Nuclear Regulatory Commission February 4, 2008 – Federal Register Recent Federal Regulation Documents
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Florida Power Corporation, et al.; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing; Correction
This document corrects a notice appearing in the Federal Register on January 15, 2008 (73 FR 2553), which informed the public that the NRC issued Amendment No. 228 to Facility Operating License No. DPR-72 for Crystal River Unit No. 3 Nuclear Generating Plant. This action is necessary to correct the date of issuance.
Notice of Opportunity To Comment on Model Safety Evaluation on Technical Specification Improvement To Revise Containment Isolation Valve Completion Times (TSTF-498, Revision 1) 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 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.
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