Document: NRC Regulatory Guide
Document ID: 5e2766ae-dd3b-4b1a-a6bb-48bde2dcbf97
Document Type: regulatory_guide
Title: Performance-Based Emergency Preparedness for Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization Facilities
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1808/ML18082A044.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.242
CFR Part: 
CFR Title: 

Content:
of licenses,” provides requirements for emergency plan changes. o 10 CFR 50.160 provides alternative performance-based EP requirements for an SMR, non- LWR, or NPUF applicant’s or licensee’s EP program. • 10 CFR Part 52 governs the issuance of ESPs, standard design certifications, COLs, standard design approvals, and manufacturing licenses for nuclear power facilities. o 10 CFR 52.1, “Definitions,” provides definitions applicable to EP programs. o 10 CFR 52.17, “Contents of applications; technical information,” describes the required contents of the site safety analysis report for an ESP. o 10 CFR 52.18, “Standards for review of applications,” describes the standards that will be used to review applications for an ESP. o 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report,” describes the technical information that must be included in the final safety analysis report for a COL application. Related Guidance The list of related guidance is provided to designers, applicants, and NRC staff to assist in the development and preparation of applications and their review. Although some guidance documents are written mainly for light-water nuclear power reactors, the designers and applicants may find the approaches described as useful information to aid in developing accident consequence assessments and source terms for their given designs and applications. The staff may use the guidance as applicable in the review of the applicants’ approaches for the given subject areas. Further information concerning consequence assessments and source terms is given in Appendix A and Appendix B, respectively. • RG 1.174, “An Approach for Using Probabilistic Risk Assessment In Risk-Informed Decisions on Plant Specific Changes to the Licensing Basis” (Ref. 3), describes an integrated decision making approach that the NRC has found acceptable. • RG. 1.183, “Alternative Radiological Source Terms for Evaluating