ML20042F423

Ro:On 900409,automatic Isolation of Reactor Recirculation Sys Sample Line Outboard Containment Isolation Valve BB-SV-4311 Occurred.Caused by Pulling Fuse Providing Power to Valve

ML20042F423
Person / Time
Site:	Hope Creek
Issue date:	04/27/1990
From:	Hagan J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9005080306
Download: ML20042F423 (1)

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- . O PSEG Pubhc Service Electnc and Gas Cornpany P.O. Box 236 Hancocks Bndge. New Jersey 08038 Hope Creek Generating Station April 27, 1990 U. S. Nuclear Regulatory Commission Document Control Desk 7 Washington, DC 205S5

Dear Sir:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 On 4/9/90 at 1159, a four hour non-emergency report was made to the NRC Operations Center regarding the automatic isolation of the Reactor Recirculation System Sample Lin Outboard Containment Isolation Valve ( BB-SV -4 311) . This valve is an Engineered Safety Feature (ESP) component due to its containment isolation function, and does not, on a system

__ level, belong to an ESF system. The transient which initiated the valve closure was the result of pulling a fuse that provided 120VAC control power to the valve, and did not occur via any containment isolation logic channel input to the valve control circuitry. As such, this incident is not classified as an ESF actuation.

During the time the valve control power was de-energized, appropriate containment isolation system Technical Specification requirements were met, and contaiment integrity a was assured via the inboard isolation valve on the subject san'ple line .

By issuance of this letter, we withdraw our initial four hour

- report and will not submit a Licensee Event Report for this occurrence, however, an internal investigation into the incident has been conducted.

Sincerely,

.J. an

, General Manager -

um Hope Creek Operations RBC/

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