Additional standards and provisions affecting class 103 licenses and certifications for commercial power
In addition to applying the standards set forth in §§ 50.40 and 50.42, paragraphs (a) through (e) of this section apply in the case of a class 103 license for a facility for the generation of commercial power. For a design certification under part 52 of this chapter, only paragraph (e) of this section applies.
a
(a) The NRC will:
- (1) Give notice in writing of each application to the regulatory agency or State as may have jurisdiction over the rates and services incident to the proposed activity;
- (2) Publish notice of the application in trade or news publications as it deems appropriate to give reasonable notice to municipalities, private utilities, public bodies, and cooperatives which might have a potential interest in the utilization or production facility; and
- (3) Publish notice of the application once each week for 4 consecutive weeks in the Federal Register. No license will be issued by the NRC prior to the giving of these notices and until 4 weeks after the last notice is published in the Federal Register.
b
(b) If there are conflicting applications for a limited opportunity for such license, the Commission will give preferred consideration in the following order: First, to applications submitted by public or cooperative bodies for facilities to be located in high cost power areas in the United States; second, to applications submitted by others for facilities to be located in such areas; third, to applications submitted by public or cooperative bodies for facilities to be located in other than high cost power areas; and, fourth, to all other applicants.
c
(c) The licensee who transmits electric energy in interstate commerce, or sells it at wholesale in interstate commerce, shall be subject to the regulatory provisions of the Federal Power Act.
d
(d) Nothing shall preclude any government agency, now or hereafter authorized by law to engage in the production, marketing, or distribution of electric energy, if otherwise qualified, from obtaining a construction permit or operating license under this part, or a combined license under part 52 of this chapter for a utilization facility for the primary purpose of producing electric energy for disposition for ultimate public consumption.
e
(e) Applications for a design certification, combined license, manufacturing license, or operating license that propose nuclear reactor designs which differ significantly from light-water reactor designs that were licensed before 1997, or use simplified, inherent, passive, or other innovative means to accomplish their safety functions, will be approved only if:
- {{
- (1)(i) The performance of each safety feature of the design has been demonstrated through either analysis, appropriate test programs, experience, or a combination thereof;
- (ii) Interdependent effects among the safety features of the design are acceptable, as demonstrated by analysis, appropriate test programs, experience, or a combination thereof; and
- (iii) Sufficient data exist on the safety features of the design to assess the analytical tools used for safety analyses over a sufficient range of normal operating conditions, transient conditions, and specified accident sequences, including equilibrium core conditions; or
- (2) There has been acceptable testing of a prototype plant over a sufficient range of normal operating conditions, transient conditions, and specified accident sequences, including equilibrium core conditions. If a prototype plant is used to comply with the testing requirements, then the NRC may impose additional requirements on siting, safety features, or operational conditions for the prototype plant to protect the public and the plant staff from the possible consequences of accidents during the testing period.
"[FR" contains the "[" character as part of a property label and has been classified as invalid.
, as amended at [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=1970_register&page=19660&position=1%7C35 FR 19660, Dec. 29, 1970]]; [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=1998_register&page=50480&position=1%7C63 FR 50480, Sept. 22, 1998]]; [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=2007_register&page=49494&position=1%7C72 FR 49494, Aug. 28, 2007]]]
External Links
[[URL::http://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-0043.html%7CNRC website 10 CFR 50.43]]
Code of Federal Regulations |
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Title 10 Part 50 - DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES |
10 CFR: 1, 2, 4, 5, 7, 9, 10, 11, 12, 13, 14, 15, 16, 19, 20, 21, 25, 26, 30, 31, 32, 33, 34, 35, 36, 37, 39, 40, 50, 51, 52, 54, 55, 60, 61, 62, 63, 70, 71, 72, 73, 74, 75, 76, 81, 95, 100, 140, 150, 160, 170, 171 |
- 1, General Provisions Basis, purpose, and procedures applicable
- 2, Definitions
- 3, Interpretations
- 4, Written communications
- 5, Deliberate misconduct
- 7, Employee protection
- 8, Information collection requirements: OMB approval
- 9, Completeness and accuracy of information
- 10, Requirement of License, Exceptions License required; limited work authorization
- 11, Exceptions and exemptions from licensing requirements
- 12, Specific exemptions
- 13, Attacks and destructive acts by enemies of the United States; and defense activities
- 20, Classification and Description of Licenses Two classes of licenses
- 21, Class 104 licenses; for medical therapy and research and development facilities
- 22, Class 103 licenses; for commercial and industrial facilities
- 23, Construction permits
- 30, Applications for Licenses, Certifications, and Regulatory Approvals; Form; Contents; Ineligibility of Certain Applicants Filing of application for licenses; oath or affirmation
- 31, Combining applications
- 32, Elimination of repetition
- 33, Contents of applications; general information
- 34, Contents of applications; technical information
- 36, Technical specifications
- 37, Agreement limiting access to Classified Information
- 38, Ineligibility of certain applicants
- 39, Public inspection of applications
- 40, Standards for Licenses, Certifications, and Regulatory Approvals Common standards
- 41, Additional standards for class 104 licenses
- 42, Additional standard for class 103 licenses
- 43, Additional standards and provisions affecting class 103 licenses and certifications for commercial power
- 44, Combustible gas control for nuclear power reactors
- 45, Standards for construction permits, operating licenses, and combined licenses
- 46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors
- 47, Emergency plans
- 48, Fire protection
- 49, Environmental qualification of electric equipment important to safety for nuclear power plants
- 50, Issuance, Limitations, and Conditions of Licenses and Construction Permits Issuance of licenses and construction permits
- 51, Continuation of license
- 52, Combining licenses
- 53, Jurisdictional limitations
- 54, Conditions of licenses
- 55, Conditions of construction permits, early site permits, combined licenses, and manufacturing licenses
- 56, Conversion of construction permit to license; or amendment of license
- 57, Issuance of operating license
- 58, Hearings and report of the Advisory Committee on Reactor Safeguards
- 59, Changes, tests and experiments
- 60, Acceptance criteria for fracture prevention measures for lightwater nuclear power reactors for normal operation
- 61, Fracture toughness requirements for protection against pressurized thermal shock events
- 62, Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants
- 63, Loss of all alternating current power
- 64, Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors
- 65, Requirements for monitoring the effectiveness of maintenance at nuclear power plants
- 66, Requirements for thermal annealing of the reactor pressure vessel
- 67, Accident source term
- 68, Criticality accident requirements
- 69, Inspections, Records, Reports, Notifications Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors
- 70, Inspections
- 71, Maintenance of records, making of reports
- 72, Immediate notification requirements for operating nuclear power reactors
- 73, Licensee event report system
- 74, Notification of change in operator or senior operator status
- 75, Reporting and recordkeeping for decommissioning planning
- 76, . Licensee's change of status; financial qualifications
- 78, US/IAEA Safeguards Agreement Facility information and verification
- 80, Transfers of Licenses--Creditors' Rights--Surrender of Licenses Transfer of licenses
- 81, Creditor regulations
- 82, Termination of license
- 83, Release of part of a power reactor facility or site for unrestricted use
- 90, Amendment of License or Construction Permit at Request of Holder Application for amendment of license, construction permit, or early site permit
- 91, Notice for public comment; State consultation
- 92, Issuance of amendment
- 100, Revocation, Suspension, Modification, Amendment of Licenses and Construction Permits, Emergency Operations by the Commission Revocation, suspension, modification of licenses, permits, and approvals for cause
- 101, Retaking possession of special nuclear material
- 102, Commission order for operation after revocation
- 103, Suspension and operation in war or national emergency
- 109, Backfitting
Appendices:
- 10 CFR 50 Appendix A, Appendix a to Part 50-General Design Criteria for Nuclear Power Plants
- 10 CFR 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants
- 10 CFR 50 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
- 10 CFR 50 Appendix D, Appendix D to Part 50--Reserved
- 10 CFR 50 Appendix E, Appendix E to Part 50-Emergency Planning and Preparedness for Production and Utilization Facilities
- 10 CFR 50 Appendix F, Appendix F to Part 50--Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities
- 10 CFR 50 Appendix G, Appendix G to Part 50-Fracture Toughness Requirements
- 10 CFR 50 Appendix H, Appendix H to Part 50-Reactor Vessel Material Surveillance Program Requirements
- 10 CFR 50 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 Reasonably Achievable" for Radioactive Material In Light-Water-Cooled Nuclear Power Reactor E
- 10 CFR 50 Appendix J, Appendix J to Part 50-Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors
- 10 CFR 50 Appendix K, Appendix K to Part 50-Eccs Evaluation Models
- 10 CFR 50 Appendix L, Appendix L to Part 50--Reserved
- 10 CFR 50 Appendix M, Appendix M to Part 50--Reserved
- 10 CFR 50 Appendix N, 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
- 10 CFR 50 Appendix O, Appendix O to Part 50-Reserved
- 10 CFR 50 Appendix P, Appendix P to Part 50--Reserved
- 10 CFR 50 Appendix Q, Appendix Q to Part 50--Pre-Application Early Review of Site Suitability Issues
- 10 CFR 50 Appendix R, Appendix R to Part 50-Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979
- 10 CFR 50 Appendix S, General Information
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