Nuclear Regulatory Commission 2019 – Federal Register Recent Federal Regulation Documents

The U.S. Nuclear Regulatory Commission (NRC) is considering an amendment to Possession Only License DPR-45 to add a license condition that reflects the NRC's approval of the license termination plan (LTP) for the La Crosse Boiling Water Reactor (LACBWR) and provides criteria for when prior NRC approval is needed to make changes to the LTP. The NRC has prepared a final environmental assessment (EA) and finding of no significant impact (FONSI) for this licensing action.

The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and a finding of no significant impact (FONSI) for its review and approval of the decommissioning funding plans submitted by Pacific Gas and Electric Company (PG&E) on December 17, 2012, and December 17, 2015, for the independent spent fuel storage installation (ISFSI) at Humboldt Bay in Eureka, California.

The U.S. Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DC/COL-ISG-03, ``Probabilistic Risk Assessment Information to Support Design Certification and Combined License Applications.'' This ISG served to supplement the guidance provided to the staff in Section 19.0, ``Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,'' of NUREG- 0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' concerning the review of probabilistic risk assessment information and severe accident assessment submitted to support design certification (DC) and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DC/ COL-ISG into Revision 3 to Section 19.0 of NUREG-0800 dated December 2015. With the issuance of Revision 3 to Section 19.0 of NUREG-0800, the staff has determined that DC/COL-ISG-03 is no longer necessary and should be withdrawn.

The Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DC/COL-ISG-10, ``Review of Evaluation to Address Adverse Flow Effects in Equipment Other than Reactor Internals.'' This ISG served to supplement the guidance provided to the staff in Sections 3.9.2, ``Dynamic Testing and Analysis of Systems, Structures, and Components,'' and 3.9.5, ``Reactor Pressure Vessel Internals,'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' concerning the review of probabilistic risk assessment information and severe accident assessment submitted to support design certification (DC) and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DC/COL-ISG into Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG-0800 dated March 2017. With the issuance of Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG-0800, the staff has determined that DC/COL-ISG-10 is no longer necessary and should be withdrawn.

The U.S. Nuclear Regulatory Commission (NRC) is giving notice once each week for four consecutive weeks for an application from Tennessee Valley Authority (TVA), for an early site permit (ESP) for the Clinch River Nuclear Site located in Oak Ridge, Tennessee.

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 237, ``Request for Access Authorization.''

The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the NAC International NAC-UMS[supreg] Universal Storage System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 7 to Certificate of Compliance No. 1015. Amendment No. 7 would revise the surveillance requirements for technical specifications A3.1.6.1 and A3.1.6.2 to ensure that adequate monitoring of the concrete cask heat removal system is performed. Amendment No. 7 would also revise the basis for technical specification A3.1.6 to clarify that the surveillance requirements for technical specification A3.1.6 require a minimum of two outlet air temperature measurements to provide an average outlet temperature.

The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Michael Taylor, dated December 3, 2018, as amended on January 24, 2019. The petitioner requests that the NRC amend its regulations to revise the measurement standards used at U.S. nuclear power plants. The petition was docketed by the NRC on March 4, 2019, and has been assigned Docket No. PRM-50-118. The NRC is examining the issues raised in PRM-50-118 to determine whether they should be considered in rulemaking. The NRC is requesting public comment on this petition.

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, ``Billing Instructions for NRC Cost Type Contract/Orders.''

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, ``Criteria and Procedures for Determining Eligibility for Access to or Control Over Special Nuclear Material.''

The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order to set a schedule for an evidentiary hearing in the Powertech USA, Inc., Dewey-Burdock In Situ Uranium Recovery Facility proceeding. The Order for Granting NRC Staff Motion and Scheduling Evidentiary Hearing became effective on April 29, 2019.

The U.S. Nuclear Regulatory Commission (NRC) has issued Revision 2 to NUREG-1556, Volume 13, ``Consolidated Guidance About Materials Licenses: Program-Specific Guidance About Commercial Radiopharmacy Licenses.'' Volume 13 of NUREG-1556 has been revised to include information on updated regulatory requirements, safety culture, security of radioactive materials, protection of sensitive information, and changes in regulatory policies and practices consistent with current regulations. This volume is intended for use by applicants, licensees, and the NRC staff.

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1353, ``Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors.'' This DG proposes new guidance for designers, applicants, and licensees of non- light water cooled nuclear reactors (non-LWRs) to inform the licensing basis and content of applications submittals to the NRC for licenses, certifications, or approvals. The DG provides guidance on using a technology-inclusive, risk-informed, and performance-based methodology to inform the licensing basis and content of applications for licenses, certifications, and approvals for non-LWRs.

The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 5 to Regulatory Guide (RG) 1.97, ``Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants.'' This guide describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for instrumentation to monitor accidents in nuclear power plants. It endorses, with exceptions and clarifications, the Institute of Electrical and Electronic Engineers (IEEE) Standard (Std.) 497-2016, ``IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations.''

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.''

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. 154 for Unit 3 and No. 153 for Unit 4 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 (collectively SNC); 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.

The U.S. Nuclear Regulatory Commission (NRC) is considering an exemption to License 45-23645-01NA, to exempt the Department of the Navy (Navy) from certain reporting requirements involving the use and storage of radioactive sealed source devices used for a helicopter in- flight blade inspection system (IBIS) during military exercises and maneuvers. The NRC has prepared an environmental assessment (EA) and finding of no significant impact (FONSI) for this licensing action.

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, ``Packaging and Transportation of Radioactive Material.''

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 March 26, 2019 to April 8, 2019. The last biweekly notice was published on April 9, 2019.

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1284, ``Anchoring Components and Structural Supports in Concrete.'' This proposed guide, Revision 1 of Regulatory Guide (RG) 1.199 of the same name, endorses Appendix D, ``Anchoring to Concrete,'' of an updated version of American Concrete Institute code ACI 349, ``Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary (2013).'' The previous version of RG 1.199 endorsed ACI 349-1997. It also endorses ACI 355.2-07, ``Qualification of Post-Installed Mechanical Anchors in Concrete and Commentary,'' and ASTM E488-15, ``Standard Test Methods for Strength of Anchors in Concrete Elements.''