Document: NRC Regulatory Guide
Document ID: db0c5d18-2d27-4720-8935-40b402e52f9a
Document Type: regulatory_guide
Title: 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 + HISTORY - HISTORY 05/2019 – Issued DG-1353 , Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1831/ML18312A242.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.233
CFR Part: 
CFR Title: 

Content:
rts supporting COLs. o 10 CFR 52.137, “Contents of applications; technical information,” describes the information to be included in final safety analysis reports supporting SDAs. o 10 CFR 52.157, “Contents of applications; technical information in final safety analysis report,” describes the information to be included in final safety analysis reports supporting MLs. Related Guidance, Communications, and Policy Statements • “Policy Statement on the Regulation of Advanced Reactors” (Volume 73 of the Federal Register, page 60612, October 14, 2008) (Ref. 3), establishes the Commission’s expectations related to advanced reactor designs to protect the environment and public health and safety and promote the common defense and security with respect to advanced reactors. • RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)” (Ref. 4), provides detailed guidance to the writers of safety analysis reports to allow for the standardization of information the NRC requires for granting construction permits and operating licenses. DG-1353, Page 3 • RG 1.181, “Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)” (Ref. 5), provides methods the NRC staff finds acceptable for complying with the provisions of 10 CFR 50.71(e), requiring periodic development of updates to final safety analysis reports. • RG 1.201, “Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance” (Ref. 6), provides guidance for complying with the Commission’s requirements in 10 CFR 50.69,” Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors,” with respect to the categorization of SSCs that are considered in risk-informing special treatment requirements. • RG 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition)” (Ref. 7), provides