DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
10 C.F.R. Part 50
in effectEffective: 2024-07-01Contents
appendixAppendix A to Part 50. Appendix A to Part 50—General Design Criteria for Nuclear Power PlantsappendixAppendix B to Part 50. Appendix B to Part 50—Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing PlantsappendixAppendix C to Part 50. Appendix C to Part 50—A Guide for the Financial Data and Related Information Required To Establish Financial Qualifications for Construction Permits and Combined LicensesappendixAppendix D to Part 50. Appendix D to Part 50 [Reserved]appendixAppendixes L-M to Part 50. Appendixes L-M to Part 50 [Reserved]appendixAppendixes O-P to Part 50. Appendixes O-P to Part 50 [Reserved]appendixAppendix E to Part 50. Appendix E to Part 50—Emergency Planning and Preparedness for Production and Utilization FacilitiesappendixAppendix F to Part 50. Appendix F to Part 50—Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management FacilitiesappendixAppendix G to Part 50. Appendix G to Part 50—Fracture Toughness RequirementsappendixAppendix H to Part 50. Appendix H to Part 50—Reactor Vessel Material Surveillance Program RequirementsappendixAppendix I to Part 50. Appendix I to Part 50—Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor EffluentsappendixAppendix J to Part 50. Appendix J to Part 50—Primary Reactor Containment Leakage Testing for Water-Cooled Power ReactorsappendixAppendix K to Part 50. Appendix K to Part 50—ECCS Evaluation ModelsappendixAppendix N to Part 50. Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple SitesappendixAppendix Q to Part 50. Appendix Q to Part 50—Pre-Application Early Review of Site Suitability IssuesappendixAppendix R to Part 50. Appendix R to Part 50—Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979appendixAppendix S to Part 50. Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power PlantssectionECFR1aad221999377bf. General ProvisionssectionECFR2f76ac8b7f9e21e. Issuance, Limitations, and Conditions of Licenses and Construction PermitssectionECFR03d779d639ae445. Applications for Licenses, Certifications, and Regulatory Approvals; Form; Contents; Ineligibility of Certain ApplicantssectionECFR6a596da2c74ca95. Transfers of Licenses—Creditors' Rights—Surrender of LicensessectionECFR8bfb434b554a770. Requirement of License, ExceptionssectionECFR49d6db99afc998e. BackfittingsectionECFR84f930ecccc7c3e. US/IAEA Safeguards AgreementsectionECFR89aa6ca4aada73c. Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization FacilitiessectionECFR092dafdfbddb968. EnforcementsectionECFR448a4b6d297d970. Additional Standards for Licenses, Certifications, and Regulatory ApprovalssectionECFRc95a36734e897a7. Classification and Description of LicensessectionECFRcabf50eea7bdf2b. Amendment of License or Construction Permit at Request of HoldersectionECFRdcc63bdb8fac7fc. Revocation, Suspension, Modification, Amendment of Licenses and Construction Permits, Emergency Operations by the CommissionsectionECFRdf2af20f8a72d91. Standards for Licenses, Certifications, and Regulatory ApprovalssectionECFReadbe827381d095. Inspections, Records, Reports, Notifications
Source: eCFRURL: https://www.ecfr.gov/api/versioner/v1/full/2024-07-01/title-10.xmlFetched: 7/26/2026