
- 9. Turbine Stop Valve - Closure 1(g) 4 8
d (EllC-SVOS-IX,2X,3X,4X) i t'
i s-
Control Oil Pressure - Low 1(8) 2 8
d d2 (EllC-PS L-17 56,17 57,1758,1759)
- 11. Reactor Itode Switch in Shutdown Pos! tion I,2,3,4,5 1
9 (C71A-51)
- 12. Manual Scram I, 2, 3, 4, 5 1
10 (C71-A-S 3A, B)
I
-l k
,l E
g.
8 1
.!!f I
C
l TABLE 3.3.1-2
~
S i
y REACTOR PROTECTION SYSTEM RESPONSE TIMES R
M RESPONSE TIME 8
FUNCTIONAL UNIT AND INSTRUMEfff NUMBER (Seconds)
C3h 1.
Intermediate Range !!onitors H
(C 51-IRM-K601 A, B,C, D, E, F,G,II) :
e a.
Neut ron Flux - liigh*
NA b.
Inoperative NA 2.
Average Power Range Monitor *
(C 51-A PR M-Cll. A, B,C, D, E, F) :
l a.
Neutron Flux - liigh, 15%
< 0.09 b.
Flow-Blased Neutron Flux - High NA R
c.
Neutron Flux - liigh, 120%
< 0.09 d.
Inoperative NA a
i*
e.
Downscale NA f.
LPRM NA a
3.
Reactor Vessel Steam Dome Pressure - liigh
-< 0.55
( B 21-PT-N023A, B,C, D)
(B21-PTM-N023A-1,B-1,C-1 D-1) 4.
Reactor Vessel Watar level - Low, Level 1
< 1.05 (B21-LT-N017A-1.B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) i Ei i
3 5.
Main Steam Line Isolation. Valve-Closure
< 0.06 l
, fj.- / - -
- 7, p
[j-(B21-F022A,B,C,D and
- cf B21-F028A,B,C,D) f
[. 1 8, J. ' ;r r9
-[k f; f A
'g:
6.
Main Steam Line Radiation - liigh i
NA j
(D12-RM-K603A,B,C,D)
Q
[ ((pA q
/ -
/
li m
g
~
~
\\
~
, !N '
+'+
. w w r
,L o
/
~)
1 4
[#
/t
, g.,
4
-w
.=-
i
^
j
~
i g
TABLE 3.3.122 (Continued)
O9 REACTOR PROTECTION SYSTE$ RESPONSE TIMES k
j n
./
P:
~
j RF.SPONSE TI E 8
FUNCTIONAL UNIT AND INSTRUFfENT NUMBER
~ (Seconds >
c) y
','
- f 7.
Drywell Pres sure - liigh NA (C71-PS-N002A,B,C,D)
'.~ 3 r
g
'g, 8.
Scrain Discharge Volume Water 'lavel - High NA (C 11-LSil-No 13A, B,C, D)
.[" }l Y.,
9.
Turbine Stop Valve - Closure
( EllC-S VOS-I X,2 X,3 X,4 X)
/
< 0.06
?*
,.e
< 0.08
.,,,.4-s lj Control Oil Pressure - low
~
(EllC-PS L-1756,1757,1758,1759) u t
y
- 11. Reactor Mode Switch in Shutdown Position NA p
(C71A-SI)
- 12. Manual Scram NA (C71 A-S 3A,B)
?
l!
- Neutron detectors are exempt f rom response time testing. Response time shall be measured from j
detector output or from the input of the first electronic component in the channel.
t
.e 8
R Bn
'4 l.
s f
'l U
F m
- l I
y TABLE 4.3.1-1 Gy REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMEl(IS M
A' GIANNEL OPERATIONAL FUNCTIONAL UNIT OIANNEL FUNCTIONAL QiANNEL Q)NDITIONS IN WHIQi 6
AND INSTRUMENT NUMBER GlECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED M
1.
Intermediate Range !!onitors:
( C51-IRM-K6 01 A, B, C,D, E, F.C,II)
S/U(b)(c) a.
Neutron Flux - liigh D
.R 2
D W
R 3,4,5 b.
Inoperative NA W
NA 2,3,4,5 2.
Average Power Range Monitor:
( CS I-APRM-Qi. A, B, C,D, E, F) l S/U(b), g(d)
Q 2
l a.
Neutron Flux - liigh 15%
S i
y S
W Q
5 b.
Flow-Biased Neutron Flux - High S
S/U(b),y g(e)(f),q g
S/U( ), W W(*), Q c.
Fixed Neutron Flux - liigh, 120%
S 1
d.
Inoperative NA W
NA 1, 2, 5 l
e.
Downscale NA W
NA 1
f.
LPRM D
NA (g) 1, 2, 5
!t 3.
Reactor Vessel Steam Dome
]
Pressure - High Si
( B21-PT-N 323A, B, C,D)
NA NA R
1, 2 l
t t
( B21-PTM-4023A-1,B-1, C-1,D-1)
D H
H 1, 2 l
4.
Reactor Ves sel Water Level -
l Low, Levei 1
_l 8'
( B21-LT-N017A-1, B-1,0-1, D-1 )
NA NA R
1, 2 l
f'
( B 21-LTM-N017 A-1, B-1, C-1, D-1)
D H
M 1, 2
=
g
.a
to TABLE 4.3.1-1 (Continued) 5 I$
REACTOR PROTECTION SYSTEM INSTRUMjNTATION SURVEILLANCE REQUIREMENTS li i
0 CHANNEL OPERATIONAL 3
FUNCTIONAL UNIT CllANNEL FUNCTIONAL CHANNEL CONDITIOl6 IN WHICH AND INSTRUMENT NUMBER CllECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED g
- 5. Main Steam Line Isolation Valve -
NA M
R(h) 3 Closure (B21-F022A,B,C,D and B21-F028A,B,C,D)
- 6. Maict Steam Line Radiation - High S
M(i)*
U)
R 1, 2
( D12-RM-K603 A, B, C, D)
- 7. Drywell Pressure - Iligh NA M
Q 1, 2
( C71-PS-N002 A, B, C, D)
- 8. Scram Discharge Volume Water Level - liigh NA Q
R 1, 2, 5 u
t (Cl 2-LSil-N013 A, B, C, D) o3
- 9. Turbine Stop Valve - Closure NA M
R( }
1, j
( EllC-S VOS-lX,2X, 3 X,4 X)
.i
- 10. Turbine Control Valve Fast Closure, Control Oil Pressure -
Iow NA M
R 1
(EllC-PSL-1756,1757,1758,1759)
- 11. Reactor Mode Switch in Shutdown NA R
NA 1,2,3,4,5 Position
( C71 A-S I)
!I'
- 12. Manual Scram NA Q
NA 1,2,3,4,5 (C71 A-S 3 A,B) l O
i
=
~
TABLE 4.3.1-1 (Continued) m N
.9 p;
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS N
O (a) Neut ron detectors may be excluded f rom CilANNEL CALIBRATION.
%h (b) Uithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
F' (c) The IRM channels shall be compared to the APmt channels and the SRM instruments for overlap during each startup, if not performed within the previous 7 days.
(d) When cl'anging f rom CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering CONDITION 2.
(e) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER.
(f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a u
30 calibrated flow signal.
(g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.
o f
(h) This calibration shall consist of a physical inspection and actuation of these position switches.
J l
(i) Instrument alignment using a standard current source.
l (j) Calibration using a standard radiation source.
(k) The transinitter channel check is satisited by the trip unit channel check. A separate transmitter check is not required.
(1) Transmitters are exempted frem the monthly channel calibration.
i 0
4 g.
a, n
{
m' JP 4
a
(.
m F2 TABLE 3.3.2-1 m
ISOLATION ACTUATION INSTRUMENTATION R
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANI;ELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION i
l H
1.
PRIMARY CONTAINMENT ISOLATION t
a.
i 1.
Low, Level 1 2,6,7,8 2
1,2,3 20 l
(B21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) 2.
Low, Level 2 1,
3 2
1,2,3 20 i
(B21-LT-N024A-1,B-1, and B21-LT-N025A-1,B-1) 22 (B21-LTM-N024A-1, B-1 and B21-LTM-N025A-1,B-1)
Y
[:
b.
Drywell Pressure - liigh 2,6,7 2
1,2,3 20 (C71-PS-N002A,B,C,D) c.
Radiation - liigh (d) 1 2
1, 2, 3 21 (D 12-RM-K603 A, B,C, D) 2.
Pressure - Low 1
2 1
22 (B21-PT-N015A,B,C,D)
(B21-PTM-N015A-1,B-1,C-1,D-1) i g
3.
Flow - lugh 1
2/line 1
22 g
(B21-PDT-N006A,B,C,D; j
g-B21-PDT-N007A,B,C,D;
)
g B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C,D) n o
j (B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1 D-1; PS B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1)
G TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSfRUMENTATION r;
8 VALVE GROUPS MINIMUM NUMBER APPLICABLE G
OPERATED BY OPERABLE CilANNELS OPERATIONAL
]
TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION d.
! bin Steam Line Tunnel Temperature - liigh 1
2(*)
1, 2, 3 21 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.
Condenser Vacuum - Low 1
2 1, 2(f) 21
( B21-PS-N056A, B,C, D)
RJ f.
Turbine Building Area Temperature - Iligh 1
4(e) 1, 2, 3 21 ja (321-TS-3225A,B,C,D;
[
B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-IS-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 a.
Reactor Building Exhaust Radiation - liigh 6
1 1, 2, 3, 5, and* 23 6
(D12-RM-N010A,B) n g-b.
Drywell Pressure - liigh 2, 6, 7 2
1,2,3 23 g
(C71-PS-N002A,B,C,D) n
.O c
m TABLE 3.3.2-1 (Continued) m h
ISOLATION ACTUATION INSTRUMENTATION s
Q VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CilANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER S IGNAL(a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION N
c.
H Low, Level 2 1,
3 2
1,2,3 23 (B21-LT-N924A-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 - liigh 3
1 1, 2, 3 24 k'
(G31-d FS-N603-1A, IB) 4 b.
Area Temperature - liigh 3
2 1,2,3 24
,8 (G31-TS-N600A,B,C,D,E,F) c.
Area Ventilation A Temp. - liigh 3
2 1, 2, 3 24 (G31-TS-N602A,B,C,D,E,F) d.
SLCS Initiation 3 (g)
NA 1, 2, 3 24 (C41 A-S I) e.
Reactor Vessel llater Level -
Low, Level 2 1, 3 2
1, 2, 3 24 (B21-LT-N024 A-1,B-1 and B21-LT-N025 A-1,B-1) j g
(B21-LTM-N024 A-1,B-1 and
~
g B21-LTM-N025 A-1,B-1) lli 1
i E.
z f
m TABLE 3.3.2-1 (Continued) n ISOLATION ACTUATION INSTRUtiENTATION ti Q
VALVE CROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CIIANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMEWT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION s
H 4.
CORE STANDBY COOLING SYSTEMS ISOLATION e-*
a, liigh Pressure Coolant Injection System Isolation l
1.
IIPCI Steam Line Flow - High 4
2 1, 2, 3 25 (E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Supply Pressure - Low 4
2 1, 2, 3 25 (E41-PS L-N001 A, B, C, D) 3.
IIPCI Steam Line Tunnel Temperature - liigh 4
2 1,2,3 25 t,)
(E41-TS-3314 ;
E41-TS-3315; j'
E41-TS-3316; Z
E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; i
E41-TS-3489) 4.
Bus Power Monitor NA(h) 1/ bus 1, 2, 3 26 (E41-K55 and E41-K56) 5, 11PCI Turbine Exhaust I
Diaphragm Pressure - liigh 4
2 1, 2, 3 25 (E41-PSit-N012A, B,C, D)
\\
g 6.
IIPCI Steam Line Ambient g-Temperature - liigh 4
2 1, 2, 3 25 g
(E51-TS-N603C, D) n 7.
IIPCI Steam Line Area A Temp. -
.f liigh 4
2 1, 2, 3 25 (E51-dTS-N604C,D) m w
8.
Emergency Area Cooler Temperature - liigh 4
2 1, 2, 3 25 (E41-TS-N602A,B)
1 m
TABLE 3.3.2-1 (Continued)
~
ISOLATION ACTUATION INSTRUMENTATION A
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CllANNELS OPERATIONAL E
TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION U
s b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - liigh 5
2 1,2,3 25 (E51-dPIS-N017 and E51-dPIS-N018) 2.
RCIC Steam Supply Pressure - Low 5
2 1,2,3 25 (E51-PS-N019A,B,C,D)
L 3.
RCIC Steam Line Tunnel Temperature
- liigh 5
2 1, 2, 3 25 (E51-TS-3319; E51-TS-3320; u,
30 E51-TS-3321; E51-TS-3322; u,
1 E51-TS-3323; E
E51-TS-3355; E51-TS-3487) 4.
Bus Power Monitor NA (h) 1/ bus 1, 2, 3 26 (E51-K42 and E51-K43) 5.
RCIC Turbine Exhaust Diaphragm Pressure - Iligh 5
2 1,2,3 25 (E51-PS-N012A,B,C,D) 6.
RCIC Steam Line Ambient Temp -
g liigh 5
2 1,2,3 25 (E51-TS-N603A,B) o h
7.
RCIC Steam Line Area A Temp - liigh 5
2 1, 2, 3 25 (E51-dTS-N604A,B) n a
8.
RCIC Equipment Room Ambient Temp - liigh 5
2 1, 2, 3 25 (E51-TS-N602A,B) u, 9.
RCIC Equipment Room A Temp - liigh 5
2 1, 2, 3 25 l
(E51-dTS-N601A,B) 1
TABLE 3.3.2-1 (Continue Q
~
N ISOLATION ACTUATION INSTRUMENTATION a
VALVE GROUPS MINIMUM nut!BER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL h
TRIP FUNCTION AND INSTRUMENT NUMBER S IGNA L(a )
PER TRIP SYSTEM (b)(c)
CONDITION ACTION H
H 5.
SHUTDOWN COOLING SYSTEM ISOLATION a.
Reactor Vessel Water lavel -
Low, Level 1 2, 6, 7, 8 2
1, 2, 3
27 l
(H21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) b.
Reactor Steam Dome Pressure-7, 8 1
1,2,3 27 High (B32-PS-N018A,B)
M>
Y C;
8 8n O
t TABLE 3.3.2-2 5
g ISOLATION ACTUATION INSTRUt!ENTATION SETPOINTS 9
i ALLOWABLE TRIP FUNCTION AND INSTRUllENT NUMBER TRIP SETPOINT VALUE g
a 1.
PRIMARY CONTAINMENT ISOLATION s
a.
1.
Low, Level 1
> + 162.5 inches *
> + 162.5 inches
- l
( B21-LTri-N017 A-1, B-1, C-1, D-1) 2.
Low, Level 2
> + 112 inches *
> + 112 inches
- l (B21-LTM-N024A-1,B-1 and
~~
B21-LTM-N025A-1,B-1) b.
Drywell Pressure - liigh g,
(C71-PS-N002A,B,C,D)
~~< 2 psig
--< 2 psig c.
l.
Radiation - liigh l
C (D12-RM-K603A,B,C,D)
--< 3 x full power background
< 3.5 x full power b'ackground 2.
Pressure - Low
> 825 psig
-- 825 psig
( B 21-PTri-N015 A-1, B-1, C-1, D-1)
~~
3.
Flow - Iligh
< 140% of rated flow
< 140% of rated flow (B21-PDT!!-N006A-1,B-1,C-1,D-1;
~~
~~
B21-PDTM-N007A-1,B-1,C-1,D-1; B21-PDTri-N008 A-1, B-1, C-1, D-1 ;
B21-PDTM-N009A-1,B-1,C-1,D-1)
N
);
8 4
8n h
li
- i i
1
m TABLE 3.3.2-2 (Continued) 8 M
LSOL ATION ACTUATION INSTRUMENTATION.SETPOINTS N
Q ALLOWABLE TRIP FUNCTION AND INSTRUMEE NUMBER TRIP SETPOINT VALUE h
d.
Main Steam Line Tunnel H
Temperature - liigh
< 200*F
< 200*F H
( B 21-TS -N0lO A, B, C, D; B21-TS-N0llA,B,C,D; B21-TS N012A,B,C,D; B21-TS-N013A,B,C,D) e.
Condenser Vacuum - Low
__ 7 inchas Hg vacuum
};7 inches Hg vacuum
( B 21-PS -N056 A, B, C, D) f.
Turbine Building Area Temp - liigh
< 200*F
< 200*F
( B 21-TS-3225 A, B, C, D; t*
B21-TS-3226A,B,C,D; B 21-TS-3227 A, B, C, D; j'
B21-TS-3228 A, B, C,D ;
5; B 21-TS -3229 A, B, C, D; B21-TS-3230 A, B, C,D ;
B 21-TS-3231 A, B,C, D; B21-TS-3232 A, B, C, D) 2.
SECONDARY CONTAINMEE ISOLATION a.
Reactor Building Exhaust Radiation - Iligh
< 11 mr/hr
< 11 ar/hr
( D12-RM-N010A,B) b.
Drywell Pressure - liigh j( 2 psig j[ 2 psig
( C71-PS -N002 A, B,C, D)
,o c.
Low, Level 2
> + 112 inches *
};+ 112 inches
- l (B21-LTM-N024 A-1,B-1 and y
B21-LTM-N025A-1,B-1)
N
- l 0
4
f e
TABLE 3.3.2-2 (Continued) m W
5 Di ISOLATION ACTUATIG.'i INSTRUMENTATION SETPOINTS
?5 h!
ALLOWABLE TRIP FUNCTION AND INSTRUMEKr NUMBER TRIP SETPOINT VALUE c
M 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION H
H a.
A Flow - liigh
< 53 gal / min
~~< 53 gal / min (C 31-d FS-N603-1 A, lB)
~~
b.
Area Temperature - High
~~< 150*F
< 150*F (G31-TS-N600A,B,C,D,E,F)
~~
c.
Area Ventilation Temperature A Temp - High
~~< 50*F
< 50*F (G31-TS-N602A,B,C,D,E,F)
~~
d.
SLCS Initiation NA NA (C41A-SI) e.
u Low, Level 2
> + 112 inches *
> + 112 inches
- l L
(H21-LTM-N024A-1,B-1 and
~~
~~
B 21-LTM-N025A-1, B-1) 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Isolation l
1.
IIPCI Steam Line Flow - High
< 300% of rated flow
< 300% of rated flow I
(E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Supply Pressure - Low
> 100 psig
>_ 100 psig (E41-PS L-N001 A, B,C, D) 3.
IIPCI Steam Line Tunnel Temperature - liigh
< 200*F
< 200*F E.
(E41-TS-3314; E41-TS-3315; S
E41-TS-3316; z
E41-TS-3317; E41-7S-3318; pj E41 -TS-3354 ;
E41-TS-3488; u,
I w
E41-TS-3489) i
\\
a
ta ps TABLE 3.3.2-2 (Continued)
E ISOLATION ACTUATION INSTRUMENTATION SETPOINTS n
P ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE E[j 4.
Bus Power Monitor NA NA (E41-K55 and E41-K56) r.
5.
IIPCI Turbine Exhaust Diaphragm Pressure - liigh
--< 10 psig
-~< 10 psig (E41-PSit-N012A, B,C, D) 6.
IIPCI Steam Line Ambient Temp - !!igh
< 200*F
< 200*F (E51-TS-N603C,D) 7.
IIPCI Steam Line Area A Temp - liigh
< 50*F
< 50*F (E51-dTS-N604C,D)
Ei 8.
Emergency Area Cooler Temp - liigh
< 175*F
< 175*F (E41-TS-N602A,B)
F Sl b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - liigh
< 300% of rated flow
< 300% of rated flow (E51-dPIS-N017 and E51-dPIS-N018) 2.
RCIC Steam Supply Pressure - Low
> 50 psig
> 50 psig (E51-PS-N019A,B,C,D) 3.
RCIC Steam Line Tunnel Temp - liigh
< 175'F
< 175*F (E51-TS-3319; E51-TS-3320; E51-TS-3321;
!i E51-TS-3322; E51-TS-3323; O'
E51-TS-3355; E51-TS-3487) n
=
4.
Bus Power Monitor NA NA P
(E51-K42 and E51-K43) i i
i4
TABLE 3.3.2-2 (Continued) wm ISOLATION ACTUATION INSTRUMENTATION SETPOINTS S
Q ALLOWABLE TRIP FUNCTION AND INSTRUMERP NUMBER TRIP SETPOINT VALUE 5
p; 5.
RCIC Turbine Exhaust Diaphragm H
Pressure - Iligh j{ 10 psig j{10psig
~
(E51-PS-N012A,B,C,D) 6.
RCIC Steam Line Ambient Temp - liigh
< 200*F
< 200*F (E51-TS-N603A,B) 7.
RCIC Steam Line Area A Temp - liigh
< 50*F
< 50*F (E51-dTS-N604A,B) 8.
RCIC Equipment Room Ambient Temp - Iligh
< 175'F
< 175"F (E51-TS-N602A,B) 9.
RCIC Equipment Room A Temp - Iligh
)
(E51-dTS-N601A,B)
~< 50*F
< 50*F w
-~
5.
SilUTDOWN COOLING SYSTEM ISOLATION g
a.
Low, Level 1 (B21-LTM-N017A-1,B-1,C-1,D-1)
~~> + 162.5 inches *
> + 162.5 inches
- l
~~
b.
Reactor Steam Dome Pressure - Iligh
< 140 psig
< 140 psig (B32-PS-N018A,B) 8 a
- Vessel water levels refer to REFERENCE LEVEL ZERO.
c W
dr
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)# l 1.
PRIMARY CONTAINMENT ISOLATION a.
1.
Low, Level 1
<13 l
(B21-LT-NOl7A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) 2.
Low, Level 2
<l.0**
[
(B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
(B21-LIM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) b.
Drywell Pressure - High
<13 (C71-PS-N002A,B, C,D) c.
<l.0**
1.
Radiation - High*
-~
(D12-RM-K603A,B,C,D) 2.
Pressure - Low
<13
( B 21-PT-N015 A, B, C, D)
-~
(B21-PTM-N015A-1,B-1,C-1,D-1) 3.
Flow - High
<0.5*d (B21-PDT-N006 A,B,C,D ;
B21-PDT-N007A,B,C,D; B21-P DT-N008 A, B, C,D ;
B 21-PDT-N009 A, B, C, D)
( B21-P DTM-N006 A-1, B-1, C-1, D-1 ;
B 21-PDTM-N007 A-1,B-1, C-1, D-1 ;
l B21-PDTM-N008 A-1, B-1, C-1,D-1 ;
B21-PDTM-N009A-1,B-1,C-1,D-1) l l
d.
Main Steam Line Tunnel Temperature - High
- <13 (B21-TS-N010A,B, C,D; B21-TS-N0llA,B,C,D; I
B 21-TS-N012 A,B, C, D ;
B21-TS-N013A,B,C,D) e.
Condenser Vacuum - Low
<l3
( B 21-PS -N056 A, B, C, D)
~"
t l
l BRUNSWICK-UNIT 1 3/4 3-22 Amendment No.38 53
TA3LE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)# l f.
Turbine Building Area Temperature - High NA (B 21-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 ISOLAT10N Reactor Building Exhaust Radiation - High*
<13 a.
(D12-RM-N010A,B) b.
Drywell Pressure - High j:13 (C71-PS-N002A,B,C,D) c.
Reactor Vessel Water Level - Low, Level 2
<1.0**
l (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
(B21-LTM-N024A-1,B-1 and B 21-LTM-N025A-1, B-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High
<13 (G31-dFS-N603-1A,1B)
~~
b.
Area Temperature - High j:13 (G31-TS-N600A,B,C,D,E,F)
Area Ventilation Temperature AT - High
<13 c.
(G31-TS-N602A,B,C,D,E,F)
"~
d.
Reactor Vessel Water Level - Low, Level 2
<1.0**
l e.
(B21-LT-NO24 A-1,3-1 and
~~
B21-LT-N025 A-1,B-1)
(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1,B-1)
BRUNSWICK - UNIT 1 3/4 3-23 Amendment No.3g 53
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)# l 4.
CORE STANDBY COOLING SYSTEMS ISOLATION High Pressure Coolant Injection System Isolation a.
l 1.
HPCI Stean Line Flow - Ndgh jJ3 (E41-dPIS -N004 and E41-dPIS-N005) 2.
HPCI Steam Supply Pressure - Low
<13 (E41-PSL-N001A,B,C,D) 3.
HPCI Steam Line Tunnel Temperature - High j)3 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-34897 4
Bus Power Monitor NA (E41-K55 and E41-K56) 5.
HPCI Turbine Exhaust Diaphragm Pressure - High NA (E41-PSH-N012A,B,C, D) 6.
HPCI Steam Line Ambient Temperature - High NA (E51-TS-N603C,D) 7.
HPCI Steam Line Area NA (E51-dTS-N604C,D) 8.
Emergency Area Cooler Temperature - High NA (E41-TS-602A,B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - High NA (E51-dPIS-N017 and E51-dPIS-N018) 2.
RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D) 3.
RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; i
E51-TS-3355; E51-TS-3487) 4 Bus Power Monitor NA (E51-K42 and E51-K43)
BRUNSWICK - UNIT 1 3/4 3-24 Amendment No. 3B 53
-+
TABLE 3.3.2-3 (Continued) i ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
l 5.
RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-PS-N012A,B,C,D) 6.
RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A,B) 7.
RCIC Steam Line Area A Temp - High NA (E51-dTS-N604A,B) 8.
Emergency Area Cooler Temperature - High NA (E51-TS-N602A,B) 9.
RCIC Equipment Room A Temp' - High NA (E51-dTS-N601A,B) 5.
SHUTDOWN COOLING SYSTEM ISOLATION a.
Reactor Vessel Water Level - Low, Level 1 NA l
(B21-LT-N017 A-1,B-1, C-1, D-1)
(B 21-LTM-N017A-1, B-1, C-1, D-1) l b.
Reactor Steam Dome Pressure - High NA (B32-PS-N018A,B)
- Radiation monitors are exempt from response time testing. Response time shall be measured f rom detector output or the input of the first electronic component in the channel.
- Isolation actuation instrumentation response time only.
- 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.
t i
BRUNSWICK - UNIT I 3/4 3-24a Amendment No. 5 3
,n---
ymy
,,-g-4
---p yg-4e ww,,m-w-,
--,.m-
m,m+m-..---
,__---,o--
._-4,n..,eg.,,
TABLE 4. 3. 2-1 a
ISOLATION ACTUATION INSTRUMEffrATION SURVEILLANCE REQUIREMENTS U
N OIANNEL OPERATIONAL M
QIANilEL FUNCTIONAL O!ANNEL CONDITIONS IN Wi!IQI TRIP FUNCTION AND INSTRUMEfff NUMBER QIECK TEST CALIBRATION SURVEILLANCE REQUIRED 9
.y 1.
PRIMARY CONTAINMENT ISOLATION H
a.
1.
Low, Level 1
( B21-LT-N017A-1, B-1, C-1, D-1 )
NA(")
NA R(b) 1, 2, 3
( B 21-LTM-N017A-1, B-1, C-1, D-1)
D H,
M 1, 2, 3 2.
Low, Level 2 l
(B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
NA NA R
1, 2, 3 l
(B21-LTM-NO24A-1,B-1 and U21-LTM-N025A-1,B-1)
D M
M 1, 2, 3 b.
Drywell Pressure - liigh NA M
Q 1, 2, 3 u/,
( C71-P S-N002A, B, C,D) w c.
Radiation - Iligh D
W R
1, 2, 3 (D12-lui-K603A,B C.D) 2.
Pressure - Low
( B21-PT-No1 SA, B, C,D)
NA("}
NA R( )
1 (B21-PTM-N015A-1,B-1,C-1,D-1)
D M
M 1
1.
Flow - liigh
( B21-P DT-N006 A, B, C,D; NA(a)
NA R(b) g B21-PDT-N007A,B,C,D; y
B21-P DT-N008 A, B, C,D ;
P B21-PDT-N009A,B,C,D)
( B21-P DTM-11006 A-1, B-1, C-1, D-1 ;
D M
M 1
D, B21-PDTM-N007A-1,B-1,C-1,D-1; a
321-P DTM-fl008 A-1, B-1, C-1, D-1 ;
.o B21-PDTM-N009A-1, B-1, C-1, D-1)
N t
TABLE 4. 3.2-1 ( Cbntinued) mg d
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMEMES
!i QlANNEL OPERATIONAL i
i OfANNEL FUNCTIONAL QlANNEL CONDITIONS IN WilIQt
,g TRIP FU!!CTION AND INSTRUMENT NUMBER GlECK TEST CALIBRATION SURVEILLANCE REQUIRED M
d d.
Main Steam Line Tunnel Temperature - Iligh NA M
R 1, 2, 3 i
(l$ 21-TS-N010A,II, C, D; B21-T S-N0 l l A,Is, C,D ;
I B 21-T S-N012 A, B, C, D; 1
B21-TS-N013A,B,C D) e.
Condenser Vacuum - Low NA M
R 1, 2#
j (B21-PS-N056A,B,C,D) f.
Turbine Building Area Temp-liigh NA M
R 1, 2, 3
( B21-T S-3225A, B, C, D; wD B21-T S-32 26A, B, C,D; is21-T S-3227 A, B, C, D; u
s'a B21-T S-3228A, B, C,D; B 21-T S-3229 A, B, C, D; l
B21-T S-3230A, B, C,D ;
B 21-T S-3231 A, B, C, D; B21-T S-323 2A, B, C, D) i 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Exhaust Radiation - liigh D
H R
1,2,3,5, and *
( D12-101-N010A, B) 1 l
Si a
I W
i, n
4 te U1 i
l
i I
~
i TABLE 4.3.2-1 (Continued) tox 5y ISOLATION ACTUATION INSTRUMEtifATION SURVEILLANCE REQUIREMEffrS 14 f
CllANNEL OPERATIONAL i
CllANNEL FUNCTIONAL CIIANNEL CONDITIONS IN WilICll g TRIP FUNCTION AND INSTRUMEf(P NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED M
b.
Drywell Pressure - liigh NA M
Q 1, 2, 3
( C71-PS-N00 2A, B, C,D) c.
1 Low, Level 2 (B21-LT-N024 A-1,B-1 and NA(8)
NA R(b) 1, 2,'3 I
B21-LT-NO25 A-1,B-1)
( B21-LTM-N024 A-1,B-1 and D
M M
1,'2, 3
l B21-LTM-N025 A-1,B-1) g 3.
REACCOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - liigh D
M L
1, 2, 3 l
Y (C31-d FS-N603-1 A, l B) io I
b.
Area Temperature - liigh NA M
R 1, 2, 3
( G31 -T S-H600A, B, C, D, E,F) l c.
Area Ventilation A Temp - liigh NA M
R 1, 2, 3
( G31 -T S-N602A, B, C, D, E, F) d.
SLCS Initiation NA R
NA 1, 2, 3 1
)
( C41 A-SI)
I j
e.
Low, Level 2
)
)
( B21-LT-N024 A-1, B-1 and NA NA R
1, 2, 3 B21-LT-N025 A-1,B-1) m
( B21-LTM-N024 A-1, B-1 and D
M M
1, 2, 3 S
B21-LT!!-N025 A-1,B-1) l.
E
- h. '
C 4
l
TABLE 4. 3.2-1 ( Continued)
ISOLATION ACTUATION INSTRUMEffrATION SURVEILLANCE REQUIREMENTS G$
QlANNEL OPERATIONAL OlANNEL FUNCTIONAL OIANNEL CONDITIONS IN WilIQi TRIP FUNCTION AND INSERUMENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED F3A 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a
a.
liigh Press'ure Coolant Injection System Isolation l
IIPCI Steam Line Flow - liigh D
M Q
1, 2, 3 (E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Supply Pressure -
Low NA M
R 1, 2, 3 (E41-PSL-N001A,B,C,D) 3.
IIPCI Steam Line Tunnel u
)
Temperature - liigh NA M
Q 1, 2, 3
( E41-T S-3314 ;
u 6
E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3388; E41-TS-3489) 4.
Bus Power Monitor NA R
NA 1, 2, 3 (E41-K55 and E41-K56) 5.
IIPCI Turbine Exhaust g
Diaphragm Pressure - liigh NA M
Q 1, 2, 3 co
( E41-P Sil-N012 A, B, C, D)
T 6.
IIPCI Steam Line Ambient Temp - liigh NA M
R 1, 2, 3
( E51-TS-N603C, D) u 7.
IIPCI Steam Line Area A Temp - Illyh NA M
R 1, 2, 3
( E51-dTS-N6d4C,D)
l TABLE 4.3.2-1 (Gntinued)
G..
j y
ISOLATION ACTUATION INSTRUMEtTrATION SURVEILLANCE REQUIREMEPTTS A
3 o
i M
QIANNEL OPERATIONAL OlANNEL FUNCTIONAL QlANNEL CONDITIONS IN WilIQI O.
TRIP FUNCPION AND INSTRUMEffr NUMBER OlECK TESr CALIBRATION SURVEILLANCE REQUIRED i
M 8.
Emergency Area Cooler i
r Temp - Iligh NA M
Q 1, 2, 3
( E41-TS-N602A,B)
I j
b.
Reactor Wre Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - liigh NA M
Q 1, 2, 3 (E51-dPIS-N017 and E51-dPIS-N018) 2.
RCIC Steam Supply R
Pressure - Low NA M
Q 1, 2, 3 i
( E51-P S-No 19 A, B, C, D) u eb 3.
RCIC Steam Line Tunnel l
liigh Temperature NA M
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) 4.
Bus Power Monitor NA R
NA 1, 2, 3 (E51-K42 and E51-K43)
P i
d 5.
RCIC Turbine Exhaust l
E.
Diaphragm Pressure - liigh NA M
R 1, 2, 3 M
( E51-P S-N012A, B, C, D) u I
i U
\\
s a
l 4
e
E TABLE 4.3.2-1 (Continued) 0.
U ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIRE!!ENTS 5
CllANNEL OPERATIONAL CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WiiICil h
TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED H
6.
RCIC Steam Line Ambient Temp - Iligh NA M.
R 1, 2, 3 (E51-TS-N603A,B) 7.
RCIC Steam Line Area A Temp - Ingh NA M
R 1, 2, 3 (E51-dTS-N604A,B) 8.
RCIC Equipment Room Ambient Temp - liigh NA Q
1, 2, 3 (E51-TS-N602A,B) u 30 9.
RCIC Equipment Room A y
Temp - liigh NA M
Q 1, 2, 3 g
(E51-dTS-N601A,B) p 5.
SilUTDOWN COOLING SYSTEM ISOLATION a.
Low, level 1 NA R(b) 1, 2, 3
( B21 -LT-N017 A-1, B-1, C-1, D-1 )
NA( )
(B21-LTM-N017A-1,B-1,C-1,D-1)
D M
M 1, 2, 3 b.
Reactor Steam Done Pre-w re -
I Iligh NA S/U(c),M R
1, 2, 3 g
(B32-PS-N018A,B) 3 11-g
- When handling irradiated fuel in the secondary containment.
(
- Uhen reactor steam pressure > 500 psig.
l y
(a) The transmitter channel checE is satisfied by the trip unit channel check.
l A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
l u,
(c) If not performed within the previous 31 days.
m.-.._...
to TABLE 3. 3. 3-1
~
l i2
.:M EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMEtTTATION N
Q MINIMUM NUMBER APPLICABLE I
i OPERABLE CllANNELS OPERATIONAL i
g TRIP FUNCrION AND INSTRUMEfft NUMiiER PER TRIP SYSTEM CONDITIONS ACTION A
]
1.
CORE SPRAY SYSTEM a.
Reactor vessel Water level - Iow, Level 3 2
1,2,3,4,5 30 l
( B21-LT-NO31 A, B, C, D)
( B21-LT S-NO31 A-4, B-4, C-4, D-4) b.
Reactor Steam Ibme Pressure - low (Injection Permissive) 2 1,2,3,4,5 31
( B 21-PT-N021 A, B, C, D)
( 1121-PT S-NO21 A-2, B-2, C-2, D-2) c.
Drywell Pressure - liigh 2
1, 2, 3 30
( E l 1-PS-N011 A, B, C, D) u l
D d.
Time Iblay Relay 1
1,2,3,4,5 31 (E21-K16A,B) l u
i e.
Bus Power Monitor #
1/ bus 1, 2, 3, 4,_5 32 i
(E21-KIA,B) 2.
LPCI MODE OF RilR SYSTEM a.
Dryuell Pressure - liigh 2
1, 2, 3 30 4
( E l l-PS-N0l l A, B, C, D) b.
Reactor Vessel Water Invel - Inw, Invel 3 2
1, 2, 3, 4*, 5*
30 l
( li21-LT-NO 31 A, B, C, D) 1
( 1121-LT S-NO31 A-4, B-4, C-4, D-4)
[7 Reactor Vessel Shroud Invel (Drywell Spray Permissive) 1 1, 2, 3, 4*, 5*
31 c.
(1121-LT-NO36 and B21-LT-NO37)
(1521-LTM-NO36-1 and B21-LTM-NO37-1) t es N
d.
Reactor Steam lhme Pressure - law (Injection Permissive) i n
( li21-PT-N021 A,il, C, D)
{
( ll21-PTM-NO21 A-1, B-1, C-1, D-1 )
( 1121-PT S-NO21 A-2,11-2, C-2, D-2) m w
1.
RilR Pianp Start and LPCI Injection Valve Actuation 2
1, 2, 3, 4*, 5*
31 2.
Recirculation loop Pump DI.:scharge Valve Actuation 2
1, 2, 3, 4*, 5*
31 i
I
usx TABLE 3.3.3-1 (Continued)
G TAg EMERCENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION
$n MINIMUM NUMBER APPLICABLE E
OPERABLE CI(ANNEl.5 OPERATIONAL TRIP FlJNCTION AND INSTRUMENT NUl!BER PER TRIP SYSTEM CONDITIONS ACTION n
r e.
RilR Pump Start - Time Delay Relay 1
1, 2, 3, 4*,
5*
31 (STR-lAl,2 and l
STR-181,2)
I f.
Bus Power Monitor #
1/ bus 1, 2, 3, 4*,
5*
32 (Ell-K106A,B) 3.
IIPCI SYSTEM a.
Reactor Vessel Water Level - Low, Level 2 2
1, 2, 3 30 (B21-LT-NO31A,B,C,D)
{
(821-LTS-NO31A-2,B-2,C-2,D-2) u b.
Drywell Pressure - liigh 2
1, 2,'3 30 b
( E l l-PS-N0 l l A, B,C, D) u c.
Condensate Storage Tank Level - Low 2**
1, 2, 3 33 (E41-LS-N002, E41-LS-N003) d.
Suppression Chamber Water Level - Iligh 2**
1, 2, 3 33 (E41-LSII-N015A, B) e.
Bus Power Monitor #
1/ bus 1, 2, 3 32 (E41-K55 and E41-K56) 4.
ADS a.
Drywell Pressure - liigh, coincident with 2
1, 2, 3 30 (E l l-PS-N010A, B,C, D) b.
Reactor Vessel Water level - Low, Lev'el 3 2
1, 2, 3 30 l
R (B21-LT-NO31A,B,C,D)
(B21-LTS-NO31A-3,B-3,C-3,D-3) 0
TABLE 3.3.3-1 (Cantinued) u
~
.$3 24 EMERCENCY CORE Q)0 LING SYSTElf ACTUATION INSTRUMEtTTATION
- A O
MINIMUM NUMBER APPLICABLE OPERABLE GIANNELS OPERATIONAL g
TRIP FUNCTION AND INSTRUMEffr PRIMBER PER TRIP SYSTEM CONDITIONS ACTION 4[
c.
Reactor Vessel Water level - low, level 1 1
1, 2, 3 30 l
( B21-LT-N042A, B) j
( B 21-LTM-N04 2A-1, B-1) d.
ADS Timer 1
1, 2, 3 31
( B21-TDPU-KSA, B)
Core Spray Pump Discharge Pressure - liigh (Permissive) 2 1,2,3 31 e.
(E21-PS-t1008A,B and E21-PS-N009A,B) f.
RIIR (LPCI MODE) Pump Discharge Pressure - liigh (Permissive) 2/ pump 1, 2, 3 31
( El 1-PS-N016A, B, C, D and El1-PS-N020A,B,C,D) u g.
Bus Power Monitor #
1/ bus 1, 2, 3 32 Y
(B21-KlA,B)
O o
APPLICABLE TOTAL NO.
QlANNELS MINIMUM QlANNELS OPERATIONAL FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE CONDITIONS ACTION S.
IDSS OF POWER a.
4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4##,5##
34 Undervoltage (loss cf Voltage)
P-b.
4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4##,5##
35 Undervoltage ( Degraded g
Voltage)
$n g
Not applicable when two core spray system subsystems are ' OPERABLE per Specification 3.5.3.1.
- Provides signal to llPCI pump suction valves only.
g
- Alarm only.
3 ## Required when ESF equipment is required to be OPERABLE.
3 l
m n
TABLE 3.3.3-2 I
E!
h E!!ERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS l
R ALLOWABLE TRIP FUNCTION AND INSTRUt1ENT NUMBER TRIP SETPOINT VALUE
- ]
U l.
CORE SPRAY SYSTEM e
a.
Reactor Vessel Water level - Low, Level 3
~~> + 2.5 inches *
> + 2.5 inches
- l (B21-LTS-NO31A-4,B-4,C-4,D-4)
~~
b.
Reactor Steam Dome Pressure - Low 410 j,- 15 psig 410 j_- 15 psig (B21-PTS-N021A-2,B-2,C-2,D-2) 1 c.
Drywell Pressure - liigh
< 2 psig
< 2 psig i
(Ell-PS-N0llA,B,C,D) d.
Time De lay-Re lay 14 < t <- 16 secs 14 < t < 16 secs (E21-K 16A, B)
~ ~
l N
e.
Bus Power Monitor NA NA yi (E21-KIA,B) u 2.
LPCI HODE OF RilR SYSTEM l
a.
Drywell Pressure - Iligh
< 2 psig
< 2 psig (Ell-PS-N0llA,B,C,D) b.
Reactor vessel Water level - Low, Level 3
> + 2.5 inches *
> + 2.5 inches
- l (B21-LTS-NO31A-4,B-4,C-4,D-4)
-~
~~
c.
React or Vessel Shroud Level
> - 53 inches *
> - 53 inches
- j (B21-LTri-NO36-1 and l
i B21-LTM-NO37-1) k el.
Reactor Steam Dome Pressure - Low 1
sg 1.
RIIR Pump Start and LCPI Valve m
Actuation j
E 410 + 15 psig 410 + 15 psig (B21-PTS-N021A-2,B-2,C-2,D-2)
~~
~~
u
,o 2.
Recirculation Pump Discharge Valve j
e.
Actuation 310 i 15 psig 310
- 15 psig (B21-PT!!-N021A-1,B-1,C-1,D-1) 4 8
1 I
TABLE 3.3.3-2 (Continued) m G
Li EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS
]fi ALLOWABLE a
TRIP FUNCTION AND INSTRllMENT NUMPER TRIP SETPOINT VALUE 5M e.
RilR Pump Start - Time Delay Relay 9<t< 11 seconds 9<t< 11 seconds (STR-IAl,2 and I
STR-1B1,2) f.
Bus Power Monitor NA NA i
(Ell-K106A,B) 3.
IIPCI SYSTEM a.
Reactor Vessel Water level - Low, Imvel 2
> + 112 inches *
}; + 112 inches
- l
( B 21-LTS-NO 31 A-2, B-2, C-2, D-2 )
b.
Drywell Pressure - liigh
~~< 2 psig
~~< 2 psig (Ell-PS-N0llA,B,C,D) u, c.
Condensate Storage Tank Level - Low
> 23 feet 4 inches
> 23 feet 4 inches l
I',
(E41-LS-N002; E41-LS-N003) v d.
Suppression Chamber Water Icvel - liigh
< -2 feet **
< -2 feet **
l (E41-LSil-N015A, B) j e.
Bus Itwer Monitor NA NA (E41-K55 and E41-K56) 4.
ADS a.
Drywell Press u re-Ili gh
< 2 psig j{ 2 psig
( E l l-PS-N010A,II,C, D) b.
Reactor Vessel Water IcVel - Low, Level 3
}; + 2.5 inches *
}; + 2.5 inches
- l
,6 (li21-LTS-NO 31 A-3, B-3, C-3, D-3) m I
f.
Reactor Vessel Water Level - Low, Level I M
(il21-LTri-N042 A-1, B - 1 )
~~> + 162.5 inches *
> + 162.5 inches
- l c.
~~
o" d.
ADS Timer 5
(B21-TDPU-KSA,B)
< 120 seconds
< 120 seconds O
~
l TABLE 3.3.3-2 (Continued)
?
d EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRIMENTATION SETPOINTS c
s Q
ALLOWABLE RIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE q
y e.
Core Spray Pump Discharge Pressure - High
> 100 psig
> 100 psig H
(E21-PS-N008A,B and E21-PS-N009A,B)
H f.
RilR (LPCI MODE) Pump Discharge Pressure - Iligh
> 100 psig
> 100 psig (El1-PS-N016A,B,C,D and El1-PS-N020A,B,C,D) g.
Bus Power Monitor NA NA (B21-KlA,B) 5.
LOSS OF POUER a.
4.16 kv Energency Bus Undervoltage a.
4.16 kv Basis - 2940 t 161 volts 2940 i 315 volts (loss of Voltage)#
b.
120 v Basis - 84 t 4.6 volts 84
- 9 volts y
c.
1 10 sec. time delay i 10 secs. time delay b.
4.16 kv Emergency Bus Undervoltage a.
4.16 kv Basis - 3727
- 9 volts 3727 t 21 volts (Degraded Voltage) b.
120 v Basis - 106.5 t 0.25 volts 106.5 t 0.60 volts c.
10 t 0.5 sec. time delay 10 t 1.0 sec. time delay P
R.
Mo
- This is an inverse time delay voltage relay. The voltages shown are the maximum that will not result y
in a trip.
Lower voltage conditions will result in. decreased trip times.
i
- Vessel water levels refer to REFERENCE LEVEL ZERO.
N
- Suppression chamber water level zero is the torus centerline minus 1 inch.
?
m w
i t
1
=
g TABLE 4.3.3-1 n
I5 EMERGENCY 0)RE COOLING SYSTEM ACTUATION INSTRUMEffrATION SURVEILLANCE REQUIREMEffrS N
y:
QIANNEL OPERATIONAL a
QIANNEL FUNCf10NAL QlANNEL CONDITIONS IN WilIQI g
TRIP FUNCfl0N AND INSTRUMENT NUMBER GlECK TESr CALIBRATION SURVEILLANCE REQUIRED A
[
- 1. Q)RE SPRAY SYSTEM a.
Low, Level 3
( li21-LT-NO31 A, B, C,D)
NA NA R
1,2,3,4,5
( B 21-LT S-NO31 A-4, B-4, C-4, D-4)
D Ms M
1,2,3,4,5 b.
Reactor Steam Dome Pressure - Low g
( B21-PT-N021 A, B, C, D)
NA NA R
1,2,3,4,5 g
( B21-PTS-N021 A-2, B-2, C-2,D-2)
D M
M 1,2,3,4,5 c.
Drywell Pressure - liigh NA M
Q 1, 2, 3
( E l l-PS-N0 l l A,li, C, D) d.
Time Delay Relay NA R
R 1,2,3,4,5 L
(E21-Kl6A,B) l
~s c.
Bus Power tbnitor NA R
NA 1,2,3,4,5 (E21-KlA,B) 2.
LPCI MODE OF RilR SYSTEM a.
Drywell Pressure - liigh NA M
Q 1, 2, 3
( E l l-P S-N0 l l A,li, C, D) b.
Low, Level 3
( B21-LT-NO31 A, B, C,D)
NA(a)
NA R(b) 1, 2, 3, 4*, 5*
g
( 1521-LT S-NO31 A-4, B-4, C-4, D-4)
D M
M 1, 2, 3, 4*, 5*
in
- g c.
Reactor Vessel Shroud Level g
(li21-LT-NO36 and B21-LT-NO3 7)
NA NA R
1, 2, 3, 4*, 5*
l g
(821-LTM-NO36-1 and B21-LTM-NO37-1) D M
M 1, 2, 3, 4*, 5*
((
=
t';
I
TABLE 4.3.3-1 (Continued)
E E}
EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS An CllANNEL OPERATIONAL CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WNICil
]
TRIP FUllCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED a
e d.
Reactor Steam Dome Pressure - Low NA(a)
NA R(b) 1, 2, 3, 4*, 5*
l (B21-PT-NO21A,B,C,D) 1.
RIIR Pump Start and LPCI Injection Valve Actuation D
M M
1, 2, 3, 4*,
5*
(B21-PTS-N021A-2,B-2,C-2,D-2) 2.
Reci rculation loop Pump Discharge Valve Actuation D
M M
1, 2, 3, 4*,
5*
(B21-PTM-f!O21A-1,B-1,C-1,D-1) e.
RilR Pump Start - Time Delay Relay NA R
R 1, 2, 3, 4*,
5*.
t!
(STR-I Al,2 and STR-1B1,2) f.
Bus Power Monitor NA R
NA 1, 2, 3, 4*,
5*
(Ell-K106A,B)
- 3. IIPCI SYSTEM a.
Low, Imvel 2 (B21-LT-NO31A,B,C,D) flA(a)
NA R(b) 1, 2, 3 (B21-LTS-NO31A-2,B-2,C-2,D-2)
D H
M 1, 2, 3 b.
Drywell Pressure - liigh NA H
Q 1, 2, 3 (Ell-PS-N0llA,B,C,D)
P M
c.
Condensate Storage Tank Level - Low NA M
Q 1, 2, 3 1
b (E41-LS-fl002; E41-LS-fl003) d.
Suppression Chamber Water level - Iligh NA M
.Q 1, 2, 3 (E41-LSil-N015A,3) v.
e.
Ilus Power Monitor 11A R
NA 1, 2, 3 (E41-K55 and E41-K56) to W
l
es TABLE 4.3.3-1 (Continued) v!
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIRE!!ENTS n
7:
CilANNEL OPERATIONAL e
CliANNEL FUNCTIONAL CilANNEL CONDITIONS IN WHICil q
TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED M
- 4. ADS a.
Drywell Pressure - liigh NA M
Q 1, 2, 3 (E I l-PS-N010A, B,C, D) b.
Low, Level 3 l
(B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 I
( B21-LTS-NO31 A-3, B-3,C-3, D-3)
D M
M 1, 2, 3 c.
Re:2ctor Vessel Water Level -
Low, Level 1 M
(B21-LT-N042A,B)
NA(a)
NA R(b) 1, 2, 3 (H21-LTM-N042A-1,B-1)
D M
M 1, 2, 3 E4 b
d.
ADS Timer NA' R
R 1, 2, 3 (B21-TDPU-K5A,B) e.
Core Spray I\\ imp Discharge Pressure - liigh NA M
0 1, 2, 3 (E21-PS-N008A,B and E 21-PS-N009A, B) f.
RilR (LPCI MODE) Pump Discharge Pressure - liigh NA M
Q 1, 2, 3 (E l l-i'S-N016A,II,C, D and Ell-PS-N020A,B,C,D)
,'I lo g.
It s Power Monitor NA R
NA 1, 2, 3
(
S.
(Is 21-KI A, B) g
'5 u
a
M TABLE 4.3.3-1 (Continued)
E$
EMERCENCY CORE COOLItC SYSTEM ACTUATION INSTRUMENTATION SURVEILLANG REQUIREMENTS
-aoA OIANNEL OPERATIONAL 8
QlANNEL FUNCTIONAL 01ANNEL CONDITIONS IN Wii101 g
TRIP FUNCTION AND INSTRUMEffr NUMBER GIECK TEST CALIBRATION SURVEILLANCE REQUIRED G
5.
U)SS OF POWER g
a.
4.16 kv Emergency Bus NA NA R
1, 2, 3, 4*, 5*
Undervoltage (loss of Voltage) b.
4.16 kv Emergency Bus S
M R
1, 2, 3, 4*, 5*
Undervoltage (Degraded Voltage)
U w
- Required when ESP equipment is required to be OPERAELE.
w d,
(a) The transmitter channel check is satisfied by the trip unit channel check.
8?
A separate transmitter check is not required.
(b) Transmitters are exempted f rom the monthly channel calibration.
!Y a
8n O
b
TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.
OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 1.
Reactor Vessel Pressure 2
l (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.
l (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
l (CAC-LT-2601; CAC-LY-2601-1; CAC-LI-2601-3)
(CAC-LT-2602; CAC-LR-2602) l 4
Suppression Chamber Water Temperature 2
l (CAC-TR-1258-14, 21;~
and C91-P602) 5.
Suppression Chamber Atmosphere Temperature 2
(CAC-TR-1258-17 thru 20; and C91-P602) 6.
Drywell Pressure 2
l (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.
Drywell Temperature 2
l l
(CAC-TR-1258-1 thru 13, 22, 23, 24;
(
and C91-P602) 8.
Drywell Radiation 2
l (CAC-AR-1260; CAC-AQH-1260-1, 2, 3; l
CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262; and CAC-AQH-1262-1, 2, 3) 9.
Drywell Oxygen 2
(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) 10 Drywell Hydrogen 2
l (CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) 11.
Safety Relief Valve Position Indication:
1/ valve Primary - Sonic (821-FY-4157 thru 4167) a.
l b.
Secondary - Temp. (B21-TR-1614, points 1-11) l BRUNSWICK - UNIT 1 3/4 3-51 Amendment No.f 7 53 l
l
i i
en j
y TABLE 4.3.5.3-1 i
M POST-ACCIDE?Tr MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CilANNEL j
g INSTRU!!ENT AND INSTRU!!ENT NUMBER CHECK CALIBRATION G
H 1.
Reactor Vessel Pressure M
R l
~
(B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.
R l
l (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; j
B21-LT-NO37; and B21-LTM-NO37-1) j 3.
Suppression Chamber Water level M
R l
(CAC-LT-2601; CAC-LY-2601-1; CAC-LI-2601-3; CAC-LT-2602; CAC-LR-2602) 4.
Suppression Chamber Water Temperature M
R l
(CAC-TR-1258-14, 21; and C91-P602) 5.
Suppression Chamber Atmosphere Temperature M
R (CAC-TR-1258-17 thru 20; and C91-P602)
{
6.
Drywell Pressure M
R 3,
(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) l 7.
Drywell Temperature H
R l
(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.
Drywell Radiation M
R l
f (CAC-AR-1260; CAC-AQll-1260-1,2,3; CAC-AR-1261; CAC-AQll-1261-1,2,3; CAC-AR-1262; and CAC-AQll-1262-1,2,3) 9.
Drywell oxygen Concentration M
R (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) l 10 Drywell liydrogen Concentration M
R R.
(CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) l l1.
Safety Relief Valve Position Indication Primary - Sonic (B21-FY-4157 thru 4167)
M R
a.
)f b.
Secondary - Temp. (B21-TR-R614, points 1-11)
M R
I
y TABLE 3.3.6.1-1 Oy ATUS RECIRCULATION PUMP TRIP SYSTEM INSTRUllENTATION Mn 8
MINIMUM NUMBER OPERABLE TRIP Q
TR IP FilflCTIOtt AND _ItiSTRUMEtTr NUMBER SYSTEMS PER OPERATING PUMP G
1.
1 g
Low, Level 2 l
(B21-L1-fl024A-2,B-2 and Il 21-LT-N0 2 5A-2, Il-2 )
(B21-LTIt-IIO24A-2,ll-2 and Il21-LTM-fl02 5A-2, B-2 )
2.
Reactor Vessel Pressure - liigh I
(ll21-PS-N015A,B,C,D)
M s~
Bn O
b
l I
m TABLE 3.3.6.1-2 E
4 z
m ATUS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS 1
4 i
n 8
TRIP ALLOWABLE g
TRIP FUriCTION AND INSTRUMEttr NUMBER SETPOIlff VALUE i
s t
H 1.
Reactor Vessel, Water Level -
> + 112 inches *
> + 112 inches
- i Low, Level 2 (B21-LTM-N024A-2,B-2; B21-LTM-N025A-2,B-2) 2.
Reactor Vessel Pressure - liigh
( B 21-PS -N04 5A, B, C, D)
--<l120 psig
-<1120 psig i
i I
1 4
W i'
i 5
I i
?
N n.
1 a
rt O
L i
m U1 W
- Vessel water levels refer to REFERENCE LEVEL ZERO.
I
4 1
TABLE 4.3.6.1-1 c:
}
M 4
ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS b
CIIANNEL CilANNEL FUNCTIONAL CHANNEL 1
TRIP FUNCTION AN3 INSTRllMENT NUMBER CllECK TEST CALIBRATION E!
y 1.
I.ow, Icvel 2 a
I NA ")
NA R(b)
I (B21-LT-N024A-2,B-2 and B21-LT-N025A-2,B-2) l (B21-LTri-N024A-2,B-2 and D
M M
)
B21-LTM-N025A-2,B-2) a 2.
Reactor Vessel Pressure - liigh NA M
R I
(B21-PS-N045A, B, C, D) t' n
T m
u.
I l
1 N
8 R
l
\\
l u
l M
(a) The transmitter channel check is satisfied by the trip unit channel m
check. A separate transmitter check is not required.
i (b) Transmitters are exempted from the monthly channel calibration.
i.
f
[+,pm vg o,
UNITED STATES
}
NUCLEAR REGULATORY COMMISSION g
wAsw.ucrow, p. c. 20sss n
t
%,..... sI CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. DPR-62 1.
The Nuclear Regulatory Conmiss, ion (the Commission) has found that:
l A.
The application for amendment by Carolina Power & Light Company dated November 12, 1982, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter 1; r
B.
Tne f acility 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 b) this anendnent 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 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 amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licehse is amended by changes to the Technical Spec-
~
ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) cf Facility Operating License No. DPR-62 is hereby anended to read as follows:
i (2) Technical Specifications i
l The Technical Specifications contained,in Appendices A and B, as revised through Amendment No. 78, are hereby incorporated in the licqnse. The licensee shall operate the facility in accordance with the Technical Specifications.
, 3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specificctions Date of Issuance: December 20, 1982 YN l
s e-
, - - - - -. ~.
, - = _
ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO 50-324 Revise the Appendix A Technical Specifications as follows:
Remove Insert 2-4 2-4 2-6 2-6 3/4 3-2 3/4 3-2 3/4 3-6 3/4 3-6 3/4 3-6a 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-Sa 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 3/4 3-14a 3/4 3-15 3/4 3-15 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 3-20 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 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 3/4 3-29a 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 3/4 3-32a 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-35a 3/4 3-35a 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3 38 3/4 3-38a 3/4 3 38a 3/4 3 38b 3/4 3-51 3/4351 3/4 3-52 3/4352 3/4 3-63 3/4 3 63 3/4364 3/4364 3/4865 3/4865 3/4 8-10 3/4 8-10
N TABLE 2.2.1-1
~
0 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS N
ALLOWABLE FUNCTIONAL UNIT AND INSTRUMENT NUMilER TRIP SETPOINT VALUES U
h 1.
Intermediate Range Monitor, Neutron Flux - liigb(I)
-< 120 divisions of full scale
< 120 divisions (C51-IRM-K601 A, B,C,D,E,F,G,II)
- of full scale ea 2.
Average Power Range Monitor
( C51-APRM-Cll. A,B,C,D,E,F)
Neutron Flux - liigh, 15%( }
< 15% of RATED TilERMAL POWER 1 15% of RATED a.
TilERMAL POWER Flow Biased Neutron Flux - liigh(3)(4)
< (0.66 W + 54%)
1 (0.66 W + 54%)
b.
Fixed Neutron Flux - liigh( )
i 120% of RATED THERMAL POWER 1120% of RATED
'[
c.
TilERMAL POWER 3.
Reactor Vessel Steam Dome Pressure - liigh
< 1045 psig i 1045 psig (B21-PTM-N023A-1,B-1,C-1,D-1) 4.
Reactor Vessel Water Level - Low, Level 1
> +162.5 inches *
> +162.5 inches *
( B21 -LTil-N017 A-1, B-1, C-1, D-1 )
5.
Main Steam Line Isolation Valve - Closure (5)
< 10% closed
< 10% closed (ll21-F022 A,II C,D; B 21-F028 A, B, C, D) 6.
flain Steam Line Radiation - !!igh 1 3 x full pouer background i 3.5 x full power g
b
( D12-MI-K603 A, B, C, D) background S.
M 7.
Drywell Pressure - Iligh
-< 2 psig
-< 2 psig S
( C7 2-PS-N002 A, II, C, D) z 8.
Scrma Discharg'e Volume Water Level - High
-< 109 gallons
-< 109 gallons
( C l 2-LS il-N013 A, B, C, D)
N
( C l 2-IS il-4 516 A,II, C, D) l 5
TABLE 2.2.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS TABLE NOTATION
- Vessel water levels refer to REFERENCE LEVEL ZERO.
l (1) The Intermediate Range Monitor scram functions are automatically bypassed when the reactor mode switch is placed in the Run position and the Average Power Range Monitors are on scale.
(2) This Average Power Range Monitor scram function is a fixed point and is increased when the reactor mode switch is placed in 'the Run position.
(3) The Average Power Range Monitor scram function is varied, Figure 2.2.1-1, as a function of recirculation loop flow (W).
The trip setting of this function must be maintained in accordance with Specification 3.2.2.
(4) The APRM flow-biased high neutron flux signal is fed through a time constant circuit of approximately.6 seconds. The APRM fixed high neutron flux signal does not incorporate the time _ constant, but responds directly to instantaneous neutron flux.
l (5)
'Ihe Main Steam Line Isolation Valve-Closure scram function is automatically bypassed when the reactor mode switch is in other than the Run position.
(6) These scram functions are bypassed when THERMAL POWER is less than 30% of RATED THERMAL POWER.
i l
l BRUNSWICK - UNIT 2 2-6 Amendment No. $$ 78 i
I e
TABLE 3.3.1-1 ww REACTOR PROTECTION SYSTEM INSTRUMENTATION n
p, APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT AND INSTRUMENT NUMBER CONDITIONS PER TRIP SYSTEM (a)
ACTION g
R H
1.
(C 51-IRM-K601 A, B,C, D,E,F, G,II)
'a a.
Neutron Flux - liigh 2, 5(b) 3 1
3, 4 2
2 b.
Inoperative 2, 5 3
1 3, 4 2
2 2.
Average Power Range Monitor (C S I-APRM-Cll. A, B,C, D,E, F) 0)
a.
Neutron Flux - liigh, 15%
2, 5 2
3 b.
Flow Biased Neutron Flux - liigh 1
2 6
8$
c.
Fixed Neutron Flux - liigh, 120%
1 2
4 d.
Inoperative 1, 2, 5 2
5 e.
Downscale 1
2 4
f.
LPRM 1, 2, 5 (c)
NA I
3.
Reactor Vessel Steam Dome Pressure - liigh 1, 2(d) 2 6
(ll21-PT-N023A, B,C, D)
{
(821-PTM-N023A-1,B-1,C-1,D-1) 4.
1, 2 2
6 i
Low, Level 1 l
( B 21-LT-N017 A-1, B-1,C-1, D-1) l g
(ll21-LTM-N017 A-1, B-1, C-1, D-1) u 5.
Main Steam Isolation Valve - Closure 1
4 4
(ll21-F022A,B,C,D and r'
y B21-F028A,B,C,D) l 6.
Main Steam Line Radiation - liigh 1, 2(d) 2 7
E (D12-RM-K603A,B,C,D)
~
F l
g TABLE 3.3.1-2 6
te REACTOR PROTECTION SYSTEM RESPONSE TIMES M
l r.
RESPONSE TIME i
FUNCTIONAL UNIT AND IrlSTRUMENT NUMBER (Seconds) c~
d 1.
(C51-IRM-K601 A, B,C, D, E, F,G,II):
n a.
Neutron Flux - liigh*
NA j
b.
Inoperative NA l
2.
Average Power Range Monitor
- s j
( C51-Al R>f-Cll. A, B, C, D,E, F) :
)
a.
Neutron Flux - liigh, 15%
< 0.09 b.
Flow-Biased Neutron Flux - High NA i
y c.
Neutron Flux - !!igh, 120%
<__ 0.09 1
o d.
Inoperative NA e
m e.
Downscale NA j
f.
LPRM NA l
3.
Reactor Vessel Steam Dome Pressure - liigh
< 0.55 (B21-PT-N023A,B,C,D)
( B 21-PTM-NO23 A-1, B-1,C-1, D-1 )
1 4.
Reactot Vessel Water Level - Low, Level 1
< 1.05 (B21-LT-N017A-1,B-1,C-1,D-1)
~
(B21-LTM-N017A-1,B-1,C-1,D-1) bY to 5.
Main Steam 1.ine Isolation Valve-Closure h
(B21-F022A,B,C,D and
~< 0.06 j
g B21-F028 A, B,C, D) t n
i y
6.
Main Steam Line Radiation - liigh NA
( D12-RM-K603 A, B, C, D) w t
M.
D 2
1 l
~
1 l
I i
y TABLE 3.3.1-2 (Continued) 1 E
y}
RE ACTOR PROTECTION SYSTEM RESPONSE TIMES R
M RESPONSE TIME FUNCTIONAL UNIT AND IISTRUMENT NUMBER (Seconds) b l
p 7.
Drywell Pressure - liigh NA
( C72-PS-N002 A, B, C, D) o 8.
Scram Discharge Volume Water level - Iligh NA
( C l 2-LS il-N013 A, B, C, D)
( C l 2-LS il-4516 A, B, C, D) 1 9.
Turbine Stop Valve - Closure
- < 0.06
( EllC-S VOS -l X,2 X,3 X,4X)
- 10. Turbine Control valve East Closure,
- C 0.08 j
h)
Control Oil Pressure - Low j
(EllC-PS L-1756,1757,1758,1759)
)
Y j
g'
- 11. Reactor Mode Switch in Shutdown Position NA j
( C72 A-S I)
I
- 12. Manual Scram NA j
i
( C72 A-S 3 A, B)
- Neutron detectors are exempt from response time testing. Response time shall be measured from detector output or from the input of the first electronic component in the channel.
i l
N 8
l W
a" i
x i
o I
l l
TABLE 4.3.1-1 g
c:
M REACTOR PROTECTION SYSTEM INSTRUMEt(FATION SURVEILLANCE REQUIREMENTS 5[j OIANNEL OPERATIONAL FUNCTIONAL UNIT QlANNEL FUNCTIONAL QIANNEL CONDITIONS IN WilIQI AND INSTRUMEttr NUMBER GlECK TESr CALIliRATION SURVEILLANCE REQUIRED gn H
1.
( C51-IRM-K601A,II,C,D,E,F C.II) a.
Neutron Flux - liigh D
S/U(b)(c)
R 2
D W
R 3, 4, 5
+
b.
Inoperative NA W
NA 2,3,4,5 2.
Average Power Range Monitor:
( C51-APRM-Clf. A, B, C,D, E, F) a.
Neutron Flux - Iligh 15%
S S/U(b), g(d)
Q 2
u S
W Q
5 S/U(b) y g(e)(f) b.
Flow-lilased Neutron Flux - liigh S
,q g
S/U(b),y g(e),q g
c.
Fixed Neutron Flux - liigh, 120%
S d.
Inoperative NA W
NA 1, 2, 5 e.
Downscale NA W
NA 1
f.
LPIO!
D NA (g) 1, 2, 5 3.
Reactor Vessel Steam Dome Pressure - liigh
( li21-PT-NO2 3A, B,C,D)
NA NA R
1, 2 j
( 1521-PTM-N023 A-1,li-1, C-1, D-1)
D M
M 1, 2 R.
4.
l 3
Low, Level I
( B21-LT-NO l 7A-1, 8-1, C-1, D-1 )
NA NA R
1, 2
(
( 1121 -LTM-No l 7A-1,II-1, C-1, D-1)
D M
M 1, 2 m
k 1
I E
TABLE 4.3.1-1 (Continued)
~
E REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
E M
CllANNEL OPERATIONAL I
FUNCTIONAL UNIT CllANNEL FUNCTIONAL CllANNEL CONDITIONS IN WHICH AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED
- 5. Main Steam Line Isolation Valve -
NA M
R( )
1 Closure (B21-F022A,II,C,D and
]
B21-F028 A, B, C, D)
- 6. Main Steam Line Radiation - liigh S
M(I)
I3 )
R 1, 2
( D12-RM-K603 A, II, C, D)
- 7. Crywell Pressure - liigh NA M
Q 1, 2 i
( C 72-PS-N002 A, B,C, D) u
- 8. Scrata Discharge Volume Water Y
Level - lligh NA Q
R 1, 2, 5
( Cl 2-LSil-N013 A, B,C, D)
( C l 2-IS il-4516 A, B, C, D)
- 9. Turbine Stop Valve - Closure NA M
R(h) g
( EliC-S VOS-I X,2 X,3 X,4 X) l
- 10. Turbine Control Valve Fast Closure, Control Oil Pressure -
Low NA M
R 1
( EllC-PS L-1756,1757,1758,1759)
~.
k
- 11. Reactor Mode Switch in Shutdown NA R
NA 1,2,3,4,5 i
l Position
( C72 A-S I) i n
z
- 12. Manual Scram NA Q
NA 1,2,3,4,5
( C72 A-S 3 A, B)
I Co I
i
csy TABLE 4.3.1-1 (Continued)
~
d}
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS n
7A 8
(a) g Neutron detectors may be excluded f rom CilANNEL CALIBRATION.
Ci 4
(b) Uithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
H tO (c) The IRil channels shall be compared to the APRM channels and the SRM instruments for overlap during each startup, if not performed within the previous 7 days.
l (d) When changing f rom CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
)
after entering CONDITION 2.
(e) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during CONDITION 1 when TilERMAL POWER > 25% of RATED TilERMAL POWER.
h (f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a calibrated flow signal.
1 u
En (g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.
m (h) This calibration shall consist of a physical inspection and actuation of these position switches.
(i) In s t rutne n t alignment using a standard current source.
(j) Calibration using a standard radiation source.
(k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitte'r check is not required.
lI g
(1) Transmitters are exempted from the monthly channel calibration.
IT 8
n g.
i s
i
..z.
i i
4 en
{
g TABLE 3.3.2-1 Gi l
ISOLATION ACTUATION INSTRUMENTATION 9
VALVE GROUPS MINIMUM NUMBER APPLICABLE j
i OPERATED BY OPERABLE CllANNELS OPERATIONAL g
j TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION i
H 1.
PRIMARY CONTAINMENT ISOLATION I
a.
1.
Low, Level 1 2,6,7,8 2
1,2,3
-20 (B21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) j 2.
Low, Level 2 1, 3 2
1,2,3 20
]
(B21-LT-N024A-1,B-1, and B21-LT-N025A-1,B-1) u
?
2 (B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) u h
b.
Drywell Pressure - Iligh 2,
6, 7 2
1,2,3 20 (C72-PS-N002A,B,C,D)
I c.
1.
Radiation - liigh (d) 1 2
1,2,3 21 i
(D12-RM-K603A,B,C,D) l 2.
Pressure - Low 1
2 1
22 l
(B21-PT-Nol5A,B,C,D) l (B21-PTM-dol 5A-1,8-1,C-1,D-1) 3.
Flow - Iligh 1
2/line 1
22 (B21-PDT-N006A,B,C,D; B21-PDT-N007A,B,C,D; j
B21-PDT-N008A,B,C,D; I
B21-PDT-N009A,B,C,D)
J (B21-PDTM-N006A-1,B-1,C-1,D-1; j
4 B21-PDTM-N007A-1,B-1,C-1,D-1; I
(
B21-PDTM-N008A-1,B-1,C-1,D-1; m
B21-PDTM-N009A-1,B-1,C-1,D-1)
i e
~
m TABLE 3.3.2-1 (Continued)
Li
$3 ISOLATION ACTUATION INSTRUMENTATION O
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CIIANNELS OPERATIONAL gh TRIP FUNCTION AND INSTRUMEKr NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION H
4.
Flow - 111gh 1
2 2,
3 21 (B21-PDTS-N006A-2; B21-PDTS-N007B-2; 321-PDTS-N008C-2 ;
B21-PDTS-N009D-2) d.
Main Steam Line Tunnel Temperature - liigh 1
2(*)
1, 2, 3
21 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; ti B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) u e.
Condenser Vacuun - Lou 1
2 1, 2(f) 21 L"
( B 21-PS-N056A, B, C, D) f.
Turbine Building Area Temperature - Iligh 1
4(")
1, 2, 3 21 (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-rS-3230A,B,C,D; g
B21-TS-3231A,B,C,D; 6
B21-IS-3232A,B,C,D) a
{T 2.
SECONDARY CONTAINMENT ISOLATION N
a.
Reactor Building Exhaust Radiation - liigh 6
1 1, 2, 3, 5, and* 23 a
(D12-RM-N010A,B)
.w 2"
b.
Drywell Pressure - liigh 2, 6, 7 2
1,2,3 23 Bj (C72-PS-U002A,B,C,D)
TABLE 3.3.2-1 (Continued) 3, E
- 4 ISOLATION ACTUATION INSTRUMENTATION N
Q VALVE GROUPS HINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CilANNELS OPERATIONAL c:
TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION N
H c.
Low, Level 2 1, 3 2
1,2,3 23 l
(H21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
(H21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - Iligh 3
1 1,2,3 24 gj (G31-d FS-N603-I A, lB) b.
Area Temperature - Iligh 3
2 1, 2, 3 24 y
(G31-TS-N600A,B,C,D,E F) c.
Area Ventilation A Temp. - liigh 3
2 1, 2, 3 24 (G31-TS-N602A,B,C,D,F.F) d.
SLCS Initiation 3 (g)
NA 1, 2, 3 24 (C41A-SI) c.
Low, Level 2 1, 3 2
1, 2, 3 24 (B21-LT-N024 A-1,B-1 and B21-LT-N025 A-1,B-1) y (B21-LTM-N024 A-1,B-1 and g
B21-LTM-N025 A-1,B-1) 0F an l$
t si l
l a.
m TABLE 3.3.2-1 (Continued)
~
8 5
ISOLATION ACTUNCION INSTRUMENTATION 5
O VALVE GROUPS MINIMUM NUMBER APPLICABLE I
OPERATED BY OPERABLE CilANNELS OPERATIONAL g
TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION U
4.
CORE STANDBY COOLING SYSTEMS ISOLATION I
a.
High Pressure Coolant Injection System Isolation l.
IIPCI Steam Line Flow - High 4
2 1,2,3 25 (E41-dPIS-N004 and E41-dPIS-N005)
I 2.
HPCI Steam Supply Pressure - Low 4
2 1,2,3 25 (E41-PS L-N001 A, B,C, D) 3.
HPCI Steam Line Tunnel Temperature - liigh 4
2 1,2,3 25 7;
(E41-TS-3314; E41-TS-3315; i
Y E41-TS-3316; 5
E41-TS-3317; I
E41-TS-3318; E41-TS-3354; j
E41-TS-3488; E41-TS-3489) 4.
Bus Power Fbnitor NA(h) 1/ bus 1, 2, 3 26 (E41-K55 and E41-K56) i 5.
IIPCI Turbine Exhaust i
Diaphragm Pressure - liigh 4
2 1,2,3 25 j
(E41-PSil-N012A,B,C, D) i i
m 6.
IIPCI Steam Line Ambient l
S.
Temperature - Iligh 4
2 1,2,3 25 l
(E51-TS-N603C,D) 7.
HPCI Steam Line Area A Temp. -
f liigh 4
2 1,2,3 25 (E51-dTS-N604C,D) 8.
Emergency Area Cooler Temperature - liigh 4
2 1,2,3 25 (E41-TS-N602A, B) l
t s
T l
TABLE 3.3.2-1 (Continued)
E
}
ISOLATION ACTUATION INSTRUMENTATION VALVE CROUPS MINIMUM NUMBER APPLICABLE t
M OPERATED BY OPERABLE CilANNELS OPERATIONAL 8
TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION E;j b.
Reactor Core Isolation Cooling System Isolation b2 1.
RCIC Steam Line Flow - liigh 5
2 1, 2, 3 25 l
(E51-dPIS-N017 and E51-dPIS-N018)
I 2.
RCIC Steam Supply Pressure - Low 5
2 1, 2, 3 25 l
(E51-PS-N019A,B,C,D) i 3.
RCIC Steam Line Tunnel Temperature
- liigh 5
2 1, 2, 3 25 (E51-TS-3319; l
E51-TS-3320; i
E51-TS-3321; 7:
E51-TS-3322; E51-TS-3323; u,
L E51-TS-3355; p
E51-TS-3487)
[
4.
Bus Power Monitor NA (h) 1/ bus 1,
2',
3 26 (E51-K42 and E51-K43) 5.
RCIC Turbine Exhaust Diaphragm Pressure - liigh 5
2 1, 2, 3 25 (E51-PS-N012A,8,C,D) 6 RCIC Steam Line Ambient Temp -
!iigh 5
2 1, 2, 3 25 (E51-TS-N603A,3) l 6
.f -
/
g 7.
RCIC Steam Line Area d Temp - High 5
2 1, 2, 3 25 g-(E51-dTS-N604A,H) m j
,,M.
RCIC Equipment Room Ambient 3
, Temp - liigh 5
2 1, 2, 3 25 f
(E51-TS-N602A,B)
' 9.
RCIC Equipment Room A Temp - liigh',[-
5 2
1, 2, 3 25
/,
(E51-dTS-N601A,B)
/
u to a
)
,e r
,o
\\
w" t'
4
cs}
TABLE 3.3.2-1 (Continued) m J
N ISOLATION ACTUATION INSTRUME!TTATION g
VALVI; GROUPS MINIMU:1 NUMBER APPLICABLE s
g OPERATED BY OPERABLE CilANNELS OPERATIONAL Q
TRIP FUNCT! r'4 AND :.NSTRUi!Eif NUMBER n
SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION 5.
SHUTDOWN COOLING SYSTEM ISOLATION a.
Reactor Vassel Water Level -
Lou, Level 1 2,6,7,8 2
1, 2, 3 27 (B21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) b.
Reactor Steam Done Pressure-7, 8
1 1,2,3 27 High (B32-PS-N018A,B) c.
G li e
8n
.O
)
y TABLE 3.3.2 _2 2
Oy ISOLATION ACTUATION 1.'4STRUMENTATION SETPOINTS N
7:
I ALLOWABLE l
Q TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE a
1.
PRIMARY CONTAINMENT ISOLATION n
- i. Reactor Vesrel Water Level -
1.
Low, level 1
> + 162.5 inches *
> + 162.5 inches *
(821-LTM-N017A-1,B-1,C-1,D-1)
~
~
2.
Low, Level 2
> + 112 inches *
> + 112 inches *
( B21-LTM-N024 A-1,B-1 and
~
B21-LTM-NO25A-1.B-1) b.
Drywell Pressure - Iligh 1 2 psig
< 2 psig
( C72-PS-NOO2 A, B, C, D) c.
l.
Radiation - !!igh 1 3 x full power background
< 3.5 x full power Z
( D12-lui-K603 A, B, C, D) background 2.
Pressure - low
> 825 psig
~> 825 psig (B21-PTM-Nol5A-1,B-1,C-1,D-1)
~
l 3.
Flow - liigh
< 140% of rated flow
< 140% of rated flow
( B21-PDT't-N006 A-1, B-1, C-1, D-1 ;
B 21-PDTri-N007 A-1, B-1, C-1, D-1 ;
il21-PDTM-N008 A-1, B-1, C-1, D-1 ;
B21-PDTM-N009A-1,B-1,C-1,D-1) 4.
Flow - liigh
< 40% of rated flow
< 40% of rated flow
?g
( B21 -PDTS-N006 A-2 ;
B21-P DTS -N00715-2 ;
Q ll21-PDTS-N008C-2; B21-PD'IS-N009D-2)
N 5
/
ton TABLE 3.3.2-2 (Continued)
E2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS k
W ALLOWABLE 8
TRIP FUNCTION AND INSTRUt1ENT NUMBER TRIP SETPOINT VALUE 52y d.
Main Steam Line Tunnel Temperature - liigh
< 200*F
< 200*F n
(ll21-TS -N010 A, B, C, D; B21-TS-N0ll A,B,C,D; B21-TS N012 A,B,C,D; B 21-TS -N013 A, B,C, D) e.
Condenser Vacuum - Low
> 7 inches IIg vacuum 17 inches lig vacuum (1521-PS-N056 A, B, C, D) f.
Turbine Building Area Temp - liigh
< 200*F
< E00*F
( B21-TS -3225 A, B, C, D; t'
B21-13 -3226 A, B, C, D; o
B 21-TS -3227 A, ll, C, D; y
B 21-TS -3228 A, B, C, D; g
B 21-TS-3229 A, B, C, D ;
B 21-13 -3 230 A, B, C, D ;
B21-TS-3231 A,B,C,D; B21-TS -3232 A, B, C, D) 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Exhaust Radiation - liigh
< 11 mr/hr
< 11 mr/hr
( D12-RM-N010 A, B)
- g b.
Drywell Pressure - liigh 1 2 psig i 2 psig g
( C72-PS-N002 A, B, C, D) h c.
g low, Level 2 1 + 112 inches *
> + 112 inches *
( B21-LTM-N024 A-1,B-1 and
,E B21-LTM-N025A-1,B-1)
M M
g TABLE 3.3.2-2 (Continued)
Oy ISOLATION ACTUATION IR3TRUMENTATION SETPOINTS ALLOWABLE M
8 TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE Oy 3.
REACTOR WATER CLE ANUP SYSTEM ISOLATION fJ a.
A Flow - liigh j[ 53 gal / min
- < 53 gal / min (C31-d FS -N603-1 A, lB) b.
Area Temperature - liigh
~~< 150*F
< 150*F
( G31-TS-N600 A, B, C, D, E, F)
~~
c.
Area Ventilation Temperature A Temp - Iligh
~~< 50*F
< 50*F
( C 31-TS -N602 A, B, C, D, E, F)
^^
d.
S LCS Initiation NA NA
( C41 A-S I)
I' e.
Low, Level 2 u
b
( B21-LTM-N024 A-1, B-1 and
~-> + 112 inches *
> + 112 inches *
~~
B21-LTM-N025A-1,B-1) 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Injection System Isolation l
1.
IIPCL Steam Line Flow - High
< 300% of rated flow
< 300% of rated flow (E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Supply Pressure - Low
> 100 psig
> 100 psig
( E41-PS L-N001 A, B, C, D)
N g
3.
IIPCI Steam Line Tunnel Temperature - liigh
< 200*F
< 200*F P.
(E41-TS-3314 ;
h E41-TS-3315 ;
E41-TS-3316; n
- g E41-TS-3317 ;
E41-TS-3318; 3$
E41-TS-3354 ;
E41-TS-3488; o$
E41-TS-3489) l l
1
I TABLE 3.3.2-2 (Continued)
~
ww9 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 7:
ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE Gp 4.
Bus Power Monitor NA NA (E41-K55 and E41-K56) 5.
IIPCI Turbine Exhaust Diaphragm Pressiere - liigh
- ( 10 psig
- ( 10 psig
( E41 -PSil-N012A,B,C, D) 6.
!!PCI Steam Line Ambient Temp - Ifigh
< 200*F
< 200*F (E51-TS-N603C,D) 7.
IIPCI Steam Line Area A Temp - liigh
< 50*F
< 50*F (E51-dTS-N604C,D) 8.
Emergency Area Cooler Temp - liigh
< 175'F
< 175'F (E41-TS-N602A,B) u th b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - High l
(E51-dPIS-N017 and E51-dPIS-N018)
--< 300% of rated flow
< 300% of rated flow 2.
RCIC Steam Supply Pressure - Low
> 50 psig
> 50 psig (E51-PS-N019A,B,C,D) 3.
RCIC Steam Line Tunnel Temp - liigh
< 175'F
< 175'F 3 (E51-TS-3319; E51-TS-3320; E51-TS-3321; p
E51-TS-3322; d
E51-TS-3323; 8.
E51-TS-3355; M
E51-TS-3487) o" 4.
Bus Power Monitor NA NA
,f (E51-K42 and E51-K43) i
~co
I mn TABLE 3.3.2-2 (Continued)
O i
m g.
ISOI.ATION ACTUATION INSTRUI1ENTATION SETPOINTS p n e aar, p i
AI.LOWABLE TRIP FilNCTION A!ID INSTRUFIENT nut!HER TRIP SETPOIffr VALUE N
l U
5.
RCIC Turbine Exhaust Diaphragm to Pressure - liigh
< 10 psig
< 10 psig (E 51 --PS-N012A, B,C, D)
'l 6.
RCIC Steam Line Ambient Temp - Iligh
< 200*F
< 200*F (E51-TS-N603A,B) 7 RCIC Steam Line Area A Temp - Iligh
< 50*F
< 50*F (E51-dTS-N604A,B) 8.
RCIC E.luipment Room Ambient Temp - liigh
~< 175*F
< 175'F (E51-TS-N602A,B)
~
M 9.
RCIC E<tuipment Room A Temp - liigh
< 50*F
< 50*F I
(E 51-dTS-fl601 A, B)
Y O
5.
SilllTDollN COOLING SYSTEM ISOLATION i
a.
i Low, Level 1 I
( 1521 -LT:1-fl017A-1, B-1, C-1, D-1 )
~> + 162.5 inches *
> + 162.5 inches *
~
I b.
Reactor Steam Dome Pressure - liigh
< 140 psig
< 140 psig i
(ll32-PS-N018A,B)
?i i
0-I N
R s
g
- Vessel water levels refer to REFERENCE LEVEL 7.ERO.
I i
W
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l
/
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSETIME(Seconds)#l 1.
PRIMARY CONTAINMENT ISOLATION a.
1.
Low, Level 1
__13 (B 21-LT-N017A-1,B-1,C-1, D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) 2.
Low, Level 2
<l.0**
(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) b.
Drywell Pressure - High
<13 (C72-PS-N002A,B,C,D)
-~
c.
<1.0**
1.
Radiation - High*
~~
(D12-RM-K603A,B,C,D) 2.
Pressure - Low
<13
( B21 -PT-N015A,B, C, D)
-~
(B21-PTM-N015A-1,B-1,C-1,D-1) 3.
Flow - High
<0.5**
(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; B21-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
<0.5**
(B21-PDTS-N006A-2; B21-PDTS-N007B-2; B21-PDTS-N008C-2; B21-PDTS-N009D-2) d.
Fbin Steam Line Tunnel Temperature - High
<13 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.
Condenser Vacuum - Low (321-PS-N056A,B,C,D)
~~<13 SRUNSWICK-UNIT 2 3/4 3-22 Amendment No. 36 78 1
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME j
TRIPFIfNCTIONANDINSTRUMENTNUMBER RESPONSETIME(Seconds)#l 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 a.
Reactor Building Exhaust Radiation - High*
<13 (D12-RM-N010A,B)
~
b.
Drywell Pressure - High (13 (C72-PS-N002A,B,C,D)
~
c.
Reactor Vessel Water Level - Low, Level 2
<l.0**
(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 - Righ
<13 (G31-dFS-N603-1A,1B)
~
b.
Area Temperature - High
<13 (G31-TS-N600A,B,C,D,E,F)
~
Area Ventilation Temperature AT - High
<13 c.
(G31-TS-N602A,B,C,D,E,F)
~
d.
Reactor Vessel Water Level - Low, Level 2
<1.0**
e.
(B21-LT-N024 A-1,B-1 and
~
B21-LT-N025 A-1,B-1)
(B21-LTM-N024 A-1,B-1 and B21-LTM-N025 A-1,B-1) l I
l BRUNSWICK - UNIT 2 3/4 3-23 Acendment No. 78 i
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
j 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation l
1.
HPCI Steam Line Flow - High j(13 (E41-dPIS-N004 and E41-dPIS-N005) 2.
HPCI Steam Supply Pressure - Low
- [13 (E41-PSL-N001A,B,C,D) 3.
HPCI Steam Line Tunnel Temperature - High
_(13 (E41-TS-3314; E41-TS-3315 ;
E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488; E41-TS-3489) 4.
Bus Power Monitor NA (E41-K55 and E41-K56) 5.
HPCI Turbine Exhaust Diaphragm Pressure - High NA (E41-PSH-N0111, B, C,D) 6.
HPCI Steam Line Ambient Temperature - High NA (E51-TS-N603C,D) 7.
HPCI Steam Line Area NA (E51-dTS-N604C,D) 8.
Emergency Area Cooler Temperature - High is (E41-TS-602A,B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - High NA (E51-dPIS-N017 and E51-dPIS-N018) 2.
RCIC Steam Supply Pressure - Low NA
( E51-PS-N019A, B, C, D) 3.
RC,IC Steam Line Tunnel Temp - High NA (E51-TS-3319 ;
i E51-IS-3320; E51-TS-3321; E51-TS-3322 ;
l E51-TS-3323; E51-TS-3355; E51-TS-3487) 4.
Bus Power Monitor NA (E51-K42 and E51-K43)
SRUNSWICK - UNIT 2 3/4 3-24 A=end=ent No.
70 I
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME l
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
l S.
RCIC Turbine Exhaust Diaphram Pressure - High NA (E51-PS-N012A,B,C, D) 6.
RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603 A,B) 7.
RCIC Steam Line Area A Temp - High NA (E51-dTS-N604A,B) 8.
Emergency Area Cooler Temperature - High NA (E51-TS-N602A,B) 9.
RCIC Equipment Room A Temp - High NA (E51-dTS-N601 A,B) 5.
SHUTDOWN COOLING SYSTEM ISOLATION a.
Reactor Vessel Water Level - Low, Level 1 NA (B21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) b.
Reactor Steam Dome Pressure - High NA
( B32-PS -N018 A,B)
- Radiation monitors are exempt from response time testing. Response time shall be measured from d'tector 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.
BRUNSWICK - UNIT 2 3/4 3-24 A Amendment No. 78
TABLE 4. 3.2-1 h
ISOLATION ACTUATION INSTRUMErffATION SURVEILLANCE REQUIREMEfffS
- 2 QIANNEL OPERATIONAL Ej OIANNEL FUNCTIONAL QlANNEL CONDITIONS IN WilIQ1 TRIP FUNCTION AND INSCRUMENT NUMBER ClldCK TEST CALIBRATION SURVEILLANCE REQUIRED FiM 1.
PRIMARY CDtTfAINMEfff ISOLATION H
ra a.
1.
Low, Level 1 i
( B21-LT-N017A-1, B-1, C-1, D-1)
NA(")
NA R(b) 1, 2, 3
( B 21-LTM-N017A-1, B-1, C-1, D-1)
D M
M 1, 2, 3 2.
Low, Level 2
( B21-LT-NO24A-1, B-1 and B21-LT-N025A-1,8-1)
NA NA R
1, 2, 3 (H21-LTM-NO24A-1,B-1 and B21-LTM-N025A-1,B-1)
D M
M 1, 2, 3 u
b.
Drywell Pressure - liigh NA M
Q 1, 2, 3
( C7 2-PS-N002A, B, C,D) c.
Radiation - liigh D
W R
1, 2, 3
( D 12-RM-K603 A, B, C, D) 2.
Pressure - Low
( 821-PT-N015A, B, C,D)
NA(")
NA R(b) g (B21-PTM-N015A-1,B-1,C-1 D-1)
D M
M 1
3.
Flow - liigh
( B21-P DT-N006 A, B, C,D; NA(")
NA R(b) y B21-PDT-N007A,B,C,D; B21 -P DT-N008 A, B, C,D ;
g in B21-PDT-N009A,B,C,D) o
{}i
( B21-P DTM-N006 A-1, B-1, C-1, D-1 ;
D M
M 1
B21-PUrM-N007A-1,B-1,C-1,D-1; B21-P DTM-N008 A-1, B-1, C-1, D-1 ;
U B21-PDTM-N009A-1,B-1,C-1,D-1) y
1 TABLE 4.3.2-1 ( Continued) to
- n O
ISOLATION ACTUATION INSTRUMEfRATION SURVEILLANCE REQUIREMEfES 9
4
)
k QlANNEL OPERATIONAL
{
QIANNEL FUNCTIONAL OIANNEL CONDITIONS IN WiiIQi TRIP FUNCT10N AND INSTRUMEfE NIHBER GIECK TEST CALIBRATION SURVEILLANCE REQUIRED l
El O
4.
Flow - liigh D
M M
2, 3 l
(B21-PIRS-N006A-2; u
B21-PIKS-N007B-2;
)
B21-P DTS-NOO8 C-2 ;
B21-PIRS-N009D-2)
I I
d.
Main Steam Line Tunnel Temperature - liigh NA M
R 1, 2, 3
( B 21-T S-N010A, B, C, D; B 21-T S-N01 I A, B, C,D ;
B21-TS-N012A, B, C, D; I
B21-T S-N013A, B, C,D) i e.
Condenser Vacutua - Low NA M
R 1, 2#
I' (B21-PS-N056A,B,C,D) o*
l f.
Turbine Building Area Temp-liigh NA M
R 1, 2, 3
( B 21-T S-3225 A, B, C, D; B21-T S-3226A, B, C,D ;
B21-T S-32 27 A, B, C, D; B21 -T S-3 228A, B, C, D ;
B21-T S-3229 A, B, C, D; B21-T S-3230A, B, C, D ;
B 21-T S-3231 A, B, C, D; B21-T S-3232A, B, C, D) 2.
SECONDARY C0fMAINMEfR ISOLATIOli g
)
a.
Reactor Building Exhaust
!}
Radiation - liigh D
M R
1,2,3,5, and *
(D12-RM-N010A,B) n it l
a i
TABLE 4. 3.2-1 (Gintinued)
N g
ISOLATION ACTUATION INSTRUllErfrATION SURVEILLANCE REQUIREMEffrS Ep QIANNEL OPERATIONAL v:
QlANNEL FUNCTIONAL QIANNEL 00NDITIONS IN WilIQI TRIP FUNCfl0N AND INSTRUMEffr NUMBER Cl!ECK TEST CALIBRATION SURVEILLANCE REQUIRED G
M b.
Drywell Pressure - liigh NA M
Q 1, 2, 3
( C72-P S-N002A, B, C,D) ra c.
Low, Level 2 g
(B21-LT-N024 A-1,B-1 and NA NA R
1, 2, 3 B21-LT-N025 A-1,B-1)
(B21-LTM-N024 A-1,B-1 and D
H H
1, 2, 3 B21-LTM-N025 A-1,B-1) 3.
REACf0R WATER CLEANUP SYSTEM ISOLATION M
a.
A Flow - liigh D
M R
1, 2, 3 (G31-d F S-N603-1 A, lB) u ab b.
Area Temperature - liigh NA H
R 1, 2, 3 (G31-TS-N600A,B,C,D,E,F) l c.
Area Ventilation a Temp - liigh NA M
R 1, 2, 3 (G31-TS-N602A,B,C D.E F) d.
SLCS Initiation NA R
NA 1, 2, 3
( C41 A-SI) i e.
Low, Level 2 (B21-LT-N024 A-1,B-1 and NA(*)
NA R
1, 2, 3 II')
B21-LT-N025 A-1,B-1) 5Y (B21-LTM-N024 A-1,B-1 and D
H H
1, 2, 3 m
dl$.
B21-1.Tri-NO25 A-1,B-1)
E s
TABLE 4.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUME?TTATION SURVEILLANCE REQUIREMEFTS 3
r 5
OIANNEL OPERATIONAL l
9 QIANNEL FUNCTIONAL QIANNEL C00;DITIONS IN Wi!IGI TRIP FUNCTION AND INSTRUME!(r NUMBER OIECK TEST CALIBRATION SURVEILLANCE REQUIREI) c:
U 4.
Q)RE STANDBY COOLING SYSTEMS ISOLATION d
1 a.
liigh Pressure Coolant Injection System Isolation l
1.
IIPCI Steam Line Flow - liigh D
M Q
1, 2, 3 (E41-dPIS-N004 and E41-dPIS-N005) 2.
IIPCI Steam Supply Pressure -
low NA M
R 1, 2, 3 (E41-PSL-N001A,B,C,D) w 3.
IIPCI Steam Line Tunnel D
Temperature - liigh NA M
Q 1, 2, 3 (E41-TS-3314; u
tb E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3388; E41-TS-3489) 4.
Bus Power Monitor NA R
NA 1, 2, 3 (E41-K55 and E41-K56) 5.
IIPCI Turbine Exhaust p
Diaphragm Pressure - liigh NA M
Q 1, 2, 3 d
( E41-P S!!-N012A, B, C, D)
- s
[f 6.
IIPCI Steam Line Ambient Temp - liigh NA M
R 1, 2, 3
[
( E51-TS-N603C,D) b 7.
IIPCI Steam Line Area A Temp - liigh NA N
R 1, 2, 3 g
( E51-dT S-N604C,D)
i f
Yj TABLE 4.3.2-1 (mntinued)
E A
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMEf(fS QlANNEL OPERATIONAL 8
OIANNEL FUNCTIONAL QIANNEL CONDITIONS IN WHIQi E
TRIP FUNCfl0N AND INSTRUMEtTC NUMBER OlECK TEST CALIBRATION SURVEILLANCE REQUIRED M
ra 8.
Emergency Area Cooler Temp - liigh NA M
Q 1, 2, 3 l
(E41-TS-N602A,B) b.
Reactor Wre Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - Illgh NA M
Q 1, 2, 3 (E51-dPIS-N017 and E51-d PIS-N018) 2.
RCIC Steam Supply R
Pressure - Low NA M
Q 1, 2, 3 (E51-PS-N019A,B,C,D) to 3.
RCIC Steam Line Tunnel liigh Temperature NA M
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) 4.
Bus Power Monitor NA R
NA 1, 2, 3 (E51-K42 and E51-K43)
P N
5.
RCIC Turbine Exhaust E.
Diaphragm Pressure - liigh NA M
R 1, 2, 3 S
( E 51-P S-N012 A, B, C, D)
N
?!
'E M
g g
TABLE 4.3.2-1 (Continued)
$g ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIRE!!ENTS I
i 8
CilANNEL 0PERATIONAL s
CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICH y
TRIP FUNCTION AND INSTRUMENT NUMBER CNBCK TEST CALIBRATION SURVEILLANCE REQUIRED 6.
RCIC Steam Line Ambient Temp - liigh NA R
1, 2, 3 j
(E51-TS-N603A,B) 1*
7.
RCIC Steam Line Area A Teap - liigh NA M
R 1, 2, 3 (E51-dTS-N604A,B) 1 8.
RCIC Equipment Room Ambient Temp - liigh NA M
Q 1, 2, 3
}
g (E51-TS-No02A,B) a c~
9.
RCIC Equipment Room a
,1, Temp - liigh NA M
Q 1, 2, 3 y
(E51-dTS-N601A,B) 5.
SilUTDOUN COOLING SYSTEtt ISOLATION a.
I low, Level 1 (B21-LT-N017A-1,B-1,C-1,D-1)
NA(a)
NA R(b) g, 2, 3 (B21-LT!!-N017A-1,B-1,C-1,D-1)
D M
M 1, 2, 3 l
t b.
Reactor Steam D)me Pressure -
liigh NA S/U(c),M R
1, 2, 3 j
k (B32-PS-N018A,d) h o
j
- When handling irradiated fuel in the secondary containment.
c
- When reactor steam pressure > 500 psig, o
(a) The transmitter channel check is satisfied by the trip unit channel check, j
A separate transmitter check is not required.
j y
(b) Transmitters are exempted from the monthly channel calibration.
(c) If not performed within the previous 31 days.
l t
I
1 l
TABLE 3.3.3-1 I
Ef!
EO EMERGENCY CORE COOLING SYSTEM ACEUATION INSTRUME?TTATION n
MINIMUM NUMBER APPLICABLE OPERABIE CilANNELS OPERATIONAL TRIP FilNCfION AND INSTRUMEUf NUMBER O
PER TRIP SYSTEM CONDITIONS ACTION O
1.
CORE SPRAY SYSTEM Reactor Vessel Water Invel - low, level 3 2
1,2,3,4,5 30 a.
( !!21 -LT-NO31 A, B, C, D)
( B21-LT S-NO31 A-4, B-4, C-4, D-4) b.
Reactor Steam Ibme Pressure - Low (Injection Permissiveh 2
1,2,3,4,5 31
( B21-PT-N021 A, B, C, D)
( 1121-PT S-NO21 A-2, B-2, C-2, D-2)
Drywell Pressure - liigh c.
2 1,2,3 30
( E l l-P S-N0 l l A, B, C, D)
M d.
Time Iblay Relay 1
1,2,3,4,5 31 (821-K16A,B) l e.
lius Power Monitor #
1/ bus 1,2,3,4,5 32 (E21-KIA,B) 2.
LPCI MODE OF RifR SYSTEM Drywell Pressure - liigh a.
2 1, 2, 3 30
( E l l-PS-N0 l l A, B, C, D) b.
Reactor vessel Water Invel - Inu, Invel 3 2
1, 2, 3, 4*, 5*
30
( li21-LT-NO31 A, B, C, D)
( B21-LTS-NO3 I A-4, B-4, C-4, D-4)
N Reactor Vessel Shroud level (Drywell Spray Permissive) 1 1, 2, 3, 4*, 5*
31 p
c.
(ll21-LT-NO36 and H21-LT-NO37)
(1121-LTM-NO36-1 and B21-LTM-NO37-1) n d.
Reactor Steam Dome Pressure - low (Injection Permissive)
( 1321-PT-N02 I A, B, C, D)
( B 21-PTM-N021 A-1, B-1, C-1, D-1 )
( 1121 -PT S-NO21 A-2, B-2, C-2, D-2) w 1.
RilR Pump Start and LPCI Injection Valve Actuation 2
1, 2, 3, 4*, 5*
31 y
2.
Recirculation loop Pump Discharge Valve Actuation 2
1, 2, 3, 4*, 5*
31 a
gj TABLE 3.3.3-1 (Continued)
O$
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 4n W
luINIMUM NUMBER APPLICABLE 8
OPERABLE CRANNELS OPERATIONAL
[j TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEN CONDITIONS ACTION
.7 e.
RllR Pump Start - Time Delay Relay 1
1, 2, 3, 4*, 5*
31 y
(STR-2Al,2 and STR-2B1,2) f.
Bus Power Monitor #
1/ bus 1, 2, 3, 4*, 5*
32 (Ell-K106A,B) i 3.
IIPCI SYSTEM a.
Reactor Vessel Water Level - Low, Level 2 2
1, 2, 3 30 (H21-LT-NO31A,B,C,D)
R (B21-LTS-NO31A-2,B-2,C-2,D-2) b.
Drywell Pressure - Illgh 2
1, 2, 3 30 (Ell-PS-N0llA,B,C,D) c.
Condensate Storage Tank Level - Low 2**
1, 2, 3 33 (E41-LS-N002, E41-LS-N003)
-l d.
Suppression Chamber Water Level - liigh 2**
1, 2, 3 33 (E41-LSil-N015A,B) e.
Bus Power Monitori 1/ bus 1, 2, 3 32 (E41-K55 and E41-K56) 4.
ADS g
a.
Drywell Pressure - liigh, coincident with 2
1,2,3 30 g
(Ell-PS-N010A,B,C,D) h b.
Reactor Vessel Water Level - Low, Level 3 2
1, 2, 3 30 (B21-LT-NO3]A,B,C,D) o
( B 21-LTS-NO31 A-3, B-3,C-3, D-3)
E Bs
m TABLE 3.3.3-1 (Continued)
'1)
.b L;
EMERCENCY CORE C001.ING SYSTEM ACTUATION INSTRUMENTATION 5
Q MINIMUM NUMBER APPLICABLE OPERABLE CilANNELS OPERATIONAL TRIP FUNCTION AND INSTRilMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION N
c.
Reactor vessel uater Level - Low, Level 1 1
1,2,3 30 (B21-LT-N042A,B)
(B21-LTM-N042A-1,F-1) d.
ADS Timer 1
1, 2, 3 31 (B21-TDPU-KSA,B) e.
Core Spray Pump Discharge Pressure - Iligh (Permissive) 2 1,2,3 31 (E21-PS-N008A,B and E21-PS-N009A,B) f.
RilR (LPCI MODE) Pump Discharge Pressure - liigh (Permissive) 2/ pump 1, 2, 3 31 (El1-PS-N016A,B,C,D and El1-PS-N020A,B,C,D) w g.
Bus Power Monitor #
1/ bus 1, 2, 3 32 2
(t21-KlA,B) w APPLICABLE
}f TOTAL NO.
CilANNELS MINIMUM CilANNELS OPERATIONAL FUNC;rION\\L llNIT OF CIIANNELS TO TRIP OPERABLE CONDITIONS ACTION 5.
I.0SS OF POWER a.
4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4##,5##
34 i
Jhidervoltage (Loss of Voltage) b.
4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4##,5##
35
[i Ibidervoltage (Degraded Voltage)
~~Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.
N Provides signal to llPCI pump suction valves only.
- Alarm only.
y
l F.
w TABLE 3. 3. 3-2
~
N d
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS )
fi ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE G
G 1.
CORE SPR AY SYSTEM H
u a.
Reactor Vessel Water Level - Iow, Level 3
~> + 2.5 inches *
~> + 2.5 inches *
( H 21-LTS-NO 31 A-4, B-4, C-4, D-4) b.
Reactor Steam Dome Pressure - Low 410 + 15 psig 410 + 15 psig (B21-PTS-N021A-2,B-2,C-2,D-2) l c.
Drywell Pressure - liigh
< 2'psig
< 2 psig
( Ell-PS-N0l l A,B,C, D) d.
Time Delay-Relay 14 < t <~ 16 secs 14 < t ~~< 16 secs (E21-K16A,B)
~
l t'
e.
Bus Power Monitor NA NA (E21-KIA,B)
Y W
2.
LPCI MODE OF RilR SYSTEM a.
Drywell Pressure - liigh
< 2 psig
< 2 psig (Ell-PS-N0ll A,B,C,D) b.
Reactor Vessel Water Level - low, Level 3
-> + 2.5 inches *
~> + 2.5 inches *
(il21-LTS-NO31 A-4,B-4,C-4, D-4) c.
Reactor Vessel Shroud Level
> - 53 inches *
> - 53 inches *
(Il21-LT!!-NO36-1 and B21-LTM-NO37-1) d.
Reactor Steam Dome Pres 3ure - Low g
1.
RilR Pump Start and LCPL Valve l
((
Actuation 410 + 15 psig
~
l
- }
(1521-PTS-N021 A-2, B-2, C-2, D-2)'
~
410 + 15 psig l
l u
2.
Recirculation Pump Discharge Valve Actuation 310 1 15 psig 310 t 15 psig E
(B21-PTM-N021A-1,B-1,C-1,D-1) l E
M i
TABLE 3.3.3-2 (continued) en
- A d
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS n
H Q
ALLOWABLE TRIP FUNCTION AND INSTRUMErff NUMBER TRIP SETPOIPTT VALUE 9h e.
RllR Pump Start - Time Delay Relay 9<t< 11 seconds 9<t< 11 seconds H
(STR-2Al,2 and N
STR-2BI,2) f.
Bus Power Monitor NA NA (EIl-K106A,B)
}
3.
IIPCI SYSTEM a.
Reactor Vessel Water level - Low, Level 2
>+ 112 inches *
> + 112 inches *
(B21-LTS-NO31A-2,B-2,C-2,D-2) b.
Drywell Pressure - Illgh
< 2 psig
< 2 psig (E l l-PS-N0 l l A, B,C, D) c.
Condensate Storage Tank Icvel - Low
> 23 feet 4 inches
> 23 feet 4 inches l
y (E41-LS-N002; E41-LS-N003)
<l.
Suppression Chamber Water Icvel - Iligh
< -2 feet **
< -2 feet **
l (E41-LSil-N015A, B) e.
Ilus Power Monitor NA NA (E41-K55 and E41-K56) 4.
ADS a.
Drywell Pressure-liigh
< 2 psig
~< 2 psig (dll-PS-N010A,B,C,D) b.
Reactor Vessel Water Level - Low, Level 3
> + 2.5 inches *
> + 2.5 inches
- g (B21-LTS-NO31A-3,B-3,C-3,D-3) m3 c.
Reactor Vessel Water Level - Low, Level 1
> + 162.5 inches *
> + 162.5 inches
- h (B2l-LT!!-N042A-1,B-1) a" d.
AUS Timer l
g (B21-TDPU-KSA,B)
< 120 seconds
< 120 seconds k
l
TABLE 3.3.3-2 (Continued) h.
EMERGENCY CORE COOLING SYSTEti ACTUATION INSTRUMENTATION SETPOINTS a
E ALLOWABLE
-TRIP FUNCTION AND INSTRUt1ENT NUMBER TRIP SETPOINT VALUE
[j Core Spray Pump Discharge Pressure - liigh
> 100 psig
> 100 psig e.
y (E21-PS-N008A,B and E21-PS-N009A,B) n f.
RilR (LPCI MODE) 1; ump Discharge Pressure - liigh
> 100 psig
> 100 psig (El1-PS-N016A,B,C,D and El1-PS-NO20A,B,C,D) g.
Bus Power Monitor NA NA (il21 -KI A, B)
M 5.
LOSS OF POUER v
Y 4.16 kv Emergency Bus Undervoltage a.
4.16 kv Basis - 2940 t 161 volts 2940 t 315 volts a.
M (loss of Voltage)#
b.
120 v Basis - 84 t 4.6 volts 84 i 9 volts c.
< 10 sec. time delay
< 10 sec. time delay b.
4.16 kv Emergency Bus Undervoltage a.
4.16 kv Basis - 3727
- 9 volts 3727 t 21 volts (Degraded Voltage) b.
120 v Basis - 106.5
- 0.25 volts 106.5 t 0.60 volts c.
10 t 0.5 sec. time delay 10 t 1.0 sec. time delay i
'G m
i L
U
- This is an inverse time delay voltage relay. The voltages shown are the maximum that will not result
's in a trip.
Iower voltage conditions will result in decreased trip times.
6
- Vessel water levels refer to REFERENCE LEVEL ZERO.
- Suppression chamber water level zero is the torus centerline minus 1 inch.
co er
g TABLE 4.3.3-1 O
ol EMERGENCY 0)RE COOLING SYSTEM ACTUATION INSTRUMEffrATION SURVEILLANCE REQUIREMEffrS 4oM QlANNEL OPERATIONAL 8
OlANNEL FUNCTIONAL QlANNEL CONDITIONS IN WilIQI g
TRIP FUNCTIoli AND INSTDIMElfr NUMBER OlECK TEST CALIBRATION SURVEILLANCE REQUIRED Il
- 1. CORE SPRAY SYSTEM g
a.
Low, Level 3
( B 21-LT-NO31 A, B, C,D)
NA(a)
NA R(b) 1,2,3,4,5
( ll21-LT S-NO 31 A-4,Il-4, C-4, D-4)
D M
M 1,2,3,4,5 b.
Reactor Steam Docte Pressure - Low l
( 1121-PT-N021 A,11, C,D)
NA(*)
NA R( }
1,2,3,4,5
( li 21 -PT S-fl021 A-2, li-2, 0-2, D-2 )
D H
M 1,2,3,4,5 c.
Drywell Pressure - liigh NA M
Q
(, 2, 3
( E l l-PS-fl0l l A,li, C, D)
{
d.
Time Delay Relay NA R
R 1,2,3,4,5 u
d,
( E21-K16 A,II) l AJ e.
Bus Power Monitor NA R
NA 1,2,3,4,5 (E21-KIA,B)
- 2. I.PCI MODE OF RllR SYSTEM a.
Drywell Pressure - liigh NA M
Q 1, 2, 3 (El1-PS-NO1IA,B,C,D) 1 I
b.
i Low, Level 3
( li21-LT-NO31 A, B, C,D)
NA(")
NA R(b) 1, 2, 3, 4*, 5*
I
( ll21-LT S-NO 31 A-4, B-4, C-4, D-4)
D M
M 1, 2, 3, 4*, 5*
uo-c.
Reactor Vessel Shroud Level h
(1521-LT-NO36 and li21-LT-NO37)
NA(a)
NA R(b) 1, 2, 3, 4*, 5*
(li21-LTM-NO36-1 and B21-LTM-NO37-1) D M
M 1, 2, 3, 4*, 5*
n M
1 e,
TABLE 4.3.3-1 (Continued)
A-G is EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREffENTS N
CllANNEL OPERATIONAL CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICit g TRIP FutJCTIOff AND INSTRUMEllT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIkED 3
el.
Reactor Steam Dome Pressure - Low NA(a)
NA R(b) 1, 2, 3, 4*, 5*
H
( B 21-PT-tIO21 A, B, C, D) l 1.
RIIR Pump Start and LPCI Injection Valve Actuation D
M M
1, 2, 3, 4*,
5*
(B21-PTS-N021A-2,B-2,C-2,D-2) a 2.
Recirculation Loop Pump Discharge Valve Actuation D
M M
1, 2, 3, 4*,
5*
( B21-PTri-NO 21 A-1, B-1, C-1, D-1 )
e.
RilR Pump Start - Time Delay Relay NA R
R 1, 2, 3, 4*,
5*
(STR-2Al,2 and u;:
STR-2BI,2) y f.
Bus Power Monitor NA R
NA 1, 2, 3, 4*,
5*
gj (Ell-K106A,B)
- 3. IIPCI SYSTEM a.
Low, Invel 2 (B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (B21-LTS-NO31A-2,B-2,C-2,D-2)
D M
M 1, 2, 3 b.
Drywell Pressure - liigh NA M
Q 1, 2, 3 (E I l-PS-fl01 I A, B,C, D) h c.
Condensate Storage Tank Level - Low NA M
Q 1, 2, 3 (E41-LS-N002; E41-1.S-N00;)
y d.
Suppression Chamber Water Level - liigh NA M
Q 1, 2, 3 (E41-LSil-N015A, B) y e.
Bus Power Monitor NA R
NA 1, 2, 3
(E41-K55 and E41-K56)
M
'\\
,3 CD
i TABLE 4.3.3-1 (Continued) m E
- f; ENZRGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS N
Q CilANNEL OPERATIONAL CIIANNEL FUNCTIONAL CllANNEL CONDITIONS IN WilICll-TRIP FUNCTION AND INSTRUt!ENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED g
4 i
H
- 4. ADS tu a.
Drywell Pressure - liigh flA H
Q 1, 2, 3 (EIl-PS-N010A,B,C,D) b.
Reactor Vessel IJacer Level -
Low, Level 3 (B21-LT-NO31A,B C,D)
NA(8)
NA R ID) 1, 2, 3 (li21-LTS-NO 31 A-3, B-3, C-3, D-3)
D M
M 1, 2, 3 c.
Reactor Vessel llater Level -
Low, Level I (B21-LT-N042A,B)
NA(a)
NA R(b) 1, 2, 3 u
(1521-LTM-N04 2 A-1, B-1)
D M
M 1, 2, 3 o
u d.
ADS TLaer NA R
R 1, 2, 3 g
(B21-TOPU-KSA,B) e.
Core Spray Pump Discharge Pressure - liigli NA N
Q 1, 2, 3 (E21-PS-N008A,B and E21-PS-N009A,B) f.
RilR (LPCI MODE) Pump Discharge Pressure - liigh NA M
0 1, 2, 3 (Ell-PS-N016A,B,C,D and E11-PS-t!020A,B,C,D) fi g.
Bus Power Monitor NA R
NA 1, 2, 3 g
(B21-KIA,B)
R E
N t
M l
y TABLE 4.3.3-1 (Continued)
Ey Ef tERGENCY CORE C00LIfC SYSTEM ACrilATION INSTRUMENTATION SURVEILLANCE REQUIREMEffrS M
- M OIANNEL' OPERATIONAL QlANNEL
$UNCTIONAL QlANNEL CONDITIONS IN Wi!IQI I
Q TRIP FUNCTIO!I AND IflSERla!Efft PRIMBER QIECK TEST CALIBRATION SURVEILLANCE REQUIRED i
U l
5.
IDSS OF POWER n
I i
a.
4.16 kv Emergency Bus NA NA R
1, 2, 3, 4*, 5*
Undervoltage (Loss of Voltage) b.
4.16 kv Emergency Bus S
M R
1, 2, 3, 4*, 5*
Undervoltage (Degraded Voltage)
M i
s~
Y M
(a) The transmitter channel check is satisfied by the trip unit channel check.
A separate transmitter check is not required.
(b) Transmitters are exempted f rom the monthly channel calibration.
t 8
B' an O
TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.
OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 1.
Reactor Vessel Pressure 2
l (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.
(B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-N037; and B21-LTM-NO37-1) 3.
Suppression Chamber Water Level 2
l (CAC-LT-2601; CAC-LY-2601-1; CAC-LI-2601-3)
(CAC-LT-2602; CAC-LR-2602) l 4.
Suppression Chamber Water Temperature 2
l (CAC-TR-1258-14, 21; and C91-P602) 5.
Suppression Chamber Atmosphere Temperature 2
(CAC-TR-1258-17 thru 20; and C91-P602) 6.
Drywell Pressure 2
l (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.
Drywell Temperature 2
l (CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.
Drywell Radiation 2
l (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 2
l (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) 10.
Drywell Hydrogen 2
(CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) 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)
BRUNSWICK - UNIT 2 3/4 3-51 A=endment No.gg 8
i
)
y TABLE 4.3.5.3-1
^
<=
1 y
POST-ACCIDEtTT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
M
,1 M
CilANNEL CilANNEL i
5 INSTRUt1EFTP AND INSTRIIMENT NUMBER CHECK CALIBRATION Cy 1.
Reactor Vessel Pressure M
R l
(B21-PI-ROO4A,B; C32-LPR-R608; and C32-PT-N005A,B) n 2.
Reactor Vessel IJater Level M
R (B21-LITS-NO26A,B; E21-LR-R615; B21-LI-R604A,B; B21-1.T-NO37; and B21-LTil-NO37-1) 3.
Suppression Chamber tJater Level M
R (CAC-LT-2601; CAC-LY-2601-1; CAC-LI-2601-3; CAC-LT-2602; CAC-LR-2602) l 4.
Suppression Chamber IJater Temperature M
R l
(CAC-TR-1258-14, 21; and C91-P602)
R 5.
Suppression Chamber Atmosphere Temperature M
R (CAC-TR-1258-17 thru 20; and C91-P602) 6.
Drywell Pressure M
R l
N (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.
Drywell Temperature M
R
, 'p ' l-
'[
(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.
Drywell Radiation M
!L' 7 /
l (CAC-AR-1260; CAC-AQll-1260-1,2,3; CAC-AR-1261; CAC-AQil-1261-1,2,3;
r.
i CaC-AR-12611 and CAC-AQil-1262-1,2,3) j#
r
(-
s 9.
DrywLil Oxygen Concentration
/!
r,_
M R
~~
l, e
(CAC-AT72 259-2; CAC-AR-1259; CAC-AT-12b3-2; and CAC-KR-1263)
, Cv-f.
a i
'^ji IPs Drywell ifpt'rogen 'Concent ration M
Rfi^
l p
(CAC-AT-1254-1; CAC-AR-(259; CAC-AT-1263-1; and CAC-AR-1263) k, ' 11 3Infety Reliel ' Valve Position Indication
(.
,z D
a.
Primary ;- Sadic (B21-FY-415n't! ra 4167) f-
'M R
(
- b. -Secondary - Temp. ( B21-TR-R614,. poi n ts' l-l i)
}
T M
R N
o e- *?
?,;
.i ;
m Y
,5, W
A 4 /,
s_
fu A
1 l
I i
3:.
c co V
J f
>p
,a
,/
- s.,
't \\.
U
'yu f; ', w,,,s,_.
5
'a g-e.
e j
i
, t..
. ~.
. 97 y.
l_. ~ ~
t.
- )
/
- ))}
l'~
,/,
afs 5
j
,,. b, ~,
TABLE 3.3.6.1-1
~
i 9
./ i j
~
y 2:
ATWS RECIRCIILATION PUMP TRIP SYSTEM INSTRtiMENTATION /,,
f' t
y
~
I MINIMUM NUMBER OPERABLE TRIP 1
Q TRIP FUNCTION AND INSTRUMENT NUMBER SYSTEMS PER OPERATING PUNP Fj i
1.
1 l
Low, Level 2 I
(B21-LT-N024A-2,B-2 and B21-LT-N025A-2,B-2)
I (B21-LTM-N024A-2,B-2 and B21-LTM-N025A-2,B-2) 2.
Reactor Vessel Pressure - liigh I
(B21-PS-N045A,B,C,D) u>
N b
b G2 i
i.
t i
,I 1
1 5.Y U
?
i m
n i
r1
'A
.O M
N CO
TABLE 3.3.6.1-2 E!
Q ATWS RECIRCULATION PUHP TRIP SYSTEM INSTRUMENTATION SETPOIN'IS E
RW TRIP ALLOWABLE 8
TRIP FUNCTION AND INSTRUMENT NUMBER S ETPOINT VALUE 5
[j 1.
Reactor vessel, Water Level -
> + 112 inches *
> + 112 inches
- Low, Level 2 g
(B21-LTM-N024 A-2,B-2; B21-LTM-N025 A-2,B-2) 2.
Reactor Vessel Pressure - High
<l120 psig
<1120 psig
( 821-PS -N045 A, B, C, D)
M n
Y 1
h S.
u
{
)
l
$5 i
5$
- Vessel water levels refer to REFERENCE LEVEt, ZERO.
w TABLE 4.3.6.1-1 I
N y
AWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS M
O CilANNEL CllANNEL FUNCTIONAL CilANNEL TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION O
M 1.
Low, Level 2 (B21-LT-N024A-2,B-2 and NA(a)
NA R(b)
B21-LT-N025A-2,B-2)
(B21-LTM-N024A-2,B-2 and D
M M
i 821-LTtt-N025A-2,B-2) 2.
Reactor Vessel Pressure - Iligh NA M
R (B21-PS-N045A, B, C, D)
M
=
g, Y
m in l
1 N
D R
m D
i l
N (a) The transmitter channel check is satisfied by the trip unit channel m
check. A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
- ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At 1 cast once per 18 months, during shutdown, by verifying that either:
1.
The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the battery is subjected to a battery service test, or 2.
The battery capacity is adequate to supply a dummy load of the following profile while maintaining the battery terminal voltage 2; 105 volts.
a)
During the initial 60 seconds of the test:
1)
Battery 2A-1 2;1056.42 amperes, 2)
Battery 2A-2 JL 1211.90 amperes, 3)
Battery 2B-1 2;1089.06 amperes, and 4)
Battery 2B-2 jt 1042.67 amperes.
b)
During the remainder of the first 30 minutes of the test:
1)
Battery 2A-1 JL 243.19 amperes, 2)
Battery 2A-2 > 159.10 amperes, 3)
Battery 2B-1 l' 176.79 amperes, and 4)
Eattery 2B-2 ][ 216.67 amperes.
c)
During the remainder of the 3-hour test:
1)
Battery 2A-1 2;89.52 amperes, 2)
Battery 2A-2 JL 50.34 amperes, 3)
Battery 2B-1 2,53.39 amperes, 4)
Battery 2B-2 jL 75.09 amperes.
3.
At the completion of either of the above terts, the battery charger shall be demonstrated capable of recharging its battery at a rate of at least 200 amperes while supplying normal D.C.
loads. The battery shall be charged to at least 95% capacity in
__ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e.
At least once per 60 months during shutdown by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.
This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test and after normal equalizer charge.
BRUNSWICK - UNIT 2 3/4 8-10 Amendment No. 78
.