Nuclear Regulatory Commission September 2018 – Federal Register Recent Federal Regulation Documents
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State of Wyoming: Discontinuance of Certain Commission Regulatory Authority Within the State; Notice of Agreement Between the NRC and the State of Wyoming
This document is announcing that on September 25, 2018, Kristine L. Svinicki, Chairman of the U.S. Nuclear Regulatory Commission (NRC or Commission), and Governor Matthew H. Mead of the State of Wyoming, signed an Agreement as authorized by Section 274b. of the Atomic Energy Act of 1954, as amended (the Act). Under the Agreement the Commission discontinues its regulatory authority, and the State of Wyoming assumes regulatory authority over the management and disposal of byproduct material as defined in Section 11e.(2) of the Act and a subcategory of source material or ores involved in extraction or concentration of uranium or thorium milling in the State. As of the effective date of the Agreement, a person in Wyoming possessing these materials is exempt from certain Commission regulations. The exemptions have been previously published in the Federal Register (FR) and are codified in the Commission's regulations. The Agreement is published here as required by Section 274e. of the Act.
Proposed Revisions to Standard Review Plan Section 2.5.3, Surface Deformation
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,'' Section 2.5.3, ``Surface Deformation.'' SRP Section 2.5.3, Surface Deformation, was last updated in 2014. This proposed update to the SRP focuses on risk-informing the staff's review in this area on the potential for tectonic or non-tectonic surface deformation that could adversely affect the safe operation of a nuclear power plant at the proposed site.
Proposed Revisions to Standard Review Plan Section 2.4.6, Tsunami Hazards; Section 2.4.9, Channel Migration or Diversion; and Section 2.3.3, Onsite Meteorological Measurements Program
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on proposed updates to NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition'' (or SRP). The staff is proposing changes to a select number of sections of SRP Chapter 2 taking into account some of the lessons-learned from the flooding hazard re-evaluations performed by the operating power reactor fleet. Specific changes are being proposed to Section 2.4.6, ``Tsunami Hazards''; Section 2.4.9, ``Channel Migration or Diversion''; and Section 2.3.3, ``Onsite Meteorological Measurements Program''.
Information Collection: Cooperation With States at Commercial Nuclear Power Plants and Other Nuclear Production and Utilization Facilities, Policy 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, ``Cooperation with States at Commercial Nuclear Power Plants and Other Nuclear Production and Utilization Facilities, Policy Statement.''
NexEra Energy Duane Arnold, LLC: Duane Arnold Energy Center
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of NextEra Energy Duane Arnold, LLC (NextEra) to withdraw its application dated December 19, 2017, for a proposed amendment to Duane Arnold Energy Center (DAEC), Facility Operating License No. DPR-49. The proposed change would have added Technical Specifications (TS) 3.2.3, ``Linear Heat Generation Rate (LHGR),'' and modified TS 1.1, ``Definitions,'' TS 3.4.1, ``Recirculation Loops Operating,'' and TS 5.6.5, ``Core Operating Limits Report (COLR)'' to reflect the LHGR change. Modifications associated with TS 3.2.1, ``Average Planar Linear Heat Generation Rate (APLHGR),'' and the new TS 3.2.3 would also have been added to the actions for TS 3.3.4.1, ``End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation,'' and TS 3.7.7, ``The Main Turbine Bypass System.'' Subsequently, by letter dated August 21, 2018, NextEra withdrew the amendment request.
Monitoring the Effectiveness of Maintenance at Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to Regulatory Guide (RG) 1.160, ``Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.'' Regulatory Guide 1.160, Revision 4, has been revised to address new issues identified since Revision 3 of RG 1.160 was issued. This RG endorses, with clarifications, NUMARC 93-01, ``Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,'' Revision 4F. The proposed revision describes methods that are acceptable to the NRC staff for compliance with the requirements for monitoring the effectiveness of maintenance at nuclear power plants.
Regulatory Guidance and Technical Basis on the Alternate Pressurized Thermal Shock Rule
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 0 to Regulatory Guide (RG) 1.230, ``Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule'' and the associated technical basis, NUREG-2163, ``Technical Basis for Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule.'' This guidance describes a method that the NRC staff considers acceptable to permit use of the alternate fracture toughness requirements for protection against pressurized thermal shock events for pressurized water reactor pressure vessels.
Proposed Revisions to Standard Review Plan Section 14.3.3, Piping Systems and Components-Inspections, Tests, Analyses, and Acceptance Criteria
The U.S. Nuclear Regulatory Commission (NRC) is re-noticing the solicitation for public comment published in the Federal Register on September 11, 2017, on NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' SRP Section 14.3.3, ``Piping Systems and Components Inspections, Tests, Analyses, and Acceptance Criteria.''
Cameco Resources; Smith Ranch-Highland Uranium Project
The U.S. Nuclear Regulatory Commission (NRC) is considering the renewal of NRC source materials license SUA-1548, to authorize continued uranium in-situ recovery (ISR) operations at the sites under the Smith Ranch-Highland Uranium Project (Smith Ranch Project) (Docket No. 40-8964). The NRC has prepared an Environmental Assessment (EA) and Finding of No Significant Impact (FONSI) for this licensing action.
Information Collection: NRC Form 361, Reactor Plant Event Notification Worksheet; NRC Form 361A, Fuel Cycle and Materials Event Notification Worksheet; NRC Form 361N, Non-Power Reactor Event Notification Worksheet
The U.S. Nuclear Regulatory Commission (NRC) invites public comment on this proposed collection of information. The information collection is entitled, ``NRC Form 361, Reactor Plant Event Notification Worksheet; NRC Form 361A, Fuel Cycle and Materials Event Notification Worksheet; NRC Form 361N, Non-Power Reactor Event Notification Worksheet.''
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 August 28, 2018 to September 10, 2018. The last biweekly notice was published on September 11, 2018.
Preparation of Environmental Reports for Nuclear Power Stations
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 of Regulatory Guide (RG) 4.2, ``Preparation of Environmental Reports for Nuclear Power Stations.'' This revision 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 approval for a new nuclear power plant.
Inflation Adjustments to the Price-Anderson Act Financial Protection Regulations
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to adjust for inflation the maximum total and annual standard deferred premiums specified in the Price-Anderson Act. The NRC must perform this adjustment at least once during each 5-year period following August 20, 2003, as mandated by the Atomic Energy Act of 1954, as amended (AEA).
Zion Nuclear Power Station, Units 1 and 2: Zion Solutions, LLC
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an application filed by the ZionSolutions, LLC (ZS) on July 24, 2018. The application seeks NRC approval of the direct transfer of Facility Operating License Nos. DPR-39 and DPR-48 for Zion Nuclear Power Station, Units 1 and 2 (ZNPS), from the current holder, ZS, to Exelon Generation Company, LLC (EGC). The NRC is also considering amending the facility operating licenses for administrative purposes to reflect the proposed transfer.
Protection Against Malevolent Use of Vehicles at Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 5.68, ``Protection against Malevolent use of Vehicles at Nuclear Power Plants,'' dated August 1994. This document is being withdrawn because it is outdated and has been superseded by other NRC guidance. Therefore, it no longer provides methods that the NRC staff finds acceptable to protect against the malevolent use of vehicles as a means to gain unauthorized access to protected areas and vital areas and to ensure that these vehicles are operated only by authorized persons with a legitimate need for access.
Proposed Revisions to Branch Technical Position 5-3: Fracture Toughness Requirements
On July 13, 2018, the U.S. Nuclear Regulatory Commission (NRC) published a request for 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) 5-3, ``Fracture Toughness Requirements.'' The public comment period was originally scheduled to close on September 11, 2018. The NRC has decided to reopen the public comment period on this document for 30 days to allow more time for members of the public to review additional revisions that the NRC made to BTP 5-3 since the draft was issued on July 13, 2018, and to assemble and submit their comments.
Entergy Nuclear Operations, Inc.: Indian Point Nuclear Generating Unit Nos. 2 and 3
The U.S. Nuclear Regulatory Commission (NRC) has issued renewed Facility Operating License Nos. DPR-26 and DPR-64 to Entergy Nuclear Operations, Inc. (Entergy or licensee), for Indian Point Nuclear Generating Unit Nos. 2 (IP2) and 3 (IP3). Renewed Facility Operating License Nos. DPR-26 and DPR-64 authorize Entergy to operate IP2 and IP3 at reactor core power levels not in excess of 3,216 megawatts thermal for each unit, in accordance with the provisions of the IP2 and IP3 renewed licenses and technical specifications. In addition, the NRC has prepared a Record of Decision (ROD) that supports the NRC's decision to issue renewed Facility Operating License Nos. DPR-26 and DPR-64.
Vogtle Electric Generating Plant, Units 3 and 4
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment and exemption to Combined Licenses (NPF-91 and NPF-92), issued to Southern Nuclear Operating Company, Inc. (SNC), 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 (collectively, SNC), for construction and operation of the Vogtle Electric Generating Plant (VEGP), Units 3 and 4, located in Burke County, Georgia.
Vogtle Electric Generating Plant, Units 3 and 4
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment and exemption to Combined Licenses (NPF-91 and NPF-92), issued to Southern Nuclear Operating Company, Inc. (SNC), 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 (collectively, SNC), for construction and operation of the Vogtle Electric Generating Plant (VEGP), Units 3 and 4, located in Burke County, Georgia.
Xcel Energy, Monticello Nuclear Generating Plant; Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a request submitted by Xcel Energy on October 18, 2017, from meeting Technical Specification (TS) 1.2.5 of Attachment A of Certificate of Compliance (CoC) No. 1004, Amendment No. 10, which requires that all dry shielded canister (DSC) closure welds, except those subjected to full volumetric inspection, be dye penetrant tested in accordance with the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section III, Division 1, Article NB-5000. This exemption applies to five loaded Standardized NUHOMS[supreg] 61BTH, Dry Shielded Canisters (DSCs) 11 through 15, at the Monticello Nuclear Generating Plant (MNGP) Independent Spent Fuel Storage Installation (ISFSI).
Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Unit No. 1
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. NPF-87, issued to Vistra Operations Company LLC (the licensee), for operation of the Comanche Peak Nuclear Power Plant (CPNPP), Unit No. 1. The proposed exigent amendment would revise CPNPP Technical Specification (TS) 3.8.4, ``DC [Direct Current] SourcesOperating,'' to allow the licensee additional time to replace two affected battery cells in the safety-related batteries for CPNPP, Unit No. 1. Specifically, the proposed one-time change would add a Required Action to TS 3.8.4, Condition B, to extend the completion time from 2 hours to 18 hours to repair each affected battery cell.
Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of exemptions in response to a March 22, 2018, request from Exelon Generation Company, LLC (Exelon or the licensee), for the Oyster Creek Nuclear Generating Station (Oyster Creek). One exemption would permit the licensee to use funds from the Oyster Creek decommissioning trust fund (DTF or the Trust) for irradiated fuel management activities and site restoration. Another exemption would allow the licensee to use withdrawals from the Trust for these activities without prior notification to the NRC. The NRC staff is issuing a final Environmental Assessment (EA) and final Finding of No Significant Impact (FONSI) associated with the proposed exemptions.
Weld Residual Stress Finite Element Analysis Validation
The U.S. Nuclear Regulatory Commission (NRC) is requesting public comment on a draft NUREG entitled, ``Weld Residual Stress Finite Element Analysis Validation: Part IIAcceptance and Guidelines.'' This report proposes a methodology by which analysts can increase confidence in modeling capabilities for regulatory applications involving weld residual stress calculation. Specifically, the NRC staff posed four questions for consideration by the public (see SUPPLEMENTARY INFORMATION).
Interim Storage Partners LLC's Consolidated Interim Spent Fuel Storage Facility; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register (FR) on September 4, 2018, reopening the scoping comment period for the NRC's Environmental Impact Statement (EIS) for the Interim Storage Partners LLC (ISP) proposed consolidated interim storage facility for spent nuclear fuel, to be located on the Waste Control Specialists LLC (WCS) site in Andrews County, Texas.
Information Collection: NRC Form 7, Application for NRC Export/Import License, Amendment, Renewal or Consent Request(s)
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``NRC Form 7, Application for NRC Export/Import License, Amendment, Renewal or Consent Request(s).''
FirstEnergy Nuclear Operating Company (FENOC) and FirstEnergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit No. 1, Perry Nuclear Power Plant, Unit No. 1
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a July 19, 2017 request from FirstEnergy Nuclear Operating Company (FENOC) and FirstEnergy Nuclear Generation, LLC (collectively, the licensee), as supplemented by letters dated March 16, 2018, and May 2, 2018. The exemption is from the NRC definition for a physical barrier regarding the construction standards for the fence bracket angle. The exemption allows the licensee to apply a fence topper bracket angle of zero degrees (or vertical) at specific locations on the protected area fence at each facility, in lieu of the 30 to 45 degree fence bracket angle required by Commission regulations. All other construction standards contained in the Commission regulations for a physical barrier fence topper remain applicable.
Disposition of Information Related to the Time Period That Safety-Related Structures, Systems, or Components Are Installed
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing draft regulatory issue summary, ``Disposition of Information Related to the Time Period that Safety-Related Structures, Systems or Components are Installed,'' which was published for public comment in the Federal Register on May 17, 2016. This document is being withdrawn because public interactions to date between NRC staff and industry have adequately communicated the issues identified by the staff to the industry. The NRC will continue to follow up on these issues via the reactor oversight process.
Guidance About Administrative Licensing Procedures
The U.S. Nuclear Regulatory Commission (NRC) is revising its guidance about administrative licensing procedures and agency policies for reviewing nuclear materials licensing requests. The NRC is requesting public comment on draft NUREG-1556, Volume 20, ``Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures.'' The document has been updated from the original version to include information on updated regulatory requirements, safety culture, security of radioactive materials, protection of sensitive information, and changes in regulatory policies and practices. This document is intended for use by the NRC staff when reviewing NRC materials licensing requests.
Proposed Revisions to Standard Review Plan Section 13.4, Operational Programs
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,'' Section 13.4, ``Operational Programs.'' The NRC seeks comments on the proposed draft section revision of the Standard Review Plan (SRP) concerning guidance for the review and implementation of operational programs required by the NRC's regulations for combined operating license applications.
Proposed Revisions to Standard Review Plan Section 13.6, Physical Security
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,'' Section 13.6, ``Physical Security.'' This section has been updated to reflect the latest NRC guidance concerning physical security.
Dispositioning of Technical Specifications That Are Insufficient To Ensure Plant Safety
On July 5, 2018, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on draft regulatory guide (DG), DG-1351, ``Dispositioning of Technical Specifications that are Insufficient to Ensure Plant Safety.'' The public comment period was originally scheduled to close on September 4, 2018. The NRC has decided to extend the public comment period by 30 days to allow more time for members of the public to develop and submit their comments.
Sacramento Municipal Utility District; Rancho Seco Nuclear Generating Station
The U.S. Nuclear Regulatory Commission (NRC) is providing public notice of the termination of the Operating License (Possession Only) No. DPR-54. The NRC has terminated the license of the decommissioned Rancho Seco Nuclear Generating Station (Rancho Seco) in Herald, California and has approved the site for unrestricted release.
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 August 14 to August 27, 2018. The last biweekly notice was published on August 28, 2018.
Virgil C. Summer Nuclear Station, Unit No. 1
The U.S. Nuclear Regulatory Commission (NRC) is proposing to determine that no significant hazards consideration is involved with the issuance of an amendment to Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station (Summer), Unit No. 1. By letter dated August 24, 2018, as supplemented by letter dated August 31, 2018, South Caroline Electric and Gas Company (SCE&G) requested a one-time extension to surveillance requirement (SR) 4.3.3.6 to allow a one-time extension of the frequency of the Core Exit Temperature Instrumentation channel calibrations from ``every refueling outage'' to ``every 19 months.''
In the Matter of Dominion Energy, Inc., and SCANA Corporation Virgil C. Summer Nuclear Station (VCSNS), Units 1, 2, and 3, and the ISFSI
The U.S. Nuclear Regulatory Commission (NRC) is issuing Orders approving an application filed by South Carolina Electric & Gas Company and Dominion Energy, Inc. (Dominion Energy) on January 25, 2018. The application sought NRC approval of the indirect transfer of Renewed Facility Operating License No. NPF-12 and Combined License Nos. NPF-93 and NPF-94 for Summer, Units 1, 2, and 3, respectively, and the general license for the Independent Spent Fuel Storage Installation, from the ultimate parent, SCANA Corporation, to Dominion Energy. The NRC's approval of the indirect license transfer is subject to certain conditions, which are described in the Orders. No physical changes to the facility or operational changes were proposed in the application. The Orders were effective upon issuance.
Information Collection: Nuclear Material Events Database (NMED) for the Collection of Event Report, Response, Analyses, and Follow-Up Data on Events Involving the Use of Atomic Energy Act (AEA) Radioactive Byproduct Material
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, ``Nuclear Material Events Database (NMED) for the Collection of Event Report, Response, Analyses, and Follow-Up Data on Events Involving the Use of Atomic Energy Act (AEA) Radioactive Byproduct Material.''
Exelon Generation Company, LLC; Peach Bottom Atomic Power Station, Units 2 and 3
The U.S. Nuclear Regulatory Commission will conduct a scoping process to gather information necessary to prepare an environmental impact statement (EIS) to evaluate the environmental impacts for the subsequent license renewal of the operating licenses for Peach Bottom Atomic Power Station, Units 2 and 3 (Peach Bottom). The NRC is seeking stakeholder input on this action and has scheduled a public meeting.
Information Collection: NRC Form 664, General Licensee Registration
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, ``General Licensee Registration.''
Identifying and Reporting Human Performance Incidents
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing the draft regulatory issue summary (RIS), RIS 2017-XX, ``Identifying and Reporting Human Factor Incidents.'' This document is being withdrawn because after further consideration, the NRC determined that the RIS did not provide the clarification intended regarding licensees' required reporting of human performance incidents.
Exelon Generation Company, LLC: Peach Bottom Atomic Power Station, Units 2 and 3
The U.S. Nuclear Regulatory Commission (NRC) is considering an application for the subsequent license renewal of Renewed Facility Operating License Nos. DPR-44 and DPR-56, that authorizes Exelon Generation Company, LLC (Exelon or the applicant) to operate Peach Bottom Atomic Power Station Units 2 and 3 (Peach Bottom). The renewed licenses would authorize the applicant to operate Peach Bottom for an additional 20 years beyond the period specified in each of the current renewed licenses. The current renewed operating licenses for Peach Bottom expire as follows: Unit 2 on August 8, 2033, and Unit 3 on July 2, 2034.
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