Nuclear Regulatory Commission 2020 – Federal Register Recent Federal Regulation Documents
Results 201 - 250 of 515
Biweekly 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 biweekly 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 biweekly notice includes all amendments issued, or proposed to be issued, from July 14, 2020, to July 27, 2020. The last biweekly notice was published on July 28, 2020.
Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 3.15, ``Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant.'' RG 3.15 describes the standard format and content that the NRC staff considers acceptable for license applications to authorize the receipt, possession, and storage of unirradiated fuel assemblies and associated radioactive materials at a nuclear power plant.
Notice of Intent To Review and Update the Generic Environmental Impact Statement for License Renewal of Nuclear Plants
The U.S. Nuclear Regulatory Commission (NRC) intends to gather information through the public scoping process to support the review to determine whether to update NUREG-1437, ``Generic Environmental Impact Statement for License Renewal of Nuclear PlantsFinal Report'' (LR GEIS). The NRC is seeking public input on the proposed action and has scheduled public scoping meetings.
NextEra Energy Duane Arnold, LLC; Duane Arnold Energy Center
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption in response to a February 25, 2020, as supplemented by letter dated May 29, 2020, request from NextEra Energy Duane Arnold, LLC (NEDA, the licensee) for Duane Arnold Energy Center (DAEC). The exemption would permit the licensee to use funds from the DAEC decommissioning trust fund (DTF, the Trust) for spent fuel management activities and site restoration. The exemption would also allow such withdrawals without prior notification to the NRC. The NRC staff is issuing a final Environmental Assessment (EA) and final Finding of No Significant Impact (FONSI) associated with the proposed exemption.
In the Matter of Dr. Melinda P. Krahenbuhl, Reed Research Reactor, Portland, Oregon
The U.S. Nuclear Regulatory Commission (NRC) is issuing Confirmatory Order (CO) IA-20-040 to Dr. Melinda Krahenbuhl, former Director of the Reed College, Reed Research Reactor, Portland, Oregon, as a result of a successful alternative dispute resolution (ADR) mediation session held on June 22, 2020. The CO confirms commitments agreed to during the ADR mediation, and the NRC is satisfied that the concerns discussed in Order IA-19-035 issued to Dr. Krahenbuhl on March 16, 2020, will be addressed with the issuance of this CO. Accordingly, the NRC is withdrawing the March 16, 2020, Order prohibiting Dr. Krahenbuhl's involvement in NRC-licensed activities for three years and, subject to the satisfactory completion of the additional corrective actions described in Order IA-20-040, the NRC will take no further action concerning the violations discussed in Order IA-19-035. The Order is effective on the date of issuance.
Development of an Ex Situ Performance Testing Protocol for Nuclear Power Plant Flood Penetration Seals
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2240, ``Development of an Ex Situ Performance Testing Protocol for Nuclear Power Plant Flood Penetration Seals.'' This draft NUREG summarizes a research project that developed a test protocol for evaluating flood penetration seals using simulated flooding conditions in a laboratory setting.
Changes to Subsequent License Renewal Guidance Documents Regarding Reactor Vessel Internal Components in Pressurized Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on draft interim staff guidance (ISG) that proposes changes to the NRC's subsequent license renewal guidance documents. Specifically, this ISG revises guidance contained in NUREG-2191, ``Generic Aging Lessons Learned for Subsequent License Renewal (GALL- SLR) Report,'' and NUREG-2192, ``Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants.'' NUREG-2191 and NUREG-2192 were published in July 2017 and are not scheduled to be updated for several years. The proposed changes to these documents are contained in a draft ISG entitled, ``Draft SLR-ISG- PWRVI-2020-XX; Updated Aging Management Criteria for Reactor Vessel Internal Components in Pressurized Water Reactors.''
Changes to Subsequent License Renewal Guidance Documents; Correction
On July 2, 2020, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on three draft interim staff guidance documents (ISGs) that propose changes to the NRC's subsequent license renewal guidance documents. Several aging management review (AMR) line items were inadvertently omitted from the draft mechanical ISG. These omitted AMR line items are provided in an errata document. The public comment period was originally scheduled to close on August 3, 2020. 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.
Information Collection: NRC Form 749, “Manual License Verification Report”/License Verification System
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 749, ``Manual License Verification Report''/License Verification System.''
Westinghouse Electric Company, LLC; Columbia Fuel Fabrication Facility
The U.S. Nuclear Regulatory Commission (NRC) will conduct a scoping process to gather information necessary to prepare an environmental impact statement (EIS) related to the review of Westinghouse Electric Company, LLC's (WEC) request to renew its operating license for its Columbia Fuel Fabrication Facility (CFFF) in Hopkins, South Carolina. The NRC had published a draft environmental assessment (EA) but determined it was not able to conclude the review in a finding of no significant impact. Therefore, the NRC staff will prepare an EIS to document the potential environmental impacts from the proposed action (i.e., whether to renew WEC's CFFF operating license) and reasonable alternatives. As part of the EIS development process, the NRC is seeking comments on the scope of its environmental review.
Information Collection: NRC Form 241, “Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore Waters”
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 241, `Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore Waters.' ''
Transfer of Very Low-Level Waste To Exempt Persons for Disposal
On March 6, 2020, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on a proposed interpretation of its low-level radioactive waste disposal regulations that would permit licensees to dispose of waste by transfer to persons who hold specific exemptions for the purpose of disposal. The public comment period was originally scheduled to close on April 20, 2020. On April 9, 2020, the public comment period was extended to July 20, 2020. In recognition of the continuing impacts of the current COVID-19 public health emergency (PHE) across the nation, the NRC has decided to reopen the public comment period to allow more time for members of the public to develop and submit their comments.
In the Matter of Wolf Creek Nuclear Operating Corporation; Wolf Creek Generating Station; Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has issued a general license to the Wolf Creek Nuclear Operating Corporation (Wolf Creek), authorizing the operation of the Wolf Creek Generating Station Independent Spent Fuel Storage Installation (ISFSI), in accordance with its regulations. The Order is being issued to Wolf Creek to impose additional security requirements because Wolf Creek has identified near term plans to store spent fuel in an ISFSI under the general license provisions of the NRC's regulations. The Order was issued July 22, 2020 and became effective immediately.
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 September 21-22, 2020. A sample of agenda items to be discussed during the public session includes: A discussion of the ACMUI's review and analysis of medical events from fiscal year 2019; a discussion of the ACMUI's review and analysis of non-medical events from fiscal year 2019; a discussion on the U.S. Food and Drug Administration's regulatory process for the development of drugs and devices; an update on the NRC's Phase 2 revision of Regulatory Guide 8.39, ``Release of Patients Administered Radioactive Material''; and an update on the activities of the NRC's Medical Radiation Safety Team. 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 / 2020.html or by emailing Ms. Kellee Jamerson 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: September 21, 2020, from 10 a.m. to 2 p.m. and September 22, 2020, from 12:15 p.m. to 1:45 p.m. Eastern Standard Time (EST).
Information Collection: NRC Form 4, Cumulative Occupational Exposure History
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 4, Cumulative Occupational Exposure History.''
Biweekly 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 biweekly 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 biweekly notice includes all amendments issued, or proposed to be issued, from June 29, 2020, to July 13, 2020. The last biweekly notice was published on July 14, 2020.
Exelon Generation Company, LLC James A. FitzPatrick Nuclear Power Plant
The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to an August 8, 2019, request from Exelon Generation Company, LLC (Exelon or the licensee). The licensee requested that the James A. FitzPatrick Nuclear Power Plant be granted a permanent exemption from regulations regarding the containment leak rate test to exclude the main steam isolation valve leakage from the leakage rate test measurements.
Union Electric Company; Callaway Plant, Unit No.1
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. NPF- 30, issued to Union Electric Company (the licensee), for operation of the Callaway Plant, Unit No. 1 (Callaway). Due to the COVID-19 public health emergency, the proposed one-time amendment would revise Callaway Technical Specification (TS) 5.5.9, ``Steam Generator (SG) Program,'' to defer the SG tube inspection currently scheduled during Refueling Outage (RFO) 24, in the fall of 2020, to RFO 25, scheduled for the spring of 2022. 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.
Social Security Number Fraud Prevention
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of August 17, 2020, for the direct final rule that was published in the Federal Register on June 2, 2020. This direct final rule amends the NRC's regulations to comply with the Social Security Number Fraud Prevention Act, signed on September 15, 2017.
Information Collection: NRC Online Form, “Request for Alternative to 10 CFR 50.55a(z)(1) and (2)”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on our request for emergency review for and OMB approval of the information collection that is summarized below. The information collection is entitled, ``NRC Online Form, `Request for Alternative to 10 CFR 50.55a(z)(1) and (2).' ''
Interim Storage Partners Consolidated Interim Storage Facility Project
On May 8, 2020, the U.S. Nuclear Regulatory Commission (NRC) issued for public comment a draft Environmental Impact Statement (EIS) for Interim Storage Partners' (ISP's) license application 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 fuel. The public comment period was originally scheduled to close on September 4, 2020. Given recent events associated with the COVID-19 public health emergency, 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.
Duke Energy Carolinas LLC; McGuire Nuclear Station Units 1 and 2; Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is considering an exemption request from Duke Energy Carolinas, LLC (Duke Energy) which would permit Duke Energy to maintain MAGNASTOR[supreg] Cask 0FCTKN045 at its McGuire Nuclear Station independent spent fuel storage installation (ISFSI) in a storage condition where the helium density is above the range specified in Certificate of Compliance No. 1031, Amendment No. 7, Technical Specification 3.1.1. The NRC prepared an environmental assessment (EA) documenting its finding 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.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM Flood/Wind Multipurpose Canister Storage System, Certificate of Compliance No. 1032, Amendment No. 5
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of July 27, 2020, for the direct final rule that was published in the Federal Register on May 13, 2020. The direct final rule amends the NRC's spent fuel storage regulations by revising the Holtec International HI-STORM Flood/Wind Multipurpose Canister Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 5 to Certificate of Compliance No. 1032. Amendment No. 5 revises the certificate of compliance to: Add new heat load patterns and revise the minimum required cooling time for two multipurpose canisters (MPC-89 and MPC-37); add new fuel types to the approved contents; allow an exception to a code to permit use of certain duplex stainless steels; use an analysis model to revise the calculation for evaluating effective fuel conductivities; add the use of the damaged fuel isolator; add two versions of the standard variable weight transfer cask; add the option of using cyclic vacuum drying; and make changes to the final safety analysis report to add new types of fuel assemblies, add a definition to it and to the certificate of compliance, and add the required shielding evaluation to Section 5.4.8. In addition, Amendment No. 5 makes several clarifications and minor changes.
Emergency Preparedness for Small Modular Reactors and Other New Technologies
On May 12, 2020, the U.S. Nuclear Regulatory Commission (NRC) issued for public comment proposed amendments to its regulations regarding new alternative emergency preparedness requirements for small modular reactors and other new technologies. The public comment period was originally scheduled to close on July 27, 2020. The NRC is extending the public comment period to allow more time for members of the public and other stakeholders to develop and submit their comments.
Issuance of Multiple Exemptions in Response to COVID-19 Public Health Emergency
The U.S. Nuclear Regulatory Commission (NRC) issued 21 exemptions in response to requests from 13 licensees. The exemptions allow these licensees temporary relief from certain requirements under NRC regulations. The exemptions are in response to the COVID-19 public health emergency (PHE). The NRC is issuing a single notice to announce the issuance of the exemptions.
Energy Harbor Nuclear Corp; Energy Harbor Nuclear Generation LLC; Perry Nuclear Power Plant Unit No. 1
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a May 15, 2020, request from the Energy Harbor Nuclear Corp. (EHNC) to allow EHNC to submit a sufficient license renewal application for Perry Nuclear Power Plant, Unit No. 1, at least three years prior to the expiration of the existing license and still receive timely renewal protection.
List of Approved Spent Fuel Storage Casks: TN Americas LLC, Standardized NUHOMS® Horizontal Modular Storage System, Certificate of Compliance No. 1004, Renewed Amendment No. 16; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register on June 30, 2020, revising the TN Americas LLC, Standardized NUHOMS[supreg] Horizontal Modular Storage System listing within the ``List of approved spent fuel storage casks'' to include Renewed Amendment No. 16 to Certificate of Compliance No. 1004. This action is necessary to provide ADAMS accession numbers in the Availability of Documents table listing that were inadvertently omitted.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM Flood/Wind Multipurpose Canister Storage System, Certificate of Compliance No. 1032, Amendment No. 4
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of July 14, 2020, for the direct final rule that was published in the Federal Register on April 30, 2020. The direct final rule amends the NRC's spent fuel storage regulations by revising the Holtec International HI-STORM Flood/Wind Multipurpose Canister Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 4 to Certificate of Compliance No. 1032. Amendment No. 4 revises the certificate of compliance to: Add multipurpose canister (MPC)-32ML for storage and allow the fuel assembly class 16X16D as content for MPC-32ML; add the fuel assembly class 16X16E as content for MPC-37; and make changes to the final safety analysis report.
Information Collection: NRC Form 629, “Authorization for Payment by Credit Card”
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a renewal for an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, NRC Form 629, ``Authorization for Payment by Credit Card.''
Information Collection: Safeguards on Nuclear Material-Implementation of United States/International Atomic Energy Agency Agreement
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, ``Safeguards on Nuclear MaterialImplementation of United States/International Atomic Energy Agency Agreement.''
Biweekly 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 biweekly 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 biweekly notice includes all amendments issued, or proposed to be issued, from June 16, 2020 to June 26, 2020. The last biweekly notice was published on June 30, 2020.
Issuance of Multiple Exemptions in Response to COVID-19 Public Health Emergency
The U.S. Nuclear Regulatory Commission (NRC) issued multiple exemptions in response to requests from Holtec Decommissioning International, LLC.; Pacific Gas and Electric Company; Portland General Electric Company; Connecticut Yankee Atomic Power Company; and Yankee Atomic Electric Company. The exemptions allow the licensees to extend certain training and requalification frequency requirements of NRC's general criteria for security personnel in response to the COVID-19 public health emergency (PHE). The NRC is issuing a single notice to announce the issuance of these exemptions.
Omaha Public Power District; Fort Calhoun Station, Unit 1
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a request dated March 26, 2020, from the Omaha Public Power District (OPPD), for Fort Calhoun Station, Unit 1 (FCS), from the requirement to investigate and report to the NRC when OPPD does not receive notification of receipt of a shipment, or part of a shipment, of low-level radioactive waste within 20 days after transfer from the FCS facility. OPPD requested that the time period for it to receive acknowledgement that the shipment has been received by the intended recipient be extended from 20 to 45 days to avoid an excessive administrative burden as operational experience indicates that such shipments may take more than 20 days to reach their destination.
Patient Release Criteria for Radioactive Iodine
The U.S. Nuclear Regulatory Commission (NRC) is announcing the withdrawal, without prejudice to a future filing, of a petition for rulemaking (PRM-35-21), dated November 15, 2019, filed by Peter Crane on behalf of Sensible Controls on Administrations of Radioactive Iodine. The petitioner requested that the NRC revise its regulations regarding the criteria for patient release after the administration of radioactive iodine. By letter dated May 22, 2020, the petitioner withdrew the petition.
Information Collection: Medical Use of Byproduct Material
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, ``Medical Use of Byproduct Material.''
Independent Spent Fuel Storage Installation; Yankee Atomic Electric Company
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption, in response to an May 2, 2019, request from Yankee Atomic Electric Company (YAEC or licensee), from NRC's requirement to comply with the terms, conditions, and specifications in Amendment No. 8 of the NAC International, Inc. (NAC)Multi-Purpose Canister (MPC) System Certificate of Compliance (CoC) No. 1025, Appendix A ``Technical Specifications for NAC-MPC System,'' Technical Specifications (TS) A.5.1 ``Training Program'' and A.5.4 ``Radioactive Effluent Control Program'' at the Yankee Nuclear Power Station (YNPS) independent spent fuel storage installation (ISFSI) in Rowe, Massachusetts. These exemptions would relieve YAEC from the requirements to: Develop training modules under the systems approach to the training (SAT) program that include comprehensive instructions for the operation and maintenance of the ISFSI, except for the NAC-MPC System; and submit an annual report specifying the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous 12 months of operation.
Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1372, ``Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments.'' This draft guide is proposed Revision 4 of regulatory guide (RG) 1.136 of the same name. It updates the guidance for materials, design, construction, fabrication, examination, and testing of concrete containments in nuclear power plants through endorsement, with exceptions, of the 2019 edition of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section III, Division 2 (American Concrete Institute Standard 359-19), ``Code for Concrete Containments.''
Leakage Tests on Packages for Shipment of Radioactive Material
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 7.4, ``Leakage Tests on Packages for Shipment of Radioactive Material.'' This RG (Revision 2) endorses the methods and procedures developed by the Standards Committee on Packaging and Transportation of Radioactive and Nonnuclear Hazardous Materials, N14 Subcommittee of the American National Standards Institute (ANSI) in ANSI N14.5-2014, ``American National Standard for Radioactive MaterialsLeakage Tests on Packages for Shipment,'' dated June 19, 2014.
Guidance for Implementation of Changes, Tests, and Experiments
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.187. This RG provides licensees with a method that the NRC considers acceptable for use in complying with the Commission's regulations on the process by which licensees, under certain conditions, may make changes to their facilities and procedures as described in the final safety analysis report (FSAR) (as updated) (also referred to as the updated final safety analysis report (UFSAR)), and conduct tests or experiments not described in the FSAR (as updated), without obtaining a license amendment pursuant to NRC requirements. This RG is effective immediately with a 30-day post- promulgation comment period.
Passport Systems, Inc.; North Billerica, MA
The U.S. Nuclear Regulatory Commission (NRC) is providing public notice of the termination of Special Nuclear Materials (SNM) License No. SNM-2016. The NRC has terminated the license held by Passport Systems, Inc. (Passport), to possess and use SNM for developing new technologies to detect special nuclear materials in cargo containers for the U.S. Department of Homeland Security (DHS), Domestic Nuclear Detection Office. The license was terminated at Passport's request since it no longer needed the sources for development of their cargo inspection system.
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 one amendment request. The amendment request is for Salem Nuclear Generating Station, Unit Nos. 1 and 2. For the amendment request, the NRC proposes to determine that it involves no significant hazards consideration. Because the amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Exelon Generation Company, LLC; Dresden Nuclear Power Station, Units 2 and 3; LaSalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Nine Mile Point Nuclear Station, Unit 2; Peach Bottom Atomic Power Station, Units 2 and 3; and Quad Cities Nuclear Power Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to the facility operating licenses for the following facilities operated by Exelon Generation Company, LLC: Dresden Nuclear Power Station (Dresden), Units 2 and 3; LaSalle County Station (LaSalle), Units 1 and 2; Limerick Generating Station (Limerick), Units 1 and 2; Nine Mile Point Nuclear Station (Nine Mile Point), Unit 2; Peach Bottom Atomic Power Station (Peach Bottom), Units 2 and 3; and Quad Cities Nuclear Power Station (Quad Cities), Units 1 and 2. The proposed amendments would revise technical specification (TS) requirements for certain physical parameters at each facility.
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