05000219/LER-1981-045, Forwards LER 81-045/03L-0.Detailed Event Analysis Encl

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Forwards LER 81-045/03L-0.Detailed Event Analysis Encl
ML20011A925
Person / Time
Site: Oyster Creek
Issue date: 10/23/1981
From: Carroll J
JERSEY CENTRAL POWER & LIGHT CO.
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20011A926 List:
References
NUDOCS 8111030361
Download: ML20011A925 (3)


LER-1981-045, Forwards LER 81-045/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2191981045R00 - NRC Website

text

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OYSTER CREEK NUCLEAR GENERATING STATION sreur J. f4,,'? ) f ffy,D '

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October 23, 1981 Mr. Ronald llaynes, Director Office of Inspection and Enforcment Region I United States Nuclear Regulatory Cm mission 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Ilaynes:

SUIDECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-45/3L This letter forwards three copics of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-45/3L in ccmpliance with para-graph 6.9.2.b.2 of the Technical Specifications.

Very truly yours,

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tt444I J. T. Carroll, Jr Acting Director ter Creek, JIC:dh

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cc: Director (40 copies) i 80Vg<>, $8 F Office of Inspection and Enforement 4J United States Nuclear hjulatory Cmmission

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Director (3)

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and Program Control United States Nuc.1 ear Regulatory Cmmission Washington, D. C. 20555 NFC Resident Inspector (1)

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

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OYSTER CREEK NUCIEAR GENERATING S'IATICN Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-45/3L Report Date October 23, 1981 Occurrence Date Septestber 24, 1981 Identification of Occurrence Failure of "B" Isolation Condenser valve V-14-32 to open during performance of a routine surwillance 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 0

2e plant was shutdown with reactor tatperature less than 212 F and vented.

Description of Occurrence During routine performance of the "B" Isolation Condenser valve operability test on Septanber 24, 1981, the AC stean isolation valve V-14-32 failed to reopen.

Subsequent investigation indicated that the opening torque switch was not being bypassed by the limit switch.

Apparent Cause of Occurrence h e bypass limit switch, which shunts the opening torque switch during the first 10% of the valve cpening stroke, was found out of adjustment. his misadjustment prevented energizing the valve opening circuit because the torque switch was open and not shunted by the bypass limit switch.

Analysis of Occurrence te purpose of the isolation condenser is to depressurize the reactor and to remove reactor decay heat in the event that the turbine generator and main condenser are unavailable as a heat sink. The safety signification of this event is considered minimal based on the fact that the plant was shutdown, reactor was vmted and water tertperature was below 212 F.

Corrective Action

%e opening bypass limit switch was adjusted properly, i.e. to shunt the opening torque switch for the first 10% of stan travel.

s Pcportable Occurr e Page 2 Feport Po. 50-219/81-45/3L Failure Data Philadelphia Gear Corp.

Limitorque Division King of Prussia, Pa.

Limitorque h pe SMB-2