10 CFR Part 50 - PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
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General Provisions (§§ 50.1 - 50.9)
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Classification and Description of Licenses (§§ 50.20 - 50.23)
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Applications for Licenses, Certifications, and Regulatory Approvals; Form; Contents; Ineligibility of Certain Applicants (§§ 50.30 - 50.39)
- § 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.
- § 50.34a Design objectives for equipment to control releases of radioactive material in effluents—nuclear power reactors.
- § 50.35 Issuance of construction permits. 1
- § 50.36 Technical specifications.
- § 50.36a Technical specifications on effluents from nuclear power reactors.
- § 50.36b Environmental conditions.
- § 50.37 Agreement limiting access to Classified Information.
- § 50.38 Ineligibility of certain applicants.
- § 50.39 Public inspection of applications.
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Standards for Licenses, Certifications, and Regulatory Approvals (§§ 50.40 - 50.49)
- § 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.
- § 50.46a Acceptance criteria for reactor coolant system venting systems.
- § 50.47 Emergency plans.
- § 50.48 Fire protection.
- § 50.49 Environmental qualification of electric equipment important to safety for nuclear power plants.
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Issuance, Limitations, and Conditions of Licenses and Construction Permits (§§ 50.50 - 50.69)
- § 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.
- § 50.55a Codes and standards.
- § 50.56 Conversion of construction permit to license; or amendment of license.
- § 50.57 Issuance of operating license. 1
- § 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.
- § 50.61a Alternate 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.
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Inspections, Records, Reports, Notifications (§§ 50.70 - 50.76)
- § 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.
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US/IAEA Safeguards Agreement (§ 50.78)
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Transfers of Licenses—Creditors' Rights—Surrender of Licenses (§§ 50.80 - 50.83)
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Amendment of License or Construction Permit at Request of Holder (§§ 50.90 - 50.92)
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Revocation, Suspension, Modification, Amendment of Licenses and Construction Permits, Emergency Operations by the Commission (§§ 50.100 - 50.103)
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Backfitting (§ 50.109)
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Enforcement (§§ 50.110 - 50.111)
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Additional Standards for Licenses, Certifications, and Regulatory Approvals (§§ 50.120 - 50.155)
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Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization Facilities (§ 50.160)
- 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 [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 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 Effluents
- Appendix J to Part 50—Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors
- Appendix K to Part 50—ECCS Evaluation Models
- Appendixes L–M to Part 50 [Reserved]
- 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
- Appendixes O–P to Part 50 [Reserved]
- 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
Authority:
Atomic Energy Act of 1954, secs. 11, 101, 102, 103, 104, 105, 108, 122, 147, 149, 161, 181, 182, 183, 184, 185, 186, 187, 189, 223, 234 (42 U.S.C. 2014, 2131, 2132, 2133, 2134, 2135, 2138, 2152, 2167, 2169, 2201, 2231, 2232, 2233, 2234, 2235, 2236, 2237, 2239, 2273, 2282); Energy Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste Policy Act of 1982, sec. 306 (42 U.S.C. 10226); National Environmental Policy Act of 1969 (42 U.S.C. 4332); 44 U.S.C. 3504 note; Sec. 109, Pub. L. 96–295, 94 Stat. 783.
Source:
21 FR 355, Jan. 19, 1956, unless otherwise noted.