ML052500307
| ML052500307 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/26/2005 |
| From: | Zwolinski J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:5046-02 | |
| Download: ML052500307 (3) | |
Text
Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place POWER BridgmanMI 49106 A unit of American Electric Power August 26, 2005 AEP:NRC:5046-02 10 CFR 50.46 Docket No: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1
SUMMARY
OF DONALD C. COOK NUCLEAR PLANT TELEPHONE CONFERENCE WITH REACTOR SYSTEMS BRANCH CHIEF
Reference:
Letter from James A. Gresham (Westinghouse) to Nuclear Regulatory Commission Document Control Desk (to the attention of J. S. Wermiel), "Fuel Criterion Evaluation Process (FCEP) Notification of the I5x 15 Upgrade Design (Proprietary/Non-Proprietary)," LTR-NRC-04-8, dated February 6,2004.
A representative from Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP), and representatives of the Nuclear Regulatory Commission (NRC) staff held a conference call on July 25, 2005, to discuss and clarify I&M's planned implementation of a Westinghouse fuel product which will address Unit 1 15x15 fuel fretting wear issues.
The Westinghouse fuel product is described in the referenced Fuel Criterion Evaluation Process notification letter. I&M summarized the effort CNP staff has devoted to reviewing the fuel product design and comparing the design to the CNP licensing basis.
I&M also noted the use of Westinghouse fuel designed and manufactured for use at the Indian Point Nuclear Generating Unit 2 and Unit 3. Based on these initial reviews of the fuel product, I&M believes the CNP Unit 1 fuel upgrade will not require prior NRC review and approval. The 15x15 Upgrade Fuel Design can be implemented for CNP Unit 1 in accordance with 10 CFR 50.59 and does not constitute a change to the 10 CFR 50.46 evaluation model.
It is I&M's understanding that the staff agreed with I&M's determination that the fuel upgrade would not require prior approval since the fuel upgrade has essentially no affect on the 10 CFR 50.46 model. The NRC staff emphasized the importance of documenting the 10 CFR 50.59 review to ensure prior NRC approval is not required.
ADUI
U. S. Nuclear Regulatory Commission AEP:NRC:5046-02 Page 2 The enclosure to this letter provides a listing of the telephone meeting participants.
This letter contains no new commitments. Should you have any questions concerning this subject, please contact Mr. Michael K. Scarpello, Supervisor of Licensing, at (269) 466-2649.
Sincerely, John A. Zwolinski Director, Safety Assurance Enclosure KAS/rdw c:
J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne, w/o attachments J. T. King - MPSC, w/o attachments J. E. Lyons - NRC Washington DC MDEQ - WHMD/HWRPS, w/o attachments J. A. Nakoski - NRC Washington DC NRC Resident Inspector B. W. Sheron - NRC Washington DC D. W. Spaulding - NRC Washington DC J. S. Wermiel - NRC Washington DC
Enclosure to AEP:NRC:5046-02 LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE ENHANCED FUEL ASSEMBLY GRID DESIGN July 25, 2005 Participants Jared Wermiel John Nak-oski C. Fred Lyon John Zwolinski Affiliations Nuclear Regulatory Commission (NRC)