Nuclear Regulatory Commission 2006 – Federal Register Recent Federal Regulation Documents
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``Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire, Draft Report for Comment''
The Nuclear Regulatory Commission (NRC) is announcing the availability of and is seeking comments on NUREG-1852, ``Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire, Draft Report For Comment.''
Abnormal Occurrence Reports: Implementation of Section 208 of the Energy Reorganization Act of 1974; Revised Policy Statement
This policy statement presents the revised abnormal occurrence (AO) criteria the Commission uses for selecting AO's for the annual report to Congress as required by Section 208 of the Energy Reorganization Act of 1974 (Pub. L. 93-438). Section 208 of the act defines an AO as an unscheduled incident or event which the U.S. Nuclear Regulatory Commission (NRC) determines to be significant from the standpoint of public health or safety. The AO criteria have been amended to ensure that the criteria are consistent with the NRC's Strategic Plan for Fiscal Year (FY) 2004-2009 and the NRC rulemaking on Title 10, Part 35, of the Code of Federal Regulations (10 CFR Part 35), ``Medical Use of Byproduct Material.'' Additionally, risk-informed criteria based on the NRC Accident Sequence Precursor (ASP) Program and Reactor Oversight Process (ROP) have been added for selecting abnormal occurrences at commercial nuclear power plants for the report to Congress. The ASP program assesses the risk significance of issues and events. The ROP is a risk-informed, tiered approach to ensuring the safety of nuclear power plants. The ROP is a process for collecting information about licensee performance, assessing the safety significance of the information, taking appropriate actions, and ensuring that licensees correct deficiencies. Some sections of the AO criteria have been restructured. The restructuring accommodates the changes in the criteria and minimizes duplication.
Solicitation of Public Comments on the Implementation of the Reactor Oversight Process
The NRC is soliciting comments from members of the public, licensees, and interest groups related to the implementation of the Reactor Oversight Process (ROP). An electronic version of the survey questions may be obtained from https://www.nrc.gov/NRR/OVERSIGHT/ASSESS/ rop2006survey.pdf. This solicitation will provide insights into the self-assessment process and a summary of the feedback will be included in the annual ROP self-assessment report to the Commission.
Privacy Act of 1974; Republication of Systems of Records Notices
The Nuclear Regulatory Commission (NRC) has conducted a comprehensive review of all its Privacy Act systems of records. The NRC is revising and republishing all its systems of records (systems) notices as a result of this review. The systems revisions are minor corrective and administrative changes that do not meet the threshold criteria established by the Office of Management and Budget (OMB) for either a new or altered system of records.
Notice of Opportunity to Comment on Model Safety Evaluation and Model License Amendment Request on Technical Specification Improvement Regarding the Removal of the Main Steam and Main Feedwater Isolation Valve Times 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 Specification NUREG-1430, 1431, 1432, (STS) 3.7.2, ``Main Stream Isolation Valves (MSIVs);'' NUREG-1430, STS 3.7.3, ``Main Feedwater Stop Valves (MFSVs), Main Feedwater Control Valves (MFCVs), and Associated Startup Feedwater Control Valves (SFCVs);'' NUREG-1431, STS 3.7.3, ``Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves (MFRVs), and Associated Bypass Valves;'' and NUREG-1432, STS 3.7.3,''Main Feedwater Isolation Valves (MFIVs), and MFIV Bypass Valves.'' These valves are herein referred to generically as the Main Steam and Main Feedwater Isolation Valves. The Babcocks and Wilcocks Owners Group (BWOG), the Combustion Engineering Owners Group (CEOG) and the Westinghouse Owners Group (WOG) participants in the Technical Specifications Task Force (TSTF) proposed these changes to the STS in TSTF-491, Revision 2 ``Removal of Main Steam and Feedwater Valve Isolation Times.'' The purpose of these models is to permit the NRC to efficiently process amendments to incorporate these changes into plant-specific Technical Specifications (TS) for Babcock and Wilcock Pressurized Water Reactors (BWPWR), Combustion Engineering Pressurized Water Reactors (CEPWR) and Westinghouse Pressurized Water Reactors (WPWR). 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.
Advisory Committee on the Medical Uses of Isotopes: Meeting Notice
NRC will convene a meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) on October 24, 2006. A sample of agenda items to be discussed during the public sessions includes: (1) NARM Legislation Update; (2) Status of Specialty Board applications for NRC recognition; (3) Staff Actions for Authorized Medical Physicist and Radiation Safety Officer; (4) Interim Inventory and National Sealed Source Tracking; (5) Status of Medical Events; (6) NARM Guidance. To review the agenda, see https://www.nrc.gov/[fxsp0]reading-rm/doc- collections/[fxsp0]acmui/agenda/ or contact Mohammad Saba, by telephone at: (301) 415-7608, or via e-mail at: mss@nrc.gov. Purpose: Discuss issues related to 10 CFR Part 35, Medical Use of Byproduct Material. Date and Time for Closed Session Meeting: October 24, 2006, from 8 a.m. to 10:15 a.m. This session will be closed so that NRC staff can brief the ACMUI on information relating solely to internal personnel rules. Dates and Times for Public Meetings: October 24, 2006, from 10:30 a.m. to 5 p.m. Address for Public Meeting: U.S. Nuclear Regulatory Commission, Two White Flint North Building, Room T2B3, 11545 Rockville Pike, Rockville, MD 20852-2738.
Notice of Availability of Model Application Concerning Technical Specification Improvement To Modify Requirements Regarding the Addition of LCO 3.0.9 on the Unavailability of Barriers 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) and model application relating to the modification of requirements regarding the impact of unavailable barriers, not explicitly addressed in technical specifications, but required for operability of supported systems in technical specifications (TS). The NRC staff has also prepared 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 that propose to add an LCO 3.0.9 that provides a delay time for entering a supported system TS when the inoperability is due solely to an unavailable barrier, if risk is assessed and managed. Licensees of nuclear power reactors to which the models apply could then request amendments utilizing the model application, as generically approved by this notice, and confirming the applicability of the SE and NSHC determination to their reactors.
Review Methodology for Seismically Initiated Event Sequences; Availability of Final Interim Staff Guidance Document
The Nuclear Regulatory Commission (NRC) is announcing the availability of final interim staff guidance (ISG) document, ``HLWRS- ISG-01, Review Methodology for Seismically Initiated Event Sequences,'' 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 for evaluating a potential license application to receive and possess high-level radioactive waste at a geologic repository constructed or operated at Yucca Mountain, Nevada.
Draft Report for Comment: Office of Nuclear Reactor Regulation Standard Review Plan, Section 13.3, “Emergency Planning”
The U.S. Nuclear Regulatory Commission's (NRC) Office of Nuclear Reactor Regulation (NRR) and Office of Nuclear Security and Incident Response (NSIR) has issued Section 13.3, Second Draft Revision 3, ``Emergency Planning,'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition,'' for public comment.
Facility Change Process Involving Items Relied on for Safety
The Nuclear Regulatory Commission (NRC) is amending its regulations to clarify a requirement pertaining to items relied on for safety (IROFS). This rulemaking corrects an inconsistency in the regulations pertaining to IROFS.
Facility Change Process Involving Items Relied on for Safety
The Nuclear Regulatory Commission (NRC) is amending its regulations to clarify a requirement pertaining to items relied on for safety (IROFS). This rulemaking corrects an inconsistency in the regulations pertaining to IROFS.
Notice of Opportunity To Comment on Model Application on Technical Specification Improvement To Modify Requirements Regarding LCO 3.10.1, Inservice Leak and Hydrostatic Testing Operation Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model licensee application relating to the modification of shutdown testing requirements in technical specifications (TS) for Boiling Water Reactors (BWR). The purpose of this model is to permit the NRC to efficiently process amendments that propose to modify LCO 3.10.1 that would allow control rod scram time testing to be performed concurrently with inservice leak and hydrostatic testing. Licensees of nuclear power reactors to which the model applies could then request amendments, confirming the applicability to their reactors. The NRC staff is requesting comment on the model application prior to announcing its availability for license amendment applications. A model safety evaluation and no significant hazards determination regarding the proposed changes to LCO 3.10.1 have been previously posted in the Federal Register for comment on August 21, 2006 (71 FR 48561).
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