Document: NRC Regulatory Guide
Document ID: 2459a562-8984-421c-8058-d096dbb9617c
Document Type: regulatory_guide
Title: Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0314/ML031430373.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.201
CFR Part: 
CFR Title: 

Content:
de the appropriate guidance for implementing the monitoring, feedback, and corrective action processes to ensure that potential performance degradations will not invalidate the factor used in the risk sensitivity study. Further, when non-PRA methods are used, it is necessary for the licensee to demonstrate that the impact on core damage frequency (CDF) and large early release frequency (LERF) from changes in treatment of LSS SSCs is acceptably small. The NRC staff recommends that the industry develop a method, or methods, to demonstrate that this is the case. C. Specific Comments on Draft Revision C of NEI 00-04 1. Section 1.2 The fourth paragraph of this section states that the integrated decision-making process “...blends risk insights, new technical information and operational feedback....” The NRC staff interprets this phrase, and such similar phrases (e.g., Section 1.3 third guiding principle), as meaning that the integrated decision-making process must systematically consider the quantitative and qualitative information available regarding the various modes of plant operation and initiating events, including PRA, quantitative risk results and insights (e.g., CDF, LERF, and importance measures); deterministic; traditional engineering factors and insights (e.g., defense in depth, safety margins, containment integrity); and any other pertinent information (e.g., industry and plant-specific operational and performance experience, feedback, and corrective actions program) in the categorization of the SSCs. 2 2. Section 1.3 The second guiding principle states that deterministic or qualitative information should be used if no PRA information exists related to a particular hazard or operating mode. This principle is not to be interpreted to mean that deterministic or qualitative information should be used only when no PRA information exists. The NRC believes that the integrated decision-making process must systematically consider the quantitative and qualitative