Federal (United States) · Regulations

Part 50 — DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES

96 sections

10 C.F.R. § 50.1Basis, purpose, and procedures applicable.
10 C.F.R. § 50.2Definitions.
10 C.F.R. § 50.3Interpretations.
10 C.F.R. § 50.4Written communications.
10 C.F.R. § 50.5Deliberate misconduct.
10 C.F.R. § 50.7Employee protection.
10 C.F.R. § 50.8Information collection requirements: OMB approval.
10 C.F.R. § 50.9Completeness and accuracy of information.
10 C.F.R. § 50.11Exceptions and exemptions from licensing requirements.
10 C.F.R. § 50.12Specific exemptions.
10 C.F.R. § 50.13Attacks and destructive acts by enemies of the United States; and defense activities.
10 C.F.R. § 50.20Two classes of licenses.
10 C.F.R. § 50.23Construction permits.
10 C.F.R. § 50.31Combining applications.
10 C.F.R. § 50.32Elimination of repetition.
10 C.F.R. § 50.33Contents of applications; general information.
10 C.F.R. § 50.34Contents of applications; technical information.
10 C.F.R. § 50.34aDesign objectives for equipment to control releases of radioactive material in effluents—nuclear power reactors.
10 C.F.R. § 50.36Technical specifications.
10 C.F.R. § 50.36aTechnical specifications on effluents from nuclear power reactors.
10 C.F.R. § 50.36bEnvironmental conditions.
10 C.F.R. § 50.37Agreement limiting access to Classified Information.
10 C.F.R. § 50.39Public inspection of applications.
10 C.F.R. § 50.40Common standards.
10 C.F.R. § 50.41Additional standards for class 104 licenses.
10 C.F.R. § 50.42Additional standard for class 103 licenses.
10 C.F.R. § 50.43Additional standards and provisions affecting class 103 licenses and certifications for commercial power.
10 C.F.R. § 50.44Combustible gas control for nuclear power reactors.
10 C.F.R. § 50.45Standards for construction permits, operating licenses, and combined licenses.
10 C.F.R. § 50.46Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors.
10 C.F.R. § 50.46aAcceptance criteria for reactor coolant system venting systems.
10 C.F.R. § 50.48Fire protection.
10 C.F.R. § 50.49Environmental qualification of electric equipment important to safety for nuclear power plants.
10 C.F.R. § 50.50Issuance of licenses and construction permits.
10 C.F.R. § 50.51Continuation of license.
10 C.F.R. § 50.52Combining licenses.
10 C.F.R. § 50.53Jurisdictional limitations.
10 C.F.R. § 50.55Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses.
10 C.F.R. § 50.55aCodes and standards.
10 C.F.R. § 50.56Conversion of construction permit to license; or amendment of license.
10 C.F.R. § 50.58Hearings and report of the Advisory Committee on Reactor Safeguards.
10 C.F.R. § 50.59Changes, tests, and experiments.
10 C.F.R. § 50.60Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation.
10 C.F.R. § 50.61Fracture toughness requirements for protection against pressurized thermal shock events.
10 C.F.R. § 50.61aAlternate fracture toughness requirements for protection against pressurized thermal shock events.
10 C.F.R. § 50.62Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants.
10 C.F.R. § 50.63Loss of all alternating current power.
10 C.F.R. § 50.64Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.
10 C.F.R. § 50.65Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
10 C.F.R. § 50.66Requirements for thermal annealing of the reactor pressure vessel.
10 C.F.R. § 50.67Accident source term.
10 C.F.R. § 50.68Criticality accident requirements.
10 C.F.R. § 50.69Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
10 C.F.R. § 50.70Inspections.
10 C.F.R. § 50.71Maintenance of records, making of reports.
10 C.F.R. § 50.72Immediate notification requirements for operating nuclear power reactors.
10 C.F.R. § 50.73Licensee event report system.
10 C.F.R. § 50.74Notification of change in operator or senior operator status.
10 C.F.R. § 50.75Reporting and recordkeeping for decommissioning planning.
10 C.F.R. § 50.76Licensee's change of status; financial qualifications.
10 C.F.R. § 50.78Facility information and verification.
10 C.F.R. § 50.80Transfer of licenses.
10 C.F.R. § 50.81Creditor regulations.
10 C.F.R. § 50.82Termination of license.
10 C.F.R. § 50.83Release of part of a power reactor facility or site for unrestricted use.
10 C.F.R. § 50.90Application for amendment of license, construction permit, or early site permit.
10 C.F.R. § 50.91Notice for public comment; State consultation.
10 C.F.R. § 50.92Issuance of amendment.
10 C.F.R. § 50.100Revocation, suspension, modification of licenses, permits, and approvals for cause.
10 C.F.R. § 50.101Retaking possession of special nuclear material.
10 C.F.R. § 50.102Commission order for operation after revocation.
10 C.F.R. § 50.103Suspension and operation in war or national emergency.
10 C.F.R. § 50.109Backfitting.
10 C.F.R. § 50.110Violations.
10 C.F.R. § 50.111Criminal penalties.
10 C.F.R. § 50.120Training and qualification of nuclear power plant personnel.
10 C.F.R. § 50.135Renewal of non-power production or utilization facility licenses issued under § 50.22 and testing facility licenses.
10 C.F.R. § 50.150Aircraft impact assessment.
10 C.F.R. § 50.155Mitigation of beyond-design-basis events.
10 C.F.R. Appendix A to Part 50General Design Criteria for Nuclear Power Plants
10 C.F.R. Appendix B to Part 50Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
10 C.F.R. Appendix C to Part 50A Guide for the Financial Data and Related Information Required To Establish Financial Qualifications for Construction Permits and Combined Licenses
10 C.F.R. Appendix D to Part 50[Reserved]Reserved
10 C.F.R. Appendix E to Part 50Emergency Planning and Preparedness for Production and Utilization Facilities
10 C.F.R. Appendix F to Part 50Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities
10 C.F.R. Appendix G to Part 50Fracture Toughness Requirements
10 C.F.R. Appendix H to Part 50Reactor Vessel Material Surveillance Program Requirements
10 C.F.R. Appendix I to Part 50Numerical 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 Effluents
10 C.F.R. Appendix J to Part 50Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors
10 C.F.R. Appendix K to Part 50ECCS Evaluation Models
10 C.F.R. Appendix N to Part 50Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites
10 C.F.R. Appendix Q to Part 50Pre-Application Early Review of Site Suitability Issues
10 C.F.R. Appendix R to Part 50Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979
10 C.F.R. Appendix S to Part 50Earthquake Engineering Criteria for Nuclear Power Plants
10 C.F.R. Appendixes L-M to Part 50[Reserved]Reserved
10 C.F.R. Appendixes O-P to Part 50[Reserved]Reserved