Nuclear Regulatory Commission October 5, 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.