Document: NRC Regulatory Guide
Document ID: e0d690ec-277f-4fe2-b92f-7f95d0f589a7
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:
.................................. 23 Table C-10: Submittal Guidelines for Sensitivity Studies ......................................................................... 25 RG 1.245 Revision 0, Page 32 REFERENCES1 1 U.S. Nuclear Regulatory Commission, 10 CFR Part 50: Domestic Licensing of Production and Utilization Facilities, Washington, DC: U.S. NRC. 2 U.S. Nuclear Regulatory Commission, 10 CFR Part 52: Licenses, Certifications, and Approvals for Nuclear Power Plants, Washington, DC: U.S. NRC. 3 U.S. Nuclear Regulatory Commission, 10 CFR Part 71: Packaging and Transportation of Radioactive Material, Washington, DC: U.S. NRC. 4 U.S. Nuclear Regulatory Commission, 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, Washington, DC: U.S. NRC. 5 U.S. Nuclear Regulatory Commission, NUREG-0800: Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Agencywide Documents Access and Management System (ADAMS) Accession No. ML042080088, Washington, DC, U.S. NRC. 6 L. Hund, J. Lewis, N. Martin, M. Starr, D. Brooks, A. Zhang, R. Dingreville , A. Eckert, J. Mullins, P. Raynaud, D. Rudland, D. Dijamco, S. Cumblidge, NUREG/CR-7278: Technical Basis for the Use of Probabilistic Fracture Mechanics in Regulatory Applications, ADAMS Accession No. ML21257A237, U.S. NRC, Washington, DC, U.S. NRC. 7 U.S. Nuclear Regulatory Commission, RG-1.174: An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Washington, DC, USA: U.S. NRC. 8 U.S. Nuclear Regulatory Commission, RG-1.175: An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing, Washington, DC: U.S. NRC. 9 U.S. Nuclear Regulatory Commission, RG-1.178: An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping, Washington, DC: U.S. NRC. 10 U.S.