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 |