AEP-NRC-2011-19, Commitment Change Notification for Steam Generator Bolting Inspection

Commitment Change Notification for Steam Generator Bolting Inspection

ML11166A068
Person / Time
Site:	Cook
Issue date:	06/06/2011
From:	Carlson M Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2011-19
Download: ML11166A068 (4)

Text

INDIANA MICHIGAN Indiana Michigan Power POWER One Cook Place Bridgman, MI 49106 A unit of American Electric Power IndianaMichiganPower.com June 6, 2011 AEP-NRC-2011-19 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Donald C. Cook Nuclear Plant Unit 1 Docket No.: 50-315 Commitment Change Notification for Steam Generator Bolting Inspection

References:

1. Letter from R. A. Hruby, Jr., Indiana Michigan Power Company, to Nuclear Regulatory Commission Document Control Desk, "Third Ten-Year Interval Inservice Inspection Program Relief Request ISIR-32," AEP-NRC-2009-53, dated September 15, 2009 (ML092680143)

2. Letter from R. A. Hruby, Jr., Indiana Michigan Power Company, to Nuclear Regulatory Commission Document Control Desk, "Response to Request for Additional Information Regarding Third Ten-Year Interval Inservice Inspection Program Relief Request ISIR-32,"

AEP-NRC-2010-20, dated February 16, 2010 (ML100500965)

3. Letter from R. J. Pascarelli, Nuclear Regulatory Commission, to J. N. Jensen, Indiana Michigan Power Company, "Donald C. Cook Nuclear Plant Unit 1 - Evaluation of Relief Request (ISIR-32) (TAC No. ME3204), "dated February 26, 2010 (ML100539516)

In Reference 1, Indiana Michigan Power Company (I&M) submitted a relief request from the American Society of Mechanical Engineers (ASME) code examination requirements associated with the Donald C. Cook Nuclear Plant (CNP), Unit 1. In that request, I&M proposed that a visual examination of the steam generator (SG) bolting would be performed at nominal operating temperature and pressure with insulation installed as an alternative to a volumetric examination during Unit 1 Cycle 23 (ULC23), the final refueling outage of the third inservice inspection (ISI) interval. The alternative examination was proposed due to the excessive personnel radiation exposure required to remove the SG manways solely for the examination. I&M committed to perform a volumetric examination during Unit 1 Cycle 24 (U1C24), the first refueling outage of the fourth ISI interval, when the manways will be removed for SG eddy current testing. I&M responded to a request for additional information (RAI) via Reference 2. The NRC authorized the proposed alternative as indicated in Reference 3.

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U.S. Nuclear Regulatory Commission AEP-NRC-2011-19 Page 2 I&M is revising the commitment to change the type of SG bolting examination that will be performed during U1C24. Instead of a volumetric examination, I&M will perform a surface examination. This alternative is permitted by ASME Code Case N-652-1, "Alternative Requirements to Categories B-G-1, B-G-2, and C-D Bolting Examination Methods and Selection Criteria,Section XI, Division 1,"

dated February 20, 2004. This Code Case is included in Table 1 "Acceptable Section Xl Code Cases" of Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1," Revision 15, dated October 2007.

This commitment change notification was processed in accordance with the I&M Commitment Management procedure. The review process follows that provided in NEI 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," dated July 1999.

There is a revised commitment in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.

Sincerely, Michael H. Carlson Vice President - Site Support Services MCS/jmr

Enclosure:

Regulatory Commitment

U. S. Nuclear Regulatory Commission AEP-NRC-2011-19 Page 3 c: J. T. King - MPSC, w/o attachment S. W. Krawec - AEP Ft. Wayne, w/o attachment MDEQ - WHMD/RPS, w/o attachment NRC Resident Inspector M. A. Satorius - NRC Region IIl P.K. Tam - NRC Washington DC W. Vallance - DLEG/BCC/BD

Enclosure to AEP-NRC-2011-19 REGULATORY COMMITMENT The following table identifies those actions 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 I&M will perform a surface examination of the Unit 1 Steam U1C24 (currently Generator Inlet and Outlet Primary Manway Studs during the scheduled for Fall 2011)

Unit 1 Cycle 24 (U1C24) refueling outage.