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Title 10

Displaying title 10, up to date as of 7/17/2026. Title 10 was last amended 7/13/2026.
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  1. Title 10 —Energy
  2. Chapter I —Nuclear Regulatory Commission
  3. Part 50 —Domestic Licensing of Production and Utilization Facilities
  4. Issuance, Limitations, and Conditions of Licenses and Construction Permits   View Full Text
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eCFR Content

The Code of Federal Regulations (CFR) is the official legal print publication containing the codification of the general and permanent rules published in the Federal Register by the departments and agencies of the Federal Government. The Electronic Code of Federal Regulations (eCFR) is a continuously updated online version of the CFR. It is not an official legal edition of the CFR.

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Title 10EnergyPart / Section
Chapter INuclear Regulatory Commission1 – 199
Part 50Domestic Licensing of Production and Utilization Facilities50.1 – 50.160
Issuance, Limitations, and Conditions of Licenses and Construction Permits50.50 – 50.69
§ 50.50Issuance of licenses and construction permits.
§ 50.51Continuation of license.
§ 50.52Combining licenses.
§ 50.53Jurisdictional limitations.
§ 50.54Conditions of licenses.
§ 50.55Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses.
§ 50.55aCodes and standards.
§ 50.56Conversion of construction permit to license; or amendment of license.
§ 50.57Issuance of operating license.
§ 50.58Hearings and report of the Advisory Committee on Reactor Safeguards.
§ 50.59Changes, tests, and experiments.
§ 50.60Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation.
§ 50.61Fracture toughness requirements for protection against pressurized thermal shock events.
§ 50.61aAlternate fracture toughness requirements for protection against pressurized thermal shock events.
§ 50.62Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants.
§ 50.63Loss of all alternating current power.
§ 50.64Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.
§ 50.65Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
§ 50.66Requirements for thermal annealing of the reactor pressure vessel.
§ 50.67Accident source term.
§ 50.68Criticality accident requirements.
§ 50.69Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
eCFR Content