10 CFR 73 Appendix G, Appendix G to Part 73--Reportable Safeguards Events
10 CFR 2 Appendix A, Appendix a to Part 2--Reserved
10 CFR 2 Appendix C, Appendix C to Part 2--Reserved
10 CFR 2 Appendix D, Appendix D to Part 2--Schedule for the Proceeding On Consideration of Construction Authorization for a High-Level Waste Geologic Repository
10 CFR 4 Appendix A, Appendix a to Part 4--Federal Financial Assistance to Which This Part Applies
10 CFR 5 Appendix A, Appendix a to Part 5--List of Federal Financial Assistance Administered by the Nuclear Regulatory Commission to Which Title Ix Applies
10 CFR 37 Appendix A, Table 1-Category 1 and Category 2 Threshold
10 CFR 50 Appendix A, Appendix a to Part 50-General Design Criteria for Nuclear Power Plants
10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 CFR 50 Appendix C, Appendix C to Part 50-A Guide for the Financial Data and Related Information Required to Establish Financial Qualifications for Construction Permits and Combined Licenses
10 CFR 50 Appendix D, Appendix D to Part 50--Reserved
10 CFR 50 Appendix E, Appendix E to Part 50-Emergency Planning and Preparedness for Production and Utilization Facilities
10 CFR 50 Appendix F, Appendix F to Part 50--Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities
10 CFR 50 Appendix G, Appendix G to Part 50-Fracture Toughness Requirements
10 CFR 50 Appendix H, Appendix H to Part 50-Reactor Vessel Material Surveillance Program Requirements
10 CFR 50 Appendix J, Appendix J to Part 50-Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors
10 CFR 50 Appendix K, Appendix K to Part 50-Eccs Evaluation Models
10 CFR 50 Appendix L, Appendix L to Part 50--Reserved
10 CFR 50 Appendix M, Appendix M to Part 50--Reserved
10 CFR 50 Appendix N, 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 Sites
10 CFR 50 Appendix O, Appendix O to Part 50-Reserved
10 CFR 50 Appendix P, Appendix P to Part 50--Reserved
10 CFR 50 Appendix Q, Appendix Q to Part 50--Pre-Application Early Review of Site Suitability Issues
10 CFR 50 Appendix R, Appendix R to Part 50-Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979
10 CFR 50 Appendix S, General Information
10 CFR 51 Appendix A, Appendix a to Subpart A--Format for Presentation of Material In Environmental Impact Statements
10 CFR 51 Appendix B, Appendix B to Subpart A-Environmental Effect of Renewing the Operating License of a Nuclear Power Plant
10 CFR 52 Appendix B, Appendix B to Part 52-Design Certification Rule for the System 80+ Design
10 CFR 52 Appendix C, Appendix C to Part 52-Design Certification Rule for the Ap600 Design
10 CFR 52 Appendix D, Appendix D to Part 52-Design Certification Rule for the Ap1000 Design
10 CFR 52 Appendix E, Appendix E to Part 52-Design Certification Rule for the Esbwr Design
10 CFR 52 Appendix N, Appendix N to Part 52-Standardization of Nuclear Power Plant Designs: Combined Licenses to Construct and Operate Nuclear Power Reactors of Identical Design At Multiple Sites
10 CFR 70 Appendix A, Appendix a to Part 70-Reportable Safety Events
10 CFR 73 Appendix B, Appendix B to Part 73-General Criteria for Security Personnel
10 CFR 73 Appendix D, Appendix D to Part 73--Physical Protection of Irradiated Reactor Fuel In Transit, Training Program Subject Schedule
10 CFR 73 Appendix E, Appendix E to Part 73--Levels of Physical Protection to Be Applied In International Transport of Nuclear Material
10 CFR 73 Appendix F, Appendix F to Part 73--Nations That Are Parties to the Convention On the Physical Protection of Nuclear Material
10 CFR 73 Appendix H, Appendix H to Part 73--Weapons Qualification Criteria
10 CFR 73 Appendix I, Appendix I to Part 73-Category 1 and 2 Radioactive Materials
10 CFR 100 Appendix A, Appendix a to Part 100-Seismic and Geologic Siting Criteria for Nuclear Power Plants
10 CFR 40 Appendix A, Appendix a to Part 40-Criteria Relating to the Operation of Uranium Mills and the Disposition of Tailings Or Wastes Produced by the Extraction Or Concentration of Source Material From Ores Processed Primarily for Their Source Ma
10 CFR 50 Appendix I, 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 E
10 CFR 52 Appendix F, Appendices F Through M to Part 52 Reserved
10 CFR 20 Appendix G, Requirements for Transfers of Low-Level Radioactive Waste Intended for Disposal at Licensed Land Disposal Facilities and Manifests