ML20054K012
| ML20054K012 | |
| 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-5, 5-1-2-V-5, NUDOCS 8206300298 | |
| Download: ML20054K012 (3) | |
Text
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PLANT OPERATIONS MANUAL Volume 5 05-1-02-V-5 Section 02 Revision:
11 Date: 6-12-82 OFF-NORMAL EVENT PROCEDURE LOSS OF FEEDWATER HEATING SAFETY RELATED Prepared:.
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List of Effective Pages:
T Page:
1-2 List of TCN's Incorporated:
Revision TCN No.
10 None 11 None 8206300298 820625 PDR ADOCK 05000416 P
PDR 1
.,3AND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
Title:
Loss of Feedwater No.:
05-1-02-V-5 Revision:
11 Page:
1 Heating 1.0 PURPOSE / DISCUSSION 1.1 The purpose of this procedure is to provide the operator with the instructions necessary to respond to a Loss of Feedwater Heating and the resultant addition of cold water to the reactor.
1.2 This procedure may interface with other procedures.
1.3 A Loss of Feedwater Heating can result from the closing of an extraction steam line to a heater, heater string isolation / bypass, or heater high
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1evel.
In any case, the reactor vessel receives cooler feedwater.
The severity of this transient will vary depending on which heater (s) isolated, mode of reactor operation, and turbine load.
At high load conditions, the resultant cold water injection will be sufficient to provide significant moderator temperature decrease and subsequently, a significant reactor power increase.
2.0 SYMPTOMS 4.c.
2.1 Incre_ase in reactor powerf'RECIRC FCV h / g / if in'TLUX AUTO. W g
2.2 HP Feedwater heater Hi-Hi level isolation of extraction steam to the j
feedwater heater, or LP heater string condensate flow isolation for the
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af fected string.
2.3 APRM Upscale alarm /LPRM Upscale alarm /any feedwater heater Hi-Hi level ala rm( s).
2.4 Decreasing feedwater (H.P. Heater Outlet) temperature to the vessel.
3.0 AUTOMATIC ACTIONS i
3.1 Possible control rod block and scram due to high neutron flux.
l-4.0 IMMEDIATE OPERATOR ACTION
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6 4.1 Reduce recirculation flow upon receiving the first indication that feedwater heating is being significantly reduced. The flow reduction should be sufficient to reduce the thermal power to at least 20% below the power level prior to the reduction in feedwater heating (or to minimum flow if this is reached first).
4.2 Af ter the recirculation flow reduction, it may be necessary to insert control rods to reduce power to the 100% load line.
4.2.1 If any shallow or fully withdrawn control rods are inserted, they should be continuously inserted to the full-in position to av'oid further perturbation of the power shape.
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(GRANDGULFNUCLEARSTATION OFF-NORMAL EVENT PROCEDURE
Title:
Loss of Feedwater No.:
05-1-02-V-5 Revision:
11 Page:
2 Heating 4.3 If a scram occurs, refer to ONEP 05-1-02-1-1, Reactor Scram.
4.4 Notify-Shift Supervisor.
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5.0 SUBSEQUENT OPERATOR ACTION i
5.1 Notify Reactor Engineering and adjust rods per'their direction, if scram did not occur.
5.2 If a feedwater heater Hi-Hi level caused isolation, correct the problem and l
restore the heater to service per the abnormal operations section of SOI 04-1-01-N23-1.
t 5.3 If the feedwater heater cannot be restored, refer to SOI 04-1-01-N23-1 for abnormal feedwater configuration and applicable load carrying limitations.
t 5.4 Continue operations in accordance with 101 03-1-01-2, Power Operations, a
if a scram did not occur.
5.5.-Ifaeactor power was reduceUS%, notify Chemistry f6r'af riactof coxtrant sample.
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