05000219/LER-1982-005, Forwards LER 82-005/03L-0.Detailed Event Analysis Encl

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Forwards LER 82-005/03L-0.Detailed Event Analysis Encl
ML20041D778
Person / Time
Site: Oyster Creek
Issue date: 02/25/1982
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20041D779 List:
References
NUDOCS 8203090179
Download: ML20041D778 (3)


LER-1982-005, Forwards LER 82-005/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2191982005R00 - NRC Website

text

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GPU Nuclear g

gf P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:

February 25, 1982 Mr. Ibnald C. Ilaynes, Adminstrator Region I c)

United States Nuclear Regulatory Ccmnission 4

631 Park Avenue g

King of Prussia, Pennsylvania 19406 flECEIVgg $

Dear Mr. Ilaynes:

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SUIDECr; Oyster Creek Nuclear Generating Station

%gp Docket No. 50-219 y

Licensee Event Report Reportable Occurrence No. 50-219/82-05/3L TO g

This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/82-05/3L in cmpliance with paragraph 6.9.2.b. (2) of the Technical Specifications.

Very truly yours, P

Vice President - Director Oyster Creek PBF:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforement United States Nuclear Regulatory Cmmission Washington, D.C.

20555 Director (3)

Office of Managment Information and Program Control United States Nuclear Regulatory Cmmission Washington, D. C. 20555 NRC Resident Inspector (1)

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

8203090179 920225 PDR ADOCK 05000219

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GPU Nuclear is a part of the General Pubhc Utihties System

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OYSTER CREEK NUCLEAR GD4ERATING STATION Forked River, New Jersey 08731 Licmsee Event Report Reportable Occurrence No. 50-219/82-5/3L Report Date February 25, 1982 Occurrence Date 1

January 25, 1982 Identification of Occurrence During a 20% load surveillance test, Diesel Generator 1-1 tripped on a signal initiated frun the low cooling water pressure sensor. A subsequent inspection indicated that the trip was due to leaks in the cooling system radiator.

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

Conditions Prior to Occurrence The reactor was in the refuel mode with reactor coolant tenperature less than 212 F and the reactor vented.

Description of Occurrence On bbnday, January 25, 1982, at approximately 0330, during a surveillance test, the 1-1 Diesel Generator tripped on an engine fault. Diesel Generator 1-2 was started in accordance witn the plants' technical specifications and a satis-factory surveillance test was performed.

Upon inspection of Diesel Generator 1-1 water leaks frun three (3) of the 450 radiator tubes in the cooling system were discovered. 'Ihe reduction of the water inventory in the cooling system resulted in a trip of the low cooling water pressure sensor. This device initiated an engine fault trip and the diesel proceeded into a normal shutdown.

Apparent Cause of Occurrence The cause of failure appears to be an approach to tle service lifetime of the heat exchangers.

Analysis of Occurrence The Standby Diesel Generators provide an emergency source of power to the 1C and 1D buses in the event of a loss of offsite power. The 1C and 1D buses supply power to safety Gysterns utilizing 4160 voltage and at reduced voltage to other

<xmponents inportant to safety.

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Peportable Occurrmcc Page 2 Report No. 50-219/825/3L

.Since Diesel Generator 1-1 was satisfactorily tested on January 12, 1982, and the reactor has been shutdown since December 11, 1982, the only concern at the time of the event would have been the loss of offsite power. Diesel Generator 1-2 was proved operable and could have handled this mergency load. Therefore, the safety significance of this event is considered minimal.

Cbrrective Action Three tube leaks were found and plugged. The radiator for Diesel Geneiator 1-1 was operationally tested and returned to service on January 29, 1982 at approxi-mately 0600. The required surveillance test was satisfactorily performed.

During the period of time Diesel Generator 1-1 was iroperable, Diesel Generator 1-2 was tested in accordance with the plants' technical specifications.

Prior to startup, both Diesel Generator Cooling Systms will be hydro tested per the manufacturer's reemmendation to assure adequacy of radiator integrity until scheduled replacment can be affected. Present replacment is scheduled for the next rrefueling outage.

Failure Data Diesel Generator 1-1 Radiator Manufactured by:

Electro-Motive Division General Fbtors Corp.

La Grange, Illinois f

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