Nuclear Regulatory Commission January 17, 2007 – Federal Register Recent Federal Regulation Documents

Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared and is making available a model safety evaluation (SE) and a model no-significant-hazards- consideration (NSHC) determination relating to the modification of technical specification (TS) requirements regarding the habitability of the control room envelope (CRE) for referencing in license amendment requests (LARs). The NRC staff is also making available an associated model LAR for use by licensees to prepare such LARs. The TS modification is based on NRC staff approved changes to the improved standard technical specifications (STS) (NUREGs 1430-1434) that were proposed by the pressurized and boiling water reactor owners groups' Technical Specifications Task Force (TSTF) on behalf of the commercial nuclear electrical power generation industry, in STS change traveler TSTF-448, Revision 3 (Rev 3). Previously, on October 17, 2006, drafts of the model SE, model NSHC determination, and model LAR were published in the Federal Register for public comment (71 FR 61075). Based on its evaluation of the public comments received in response to that notice, the NRC staff made appropriate changes to the models, and is including the final versions of the models in this notice. This notice also contains a description of each public comment and its disposition by the NRC staff. Based on its evaluation of the public comments, the NRC staff has decided to announce the availability of the model SE and model NSHC determination to licensees for referencing in LARs to adopt TSTF-448, Rev 3, using the consolidated line item improvement process (CLIIP). An LAR that references the model SE and model NSHC determination will permit the NRC to efficiently process a license amendment that proposes to adopt the changes in TSTF-448, Rev 3. Licensees of nuclear power reactors proposing to adopt these changes should follow the guidance in the model LAR and confirm the applicability of the model SE and model NSHC determination to their reactors.