ML17320A412
| ML17320A412 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/28/1983 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17320A413 | List: |
| References | |
| AEP:NRC:0745B, AEP:NRC:745B, NUDOCS 8303080141 | |
| Download: ML17320A412 (5) | |
Text
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INDIANA R MICHIGAN ELECTRIC COMPANY P. O.
BOX 18 BOWLING GR E EN STATION NEW YORK, N. Y. 10004 February 28, 1983 AEP:NRC:0745B Donald C. Cook Nuclear Plant Unit Nos.
1
& 2 Docket No. 50-315 and 50-316 License No. DPR-58 and DPR-74 FUEL STORAGE TECHNICAL SPECIFICATION CHANGE REQUEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter and its Attachments request changes to the D.
C.
Cook Unit 1 and 2 "Appendix A" Technical Specifications.
These changes will permit the storage of the Westinghouse 15xl5 Optimized Fuel Assembly (OFA) design fuel in the D.
C.
Cook new fuel storage area and spent fuel pool.
A change to the maximum reload fuel enrichment in Unit 1 is also being requested.
Attachment No.
1 is a summary of the new and spent fuel storage array criticality safety analyses performed by Westinghouse in support of the storage of the higher enrichment fuel assemblies.
Attachment No.
2 contains revised Technical Specifications 5.6.1.2 and 5.6.2 for both Unit' and Unit 2.
These Technical Specifications pertain to the criticality criteria for the spent and new fuel storage area.
Attachment 2 also proposes a
revised Technical Specification 5.3.1 which limits the maximum U-235 enrichment of the Unit 1
fuel assemblies.
The Technical Specifications 5.6.1.2 and 5.6.2 are being changed to include Type V
fuel which is the Westinghouse 15xl5 Optimized Fuel Assembly with a maximum enrichment of 4,0 w/o U-235.
All proposed changes to the Technical Specifications have been indicated by a vertical line on the right hand side of the page.
These Technical Specifications changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee (NSDRC) at their next scheduled meeting.
Our letter No.
AEP:NRC:0745A, dated February 7, 1983, transmitted to you the Class III fee levied by the NRC for the review of the Cycle 8 reload for Unit 1.
The request contained in this letter is part of that review
- and, therefore, no fee is required by this submittal.
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This document has been prepared following corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, RSH;mm R.
S. Hunter Vice President cc:
John E. Dolan N. P. Alexich R.
W. Jurgensen W.
G. Smith, Jr.
Bridgman R. C. Callen G. Charnoff NRC Resident Inspector at Cook Plant - Bridgman