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

The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order to Duke Energy Progress, Inc. (Duke Energy) and North Carolina Eastern Municipal Power Agency (NCEMPA), approving the direct transfer of control of the Renewed Facility Operating License Nos. DPR-71 and DPR-62, and ownership interest for the Brunswick Steam Electric Plant (Brunswick), Units 1 and 2, to the extent currently held by NCEMPA. As a result of the transaction, Duke Energy will become the sole owner of the Brunswick facility and will hold 100 percent ownership of the facility. The conforming license amendments will remove references to NCEMPA. No physical changes to the facility or operational changes were proposed in the application and Duke Energy will remain as the licensed operator of the facility. This Order is effective upon issuance.

The United States (U.S.) Nuclear Regulatory Commission (NRC) is issuing a notice regarding a finalized Memorandum of Understanding (MOU) between the NRC, the U.S. Department of Homeland Security (DHS) and the U.S. Department of Transportation (DOT) that defines a cooperative working relationship between the agencies for radioactive material transportation security. The goal of the MOU is to ensure that the transportation of radioactive material in the U.S. and across U.S. borders is carried out in a secure manner that protects public health and safety, and in a manner that is not inimical to the common defense and security of the U.S.

The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 8.11, ``Applications of Bioassay for Uranium.'' This guide provides methods that the NRC staff considers acceptable for the development and implementation of a bioassay program for monitoring the intake of mixtures of uranium isotopes by occupationally exposed workers. This guide applies to licenses issued under ``Domestic Licensing of Special Nuclear Material.''

The U.S. Nuclear Regulatory Commission (NRC) is issuing a final revision to the following section of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' Section 13.6.2, ``Physical SecurityReview of Physical Security System DesignsStandard Design Certification and Operating Reactor Licensing Applications.''

The U.S. Nuclear Regulatory Commission (NRC) is announcing the availability of Interim Staff Guidance (ISG) for Natural Phenomena Hazards (NPH) in Fuel Cycle Facilities. Fuel cycle facility licensees are required to conduct and maintain an Integrated Safety Analysis (ISA). This analysis must examine potential accident sequences caused by process deviations or other events internal to the facility and credible external events, including natural phenomena. The staff is issuing this ISG to provide additional guidance to the NRC staff for the review of fuel cycle facilities ISA evaluation of accident sequences that may result from NPH. This ISG will be incorporated into future revisions of Appendix D of Chapter 3 of NUREG 1520, ``Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility.'' Specific emphasis was provided on seismic hazards due to recent events such as the Fukushima Dai-ichi accident and recent updates to the U.S. Geological Survey hazard curves.

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG-1927, Revision 1, ``Standard Review Plan for Renewal of Specific Licenses and Certificates of Compliance for Dry Storage of Spent Nuclear Fuel.'' The draft NUREG provides guidance to the NRC staff for the safety review of renewal applications for specific licenses of independent spent fuel storage installations (ISFSIs) and certificates of compliance (CoCs) of spent fuel storage casks. The NRC is soliciting public comments on this draft NUREG and will consider received comments as it finalizes the guidance.

The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of eight amendment requests. The amendment requests are for Peach Bottom Atomic Power Station, Unit 3; Beaver Valley Power Station, Units Nos. 1 and 2; Monticello Nuclear Generating Plant; Fort Calhoun Station, Unit No. 1; Salem Nuclear Generating Station, Unit Nos. 1 and 2; Susquehanna Steam Electric Station, Unit Nos. 1 and 2; Browns Ferry Nuclear Plant, Unit 3; and Callaway Plant, Unit 1. For each amendment request, the NRC proposes to determine that they involve no significant hazards consideration. In addition, each amendment request contains sensitive unclassified non-safeguards information (SUNSI).

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1323, ``Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Startup Testing.'' This guide describes methods and procedures that the staff of the NRC considers acceptable when a developing a comprehensive vibration assessment program (CVAP) for power reactor internals during preoperational and startup testing.

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1305, ``Acceptance of Commercial-Grade Design and Analysis Computer Programs for Nuclear Power Plants.'' This DG provides new (i.e., not preceded by earlier guidance on the same subject) guidance that describes acceptance methods that the staff of the NRC considers acceptable in meeting regulatory requirements for acceptance and dedication of commercial- grade design and analysis computer programs for nuclear power plants.

On January 27, 2010, the U.S. Nuclear Regulatory Commission (NRC) notified the public of its opportunity to participate in the scoping process associated with the preparation of an environmental impact statement (EIS) related to the review of the license renewal application submitted by Pacific Gas and Electric Company (PG&E) for the renewal of Facility Operating Licenses DPR-80 and DPR-82 for an additional 20 years of operation at Diablo Canyon Power Plant (DCPP), Units 1 and 2. The current operating licenses for DCPP, Units 1 and 2 expire on November 2, 2024, and August 26, 2025, respectively. The scoping period closed on April 12, 2010. The NRC has decided to reopen the scoping process and allow members of the public an additional opportunity to participate.