Nuclear Regulatory Commission March 2007 – Federal Register Recent Federal Regulation Documents
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Advisory Committee on the Medical Uses of Isotopes: Call for Nominations
The U.S. Nuclear Regulatory Commission (NRC) is advertising for nominations for the position of nuclear pharmacist on the Advisory Committee on the Medical Uses of Isotopes (ACMUI).
Project on Government Oversight and Union of Concerned Scientists; Receipt of Petition for Rulemaking
The U.S. Nuclear Regulatory Commission (NRC) is publishing for public comment a notice of receipt of a petition for rulemaking, dated February 23, 2007, which was filed with the Commission by David Lochbaum, on behalf of the Project On Government Oversight and the Union of Concerned Scientists. The petition was docketed by the NRC on March 5, 2007, and has been assigned Docket No. PRM-50-83. The petitioners request that the NRC amend its regulations to require periodic demonstrations by applicable local, State and Federal entities to ensure that nuclear power plants can be adequately protected against radiological sabotage greater than the design basis threat.
Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB) Review; Comment Request
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: Revision. 2. The title of the information collection: Policy Statement for the ``Criteria for Guidance of States and NRC in Discontinuance of NRC Regulatory Authority and Assumption Thereof By States Through Agreement,'' Maintenance of Existing Agreement State Programs, Request for Information Through the Integrated Materials Performance Evaluation Program (IMPEP) Questionnaire, and Agreement State Participation in IMPEP. 3. The form number if applicable: Not applicable. 4. How often the collection is required: There are four activities that occur under this collection: information collection activities required by the IMPEP questionnaire in preparation for an IMPEP review conducted no less frequently than every four years; while the following activities are all collected on an annual basispolicy statement addressing requirements for new Agreement States; participation by Agreement States in the IMPEP reviews; and annual requirements for Agreement States to maintain their programs. 5. Who is required or asked to report: 34 Agreement States who have signed Section 274b. Agreements with NRC. 6. An estimate of the number of annual responses: For States interested in becoming an Agreement State, approximately one State per year. For Agreement State participation in IMPEP reviews: 10 (7 State, 1 NRC Region, and 2 Follow-up reviews per year). For maintenance of existing Agreement State programs: 34 States. For Agreement State response to IMPEP questionnaires: 7 States. The total number of annual responses is 52. 7. The estimated number of annual respondents: 34. 8. An estimate of the total number of hours needed annually to complete the requirement or request: For States interested in becoming Agreement States: Approximately 4,300 hours. For Agreement State participation in 10 IMPEP reviews (7 Agreement State, 1 NRC Regional Office and 2 Follow-up reviews): 360 hours (an average of 36 hours per review). For maintenance of existing Agreement State programs: 255,600 hours (an average of approximately 7,517 hours per State for 34 Agreement States). For Agreement State response to 7 IMPEP questionnaires annually: 371 hours (an average of 53 hours per program). The total number of hours expended annually is 260,631 hours. 9. An indication of whether Section 3507(d), Public Law 104-13 applies: Not applicable. 10. Abstract: States wishing to become Agreement States are requested to provide certain information to the NRC as specified by the Commission's Policy Statement, ``Criteria for Guidance of States and NRC in Discontinuance of NRC Regulatory Authority and Assumption Thereof By States Through Agreement.'' Agreement States need to ensure that the Radiation Control Program under the Agreement remains adequate and compatible with the requirements of Section 274 of the Atomic Energy Act (Act) and must maintain certain information. NRC conducts periodic evaluations through IMPEP to ensure that these programs are compatible with the NRC's program, meet the applicable parts of the Act, and are adequate to protect public health and safety. 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 World Wide 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 April 26, 2007. 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. OMB Desk Officer, Office of Information and Regulatory Affairs (3150-0183), NEOB-10202, Office of Management and Budget, Washington, DC 20503. Comments can also be submitted by telephone at (202) 395-3087. The NRC Clearance Officer is Margaret A. Janney, (301) 415-7245.
Notice of Availability Concerning Technical Specification Improvement To Add an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems to the Technical Specifications Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model Application related to changes to the Standard Technical Specifications (STS), Section 3.7.5 (STS 3.7.4 for BWR/6), ``Control Room Air Conditioning (AC) System'' for NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6), Rev. 3.0. The changes add an Action Statement to Limiting Condition for Operation (LCO) (LCO 3.7.5 for BWR/4 and LCO 3.7.4 for BWR/6). The new Action Statement allows a finite time to restore one control room AC subsystem to operable status and requires verification that control room temperature remains < 90[deg]F every 4 hours. The proposed changes would also revise the Bases for STS 3.7.5 (STS 3.7.4 for BWR/6). The NRC staff has also prepared a model safety evaluation (SE) and no significant hazards consideration (NSHC) determination relating to this matter. The purpose of these models is to permit the NRC to efficiently process amendments that propose to adopt the associated changes into plant-specific technical specifications (TS). Licensees of nuclear power reactors to which the models apply may request amendments confirming the applicability of the SE and NSHC determination to their reactors.
Florida Power Corporation; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing; Correction
This document corrects a notice published in the Federal Register on March 13, 2007 (72 FR 11381), which informs the public that the NRC is considering issuance of an amendment to Renewed Facility Operating License No. DPR-72. This action is necessary to correct the name of the licensee.
Preclosure Safety Analysis-Level of Information and Reliability Estimation; Availability of Final Interim Staff Guidance Document
The U.S. Nuclear Regulatory Commission (NRC) is announcing the availability of the final interim staff guidance (ISG) document HLWRS- ISG-02, ``Preclosure Safety AnalysisLevel of Information and Reliability Estimation,'' and NRC responses to the public comments received on that document. The ISG clarifies or refines the guidance provided in the Yucca Mountain Review Plan (YMRP) (NUREG-1804, Revision 2, July 2003). The YMRP provides guidance to NRC staff to evaluate a potential license application for a high-level radioactive waste at a geologic repository constructed or operated at Yucca Mountain (YM), Nevada.
Proposed Revisions to NUREG/BR-0006 and NUREG/BR-0007
The U.S. Nuclear Regulatory Commission (NRC) is proposing revisions to NUREG/BR-0006, ``Instructions for the Preparation and Distribution of Material Transaction Reports.'' https://www.nrc.gov/ reading-rm/doc-collections/nuregs/brochures/br0006/ and NUREG/BR-0007, ``Instructions for the Preparation and Distribution of Material Status Reports.'' https://www.nrc.gov/reading-rm/doc-collections/nuregs/ brochures/br0007/ The purpose of these revisions are to incorporate (1) proposed rule changes for nuclear material reporting requirements, (2) upgrades to the Nuclear Material Management and Safeguards System, and (3) editorial changes. The NRC is seeking comment from interested parties on the clarity of the proposed revisions and will consider the comments received in its final evaluation of the NUREGs. Comments should address the contents of the guidance presented in the NUREGs but not the regulations associated with it.
Notice of Opportunity for Comment on Model Safety Evaluation for Technical Specification Task Force (TSTF) Traveler To Provide Actions for One Steam Supply to Turbine Driven AFW/EFW Pump Inoperable Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) relating to proposed changes to Actions in the Standard Technical Specifications (STS) relating to One Steam Supply to Turbine Driven Auxiliary Feedwater / Emergency Feedwater (AFW/EFW) Pump Inoperable. This change would establish a Completion Time in the Standard Technical Specifications for the Condition where one steam supply to the turbine driven AFW/EFW pump is inoperable concurrent with an inoperable motor driven AFW/EFW train. The NRC staff has also prepared a model application and 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 that propose to adopt the associated changes into plant-specific technical specifications (TS). Licensees of nuclear power reactors to which the models apply can request amendments confirming the applicability of the SE and NSHC determination to their reactors. The NRC staff is requesting comments on the Model SE, Model Application and Model NSHC determination prior to announcing their availability for referencing in license amendment applications.
Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the U.S. Nuclear Regulatory Commission (NRC) has prepared a model license amendment request (LAR), model safety evaluation (SE), and model proposed no significant hazards consideration (NSHC) determination related to deletion of the E Bar definition and revision to reactor coolant system (RCS) specific activity technical specification. This request revises the RCS specific activity specification for pressurized water reactors to utilize a new indicator, Dose Equivalent Xenon-133 instead of the current indicator known as E Bar. The purpose of these models is to permit the NRC staff to efficiently process amendments to incorporate these changes into plant- specific technical specifications (TS) for Babcock and Wilcox, Westinghouse, and Combustion Engineering pressurized water reactors (PWRs). 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 model LAR, model SE and NSHC determination to its plant.
Design Basis Threat
The Nuclear Regulatory Commission (NRC) is amending its regulations that govern the requirements pertaining to the design basis threats (DBTs). This final rule makes generically applicable security requirements similar to those previously imposed by the Commission's April 29, 2003 DBT Orders, based upon experience and insights gained by the Commission during implementation, and redefines the level of security requirements necessary to ensure that the public health and safety and common defense and security are adequately protected. Pursuant to Section 170E of the Atomic Energy Act (AEA), the final rule revises the DBT requirements for radiological sabotage, generally applicable to power reactors and Category I fuel cycle facilities, and for theft or diversion of NRC-licensed Strategic Special Nuclear Material (SSNM), applicable to Category I fuel cycle facilities. Additionally, a petition for rulemaking (PRM-73-12), filed by the Committee to Bridge the Gap, was considered as part of this rulemaking. The NRC partially granted PRM-73-12 in the proposed rule, but deferred action on other aspects of the petition to the final rule. The NRC's final disposition of PRM-73-12 is contained in this document.
Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the U. S. Nuclear Regulatory Commission (NRC) has prepared a model license amendment request (LAR), model safety evaluation (SE), and model proposed no significant hazards consideration (NSHC) determination related to deletion of the E Bar definition and revision to reactor coolant system (RCS) specific activity technical specification. This request revises the RCS specific activity specification for pressurized water reactors to utilize a new indicator, Dose Equivalent Xenon-133 instead of the current indicator known as E Bar. The purpose of these models is to permit the NRC staff to efficiently process amendments to incorporate these changes into plant- specific technical specifications (TS) for Babcock and Wilcox, Westinghouse, and Combustion Engineering pressurized water reactors (PWRs). 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 model LAR, model SE and NSHC determination to its plant.
Notice of Opportunity To Comment on Model Safety Evaluation and Model License Amendment Request on Technical Specification Improvement Regarding Relocation of Departure From Nucleate Boiling Parameters to the Core Operating Limits Report for Combustion Engineering Pressurized Water Reactors Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the U. S. Nuclear Regulatory Commission (NRC) has prepared a model license amendment request (LAR), model safety evaluation (SE), and model proposed no significant hazards consideration (NSHC) determination related to changes to Standard Technical Specifications (STSs) for Combustion Engineering Pressurized Water Reactors (PWRs), NUREG-1432, Revision 3.1. This change would allow the numerical limits located in technical specification (TS) 3.4.1, ``RCS Pressure, Temperature, and Flow [Departure from Nucleate Boiling (DNB)] Limits'' to be replaced with references to the Core Operating Limits Report (COLR). Associated changes are also included for the TS 3.4.1 Bases, and TS 5.6.3 ``Core Operating Limits Report (COLR).'' The Technical Specifications Task Force (TSTF) proposed these changes to the TS in TSTF-487 Revision 0, ``Relocate DNB Parameters to the COLR.'' The purpose of the model SE, LAR, and NSHC is to permit the NRC to efficiently process amendments to incorporate these changes into plant- specific TSs for Combustion Engineering PWRs. 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 model LAR, model SE and NSHC determination to its plant. The NRC staff is requesting comments on the model LAR, model SE and NSHC determination before announcing their availability for referencing in license amendment applications.
Notice of Opportunity for Comment on Model Safety Evaluation for Technical Specification Task Force (TSTF) Traveler To Provide Actions for One Steam Supply to Turbine Driven AFW/EFW Pump Inoperable Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) relating to proposed changes to Actions in the Standard Technical Specifications (STS) relating to One Steam Supply to Turbine Driven Auxiliary Feedwater / Emergency Feedwater (AFW/EFW) Pump Inoperable. This change would establish a Completion Time in the Standard Technical Specifications for the Condition where one steam supply to the turbine driven AFW/EFW pump is inoperable concurrent with an inoperable motor driven AFW/EFW train. The NRC staff has also prepared a model application and 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 that propose to adopt the associated changes into plant-specific technical specifications (TS). Licensees of nuclear power reactors to which the models apply can request amendments confirming the applicability of the SE and NSHC determination to their reactors. The NRC staff is requesting comments on the Model SE, Model Application and Model NSHC determination prior to announcing their availability for referencing in license amendment applications.
Agency Information Collection Activities: Proposed Collection; Comment Request
The NRC is preparing a submittal to OMB for review of continued approval of information collection 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 titles of the information collection: (1) NRC Form 212, ``Qualifications Investigation, Professional, Technical, and Administrative Positions'' (other than clerical positions); (2) NRC Form 212A, ``Qualifications Investigation, Secretarial/Clerical''. 2. Current OMB approval numbers: (1) 3150-0033; (2) 3150-0034. 3. How often the collection is required: On occasion. 4. Who is required or asked to report: Current/former supervisors, co-workers of applicants for employment. 5. The estimated number of annual respondents: (1) NRC Form 212: 1200; (2) NRC Form 212A: 400. 6. The estimate of the total number of hours needed annually to complete the requirement or request: (1) NRC Form 212: 300 hours (15 minutes per response); (2) NRC Form 212A: 100 hours (15 minutes per response). 7. Abstract: Information requested on NRC Form 212, ``Qualifications Investigation, Professional, Technical, and Administrative Positions (other than clerical positions)'' and NRC Form 212A, ``Qualifications Investigation, Secretarial/Clerical'' is used to determine the qualifications and suitability of external applicants for employment with NRC. The completed forms may be used to examine, rate and/or assess the prospective employee's qualifications. The information regarding the qualifications of applicants for employment is reviewed by professional personnel of the Office of Human Resources, in conjunction with other information in the NRC files, to determine the qualifications of the applicant for appointment to the position under consideration. Submit, by May 14, 2007, 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? 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, Margaret A. Janney, Mail Stop: T-5F52, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, by telephone at 301-415-7245, or by Internet electronic mail to InfoCollects@nrc.gov.
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