ML20054K024
| ML20054K024 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/22/1982 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20054J949 | List:
|
| References | |
| 05-1-02-V-10, 5-1-2-V-10, NUDOCS 8206300310 | |
| Download: ML20054K024 (6) | |
Text
a PLANT OPERATIONS MANUAL volume 5 05-1-02-V-10 Se c t ion "02 Revis ion:
10 Date: 3-22-82 OFF-NORMAL EVENT PROCEDURE q
LOSS OF STANDBY SERVICE WATER LOOP A, B, OR C SAFETY RELATED
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Prepared:
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Reviewed:
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Nucl'ar Plant Quality Superintendent / Technical-Review e
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IJ Rev iewed :
fY h k Operapions Superintendent Approved:
Lzt1 A's s is t ant Plant a
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PSRC:
f 7 List of Ef fective Pages:
Page:
Revision:
1-5 10 V
't 8206300310 820625 PDR ADOCK 05000416 P
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- GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l Tit le :
Loss.of Standby Service lNo.:
05-1-02-V-10
( Revis ion: 10 iPage:
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l Water Loop A, B, or C l
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l 5
1 1.0 PURPOSE / DISCUSSION 1.1 The purpose of this procedure is to provide inst ruct ions for the operator during a loss of one of the SSW loops A, B or C.
This procedure assumes that the SSW loop that was lost was previously supplying all components capable of being supplied by the loop during either a LOCA or a loss of off-site power.
1.2 This procedure may interface with the Emergency Plan, Emergency 4
Procedures, or other Of f-Normal Event Procedures.
1.3 A failure of one loop of the SSW System interrups the cooling water supply to the following components:
1.3.1 Loop A a.
Drywell Purge Compressor Coolers A r#
b.
LPCS Room Coolers
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c.
Standby Diesel Generator 11 d.
RHR A Heat Exchanger
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e.
ESF Switchgear Room Coolers f.
Control Room A/C Unit A g.
RCIC Room Coolers h.
RHR Pump A Seal Cooler
- i. RHR "A" Room Cooler
E 1.3.2 Loop B a.
Drywell Purge Compressor Coolers B b.
Standby Diesel Generator 12 c.
RHR Pump C Seal Cooler d.
RilR "C" Room Cooler e.
Control Room A/C Unit B f.
RHR Pump B Seal Cooler l
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l
r CRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l Tit le : Loss of Standby Service lNo.:
05-1-02-V-10 l Rev is ion:
10 (Page: 2 l
l Water Loop A, B, or C l
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... g. ;RHR B Room Cooler
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j h.
ESF Switchgear Room Coolers i.
RHR B Heat Exchanger l
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Instrument and Service Air Compressors
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CCW Heat Exchangers
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Drywell coolers
- n.
Steam Tunnel Cooler Inside Containment These components will not be supplied by SSW if a LOCAf condition exists.
1.3.3 Loop C (HPCS Service Water) a.
HPCS Diesel Generator (h
b.
HPCS Room Cooler The SSW subsystems supply cooling water to components that are needed during a LOCA or a loss of of f-site power. Any two SSW loop will provide adequate cooling water to meet safe shutdown requirements. This procedure is used to ensure the remaining SSW loops are in operation and that the equipment supplied by the inoperat ive loop is shutdown to prevent its damage.
4 2.0 SYMPTOMS 2.1 Loss of Loop A i
2.1.1 STBY SVCE WATER PUMP A TRIP alarm 2.1.2 STBY SVCE WATER DIVISION I IN OPERATION alarm NOT actuated after a LOCA or Manual Initiation i
2.1.3 STBY SVCE RATER PUMP A DISCH PRESS LOW alarm 2.1.4 STBY SVCE WATER LOOP A LEAKAGE HIGH alarm 2.1.5 SSW Cooling Tower Fans A or B Trip alarm 2.1.6 SSW PMP A OVERLD alarm
GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l
l
Title:
Loss of Standby Service (No.:
05-1-02-V-10 (Revis ion:
10 iPage:
3 l
l Water Loop A, B, or C l
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2.2 Loss of Loop B 1
2.2.1 STBY SVCE WATER PUMP B TRIP alarm j
2.2.2 STBY SVCE WATER DIVISION 2 IN OPERATION alarm NOT actuated after a LOCA or Manual Initiation l
2.2.3 STBY SVCE WATER PUMP B DISCH PRESS LOW alarm 2.2.4 STBY SVCE WATER LOOP B LEAKAGE HIGH alarm 2.2.5 SSW Cooling Tower Fans Trip C or D alarm i
2.2.6 SSW Pmp B OVERLD alarm 2.3 Loss of Loop C
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2.3.1 HPCS STBY SVCE WATER SYTEM STATUS LIGHT lit f
2.3.2 HPCS SERVICE WATER LEAKAGE HIGH alarm 2
2.3.3 HPCS SERVICE WATER OUT OF SERVICE alarm NOTE Loss of Cooling Tower Fans makes the Standby Service Water System i
inoperable. However, in the event of a LOCA or a Loss of Of f-site i
Power, the Standby Service Water Loop with inoperable Cooling i
Tower Fans may be used unt il its heat trans fer capability is inadequate.
j 3.0 AUTOMATIC ACTIONS 3.1 Loop A i
3.1.1 None 3.2 Loop B 3.2.1 Instrument and Service Air Compressors trip if they are being cooled by SSW 3.3 Loop C 3.3.1 None
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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE i
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Title:
Loss of Standby Service INo.:
05-1-02-V-10 I Rev is ion:
10 iPage: 4 l
l Water Loop A, B, or C l
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l 1
4.0 IMMEDIATE OPERATOR ACTION i
4.1 Loss of Loop A 4.1.1 Ensure SSW Loops B and C are in operation, or start them per SOI 04-1-01-P41-1, if needed.
4.1.2 If Diesel Generator 11 has started due to a loss of offsite power, transfer all operation being performed with equipment supplied l
from the Division I ESF bus to equipment applied from the Division II ESF bus.
4.1.3 Shutdown Division I loads as necessary to prevent equipment damage.
Redundant loads associated with Division II may be started to compensate for loss of Division I loads.
NOTE
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RitR Pump A can operate safely without seal cooling unless in the j
Shutdown Cooling mode, where water temperature is high.
4.2 Loss of Loop B 1
4.2.1 Ensure SSW Loops A and C are in operat ion, or start them per SOL q'
04-1-01-P41-1, if needed.
4.2.2 If Diesel Generator 12 has started due to a. loss of.of fsite power, transfer all operation being performed with equipment supplied from the. Division II ESF bus to equipment supplied-from the 5
Division I ESF bus.
4.2.3 If a loss of offsite power has occurred, loss of SSW B will cause cooling to be lost to CCW (refer to ONEP 05-1-02-V-1, Loss of Component Cooling Water), the air compressors (refer to ONEP 0 5-1-02-V-9, Loss of Ins trument air), and the Drywell Coolers (eventual high drywell pressure, enter EP-3).
4.2.4 Shutdown Division II loads as necessary to prevent equipment damage.
Redundant loads associated with Division I may be started to compensate for loss of Division.II loads.
NOTE RilR pumps B and C can operate safely without seal cooling for Pump B operation in the Shutdown Cooling Mode, where water temperature is high.
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GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
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Irie1e: Loss of Standby Service lNo.:
05-1-02-V-10 l Rev is ion:
10 lPage:
5 l
l Water Loop A, B, or C 1
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l 4.3 Loss of Loop C --
4.3.1 Ensure SSW Loops A and B are in operation, or start then per SOI 04-1-01-P41-1, if needed.
5.0 SUBSEQUENT OPERATOR ACTION 5.1 Determine and correct the cause and return the loop to service if j
necessary.
5.2 Monitor the temperature of rooms which have lost cooling water to room coolers and contain operating equipment (HPCS Room, RCIC Room, RHR Rooms,
ESF Switchgear Rooms).
5.3 If it is determined that a Reactor Shutdown is required proceed to 101 03-1-01-3, Plant Shutdown.
5.4 Proceed to implement Emergency Plan, if directed by the Shif t Supe rvisor or Shif t, superintendent.
5.5 Observe Technical Specificat ion Sect ion 3/4.7.1 Standby Service Water System LCO.
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