Spotlight
Information Notices - 1993
| Document Number | Title | Revision | Publish Date | Reviewed Date |
|---|---|---|---|---|
| IN-93-101 | Jet Pump Hold-Down Beam Failure | -- | 12/17/1993 | -- |
| IN-93-100 | Reporting Requirements for Bankruptcy | -- | 12/22/1993 | -- |
| IN-93-99 | Undervoltage Relay and Thermal Overload Setpoint Problems | -- | 12/21/1993 | -- |
| IN-93-98 | Motor Brakes on Valve Actuator Motors | -- | 12/20/1993 | -- |
| IN-93-97 | Failures of Yokes Installed on Walworth Gate and Globe Valves | -- | 12/17/1993 | -- |
| IN-93-96 | Improper Reset Causes Emergency Diesel Generator Failures | -- | 12/14/1993 | -- |
| IN-93-95 | Storm-Related Loss of Offsite Power Events Due to Salt Buildup on Switchyard Insulators | -- | 12/13/1993 | -- |
| IN-93-94 | Unauthorized Forced Entry Into the Protected Area At Three Mile Island Unit 1 on February 7, 1993 | -- | 12/09/1993 | -- |
| IN-93-93 | Inadequate Control of Reactor Coolant System Conditions During Shutdown | -- | 12/08/1993 | -- |
| IN-93-92 | Plant Improvements to Mitigate Common Dependencies in Component Cooling Water Systems | -- | 12/07/1993 | -- |
| IN-93-91 | Misadjustment Between General Electric 4.16-KV Circuit Breakers and Their Associated Cubicles | -- | 12/03/1993 | -- |
| IN-93-90 | Unisolatable Reactor Coolant System Leak Following Repeated Applications of Leak Sealant | -- | 12/01/1993 | -- |
| IN-93-89 | Potential Problems with BWR Level Instrumentation Backfill Modifications | -- | 11/26/1993 | -- |
| IN-93-88 | Status of Motor-Operated Valve Performance Prediction Program by the Electric Power Research Institute | -- | 11/30/1993 | -- |
| IN-93-87 | Fuse Problems with Westinghouse 7300 Printed Circuit Cards | -- | 11/04/1993 | -- |
| IN-93-86 | Identification of Isotopes in the Production and Shipment of Byproduct Material at Non-Power Reactors | -- | 10/29/1993 | -- |
| IN-93-85 | Problems with X-Relays in DB- and DHB-Type Circuit Breakers Manufactured by Westinghouse | 1 | 01/20/1994 | -- |
| -- | 10/20/1993 | -- | ||
| IN-93-84 | Determination of Westinghouse Reactor Coolant Pump Seal Failure | -- | 10/20/1993 | -- |
| IN-93-83 | Potential Loss of Spent Fuel Pool Cooling Following a Loss of Coolant Accident (LOCA) | S1 | 08/24/1995 | -- |
| -- | 10/07/1993 | -- | ||
| IN-93-82 | Recent Fuel and Core Performance Problems in Operating Reactors | -- | 10/12/1993 | -- |
| IN-93-81 | Implementation of Engineering Expertise on Shift | -- | 10/12/1993 | -- |
| IN-93-80 | Implementation of the Revised 10 CFR Part 20 | W | 82 FR 18316 04/18/2017 |
-- |
| -- | 10/08/1993 | -- | ||
| IN-93-79 | Core Shroud Cracking at Beltline Region Welds in Boiling-Water Reactors | -- | 09/30/1993 | -- |
| IN-93-78 | Inoperable Safety Systems at a Non-Power Reactor | -- | 10/04/1993 | -- |
| IN-93-77 | Human Errors That Result in Inadvertent Transfers of Special Nuclear Material at Fuel Cycle Facilities | -- | 10/04/1993 | -- |
| IN-93-76 | Inadequate Control of Paint and Cleaners for Safety-Related Equipment | -- | 09/21/1993 | -- |
| IN-93-75 | Spurious Tripping of Low-Voltage Power Circuit Breakers with GE RMS-9 Digital Trip Units | -- | 09/17/1993 | -- |
| IN-93-74 | High Temperatures Reduce Limitorque AC Motor Operator Torque | -- | 09/16/1993 | -- |
| IN-93-73 | Criminal Prosecution of Nuclear Suppliers for Wrongdoing | -- | 09/15/1993 | -- |
| IN-93-72 | Observations From Recent Shutdown Risk and Outage Management Pilot Team Inspections | -- | 09/14/1993 | -- |
| IN-93-71 | Fire At Chernobyl Unit 2 | -- | 09/13/1993 | -- |
| IN-93-70 | Degradation of Boraflex Neutron Absorber Coupons | -- | 09/10/1993 | -- |
| IN-93-69 | Radiographic Events At Operating Power Reactors | -- | 09/02/1993 | -- |
| IN-93-68 | Failure of Pump Shaft Coupling Caused By Temper Embrittlement During Manufacture | -- | 09/01/1993 | -- |
| IN-93-67 | Bursting of High Pressure Coolant Injection Steam Line Rupture Discs Injures Plant Personnel | -- | 08/16/1993 | -- |
| IN-93-66 | Switchover to Hot-Leg Injection Following a Loss-Of-Coolant Accident in Pressurized Water Reactors | -- | 08/16/1993 | -- |
| IN-93-65 | Reactor Trips Caused By Breaker Testing with Fault Protection Bypassed | -- | 08/13/1993 | -- |
| IN-93-64 | Periodic Testing and Preventative Maintenance of Molded Case Circuit Breakers | -- | 08/12/1993 | -- |
| IN-93-63 | Improper Use of Soluble Weld Purge Dam Material | -- | 08/11/1993 | -- |
| IN-93-62 | Thermal Stratification of Water in BWR Reactor Vessels | -- | 08/10/1993 | -- |
| IN-93-61 | Excessive Reactor Coolant Leakage Following a Seal Failure in a Reactor Coolant Pump or Reactor Recirculation Pump | -- | 08/09/1993 A 08/09/1993 B | -- |
| IN-93-60 | Reporting Fuel Cycle and Materials Events to the NRC Operations Center | S1 | 10/20/1994 | -- |
| -- | 08/04/1993 | -- | ||
| IN-93-59 | Unexpected Opening of Both Doors in an Airlock | -- | 07/26/1993 | -- |
| IN-93-58 | Nonconservatism in Low-Temperature Overpressure Protection for Pressurized-Water Reactors | -- | 07/26/1993 | -- |
| IN-93-57 | Software Problems Involving Digital Control Console Systems at Non-Nuclear Reactors | -- | 07/23/1993 | -- |
| IN-93-56 | Weakness in Emergency Operating Procedures Found as Result of Steam Generator Tube Rupture | -- | 07/22/1993 | -- |
| IN-93-55 | Potential Problem with Main Steamline Break Analysis for Main Steam Vaults/Tunnels | -- | 07/21/1993 | -- |
| IN-93-54 | Motor-Operated Valve Actuator Thrust Variations Measured with a Torque Thrust Cell and a Strain Gage | -- | 07/20/1993 | -- |
| IN-93-53 | Effect of Hurricane Andrew on Turkey Point Nuclear Generating Station and Lessons Learned | S1 | 04/29/1994 | -- |
| -- | 07/20/1993 | -- | ||
| IN-93-52 | Draft NUREG-1477, "Voltage-Based Interim Plugging Criteria for Steam Generator Tubes" | -- | 07/14/1993 | -- |
| IN-93-51 | Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater Pumps | -- | 07/09/1993 | -- |
| IN-93-50 | Extended Storage of Sealed Sources | -- | 07/08/1993 | -- |
| IN-93-49 | Improper Integration of Software Into Operating Practices | -- | 07/08/1993 | -- |
| IN-93-48 | Failure of Turbine-Driven Main Feedwater Pump To Trip Because of Contaminated Oil | -- | 07/06/1993 | -- |
| IN-93-47 | Unrecognized Loss of Control Room Annunciators | -- | 06/18/1993 | -- |
| IN-93-46 | Potential Problem with Westinghouse Rod Control System & Inadvertent Withdrawal of a Single Rod Control Cluster Assembly | -- | 06/10/1993 | -- |
| IN-93-45 | Degradation of Shutdown Cooling System Performance | -- | 06/16/1993 | -- |
| IN-93-44 | Operational Challenges During a Dual-Unit Transient | -- | 06/15/1993 | -- |
| IN-93-43 | Use of Inappropriate Lubrication Oils in Safety-Related Applications | -- | 06/10/1993 | -- |
| IN-93-42 | Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Velan | -- | 06/09/1993 | -- |
| IN-93-41 | One Hour Fire Endurance Test Results for ... Kaowool, ... FS-195, and ... Interam E-50 Fire Fire Barrier Systems | -- | 05/28/1993 | -- |
| IN-93-40 | Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material | -- | 05/26/1993 | -- |
| IN-93-39 | Radiation Beams From Power Reactor Biological Shields | -- | 05/25/1993 | -- |
| IN-93-38 | Inadequate Testing of Engineered Safety Features Actuation Systems | -- | 05/24/1993 | -- |
| IN-93-37 | Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers | -- | 05/19/1993 | -- |
| IN-93-36 | Notifications, Reports, and Records of Misadministrations | -- | 05/07/1993 | -- |
| IN-93-35 | Insights From Common-Cause Failure Events | -- | 05/12/1993 | -- |
| IN-93-34 | Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment | S1 | 05/06/1993 | -- |
| -- | 04/26/1993 | -- | ||
| IN-93-33 | Potential Deficiency of Certain Class 1E Instrumentation and Control Cables | -- | 04/28/1993 | -- |
| IN-93-32 | Nonconservative Inputs for Boron Dilution Event Analysis | -- | 04/21/1993 | -- |
| IN-93-31 | Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants | -- | 04/13/1993 | -- |
| IN-93-30 | NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments | -- | 04/12/1993 | -- |
| IN-93-29 | Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry | -- | 04/12/1993 | -- |
| IN-93-28 | Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis | -- | 04/09/1993 | -- |
| IN-93-27 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | -- | 04/08/1993 | -- |
| IN-93-26 | Grease Solidification Causes Molded-Case Circuit Breaker Failure to Close | S1 | 01/31/1994 | -- |
| -- | 04/07/1993 | -- | ||
| IN-93-25 | Electrical Penetration Assembly Degradation | -- | 04/01/1993 | -- |
| IN-93-24 | Distribution of Revision 7 of NUREG-1021, "Operator Licensing Examiner Standards" | -- | 03/31/1993 | -- |
| IN-93-23 | Weschler Instruments Model 252 Switchboard Meters | -- | 03/31/1993 | -- |
| IN-93-22 | Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure | -- | 03/26/1993 | -- |
| IN-93-21 | Summary of ... Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs | -- | 03/25/1993 | -- |
| IN-93-20 | Thermal Fatigue Cracking of Feedwater Piping to Steam Generators | -- | 03/24/1993 | -- |
| IN-93-19 | Slab Hopper Bulging | -- | 03/17/1993 | -- |
| IN-93-18 | Portable Moisture-Density Gauge User Responsibilities During Field Operations | -- | 03/10/1993 | -- |
| IN-93-17 | Safety Systems Response to Loss of Coolant and Loss of Offsite Power | 1 | 03/25/1994 | -- |
| -- | 03/08/1993 | -- | ||
| IN-93-16 | Failures of Nut-Locking Devices in Check Valves | -- | 02/19/1993 | -- |
| IN-93-15 | Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches | -- | 02/18/1993 | -- |
| IN-93-14 | Clarification of 10 CFR 40.22, Small Quantities of Source Material | -- | 02/18/1993 | -- |
| IN-93-13 | Undetected Modification of Flow Characteristics in the High Pressure Safety Injection System | -- | 02/16/1993 | -- |
| IN-93-12 | Off-Gassing in Auxiliary Feedwater System Raw Water Sources | -- | 02/11/1993 | -- |
| IN-93-11 | Single Failure Vulnerability of Engineered Safety Features Actuation Systems | -- | 02/04/1993 | -- |
| IN-93-10 | Dose Calibrator Quality Control | -- | 02/02/1993 | -- |
| IN-93-09 | Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker | -- | 02/02/1993 | -- |
| IN-93-08 | Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading | -- | 02/01/1993 | -- |
| IN-93-07 | Classification of Transportation Emergencies | -- | 02/01/1993 | -- |
| IN-93-06 | Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems | -- | 01/22/1993 | -- |
| IN-93-05 | Locking of Radiography Exposure Devices | -- | 01/14/1993 | -- |
| IN-93-04 | Investigation and Reporting of Misadministrations by the Radiation Safety Officer | -- | 01/07/1993 | -- |
| IN-93-03 | Recent Revisions to 10 CFR Part 20 and Change of Implementation Date to January 1, 1994 | W | 82 FR 18316 04/18/2017 |
-- |
| -- | 01/05/1993 | -- | ||
| IN-93-02 | Malfunction of a Pressurizer Code Safety Valve | -- | 01/04/1993 | -- |
| IN-93-01 | Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies | -- | 01/04/1993 | -- |
Page Last Reviewed/Updated Monday, March 03, 2025
Page Last Reviewed/Updated Monday, March 03, 2025