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10 C.F.R. PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES

TITLE 10--Energy

CHAPTER I--NUCLEAR REGULATORY COMMISSION

PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES

�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.

�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 for licenses; 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 standards for class 103 licenses.

�50.43

Additional standards and provisions affecting class 103 licenses for commercial power.

�50.44

Combustible gas control for nuclear power reactors.

�50.45

Standards for construction permits.

�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.

�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

Installation 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 or construction permit.

�50.91

Notice for public comment; State consultation.

�50.92

Issuance of amendment.

�50.100

Revocation, suspension, modification of licenses and construction permits 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.

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 Facility Construction Permits

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--Standardization of Design; Manufacture of Nuclear Power Reactors; Construction and Operation of Nuclear Power Reactors Manufactured Pursuant to Commission License

Appendix

Appendix N to Part 50--Standardization of Nuclear Power Plant Designs: Licenses To Construct and Operate Nuclear Power Reactors of Duplicate Design at Multiple Sites

Appendix

Appendix O to Part 50--Standardization of Design: Staff Review of Standard Designs

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