Nuclear Regulatory Commission March 19, 2007 – Federal Register Recent Federal Regulation Documents
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Notice of Opportunity for Comment on Model Safety Evaluation for Technical Specification Task Force (TSTF) Traveler To Provide Actions for One Steam Supply to Turbine Driven AFW/EFW Pump Inoperable 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) relating to proposed changes to Actions in the Standard Technical Specifications (STS) relating to One Steam Supply to Turbine Driven Auxiliary Feedwater / Emergency Feedwater (AFW/EFW) Pump Inoperable. This change would establish a Completion Time in the Standard Technical Specifications for the Condition where one steam supply to the turbine driven AFW/EFW pump is inoperable concurrent with an inoperable motor driven AFW/EFW train. The NRC staff has also prepared a model application and 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 adopt the associated changes into plant-specific technical specifications (TS). Licensees of nuclear power reactors to which the models apply can request amendments confirming the applicability of the SE and NSHC determination to their reactors. The NRC staff is requesting comments on the Model SE, Model Application and Model NSHC determination prior to announcing their availability for referencing in license amendment applications.
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
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.
Design Basis Threat
The Nuclear Regulatory Commission (NRC) is amending its regulations that govern the requirements pertaining to the design basis threats (DBTs). This final rule makes generically applicable security requirements similar to those previously imposed by the Commission's April 29, 2003 DBT Orders, based upon experience and insights gained by the Commission during implementation, and redefines the level of security requirements necessary to ensure that the public health and safety and common defense and security are adequately protected. Pursuant to Section 170E of the Atomic Energy Act (AEA), the final rule revises the DBT requirements for radiological sabotage, generally applicable to power reactors and Category I fuel cycle facilities, and for theft or diversion of NRC-licensed Strategic Special Nuclear Material (SSNM), applicable to Category I fuel cycle facilities. Additionally, a petition for rulemaking (PRM-73-12), filed by the Committee to Bridge the Gap, was considered as part of this rulemaking. The NRC partially granted PRM-73-12 in the proposed rule, but deferred action on other aspects of the petition to the final rule. The NRC's final disposition of PRM-73-12 is contained in this document.
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