Nuclear Regulatory Commission – Federal Register Recent Federal Regulation Documents
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Safety Review of Light-Water Power Reactor Construction Permit Applications
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) ``Safety Review of Light-Water Power Reactor Construction Permit Applications'' to clarify existing guidance and to assist the NRC staff in determining whether an application to construct a light-water power reactor (LWR) facility meets the minimum requirements to issue a construction permit (CP). The NRC anticipates the submission of power reactor CP applications in the next few years based on preapplication engagement initiated by several prospective applicants. This guidance is applicable to all applicants for a CP for a light-water power reactor but not to non-LWR applicants or those following the Advanced Reactor Content of Application Project (ARCAP) guidance to the extent the guidance is issued as final and is relevant to the application from a technical and regulatory perspective.
SHINE Medical Technologies, LLC; SHINE Medical Isotope Production Facility
The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) regarding the SHINE Medical Technologies, LLC (SHINE, the licensee) request to amend Construction Permit No. CPMIF-001 for the SHINE Medical Isotope Production Facility (SHINE facility) in Rock County, Wisconsin. The amendment request seeks, in part, NRC approval to extend the latest date for completion of the construction of the SHINE facility from December 31, 2022, to December 31, 2025.
Reporting Requirements for Nonemergency Events at Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is requesting comment on a regulatory basis to support a rulemaking that would amend its regulations for nonemergency event notifications. The NRC is evaluating the current requirements and guidance for immediate notification of nonemergency events for operating nuclear power reactors and assessing whether the requirements present an unnecessary reporting burden. The regulatory basis contains an analysis of whether reporting requirements can be reduced or eliminated when they do not have a commensurate safety benefit.
Advisory Committee on the Medical Uses of Isotopes: Meeting Notice
The U.S. Nuclear Regulatory Commission (NRC) will convene a meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) on December 5-6, 2022. A sample of agenda items to be discussed during the public session includes: an overview of Y-90 medical events; overview of the review of Lu-177-PSMA for the treatment of adult patients with prostate cancer; review of pre-rulemaking documents for the rulemaking to establish requirements for Rb-82 generators and emerging medical technologies; and overview of the status of rulemaking for regulations for decommissioning financial assurance for sealed and unsealed radioactive materials. The agenda is subject to change. The current agenda and any updates will be available on the ACMUI's Meetings and Related Documents web page at https://www.nrc.gov/reading- rm/doc-collections/acmui/meetings/2022.html or by emailing Ms. Gupta Sarma at the contact information below. Purpose: Discuss issues related to 10 CFR part 35, Medical Use of Byproduct Material. Date and Time for Open Sessions: December 5, 2022, from 8:30 a.m. to 4:30 p.m. EST, December 6, 2022, from 10:00 a.m. to 12:00 p.m. EST. Date and Time for Closed Session: December 6, 2022, from 1:30 p.m. to 3:30 p.m. EST. This session will be closed to conduct the ACMUI's required annual training. Address for Public Meeting: U.S. Nuclear Regulatory Commission, One White Flint North Building, Commissioner's Hearing Room, 11555 Rockville Pike, Rockville, Maryland 20852.
Applications and Amendments to Facility Operating Licenses and Combined 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 three amendment requests. The amendment requests are for Salem Nuclear Generating Station, Unit 2; Vogtle Electric Generating Plant, Units 1 and 2; and Surry Power Station, Units 1 and 2. For each amendment request, the NRC proposes to determine that they involve 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.
Susquehanna Steam Electric Station, Units 1 and 2 and Associated Independent Spent Fuel Storage Installation; Consideration of Approval of Indirect 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 Susquehanna Nuclear, LLC (Susquehanna Nuclear) on September 29, 2022, as supplemented by letter dated October 28, 2022. The application seeks NRC approval of the indirect transfer of Renewed Facility Operating License Nos. NPF-14 and NPF-22 for Susquehanna Steam Electric Station (Susquehanna), Units 1 and 2, respectively, and the general license for the Susquehanna independent spent fuel storage installation (ISFSI) as a result of the restructuring of Talen Energy Corporation, an indirect parent of Susquehanna Nuclear, as a reorganized company yet to be named (referred to as ``Reorganized Talen''). The NRC is also considering amending the renewed facility operating licenses for administrative purposes to reflect the proposed transfer. The application and supplement contain sensitive unclassified non-safeguards information (SUNSI).
Advance Tribal Notification of Certain Radioactive Material Shipments
The U.S. Nuclear Regulatory Commission (NRC) will consider in its rulemaking process the issue raised in a petition for rulemaking (PRM), PRM-37-2, submitted by Richard Arnold and Ron Johnson, on behalf of the Tribal Radioactive Materials Transportation Committee, dated December 4, 2020. The petitioner requests that the NRC amend its regulations to include advance Tribal notification of certain radioactive material shipments.
List of Approved Spent Fuel Storage Casks: NAC International, Inc. MAGNASTOR® Storage System, Certificate of Compliance No. 1031, Amendment No. 10
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. MAGNASTOR[supreg] Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 10 to Certificate of Compliance No. 1031. Amendment No. 10 revises the certificate of compliance by adding a new metal storage overpack.
List of Approved Spent Fuel Storage Casks: NAC International, Inc. MAGNASTOR® Storage System, Certificate of Compliance No. 1031, Amendment No. 10
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel regulations by revising the NAC International, Inc. MAGNASTOR[supreg] Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 10 to Certificate of Compliance No. 1031. Amendment No. 10 revises the certificate of compliance by adding a new metal storage overpack.
Holtec International HI-STORE Consolidated Interim Storage Facility Project
The U.S. Nuclear Regulatory Commission (NRC) is issuing Supplement 1 to a final Environmental Impact Statement (FEIS), NUREG- 2237, ``Environmental Impact Statement for the Holtec International's License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico.'' Supplement 1 to NUREG- 2237 updates the responses to public comments by adding responses to certain comments that were inadvertently not included in the FEIS. Supplement 1 does not include any changes to impact analysis or determinations. Holtec International (Holtec) has requested a license to construct and operate a consolidated interim storage facility (CISF) for spent nuclear fuel (SNF) and Greater-Than-Class C (GTCC) waste, along with a small quantity of mixed oxide (MOX) fuel. The proposed CISF would be located in southeast New Mexico at a site located approximately halfway between the cities of Carlsbad and Hobbs. The proposed action is the issuance of an NRC license authorizing a CISF to store up to 8,680 metric tons of uranium (MTUs) [9,568 short tons] of SNF in 500 canisters for a license period of 40 years.
TMI-2 Solutions, LLC; Three Mile Island Station, Unit No. 2
The U.S. Nuclear Regulatory Commission (NRC) is issuing partial exemptions, with a conforming amendment, from several of the record keeping requirements in its regulations in response to a request from TMI-2 Solutions, LLC. Specifically, the licensee requested partial exemptions for certain NRC regulations which require certain records to be retained for the period specified by the appropriate regulation, license condition, or technical specifications (TS), or until termination of the license if not otherwise specified. In response to the licensee's requests, the NRC also issued a conforming amendment that revised the license to reflect the specific exemptions and associated changes in the TS.
Entergy Operations, Inc.; Arkansas Nuclear One; Unit 1
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. DPR- 51, issued to Entergy Operations, Inc., for operation of Arkansas Nuclear One, Unit 1 (ANO-1). The proposed amendment would revise the dose equivalent Iodine (I)-131 and the reactor coolant system (RCS) primary activity limits required by ANO-1 Technical Specification (TS) 3.4.12, ``RCS Specific Activity,'' and the primary-to-secondary leak rate limit provided in TS 3.4.13, ``RCS Operational LEAKAGE.'' For this amendment request, the NRC proposes to determine that it involves no significant hazards consideration. Because this amendment request contains sensitive unclassified non- safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.250, ``Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants.'' RG 1.250 provides guidance that the staff of the NRC considers acceptable to meet, in part, regulatory requirements for the dedication of commercial-grade digital instrumentation and control items (I&C) for use in nuclear power plant safety applications.
Acceptability of ASME Code, Section XI, Division 2, ‘Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.246, ``Acceptability of ASME Code, Section XI, Division 2, `Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors.'' This RG describes an approach that is acceptable to the NRC staff for the development and implementation of a preservice inspection (PSI) and inservice inspection (ISI) program for non-light water reactors (non-LWRs). It endorses, with conditions, the 2019 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), Section XI, ``Rules for Inservice Inspection of Nuclear Power Plant Components,'' Division 2, for non-LWR applications. This RG also describes a method that applicants can use to incorporate PSI and ISI programs into a licensing basis.
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.
Holtec Decommissioning International, LLC; Indian Point Energy Center; Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is considering an exemption request from Holtec Decommissioning International, LLC (HDI) for the Indian Point Energy Center Independent Spent Fuel Storage Installation. This exemption would, if granted, allow HDI to load up to three MPC-32Ms, using Amendment No. 15 for Certificate of Compliance (CoC) No. 1014 for the HI-STORM 100 storage system, with either up to thirty-two fuel assemblies having either Californium (Cf-252) or Antimony-Beryllium (Sb-Be) neutron source assemblies (NSAs) with sufficient cooling time, or a combination of up to five fuel assemblies having primary Plutonium Beryllium (Pu-Be) NSAs and the remaining basket locations with fuel assemblies having either Cf-252 or Sb-Be NSAs with sufficient cooling time. As discussed further, the proposed exemption would permit HDI to load the fuel assemblies having either Cf-252 or Sb-Be NSAs in any location in the basket and the fuel assemblies having Pu-Be NSAs such that one is located in the center of the basket and one is located in each of the four basket quadrants. The NRC prepared an environmental assessment (EA) and concluded that the proposed action would have no significant environmental impact. Accordingly, the NRC staff is issuing a finding of no significant impact (FONSI) associated with the proposed exemption.
Union Electric Company, dba Ameren Missouri, Callaway Plant; Unit No. 1
The U.S. Nuclear Regulatory Commission (NRC) is granting exemptions from certain portions of the acceptance criteria for emergency core cooling, and the general design criteria for emergency core cooling, containment heat removal, and atmosphere cleanup to allow the use of a risk-informed analysis to evaluate the effects of debris in containment following a loss-of-coolant accident for the Callaway Plant, Unit No. 1 (Callaway) located in Callaway County, Missouri. The exemptions are in response to a request dated March 31, 2021, from Union Electric Company, doing business as Ameren Missouri (the licensee) related to the licensee's proposed approach to resolve a generic safety concern for pressurized water reactors associated with potential clogging of emergency core cooling and containment spray system strainers during certain design basis events.
Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has received an application for the renewal of Facility Operating License Nos. NPF-87 and NPF-89, which authorize Vistra Operations Company LLC (VOC or the applicant) to operate Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2. The renewed licenses would authorize the applicant to operate CPNPP for an additional 20 years beyond the period specified in each of the current licenses. The current operating licenses for CPNPP expire as follows: Unit 1 on February 8, 2030, and Unit 2 on February 2, 2033.
Harmonization of Transportation Safety Requirements With IAEA Standards; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a document that was published in the Federal Register on September 12, 2022, regarding changes to maintain a consistent regulatory framework with the U.S. Department of Transportation for the domestic packaging and transportation of radioactive material and to ensure general accord with International Atomic Energy Agency standards. This action is necessary to make corrections in the estimated burden for the information collection and to make other corrections. The public comment period on the amended information collection was originally scheduled to close on November 14, 2022. The NRC has decided to extend the public comment period for the information collection to allow more time for members of the public to develop and submit their comments; the extended comment period for the information collection now aligns with the end of the general period for public comment.
American Society of Mechanical Engineers 2019-2020 Code Editions
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to incorporate by reference the 2019 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, Division 1, and Section XI, Division 1, and the 2020 Edition of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants, Division 1: OM Code: Section IST, for nuclear power plants. The NRC is also incorporating by reference the American Society of Mechanical Engineers OM Code Case OMN-28, ``Alternative Valve Position Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible to Stem-Disk Separation''; the 2011 Addenda to ASME NQA-1-2008, ``Quality Assurance Requirements for Nuclear Facility Applications'' (ASME NQA-1b-2011); and the 2012 and 2015 Editions of ASME NQA-1, ``Quality Assurance Requirements for Nuclear Facility Applications.'' This action is in accordance with the NRC's policy to periodically update the regulations to incorporate by reference new editions of the American Society of Mechanical Engineers Codes and is intended to maintain the safety of nuclear power plants and to make NRC activities more effective and efficient.
Perma-Fix Northwest Richland, Inc.
On September 20, 2022, the U.S. Nuclear Regulatory Commission (NRC) received an application for an export license (XW030) from Perma- Fix Northwest Richland, Inc. (PFNW) seeking approval for a license to export of low-level radioactive waste to Nuklearna Elektrama Krsko d.o.o, in Slovenia. The NRC is providing notice of the opportunity to comment, request a hearing, and petition to intervene on PFNW's application.
Crow Butte Resources, Inc.; In Situ Uranium Recovery Facility
The U.S. Nuclear Regulatory Commission (NRC) is issuing a final finding of no significant impact (FONSI) and accompanying supplement to the NRC staff's environmental assessment (EA) for the license renewal of the Crow Butte Resources, Inc. (CBR) in situ uranium recovery (ISR) facility located Dawes County, Nebraska. Based on the analysis in the EA supplement, the NRC staff has concluded that there will be no significant impacts to cultural resources from the renewal of CBR's license and, therefore, a FONSI remains appropriate.
Privacy Act of 1974; Systems of Records
Pursuant to the Privacy Act of 1974 and Office of Management and Budget (OMB) Circular No. A-108, to ensure the system of records notices remain accurate, the U.S. Nuclear Regulatory Commission (NRC) staff reviews each notice on a periodic basis. As a result of this systematic review, the NRC is republishing 13 of its system of records notices and has made various revisions to ensure that the NRC's notices remain clear, accurate, and up to date. Four of the system noticesNRC 5, Grants Management System, NRC 8, Employee Disciplinary Actions, Appeals, Grievances, and Complaints Records, NRC 11, Reasonable Accommodations Records, and NRC 23, Case Management SystemIndices, Files, and Associated Records are subject to a 30-day comment period. The revisions to these systems, with the exception of the modifications to routines uses for the NRC 5 and NRC 8 systems, are in effect upon this publication. The NRC 5 and NRC 8 routine use modifications will go into effect 30 days after this publication. The remaining systems revisions are minor corrective and administrative changes that do not meet the threshold criteria established by OMB for either a new or altered system of records. The minor modifications include updating authorities, narrowing the scope of one system notice, renaming two systems for clarity, and various other minor updates, in accordance with OMB Circular A-108. Additional details are provided in the SUPPLEMENTARY INFORMATION section of this document.
Regents of the University of California, University of California-Davis McClellan Nuclear Research Center Training, Research, Isotopes, General Atomics Reactor
The U.S. Nuclear Regulatory Commission (NRC) is considering renewal of Operating Facility License No. R-130, held by the Regents of the University of California for the University of California Davis (UCD, the licensee), for the continued operation of the McClellan Nuclear Research Center (MNRC) Training, Research, Isotopes, General Atomics (TRIGA) reactor (the reactor, facility), located in the city of North Highlands, Sacramento County, California. In connection with the renewed license, the licensee also seeks to operate at a maximum licensed power level of 1.0 megawatt-thermal (MWt). The NRC is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) associated with the proposed action.
Confirmatory Order Modifying License of Cammenga and Associates, LLC
The U.S. Nuclear Regulatory Commission (NRC) is issuing a Confirmatory Order to Cammenga and Associates, LLC, as a result of a successful alternative dispute resolution mediation session. The commitments outlined in the Confirmatory Order were made as a part of a settlement agreement concerning apparent violations by Cammenga and Associates regarding the distribution of products containing byproduct material (hydrogen-3) without the required licensing authorization.
In the Matter of Steel City Gamma, LLC
The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order to Steel City Gamma, LLC, imposing a civil monetary penalty of $25,600. The NRC determined that two willful violations of NRC regulations occurred as identified during an investigation by the NRC's Office of Investigations that was completed on March 1, 2021. The violations involved Steel City Gamma's failure to file for reciprocity prior to performing work in NRC jurisdiction and Steel City Gamma's performance of licensed activities in NRC jurisdiction without a valid NRC or Agreement State license. This order is effective on the date of issuance.
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) 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 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.''
Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities
The U.S. Nuclear Regulatory Commission (NRC) is addressing comments received after issuing for public comment on the trial use of the new regulatory guide (RG) 1.247, ``Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities.'' The NRC will not make any changes to the RG as a result of these comments.
Abilene Christian University
The U.S. Nuclear Regulatory Commission (NRC) is providing public notice of receipt and availability of an application for a construction permit from Abilene Christian University (ACU). The construction permit application is dated August 12, 2022.
Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.248, ``Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities.'' This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for managing, monitoring, and mitigating the aging effects on electrical equipment. It endorses Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 1205 2014, ``IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities.''
Information Collection: Export and Import of Nuclear Equipment and Material; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that published in the Federal Register (FR) on September 27, 2022, regarding a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. This action is necessary to correct the estimated number of annual responses.
Oregon State University
The U.S. Nuclear Regulatory Commission (NRC) staff has issued a renewal to special nuclear materials (SNM) License No. SNM-2013 to Oregon State University (OSU) in Corvallis, Oregon. The renewed license will authorize the applicant to continue research on research and test reactor fuel rods that contain greater than critical mass amounts of SNM. The license renewal would allow OSU to continue licensed activities for 10 years beyond its current license.
Monthly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to 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: NRC Form 237, Request for Access Authorization
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 237, Request for Access Authorization.''
Information Collection: NRC Form 277, Request for Visit
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 277, Request for Visit.''
Placement of the Mississippi Agreement State Program on Probation
The U.S. Nuclear Regulatory Commission (NRC) is announcing the placement of the Mississippi Agreement State Program (Mississippi Program) for the regulation of certain Atomic Energy Act of 1954, as amended, materials on Probation. The NRC is further increasing its oversight of the Mississippi Program and will oversee implementation of a Program Improvement Plan developed by the Mississippi Program's staff. The NRC Chairman notified the Governor of Mississippi of this decision in a letter dated September 26, 2022. Depending on the progress of the Agreement State in meeting the commitments in the Program Improvement Plan and demonstration of significant and sustained improvements in program performance, the Management Review Board (MRB) Chair will make a recommendation to the Commission on the probationary status. The NRC will make further announcements regarding the status of the Mississippi Program, as appropriate.
Applications and Amendments to Facility Operating Licenses and Combined 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 two amendment requests. The amendment requests are forConstellation Energy Generation, LLC; Dresden Nuclear Power Station, Units 2 and 3; Grundy County, IL and Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 1 and 2; Burke County, GA. For each amendment request, the NRC proposes to determine that they involve 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.
Kairos Power, LLC; Hermes Test Reactor
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG-2263, Environmental Impact Statement (EIS) for the Construction Permit for the Kairos Hermes Test Reactor. Kairos Power, LLC (Kairos) is requesting a license to construct a test reactor in Oak Ridge, Tennessee. The NRC is seeking public comment on this action and has scheduled a public meeting that will take place both in Oak Ridge, Tennessee and as an online webinar.
Performance Review Boards for Senior Executive Service
The Nuclear Regulatory Commission (NRC) has announced appointments to the NRC Performance Review Board (PRB) responsible for making recommendations on performance appraisal ratings and performance awards for NRC Senior Executives and Senior Level System employees and appointments to the NRC PRB Panel responsible for making recommendations to the appointing and awarding authorities for NRC PRB members.
Financial Qualifications Requirements for Reactor Licensing
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing a rulemaking activity that would have revised the current financial qualification requirements of ``reasonable assurance'' to the review standard of ``appears to be financially qualified.'' The purpose of this document is to inform members of the public that the NRC is discontinuing this rulemaking activity. The staff will address financial qualifications during the development of an ongoing rulemaking activity to establish a risk-informed, technology inclusive regulatory framework for advanced reactors.
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