Document: NRC Regulatory Guide
Document ID: aa450282-f5b0-4dd2-b41a-917a7491deb2
Document Type: regulatory_guide
Title: Preparing Probabilistic Fracture Mechanics (Rev. 0)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2133/ML21334A158.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.245
CFR Part: 
CFR Title: 

Content:
f the reactor pressure vessel. o 10 CFR 50.69: Risk-informed categorization and treatment of structures, systems, and components for nuclear power reactors. o Appendix G to Part 50: Fracture Toughness Requirements. o Appendix H to Part 50: Reactor Vessel Material Surveillance Program Requirements. • 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” applies to applicants for, and holders of, early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. o Appendix A to Part 52: Design Certification Rule for the U.S. Advanced Boiling Water Reactor. o Appendix B to Part 52: Design Certification Rule for the System 80+ Design. o Appendix C to Part 52: Design Certification Rule for the AP600 Design. o Appendix D to Part 52: Design Certification Rule for the AP1000 Design. o Appendix E to Part 52: Design Certification Rule for the ESBWR Design. o Appendix F to Part 52: Design Certification Rule for the APR1400 Design. • 10 CFR Part 71, “Packaging and Transportation of Radioactive Material,” provides requirements for packaging, preparation for shipment, and transportation of licensed material. o 10 CFR 71.43: General standards for all packages. o 10 CFR 71.45: Lifting and tie-down standards for all packages. o 10 CFR 71.51: Additional requirements for Type B packages. o 10 CFR 71.55: General requirements for fissile material packages. o 10 CFR 71.64: Special requirements for plutonium air shipments. o 10 CFR 71.71: Normal conditions of transport. o 10 CFR 71.73: Hypothetical accident conditions. o 10 CFR 71.74: Accident conditions for air transport of plutonium. o 10 CFR 71.75: Qualification of special form radioactive material. RG 1.245 Revision 0, Page 3 • 10 CFR Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste,”