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:
s section for a SSC, changes to the quality assurance plan for the implementation of the changes in accordance with § 50.69(d) need not include a supporting § 50.54(a) review of the changes directly related to implementation. Thereafter, changes to the programs and procedures for implementation of § 50.69(d) , as described in the quality assurance plan may be made if the requirements of this section and § 50.54(a) continue to be met. ( g ) Reporting. The licensee shall submit a licensee event report under § 50.73(b) for any event or condition that prevented, or would have prevented, a RISC-1 or RISC-2 SSC from performing a safety significant function. [ 69 FR 68047 , Nov. 22, 2004]