Nuclear Regulatory Commission November 2019 – Federal Register Recent Federal Regulation Documents
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Organizational Changes and Conforming Amendments
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to reflect internal organizational changes and make conforming amendments. These changes include removing all references to the Office of New Reactors because that office has merged with the Office of Nuclear Reactor Regulation, changing the names of divisions that are affected by the reorganization of the Office of Nuclear Material Safety and Safeguards, and making conforming amendments throughout the regulations to reflect the office merger and the office reorganization. This document is necessary to inform the public of these non-substantive amendments to the NRC's regulations.
SHINE Medical Technologies, LLC
The U.S. Nuclear Regulatory Commission (NRC) intends to gather information through the public scoping process to prepare a supplement the to the final environmental impact statement (FEIS) on the construction permit related to the operating license application for the SHINE Medical Isotope Production Facility. The NRC is seeking public input on the proposed action and has scheduled a public scoping meeting.
In the Matter of Southern Nuclear Operating Company
The U.S. Nuclear Regulatory Commission (NRC) is issuing a Confirmatory Order to Southern Nuclear Operating Company (SNC). This action is based on two investigations conducted by the NRC Office of Investigations (OI), that apparent willful violations of NRC's regulations regarding ``Employee Protection,'' occurred. Specifically, two contract employees at Vogtle Units 3 and 4 were terminated from employment in 2016 and 2017, respectively. The NRC determined that these terminations were, in part, because the contract employees engaged in protected activity. An ADR mediation session was held on August 5, 2019, with SNC, and a preliminary settlement agreement was reached. Subsequently, SNC consented to the specific actions listed in section V of the Confirmatory Order and the NRC agrees to no pursue any further enforcement action in connection with this apparent violation. The Confirmatory Order becomes effective upon issuance.
Portland General Electric Company; Eugene Water and Electric Board, and PacifiCorp; Trojan Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) issued a renewed license to Portland General Electric (PGE), Eugene Water and Electric Board, and PacifiCorp (together ``licensee'') for Special Nuclear Materials (SNM) License No. SNM-2509 for the receipt, possession, transfer, and storage of spent fuel from the Trojan Nuclear Plant in the Trojan Independent Spent Fuel Storage Installation (ISFSI), located in Columbia County, Oregon on August 9, 2019. On October 23, 2019, the renewed license and technical specifications were corrected to reflect the current amendment and to remove obsolete pages from the technical specifications.
Nuclear Power Plant License Fees Upon Commencing Commercial Operation
The U.S. Nuclear Regulatory Commission (NRC) will consider in its rulemaking process one issue raised in a petition for rulemaking, PRM-171-1, dated February 28, 2019, submitted by Dr. Michael D. Meier on behalf of the Southern Nuclear Operating Company (the petitioner), and is denying the remaining issue in PRM-171-1. The petitioner requested that the NRC amend its regulations related to the start of the assessment of annual fees for certain nuclear power plants.
Improved Identification Techniques Against Alkali-Silica Reaction (ASR) Concrete Degradation at Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), PRM-50-109, dated September 25, 2014, submitted by the C-10 Research and Education Foundation (C-10 or the petitioner). The petitioner requests that the NRC amend its regulations to provide improved identification techniques for better protection against concrete degradation due to alkali-silica reaction (ASR) at U.S. nuclear power plants. The petitioner asserts that reliance on visual inspection will not adequately identify ASR, confirm ASR, or provide the current state of ASR damage without petrographic examination. The NRC is denying the petition because existing NRC regulations and NRC oversight activities provide reasonable assurance of adequate protection of public health and safety. Specifically, existing NRC regulations are sufficient to ensure that concrete degradation due to ASR will not result in unacceptable reductions in the structural capacity of safety-related structures at nuclear power plants.
Bellefonte Nuclear Plant; Consideration of Approval of Transfer of Construction Permits and Conforming Amendment
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an application filed by Nuclear Development, LLC (ND) on November 13, 2018. The application seeks NRC approval of the direct transfer of construction permits Nos. CPPR-122 and CPPR-123, for Bellefonte Nuclear Plant, Units 1 and 2, from the current holder, Tennessee Valley Authority (TVA), to ND. The application contains sensitive unclassified non-safeguards information (SUNSI).
Curtiss-Wright Electro-Mechanical Corporation
The U.S. Nuclear Regulatory Commission (NRC) is considering an export license amendment (XR177/01), requested by Curtiss-Wright Electro-Mechanical Corporation (CW-EMD). On October 23, 2019, CW-EMD filed a license amendment application to export nuclear reactor equipment. The request seeks the NRC's approval for the export of six reactor coolant pumps (RCPs)two of the six, will serve as replacement RCPsto the People's Republic of China (PRC). The NRC is providing notice of the opportunity to request a hearing on CW-EMD's revised application. The request seeks the NRC's approval of the application authorizing the export of the RCPs to PRC.
Guidance for Implementation of Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material
The U.S. Nuclear Regulatory Commission (NRC) is revising its guidance for implementation of physical protection of Category 1 and Category 2 quantities of radioactive material. The NRC is requesting public comments on draft NUREG-2155, Revision 2, ``Implementation Guidance for 10 CFR part 37, `Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material.' '' The document has been updated from NUREG-2155, Revision 1, to include revisions to questions and answers and guidance related to general provisions in the rule, background investigations and access authorization programs, and physical protection requirements during use and in transit.
Nuclear Waste Partnerships, LLC
The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) for an exemption request from Nuclear Waste Partnerships, LLC for the one-time shipment of transuranic waste in two TRUPACT-III packages from the Savannah River Site, Aiken, South Carolina, to the Waste Isolation Pilot Plant, Carlsbad, New Mexico.
Power Reactor In-Core Monitoring
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), dated March 13, 2015, submitted by Mark Edward Leyse (petitioner). The petition was docketed by the NRC on April 24, 2015, and assigned Docket No. PRM-50-111. The petitioner requested that the NRC require all holders of operating licenses for nuclear power plants to operate them with in-core temperature- monitoring devices (e.g., thermoacoustic sensors or thermocouples) located at different elevations and radial positions throughout the reactor core. The NRC is denying the petition because current regulations provide a sufficient level of safety, such that additional requirements for in-core temperature-monitoring devices as specified in the petition are not needed.
Alternative Method for Calculating Embrittlement for Steel Reactor Vessels
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Thomas A. Bergman, on behalf of NuScale Power, LLC, dated August 19, 2019, requesting that the NRC revise its regulations to alleviate a requirement for calculating the embrittlement for advanced reactor designs and to add the embrittlement trend curve formula for calculating the mean value of the transition temperature shift described in American Society for Testing and Materials E900-152 to the NRC's regulations and guidance documents. The petition was docketed by the NRC on September 11, 2019, and has been assigned Docket No. PRM-50-120. The NRC is examining the issues raised in PRM-50-120 to determine whether these issues should be considered in rulemaking. The NRC is requesting public comment on this petition at this time.
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to 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 October 22, 2019, to November 4, 2019. The last biweekly notice was published on November 5, 2019.
Miscellaneous Corrections
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to make miscellaneous corrections. These changes include removing obsolete language and correcting references, a typographical error, mailing, email, and web page addresses, grammatical errors, a division title, and a division address and title. This document is necessary to inform the public of these non-substantive amendments to the NRC's regulations.
Stakeholder Input on Best Practices for Establishment and Operation of Local Community Advisory Boards in Response to a Portion of the Nuclear Energy Innovation and Modernization Act
On September 27, 2019, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on best practices for establishment and operation of local community advisory boards (CABs) associated with decommissioning activities, including lessons learned from existing boards, as required by the Nuclear Energy Innovation and Modernization Act (NEIMA). The public comment period was originally scheduled to close on November 15, 2019. The NRC has elected to reopen the public comment period to allow more time for members of the public to develop and submit their comments. Consistent with the consultation requirements in NEIMA Section 108, the NRC has hosted 11 public meetings and a public webinar to consult with host States, communities within the emergency planning zone of an applicable nuclear power reactor, and existing local CABs. The NRC is planning to host a second public webinar on November 19, 2019. In addition to these public meetings and public webinars, the NRC has developed a questionnaire to collect information regarding the areas identified in NEIMA with respect to the creation and operation of CABs from CABs in the vicinity of power reactors undergoing decommissioning, similar established stakeholder groups, or local government organizations. The results of the meetings, along with any other data received as a result of the NRC's information collection activities associated with the NEIMA Section 108, will be captured in a best practices report that will be submitted to Congress.
NextEra Energy Duane Arnold, LLC; Duane Arnold Energy Center
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a February 28, 2019, request from NextEra Energy Duane Arnold, LLC. The exemption allows a certified fuel handler, in addition to a licensed senior operator, to suspend security measures in an emergency or during severe weather at the Duane Arnold Energy Center (DAEC) after both the ``Certification of Permanent Cessation of Operations'' and the ``Certification of Permanent Fuel Removal'' have been docketed for the facility.
Agency Action Regarding the Exploratory Process for the Development of an Advanced Nuclear Reactor Generic Environmental Impact Statement
The U.S. Nuclear Regulatory Commission (NRC) is conducting an exploratory process to gather information on potential environmental impacts resulting from the construction and operation of advanced nuclear reactors. The NRC is planning to conduct two public meetings and a workshop to explore the interaction of various advanced nuclear reactor designs with the environment. NRC intends to gather information that will inform its decision on whether to proceed with the development of a generic environmental impact statement for the construction and operation of advanced nuclear reactors (ANR GEIS). The intent of an ANR GEIS is to improve the efficiency of the environmental review process.
Proposed Revisions To Draft Branch Technical Position 8-8 Onsite (Emergency Diesel Generators) and Offsite Power Sources Completion Time Extensions
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on draft NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' Branch Technical Position (BTP) 8-8, ``Onsite (Emergency Diesel Generators) and Offsite Power Sources Completion Time Extensions.'' The NRC seeks comments on the proposed draft section revision of the BTP concerning guidance for the completion time extension requests for onsite or offsite power sources.
Perma-Fix Northwest Richland, Inc.
The U.S. Nuclear Regulatory Commission (NRC) is considering issuing an export license (XW025), requested by Perma-Fix Northwest Richland, Inc. (PFNW). On September 27, 2019, PFNW filed an application with the NRC for a license to export radioactive waste. The request seeks NRC approval for the export of low-level radioactive waste to Italy. The NRC is providing notice of the opportunity to request a hearing on PFNW's revised application. The request seeks the NRC's approval of the application authorizing the export of radioactive waste to Italy.
Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2; Revisions to Technical Specification Table 3.3.5-1
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to Facility Operating Licenses Nos. NPF-90 and NPF-96, issued to Tennessee Valley Authority, for operation of the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2. The amendments would correct unbalanced voltage relay instrumentation values.
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Pursuant to 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 October 8, 2019, to October 21, 2019. The last biweekly notice was published on October 22, 2019.
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