ML19290E396

LER 80-006/03L-0:on 800131,during Reactor Recirculation Flow Calibr surveillance,as-found Values of Recirculation Flow Sensors at Zero Percent Simulated Flow Were Out of Tolerance.Caused by Instrument Drift

ML19290E396
Person / Time
Site:	Oyster Creek
Issue date:	02/29/1980
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19290E390	List: ML19290E389 ML19290E396
References
LER-80-006-03L, LER-80-6-3L, NUDOCS 8003110068
Download: ML19290E396 (3)

Text

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'O l On January 31, 1980. durino the reactor recirculation flow calipration l surveillance procedure, the as-found values of the ecirc flow sensors j c,,il

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' Momstown. Neu Jersey 07960 (201)455-820; OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-6/3L Report Date February 29, 1980 Occurrence Date January 31, 1980 Identification of Occurrence Exceeding a limiting condition for operation as per Technical Specifications, table 3.1.1.A.8, when the recirc flow sensors safety settings were found to be less conservative than required.

This event is considered to be a reportable occurrence as defined in the Tech-nical Speci fica t ions, paragraph 6.9.2.b.1.

Conditions Prior to Occurrence The plant was shut down for a refueling / maintenance outage.

The reactor was subcritical.

The reactor mode switch was locked in refuel.

The cavity was flooded.

Description of Occurrence On Thursday, January 31, 1980, during the Reactor Recirculation Flow Calibration (603.3 002) Survelliance procedure, the as-found values of the recirc flow sensors at zero percent simulated flow were out of tolerances on all APRM channels except 5 and 6. A Job Order (2721 l) was initiated to perform a surveillance test to determine the significance of out of tolerance value on respective APRM powec/

Flow rod block and scram trip points.

All APRM channels were tested using a simulated flow equivalent to the magnitude of zero error and increasing simulated power to the rod block and scram tr ip points.

1 - Rod block occurred at less than the Technical Specifications required value on all APRM channels for both as-found and as-lef t recirc flow data values.

erw Ce~ra-ower t. Legnt Comer.y :s a Memw o':ne Gevri Pumc Ut/ res 5,: e-

Reportable Occurrence No. 50-219/80-6/3L Page 2 February 29, 1980 2 - Scram trip occurred at < 34% (Technical Specification required value) on all APRM channels except #27 #7, and #8 when using an as-found error value of recirc flow.

3 - Scram trip occurred at 36.5% for APRM #2, 35% for APRM #7, and 39% for APRM #8.

The out of tolerance readings were at zero percent simulated flow only. The plant will not experience power operation at this flow.

Apparent Cause of Occurrence The caJse of this occurrence is attributed to instrunent dr:ft.

Analysis of Occurrence The Avc-rage Power Range Monitor (APRM) system consists of eight channels, four in each reactor protection system. Each channel averzges the signals from eight Local Power Range Monitors (LPRM). The reactor is divided into four quadrants and each reactor protection system has an APRM in each quadrant.

The safety significance of this event is considered minimal since the reactor is not operated in this ptwer/ flow region.

Corrective Action The flow sensors were recalibrated to all required flow rates.

Failure Data Not Applicable.