Nuclear Regulatory Commission 2016 – Federal Register Recent Federal Regulation Documents
Results 551 - 586 of 586
Advisory Committee on the Medical Uses of Isotopes: Meeting Notice
The U.S. Nuclear Regulatory Commission will convene a meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) on March 17-18, 2016. A sample of agenda items to be discussed during the public session includes: A discussion on the reporting of medical events for various modalities; an update on medical-related events; a discussion on the training and experience requirements for authorized users of alpha and beta emitters; an update on the licensing guidance for yttrium-90 microsphere brachytherapy; and a discussion on the licensing guidance for the Leksell Gamma Knife[supreg] IconTM unit. The agenda is subject to change. The current agenda and any updates will be available at https://www.nrc.gov/reading-rm/doc- collections/acmui/meetings/2016.html or by emailing Ms. Sophie Holiday 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: March 17, 2016, from 9:30 a.m. to 5:00 p.m. and March 18, 2016, from 8:00 a.m. to 11:30 a.m. Data and Time for Closed Sessions: March 17, 2016, from 7:30 a.m. to 9:30 a.m., March 18, 2016, from 7:30 a.m. to 8:00 a.m., and March 18, 2016, from 12:00 p.m. to 1:00 p.m. Address for Public Meeting: U.S. Nuclear Regulatory Commission, Two White Flint North Building, Room T2-B3, 11545 Rockville Pike, Rockville, Maryland 20852. Public Participation: Any member of the public who wishes to participate in the meeting in person or via phone should contact Ms. Holiday using the information below. The meeting will also be webcast live: video.nrc.gov. Contact Information: Ms. Sophie J. Holiday, email: sophie.holiday@nrc.gov, telephone: (301) 415-7865.
Exelon Generation Company, LLC, Braidwood Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has issued renewed facility operating license Nos. NPF-72 and NPF-77 to Exelon Generation Company, LLC (Exelon or the licensee), the operator of Braidwood Station, Units 1 and 2 (Braidwood), respectively. Renewed facility operating license Nos. NPF-72 and NPF-77 authorize the operation of Braidwood Units 1 and 2 at reactor core power levels not in excess of 3645 megawatts thermal each, in accordance with the provisions of the renewed licenses and technical specifications. In addition, the NRC has prepared a record of decision (ROD) that supports the NRC's decision to renew facility operating license Nos. NPF-72 and NPF-77.
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 January 5, 2016, to January 15, 2016. The last biweekly notice was published on January 19, 2016.
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 Shearon Harris Nuclear Power Plant, Unit 1; and H. B. Robinson Steam Electric Plant, Unit No. 2. The NRC proposes to determine that the amendment request involves no significant hazards consideration. In addition, the amendment request contains sensitive unclassified non- safeguards information (SUNSI).
Draft NUREG/CR-7209, A Compendium of Spent Fuel Transportation Package Response Analyses to Severe Fire Accident Scenarios
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG/CR-7209, ``A Compendium of Spent Fuel Transportation Package Response Analyses to Severe Fire Accident Scenarios.'' This report summarizes studies of rail and truck transport accidents involving fires, relative to regulatory requirements for shipment of commercial spent nuclear fuel (SNF).
Information Collection: NRC's Policy Statement on Cooperation With States at Commercial Nuclear Power Plants and Other Nuclear Production and Utilization Facilities
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, ``Cooperation with States at Commercial Nuclear Power Plants and Other Nuclear Production and Utilization Facilities, Policy Statement.''
List of Approved Spent Fuel Storage Casks: NAC International, Inc., MAGNASTOR® Cask System; Certificate of Compliance No. 1031, Amendment Nos. 0-3, Revision 1
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of February 1, 2016, for the direct final rule that was published in the Federal Register on November 18, 2015. This direct final rule amended the NRC's spent fuel storage regulations by revising the NAC International, Inc., MAGNASTOR[supreg] Cask System listing within the ``List of approved spent fuel storage casks'' to include Revision 1 to Amendment Nos. 0-3 to Certificate of Compliance (CoC) No. 1031. Revision 1 to Amendment Nos. 0-3 to CoC No. 1031 makes changes to the Technical Specifications (TS), including correcting a typographical error in two actual boron loadings in TS 4.1.1(a), and revising the decay times in Tables B2-4 (for Amendment Nos. 0 and 1) and B2-5 (for Amendment Nos. 2 and 3) in Appendix B of the TSs for minimum additional decay time required for spent fuel assemblies that contain nonfuel hardware.
In the Matter of Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 1, 2, and 3, and James A. Fitzpatrick Nuclear Power Plant; Exelon Generation Company, LLC, Nine Mile Point Nuclear Station, Units 1 and 2, and R.E. Ginna Nuclear Power Plant; Pacific Gas and Electric Company, Diablo Canyon Power Plant, Units 1 and 2; and Southern California Edison Company, San Onofre Nuclear Generating Station, Units 2 and 3, including Independent Spent Fuel Storage Installations for All Facilities; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting the attachment to a notice that was published in the Federal Register (FR) on January 15, 2016, regarding authorizing the licensees to transfer, receive, possess, transport, import, and use certain firearms and large-capacity ammunition feeding devices not previously permitted to be owned or possessed under Commission authority, notwithstanding certain local, State, or Federal firearms laws, including regulations that prohibit such actions, as reflected in the confirmatory orders for the nuclear plant facilities listed above. This action is necessary to correct an order number.
Concentration Averaging and Encapsulation Branch Technical Position
The U.S. Nuclear Regulatory Commission (NRC) is requesting comments on whether the NRC staff should formally document a position on contaminated material and contaminated trash. The NRC issued Revision 1 of the Branch Technical Position on Concentration Averaging and Encapsulation (CA BTP) in February of 2015. The CA BTP provides acceptable methods that can be used to perform concentration averaging of Low-Level Radioactive Waste (LLRW) for the purpose of determining its waste class for disposal. When the NRC issued the revised CA BTP, it noted that one issue, distinguishing contaminated materials from contaminated trash, may need further clarification. The NRC also stated that it would consider whether additional guidance, such as a Regulatory Issue Summary (RIS), would be warranted for distinguishing contaminated materials from contaminated trash.
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 December 22, 2015, to January 4, 2016. The last biweekly notice was published on January 5, 2016.
In the Matter of Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 1, 2, and 3, and James A. Fitzpatrick Nuclear Power Plant; Exelon Generation Company, LLC, Nine Mile Point Nuclear Station, Units 1 and 2, and R.E. Ginna Nuclear Power Plant; Pacific Gas and Electric Company, Diablo Canyon Power Plant, Units 1 and 2; and Southern California Edison Company, San Onofre Nuclear Generating Station, Units 2 and 3, including Independent Spent Fuel Storage Installations for All Facilities
The U.S. Nuclear Regulatory Commission (NRC) is authorizing the licensees to transfer, receive, possess, transport, import, and use certain firearms and large-capacity ammunition feeding devices not previously permitted to be owned or possessed under Commission authority, notwithstanding certain local, State, or Federal firearms laws, including regulations that prohibit such actions, as reflected in the confirmatory orders for the nuclear plant facilities listed above.
Entergy Nuclear Operations, Inc.; Grand Gulf Nuclear Station, Unit 1
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of Entergy Nuclear Operations, Inc. (Entergy, the licensee), to withdraw its application dated June 26, 2014, for a proposed amendment to Facility Operating License No. NPF-29, for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The proposed amendment would have revised GGNS Technical Specifications (TSs) Surveillance Requirements (SRs) for safety-related battery resistances in TS SRs 3.8.4.2 and 3.8.4.5 for batteries 1A3, 1B3, and 1C3.
In the Matter of Northern States Power Company, Minnesota
The U.S. Nuclear Regulatory Commission (NRC) and Northern States Power Company, Minnesota, doing business as Xcel Energy, engaged in mediation as part of the NRC's Alternative Dispute Resolution Program which resulted in a settlement agreement as reflected in the Confirmatory Order (CO) related to Xcel Energy. The purpose of the CO is to ensure that the licensee restores compliance with NRC regulations.
List of Approved Spent Fuel Storage Casks: Holtec International, HI-STORM Flood/Wind Multipurpose Storage System, Certificate of Compliance No. 1032, Amendment No. 0, Revision 1
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of April 25, 2016, for the direct final rule that was published in the Federal Register on September 28, 2015. This direct final rule amended the NRC's spent fuel storage regulations by revising the Holtec International (Holtec), HI-STORM (Holtec International Storage Module) Flood/Wind (FW) Multipurpose Canister Storage (MPC) Storage System listing within the ``List of approved spent fuel storage casks'' to add Amendment No. 0, Revision 1, to Certificate of Compliance (CoC) No. 1032. This revision corrects the CoC's expiration date (editorial change), clarifies heat load limits for helium backfill ranges, clarifies the wording for the Limiting Condition for Operation (LCO) on vent blockage, and revises the vacuum drying system heat load.
Determining Which Structures, Systems, Components and Functions are Important to Safety
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking (PRM) requesting that the NRC amend its ``Domestic licensing of production and utilization facilities'' regulations to define the term ``important to safety'' and provide a set of specific criteria for determining which structures, systems, components (SSCs), and functions are ``important to safety.'' The petition, dated July 20, 2015, was submitted by Kurt T. Schaefer (the petitioner) and was supplemented on August 31, 2015. The petition was docketed by the NRC on September 4, 2015, and was assigned Docket Number PRM-50-112. The NRC is examining the issues raised in this petition to determine whether it should be considered in rulemaking. The NRC is requesting public comments on this petition for rulemaking.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System; Amendment No. 9, Revision 1
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International (``Holtec,'' or ``the applicant'') HI-STORM 100 Cask System listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 9, Revision 1, to Certificate of Compliance (CoC) No. 1014. Amendment No. 9, Revision 1, changes cooling time limits for thimble plug devices (TPDs), removes certain testing requirements for the fabrication of Metamic HT neutron-absorbing structural material, and reduces certain minimum guaranteed values (MGV) used in bounding calculations for this material. Amendment No. 9, Revision 1, also changes fuel definitions to classify certain boiling water reactor (BWR) fuel within specified guidelines as undamaged fuel.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System; Amendment No. 9, Revision 1
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the Holtec International (Holtec or the applicant) HI-STORM 100 Cask System listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 9, Revision 1, to Certificate of Compliance (CoC) No. 1014. Amendment No. 9, Revision 1, changes cooling time limits for thimble plug devices, removes certain testing requirements for the fabrication of Metamic HT neutron-absorbing structural material, and reduces certain minimum guaranteed values used in bounding calculations for this material. Amendment No. 9, Revision 1, also changes fuel definitions to classify certain boiling water reactor fuel within specified guidelines as undamaged fuel.
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 December 8, 2015, to December 21, 2015. The last biweekly notice was published on December 22, 2015.
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 for Limerick Generating Station, Unit 1, and Browns Ferry Nuclear Plant, Unit 1. The NRC proposes to determine that the amendment requests involve no significant hazards consideration. In addition, each amendment request contains sensitive unclassified non-safeguards information (SUNSI).
Northwest Medical Isotopes, LLC
The U.S. Nuclear Regulatory Commission (NRC) has determined that the second and final part of the application for a construction permit, submitted by Northwest Medical Isotopes, LLC (NWMI) is acceptable for docketing. NWMI proposes to build a medical radioisotope production facility located in Columbia, Missouri.
Crystal River Nuclear Generating Plant, Unit 3; Consideration of Approval of Transfer of License and Conforming Amendment
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an application filed by Duke Energy Florida, Inc. (DEF) on July 28, 2015, as supplemented on September 22, 2015. The application seeks NRC approval of the direct transfer of Facility Operating License DPR-72 for Crystal River Nuclear Generating Plant, Unit 3, from Seminole Electric Cooperative, Inc., to DEF. The NRC is also considering amending the facility operating license for administrative purposes to reflect the proposed transfer.
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