Nuclear Regulatory Commission 2016 – Federal Register Recent Federal Regulation Documents
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Duke Energy Florida, Inc. Crystal River, Unit 3
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption from the requirement to maintain a specified level of onsite property damage insurance in response to a request from Duke Energy Florida, Inc. (DEF or the licensee) dated December 17, 2015. This exemption would permit the licensee to reduce its onsite property damage insurance from $1.06 billion to $50 million at the Crystal River Unit 3 Nuclear Generating Station (CR-3) based on the reduced risks and consequences of a nuclear incident at a decommissioning nuclear power reactor.
Information Collection: “Specific Domestic Licenses To Manufacture or Transfer Certain Items Containing 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 titled, ``Specific Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct Material.''
Information Collection: NRC Form 277, Request for Visit
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``NRC Form 277, Request for Visit.''
In the Matter of All Operating Reactor Licensees
The U.S. Nuclear Regulatory Commission (NRC) is giving notice that by petition dated February 19, 2016, Roy Mathew, Sheila Ray, Swagata Som, Gurcharan Singh Matharu, Tania Martinez Navedo, Thomas Koshy, and Kenneth Miller (the petitioners) have requested that the NRC take action with regard to all current operating nuclear power plants. The petitioners' requests are included in the SUPPLEMENTARY INFORMATION section of this document.
Integrated Action Plan To Modernize Digital Instrumentation and Controls Regulatory Infrastructure
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment its preliminary draft action plan, ``Integrated Action Plan to Modernize Digital Instrumentation and Controls Regulatory Infrastructure.'' This preliminary draft action plan outlines the strategy and implementation milestones the NRC staff has identified in order to modernize the NRC's digital instrumentation and controls (I&C) regulatory infrastructure.
Generic Aging Lessons Learned for Subsequent License Renewal Report and Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on supplemental guidance to draft NUREG-2191, ``Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report,'' Vol. I and II, and draft NUREG-2192, ``Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants'' (SRP-SLR). This supplemental guidance was developed subsequent to the release of draft NUREG-2191 and NUREG-2192 on December 23, 2015. Changes to the supplemental guidance will be incorporated into the final versions of NUREG-2191 and NUREG-2192.
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 March 1, 2016, to March 14, 2016. The last biweekly notice was published on March 15, 2016.
U.S. Army Installation Management Command, Multiple Locations
The U.S. Nuclear Regulatory Commission (NRC) has issued Amendment No. 1 to Source Materials License No. SUC-1593 to the U.S. Army, Installation Management Command (Army), for possession of Depleted Uranium (DU) from the Davy Crockett M101 spotting rounds at the following Army installations: Donnelly Training Area, Fort Wainwright, AK (Alaska); Fort Benning, GA (Georgia); Fort Bragg, NC (North Carolina); Fort Campbell, KY (Kentucky); Fort Carson, CO (Colorado); Fort Gordon, GA (Georgia); Fort Hood, TX (Texas); Fort Hunter Liggett, CA (California); Fort Jackson, SC (South Carolina); Fort Knox, KY (Kentucky); Fort Polk, LA (Louisiana); Fort Riley, KS (Kentucky); Fort Sill, OK (Oklahoma); Joint Base Lewis-McChord/Yakima Training Center, WA (Washington); Joint Base McGuire-Dix-Lakehurst, NJ (New Jersey); and Schofield Barracks/Pohakuloa Training Area, HI (Hawaii). This license amendment allows the Army to possess DU at the specified Army Installation sites where testing of Davy Crockett M101 spotting rounds occurred.
Department of Energy; Fort St. Vrain Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) reviewed an application by the Department of Energy (DOE) for an amendment to License No. SNM-2504 that was renewed in 2011. Under this license, DOE is authorized to receive, possess, store, and transfer spent nuclear fuel and associated radioactive materials at the Fort St. Vrain (FSV) independent spent fuel storage installation (ISFSI). The DOE requested approval to revise response times stated in the license's technical specifications that are associated with fuel storage container leak tests, and to make an editorial change to the technical specifications table of contents.
TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing
The U.S. Nuclear Regulatory Commission (NRC) is issuing Technical Specifications (TS) Task Force (TSTF) Traveler TSTF-545, Revision 3, ``TS Inservice Testing [(IST)] Program Removal & Clarify [Surveillance Requirement] SR Usage Rule Application to Section 5.5 Testing,'' for plant-specific adoption using the Consolidated Line Item Improvement Process (CLIIP).
Memorandum of Understanding Between the U.S. Nuclear Regulatory Commission and the U.S. Department of Homeland Security/Federal Emergency Management Agency
On December 7, 2015, the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Homeland Security (DHS)/Federal Emergency Management Agency (FEMA) entered into a Memorandum of Understanding (MOU) that establishes a framework of cooperation between them in radiological emergency response planning and preparedness matters. The MOU ensures that the agencies' mutual efforts will be directed toward more effective preparedness plans, and related response measures at and in the vicinity of utilization facilities.
Information Collection: NRC Form 136, “Security Termination Statement”
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, NRC Form 136, ``Security Termination Statement.''
Information Collection: Access Authorization
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Access Authorization.''
Revision of Fee Schedules; Fee Recovery for Fiscal Year 2016
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend the licensing, inspection, special project, and annual fees charged to its applicants and licensees and, for the first time, the NRC is proposing to recover its costs when it responds to third-party demands for information in litigation where the United States is not a party (``Touhy requests''). These proposed 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.
Fees Development and Communications
The U.S. Nuclear Regulatory Commission (NRC) is requesting information from the public on a number of issues associated with the development of the agency's fees. Specifically, the NRC would like stakeholder input regarding the general communications the NRC provides about its fees and the public's understanding of the NRC's fees. The information collected will be used by the NRC in developing ways to improve the transparency of its fees development and invoicing processes.
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 confirming the effective date of March 21, 2016, for the direct final rule that was published in the Federal Register on January 6, 2016. This direct final rule amended spent fuel storage regulations by revising the Holtec International 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 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.
License Amendment Application for Source Materials License Jefferson Proving Ground
The U.S. Nuclear Regulatory Commission (NRC) is announcing the withdrawal of a license amendment application from the U.S. Department of the Army (the licensee) for its Jefferson Proving Ground (JPG) site located in Madison, Indiana, to decommission the site under restricted release conditions as defined in the NRC's regulations.
Nuclear Innovation North America LLC; South Texas Project, Units 3 and 4
The U.S. Nuclear Regulatory Commission (NRC) has issued combined license numbers NPF-097 and NPF-098 to Nuclear Innovation North America LLC (NINA), STP Nuclear Operating Company, NINA Texas 3 LLC, NINA Texas 4 LLC, and the City of San Antonio, Texas, acting by and through the City Public Service Board (collectively, the Licensees) for South Texas Project, Units 3 and 4 (STP Units 3 and 4). In addition, the NRC has prepared a Summary Record of Decision (ROD) that supports the NRC's decision to issue combined license numbers NPF-097 and NPF-098.
La Crosse Boiling Water Reactor, Dairyland Power Cooperative, 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 the Dairyland Power Cooperative (DPC) on October 8, 2015. The application seeks NRC approval of the direct transfer of Facility Operating License No. DPR- 45 for the La Crosse Boiling Water Reactor (LACBWR), from the current holder, DPC, to LaCrosseSolutions, LLC (LS) a wholly owned subsidiary of EnergySolutions (ES). The NRC is also considering amending the facility operating license for administrative purposes to reflect the proposed transfer.
Exelon Generation Company, LLC; Dresden Nuclear Power Station, Units 1, 2, and 3; Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption from certain requirements regarding the storage of a thoria rod canister in response to a request submitted by Exelon Generation Company, LLC (EGC) on January 29, 2015, for its general license to operate an independent spent fuel storage installation (ISFSI) at the Dresden Nuclear Power Station (DNPS). This exemption would permit EGC to load and store the DNPS Unit 1 thoria rod canister containing 18 DNPS Unit 1 thoria rods in a Holtec International, Inc., HI-STORM 100 multi-purpose canister (MPC)-68M using Certificate of Compliance (CoC) No. 1014, Amendment No. 8, Rev. 1.\1\
Advisory Committee on the Medical Uses of Isotopes; Renewal
The U.S. Nuclear Regulatory Commission (NRC) has determined that the renewal of the Charter for the Advisory Committee on the Medical Uses of Isotopes for the 2 year period commencing on March 10, 2016, is in the public interest, in connection with duties imposed on the Commission by law. This action is being taken in accordance with the Federal Advisory Committee Act, after consultation with the Committee Management Secretariat, General Services Administration.
Criteria and Design Features for Inspection of Water-Control Structures Associated With Nuclear Power Plants; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register (FR) on February 18, 2016, regarding the issuance of Revision 2 of Regulatory Guide (RG) 1.127, ``Criteria and Design Features for Inspection of Water-Control Structures Associated with Nuclear Power Plants.'' This action is necessary to correct an ADAMS accession number.
License Amendment Requests for Changes to Emergency Response Organization Staffing and Augmentation
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) to inform certain nuclear power reactor licensees of the use of guidance documents to support license amendment requests (LAR) to change augmenting emergency response organization (ERO) staffing and arrival times. The RIS will clarify the scope and level of detail that should be provided to facilitate NRC review of the LARs.
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 February 13, 2016, to February 29, 2016. The last biweekly notice was published on March 1, 2016.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System; Certificate of Compliance No. 1014, Amendment No. 10
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International (Holtec or applicant) 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. Amendment No. 10 adds new fuel classes to the contents approved for the loading of 16x16-pin fuel assemblies into a HI-STORM 100 Cask System; allows a minor increase in manganese in an alloy material for the system's overpack and transfer cask; clarifies the minimum water displacement required of a dummy fuel rod (i.e., a rod not filled with uranium pellets); and clarifies the design pressures needed for normal operation of forced helium drying systems. Additionally, Amendment No. 10 revises Condition No. 9 of CoC No. 1014 to provide clearer direction on the measurement of air velocity and modeling of heat distribution through the storage system. Each of these changes is described in Section IV, ``Discussion of Changes,'' in the SUPPLEMENTARY INFORMATION section of this document.
List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System; Certificate of Compliance No. 1014, Amendment No. 10
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the Holtec International (Holtec or applicant) 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. Amendment No. 10 adds new fuel classes to the contents approved for the loading of 16X16-pin fuel assemblies into a HI-STORM 100 Cask System; allows a minor increase in manganese in an alloy material for the system's overpack and transfer cask; clarifies the minimum water displacement required of a dummy fuel rod (i.e., a rod not filled with uranium pellets); and clarifies the design pressures needed for normal operation of forced helium drying systems. Additionally, Amendment No. 10 revises Condition No. 9 of CoC No. 1014 to provide clearer direction on the measurement of air velocity and modeling of heat distribution through the storage system.
Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material
On March 19, 2013, the U.S. Nuclear Regulatory Commission (NRC) published a final rule that amended its regulations to establish security requirements for the use and transport of category 1 and category 2 quantities of radioactive material. Specifically, the final rule provided reasonable assurance of preventing the theft or diversion of category 1 and category 2 quantities of radioactive material, and included security requirements for the transportation of irradiated reactor fuel that weighs 100 grams or less in net weight of irradiated fuel. In December 2014, the Committees on Appropriations of the House of Representatives and the Senate directed the NRC to evaluate the effectiveness of the new regulations and determine whether the requirements are adequate to protect ``high-risk radiological material.'' In response to this mandate, the NRC is implementing a retrospective program review to provide an objective assessment of the new requirements and associated implementation guidance. This action seeks information that will be used in developing a report to Congress. The NRC plans to hold a series of public meetings to facilitate public participation. These meetings will consist of a public meeting and a series of webinar teleconferences, and the staff will publicly notice the date and times of these meetings. The staff is planning to conduct these meetings in March 2016.
Virgil C. Summer Nuclear Station, Units 2 and 3
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Combined Licenses (COLs), NPF-93 and NPF- 94, issued to South Carolina Electric and Gas (SCE&G) and South Carolina Public Service Authority (Santee Cooper) (the licensee), for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3 located in Fairfield County, South Carolina. The proposed amendment to COL Appendix C information, and supporting Tier 2 information, requires a corresponding plant-specific Tier 1 departure and exemption.
Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption for Facility Operating License Nos. NPF-9 and NPF-17, issued to Duke Energy Carolinas, LLC (Duke, the licensee) for operation of McGuire Nuclear Station, Units 1 and 2 (McGuire), located near Huntersville, North Carolina. The licensee requested an exemption from certain physical inventory requirements because the inventory items are no longer in service and are not readily accessible. The NRC prepared an environmental assessment (EA) documenting its finding. The NRC concluded that the proposed actions will have no significant environmental impact. Accordingly, the NRC staff is issuing its final EA and a final finding of no significant impact (FONSI) associated with the proposed exemption.
Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Control Rod Drive Mechanism Motor Generator Set Field Relay Change
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. 38 to Combined Licenses (COLs), 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., 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. 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.
Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Reclassification of Tier 2* Information on Fire Area Figures
The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption from certain Tier 2* information in the generic design control document (DCD) and issuing License Amendment No. 40 to Combined Licenses (COL), NPF-93 and NPF-94. The COLs were issued to South Carolina Electric and Gas (SCE&G) and South Carolina Public Service Authority (Santee Cooper) (the licensee), for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3 located in Fairfield County, South Carolina. The granting of the exemption allows the changes to Tier 2* information 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.
Power Resources, Inc.
The U.S. Nuclear Regulatory Commission (NRC) is issuing a temporary exemption from certain NRC financial assurance requirements to Power Resources, Inc., doing business as Cameco Resources (Cameco), in response to its annual financial assurance updates for its Smith Ranch-Highland In-Situ Recovery (ISR) project and the associated remote satellite facilities at Ruth and Gas Hills. Issuance of this temporary exemption will not remove the requirement for Cameco to provide adequate financial assurance through an approved mechanism but will allow the NRC staff to further evaluate whether the State of Wyoming's separate account provision for financial assurance instruments Cameco holds is consistent with the NRC's requirement for a standby trust agreement.
Strata Energy, Inc, Kendrick Expansion Area In Situ Uranium Recovery Project
The U.S. Nuclear Regulatory Commission (NRC) received a license amendment application for License SUA-1601, by letters dated March 20, 2015, and April 24, 2015, from Strata Energy, Inc. (Strata). The amendment application requested authorization to expand its Ross In Situ Uranium Recovery (ISR) Project (Ross) to include the Kendrick expansion area (Kendrick). The requested amendment would allow Strata to construct and operate additional uranium recovery wells at Kendrick. Kendrick covers approximately 3,186 hectares (7,784 acres) adjacent to Ross. Ross is located in Crook County, Wyoming, 43 kilometers (27 miles) northeast of Gillette, Wyoming and 46 kilometers (29 miles) northwest of Sundance, Wyoming. A notice of license amendment request and opportunity to request a hearing was published in the Federal Register on February 29, 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 Turkey Point Nuclear Generating, Unit Nos. 3 and 4. 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).
Environmental Qualification of Electrical Equipment
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM) submitted by the Natural Resources Defense Council, Inc. (NRDC), and Mr. Paul M. Blanch (collectively, the petitioners) on June 18, 2012. The petitioners requested that the NRC amend its regulations to clearly and unequivocally require the environmental qualification of all safety-related cables, wires, splices, connections and other ancillary electrical equipment that may be subjected to submergence and/or moisture intrusion during normal operating conditions, severe weather, seasonal flooding, and seismic events, and post-accident conditions, both inside and outside of a reactor's containment building. The NRC is denying this petition because the current regulations already address environmental qualification in both mild and design basis event conditions of electrical equipment located both inside and outside of the containment building that is important to safety, and the petition does not provide significant new or previously unconsidered information sufficient to justify rulemaking.
SHINE Medical Technologies, Inc.; SHINE Medical Isotope Facility
The U.S. Nuclear Regulatory Commission (NRC) is providing notice of the issuance of Construction Permit CPMIF-001 to SHINE Medical Technologies, Inc. (SHINE) and record of decision, located in Janesville, Wisconsin.
Department of the Air Force; Hill Air Force Base, Utah
The Nuclear Regulatory Commission (NRC) is considering an amendment to Master Materials License 42-23539-01AF, Docket No. 030- 28641, issued to the Department of the Air Force (the licensee). This amendment will allow the licensee to decommission a former magnesium- thorium alloy disposal trench at Hill Air Force Base, Utah, in accordance with instructions provided in an NRC-approved decommissioning plan. The NRC conducted an environmental impact assessment in support of this licensing action. Based on the results of this assessment, the NRC concluded that a Finding of No Significant Impact (FONSI) is appropriate.
Duke Energy Progress; Combined License Application for Shearon Harris Nuclear Power Plants Units 2 and 3
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to an August 12, 2015, letter from Duke Energy Progress (DEP), which requested an exemption from certain regulatory requirements that requires DEP to submit an update to the Final Safety Analysis Report (FSAR) included in their combined license (COL) application by December 31, 2015. The NRC staff reviewed this request and determined that it is appropriate to grant the exemption, but stipulated that the update to the FSAR must be submitted prior to, or coincident with the resumption of the COL application review or by December 31, 2016, whichever comes first.
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