The purpose of this meeting, between Entergy Operations, Inc. (Entergy) and the U.S. Nuclear Regulatory Commission (NRC) staff, is to discuss Entergy's pre-submittal for a relief request for Grand Gulf Nuclear Station, Unit 1 (Grand Gulf). In accordance w

The purpose of this meeting, between Entergy Operations, Inc. (Entergy) and the U.S. Nuclear Regulatory Commission (NRC) staff, is to discuss Entergy's pre-submittal for a relief request for Grand Gulf Nuclear Station, Unit 1 (Grand Gulf). In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(z)(1), Entergy plans to propose an alternative to the requirements of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, Subsection ISTC-3522, "Category C Check Valves," and subparagraph ISTC-3630(a) under Subsection ISTC-3630, "Leakage Rate for Other Than Containment Isolation Valves," for 22 pressure isolation valves (PIVs) at Grand Gulf. The proposed alternative will request NRC approval to implement PIV testing at Grand Gulf on a performance-based frequency, consistent with the containment isolation valve testing process under 10 CFR Part 50, Appendix J, Option B.