10 CFR 50.1, Basis, Purpose, and Procedures Applicable
10 CFR 50.8, Information Collection Requirements: Omb Approval
10 CFR 50.9, Completeness and Accuracy of Information
10 CFR 50.10, License Required; Limited Work Authorization
10 CFR 50.11, Exceptions and Exemptions From Licensing Requirements
10 CFR 50.13, Attacks and Destructive Acts by Enemies of the United States; and Defense Activities
10 CFR 50.21, Class 104 Licenses; for Medical Therapy and Research and Development Facilities
10 CFR 50.22, Class 103 Licenses; for Commercial and Industrial Facilities
10 CFR 50.30, Filing of Application for Licenses; Oath Or Affirmation
10 CFR 50.33, Contents of Applications; General Information
10 CFR 50.34, Contents of Applications; Technical Information
10 CFR 50.37, Agreement Limiting Access to Classified Information
10 CFR 50.38, Ineligibility of Certain Applicants
10 CFR 50.39, Public Inspection of Applications
10 CFR 50.41, Additional Standards for Class 104 Licenses
10 CFR 50.42, Additional Standard for Class 103 Licenses
10 CFR 50.43, Additional Standards and Provisions Affecting Class 103 Licenses and Certifications for Commercial Power
10 CFR 50.44, Combustible Gas Control for Nuclear Power Reactors
10 CFR 50.45, Standards for Construction Permits, Operating Licenses, and Combined Licenses
10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors
10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants
10 CFR 50.50, Issuance of Licenses and Construction Permits
10 CFR 50.53, Jurisdictional Limitations
10 CFR 50.55, Conditions of Construction Permits, Early Site Permits, Combined Licenses, and Manufacturing Licenses
10 CFR 50.56, Conversion of Construction Permit to License; Or Amendment of License
10 CFR 50.57, Issuance of Operating License.
10 CFR 50.58, Hearings and Report of the Advisory Committee On Reactor Safeguards
10 CFR 50.59, Changes, Tests and Experiments
10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation
10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events
10 CFR 50.62, Requirements for Reduction of Risk From Anticipated Transients Without Scram (Atws) Events for Light-Water-Cooled Nuclear Power Plants
10 CFR 50.63, Loss of All Alternating Current Power
10 CFR 50.64, Limitations On the Use of Highly Enriched Uranium (Heu) In Domestic Non-Power Reactors
10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance At Nuclear Power Plants
10 CFR 50.66, Requirements for Thermal Annealing of the Reactor Pressure Vessel
10 CFR 50.68, Criticality Accident Requirements
10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
10 CFR 50.71, Maintenance of Records, Making of Reports
10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors
10 CFR 50.73, Licensee Event Report System
10 CFR 50.74, Notification of Change In Operator Or Senior Operator Status
10 CFR 50.75, Reporting and Recordkeeping for Decommissioning Planning
10 CFR 50.76, . Licensee'S Change of Status; Financial Qualifications
10 CFR 50.78, Facility Information and Verification
10 CFR 50.83, Release of Part of a Power Reactor Facility Or Site for Unrestricted Use
10 CFR 50.90, Application for Amendment of License, Construction Permit, Or Early Site Permit
10 CFR 50.91, Notice for Public Comment; State Consultation
10 CFR 50.100, Revocation, Suspension, Modification of Licenses, Permits, and Approvals for Cause
10 CFR 50.101, Retaking Possession of Special Nuclear Material
10 CFR 50.102, Commission Order for Operation After Revocation
10 CFR 50.103, Suspension and Operation In War Or National Emergency
10 CFR 50.120, Training and Qualification of Nuclear Power Plant Personnel
10 CFR 50.150, Aircraft Impact Assessment
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 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