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Home Page > Executive Branch > Code of Federal Regulations > Electronic Code of Federal Regulations

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e-CFR Data is current as of November 19, 2009

TITLE 10--Energy

CHAPTER I--NUCLEAR REGULATORY COMMISSION

PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES

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§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.
§50.62
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.
§50.150
Aircraft impact assessment.
Appendix
Appendix A to Part 50 --General Design Criteria for Nuclear Power Plants
Appendix
Appendix B to Part 50 --Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
Appendix
Appendix C to Part 50 --A Guide for the Financial Data and Related Information Required To Establish Financial Qualifications for Construction Permits and Combined Licenses
Appendix
Appendix D to Part 50 --[Reserved]
Appendix
Appendix E to Part 50 --Emergency Planning and Preparedness for Production and Utilization Facilities
Appendix
Appendix F to Part 50 --Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities
Appendix
Appendix G to Part 50 --Fracture Toughness Requirements
Appendix
Appendix H to Part 50 --Reactor Vessel Material Surveillance Program Requirements
Appendix
Appendix I to Part 50 --Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion ''As Low as is Reasonably Achievable'' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents
Appendix
Appendix J to Part 50 --Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors
Appendix
Appendix K to Part 50 --ECCS Evaluation Models
Appendix
Appendix L to Part 50 --[Reserved]
Appendix
Appendix M to Part 50 --[Reserved]
Appendix
Appendix N to Part 50 --Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites
Appendix
Appendix O to Part 50 --[Reserved]
Appendix
Appendix P to Part 50 --[Reserved]
Appendix
Appendix Q to Part 50 --Pre-Application Early Review of Site Suitability Issues
Appendix
Appendix R to Part 50 --Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979
Appendix
Appendix S to Part 50 --Earthquake Engineering Criteria for Nuclear Power Plants
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