Document: NRC Regulatory Guide
Document ID: 7d480029-59df-44fe-9db8-c1c86566dac9
Document Type: regulatory_guide
Title: Operation and Maintenance Code Case Acceptability, ASME OM Code (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2219/ML22196A063.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.192
CFR Part: 
CFR Title: 

Content:
to the Licensing Basis” (Ref. 7). (3) Section 4.4.4, “Defense in Depth,” of the OM Code Case must be consistent with the guidance contained in Sections 2.2.1, “Defense-in-Depth Evaluation,” and 2.2.2, “Safety Margin Evaluation,” of RG 1.175, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing” (Ref. 8). (4) Implementation of Section 4.5, “Inservice Testing Program,” and Section 4.6, “Performance Monitoring,” of the OM Code Case must be consistent with the guidance pertaining to IST of pumps and valves provided in Section 3.2, “Program Implementation,” and Section 3.3, “Performance Monitoring,” of RG 1.175. Testing and performance monitoring of individual components must be performed as specified in the risk-informed components OM Code Cases (e.g., OMN-1, OMN-4, OMN-7, and OMN-12, as modified by the conditions discussed in this RG). (5) Implementation of Section 3.2, “Plant Specific PRA,” of the OM Code Case must be consistent with the guidance that the owner is responsible for demonstrating and justifying the technical adequacy of the probabilistic risk assessment (PRA) analyses used as the basis to perform component risk ranking and for estimating the aggregate risk impact. RG 1.200, “Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities” (Ref. 9), provides guidance for determining the technical adequacy of the PRA used in a risk-informed regulatory activity. RG 1.201, “Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance” (Ref. 10), describes one acceptable method to categorize the safety significance of an active component, including methods to use when a plant-specific PRA that meets the appropriate RG 1.200 capability for specific hazard group(s) (e.g., seismic and fire) is not available. (6) Section 4.2.4, “Reconciliation,” Paragraph (b), is not endorsed. The expert panel may not