10 CFR Part 50
PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
- PART 50—DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
- Chapter I—Nuclear Regulatory Commission
- 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.
- 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.
- 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.
- 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.
- § 50.34a 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.
- 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.
- § 50.46a 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.
- 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.
- § 50.55a 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.
- 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.
- US/IAEA Safeguards Agreement
- § 50.78 Facility information and verification.
- Transfers of Licenses—Creditors' Rights—Surrender of Licenses
- § 50.80 Transfer of licenses.
- § 50.81 Creditor regulations.
- § 50.82 Termination of license.
- § 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
- § 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.
- 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.
- Backfitting
- § 50.109 Backfitting.
- 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.
- § 50.135 Renewal of non-power production or utilization facility licenses issued under § 50.22 and testing facility licenses.
- § 50.150 Aircraft impact assessment.
- § 50.155 Mitigation of beyond-design-basis events.
- 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.
- 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
Feedback