Nuclear Regulatory Commission – Federal Register Recent Federal Regulation Documents
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Pacific Gas and Electric Company; Diablo Canyon Power Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to an October 31, 2022, request from Pacific Gas and Electric Company regarding the submittal of a license renewal application for Diablo Canyon Power Plant, Units 1 and 2. Pursuant to this exemption, if the licensee submits a license renewal application less than 5 years prior to expiration of the existing operating licenses but no later than December 31, 2023, 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 license renewal application.
Information Collection: Requests to Federally Recognized Indian Tribes for Information
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, ``Requests to Federally Recognized Indian Tribes for Information.''
Applications for Amendments to Facility Operating Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of four amendment requests. The amendment requests are for LaSalle County Station, Units 1 and 2; Prairie Island Nuclear Generating Plants, Unit Nos. 1 and 2; Callaway Plant, Unit No. 1; and Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2. For each amendment request, the NRC proposes to determine that it involves no significant hazards consideration (NSHC). Because each amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation by persons who file a hearing request or petition for leave to intervene.
Material Compatibility for Non-Light Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment on its draft Interim Staff Guidance (ISG) ``Material Compatibility for non-Light Water Reactors, DANU-ISG-2023-01.'' The purpose of this draft ISG is to assist the NRC staff in reviewing certain applications for construction and operation of non-light water reactor designs, including power and non-power reactors.
Consideration of Current Operating Issues and Licensing Actions in License Renewal
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) concerning how the NRC considers current operation of a facility in the NRC's license renewal review under NRC regulations. NRC regulations identify the technical information that must be submitted in a license renewal application (LRA) to enable the NRC staff to make a determination that the license may be renewed. In part, an applicant is required to demonstrate that the effects of aging on the functionality of structures and components subject to an aging management review will be adequately managed; the consideration of recent operating experience is an important aspect of that demonstration. In addition, as required by NRC regulations, license renewal applicants need to update their applications with new information related to any current licensing basis changes that could impact aging management of structures and components.
NRC Bulletin 2012-01: Design Vulnerability in Electric Power System
The U.S. Nuclear Regulatory Commission (NRC) is issuing this notice to inform all holders of operating licenses and combined licenses for nuclear power reactors of the closure of ``NRC Bulletin 2012-01: Design Vulnerability in Electric Power System'' (Bulletin). NRC has completed evaluations and inspections of the responses and other actions taken by the licensees of the nuclear power plants in response to NRC Bulletin 2012-01. The staff has approved the actions to be taken by the licensee for Vogtle Units 3 and 4 following commencement of operations and will inspect these actions under the Reactor Oversight Process. The NRC staff concludes that any potential adverse impact on nuclear plant safety due to an open phase condition (OPC) in the plant offsite power system has been adequately addressed by the licensees.
Draft Regulatory Guide: Sizing of Large Lead-Acid Storage Batteries
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1418, ``Sizing of Large Lead-Acid Storage Batteries.'' This DG is proposed Revision 2 of Regulatory Guide (RG) 1.212 of the same name. DG-1418 describes an approach that is acceptable to the NRC staff to meet regulatory requirements for sizing of large lead-acid storage batteries for production and utilization facilities. It endorses, with clarifications, the Institute of Electrical and Electronic Engineers (IEEE) Standard 485-2020, ``IEEE Recommended Practice for Sizing Lead- Acid Batteries for Stationary Applications.''
American Society of Mechanical Engineers Code Cases and Update Frequency
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference proposed revisions of three regulatory guides, which would approve new, revised, and reaffirmed code cases published by the American Society of Mechanical Engineers. 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 regulatory guides as voluntary alternatives to engineering standards for the construction, inservice inspection, and inservice testing of nuclear power plant components. The NRC is requesting comments on this proposed rule and on the draft versions of the three regulatory guides proposed to be incorporated by reference. The NRC also is making available a related draft regulatory guide that lists code cases that the NRC has not approved for use. This draft regulatory guide will not be incorporated by reference into the NRC's regulations. In addition, this rulemaking proposes to extend the time periods required for licensees to update their codes of record.
Northern States Power Company-Minnesota; Xcel Energy; Monticello Nuclear Generating Plant, Unit 1
The U.S. Nuclear Regulatory Commission (NRC) is considering an application for the subsequent license renewal of Renewed Facility Operating License No. DPR-22, which authorizes Northern States Power Company, a Minnesota corporation (NSPM or the applicant), doing business as Xcel Energy, to operate Monticello Nuclear Generating Plant (MNGP), Unit 1. The subsequent renewed license would authorize the applicant to operate MNGP for an additional 20 years beyond the period specified in the current license. The current operating license for MNGP expires September 8, 2030.
Renewing Nuclear Power Plant Operating Licenses-Environmental Review
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its environmental protection regulations by updating the Commission's 2013 findings on the environmental effect of renewing the operating license of a nuclear power plant. The NRC proposes to redefine the number and scope of the environmental issues that must be addressed during the review of each application for license renewal. As part of this update, the NRC has prepared draft Revision 2 to NUREG- 1437, ``Generic Environmental Impact Statement for License Renewal of Nuclear Plants'' (LR GEIS), to account for new information and to address the impacts of initial license renewals, which the previous versions considered, as well as first subsequent license renewals. The draft revised LR GEIS provides the technical basis for this proposed rule. The NRC is providing an opportunity for interested parties to submit comments on this proposed rule, the draft revised LR GEIS, and associated draft guidance.
Revision of Fee Schedules; Fee Recovery for Fiscal Year 2023
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend the licensing, inspection, special project, and annual fees charged to its applicants and licensees. The proposed 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.
Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Unit 3
The U.S. Nuclear Regulatory Commission (NRC) has issued License Amendment No. 190 to Combined License (COL) NPF-91. The COL amendment involved changes to Vogtle Electric Generating Plant (VEGP), Unit 3, COL Appendix A, Technical Specifications (TS). The amendment involved changes to remove operability requirements prior to initial criticality for (1) the In-containment Refueling Water Storage Tank (IRWST) in Mode 5 (TS 3.5.7) and Mode 6 (TS 3.5.8), and (2) various Protection and Safety Monitoring System and Diverse Actuation System (DAS) automatic and/or manual actuation signals that initiate IRWST, Automatic Depressurization System (ADS) stage 4, and Chemical and Volume Control System (CVS) letdown isolation valves in Modes 5 and 6. These changes allow disabling the IRWST injection and recirculation function during the repair activities on VEGP Unit 3 IRWST injection isolation valve 3-PXS-V123A. Southern Nuclear Operating Company, Inc., (SNC) is licensed to operate VEGP, Unit 3, located in Burke County, Georgia.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM Flood/Wind Multipurpose Canister Storage System, Certificate of Compliance No. 1032, AmendmentNo. 6
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of March 22, 2023, for the direct final rule that was published in the Federal Register on January 6, 2023. This direct final rule amended the Holtec International Storage Module Flood/Wind (HI- STORM FW) Multipurpose Canister Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 6 to Certificate of Compliance No. 1032.
Information Collection: NRC Form 629, Authorization for Payment by Credit Card
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 629, Authorization for Payment by Credit Card.''
Information Collection: Access Authorization
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, ``Access Authorization.''
Holtec Decommissioning International, LLC; Pilgrim Nuclear Power Station Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption to Holtec Decommissioning International, LLC, (HDI), for Pilgrim Nuclear Power Station (PNPS), Independent Spent Fuel Storage Installation (ISFSI). The exemption allows PNPS to deviate from the requirements in Certificate of Compliance (CoC) No. 1014, Amendment No. 14, Appendix A, Technical Specifications (TS) for the HI-STORM 100 System, Section 5.4, ``Radioactive Effluent Control Program,'' subsection c related to the timing of submission for an annual radiological effluent report.
Unified Agenda of Federal Regulatory and Deregulatory Actions
The following agenda of the National Labor Relations Board is published in accordance with Executive Order 12866, ``Regulatory Planning and Review,'' and the Regulatory Flexibility Act (RFA), 5 U.S.C. 601-612, as amended by the Small Business Regulatory Enforcement Fairness Act. The complete Unified Agenda is available online at www.reginfo.gov. Publication in the Federal Register is mandated only for regulatory flexibility agendas required under the RFA. Because the RFA does not require regulatory flexibility agendas for the regulations proposed and issued by the Board, the Board's agenda appears only on the internet at www.reginfo.gov. The Board's agenda refers to www.regulations.gov, the Government website at which members of the public can find, review, and comment on Federal rulemakings that are published in the Federal Register and open for comment.
Notice of Intent To Conduct Scoping Process and Prepare Environmental Impact Statement; Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) will conduct an extended scoping process to gather information necessary to prepare an environmental impact statement (EIS) to evaluate the environmental impacts for the proposed license renewal of the operating licenses for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2. The NRC is seeking stakeholder input on this action and has scheduled an additional public scoping meeting that will take place in Glen Rose, Texas.
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.
Draft Regulatory Guide: Perimeter Intrusion Alarm Systems
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft Regulatory Guide (DG), DG-5065, ``Perimeter Intrusion Alarm Systems.'' This DG is proposed Revision 4 to Regulatory Guide (RG) 5.44 of the same name. This proposed revision describes an approach acceptable to the NRC staff for meeting requirements in NRC regulations related to the functions of perimeter intrusion detection sensors and detection methods.
Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 1307, Revision 19, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities.'' This report, which is revised periodically, explains the formula acceptable to the NRC for determining the minimum decommissioning fund requirements for nuclear power reactor licensees, as required by NRC regulations. Specifically, this report provides the adjustment factor and updates the values for the labor, energy, and waste burial escalation factors of the minimum formula.
Westinghouse Electric Company LLC; Consideration of Approval of Transfer of License
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an application filed by Westinghouse Electric Company, LLC (Westinghouse) on December 20, 2022. The application seeks NRC approval of the indirect transfer of materials license SNM-1107 and several export licenses for Westinghouse, from Brookfield Corporation (Brookfield), the parent company of the license holder, to Watt New Aggregator L.P., which Brookfield will hold a controlling 51 percent interest in and Cameco Corporation (Cameco) will hold the remaining 49 percent interest. The application contains sensitive unclassified non- safeguards information (SUNSI).
Information Collection: NRC Form 850, Request for Contractor Assignment(s)
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 850, Request for Contractor Assignment(s).''
Information Collection: NRC Form 974 “Privacy Act Complaint Form”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on this proposed information collection. The information collection is entitled, ``NRC Form 974 `Privacy Act Complaint Form'.''
Information Collection: NRC Form 212, “Qualifications Investigation Professional, Technical, and Administrative Positions”
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 212, ``Qualifications Investigation Professional, Technical, and Administrative Positions.''
Qualification of Connection Assemblies for Production and Utilization Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 of Regulatory Guide (RG) 1.156, ``Qualification of Connection Assemblies for Production and Utilization Facilities.'' This revised guide was updated to endorse ``Institute of Electrical and Electronics Engineers'' Std. 572-2019 to provide the latest technical information on approaches to satisfy the qualification requirements for connection assemblies. This includes guidance that when used in conjunction with the guidance in RG 1.89, ``Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants,'' provides an acceptable method of demonstrating compliance with the NRC regulations pertaining to the environmental qualification of connectors, terminations, and environmental seals in combination with cables or wires as assemblies for service in production and utilization facilities to ensure that the connection assemblies can perform their safety functions. Further, the revised guide modifies the title of the RG to include other nuclear facilities, as discussed in the RG Section A, under Applicability.
Cyber Security Programs for Nuclear Power Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.71, ``Cyber Security Programs for Nuclear Power Reactors.'' Revision 1 incorporates references to industry guidance on identifying and protecting critical digital assets for safety-related, important to safety, balance of plant, and emergency preparedness equipment. It also clarifies guidance on defense-in-depth for cyber security and includes updated text based on the latest National Institute of Standards and Technology (NIST) and International Atomic Energy Agency (IAEA) cyber security guidance. Specifically, this revision clarifies issues identified from cyber security inspections, insights gained through the Security Frequently Asked Questions (SFAQ) process, documented cyber security attacks, new technologies, and new regulations. This revision also considers the changes in the most recent revision to the NIST Special Publications (SP) 800-53, upon which Revision 0 of Regulatory Guide (RG) 5.71, ``Cyber Security Programs for Nuclear Facilities'' was based.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Renewal of Initial Certificate and Amendment Nos. 1 Through 15
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the Holtec International HI-STORM 100 Cask System listing within the ``List of approved spent fuel storage casks'' to renew, for 40 years, the initial certificate (Amendment 0) and Amendment Nos. 1 through 15 of Certificate of Compliance No. 1014. The renewal of the initial certificate and Amendment Nos. 1 through 15 would revise the certificate of compliance's conditions and technical specifications to address aging management activities related to the structures, systems, and components important to safety of the dry storage system to ensure that these will maintain their intended functions during the period of extended storage operations.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System, Certificate of Compliance No. 1014, Renewal of Initial Certificate and Amendment Nos. 1 Through 15
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International HI- STORM 100 Cask System listing within the ``List of approved spent fuel storage casks'' to renew, for 40 years, the initial certificate and Amendment Nos. 1 through 15 of Certificate of Compliance No. 1014. The renewal of the initial certificate and Amendment Nos. 1 through 15 revises the certificate of compliance's conditions and technical specifications to address aging management activities related to the structures, systems, and components important to safety of the dry storage system to ensure that these will maintain their intended functions during the period of extended storage operations.
National Institute of Standards and Technology; National Bureau of Standards Test Reactor
The U.S. Nuclear Regulatory Commission (NRC, the Commission) is considering issuance of an amendment to Renewed Facility Operating License No. TR-5, issued to the National Institute of Standards and Technology (NIST, the licensee), for operation of the National Bureau of Standards Test Reactor (NBSR). The proposed amendment would authorize the use of a specific method to perform core loading analyses of the NBSR.
Application for Amendment to Facility Operating License Involving a Proposed No Significant Hazards Consideration and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of one amendment request. The amendment request is for Callaway Plant, Unit No. 1. For the amendment request, the NRC proposes to determine that it involves no significant hazards consideration (NSHC). Because the amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation by persons who file a hearing request or petition for leave to intervene.
SHINE Medical Technologies, LLC; Medical Isotope Production Facility
The U.S. Nuclear Regulatory Commission (NRC) has issued Supplement 1 to NUREG-2183, ``Environmental Impact Statement Supplement Related to the Operating License for the SHINE Medical Isotope Production Facility.'' NUREG-2183 was issued October 2015. SHINE Medical Technologies, LLC (SHINE) is requesting a license to operate the Medical Isotope Production Facility (SHINE facility) in Janesville, Wisconsin.
Information Collection: NRC Policy Statement, “Criteria for Guidance of States and NRC in Discontinuance of NRC Regulatory Authority and Assumption Thereof by States Through Agreement,” Maintenance of Existing Agreement State Programs, Requests for Information Through the Integrated Materials Performance Evaluation Program (IMPEP) Questionnaire, and Agreement State Participation in IMPEP
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 Policy Statement, ``Criteria for Guidance of States and NRC in Discontinuance of NRC Regulatory Authority and Assumption Thereof by States Through Agreement,'' Maintenance of Existing Agreement State Programs, Requests for Information Through the Integrated Materials Performance Evaluation Program (IMPEP) Questionnaire, and Agreement State Participation in IMPEP.
Information Collection: NRC Form 327, Special Nuclear Material (SNM) and Source Material (SM) Physical Inventory Summary Report, and NUREG/BR-0096, Instructions and Guidance for Completing Physical Inventory Summary Reports
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 327, Special Nuclear Material (SNM) and Source Material (SM) Physical Inventory Summary Report, and NUREG/ BR-0096, Instructions and Guidance for Completing Physical Inventory Summary Reports.''
Acceptability of ASME Code, Section III, Division 5, High Temperature Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG), 1.87, ``Acceptability of ASME Code, Section III, Division 5, `High Temperature Reactors.' '' This RG describes an approach that is acceptable to the NRC staff to assure the mechanical/structural integrity of components that operate in elevated temperature environments and that are subject to time-dependent material properties and failure modes. It endorses, with exceptions and limitations, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code (ASME Code) Section III, ``Rules for Construction of Nuclear Facility Components,'' Division 5, ``High Temperature Reactors,'' and Code Cases N-861, N-862, N-872, and N-898. The NRC is also issuing NUREG-2245, ``Technical Review of the 2017 Edition of ASME Section III, Division 5, `High Temperature Reactors,' '' that documents the NRC staff's review of the 2017 Edition of ASME Section III, Division 5, certain portions of the 2019 Edition, and Code Cases N-861 and N-862. The technical basis for the NRC's endorsement of Code Cases N-872 and N-898 is contained in Technical Letter Report (TLR)-RES/DE/REB-2022-01, ``Review of Code Cases Permitting Use of Nickel-Based Alloy 617 in Conjunction with ASME Section III, Division 5.''
Qal-Tek Associates LLC; Mayfield, Idaho Waste Handling and Temporary Storage Facility
The U.S. Nuclear Regulatory Commission (NRC) is issuing a finding of no significant impact (FONSI) and accompanying environmental assessment (EA) for an application from Qal-Tek Associates LLC (QTA) to operate a waste handling and temporary storage facility near Mayfield, Idaho. Based on the analysis in the EA, the NRC staff has concluded that there would be no significant impacts to environmental resources from QTA's proposed activities at the proposed facility and, therefore, a FONSI is appropriate.
SHINE Technologies, LLC; SHINE Medical Isotope Production Facility
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Construction Permit No. CPMIF-001, issued to SHINE Technologies, LLC (SHINE, the licensee), for the construction of the SHINE Medical Isotope Production Facility. The proposed amendment would allow the receipt and possession of contained special nuclear material for the continued construction of the SHINE Medical Isotope Production Facility.
Eastern Technologies, Inc.
The U.S. Nuclear Regulatory Commission (NRC) received and is considering issuing an export license (XW031), requested by Eastern Technologies, Inc. (ETI) by application dated November 28, 2022. The application seeks the NRC's approval to return residual radioactive waste to the Barakah Nuclear Power Plant in the United Arab Emirates (UAE) after treatment at an ETI facility in Ashford, Alabama. The NRC is providing notice of the opportunity to comment, request a hearing, and petition to intervene on ETI's application.
Environmental Assessment and Finding of No Significant Impact of Independent Spent Fuel Storage Facilities Decommissioning Funding Plans
The U.S. Nuclear Regulatory Commission (NRC) is publishing this notice regarding the issuance of a final environmental assessment (EA) and a finding of no significant impact (FONSI) for its review and approval of the updated decommissioning funding plans (DFPs) submitted by independent spent fuel storage installation (ISFSI) licensees for the ISFSIs listed in the ``Discussion'' section of this document.
TRISO-X, LLC; TRISO‐X Special Nuclear Material License
The United States Nuclear Regulatory Commission (NRC) received a license application, by letters dated April 5, 2022, and September 23, 2022, from TRISO-X, LLC to possess and use special nuclear material for the manufacture of high-assay low-enriched uranium fuel at a fuel fabrication facility, to be located in Roane County, Tennessee. TRISO- X, LLC seeks a special nuclear material license for a term of 40 years to manufacture fuel, consisting of coated uranium particles enriched to less than 20 weight percent uranium[hyphen]235 (Uranium-235) for use in advanced commercial reactors. Because the license application contains Sensitive Unclassified Non-Safeguards Information and Safeguards Information, an order imposes procedures to obtain access to this type of information for contention preparation.
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