Prairie Island Nuclear Generating Plant, Unit 1, Northern States Power Company-Minnesota; Notice of Consideration of Issuance of Amendment to Facility Operating License Involving No Significant Hazards Considerations; Correction
This document corrects a notice appearing in the Federal Register on February 22, 2011 (76 FR 9827), which informed the public that the Nuclear Regulatory Commission was considering the issuance of amendments to Facility Operating License Nos. DPR-42 and DPR-60, respectively, for the Prairie Island Nuclear Generating Plant, Units 1 and 2. This action is necessary to correct the affected Facility License and Docket Nos., since the amendment request applies to Unit 1 only.
Public Workshop to Discuss Low-Level Radioactive Waste Management
The U.S. Nuclear Regulatory Commission (NRC), in coordination with the U.S. Department of Energy (DOE), plans to conduct a workshop to discuss possible approaches to revising the regulatory framework for the management of commercial low-level radioactive waste (LLW). The purpose of this workshop is to gather information from a broad spectrum of stakeholders concerning the NRC's proposed options for a comprehensive revision to NRC's and DOE's waste regulations and to discuss possible options.
Dan Kane; Denial of Petition for Rulemaking
The Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM) submitted by Dan Kane. Mr. Kane requested that the NRC rescind the Waste Confidence Rule, suspend all ongoing reactor licensing proceedings, and phase out operations at all operating nuclear power plants. The NRC is denying the petition because, contrary to the assertions made in the PRM, the Commission's Waste Confidence Decision and Rule consider the political uncertainty discussed in the petition and do not depend on the availability of a repository at Yucca Mountain, Nevada.
Amendments to Adjudicatory Process Rules and Related Requirements
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is proposing to amend its adjudicatory rules of practice. This proposed rule would make changes to the NRC's adjudicatory process that NRC believes will promote fairness, efficiency, and openness in NRC adjudicatory proceedings. This proposed rule would also correct errors and omissions that have been identified since the major revisions to the NRC's Rules of Practice in early 2004.
AP1000 Design Certification Amendment
The U.S. Nuclear Regulatory Commission (NRC or Commission) proposes to amend its regulations to certify an amendment to the AP1000 standard plant design. The purpose of the amendment is to replace the combined license (COL) information items and design acceptance criteria (DAC) with specific design information, address the effects of the impact of a large commercial aircraft, incorporate design improvements, and increase standardization of the design. Upon NRC rulemaking approval of its amendment to the AP1000 design, an applicant seeking an NRC license to construct and operate a nuclear power reactor using the AP1000 design need not demonstrate in its application the safety of the certified design. The applicant for this amendment to the AP1000 certified design is Westinghouse Electric Company, LLC (Westinghouse). The public is invited to submit comments on this proposed design certification rule (DCR), the revised generic design control document (DCD) that would be incorporated by reference into the DCR, and the environmental assessment (EA) for this amendment to the AP1000 design.
Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System Voltages; Reopening of Public Comment Period
This notice revises a notice published on January 18, 2011, in the Federal Register (76 FR 2924), which announced, in part, that the public comment period for the U.S. Nuclear Regulatory Commission's (NRC's) Draft Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System Voltages, closes on February 17, 2011. The purpose of this notice is to reopen the public comment period on the Draft RIS for an additional 30 days to allow more time for industry to assemble comments.
Office of New Reactors; Proposed Revision 1 to Standard Review Plan, Section 188.8.131.52 on Administrative Procedures-General; Correction
This document corrects a notice appearing in the Federal Register on February 9, 2011, that announced the solicitation for comments of the proposed Revision 1 to Standard Review Plan, Section 184.108.40.206 on Administrative ProceduresGeneral. This action is necessary to correct the Agencywide Documents Access and Management System (ADAMS) accession number for the redline document mentioned in the last line under the SUMMARY section.
Agency Information Collection Activities: Proposed Collection; Comment Request
The NRC invites public comment about our intention to request the OMB's approval for renewal of an existing 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 (44 U.S.C. Chapter 35). Information pertaining to the requirement to be submitted: 1. The title of the information collection: NRC Form 64, ``Travel Voucher'' (Part 1); NRC Form 64A, ``Travel Voucher'' (Part 2); and NRC Form 64B, ``Optional Travel Voucher'' (Part 2). 2. Current OMB approval number: 3150-0192. 3. How often the collection is required: On occasion. 4. Who is required or asked to report: Contractors, consultants and invited NRC travelers who travel in the course of conducting business for the NRC. 5. The number of annual respondents: 100. 6. The number of hours needed annually to complete the requirement or request: 100 (1 hour per form). 7. Abstract: Consultants, contractors, and those invited by the NRC to travel (e.g., prospective employees) must file travel vouchers and trip reports in order to be reimbursed for their travel expenses. The information collected includes the name, address, social security number, and the amount to be reimbursed. Travel expenses that are reimbursed are confined to those expenses essential to the transaction of official business for an approved trip. Submit, by April 19, 2011, 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?
Notice of Availability of the Proposed Models for Plant-Specific Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, “Technical Specifications End States, NEDC-32988-A,” for Boiling Water Reactor Plants Using the Consolidated Line Item Improvement Process
The NRC is announcing the availability of the model application (with model no significant hazards consideration (NSHC) determination) and model safety evaluation (SE) for plant-specific adoption of Technical Specifications Task Force (TSTF) Traveler TSTF- 423, Revision 1, ``Technical Specifications End States, NEDC-32988-A,'' for boiling water reactor (BWR) plants using the consolidated line item improvement process (CLIIP). TSTF-423, Revision 1, is available in the Agencywide Documents Access and Management System (ADAMS) under Accession Number ML093570241. The changes in TSTF-423, Revision 1, modify every Required Action with the preferred end state with addition of a Note prohibiting the use of the provisions of limiting condition for operation (LCO) 3.0.4.a to enter the end state Mode within the Applicability during startup. The Bases of each Required Action is revised to describe the Note. Additionally, this revision to TSTF-423 removes the proposed changes to Technical Specification (TS) 220.127.116.11, ``Primary Containment.'' This model SE will facilitate expedited approval of plant-specific adoption of TSTF-423, Revision 1. Please note, this notice of availability (NOA) supersedes in its entirety the NOA for TSTF-423, Revision 0, published in the Federal Register on March 23, 2006 (71 FR 14726-14745, ADAMS Accession Number ML060760206). You can access publicly available documents related to this notice using the following methods: NRC's Public Document Room (PDR): The public may examine and have copied, for a fee, publicly available documents at the NRC's PDR, Public File Area O1 F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. NRC's Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received at the NRC are available electronically at the NRC's Electronic Reading Room at http:/ /www.nrc.gov/reading-rm/adams.html. From this page, the public can gain entry into the ADAMS, which provides text and image files of NRC's public documents. If you do not have access to the ADAMS, or if there are problems in accessing the documents located in the ADAMS, contact the NRC's PDR reference staff at 1-800-397-4209, 301-415-4737, or by e- mail to email@example.com. The model application (with model NSHC determination) and model SE for plant-specific adoption of TSTF-423, Revision 1, are available electronically under ADAMS Accession Number ML0126730688. The NRC staff disposition of comments received to the Notice of Opportunity for Public Comment announced in the Federal Register on December 14, 2005 (70 FR 74037), is available electronically under ADAMS Accession Number ML102700373. Federal rulemaking Web site: Public comments received and supporting materials related to this notice can be found at http:// www.regulations.gov by searching on Docket ID: NRC-2011-0039.
Notice of Availability of Final Environmental Impact Statement for the AREVA Enrichment Services LLC Proposed Eagle Rock Enrichment Facility in Bonneville County, ID
Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) has published the Final Environmental Impact Statement (EIS) for the AREVA Enrichment Services LLC (AES) Proposed Eagle Rock Enrichment Facility (EREF). On December 30, 2008, AES submitted a license application to the NRC that proposes the construction, operation, and decommissioning of a gas centrifuge-based uranium enrichment facility on a presently undeveloped site near Idaho Falls in Bonneville County, Idaho (the ``proposed action''). This application is for a license to possess and use byproduct material, source material, and special nuclear material at the proposed uranium enrichment facility. The application included an Environmental Report (ER) regarding the proposed action. AES subsequently submitted revisions to the license application on April 23, 2009 (Revision 1), and April 30, 2010 (Revision 2), which included ER Revision 1 and ER Revision 2, respectively. License application Revision 1 addresses the expansion of the proposed EREF to increase its production capacity from 3.3 million Separative Work Units (SWUs) per year to 6.6 million SWUs per year; and ER Revision 1 includes information on the environmental impacts of the proposed 6.6- million-SWU-per-year EREF. Revision 2 to the license application and the ER incorporates into Revision 1 additional information that AES previously provided the NRC in response to NRC staff requests for additional information for its safety and environmental reviews, as well as supplemental information on a proposed electrical transmission line required to power the proposed EREF. On June 17, 2009, AES submitted a request for an exemption from certain NRC regulations so that it could commence certain preconstruction activities (e.g., site preparation) on the proposed EREF site prior to the NRC's decision on whether to grant or deny a license. On March 17, 2010, the NRC granted an exemption authorizing AES to conduct the requested preconstruction activities. The Final EIS is being issued as part of the NRC's process to decide whether to issue a license to AES, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) parts 30, 40, and 70, to construct and operate the proposed uranium enrichment facility. Specifically, AES proposes to use gas centrifuge technology to enrich the uranium-235 isotope found in natural uranium to concentrations up to 5 percent by weight. The enriched uranium would be used to manufacture nuclear fuel for commercial nuclear power reactors. In the Final EIS, the NRC staff assessed the potential environmental impacts from the preconstruction, construction, operation, and decommissioning of the proposed EREF project. The Final EIS was prepared in compliance with the National Environmental Policy Act of 1969, as amended (NEPA), and the NRC's regulations for implementing NEPA in 10 CFR part 51. The NRC staff assessed the impacts of the proposed action on land use, historic and cultural resources, visual and scenic resources, air quality, geology and soils, water resources, ecological resources, noise, transportation, public and occupational health, waste management, socioeconomics, and environmental justice. Additionally, the NRC staff analyzed and compared the benefits and costs of the proposed action. In preparing this Final EIS, the NRC staff also reviewed, considered, evaluated, and addressed the public comments received on the Draft EIS. In addition to the proposed action, the NRC staff considered the no-action alternative and other alternatives. Under the no-action alternative, the NRC would deny AES's request to construct and operate a uranium enrichment facility at the EREF site. The no-action alternative serves as a baseline for comparison of the potential environmental impacts of the proposed action. Other alternatives the NRC staff considered but eliminated from further analysis include: (1) Alternative sites for the EREF; (2) alternative sources of enriched uranium; and (3) alternative technologies for uranium enrichment. These alternatives were eliminated from further analysis due to economic, environmental, national security, technological maturity, or other reasons. The Final EIS also discusses alternatives for the disposition of depleted uranium hexafluoride (UF6) resulting from enrichment operations over the lifetime of the proposed EREF. After weighing the impacts, costs, and benefits of the proposed action and comparing alternatives, the NRC staff, in accordance with 10 CFR 51.91(d), sets forth its recommendation regarding the proposed action. The NRC staff recommends that, unless safety issues mandate otherwise, the proposed action should be approved (i.e., NRC should issue a license). In this regard, the NRC staff has concluded that the environmental impacts of the proposed action are generally small, and that implementation of the proposed AES environmental monitoring program and AES mitigation measures discussed in the Final EIS would eliminate or substantially lessen any adverse environmental impacts associated with the proposed action. Document Availability: The Final EIS and other publicly available documents related to this notice can be accessed using any of the methods described in this section. Because one appendix of the Final EIS contains Sensitive Unclassified Non-Safeguards Information (SUNSI), this appendix has been withheld from public inspection in accordance with 10 CFR 2.390, ``Availability of Public Records.'' This appendix contains proprietary business information as well as security-related information. The NRC staff has considered the information in this appendix in forming the conclusions presented in the EIS. Procedures for obtaining access to SUNSI were previously published in the NRC's Notice of Hearing and Commission Order related to AES's application for the EREF. Notice of Receipt of Application for License; Notice of Consideration of Issuance of License; Notice of Hearing and Commission Order and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information and Safeguards Information for Contention Preparation; In the Matter of Areva Enrichment Services, LLC (Eagle Rock Enrichment Facility), 74 FR. 38052 (July 30, 2009). NRC's Public Document Room (PDR): The public may examine and have copied, for a fee, publicly available documents related to the EREF project at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. Members of the public can contact the NRC's PDR reference staff by calling 1-800-397- 4209, by faxing a request to 301-415-3548, or by e-mail to firstname.lastname@example.org. NRC Web sites: Documents related to this notice are available on the NRC's AREVA Enrichment Services, LLC Gas Centrifuge Facility website at http://www.nrc.gov/materials/fuel-cycle-fac/arevanc.html. The Final EIS for the proposed EREF may also be accessed on the internet at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/ by selecting ``NUREG-1945.'' NRC's Agencywide Documents Access and Management System (ADAMS): Members of the public can access the NRC's ADAMS at http://www.nrc.gov/ reading-rm/adams.html. From this Web site, enter the ADAMS Accession Numbers included here for AES's license application and ER Revision 2 (ADAMS Accession Number: ML101610549), the exemption authorizing certain preconstruction activities (ADAMS Accession Number: ML093220446), and NRC's Final EIS (ADAMS Accession Numbers: ML11014A005 [Volume 1] and ML11014A006 [Volume 2]). Federal rulemaking Web site: Materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID: NRC- 2009-0187. Public Library: A copy of the Final EIS will be available at the Idaho Falls Public Library, 457 West Broadway, Idaho Falls, ID 83402, 208-612-8460.
License and Certificate of Compliance Terms
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is amending its regulations that govern licensing requirements for the independent storage of spent nuclear fuel. These amendments include changes that enhance the effectiveness and efficiency of the licensing process for spent nuclear fuel storage. Specifically, they extend and clarify the term limits for storage cask Certificates of Compliance (CoCs) and independent spent fuel storage installation (ISFSI) specific licenses. The amendments also provide consistency between the general and specific ISFSI license requirements, and allow general licensees subject to these regulations to implement changes authorized by an amended CoC to a cask loaded under the initial CoC or an earlier amended CoC (a ``previously loaded cask'').
Office of New Reactors; Interim Staff Guidance on Impacts of Construction of New Nuclear Power Plants on Operating Units at Multi-Unit Sites
The NRC staff is soliciting public comment on its proposed Interim Staff Guidance (ISG) COL-ISG-022 entitled ``Impacts of Construction of New Nuclear Power Plants on Operating Units at Multi-Unit Sites'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093440252). Through this ISG, the NRC staff provides guidance for assessing combined license (COL) applicant compliance with the requirements of Title 10 of the Code of Federal Regulations, Section 52.79(a)(31) (10 CFR 52.79(a)(31)). This regulation requires applicants for a COL intending to construct and operate new nuclear power plants (NPPs) on multi-unit sites to provide an evaluation of the potential hazards to structures, systems, and components (SSCs) important to safety for the operating units resulting from construction activities. The NRC staff issues COL-ISGs to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for COLs by the Office of New Reactors (NRO). This ISG supplements the guidance contained in Regulatory Guide (RG) 1.206, Revision 0, ``Combined License Applications for Nuclear Power Plants (LWR Edition).'' In addition, this ISG supplements the guidance provided for NRC staff review of COL applications contained in NUREG- 0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (SRP),'' Chapter 1.0, dated November 2007. The NRC staff intends to incorporate the final approved COL-ISG-022 into the next revision of RG 1.206 and NUREG-0800 SRP Chapter 1.0.
Office of New Reactors; Proposed Revision 1 to Standard Review Plan, Section 18.104.22.168 on Administrative Procedures-General
The NRC is soliciting public comment on NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' on a proposed Revision 1 to Standard Review Plan (SRP), Section 22.214.171.124 on ``Administrative ProceduresGeneral,'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110100193). The previous version of this SRP section was published in July 19, 2010, as proposed revision 1 (ADAMS Accession No. ML101340264). Since then, the NRC staff has made substantial changes to that guidance and it is being re-noticed for comments (Enclosure 1, ADAMS Accession No. ML110100212). A redline document comparing the version of the previous SRP Section 126.96.36.199, Revision 1 that was issued for public comments and the current version can be found under ADAMS Accession No. ML101340165. The NRC staff issues notices to facilitate timely implementation of the current staff guidance and to facilitate activities associated with the review of amendment applications and review of design certification and combined license applications for the Office of New Reactors. The NRC staff intends to incorporate the final approved guidance into the next revision of NUREG-0800, SRP Section 188.8.131.52, Revision 1 and Regulatory Guide 1.206, ``Combined License Applications for Nuclear Power Plants (LWR Edition),'' June 2007.