05000219/LER-1981-047, Forwards LER 81-047/03L-0.Detailed Event Analysis Encl

Forwards LER 81-047/03L-0.Detailed Event Analysis Encl

ML20049H186
Person / Time
Site:	Oyster Creek
Issue date:	11/03/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20049H189	List: 05000219/LER-1981-047, Forwards LER 81-047/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-047-03, /03L-0:on 811005,during Diesel Surveillance Test, Diesel Failed to Automatically Increase Load Above 2,400 Kw. Caused by Operational Deterioration of Governor.Governor Replaced
References
NUDOCS 8111110625
Download: ML20049H186 (3)

LER-1981-047, Forwards LER 81-047/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981047R00 - NRC Website

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NUCLEAR GENERATING STATION GkVJib' OYSTER CREEK PM:I:Unf (609) 693-1951 P.O. BOX 3S8

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Noverrber 3, 1981 Mr. Ronald Haynes, Director Office of Inspection and Enforcerent Region I United States Nuclear Regulatory Ccanissian 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-47/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-47/3L in corpliance with paragraph 6.9.2.b.2 of the Technical Specifications.

Very truly yours,

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d.Ltd$

. T. Carroll, a.

Acting Director Oyster Creek JIC:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforcenent United States Nuclear Regulatory Ccmnission Washington, D.C.

20555 Director (3)

Office of Manage'unt Information and Program Control [j,

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United States Nuclear Regulatory Ccmnission V

g Washington, D. C. 20555 i

NBC Resident Inspector (1)

Oyster Creek Nuclear Generating Station Forked River, N. J.

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OYSIER CREEK NUCLEMI N SIATICN Forked River, New Jersey 08731 Licensee Event Peport Reportable Occurrence No. 50-219/81-47/3L Report Date Novmber 3, 1981 Occurrence Date October 5, 1981 Identification of Occurrence One of the plants' diesel generators was in a degraded condition for operation as per Technical Specification Section 6.9.2.B.2 when the 1-1 diesel generator failed to achieve peak load during a surveillance. test.

mis event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.

Conditions Prior to Occurrence me plant was shutdown in the refuel node with the reactor Wrature less than 212 F.

Description of Occurrence On Monday, October 5, 1981, at approximate 1, 1430 a surveillance test was perfonned on diesel generator 1-1.

During the test the diesel generator failed to autcmatically increase load above 2400 KW.

Electrical maintenance was dispatched to investigate the problem.

In an att s pt to increase diesel loading, electrical maintenan made several adjustments to the centrifugal governor's mechanical stop. However, this failed to produce satisfactory results.

On October 9, at 1650, diesel generator 1-1 was rmoved frcm service and the unit's governor assm bly was replaced. A satisfactory 20% load surveill:mce

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test was perfanned on the diesel, and at 2230 the unit was available for operation.

i Apoarent Cause of Occurrence t e cause of the occurrence was attributed to normal operational deterioratia within the governor. Se governor could not properly adjust the diesel fuel supply and, therefore, could not increase load above 2400 KW.

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s Peportable Occurrence Page 2 Report No. 50-219/81-47/3L Analysis of Occurrence

'Ihe diesel generators have full load ratings of 2500 KW and peak load ratings of 2750. Recent load studies have indicated that in the worst case situation (II)CA with loss of off-site power and one diesel inoperable) the operable diesel nust be able to provide 2679.4 KW of power. In an emergency situation, diesel 1-1 might possibly not have been able to provide the required power. However, at the time of the incident the reactor was in the refuel mode and vented, and diesel generator 1-2 was fully operational. Therefore, the safety significance of this event is considered mini = 1.

Corrective Action

The defective governor was replaced and will be sent to the manufacturer for further failure analysis.

1-2 Diesel Generator Governor will be replaced, as a preventive measure, during the next major ingxction.

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