ML20054K019
| ML20054K019 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/19/1982 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20054J949 | List:
|
| References | |
| 05-1-02-V-8, 5-1-2-V-8, NUDOCS 8206300304 | |
| Download: ML20054K019 (4) | |
Text
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- j PLANT OPERATIONS MANUAL i
Volume 05 05-1-02-V-8 t
I Section 02 Revision:
10 Date: 3-19-82 i
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OFF NORMAL EVENT PROCEDURE I
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SAFETY RELATED i
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Nuclear Plant Quality Superintendent Tect(nical Review r
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O'peratiots Superintendent Approved:
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List of Effective Pages:
Page:
Revision:
1-3 10 8206300304 820625 PDR ADOCK 05000416 P
- l CRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE i.
l Title loss of Condenser lNo.:
05-1-02-V-8 lRevis ion:
10 lPage:
1 l
l Vacuum l
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l 1.0 PURPOSE / DISCUSSION I
1.1 The purpose of this procedure is to provide ins t ruct ions in the event of decreasing, or loss, of condenser vacuum.
1.2 This procedure may interface with the Emergency Plan, ONEP's,101's, and SOI's.
1.3 A loss of condenser vacuum may be either gradual or rapid loss. The loss j
of circulating water flow or the steam ejectors, would cause vaccum to decrease rapidly, while a blockage in the off gas system or low seal steam pressure would result in a slower or gradual loss of vacuum.
If the conditions cannot be corrected quickly, a turbine trip and reactor scram will result and eventually, an MSIV closure, loss of feedwater pumps, and loss of bypass capability.
HPCS, RCIC, and the pressure relief valves will be required to maintain reactor water level and pressure.
2.0 SYMPTOMS i
2.1 Possible Circulating Water Pump or pumps tripped.
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2.2 Failed Seal Steam regulator / improper seal steam pressure.
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2.3 Decreasing condenser vacuum.
2.4 Increasing condensate temperature out of the condenser hotwell.
2.5 Increasing Turbine exhaust hood temperature.
' 2.6 One or more of the following alarms are received in the Control Room:
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l 2.6.1 CIRC WTR PMP A(B) 2.6.2 SJAE A(B) STM SPLY PRESS LO 2:c
.2.6.3 SJAE A(B) STM SPLY FLO LO;
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2.6.4 TURB SS PRESS LO 2.6.5 ABSORBER TRAIN A(B) Flow
'gh-Low 2.6.6 CNDSR VAC BRKR LVL LO 2.6.7 H.P. CNDSR Shell PRESS HI
o o
GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l
Title:
Loss of Condenser lNo.:
05-1-02-V-8 l Revis ion:
10 lPage:
2 l l
Vacuum l
l l
l 2.6.8 L.P. CNDSR Shell PRESS HI 2.6.9 L.P. CNDSR Shell PRESS HI 2.7 Increasing Of f Gas System Flow, due to condenser inleakage.
3.0 AUTOMATIC ACTION 3.1 Turbine Trip 21" Hg i
3.2 Reactor Feedwater Pump Trip 16" Hg 3.3 Main Steam Bypass Valves closure 12" Hg 3.4 MSIV Closure 9" Hg 3.5 Possible Reactor Scram 4.0 IMMEDIATE OPERATOR ACTION 4.1 Verify that the automatic actions occurred on complete loss of vacuum.
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4.2 If a scram has occurred as the result of the Turbine trip refer to Reactor Scram ONEP 05-1-02-1-1, and the Turbine and Generator trips ONEP 4.3 If a scram did not occur, reduce Reactor power rapidly.
~ {#r; 05-1-02-I-2.
If the MSIV's closed, refer to EP-1, Level Control.
4.4 Attempt to start or restart a Circulating Water Pump if a trip occurred, r
4.5 If the operating SJAE malfunctioned, place the standby SJAE and recombiner train in service.
L 4.6 If a component La the Off Gas Train is obstructing flow, shift to the standby component.
4.7 Check the Main Condenser Vacuum breaker indication on panel lH13-P870 and verify they are closed or close them if open.
4.8 If seal steam pressure was lost, check the seal steam supply has shifted over to auxiliary steam by checking SN12-F068 and N33-F075 open on panel SH13-P854.
5.0 SUBSEQUENT OPERATOR ACTION 5.1 Continue to reduce reactor power as necessary to stabilize condenser vacuum, if Reactor scram did not occur.
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6 GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE -
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Title:
Loss of Condenser (No.:
05-1-02-V-8 (Revis ion:
10 lPage: 3 l
l Vacuum l
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l 1
5.2 If loss of vacuum is due to the excessive condenser inleakage, ' attempt to 3
l locate and isolate the source of the inleakage.
f 5.3 Check and verify that deicing and bypassing valves for the cooling tower are closed.
5.4 Add seal water to the vacuum breakers if seal water was lost.
5.5 If vacuum cannot be maintained, initiate a controlled shutdown of the Reactor and Turbine in accordance with 10I 03-1-01-3, Plant Shutdown.
5.6 Cont inue Reactor Cooldown with SOI 04-1-01-E12-1, Steam condensing Mode j
RCIC and shutdown cooling as required.
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