ML17328A928

Application for Amends to Licenses DPR-58 & DPR-74,changing Tech Spec Section 5.6.1.1 Re Spent Fuel Pool During Unit 2 Cycle 9 Operation

ML17328A928
Person / Time
Site:	Cook
Issue date:	02/15/1991
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17328A929	List: ML17328A928 ML17328A930 ML17328A931
References
AEP:NRC:1071N, NUDOCS 9102250091
Download: ML17328A928 (8)

Text

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ACCESSION NBR:9102250091 DOC.DATE: 91/02/15 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT- AFFILIATION 'R MURLEY,T.E. Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to Licenses DPR-58 & DPR-74,changing Tech Spec Section 5.6.1.1 re spent fuel pool during util D Cycle 9 operation.

DISTRIBUTION CODE: AOOID COPIES RECEIVED: R t ENCL I SIZE: cS +

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES CIPIE ID CODE/NAME LTTR ENCL ID CODE/NAME D PD3-1 LA 1 1 PD3-1 PD COLBURN,T. 2 2 D INTERNAL: NRR/DET/ECMB 9H 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTSBll 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 O C/LFMB 1 0 OGC/HDS2 1 0 E~Z% Q Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: DR 1 1 NSIC 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP VS TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16

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indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP: NRC: 1071N Donald C. Cook Nuclear Plant Units 1 and 2 License Nos. DPR-58 and DPR-74 Docket Nos. 50-315 and 50-316 PROPOSED TECHNICAL SPECIFICATIONS CHANGES FOR UNITS 1 AND 2 REGARDING THE SPENT FUEL POOL DURING UNIT 2 CYCLE 9 OPERATION U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley:

February 15, 1991

Dear Dr. Murley:

This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C.

Cook Nuclear Plant Units 1 and 2. The proposed T/Ss changes affect Units 1 and 2 T/S Section 5.6.1.1, "Criticality - Spent Fuel,"

subparagraphs c.l and c.2. Subparagraph c.l, which identifies storage requirements for Region 1 of the spent fuel pool, has been modified; the existing subparagraph c.2, which identifies storage requirements for the boundary between Regions 1 and 2, has been slightly modified and renumbered as c.3; and a new subparagraph c.2 that identifies storage requirements for Region 2 has been added.

In addition, Figure 5.6-1 has been revised and Figure 5.6-2 is being added.

An administrative change is being requested to page 2 of Unit 2 Table 5.7-1 to correct the table number, This last change is purely editorial and is therefore not included in the significant hazards consideration analysis. Also, the pages for both units have been renumbered as necessary and any pages required to be submitted because of a change in page number have been included.

These changes would revise the 3-out-of-4 fuel storage scheme for highly reactive fuel assemblies currently allowed in Region 1 by the T/Ss. Currently, Westinghouse fuel assemblies with fuel enrichments greater than 3.95 weight percent U-235 and burnup less than 5,550 MWD/MTU are required to be stored in Region 1 of the spent fuel pool in a 3-out-of-4 array in which 1 of any 4 fuel storage cells of a symmetric arrangement must remain empty. The proposed changes will enable us to better utilize remaining open fuel pool storage 9102250091 9102i5 PDR ADOCK 05000315

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Dr. T. E. Murley AEP: NRC: 1071N locations in Region 1 by allowing 2-out-of-4 arrays of highly reactive fuel with adequately burnt fuel in a checkerboard pattern (see Figures 5 '-1 and 5.6-2) and by eliminating the required empty storage cells'he proposed changes in subparagraphs c.l and c.3 for Region 1 and the boundary between Regions 1 and 2 are supported by criticality analyses performed by Westinghouse, which are contained in . The proposed change in subparagraph c.2 is a clarification of the storage requirements for Region 2, which have not changed since our previous submittal AEP:NRC:1071F, Attachment 2 contains a description of the proposed T/Ss changes and our 10 CFR 50.92 significant hazards consideration analysis. Attachment 3 contains the proposed, revised T/Ss pages. Attachment 4 contains a copy of the existing T/Ss pages marked-up to reflect the changes proposed in this submittal. The T/Ss that we are proposing to revise with this submittal are not impacted by any other requests currently pending NRC review and approval.

We believe that the proposed T/Ss 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 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 wi11 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 9 fresh fuel assemblies will be limited to 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 T/Ss changes have been reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee.

Dr. T. E. Murley AEP: NRC: 1071N In compliance with the requirements of 10 CFR 50.91(b)(10), copies of this letter and its attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health.

Approval of this change is requested to accommodate storage of Unit 2 Cycle 9 fuel in the spent fuel pool, which is expected to be required approximately February 1992.

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, Ale ich Vice President ldp Attachments cc: D. H, Williams, Jr.

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

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Dr. T. E. Murley AEP:NRC:1071N bc: S. J. Brewer/T. R. Satyan-Sharma/J. M. Nieto T. 0. Argenta/R. F. Kroeger w/o ,

J. G. Feinstein - w/o M. L. Horvath - Bridgman - w/o J. F. Kurgan - w/o D. H. Malin/T. A. Georgantis/G. John/E. Neymotin J. J. Markowsky w/o J. B. Shinnock - w/o S. H. Steinhart/S. P. Hodge w/o B. Holian, NRC - Washington, D.C.

DC-N-6015.1 w/o AEP:NRC:1071N