05000219/LER-1981-063, Forwards LER 81-063/03L-0.Detailed Event Analysis Encl

Forwards LER 81-063/03L-0.Detailed Event Analysis Encl

ML20039G236
Person / Time
Site:	Oyster Creek
Issue date:	12/21/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20039G237	List: 05000219/LER-1981-063, Forwards LER 81-063/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-063-03, /03L-0:on 811119,during Surveillance Testing, Isolation Condenser Valve V-14-30 Failed to Close.Caused by Torque Switch Setting & Packing Gland Tightness.Torque Switch Setting Corrected
References
NUDOCS 8201150409
Download: ML20039G236 (3)

LER-1981-063, Forwards LER 81-063/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981063R00 - NRC Website

text

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CYSTER CREEK NUCLEAR GENERATING STATION mmw 7 "y;;;3, [N,;l.*n S,,;f (609) 693-1951 P O. BOX 363

• FORKED HiVER

• NEW JERSEY

• 08731 c.m. e - m - u Decenber 21, 1981 Mr. Ibnald Haynes, Director CD D

Office of Inspection and Enforcenent Region I

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United States Nuclear Regulatory Camtission nECgtVED 631 Park Avenue

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jgg 1319827 h King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

h 5 nU* *2's'e' ur R suge es15

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- 2, SUBJECT: Oyster Creek Nuclear Generating Docket No. 50-219

• /w Licensee Event Report Reportable Occurrence No. 50-219/81-63/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-63/3L in carpliance with paragraph 6.9.2.b.2 of the Technical Specifications.

Very truly yours, 0

gbY

/

. T. Carroll, J.

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

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

20555 Director (3)

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

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

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$9

$6 Qi eda

E OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-63/3L Report Date Deceber 21, 1981 Occurrence Date November 19, 1981 Identification of Occurrence Operation under a Limiting Condition for Operation as defined in Technical Specification 3.8.C.

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

Conditions Prior to Occurrence Major plant parameters were as follows:

Power:

Reactor 1867 N t Generator 651 Ne Flow:

Recirculation 15.2 x 104 gpn Feedwater 7.15 x 10 lbs/hr Description of Occurrence During performance of the " Isolation Condenser Valve Operability Test" (Surveillance Procedure 609.4.001) valve V-14-30 failed to close when closure was initiated from the control rocm switch. It was found that the valve was binding at the 95% open position while closing. This binding was confirmed by observing excessive current flow through the motor during closure initiation.

Apparent Cause of Occurrence After subsequent investigation, it was felt that the failure to close was due to the torque switch setting and packing gland tightness. Corrective action was taken and subsequent testing confirmed valve operability.

On Dwmber 3,1981, additional failures occurred and are the subject of Pre-ljminary Notification of Peportable Occurrence 81-65 which has been subnitted.

)

Reportable Occurrence Page 2 Report No. 60-219/81-63/3L Analysis of Occurrence The Isolation Condenser Systen consists of two 100% redundant circulation loops.

j Each loop has three normally open MOV's in series. Two high flow sensing Delta P switches will cause the autanatic isolation of the affected ccndenser by closing the isolation valves on the steam and condensate side. Valve V-14-30 and series valve V-14-31 are on the steam side. Failure of V-14-30 in the everit i

of a tube rupture in the steam side is considered a single failure. The signifi-

~

cance of the event is considered minimal since V-14-31 would have successfully isolated the steam piping.

Corrective Action

The Imnediate Corrective Action was to preform valve torque switch setting and Packing gland adjustment checks and correcting as necessary. The valve was i

fully stroked several times. After a successful valve operability test was preformed the valve was returned to operable status.

Since that time, additional failures have occurred (Prel2minary Report 81-65) and a detailed analysis of the closure probleus is being carried out..The results of this analysis will be reported in Reportable Occurrence 81-65 in the near future.

Failure Data Not applicable.

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