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:
o new reactor applicants and licensees under 10 CFR Part 50 or 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” DG-1389, Page 2 Applicable Regulations • 10 CFR Part 50 provides regulations for licensing production and utilization facilities. o 10 CFR 50.67, “Accident Source Term,” allows applicable licensees to voluntarily revise the accident source term used in design basis radiological consequences analyses. A licensee who seeks to revise its current accident source term shall apply for a license amendment under 10 CFR 50.90. It also allows the NRC to issue these amendments if the applicant’s analysis demonstrates with reasonable assurance that certain dose reference values are met. o 10 CFR Part 50, Appendix A, “General Design Criteria [GDC] for Nuclear Power Plants,” Criterion 19, “Control Room,” requires that a control room be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss- of-coolant accidents (LOCAs). It also states that adequate radiation protection is provided to permit access and occupancy of the control room under accident conditions. o 10 CFR 50.34, “Contents of Applications; Technical Information,” requires that each applicant for a construction permit or operating license must provide an analysis and evaluation of the design and performance of structures, systems, and components (SSCs) of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. This regulation also requires applicants to provide an analysis of the proposed site. o A holder of an operating license 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. • 10 CFR Part 52 governs the issuance of early site permits,