| File Name |
Date |
Description |
| in96048s1 |
07/24/1998 |
Motor-Operated Valve Performance Issues |
| in96044s1 |
07/02/1997 |
Failure of Reactor Trip Breaker from Cracking of Phenolic
Material in Secondary Contact Assembly |
| in96053s1 |
06/23/1997 |
Retrofit to Amersham 660 Posilock Radiography Camera
to Correct Inconsistency in 10 CFR Part 34 Compatibility |
| in96071 |
12/27/1996 |
Licensee Response to Indications of Tampering, Vandalism,
or Malicious Mischief |
| in96072 |
12/24/1996 |
Undetected Failures That May Occur During Patient Treatments
with Teletherapy Devices |
| in96070 |
12/24/1996 |
Year 2000 Effect on Computer System Software |
| in96069 |
12/20/1996 |
Operator Actions Affecting Reactivity |
| in96068 |
12/19/1996 |
Incorrect Effective Diaphragm Area Values in Vendor
Manual Result in Potential Failure of Pneumatic Diapragm Actuators
|
| in96067 |
12/19/1996 |
Vulnerability of Emergency Diesel Generators to Fuel
Oil/Lube Oil Incompatibility |
| in96066 |
12/13/1996 |
Recent Misadministrations Caused by Incorrect Calibrations
of Strontium-90 Eye Applicators |
| in96065 |
12/11/1996 |
Undetected Accumulations of Gas in Reactor Coolant System
and Inaccurate Reactor Water Level Indication During Shutdown (with
figure) |
| in96064 |
12/10/1996 |
Modifications to Containment Blowout Panels Without
Appropriate Design Controls |
| in96063 |
12/05/1996 |
Potential Safety Issue Regarding the Shipment of Fissile
Material |
| in96062 |
11/20/1996 |
Potential Failure of the Instantaneous Trip Function
of General Electric RMS-9 Programmers |
| in96061 |
11/20/1996 |
Failure of a Main Steam Safety Valve to Reseat Caused
by an Improperly Installed Release Nut (with figure) |
| in96060 |
11/14/1996 |
Potential Common-Mode Post-Accident Failure of Residual
Heat Removal Heat Exchangers |
| in96059 |
10/30/1996 |
Potential Degradation of Post Loss-of-Coolant Re- Circulation
Capability as a Result of Debris |
| in96058 |
10/30/1996 |
RCP Seal Replacement with Pump on Backseat |
| in96057 |
10/30/1996 |
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) |
| in96056 |
10/22/1996 |
Problems Associated with Testing, Tuning, or Resetting
of Digital Control Systems While at Power |
| in96055 |
10/22/1996 |
Inadequate Net Positive Suction Head of Emergency Core
Cooling and Containment Heat Removal Pumps under Design Basis Accident
Conditions |
| in96054 |
10/17/1996 |
Vulnerability of Stainless Steel to Corrosion When Sensitized
|
| in96053 |
10/15/1996 |
Retrofit to Amersham 660 Posilock Radiography Camera
to Correct Inconsistency in 10 CFR Part 34 Compatibility |
| in96040s1 |
10/07/1996 |
Deficiencies in Material Dedication and Procurement
Practices and in Audits of Vendors |
| in96052 |
09/26/1996 |
Cracked Insertion Rods on Troxler Model 3400 Series
Portable Moisture Density Guages |
| in96051 |
09/11/1996 |
Residual Contamination Remaining in Krypton-85 Handling
System after Venting |
| in96050 |
09/04/1996 |
Problems with Levering-in Devices in Westinghouse Circuit
Breakers (with figures) |
| in96048 |
08/21/1996 |
Motor-Operated Valve Performance Issues |
| in96049 |
08/20/1996 |
Thermally Induced Pressurization of Nuclear Power Facility
Piping |
| in96047 |
08/19/1996 |
Recordkeeping, Decommissioning Notifications for Disposals
of Radioactive Waste by Land Burial Authorized under Former 10 CFR
20.304, 20.302, and Current 20.2002 |
| in96046 |
08/12/1996 |
Zinc Plating of Hardened Metal Parts and Removal of
Protective Coatings in Refurbished Circuit Breakers |
| in96045 |
08/12/1996 |
Potential Common-Mode Post-Accident Failure of Containment
Coolers |
| in96044 |
08/05/1996 |
Failure of Reactor Trip Breaker from Cracking of Phenolic
Material in Secondary Contact Assembly |
| in96042 |
08/05/1996 |
Unexpected Opening of Multiple Safety Relief Valves
|
| in96043 |
08/02/1996 |
Failures of General Electric Magne-Blast Circuit Breakers
|
| in96041 |
07/26/1996 |
Effects of a Decrease in Feedwater Temperature on Nuclear
Instrumentation |
| in96040 |
07/25/1996 |
Deficiencies in Material Dedication and Procurement
Practices and in Audits of Vendors |
| in96009s1 |
07/10/1996 |
Damage in Foreign Steam Generator Internals |
| in96039 |
07/05/1996 |
Estimates of Decay Heat Using Ans 5.1 Decay Heat Standard
May Vary Significantly |
| in96038 |
06/21/1996 |
Results of Steam Generator Tube Examinations |
| in96037 |
06/18/1996 |
Inaccurate Reactor Water Level Indication and Inadvertent
Draindown During Shutdown |
| in96036 |
06/12/1996 |
Degradation of Cooling Water Systems Due to Icing |
| in96035 |
06/11/1996 |
Failure of Safety Systems on Self-Shielded Irradiators
Because of Inadequate Maintenance and Training |
| in96032 |
06/05/1996 |
Implementation of 10 CFR 50.55a(g)(6)(Ii)(A), "Augmented
Examination of Reactor Vessel" |
| in96034 |
05/31/1996 |
Hydrogen Gas Ignition During Closure Welding of a VSC-24
Multi-Assembly Sealed Basket |
| in96033 |
05/24/1996 |
Erroneous Data from Defective Thermocouple Results in
a Fire |
| in96031 |
05/22/1996 |
Cross-Tied Safety Injection Accumulators |
| in96030 |
05/21/1996 |
Inaccuracy of Diagnostic Equipment for Motor-Operated
Butterfly Valves |
| in96029 |
05/20/1996 |
Requirements in 10 CFR Part 21 for Reporting and Evaluating
Software Errors |
| in96028 |
05/01/1996 |
Suggested Guidance Relating to Development and Implementation
of Corrective Action |
| in96027 |
05/01/1996 |
Potential Clogging of High Pressure Safety Injection
Throttle Valves During Recirculation |
| in96026 |
04/30/1996 |
Recent Problems with Overhead Cranes |
| in96025 |
04/30/1996 |
Traversing In-Core Probe Overwithdrawn at Lasalle County
Station, Unit 1 |
| in96024 |
04/25/1996 |
Preconditioning of Molded-Case Circuit Breakers Before
Surveillance Testing |
| in96023 |
04/22/1996 |
Fires in Emergency Diesel Generators Exciters During
Operation Following Undetected Fuse Blowing |
| in96022 |
04/11/1996 |
Improper Equipment Settings Due to the Use of Nontemperature-Compensated
Test Equipment |
| in96021 |
04/10/1996 |
Safety Concerns Related to the Design of the Door Interlock
Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading
Brachytherapy Devices |
| in96020 |
04/04/1996 |
Demonstration of Associated Equipment Operability |
| in96019 |
04/02/1996 |
Failure of Tone Alert Radios to Activate When Receiving
a Shortened Activation Signal |
| in96018 |
03/25/1996 |
Compliance with 10 CFR Part 20 for Airborne Thorium
|
in96017 |
03/18/1996 |
Reactor Operation Inconsistent with the Updated Final
Safety Analysis Report |
| in96016 |
03/14/1996 |
Bwr Operation with Indicated Flow less than Natural
Circulation |
| in96015 |
03/08/1996 |
Unexpected Plant Performance During Performance of New
Surveillance Tests |
| in96014 |
03/01/1996 |
Degradation of Radwaste Facility Equipment at Millstone
Nuclear Power Station, Unit 1 |
| in96013 |
02/26/1996 |
Potential Containment Leak Paths Through Hydrogen Analyzers
|
| in96012 |
02/15/1996 |
Control Rod Insertion Problems |
| in96011 |
02/14/1996 |
Ingress of Demineralizer Resins Increases Potential
for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations
|
| in96010 |
02/13/1996 |
Potential Blockage by Debris of Safety System Piping
Which Is Not Used During Normal Operation or Tested During Surveillances |
| in96009 |
02/12/1996 |
Damage in Foreign Steam Generator Internals |
| in96008 |
02/05/1996 |
Thermally Induced Pressure Locking of a High Pressure
Coolant Injection Gate Valve |
| in96007 |
01/26/1996 |
Slow Five Percent Scram Insertion Times Caused by Viton
Diaphragms in Scram Solenoid Pilot Valves |
| in96006 |
01/25/1996 |
Design and Testing Deficiencies of Tornado Dampers at
Nuclear Power Plants |
| in96005 |
01/18/1996 |
Partial Bypass of Shutdown Cooling Flow from the Reactor
Vessel |
| in96004 |
01/10/1996 |
Incident Reporting Requirements for Radiography Licensees
|
| in96003 |
01/05/1996 |
Main Steam Safety Valve Setpoint Variation as a Result
of Thermal Effects |
| in96002 |
01/05/1996 |
Inoperability of Power-Operated Relief Valves Masked
by Downstream Indications |
| in96001 |
01/03/1996 |
Potential for High Post-Accident Closed-cycle |
