ML20054J992
| ML20054J992 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/12/1982 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20054J949 | List:
|
| References | |
| 05-1-02-III-3, 5-1-2-III-3, NUDOCS 8206300277 | |
| Download: ML20054J992 (4) | |
Text
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PLANT OPERATIONS MANUAL Volume 05 05-1-02-III-3 Section 02 Revision:
11 Eate: 6-12-82 i
0FF-NORMAL EVENT PROCEDURE DECREASE IN RECIRCULATION SYSTEM FLOW RATE SAFETY RELATED 4
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List of Effective Pages:
Page:
1-3 List of TCN's Inc orpo ra t ed :
Revision TCN No.
10 None 11 None 8206300277 820625 PDR ADOCK 05000416 p
., GRAND GULF NUCLEAR STATION OFF-NORHML EVENT PROCEDURE
Title:
Dacrease in ik). :
05-1-02-III-3 Ravision:
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1 Recirculation System Flow Rate 1.0 PURPOSE / DISCUSSION 1.1 The purpose of this procedure is to provide the operator with instructions in the event an unexpected decrease in reactor coolant system flow rate occurs from one of the following:
1.1.1 Trip of one or both recirculation pumps.
1.1.2 Rapid closure of one or both recirculation Loop Flow Control Valves.
1.1.3 Shaft seizure or break on one of the recirculation pumps.
1.2 This procedure may interface with 'the Emergency Plan, the Emergency procedures or other ONEP's.
1.3 The rapid closure of single loop Flow Control Valve affects the reactor in nearly the same manner as the trip of a single recirculation pump.
Since this event is within the ability of the reactor to recover, a scram is not expected for either event.
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Rapid closure of both loop Flow Control Valves or a' trip of both recirculation pumps from 100% power will result in a rapid decrease in core flow and increase in water level, causing a turbine trip and
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r; reactor scram. Likewise, a single recirculation pump shaft seizure or break will also.cause a very rapid reduction in flow due to the hydraulic resistance.of the impeller, also resulting in a high level turbine trip
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2.0 SYMPTOMS 2.1 Rapid decrease in recirculation loop flow.
2.2-Rapid increase in reactor water level, possibly with resultant REACTOR c
WATER LEVEL HIGH alarm.
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2.3 Rapid decrease in reactor power.
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2.4 Rapid decrease in generator output.
2.5 MASTER CONT OTPT SIG ABNORMAL alarm.
2.6 FLUX CONT OTPT SIG ABNORMAL alarm.
2.7 RECIRC PMP A(B) OVERLD/ TRIP alarm.
2.8 RECIRC FCV A(B) HYD EQUIP INOP alarm.
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e CPAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
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Title:
Decrease in No.:
05-1-02-III-3 Revision:
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-2 Recirculation System Flow Rate t
i 3.0 AUTOMATIC ACTIONS 3.1 Rapid closure of a single loop FCV, or trip of a single Recirculation Pump.
3.1.1 Rapid decrease in generator output.
3.1.2 Increase in Reactor Water Level but not reaching the high level scram (Run Mode).
I 3.2 Rapid closure of both loop FCV's, trip of both recire pumps, shaft seizure or break of a single recirculation pump.
3.2.1 Probable high water level turbine trip, t
3.2.2 Probable high water level reactor scram (Run Mode).
3.2.3 Probaole high water level RFPT trip.
3.2.4 Rapid decrease in generator output.
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3.2.5 Possible trip of recirculation pump tb slow speed.
4.0 IMMEDIATE OPERATOR ACTIONS
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4.1 If a Reactor Scram does not occur:
4.1.1 If no recirculation loops are operating, place the reactor mode switch in SHUTDOWN and carry out the provisions on ONEP 05-1-02-I-1, Reactor Scram.
4.1.2 If both recirculation loops are still operating, transfer the FCV 's to LOOP MANUAL and reduce flow and drive Rods to establish less than 50% reactor power.
Balance loop flows to within 10% at less than 70% core; flow.
4.1.3 If one recirculation pump is stopped, close RECIRC PMP A(B) DISCH
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VLV B33-F067A(B) in the affected loop.
Place the FCV in the minimum position in the affected loop.
Reduce flow on the running pump to less than 75%.
4.2 REACTOR SCRAM OCCURS:
4.2.1 Refer t'o Reactor Scram ONEP 05-1-02-1-1.
4.2.2 Establish normal reactor water level using RCIC or HPCS.
Should level fall below +10" enter EP-1, Level Control concurrently with this procedure.
pRAND GULF NUCLEAR STATION OFF-NORMAL EVEhT PROCEDURE
Title:
Decrease in No.:
05-1-02-III-3 Revision:
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3 Recirculation System Flow Rate l
5.0 SUBSEQUENT ACTIONS 5.1 Restore the RFPT in accordance with SOI 04-1-01-N21-1.
Return RCIC and HPCS to standby after restoring the RFPT.
5.2 Reopen RECIRC PMP A(B) DISCH VLV B33-F067A(B) after 5 min.
to maintain differential temperature between the loops and the reactor within limits.
5.3 Determine and correct the cause of the decrease in Recirculation System flow rate.
Observe the requirements of Technical Specifications Section 3.4.1.1, 3.4.1.3, 3.4.1.4.
5.4 Initiate monitoring of reactor steam dome, bottom head drain, and recire. loop temperatures as delin'eated in SOI 04-1-01-B33-1.
5.5 Restart the recirculation pump and/or. establish normal recire flow in available recirculation loops in accordance with SOI 04-1-01-B33-1.
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