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:
results; this assessment must also address the potential impacts on the deterministic, traditional engineering (e.g., defense-in-depth), non-PRA type analyses (e.g., seismic margins), 15 and operating modes considerations (e.g., shutdown) of prior SSC categorizations. Further, any proposed changes in prior SSC categorizations must be documented, provided to the IDP, and determined to be appropriate by the IDP before recategorizing the SSC. This is not intended to obviate the need for the licensee to properly implement their corrective action program. NEI 00-04 identifies a number of reviews that are to be performed following revisions or updates to the PRA as part of a review of the SSC categorization. The NRC believes that the review of the updated PRA must include an independent review of the PRA update to ensure that it properly reflects the as-built, as-operated plant. In addition, the results of the risk sensitivity study of Chapter 8 must be confirmed to still be acceptable. 27. Appendix B This appendix provides an outline/example of the information to be provided to the NRC for those licensees implementing 10 CFR 50.69. Based on the resolution of other comments presented above, some aspects of this outline may need to be further enhanced or expanded. Therefore, at this time, the NRC staff cannot endorse that this outline contains the requisite level of information to satisfy the requirements of 10 CFR 50.69. Licensee submittals will be evaluated on a plant-specific basis to ensure that they properly implement the categorization process requirements of 10 CFR 50.69.