United States Nuclear Regulatory Commission - Protecting People and the Environment

Information Notices - 1995

File Name Date Description
in95049s1 12/10/1997 Seismic Adequacy of Thermo-Lag Panels – Supplement 1
in95052s1 03/17/1998 NRC Information Notice 95-52, Supplement 1: Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials – Supplement 1
in95036s1 06/10/1997 Potential Problem in Post-Fire Emergency Lighting – Supplement 1
in95058 12/18/1995 10 CFR 34.20; Final Effective Date
in95057 12/13/1995 Risk Impact Study Regarding Maintenance During Low-Power Operation and Shutdown
in95056 12/11/1995 Shielding Deficiency in Spent Fuel Transfer Canal at a Boiling-water Reactor
in95055 12/06/1995 Handling Uncontained Yellowcake Outside of a Facility Processing Circuit
in95054 12/01/1995 Decay Heat Management Practices During Refueling Outages
in95053 12/01/1995 Failures of Main Steam Isolation Valves as a Result of Sticking Solenoid Pilot Valves
in95047r1 11/30/1995 Unexpected Opening of a Safety/Relief Valve and Complications Involving Suppression Pool Cooling Strainer Blockage – Revision 1
in95013s1 11/22/1995 Potential for Data Collection Equipment to Affect Protection System Performance – Supplement 1
in95052 11/14/1995 Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed From 3M Company Interam Fire Barrier Materials
in95050 10/30/1995 Safety Defect in Gammamed 12I Bronchial Catheter Clamping Adapters
in95051 10/27/1995 Recent Incidents Involving Potential Loss of Control of Licensed Material
in95049 10/27/1995 Seismic Adequacy of Thermo-Lag Panels
in95048 10/10/1995 Results of Shift Staffing Study
in95046 10/06/1995 Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor
in95045 10/04/1995 American Power Service Falsification of American Society of Nondestructive Testing (ASNT) Certificates
in95047 10/04/1995 Unexpected Opening of a Safety/Relief Valve and Complications Involving Suppression Pool Cooling Strainer Blockage
in95043 09/28/1995 Failure of the Bolt-Locking Device on Reactor Coolant Pump Turning Vane
in95044 09/26/1995 Ensuring Compatible Use of Drive Cables Incorporating Use of Industrial Nuclear Company Ball-Type Male Connectors
in95041 09/22/1995 Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators
in95042 09/22/1995 Commission Decision on the Resolution of Generic Issue 23, "Reactor Coolant Pump Seal Failure"
in95040 09/20/1995 Supplemental Information to Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes"
in95039 09/19/1995 Brachytherapy Incidents Involving Treatment Planning Errors
in95038 09/08/1995 Degradation of Boraflex Neutron Absorber in Spent Fuel Pool Storage Racks
in95037 09/07/1995 Inadequate Offsite Power Systems Voltages During Design-Basis Events
in95036 08/29/1995 Potential Problems with Post-Fire Emergency Lighting
in95035 08/28/1995 Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation
in95034 08/25/1995 Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves
in95033 08/23/1995 Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3
in95010s2 08/11/1995 Sup 2 for IN 95-10, Potential for Loss of Automatic Engineered Safety Features Actuation – Supplement 2
in95032 08/10/1995 Thermo-Lag 330-1 Flame Spread Test Results
in95031 08/09/1995 Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference
in95030 08/03/1995 Susceptibility of Low-Pressure Coolant Injection and Core Spray Injection Valves to Pressure Locking
in95003s2 07/03/2000 Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition – Supplement 2
in95029 06/07/1995 Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems
in95028 06/05/1995 Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites
in95027 05/31/1995 NRC Review of Nuclear Energy Institute, "Thermo- Lag Combustibility Evaluation Methodology Plant Screening Guide
in95026 05/31/1995 Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit
in95025 05/11/1995 Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit
in95024 04/25/1995 Summary of Licensed Operator Requalification Inspection Program Findings
in95023 04/24/1995 Control Room Staffing Below Minimum Regulatory Requirements
in95022 04/21/1995 Hardened or Contaminated Lubricants Cause Metal- Clad Circuit Breaker Failures
in95021 04/20/1995 Unexpected Degradation of Lead Storage Batteries
in95003s1 03/25/1996 Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition – Supplement 1
in95018s1 03/31/1995 Sup 1 to IN 95-18, Potential Pressure-locking of Safety-Related Power-Operated Gate Valves – Supplement 1
in95020 03/22/1995 Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation into the Sensor Cell
in95019 03/22/1995 Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism
in95018 03/15/1995 Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves
in95017 03/10/1995 Reactor Vessel Top Guide And Core Plate Cracking
in95016 03/09/1995 Vibration Caused by Increased Flow in a Boiling Water Reactor
in95015 03/07/1995 Inadequate Logic Testing of Safety-Related Circuits
in95014 02/28/1995 Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking
in95013 02/24/1995 Potential For Data Collection Equipment to Affect Protection System Performance
in95011 02/24/1995 Failure of Condensate Piping Because of Erosion/ Corrosion at Flow-Straightening Device
in95012 02/21/1995 Potentially Nonconforming Fasteners Supplied by A&G; Engineering II, Inc.
in95010s1 02/10/1995 Potential for Loss of Automatic Engineered Safety Features Actuation – Supplement 1
in95010 02/03/1995 Potential For Loss of Automatic Engineered Safety Features Actuation
in95009 01/31/1995 Use of Inappropriate Guidelines And Criteria For Nuclear Piping And Pipe Support Evaluation And Design
in95008 01/30/1995 Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments
in95007 01/27/1995 Radiopharmaceutical Vial Breakage During Preparation
in95006 01/25/1995 Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment
in95005 01/20/1995 Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics
in95004s1 10/11/1996 Excessive Cooldown and Depressurization of the Reactor Coolant System Following a Loss of Offsite Power – Supplement 1
in95004 01/19/1995 Excessive Cooldown and Depressurization of the Reactor Coolant System Following a Loss of Offsite Power
in95003 01/18/1995 Loss of Reactor Coolant Inventory And Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition
in95002 01/17/1995 Problems With General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers
in95001 01/04/1995 DOT Safety Advisory: High Pressure Aluminum
Page Last Reviewed/Updated Monday, November 18, 2013