Information Notices - 1996
| 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 |
Page Last Reviewed/Updated Thursday, March 29, 2012
