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 -

• § 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.

• § 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 Appendix A - Appendix A to Part 50—General Design Criteria for Nuclear Power Plants

• Appendix Appendix B - Appendix B to Part 50—Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

• Appendix Appendix C - 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 Appendix D - Appendix D to Part 50 [Reserved]

• Appendix Appendix E - Appendix E to Part 50—Emergency Planning and Preparedness for Production and Utilization Facilities

• Appendix Appendix F - Appendix F to Part 50—Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities

• Appendix Appendix G - Appendix G to Part 50—Fracture Toughness Requirements

• Appendix Appendix H - Appendix H to Part 50—Reactor Vessel Material Surveillance Program Requirements

• Appendix Appendix I - 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 Appendix J - Appendix J to Part 50—Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors

• Appendix Appendix K - Appendix K to Part 50—ECCS Evaluation Models

• Appendix - Appendixes L-M to Part 50 [Reserved]

• Appendix Appendix N - 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

• Appendix - Appendixes O-P to Part 50 [Reserved]

• Appendix Appendix Q - Appendix Q to Part 50—Pre-Application Early Review of Site Suitability Issues

• Appendix Appendix R - Appendix R to Part 50—Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979

• Appendix Appendix S - Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power Plants