ML043090409
| ML043090409 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/28/2004 |
| From: | Jensen J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:4054-10, BL-04-001, TAC MB3473, TAC MB3474 | |
| Download: ML043090409 (4) | |
Text
Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1395 INDIANA MICHIGAN POWER October 28, 2004 AEP:NRC:4054-10 10 CFR 50.54(f)
Docket Nos.
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, D. C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 NUCLEAR REGULATORY COMMISSION BULLETIN 2004-01 INSPECTION OF ALLOY 82/182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE PIPING CONNECTIONS AT PRESSURIZED-WATER REACTORS SUPPLEMENTAL RESPONSE (TAC NOS. MB3473 and MB3474)
Reference:
Letter from Joseph N. Jensen, Indiana Michigan Power Company (I&M) to Nuclear Regulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Nuclear Regulatory Commission Bulletin 2004-01, Inspection Of Alloy 82/182/600 Materials Used In The Fabrication Of Pressurizer Penetrations And Steam Space Piping Connections At Pressurized-Water Reactors, Sixty-Day Response," AEP:NRC:4054-07, dated July 26, 2004.
The referenced letter provided I&M's 60-day response to NRC Bulletin 2004-01.
Subsequent to that submittal, NRC personnel, on September 15, 2004, requested that I&M submit a supplemental response discussing I&M's plans to notify the NRC of I&M's actions should planned inspections identify circumferential cracking in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of NRC Bulletin 2004-01.
As such, I&M's response to NRC Bulletin 2004-01, Question (1)(c) is supplemented to state: "If circumferential cracking is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of NRC Bulletin 2004-01, I&M will develop plans to perform an adequate extent-of-condition evaluation, and I&M will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit."
fSlIO
U. S. Nuclear Regulatory Commission Page 2 AEP:NRC:4054-1 0 The commitment is provided in the attachment to this letter. Should you have any questions, please contact Mr. John A. Zwolinski, Safety Assurance Director, at (269) 466-2428.
Sincerely,
-leeh N. Jensen Site Vice President RV/rdw
Attachment:
J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP J. T. King, MPSC C. F. Lyon, NRC Washington, DC MDEQ - WHMD/HWRPS NRC Resident Inspector
U. S. Nuclear Regulatory Commission Page 3 AEP:NRC:4054-10 AFFIRMATION I, Joseph N. Jensen, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.
Indiana Michigan Power Company Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME TDAY DAY OF i
2004 Notary PuU0 -
-- Miy.Commission Expires DANIELLE M. BURGOYNE Notary Public, State of Michigan County of Berrien My Commission Expires Apr. 4, 2008 Acting in the County of
ATTACHMENT TO AEP:NRC:4054-10 REGULATORY COMMITMENT The following table identifies the action committed to by Indiana Michigan Power Company (I&M) in this document. Any other actions discussed in this submittal represent intended or planned actions by I&M. They are described to the Nuclear Regulatory Commission (NRC) for the NRC's information and are not regulatory commitments.
Commitment Date If circumferential cracking is observed in As required.
either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of NRC Bulletin 2004-01,.
I&M will develop plans to perform an adequate extent-of-condition evaluation, and I&M will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit.