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No license under this part shall be deemed to have been issued for activities which are not under or within the jurisdiction of the United States.
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 2015-01-01
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 issuing this advance notice of proposed rulemaking (ANPR) to obtain input from stakeholders on the development of a draft regulatory basis. The draft regulatory basis would support potential changes to the NRC's regulations for the decommissioning of nuclear power reactors. The NRC's goals in amending these regulations would be to provide an efficient decommissioning process, reduce the need for exemptions from existing regulations, and support the principles of good regulation, including openness, clarity, and reliability. The NRC is soliciting public comments on the contemplated action and invites stakeholders and interested persons to participate. The NRC plans to hold a public meeting to promote full understanding of the questions contained in this ANPR and facilitate public comment.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations that establish regulatory requirements for nuclear power reactor applicants and licensees to mitigate beyond-design-basis events. The NRC is proposing to make generically applicable requirements in Commission orders for mitigation of beyond-design-basis events and for reliable spent fuel pool instrumentation. This proposed rule would establish regulatory requirements for an integrated response capability, including supporting requirements for command and control, drills, training and change control. This proposed rule also would establish requirements for enhanced onsite emergency response capabilities. Finally, this proposed rule would address a number of petitions for rulemaking (PRMs) submitted to the NRC following the March 2011 Fukushima Dai-ichi event. This rulemaking is applicable to power reactor licensees, power reactor license applicants, and decommissioning power reactor licensees. This rulemaking combines two NRC activities for which documents have been published in the Federal Register —Onsite Emergency Response Capabilities (RIN 3150-AJ11; NRC-2012-0031) and Station Blackout Mitigation Strategies (RIN 3150-AJ08; NRC-2011-0299). The new identification numbers for this consolidated rulemaking are RIN 3150-AJ49 and NRC-2014-0240.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference seven recent editions and addenda to the American Society of Mechanical Engineers (ASME) codes for nuclear power plants and a standard for quality assurance. The NRC is also proposing to incorporate by reference four ASME code cases. This action is in accordance with the NRC's policy to periodically update the regulations to incorporate by reference new editions and addenda of the ASME codes and is intended to maintain the safety of nuclear power plants and to make NRC activities more effective and efficient.
On May 4, 2015, the U.S. Nuclear Regulatory Commission (NRC) requested public comment on an advance notice of proposed rulemaking (ANPR) to obtain input for the development of a regulatory basis that would support potential amendments to those regulations concerning how NRC licensees demonstrate meeting the “as low as is reasonably achievable” standard with respect to effluents from nuclear power plants. The purpose of the potential amendments would be to more closely align these NRC regulations with the terminology and dose-related methodology published by the International Commission on Radiation Protection (ICRP), as contained in the ICRP Publication 103 (2007). The public comment period was originally scheduled to close on September 1, 2015. The NRC received a request to extend the public comment period on the ANPR and is approving a one-time, 30-day extension to provide additional time for members of the public and other stakeholders to develop and submit their comments.
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to make miscellaneous corrections. These changes include updating the name and the phone number of the U.S. Government Publishing Office, updating the address for the National Technical Information Service, correcting typographical errors, correcting misspellings, and correcting references. This document is necessary to inform the public of these non-substantive changes to the NRC's regulations.
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 require all nuclear power plant (NPP) licensees to use in-core monitoring devices at different elevations and radial positions throughout the reactor core. The PRM was submitted by Mr. Mark Edward Leyse (the petitioner) on March 13, 2015, docketed by the NRC on April 24, 2015, and assigned Docket No. PRM-50-111. The NRC is examining the issues raised in this PRM to determine whether they should be considered in rulemaking. The NRC is not requesting public comment on this PRM at this time.
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on a draft regulatory basis for a proposed rulemaking to amend the current financial qualification requirements of “reasonable assurance” to the review standard of “appears to be financially qualified.” The NRC plans to hold a public meeting to promote full understanding of this regulatory basis and facilitate public comment.
The U.S. Nuclear Regulatory Commission (NRC) is issuing this advance notice of proposed rulemaking (ANPR) to obtain input from stakeholders on the development of a regulatory basis for the NRC's regulations governing radioactive effluents from nuclear power plants. The regulatory basis would support potential changes to better align the NRC regulations governing dose assessments for radioactive effluents from nuclear power plant operations with the most recent terminology and dose-related methodology published by the International Commission on Radiological Protection (ICRP) contained in the ICRP Publication 103 (2007). The NRC has identified specific questions and issues with respect to a possible revision of the NRC's current regulations and guidance governing radioactive gaseous and liquid effluents from nuclear power plants. The NRC seeks public and other stakeholder input on these questions and issues in order to develop the regulatory basis.
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1322, “Alternate Risk-Informed Approach for Addressing the Effects of Debris On Post-Accident Long-Term Core Cooling.” This DG proposes new guidance that describes methods and procedures that the NRC staff considers acceptable for complying with a voluntary, risk-informed alternative in a proposed revision of the NRC's regulation governing the design of emergency core cooling systems (ECCS).
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Michael D. Tschiltz, on behalf of the Nuclear Energy Institute (NEI or the petitioner), dated January 15, 2015, requesting that the NRC clarify the applicability of an NRC regulation to combined licenses (COLs). The NRC regulation allows structures, systems, and components (SSCs) of nuclear power reactors to be re-categorized based upon risk-informed considerations. Such re-categorization would result in changes in which NRC requirements would apply to those SSCs. The petition was docketed by the NRC on February 6, 2015, and has been assigned Docket No. PRM-50-110. The NRC is not requesting public comment on PRM-50-110 at this time.
The U.S. Nuclear Regulatory Commission (NRC) will consider in the rulemaking process the issues raised in a petition for rulemaking (PRM), PRM-50-107, submitted by James Lieberman (the petitioner). The petitioner requested that the NRC amend its regulations to require that all persons seeking NRC approvals provide the NRC with complete and accurate information. Current NRC regulations pertaining to completeness and accuracy of information apply only to NRC licensees and license applicants. The NRC has determined that the issues raised in the PRM have merit and are appropriate for consideration in the rulemaking process.
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking (PRM) from Sandra Gavutis on behalf of C-10 Research and Education Foundation (C-10 or the petitioner), dated September 25, 2014, requesting that the NRC amend its regulations to provide improved identification techniques against Alkali-Silica Reaction (ASR) concrete degradation at nuclear power plants. The petition was docketed by the NRC on October 8, 2014, and has been assigned Docket No. PRM-50-109. The NRC is requesting public comments on this petition for rulemaking.