Nuclear Regulatory Commission September 2015 – Federal Register Recent Federal Regulation Documents

The U.S. Nuclear Regulatory Commission (NRC) published a final rule in the Federal Register on September 9, 2015, that amended its regulations to better adhere to the Office of Federal Register's (OFR) guidance for formatting authority citations. In addition, the final rule corrected typographical errors and made other non-substantive corrections to the NRC's authority citations. The final rule contained incorrect punctuation and spacing, one incorrect reference, and omitted two references. This document makes additional corrections to NRC's authority citations.

The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on the following sections in Chapter 3, ``Design of Structures, Components, Equipment, and Systems Reactor Coolant System and Connected Systems'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' Section 3.9.2, ``Dynamic Testing and Analysis of Systems, Structures, and Components,'' Section 3.9.4, ``Control Rod Drive Systems,'' Section 3.9.5, ``Reactor Pressure Vessel Internals,'' and Section 3.9.6, ``Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints.''

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 September 1 to September 14, 2015. The last biweekly notice was published on September 15, 2015.

The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG), FCSE ISG-14, ``Acute Uranium Standards for Workers,'' dated June 15, 2015. The ISG provides guidance to the NRC staff when reviewing licensee-proposed standards in the Integrated Safety Analysis Summary for determining worker uranium exposures that would result in high or intermediate consequences consistent with the general definition of these events in NRC regulations.

The U.S. Nuclear Regulatory Commission (NRC) is issuing a final revision to Section 9.2.7, ``Chilled Water System,'' of NUREG- 0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition.''

The U.S. Nuclear Regulatory Commission (NRC) is withdrawing an application for a combined license (COL) for a single unit of the Economic Simplified Boiling-Water Reactor (ESBWR). This reactor would be identified as Grand Gulf Nuclear Station, Unit 3 (GGNS3) and is located adjacent to the current Grand Gulf Nuclear Station site in Claiborne County, Mississippi.

The U.S. Nuclear Regulatory Commission (NRC) has received an application dated September 5, 2015, from Exelon Generation Company, LLC, for amendment of Clinton Power Station, Unit 1. The application proposes a one-time extension from 72 hours to 7 days of the technical specification (TS) completion time [CT] associated with the Division 2 (Div. 2) Shutdown Service Water (SX) Subsystem in support maintenance activities.

The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference seven recent editions and addenda to the American Society of Mechanical Engineers (ASME) codes for nuclear power plants and a standard for quality assurance. The NRC is also proposing to incorporate by reference four ASME code cases. This action is in accordance with the NRC's policy to periodically update the regulations to incorporate by reference new editions and addenda of the ASME codes and is intended to maintain the safety of nuclear power plants and to make NRC activities more effective and efficient.

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1315, ``Seismic Design Classification for Nuclear Power Plants.'' The DG describes a method that the NRC staff considers acceptable for use in identifying and classifying those features of light-water-reactor (LWR) nuclear power plants that must be designed to withstand the effects of the safe- shutdown earthquake (SSE). DG-1315 is proposed revision 5 of Regulatory Guide (RG) 1.29.

The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comments on proposed changes to the ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' (NUREG-0800) for changes to 33 individual sections of Chapter 7, ``Instrumentation and Controls,'' as listed in the table in Section IV of this notice entitled, Availability of Documents.

The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an application filed by FirstEnergy Nuclear Operating Company (FENOC) on June 30, 2015. The application seeks NRC approval of the direct transfer of the leased interests in NPF-58 for Perry Nuclear Power Plant, Unit 1, from the current holder, the Ohio Edison Company (OE), to FirstEnergy Nuclear Generation, LLC (FENGen). The NRC is also considering amending the facility operating license for administrative purposes to reflect the proposed transfer. The application contains sensitive unclassified non-safeguards information (SUNSI).

The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. NFP-90, issued to the Tennessee Valley Authority (the licensee), for operation of the Watts Bar Nuclear Plant (WBN), Unit No. 1. The proposed amendment would modify the technical specifications (TSs) to define support systems needed in the first 48 hours after a unit shutdown when steam generators are not available for heat removal. The proposed amendment would also make changes consistent with Technical Specification Task Force (TSTF) Traveler TSTF-273-A, Revision 2, to provide clarifications related to the requirements of the Safety Function Determination Program (SFDP). The proposed license amendment was submitted by letter dated June 17, 2015, and was supplemented by letters dated July 14, August 28, and September 3, 2015. The NRC staff previously made a proposed determination that the amendment involves no significant hazards consideration. By letter dated September 3, 2015, the licensee provided additional information that expanded the scope of the amendment request as originally noticed. The September 3, 2015, supplement proposed new modifications to TS 3.3.2 and TS 3.4.6. This notice supersedes the previous notice in its entirety to update the description of the amendment request and the no significant hazards determination.