ML20217C373

Application for Amends to Licenses NPF-2 & NPF-8,allowing Use of VANTAGE-5 Fuel in Reactor Operation Planned to Be Submitted at Future Date

ML20217C373
Person / Time
Site:	Farley
Issue date:	07/01/1991
From:	Woodard J ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217C378	List: ML20217C373 ML20217C388 ML20217C419
References
NUDOCS 9107150246
Download: ML20217C373 (2)

Text

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J. D. Woodard /\lithilillil POWCf weenme m ne Iltney Prowl  !% 2 ;" ' nth 79 ,r July 1, 1991 Docket Nos. 50-348 10CFR50.90 50-364 U.S. Nuclear Regulstory Commission ATIN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Fuel Enrichment increase Amendment Gentlemen:

In order to implement ; long-term fuel management strategy for Farley Nuclear Plant Units 1 and 2, Alabama Power Company plans to use the Westinghouse VANTAGE-5 fuel design in both units starting with Unit 2 Cycle 9 and Unit 1 Cycle 12. In support of this effort, plant-specific evaluations and analyses have been performed to qualify the new fuel and spent fuel storage racks for storage of 0FA and VANTAGE-5 fuel. These evaluations and analyses include 0FA and VANTAGE-5 fuel enrichments of up to 5.05 w/o (includes 0.05 w/o manufacturing uncertainty) in order to provide the maximum flexibility in core designs. Support for implementing the reanalysis is based on a plant-specific criticality analysis of the spent fuel racks, taking credit for the presence of Integral Fuel Burnable Absorbers (IFBA) in 0FA and VANTAGE-5 fuel. Thus, Alabama Power Company proposes that the Farley Nuclear Plant Units 1 and 2 Technical Specifications be amended by revising the design features requirements to allow for the use of up to 5.05 w/o (includes 0.05 w/o manufacturing uncertainty) U-235 0FA and VANTAGE-5 fuel in the reactor core and spent fuel and new fuel pit storage racks.

A request for Technical Specifications amendments to allow for the use of VANTAGE-5 fuel in reactor operation is planned to be submitted at a future i date. Since VANTAGE-5 fuel must be received on site several weeks prior to reactor operation, this amendment is being requested at this time to allow for receipt of the fuel. Approval of the future VANTAGE-5 submittal will allow for operation of the reactor with VANTAGE-5 fuel.

The analysis of the spent fuel racks shows that Westinghouse 17x17 0FA and l 17x17 VANTAGE-5 fuel assemblies with enrichments up to 3.95 w/o can be safely stored in the spent fuel racks utilizing all locations. OFA and VANTAGE-5 enrichments above 3.95 w/o and up to 5.05 w/o can also be stored j' in the spent fuel racks, provided credit for IFBA is taken. In addition, it is shown that Westinghouse 17x17 0FA and 17x17 VANTAGE-5 fuel assemblies with enrichments up to 4.85 w/o can be safely stored in the fresh fuel racks utilizing all locations. Storage of 0FA and VANTAGE-5 fuel with enrichments above 4.85 w/o and up to 5.05 w/o is shown to be acceptable by 9107150246 910701 PDR P

ADOCK 05000348 I PDR l L

U.S. Nuclear Regulatory Commission Page 2 taking credit for the same IFBAs which are required to satisfy the spent fuel rack limit. Use of the remaining current Westinghouse 17xl7 low parasitic (LOPAR) fuel assemblies at Units 1 and 2 will continue to be restricted to 4.3 w/o as the current Technical Specifications allow. No IFBAs are necessary to support the LOPAR fuel enrichment limit. All enrichments discussed above include 0.05 w/o manufacturing uncertainty.

The proposed changes to the Technical Specifications are provided in Attachment 1. The technical justification for the changes to the Technical Specifications is provided in Attachment 2 (non-proprietary). ,

Farley Nuclear Plant Unit 2 is presently scheduled to shut down for the l eighth refueling outage in March 1992. The earliest delivery of VANTAGE-5 l fuel to support this outage is presently scheduled for January 1992. In order to allow fuel receipt based on this schedule, Alabama Power Company requests that the NRC review and approve these proposed changes by December 13, 1991.

Alabama Power Company has determined that the proposed changes do not involve a significant hazards consideration. In accordance with 10 CFR 50.92, a significant hazards consideration evaluation is provided as Attachment 3. I Alabama Power Company's Plant Operations Review Committee has reviewed the proposed changes, and the Nuclear Operations Review Board will review the changes at a future meeting. A copy of these proposed changes is being sent to Dr. C. E. Fox, the Alabama State Designee, in accordance with 10 CFR 50.91 (b)(1).

If you have any questions, please advise.

Respectfully submitted, Alabama Power Company

( );n Woodard JDW: RAH / gps Attachments 1,2,3 SWORN TO AND SUBSCF' BED BEFORE ME 1

l cc: Mr. S. D. Ebneter THIS / DAY OF G'(1991 l Mr. S. T. Hoffman Mr. G. F. Maxwell --j/,

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/ fw[ ir, Dr. C. E. Fox '

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