Document: NRC Regulatory Guide
Document ID: 303ef13e-f2e6-41b2-be1a-56f2ba131bb9
Document Type: regulatory_guide
Title: Restart of a Nuclear Power Plant Shut Down by a Seismic Event
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003740093.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.167
CFR Part: 
CFR Title: 

Content:
PTIONS TO SECTION 6.3.4.1 OF EPRI NP-6695 1.1 Item (1) should read: If the calculated stresses from the actual seis mic loading conditions are less than the allow ables for emergency conditions (e.g., ASME Code Level C Service Limits or equivalent) or original design bases, the item is considered acceptable, provided the results of inspections and tests (Section 5.3.2) show no damage. 1.2 The second dashed statement of Item (3) should read: -An engineering evaluation of the effects of the calculated stresses on the functionality of the item. This evaluation should address all lo- cations where stresses exceed faulted allow ables and should include fatigue analysis for ASME Code Class 1 components and systems. 2. LONG-TERM EVALUATIONS Coincident with the long-term evaluations, the plant should be restored to its current licensing basis. Exceptions to this must be approved by the Director, Office of Nuclear Reactor Regulation. D. IMPLEMENTATION The purpose of this section is to provide guidance to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. Except in those cases in which the applicant pro poses an acceptable alternative method for complying with the specified portions of the Commission's regula tions, the method described in this guide will be used in the evaluation of applications for construction permits, operating licenses, combined licenses, or design certi fication submitted after January 10, 1997. This guide will not be used in the evaluation of an application for an operating license submitted after January 10, 1997, if the construction permit was issued prior to that date. Holders of an operating license or construction per mit issued prior to January 10, 1997, may voluntarily implement the methods described in this guide in com bination with the methods in Regulatory Guides 1.12, Revision 2, "Nuclear Power Plant Instrumentation for Earthquakes," and 1.166, "Pre-Earthquake Planning and Immediate Nuclear Power Plant