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:
esign or effluent objectives. In some areas, local atmospheric conditions cause inversion, which severely limits DG-4034, Page 16 local atmospheric dispersion capabilities. Therefore, siting decisions should consider the likelihood of inversion due to local conditions. Engineered safety features can compensate for safety-related design-basis atmospheric dispersion characteristics that are unfavorable. Accordingly, section C.1.3 of this RG describes the NRC staff’s regulatory position on atmospheric dispersion of radiological effluents. 1.3 Exclusion Area and Low Population Zone In the event of a postulated accident at a commercial nuclear power station, radiological consequences for individual members of the public outside the station must be acceptably low. Defining exclusion areas and LPZs around the station is integral in achieving this goal. A reactor licensee is required to designate an exclusion area and to have authority to determine all activities within that area, including removal of personnel and property. In selecting a site for a commercial nuclear power station, it is necessary to provide an exclusion area in which the applicant has such authority. A reactor licensee is also required to designate an area immediately surrounding the exclusion area as an LPZ. The site selection process should account for this as well. 1.3.1 Relevant Regulations • 10 CFR 50.34a, “Design objectives for equipment to control releases of radioactive material in effluents— nuclear power reactors;” o 10 CFR 50.34(a)(1)(ii)(D)(1); o 10 CFR 50.34(a)(1)(ii)(D)(2); • 10 CFR 52.17 “Contents of application: technical information;” o 10 CFR 52.17(a)(1)(ix)(A); o 10 CFR 52.17(a)(1)(ix)(B); • 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report;” o 10 CFR 52.79(a)(1)(vi)(A); o 10 CFR 52.79(a)(1)(vi)(B); and • 10 CFR 100.21, “Non-seismic site criteria;” o 10 CFR 100.21(a). 1.3.2 Related Guidance • RG 1.183,