Part 50. PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES

• General Provisions

  • SECTION § 50.1 - Basis, purpose, and procedures applicable.
  • SECTION § 50.2 - Definitions.
  • SECTION § 50.3 - Interpretations.
  • SECTION § 50.4 - Written communications.
  • SECTION § 50.5 - Deliberate misconduct.
  • SECTION § 50.7 - Employee protection.
  • SECTION § 50.8 - Information collection requirements: OMB approval.
  • SECTION § 50.9 - Completeness and accuracy of information.

• Requirement of License, Exceptions

  • SECTION § 50.10 - License required; limited work authorization.
  • SECTION § 50.11 - Exceptions and exemptions from licensing requirements.
  • SECTION § 50.12 - Specific exemptions.
  • SECTION § 50.13 - Attacks and destructive acts by enemies of the United States; and defense activities.

• Classification and Description of Licenses

  • SECTION § 50.20 - Two classes of licenses.
  • SECTION § 50.21 - Class 104 licenses; for medical therapy and research and development facilities.
  • SECTION § 50.22 - Class 103 licenses; for commercial and industrial facilities.
  • SECTION § 50.23 - Construction permits.

• • SECTION § 50.30 - Filing of application; oath or affirmation.
  • SECTION § 50.31 - Combining applications.
  • SECTION § 50.32 - Elimination of repetition.
  • SECTION § 50.33 - Contents of applications; general information.
  • SECTION § 50.34 - Contents of applications; technical information.
  • SECTION § 50.34a - Design objectives for equipment to control releases of radioactive material in effluents—nuclear power reactors.
  • SECTION § 50.35 - Issuance of construction permits. 1
  • SECTION § 50.36 - Technical specifications.
  • SECTION § 50.36a - Technical specifications on effluents from nuclear power reactors.
  • SECTION § 50.36b - Environmental conditions.
  • SECTION § 50.37 - Agreement limiting access to Classified Information.
  • SECTION § 50.38 - Ineligibility of certain applicants.
  • SECTION § 50.39 - Public inspection of applications.

• Standards for Licenses, Certifications, and Regulatory Approvals

  • SECTION § 50.40 - Common standards.
  • SECTION § 50.41 - Additional standards for class 104 licenses.
  • SECTION § 50.42 - Additional standard for class 103 licenses.
  • SECTION § 50.43 - Additional standards and provisions affecting class 103 licenses and certifications for commercial power.
  • SECTION § 50.44 - Combustible gas control for nuclear power reactors.
  • SECTION § 50.45 - Standards for construction permits, operating licenses, and combined licenses.
  • SECTION § 50.46 - Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors.
  • SECTION § 50.46a - Acceptance criteria for reactor coolant system venting systems.
  • SECTION § 50.47 - Emergency plans.
  • SECTION § 50.48 - Fire protection.
  • SECTION § 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

• Issuance, Limitations, and Conditions of Licenses and Construction Permits

  • SECTION § 50.50 - Issuance of licenses and construction permits.
  • SECTION § 50.51 - Continuation of license.
  • SECTION § 50.52 - Combining licenses.
  • SECTION § 50.53 - Jurisdictional limitations.
  • SECTION § 50.54 - Conditions of licenses.
  • SECTION § 50.55 - Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses.
  • SECTION § 50.55a - Codes and standards.
  • SECTION § 50.56 - Conversion of construction permit to license; or amendment of license.
  • SECTION § 50.57 - Issuance of operating license. 1
  • SECTION § 50.58 - Hearings and report of the Advisory Committee on Reactor Safeguards.
  • SECTION § 50.59 - Changes, tests, and experiments.
  • SECTION § 50.60 - Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation.
  • SECTION § 50.61 - Fracture toughness requirements for protection against pressurized thermal shock events.
  • SECTION § 50.61a - Alternate fracture toughness requirements for protection against pressurized thermal shock events.
  • SECTION § 50.62 - Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants.
  • SECTION § 50.63 - Loss of all alternating current power.
  • SECTION § 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.
  • SECTION § 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
  • SECTION § 50.66 - Requirements for thermal annealing of the reactor pressure vessel.
  • SECTION § 50.67 - Accident source term.
  • SECTION § 50.68 - Criticality accident requirements.
  • SECTION § 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.

• Inspections, Records, Reports, Notifications

  • SECTION § 50.70 - Inspections.
  • SECTION § 50.71 - Maintenance of records, making of reports.
  • SECTION § 50.72 - Immediate notification requirements for operating nuclear power reactors.
  • SECTION § 50.73 - Licensee event report system.
  • SECTION § 50.74 - Notification of change in operator or senior operator status.
  • SECTION § 50.75 - Reporting and recordkeeping for decommissioning planning.
  • SECTION § 50.76 - Licensee's change of status; financial qualifications.

• US/IAEA Safeguards Agreement

  • SECTION § 50.78 - Facility information and verification.

• Transfers of Licenses—Creditors' Rights—Surrender of Licenses

  • SECTION § 50.80 - Transfer of licenses.
  • SECTION § 50.81 - Creditor regulations.
  • SECTION § 50.82 - Termination of license.
  • SECTION § 50.83 - Release of part of a power reactor facility or site for unrestricted use.

• Amendment of License or Construction Permit at Request of Holder

  • SECTION § 50.90 - Application for amendment of license, construction permit, or early site permit.
  • SECTION § 50.91 - Notice for public comment; State consultation.
  • SECTION § 50.92 - Issuance of amendment.

• Revocation, Suspension, Modification, Amendment of Licenses and Construction Permits, Emergency Operations by the Commission

  • SECTION § 50.100 - Revocation, suspension, modification of licenses, permits, and approvals for cause.
  • SECTION § 50.101 - Retaking possession of special nuclear material.
  • SECTION § 50.102 - Commission order for operation after revocation.
  • SECTION § 50.103 - Suspension and operation in war or national emergency.

• Backfitting

  • SECTION § 50.109 - Backfitting.

• Enforcement

  • SECTION § 50.110 - Violations.
  • SECTION § 50.111 - Criminal penalties.

• Additional Standards for Licenses, Certifications, and Regulatory Approvals

  • SECTION § 50.120 - Training and qualification of nuclear power plant personnel.
  • SECTION § 50.150 - Aircraft impact assessment.
  • SECTION § 50.155 - Mitigation of beyond-design-basis events.

• Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization Facilities

  • SECTION § 50.160 - Emergency preparedness for small modular reactors, non-light-water reactors, and non-power production or utilization facilities.

• APPENDIX

  • 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