Document: NRC Regulatory Guide
Document ID: 239cc7c1-f2cb-46cc-945d-8009db28aa6c
Document Type: regulatory_guide
Title: General Site Suitability Criteria for Nuclear Power Stations + HISTORY - HISTORY 12/2023 – DG-4034 , Proposed Revision 4 12/2011 – DG-4021 , Proposed Revision 3 02/1995 – DG-4004, Second Proposed Revision 2 11/1992 – DG-4003, Proposed Revision 2 (Rev. 4)
Source: NRC Regulatory Guide Division 4
Source URL: https://www.nrc.gov/docs/ML2312/ML23123A090.pdf
Revision Date: 2023-10
Chapter: 
Section ID: RG-4.7
CFR Part: 
CFR Title: 

Content:
idance for addressing these characteristics. NUREG 2213 provides guidance on a suitable approach for capturing the uncertainties associated with determining the safe shutdown earthquake ground motion, as required by 10 CFR Part 100.23. ANS 2.27 provides the most recent guidance on the geologic investigations necessary to perform a probabilistic seismic hazard analysis (PSHA) for nuclear power facilities and ANS 2.29 provides the most recent guidance on performing a suitable PSHA for nuclear power facilities. 1.2 Atmospheric Extremes and Dispersion The potential effect of natural atmospheric extremes on the safety-related structures of a nuclear station should be considered. Site atmospheric conditions important to site suitability also relate to the calculation of radiation doses resulting from the airborne release of fission products from routine operations, anticipated operational occurrences, and postulated design-basis accidents. 1.2.1 Atmospheric Extremes The potential effect of natural atmospheric extremes (e.g., tornadoes, hurricanes, and exceptional icing conditions), regional climatology, and local meteorology on the safety-related structures of a nuclear station should be considered. 1.2.1.1 Relevant Regulations • 10 CFR Part 50, Appendix A, Criterion 2, “Design bases for protection against natural phenomena;” • 10 CFR 52.17, “Contents of applications; technical information;” • 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report.” DG-4034, Page 13 1.2.1.2 Related Guidance • RG 1.27, “Ultimate Heat Sink for Nuclear Power Plants” (Ref. 39); • RG 1.76, “Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants” (Ref. 40); • RG 1.221, “Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants” (Ref. 41); and • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition.” 1.2.1.3 Considerations,