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:
d May 25, 2023, the Commission approved the staff’s recommendation in SECY-22-0076, with edits, and provided directions to the staff. Specifically, the Commission directed that the proposed revision to the CCF policy (as amended by the SRM) be applied independent of the licensing pathway.  In SRM-SECY-10-0121, dated March 2, 2011, the Commission disapproved the staff’s recommendation to modify risk guidance for new reactors described in SECY-10-0121, “Modifying the Risk-Informed Regulatory Guidance for New Reactors,” dated September 14, 2010. The SRM reaffirmed that the existing safety goals, safety performance expectations, subsidiary risk goals and associated risk guidance (such as the Commission’s Policy Statement on the Regulation of Advanced Reactors (73 FR 60612; October 14, 2008) and Regulatory Guide (RG) 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis”), key principles, and quantitative metrics for implementing risk-informed decision-making are sufficient for new plants.  RG 1.62, “Manual Initiation of Protective Actions,” describes a method that the NRC staff considers acceptable for use in complying with the NRC’s regulations on the means for manual initiation of protective actions provided (1) by otherwise automatically initiated safety systems or (2) as a method diverse from automatic initiation.  Regulatory Issue Summary (RIS) 2002-22, Supplement 1, “Clarification on Endorsement of Nuclear Energy Institute Guidance in Designing Digital Upgrades in Instrumentation and Control Systems,” dated May 31, 2018, clarifies guidance for preparing and documenting qualitative assessments that can be used to evaluate the likelihood of failure of a proposed DI&C system or component modification.  RG 1.152, “Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants,” provides guidance on measures to ensure