ML20215J443

Application for Amend to License NPF-57,renumbering Tech Spec Sections 3/4.3.7.8 Through 3/4.3.7.10 & Adding Statement to Renumbered Section 3/4.3.7.8 to Indicate That Original Matl Re Fire Protection Deleted.Fee Paid

ML20215J443
Person / Time
Site:	Hope Creek
Issue date:	05/01/1987
From:	Corbin McNeil Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20215J446	List: ML20215J443 ML20215J480
References
NLR-N87076, NUDOCS 8705080025
Download: ML20215J443 (5)

Text

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e Pubhc Service Electric and Gas Company

- Corbin A. McNe4H,'Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609339-4800 6enor Vce President -

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MAY 01 ISd/

NLR-N87076 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In-accordance with the requirements of 10 CPR 50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS). In accordance with the requirements of 10 CFR 170.21, a check in the amount of $150.00

-is enclosed. In accordance with the requirements of 10 CFR 50.91(b)(1), a copy of this request for amendment has been sent to the State of New Jersey as indicated below.

This amendment request revises the numbering for Technical Specifications 3/4.3.7.8 through 3/4.3.7.10 and 3/4.11.2.6 (see Attachment 2). This change permits HCGS procedures to correctly reference the proper specifications, as those specifications associated with Fire Protection were deleted when the Full-Power Operating License was issued (see Attachment 1).

This submittal includes one (1) signed original, including affidavit, and thirty-even (37) copies pursuant to 10 CFR 5,0.4(b)(2)(ii).

Should you have any questions on the subject transmittal' please ,

do not hesitate to contact us.

Sincerely, 8705080025 870501 PDR ,ADOCK 0500 4

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Enclosure (check) g Affidavit kl(0 gh Attachments (2) - Og{

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m Document Control Desk 2 C Mr. G. W. Rivenbark NRC Licensing Project Manager Mr. R. W. Borchardt NRC Senior Resident Inspector Director, Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 Regional' Administrator, Region I

~U. S. Nuclear Regulatory Commission 631 Park Avenue

-King of Prussia, PA 19406 l

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Reft LCR 87-07

' STATE OF NEW JERSEY )

) SS.

. COUNTY OP. SALEM )

Corbin A. McNeill, Jr., being duly sworn according to law deposes

-and says:

I am Senior Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated AIAY 01 1987 , concerning Facility Operating License NPF-57 for Hope Creek Generating Station, is true to the best of my knowledge, information and belief.

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-Subscribpd and Sworn to-before me this-/5 & day of /y) u , 1987

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T'. Sot.arycPublic of New Jersey DELORt3D.HADODI A Notary Pubhc of New Jeney My Commssion Expres March 14,1990 My' Commission expires on-

PROPOSED CHANGE TO Ref. LCR 87-07 TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION DESCRIPTION OF CHANGE Renumber Technical Specifications Sections 3/4.3.7.3 through 3/4.3.7.10 per the attached marked-up pages and add a statement to the renumbered section 3/4.3.7.8 to indicate that the original material contained.in that section has been deleted, but that the section will remain blank so that succeeding sections revert to their original (Draft) numbering. Also, modify Section 4.11.2.6 and the Bases Section per the marked-up pages to reflect the revised numbering.

REASON FOR CHANGE The Draft and Low Power License Technical Specifications-for Hope Creek Station contained a section on Fire Detection Instrumentation that, as the result of a PSE&G request, was removed f rom the Technical Specifications as described in Section 9.5.1, Supplement No. 6 of NRC Safety Evaluation Report (NUREG 1048) for Hope Creek Station, when the Full Power Operating License was issued. All of the instrumentation sections that originally followed the fire detection instrumentation section were renumbered to avoid a sequential void in Revision 0 of the specifications.

A large number of existing station procedures, written prior to issuance of the Full Power Operating License, make reference, by section number, to various portions of the original (Draft and Low Power) Technical Specifications. To avoid a cumbersome review and rewrite of all procedures affected by the renumbering of the Technical Specifications in Revision 0, this amendment is being proposed. The requested changes will restore the numbering, for those specifications that are associated with the above procedural references, to that which was in place when the procedures were written.

Section 3/4.3.7.8, which will be left intentionally blank, may be utilized in the event that new instrumentation requirements are added to the Technical Specifications at

. some later date.

SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS This change does not involve a significant increase in the probability or consequences of any previously evaluated accident or malfunction of equipment important to safety The change is purely administrative in nature... renumbering existing Technical Specifications to intentionally permit an unused section to remain in the numbering sequence of the specifications.

Ref. LCR 87-07 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS (Cont'd)

This proposed change does not create the possibility of a new or dif ferent kind of accident from any previously e'~aluated v because there is no change.to existing plant equipment, procedures, operating parameters or to the existing wording of any limiting condition for operation or to any surveillance requirement in the Technical-Specifications.

This proposed change does not involve a'significant reduction in any margin of safety. Being a purely administrative change to the numbering of existing specifications, there..will be no impact on any margin of

. safety.

Based on the above, _we have determined that this proposed change does.not involve a Significant Hazards Consideration. Additionally, we suggest that this change conforms to example (i) of the guidance provided by the Commission in 48FR14870 of'the Federal Register for Amendments Not Likely To Involve A Significant Hazards Consideration, in that, the change is purely administrative in nature... making only typographical changes to make the specifications' ~ numbering agree.with existing station procedural references to those specifications.

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