| Document Number |
Title |
Revision |
Publish Date |
Reviewed Date |
| IN-96-72 |
Undetected Failures That May Occur During Patient Treatments with Teletherapy Devices |
-- |
12/24/1996 |
-- |
| IN-96-71 |
Licensee Response to Indications of Tampering, Vandalism, or Malicious Mischief |
-- |
12/27/1996 |
-- |
| IN-96-70 |
Year 2000 Effect on Computer System Software |
-- |
12/24/1996 |
-- |
| IN-96-69 |
Operator Actions Affecting Reactivity |
-- |
12/20/1996 |
-- |
| IN-96-68 |
Incorrect Effective Diaphragm Area Values in Vendor Manual Result in Potential Failure of Pneumatic Diaphragm Actuators |
-- |
12/19/1996 |
-- |
| IN-96-67 |
Vulnerability of Emergency Diesel Generators to Fuel Oil/Lube Oil Incompatibility |
-- |
12/19/1996 |
-- |
| IN-96-66 |
Recent Misadministrations Caused by Incorrect Calibrations of Strontium-90 Eye Applicators |
-- |
12/13/1996 |
-- |
| IN-96-65 |
Undetected Accumulations of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown (with figure) |
-- |
12/11/1996 |
-- |
| IN-96-64 |
Modifications to Containment Blowout Panels Without Appropriate Design Controls |
-- |
12/10/1996 |
-- |
| IN-96-63 |
Potential Safety Issue Regarding the Shipment of Fissile Material |
-- |
12/05/1996 |
-- |
| IN-96-62 |
Potential Failure of the Instantaneous Trip Function of General Electric RMS-9 Programmers |
-- |
11/20/1996 |
-- |
| IN-96-61 |
Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly Installed Release Nut (with figure) |
-- |
11/20/1996 |
-- |
| IN-96-60 |
Potential Common-Mode Post-Accident Failure of Residual Heat Removal Heat Exchangers |
-- |
11/14/1996 |
-- |
| IN-96-59 |
Potential Degradation of Post Loss-of-Coolant Re- Circulation Capability as a Result of Debris |
-- |
10/30/1996 |
-- |
| IN-96-58 |
RCP Seal Replacement with Pump on Backseat |
-- |
10/30/1996 |
-- |
| IN-96-57 |
Incident-reporting Requirements Involving Intakes During a 24-hour Period That May Cause a Total Effective Dose Equivalent in Excess of 0.05 SV (5 rems) |
-- |
10/30/1996 |
-- |
| IN-96-56 |
Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
-- |
10/22/1996 |
-- |
| IN-96-55 |
Inadequate Net Positive Suction Head of Emergency Core Cooling and Containment Heat Removal Pumps under Design Basis Accident Conditions |
-- |
10/22/1996 |
-- |
| IN-96-54 |
Vulnerability of Stainless Steel to Corrosion When Sensitized |
-- |
10/17/1996 |
-- |
| IN-96-53 |
Retrofit to Amersham 660 Posilock Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility |
S1 |
06/23/1997 |
-- |
| -- |
10/15/1996 |
-- |
| IN-96-52 |
Cracked Insertion Rods on Troxler Model 3400 Series Portable Moisture Density Gauges |
-- |
09/26/1996 |
-- |
| IN-96-51 |
Residual Contamination Remaining in Krypton-85 Handling System after Venting |
-- |
09/11/1996 |
-- |
| IN-96-50 |
Problems with Levering-in Devices in Westinghouse Circuit Breakers (with figures) |
-- |
09/04/1996 |
-- |
| IN-96-49 |
Thermally Induced Pressurization of Nuclear Power Facility Piping |
-- |
08/20/1996 |
-- |
| IN-96-48 |
Motor-Operated Valve Performance Issues |
S1 |
07/24/1998 |
-- |
| -- |
08/21/1996 |
-- |
| IN-96-47 |
Recordkeeping, Decommissioning Notifications for Disposals of Radioactive Waste by Land Burial Authorized under Former 10 CFR 20.304, 20.302, and Current 20.2002 |
-- |
08/19/1996 |
-- |
| IN-96-46 |
Zinc Plating of Hardened Metal Parts and Removal of Protective Coatings in Refurbished Circuit Breakers |
-- |
08/12/1996 |
-- |
| IN-96-45 |
Potential Common-Mode Post-Accident Failure of Containment Coolers |
-- |
08/12/1996 |
-- |
| IN-96-44 |
Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly |
S1 |
07/02/1997 |
-- |
| -- |
08/05/1996 |
-- |
| IN-96-43 |
Failures of General Electric Magne-Blast Circuit Breakers |
-- |
08/02/1996 |
-- |
| IN-96-42 |
Unexpected Opening of Multiple Safety Relief Valves |
-- |
08/05/1996 |
-- |
| IN-96-41 |
Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation |
-- |
07/26/1996 |
-- |
| IN-96-40 |
Deficiencies in Material Dedication and Procurement Practices and in Audits of Vendors |
S1 |
10/07/1996 |
-- |
| -- |
07/25/1996 |
-- |
| IN-96-39 |
Estimates of Decay Heat Using Ans 5.1 Decay Heat Standard May Vary Significantly |
-- |
07/05/1996 |
-- |
| IN-96-38 |
Results of Steam Generator Tube Examinations |
-- |
06/21/1996 |
-- |
| IN-96-37 |
Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
-- |
06/18/1996 |
-- |
| IN-96-36 |
Degradation of Cooling Water Systems Due to Icing |
-- |
06/12/1996 |
-- |
| IN-96-35 |
Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training |
-- |
06/11/1996 |
-- |
| IN-96-34 |
Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket |
-- |
05/31/1996 |
-- |
| IN-96-33 |
Erroneous Data from Defective Thermocouple Results in a Fire |
-- |
05/24/1996 |
-- |
| IN-96-32 |
Implementation of 10 CFR 50.55a(g)(6)(Ii)(A), "Augmented Examination of Reactor Vessel" |
-- |
06/05/1996 |
-- |
| IN-96-31 |
Cross-Tied Safety Injection Accumulators |
-- |
05/22/1996 |
-- |
| IN-96-30 |
Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves |
-- |
05/21/1996 |
-- |
| IN-96-29 |
Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors |
-- |
05/20/1996 |
-- |
| IN-96-28 |
Suggested Guidance Relating to Development and Implementation of Corrective Action |
-- |
05/01/1996 |
-- |
| IN-96-27 |
Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation |
-- |
05/01/1996 |
-- |
| IN-96-26 |
Recent Problems with Overhead Cranes |
-- |
04/30/1996 |
-- |
| IN-96-25 |
Traversing In-Core Probe Overwithdrawn at LaSalle County Station, Unit 1 |
-- |
04/30/1996 |
-- |
| IN-96-24 |
Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing |
-- |
04/25/1996 |
-- |
| IN-96-23 |
Fires in Emergency Diesel Generators Exciters During Operation Following Undetected Fuse Blowing |
-- |
04/22/1996 |
-- |
| IN-96-22 |
Improper Equipment Settings Due to the Use of Nontemperature-Compensated Test Equipment |
-- |
04/11/1996 |
-- |
| IN-96-21 |
Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices |
-- |
04/10/1996 |
-- |
| IN-96-20 |
Demonstration of Associated Equipment Operability |
-- |
04/04/1996 |
-- |
| IN-96-19 |
Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal |
-- |
04/02/1996 |
-- |
| IN-96-18 |
Compliance with 10 CFR Part 20 for Airborne Thorium |
-- |
03/25/1996 |
-- |
| IN-96-17 |
Reactor Operation Inconsistent with the Updated Final Safety Analysis Report |
-- |
03/18/1996 |
-- |
| IN-96-16 |
BWR Operation with Indicated Flow less than Natural Circulation |
-- |
03/14/1996 |
-- |
| IN-96-15 |
Unexpected Plant Performance During Performance of New Surveillance Tests |
-- |
03/08/1996 |
-- |
| IN-96-14 |
Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 |
-- |
03/01/1996 |
-- |
| IN-96-13 |
Potential Containment Leak Paths Through Hydrogen Analyzers |
-- |
02/26/1996 |
-- |
| IN-96-12 |
Control Rod Insertion Problems |
-- |
02/15/1996 |
-- |
| IN-96-11 |
Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations |
-- |
02/14/1996 |
-- |
| IN-96-10 |
Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances |
-- |
02/13/1996 |
-- |
| IN-96-09 |
Damage in Foreign Steam Generator Internals |
S1 |
07/10/1996 |
-- |
| -- |
02/12/1996 |
-- |
| IN-96-08 |
Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve |
-- |
02/05/1996 |
-- |
| IN-96-07 |
Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves |
-- |
01/26/1996 |
-- |
| IN-96-06 |
Design and Testing Deficiencies of Tornado Dampers at Nuclear Power Plants |
-- |
01/25/1996 |
-- |
| IN-96-05 |
Partial Bypass of Shutdown Cooling Flow from the Reactor Vessel |
-- |
01/18/1996 |
-- |
| IN-96-04 |
Incident Reporting Requirements for Radiography Licensees |
-- |
01/10/1996 |
-- |
| IN-96-03 |
Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects |
-- |
01/05/1996 |
-- |
| IN-96-02 |
Inoperability of Power-Operated Relief Valves Masked by Downstream Indications |
-- |
01/05/1996 |
-- |
| IN-96-01 |
Potential for High Post-Accident Closed-cycle |
-- |
01/03/1996 |
-- |