Nuclear Regulatory Commission February 2008 – Federal Register Recent Federal Regulation Documents

NRC will convene a meeting of the Independent External Review Panel To Identify Vulnerabilities in the U.S. Nuclear Regulatory Commission's (NRC) Materials Licensing Program on February 19 through 21, 2008. A copy of the agenda for the meeting can be obtained by e- mailing Mr. Aaron T. McCraw at the contact information below. Purpose: To initiate the Panel's discussions and deliberations in developing their final report and to allow members of the public an opportunity to provide comments to the Panel on its draft report. The Panel's draft report will be publicly available no later than Monday, February 11, 2008, and will be located in the NRC's Agencywide Document Access and Management System (ADAMS) using Accession Number ML080230554. Date and Time for Closed Sessions: There will be no closed sessions during this meeting. Date and Time for Open Session: February 19, 2008, from 2 p.m. to 4:30 p.m; February 20, 2008, from 9 a.m. to 4:30 p.m.; and February 21, 2008, from 9 a.m. to 12 p.m. Address for Public Meeting: U.S. Nuclear Regulatory Commission, Two White Flint North Building, 11545 Rockville Pike, Rockville, Maryland 20852. Specific room locations will be indicated on the agenda. Public Participation: Any member of the public who wishes to participate in the meeting should contact Mr. McCraw using the information below.

Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) relating to the modification of technical specification (TS) 3.6.3, Containment Isolation Valves associated with implementation of BAW- 2461-A, ``Risk-Informed Justification for Containment Isolation Valve Allowed Outage Time Change.'' 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 are to permit the NRC to efficiently process amendments that propose to modify TS Containment Isolation Valve Completion Times. Licensees of nuclear power reactors to which the models apply could then request amendments, confirming the applicability of the SE and NSHC determination to their reactors. The NRC staff is requesting comment on the model SE and model NSHC determination prior to announcing their availability for referencing in license amendment applications.