Spotlight
Information Notices - 1995
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Document Number | Title | Revision | Publish Date | Reviewed Date |
|---|---|---|---|---|
IN-95-58 | 10 CFR 34.20; Final Effective Date | -- | -- | |
IN-95-57 | Risk Impact Study Regarding Maintenance During Low-Power Operation and Shutdown | -- | -- | |
IN-95-56 | Shielding Deficiency in Spent Fuel Transfer Canal at a Boiling-water Reactor | -- | -- | |
IN-95-55 | Handling Uncontained Yellowcake Outside of a Facility Processing Circuit | -- | -- | |
IN-95-54 | Decay Heat Management Practices During Refueling Outages | -- | -- | |
IN-95-53 | Failures of Main Steam Isolation Valves as a Result of Sticking Solenoid Pilot Valves | -- | -- | |
IN-95-52 | Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed From 3M Company Interim Fire Barrier Materials | S1 | -- | |
-- | -- | |||
IN-95-51 | Recent Incidents Involving Potential Loss of Control of Licensed Material | -- | -- | |
IN-95-50 | Safety Defect in Gammamed 12I Bronchial Catheter Clamping Adapters | -- | -- | |
IN-95-49 | Seismic Adequacy of Thermo-Lag Panels | S1 | -- | |
-- | -- | |||
IN-95-48 | Results of Shift Staffing Study | -- | -- | |
IN-95-47 | Unexpected Opening of a Safety/Relief Valve and Complications Involving Suppression Pool Cooling Strainer Blockage | 1 | -- | |
-- | -- | |||
IN-95-46 | Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor | -- | -- | |
IN-95-45 | American Power Service Falsification of American Society of Nondestructive Testing (ASNT) Certificates | -- | -- | |
IN-95-44 | Ensuring Compatible Use of Drive Cables Incorporating Use of Industrial Nuclear Company Ball-Type Male Connectors | -- | -- | |
IN-95-43 | Failure of the Bolt-Locking Device on Reactor Coolant Pump Turning Vane | -- | -- | |
IN-95-42 | Commission Decision on the Resolution of Generic Issue 23, "Reactor Coolant Pump Seal Failure" | -- | -- | |
IN-95-41 | Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators | -- | -- | |
IN-95-40 | Supplemental Information to Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes" | -- | -- | |
IN-95-39 | Brachytherapy Incidents Involving Treatment Planning Errors | -- | -- | |
IN-95-38 | Degradation of Boraflex Neutron Absorber in Spent Fuel Pool Storage Racks | -- | -- | |
IN-95-37 | Inadequate Offsite Power Systems Voltages During Design-Basis Events | -- | -- | |
IN-95-36 | Potential Problems with Post-Fire Emergency Lighting | S1 | -- | |
-- | -- | |||
IN-95-35 | Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation | -- | -- | |
IN-95-34 | Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves | -- | -- | |
IN-95-33 | Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 | -- | -- | |
IN-95-32 | Thermo-Lag 330-1 Flame Spread Test Results | -- | -- | |
IN-95-31 | Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference | -- | -- | |
IN-95-30 | Susceptibility of Low-Pressure Coolant Injection and Core Spray Injection Valves to Pressure Locking | -- | -- | |
IN-95-29 | Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems | -- | -- | |
IN-95-28 | Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites | -- | -- | |
IN-95-27 | NRC Review of Nuclear Energy Institute, "Thermo- Lag Combustibility Evaluation Methodology Plant Screening Guide | -- | -- | |
IN-95-26 | Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit | -- | -- | |
IN-95-25 | Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit | -- | -- | |
IN-95-24 | Summary of Licensed Operator Requalification Inspection Program Findings | -- | -- | |
IN-95-23 | Control Room Staffing Below Minimum Regulatory Requirements | -- | -- | |
IN-95-22 | Hardened or Contaminated Lubricants Cause Metal- Clad Circuit Breaker Failures | -- | -- | |
IN-95-21 | Unexpected Degradation of Lead Storage Batteries | -- | -- | |
IN-95-20 | Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation into the Sensor Cell | -- | -- | |
IN-95-19 | Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism | -- | -- | |
IN-95-18 | Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves | S1 | -- | |
-- | -- | |||
IN-95-17 | Reactor Vessel Top Guide and Core Plate Cracking | -- | -- | |
IN-95-16 | Vibration Caused by Increased Flow in a Boiling Water Reactor | -- | -- | |
IN-95-15 | Inadequate Logic Testing of Safety-Related Circuits | -- | -- | |
IN-95-14 | Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking | -- | -- | |
IN-95-13 | Potential for Data Collection Equipment to Affect Protection System Performance | S1 | -- | |
-- | -- | |||
IN-95-12 | Potentially Nonconforming Fasteners Supplied by A&G; Engineering II, Inc. | -- | -- | |
IN-95-11 | Failure of Condensate Piping Because of Erosion/ Corrosion at Flow-Straightening Device | -- | -- | |
IN-95-10 | Potential for Loss of Automatic Engineered Safety Features Actuation | S2 | -- | |
S1 | -- | |||
-- | -- | |||
IN-95-09 | Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design | -- | -- | |
IN-95-08 | Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments | -- | -- | |
IN-95-07 | Radiopharmaceutical Vial Breakage During Preparation | -- | -- | |
IN-95-06 | Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment | -- | -- | |
IN-95-05 | Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics | -- | -- | |
IN-95-04 | Excessive Cooldown and Depressurization of the Reactor Coolant System Following a Loss of Offsite Power | S1 | -- | |
-- | -- | |||
IN-95-03 | Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition | S2 | -- | |
S1 | -- | |||
-- | -- | |||
IN-95-02 | Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers | -- | -- | |
IN-95-01 | DOT Safety Advisory: High Pressure Aluminum | -- | -- |
Page Last Reviewed/Updated Thursday, November 06, 2025
Page Last Reviewed/Updated Thursday, November 06, 2025