| 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 |
-- |
| 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 |
-- |