ML20214V467

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Requests Expedition of 861205 Request for Amend to License NPF-57 Concerning Min Critical Power Ratio & end-of-cycle Recirculation Pump Trip Sys,Based on Results of Recirculation Pump Trip Test
ML20214V467
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 12/08/1986
From: Corbin McNeil
Public Service Enterprise Group
To: Adensam E
Office of Nuclear Reactor Regulation
References
NLR-N86190, NUDOCS 8612090695
Download: ML20214V467 (2)


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Public Service Electric and Gas Cornpany C:rbin A. McNeill, Jr.

Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609339-4800 Vice President -

Nuclear NLR-N86190 December 8, 1986 Director of Nuclear Reactor Regulation United Stated Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:

Ms. Elinor Adensam, Director Project Directorate #3 Division of BWR Licensing

Dear Ms. Adensam:

REQUEST FOR AMENDMENT - ADDITIONAL INFORMATION FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) submitted a Request for Amendment to Facility Operating License NPF-57 on December 5, -1986 regarding Hope Creek Generating Station (HCGS)

Technical Spm.ifications 3.2.3, MINIMUM CRITICAL POWER RATIO, and 3.3.4.2, END-OF-CYCLE, RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION.

The request was submitted as a standard license change request; however, the results of a recirculation pump trip test, conducted after the submittal, necessitated an escalation of our request to Emergency Classification on December 8, 1986.

Our amendment request was supported by a General Electric Company analysis that bounded the unacceptable flow coastdown values measured during the test by assuming no recirculation pump trip.

The analysis provided by General Electric Company was performed using the ODYN Option

'A' and Option

'B' Codes with Hope Creek Generating Station specific data inputs.

All input assumptions for the reanalysis were the same as those used in the original HCGS FSAR Chapter 15 analysis with the exception of the assumption of no recirculation pump trip.

Sincerely, C#a'AE l

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8612090695 861208 "7

D PDR ADOCK 05000354

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H. Wagner Licensing Project Manager Mr.

R. W. Borchard t Senior Resident Inspector 4

Mr. David M. Scott, Acting Chief-Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware 820 North French Street Wilmington, DE 19801 i

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