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Code of Federal Regulations (Last Updated: November 8, 2024) |
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Title 10 - Energy |
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Chapter I - Nuclear Regulatory Commission |
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Part 50 - Domestic Licensing of Production and Utilization Facilities |
| Classification and Description of Licenses |
| § 50.20 - Two classes of licenses. |
| § 50.21 - Class 104 licenses; for medical therapy and research and development facilities. |
| § 50.22 - Class 103 licenses; for commercial and industrial facilities. |
| § 50.23 - Construction permits. |
| Transfers of Licenses - Creditors' Rights - Surrender of Licenses |
| § 50.80 - Transfer of licenses. |
| § 50.81 - Creditor regulations. |
| § 50.83 - Release of part of a power reactor facility or site for unrestricted use. |
| Transfers of Licenses—Creditors’ Rights—Surrender of Licenses |
| Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization Facilities |
| § 50.160 - Emergency preparedness for small modular reactors, non-light-water reactors, and non-power production or utilization facilities. |
| Enforcement |
| § 50.110 - Violations. |
| § 50.111 - Criminal penalties. |
| Additional Standards for Licenses, Certifications, and Regulatory Approvals |
| § 50.120 - Training and qualification of nuclear power plant personnel. |
| § 50.150 - Aircraft impact assessment. |
| § 50.155 - xxx |
| Standards for Licenses and Construction Permits |
| Standards for Licenses, Certifications, and Regulatory Approvals |
| § 50.40 - Common standards. |
| § 50.41 - Additional standards for class 104 licenses. |
| § 50.42 - Additional standard for class 103 licenses. |
| § 50.43 - Additional standards and provisions affecting class 103 licenses and certifications for commercial power. |
| § 50.44 - Combustible gas control for nuclear power reactors. |
| § 50.45 - Standards for construction permits, operating licenses, and combined licenses. |
| § 50.46 - Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors. |
| § 50.47 - Emergency plans. |
| § 50.48 - Fire protection. |
| § 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants. |
| § 50.46a - Acceptance criteria for reactor coolant system venting systems. |
| Amendment of License or Construction Permit at Request of Holder |
| § 50.90 - Application for amendment of license, construction permit, or early site permit. |
| § 50.91 - Notice for public comment; State consultation. |
| § 50.92 - Issuance of amendment. |
| Inspections, Records, Reports, Notifications |
| § 50.70 - Inspections. |
| § 50.71 - Maintenance of records, making of reports. |
| § 50.72 - Immediate notification requirements for operating nuclear power reactors. |
| § 50.73 - Licensee event report system. |
| § 50.74 - Notification of change in operator or senior operator status. |
| § 50.75 - Reporting and recordkeeping for decommissioning planning. |
| § 50.76 - Licensee's change of status; financial qualifications. |
| Transfers of Licenses—Creditors' Rights—Surrender of Licenses |
| § 50.82 - Termination of license. |
| Applications for Licenses, Form, Contents, Ineligibility of Certain Applicants |
| § 50.33a - Information requested by the Attorney General for antitrust review. |
| Backfitting |
| § 50.109 - Backfitting. |
| Issuance, Limitations, and Conditions of Licenses and Construction Permits |
| § 50.50 - Issuance of licenses and construction permits. |
| § 50.51 - Continuation of license. |
| § 50.52 - Combining licenses. |
| § 50.53 - Jurisdictional limitations. |
| § 50.54 - Conditions of licenses. |
| § 50.55 - Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses. |
| § 50.56 - Conversion of construction permit to license; or amendment of license. |
| § 50.57 - Issuance of operating license. |
| § 50.58 - Hearings and report of the Advisory Committee on Reactor Safeguards. |
| § 50.59 - Changes, tests, and experiments. |
| § 50.60 - Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation. |
| § 50.61 - Fracture toughness requirements for protection against pressurized thermal shock events. |
| § 50.62 - Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants. |
| § 50.63 - Loss of all alternating current power. |
| § 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors. |
| § 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants. |
| § 50.66 - Requirements for thermal annealing of the reactor pressure vessel. |
| § 50.67 - Accident source term. |
| § 50.68 - Criticality accident requirements. |
| § 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors. |
| § 50.61a - Alternate fracture toughness requirements for protection against pressurized thermal shock events. |
| § 50.55a - Codes and standards. |
| Revocation, Suspension, Modification, Amendment of Licenses and Construction Permits, Emergency Operations by the Commission |
| § 50.100 - Revocation, suspension, modification of licenses, permits, and approvals for cause. |
| § 50.101 - Retaking possession of special nuclear material. |
| § 50.102 - Commission order for operation after revocation. |
| § 50.103 - Suspension and operation in war or national emergency. |
| Applications for Licenses, Certifications, and Regulatory Approvals; Form; Contents; Ineligibility of Certain Applicants |
| § 50.30 - Filing of application; oath or affirmation. |
| § 50.31 - Combining applications. |
| § 50.32 - Elimination of repetition. |
| § 50.33 - Contents of applications; general information. |
| § 50.34 - Contents of applications; technical information. |
| § 50.35 - Issuance of construction permits. |
| § 50.36 - Technical specifications. |
| § 50.37 - Agreement limiting access to Classified Information. |
| § 50.38 - Ineligibility of certain applicants. |
| § 50.39 - Public inspection of applications. |
| § 50.34a - Design objectives for equipment to control releases of radioactive material in effluents - nuclear power reactors. |
| § 50.36a - Technical specifications on effluents from nuclear power reactors. |
| § 50.36b - Environmental conditions. |
| Us/IAEA Safeguards Agreement |
| § 50.78 - Facility information and verification. |
| Requirement of License, Exceptions |
| § 50.10 - License required; limited work authorization. |
| § 50.11 - Exceptions and exemptions from licensing requirements. |
| § 50.12 - Specific exemptions. |
| § 50.13 - Attacks and destructive acts by enemies of the United States; and defense activities. |
| Appendix A to Part 50 - General Design Criteria for Nuclear Power Plants |
| Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants |
| 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 |
| Appendix D to Part 50 |
| Appendix D to Part 50 - [Reserved] |
| Appendix E to Part 50 - —Emergency Planning and Preparedness for Production and Utilization Facilities |
| Appendix F to Part 50 - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities |
| Appendix G to Part 50 - Fracture Toughness Requirements |
| Appendix H to Part 50 - —Reactor Vessel Material Surveillance Program Requirements |
| Appendix J to Part 50 - —Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors |
| Appendix K to Part 50 - ECCS Evaluation Models |
| Appendix L to Part 50 - Information Requested by the Attorney General for Antitrust Review of Facility Construction Permits and Initial Operating Licenses |
| Appendix M to Part 50 - Standardization of Design; Manufacture of Nuclear Power Reactors; Construction and Operation of Nuclear Power Reactors Manufactured Pursuant to Commission License |
| 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 |
| Appendix O to Part 50 - Standardization of Design: Staff Review of Standard Designs |
| Appendix Q to Part 50 - Pre-Application Early Review of Site Suitability Issues |
| Appendix R to Part 50 - Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979 |
| Appendix S to Part 50 - Earthquake Engineering Criteria for Nuclear Power Plants |
| Appendixes L-M to Part 50 - [Reserved] |
| Appendixes L-M to Part 50 - [Reserved] |
| Appendixes O-P to Part 50 - [Reserved] |
| Appendixes O-P to Part 50 - [Reserved] |
| General Provisions |
| § 50.1 - Basis, purpose, and procedures applicable. |
| § 50.2 - Definitions. |
| § 50.3 - Interpretations. |
| § 50.4 - Written communications. |
| § 50.5 - Deliberate misconduct. |
| § 50.7 - Employee protection. |
| § 50.8 - Information collection requirements: OMB approval. |
| § 50.9 - Completeness and accuracy of information. |