United States Nuclear Regulatory Commission - Protecting People and the Environment

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 --
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 --
Page Last Reviewed/Updated Tuesday, September 01, 2015