Issuance, Limitations, and Conditions of Licenses and Construction Permits

1. CFR
2. ›
3. Title 10
4. ›
5. Chapter I
6. ›
7. Part 50
8. ›
9. Subject Group Issuance, Limitations, and Conditions of Licenses and Construction Permits

Sections

• 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.