ML072890355

Proposal for Response to Small Break Loss-of-Coolant Accident Reanalysis Request for Additional Information

ML072890355
Person / Time
Site:	Cook
Issue date:	10/05/2007
From:	Peifer M Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC-7046-04
Download: ML072890355 (2)

Text

Z Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman, MI 49106 POVER AEPcom A unit of American Electric Power October 5, 2007 AEP:NRC:7046-04 10 CFR 50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001

SUBJECT:

Donald C. Cook Nuclear Plant Unit 1 Docket Nos. 50-315 Proposal for Response to Small Break Loss-of-Coolant Accident Reanalysis Request for Additional Information

References:

1. Letter from Mark A. Peifer, Indiana Michigan Power Company (I&M), to U. S.

Nuclear Regulatory Commission (NRC) Document Control Desk, "Small Break Loss-of-Coolant Accident Evaluation Model Reanalysis," AEP:NRC:7046, dated March 29, 2007 (ML071000431).

2. Letter from Peter S. Tam, NRC, to Mano K. Nazar, I&M, "D. C. Cook Nuclear Plant Unit 1 (DCCNP-1) - Request for Additional Information Regarding Re-analysis of Small-Break Loss-of-Coolant Accident (TAC MD5297)," dated August 10, 2007 (ML072050570).

Dear Sir or Madam:

By Reference 1, Ildiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Unit 1., provided the Nuclear Regulatory Commission (NRC) with the reanalyzed small break loss-of-coolant accident (SBLOCA) analysis to meet commitments made in accordance with 10 CFR 50.46(a)(3)(ii). The analysis used the Westinghouse NOTRUMP SBLOCA emergency core cooling system evaluation model methodology, which is the current methodology used for the Unit 1 SBLOCA analysis-of-record.

By Reference 2, the NRC sent a request for additional information (RAI) on the CNP Unit I SBLOCA reanalysis. The NRC staff requested a 60-day response to the RAI from the date of that letter. In a September 17, 2007, discussion with the NRC Project Manager, I&M requested additional time to respond to the RAI. The Project Manager requested I&M formally inform the NRC of a new date for responding to Reference 2.

I&M plans to respond to the Reference 2 RAI by February 29, 2008. The SBLOCA reanalysis was submitted in order to meet a 10 CFR 50.46 commitment using a methodology approved for use by the NRC for analyzing the CNP Unit 1 SBLOCA. Resources necessary to prepare the response to the RAI for the SBLOCA reanalysis are currently working on the license amendment request (LAR)

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U. S. Nuclear Regulatory Commission AEP:NRC:7046-04 Page 2 to submit, for NRC review and approval, the Unit I large break loss-of-coolant accident (LBLOCA) reanalysis using the best estimate methodology, ASTRUM. I&M is committed to submitting this reanalysis to the NRC by December 2007. These resources are not available for responding to an RAI on the SI3LOCA reanalysis, which uses an approved methodology, at the same time as the development of the Unit 1 LBLOCA reanalysis and LAR. As discussed with the Project Manager, no NRC response to this letter is required.

This letter contains no new or revised commitments. Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.

Sin ce

• Mark A. Pei Vice President - Site Support Services KS/jen c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J. T. King - MPSC MDEQ - WHMD/RPMWS NRC Resident Inspector P. S. Tam - NRC Washington, DC