ML20039F309

Forwards LER 81-016/03L-0.Detailed Event Analysis Encl

ML20039F309
Person / Time
Site:	Oconee
Issue date:	12/31/1981
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20039F310	List: ML20039F309 ML20039F317
References
NUDOCS 8201120330
Download: ML20039F309 (2)

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Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: Oconee Nuclear Station Docket No. 50-287

Dear Mr. O'Reilly:

Please find attached Reportable Occurrence Report R0-287/81-16. This report is submitted pursuant to Oconee Nuclear Station Technical Specification 6.6.2.1.b(1) which concerns reactor protection system settings which are found to be less conservative than those established by the Technical Spec-ifications but which do not prevent the fulfillment of the functional re-quirements of the affected systems. This report describes an incident which is considered to be of no significance with respect to its effect on the health and safety of the public. & m Very truly yours, f CfVEQ g N 7 JAN 111985,1-u d ch William O. Parker, Jr.

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cc: Director Records Center Office of Management & Program Analysis Institute of Nuclear Power Operations U. S. Nuclear Regulatory Commission 1820 Water Place Washington, D. C. 20555 Atlanta, Georgia 30339 Mr. W. T. Orders NRC Resident Inspector Oconee Nuclear Station ICIAL COPY 8201120330 811231 gDRADOCK 05000287 PDR

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DUKE POWER COMPANY OCONEE UNIT 3 Report Number: R0-287/81-16 Report Date: December 31, 1981 Occurrence Date: December 2, 1981 Facility: Oconee Unit 3, Seneca, South Carolina Identification of Occurrence _: Channel C Pump Power Monitor Failure Conditions Prior to Occurrence: 100% FP Description of Occurrence: On Decemb4r 2,1981, wilile performing on-line testing, the-Channel C Pump Power Monitor failed to send a trip signal.

Apparent Cause of Occurrence: The apparent cause of this incident was a failed IC on the logic board of the Channel C Pump Power Monitor.

Analysis of Occurrence: The Reactor Protective System is required to have three pump power monitor channels operable. Channels A, B, and D were' operable at the time of the Channel C failure; thus, the health and safety of the public were not affected by this incident.

Corrective Action: The defective logic board was replcced. The Channel C Pump Power Monitor was tested satisfactorily and returned to service.

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