10 CFR 50 - DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES
- — 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.
- § 50.150 — Aircraft impact assessment.
- 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
Source: 21 FR 355, Jan. 19, 1956, unless otherwise noted.
Title 10 published on 2012-01-01
The following are only the Rules published in the Federal Register after the published date of Title 10.
For a complete list of all Rules, Proposed Rules, and Notices view the Rulemaking tab.
This is a list of United States Code sections, Statutes at Large, Public Laws, and Presidential Documents, which provide rulemaking authority for this CFR Part.
This list is taken from the Parallel Table of Authorities and Rules provided by GPO [Government Printing Office].
It is not guaranteed to be accurate or up-to-date, though we do refresh the database weekly. More limitations on accuracy are described at the GPO site.
The following are ALL rules, proposed rules, and notices (chronologically) published in the Federal Register relating to 10 CFR 50
- 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
