ML20127P326
| ML20127P326 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/25/1993 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20127P302 | List: |
| References | |
| TAC-M85018, TAC-M85019, NUDOCS 9302010249 | |
| Download: ML20127P326 (7) | |
Text
e-ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50 324 OPERATING LICENSE NOS. DPR 71 & DPR-62 ECCS ACTUATION INSTRUMENTATION OPERABILITY (NRC TAC NOS. M85018 AND M85019)
TECHNICAL SPECIFICATION PAGES - UNIT 1 i
L f
9302010249 930125-
'v PDR.-ADOCK 05000324--
P-PDR-
TABLE 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMitM NUMBER APPLICABLE-OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP SYSTEM" CONDITIONS
. ACTION j.
- 1. CORE SPRAY SYSTEM a.
Reactor Vessel Water Level - Low, Level 3 2'
I,2,3,4,5 30 b.
Reactor Steam' Dome Pressure - Low (Injection Permissive) 2" I,2,3,4,5 31 c.
Drywell Pressure - High 2
1,2,3 30 d.
Time Delay Relay 1
1,2,3,4,5 31 e.
Bus Power Monitor" 1/ bus 1,2,3,4,5 32 2.' LOW PRESSURE COOLANT INJECTION' MODE OF RHR SYSTEM a.
Drywell Pressure - High 2
1,2,3 30 b.
Reactor Vessel Water level - Low, levelL 3 2
1, 2, 3, 4", 5" 30-
~
c.
Reactor Vessel Shroud Level (Drywell Spray Permissive) 1 1, 2, 3, 4", 5" 31 11.
Reactor Steam Dome Pressure - Low-(Injection Permissive) 1.-
RHR Pump Start.and LPCI-Injection Valve Actuation 2"
1, 2, 3, 4", 5" 31-2.
Recirculation Loop Pump Discharge-Valve Actuation 2"
1, 2, 3, 4", 5" 31 e.
RHR ' Pump' Start - LTime Delay Relay -
1 1, 2, 3,14", 5" 31-f.
'BusLPower Monitor"'
1/ bus 1, 2, 3, 4", 5" 32 BRUNSWICK:- U741T 1, 3/4 3.34 Amendment No.
~
I, l TABLE 3.3'.3 1 (Continued)-
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION NOTES (a) A channel may be placed in :- inoperable status for up to two hours-for required surveillance without placing the trip system in the tripped-condition, provided at least one OPERABLE channel in the same trip system-is monitoring the affected parameter.
(b) Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.
(c) Provides signal to HPCI pump suction valves only.
(d) Alarm only.
(e) Required wnen ESF equipment is required to be'0PERABLE.
(f) On a one-time basis, prior to start-up from the outage that began on April-21, 1992, the Minimum Number OPERABLE Channels per Trip Systan for one reactor steam dome pressure - low (injection permissive) trip function may be reduced, for no longer than 7 days, from two (2) channels to one -
(1) channel without declaring the associated ECCS inoperable in accordance with ACTION 31. This will be _one on one occasion for Unjt I and two occasions for Unit 2.
During these periods, the following actions-shallL be implemented:
(1)
The-inoperable channel shall be placed in the condition that will.
satisfy the logic for allowing injection by the associated ECCS with the-' reactor steam dome pressure below 410 psig i 15 psig.
(2)
Both channels in the other trip system shall be maintained OPERABLE.
~
(3)
The reactor vessel head vent shall be maintained in the open-position.
f
{.
BRUNSWICK?- UNIT:1 3/4 3-38.
' Amendment No.
w c.
- b.
ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND'2 -
NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR 71 & DPR-62 ECCS ACTUATION INSTRUMENTAT!ON OPERABILITY (NRC TAC NOS. M85018 AND M85019)
TECHNICAL SPECIFICATION PAGES - UNIT 2 P
+
k k
s 4
1
..~
TABLE 3.3.3-1 ENERGENCY CORE COOLING SYSTEM ACTUATION INSTRLHENTATION MINIMUM NUMBER APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP SYSTEM" CONDITIONS ACTION l_
- l. CORE 1 PRAY SYSTEM a.
Reactor Vessel Water Level'- Low, Level 3 2
1,2,3,4,5 30 b.
Reactor Steam Dome Pressure - Low (Injection Permissive) 2" 1,2,3,4,5 31 c.
Drywell Pressure - High 2
1, 2, 3 30 d.
Time Delay-Relay 1
1,2,3,4,S 31 e.
Bus Power Monitor" 1/ bus 1,2,3,4,5 32
Drywell Pressure -- High 2
1,2,3 30-b.
Reactor Vessel Water-Level - Low,: Level'3 2
1, 2, 3, 4", 5" 30 c.
Reactor Vessel Shroud Level (Drywell Spray Permissive)-
1 1, 2, 3, 4", 5" 31 d.
Reactor Steam Dome Pressure - Low (Injection Permissive) 1.
RHR Pump Start and LPCI Injection Valve Actuation 2"
1, 2, 3, 4", 5" 31 8
2.
Recirculation Lcop Pump Discharge Valve Actuation 2
1, 2, 3, A", 5" 31-
-e.
RHR Pump Start - Time Delay Relay 1
1, 2, 3,.4", 5" 31-f.
Bus Power Monitor"'
1/ bus 1, 2, 3, 4", 5"'
32 BRUNSWICK - UNIT 2 3/4 3-34 Amendment No.
I.
TABLE 3.3.3-1'(Continued)
^
DiERGENCY CORE._ COOLING SYSTEM ACTUATION INSTRUMENTATION NOTES (a) A channel may be placed in an inoperable status for up to two hours for required surveillance without placing the trip system in the tripped condition, provided at least one OPERABLE channel in the same trip system
.is monitoring the affected parameter.
(b) Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.
(c) Provides signal to HPCI pump suction valves only.
(d) Alarm only.
(e) Required when ESF equipment is required to be OPiRABLE.
(f) On a one-time basis, prior to start-up from the outage that began on April 21,1992, the Minimum Number OPERABLE Channels per Trip System for one reactor steam dome pressure - low (injection permissive) trip function may be reduced, for no longer than-7-days, from two (2) channels to one-(1) channel without declaring the associated ECCS inoperable 'in accordance with ACTION 31. This will be done on one occasion for Unit 1 and two occasions for Unit 2.
During these periods, the following: actions shall be implemented:
(1)
The inoperable channel shall be placed in the condition that will satisfy the logic for allowing injection by the associated ECCS with the reactor steam dome pressure below 410 psig 15 psig.
(2)
Both channels in the other trip system shall be maintained OPERABLE.
(3)
The reactor vessel _ head vent-shall be maintained in the open position.
-BRUNSWICK - UNIT 2 3/4 3-38 Amendment No.
.