ML20203F244

Supplemental Application for Amend to License NPF-50, Revising Tech Specs Re Operating Ac Sources & Special Repts, Pending Issuance of Full Power License

ML20203F244
Person / Time
Site:	Hope Creek
Issue date:	07/24/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
Shared Package
ML20203F249	List: ML20203F244 ML20203F250
References
NLR-N86079, NUDOCS 8607300234
Download: ML20203F244 (3)

Text

s Pubhc Service Electric and Gas Company Ctrbin A. McNeill, Jr. Pubhc Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Vice President -

Nuclear July 24, 1986 NLR-N86079 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814

, Attention: Ms. Elinor Adensam, Director

. Project Directorate #3 Division of BWR Licensing

Dear Ms. Adensam:

HOPE CREEK GENERATING STATION TECHNICAL SPECIFICATION CHANGES FOR INCORPORATION IN THE FULL-POWER OPERATING LICENSE HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G): is currently operating Hope Creek Generating Station (HCGS) in accordance with the Technical Specifications contained in Appendix A of Operating License NPP-50, dated April 11, 1986. As a result of operating experience gained since the issuance of the low power operating

-license, PSE&G is requesting that the HCGS Technical Specifications be revised, as shown in the Attachments, when the full-power operating license is issued. Since HCGS currently meets the requirements of the existing Technical Specifications, no amendment to the present low-power operating. license is sought. It can be concluded from the justification and explanation for the changes indicated in the Attachments that these revisions do not involve a significant hazards consideration. This change supplements previous changes forwarded in a letter dated June 13, 1986.

Should you have any questions, do not hesitate to contact us.

Sincerely, m

Attachments 8607300234 860724 1$

D PDR ADOCK 05000354 k P PDR i

Director of Nuclear 2 Reactor Regulation 7/24/86 C Mr. D. H. Wagner USNRC Licensing Project Manager Mr. R.W. Borchardt USNRC Senior Resident Inspector

ATTACHMENT I TECHNICAL SPECIFICATION 4. 8.1.1. 2. f l .b AC SOURCES - OPERATING Surveillance Requirement 4.8.1.1.2.f.l.b specifies a Saybolt Second Universal (SSU) viscosity of less than or equal to 45 SSU for diesel generator new fuel oil or a fuel oil sample from the storage tanks. The attached change would revise the upper limit from 45 SSU to 40.1 SSU.

Although this change will have no discernible effect on the performance or operation of the Emergency Diesel Generators, this Technical Specification revision is necessary to maintain strict compliance with the requirements of ASTM Standard D975.77 for No. 2 grade diesel fuel oil, t

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