ML20097A358

Provides Listed Test Schedule for Retest of Drywell to Suppression Chamber Vacuum Breakers,Per SR 4.6.2.1.e.Details Re Issue Will Be Provided in Suppl to LER 354/95-031-00

ML20097A358
Person / Time
Site:	Hope Creek
Issue date:	01/31/1996
From:	Reddemann M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N95239, NUDOCS 9602050277
Download: ML20097A358 (3)

Text

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DPSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 l

Nuclear Business Unit 1 JAN 31 1996 LR-N95239 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 RETEST SCHEDULE FOR DRYWELL TO SUPPRESSION CHAMBER VACUQH BREAKERS PER TECHNICAL SPECIFICATION 4.6.2.1.e HOPE CREEK DOCKET NO. 50-354 On November 10, 1995, at 1344, Hope Creek Generating Station (HCGS) entered Limiting Condition for Operation (LCO) 3.6.1.1 ,

because the Surveillance Requirements of 4.6.2.1.e could not be I met. A unit shutdown was initiated at 1422, and the plant was I subsequently brought to Hot Shutdown on November 11, 1995, at '

0145.

The cause of the failure to meet the Surveillance Requirements of 4.6.2.3.e is that one or more of the Suppression Chamber vacuum Breakers were experiencing bypass leakage. In Licensee Event Report (LER) 354/95-031-00, issued to the NRC on December 11, 1995, Public Service Electric and Gas (PSE&G) stated that'the 'F' and 'G' vacuum breakers appear to be the main contributors to this occurrence. Testing conducted to date has confirmed that the 'F' vacuum breaker was a contributor to the surveillance test failure.

In LER 354/95-031-00, PSE&G committed to revise the testing ,

methodology and to establish a vacuum breaker performance trending program The Drywell to Suppression Chamber Pressure Decay Tests will be performed in Operational Condition 4 (Cold Shutdown), following a one hour temperature stabilization period and utilizing an Integrated Leak Rate Test type valve lineup. An administrative bypass leakage limit, lower than that allowed by Technical Specifications, will be established. The results from the tests will be trended, and corrective maintenance will be performed when the bypass leakage exceeds the administrative limit.

A Drywell to Suppression Chamber Pressure Decay Test will be successfully completed prior to startup from the current refueling outage. The program to trend vacuum breaker performance will be established by March 1, 1996.

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JAN 31 1996 Document Control Desk 2 LR-N95239 During the implementation of these corrective actions, PSE&G discovered that the existing test methodology is not in compliance with the UFSAR requirements and has determined that the past Drywell to Suppression Chamber Pressure Decay surveillance tests are suspect. If the past Drywell to suppression Chamber Pressure Decay surveillance tests are determined to have been inadequate, details concerning this issue <

will be provided in a supplement to LER 354/95-031-00.

HCGS previously experienced a Drywell to Suppression Chamber P.ressure Decay surveillance test failure in 1992. The corrective maintenance that was performed in 1992 included work on the 'F' vacuum breaker. This work included replacing the hinge alignment pins, adjusting the pallet to attain proper seating of the seal, and readjusting the seal bolting to attain a satisfactory seal.

PSE&G has now determined that the root cause of the 'F' vacuum breaker, on both occasions, was a hinge arm to valve body ,

misalignment. The corrective maintenance that was performed in 1992 did not address this root cause, and, therefore, was not effective for the long-term.

In accordance with the Surveillance Requirements of 4.6.2.1.e, PSE&G provides the following test schedule for Commission review and approval.

PSE&G believes that it is appropriate for HCGS to continue to perform Technical Specification Surveillance Requirement 4.6.2.1.e on an eighteen month interval. This test schedule is proposed based on the enhanced vacuum breaker trending and the l corrective maintenance that is being performed on the vacuum breakers during the current refueling outage, including addressing the root cause of the failures of the 'F' vacuum I breaker.

This proposed test schedule is being submitted for your review and approval as required by Technical Specification 4.6.2.1.e.

Please do not hesitate to contact us if you have any questions regarding this submittal.

Sincerely, s fffd.----  :

M E. Reddemann General Manager -

Hope Creek Operations

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JAN 311996 Document Control Desk 3 LR-N95239 C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 William F. Kane, Deputy Administrator - Region I U. S. Nuclear Regulatory Commission 476 Allendale Road King of Prussia, PA 19406-1413 Mr. D. Jaffe, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. R. Summers (X24)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 i

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