Notice of Availability of 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 allows 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.'' This request was slightly modified in TSTF-487 Revision 1 on May 4, 2007. 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.