Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.

CFR · 2024-01-01 · US · Title 10

(a) (b) (i) 10 CFR part 21. (ii) The portion of 10 CFR 50.46a(b) that imposes requirements to conform to Appendix B to 10 CFR part 50. (iii) 10 CFR 50.49. (iv) 10 CFR 50.55(e). (v) The inservice testing requirements in 10 CFR 50.55a(f); the inservice inspection, and repair 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: ( ( ( ( (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

official document · source cfr-2024 · id 10:§ 50.69