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:
a role in the prevention or mitigation of events. Many of the basic reactor characteristics have traditionally been described in Chapters 4, 5, and 6 of safety analysis reports. These chapters address the reactor, including fuel and reactivity control systems, the reactor coolant and connecting systems, backup cooling systems, and functional barriers for retaining radionuclides within the facility. The material in these chapters largely addresses the fundamental safety functions of reactivity and power control, heat removal, and radionuclide retention. The next set of information to be provided describes the fuel or fuel system boundary and primary system in terms of the limits on operation (e.g., values or ranges of values for key parameters) to prevent failures or degradation or to remain within the bounds of testing or qualification of related SSCs. These limits on operation thus establish the safety functions needed to prevent damage to barriers to the release of radionuclides (e.g., functions to maintain integrity of fuel cladding, coatings, or other fuel system boundary). This information is needed to address the NEI 18-04 methodologies and for the development of a mechanistic source term for the specific non-LWR design. As discussed in the various sections of NEI 18-04 and depicted in Figure 5-2, deterministic evaluations and PRAs inform design decisions and ultimately support the safety arguments presented in applications for licenses, certifications, and approvals for non-LWRs. The interrelationship between the LBEs and the derivation of both plant capabilities and programmatic controls are discussed in NEI 18-04 and non-LWR applicants that reference NEI 18-04 and this RG should reflect this interrelationship in the layout of the safety analysis report. The approach described in NEI 18-04 and this RG involves the assessment of event categories that extend from benign to severe. The analysis of AOOs, DBEs, and BDBEs plays an important role in defining safety