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Information Notices - 2005

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Document Number Title Revision Publish Date Reviewed Date
IN-05-33 Managing the Safety/Security Interface -- 12/30/2005 --
IN-05-32 Product Alert for Fire Hydrants -- 12/23/2005 --
IN-05-31 Potential Non-Conservative Error in Preparing Problem-Dependent Cross Sections for Use with the Keno V.A. or Keno-VI Criticality Code -- 11/17/2005 --
IN-05-30 Safe Shutdown Potentially Challenged by Unanalyzed Internal Flooding Events and Inadequate Design -- 11/07/2005 --
IN-05-29 Steam Generator Tube and Support Configuration -- 10/27/2005 --
IN-05-28 Inadequate Test Procedures Fails to Detect Inoperable Criticality Accident Alarm Horns -- 10/31/2005 --
IN-05-27 Low-Dose-Rate Manual Brachytherapy — Equipment-Related Medical Events -- 10/07/2005 --
IN-05-26 Results of Chemical Effects Head Loss Tests in a Simulated PWR Sump Pool Environment S1 01/20/2006 --
-- 09/16/2005 --
IN-05-25 Inadvertent Reactor Trip and Partial Safety Injection Actuation Due to Tin Whisker -- 08/25/2005 --
IN-05-24 Nonconservatism in Leakage Detection Sensitivity -- 08/03/2005 --
IN-05-23 Vibration-Induced Degradation of Butterfly Valves -- 08/01/2005 --
IN-05-22 Inadequate Criticality Safety Analysis of Ventilation Systems at Fuel Cycle Facilities -- 07/29/2005 --
IN-05-21 Plant Trip and Loss of Preferred AC Power from Inadequate Switchyard Maintenance -- 07/21/2005 --
IN-05-20 Electrical Distribution System Failures Affecting Security Equipment -- 07/19/2005 --
IN-05-19 Effect of Plant Configuration Changes on the Emergency Plan -- 07/18/2005 --
IN-05-18 Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 2001, 2002 and 2003 -- 07/15/2005 --
IN-05-17 Manual Brachytherapy Source Jamming -- 06/23/2005 --
IN-05-16 Outage Planning and Scheduling - Impacts on Risk -- 06/20/2005 --
IN-05-15 Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear Generating Station -- 06/01/2005 --
IN-05-15 Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear Generating Station -- 06/01/2005 --
IN-05-14 Fire Protection Findings on Loss of Seal Cooling to Westinghouse Reactor Coolant Pumps -- 06/01/05 --
IN-05-13 Potential Non-Conservative Error in Modeling Geometric Regions in the Keno-V.a Criticality Code -- 05/17/2005 --
IN-05-12 Excessively Large Criticality Safety Limits Fail to Provide Double Contingency at Fuel Cycle Facility -- 05/17/2005 --
IN-05-11 Internal Flooding/Spray-Down of Safety-Related Equipment Due to Unsealed Equipment Hatch Floor Plugs and/or Blocked Floor Drains -- 05/06/2005 --
IN-05-10 Changes to 10 CFR Part 71 Packages -- 04/07/2005 --
IN-05-09 Indications in Thermally Treated Alloy 600 Steam Generator Tubes and Tube-to-Tubesheet Welds -- 04/07/2005 --
IN-05-08 Monitoring Vibration to Detect Circumferential Cracking of Reactor Coolant Pump and Reactor Recirculation Pump Shafts -- 04/05/2005 --
IN-05-07 Results of HEMYC Electrical Raceway Fire Barrier System Full Scale Fire Testing -- 04/01/2005 --
IN-05-06 Failure to Maintain Alert and Notification System Tone Alert Radio Capability -- 03/30/2005 --
IN-05-05 Improving Material Control and Accountability Interface with Criticality Safety Activities at Fuel Cycle Facilities -- 03/10/2005 --
IN-05-04 Single-Failure and Fire Vulnerability of Redundant Electrical Safety Buses -- 02/14/2005 --
IN-05-03 Inadequate Design and Installation of Seismic-Gap Fire Barriers -- 02/10/2005 --
IN-05-02 Pressure Boundary Leakage Identified on Steam Generator Bowl Drain Welds -- 02/04/2005 --
IN-05-01 Halon Fire-Extinguishing System Piping Incorrectly Connected -- 02/04/2005 --

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Page Last Reviewed/Updated Thursday, January 23, 2025