Nuclear Regulatory Commission October 2016 – Federal Register Recent Federal Regulation Documents
Results 1 - 47 of 47
NuScale Power, LLC, Design-Specific Review Standard and Scope and Safety Review Matrix
The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued the NuScale Power, LLC, (NuScale), Design-Specific Review Standard (DSRS) Sections, and is issuing the final NuScale DSRS Scope and Safety Review Matrix, for NuScale Design Certification (DC), Combined License (COL), and Early Site Permit (ESP) reviews. The NRC staff is also issuing the DSRS public comment resolution matrices, which address the comments received on the draft DSRS. The NuScale DSRS provides guidance to the NRC staff for performing safety reviews for those specific areas where existing NUREG-0800, ``Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' sections do not address the unique features of the NuScale design.
Duke Energy Florida, LLC; Levy Nuclear Plant Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is issuing a notice of intent to enter into a modified indemnity agreement with Duke Energy Florida, LLC, (DEF) to operate Levy Nuclear Plant Units 1 and 2 (LNP 1 and 2). The NRC is required to publish notice of its intent to enter into an indemnity agreement which contains provisions different from the general form found in the NRC's regulations. A modification to the general form is necessary to accommodate the unique timing provisions of a combined license (COL).
Information Collections: DOE/NRC Form 740M, “Concise Note;” DOE/NRC Form 741, “Nuclear Material Transaction Report;” DOE/NRC Form 742, “Material Balance Report;” and DOE/NRC Form 742C, “Physical Inventory Listing”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for four existing collections of information. The information collections are entitled, DOE/NRC Form 740M, ``Concise Note;'' DOE/NRC Form 741, ``Nuclear Material Transaction Report;'' DOE/NRC Form 742, ``Material Balance Report;'' and DOE/NRC Form 742C, ``Physical Inventory Listing.''
Purdue University Reactor
The U.S. Nuclear Regulatory Commission (NRC) is considering renewal of Facility Operating License No. R-87, held by Purdue University (the applicant), for the continued operation of the Purdue University Reactor (PUR-1), located in West Lafayette, Tippecanoe County, Indiana for an additional 20 years. In connection with the renewed license, the applicant is also seeking a power increase from 1 kilowatt thermal (kW(t)) to a licensed power level of 12 kW(t). The NRC is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) associated with the renewal of the license.
Entergy Nuclear Operations, Inc.; FitzPatrick Nuclear Power Plant
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a January 15, 2016, request from Entergy Nuclear Operations, Inc. (Entergy or the licensee), from certain regulatory requirements. The exemption would permit a certified fuel handler to approve the emergency suspension of security measures for James A. Fitzpatrick Nuclear Power Plant (JAF) during certain emergency conditions or during severe weather. The exemption will be effective after JAF has submitted the certifications that it has permanently ceased power operation and has permanently removed fuel from the reactor vessel.
Exelon Generation Company, LLC.; LaSalle County Station, Units 1 and 2; License Renewal
The U.S. Nuclear Regulatory Commission (NRC) has issued renewed facility operating license Nos. NPF-11 and NPF-18 to Exelon Generation Company, LLC (Exelon or the licensee), the operator of LaSalle County Station, Units 1 and 2. Renewed facility operating license Nos. NPF-11 and NPF-18 authorize the operation of LaSalle County Station, Units 1 and 2 by the licensee at reactor core power levels not in excess of 3546 megawatts thermal in accordance with the provisions of the renewed licenses and technical specifications until April 17, 2042 and December 16, 2043, respectively. The NRC prepared a safety evaluation report, a final supplemental environmental impact statement (FSEIS), and a record of decision (ROD) that support its decision to issue renewed facility operating license Nos. NPF-11 and NPF-18.
Southern Nuclear Operating Company, Inc.; Joseph M. Farley Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of the Southern Nuclear Operating Company, Inc. (SNCthe licensee) to withdraw its license amendment application dated November 24, 2014, as supplemented on September 28, 2015; March 3, 2016; and July 25, 2016, for proposed amendments to Renewed Facility Operating License Nos. NPF 2 and NPF 8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively, located in Houston County, Alabama. The application contained 24 requests. Twenty-three of those requests were addressed in NRC letter dated August 3, 2016. The amendments adopted previously approved Technical Specifications Task Force Travelers and made two changes not associated with Travelers. A request to incorporate TSTF-312-A, Revision 1, ``Administratively Control Containment Penetrations,'' has been withdrawn by SNC in a letter dated October 17, 2016.
Southern Nuclear Operating Company, Vogtle Electric Generating Plant, Units 3 and 4; Passive Core Cooling System (PXS) Design Changes To Address Potential Gas Intrusion
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 No. 55 to Combined Licenses (COL), NPF-91 and NPF-92. 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, Authority of Georgia, 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.
Independent Assessment of Nuclear Material Control and Accounting Systems
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.51, ``Independent Assessment of Nuclear Material Control and Accounting Systems.'' Revision 1 is based on experience gained since RG 5.51 was initially published in June 1975, and reflects revisions to the NRC's material control & accounting (MC&A) regulations that have been made since 1975. Updates include use of the term ``independent assessment'' to replace ``management review,'' and use of the term ``inventory difference'' to replace ``material unaccounted for.''
In the Matter of Tetra Tech EC, Inc.
The U.S. Nuclear Regulatory Commission (NRC) is issuing a Confirmatory Order (CO) to Tetra Tech EC, Inc. (TtEC) to memorialize the agreements reached during an alternative dispute resolution mediation session held on September 7, 2016. This Order will resolve the issue that was identified during an NRC Investigation of TtEC employees at Hunters Point Naval Shipyard site in San Francisco, California. The Confirmatory Order is effective upon issuance.
Performance Review Boards for Senior Executive Service
The Nuclear Regulatory Commission (NRC) has announced appointments to the NRC Performance Review Board (PRB) responsible for making recommendations on performance appraisal ratings and performance awards for NRC Senior Executives and Senior Level System employees and appointments to the NRC PRB Panel responsible for making recommendations to the appointing and awarding authorities for NRC PRB members.
United States Department of the Interior; United States Geological Survey TRIGA Research Reactor
The U.S. Nuclear Regulatory Commission (NRC) issued a renewal of Facility Operating License No. R-113, held by the United States Geological Survey (USGS or the licensee), for the continued operation of its USGS Training, Research, Isotope Production, General Atomics (TRIGA) research reactor (GSTR or the reactor) at a steady-state power level of 1.0 megawatt (MW) and a pulse power level as provided in the licensee's Technical Specifications, for an additional 20 years. The GSTR facility is located on the property of the Denver Federal Center in Lakewood, Colorado.
Rhode Island Atomic Energy Commission; Rhode Island Nuclear Science Center Reactor
The U.S. Nuclear Regulatory Commission (NRC) is considering an application for the renewal of Facility Operating License No. R-95, which currently authorizes the Rhode Island Atomic Energy Commission (RIAEC or the licensee) to operate the Rhode Island Nuclear Science Center (RINSC) reactor at a maximum steady-state thermal power of 2 megawatts (MW). The RINSC reactor is a plate type fueled research reactor located at the University of Rhode Island Narragansett Bay Campus, in Narragansett, Rhode Island. If approved, the renewed license would authorize the licensee to operate the RINSC reactor up to a steady-state thermal power of 2 MW for an additional 20 years from the date of issuance of the renewed license. Because the license renewal application contains sensitive unclassified non-safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Exelon Generation Company, LLC; Braidwood Station, Unit 2
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. NPF- 77, issued to Exelon Generation Company, LLC, for operation of Braidwood Station, Unit 2, located in Will County, Illinois. The proposed amendment would allow a one-time extension from 72 hours to 200 hours of the technical specification (TS) completion time associated with the 2A service water (SX) pump in support of maintenance activities.
LaCrosseSolutions, LLC; La Crosse Boiling Water Reactor Partial Site Release
On June 27, 2016, the U.S. Nuclear Regulatory Commission (NRC) received from LaCrosseSolutions, LLC (LS) a request for approval to remove portions of the site from the operating license for the La Crosse Boiling Water Reactor. Specifically, LS intends to remove and release five radiologically non-impacted portions of the site from its license. The partial site release request was submitted concurrently with the La Crosse License Termination Plan and supports ongoing decommissioning activities at the site. The NRC is requesting public comments on LS's partial site release request and the La Crosse License Termination Plan.
Conduct of Operations
The U.S. Nuclear Regulatory Commission (NRC) is issuing final revisions to Section 13.6.4, ``Access AuthorizationOperational Program;'' Section 13.7, ``Fitness-for-Duty;'' Section 13.7.1, ``Fitness-for-DutyOperational Program;'' Section 13.7.2, ``Fitness for DutyConstruction;'' and Section 13.6.3, ``Physical Security Operational ProgramEarly Site Permits and Reactor Siting Criteria;'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition.''
In the Matter of Power Resources, Inc.
The U.S. Nuclear Regulatory Commission (NRC) is issuing a confirmatory order to Power Resources, Inc., confirming agreements reached in an alternative dispute resolution mediation session held on September 22, 2016. As part of the agreement, Power Resources, Inc., will conduct annual meetings among key management, radiation safety officer, facility managers, and other appropriate technical personnel to provide assurance that management understands the requirements of a radiation protection program are being met; will provide training which will emphasize the importance of complete and accurate information for all required records, correspondence, and communications with the NRC and its staff; and will have a qualified member of the heath physics staff available at any of its facilities when equipment is being released from a radiologically-controlled are to an unrestricted area.
Site Characteristics and Site Parameters
The U.S. Nuclear Regulatory Commission (NRC) is issuing a final revision to Section 2.0, ``Site Characteristics and Site Parameters'' of NUREG-0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition.''
In the Matter of AREVA Enrichment Services, LLC, AREVA, Inc.; Order Approving Change of Control of Licenses and Conforming Amendments
The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order approving a request, submitted by AREVA Inc., seeking the NRC's consent to the following license transfers: (1) The indirect transfer of control of special nuclear material (SNM) License SNM-2015, regarding the Eagle Rock Enrichment Facility, that authorizes the future construction and operation of this uranium enrichment facility in Bonneville County, Idaho, (2) the direct transfer of control of source material License SUA-672, regarding the former Lucky Mc uranium mill, and its existing tailings site, in Fremont County, Wyoming, and (3) the direct transfer of control of Export Licenses XSNM3643, XSNM3722, and XSOU8780. In addition, AREVA Inc. requested approval of conforming license amendments to reflect the new names of AREVA corporate entities associated with the license transfers due to the reorganization of the AREVA family of companies. AREVA Inc. also requested NRC confirmation that the proposed reorganization would not involve any transfer of control of Construction Authorization (CA) Number CAMOX-001, for the MOX Fuel Fabrication Facility that is being constructed on a site near Aiken, South Carolina.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System; Certificate of Compliance No. 1014, Amendment No. 10
On May 31, 2016, the U.S. Nuclear Regulatory Commission (NRC) confirmed the effective date of May 31, 2016, for the direct final rule that was published in the Federal Register on March 14, 2016. The direct final rule amended the NRC's spent fuel storage regulations by revising the Holtec International (Holtec) HI-STORM 100 Cask System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 10 to Certificate of Compliance (CoC) No. 1014. The NRC confirmed the effective date because it determined that none of the comments submitted on the direct final rule met any of the criteria for a significant adverse comment. The purpose of this document is to provide responses to the comments received on the direct final rule.
In the Matter of Southern Nuclear Operating Co., Inc.; Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is issuing a confirmatory order (Order) to revise the Edwin I. Hatch Nuclear Plant Unit Nos. 1 and 2 (Hatch) National Fire Protection Association (NFPA) 805 License Amendment Request submittal date of October 4, 2016 to April 4, 2018. This new submittal date extends enforcement discretion until April 4, 2018, and supports the Southern Nuclear Operating Company, Inc. (the licensee) continued progress in activities related to the transition to NFPA 805.
Tennessee Valley Authority, Sequoyah Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of Tennessee Valley Authority (the licensee) to withdraw its application dated July 3, 2013, for a proposed amendment to DPR-77 and DPR-79. The proposed amendment would have revised Units 1 and 2 Technical Specification \3/4\.6.5, ``Ice Condenser.''
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 September 13, 2016 to September 26, 2016. The last biweekly notice was published on September 27, 2016.
List of Approved Spent Fuel Storage Casks: NAC International MAGNASTOR® Cask System; Certificate of Compliance No. 1031, Amendment No. 6
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International (NAC), MAGNASTOR[supreg] Cask System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 6 to Certificate of Compliance (CoC) No. 1031. Amendment No. 6 revises NAC-MAGNASTOR technical specifications (TSs) to align with the NAC Multi-Purpose Canister (MPC) and NAC Universal MPC System (UMS) TSs. The CoC No. 1031 TSs require that a program be established and maintained for loading, unloading, and preparing fuel for storage without any indication of duration for the program. Amendment No. 6 limits maintenance of this program until all spent fuel is removed from the spent fuel pool and transport operations are completed. Related training and radiation protection program requirements are modified accordingly. Additionally, Amendment No. 6 incorporates the change to Limiting Condition for Operation (LCO) 3.1.1 previously approved by the NRC in CoC No. 1031 Amendment No. 4.
List of Approved Spent Fuel Storage Casks: NAC International MAGNASTOR® Cask System; Certificate of Compliance No. 1031, Amendment No. 6
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the NAC International (NAC), MAGNASTOR[supreg] Cask System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 6 to Certificate of Compliance (CoC) No. 1031. Amendment No. 6 revises NAC-MAGNASTOR technical specifications (TSs) to align with the NAC Multi-Purpose Canister (MPC) and NAC Universal MPC System TSs. The CoC No. 1031 TSs require that a program be established and maintained for loading, unloading, and preparing fuel for storage without any indication of duration for the program. Amendment No. 6 limits maintenance of this program until all spent fuel is removed from the spent fuel pool and transport operations are completed. Related training and radiation protection program requirements are modified accordingly. Additionally, Amendment No. 6 incorporates the change to Limiting Condition for Operation 3.1.1 previously approved by the NRC in CoC No. 1031 Amendment No. 4.
Strata Energy, Inc.; Ross Uranium In-Situ Recovery Facility; Source and Byproduct Materials License
The U.S. Nuclear Regulatory Commission (NRC) has issued an updated Record of Decision (ROD) related to the license for Strata Energy, Inc. (Strata), Ross Uranium In-Situ Recovery (ISR) Facility in Crook County, Wyoming. Strata's request for a source and byproduct materials license for the Ross ISR facility was contested through the NRC's adjudicatory process. On June 29, 2016, the Commission denied a petition for review of the Atomic Safety and Licensing Board's (ASLB) decision. The ROD has been updated to account for the ASLB's decision and the Commission's ruling.
Vogtle Electric Generating Plant, Units 3 and 4
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests, and analyses have been successfully completed, and that the specified acceptance criteria are met for multiple inspections, tests, analyses, and acceptance criteria (ITAAC) for the Vogtle Electric Generating Plant (VEGP), Units 3 and 4.
Risk-Informed Changes to Loss-of-Coolant Accident Technical Requirements
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing a rulemaking activity titled, ``Risk-Informed Changes to Loss-Of- Coolant Accident Technical Requirements.'' The purpose of this action is to inform members of the public of the discontinuation of this rulemaking and to provide a brief discussion of the NRC's decision to discontinue it. This rulemaking activity will no longer be reported in the NRC's portion of the Unified Agenda of Regulatory and Deregulatory Actions (the Unified Agenda).
Processing Fitness-for-Duty Drug and Alcohol Cases
The U.S. Nuclear Regulatory Commission (NRC) is requesting public comments on proposed revisions to its Enforcement Policy (the Policy). The NRC is proposing to revise Section 4.1, ``Considerations in Determining Enforcement Actions Involving Individuals,'' of the Policy to indicate that the NRC typically will not consider Fitness- for-Duty (FFD) Drug and Alcohol (D&A) related violations for enforcement unless the licensee's FFD program has apparent deficiencies.
General Use of Locks in the Protection and Control of: Facilities, Radioactive Materials, Classified Information, Classified Matter, and Safeguards Information
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.12, ``General Use of Locks in Protection and Control of: Facilities Radioactive Materials, Classified Information, Classified Matter, and Safeguards Information.'' This RG describes methods and procedures that the staff of the NRC considers acceptable for the selection, use, and control of locking devices in the protection of areas, facilities, certain radioactive materials, and specific types of information (e.g. classified matter, National Security Information (NSI), Restricted Data (RD), Formerly Restricted Data (FRD), Safeguards Information (SGI)).
Susquehanna Nuclear, LLC; Susquehanna Steam Electric Station, Units 1 and 2; Consideration of Indirect License Transfer
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an application filed by Susquehanna Nuclear, LLC (Susquehanna Nuclear), on June 29, 2016. The application seeks NRC approval of the indirect transfer of Susquehanna Nuclear's interests in Renewed Facility Operating License Nos. NPF-14 and NPF-22 for Susquehanna Steam Electric Station, Units 1 and 2 (SSES), respectively, as well as the general license for the SSES Independent Spent Fuel Storage Installation (ISFSI), from the current parent holder, Talen Energy Corporation (Talen), to Riverstone Holdings, LLC (Riverstone). Because the application contains sensitive unclassified non-safeguards information (SUNSI) an order imposes procedures to obtain access to SUNSI for contention preparation.
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 four amendment requests. The amendment requests are for Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Columbia Generating Station; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2; and Virgil C. Summer Nuclear Station, 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.
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