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Meeting info
Purpose
The U.S. Nuclear Regulatory Commission (NRC) and Indian Michigan Power Company (I&M or licensee) staff will discuss a proposed license amendment related to Title 10 of the Code of Federal Regulations, Part 50, Appendix A, General Design Criterion 4, dynamic response requirements using leak-before-break (LBB) methods for the Donald C. Cook Nuclear Power Station, Unit 1, on certain reactor coolant system piping. The discussion will include the licensee's clarification of its proposed approach using Westinghouse LBB methods.
Meeting Feedback
Meeting Dates and Times
02/27/19
1:00PM - 3:00PM

Meeting Location
NRC Headquarters
11555 Rockville Pike
HQ-OWFN-10B04
Rockville MD
Contact
Russell Haskell
(301) 415-1129

Robert Kuntz
(301) 415-3733

Participation Level
Category 1
NRC Participants
Russell Haskell, Office of Nuclear Reactor Regulation
External Participants
Helen Levendosky, Westinghouse
Michael Scarpello, Indiana Michigan Power Company
Docket Numbers - Facility Names
05000315 - D.C. Cook 1
Related Documents
ML19067A048 - 02/27/19 Summary of Public Teleconference with Indiana Michigan Power Co. (I&M) Re: Review of LAR for Approval of Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping (EPID-2019-LLA-0054).

ML19046A302 - 02/27/2019 NOTICE OF MEETING WITH INDIANA MICHIGAN POWER COMPANY RE: DONALD C. COOK, UNIT 1, LICENSE AMENDMENT REQUEST TO UTILIZE LEAK-BEFORE-BREAK TECHNOLOGY

Comments
Please request teleconference information from meeting contacts listed in this notification.

Page Last Reviewed/Updated Friday, November 19, 2021

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