Nuclear Regulatory Commission 2018 – Federal Register Recent Federal Regulation Documents
Results 301 - 350 of 546
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to Section 189a.(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, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued, from June 5, 2018, to June 18, 2018. The last biweekly notice was published on June 19, 2018.
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 Oconee Nuclear Station, Unit Nos. 1, 2, and 3; Duane Arnold Energy Center; and Callaway Plant, Unit No. 1. For each amendment request, the NRC proposes to determine that they involve no significant hazards consideration. Because each amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Nebraska Public Power District; Cooper Nuclear Station
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. DPR- 46, issued to Nebraska Public Power District (NPPD), for operation of the Cooper Nuclear Station (CNS). The proposed amendment would modify the CNS technical specifications by revising the two recirculation loop and single recirculation loop Safety Limit Minimum Critical Power Ratio (SLMCPR) values to reflect the results of a cycle specific calculation. 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.
Draft Letter to the Nuclear Energy Institute Regarding the Clarification of Regulatory Paths for Lead Test Assemblies
On June 7, 2018, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on a draft letter to the Nuclear Energy Institute (NEI) clarifying the regulatory paths for the use of lead test assemblies (LTAs). The public comment period closed on June 27, 2018. 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.
Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is considering an amendment to nuclear reactor licenses DPR-39 and DPR-48 to add a license condition that reflects the NRC's approval of the license termination plan (LTP) and provides criteria for when NRC approval is needed for LTP changes. The NRC has prepared a final environmental assessment (EA) and finding of no significant impact (FONSI) for this licensing action.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Technical Specifications for Reactor Coolant System Vacuum Fill and Inspections, Tests, Analyses, and Acceptance Criteria for Containment Floodup
The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment Nos. 118 and 117 to Combined Licenses (COL), NPF-91 and NPF-92, respectively. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM, LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, and the City of Dalton, Georgia (the licensee); for construction and operation of the Vogtle Electric Generating Plant (VEGP) Units 3 and 4, located in Burke County, Georgia. The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.
Miscellaneous Corrections
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to make miscellaneous administrative updates and corrections. The amendments update descriptions of agency organization and functions, correct cross-reference, typographical, and grammatical errors, and add a certification recipient and clarifying language. This document is necessary to inform the public of these non-substantive amendments to the NRC's regulations.
Monitoring the Effectiveness of Maintenance at Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1336, ``Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.'' This proposed guide, Revision 4, has been revised to addresses new issues identified since Revision 3 of RG 1.160 was issued and endorses with clarification NUMARC 93-01, ``Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,'' Revision 4F. The proposed revision describes methods that are acceptable to the NRC staff for compliance with the requirements for monitoring the effectiveness of maintenance at nuclear power plants.
Tennessee Valley Authority, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Independent Spent Fuel Storage Installation; Sequoyah Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation; Watts Bar Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to Renewed Facility Operating License Nos. DPR- 33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, respectively; Renewed Facility Operating License Nos. DPR-77 and DPR-79 for the Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2, respectively; and Facility Operating License Nos. NPF-90 and NPF-96 for the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2, respectively. The proposed amendments would revise the implementation date for the NRC-approved license amendments to upgrade the Emergency Action Level (EAL) schemes for Browns Ferry, Units 1, 2, and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Changes to Containment Cooling and Spent Fuel Pool Makeup Strategies
The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment Nos. 126 and 125 to Combined Licenses (COLs), NPF-91 and NPF-92, respectively. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company; Oglethorpe Power Corporation; MEAG Power SPVM, LLC; MEAG Power SPVJ, LLC; MEAG Power SPVP, LLC; and the City of Dalton, Georgia (the licensee), for construction and operation of the Vogtle Electric Generating Plant (VEGP) Units 3 and 4, located in Burke County, Georgia. The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Changes to Construction Fitness-for-Duty Commitments
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Combined Licenses (NPF-91 and NPF-92), issued to Southern Nuclear Operating Company, Inc. (SNC), and Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM, LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, Authority of Georgia, and the City of Dalton, Georgia (together ``the licensees''), for construction and operation of the Vogtle Electric Generating Plant (VEGP), Units 3 and 4, located in Burke County, Georgia.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Unit Nos. 3 and 4
On June 19, 2018, the U.S. Nuclear Regulatory Commission (NRC) published a biweekly notice providing the public with the opportunity to comment, request a hearing, and petition for leave to intervene. Due to a publication error, which was corrected by the Office of the Federal Register on June 22, 2018, incorrect information about a license amendment request submitted to the NRC on April 13, 2018, by Southern Nuclear Operating Company, Inc., regarding Vogtle Electric Generating Plant, Unit Nos. 3 and 4, was published in the biweekly notice. The NRC is issuing this notice to provide adequate time for members of the public to submit comments, request a hearing, and petition for leave to intervene on this license amendment request.
State of Wyoming: NRC Staff Assessment of a Proposed Agreement Between the Nuclear Regulatory Commission and the State of Wyoming
By letter dated November 14, 2017, Governor Matthew H. Mead of the State of Wyoming requested that the U.S. Nuclear Regulatory Commission (NRC or Commission) enter into an Agreement with the State of Wyoming as authorized by Section 274b. of the Atomic Energy Act of 1954, as amended (AEA). Under the proposed Agreement, the Commission would discontinue, and the State of Wyoming would assume, regulatory authority over the management and disposal of byproduct materials as defined in Section 11e.(2) of the AEA and a subcategory of source material associated with uranium or thorium milling within the State. Pursuit to Commission direction, the proposed Agreement would state that the NRC will retain regulatory authority over the American Nuclear Corporation (ANC) license. As required by Section 274e. of the AEA, the NRC is publishing the proposed Agreement for public comment. The NRC is also publishing the summary of a draft assessment by the NRC staff of the State of Wyoming's regulatory program. Comments are requested on the proposed Agreement, especially its effect on public health and safety. Comments are also requested on the draft staff assessment, the adequacy of the State of Wyoming's program, and the State's program staff, as discussed in this notice. The proposed Agreement would exempt persons who possess or use byproduct materials as defined in Section 11e.(2) of the AEA and a subcategory of source material involved in the extraction or concentration of uranium or thorium in source material or ores at uranium or thorium milling facilities in the State of Wyoming from portions of the Commission's regulatory authority. Radioactive materials not covered by the proposed Agreement will continue to be subject to the Commission's regulatory authority. Section 274e. of the AEA requires that the NRC publish these exemptions. Notice is hereby given that the pertinent exemptions have been previously published in the Federal Register and are codified in the NRC's regulations.
Duane Arnold Energy Center
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of NextEra Energy Duane Arnold, LLC (NextEra) to withdraw its application dated August 31, 2017, for a proposed amendment to Duane Arnold Energy Center (DAEC), Facility Operating License No. DPR-49. The proposed amendment would have modified the licensing basis by the addition of a license condition to allow for the implementation of the NRC's regulations on ``Risk-Informed Categorization and Treatment of Structures, Systems, and Components (SSCs) for Nuclear Power Reactors.''
Clarification on Endorsement of Nuclear Energy Institute Guidance in Designing Digital Upgrades in Instrumentation and Control Systems
The U.S. Nuclear Regulatory Commission (NRC) issued a Regulatory Issue Summary (RIS) entitled, RIS 2002-22, Supplement 1, ``Clarification on Endorsement of Nuclear Energy Institute Guidance in Designing Digital Upgrades in Instrumentation and Control Systems.'' This RIS supplement clarifies RIS 2002-22, which remains in effect. The NRC continues to endorse Nuclear Energy Institute (NEI)-01-01, as stated in RIS 2002-22 and clarified RIS 2002-22, Supplement 1. This RIS supplement clarifies the guidance in RIS 2002-22 for preparing and documenting qualitative assessments that licensees can use to develop written evaluations to address the criteria in NRC's regulations for digital instrumentation and control (I&C) modifications. This clarification is intended to reduce regulatory uncertainty for licensees applying the process set in the NRC's regulations and making digital I&C modifications without prior NRC approval.
Pennsylvania State University
The U.S. Nuclear Regulatory Commission (NRC) has issued a renewal of special nuclear materials (SNM) License No. SNM-95 held by the Pennsylvania State University (PSU), University Park, Pennsylvania, to possess and use SNM for education, research, and training programs. The renewed license authorizes PSU to continue to possess and use SNM for an additional 10 years from the date of issuance.
Report to Congress on Abnormal Occurrences; Fiscal Year 2017 Dissemination of Information
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 0090, Volume 40, ``Report to Congress on Abnormal Occurrences: Fiscal Year 2017.'' The report describes those events that the NRC or an Agreement State identified as abnormal occurrences (AOs) during fiscal year (FY) 2017, based on the criteria defined in the report. The report describes six events at Agreement State-licensed facilities and five events at an NRC-licensed facilities.
Revision of Fee Schedules; Fee Recovery for Fiscal Year 2018
The U.S. Nuclear Regulatory Commission (NRC) is amending the licensing, inspection, special project, and annual fees charged to its applicants and licensees. These amendments are necessary to implement the Omnibus Budget Reconciliation Act of 1990, as amended (OBRA-90) which requires the NRC to recover approximately 90 percent of its annual budget through fees.
Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Improvements to Main Control Room Post-Accident Radiological Consequences
The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic AP1000 design control document (DCD) and is issuing License Amendment Nos. 123 and 122 to Combined Licenses (COL), NPF-91 and NPF-92, respectively. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM, LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, and the City of Dalton, Georgia (the licensee); for construction and operation of the Vogtle Electric Generating Plant (VEGP) Units 3 and 4, located in Burke County, Georgia. The granting of the exemption allows the changes to Tier 1 information that is requested in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.
Exelon Generation Company, LLC; Braidwood Station, Units 1 and 2; Byron Station, Units 1 and 2; Clinton Power Station, Unit 1; Dresden Nuclear Power Station, Units 1, 2, and 3; LaSalle County Station, Units 1 and 2; and Quad Cities Nuclear Power Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to licenses held by Exelon Generation Company, LLC (Exelon, the licensee) for the operation of Braidwood Station (Braidwood), Unit Nos. 1 and 2; Byron Station (Byron), Unit Nos. 1 and 2; Clinton Power Station (Clinton), Unit No. 1; Dresden Nuclear Power Station (Dresden), Unit Nos. 1, 2, and 3; LaSalle County Station (LaSalle), Unit Nos. 1 and 2; and Quad Cities Nuclear Power Station (Quad Cities), Unit Nos. 1 and 2 (the facilities). The proposed amendments would revise the emergency response organization (ERO) positions identified in the emergency plan for each facility. The NRC is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) associated with the proposed license amendments.
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to Section 189a.(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, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued, from May 22, 2018, to June 4, 2018. The last biweekly notice was published on June 5, 2018.
Westinghouse Electric Company, LLC; Columbia Fuel Fabrication Facility
The U.S. Nuclear Regulatory Commission (NRC) is considering the renewal of Special Nuclear Materials (SNM) License No. SNM-1107 to allow Westinghouse Electric Company, LLC (WEC) to continue to operate its Columbia Fuel Fabrication Facility (CFFF) for an additional 40 years. The NRC has prepared a final environmental assessment (EA) and finding of no significant impact (FONSI) for this licensing action.
Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Units 1 and 2; Suspension of Security Measures in an Emergency or During Severe Weather
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption from regulatory requirements in response to an August 1, 2017, request from Exelon Generation Company, LLC (Exelon or the licensee). The exemption allows a certified fuel handler (CFH), besides a licensed senior operator, to approve the emergency suspension of security measures for Three Mile Island Nuclear Station (TMI), Units 1 and 2, during certain emergency conditions or during severe weather. Although the exemption is effective upon receipt, the actions permitted by the exemption may not be implemented until both the ``Certification of Permanent Cessation of Operations'' and the ``Certification of Permanent Fuel Removal'' have been submitted. While Exelon submitted a Certification of Permanent Cessation of Operations for TMI, Unit 1, the Certification of Permanent Fuel Removal has not yet been submitted. Since the TMI, Unit 2, license had already been modified to allow possession but not operation before the effective date of the rule requiring these certifications; the certifications have been deemed submitted.
Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Post-Shutdown Decommissioning Activities Report
On May 21, 2018, the U.S. Nuclear Regulatory Commission (NRC) received the Post-Shutdown Decommissioning Activities Report (PSDAR) for the Oyster Creek Nuclear Generating Station (Oyster Creek). The PSDAR, which includes the site-specific decommissioning cost estimate (DCE), provides an overview of Exelon Generation Company, LLC's (Exelon or the licensee) planned decommissioning activities, schedule, projected costs, and environmental impacts for Oyster Creek. The NRC will hold a public meeting to discuss the PSDAR's content and receive comments.
Unified Agenda of Federal Regulatory and Deregulatory Actions
We are publishing our semiannual regulatory agenda (the Agenda) in accordance with Public Law 96-354, ``The Regulatory Flexibility Act,'' and Executive Order 12866, ``Regulatory Planning and Review.'' The Agenda is a compilation of all rulemaking activities on which we have recently completed action or have proposed or are considering action. We have completed 6 rulemaking activities since publication of our last Agenda on January 12, 2018 (83 FR 2018). This issuance of our Agenda contains 28 active and 20 long-term rulemaking activities: 3 are Economically Significant; 8 represent Other Significant agency priorities; 35 are Substantive, Nonsignificant rulemaking activities; and 2 are Administrative rulemaking activities. In addition, 3 rulemaking activities impact small entities. We are requesting comment on the rulemaking activities as identified in this Agenda.
Clarification of Export Reporting Requirements for Nuclear Facilities, Equipment, and Non-Nuclear Materials
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) to clarify the reporting requirements for certain exports of nuclear facilities, equipment, and non-nuclear materials.
Kennecott Uranium Corporation; Sweetwater Uranium Project
The U.S. Nuclear Regulatory Commission (NRC) is considering renewal of Source Material License SUA-1350 issued to Kennecott Uranium Corporation (KUC) for continued operations at the Sweetwater Uranium Project (SUP) in Sweetwater County, Wyoming (Docket No. 40-8584). The NRC has prepared an environmental assessment (EA) and finding of no significant impact (FONSI) for this licensing action.
Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) received, and is considering approval of, an application from Tennessee Valley Authority (TVA or the licensee) for amendments to Facility Operating License Nos. NPF-90 and NPF-96, which authorizes the operation of Watts Bar Nuclear Plant (WBN), Unit Nos. 1 and 2, respectively. The amendments would allow the loading of tritium producing burnable absorber rods (TPBARs) in WBN, Unit 2 and would make associated technical specification changes for WBN, Unit Nos. 1 and 2. Because this amendment request contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Draft Letter to the Nuclear Energy Institute Regarding the Clarification of Regulatory Paths for Lead Test Assemblies
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comments on a draft letter to the Nuclear Energy Institute (NEI) clarifying the regulatory paths for the use of lead test assemblies (LTAs). This draft letter would finalize the NRC staff's views on the preliminary positions regarding LTAs provided in a letter to NEI dated June 29, 2017. The NRC does not currently have consolidated regulatory guidance regarding the use of LTAs. Therefore, the NRC has drafted this letter to clarify its positions regarding the use of LTAs. These positions would affect light-water reactor licensees who wish to irradiate LTAs.
Advisory Committee on the Medical Uses of Isotopes: Meeting Notice
The U.S. Nuclear Regulatory Commission (NRC) will convene a teleconference meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) on July 16, 2018, to discuss the draft report of the ACMUI Subcommittee on Training and Experience Requirements for All Modalities. This report will include the subcommittee's comments on the NRC staff's evaluation of the training and experience requirements for different categories of radiopharmaceuticals in Title 10 of the Code of Federal Regulations, part 35, ``Medical Use of Byproduct Material,'' Subpart E, ``Unsealed Byproduct MaterialWritten Directive Required.'' Meeting information, including a copy of the agenda and handouts, will be available at https://www.nrc.gov/reading-rm/doc-collections/acmui/ meetings/2018.html. The agenda and handouts may also be obtained by contacting Ms. Maryann Ayoade using the information below.
Pacific Gas and Electric Company Diablo Canyon Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is considering issuing an environmental assessment (EA) and a finding of no significant impact (FONSI) for its review and approval of the decommissioning funding plans (DFPs) submitted by Pacific Gas and Electric Company (PGEC) on December 17, 2012, and December 17, 2015, for the independent spent fuel storage installation (ISFSI) at Diablo Canyon in Avila Beach, California.
Entergy Operations, Inc.; River Bend Station, Unit 1
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft plant-specific Supplement 58 to the Generic Environmental Impact Statement (GEIS) for License Renewal of Nuclear Plants, NUREG-1437, regarding the renewal of operating license NPF-47 for an additional 20 years of operation for River Bend Station (RBS), Unit 1. The RBS is located in West Feliciana Parish, Louisiana. Possible alternatives to the proposed action (license renewal) include no action and reasonable alternative energy sources.
Effect of LWR Water Environments on the Fatigue Life of Reactor Materials
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG/ CR-6909, Revision 1, ``Effect of LWR Water Environments on the Fatigue Life of Reactor Materials.'' This report summarizes the results of NRC research efforts and work performed at Argonne National Laboratory on the fatigue of piping and pressure vessel steels in light-water reactor (LWR) environments. Revision 1 of this report provides updates and improvements to the environmental fatigue correction factor approach based on an extensive update to available laboratory fatigue data from testing and results available since this report was first published in 2007. This final document also incorporates changes to address public comments provided on the draft of Revision 1 of NUREG/CR-6909.
Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.207, ``Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components.'' This RG describes methods and procedures that the staff of the NRC considers acceptable for use in determining the acceptable fatigue lives of components evaluated by a cumulative usage factor calculation in accordance with the fatigue design provisions in Section III, ``Rules for Construction of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code to account for the effects of light-water reactor water environments.
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to Section 189a.(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, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued, from May 8, 2018, to May 21, 2018. The last biweekly notice was published on May 22, 2018.
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 River Bend Station, Unit 1; Grand Gulf Nuclear Station, Unit 1; and Browns Ferry Nuclear Plant, Units 1, 2, and 3. For each amendment request, the NRC proposes to determine that they involve no significant hazards consideration. Because each amendment request contains sensitive unclassified non-safeguards information (SUNSI) an order imposes procedures to obtain access to SUNSI for contention preparation.
This site is protected by reCAPTCHA and the Google
Privacy Policy and
Terms of Service apply.
