ML022030118
| 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, MI 49107 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
~AEIR d merica *" Lue*Rr Par/ncr
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