Information notices inform addressees of significant, recently identified operating experience that involves safety, safeguards, or environmental issues. Addressees are expected to review the information for applicability to their operations, and consider appropriate actions to avoid similar problems. However, information notices do not impose or imply new requirements, do not interpret regulations, and do not require specific actions. The following table lists (in chronological order) the information notices that the U.S. Nuclear Regulatory Commission (NRC) has issued regarding topics related to fire protection for licensed facilities and materials. The complete collection of NRC information notices is available through the agency's Electronic Reading Room.
Document # |
Document Title |
IN-79-14 |
Safety Classification of Electrical Cable Support Systems |
IN-79-32 |
Separation of Electrical Cables for HPCI and ADS |
IN-80-05 |
Chloride Contamination of Safety Related Piping and Components |
IN-80-11 |
Generic Problems with ASCO Valves in Nuclear Applications Including Fire Protection Systems |
IN-80-25 |
Transportation of Pyrophoric Uranium |
IN-81-27 |
Flammable Gas Mixtures in the Waste Gas Decay Tanks in PWR Plants |
IN-82-28 |
Hydrogen Explosion While Grinding in the Vicinity of Drained and Open Reactor Coolant System |
IN-82-42 |
Defects Observed in Panasonic Model 801 and Model 802 Thermoluminescent Dosimeters |
IN-82-53 |
Main Transformer Failures at the North Anna Nuclear Power Station |
IN-83-41 |
Actuation of Fire Suppression System Causing Inoperability of Safety-Related Equipment |
IN-83-62 |
Failure of Redundant Toxic Gas Detectors Positioned at Control Room Ventilation Air Intakes |
IN-83-69 |
Improperly Installed Fire Dampers at Nuclear Power Plants |
IN-83-83 |
Use of Portable Radio Transmitters Inside Nuclear Power Plants |
IN-84-01 |
Excess Lubricant in Electric Cable Sheaths |
IN-84-09 |
Lessons Learned from NRC Inspections of Fire Protection Safe Shutdown Systems (10 CFR 50, Appendix R) |
IN-84-09, Rev. 1 |
Lessons Learned from NRC Inspections of Fire Protection Safe Shutdown Systems (10 CFR 50, Appendix R) |
IN-84-16 |
Failure of Automatic Sprinkler System Valves to Operate |
IN-84-42 |
Equipment Availability for Conditions During Outages not Covered by Technical Specifications |
IN-84-92 |
Cracking of Flywheels on Cummins Fire Pump Diesel Engines |
IN-85-09 |
Isolation Transfer Switches and Post-Fire Shutdown Capability |
IN-85-30 |
Microbiologically Induced Corrosion of Containment Service Water System |
IN-85-85 |
Systems Interaction Event Resulting in Reactor System Safety Relief Valve Opening Following a Fire Protection Deluge System Malfunction |
IN-86-13 |
Standby Liquid Control System Squib Valves Failure to Fire |
IN-86-13, Supp. 1 |
Standby Liquid Control System Squib Valves Failure to Fire |
IN-86-17 |
Update of Failure of Automatic Sprinkler System Valves to Operate |
IN-86-35 |
Fire in Compressible Material at Dresden Unit 3 |
IN-86-106 |
Feedwater Line Break |
IN-86-106, Supp. 1 |
Feedwater Line Break |
IN-86-106, Supp. 2 |
Feedwater Line Break |
IN-86-106, Supp. 3 |
Feedwater Line Break |
IN-87-14 |
Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment |
IN-87-20 |
Hydrogen Leak in Auxiliary Building |
IN-87-50 |
Potential LOCA at High- and Low-Pressure Interfaces from Fire Damage |
IN-88-04 |
Inadequate Qualification and Documentation of Fire Barrier Penetration Seals |
IN-88-04, Supp. 1 |
Inadequate Qualification and Documentation of Fire Barrier Penetration Seals |
IN-88-05 |
Fire in Annunciator Control Cabinets |
IN-88-45 |
Problems in Protective Relay and Circuit Breaker Coordination |
IN-88-56 |
Potential Problems With Silicone Foam Fire Barrier Penetration Seals, dated August 4, 1988 |
IN-88-60 |
Inadequate Design and Installation of Watertight Penetration Seals |
IN-88-61 |
Control Room Habitability - Recent Reviews of Operating Experience |
IN-88-64 |
Reporting Fires in Nuclear Process Systems at Nuclear Power Plants |
IN-89-44 |
Hydrogen Storage on the Roof of the Control Room |
IN-89-52 |
Potential Fire Damper Operational Problems |
IN-90-70 |
Pump Explosions Involving Ammonium Nitrate |
IN-91-17 |
Fire Safety of Temporary Installations or Services |
IN-91-20 |
Electrical Wire Insulation Degradation Caused Failure in a Safety-Related Motor Control Center |
IN-91-37 |
Compressed Gas Cylinder Missile Hazards |
IN-91-47 |
Failure of Thermo-Lag Fire Barrier Material to Pass Fire Endurance Test |
IN-91-53 |
Failure of Remote Shutdown System Instrumentation Because of Incorrectly Installed Components |
IN-91-63 |
Natural Gas Hazards at Fort St. Vrain Nuclear Generating Station |
IN-91-77 |
Shift Staffing at Nuclear Power Plants |
IN-91-79 |
Deficiencies in the Procedures for Installing Thermo-Lag Fire Barrier Materials |
IN-91-79, Supp. 1 |
Deficiencies in the Procedures for Installing Thermo-Lag Fire Barrier Materials |
IN-92-14 |
Uranium Oxide Fires at Fuel Cycle Facilities |
IN-92-18 |
Potential for Loss of Remote Shutdown Capability During a Control Room Fire |
IN-92-28 |
Inadequate Fire Suppression System Testing |
IN-92-46 |
Thermo-Lag Fire Barrier Material Special Review Team Final Report Findings, Current Fire Endurance Tests, and Ampacity Calculation Errors |
IN-92-46, Att. 1 |
Final Report of the Special Review Team for the Review of Thermo-Lag Fire Barrier Performance |
IN-92-55 |
Current Fire Endurance Test Results for Thermo-Lag Fire Barrier Material |
IN-92-82 |
Results of Thermo-Lag 330-1 Combustibility Testing |
IN-93-33 |
Potential Deficiency of Certain Class 1E Instrumentation and Control Cables |
IN-93-40 |
Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material |
IN-93-41 |
One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems |
IN-93-71 |
Fire at Chernobyl Unit 2 |
IN-94-12 |
Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment |
IN-94-22 |
Fire Endurance and Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers |
IN-94-26 |
Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor |
IN-94-28 |
Potential Problems with Fire Barrier Penetration Seals |
IN-94-31 |
Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles |
IN-94-34 |
Thermo-Lag 330-660 Flexi-Blanket Ampacity Derating Concerns |
IN-94-53 |
Hydrogen Gas Burn Inside Pressurizer During Welding |
IN-94-58 |
Reactor Coolant Pump Lube Oil Fire |
IN-94-59 |
Accelerated Dealloying of Cast Aluminum-Bronze Valves Caused by Microbiologically Induced Corrosion |
IN-94-86 |
Legal Actions Against Thermal Science, Inc., Manufacturer of Thermo-Lag |
IN-94-86, Supp. 1 |
Legal Actions Against Thermal Science, Inc., Manufacturer of Thermo-Lag |
IN-95-27 |
NRC Review of Nuclear Energy Institute, "Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide" |
IN-95-32 |
Thermo-Lag 330-1 Flame Spread Test Results |
IN-95-33 |
Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 |
IN-95-36 |
Potential Problems with Post-Fire Emergency Lighting |
IN-95-36, Supp. 1 |
Potential Problem with Post-Fire Emergency Lighting |
IN-95-48 |
Results of Shift Staffing Study |
IN-95-49 |
Seismic Adequacy of Thermo-Lag Panels |
IN-95-49, Supp. 1 |
Seismic Adequacy of Thermo-Lag Panels |
IN-95-52 |
Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials, dated November 14, 1995 |
IN-95-52, Supp. 1 |
Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials |
IN-96-23 |
Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing |
IN-96-33 |
Erroneous Data from Defective Thermocouple Results in a Fire |
IN-96-34 |
Hydrogen Gas Ignition During Closure Welding of a VSC 24 Multi-Assembly Sealed Basket |
IN-97-01 |
Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room |
IN-97-23 |
Evaluation and Reporting of Fires and Unplanned Chemical Reactor Events at Fuel Cycle Facilities |
IN-97-37 |
Main Transformer Fault with Ensuring Oil Spill into Turbine Building |
IN-97-48 |
Inadequate or Inappropriate Interim Fire Protection Compensatory Measures |
IN-97-59 |
Fire Endurance Test Results of Versawrap Fire Barriers |
IN-97-70 |
Potential Problems with Fire Barrier Penetration Seals |
IN-97-72 |
Potential for Failure of the Omega Series Sprinkler Heads |
IN-97-73 |
Fire Hazard in the Use of a Leak Sealant |
IN-97-82 |
Inadvertent Control Room Halon Actuation Due to a Camera Flash |
IN-98-31 |
Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2 |
IN-99-03 |
Exothermic Reactions Involving Dried Uranium Oxide Powder (Yellowcake) |
IN-99-05 |
Inadvertent Discharge of Carbon Dioxide Fire Protection System and Gas Migration |
IN-99-07 |
Failed Fire Protection Deluge Valves and Potential Testing Deficiencies in Preaction Sprinkler Systems |
IN-99-17 |
Problems Associated with Post-Fire Safe-Shutdown Circuit Analyses |
IN-99-28 |
Recall of Star Brand Fire Protection Sprinkler Heads |
IN-99-28, Supp. 1 |
Recall of Star Brand Fire Protection Sprinkler Heads |
IN-99-34 |
Potential Fire Hazard in the Use of Polyalphaolefin in Testing of Air Filters |
IN-00-12 |
Potential Degradation of Firefighter Primary Protective Garments |
IN-00-14 |
Non-Vital Bus Fault Leads to Fire and Loss of Offsite Power |
IN-01-04 |
Neglected Fire Extinguisher Maintenance Causes Fatality |
IN-01-10 |
Failure of Central Sprinkler Company Model GB Series Fire Sprinkler Head |
IN-01-12 |
Hydrogen Fire at Nuclear Power Station |
IN-01-12 (Errata) |
Hydrogen Fire at Nuclear Power Station |
IN-02-01 |
Metalclad Switchgear Failures and Consequent Losses of Offsite Power |
IN-02-04 |
Wire Degradation at Breaker Cubicle Door Hinges, dated January 10, 2002. |
IN-02-07 |
Use of Sodium Hypochlorite for Cleaning Diesel Fuel Oil Supply Tanks |
IN-02-15 |
Hydrogen Combustion Events in Foreign BWR Piping |
IN-02-15, Supp. 1 |
Potential Hydrogen Combustion Events in BWR Piping |
IN-02-24 |
Potential Problems with Heat Collectors on Fire Protection Sprinklers |
IN-02-27 |
Recent Fires at Commercial Nuclear Power Plants in the United States |
IN-03-08 |
Potential Flooding Through Unsealed Concrete Floor Cracks |
IN-03-19 |
Unanalyzed Condition of Reactor Coolant Pump Seal Leakoff Line During Postulated Fire Scenarios or Station Blackout |
IN-04-19 |
Problems Associated with Back-up Power Supplies to Emergency Response Facilities and Equipment |
IN-05-01 |
Halon Fire-Extinguishing System Piping Incorrectly Connected |
IN-05-03 |
Inadequate Design and Installation of Seismic-Gap Fire Barriers |
IN-05-04 |
Single-Failure and Fire Vulnerability of Redundant Electrical Safety Buses |
IN-05-07 |
Results of Hemyc Electrical Raceway Fire Barrier System Full Scale Fire Testing |
IN-05-14 |
Fire Protection Findings on Loss of Seal Cooling to Westinghouse Reactor Coolant Pumps |
IN-05-20 |
Electrical Distribution System Failures Affecting Security Equipment |
IN-05-30 |
Safe Shutdown Potentially Challenged by Unanalyzed Internal Flooding Events and Inadequate Design |
IN-05-32 |
Product Alert for Fire Hydrants |
IN-06-02 |
Use of Galvanized Supports and Cable Trays with Meggitt Si 2400 Stainless-Steel-Jacketed Electrical Cables |
IN-06-08 |
Secondary Piping Rupture at the Mihama Power Station in Japan |
IN-07-07 |
Potential Failure of All Control Rod Groups to Insert in a Boiling Water Reactor Due to a Fire |
IN-07-12 |
Tactical Communications Interoperability Between Nuclear
Power Reactor Licensees and First Responders |
IN-07-17 |
Fire at Nuclear Power Plants involving Inadequate Fire
Protection Administrative and Design Control |
IN-07-19 |
Fire Protection Recalls and Design Notices |
IN-07-23 |
Inadvertent Discharge of Halon 1301 Fire Suppression
System from Incorrect and/or Out-of-Date Procedures |
IN-07-26 |
Combustibility of Epoxy Floor Coatings at Commercial
Nuclear Power Plants |
IN-07-27 |
Recurring Events Involving Emergency Diesel Generator
Operability |
IN-08-05 |
Fire Involving Emergency Diesel Generator Exhaust Manifolds |