Nuclear Regulatory Commission December 2022 – Federal Register Recent Federal Regulation Documents
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Reporting Nuclear Medicine Injection Extravasations as Medical Events
The U.S. Nuclear Regulatory Commission (NRC) will consider in its rulemaking process issues raised in a petition for rulemaking (PRM), PRM-35-22, submitted by Ronald K. Lattanze on behalf of Lucerno Dynamics, LLC. The petitioner requested that the NRC amend its regulations to require reporting of certain nuclear medicine injection extravasations as medical events.
Southern California Edison; San Onofre Nuclear Generating Station, Units 1, 2, and 3
The U.S. Nuclear Regulatory Commission (NRC) is issuing a finding of no significant impact (FONSI) and accompanying environmental assessment (EA) for a requested exemption from certain NRC requirements regarding the Controlled Area Boundary (CAB) for the San Onofre Nuclear Generating Station (SONGS) located in San Diego County, California. Based on the analysis in the EA, the NRC staff has concluded that there will be no significant impacts to environmental resources from the requested exemption and, therefore, a FONSI is appropriate.
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 confirming the effective date of January 18, 2023, for the direct final rule that was published in the Federal Register on November 4, 2022. This direct final rule amended 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.
Reporting Requirements for Nonemergency Events at Nuclear Power Plants
On November 9, 2022, the U.S. Nuclear Regulatory Commission (NRC) requested comments on a regulatory basis to support a rulemaking that would amend its regulations for nonemergency event notifications. The public comment period was originally scheduled to close on January 9, 2023. The NRC is extending the comment period to allow more time for members of the public to develop and submit their comments.
Holtec Decommissioning International, LLC; Oyster Creek Nuclear Generating Station
The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to an August 2, 2022 request from Holtec Decommissioning International, LLC (HDI) that would permit HDI to investigate and report to the NRC when the Oyster Creek Nuclear Generating Station does not receive notification of receipt of a shipment, or part of a shipment, of low-level radioactive waste within 90 days after transfer, instead of the 20-day investigation requirement currently delineated in the NRC's regulations.
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. This monthly notice includes all amendments issued, or proposed to be issued, from November 4, 2022, to December 8, 2022. The last monthly notice was published on November 29, 2022.
In the Matter of Cabell Huntington Hospital
The U.S. Nuclear Regulatory Commission (NRC) is issuing a Confirmatory Order to Cabell Huntington Hospital (CHH) to memorialize the agreement reached during an alternative dispute resolution mediation session held on August 24, 2022. The Confirmatory Order contains commitments made to resolve 14 apparent violations of NRC requirements related to the development and implementation of CHH's radiation protection program, CHH's compliance with occupational dose limits, and CHH's possession of licensed material at an unauthorized location. These violations were identified during NRC inspections and an investigation conducted by the NRC Office of Investigations. The Confirmatory Order is effective upon issuance.
GE-Hitachi Nuclear Energy Americas, LLC; Vallecitos Boiling Water Reactor and the Empire State Atomic Development Agency Vallecitos Experimental Superheat Reactor; Limited Post-Shutdown Decommissioning Activities Report
By letter dated September 21, 2022, as supplemented by letter dated November 22, 2022, GE-Hitachi Nuclear Energy Americas, LLC (GEH, the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) a ``limited'' post-shutdown decommissioning activities report (LPSDAR) for the Vallecitos Boiling Water Reactor (VBWR) and the Empire State Atomic Development Agency Vallecitos Experimental Superheat Reactor (EVESR). The LPSDAR provides an overview of GEH's planned activities, schedule, projected costs, and environmental impacts for the decommissioning of the VBWR and EVESR. Accordingly, the NRC is noticing receipt of the LPSDAR and making it available for public comment.
Constellation Energy Generation, LLC; Braidwood Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of Constellation Energy Generation, LLC, to withdraw its application dated August 2, 2021, as supplemented by letter dated June 6, 2022, for proposed amendments to Renewed Facility Operating License Nos. NPF-72 and NPF-77, issued to the licensee for operation of the Braidwood Station, Units 1 and 2, located in Will County, Illinois. The proposed amendments would have revised Technical Specification (TS) 3.7.9, ``Ultimate Heat Sink [UHS]'' for an inoperable UHS due to the average water temperature to allow utilization of existing margin in the design analysis to offset the increase in the TS UHS temperature. The proposed amendments also would have revised TS 3.7.9 Surveillance Requirement (SR) 3.7.9.2 to delete the temporary allowance for the UHS average water temperature of 102.8 degrees Fahrenheit ([deg]F) until September 30, 2021.
Licensing Support Network Advisory Review Panel
The Licensing Support System Advisory Review Panel was established by the U.S. Nuclear Regulatory Commission (NRC) as a Federal Advisory Committee in 1989. Its purpose was to provide advice on the fundamental issues of design and development of an electronic information management system to be used to store and retrieve documents relating to the licensing of a geologic repository for the disposal of high-level radioactive waste, and on the operation and maintenance of the system. This electronic information management system was known as the Licensing Support System.
Information Collection: Generic Clearance for the Collection of Qualitative Feedback on Agency Service Delivery
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, ``Generic Clearance for the Collection of Qualitative Feedback on Agency Service Delivery.''
Notice of Intent To Conduct a Supplemental Scoping Process and Prepare a Draft Environmental Impact Statement; Duke Energy Carolinas, LLC; Oconee Nuclear Station, Units 1, 2, and 3
In response to the U.S. Nuclear Regulatory Commission's (NRC) Memorandum and Order, CLI-22-03 (February 24, 2022), the NRC received Subsequent License RenewalAppendix E Environmental Report Supplement 2 (ER Supplement), dated November 7, 2022, related to the subsequent renewal of Renewed Facility Operating License Nos. DPR-38, DPR-47, and DPR-55, which authorizes Duke Energy Carolinas, LLC (Duke Energy, the applicant) to operate Oconee Nuclear Station (Oconee), Units 1, 2, and 3. The ER Supplement addresses certain environmental impacts of operating Oconee for an additional period of 20 years beyond the current license expiration dates. The NRC will conduct a limited scoping process to gather additional information necessary to prepare an environmental impact statement (EIS) to evaluate the environmental impacts for the subsequent license renewal (SLR) of the operating licenses for Oconee. The NRC is seeking public comment on the proper scope of the EIS to be prepared for this action.
Notice of Intent To Conduct Scoping Process and Prepare Environmental Impact Statement; TRISO-X Special Nuclear Material License
The U.S. Nuclear Regulatory Commission (NRC) received a license application by letters dated April 5, 2022, and September 23, 2022, from TRISO-X, LLC (TRISO-X) a wholly owned subsidiary of X-energy LLC. By its application, TRISO-X is requesting a license to possess and use special nuclear material for the manufacture of high-assay low- enriched uranium (HALEU) fuel at a fuel fabrication facility (FFF) to be located in Oak Ridge, Roane County, Tennessee. The proposed action is the issuance of a license for the possession and use of special nuclear material. The NRC staff will prepare an environmental impact statement (EIS) to document the potential environmental impacts from the proposed action. As part of the EIS development process, the NRC is seeking comments on the scope of its environmental review.
In the Matter of LaCrosseSolutions
The U.S. Nuclear Regulatory Commission (NRC) is issuing an order to extend the effectiveness of a September 24, 2019, order, which approved the direct transfer of Possession Only License No. DPR-45 for the La Crosse Boiling Water Reactor from the current holder, LaCrosseSolutions, LLC, to Dairyland Power Cooperative and approved a conforming license amendment, for 3 months beyond its current December 24, 2022, expiration date.
Pacific Gas and Electric Company; Humboldt Bay Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is issuing License Amendment No. 5 to Special Nuclear Materials (SNM) License No. SNM-2514 for the Humboldt Bay Independent Spent Fuel Storage Installation (ISFSI), located in Humboldt County, California, and is granting an exemption that would relieve Pacific Gas and Electric Company (PG&E, the licensee) from the requirement to submit annual effluent monitoring reports for the Humboldt Bay ISFSI. The requested amendment proposes to delete and make administrative changes to certain license conditions, revise certain technical specifications that are no longer applicable to the Humboldt Bay ISFSI, and add a new administrative technical specification concerning the processing of administrative changes to Humboldt Bay ISFSI's quality assurance program. The amendment also removes license condition 18, which requires the licensee to update its final safety analysis report within 90 days of the NRC issuing a renewed license.
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 a scoping process to gather information necessary to prepare an environmental impact statement (EIS) to evaluate the environmental impacts for the license renewal of the operating licenses for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2. The NRC is seeking public comment on this action and has scheduled a public scoping meeting that will take place in Glen Rose, Texas.
Relocation of Draft and Regulatory Guide Notices in the Federal Register
The U.S. Nuclear Regulatory Commission (NRC) is notifying the public that documents regarding draft and final Regulatory Guides that historically have been published in the ``Notices'' section of the Federal Register will now be published in the ``Proposed Rules'' and ``Rules and Regulations'' sections of the Federal Register. The Office of the Federal Register recently informed the NRC that under their guidelines, these documents fall into the ``Proposed Rules'' and ``Rules and Regulations'' categories and requested that the NRC reclassify these notices.
Standard Review Plan for Applications for 10 CFR Part 70 Licenses for Possession and Use of Special Nuclear Materials of Critical Mass but Not Subject to the Requirements in 10 CFR part 70, Subpart H
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2212, ``Standard Review Plan for Applications for 10 CFR part 70 Licenses for Possession and Use of Special Nuclear Materials of Critical Mass but not Subject to the Requirements in 10 CFR part 70, subpart H.'' This NUREG contains information intended to provide staff guidance to assist applicants and licensees in preparing license applications for possession and use of special nuclear materials (SNM) exceeding specific threshold quantities. It describes methods or approaches acceptable to the NRC staff for implementing NRC requirements in the Code of Federal Regulations.
In the Matter of SHINE Medical Technologies, LLC; SHINE Medical Isotope Production Facility
The U.S. Nuclear Regulatory Commission (NRC) has approved the SHINE Medical Technologies, LLC (SHINE) request to amend Construction Permit No. CPMIF-001 for the SHINE Medical Isotope Production Facility (SHINE facility) in Rock County, Wisconsin. The approved amendments extend the latest date for completion of the construction of the SHINE facility from December 31, 2022, to December 31, 2025, and administratively change the name of the construction permit holder from SHINE Medical Technologies, LLC to SHINE Technologies, LLC.
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) has issued a renewal for Facility Operating License No. R-130, held by the Regents of the University of California (the licensee), for the continued operation of the University of California-Davis McClellan Nuclear Research Center (UCD, MNRC) Training, Research, Isotopes, General Atomics (TRIGA) reactor (the reactor, facility), for an additional 20 years from the date of issuance. The facility is located in the city of North Highlands, Sacramento County, California. In connection with the renewed license, the licensee is authorized to operate the reactor at a maximum licensed power level of 1.0 megawatt- thermal (MWt).
Information Collection: Equal Employment Opportunity Electronic Complaint System
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a proposed collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``Equal Employment Opportunity Electronic Complaint System.''
Holtec Decommissioning International, LLC, Holtec Indian Point 2, LLC; Indian Point Nuclear Generating Unit No. 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility License No. DPR-26, issued to Holtec Decommissioning International, LLC (HDI), on behalf of Holtec Indian Point 2, LLC, for Indian Point Nuclear Generating Unit No. 2. The proposed amendment would modify the Indian Point Unit 2 (IP2) staffing requirements, prohibit the transfer of Indian Point Unit 3 (IP3) spent fuel to the IP2 spent fuel pool (SFP), and prohibit storing spent fuel in the IP2 SFP. This change would support transfer of the spent fuel from the IP2 SFP to dry storage within an independent spent fuel storage installation (ISFSI) as part of ongoing decommissioning activities at the Indian Point Energy Center (IPEC).
Holtec Decommissioning International, LLC, Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; Indian Point Nuclear Generating Unit Nos. 1, 2, and 3
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Provisional Operating License No. DPR-5, and Renewed Facility License Nos. DPR-26 and DPR-64, issued to Holtec Decommissioning International, LLC, on behalf of Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC, for Indian Point Nuclear Generating Unit Nos. 1, 2, and 3, collectively referred to as the Indian Point Energy Center. The proposed amendment would remove the Cyber Security Plan requirements contained in License Condition 3.d of the Indian Point Unit 1 Provisional License, License Condition 2.H of the Indian Point Unit 2 Renewed Facility License, and License Condition 2.G of the Indian Point Unit 3 Renewed Facility License to reflect the cyber security requirements associated with decommissioning power reactors.
Advisory Committee on Reactor Safeguards: Charter Renewal
The Advisory Committee on Reactor Safeguards (ACRS) was established by section 29 of the Atomic Energy Act (AEA) of 1954, as amended. Its purpose is to provide advice to the Commission with regard to the hazards of proposed or existing reactor facilities, to review each application for a construction permit or operating license for certain facilities specified in the AEA, and such other duties as the Commission may request.
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 Joseph M. Farley Nuclear Plant, Units 1 and 2; Byron Station, Unit 2; and Beaver Valley 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.
STP Nuclear Operating Company; South Texas Project, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) under the National Environmental Policy Act of 1969 (NEPA) and NRC's regulations. This EA summarizes the results of the NRC staff's environmental review, which evaluates the potential environmental impacts of approving an alternate disposal request in response to a request from STP Nuclear Operating Company (STPNOC) for Renewed Facility Operating Licenses NPF-76 and NPF-80 for South Texas Project, Units 1 and 2 (STP). Specifically, the alternate disposal request, if approved, would allow the licensee to dispose of very-low-level waste (VLLW) generated during day-to-day operations at the STP reactor site at Texas Class 1 or Class 2 industrial landfills.
GE-Hitachi Nuclear Energy Americas, LLC; Morris Operation Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has issued a subsequent renewed license to GE-Hitachi Nuclear Energy Americas, LLC (GEH) for Special Nuclear Materials (SNM) License No. SNM-2500 for the possession, transfer, and storage of radioactive material at the Morris Operation Independent Spent Fuel Storage Installation (ISFSI) (GEH-MO). GEH-MO is located in Grundy County, Illinois, near Morris, Illinois. The subsequent renewed license authorizes operation of GEH-MO in accordance with the provisions of the subsequent renewed license and its technical specifications. The subsequent renewed license expires on May 31, 2042.
American Society of Mechanical Engineers 2019-2020 Code Editions; Correction
The U.S. Nuclear Regulatory Commission (NRC) published a final rule in the Federal Register on October 27, 2022, 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. These amendments were made in accordance with NRC's policy to periodically update the regulations to incorporate by reference new editions of the American Society of Mechanical Engineers Codes and are intended to maintain the safety of nuclear power plants and to make NRC activities more effective and efficient. The final rule contained minor editorial errors, and this action is necessary to correct the final rule and the regulations.
Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is considering an application for the renewal of Facility Operating License Nos. NPF-87 and NPF-89, which authorize Vistra Operations Company LLC (Vistra, 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.
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