Category:CFR Appendix: Difference between revisions
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Latest revision as of 01:17, 5 September 2016
Pages in category "CFR Appendix"
The following 58 pages are in this category, out of 58 total.
1
- 10 CFR 100 Appendix A, Appendix a to Part 100-Seismic and Geologic Siting Criteria for Nuclear Power Plants
- 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 20 Appendix A
- 10 CFR 20 Appendix B
- 10 CFR 20 Appendix C
- 10 CFR 20 Appendix D
- 10 CFR 20 Appendix E
- 10 CFR 20 Appendix F
- 10 CFR 20 Appendix G, Requirements for Transfers of Low-Level Radioactive Waste Intended for Disposal at Licensed Land Disposal Facilities and Manifests
- 10 CFR 25 Appendix A
- 10 CFR 30 Appendix A
- 10 CFR 30 Appendix B
- 10 CFR 30 Appendix C
- 10 CFR 30 Appendix D
- 10 CFR 30 Appendix E
- 10 CFR 34 Appendix A
- 10 CFR 37 Appendix A, Table 1-Category 1 and Category 2 Threshold
- 10 CFR 4 Appendix A, Appendix a to Part 4--Federal Financial Assistance to Which This Part Applies
- 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 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 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 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 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 F, Appendices F Through M to Part 52 Reserved
- 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 71 Appendix A
- 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 G, Appendix G to Part 73--Reportable Safeguards Events
- 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