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Licenses will be issued to named persons applying to the Commission therefor, and will be either class 104 or class 103.
This is a list of United States Code sections, Statutes at Large, Public Laws, and Presidential Documents, which provide rulemaking authority for this CFR Part.
This list is taken from the Parallel Table of Authorities and Rules provided by GPO [Government Printing Office].
It is not guaranteed to be accurate or up-to-date, though we do refresh the database weekly. More limitations on accuracy are described at the GPO site.
§ 2131 - License required
§ 2132 - Utilization and production facilities for industrial or commercial purposes
§ 2133 - Commercial licenses
§ 2134 - Medical, industrial, and commercial licenses
§ 2135 - Antitrust provisions governing licenses
§ 2138 - Suspension of licenses during war or national emergency
§ 2152 - Policies contained in international arrangements
§ 2201 - General duties of Commission
§ 2232 - License applications
§ 2233 - Terms of licenses
§ 2234 - Inalienability of licenses
§ 2236 - Revocation of licenses
§ 2237 - Modification of license
§ 2239 - Hearings and judicial review
§ 2282 - Civil penalties
§ 4332 - Cooperation of agencies; reports; availability of information; recommendations; international and national coordination of efforts
§ 5841 - Establishment and transfers
§ 5842 - Licensing and related regulatory functions respecting selected Administration facilities
§ 5844 - Office of Nuclear Safety and Safeguards
§ 5846 - Compliance with safety regulations
§ 3504 note - Authority and functions of Director
119 Stat. 594
92 Stat. 2951
Title 10 published on 2015-12-04
The following are ALL rules, proposed rules, and notices (chronologically) published in the Federal Register relating to 10 CFR Part 50 after this date.
The U.S. Nuclear Regulatory Commission (NRC) is requesting comments on a draft regulatory basis to support a rulemaking that would amend NRC's regulations for the decommissioning of nuclear power reactors. The NRC's goals in amending these regulations would be to provide for an efficient decommissioning process; reduce the need for exemptions from existing regulations; address other decommissioning issues deemed relevant by the NRC staff; and support the principles of good regulation, including openness, clarity, and reliability. The NRC plans to hold a public meeting to discuss the draft regulatory basis and facilitate public comment.
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), dated September 10, 2015, submitted by Dr. Alexander DeVolpi (the petitioner). The petition was docketed by the NRC on September 21, 2015, and was assigned Docket No. PRM-50-113. The petitioner requested that the NRC amend its regulations to require “installation of ex-vessel instrumentation for uninterruptible monitoring of coolant and fuel in reactors and spent-fuel pools.” The NRC is denying the petition because the Commission finds that the issues raised by the petitioner have been addressed by actions taken by the NRC in response to the Fukushima Dai-ichi nuclear accident.
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing the rulemaking activities associated with potential changes to its radiation protection and reactor effluents regulations. The purpose of this action is to inform members of the public that these rulemaking activities are being discontinued and to provide a brief discussion of the NRC's decision to discontinue them. These rulemaking activities will no longer be reported in the NRC's portion of the Unified Agenda of Regulatory and Deregulatory Actions (the Unified Agenda).
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1334, “Guidance for Implementation of 10 CFR 50.59, `Changes, Tests, and Experiments.' ” This draft regulatory guide provides licensees and applicants with a method that the staff of the NRC considers acceptable for use in complying with the Commission's regulations on the process by which licensees may make changes to their facilities and procedures, as described in the safety analysis report, without prior NRC approval, under certain conditions.
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking (PRM), dated September 1, 2016, from David Lochbaum on behalf of the Union of Concerned Scientists and two co-petitioners (the petitioners). The petitioners request that the NRC “promulgate regulations applicable to nuclear power reactors with operating licenses issued by the NRC but in an extended outage.” The PRM was docketed by the NRC on September 14, 2016, and has been assigned Docket No. PRM-50-114. The NRC is examining the issues raised in PRM-50-114 to determine whether they should be considered in rulemaking. The NRC is requesting public comment on the petition.
The U.S. Nuclear Regulatory Commission (NRC) is announcing the discontinuation of further regulatory action on Draft Regulatory Guide (DG) DG-1216, “Plant-Specific Applicability of Transition Break Size Specified in 10 CFR 50.46a,” and its withdrawal. Draft Regulatory Guide DG-1216 was a proposed new regulatory guide written to provide implementing guidance for a proposed rule “Risk-Informed Changes to Loss-of-Coolant Accident Technical Requirements,” (Emergency core cooling system (ECCS) rulemaking)) that provided a voluntary, alternate approach for evaluating the performance of an ECCS. The NRC is discontinuing further regulatory action on the DG and not publishing the DG in final form because the NRC has discontinued the underlying rulemaking.
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to make miscellaneous corrections. The amendments include correcting a senior NRC management position title; correcting terminology for consistency in NRC regulations; and correcting contact information, references, typographical errors, and misspellings. This document is necessary to inform the public of these non-substantive amendments to the NRC's regulations.
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing a rulemaking activity titled, “Risk-Informed Changes to Loss-Of-Coolant Accident Technical Requirements.” The purpose of this action is to inform members of the public of the discontinuation of this rulemaking and to provide a brief discussion of the NRC's decision to discontinue it. This rulemaking activity will no longer be reported in the NRC's portion of the Unified Agenda of Regulatory and Deregulatory Actions (the Unified Agenda).
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing eight rulemaking activities. The purpose of this action is to inform members of the public that these rulemaking activities are being discontinued and to provide a brief discussion of the NRC's decision to discontinue them. These rulemaking activities will no longer be reported in the NRC's portion of the Unified Agenda of Regulatory and Deregulatory Actions (the Unified Agenda).
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM or the petition), PRM-50-108, submitted by Mr. Mark Edward Leyse (the petitioner). The petitioner requested that the NRC require power reactor licensees to perform evaluations to determine the potential consequences of various postulated spent fuel pool (SFP) accident scenarios. The evaluations would be required to be submitted to the NRC for informational purposes. The NRC is denying the petition because the NRC does not believe the information is needed for effective NRC regulatory decisionmaking with respect to SFPs or for public safety, environmental protection, or common defense and security.
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM) submitted by the Natural Resources Defense Council, Inc. (NRDC), and Mr. Paul M. Blanch (collectively, the petitioners) on June 18, 2012. The petitioners requested that the NRC amend its regulations to clearly and unequivocally require the environmental qualification of all safety-related cables, wires, splices, connections and other ancillary electrical equipment that may be subjected to submergence and/or moisture intrusion during normal operating conditions, severe weather, seasonal flooding, and seismic events, and post-accident conditions, both inside and outside of a reactor's containment building. The NRC is denying this petition because the current regulations already address environmental qualification in both mild and design basis event conditions of electrical equipment located both inside and outside of the containment building that is important to safety, and the petition does not provide significant new or previously unconsidered information sufficient to justify rulemaking.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference proposed revisions of three regulatory guides (RGs) which would approve new, revised, and reaffirmed Code Cases published by the American Society of Mechanical Engineers (ASME). This proposed action would allow nuclear power plant licensees, and applicants for construction permits, operating licenses, combined licenses, standard design certifications, standard design approvals and manufacturing licenses, to use the Code Cases listed in these draft RGs as alternatives to engineering standards for the construction, inservice inspection, and inservice testing of nuclear power plant components. These engineering standards are set forth in ASME Boiler and Pressure Vessel Codes and ASME Operations and Maintenance Codes, which are currently incorporated by reference into the NRC's regulations. The NRC is requesting comments on this proposed rule and on the draft versions of the three RGs proposed to be incorporated by reference. The NRC is also making available a related draft RG that lists Code Cases that the NRC has not approved for use. This draft RG will not be incorporated by reference into the NRC's regulations.
The U.S. Nuclear Regulatory Commission (NRC) plans to hold a public meeting to discuss proposed amendments to its regulations to incorporate by reference seven recent editions and addenda to the American Society of Mechanical Engineers (ASME) codes for nuclear power plants, an ASME standard for quality assurance, and four ASME code cases. The purpose of the meeting is to discuss public comments on the proposed rule, in order to enhance the NRC's understanding of the comments.
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking (PRM) requesting that the NRC amend its “Domestic licensing of production and utilization facilities” regulations to define the term “important to safety” and provide a set of specific criteria for determining which structures, systems, components (SSCs), and functions are “important to safety.” The petition, dated July 20, 2015, was submitted by Kurt T. Schaefer (the petitioner) and was supplemented on August 31, 2015. The petition was docketed by the NRC on September 4, 2015, and was assigned Docket Number PRM-50-112. The NRC is examining the issues raised in this petition to determine whether it should be considered in rulemaking. The NRC is requesting public comments on this petition for rulemaking.
On November 19, 2015, the U.S. Nuclear Regulatory Commission (NRC) requested comments on an advance notice of proposed rulemaking (ANPR) on regulatory improvements for decommissioning power reactors. The public comment period was originally scheduled to close on January 4, 2016. The NRC has decided to extend the public comment period to allow more time for members of the public to develop and submit their comments.