ML040840495

Summary from Public Meeting Held February 24, 2004

ML040840495
Person / Time
Site:	Cook
Issue date:	03/16/2004
From:	Zwolinski J Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:4565-01
Download: ML040840495 (2)

Text

Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1373 INDIANA MICHIGAN POWER March 16, 2004 AEP:NRC:4565-01 Docket Nos: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2

SUMMARY

FROM PUBLIC MEETING HELD FEBRUARY 24, 2004 Indiana Michigan Power Company (I&M) would like to take this opportunity to thank the Nuclear Regulatory Commission (NRC) staff for the time spent with I&M and Framatome ANP, Inc. (FANP) during the public meeting regarding nuclear fuel supplier transition on Tuesday, February 24, 2004. I&M appreciates the candid feedback and interchange on the subject of the Donald C. Cook Nuclear Plant nuclear fuel supplier transition. To assure that I&M understands and fully meets the NRC staff's expectations clearly, I&M is providing a list of issues discussed during the February 24 meeting. In addition, I&M has discussed these issues with the NRC during telephone calls held on March 2, and March 12, 2004, and understands this list to be complete and correct, achieving a mutual goal of comprehensive and accurate communication on this critical project.

Issues:

1. CRITICALITY - NRC guidance is to comply with either 10 CFR 70.24 or 10 CFR 50.68.

2. DOSE ANALYSES - If the locked rotor analysis indicates fuel rods in departure from nucleate boiling, I&M will provide the appropriate dose analysis documentation to the NRC for review and approval with the second license amendment request (LAR) in June 2004.

3. NON-LOSS OF COOLANT ACCIDENT (LOCA) TRANSIENTS - Based on the discussion at the meeting, I&M will have available in Lynchburg, VA, the following non-LOCA transient analyses for NRC inspection: reactor cool down, over pressure, and reactivity event. The work will be completed approximately three months after the second LAR is submitted in June 2004,

U. S. Nuclear Regulatory Commission AEP:NRC:4565-01 Page 2 and available for your inspection in October 2004. The locked rotor non-LOCA transient analysis is scheduled to be submitted in June 2004 as previously communicated.

4. LARGE BREAK (LB) LOCA - I&M will review the dockets of other licensees LBLOCAs and incorporate the lessons learned from these submittals, and associated requests for additional information, to facilitate the NRC review, for the planned LBLOCA submittal in June 2004.

5. DISPOSITION OF EVENTS (DOE) - For each event, I&M will provide a brief description of the event, in the second LAR (June 2004), and why it was, or why it was not, analyzed. There will be specific reference to the topical report and methodology sections which support the DOE approach.

6. NON-IMPACT EVALUATION OF CO-RESIDENT FUEL - FANP will perform this evaluation on the coresident fuel.

There are no new commitments in this submittal. Should you have any questions, please contact Mr. Michael K. Scarpello, Supervisor of Nuclear Licensing, at (269) 697-5020.

Sincerely, J

John . Zwolinski Director of Design Engineering and Regulatory Affairs DB/rdw c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP Director, Office of Nuclear Reactor Regulations J. T. King, MPSC MDEQ - WHMD/HWRPS L. Raghavan, NRC Washington DC NRC Resident Inspector M. A. Shuaibi, NRC Washington DC J. F. Stang, Jr., NRC Washington DC