Nuclear Regulatory Commission February 2017 – Federal Register Recent Federal Regulation Documents
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Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 5.18, ``Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control.'' This RG is being withdrawn because the term ``limit of error'' is no longer used in the material control and accounting (MC&A) requirements in NRC's regulations, and therefore the RG 5.18 guidance is no longer needed. The MC&A requirements now include the term ``standard error'' in place of the term ``limit of error.'' The ``standard error'' term is used in evaluating the significance of an inventory difference (ID). The NRC has issued guidance separately for the term ``standard error.''
Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 5 to Regulatory Guide (RG) 1.26, ``Quality Group Classifications and Standards for Water-, Steam-, and Radioactive- Waste-Containing Components of Nuclear Power Plants.'' This guidance has been revised to update references to related NRC's guidance, to incorporate lessons learned from recent NRC reviews and regulatory activities, and to align the format and content of the guide with the current program guidance for RGs which was developed since Revision 4 of RG 1.26 was issued.
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 31, 2017 to February 13, 2017. The last biweekly notice was published on February 14, 2017.
AUC, LLC., Reno Creek Uranium In-Situ Recovery Project
The U.S. Nuclear Regulatory Commission (NRC) has issued a license to AUC, LLC (AUC) for its Reno Creek Uranium In-Situ Recovery (ISR) Facility in Campbell County, Wyoming. Under conditions listed in the license, the Source and Byproduct Materials License SUA-1602 authorizes AUC to operate its facilities as proposed in its license application, as amended, and to possess uranium source and byproduct material at the Reno Creek ISR Facility. In addition, the NRC has published a record of decision (ROD) that supports the NRC's decision to approve AUC's license application for the Reno Creek ISR Facility and to issue the license.
Emergency Planning For Research and Test Reactors and Other Non-Power Production and Utilization Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-2004, ``Emergency Planning for Research and Test Reactors and Other Non-Power Production and Utilization Facilities.'' This DG is proposed Revision 2 of Regulatory Guide (RG) 2.6, ``Emergency Planning for Research and Test Reactors.'' The NRC proposes to revise the RG by updating it to approve the use of the most current version of the American National Standards Institute (ANSI)/American Nuclear Society (ANS) standard ANSI/ANS- 15.16-2015, ``Emergency Planning for Research Reactors.'' The proposed revision provides licensees and applicants with a method that the NRC staff considers acceptable for use in complying with the regulations on the content of emergency plans for research and test reactors and other non-power production and utilization facilities.
Physical Inventories and Material Balances at Fuel Cycle Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG- 5056, ``Physical Inventories and Material Balances at Fuel Cycle Facilities.'' This new regulatory guide (RG) would provide implementing guidance for material control and accounting (MC&A) requirements in NRC regulations related to the performance, evaluation, and reporting of physical inventories of special nuclear material, and material balances at fuel cycle facilities. Guidance on these requirements was previously provided in RG 5.13, ``Conduct of Nuclear Material Physical Inventories,'' and RG 5.33, ``Statistical Evaluation of Material Unaccounted For,'' that were issued in 1973 and 1974, respectively. Both RG 5.13 and RG 5.33 would be withdrawn concurrent with issuance of DG-5056 in final form.
Department of Energy; Fort St. Vrain Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has docketed a license amendment application from the Department of Energy (DOE or the licensee) for amendment of Materials License No. SNM-2504, for the Fort St. Vrain independent spent fuel storage installation located in Platteville, Colorado. If granted, the amendment would update the licensee delegation of authority in the license, the technical specifications, and the final safety analysis report. These documents currently delegate authority under the license to the Manager, DOE Idaho Operations Office. The amendment would replace that reference with the Deputy Manager, Idaho Cleanup Project in each of the documents.
Department of Energy; Idaho Spent Fuel Facility Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has docketed a license amendment application from the Department of Energy (DOE or the licensee) for amendment of Materials License No. SNM-2512, for the Idaho Spent Fuel Facility independent spent fuel storage installation located at the Idaho National Engineering Laboratory in Butte County, Idaho. If granted, the amendment would update the licensee delegation of authority in the license, the technical specifications, and the final safety analysis report. These documents currently delegate authority under the license to the Manager, DOE Idaho Operations Office. The amendment would replace that reference with the Deputy Manager, Idaho Cleanup Project in each of the documents.
Clarification of Licensee Actions in Enforcement Guidance Memorandum EGM 15-002, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance, Revision 1
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG), Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum (EGM) 15-002, ``Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance,'' Revision 1. The NRC staff is publishing this revised ISG for public comment. The revisions provide clarifying guidance to facilitate staff understanding of expectations for consistent oversight associated with implementing enforcement discretion for tornado missile protection noncompliance(s), as discussed in EGM 15-002, Revision 1.
In the Matter of Casey Pooler
The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order prohibiting Mr. Casey Pooler from involvement in NRC-licensed activities for a period of 3 years. The Order also requires Mr. Pooler to notify the NRC of any current involvement in NRC-licensed activities. Additionally, Casey Pooler is required to notify the NRC of his first employment in NRC-licensed activities for a period of one year following the 3-year prohibition period.
NuScale Power, LLC
The U.S. Nuclear Regulatory Commission (NRC) received a design certification application (DCA) from NuScale Power, LLC (NuScale), on January 6, 2017, for a Small Modular Reactor (SMR). The DCA package included a transmittal letter, dated December 31, 2016, which indicated the application would be supplemented with one topical report and four technical reports by January 10, 2017. By January 12, 2017, NuScale provided updated files that allowed for the successful completion of the NRC's electronic processing of the DCA package.
Department of Energy; Three Mile Island 2 Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has docketed a license amendment application from the Department of Energy (DOE or the licensee) for amendment of Materials License No. SNM-2508, for the Three Mile Island 2 (TMI-2) independent spent fuel storage installation located at the Idaho National Laboratory in Butte County, Idaho. If granted, the amendment would update the licensee delegation of authority in the license, the technical specifications, and the final safety analysis report. These documents currently delegate authority under the license to the Manager, DOE Idaho Operations Office. The amendment would replace that reference with the Deputy Manager, Idaho Cleanup Project in each of the documents.
Uninterruptible Monitoring of Coolant and Fuel in Reactors and Spent Fuel Pools
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), dated September 10, 2015, submitted by Dr. Alexander DeVolpi (the petitioner). The petition was docketed by the NRC on September 21, 2015, and was assigned Docket No. PRM-50-113. The petitioner requested that the NRC amend its regulations to require ``installation of ex-vessel instrumentation for uninterruptible monitoring of coolant and fuel in reactors and spent-fuel pools.'' The NRC is denying the petition because the Commission finds that the issues raised by the petitioner have been addressed by actions taken by the NRC in response to the Fukushima Dai-ichi nuclear accident.
Guidance for the Application of the Theft and Diversion Design-Basis Threat for Category I Fuel Cycle Facilities
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.70, ``Guidance for the Application of the Theft and Diversion Design-Basis Threat for Category I Fuel Cycle Facilities.'' This regulatory guide provides methods that the NRC staff finds acceptable for an applicant or licensee to meet the requirements of the underlying NRC's regulations. Revision 1 of RG 5.70 contains clarifying information regarding technical matters and rule language, administrative changes, and lessons learned from inspection activities, operating experience, and current threat data.
Southern Nuclear Company, Inc.; Vogtle Electric Generating Plant, Units 1, 2, 3 and 4
The U.S. Nuclear Regulatory Commission (NRC) is making a finding of no significant impact for a proposed issuance of amendments to Renewed Facility Operating License NPF-68; Renewed Facility Operating License NPF-81; Facility Combined License NPF-91; and Facility Combined License NPF-92, held by Southern Nuclear Company, Inc. (SNC, the licensee) for the operation of Vogtle Electric Generating Plant (VEGP), Units 1, 2, 3, and 4, respectively, located in Burke County, Georgia. The proposed amendments would allow for the adoption of a common (fleet-wide) SNC Standard Emergency Plan (SEP), with site-specific annexes.
Southern Nuclear Company, Inc.; Joseph M. Farley Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is making a finding of no significant impact for a proposed issuance of amendments to Renewed Facility Operating License Nos. NPF-2 and NPF-8, held by Southern Nuclear Company, Inc. (SNC, the licensee) for the operation of Joseph M. Farley Nuclear Plant (Farley), Unit 1 and Unit 2, respectively, located in Houston County, Alabama. The proposed amendments would allow for the adoption of a common (fleet-wide) SNC Standard Emergency Plan (SEP), with site-specific annexes.
Southern Nuclear Company, Inc.; Edwin I. Hatch Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is making a finding of no significant impact for a proposed issuance of an amendment to Renewed Facility Operating License Nos. DPR-57 and NPF-5, held by Southern Nuclear Company, Inc. (SNC, the licensee) for the operation of Edwin I. Hatch Nuclear Plant (Hatch), Unit 1 and Unit 2, respectively, located in Appling County, Georgia. The proposed amendments would allow for the adoption of a common (fleet-wide) SNC Standard Emergency Plan (SEP), with site-specific annexes.
Information Collection: NUREG/BR-0254, Payment Methods and NRC Form 629, Authorization for Payment by Credit Card
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, NUREG/BR-0254, Payment Methods and NRC Form 629, Authorization for Payment by Credit Card.
Operator Licensing Examination Standards for Power Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG- 1021, Revision 11, ``Operator Licensing Examination Standards for Power Reactors.''
Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Radiologically Controlled Area Ventilation System Design Changes
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. 57 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, 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.
Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Station, Units 3 and 4; Fire Pump Head and Diesel Fuel Day Tank Changes
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. 58 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.
Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Relocation of Air Cooled Chiller Pump 3, VWS-MP-03
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. 64 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.
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 14 to January 30, 2017. The last biweekly notice was published on January 31, 2017.
Preparation of Environmental Reports for Nuclear Power Stations
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-4026, ``Preparation of Environmental Reports for Nuclear Power Stations.'' This proposed guide, revision 3, provides general guidance to applicants for the format and content of environmental reports (ERs) that are submitted as part of an application for a permit, license, or other authorization to site, construct, and/or operate a nuclear power plant.
Initiatives To Address Gas Accumulation Following Generic Letter 2008-01
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) setting forth a licensee's responsibility for ensuring systems remain operable with respect to the accumulation of gas, regardless of whether the licensee chooses to voluntarily implement two industry initiatives to address weaknesses in the management of gas accumulation.
Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Startup Testing
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to Regulatory Guide (RG) 1.20, ``Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Startup Testing.'' This RG describes methods and procedures that the NRC staff considers acceptable when developing a comprehensive vibration assessment program for reactor internals during preoperational and startup testing.
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register (FR) on December 20, 2016, regarding notice of issuance of amendments to facility operating licenses and combined licenses. This action is necessary to correct an administrative error.
Information Collection: “Licenses and Radiation Safety Requirements for Well Logging”
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, ``Licenses and Radiation Safety Requirements for Well Logging.''
Source Materials License No. SUC-1593, Amendment 2, Davy Crockett Depleted Uranium at Various United States Army Installations
The U.S. Nuclear Regulatory Commission (NRC) is issuing an amendment to Source Materials License No. SUC-1593, issued to the U.S. Army Installation Command (Army). The Army submitted site-specific Environmental Radiation Monitoring Plans (ERMPs) and site-specific dose modeling that are consistent with the programmatic ERMP and the dose modeling methodology approved by License Amendment 1. All site-specific ERMPs meet license conditions (LCs) 18 and 19. License condition 18 was modified indicating that each site-specific ERMP shall be fully implemented within 6 months of approval of License Amendment 2 and LC 19 was deleted because the Army's submittal met this LC. The programmatic ERMP, dated September 15, 2016, was determined to be identical to the approved programmatic ERMP except for the removal of RESRAD environmental default parameters and has been incorporated into the license by reference.
In the Matter of Curtis Thompson
The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order prohibiting Mr. Curtis Thompson from involvement in NRC-licensed activities for a period of 1 year. The Order also requires Mr. Thompson to notify the NRC of any current involvement in NRC-licensed activities and for a period of 1 year after the 1-year period of prohibition has expired, that he provide a written notice for his first employment offer involving NRC-licensed activities.
Program-Specific Guidance About Exempt Distribution Licenses
The U.S. Nuclear Regulatory Commission (NRC) is revising its licensing guidance for licenses authorizing initial distribution of byproduct material or source material to persons exempt from the requirements (exempt distribution) for an NRC license. The NRC is requesting public comment on draft NUREG-1556, Volume 8, Revision 1, ``Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Exempt Distribution Licenses.'' The document has been updated from the original version to include information on safety culture, protection of sensitive information, and changes in regulatory policies and practices. This document is intended for use by applicants, licensees, and the NRC staff.
Access Authorization and Fitness-For-Duty Determinations
The U.S. Nuclear Regulatory Commission (NRC) plans to hold a public meeting to discuss a rulemaking activity regarding the role of third parties in access authorization and fitness-for-duty determinations. The purpose of the meeting is to provide information on the background and status of this rulemaking activity and to obtain input from interested stakeholders.
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 Seabrook Station, Unit No. 1; Virgil C. Summer Nuclear Station, Units 2 and 3; and Limerick Generating Station, Unit 2. The NRC proposes to determine that each amendment request involves 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.
Southern Nuclear Operating Company, Vogtle Electric Generating Station, Units 3 and 4; Qualified Data Processing System and Safety Display
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. 60 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, 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.
Exelon Generation Company, LLC; Clinton Power Station, Unit No. 1; Quad Cities Nuclear Power Station, Units 1 and 2; Oyster Creek Nuclear Generating Station
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to an August 16, 2016, request from Exelon Generation Company, LLC (Exelon or the licensee), from certain regulatory requirements. The exemption would allow a certified fuel handler (CFH), besides a licensed senior operator, to approve the emergency suspension of security measures for Clinton Power Station, Unit No. 1 (CPS); Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS); and Oyster Creek Nuclear Generating Station (OCNGS) during certain emergency conditions or during severe weather.
Guidance for Developing Principal Design Criteria for Non-Light Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1330, ``Guidance for Developing Principal Design Criteria for Non-Light Water Reactors.'' This DG is a proposed new regulatory guide (RG) to provide designers, applicants, and licensees of non-light water cooled nuclear reactors (non-LWR) guidance for developing principal design criteria (PDC) for a proposed facility. The PDC establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety; that is, structures, systems, and components that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public.
In the Matter of Entergy Nuclear Operations, Inc., Entergy Nuclear Indian Point 3, LLC; Indian Point Nuclear Generating Unit No. 3; and Entergy Nuclear FitzPatrick, LLC; James A. FitzPatrick Nuclear Power Plant
The U.S. Nuclear Regulatory Commission (NRC) is issuing an order approving the transfer of the Master Decommissioning Trust for Indian Point Nuclear Generating Unit No. 3 and James A FitzPatrick Nuclear Power Plant from the Power Authority of the State of New York to Entergy Nuclear Operations, Inc., amendments to the Master Decommissioning Trust Agreement dated July 25, 1990, as amended, governing the Master Trust to facilitate the transfer, and license amendments to the operating licenses of Indian Point and FitzPatrick to modify the existing trust-related license conditions to reflect the proposed transfer of the Master Trust and to delete other license conditions in order to apply the requirements of 10 CFR 50.75(h)(1).
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