Document: NUREG-0800
Document ID: fe8ec6c2-e960-404c-854f-55c77bde1672
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2400/ML24005A077.pdf
Revision Date: 2024-05
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
oved for use by the NRC are met, and (2) safety analysis acceptance criteria in the licensing basis (e.g., FSAR, supporting analyses) are met or proposed revisions provide sufficient margin to account for uncertainty in the analysis and data. 3.4.1 Determining Consistency with NRC Policy and Guidance on Risk-Informed Decision-Making Point 2 of SRM-SECY-22-0076 states that applicants using a risk-informed approach must include an evaluation of the approach against the Commission’s policy and guidance, including any applicable regulations, for risk-informed decision-making. Point 2 also states that the NRC staff will review applications that use risk-informed approaches for consistency with established NRC policy and guidance on risk-informed decision-making, and Point 2 provides RG 1.174 as an example. BTP 7-19-30 Revision 9 — May 2024 RG 1.174 describes an approach that is acceptable to the NRC staff for developing risk-informed applications for a licensing-basis change. RG 1.174 references RG 1.200, which provides an approach for determining whether the base PRA (in total or in the portions that are used to support an application) is acceptable for use in regulatory decision-making. If an application uses a risk-informed approach to address a CCF, the reviewer should follow current NRC staff review guidance, as applicable, to confirm that the risk-informed approach is consistent with the Commission’s policy and guidance. The following examples provide NRC staff review guidance for applications that use a risk-informed approach for modeling DI&C systems in PRA models:  SRP Section 19.0, “Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,” provides review guidance for the design-specific PRA for a design certification and plant-specific PRA for a combined license, respectively. SRP Section 19.0 also provides guidance for reviewing DI&C system risk assessments for new reactors.  SRP Section 19.1, “Determining the Technical