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, dynam

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.