ML20054K016
| ML20054K016 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/12/1982 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20054J949 | List:
|
| References | |
| 05-1-02-V-7, 5-1-2-V-7, NUDOCS 8206300302 | |
| Download: ML20054K016 (3) | |
Text
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ga PLANT OPERATIONS MANUAL Volume 05 05-1-02-V-7 Section 02 Revision:
11 Date: 6-12-82 OFF-NORMAL EVENT PROCEDUPE LOSS OF FEEDWATER FLOW SAFETY RELATED Prepared: --
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List of Effective Pages:
Page:
1-2 List of TCN's Incorporated:
Revision TCN No.
10 None 11 None 8206300302 820625 PDR ADOCK 05000416 P
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dGRAND' GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
Title:
Loss of Feedwater No.:
05-1-02-V-7 Revision:
11 Page:
1 Flow 1.0 PURPOSE / DISCUSSION 1.1 The purpose of this procedure is to provide instructions for the operator in the event of a partial or total Loss of Feedwater Flow.
1.2 This procedure may interface with the Emergency Plan and Emergency Procedures.
1.3 A Loss of Feedwater Flow results in a net decrease in coolant inventory available for core cooling.
This may be caused in startup by a failure of the Startup Level Control Valve or a Condensate Booster Pump, or a Reactor Feed Pump Trip.
In run, a partial Loss of Feedwater may be caused by a Heater Drain Pump, Condensate Booster Pump, or Reactor Feed Pump Trip. A total Loss of Feedwater may be caused by a trip of all running feed / condensate pumps.
If a total Loss of Feedwater is experienced, a Reactor Scram will occur and HPCS or RCIC will be utilized to restore aad maintain Reactor Water Level.
2.0 SYMPTOMS 2.1. Heater Drain Tank Level-Prettlems
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2.2 Condensate Pump Trip Alarms' 2.3 Condensate Booster Pump Trip Alarms
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2.4 Heater Drain Pump Trip Alarms 2.5 Reactor Feed Pump Trip Alarms 2.6 Reactor Water Level Low Alarms i.
2.7 Decreasing Feed Flow 2.8 Reactor Scram
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3.0 AUTOMATIC ACTIONS 3.1 A recire flow control valve runback will occur at +31.7" with'<2 RFPT's running.
3.2 Recirculation Pumps will shift to slow speed if feed flow is <35% for 15 seconds with the FCV at minimum.
3.3 A Reactor Scram at +11.4".
3.4 A Group III Isolation at +11.4".
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[J1RAN6 GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
Title:
Loss of Feedwater No.:
05-1-02-V-7 l Revision:
liflPage:
2 Flow l
s 3.5 Recirculation Pump Trip at -51" s
3.6 RPCS and RCIC initiate at -41.6".
3.7 Group VI, VII, VIII, X and Auxiliary Building Isolations a't -41,6" 4.0 IMMEDIATE OPERATOR ACTIONS 4.1 verify automatic actions occur.
4.2 If reactor water level decreases below +11.4", verify the reactor scrams and enter EP-1, Level Control.
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4.3 If the reactor has not scrammed, perform any or all of the followirg as necessary to maintain reactor water level between +32" and +42":
4.3.1 Reduce reactor power level.
4.3.2 Start a standby condensate pump, Condensate Booster Pump, Reactor Feed pump, and/or Heater Drain Pump, if available.
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-4 4.3.3 If the Startup Level Control Valve has failed closed and should be controlling level, open the FW SU BYP VLV IN21-F040 using IN21 HS-M631 on 1H13-P680.
5.0 SUBSEQUENT ACTIONS 5.1 Determine and correct cause of loss of feedwater flow.
5.2 Once feedwater has been restored, refer to 101 03-1-01-2, Power Operation. -
5.3 If RCIC has started, establish at least 2000 gpm in SSW Loop A, in l
accordance with S01-04-1-01-P41-1 Standby Service Water System.
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