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10 CFR 50.92, Issuance of Amendment - kanterella
10 CFR 50.92, Issuance of Amendment
Issuance of amendment
4 Federal Register
(a) In determining whether an amendment to a license, construction permit, or early site permit will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses, construction permits, or early site permits to the extent applicable and appropriate. If the application involves the material alteration of a licensed facility, a construction permit will be issued before the issuance of the amendment to the license, provided however, that if the application involves a material alteration to a nuclear power reactor manufactured under part 52 of this chapter before its installation at a site, or a combined license before the date that the Commission makes the finding under § 52.103(g) of this chapter, no application for a construction permit is required. If the amendment involves a significant hazards consideration, the Commission will give notice of its proposed action:
(1) Under § 2.105 of this chapter before acting thereon; and
(2) As soon as practicable after the application has been docketed.
(b) The Commission will be particularly sensitive to a license amendment request that involves irreversible consequences (such as one that permits a significant increase in the amount of effluents or radiation emitted by a nuclear power plant).
(c) The Commission may make a final determination, under the procedures in § 50.91, that a proposed amendment to an operating license or a combined license for a facility or reactor licensed under §§ 50.21(b) or 50.22, or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or
(2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or
(3) Involve a significant reduction in a margin of safety.
[[[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=1986_register&page=7767&position=1%7C51 FR 7767, Mar. 6, 1986]]; [[FR::http://frwebgate.access.gpo.gov/cgi-bin/getpage.cgi?dbname=2007_register&page=49504&position=1%7C72 FR 49504, Aug. 28, 2007]]]
[[URL::http://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-0092.html%7CNRC website 10 CFR 50.92]]
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
110, Enforcement Violations
111, Criminal penalties
120, Additional Standards for Licenses, Certifications, and Regulatory Approvals Training and qualification of nuclear power plant personnel
150, Aircraft impact assessment
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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This page was last edited on 1 December 2016, at 02:24.