Spotlight
Information Notices - 1990
Document Number | Title | Revision | Publish Date | Reviewed Date |
|---|---|---|---|---|
IN-90-82 | Requirements for Use of NRC-Approved Packages for Shipment of Type A Quantities of Radioactive Material | -- | -- | |
IN-90-81 | Fitness for Duty | -- | -- | |
IN-90-80 | Sand Intrusion Resulting in Two Diesel Generators Becoming Inoperable | -- | -- | |
IN-90-79 | Failures of Main Steam Isolation Check Valves Resulting in Disc Separation | -- | -- | |
IN-90-78 | Previously Unidentified Release Path from Boiling Water Reactor Control Rod Hydraulic Units | -- | -- | |
IN-90-77 | Inadvertent Removal of Fuel Assemblies from the Reactor Core | S1 | -- | |
-- | -- | |||
IN-90-76 | Failure of Turbine Overspeed Trip Mechanism Because of Inadequate Spring Tension | -- | -- | |
IN-90-75 | Denial of Access to Current Low-Level Radioactive Waste Disposal Facilities | -- | -- | |
IN-90-74 | Information on Precursors to Severe Accidents | -- | -- | |
IN-90-73 | Corrosion of Valve-to-Torque Tube Keys in Spray Pond Cross Connect Valves | -- | -- | |
IN-90-72 | Testing of Parallel Disc Gate Valves in Europe | -- | -- | |
IN-90-71 | Effective Use of Radiation Safety Committees to Exercise Control over Medical Use Programs | -- | -- | |
IN-90-70 | Pump Explosions Involving Ammonium Nitrate | -- | -- | |
IN-90-69 | Adequacy of Emergency and Essential Lighting | -- | -- | |
IN-90-68 | Stress Corrosion Cracking of Reactor Coolant Pump Bolts | S1 | -- | |
-- | -- | |||
IN-90-67 | Potential Security Equipment Weaknesses | -- | -- | |
IN-90-66 | Incomplete Draining and Drying of Shipping Casks | -- | -- | |
IN-90-65 | Recent Orifice Plate Problems | -- | -- | |
IN-90-64 | Potential for Common-Mode Failure of HPSI Pumps or Release of Reactor Coolant Outside Containment During a LOCA | -- | -- | |
IN-90-63 | Management Attention to the Establishment and Maintenance of a Nuclear Criticality Safety Program | -- | -- | |
IN-90-62 | Requirements for Import and Distribution of Neutron-Irradiated Gems | -- | -- | |
IN-90-61 | Potential for Residual Heat Removal Pump Damage Caused by Parallel Pump Interaction | -- | -- | |
IN-90-60 | Availability of Failure Data in the Government-Industry Data Exchange Program | -- | -- | |
IN-90-59 | Errors in the Use of Radioactive Iodine-131 | -- | -- | |
IN-90-58 | Improper Handling of Ophthalmic Strontium-90 Beta Radiation Applicators | -- | -- | |
IN-90-57 | Substandard, Refurbished Potter & Brumfield Relays Misrepresented as New | S1 | -- | |
-- | -- | |||
IN-90-56 | Inadvertent Shipment of a Radioactive Source in a Container Thought to Be Empty | -- | -- | |
IN-90-55 | Recent Operating Experience on Loss of Reactor Coolant Inventory While in a Shutdown Condition | -- | -- | |
IN-90-54 | Summary of Requalification Program Deficiencies | -- | -- | |
IN-90-53 | Potential Failures of Auxiliary Steam Piping and the Possible Effects on the Operability of Vital Equipment | -- | -- | |
IN-90-52 | Retention of Broken Charpy Specimens | -- | -- | |
IN-90-51 | Failures of Voltage-Dropping Resistors in the Power Supply Circuitry of Electric Governor Systems | S1 | -- | |
-- | -- | |||
IN-90-50 | Minimization of Methane Gas in Plant Systems and Radwaste Shipping Containers | -- | -- | |
IN-90-49 | Stress Corrosion Cracking in PWR Steam Generator Tubes | -- | -- | |
IN-90-48 | Enforcement Policy for Hot Particle Exposures | -- | -- | |
IN-90-47 | Unplanned Radiation Exposures to Personnel Extremities Due to Improper Handling of Potentially Highly Radioactive Source | -- | -- | |
IN-90-46 | Criminal Prosecution of Wrongdoing Committed by Suppliers of Molded-Case Circuit Breakers and Related Components | -- | -- | |
IN-90-45 | Overspeed of the Turbine-Driven Auxiliary Feedwater Pumps and Overpressurization of the Associated Piping System | -- | -- | |
IN-90-44 | Dose-Rate Instruments Underresponding to the True Radiation Fields | -- | -- | |
IN-90-43 | Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers | S1 | -- | |
-- | -- | |||
IN-90-42 | Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances | -- | -- | |
IN-90-41 | Potential Failure of General Electric Magne-Blast Circuit Breakers and AK Circuit Breakers | -- | -- | |
IN-90-40 | Results of NRC-Sponsored Testing of Motor-Operated Valves | -- | -- | |
IN-90-39 | Recent Problems with Service Water Systems | -- | -- | |
IN-90-38 | Requirements for Processing Financial Assurance Submittals for Decommissioning | S1 | -- | |
-- | -- | |||
IN-90-37 | Sheared Pinion Gear-to-Shaft Keys in Limitorque Motor Actuators | -- | -- | |
IN-90-36 | Apparent Falsification of State of Connecticut Weight Certificates | -- | -- | |
IN-90-35 | Transportation of Type A Quantities of Non-Fissile Radioactive Materials | -- | -- | |
IN-90-34 | Response to False Siren Activations | -- | -- | |
IN-90-33 | Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools | -- | -- | |
IN-90-32 | Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head | S1 | -- | |
-- | -- | |||
IN-90-31 | Update on Waste Form and High Integrity Container ... Review Status, Identification of Problems with Cement Solidification ... Waste Mishaps | -- | -- | |
IN-90-30 | Ultrasonic Inspection Techniques for Dissimilar Metal Welds | -- | -- | |
IN-90-29 | Cracking of Cladding and its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head | -- | -- | |
IN-90-28 | Potential Error in High Steamline Flow Setpoint | -- | -- | |
IN-90-27 | Clarification of ... Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation | -- | -- | |
IN-90-26 | Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems | -- | -- | |
IN-90-25 | Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up | S1 | -- | |
-- | -- | |||
IN-90-24 | Transportation of Model SPEC 2-T Radiographic Exposure Device | -- | -- | |
IN-90-23 | Improper Installation of Patel Conduit Seals | -- | -- | |
IN-90-22 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | -- | -- | |
IN-90-21 | Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated | -- | -- | |
IN-90-20 | Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators | -- | -- | |
IN-90-19 | Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities | -- | -- | |
IN-90-18 | Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks | -- | -- | |
IN-90-17 | Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves | -- | -- | |
IN-90-16 | Compliance with New Decommissioning Rule | -- | -- | |
IN-90-15 | Reciprocity: Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States | -- | -- | |
IN-90-14 | Accidental Disposal of Radioactive Materials | -- | -- | |
IN-90-13 | Importance of Review and Analysis of Safeguards Event Logs | -- | -- | |
IN-90-12 | Monitoring or Interruption of Plant Communications | -- | -- | |
IN-90-11 | Maintenance Deficiency Associated with Solenoid-Operated Valves | -- | -- | |
IN-90-10 | Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 | -- | -- | |
IN-90-09 | Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees | -- | -- | |
IN-90-08 | KR-85 Hazards from Decayed Fuel | -- | -- | |
IN-90-07 | New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps | -- | -- | |
IN-90-06 | Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels | -- | -- | |
IN-90-05 | Inter-System Discharge of Reactor Coolant | -- | -- | |
IN-90-04 | Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators | -- | -- | |
IN-90-03 | Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm | -- | -- | |
IN-90-02 | Potential Degradation of Secondary Containment | -- | -- | |
IN-90-01 | Importance of Proper Response to Self-Identified Violations by Licensees | -- | -- |
Page Last Reviewed/Updated Thursday, November 06, 2025
Page Last Reviewed/Updated Thursday, November 06, 2025