05000219/LER-1981-026, Forwards LER 81-026/03L-0.Detailed Event Analysis Encl

Forwards LER 81-026/03L-0.Detailed Event Analysis Encl

ML20030B218
Person / Time
Site:	Oyster Creek
Issue date:	07/27/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20030B219	List: 05000219/LER-1981-026, Forwards LER 81-026/03L-0.Detailed Event Analysis Encl 05000219/LER-1981-026-03, /03L-0:on 810627,while Performing Isolation Condenser Sensor Calculation & Test,Trip Point of One High Pressure Switch Found Less than Tech Specs Limit.Caused by Instrument Repeatability.Pressure Switch Reset
References
NUDOCS 8108060231
Download: ML20030B218 (3)

LER-1981-026, Forwards LER 81-026/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191981026R00 - NRC Website

text

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EA L

C OYSTER CREEK t

NUCLEAR GENERATING STATION EbiM MWV G1 (609)693-6000 P.O BOX 388

• FORKED RIVER

• NEW JERSEY

• 08731 July 27, 1981 e

A Mr. Boyce H. Grier, Director k

bC Office of Inspection and Enforement T.

)J UE N m g'1U0O319816fg Region I United States Nuclear Regulatory Camission i

D 7s,2,N 631 Park Avenue

/

King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

b SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-26/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/81-26/3L in compliance with paragraph 6.9.2.b. (1) of the Technical Specifications.

Very truly yours,

(*

I

. T.

L, Jr.

Director Station Operations JIC:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforement 1

United States Nuclear Regulatory Cm mission l

Washington, D.C.

20555 l

Director (3)

Office of Management Information and Program Control l

United States Nuclear Regulatory Cmmissior.

Washington, D. C. 20555 NRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station p

Forked River, N. J.

GIfil 8108060231 810727 PDR ADOCK 05000219 g

PDR

OYSTER CREEK NUCLEAR GENERATING STATICN Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-2i9/81-26/3L Report Date July 27, 1981 Occurrence Date June 27, 1981 Identification of Occurrence Reactor high pressure isolation condenser initiation pressure switch RE15A tripped at a value greater than that specified in the Technical Specifications, Section 2.3.5.

This event is considered to be a reportable occurrence as defined in the 'Ibchnical Specifications, paragraph 6.9.2.b. (1).

Conditions Prior to Occurrence 0

Reactor shutdown : all rods at 00. Water taiperature 265 F.

l Description of Occurrence i

On Saturday, June 27, 1981, at approxu utely 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, while performing the l

" Isolation Condenser Autcmatic Actuation Sensor Calibration and Test", the RE15A trip point was found to be less conservative than that specified in the Technical Specifications. Surveillance test on the high pressure switches for the Isolation Condenser Systan revealed the following data:

Pressure Switch Desire Set Point As Found As left Designation RE15A 1068 1075 1067 RE15B 1068 1068 1068 RE15C 1066 1065 1065 RE15D 1066 1055 1066 Apparent Cause of Occurrence The cause of the occurrence was attributed to instrument repeatability. The set point actuation is 1068 psig and the long term repeatability of the instrument is 1-2% (11.50-23.00 psig) of full range. Therefore, although the instrument will be operating within design accuracy, the Technical Specification limit of 1068 psig was exceeded between scheCaled tests.

Reportable Occurrence Page 2 Report No. 50-219/81-26/3L Analysis of Occurrence The purpose of the Isolation Condenser is to depressurize the reactor and to renove decay heat in the event that the turbine generator and mein condenser is unavailable as a heat sink. Either of the two Isolation Condensers can acccruplish the purpose of the system. If one condenser is found to be inoperable, there is no innediate threat to the heat removal capability for the reactor.

The safety significance of this event is considered minimal since the pressure switch would have actuated but at a setpoint 7 psig above the Technical Specifica-tion limit. Both isolation condensers were operable but the redundant instrument channel in one of two isolation condensers was above limits.

Corrective Action

Imnediate corrective action was to reset the pressure switch to the desired set point. Replao3nent of the pressure switches with analog devices is also planned.

Failure Data Barksdale Switch #B2T A1259 Proof 1800 psi Adjustable range 50-1200 psi l

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