Nuclear Regulatory Commission October 2006 – Federal Register Recent Federal Regulation Documents

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.

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 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.