Category:10 CFR 50
Jump to navigation
Jump to search
Pages in category "10 CFR 50"
The following 100 pages are in this category, out of 100 total.
1
- 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 50.1, Basis, Purpose, and Procedures Applicable
- 10 CFR 50.10, License Required; Limited Work Authorization
- 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 50.109, Backfitting
- 10 CFR 50.11, Exceptions and Exemptions From Licensing Requirements
- 10 CFR 50.110, Violations
- 10 CFR 50.111, Criminal Penalties
- 10 CFR 50.12, Specific Exemptions
- 10 CFR 50.120, Training and Qualification of Nuclear Power Plant Personnel
- 10 CFR 50.13, Attacks and Destructive Acts by Enemies of the United States; and Defense Activities
- 10 CFR 50.150, Aircraft Impact Assessment
- 10 CFR 50.155, Mitigation of beyond-design-basis events
- 10 CFR 50.2, Definitions
- 10 CFR 50.20, Two Classes of Licenses
- 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 50.23, Construction Permits
- 10 CFR 50.3, Interpretations
- 10 CFR 50.30, Filing of Application for Licenses; Oath Or Affirmation
- 10 CFR 50.31, Combining Applications
- 10 CFR 50.32, Elimination of Repetition
- 10 CFR 50.33, Contents of Applications; General Information
- 10 CFR 50.34, Contents of Applications; Technical Information
- 10 CFR 50.36, Technical Specifications
- 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 50.4, Written Communications
- 10 CFR 50.40, Common Standards
- 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 50.47, Emergency Plans
- 10 CFR 50.48, Fire Protection
- 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants
- 10 CFR 50.5, Deliberate Misconduct
- 10 CFR 50.50, Issuance of Licenses and Construction Permits
- 10 CFR 50.51, Continuation of License
- 10 CFR 50.52, Combining Licenses
- 10 CFR 50.53, Jurisdictional Limitations
- 10 CFR 50.54, Conditions of licenses
- 10 CFR 50.55, Conditions of Construction Permits, Early Site Permits, Combined Licenses, and Manufacturing Licenses
- 10 CFR 50.55a, Codes and Standards
- 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 50.67, Accident Source Term
- 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 50.7, Employee Protection
- 10 CFR 50.70, Inspections
- 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 50.8, Information Collection Requirements: Omb Approval
- 10 CFR 50.80, Transfer of Licenses
- 10 CFR 50.81, Creditor Regulations
- 10 CFR 50.82, Termination of License
- 10 CFR 50.83, Release of Part of a Power Reactor Facility Or Site for Unrestricted Use
- 10 CFR 50.9, Completeness and Accuracy of Information
- 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 50.92, Issuance of Amendment