Information Notices Related to Fire Protection

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 NRC Library.

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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, Revision 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, Supplement 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, Supplement 1 Feedwater Line Break
IN-86-106, Supplement 2 Feedwater Line Break
IN-86-106, Supplement 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, Supplement 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, Supplement 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,
Attachment 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, Supplement 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, Supplement 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, Supplement 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, Supplement 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, Supplement 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, Supplement 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-06-31 Inadequate Fault Interrupting Rating of Breakers
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-07-34 Operating Experience Regarding Electrical Circuit Breakers
IN-08-05 Fire Involving Emergency Diesel Generator Exhaust Manifolds
IN-09-29 Potential Failure of Fire Water Supply Pumps to Automatically Start Due to a Fire
IN-10-09 Importance of Understanding Circuit Breaker Control Panel Indications