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:
ve established. The system designs and safety evaluations may demonstrate compliance with or justify exemptions from specific NRC regulations and identify where design-specific regulatory controls are warranted. The guidance in this RG for licensing non-LWR technologies will need to be supplemented by other RGs and documents to help non-LWR developers and the NRC staff prepare and review applications for licenses, certifications, and approvals. An important area to expand upon in other guidance documents is how SSC capabilities and reliabilities will be monitored and maintained during plant operations. Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of technical reports, safety guides, and standards constituting a high level of safety for protecting people and the environment. IAEA guides present international good practices and identify best practices to help users striving to achieve high levels of safety. This RG and the NEI technical document endorsed by it contain guidance similar to guidance prepared by IAEA on topics such as the design of nuclear power plants and DID. This RG and the NEI technical document are, with the exception of technology-specific topics, generally consistent with the principles and guidance in the IAEA document series, including the IAEA documents listed below. • Safety Fundamentals (SF), No. SF-1, “Fundamental Safety Principles” (Ref. 21) • General Safety Requirements (GSR), No. GSR Part 4, “Safety Assessment for Facilities and Activities” (Ref. 22) 3 The chapter- and section-level organization of safety analysis reports for LWRs is described in guidance such as RG 1.70, RG 1.206, and NUREG-0800. DG-1353, Page 9 • Specific Safety Requirements (SSR), No. SSR- 2/1, “Safety of Nuclear Power Plants Design” (Ref. 23) • Specific Safety Guide (SSG), No. SSG-2, “Deterministic Safety Analysis for Nuclear Power Plants” (Ref. 24) • No. SSG-3,