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:
ed for the siting evaluation. • Consider uncertainties related to the performance of the barriers commensurate with the scope of the analysis performed. • Demonstrate adequate defense in depth for confining and retaining radionuclides considering the uncertainties related to barrier performance. The NRC anticipates three types of advanced reactor applications: (1) non-LWR technologies using the LMP methodology (RG 1.233); (2) LWR technologies using a traditional major accident DG-4034, Appendix A, Page A-4 approach or a deterministic approach to assess the potential consequences from reactor accidents; and (3) non-LWR technologies not using the LMP methodology and choosing to use a traditional or a deterministic approach to establish the requirements for a containment-type barrier for limiting the release of radionuclides. The following sections provide guidance for estimating offsite consequences to inform the alternative population-related siting considerations for each of these types of applications. A-3.1 Regulatory Guide 1.233 Approach (non-LWRs)e For an applicant using a methodology like that described in RG 1.233, the results from the DBA analyses are used to determine or confirm the boundaries of the exclusion area and LPZ by comparing the calculated consequences against the requirements in 10 CFR 50.34(a)(1)(ii)(D) or the corresponding requirements in 10 CFR Part 52 (10 CFR 52.17(a)(1)(ix) for early site permits or 10 CFR 52.79(a)(1)(vi) for combined licenses). An applicant using this approach may need to request an exemption from the regulations in 10 CFR 50.34, “Contents of applications; technical information,” 10 CFR 52.17, “Contents of applications; technical information,” or 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report,” if the DBA does not involve the equivalent of significant core damage such as that resulting from a major accident. Those regulations require an assumed “major