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Information Notices - 1995

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Document Number Title Revision Publish Date Reviewed Date
IN-95-58 10 CFR 34.20; Final Effective Date -- 12/18/1995 --
IN-95-57 Risk Impact Study Regarding Maintenance During Low-Power Operation and Shutdown -- 12/13/1995 --
IN-95-56 Shielding Deficiency in Spent Fuel Transfer Canal at a Boiling-water Reactor -- 12/11/1995 --
IN-95-55 Handling Uncontained Yellowcake Outside of a Facility Processing Circuit -- 12/06/1995 --
IN-95-54 Decay Heat Management Practices During Refueling Outages -- 12/01/1995 --
IN-95-53 Failures of Main Steam Isolation Valves as a Result of Sticking Solenoid Pilot Valves -- 12/01/1995 --
IN-95-52 Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed From 3M Company Interim Fire Barrier Materials S1 03/17/1998 --
-- 11/14/1995 --
IN-95-51 Recent Incidents Involving Potential Loss of Control of Licensed Material -- 10/27/1995 --
IN-95-50 Safety Defect in Gammamed 12I Bronchial Catheter Clamping Adapters -- 10/30/1995 --
IN-95-49 Seismic Adequacy of Thermo-Lag Panels S1 12/10/1997 --
-- 10/27/1995 --
IN-95-48 Results of Shift Staffing Study -- 10/10/1995 --
IN-95-47 Unexpected Opening of a Safety/Relief Valve and Complications Involving Suppression Pool Cooling Strainer Blockage 1 11/30/1995 --
-- 10/04/1995 --
IN-95-46 Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor -- 10/06/1995 --
IN-95-45 American Power Service Falsification of American Society of Nondestructive Testing (ASNT) Certificates -- 10/04/1995 --
IN-95-44 Ensuring Compatible Use of Drive Cables Incorporating Use of Industrial Nuclear Company Ball-Type Male Connectors -- 09/26/1995 --
IN-95-43 Failure of the Bolt-Locking Device on Reactor Coolant Pump Turning Vane -- 09/28/1995 --
IN-95-42 Commission Decision on the Resolution of Generic Issue 23, "Reactor Coolant Pump Seal Failure" -- 09/22/1995 --
IN-95-41 Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators -- 09/22/1995 --
IN-95-40 Supplemental Information to Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes" -- 09/20/1995 A 09/20/1995 B --
IN-95-39 Brachytherapy Incidents Involving Treatment Planning Errors -- 09/19/1995 --
IN-95-38 Degradation of Boraflex Neutron Absorber in Spent Fuel Pool Storage Racks -- 09/08/1995 --
IN-95-37 Inadequate Offsite Power Systems Voltages During Design-Basis Events -- 09/07/1995 --
IN-95-36 Potential Problems with Post-Fire Emergency Lighting S1 06/10/1997 --
-- 08/29/1995 --
IN-95-35 Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation -- 08/28/1995 --
IN-95-34 Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves -- 08/25/1995 --
IN-95-33 Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 -- 08/23/1995 --
IN-95-32 Thermo-Lag 330-1 Flame Spread Test Results -- 08/10/1995 --
IN-95-31 Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference -- 08/09/1995 --
IN-95-30 Susceptibility of Low-Pressure Coolant Injection and Core Spray Injection Valves to Pressure Locking -- 08/03/1995 --
IN-95-29 Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems -- 06/07/1995 --
IN-95-28 Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites -- 06/05/1995 --
IN-95-27 NRC Review of Nuclear Energy Institute, "Thermo- Lag Combustibility Evaluation Methodology Plant Screening Guide -- 05/31/1995 --
IN-95-26 Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit -- 05/31/1995 --
IN-95-25 Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit -- 05/11/1995 --
IN-95-24 Summary of Licensed Operator Requalification Inspection Program Findings -- 04/25/1995 --
IN-95-23 Control Room Staffing Below Minimum Regulatory Requirements -- 04/24/1995 --
IN-95-22 Hardened or Contaminated Lubricants Cause Metal- Clad Circuit Breaker Failures -- 04/21/1995 --
IN-95-21 Unexpected Degradation of Lead Storage Batteries -- 04/20/1995 --
IN-95-20 Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation into the Sensor Cell -- 03/22/1995 --
IN-95-19 Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism -- 03/22/1995 --
IN-95-18 Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves S1 03/31/1995 --
-- 03/15/1995 --
IN-95-17 Reactor Vessel Top Guide and Core Plate Cracking -- 03/10/1995 --
IN-95-16 Vibration Caused by Increased Flow in a Boiling Water Reactor -- 03/09/1995 --
IN-95-15 Inadequate Logic Testing of Safety-Related Circuits -- 03/07/1995 --
IN-95-14 Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking -- 02/28/1995 --
IN-95-13 Potential for Data Collection Equipment to Affect Protection System Performance S1 11/22/1995 --
-- 02/24/1995 --
IN-95-12 Potentially Nonconforming Fasteners Supplied by A&G; Engineering II, Inc. -- 02/21/1995 --
IN-95-11 Failure of Condensate Piping Because of Erosion/ Corrosion at Flow-Straightening Device -- 02/24/1995 --
IN-95-10 Potential for Loss of Automatic Engineered Safety Features Actuation S2 08/11/1995 --
S1 02/10/1995 --
-- 02/03/1995 --
IN-95-09 Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design -- 01/31/1995 --
IN-95-08 Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments -- 01/30/1995 --
IN-95-07 Radiopharmaceutical Vial Breakage During Preparation -- 01/27/1995 --
IN-95-06 Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment -- 01/25/1995 --
IN-95-05 Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics -- 01/20/1995 --
IN-95-04 Excessive Cooldown and Depressurization of the Reactor Coolant System Following a Loss of Offsite Power S1 10/11/1996 --
-- 01/19/1995 --
IN-95-03 Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition S2 07/03/2000 --
S1 03/25/1996 --
-- 01/18/1995 --
IN-95-02 Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers -- 01/17/1995 --
IN-95-01 DOT Safety Advisory: High Pressure Aluminum -- 01/04/1995 --

Page Last Reviewed/Updated Friday, November 3, 2023