05000219/LER-1980-051, Forwards LER 80-051/03L-0

Forwards LER 80-051/03L-0

ML19345D743
Person / Time
Site:	Oyster Creek
Issue date:	12/04/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19345D744	List: 05000219/LER-1980-051, Forwards LER 80-051/03L-0 05000219/LER-1980-051-03, /03L-0:on 801108,daily Surveillance Checks Not Made of Linear Heat Generation Rate,Average Planar Linear Heat Generation Rate & Max Critical Power Ratio.Caused by Personnel Error.Insps Performed
References
NUDOCS 8012160546
Download: ML19345D743 (3)

LER-1980-051, Forwards LER 80-051/03L-0

Event date:
Report date:
2191980051R00 - NRC Website

text

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N OYSTER CREEK NUCLEAR GENERATING STATION F iel:2: N M [c d]

geqfg wh wu,.fjg (609) 693-1951 P.O. BOX 388

• FORKED F4VER

• NEW JERSEY

• o8731 soc..

December 4, 1980 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Ccmission 641 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/80-51/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/80-51/3L in compliance with paragraph 6.9.2.b.(3) of the Technical Specifications.

Very truly yours,

/

46 t/ V Ivan R. Finfrock,

/

Vice President Gen ation IRF:dh Enclosures cc:

Mr. John G. Davis, Acting Director (40 copies)

Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D.C.

20555 Mr. William G. Mcdonald, Director (3 copies) g 9j g

Office of Management Information and Program Control ro i: _

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United States Nuclear Regulatory Commission E. Q-4 4

Washington, D.C.

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N 0YSTER CREEK NUCLEAR GENERATING STATION I

Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-51/3L I

Report Date December 4, 1980 Occurrence Date November 8, 1980 Identification of Occurrence Violation of the Technical Specifications, paragraph 4.10. A,B & D, in that the dcily required surveillance for APLHGR, LHGR, and MCPR was not performed on No < ember 8,1980.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.(3).

4 Conditions Prior to Occurrence Steady State Power Core Thermal Power (MWt):

957 4

Total Reciculation Flow (GPM): 9.89 x 10 i

Recirculation Water Temp ( F Avg.): 527.5 Reactor Pressure (PSIA): 1020.4 i

i Description of Occurrence At approximately 8:00 AM on November 9,1980 it was discovered that the daily surveillance check of APLHGR, LHGR, and MCPR was not performed on November 8, 1980.

Apparent Cause of Occurrence The apparent cause of the occurence is attributed to personnel error in that responsible engineer forgot to perform the check.

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f Reportable Occurrence Page 2 Report No. 50-219/80-51/3L Analysis of Occurrence A detailed review of the reactor operating history from November 7,1980 to November 9,1980 was perforined. At approximately 9:00 PM on November 7, a load e

reduction was initiated to perform piant maintenance. The reduction was initiated l

at approximately 98% power and reached a steady state power level of approximately 50% at 9:00 AM on November 8,1980. Steady state power operation was maintained until approximately 8:30 PM when a power level increase to approximately 67% was initiated. Between 9:00 AM and 8:00 PM on November 8,1980, therefore, the reactor was at a steady state operating condition of approximately 50% power.

Operating experience has demonstrated that exceeding APLHGR, LHGR, and MCPR operating limits at such steady state low power conditions are highly improbable.

In addition a surveillance check of APLHGR, LHGR, and MCPR was performed on November 9,1980 while operating at approximately 67% power. At that power, the surveillance check revealed the APLHGR, LHGR and MCPR percent of limits was l

85.7%, 76.9% and 80.6% respectively. This surveillance demonstrated that although the power level was increased by 20% APLHGR, LHGR, and MCPR were well within limits and, therefore, were most probably within limits on November 8,1980.

Corrective Action

An APLHGR, LHGR, and MCPR surveillance was immediately initiated upon discovery of the event. A revision will be made to the Group Shift Supervisor's turnover sheet to insure that the daily core checks have been completed.

t Failure Data, Not applicable.

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