ML20126H678
| ML20126H678 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/28/1992 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20126H655 | List: |
| References | |
| NUDOCS 9301050282 | |
| Download: ML20126H678 (8) | |
Text
_
ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS _1 AND 2 NRC DOCKET NOS. 50 325 & 50-324 OPERATING LICENSE NOS, DPR.71 & DPR 62-REQUEST FOR LICENSE AMENDMENTS.
STANDBY LIQUID CONTROL SYSTEM TECHNICAL SPECIFICATION PAGES UNIT 1 4
9301050282-921228-
~PDR' ADOCK 05000324
'. P.:
. REACTIVITY CONTROL SYSTEMS 3/4.1.5 STANDBY LIOUID CONTROL SYSTEM i
LIMITINO CONDITION FOR OPERATION 31.5 The standby liquid control system shall be OPERABLE with:
a.
An OPERABLE flow path f rom the storage tank to the reactor core, containing two pumps and two inline explosive injection valves, b.
The contained solution volume-concentration within the limits of Figure 3.1. 5-1, and c.
The solution temperature above the limit of Figure 3.1. 5-2.
/1f tCONDITIONS 1, 2{ and 5.)
APPLICABIL1rY:
OPERATIONAL ACTION:
r0PEMT/eh'Al a.
Inf 00NDITION 1 or 2:
1.
With one pump and/or one explosive valve inoperable, restore the inoperable pump and/or explosive valve to OPERABLE status within 7 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 />.
2.
With the standby liquid control system inoperable, restore the C-system to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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.
In CONDITION 5:
1.
With one pump and/or one explosive valve inoperable, restore the fq[
inoperable pump and/or explosive valve to OPERABLE status within 31 days or suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
2.
With the standby liquid control system inoperable, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.
3.
The provisions of Specification 3.0.3 are not applicable.
BRUNSWICK - UNIT 1 3/4 1-18 RETYPED TECH. SPECS.
Updated Thru. Amend. 53
l'
" TABLE 3.3.2-1 (Continued) lE' LE.
ISOLAT70N ACTUATION INSTRUMENTATION EL R
'5 VALVE CROUPS HINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION' SICNAL(a)
PER TRIP SYSTEM (b)(c) CONDITION _
. ACTION E.E
~2.
. SECONDARY CONTAINHENT ISOLATION a.
Reactor Building Exhaust Radiation - High.
(1) 1-1, 2, 3, 5, and* 23 6
1 1,2,3 20
'b.
'Deywell Pressure'- High (1) 2 1, 2, 3 23 2, 6 2
1, 2,' 3 20 c.
Reactor. Vessel. Water Level -
Low,' Level 2 (1) 2 1,2,3 23 3
2 1, 2, 3 24 w
R.
I 3.
REACTOR WATER' CLEANUP SYSTEM ISOLATION a;
a Flow - High-3 1
1,2,3 24 b.
Area Temperature'- High 3
2
' 1, 2, 3 24 c.
Area Ventilation a Temperature - High 3'
2 1,2,3 24 l.
b d.
SLCS' Initiation 3'II)
NA 1,2(,3}
24 L Reactor Vessel' Water Level -
e.
Low,-Level 2 3
2 1,2,3
'24.
E.
f.
- A Flow - High L Time Delay Relay NA 1
1, 2, 3 24-l 5
E g.
- o i....
_.:.. -.. ~..
w.
I g
TABLE 4.3.2-1 (Continued)
.E;
- g
' ISOLATION-ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS vi
' Ii CHANNEL OPERATIONAL
- Q' CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E
2.
' SECONDARY CONTAINHENT ISOLATION
~1 '
a.:
Reactor Building' Exhaust U)
'l Radiation - High D
H R
1,2,3,5, and b.
Drywell Pressure High gg
" Transmitter: '
NA(a)
NA R
1, 2,. 3
- Trip - Logic D
H H
1, 2, 3 c.
Reacto Vessel Water Level -
Low, Level 2 Transmitter:
NA(a)
NA R(b)
I, 2, 3
-Trip Logic: ^
D H
H 1, 2, 3 3.
REACTOR WATER CLEANUP SYSTEH' ISOLATION
. w a.-
A. Flow
-High D
H R
1, 2, 3 4'
t oo -
b.-
Area Temperature - High..
NA H
R 1, 2, 3
~
c.
Area Ventilation A Temperature - High
- NA H
R
' 1, 2, 3
-l
'd.-
- SLCS Initiation
- NA R
'NA 1,.2 3
c.
Low,' Level 2-Transmitter:
NA(a).
NA R(b).
1, 2, 3 Trip Logic:-
D H
H 1, 2, 3
^
f.
- A Flow -'High - Time Delay' Relay NA H
R 1, 2, 3
.{-
l a
R
_ g; g.
~
p I 1 V
Y
'+%
- m. m.m.2-.m---
A
i ENCLOSURE 6' BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2--
. NRC DOCKET NOS. 50 325 & 50-324 OPERATING LICENSE NOS. DPR 71 & DPR 62-REQUEST FOR LICENSE AMENDMENTS-STANDBY LlOUID CONTROL SYSTEM-l TECHNICAL SPECIFICATION PAGES-UNIT 2 v
E Y
\\ ~~
i
[.
l-
, ?,. ~
~.
.1 REACTIVITY CONTROL SYSTEMS 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.1.5 The standby liquid control system shall be OPERABLE with:
a.
An OPERABLE flow path f rom the storage tank to the reactor core, containing two pumps and two inline explosive -injection valves, b.
The contained solution volume-concentration within the limits of Figure 3.1. 5-1, and I
c.
The solution temperature above the limit of Figure 3 1 5-2.
APPLICABILITY CONDITIONS 1, and 5.
^
ACTION:
OPERATIONhL a.
In CONDITION 1 or 2:
1.
With one pump and/or one explosive valve -inoperable, restore the inoperable pump and/or explosive valve to. 0PERABLE status within 7 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 />.
2.
With the standby liquid control system inoperable, restore the-system to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 />.
'h.
In CONDITION 5 -
1.
With one pump and/or one explosive' valve inoperable, restore-the inoperable pump and/or explosive valve to OPERABLE status s
within 31 days or suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
2.
With the standby liquid contro1T system inoperable, suspend all-operations involving CORE ALTERATIONS or - positive reactivity changes and fully insert all-insertable control rods within one hour.
3.
The provisions of Specification 3.0.3 are not applicable.
& f$-fl85-Df BR'JNSWICK - UNIT 2 3/4 1-18 RETYPED TECH.. SPECS..
Updated Thru. Amend. 78;
- ~~ Y ~
,,.. + - -
m:
v.-:
v: -- -~ ;
-..a
1
?f TABLE 7.3.2-1 (Continued) s"o E
ISOLATION ACTUATION INSTRUMENTATION E!
. n" VALVE CROUPS HINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL SIGNAL (a)
PER TRIP SYSTEM (5)(c) CONDITION ACTION E
TRIP FUNCTION 54 u
2.
SECONDARY CONTAINHENT ISOLATION a.
Reactor Building Exhaust (1) 1 1, 2, 3, 5, 23 l
and
- Radiation - High 6
1 1, 2, 3 20 l
(1) 2 1, 2, 3 23 b.
Drywell Pressure - High 2, 6 2
1, 2, 3 20 Reactor Vessel Water Level -
(1) 2 1, 2, 3 23 3
2 1,2,3 24 c.
Low, Level 2 un
~
s~
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION 1
'$t u.
.L 3
1 1, 2, 3 24 a.
A Flow - High 3
2 1, 2, 3 24 b.
Area Temperature - High Area Ventilation A Temperature - High 3
2 1, 2, 3.
24 l
c.
3 (f)
NA 1, 2, 3 24 d.
SLCS Initiati Reactor Vessel Water Level -
3 2
1, 2, 3 24 e.
Low, Level 2 a
f.
A Flow - liigh - Time Delay Relay NA I
1, 2, 3 24 l
F S.
-R R
E, e
q
I.
i!t TABLE 4.3.2-1 (Continued) su E
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
]c CllANNEL OPERATIONAL l
n f
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH l
'CEECK TEST CALIBRATION SURVEILLANCE REQUIRED E
TRIP FUNCTION w-2.
SECONDAt<Y CONTAINHENT ISOLATION 1
a.
Reactor Building Exhaust II}
l Radiation - fligh D
H R
1,2,3,5, and b.
Drywell Pressure - High R(b) 1, 2, 3 NA(a)
NA Transmitter:
D M
M 1, 2, 3 Trip Logic:
c.
Low, Level 2 R(b) 1, 2, 3 NA(a)
NA u
E Transmitter:
D M
M 1, 2. 3 Trip Logic:
t
' "1 u
0 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
5 Flow - High D
H R
1, 2, 3 b.
Area Temperature - liigh NA H
R 1, 2, 3 l
Area Ventilation a lemperature - !!igh NA M
R 1, 2, 3 if>
c.
d.
SLCS Initiation HA R
NA 1, 2 c.
8
' Low, Level 2 R(b) 1, 2, 3 NA(a)
NA Transmitter:
D M
M 1, 2, 3
' Trip Logic:
3
- e f.
A Flow - High - Time' Delay Relay NA H
R 1, 2, 3 l
?
i_.
_ - _ _ ~...,