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:
range of regulations; consequently, it is not possible to provide a comprehensive list of such applications. However, the staff anticipates that this RG could apply to nonreactor and reactor licensees subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 1) ; 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 2); 10 CFR Part 71, “Packaging and Transportation of Radioactive Material” (Ref. 3); and 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” (Ref. 4). Applicable Regulations This RG discusses acceptable ways to present PFM analyses in regulatory submittals to the NRC and can be used to demonstrate compliance with a wide range of regulations. The following is a list of regulations where PFM may be a useful tool for developing the technical basis for submittals. Potential uses of PFM in regulatory applications are not limited to the following list of regulations. • 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” applies to applicants for, and holders of, licenses for production and utilization facilities. o 10 CFR 50.55a: Codes and standards. o 10 CFR 50.60: Acceptance criteria for fracture prevention measures for light-water nuclear power reactors for normal operation. RG 1.245 Revision 0, Page 2 o 10 CFR 50.61: Fracture toughness requirements for protection against pressurized thermal shock events. o 10 CFR 50.61a: Alternate fracture toughness requirements for protection against pressurized thermal shock events. o 10 CFR 50.66: Requirements for thermal annealing of 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