ML20087B496

Forwards Application for Amends to License NPF-29, Revising TS Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident

ML20087B496
Person / Time
Site:	Grand Gulf
Issue date:	08/04/1995
From:	Meisner M ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20087B498	List: ML20087B496 ML20087B503 ML20087B506
References
GNRO-95-00090, GNRO-95-90, NUDOCS 9508080134
Download: ML20087B496 (3)

Text

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g[.'~fENTERGY Port Gtison MS 39150 Tel 601437 6470 ~

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' August 4, 1995-- tww huw Sa:af & Braulavry Arnn L

U.S.' Nuclear Regulatory Commission Mail Station P1-137 .

Washington, D.C. 20555 Attention: Document Control Desk q

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 s Fuel Handling Accident Operational Conditions 4 Proposed Amendment to the Operating License (PCOL-93/08 Revision 1)

Reference:

GNRO-94/00131, Fuel Handling Accident Operational Conditions, Proposed Amendment to the Operating License (PCOL-93/08), dated November 9,  !

e> 1994.

GNRO-95/00090

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Gentlemen:

Entergy Operations, Inc. is submitting by this letter a revision to a proposed amendment to

' the Grand Gulf Nuclear Station (GGNS) Operating License. The original request was j transmitted to you via GNRO-94/00131. This letter revises the original submittal by j updating the request to reflect implementation of the improved Technical Specifications on l March 20,1995. This revision also provides additional information concerning this submittal and incorporates generic improvements to the proposed Technical Specification I requirements as discussed with members of the NRC Staff during a meeting on July 20, i 1995.

The requested Technical Specification changes revise those specifications associated with various engineered safety feature (ESF) systems following a design basis fuel handling accident. The proposed changes affect conditions where irradiated fuel is handled in the primary or secondary containment and certain specifications related to performing core alterations. These changes are based on the recent re-analysis of the fuel handling

- accident for GGNS.

To reduce NRC Staff resource demands at the request of the NRC Staff, GGNS and the other BWR 6's (Clinton Power Station, Perry Nuclear Power Plant, and River Bend Station) met with the NRC Stoff on July 20,1995 and discussed the justification for the proposed '

changes and the generic aspects of the proposed changes to the Technical Specifications.

During this meeting the BWR 6's provided the NRC Staff with proposed changes to the NUREG-1434, BWR 6 Improved Standard Technical Specifications, Revision 1. The changes requested byrthis e

• letter are consistent with the proposed changes to  !

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August 4, 1995 l

GNRo-95/00090 page 2 of 3 NUREG-1434. The other BWR 6's when they request similar Technical Specification  !'

changes also plan to be consistent with the proposed changes to NUREG-1434.

Specifically, River Bend Station plans to submit the proposed changes to support having this change approved in time for their January 1996 refueling outage. To meet River Bend ,

Station's schedule, we request NRC Staff review and approval of this proposed change be completed by November 1,1995. We additionally request that the proposed changes be  !

added to NUREG-1434 to facilitate the review and approve process for the other BWR 6's.

This proposed amendment is being subtnitted as part of the cost beneficiallicensing action (CBLA) program established within NRR where increased priority is granted to licensee j requests for changes requiring NRC Staff review that involve high cost without a commensurate safety benefit. Entergy developed the proposed changes to decrease the operational burden placed on outage resources. We expect accrued cost reductions in excess of $500,000 over the remaining operating life of the plant without reducing safety margin.

Attachment 2 provides a detailed description of the proposed changes, justification, and the No Significant Hazards Considerations. Attachment 3 is a copy of the marked-up TS pages.

Based on the guidelines in 10CFR50.92, Entergy Operations has concluded that this proposed amendment involves no significant hazards considerations. Attachment 2 details the basis for this determination. The basis that proposed amendment involves no significant hazards considerations that was presented in Revision O of this requested change bounds the changes made in requested Technical Specifications by Revision 1. This letter clarifies the original evaluation by updating the evaluation to reflect implementation of the improved Technical Specifications on March 20,1995 and reflect the discussions with members of the NRC Staff during the meeting on July 20,1995.

In accordance with the provisions of 10CFR50.4, the signed original of the requested .

amendment is enclosed.  !

l Yours truly, ',',

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v LFD/BSF attachments: 1. Affirmation per 10CFR50.30 (1 page)

2. Proposed Change to the Operating Licensee, Fuel Handling Operational Conditions, GGNS PCOL 93/08 Revision 1 (12 pages)

3. Mark-up of Affected Technical Specifications and Bases (86 pages) cc: Mr. R. H. Bernhard (w/a)

Mr. H. W. Keiser (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

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August 4, 1995  ;

I I GNRo-95/OOO90 page 3 of 3 >

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cc: (continued) .

Mr. Stewart D. Ebneter (w/a) j Regional Administrator l U.S. Nuclear Regulatory Commission i Region ll l 101 Marietta St., N.W., Suite 2900 1 Atlanta, Georgia 30323' ,

i Mr. P. W. O'Connor, Project Manager (w/2) ;j Office of Nuclear Reactor Regulation l U.S. Nuclear Regulatory Commission Mail Stop 13H3 .

Washington, D.C. 20555 i Dr. Eddie F. Thompson (w/a) l State Health Officer . j State Board of Health i P.O. Box 1700 l Jackson, Mississippi 39205  ;{

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