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