Nuclear Regulatory Commission 2013 – Federal Register Recent Federal Regulation Documents

The U.S. Nuclear Regulatory Commission (NRC) is considering an amendment to Source Materials License SUA-1598 for continued uranium production operations and in-situ recovery (ISR) of uranium at the Lost Creek Project in Sweetwater County, Wyoming.

The U.S. Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 4.4, ``Reporting Procedure for Mathematical Models Selected to Predict Heated Effluent Dispersion in Natural Water Bodies.'' The guide is being withdrawn because it is obsolete and new guidance has been included in models developed by the Environmental Protection Agency (EPA) that provides updated direction.

The U.S. Nuclear Regulatory Commission (NRC) requests public comment on Draft Spent Fuel Storage and Transportation Interim Staff Guidance No. 26A (SFST-ISG-26A), Revision 0, ``Shielding and Radiation Protection Review Effort and Licensing Conditions for 10 CFR Part 72 Applications.''

The U.S. Nuclear Regulatory Commission (NRC) is providing notice of issuance of a license renewal for Materials License No. SUA- 1341 to Uranium One USA, Inc. (Uranium One) for its Willow Creek Uranium In Situ Recovery (ISR) Project in Johnson and Campbell Counties, Wyoming.

The U.S. Nuclear Regulatory Commission is correcting a notice that was published in the Federal Register (FR) on March 5, 2013 (78 FR 14361), regarding the order approving the proposed internal restructuring and indirect transfer of license. This action is necessary to correct the date of a safety evaluation that was incorrectly referenced in Section II of this notice. The safety evaluation date was corrected by letter dated February 25, 2013, which is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML13056A266.

The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to establish security requirements for the use and transport of category 1 and category 2 quantities of radioactive material. The NRC considers these quantities to be risk significant and, therefore, to warrant additional protection. Category 1 and category 2 thresholds are based on the quantities established by the International Atomic Energy Agency (IAEA) in its Code of Conduct on the Safety and Security of Radioactive Sources, which the NRC endorses. The objective of this final rule is to provide reasonable assurance of preventing the theft or diversion of category 1 and category 2 quantities of radioactive material. The regulations also include security requirements for the transportation of irradiated reactor fuel that weighs 100 grams or less in net weight of irradiated fuel. The final rule affects any licensee that possesses an aggregated category 1 or category 2 quantity of radioactive material, any licensee that transports these materials using ground transportation, and any licensee that transports small quantities of irradiated reactor fuel. The rule also considers a petition for rulemaking (PRM-71-13) submitted by the State of Washington that requested that the NRC adopt the use of global positioning satellite tracking as a national requirement for vehicles transporting highly radioactive mobile or portable radioactive devices.

The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. (NAC) Modular Advanced Generation Nuclear All-purpose Storage (MAGNASTOR[supreg]) System listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 3 to Certificate of Compliance (CoC) No. 1031. Amendment No. 3 revises authorized contents to include: Pressurized water reactor (PWR) damaged fuel contained in damaged fuel (DF) cans that are placed in a damaged fuel basket assembly; PWR fuel assemblies with nonfuel hardware per the expanded definition in the Amendment No. 3 application; and PWR fuel assemblies with up to five activated stainless steel fuel replacement rods at a maximum burnup/exposure of 32.5 gigawatt days per metric ton of uranium (GWd/MTU). Additionally, Amendment No. 3 revises paragraph 4.3.1(i) in appendix A of the CoC Technical Specifications (TS) to clarify that the maximum design basis earthquake accelerations of 0.37g in the horizontal direction (without cask sliding) and 0.25g in the vertical direction at the independent spent fuel storage installation (ISFSI) pad top surface do not result in cask tip-over. Amendment No. 3 also makes additional changes to appendix A, Technical Specifications and Design Features for the MAGNASTOR[supreg] System, and appendix B, Approved Contents for the MAGNASTOR[supreg] System, of the CoC.

The U.S. Nuclear Regulatory Commission (NRC) is granting the request of Florida Power Corporation (the licensee), through its owner Duke Energy, to withdraw its June 15, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112070659), application for proposed amendment to Facility Operating License No. DPR-72 for the Crystal River Unit 3 Nuclear Generating Plant (CR-3), located in Florida, Citrus County. The proposed amendment would have revised the facility operating license and the technical specifications to support operation at an increased core thermal power level.

The U.S. Nuclear Regulatory Commission (NRC) has issued for public comment a document entitled: Compendium of Analyses to Investigate Select Level 1 Probabilistic Risk Assessment End-State Definition and Success Criteria Modeling IssuesDraft Report for Comment.

The U.S. Nuclear Regulatory Commission (NRC) is providing a notice of consent to the direct transfer of licenses and issuance of License Amendment 7 to Materials License No. SNM-7003 for the American Centrifuge Lead Cascade Facility (Lead Cascade), and Amendment 3 to Materials License No. SNM-2011 for the American Centrifuge Plant (ACP). This action authorized the direct transfer of these licenses from USEC Inc. (USEC) to American Centrifuge Operating, LLC (ACO).

The U.S. Nuclear Regulatory Commission (NRC) invites public comment about our intention to request the OMB's approval for a new information collection that is summarized below. We are required to publish this notice in the Federal Register under the provisions of the Paperwork Reduction Act of 1995. Information pertaining to the requirement to be submitted: 1. The title of the information collection: Reactor Oversight Process External Survey. 2. Current OMB approval number: 3150-XXXX. 3. How often the collection is required: Once every 2 years. 4. Who is required or asked to report: Members of the public, licensees, and other interested stakeholders. 5. The number of annual respondents: 13. 6. The number of hours needed annually to complete the requirement or request: 13. 7. Abstract: The mission of the NRC is to regulate the nation's civilian use of byproduct, source, and special nuclear materials to ensure adequate protection of public health and safety, to promote the common defense and security, and to protect the environment. One way to support this mission is through the implementation of the Reactor Oversight Process (ROP), which is the agency's program to inspect, measure, and assess the safety performance of commercial nuclear power plants and to respond to any decline in performance. The NRC seeks to achieve continuous improvement of the ROP through the ROP self-assessment process. The CY 2013 and 2015 ROP self- assessments will rely, in part, on direct feedback from external stakeholders. The information collected through the voluntary survey will support this purpose, and a summary of the survey results will be included in the annual ROP self-assessment report to the Commission. Submit, by May 7, 2013, comments that address the following questions: 1. Is the proposed collection of information necessary for the NRC to properly perform its functions? Does the information have practical utility? 2. Is the burden estimate accurate? 3. Is there a way to enhance the quality, utility, and clarity of the information to be collected? 4. How can the burden of the information collection be minimized, including the use of automated collection techniques or other forms of information technology? The public may examine and have copied for a fee publicly available documents, including the draft supporting statement, at the NRC's Public Document Room, Room O-1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. The OMB clearance requests are available at the NRC's Web site: https://www.nrc.gov/public-involve/ doc-comment/omb/. The document will be available on the NRC's home page site for 60 days after the signature date of this notice. Comments submitted in writing or in electronic form will be made available for public inspection. Because your comments will not be edited to remove any identifying or contact information, the NRC cautions you against including any information in your submission that you do not want to be publicly disclosed. Comments submitted should reference Docket No. NRC-2013-0018. You may submit your comments by any of the following methods. Electronic comments: Go to https:// www.regulations.gov and search for Docket No. NRC-2013-0018. Mail comments to the NRC Clearance Officer, Tremaine Donnell (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. Questions about the information collection requirements may be directed to the NRC Clearance Officer, Tremaine Donnell (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, by telephone at 301- 415-6258, or by email to INFOCOLLECTS.Resource@NRC.GOV.