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:
and replacement (with the exception of fracture toughness), requirements for ASME Class 2 and Class 3 SSCs in 10 CFR 50.55a(g) ; and the electrical component quality and qualification requirements in Section 4.3 and 4.4 of IEEE 279, and Sections 5.3 and 5.4 of IEEE 603-1991, as incorporated by reference in 10 CFR 50.55a(h) . ( vi ) 10 CFR 50.65 , except for paragraph (a)(4). ( vii ) 10 CFR 50.72 . ( viii ) 10 CFR 50.73 . ( ix ) Appendix B to 10 CFR part 50. ( x ) The Type B and Type C leakage testing requirements in both Options A and B of Appendix J to 10 CFR part 50, for penetrations and valves meeting the following criteria: ( A ) Containment penetrations that are either 1-inch nominal size or less, or continuously pressurized. ( B ) Containment isolation valves that meet one or more of the following criteria: ( 1 ) The valve is required to be open under accident conditions to prevent or mitigate core damage events; ( 2 ) The valve is normally closed and in a physically closed, water-filled system; ( 3 ) The valve is in a physically closed system whose piping pressure rating exceeds the containment design pressure rating and is not connected to the reactor coolant pressure boundary; or ( 4 ) The valve is 1-inch nominal size or less. ( xi ) Appendix A to part 100, Sections VI(a)(1) and VI(a)(2), to the extent that these regulations require qualification testing and specific engineering methods to demonstrate that SSCs are designed to withstand the Safe Shutdown Earthquake and Operating Basis Earthquake. ( 2 ) A licensee voluntarily choosing to implement this section shall submit an application for license amendment under § 50.90 that contains the following information: ( i ) A description of the process for categorization of RISC-1, RISC-2, RISC-3 and RISC-4 SSCs. ( 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,