| Document Number |
Title |
Revision |
Publish Date |
Reviewed Date |
| IN-94-90 |
Transient Resulting in a Reactor Trip and Multiple Safety Injection System Actuations at Salem |
-- |
12/30/1994 |
-- |
| IN-94-89 |
Equipment Failures at Irradiator Facilities |
-- |
12/28/1994 |
-- |
| IN-94-88 |
Inservice Inspection Deficiencies Result in Severely Degraded Steam Generator Tubes |
-- |
12/23/1994 |
-- |
| IN-94-87 |
Unanticipated Crack in a Particular Heat of Alloy 600 Used for Westinghouse Mechanical Plugs for Steam Generator Tubes |
-- |
12/22/1994 |
-- |
| IN-94-86 |
Legal Actions Against Thermal Science, Inc., Manufacturer of Thermo-Lag |
S1 |
11/15/1995 |
-- |
| -- |
12/22/1994 |
-- |
| IN-94-85 |
Problems with the Latching Mechanism in Potter and Brumfield R-10-E3286-2 Relays |
-- |
12/21/1994 |
-- |
| IN-94-84 |
Air Entrainment in Terry Turbine Lubricating Oil System |
-- |
12/04/1994 |
-- |
| IN-94-83 |
Reactor Trip Followed by Unexpected Events |
-- |
12/06/1994 |
-- |
| IN-94-82 |
Concerns Regarding Essential Chiller Reliability During Periods of Low Cooling Water Temperature |
-- |
12/05/1994 |
-- |
| IN-94-81 |
Accuracy of Bioassay and Environmental Sampling Results |
-- |
11/25/1994 |
-- |
| IN-94-80 |
Inadequate DC Ground Detection in Direct Current Distribution System |
-- |
11/25/1994 |
-- |
| IN-94-79 |
Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping |
-- |
11/23/1994 |
-- |
| IN-94-78 |
Electrical Component Failure Due to Degradation of Polyvinyl Chloride Wire Insulation |
-- |
11/21/1994 |
-- |
| IN-94-77 |
Malfunction in Main Generator Voltage Regulator Causing Overvoltage at Safety-related Electrical Equipment |
-- |
11/17/1994 |
-- |
| IN-94-76 |
Recent Failures of Charging/safety Injection Pumps |
-- |
10/26/1994 |
-- |
| IN-94-75 |
Minimum Temperature for Criticality |
-- |
10/14/1994 |
-- |
| IN-94-74 |
Facility Management Responsibilities for Purchased or Contracted Services for Radiation Therapy Programs |
-- |
10/13/1994 |
-- |
| IN-94-73 |
Clarification of Criticality Reporting Criteria |
-- |
10/12/1994 |
-- |
| IN-94-72 |
Increased Control Rod Drop Time From Crud Buildup |
-- |
10/05/1994 |
-- |
| IN-94-71 |
Degradation of Scram Solenoid Pilot Valve Pressure and Exhaust Diaphragms |
-- |
10/04/1994 |
-- |
| IN-94-70 |
Issues Associated with Use of Strontium-90 and Other Beta Emitting Radiopharmaceuticals |
-- |
09/29/1994 |
-- |
| IN-94-69 |
Potential Inadequacies in the Prediction of Torque Requirements for and Torque Output of Motor- Operated Butterfly Valves |
-- |
09/28/1994 |
-- |
| IN-94-68 |
Safety-Related Equipment Failures Caused by Faulted Indicating Lamps |
-- |
09/27/1994 |
-- |
| IN-94-67 |
Problems with Henry Pratt Motor-Operated Butter- Fly Valves |
-- |
09/26/1994 |
-- |
| IN-94-66 |
Overspeed of Turbine-Driven Pumps Caused by Governor Valve Stem Binding |
S1 |
06/16/1995 |
-- |
| -- |
09/19/1994 |
-- |
| IN-94-65 |
Potential Error in Manual Brachytherapy Dose Calculations Generated Using a Computerized Treatment Planning System |
-- |
09/12/1994 |
-- |
| IN-94-64 |
Reactivity Insertion Transient and Accident Limits for High Burnup Fuel |
S1 |
04/06/1995 |
-- |
| -- |
08/31/1994 |
-- |
| IN-94-63 |
Boric Acid Corrosion of Charging Pump Casing Caused by Cladding Cracks. |
-- |
08/30/1994 |
-- |
| IN-94-62 |
Operational Experience on Steam Generator Tube Leaks and Tube Ruptures |
-- |
08/30/1994 |
-- |
| IN-94-61 |
Corrosion of William Powell Gate Valve Disc Holders |
S1 |
05/25/1995 |
-- |
| -- |
08/25/1994 |
-- |
| IN-94-60 |
Potential Overpressurization of Main Stream System |
-- |
08/24/1994 |
-- |
| IN-94-59 |
Accelerated Dealloying of Cast Aluminum-Bronze Valves Caused by Microbiologically Induced Corrosion |
-- |
08/17/1994 |
-- |
| IN-94-58 |
Reactor Coolant Pump Lube Oil Fire |
-- |
08/16/1994 |
-- |
| IN-94-57 |
Debris in Containment and the Residual Heat Removal System |
-- |
08/12/1994 |
-- |
| IN-94-56 |
Inaccuracy of Safety Valve Set Pressure Determination Using Assist Devices |
-- |
08/11/1994 |
-- |
| IN-94-55 |
Problems with Copes-Vulcan Power-Operated Relief Valves |
-- |
08/04/1994 |
-- |
| IN-94-54 |
Failures of General Electric Magne-Blast Circuit Breakers to Latch Closed |
-- |
08/01/1994 |
-- |
| IN-94-53 |
Hydrogen Gas Burn Inside Pressurizer During Welding |
-- |
07/18/1994 |
-- |
| IN-94-52 |
Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
-- |
07/15/1994 |
-- |
| IN-94-51 |
Inappropriate Greasing of Double Shielded Motor Bearings |
-- |
07/15/1994 |
-- |
| IN-94-50 |
Failure of General Electric Contactors to Pull in at the Required Voltage |
-- |
07/14/1994 |
-- |
| IN-94-49 |
Failure of Torque Switch Roll Pins |
-- |
07/06/1994 |
-- |
| IN-94-48 |
Snubber Lubricant Degradation in High-Temperature Environments |
-- |
06/30/1994 |
-- |
| IN-94-47 |
Accuracy of Information Provided to NRC During the Licensing Process |
-- |
06/21/1994 |
-- |
| IN-94-46 |
Nonconservative Reactor Coolant System Leakage Calculation |
-- |
06/20/1994 |
-- |
| IN-94-45 |
Potential Common-Mode Failure Mechanism for Large Vertical Pumps |
-- |
06/17/1994 |
-- |
| IN-94-44 |
Main Steam Isolation Valve Failure To Close On Demand Because Of Inadequate Maintenance and Testing |
-- |
06/16/1994 |
-- |
| IN-94-43 |
Determination of Primary-to-Secondary Steam Generator Leak Rate |
-- |
06/10/1994 |
-- |
| IN-94-42 |
Cracking in the Lower Region of the Core Shroud in Boiling-water Reactors |
-- |
06/07/1994 |
-- |
| IN-94-41 |
Problems with General Electric Type CR124 Overload Relay Ambient Compensation |
-- |
06/07/1994 |
-- |
| IN-94-40 |
Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood Unit 2 |
S1 |
12/15/1994 |
-- |
| -- |
05/26/1994 |
-- |
| IN-94-39 |
Identified Problems in Gamma Stereotactic Radiosurgery |
-- |
05/31/1994 |
-- |
| IN-94-38 |
Results of a Special NRC Inspection at Dresden ... Unit 1 Following a Rupture of Service Water Inside Containment |
-- |
05/27/1994 |
-- |
| IN-94-37 |
Misadministration Caused By a Bent Interstitial Needle During Brachytherapy Procedure |
-- |
05/27/1994 |
-- |
| IN-94-36 |
Undetected Accumulation of Gas in Reactor Coolant System |
-- |
05/24/1994 |
-- |
| IN-94-35 |
NIOSH Respirator User Notices, "Inadvertent Separation of the MMR From the Facepiece of MSA Company MMR SCBA and Status" |
-- |
05/16/1994 |
-- |
| IN-94-34 |
Thermo-Lag 330-660 Flexi-Blanket Ampacity Derating Concerns |
-- |
05/13/1994 |
-- |
| IN-94-33 |
Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems |
-- |
05/09/1994 |
-- |
| IN-94-32 |
Revised Seismic Hazard Estimates |
-- |
04/29/1994 |
-- |
| IN-94-31 |
Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles |
-- |
04/14/1994 |
-- |
| IN-94-30 |
Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station |
S1 |
08/19/1994 |
-- |
| -- |
04/12/1994 |
-- |
| IN-94-29 |
Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure |
-- |
04/11/1994 |
-- |
| IN-94-28 |
Potential Problems with Fire-Barrier Penetration Seals |
-- |
04/05/1994 |
-- |
| IN-94-27 |
Facility Operating Concerns Resulting From Local Area Flooding |
-- |
03/31/1994 |
-- |
| IN-94-26 |
Personnel Hazards and Other Problems From Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor |
-- |
03/28/1994 |
-- |
| IN-94-25 |
Failure of Containment Spray Header Valve to Open Due to Excessive Pressure From Inertial Effects of Water |
-- |
03/25/1994 |
-- |
| IN-94-24 |
Inadequate Maintenance of Uninterruptable Power Supplies and Inverters |
-- |
03/24/1994 |
-- |
| IN-94-23 |
Guidance to hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program |
-- |
03/25/1994 |
-- |
| IN-94-22 |
Fire Endurance and Ampacity Derating Test Results for 3-hour Fire-Rated Thermo-Lag 330-1 Fire Barriers |
-- |
03/16/1994 |
-- |
| IN-94-21 |
Regulatory Requirements When No Operations Are Being Performed |
-- |
03/18/1994 |
-- |
| IN-94-20 |
Common-Cause Failures Due to Inadequate Design Control and Dedication |
-- |
03/17/1994 |
-- |
| IN-94-19 |
Emergency Diesel Generator Vulnerability to Failure From Cold Fuel Oil |
-- |
03/16/1994 |
-- |
| IN-94-18 |
Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) |
-- |
03/16/1994 |
-- |
| IN-94-17 |
Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use |
-- |
03/11/1994 |
-- |
| IN-94-16 |
Recent Incidents Resulting in Offsite Contamination |
-- |
03/03/1994 |
-- |
| IN-94-15 |
Radiation Exposures During an Event Involving a Fixed Nuclear Gauge |
-- |
03/02/1994 |
-- |
| IN-94-14 |
Failure to Implement Requirements for Biennial Medical Examinations and Notification to NRC of Changes in Medical Condition of Licensed Operators |
S1 |
04/14/1997 |
-- |
| -- |
02/24/1994 |
-- |
| IN-94-13 |
Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment |
S2 |
11/28/1994 |
-- |
| S1 |
06/28/1994 |
-- |
| -- |
02/22/1994 |
-- |
| IN-94-12 |
Insights Gained From Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment |
-- |
02/09/1994 |
-- |
| IN-94-11 |
Turbine Overspeed and Reactor Cooldown During Shutdown Evolution |
-- |
02/08/1994 |
-- |
| IN-94-10 |
Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key |
-- |
02/04/1994 |
-- |
| IN-94-09 |
Release of Patients with Residual Radioactivity From Medical Treatment and Control Areas ... Revised 10 CFR Part 20 |
-- |
02/03/1994 |
-- |
| IN-94-08 |
Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve |
-- |
02/01/1994 |
-- |
| IN-94-07 |
Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 |
-- |
01/28/1994 |
-- |
| IN-94-06 |
Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves |
-- |
01/28/1994 |
-- |
| IN-94-05 |
Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves |
-- |
01/19/1994 |
-- |
| IN-94-04 |
Digital Integrated Circuit Sockets with Intermittent Contact |
-- |
01/14/1994 |
-- |
| IN-94-03 |
Deficiencies Identified During Service Water System Operational Performance Inspections |
-- |
01/11/1994 |
-- |
| IN-94-02 |
Inoperability of General Electric Magne-blast |
-- |
01/07/1994 |
-- |
| IN-94-01 |
Turbine Blade Failure Caused by Torsional Excitation from Electrical System Disturbance |
-- |
01/07/1994 |
-- |