Document: NRC Regulatory Guide
Document ID: acab976c-e936-49be-8c59-865767973599
Document Type: regulatory_guide
Title: Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2319/ML23194A194.pdf
Revision Date: 2023-09
Chapter: 
Section ID: RG-1.253
CFR Part: 
CFR Title: 

Content:
the CP applicant may use the PRA to demonstrate, in part, that the following regulations in 10 CFR Part 50 have been met: 1. 10 CFR 50.34(a)(1)(ii), which states, “It is expected that reactors will reflect through their design, construction and operation an extremely low probability for accidents that could result in the release of significant quantities of radioactive fission products.” 2. 10 CFR 50.34(a)(4), which requires the PSAR to include, “[a] preliminary analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility and including determination of the margins of safety during normal operations and transient conditions anticipated during the life of the facility, and the adequacy of structures, systems, and components provided for the prevention of accidents and the mitigation of the consequences of accidents.” Commission Policy Positions The Commission’s “Policy Statement on the Regulation of Advanced Reactors” (Volume 73 of the Federal Register (FR), page 60612 (73 FR 60612); October 14, 2008) (Ref. B-10) cites the following policy statements that express Commission expectations for use of the PRA. Specifically: 1. The advanced reactor policy statement articulates the expectation that advanced reactor designs will comply with the Commission’s safety goal policy statement (“Safety Goals for Operations of Nuclear Power Plants; Policy Statement; Republication,” 51 FR 28044; August 4, 1986, as corrected and republished at 51 FR 30028; August 21, 1986) (Ref. B-11). The safety goal policy statement broadly defines an acceptable level of radiological risk and establishes two qualitative safety goals which are supported by two quantitative objectives. Consistent with the safety goal policy statement, PRA is an acceptable tool for assessing conformance with the underlying purposes of the