Nuclear Regulatory Commission March 15, 2007 – Federal Register Recent Federal Regulation Documents

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
Document Number: E7-4754
Type: Notice
Date: 2007-03-15
Agency: Nuclear Regulatory Commission, Agencies and Commissions
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
Document Number: E7-4752
Type: Notice
Date: 2007-03-15
Agency: Nuclear Regulatory Commission, Agencies and Commissions
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 License Renewal Request of AREVA NP, Richland, WA, and Opportunity To Request a Hearing
Document Number: E7-4750
Type: Notice
Date: 2007-03-15
Agency: Nuclear Regulatory Commission, Agencies and Commissions