Document: 10 CFR Part 50
Document ID: 94032a42-694d-452c-a4bf-3906aee6f0b7
Document Type: cfr
Title: Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
Source: 10 CFR Part 50
Source URL: https://www.ecfr.gov/current/title-10/part-50/section-50.69
Revision Date: 
Chapter: 
Section ID: 50.69
CFR Part: 50
CFR Title: 10

Content:
( ii ) A description of the measures taken to assure that the quality and level of detail of the systematic processes that evaluate the plant for internal and external events during normal operation, low power, and shutdown (including the plant-specific probabilistic risk assessment (PRA), margins-type approaches, or other systematic evaluation techniques used to evaluate severe accident vulnerabilities) are adequate for the categorization of SSCs. ( iii ) Results of the PRA review process conducted to meet § 50.69(c)(1)(i) . ( iv ) A description of, and basis for acceptability of, the evaluations to be conducted to satisfy § 50.69(c)(1)(iv) . The evaluations must include the effects of common cause interaction susceptibility, and the potential impacts from known degradation mechanisms for both active and passive functions, and address internally and externally initiated events and plant operating modes (e.g., full power and shutdown conditions). ( 3 ) The Commission will approve a licensee's implementation of this section if it determines that the process for categorization of RISC-1, RISC-2, RISC-3, and RISC-4 SSCs satisfies the requirements of § 50.69(c) by issuing a license amendment approving the licensee's use of this section. ( 4 ) An applicant choosing to implement this section shall include the information in § 50.69(b)(2) as part of application. The Commission will approve an applicant's implementation of this section if it determines that the process for categorization of RISC-1, RISC-2, RISC-3, and RISC-4 SSCs satisfies the requirements of § 50.69(c) . ( c ) SSC Categorization Process. ( 1 ) SSCs must be categorized as RISC-1, RISC-2, RISC-3, or RISC-4 SSCs using a categorization process that determines if an SSC performs one or more safety significant functions and identifies those functions. The process must: ( i ) Consider results and insights from the plant-specific PRA. This PRA must at a minimum model severe accident scenarios resulting from