Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors

Resumen

The U.S. Nuclear Regulatory Commission (NRC or the Commission) requests public comment on draft license renewal interim staff guidance (LR-ISG), LR-ISG-2011-04, "Updated Aging Management Criteria for PWR Reactor Vessel Internal Components." This draft LR-ISG revises the guidance in the Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) and Generic Aging Lessons Learned (GALL) Report for the aging management of stainless steel structures and components exposed to treated borated water.