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, 1PM - 3PM EST
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
Office of Nuclear Reactor Regulation
External Participants
Indiana Michigan Power Company
Westinghouse
Michael Scarpello
Joe Tanko
David Wrona
Russell Haskell
Gerry Purciarello
Helen Levendosky
Docket Numbers - Facility Names
05000315 - D.C. Cook 1
Comments
Please request teleconference information from meeting contacts listed in this notification.