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:
censes (COLs), standard design approvals, and manufacturing licenses for nuclear power facilities licensed under section 103 of the Atomic Energy Act of 1954, as amended (Ref. 10), and Title II of the Energy Reorganization Act of 1974 (Ref. 11). Some of the 10 CFR Part 52 criteria are directly related to site characteristics, as well as to events and conditions outside the nuclear power unit. • 10 CFR Part 100 requires the NRC, in determining the acceptability of a site for a nuclear power reactor, to consider population density; use of the site environs, including proximity to manmade hazards; and the physical characteristics of the site, including seismology, meteorology, geology, and hydrology. Particularly relevant sections are 10 CFR 100.20, “Factors to be considered when evaluating sites;” 10 CFR 100.21, “Non-seismic site criteria;” and 10 CFR 100.23, “Geologic and seismic siting criteria.” Related Guidance • RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants” (Ref. 12), identifies requirements for safety-related site characteristics. • RG 1.206, “Applications for Nuclear Power Plants” (Ref. 13), provides guidance on the format and content of applications for nuclear power plants submitted to the NRC under 10 CFR 52. • RG 1.233, “Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors” (Ref. 14), provides guidance to nuclear reactor designers, applicants, and licensees of advanced non-light-water reactor (non-LWR) designs applying for permits, licenses, certifications, and approvals under 10 CFR Part 50 and 10 CFR Part 52. DG-4034, Page 3 • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (Ref. 15), provides the criteria used by the NRC staff for reviewing