Nuclear Regulatory Commission – Federal Register Recent Federal Regulation Documents
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Information Collection: NRC Form 212, Qualifications Investigation Professional, Technical, and Administrative Positions
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, NRC Form 212, ``Qualifications Investigation Professional, Technical, and Administrative Positions.''
Information Collection: NRC Form 536, “Operator Licensing Examination Data”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``NRC Form 536, ``Operator Licensing Examination Data.''
Draft Interim Staff Guidance: Use of the Decommissioning Trust Fund During Operations for Major Radioactive Component Disposal
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft Interim Staff Guidance (ISG) ``Use of the Decommissioning Trust Fund During Operations for Major Radioactive Component Disposal.'' The purpose of this proposed ISG is to provide the NRC staff's regulatory position to licensees of nuclear power reactors regarding the use of funds from the decommissioning trust fund dedicated to the radiological decommissioning of a reactor facility for the disposal of major radioactive components (MRCs) while the facility is in an operational status. This proposed ISG may be used in connection with requests for exemption from NRC regulations related to the withdrawal of funds from reactor decommissioning trust funds (DTFs).
Regulatory Guide: Sizing Large Lead-Acid Storage Batteries
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.212, ``Sizing Large Lead-Acid Storage Batteries''. This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for sizing large lead-acid storage batteries for production and utilization facilities.
NUREG: Report to Congress on Abnormal Occurrences: Fiscal Year 2022; Dissemination of Information
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 0090, Volume 45, ``Report to Congress on Abnormal Occurrences: Fiscal Year 2022.'' The report describes those events that the NRC or an Agreement State identified as abnormal occurrences (AOs) during fiscal year (FY) 2022, based on the criteria defined by the Commission. The report describes eight events at Agreement State-licensed facilities and one event at an NRC-licensed facility.
Constellation Energy Generation, LLC; Braidwood Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to Renewed Facility Operating License Nos. NPF- 72 and NPF-77, which authorize Constellation Energy Generation, LLC, (Constellation, licensee) to operate Braidwood Station (Braidwood), Units 1 and 2. The proposed amendments would change Technical Specification (TS) Surveillance Requirement (SR) 3.7.9.2 to allow an ultimate heat sink (UHS) temperature of less than or equal to 102.8 degrees Fahrenheit ([deg]F) from the date of issuance of the amendments through September 30, 2023.
In the Matter of APINDE Inc.
On May 11, 2023, the NRC staff issued an Order revoking APINDE Inc's NRC license, effective 30 days from the date of the Order, due to a determination that the license was issued based on inaccurate information and in consideration that APINDE Inc. does not have a qualified Radiation Safety Officer (RSO). The license has been suspended since August 22, 2019, when the NRC staff, through an investigation by the NRC's Office of Investigations, first identified sufficient cause that the license had been issued based on inaccurate information and that APINDE Inc's RSO was not qualified. In a September 10, 2019, letter, the APINDE Inc. President/CEO acknowledged errors in the license application and stated that corrective actions would be taken. Beyond this written response, APINDE Inc. did not take any steps to restore the requisite reasonable assurance that operations could be conducted in compliance with the Commission's requirements and that the health and safety of the public would be protected.
List of Approved Spent Fuel Storage Casks: TN Americas LLC, NUHOMS® EOS Dry Spent Fuel Storage System Certificate of Compliance No. 1042, Amendment No. 3
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of July 17, 2023, for the direct final rule that was published in the Federal Register on May 2, 2023. The direct final rule amended the TN Americas LLC, NUHOMS[supreg] EOS Dry Spent Fuel Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 3 to Certificate of Compliance No. 1042.
Revision of Fee Schedules; Fee Recovery for Fiscal Year 2023
The U.S. Nuclear Regulatory Commission (NRC) is amending the licensing, inspection, special project, and annual fees charged to its applicants and licensees. These amendments are necessary to comply with the Nuclear Energy Innovation and Modernization Act, which requires the NRC to recover, to the maximum extent practicable, approximately 100 percent of its annual budget less certain amounts excluded from this fee-recovery requirement.
Draft Regulatory Guide: Release of Patients Administered Radioactive Material
On April 21, 2023, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on draft regulatory guide (DG), DG-8061, ``Release of Patients Administered Radioactive Material.'' The public comment period was originally scheduled to close on June 20, 2023. 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.
Draft Regulatory Guide: Damping Values for Seismic Design of Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1364, ``Damping Values for Seismic Design of Nuclear Power Plants.'' This DG is proposed Revision 2 of Regulatory Guide (RG) 1.61. This DG describes an approach on damping values that is acceptable to the NRC staff for use in meeting regulatory requirements for the seismic response analysis of seismic Category I nuclear power plant structures, systems, and components.
Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to section 189.a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular monthly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration (NSHC), notwithstanding the pendency before the Commission of a request for a hearing from any person.
Information Collection: Reporting of Defects and Noncompliance
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``Reporting of Defects and Noncompliance.''
Information Collection: Notices of Enforcement Discretion (NOEDs) for Operating Power Reactors and Gaseous Diffusion Plants (NRC Enforcement Policy)
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Notices of Enforcement Discretion (NOEDs) for Operating Power Reactors and Gaseous Diffusion Plants (NRC Enforcement Policy).''
Draft Regulatory Guide: Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-3057, ``Weather- Related Administrative Controls at Independent Spent Fuel Storage Installations.'' This DG is a proposed new regulatory guide (RG) 3.77 and provides licensees with methods that the NRC staff considers acceptable for specific or general licensees of an independent spent fuel storage installation and certificate of compliance holders to comply with protection against environmental conditions and natural phenomena.
GE-Hitachi Nuclear Energy Americas, LLC; Nuclear Test Reactor; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register on March 22, 2023, regarding an environmental assessment and finding of no significant impact for the consideration of renewal of Facility License No. R-33, held by the GE-Hitachi Nuclear Energy Americas, LLC, for the continued operation of the Nuclear Test Reactor. This action is necessary to correct the radioactivity concentration units used.
NUREG: Artificial Intelligence Strategic Plan: Fiscal Years 2023-2027
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 2261, ``Artificial Intelligence Strategic Plan: Fiscal Years 2023- 2027,'' dated May 31, 2023. The NRC's Artificial Intelligence (AI) Strategic Plan, establishes the vision and goals for the NRC to continue to improve its skills and capabilities to review and evaluate the application of AI to NRC-regulated activities, maintain awareness of technological innovations, and ensure the safe and secure use of AI in NRC-regulated activities. The AI Strategic Plan includes five goals: (1) ensure NRC readiness for regulatory decision-making, (2) establish an organizational framework to review AI applications, (3) strengthen and expand AI partnerships, (4) cultivate an AI proficient workforce, and (5) pursue use cases to build an AI foundation across the NRC.
Waste Control Specialists LLC; Superseding Exemption Order
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Order superseding a previously issued Order to Waste Control Specialists LLC (WCS) on December 3, 2014 (2014 Order), as supplemented by NRC letters to WCS from 2016 to 2022. The current and past NRC Orders are associated with an exemption from NRC regulations, which requires persons who own, acquire, deliver, receive, possess, use, or transfer Special Nuclear Material (SNM) to obtain an NRC license pursuant to the NRC requirements. The current action is in response to a request by WCS dated June 30, 2022. In the letter, WCS requested permission to: (1) move the U.S. Department of Energy (DOE) Los Alamos National Laboratory (LANL) Waste from the WCS Federal Waste Facility (FWF) disposal cell to the WCS Treatment, Storage, and Disposal Facility (TSDF) Bin Storage Area (BSA)-1 Enclosure; (2) prepare the LANL Waste for shipment in the TSDF BSA-1 Enclosure; and (3) temporarily store the LANL Waste in the TSDF BSA-1 Enclosure.
Cimarron Environmental Response Trust; Cimarron Facility
The U.S. Nuclear Regulatory Commission (NRC) has received a license amendment application from Cimarron Environmental Response Trust (CERT or the applicant) for the Cimarron Facility, located in the city of Guthrie, which is in Logan County, Oklahoma. The license authorizes Possession of Byproduct, Source, and Special Nuclear Material (SNM-928). In this amendment request, CERT requests approval of its proposed Facility Decommissioning Plan (DP), Revision 3 for the Cimarron Facility. The requested license amendment is necessary for CERT to complete the remaining decommissioning activities needed for the NRC to release the Cimarron site for unrestricted use. The requested license amendment is also necessary to ultimately terminate SNM-928; however, license termination is a separate action that requires a separate application from CERT and a separate NRC finding that the site is suitable for release. Because the license application contains Sensitive Unclassified Non-Safeguards Information (SUNSI), an order imposes procedures to obtain access to this type of information for contention preparation.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 9, “Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 03, Chapter 9, ``Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 12, “Post-Construction Inspection, Testing, and Analysis Program”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 06, Chapter 12, ``Post-Construction Inspection, Testing, and Analysis Program.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non- light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project, “Risk-informed Technical Specifications”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 08, ``Risk-informed Technical Specifications.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non- LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Review of Risk-Informed, Technology Inclusive Advanced Reactor Applications-Roadmap
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 01, ``Review of Risk-Informed, Technology Inclusive Advanced Reactor ApplicationsRoadmap.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project, “Risk-informed Performance-Based Fire Protection Program (for Operations)”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 09, ``Risk-informed Performance-based Fire Protection Program (for Operations).'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 11, “Organization and Human-System Considerations”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 05, Chapter 11, ``Organization and Human-System Considerations.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 2, “Site Information”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 02, Chapter 2, ``Site Information.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 10, “Control of Occupational Dose”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 04, Chapter 10, ``Control of Occupational Dose.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non- LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, manufacturing licenses, standard design approval, or design certifications.
Draft Interim Staff Guidance: Advanced Reactor Content of Application Project, “Risk-informed Inservice Inspection/Inservice Testing”
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 07, ``Risk-informed Inservice Inspection/Inservice Testing.'' The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined license, manufacturing licenses, standard design approval, or design certifications.
Draft Regulatory Guide: Guidance for a Technology-Inclusive Content of Application Methodology To Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Regulatory Guide (DG-1404), ``Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors.'' This DG is a proposed new regulatory guide to provide guidance to assist interested parties and prospective applicants for the development of content for major portions of their safety analysis reports required in applications for licenses, certifications, and approvals by the NRC to ensure that non-light water reactor (non-LWR) facility designs using the Licensing Modernization Project (LMP) process meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
Constellation Energy Generation, LLC; Limerick Generating Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has issued amendments to Constellation Energy Generation, LLC (Constellation, the licensee) for Renewed Facility Operating License Nos. NPF-39 and NPF-85 for operation of the Limerick Generating Station, Units 1 and 2 (Limerick), located in Montgomery County, Pennsylvania. These amendments revise a license condition in each license to allow the use of an alternative seismic approach to categorizing structures, systems, and components in the licensee's application of NRC regulations. The NRC has also denied Constellation's request for amendments to Renewed Facility Operating License Nos. NPF-39 and NPF-85 for operation of Limerick to allow proposed alternative defense-in-depth and pressure boundary component processes for categorizing structures, systems, and components in the licensee's application of NRC regulations.
Vistra Operations Company LLC and Energy Harbor Nuclear Corp.; Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Beaver Valley Power Station, Unit Nos. 1 and 2; Davis-Besse Nuclear Power Station, Unit No. 1; Perry Nuclear Power Plant, Unit No. 1; and the Associated Independent Spent Fuel Storage Installations; Consideration of Approval of Transfer of Licenses and Conforming Amendments
The U.S. Nuclear Regulatory Commission (NRC, the Commission) received and is considering approval of an application filed by Vistra Operations Company LLC (VistraOps) and Energy Harbor Nuclear Corp. (collectively, the applicants) on April 14, 2023, as supplemented by letter dated April 20, 2023. The application seeks NRC approval of the indirect transfer of control of Facility Operating License Nos. NFP-87 and NFP-89 for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (Comanche Peak), respectively, and its generally licensed independent spent fuel storage installation (ISFSI); the indirect transfer of control of Renewed Facility Operating License Nos. DPR-66, NPF-73, and NPF-3 for Beaver Valley Power Station, Unit Nos. 1 and 2 (Beaver Valley), and Davis-Besse Nuclear Power Station, Unit No. 1 (Davis- Besse), respectively, and Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit No. 1 (Perry), and their associated generally licensed ISFSIs (collectively, the EH Facilities); and the direct transfer of the operating authority for the EH Facilities to VistraOps. The NRC is also considering amending the licenses for administrative purposes to reflect the proposed transfer. The application contains sensitive unclassified non-safeguards information (SUNSI).
Draft Regulatory Guide: Qualification of Safety-Related Actuators in Production and Utilization Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1386, ``Qualification of Safety-Related Actuators in Production and Utilization Facilities.'' This DG is the proposed Revision 2 of Regulatory Guide (RG) 1.73 ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants.'' This DG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for the environmental qualification of safety related actuators in production and utilization facilities. It endorses, with exceptions, additions, and clarifications, the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 382-2019, ``IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations and Other Nuclear Facilities.''
Abnormal Occurrence Reporting
The U.S. Nuclear Regulatory Commission (NRC) is proposing limited revisions to its policy statement on reporting abnormal occurrences (AO) to Congress. The proposed revisions are to the medical event criteria for determining events that are significant from the standpoint of public health or safety.
Southern Nuclear Operating Company Inc.; Vogtle Electric Generating Plant, Unit 4
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Combined License (COL) NPF-92, issued to Southern Nuclear Operating Company, Inc. (SNC), and Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM, LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, Authority of Georgia, and the City of Dalton, Georgia (collectively, SNC), for construction and operation of the Vogtle Electric Generating Plant (VEGP), Unit 4, located in Burke County, Georgia.
Constellation Energy Generation, LLC; Quad Cities Nuclear Power Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to a January 27, 2023, request from Constellation Energy Generation, LLC (Constellation), regarding the submittal of a subsequent license renewal application for Quad Cities Nuclear Power Station, Units 1 and 2. Pursuant to this exemption, if the licensee submits a subsequent license renewal application at least 3 years prior to the expiration of the existing operating licenses, and if the NRC staff finds it acceptable for docketing, the existing operating licenses will be in timely renewal under NRC regulations until the NRC has made a final determination on whether to approve the subsequent license renewal application.
Westinghouse Electric Company, LLC; Order Approving Indirect Transfer of Control of License
The U.S. Nuclear Regulatory Commission (NRC) issued an Order approving the indirect transfer of several licenses for Westinghouse Electric Company, LLC (Westinghouse). Westinghouse is the holder of special nuclear materials (SNM) license number SNM-1107, which authorizes the possession and use of SNM at the Columbia Fuel Fabrication Facility in Hopkins, South Carolina. Westinghouse is also the holder of several export licenses as noted in the Order. The Order approves the indirect transfer of control of these licenses resulting from the acquisition of Westinghouse's intermediate parent company, Brookfield WEC Holdings Inc., by Watt New Aggregator L.P., in which Brookfield Corporation will hold a controlling 51 percent interest and Cameco Corporation will hold the remaining 49 percent interest. The Order became effective upon issuance.
Waste Control Specialists LLC
The U.S. Nuclear Regulatory Commission (NRC) is issuing an Environmental Assessment (EA) and Finding of No Significant Impact (FONSI) in support of the NRC's consideration of a June 30, 2022, Waste Control Specialists LLC (WCS) request for a superseding Order to its current (2014) NRC Order (as supplemented by subsequent NRC letters to WCS from 2016 to 2022). In its letter, WCS requested authorization to (1) move the U.S. Department of Energy (DOE) Los Alamos National Laboratory (LANL) Waste at the WCS Site from its current location at the WCS Federal Waste Facility (FWF) disposal cell to another location at the WCS Site, the WCS Treatment, Storage, and Disposal Facility (TSDF) Bin Storage Area (BSA)-1 Enclosure, (2) prepare the LANL Waste in the WCS TSDF BSA-1 Enclosure for shipment (e.g., replace lifting straps for Standard Waste Boxes (SWBs), replace filter vents in SWBs, perform borescope in SWBs, take air samples from head space in SWBs), and (3) temporarily store the LANL Waste in the WCS TSDF BSA-1 Enclosure until the DOE ships the LANL Waste off the WCS Site to a future DOE determined location, which is currently expected to be either the DOE LANL or the DOE Waste Isolation Pilot Plant (WIPP) Facility.
Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to section 189.a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular monthly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration (NSHC), notwithstanding the pendency before the Commission of a request for a hearing from any person.
Rare Element Resources, Inc.; Upton Pilot Project
The U.S. Nuclear Regulatory Commission (NRC) received a license application from Rare Element Resources, Inc. which authorizes possession and use of source material associated with its Upton Pilot Project. The Upton Pilot Project includes a mined ore pile in the Black Hills National Forest in Crook County, Wyoming for the purpose of extracting rare earth element ores, and a rare earth element processing plant in Upton, Wyoming. Because the license application contains Sensitive Unclassified Non-Safeguards Information (SUNSI), an order imposes procedures to obtain access to this type of information for contention preparation.
Holtec International; HI-STORE Consolidated Interim Storage Facility
The U.S. Nuclear Regulatory Commission (NRC) has issued Materials License No. SNM-2516 to Holtec International (Holtec) to construct and operate the HI-STORE Consolidated Interim Storage Facility (CISF) as proposed in its license application, as amended, and to receive, possess, store, and transfer spent nuclear fuel at the HI- STORE CISF in Lea County, New Mexico. Holtec will be required to operate under the conditions listed in Materials License No. SNM-2516. The NRC staff has published a record of decision (ROD) that supports the NRC's decision to approve Holtec's license application for the HI- STORE CIS Facility and to issue the license.
Framatome, Inc.
The U.S. Nuclear Regulatory Commission (NRC) received and is considering issuing an extension on an export license (XW015), requested by Framatome, Inc. by application dated February 8, 2023. Under export license, XW015, Framatome, Inc. is authorized to return up to 25,000 kilograms (kg) of non-combustible Class A radioactive waste (e.g., glass, metal, slag) contaminated with up to 40 kg of uranium (containing up to 5 percent by weight total of U-235) after treatment at a Framatome facility in Richland, Washington to Germany. The request seeks the approval to extend the expiration date for this license for an additional 5 years, to December 31, 2028. The NRC is providing notice of the opportunity to comment, request a hearing, and petition to intervene on Framatome, Inc.'s application.
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