Nuclear Regulatory Commission May 25, 2005 – Federal Register Recent Federal Regulation Documents

Agency Information Collection Activities: Proposed Collection; Comment Request
Document Number: E5-2632
Type: Notice
Date: 2005-05-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The NRC is preparing a submittal to OMB for review of continued approval of information collections 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: 10 CFR Part 26, ``Fitness for Duty Program.'' 2. Current OMB approval number: 3150-0146. 3. How often the collection is required: On occasion. 4. Who is required or asked to report: All licensees authorized to construct or operate a nuclear power reactor; all licensees authorized to use, possess, or transport Category 1 nuclear material; and contractors/vendors who have developed a fitness-for-duty program that is formally reviewed and approved by a licensee, which meets the requirements of part 26. 5. The number of annual respondents: 69. 6. The number of hours needed annually to complete the requirement or request: 61,143 (5,853 hours reporting [an average of 4.3 hours/ response] and 55,290 hours recordkeeping [an average of 801 hours/ recordkeeper]). 7. Abstract: 10 CFR Part 26, ``Fitness for Duty Program,'' requires licensees of nuclear power plants, contractors/vendors who have developed a fitness-for-duty program that is formally reviewed by a licensee, and licensees authorized to possess, use, or transport Category 1 nuclear material to implement fitness-for-duty programs to assure that personnel are not under the influence of any substance or mentally or physically impaired, to retain certain records associated with the management of these programs, and to provide reports concerning significant events and program performance. Compliance with these program requirements is mandatory for licensees subject to 10 CFR part 26. In addition, licensees of nuclear power plants are required to comply with security order EA-03-038, which implements work hour controls for security force personnel and requires licensees to retain certain records associated with the management of this security order. Submit, by July 25, 2005, comments that address the following questions: 1. Is the proposed collection of information necessary for the NRC toproperly 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? A copy of the draft 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 about the information collection requirements may be directed to the NRC Clearance Officer, Brenda Jo. Shelton, U.S. Nuclear Regulatory Commission, T-5 F53, Washington, DC 20555-0001, by telephone at 301-415-7233, or by internet electronic mail at infocollectsnrc.gov.
Notice of Opportunity To Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Revision to the Completion Time in STS 3.6.1.3, “Primary Containment Isolation Valves” for General Electric Boiling Water Reactors Using the Consolidated Line Item Improvement Process
Document Number: E5-2631
Type: Notice
Date: 2005-05-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
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.
Export and Import of Nuclear Equipment and Material; Exports to Syria Embargoed
Document Number: 05-10391
Type: Rule
Date: 2005-05-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is amending its export/import regulations to remove Syria from the list of restricted destinations and add it to the list of embargoed destinations. This amendment is necessary to conform the NRC's regulations with U.S. law and foreign policy.
List of Approved Spent Fuel Storage Casks: Standardized NUHOMS®
Document Number: 05-10390
Type: Proposed Rule
Date: 2005-05-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
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.
List of Approved Spent Fuel Storage Casks: Standardized NUHOMS®
Document Number: 05-10389
Type: Rule
Date: 2005-05-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is amending 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 will 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.
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