ML20079R652
| ML20079R652 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/20/1983 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20079R646 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8306240149 | |
| Download: ML20079R652 (44) | |
Text
- _ _ _ _ _ _ _ _ _ - _ _.
8306240149 F30620 PDR ADOCK C5000325 P
PDR E
E TABLE 2.2.1-1 un M
REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS g
ALLOWABLE f
FIINCTIONAL UNIT AND INSTRUMENT NUMBER TRIP SETPOINT VALUE S.-
H Intermediate Range Monitor, Neutron Flux - High(I) of full scale
< 120 divisions of full scale
< 120 divisions e
1.
( C51 -IRM-K601 A,B,C,D, E,F,G,il) 2.
Average Power Range Monitor
( CS I-APRM-Cll. A, B,C,D,E, F)
Neutron Flux - liigh,15%(2)
< 15% of RATED THERMAL POWER
< 15% of RATED a.
l THERMAL POWER b.
Flow-Biased Neutron Flux - High(3)(4)
< (0.66 W + 54%)
< (0.66 W + 54%)
w Fixed Neutron Flux - liigh(4)
< 120% of RATED TilERMAL POWER 1 120% of RATED S-c.
THERMAL POWER 3.
Reactor Vessel Steam Dome Pressure - Iligh
< 1045 psig
< 1045 psig
( B21-PTil-N 02 3A-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) i 5.
liain Steam Line Isolation Valve - Closure (5)
- }0% closed
< 10% closed
( B21 -F02 2A, B,C,D ;
B21-F02 8A, B, C,D)
Ei 6.
Ifain Steam Line Radiation - 111gh I 3 x full power background
< 3.5 x full power l g g
(D 12-R M-K60 3A, B, C, D) hackground 7
Q 1 u ft 7.
Drywell Pressure - liigh
< 2 psig
< 2 psig g
( C71 -PTil-N002 A-1, B-1, 0- 1, D-1) g r,
8.
Scram Discharge Volume Water Level - liigh
< 109 gallons
< 109 gallons 8.
( Cl 1 -LSil-N013A, B,C, D)
H (Cl 1-L Sit-4 516A, B,C,D) l 3
w
E TABLE 2.2.1-1 (Continued)
E h
REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS R
ALLOWABLE FUNCTIONAL UNIT AND INSTRUMENT NUMBER TRIP SETPOINT VALUES U
9.
Turbine Stop Valve - Closure (6)
< 10% closed
< 10% closed r
(EHC-SVOS-lX,2X,3X,4X) 10.
Turbine Control Valve Fast gsure, Control Oil Pressure - Iow
> 500 psig
> 500 psig (EllC-PSL-1756,1757,1758,1759)
'i' u,
h li E
9 r'
R 9
4 n
M
~
R.
t' W
~
5
to g
TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEH INSTRilllENTATION R
I APPLICABLE MINDtJH NUMBER g
OPERATIONAL OPERABLE CHANNELS t
FUNCTIONAL UNIT AND INSTRilHENT NUHRER CONDITIONS PER TRIP SYSTEM (a)
ACTION l
- 7. Drywell Pressure - High 1, 2 *)
2 6
I
( C71 -P T-N002A, B,C, D)
(C71-PTri-N002 A-1, B-1, C-1, D-1)
- 8. Scram Discharge Voltune Water level -
If)'
High 1, 2, S 2
5 (Cl 1 -LSil-N013A, B,C,D)
(Cl 1-LSit-4 516A, B,C,D) l R
- 9. Turbine Stop Valve - Closure 1(g) 4 8
(EliC-SVO S-1 X,2 X,3 X,4 X)
Y 10, Turbine Control Valve Fast Closure, I8) 2 8
Control Oil Pressure - Low I
(EllC-PS L-17 56,17 57,1758,1759)
- 11. Reactor Mode Switch in Shutdown Position 1,2,3,4,5 1
9 (C71 A-51)
- 12. Manual Scram 1, 2, 3,'4, 5
1 10 y
( C71 -A-S 3A, B)
Q F
R 9
om z
8.
t W
1 s
5
,g TABLE.3.3.1-2 (Continued)
REACTOR PROTECTION SYSTEN RESPONSE TIMES
.R RESPONSE TIME FUNCTIONAL IINIT AND INSTRUMENT NUMBER
( Second s) g t
rm
!H 7.
Drywell Pressure - High NA
( C71 -PT-N00 2A,B, C, D)
(C71-PTIF H002 A-1, B-1, C-1,D-1) 8.
Scram Discharge Volume Water Level - High NA (Cl 1 -LSit-N013A,B,C,D)
(Cl 1-L Sil-4 516A,B,C,D) l 9.
Turbine Stop Valve - Closure 1 0.06 (EllC-SVO S-1 X,2 X,3 X,4 X)
R
- 10. Turbine Control Valve Fast Closure, 1 0.08 Control Oil Pressure - Low Y
(EllC-PSL-1756,17 57,17 58,17 59)
- 11. Reactor Mode Switch in Shutdown Position NA (C71A-SI)
- 12. Manual Scram NA
( C7 i A-S3A, H) i p
- Neutron detectors are exempt f rom response time testing.
Response time shall be measured from
.letector output or f rom the input of the first electronic component in the channel.
Q b
I es 1 CL 4
=
rt M
rt O
t
$3w
' tw TABLE 4.3.1-1 (Continued) s REACTOR PROTECTION SYSTEM INSTRUMENTATION S11RVEILLANCE REQUIREMENTS g
CHANNEL OPERATIONAL E
FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS JN IAIICR U
AND IllSTRUMEllT NilitBER CHEN TEST CALIBRATION (a)
SURVEILLANCE REQllIRED e
R(h) g
- 5. Main Steam Line Isolation Valve -
NA H
Closure (B21-F022A,B,C,D and B21-1T)2 8A,B,C,D)
- 6. Main Steam Line Radiation - liigh S
M(I)
R(3 )
1, 2 (D 12-Rtt-K60 3A,B,C,D)
- 7. Drywell Pressure - liigh II)
( C71-PT-N002A,B,C,0)
NA(k)
NA R
1, 2 w)
( C71 -PT!!-N002 A-1, B-1,0- 1,D-1)
D H
H 1, 2
- 8. Scram Discharge Volume Water Level - liigh NA Q
R 1, 2, 5 (Cl 1 -LSit-N013A, B,C,D)
(Cl 1-L Sit-4 516A,B,C,D)
- 9. Turbine Stop Valve - Closure NA M
R(b) 1 (EllC-SVO S-I X,2 X,3 X,4 X)
- 10. Turbine Control Valve Fast Closure, Q)ntrol Oil Pressure -
g Low NA M
R 1
e+
(EllC-PS L-17 56,17 57,17 58,1759)
[
f,
- 11. Reactor tiode Switch in Shutdown NA R
NA 1,2,3,4,5 I*
S Posit ion (C71A-S1) g f
- O
- 12. ilanual Scram NA Q
NA 1,2,3,4,5 E-( C71 A-S 3A, B) t l
t
~
l 3
1
2?Y TABLE 3.3.2-1 z
I ISOLATION ACTUATION INSTRUMENTATION n
VALVE GROUPS MINIMUM NUMBER APPLICABLE i
OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION 1.
PRIMARY CONTAINHENT ISOLATION 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) 2.
Low, Level 2 1, 3 2
1,2,3 20 (B21-LT-N024A-1,B-1, and B21-UT-N025A-1,B-1) u SI (B21-LTM-N024 A-1, B-1 and y
B21-LTM-N025A-1,B-1)
U b.
Drywell Pressure - liigh 2,6,7 2
1,2,3 20 (C71-PT-N002A,B,C,D)
(C71-PTM-N002A-1,8-1,C-1,D-1) c.
Main St'eam Line 1.
Radiation - liigh (d) 1 2
1,2,3 21 (D 12-RM-K603A,B,C, D) 2 1
22 o'
2.
Pressure - Low I
(B21-PT-N015A,B,C,D)
(B21-PTM-N015A-1,B-1,C-1,D-1) g 3.
Flow - liigh 1
2/line 1
22 (B21-PDT-N006A,B,C,D; E'
y B21-PDT-N007A,B,C D; N
B21-PDT-NOO8A,B,C,D; g
821-PDT-N009A,B,C,D) g.
n
( H21-PDTM-N006 A-1, B-1, 0-1, D-1 ;
E. -
821-PDTM-N007A-1,B-1,C-1,D-1; t*
821-PDTM-N008A-1,B-1,C-1,D-1; y
B21-PDTM-N009A-1,B-1,C-1,D-1) g; i
w
l
!' to
~
TABLE 3.3.2-1 (Continued) j
'm j$
ISOLATION ACTUATION INSTRIMENTATION R
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CilANNELS-OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION H
- H PRIMARY CONTAINMENT ISOLATION (Continued) d.
Main Steam Line Tunnel Temperature - High 1
2(* )
1, 2, 3 21 l
(B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) iw e.
Condenser Vacuum - Iow 1
2 1, 2(f) 21 i)
(B21-PT-N056A,B,C,D)
(B21-PTM-N056A-1,B-1,C-1,D-1) u h
f.
Turbine Building Area Temperature - liigh 1
4(*)
1, 2, 3 21 (B21-TS-3225A,B,C,D; l
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; m
B21-TS-3232A,B,C,D) 2 E.I Oe i c.
e.
t !!
A P,
2n O-A R.
t u
3
N TABLE 3.3.2-1 (Continued)
O h
ISOLATION ACTUATION INSTRUMENTATION R
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL h
TRIP FUNCTION AND INSTRUMENT t! UMBER SIGNAL (a)
- PER TRIP SYSTEM (b)(c) CONDITION ACTION' 00 e
2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Exhaust Radiation - High 6
1 1, 2, 3, 5, and* 23 (012-RM-N010A,B) b.
Drywell Pressure - liigh 2,6,7 2
1,2,3 23 (C71-PT-N002A,B,C,D)
(C71-PTM-N002A-1,8-1,C-1 D-1) c.
Reactor Vessel Water Invel -
g Low, Level 2 1, 3 2
1,2,3 23 (B21-LT-NO24A-1,B-1 and B21-LT-NO25A-1,B-1) lyU (B21-LTM-N024A-1,B-1 and 821-LTM-N02SA-1,B-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - liigh 3
1 1,2,3 24 (G31-dFS-N603-1A,lB) i b.
Area Temperature - liigh 3
2 1,2,3 24 (G31-TS-N600A,B,C,D,E,F) c.
Area Ventilation A Temp. - High 3
2 1,2,3 24 Q
jk (G31-TS-N602A,B,C,D,E,F) d.
SLCS Initiation 3 (E)
NA 1, 2, 3 24 li' lh la (C41A-SI)
N
.n m
e.
Low, Level 2 1, 3 2
1,2,3 24 l
j' (B21-LT-N024 A-1,B-1 and
{
B21-LT-N025 A-!,B-1)
(B21-LTM-N024 A-1,B-1 and D
B21-LTM-N025 A-1,B-1) w
TABLE 3.3.2-1 (Continued) h ISOLATION ACTUATION INSTRUMENTATION R
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL f
TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION H
H 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 1.
HPCI Steam Line Flow - High 4,
1 1,2,3 25 (E41-PDT-N004; E41-PDT-N005)
(E41-PDTS-N004-2; E41-PDTS-N005-2)
{
2.
HPCI Steam Supply Pressure - Iow 4
2 1, 2, 3 25 (E41-PSL-NOO1 A,B,C, D) b 3.
HPCI Steam Line Tunnel Temperature - liigh 4
2 1,2,3 25 (E41-TS-3314; E41-TS-3315; j
E41-TS-3316; E41-TS-3317; E41-TS-3318; 1
E41-TS-3354; E41-TS-3488; E41-TS-3489) 4.
Bus Power Monitor NA(h) 1/ bus 1, 2, 3 26 g
if (E41-K55 and E41-K56) p l h 5.
HPC[ Turbine Exhaust y
g Diaphragm Pressure - High 4
2 1,2,3 25 g
(E41-PSil-N012A, B,C, D) re I
6.
IIPCI Steam Line Ambient g
{
l Temperature - liigh 4
1 1,2,3 25 (E51-TS-N603C,D)
~
N l'
5
88 TABLE 3.3.2-1 (Continued)
E ISOLATION ACTUATION INSTRUMENTATION
)O VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CilANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a)
PER TRIP SYSTEM (b)(c) CONDITION
.- ACTION
- E 7.
IIPCI Steam Line Area A Temp. -
High 4
1 1,2,3 25 l
- g (E51-dTS-N604C D) 8.
Emergency Area Cooler Temperature - High 4
1 1,2,3 25 (E41-TS-N602A,B) b.
Reactor Core Isolation Cooling Syntem Isolation 14 1.
RCIC Steam Line Flow - High 5
1 1,2,3 25 8'
(E51-PDT-N017; y
E51-PDT-N018) h (E51-PDTS-N017-2; E51-PDTS-N018-2) 2.
RCIC Steam Supply Pressure - Low 5
2 1,2,3 25 (E51-PS-N019A,B,C,D) 3.
RCIC Steam Line Tunnel Temperature
- liigh 5
2 1,2,3 25 (E51-TS-3319; E51-TS-3320; s'
E51-TS-3321; E51-TS-3322; Q
f(
E51-TS-3323; E
aD E51-TS-3355; e
'I E51-TS-3487) e n
E 4.
Bus Power Fbnitor NA (h) 1/ bus 1, 2, 3 26 3
g (E51-K42 and E51-K43) g.
n 8.
t W3w
TABLE 3.3.2-1 (Continued)
- h ISOLATION ACTUATION INSTRUMENTATION
- O VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL
{f TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION iH r=
5.
RCIC Turbine Exhaust Diaphragm Pressure - High 5
2 1, 2, 3 25 (E51-PS-NO12A,B,C,D) 6.
RCIC Steam Line Ambient Temp -
liigh 5
1 1,2,3 25 (E51-TS-N603A,B) l 7.
RCIC Steam Line Area A Temp - High 5 1
1, 2, 3 25 (E51-dTS-N604A,B) iM 8.
RCIC Equipment Room Ambient Temp - liigh 5
1 1,2,3 25 l
Y (E51-TS-N602A,B) 9.
RCIC Equipment Room A Temp - High 5 1
1,2,3 25 l
(E51-dTS-N601A,B) 5.
Sil0TDOWN COOLING SYSTEM ISOLATION a.
Reactor Vessel Water Imvel -
Low, Level 1 2,6,7,8 2
1,2,3 27 (B21-LT-N017A-1,B-1,C-1,D-1) i (B21-LTM-N017A-1,B-1,C-1,D-1)
{
~
b.
Reactor Steam Dome Pressure-7, 8 1
1, 2,_3 27 g
N High e
{
(B32-PS-N018A,B) g A-3 N
'if g-n R.
t W
s W
E TABLE 3.3.2-2 Si h'
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS R
ALLOWABLE N
TRIP FUNCTION AND INSTRUMENT NUMBER
' TRIP SETPOINT VALUE E
x 1.
PRIMARY CONTAINMENT ISOLATION a.
1.
Iow, Level 1
> + 162.5 inches *
> + 162.5 inches *
(B21-LTM-N017A-1,B-1,C-1,D-1) 2.
Iow, Level 2
> + 112 inches *
> + 112 inches *
(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) b.
Drywell Pressure - liigh
< 2 psig
< 2 psig
{
(C71-PTM-N002A-1,B-1,C-1,D-1) w c.
1.
Radiation - liigh
< 3 x fu11 power background
< 3.5 x full power (D12-RM-K603A,B,C,D) background
__ 825 psig
> 825 psig 2.
Pressure - Iow (B21-PTM-N015A-1,B-1,C-1,D-1) 3.
Flow - liigh
< 140% of rated flow
< 140% of rated flow (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; B21-PDTM-N009A-1,B-1,C-1,D-1) g N
r
'd "n
s a-n 2.
t
$3 w
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS R
ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE l
PRIMARY CONTAINMENT ISOLATION (Continued) d.
Main Steam Line Tunnel Temperature - liigh
< 200*F
< 200*F (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS N012A,B,C,D; B21-TS-N013A,'B,C.D) e.
Condenser Vacuum - Low
> 7 inches lig vacuum
> 7 inches lig vacuum (B21-PTM-N056A-1,B-1,C-1,D-1) y N
f.
Turbine Building Area Temp - liigh
< 200*F
< 200*F y
(B21-TS-3225A,B,C.D; g
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 g
Radiation - liigh
< 11 mr/hr
< 11 mr/hr h,
r*
j (D12-RM-NO10A,B)
=
~
o.
P, b.
Drywell Pressure - liigh
< 2 psig
< 2 psig 3
(C71-PT!!-N002A-1,B-1,C-1,D-1)
E 1
c.
a, y
Low, level 2
~> + 112 inches *
~> + 112 inches *.-
R (B21-LTM-N024A-1,B-1 and 8,
B21-LTM-N025A-1,B-1) rDR 5
~
+
4 a
TABLE 3.3.2-2 (Continued)
~
u3
.s 1
- t s.
s
, ISOLATION ACTUATION INSTRUMENTATION SE1 POINTS s
)
~ g ALLOWABLE
'~
TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE e
^
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION H
a.
A Flow - liigh
< 53 gal / min
< 53 gal / min (G31-dFS-N603-1A,lB) b.
Area Temperature - liigh
< 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 g
(C41A-SI) u e.
h Low, level 2
> + 112 inches *
> + 112 inches *
(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
liigh Pressure Coolant Ir.jection Syctem Isolation 1.
IIPCI Steam Line Flow - High
< 300% of rated flow
< 300% of rated flow un (E41-PDTS-N004-2; ee E41-PDTS-N005-2) g 2.
IIPCI Steam Supply Pressure - Low
~> 100 psig
-> 100 psig Q
E g
(E41-PSL-N001A,B,C,D)
I 3.
IIPCI Steam Line Tunnel Temperature - liigh
< 200*F
< 200*F e
"o (E41-TS-3314; y
1 E41-TS-3315;
,o E41-TS-3316; g
a E41-TS-3317; E'
E41-TS-3318; E41-TS-3354; q
w E41-TS-3488; h
1 E41-TS-3489) u
3-f' e >
9" g
l I.-
- /*V J
to -
[:
TABLE 3.3.2-2 (Continued)
T h
ISOLATION ACTUATION INSTRUMEtdATION SETPOINTS
,R ALLOWABLE 3
TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE
'E i
i HH 4.
Bus Power Monitor NA f
NA H
(E41-K55 and E41-K56)-
/
o 5.
HPCI Turbine Exhaust Diaphragm
/
' (E41-PSH-N012A,B,C ! D)
-< 10'psig
< 10 psig
/
Pressure - High i
~
,i 6.
11PCL Steam Line A.thient Temp - High
-< 200*F
./ ' '
(E51-TS-N603C D)r
/
-<-200*F
~
i 7.
HPCI Steam Line Area A Tump - High
< 50*F
. < 50*F
/,
(E51-dTS-N604C,D) u
- y (E41-TS-N602A,B)
~< 175"F'
-< 175'F D
8.
Emergency Area Cooler Temp - High l'
/
j $
b.
Reactor Core Isolation Cooling Systey Isolation ~ < 300% of rated flow
< 300% of rated flow 1.
RCIC Steam Line Flow - HigW l
(E51-PDTS-N017-2; E51-PDTS-N018-2) 2.
RCIC Steam Supply Pressure - Iow
> 50 psig
> 50 psig (E51-PS-N019A,B,C, D)
< 175*F y
3.
RCIC Steam Line Tunnel Temp - High
< 175*F (E51-TS-3319; j
Q E51--TS-3320 ;.
j p
p g
E51-TS-3321; c
3 E51-TS-3322; r'
h E51-TS-3323; 2
g E51-TS-3355; 2"
E51-TS-3487) 2 4.
Bus Power Monitor NA NA O
(E51-K42 and E51-K43) 8.
t C
W s
5
See CP&L icetcr dated 1/26/83 l
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water I4 vel -
1.
Iow, Invel 1
-<13 (B21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) 2.
Iow, 14 vel 2
-<l.0**
(B21-LT-N024A-1,B-1 and B21-LT-NO25A-1,B-1)
(B21-LTM-N024A-1,B-2 and B21-LTM-N025A-1,B-1) b.
. Drywell Pressure - High
<13 (C71-PT-N002A,B,C,D)
(C71-PTM-N002A-1,B-1,C-1 D-1) c.
<l.0**
1.
Radiation - High*
(D12-RM-K603A,B,C,D) 2.
Pressure - Iow
-<13 (B21-PT-N015A,B,C,D)
(B21-PTM-N015A-1,B-1,C-1,D-1) 3.
Plow - High
<0.5**
(B 21-PDT-N006A,B,C,D; B21-PDT-N007A,B,C,D; B21-PDT-N008A,B,C,D; B21-PDT-NOO9A,B,C,D)
(B21-PDTM-NOO6A-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; B21-PDTM-NOO9A-1,B-1,C-1,D-1) d.
' Main Steam Line Tunnel Temperature - High
<l3 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D;
+
B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) e.
Condenser Vacuum - Low
-<13 (B21-PT-N056A,B,C,D)
(B21-PTM-N056A-1,B-1,C-1,D-1)
BRUNSWICK-UNIT 1 3/4 3-22 Amendment No.
~
.~
See CP&L icetcr dated 1/26/83 TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
PRIMARY CONTAINMENT ISOLATION (Continued) 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 (C71-PT-N002A,B,C,D)
(C71-PTM-N002A-1,B-1,C-1,D-1) c.
Reactor Vessel Water Level - Iow, Level 2
<1.0**
~
(B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
(B2.1-LTM-N024A-1,B-1 and B21-LTM-NO25A-1,B-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High
<13 (G31-dFS-N603-1A,1B) b.
Area Temperature - High
-<13 (G31-TS-N600A,B,C,D,E,F) c.
Area Ventilation-Temperature AT - High
-<13 (G31-TS-N602A,B,C,D,E,F) d.
SLCS Initiation NA (C41A-SI) e.
Reactor Vessel Water Level - Iow, Level 2
-<1.0**
(B21-LT-N024 A-1,B-1 and B21-LT-N025 A-1,B-1)
(B21-LTM-N024 A-1,B-1 and 821-LTM-N025 A-1,B-1)
BRUNSWICK - UNIT 1 3/4 3-23 Amendment No.
See CP&L lctter d:ted 1/26/83 TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME I
TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
Righ Pressure Coolant Injection System Isolation 1.
HPCI Steam line Flow - Righ
-<13 (E41-PDT-N004; E41-PDT-N005)
(E41-PDTS-N004-2; E41-PDTS-N005-2) 2.
HPCI Steam Supply Pressure - Low
<13
~~
(E41-PSL-N001A,B,C,D) 3.
HPCI Steam Line Tunnel Temperature - Righ
<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-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 - Righ NA (E41-TS-602A,B) b.
Reactor Core Isolation Cooling System Isolation 1.
RCIC Steam Line Flow - High NA (E51-PDT-N017; E51-PDT-N018)
(E51-PDTS-N017-2; E51-PDTS-N018-2) 2.
RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D)
BRUNSWICK - (Ti3R57 R 9/4 T->24 Amendment No.
Sao CP&L latter dsted 1/26/83 TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
3.
RCIC Steam Line Tunnel Temp - High NA (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 (E51-K42 and E51-K43) 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 (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-N018A,B)
- Radiation monitors are exempt from response time testing.
Response time shall be measured from detector output or the input of the first electronic component in the channel.
- Isolation actuation instrumentation response time only.
- Isolation system instrumentacion 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 1 3/4 3-24a Amendment No.
ts TABLE 4.3.2-1 vs ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
- R i,
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATICN SURVEILLANCE. REQUIRED
'H H
1.
PRIMARY CONTAINMENT ISOLATION a.
1.
Iow, level 1 (B21-LT-N017A-1 B-1,C-1,D-1)
NA(a)
NA R(b) 1, 2, 3 (B21-LTM-N017A-1,B-1,C-1,D-1)
D M
M 1, 2, 3 2.
Iow, level 2 (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
NA(a)
NA R(b) 1, 2, 3 y
)N (B21-LTM-N024A-1,B-1 and y
B21-LTM-N025A-1,B-1)
D M
M 1, 2, 3
- u b.
Drywell Pressure - High (C71-PT-N002A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (C71-PTM-N002A-1,B-1,0-1,D-1)
D M
M 1, 2, 3 c.
Main Stearn Line 1.
Radiation - liigh D
W R
1, 2, 3 i
(D12-RM-K603A,B,C,D) i 2.
Pressure - Iow (B21-PT-N015A,B,C,D)
HA(a)
NA-R(b) g (B21-PTM-N015A-1,B-1,C-1,D-1)
D M
M 1
O g
3.
Flow - liigh g
(B21-PDT-N006A,B,C,D; NA(a)
NA R(D) 1 E
- g B21-PDT-N007A,B,C,D; y
- y B21-PDT-N008A,B,C D; g
B21-PDT-N009A,B,C,D) f, (B21-PDTM-N006A-1,B-1,C-1,D-1; D
M M
1 g
B21-PDTM-N007A-1,B-1,C-1,D-1;
{
j B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1)
C 2
w
'em P8 TABLE 4.3.2-1 (Continued) en ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CllANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED H
PRIMARY CONTAINMENT ISOLATION (Continued) l H
d.
Main Steam Line Tunnel Temperature - liigh NA M
R 1, 2, 3 (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 - Inw i
(B21-PT-N056A,B,C D)
NA(a)
NA R(b) 1, 2#
(B21-PTit-N056A-1,B-1,C-1,D-1)
D M
M 1, 2#
3 jy f.
Turbine Building Area Temp-liigh NA M
R 1, 2, 3 (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) i
,Ili 3e l t1 H
k lB n
n t:.
o D.
C.
W2*
r
TABLE 4.3.2-1 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS O
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CilANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED H
s 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Building Exhaust Radiation - liigh D
M R
1,2,3,5, and *
(D12-Ril-N010A,B) b.
Drywell Pressure - liigh (C71-PT-N002A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (C71-PT!1-N002A-1,B-1,C-1,D-1)
D M
M 1, 2, 3 c.
Reactor Vessel Water Imvel -
N Iow, Level 2 (B21-LT-N024 A-1,B-1 and Nga)
NA R(b) 1, 2, 3 g
B21-LT-N025 A-1,B-1)
(B21-LTM-N024 A-1,B-1 and D
M M
1, 2, 3 B21-LTM-N025 A-1,B-1) 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - liigh D
M R
1, 2, 3 (C31-dFS-N603-lA,1B) b.
Area Temperature - High NA M.
R 1, 2, 3 (G31-TS-N600A,B,C,D,E,F) g c.
Area Ventilation A Temp - liigh NA M
R 1, 2, 3 Q
k (G31-TS-N602A,B,C,D,E,F) p h
d.
SLCS Initiation NA R
NA 1, 2, 3 7
g (C41A-SI) e.
low, Level 2 S'
(B21-LT-N024 A-1,B-1 and NA(a)
NA R(b) 1, 2, 3
{
B21-LT-N025 A-1,B-1) w (B21-LTM-N024 A-1,B-1 and D
M M
1, 2, 3 D
B21-LTM-N025 A-1,B-1) 5
TABLE 4.3.2-1 (Continued)
(
as
- =
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
Q CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED g
4.
CORE STANDBY COOLING SYSTEMS ISOLATION a.
High Pressure Coolant Injection System Isolation 1.
IIPCI Steam Line Flow - High (E41-PDT-N004; NA(a)
NA R(b) 1, 2, 3 E41-PDT-N005)
(E41-PDTS-N004-2; D
M M
1, 2, 3 E41-PDTS-N005-2) 2.
IIPCI Steam Supply Pressure -
u3 Low NA M
R 1, 2, 3 (E41-PSL-N001 A, B,C, D) 3.
HPCI Steam Line Tunnel Temperature - High NA M
Q 1, 2, 3 (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354;
{
E41-TS-3388; E41-TS-3489) h k
4.
Bus Power Monitor NA R
NA 1, 2, 3 8.
(E41-K55 and E41-K56) 5 k
5.
IIPCI Turbine Exhaust g
Diaphragm Pressure - High NA M
Q 1, 2, 3 g
(E41-PSil-N012A,B,C, D) 2 6.
IIPCI Steam Line Ambient Temp - liigh NA M
R 1, 2, 3 t'
(E51-TS-N603C,D)
M s
5
TABLE 4.3.2-1 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS O
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CilANNEL CONDITIONS IN Wil1CH h
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED H
e 7.
IIPCI Steam Line Area A Temp - liigh NA M
R 1, 2, 3 (E51-dTS-N604C,D) 8.
Emergency Area Cooler Temp - liigh NA M
Q 1, 2, 3 (E41-TS-N602A,B) b.
Reactor Core Isolation Cooling System Isolation u
1.
RCIC Steam Line Flow - High 7
(E51-PDT-N017; NA(a)
NA R(D) 1, 2, 3 w
E51-PDT-N018)
U$
(E51-PDTS-N017-2; D
M M
1, 2, 3 (E51-PDTS-N018-2) 2.
RCIC Steam Supply Pressure - Low NA M
Q 1, 2, 3 (E51-PS-N019A,B,C,D) 3.
RCIC Steam Line Tunnel liigh Temperature NA M,
R 1, 2, 3 y
(E51-TS-3319; t
E51-TS-3320; E51-TS-3321; Q
k E51-TS-3322; p
- s E51-TS-3323; g
I E51-TS-3355; 2
E51-TS-3487) g n
z 4.
Bus Power Monitor NA R
NA 1, 2, 3 o.
(E51-K42 and E51-K43)
R 5.
RCIC Turbine Exhaust Diaphragm Pressure - liigh NA M
R 1, 2, 3 C
(E51-PS-N012A,B,C,D) s 5
TABLE 3.3.3-1 9
d EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM NUMBER APPLICABLE OPERABLE CilANMELS OPERATIONAL f
TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION 1.
CORE SPRAY SYSTEM a.
Reactor Vessel Water level - Iow, Imvel 3 2
1,2,3,4,5 30 (B21-LT-NO31A,B,C,D)
(B21-LTS-NO31A-4,B-4,C-4,D-4) b.
Reactor Steam Dome Pressure - low (Injection Permissive) 2 1,2,3,4,5 31 (B21-PT-N021A,B,C,D)
(B21-PTS-N021A-2,B-2,C-2,D-2) c.
Drywell Pressure - liigh 2
1,2,3 30 M
(El1-PT-N011A,B,C,D)
(Ell-PTS-N0llA-2,B-2,C-2,D-2) ta ts d.
Time Delay Relay 1
1, 2, 3, 4, 5 31 (E21-K16A,B) e.
Bus Power Monitor #
1/ bus 1,2,3,4,5 32 (E21-KlA.D) 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM l
a.
Drywell Pressure - liigh 2
1,2,3 30 (Ell-PT-N0llA,B,C.D) i, (Ell-PTM-N0llA-1,B-1,C-1,D-1) g b.
Reactor Vessel Water level - Iow, Level 3 2
1, 2, 3, 4*,
5*
30 g
f (B21-LT-NO31A,B,C,D) p b
(B21-LTS-NO31A-4,B-4,C-4,D-4) g a
c.
Reactor Vessel Shroud Level (Drywell Spray Permissive) 1 1, 2, 3, 4*, 5*
31 g
g (B21-LT-NO36 and B21-LT-NO37) et g
(B21-LTM-NO36-1 and B21-LTM-NO37-1) d.
Reactor Steam Dome Pressure - Iow (Injection Permissive) g (B21-PT-N021A,B,C,D)
(B21-PTM-N021A-1,B-1,C-1,D-1)
C (B21-PTS-NO21A-2,B-2,C-2,D-2) 1.
RilR Pump Start and LPCI Injection Valve Actuation 2
1, 2, 3, 4*,
5*
31 3"
2.
Recirculation loop Pump Discharge Valve Actuation 2
1, 2, 3, 4*, 5*
31
e TABLE 3.3.3-1 (Continued)
H EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION O
I MINIMUM NUMBER APPLICABLE OPERABLE CHANNELS OPERATIONAL g
y TRIP FUNCTION AND INSTRUMENi' NUMBER PER TRIP SYSTEM CONDITIONS
' ACTION l
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Continued) e.
RilR Pump Start - Time Delay. Relay 1
1, 2, 3, 4*,.5*
31 (STR-lAl,2 and STR-1BI,2) f.
Bus Power Monitor #
1/ bus 1, 2, 3, 4*,
5*
32 (Ell-K106A,B) 3.
HIGil PRESSURE COOLANT INJECTION SYSTEM l
{
y a.
Reactor Vessel Water level - low, level 2 2
1, 2, 3 30 g
(B21-LT-NO31A,B,C,D)
(B21-LTS-NO31A-2,B-2,C-2,D-2)
'b.
Drywell Pressure - liigh 2
1, 2, 3 30 ~
(El1-PT-N011A,B,C,D)
(Ell-PTS-N0llA-2,B-2,C-2,D-2) c.
Condensate Storage Tank level - low 2**
1, 2, 3 33 (E41-LS-N002, E41-LS-N003) d.
Suppression Chamber Water level - liigh 2**
1, 2, 3 33 e
(E41-LSil-N015A,B) e.
Bus Power Monitor #
1/ bus 1, 2, 3 32 Q
f (E41-K55 and E41-K56) 7 l
k 4.
AUTOMATIC DEPRESSURIZATION SYSTEM on a.
Drywell Pressure - liigh, coincident with 2
1, 2, 3 30 Z
(Ell-PT-N010A,B,C,D) e,,
(El1-PTM-N010A-1,B-1,C-1,D-1) b.
Reactor Vessel Water level - Low, level 3 2
1,2,3 30 (B21-LT-NO31A,B,C,D) s (B21-LTS-NO31A-3,B-3,C-3,D-3) 3 W
w.
88 TABLE 3.3.3-1 (Continued)
E un
]$
-EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM NUMBER APPLICABLE OPERABLE CilANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS
, ACTION M
- P AUTOMATIC DEPRESSURIZATION SYSTEM (Continued) l 1
c.
Reactor Vessel Water Level - Low,1 Level 1 1
1,2,3 30-(B21-LT-N042A,B)
(B21-LTM-N042A-1,B-1) d.
ADS Timer ft 1, 2, 3 31 (B21-TDPU-K5A,B) e.
Core Spray Pump Discharge Pressure - High (Permissive) 2 1, 2, 3 31 (E21-PS-N008A,B and E21-PS-N009A,B) 20 f.
RilR (LPCI MODE) Pump Discharge Pressure - High (Permissive) 2/ pump 1, 2, 3 31 y
(Ell-PS-N016A,B,C,D and g
Ell-PS-N020A,B,C,D) m g.
Bus Power Monitor #
1/ bus 1, 2, 3 32 (B21-KIA,B)
APPLICABLE TOTAL NO.
CHANNELS MINIMUM CilANNELS OPERATIONAL FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE CONDITIONS ACTION 5.
LOSS OF POWER
$'e a.
4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4##,5##
34 Q
k Undervoltage (Loss of El Voltage) g.
.g b.
4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4##,5##
{
35 Undervoltage (Degraded n
y Voltage) g.
n 8.
n Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.
t',
- Provides signal to llPCI pump suction valves only, g
- Alarm only.
O
em TABLE 3.3.3-2 g
h EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS R
ALLOWABLE I
TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE m
H 1.
CORE SPRAY SYSTEM e
Reactor Vessel Water Level - Iow, IAvel 3
> + 2.5 inches
- __> + 2.5 inches
- a.
(B21-LTS-NO31A-4,B-4,C-4,D-4) b.
Reactor Steam Dome Pressure - Iow 410 + 15 psig 410 + 15 psig (B21-PTS-N021A-2,B-2,C-2,D-2) c.
Drywell Pressure - liigh
-< 2 psig
< 2 psig (Ell-PTS-N0llA-2,B-2,C-2,D-2) d.
Time Delay-Relay 14 < t < 16 secs 14 < t < 16 secs (E21-K16A,B) u n
e.
Bus Power Monitor NA NA y
d, (E21-KIA,B)
+
2.
. LOW PRESSURE COOLANT INJECTION HODE OF RHR SYSTEM l
a.
Drywell Pressure - liigh
< 2 psig
< 2 psig (Ell-PTM-N0llA-1,B-1,C-1,D-1) b.
Reactor Vessel Water IAvel - Iow, Level 3
> + 2.5 inches *
> + 2.5 inches *
(B21-LTS-NO31A-4,B-4,C-4,D-4) c.
Reactor Vessel Shroud level 53 inchee*
> - 53 inches *
{
(B21-LTM-NO36-1 and B21-LTM-NO37-1)
O E,i d.
Reactor Steam Come Pressure - Iow p.
h 1.
RilR Pump Start and LCPI Valve p
y Actuation 410 + 15 psig 410 + 15 psig g
(B21-PTS-NO21A-2,B-2,C-2,D-2) m x
- ,o 2.
Recirculation Pump Discharge Valve g
Actuation 310 i 15 psig 310
- 15 psig a
l E
(B21-PT!!-N021A-1,B-1,C-1,D-1)
C W
s 3
TABLE 3.3.3-2 (Continued) i EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS n
ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE z
LOW PRESSURE C00LAfft INJECTION MODE OF RHR SYSTEM (Continued) e.
RilR Pump Start - Time Delay Relay 9<t< 11 seconds 9<t< 11 seconds (STR-1Al,2 and STR-1B1,2) f.
Bus Power Monitor NA NA (Ell-K106A,B) 3.
IIIGH PRESSURE COOLANT INJECTION SYSTEM
'a.
Reactor Vessel Water level - low, Imvel 2
> + 112 inches *
> + 112 inches
- h (821-LTS-NO31A-2,B-2,C-2,D-2) y b.
Drywell Pressure - liigh
< 2 psig
< 2 psig y
(E11-PTS-NO11A-2,B-2,C-2,D-2) c.
Condensate Storage Tank Level - Iow
> 23 feet 4 inches
> 23 feet 4 inches (E41-LS-N002; E41-LS-N003) d.
Suppression Chamber Water Level - liigh
< -2 feet **
< -2 feet **
(E41-LSil-N015A,B) e.
Bus Power Monitor NA NA (E41-K55 and E41-K56) 4.
AUTOMATIC DEPRESSURIZATION SYSTEM l
{
a.
Drywell Pressure-liigh
< 2 psig
< 2 psig g
(El1-PTM-N010A-1,B-1,C-1,D-1) p I
b.
Reactor Vessel Water Level - Iow,14 vel 3
> + 2.5 inches *
> + 2.5 inches
- y (B21-LTS-NO31A-3,B-3,C-3,D-3) g c.
Reactor Vessel Water Imvel - Iow, level 1
> + 162.5 inches *
> + 162.5 inches *
(B21-LTM-N042A-1,B-1) r, d.
ADS Timer 8,
_ 120 seconds
_ 120 seconds
( B 21-TDPU-K5A, B)
R 3
TABLE 3.3.3-2 (Continued) f EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS k
ALLOWABLE 5'
TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE E
N AUTOMATIC DEPRESSURIZATION SYSTEM (Continued) e.
Core Spray Pump Discharge Pressure - High
> 100 psig
> 100 psig (E21-PS-N008A,B and E21-PS-N009A, B) f.
RHR (LPCI MODE) Pump Discharge Pressure - High
> 100 psig
> 100 psig (Ell-PS-N016A,B,C,D and Ell-PS-N020A,B,C,D) g.
Bus Power Monitor NA NA lQ (B21-KIA,B) s~
ly 5.
LOSS OF POWER l
a.
4.16 kv Faergency Bus Undervoltage a.
4.16 kv Basis - 2940 t 161 volts 2940 i 315. volts (loss of Voltage)#
b.
120 v Basis - 84 i 4.6 volts 84 i 9 volts c.
< 10 sec. time delay
< 10 secs. time delay b.
4.16 kv Emergency Bus Undervoltage a.
4.16 kv Basis - 3727 i 9 volts 3727 i 21 volts (Degraded Voltage) b.
120 v Basis - 106.5 i 0.25 volts 106.5 i 0.60 volts c.
10 t 0.5 sec. time delay 10 t 1.0 sec. time delay
\\
e 9
!g
. :s
.I e,
r e
- fe e
y
- This is an inverse time delay voltage relay.
The voltagee shown are the maximum that will not result
,e in a trip.
Iower voltage conditions will result in decreased trip times, g
- Vessel water levels refer to REFERENCE LEVEL ZERO.
g
(
- Suppression chamber water level zero is the torus centerline minus 1 inch.
g N
t 8
TABLE 4.3.3-1 5"{
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL
. CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH E
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED M
- 1. CORE SPRAY SYSTEM s
a.
Iow, Level 3 (B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3,4,5 (B21-LTS-NO31 A-4, B-4,C-4,D-4)
D M
M 1,2,3,4,5 b.
Reactor Steam Dome Pressure - low
( B21-PT-N021 A, B,C,D)
NA(a)
NA R(b) 1,2,3,4,5 (B21-PTS-N021A-2,B-2,C-2,D-2)
D M
M 1,2,3,4,5 R
c.
Drywell Pressure - liigh (E l 1-PT-N011 A, B,C,D)
NA(a)
NA R(b) 1, 2, 3 y
(Ell-PTS-N0llA-2,B-2,C-2,D-2)
D M,
M 1, 2, 3 d.
Time Delay Relay
.NA R
R 1,2,3,4,5 (E21-Kl6A,B) e.
Bus Power Monitor NA R
NA 1,2,3,4,5 (E21-KIA,B)
- 2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.
Drywell Pressure - liigh ID)
(E l 1-PT-N011 A, B,C, D)
NA(*)
'{iA R
1, 2; 3 y
(Ell-PTM-N0llA-1,B-1,C-1,D-1)
D M
M 1, 2, 3 m
b.
h g
e Iow, Level 3
{
(B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3, 4*,
5*
y (B21-LTS-NO31A-4,B-4,C-4,D-4)
D M
M 1, 2, 3, 4*,
5*
g e
D
't Reactor Vessel Shroud level c.
CD) l',
2,.3, 4*,
5*
g l
(B21" LT-NO36 and B21-LT-NO37)
NA(a)
NA R
(B21-LTM-NO36-1 and B21-LTM-NO37-1)
D M
M 1, 2, 3, 4*,
5*
l I.
t I
W s
5 l
l
5 TABLE 4.3.3-1 (Continued) 5 h
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CilANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICil E
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED U
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Con.inued) l e
d.
Reactor Steam Dome Pressure - Inw NA(a)
NA R(b) 1, 2, 3, 4*,
5*
(B21-PT-N021A,B,C,D) 1.
RilR 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.
Recirculation loop Pump Discharde Valve Actuation D
M M
1, 2, 3, 4*,
5*
,t (B21-PTM-N021A-1,B-1,C-1,D-1)
- s.
lu e.
RilR Pump Start - Time Delay Relay NA R
R 1, 2, 3, 4*,
5*
!b (STR-1Al 2 and
]"
STR-1B1,2) l f '.
Bus Power Monitor NA R
NA 1, 2, 3, 4*,
5*
(Ell-K106A,B) j 3.111C11 PRESSURE COOLANT INJECTION SYSTEM
)
a.
l Iow, Level 2
)
1, 2, 3 (B21-LT-NO31A,B,C,D)
NA NA R
(B21-LTS-NO31A-2,B-2,C-2,D-2)
D M
M 1, 2, 3 O
,k b.
DrywelL Pressure - liigh lE (Ell-PT-N0llA,B,C,D)
NA(a)
NA R(b) 1, 2, 3 j "@
(El1-PTS-N011A-2,B-2,C-2,D-2)
D M
M 1, 2, 3 n
lN c.
Condensate Storage Tank level - low NA M
Q 1, 2, 3 g
iz (E41-LS-N002; E41-LS-N003) o, iO D
t l*
d.
Suppression Chamber Water level - liigh NA H
Q 1, 2, 3
{
( E41-LSil-N015A, B) e-*
e.
Bus Power Monitor NA R
NA 1, 2, 3 D
(E41-K55 and E41-K56)
R 3
J
j TABLE 4.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL
'8 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E
a.
Drywell Pressure - liigh (Ell-PT-N010A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (E11-PTM-N010A-1,B-1,C-1,D-1)
D M
M 1, 2, 3 b.
Iow, Level 3 i
(B21-LT-NO31A,B,C,D)
NA(a)
NA R(b) 1, 2, 3 (B21-LTS-NO31A-3,B-3,C-3,D-3)
D M
M 1, 2, 3
- R c.
1
- Iow, Level 1 1y (821-LT-N042A,B)
NA(a)
NA R(b) 1, 2, 3 (B21-LTM-N042A-1.B-1)
D M
M 1, 2, 3 d.
ADS Timer NA R
R 1, 2, 3 j
(B21-TDPU-KSA,B) l e.
Core Spray Pump Discharge Pressure - liigh NA M
Q 1, 2, 3 f
(E21-PS-N008A,B and E21-PS-N009A,B) un f.
RilR (LPC1 MODE) Pump Discharge Pressure - liigh NA M
Q 1, 2, 3 g
(Ell-PS-N016A,B,C,D and e,
y g
El1-PS-N020A,B,C,D)
H
- sg g.
Bus Power Monitor NA R
NA 1, 2, 3 f,
',y
( B21-KI A, II) en n
8.
t s
5
m TABLE 3.3.5.2-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION M
MINIMUN
'E READOUT CHANNELS i
FUNCTIONAL UNIT AND INSTRUNENT NUMBER LOCATION OPERABLE
- 1. Reactor Vessel Pressure RS P*
1 (C32-PI-3332 and C32-PT-3332)
- 2. Reactor Vessel Water Level RSF*
1 (B21-LI-3331, B21-LI-R604AX, B21-LT-3331, B21-LT-N026A, B21-LT-NO17D-3, and B21 -LSil-N017 D-3)
- 3. Suppression Chamber Water Level RSP*
I (CAC-LI-3342 and CAC-LT-3342) a
- 4. Suppression Chamber Water Temperature RSP*
1 u
I-(CAC-TR-778-7)
O3
- 5. Drywell Pressure RSP*
1 (CAC-PI-3341 and CAC-PT-3341)
- 6. Drywell Temperature RSP*
1 (CAC-TR-778-1,3,4)
I" '
- 7. Residual llent Removal Ikad Spray Flow RSP*
1 (Ell-FT-3339 and Ell-FI-3339) 0 l
llk
- 8. Residual lleat Removal System Flow RSP*
1
- o (Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338) r.
B-g
,0
1 l
E Discharge Differential Pressure (Ell-PDT-N002BX and Ell-PDI-3344)
S' n
8.
- Remote Shutdown Panel, Reactor Building 20' Elevation D
l ti 5
- us TABLE 4.3.5.2-1
~
'M REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
8 CHANNEL CHANNEL FUNCTIONAL UNIT AND INSTRUMENT NUMBER CHECK CALIBRATION e4
- 1. Reactor Vessel Pressure M
Q 3
(C32-PI-3332 and C32-PT-3332)
Q (B21-LI-3331, B21-LI-R604AX, B21-LT-3331, B21-LT-N026A, B21-N017D-3, and B21-LSil-N017D-3)
- 3. Suppression Chamber Water level M
R (CAC-LI-3342 and CAC-LT-3342)
,4
- 4. Suppression Chamber Water Temperature M
R
, i' (CAC-TR-778-7)
- 5. Drywell Pressure M
Q (CAC-PI-3341 and CAC-PT-3341)
- 6. Drywell Temperature M
R (CAC-TR-778-1,3,4)
- 7. Residual Heat Removal Head Spray Flow M
Q us' (Ell-FT-3339 and Ell-FI-3339) t
- 8. Residual Heat Removal System Flow M
Q l
g I
(Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338) p
- 9. Residual Heat Removal Service Water Discharge M
Q l
e N
E Differential Pressure (El1-PDT-N002BX and El1-PDI-3344)
I n
8.
t W3 w
'See CP&L 1sttcr deced 4/28/83 INSTRUMENTATION POST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.5.3 The post-accident monitoring instrumentation channels shown in Table 3.3.5.3-1 shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1 and 2.
l ACTION:
a.
With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3.5.3-1, either restore the inoperable chanrels to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
The provisions of Specification 3.0.4 are not applicabic.
SURVEILLANCE REQUIREMENTS 4.3.5.3 Each of the above required post-accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.3-1.
l BRUNSWICK - UNIT 1 3/4 3-50 Amendment No.
~See CP&L 1cetcr d:ted 4/28/83 TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.
0F OPERABLE INSTRU3ENT INSTRUMENT AND INSTRIMENT NINBER CHANNELS 1.
Reactor Vessel Pressure 2
(B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.
(B21-LITS-NO26A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1) 3.
Suppression Chamber Water Level 2
(CAC-LT-2601; CAC-LI-2601-1)
(CAC-LT-2602; CAC-LR-2602) 4.-
Suppression Chamber Water Temperature 2
(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
(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.
Drywell Temperature 2
(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.
Drywell Radiation 2
(CAC-AR-1260; CAC-AQH-1260--1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262; and CAC-AQH-1262-1, 2, 3) 2(*)
9.
Drywell Oxygen Concentration (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-AR-4409-41)
(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2; CAC-X-XY-4363-2; CAC-AR-4410-41)
BRUNSWICK - UNIT 1 3/4 3-51 Amendment No.
'See CP&L 1cttsr dcted 4/28/83 TABLE 3.3.5.3-1 (Continued)
POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.
0F OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 10.
Drywell Hydrogen Concentration Analyzer and Monitor 2(*)
(CAC-AT-4409-38; CAC-AI-4409-32; CAC-X-XY-4348-1; CAC-X-XY-4349-1; CAC-AR-4409-42)
(CAC-AT-4410-38; CAC-AI-4410-32; CAC-X-XY-4362-1; CAC-X-XY-4363-1; CAC-AR-4410-42) 11.
Drywell Ares Radiation Monitors 2
(D22-RM-4195; D22-RI-4195)
(D22-PM-4196; D22-RI-4196)
( 022-RM-4197; D22-RI-4197)
(D22-RM-4198; D22-RI-4198) 12.
Safety Relief Valve Position Indication:
1/ valve Primary - Sonic (B21-FY-4137 thru 4167) a.
b.
Secondary - Temp. (B21-TR-R614, points 1-11) 13.
Off-gas Stack Ventilation Monitor 1
(D12-RE-4982; D12-RE-4573; D12-RE-4574; D12-RM-805; D12-RR-4599; D12-RR-4600) 14.
Turbine Building Ventilation Monitor 1
(D12-RE-4561; D12-RE-4562; D12-RE-4563; D12-RR-4548)
(a)
An OPERABLE instrument channel shall consist of the AT instrument and l
either the AI instrument or the XY-XY-AR instruments.
l BRUNSWICK - UNIT 1 3/4 3-51a Amendment No.
l
TABLE 4.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS to CHANNEL CHANNEL
_ CHECK CALIBRATION
{ INSTRUMENT AND INSTRUMENT NUMBER n
M R
i 1.
Reactor Vessel Pressure (821-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B)
E.
2.
R r
( B21-LITS-N026 A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1)
M R
3.
Suppression Chamber Water Level (CAC-LT-2601; CAC-LI-2601-1; CAC-LT-2602; CAC-LR-2602)
H R
4.
Suppression Chamber Water Temperature (CAC-TR-1258-14, 21; and C91-P602)
M R
5.
Suppression Chamber Atmosphere Temperature (CAC-TR-1258-17 thru 20; and C91-P602) w s
M R
6.
Drywell Pressure Y
(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) so M
R 7.
Drywell Temperature (CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602)
M R
8.
Drywell Radiation (CAC-AR-1260; CAC-AQll-1260-1,2,3; CAC-AR-1261; CAC-AQll-1261-1,2,3; CAC-AR-1262; and CAC-AQ!!-1262-1,2,3)
M R
un' 9.
Drywell Oxygen Concentration (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-AR-4409-41) g (CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2; e
CAC-X-XY-4363-2; CAC-AR-4410-41) s.
8 10.
Drywell liydrogen Concentration Analyzer and Monitor M
R S-n.
e N
(CAC-AT-4409-38; CAC-Al-4409-32; CAC-X-XY-4348-1; CAC-X-XY-4349-1; CAC-AR-4409-42)
(CAC-AT-4410-38; CAC-Al-4410-32; CAC-X-XY-4362-1; k
z CAC-X-XY-4363-1; CAC-AR-4410-42) g, t
M A
w
TABLE 4.3.5.3-1 (Continued)_
POST-ACCIDENT MONITORING INSTRLMENTATION SIRVEILLANCE REQUIREMENTS a
E CilANNEL CHANNEL
" INSTRIMEfff AND INSTRlHErfr NIMBER
_CilECK CALIBRATION I
N 11.
Drywell Area Radiation Honitor M
R U
( D22-R!i-4195; D22-RI-4195)
(D22-RM-4196; D22-RI-4196)
( D22-RM-4197; D22-RI-4197)
(D22-RM-4198; D22-RI-4198) 12.
Safety Relief Valve Position Indication Primary - Sonic (B21-FY-4157 thru 4167)
H R
a.
b.
Secondary - Temp. (B21-TR-R614, points 1-11)
M R
13.
Of f-gas Stack Ventilation Monitor M
R
( D12-RE-4982; D12-RE-4573; D12-RE-4574; D12-RM-805; D12-RR-4599; D12-RR-4600)
~
c~
14.
Turbine Building ventilation Monitor M
R Y
( D12-RE-4561; D12-RE-4562; D12-RE-4563; D12-RR-4548)
M u
g 2
4 5
F E
E a
2
,0 n
,n 8.
t w
I
l
~See CF6L 1cetcr dated 4/28/83 I
REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE
~
LEAKAGE DETECTION SYSTEMS '
LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems.shall be-OPERABLE:
a.
The primary containment atmosphere particulate radioactivity l
monitoring system,*
b.
The primary containment sump flow integrating system, and The primary containment gaseous radicactivity monitoring system.*
c.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
l ACTION:
With only two of the above required leakage detection systems GPERABLE, operation may continue for up to 31 days provided grab samples of the containment atmosphere are obtained and analyzed at least.once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactive monitoring system is inoperable; otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE - REQUIREMEliTS 4.4.3.1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:
4 a.
Primary containment atmosphere particulate and gaseous radioactivity l
monitoring systems-performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at-least once per 18 months.
(CAC-AQH-1260-l 1,2,3; CAC-AQH-1262-1,2,3; CAC-AQH-1261-1,2,3) b.
Containment sump. flow integrating systems-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and of a CHANNEL CALIBRATION at least once per 18 months.
(G16-FQ-K603; G16-FYQ-K603; G16-FQ-K601; G16-FYQ-K601; G16-FY-K602; G16-FY-K600; G16-FT-N013; G16-FT-N003) 4
~
BRUNSWICK - UNIT 1 3/4 4-5 Amendment No.
~See CP&L 1cetcr d ted 4/28/83 REACTOR COOLANT SYSTEM i
OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 ' Reactor coolant system leakage shall be limited to:
a.
- b. _ 5 gpm UNIDENTIFIED LEkKAGE averaged over any 24-hour period.
25 gpm total leakage averaged over any 24-hour period.
c.
APPLICABILITT:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN a.
within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN vithin the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With any reactor coolent system leakage greatar than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate' to trithin the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be la at least HOT SHUTDOWN-withia the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3.2 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
a.
Monitoring the dryvell and equipment drain sump flow rates at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (G16-FQ-K603; G16-FYQ-K603; G16-FQ-K601; G16-FYQ-K601; G16-FY-K602; G16-FY-K600;G16-FT-N013; G16-FT-N003) b.
Monitoring the primary containment atmospheric particulate and gaseous radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(CAC-AQH-1260-1,2,3; CAC-AQH-1262-1,2,3 and CAC-AQH-1261-1,2,3).
BRUNSWICK - UNIT 1 3/4 4-6 Amendment No.
l
__ = _ _
~Sco CP&L icttcr d ted 4/28/83 CONTAINMENT SYSTEMS CAS ANALYZER SYSTEMS LIMITING CONDITION F0i OPERATION 3.6.6.4 Two independent gas analyzer systems for the drywell and suppression chamber shall be OPERABLE with each system consisting of an oxygen analyzer and a hydrogen analyzer.
APPLICABILITY:
OPERATIONAL CONDITION 1.
l ACTION:
With one oxygen and/or one hydrogen analyzer inoperable, restore at a.
least two oxygen and two hydrogen analyzers to OPERABLE status within 31 days or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The provisions of Specification 3.0.4 are not applicable.
b.
With no gas analyzer OPERABLE for oxygen and/or hydrogen, be in at i
least STARTUP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
)
SURVEILLANCE REQUIREMENTS 4.6.6.4 Each gas analyzer system (CAC-AT-4409, Division I and CAC-AT-4410, Division II) shall b*e demonstrated MPERABLE at least once per 92 days by performing a CHANNEL CALIBRATION using standard gas samples containing a nominal:
a.
Zero volume percent hydrogen, balance nitrogen.
l b.
Seven to ten volume percent hydrogen, balance nitrogen.
Twenty-five to thirty volume percent hydrogen, balance nitrogen.
c.
d.
Zero volume percent oxygen, balance nitrogen.
e.
Seven to ten volume percent oxygen, balance nitrogen.
f.
Twenty to twenty-five volume percent oxygen, balance nitrogen.
BRUNSWICK - UNIT 1 3/4 6-30 Amendment No.
=M tzf TABLE 3.7.5-1 (Continued)
SAFETY-RELATED HYDRAULIC SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE I
Condensate Drain System IB21-51SS103 Dryweli 29' I
No No
~
SISS105 29' I
No No SISS106 26' I
No No 50SS109 18' I
No No 50SSIi1 3l' I
No No 51SS113 28' I
No No SISSil5 23' I
No No SISSI18 24' TI No No Con t roil Rod Drive System u)
ICIl-16SSI1 Drywell 72' I
No No 16SS12 72' I
No No y
b liigh Pressure Coolant Injection System lE41-4SS44 Drywell 40' I
No No 4SS45 35' I
No No 4SS47 40' I
No No 4SS49 37' I
No No 4SS50 50' I
No No 4SS51 30' I
No No Ea' No No 60SS9 Reactor Building 4'
A S
6SS27
-5' A
No No 6SS28 l'
A No No Q
R 6SS30
-l' A
No No y
6SS32
-5' A
No No 6SS33 l'
A No No R
9 6SS35
-l' A
No No 2
6SS36
-5' A
No No R.
R W
3 w
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