ML17328A231

Application for Amend to Licenses DPR-58 & DPR-74,adding Tech Spec 3/4.9.15 & Revising Tech Specs 5.3.1,5.6.1.2 & 5.6.2 to Allow Westinghouse Fuel Assemblies W/Enrichments of Up to 4.95 Weight Percent U-235 to Be Received

ML17328A231
Person / Time
Site:	Cook
Issue date:	12/08/1989
From:	Alexich M Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	Murley T NRC/IRM
Shared Package
ML17328A232	List: ML17328A231 ML17328A233 ML19332G328
References
AEP:NRC:1071F, NUDOCS 8912210072
Download: ML17328A231 (6)

Text

ACCELERATED D UTION DEMON ATION SYSTEM "I

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: S912210072 DOC. DATE: 89/12/08 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2,=Indiana 6 05000316 AUTH. NAME AUTHOR, AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele ..

RECIP.NAME RECIPIENT AFFILIATION 8 MURLEY,T.E.

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Document Control Branch (Document Control Desk)

SUBJECT:

Application for amend to Licenses DPR-58 6 DPR-74,adding I Tech Spec 3/4.9.15.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution .S NOTES:

RECIPIENT ID CODE/NAME

,COPIES LTTR ENCL ID RECIPIENT CODE/NAME COPIES LTTR ENCL A]

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D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'ONTACT THE.DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR blAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19

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Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1071F Donald C. Cook Nuclear Plant Units 1 and 2 License No. DPR-58 and DPR-74 Docket No, 50-315 and 50-316 PROPOSED UNITS 1 AND 2 LICENSE CONDITIONS AND TECHNICAL SPECIFICATIONS CHANGES FOR UNIT 2 CYCLE 8 SPENT FUEL POOL AND NEW FUEL STORAGE VAULT U.S, Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley:

December 8, 1989

Dear Dr. Murley:

This letter and its attachments constitute an application for amendment to the license conditions and Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Units 1 and 2 ~ Specifically, we are proposing to add a new T/S 3/4 ' '5 and corresponding basis for both units, to revise T/S 5.3.1 (Fuel Assemblies) for Unit 2 only, to revise T/Ss 5.6.1.2 (Criticality-Spent Fuel) and 5.6.2 (Criticality-New Fuel) and the license conditions for both units. These changes are being made so that Westinghouse Electric Corp. fuel assemblies with enrichments of up to 4.95 weight percent U-235 may be received, In particular, these changes are required to allow delivery of the Unit 2 Cycle 8 fresh fuel assemblies with an enrichment of 4 ' weight percent U-235. The assemblies are currently scheduled to be shipped from Westinghouse's Columbia, SC, fabrication facility beginning June 3, 1990. Therefore, we request your approval of these proposed license conditions and T/S changes by June 1, 1990, so that fuel shipment will not be impacted.

The proposed changes are supported by criticality analyses performed by Westinghouse. The analyses are contained in Attachment 1.

Attachment 2 contains a description of the proposed license conditions and T/S changes and our 10 CFR 50.92 significant hazards consideration analysis. Attachment 3 contains the proposed revised license conditions and T/S pages.

We believe that the proposed license conditions and T/S changes will not result in (1) a significant change in the amount of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. This conclusion is based on the NRC staff's findings with

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Dr. T. E. Murley AEP:NRC:1071F regard to the environmental impact of extended burnup fuel, which were published in Volume 53, No, 39 of the Federal Register on February 29, 1988 (pp. 6040-6043).

In that Federal Register entry, the NRC staff concludes that:

...there are no significant adverse radiological or non-radiological impacts associated with the use of extended burnup fuel and that this use will not significantly affect the quality of the human environment. Therefore, pursuant to 10 CFR 51.31, the Commission has determined that an environmental impact statement need not be prepared for this action.

The NRC staff's evaluation covered fuel assembly enrichments up to 5.0 weight percent U-235 and fuel assembly average burnups up to 60,000 MWD/MTU. The Unit 2 Cycle 8 fresh fuel assemblies will be limited to 4.55 weight percent U-235 for storage in the new fuel storage vault, 4.95 weight percent U-235 for storage in the spent fuel pool, and at discharge will not exceed 56,000 MWD/MTU, and are therefore bounded by the staff's previous evaluation.

These proposed license conditions and T/S changes have been reviewed by the Plant Nuclear Safety Review Committee and will be r'eviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.

In compliance with the requirements of 10 CFR 50.91(b)(10), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and the Michigan Department of Public Health.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M. P. A exich Vice President ldp Attachments cc; D. H, Williams, Jr.

A. A. Blind - Bridgman R. C. Callen G. Charnoff A. B, Davis - Region III NRC Resident Inspector - Bridgman NFEM Section Chief

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~ i Dr. T. E. Murley AEP: NRC: 1071F bc: S. J. Brever/M. S. Ackerman/J. M. Nieto T. 0." Argenta/R. F. Kroeger P. A. Barrett - v/o J. G. Feinstein - w/o M. L. Horvath - Bridgman - v/o J. F. Kurgan - w/o

=D. H. Malin/T. A. Georgantis/V. Vanderburg/G. John J. J. Markovsky J. B. Shinnock - w/o S. H'. Steinhart/S, P. Hodge J. Giitter, NRC - Washington, D.C.

DC-N-6015.1 AEP:NRC:1071F

ATTACHMENT 1 TO AEP:NRC:1071F WESTINGHOUSE CRITICALITY ANALYSES