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Information Notices - 1996
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| 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 A 03/18/1996 B | -- |
| 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 A 02/14/1996 B | -- |
| 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 | -- |
Page Last Reviewed/Updated Wednesday, February 12, 2025
Page Last Reviewed/Updated Wednesday, February 12, 2025