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Énergie et environnement · 20/03/20121 min de lecture
Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors
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Résumé
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.
Langue originale de la source: Federal Register — Nuclear Regulatory CommissionOuvrir le communiqué original →