Nuclear Regulatory Commission 2005 – Federal Register Recent Federal Regulation Documents

The Nuclear Regulatory Commission (NRC) is amending its regulations to revise the Holtec International HI-STORM 100 cask system listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 2 to Certificate of Compliance (CoC) Number 1014. Amendment No. 2 modifies the cask design to include changes to materials used in construction, changes to the types of fuel that can be loaded, changes to shielding and confinement methodologies and assumptions, revisions to various temperature limits, changes in allowable fuel enrichments, and other changes to reflect current NRC staff guidance and use of industry codes, under a general license.

The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. 1. Type of submission, new, revision, or extension: Revision. 2. The title of the information collection: 10 CFR Part 100, ``Reactor Site Criteria''. 3. The form number if applicable: Not applicable. 4. How often the collection is required: As necessary in order for NRC to assess the adequacy of proposed seismic design bases and the design bases for other geological hazards for nuclear power and test reactors constructed and licensed in accordance with 10 CFR parts 50 and 52 and the Atomic Energy Act of 1954, as amended. 5. Who will be required or asked to report: Applicants and licensees for nuclear power and test reactors. 6. An estimate of the number of annual responses: 2. 7. The estimated number of annual respondents: .33 (1 respondent every 3 years). 8. An estimate of the total number of hours needed annually to complete the requirement or request: 8,711. 9. An indication of whether section 3507(d), Pub. L. 104-13 applies: Not applicable. 10. Abstract: 10 CFR part 100, ``Reactor Site Criteria,'' establishes approval requirements for proposed sites for the purpose of constructing and operating stationary power and testing reactors pursuant to the provisions of 10 CFR parts 50 or 52. These reactors are required to be sited, designed, constructed, and maintained to withstand geologic hazards, such as faulting, seismic hazards, and the maximum credible earthquake, to protect the health and safety of the public and the environment. Non-seismic siting criteria must also be evaluated. Non-seismic siting criteria include such factors as population density, the proximity of man-related hazards, and site atmospheric dispersion characteristics. NRC uses the information required by 10 CFR part 100 to evaluate whether natural phenomena and potential man-made hazards will be appropriately accounted for in the design of nuclear power and test reactors. A copy of the final supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O-1 F21, Rockville, MD 20852. OMB clearance requests are available at the NRC Worldwide Web site: https:// www.nrc.gov/public-involve/doc-comment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions should be directed to the OMB reviewer listed below by July 6, 2005. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. John A. Asalone, Office of Information and Regulatory Affairs (3150-0093), NEOB-10202, Office of Management and Budget, Washington, DC 20503. Comments can also be e-mailed to JohnA.Asalone@omb.eop.gov or submitted by telephone at (202) 395-4650. The NRC Clearance Officer is Brenda Jo. Shelton, 301-415-7233.

The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. 1. Type of submission, new, revision, or extension: Extension. 2. The title of the information collection: 10 CFR Part 75 Safeguards on Nuclear Material, Implementation of US/IAEA Agreement. 3. The form number if applicable: N/A. 4. How often the collection is required: Installation information is submitted upon written notification from the Commission. Changes are submitted as they occur. Nuclear material accounting and control information is submitted in accordance with specific instructions. 5. Who will be required or asked to report: All persons licensed or certified by the Commission or Agreement States to possess source or special nuclear material at an installation specified on the U.S. eligible facilities list as determined by the Secretary of State or his designee and filed with the Commission, as well as holders of construction permits and persons who intend to receive source material. 6. An estimate of the number of annual responses: 8. 7. The estimated number of annual respondents: Seven, one of which perform the reporting and recordkeeping and the other six perform the recordkeeping only. The NRC-licensed facilities selected for inspection will be reporting or updating design information. This one facility and the six facilities selected pursuant to a separate protocol will maintain transfer and material balance records, but reporting to the IAEA will be through the U.S. State system (Nuclear Materials Management and Safeguards System). 8. An estimate of the total number of hours needed annually to complete the requirement or request: 2,800 (.2 hours for reporting and 2,800 hours for recordkeeping [400 hours per recordkeeper]). 9. An indication of whether Section 3507(d), Public Law 104-13 applies: N/A. 10. Abstract: 10 CFR Part 75 establishes requirements to implement the agreement between the United States and the International Atomic Energy Agency (IAEA). Under that agreement, NRC is required to collect information and make it available to the IAEA. A copy of the final supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O-1 F21, Rockville, MD 20852. OMB clearance requests are available at the NRC worldwide Web site: https:// www.nrc.gov/public-involve/doc-comment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions should be directed to the OMB reviewer listed below by July 5, 2005. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. John Asalone, Office of Information and Regulatory Affairs (3150- 0055), NEOB-10202, Office of Management and Budget, Washington, DC 20503. Comments can also be e-mailed to JohnA.Asalone@ombeop.gov or submitted by telephone at (202) 395-3087. The NRC Clearance Officer is Brenda Jo. Shelton, 301-415-7233.

The Nuclear Regulatory Commission (NRC) is noticing the termination of the TNP Facility Operating (Possession Only) License, No. NPF-1, (NRC Docket No. 50-344), located near Portland, Oregon. Background: The TNP facility is located in Columbia County, Oregon, approximately 42 miles north of Portland, Oregon. TNP began commercial operation in May 1976. The reactor output was rated at 3411 MWt with an approximate net electrical output rating of 1130 MWe. The nuclear steam supply system was a four- loop pressurized water reactor designed by Westinghouse Electric Corporation. TNP was shut down for the last time on November 9, 1992. In August 1999, PGE submitted its License Termination Plan (LTP) for the TNP facility. Under the provisions of 10 CFR 50.82(a)(10), the NRC approved the LTP by license amendment dated February 12, 2001. PGE conducted decommissioning activities at TNP in accordance with the approved LTP from February 2001 to December 2004. In accordance with the approved LTP, the licensee conducted final status surveys (FSSs) to demonstrate that the facility and site meet the criteria for unrestricted release as presented in 10 CFR 20.1402. Details of the FSS results were submitted to the NRC in 10 separate FSS reports (FSSRs). PGE submitted an application for termination of the TNP Facility Operating (Possession Only) License, No. NPF-1, on December 20, 2004. The application states that PGE has completed remaining radiological decommissioning and FSSs of the TNP facility and site in accordance with the NRC-approved LTP, and the FSSs demonstrate that the facility and site meet the criteria for decommissioning and release of the site for unrestricted use that are stipulated in 10 CFR part 20, subpart E. The NRC conducted a number of performance-based in-process inspections of the licensee's FSS program during the decommissioning process. The purpose of the inspections was to verify that the FSS was being conducted in accordance with of the commitments made by the licensee in the LTP, and to evaluate the quality of the FSS by reviewing the FSS procedures, methodology, equipment, surveyor training and qualifications, document quality control, and survey data supporting the FSSRs. In addition, the NRC conducted a number of independent confirmatory surveys to verify the FSS results obtained and reported by the licensee. Confirmatory surveys consisted of surface scans for beta and gamma radiation, direct measurements for total beta activity, and collection of smear samples for determining removable radioactivity levels. The NRC staff reviewed the FSS Report and concludes that: (I) Dismantlement and decontamination activities were performed in accordance with the approved LTP; and (ii) The FSS and associated documentation, including an assessment of dose contributions associated with parts released for use before approval of the LTP, demonstrate that the facility and site have met the criteria for decommissioning in 10 CFR Part 20, Subpart E. Therefore, NRC is terminating TNP Facility Operating License No. NPF-1.

The Nuclear Regulatory Commission (NRC) is revising its regulations to change the references from Deputy Executive Director for Management Services to Deputy Executive Director for Information Services and Administration and Chief Information Officer. The revision is necessary to reflect a recent realignment in the Office of the Executive Director for Operations. This final rule is necessary to inform the public of organizational changes within the NRC.

The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. 1. Type of submission, new, revision, or extension: Extension. 2. The title of the information collection: Design Information QuestionnaireIAEAN-71 and associated Forms N-72, N-73, N-74, N-75, N-91, N-92, N-93, N-94. 3. The form number if applicable: IAEA Form N-71 and associated Forms N-72, N-73, N-74, N-75, N-91, N-92, N-93, N-94. 4. How often the collection is required: Approximately 1 time annually. 5. Who will be required or asked to report: Licensees of facilities on the U.S. eligible list who have been notified in writing by the Commission to submit the form. 6. An estimate of the number of annual responses: 1. 7. The estimated number of annual respondents: 1. 8. An estimate of the total number of hours needed annually to complete the requirement or request: 360 reporting hours (360 hours per response). 9. An indication of whether Section 3507(d), Pub. L. 104-13 applies: N/A. 10. Abstract: Licensees of facilities that appear on the U.S. eligible list, pursuant to the US/IAEA Safeguards Agreement, and who have been notified in writing by the Commission, are required to complete and submit a Design Information Questionnaire, IAEA Form N-71 (and the appropriate associated IAEA Form) or Form N-91, to provide information concerning their installation for use of the International Atomic Energy Agency. A copy of the final supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O-1 F21, Rockville, MD 20852. OMB clearance requests are available at the NRC worldwide Web site: https://www.nrc.gov/public- involve/doc-comment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions should be directed to the OMB reviewer listed below by June 27, 2005. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. John Asalone, Office of Information and Regulatory Affairs (3150-0056), NEOB-10202, Office of Management and Budget, Washington, DC 20503. Comments can also be e-mailed to JohnA.Asalone@ombeop.gov or submitted by telephone at (202) 395-3087. The NRC Clearance Officer is Brenda Jo. Shelton, 301-415-7233.

The Nuclear Regulatory Commission (NRC) is amending the licensing, inspection, and annual fees charged to its applicants and licensees. The amendments are necessary to implement the Omnibus Budget Reconciliation Act of 1990 (OBRA-90), as amended, which requires that the NRC recover approximately 90 percent of its budget authority in fiscal year (FY) 2005, less the amounts appropriated from the Nuclear Waste Fund (NWF). The total amount to be recovered for FY 2005 is approximately $540.7 million. After accounting for carryover and billing adjustments, the net amount to be recovered through fees is approximately $538 million.

Notice is hereby given that the staff of the U.S. Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) relating to changes to the completion time (CT) in Standard Technical Specification (STS) 3.6.1.3 ``Primary Containment Isolation Valves (PCIVs).'' The proposed change to the Technical Specifications (TS) would extend to 7 days the CT (or allowed outage time (AOT)) to restore an inoperable PCIV or isolate the affected penetration flow path for selected primary containment penetrations with two (or more) PCIVs and for selected primary containment penetrations with only one PCIV. This change is based on analyses provided in a generic topical report (TR) submitted by the Boiling Water Reactors Owner's Group (BWROG). The BWROG participants in the TS Task Force (TSTF) proposed this change to the STS in Change Traveler No. TSTF-454, Revision 0. This notice also includes a model no significant hazards consideration (NSHC) determination relating to this matter. The purpose of these models is to permit the NRC to efficiently process amendments to incorporate this change into plant-specific TS for General Electric boiling water reactors (BWRs). Licensees of nuclear power reactors to which the models apply can request amendments conforming to the models. In such a request, a licensee should confirm the applicability of the SE and NSHC determination to its plant. The NRC staff is requesting comments on the model SE and model NSHC determination before announcing their availability for referencing in license amendment applications.

The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations revising the Transnuclear, Inc., Standardized NUHOMS[reg] System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 8 to Certificate of Compliance Number (CoC No.) 1004. Amendment No. 8 to the Standardized NUHOMS[reg] System CoC would modify the cask design by adding a new spent fuel storage and transfer system, designated the NUHOMS[reg]-24PTH System. The NUHOMS[reg]-24PTH System consists of new or modified components: the -24PTH dry shielded canister (DSC); a new -24PTH DSC basket design; a modified horizontal storage module (HSM), designated the HSM-H; and a modified transfer cask (TC), designated the OS 197FC TC. The NUHOMS[reg]-24PTH System is designed to store fuel with a maximum average burnup of up to 62 gigawatts-day/metric ton of uranium; maximum average initial enrichment of 5.0 weight percent; minimum cooling time of 3.0 years; and maximum heat load of 40.8 kilowatts per DSC, under a general license.

This document corrects a notice published on May 17, 2005 (70 FR 28324), that announces the appointments to the NRC Performance Review Boards. This notice is necessary to correct an omission in the listing. On page 28324, in the third column, insert ``Annette Vietti-Cook, Secretary of the Commission'' after the listing for ``Jack R. Strosnider, Director, Office of Nuclear Material Safety and Safeguards.''

The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. 1. Type of submission, new, revision, or extension: Extension. 2. The title of the information collection: 10 CFR 81, Standard Specifications for Granting of Patent Licenses. 3. The form number if applicable: Not applicable. 4. How often the collection is required: Applications for licenses are submitted once. Other reports are submitted annually or as other events require. 5. Who will be required or asked to report: Applicants for and holders of NRC licenses to NRC inventions. 6. An estimate of the number of annual responses: 1. 7. The estimated number of annual respondents: 1. 8. An estimate of the total number of hours needed annually to complete the requirement or request: 37; however, no applications are anticipated during the next three years. 9. An indication of whether Section 3507(d), Pub. L. 104-13 applies: Not applicable. 10. Abstract: 10 CFR Part 81 establishes the standard specifications for the issuance of licenses to rights in inventions covered by patents or patent applications invested in the United States, as represented by or in the custody of the Commission and other patents in which the Commission has legal rights. A copy of the final supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room 0-1F21, Rockville, MD 20852. OMB clearance requests are available at the NRC Worldwide Web site: https:// www.nrc.gov/public-involve/doc-comment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions should be directed to the OMB reviewer listed below by June 22, 2005. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. John A. Asalone, Office of Information and Regulatory Affairs (3150-0121), NEOB-10202, Office of Management and Budget, Washington, DC 20503. Comments can also be e-mailed to JohnA.Asalone@omb.eop.gov or submitted by telephone at (202) 395-4650. The NRC Clearance Officer is Brenda Jo. Shelton, 301-415-7233.

The U.S. Nuclear Regulatory Commission (NRC) has announced the following appointments to the NRC Performance Review Boards. The following individuals are appointed as members of the NRC Performance Review Board (PRB) responsible for making recommendations to the appointing and awarding authorities on performance appraisal ratings and performance awards for Senior Executives and Senior Level employees: Samuel J. Collins, Regional Administrator, Region I. Karen D. Cyr, General Counsel. James E. Dyer, Director, Office of Nuclear Reactor Regulation. Jesse L. Funches, Chief Financial Officer. William F. Kane, Deputy Executive Director for Reactor & Preparedness Programs, Office of the Executive Director for Operations. Bruce S. Mallett, Regional Administrator, Region IV. Luis A. Reyes, Executive Director for Operations. Jacqueline E. Silber, Deputy Executive Director for Information Services and Administration and Chief Information Officer. Jack R. Strosnider, Director, Office of Nuclear Material Safety and Safeguards. Michael F. Weber, Deputy Director, Office of Nuclear Security and Incident Response. James T. Wiggins, Deputy Director, Office of Nuclear Regulatory Research. The following individuals will serve as members of the NRC PRB Panel that was established to review appraisals and make recommendations to the appointing and awarding authorities for NRC PRB members: Stephen G. Burns, Deputy General Counsel, Office of the General Counsel. Carl J. Paperiello, Director, Office of Nuclear Regulatory Research. Martin J. Virgilio, Deputy Executive Director for Materials, Research, State and Compliance Programs. All appointments are made pursuant to Section 4314 of Chapter 43 of Title 5 of the United States Code.