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:
EPRI reports may be obtained from the Electric Power Research Insti tute, EPRI Distribution Center, 207 Coggins Dr., RO. Box 23205, Pleasant Hill, CA 94523. The guLides wre Issued In the following ten broad divisions: 1. Power Reactors 2. Research and Test Reactors 3. Fuels and Materials Faclities 4. Environmental msd Siting 5. Materials end Plant Protection 6. Products 7. Transportation a. o=upational Health 9. Antirust nd Financial Review 10. General Single copies of regulatory guides may be obtained free of charge by writing the Office of Administration, Attention: Distribution and Mall Services Section, U.S. Nuclear Regulatory Commission, Washington. DC 20555-0001; or by fax at (301)415-2260. Issued guides may also be purchased from the National Technical Infomation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port "Royl Road, Springfield, VA 22161. EPRI NP-6695 has been supplemented to add in spections and tests as a basis for acceptance of stresses in excess of Service Level C and to recommend that en gineering evaluations of components with calculated stresses in excess of service Level D focus on areas of high stress and include fatigue analyses. C. REGULATORY POSITION After a plant has been shut down by an earthquake, the guidelines for inspections and tests of nuclear pow er plant equipment and structures that are in EPRI NP-6695, depicted in Figure 3-2 and specified in Sec tions 5.3.2, 5.3.3, and 5.3.4; the documentation speci fied in Section in 5.3.5 to be submitted to the NRC; and the long-term evaluations that are specified in Section 6.3, with the exceptions specified below, are acceptable to the NRC staff for satisfying the requirements in Para graph IV(a)(3) of Appendix S to 10 CFR Part 50. 1. EXCEPTIONS 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.,