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:
, “Federal Actions to Address Environmental Justice in Minority Populations and Low-Income Populations,” Federal Register, Vol. 59, No. 32, February 11, 1994, pp. 7629–7633.17 78. NRC, “Policy Statement on the Treatment of Environmental Justice Matters in NRC Regulatory and Licensing Actions,” Federal Register, Vol. 69, No. 163, August 24, 2004, pp. 52040–52048. 15 Copies of ASTM International standards may be purchased from ASTM, 100 Barr Harbor Drive, P.O. Box C700, West Conshohocken, PA 19428-2959; telephone (610) 832-9585. Purchase information is available through the ASTM website at http://www.astm.org. 16 Copies of U.S. Department of the Interior reports can be obtained from the Department at 1849 C Street, NW., Washington, DC 20240; telephone: (202) 208-3100; or electronically through the Department’s website at http://www.doi.gov. 17 Executive orders of the President of the United States are available electronically at http://www.whitehouse.gov. DG-4034, Appendix A, Page A-1 APPENDIX A Alternative Approaches to Address Population-Related Siting Considerations To demonstrate compliance with the United States Nuclear Regulatory Commission’s (NRC) regulatory requirements in Title 10 of the Code of Federal Regulations (10 CFR) 100.21, 10 CFR 50.34(a)(1), 10 CFR 52.17(a)(1)(ix), and 10 CFR 52.79(a)(1)(vi), as applicable, commercial nuclear power reactor siting analyses should account for the potential for radiological releases due to possible accident conditions. Historically, analyses for such releases have been based on regulatory guidance developed for large light-water reactor (LWR) technology (e.g., Regulatory Guide (RG) 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,”) which may not be applicable for many of the advanced reactor (e.g., non-LWR technologies and light-water small modular reactor) designs being developed. Because of the wide variety of potential advanced reactor