2008 CFR Title 10, Volume 1

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.
	50.2	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 construction permit and operating license 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 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.
	50.55a	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, 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.
	Appendix A	Appendix A to Part 50--General Design Criteria for Nuclear Power Plants.
	Appendix B	Appendix B to Part 50--Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.
	Appendix C	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 D	Appendix D to Part 50 [Reserved].
	Appendix E	Appendix E to Part 50--Emergency Planning and Preparedness for Production and Utilization Facilities.
	Appendix F	Appendix F to Part 50--Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities.
	Appendix G	Appendix G to Part 50--Fracture Toughness Requirements.
	Appendix H	Appendix H to Part 50--Reactor Vessel Material Surveillance Program Requirements.
	Appendix I	Appendix I to Part 50--Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion ''As Low as is Reasonable Achievable'' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.
	Appendix J	Appendix J to Part 50--Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
	Appendix K	Appendix K to Part 50--ECCS Evaluation Models.
	Appendix L	Appendix L to Part 50 [Reserved].
	Appendix M	Appendix M to Part 50 [Reserved].
	Appendix N	Appendix N to Part 50--Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactor or Identical Design at Multiple Sites.
	Appendix O	Appendix O to Part 50 [Reserved].
	Appendix P	Appendix P to Part 50 [Reserved].
	Appendix Q	Appendix Q to Part 50--Pre-Application Early Review of Site Suitability Issues.
	Appendix R	Appendix R to Part 50--Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979.
	Appendix S	Appendix S to Part 50--Earthquake Engineering Criteria for Nuclear Power Plants.