Information Notices - 1986
This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.
Document Number | Title | Revision | Publish Date | Reviewed Date |
|---|---|---|---|---|
IN-86-110 | Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants | -- | -- | |
IN-86-109 | Diaphragm Failure in Scram Outlet Valve Causing Rod Insertion | -- | -- | |
IN-86-108 | Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion | S3 | -- | |
S2 | -- | |||
S1 | -- | |||
-- | -- | |||
IN-86-107 | Entry into PWR Cavity with Retractable Incore Detector Thimbles Withdrawn | -- | -- | |
IN-86-106 | Feedwater Line Break | S3 | -- | |
S2 | -- | |||
S1 | -- | |||
-- | -- | |||
IN-86-105 | Potential for Loss of Reactor Trip Capability at Intermediate Power Levels | -- | -- | |
IN-86-104 | Unqualified Butt Splice Connectors Identified in Qualified Penetrations | -- | -- | |
IN-86-103 | Respirator Coupling Nut Assembly Failures | -- | -- | |
IN-86-102 | Repeated Multiple Failures of Steam Generator Hydraulic Snubbers Due to Control Valve Sensitivity | -- | -- | |
IN-86-101 | Loss of Decay Heat Removal Due to Loss of Fluid Levels in Reactor Coolant System | -- | -- | |
IN-86-100 | Loss of Offsite Power to Vital Busses at Salem 2 | -- | -- | |
IN-86-99 | Degradation of Steel Containments | S1 | -- | |
-- | -- | |||
IN-86-98 | Offsite Medical Services | -- | -- | |
IN-86-97 | Emergency Communications System | -- | -- | |
IN-86-96 | Heat Exchanger Fouling Can Cause Inadequate Operability of Service Water Systems | -- | -- | |
IN-86-95 | Leak Testing Iodine-125 Sealed Sources in Lixi, Inc. Imaging Devices and Bone Mineral Analyzers | -- | -- | |
IN-86-94 | Hilti Concrete Expansion Anchor Bolts | -- | -- | |
IN-86-93 | IEB 85-03 Evaluation of Motor-Operators Identifies Improper Torque Switch Settings | -- | -- | |
IN-86-92 | Pressurizer Safety Valve Reliability | -- | -- | |
IN-86-91 | Limiting Access Authorizations | -- | -- | |
IN-86-90 | Requests to Dispose of Very Low-Level Radioactive Waste Pursuant to 10 CFR 20.302 | -- | -- | |
IN-86-89 | Uncontrolled Rod Withdrawal Because of a Single Failure | -- | -- | |
IN-86-88 | Compensatory Measures for Prolonged Periods of Security System Failures | -- | -- | |
IN-86-87 | Loss of Offsite Power upon an Automatic Bus Transfer | -- | -- | |
IN-86-86 | Clarification of Requirements for Fabrication and Export of Certain Previously Approved Type B Packages | -- | -- | |
IN-86-85 | Enforcement Actions Against Medical Licensees for Willfull Failure to Report Misadministrations | -- | -- | |
IN-86-84 | Rupture of Nominal 40-Millicurie Iodine-125 Brachytherapy Seed Causing Significant Spread of Radioactive Contamination | -- | -- | |
IN-86-83 | Underground Pathways into Protected Areas, Vital Areas, Material Access Areas, and Controlled Access Areas | -- | -- | |
IN-86-82 | Failures of Scram Discharge Volume Vent and Drain Valves | 1 | -- | |
-- | -- | |||
IN-86-81 | Broken External Closure Springs on Atwood & Morrill Main Steam Isolation Valves | S1 | -- | |
-- | -- | |||
IN-86-80 | Unit Startup with Degraded High Pressure Safety Injection System | -- | -- | |
IN-86-79 | Degradation or Loss of Charging Systems at PWR Nuclear Power Plants Using Swing-Pump Design | -- | -- | |
IN-86-78 | Scram Solenoid Pilot Valve (SSPV) Rebuild Kit Problems | -- | -- | |
IN-86-77 | Computer Program Error Report Handling | -- | -- | |
IN-86-76 | Problems Noted in Control Room Emergency Ventilation Systems | -- | -- | |
IN-86-75 | Incorrect Maintenance Procedure on Traversing Incore Probe Lines | -- | -- | |
IN-86-74 | Reduction of Reactor Coolant Inventory because of Misalignment of RHR Valves | -- | -- | |
IN-86-73 | Recent Emergency Diesel Generator Problems | -- | -- | |
IN-86-72 | Failure 17-7 PH Stainless Steel Springs in Valcor Valves Due to Hydrogen Embrittlement | -- | -- | |
IN-86-71 | Recent Identified Problems with Limitorque Motor Operators | -- | -- | |
IN-86-70 | Potential Failure of All Emergency Diesel Generators | -- | -- | |
IN-86-69 | Spurious System Isolations Caused by the Panalarm Model 86 Thermocouple Monitor | -- | -- | |
IN-86-68 | Stuck Control Rod | -- | -- | |
IN-86-67 | Portable Moisture/Density Gauges: ... Incidents and Common Violations of Requirements for Use, Transportation, and Storage | -- | -- | |
IN-86-66 | Potential for Failure of Replacement AC Coils ... Westinghouse Electric ... for ... Class 1E Motor Starters and Contactors | -- | -- | |
IN-86-65 | Malfunctions of ITT Barton Model 580 Series Switches During Requalification Testing | -- | -- | |
IN-86-64 | Deficiencies in Upgrade Programs for Plant Emergency Operating Procedures | S1 | -- | |
-- | -- | |||
IN-86-63 | Loss of Safety Injection Capability | -- | -- | |
IN-86-62 | Potential Problems in Westinghouse Molded Case Circuit Breakers Equipped with a Shunt Trip | -- | -- | |
IN-86-61 | Failure of Auxiliary Feedwater Manual Isolation Valve | -- | -- | |
IN-86-60 | Unanalyzed Post-LOCA Release Paths | -- | -- | |
IN-86-59 | Increased Monitoring of ... Patients with Implanted Coratomic, Inc. Model C-100 and C-101 Nuclear-Powered Cardiac Pacemakers | -- | -- | |
IN-86-58 | Dropped Fuel Assembly | -- | -- | |
IN-86-57 | Operating Problems with Solenoid Operated Valves at Nuclear Power Plants | -- | -- | |
IN-86-56 | Reliability of Main Steam Safety Valves | -- | -- | |
IN-86-55 | Delayed Access to Safety-Related Areas and Equipment During Plant Emergencies | -- | -- | |
IN-86-54 | Criminal Prosecution ... Former Radiation Safety Officer Who ... Directed an Unqualified Individual to Perform Radiography | -- | -- | |
IN-86-53 | Improper Installation of Heat Shrinkable Tubing | -- | -- | |
IN-86-52 | Conductor Insulation Degradation on Foxboro Model E Controllers | -- | -- | |
IN-86-51 | Excessive Pneumatic Leakage in the Automatic Depressurization System | -- | -- | |
IN-86-50 | Inadequate Testing to Detect Failures of Safety-Related Pneumatic Components or Systems | -- | -- | |
IN-86-49 | Age/Environment Induced Electrical Cable Failures | -- | -- | |
IN-86-48 | Inadequate Testing of Boron Solution Concentration in the Standby Liquid Control System | -- | -- | |
IN-86-47 | Erratic Behavior of Static "O" Ring Differential Pressure Switches | -- | -- | |
IN-86-46 | Improper Cleaning and Decontamination of Respiratory Protection Equipment | -- | -- | |
IN-86-45 | Potential Falsification of Test Reports on Flanges Manufactured by Golden Gate Forge and Flange, Inc. | -- | -- | |
IN-86-44 | Failure to Follow Procedures when Working in High Radiation Areas | -- | -- | |
IN-86-43 | Problems with Silver Zeolite Sampling of Airborne Radioiodine | -- | -- | |
IN-86-42 | Improper Maintenance of Radiation Monitoring Systems | -- | -- | |
IN-86-41 | Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters | -- | -- | |
IN-86-40 | Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs | -- | -- | |
IN-86-39 | Failures of RHR Pump Motors and Pump Internals | -- | -- | |
IN-86-38 | Deficient Operator Actions Following Dual Function Valve Failures | -- | -- | |
IN-86-37 | Degradation of Station Batteries | -- | -- | |
IN-86-36 | Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors | -- | -- | |
IN-86-35 | Fire in Compressible Material at Dresden Unit 3 | -- | -- | |
IN-86-34 | Improper Assembly, Material Selection, and Test of Valves and Their Actuators | -- | -- | |
IN-86-33 | Information for Licensee Regarding the Chernobyl Nuclear Plant Accident | -- | -- | |
IN-86-32 | Request for Collection of Licensee Radioactivity Measurements Attributed to the Chernobyl Nuclear Plant Accident | S1 | -- | |
-- | -- | |||
IN-86-31 | Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges | S1 | -- | |
-- | -- | |||
IN-86-30 | Design Limitations of Gaseous Effluent Monitoring Systems | -- | -- | |
IN-86-29 | Effects of Changing Valve Motor-Operator Switch Settings | -- | -- | |
IN-86-28 | Telephone Numbers to the NRC Operations Center and Regional Offices | -- | -- | |
IN-86-27 | Access Control at Nuclear Facilities | -- | -- | |
IN-86-26 | Potential Problems in Generators Manufactured by Electrical Products Incorporated | -- | -- | |
IN-86-25 | Traceability and Material Control of Material and Equipment, Particularly Fasteners | S1 | -- | |
-- | -- | |||
IN-86-24 | Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders | -- | -- | |
IN-86-23 | Excessive Skin Exposures Due to Contamination with Hot Particles | -- | -- | |
IN-86-22 | Underresponse of Radiation Survey Instrument to High Radiation Fields | -- | -- | |
IN-86-21 | Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders | S2 | -- | |
S1 | -- | |||
-- | -- | |||
IN-86-20 | Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 | -- | -- | |
IN-86-19 | Reactor Coolant Pump Shaft Failure at Crystal River | -- | -- | |
IN-86-18 | NRC On-Scene Response During a Major Emergency | -- | -- | |
IN-86-17 | Update of Failure of Automatic Sprinkler System Valves to Operate | -- | -- | |
IN-86-16 | Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves | -- | -- | |
IN-86-15 | Loss of Offsite Power Caused by Problems in Fiber Optics Systems | -- | -- | |
IN-86-14 | PWR Auxiliary Feedwater Pump Turbine Control Problems | S2 | -- | |
S1 | -- | |||
-- | -- | |||
IN-86-13 | Standby Liquid Control System Squib Valves Failure to Fire | S1 | -- | |
-- | -- | |||
IN-86-12 | Target Rock Two-Stage SRV Setpoint Drift | -- | -- | |
IN-86-11 | Inadequate Service Water Protection Against Core Melt Frequency | -- | -- | |
IN-86-10 | Safety Parameter Display System Malfunctions | -- | -- | |
IN-86-09 | Failure of Check and Stop Check Valves Subjected to Low Flow Conditions | -- | -- | |
IN-86-08 | Licensee Event Report (LER) Format Modification | -- | -- | |
IN-86-07 | Lack of ... Instruction and ... Observance of Precautions During Maintenance and Testing of Diesel Generator ... Governors | -- | -- | |
IN-86-06 | Failure of Lifting Rig Attachment While Lifting the Upper Guide Structure at St. Lucie Unit 1 | -- | -- | |
IN-86-05 | Main Steam Safety Valve Test Failures and Ring Setting Adjustments | S1 | -- | |
-- | -- | |||
IN-86-04 | Transient Due to Loss of Power to Integrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox | -- | -- | |
IN-86-03 | Potential Deficiencies in Environmental Qualification of Limitorque Motor Valve Operator Wiring | -- | -- | |
IN-86-02 | Failure of Valve Operator Motor During Environmental Qualification Testing | -- | -- | |
IN-86-01 | Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage | -- | -- |
Page Last Reviewed/Updated Thursday, February 19, 2026
Page Last Reviewed/Updated Thursday, February 19, 2026