Nuclear Regulatory Commission December 13, 2005 – Federal Register Recent Federal Regulation Documents

Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model application relating to changes to the Standard Technical Specifications (STSs) 3.6.1.3, ``Primary Containment Isolation Valves (PCIVs),'' for boiling-water reactors (BWR) in NUREG-1433, Revision 3, ``Standard Technical Specifications, General Electric Plants, BWR/4,'' and ``NUREG-1434, Revision 3, ``Standard Technical Specifications, General Electric Plants, BWR/6.'' The proposed change to the STSs 3.6.1.3 would extend to 7 days the completion time (CT) (or allowed outage time (AOT)) to restore an inoperable PCIV to operable status or isolate the affected penetration flow path both for selected primary containment penetrations with two (or more) PCIVs and for selected primary containment penetrations with only one PCIV. This change is based on analyses provided in a generic topical report (TR) submitted by the BWR Owners' Group (BWROG). The BWROG, through its participation in the Technical Specification (TS) Task Force (TSTF) proposed this change to the STSs in Change Traveler No. TSTF-454, Revision 1. This notice also includes a model safety evaluation (SE) and 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 to incorporate this change into plant-specific TSs for General Electric (GE) BWRs. Licensees of nuclear power reactors to which the models apply can request amendments conforming to the models. In such a request, a licensee should provide supporting documentation to confirm the applicability of the SE and NSHC determination to its plant.