Nuclear Regulatory Commission Notice of Availability of Model Application concerning Technical Specification Improvement to Revise Control Rod Notch Surveillance Frequency, Clarify Srm Insert Control Rod Action, and Clarify Frequency Example Background

need to prepare an environmental impact statement. Document Access and Management System (ADAMS), which provides text and image files of NRC's public documents. The ADAMS accession numbers for the documents related to this notice are as follows: Document ADAMS accession No. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the NRC's Public Document Room (PDR) Reference staff at 1–800–397–4209, 301– 415–4737, or by e-mail to [email protected]. SUMMARY: Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) relating to the revision of Standard Technical (2) a clarification to the requirement to fully insert all insertable control rods for the limiting condition for operation (LCO) in STS 3.3.1.2, Required Action E.2, ''Source Range Monitor Instrumentation'' (NUREG– 1434 only), and (3) the revision of Example 1.4–3 in STS Section 1.4 ''Frequency'' to clarify the applicability of the 1.25 surveillance test interval extension (NUREG–1430 through NUREG–1434). The NRC staff has also prepared a model license amendment request 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 that propose to modify TS control rod SR testing frequency, clarify TS control insertion requirements, and clarify SR frequency discussions. Licensees of nuclear power reactors to which the models apply can request amendments, confirming the applicability of the SE and NSHC determination to their plant licensing basis. DATES: The NRC staff issued a Federal Register notice (72 FR 46103; August 16, 2007) which provided a model SE, model application, and model NSHC related to BWR plant control rod notch surveillance frequency, BWR SRM control rod insertion action, and clarification of a surveillance frequency example for all plant types. Similarly, the NRC staff herein provides a revised model SE, model LAR, and model NSHC incorporating changes based upon the public comments received. The NRC staff can most efficiently consider applications based upon the model LAR, which references the model SE, if the LAR is submitted within one year of this Federal Register Notice.