ML022030118

Withdrawal of Proposed Alternatives to Requirements of Section XI of American Society of Mechanical Engineers Code

ML022030118
Person / Time
Site:	Cook
Issue date:	07/17/2002
From:	Greenlee S Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:2055-04, TAC MB3551, TAC MB3552
Download: ML022030118 (2)

Text

Indiana Michigan Power Company CoDk Nuear Pnt 500 Crde Drnve Bud'on, MI49107 61&65-11 INDIANA MICHIGAN POWER July 17, 2002 AEP:NRC:2055-04 10 CFR 50.55a Docket Nos. 50-315 50-316 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 WITHDRAWAL OF PROPOSED ALTERNATIVES TO THE REQUIREMENTS OF SECTION XI OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE (TAC Nos. MB3551 AND MB3552)

References:

1. Letter from S. A. Greenlee, Indiana Michigan Power Company, to U.S. Nuclear Regulatory Commission Document Control Desk, "Donald C. Cook Nuclear Plant Units I and 2 Proposed Alternatives to the Requirements of Section XI of the American Society of Mechanical Engineers Code," submittal C1201-02, dated December 6, 2001

2. Letter from S. A. Greenlee, Indiana Michigan Power Company, to U.S. Nuclear Regulatory Commission Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2 Proposed Alternatives to the Requirements of Section XI of the American Society of Mechanical Engineers Code - Request for Additional Information (TAC Nos. MB3551 and MB3552)," submittal AEP:NRC:2055, dated April 25, 2002 During the recent Unit 1 Cycle 18 and Unit 2 Cycle 13 refueling outages, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant Units 1 and 2 performed nondestructive examinations of each unit's reactor vessel head. In conjunction with the examinations, I&M submitted proposed alternatives to Section XI of the American Society of Mechanical Engineers Code for the repair of flaws under the provisions of

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U. S. Nuclear Regulatory Commission AEP:NRC:2055-04 Page 2 10 CFR 50.55a(a)(3)(ii). The proposed alternatives would allow the use of an ambient temperature automatic or machine gas tungsten arc weld temper bead process for certain repairs to J-groove welds on vessel head penetrations (VHPs),

and the use of the embedded flaw technique for repairs to J-groove welds on VHPs (Reference 1). Reference 2 responded to a Nuclear Regulatory Commission Request for Additional Information regarding the proposed alternatives.

No repairs were required following the examination of each unit's reactor vessel head. Therefore, I&M does not require approval of the proposed alternatives, and I&M is withdrawing the request.

This letter contains no new commitments. Should you have any questions, please contact Mr. Gordon P. Arent, Manager of Regulatory Affairs, at (269) 697-5553.

Sincerely A. Greenlee Director, Nuclear Technical Services RV/bjb c: K. D. Curry J. E. Dyer MDEQ - DW & RPD NRC Resident Inspector R. Whale