Document: NRC Regulatory Guide
Document ID: 4d46a966-d280-43da-9b03-8b0abe7b29ce
Document Type: regulatory_guide
Title: Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2120/ML21204A065.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.183
CFR Part: 
CFR Title: 

Content:
can, in accordance with 10 CFR 50.67, voluntarily revise the accident source term used in design basis radiological consequence analyses. • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. 10 CFR Part 52, Section 52.47, “Contents of Applications; Technical Information,” and Section 52.79, “Contents of Applications; Technical Information in Final Safety Analysis Report,” also require applicants of standard design certification and combined license applicants to provide a final safety analysis report (FSAR) that presents a safety analysis of the SSCs as a whole and to perform an evaluation of the offsite radiological consequences from accidents. 10 CFR Part 52 applicants and licensees are not required to comply with 10 CFR 50.67; however, those applicants and licensees may find that this guidance is useful for performing evaluations of fission product releases and the radiological consequences of LWR DBAs. Although the source term information is specific to LWR designs, this guide could provide useful information on radiological consequence analysis for non-LWR designs. • A holder of a renewed license under 10 CFR Part 54 whose initial operating license was issued before January 10, 1997, can, in accordance with 10 CFR 50.67 voluntarily revise the accident source term used in design basis radiological consequence analyses. DG-1389, Page 3 Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (SRP) (Ref. 5), provides guidance to the NRC staff for review of safety analysis reports submitted as part of license applications for nuclear power plants. o SRP Section 15.0.1, “Radiological Consequence Analyses Using Alternative Source Terms,” provides guidance to the NRC staff for reviewing the radiological consequence analyses for