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:
shed guidance for two general approaches for the development of accident radiological consequence analyses to address regulatory requirements related to reactor designs and reactor sites. One approach developed for non-LWR technologies involves the use of the methodology described in 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,” which is often referred to as the licensing modernization project (LMP) methodology for identifying and analyzing licensing-basis events, determining appropriate special treatments for plant structures, systems, and components (SSCs), and assessing defense in depth. The LMP methodology includes the assessment of potential consequences for a spectrum of event sequences using probabilistic risk assessment approaches and, as needed, event- specific or mechanistic consideration of the movement of radionuclides past various barriers. The second approach is the prescriptive and conservative source term design-basis accident (DBA) consequence analysis described in RG 1.183, which involves the modeling of containment performance to ensure that it limits offsite consequences assuming the introduction of a prescribed mix of radionuclides. For LWRs, various studies and analyses have defined the prescribed isotopic mix, magnitude, and physical and d SRM-SECY-20-0045, “Staff Requirements – SECY-20-0045 – Population-Related Siting Criteria for Advanced Reactors,” dated July 13,2022 (ML22194A885) DG-4034, Appendix A, Page A-3 chemical forms of radionuclides released to the containment or “source term” to bound events involving the breach of barriers upstream of the containment structure. In Figure 1, the two paths represent the two approaches to determining the releases of radionuclides for possible atmospheric dispersion and resultant doses to members of the