Browse Federal regulations
Read the original sections, or search by topic.
- 10 CFR 50.36 · Technical specifications.
- 10 CFR 50.36a · a Technical specifications on effluents from nuclear power reactors.
- 10 CFR 50.36b · b Environmental conditions.
- 10 CFR 50.37 · Agreement limiting access to Classified Information.
- 10 CFR 50.38 · Ineligibility of certain applicants.
- 10 CFR 50.39 · Public inspection of applications.
- 10 CFR 50.40 · Common standards.
- 10 CFR 50.41 · Additional standards for class 104 licenses.
- 10 CFR 50.42 · Additional standard for class 103 licenses.
- 10 CFR 50.43 · Additional standards and provisions affecting class 103 licenses and certifications for commercial power.
- 10 CFR 50.44 · Combustible gas control for nuclear power reactors.
- 10 CFR 50.45 · Standards for construction permits, operating licenses, and combined licenses.
- 10 CFR 50.46 · Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors.
- 10 CFR 50.46a · a Acceptance criteria for reactor coolant system venting systems.
- 10 CFR 50.47 · Emergency plans.
- 10 CFR 50.48 · Fire protection.
- 10 CFR 50.49 · Environmental qualification of electric equipment important to safety for nuclear power plants.
- 10 CFR 50.50 · Issuance of licenses and construction permits.
- 10 CFR 50.51 · Continuation of license.
- 10 CFR 50.52 · Combining licenses.
- 10 CFR 50.53 · Jurisdictional limitations.
- 10 CFR 50.54 · Conditions of licenses.
- 10 CFR 50.55 · Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses.
- 10 CFR 50.55a · a Codes and standards.
- 10 CFR 50.56 · Conversion of construction permit to license; or amendment of license.
- 10 CFR 50.57 · Issuance of operating license. 1
- 10 CFR 50.58 · Hearings and report of the Advisory Committee on Reactor Safeguards.
- 10 CFR 50.59 · Changes, tests, and experiments.
- 10 CFR 50.60 · Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation.
- 10 CFR 50.61 · Fracture toughness requirements for protection against pressurized thermal shock events.
- 10 CFR 50.61a · a Alternate fracture toughness requirements for protection against pressurized thermal shock events.
- 10 CFR 50.62 · Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants.
- 10 CFR 50.63 · Loss of all alternating current power.
- 10 CFR 50.64 · Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.
- 10 CFR 50.65 · Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
- 10 CFR 50.66 · Requirements for thermal annealing of the reactor pressure vessel.
- 10 CFR 50.67 · Accident source term.
- 10 CFR 50.68 · Criticality accident requirements.
- 10 CFR 50.69 · Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
- 10 CFR 50.70 · Inspections.
- 10 CFR 50.71 · Maintenance of records, making of reports.
- 10 CFR 50.72 · Immediate notification requirements for operating nuclear power reactors.
- 10 CFR 50.73 · Licensee event report system.
- 10 CFR 50.74 · Notification of change in operator or senior operator status.
- 10 CFR 50.75 · Reporting and recordkeeping for decommissioning planning.
- 10 CFR 50.76 · Licensee's change of status; financial qualifications.
- 10 CFR 50.78 · Facility information and verification.
- 10 CFR 50.80 · Transfer of licenses.
- 10 CFR 50.81 · Creditor regulations.
- 10 CFR 50.82 · Termination of license.
- 10 CFR 50.83 · Release of part of a power reactor facility or site for unrestricted use.
- 10 CFR 50.90 · Application for amendment of license, construction permit, or early site permit.
- 10 CFR 50.91 · Notice for public comment; State consultation.
- 10 CFR 50.92 · Issuance of amendment.
- 10 CFR 50.100 · Revocation, suspension, modification of licenses, permits, and approvals for cause.
- 10 CFR 50.101 · Retaking possession of special nuclear material.
- 10 CFR 50.102 · Commission order for operation after revocation.
- 10 CFR 50.103 · Suspension and operation in war or national emergency.
- 10 CFR 50.109 · Backfitting.
- 10 CFR 50.110 · Violations.
- 10 CFR 50.111 · Criminal penalties.
- 10 CFR 50.120 · Training and qualification of nuclear power plant personnel.
- 10 CFR 50.135 · Renewal of non-power production or utilization facility licenses issued under § 50.22 and testing facility licenses.
- 10 CFR 50.150 · Aircraft impact assessment.
- 10 CFR 50.155 · Mitigation of beyond-design-basis events.
- 10 CFR 50.160 · Emergency preparedness for small modular reactors, non-light-water reactors, and non-power production or utilization facilities.
- 10 CFR Appendix A to Part 50 · Appendix A to Part 50—General Design Criteria for Nuclear Power Plants
- 10 CFR Appendix B to Part 50 · Appendix B to Part 50—Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
- 10 CFR Appendix C to Part 50 · 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
- 10 CFR Appendix D to Part 50 · Appendix D to Part 50 [Reserved]
- 10 CFR Appendix E to Part 50 · Appendix E to Part 50—Emergency Planning and Preparedness for Production and Utilization Facilities
- 10 CFR Appendix F to Part 50 · Appendix F to Part 50—Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities
- 10 CFR Appendix G to Part 50 · Appendix G to Part 50—Fracture Toughness Requirements
- 10 CFR Appendix H to Part 50 · Appendix H to Part 50—Reactor Vessel Material Surveillance Program Requirements
- 10 CFR Appendix I to Part 50 · 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
- 10 CFR Appendix J to Part 50 · Appendix J to Part 50—Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors
- 10 CFR Appendix K to Part 50 · Appendix K to Part 50—ECCS Evaluation Models
- 10 CFR Appendixes L-M to Part 50 · Appendixes L-M to Part 50 [Reserved]
- 10 CFR Appendix N to Part 50 · 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
- 10 CFR Appendixes O-P to Part 50 · Appendixes O-P to Part 50 [Reserved]
- 10 CFR Appendix Q to Part 50 · Appendix Q to Part 50—Pre-Application Early Review of Site Suitability Issues
- 10 CFR Appendix R to Part 50 · Appendix R to Part 50—Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979
- 10 CFR Appendix S to Part 50 · Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power Plants
- 10 CFR 51.1 · Scope.
- 10 CFR 51.2 · Subparts.
- 10 CFR 51.3 · Resolution of conflict.
- 10 CFR 51.4 · Definitions.
- 10 CFR 51.5 · Interpretations.
- 10 CFR 51.6 · Specific exemptions.
- 10 CFR 51.10 · Purpose and scope of subpart; application of regulations of Council on Environmental Quality.
- 10 CFR 51.11 · Relationship to other subparts. [Reserved]
- 10 CFR 51.12 · Application of subpart to ongoing environmental work.
- 10 CFR 51.13 · Emergencies.
- 10 CFR 51.14 · Definitions.
- 10 CFR 51.15 · Time schedules.
- 10 CFR 51.16 · Proprietary information.
- 10 CFR 51.17 · Information collection requirements; OMB approval.
- 10 CFR 51.20 · Criteria for and identification of licensing and regulatory actions requiring environmental impact statements.
- 10 CFR 51.21 · Criteria for and identification of licensing and regulatory actions requiring environmental assessments.
- 10 CFR 51.22 · Categorical exclusions.