ISSUANCE, LIMITATIONS, AND CONDITIONS OF LICENSES AND CONSTRUCTION PERMITS
- Section 50.50 - Issuance of licenses and construction permits
- Section 50.51 - Continuation of license
- Section 50.52 - Combining licenses
- Section 50.53 - Jurisdictional limitations
- Section 50.54 - Conditions of licenses
- Section 50.55 - Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses
- Section 50.55a - Codes and standards
- Section 50.56 - Conversion of construction permit to license; or amendment of license
- Section 50.57 - Issuance of operating license.1
- Section 50.58 - Hearings and report of the Advisory Committee on Reactor Safeguards
- Section 50.59 - Changes, tests, and experiments
- Section 50.60 - Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation
- Section 50.61 - Fracture toughness requirements for protection against pressurized thermal shock events
- Section 50.61a - Alternate fracture toughness requirements for protection against pressurized thermal shock events
- Section 50.62 - Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants
- Section 50.63 - Loss of all alternating current power
- Section 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors
- Section 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants
- Section 50.66 - Requirements for thermal annealing of the reactor pressure vessel
- Section 50.67 - Accident source term
- Section 50.68 - Criticality accident requirements
- Section 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors