ML19345A980

Forwards LER 80-049/01T-0

ML19345A980
Person / Time
Site:	Oyster Creek
Issue date:	11/19/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19345A981	List: ML19345A980 ML19345A982
References
NUDOCS 8011250524
Download: ML19345A980 (3)

Text

. _ . _ _ _ _ _ . :_ _ . . _ .

_f . _ . .c _ . . _ _ , - -- -- -- -- - - - - - - -

~

.,,,...P'"~

OYSTER CREEK NUCLEAR GENERATING STATION

, - yyL bks. q:3 / tr g f ";"QCf,7 pa 3 01 (6o9) 693-1951 P.O. BOX 388

• FORKED RIVER

• NEW JERSEY

• C8731 c - .,"". g p @ ,,, t

'~']yj;ggs November 19, 1980

• ~

i,CH Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Comission 641 Park Avenue King of Prussia, Pennsylvania 19406

SUBJECT:

Oyster Creek Nuclear Generating Station Docket No. 50-219

• Licensee Event Report Reportable Occurrence No. 50-219/80-49/0lT This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/80-49/0lT in compliance with paragraphs 6.9.2.a.(3) and 6.9.2.b.(2) of the Techni il Specifications.

. Very truly yours, p d t / Otal/

van R. Finfrock, J . ')

Vice President Ger ati.

IRF:dh Enclosures cc: Mr. John G. Davis, Acting Director (40 copies)

Office of Inspection and Enforcement United States Nuclear Regulatory Comission Washington, D.C. 20555 Mr. William G. Mcdonald, Director (3 copies)

Office of Management Infonnation and Program Control United States Nuclear Regulatory Comission Washington, D.C. 20555 ,

i 8011'J50 3_ = - = -  := - .-

4- ,

a OYSTER CREEK NUCLEAR-GENERATING STATION Forked River, New Jersey 08731 Licenree Event Report Reportable Occurrence No. 50-219/80-49/0lT Report Date November 19, 1980 4

Occurrence Date i ' November 5, 1980 l

Identification of Occurrence Degradation of the reactor coolant pressure boundary and primary containment when the Isolation Condenser vent isolation valves (V-14-1 and V-14-19) for Isolation Condenser "B" were suspected to have failed to close and also operation in a degraded mode as per Technical Specifications section 3.8.C.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.a.(3) and 6.9.2.b.(2).

Conditions prior to Occurrence The plant was operating at steady state power.

plant parameters at the time of occurrence were:

Power: Core 1737 MWt Electrical 535 MWe Flow: Recirculation 14.6 x i 4 gpm Feedwater 5.9 x 10g lb/hr Description of Occurrence On Wednesday, November 5, 1980, Isolation Condenser "B" was removed from service to repair a packing leak on vent isolation valve V-14-19. At approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, while isolating the condenser for maintenance, vent isolation valves V-14-1 and V-14-19 apparently failed to operate properly from the control room as indicated by valve position indication.

Apparent Cause of Occurrence Isolation Condenser "B" was renoved from service to repair a stem packing leak .

I on vent isolation valve V-14-19. Despite extensive investigation and trouble-shooting, the cause of the failure for valves V-14-1 and V-14-19 to close could not be determined.

+

e 4

s.wmm. m m ,

4

,e-+w+-_ -

a_.+ .w.we_ --

y e oe- _

t i

Reportable Occurrence Page 2 Report No. 50-219/80-49/0lT Analysis of Occurrence The Isolatior. Condenser System is used to depressurize the reactor and to remove decay heat in the event that the turbine generator and main condensers are unavailable as a heat sink. The system consists of two independent condensers each capable of accomplishing the purpose of the system.

The vent lines from each of the isolation condenser loops to the main steam i lines downstream of the Main Steam Isolation Valves (MSIV's) are provided with two (2) isolation valves in series which close automatically on isolation condenser actuation or on signals which close the MSIV's. Failure of these valves to close would have resulted in a degradation of the reactor coolant pressure boundary and primary containment.

Corrective Action Imediate corrective action was to perform ar, operability check on Isolation Condenser System "A" and then to close the steam inlet valves to "B" condenser.

The steam packing leak on V-14-19 prohibited observation of the valve stem position shortly after the reported failure.

Initial troubleshooting indicated that the transition to an absence of voltage occurred at the load side of the valve control switch when positioned to the

" CLOSED" position. After the vent header was completely isolated and depress-urized the valves were cycled satisfactorily by lifting the leads feeding the solenoid valves. Both valves were observed to cycle satisfactorily. The packing on V-14-19 was replaced and the valve was cycled to verify freedom of movement.

Extensive troubleshooting and inspection did not reveal any cause for the failure of the valves to close, either mechanically or electrically. The valve operation was tested satisfactorily locally and from the control room both before and after repressurizing the vent header. No steam leakage from V-14-19 was observed at all during valve operation after the packing was replaced. On November 7, 1980 Isolation Condenser "B" was returned to service.

This event will be further investigated by the Plant Operations Review Committee (P,0RC) .

Failure Data Skinner Precision Industries, Inc.

Skinner /Uniflow Valve Division 3/4" Type 800 straight through valve Serial #'s 1021C (V-14-1) 1021E (V-14-19)

O L

...n ~.. -n ., _.

- .N ..n .