10 CFR Part 50 — Domestic Licensing of Production and Utilization Facilities
- § 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.
- § 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.
- § 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.
- § 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.
- § 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.
- § 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.
- § 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.
- § 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.
- § 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.
- § 50.78— Facility information and verification.
- § 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.
- § 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.
- § 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.
- § 50.109— Backfitting.
- § 50.110— Violations.
- § 50.111— Criminal penalties.
- § 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.
- § 50.160— Emergency preparedness for small modular reactors, non-light-water reactors, and non-power production or utilization facilities.