| Document Number |
Title |
Revision |
Publish Date |
Reviewed Date |
| IN-95-58 |
10 CFR 34.20; Final Effective Date |
-- |
12/18/1995 |
-- |
| IN-95-57 |
Risk Impact Study Regarding Maintenance During Low-Power Operation and Shutdown |
-- |
12/13/1995 |
-- |
| IN-95-56 |
Shielding Deficiency in Spent Fuel Transfer Canal at a Boiling-water Reactor |
-- |
12/11/1995 |
-- |
| IN-95-55 |
Handling Uncontained Yellowcake Outside of a Facility Processing Circuit |
-- |
12/06/1995 |
-- |
| IN-95-54 |
Decay Heat Management Practices During Refueling Outages |
-- |
12/01/1995 |
-- |
| IN-95-53 |
Failures of Main Steam Isolation Valves as a Result of Sticking Solenoid Pilot Valves |
-- |
12/01/1995 |
-- |
| IN-95-52 |
Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed From 3M Company Interim Fire Barrier Materials |
S1 |
03/17/1998 |
-- |
| -- |
11/14/1995 |
-- |
| IN-95-51 |
Recent Incidents Involving Potential Loss of Control of Licensed Material |
-- |
10/27/1995 |
-- |
| IN-95-50 |
Safety Defect in Gammamed 12I Bronchial Catheter Clamping Adapters |
-- |
10/30/1995 |
-- |
| IN-95-49 |
Seismic Adequacy of Thermo-Lag Panels |
S1 |
12/10/1997 |
-- |
| -- |
10/27/1995 |
-- |
| IN-95-48 |
Results of Shift Staffing Study |
-- |
10/10/1995 |
-- |
| IN-95-47 |
Unexpected Opening of a Safety/Relief Valve and Complications Involving Suppression Pool Cooling Strainer Blockage |
1 |
11/30/1995 |
-- |
| -- |
10/04/1995 |
-- |
| IN-95-46 |
Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor |
-- |
10/06/1995 |
-- |
| IN-95-45 |
American Power Service Falsification of American Society of Nondestructive Testing (ASNT) Certificates |
-- |
10/04/1995 |
-- |
| IN-95-44 |
Ensuring Compatible Use of Drive Cables Incorporating Use of Industrial Nuclear Company Ball-Type Male Connectors |
-- |
09/26/1995 |
-- |
| IN-95-43 |
Failure of the Bolt-Locking Device on Reactor Coolant Pump Turning Vane |
-- |
09/28/1995 |
-- |
| IN-95-42 |
Commission Decision on the Resolution of Generic Issue 23, "Reactor Coolant Pump Seal Failure" |
-- |
09/22/1995 |
-- |
| IN-95-41 |
Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators |
-- |
09/22/1995 |
-- |
| IN-95-40 |
Supplemental Information to Generic Letter 95-03, "Circumferential Cracking of Steam Generator Tubes" |
-- |
09/20/1995 A 09/20/1995 B |
-- |
| IN-95-39 |
Brachytherapy Incidents Involving Treatment Planning Errors |
-- |
09/19/1995 |
-- |
| IN-95-38 |
Degradation of Boraflex Neutron Absorber in Spent Fuel Pool Storage Racks |
-- |
09/08/1995 |
-- |
| IN-95-37 |
Inadequate Offsite Power Systems Voltages During Design-Basis Events |
-- |
09/07/1995 |
-- |
| IN-95-36 |
Potential Problems with Post-Fire Emergency Lighting |
S1 |
06/10/1997 |
-- |
| -- |
08/29/1995 |
-- |
| IN-95-35 |
Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation |
-- |
08/28/1995 |
-- |
| IN-95-34 |
Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves |
-- |
08/25/1995 |
-- |
| IN-95-33 |
Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 |
-- |
08/23/1995 |
-- |
| IN-95-32 |
Thermo-Lag 330-1 Flame Spread Test Results |
-- |
08/10/1995 |
-- |
| IN-95-31 |
Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference |
-- |
08/09/1995 |
-- |
| IN-95-30 |
Susceptibility of Low-Pressure Coolant Injection and Core Spray Injection Valves to Pressure Locking |
-- |
08/03/1995 |
-- |
| IN-95-29 |
Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems |
-- |
06/07/1995 |
-- |
| IN-95-28 |
Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites |
-- |
06/05/1995 |
-- |
| IN-95-27 |
NRC Review of Nuclear Energy Institute, "Thermo- Lag Combustibility Evaluation Methodology Plant Screening Guide |
-- |
05/31/1995 |
-- |
| IN-95-26 |
Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit |
-- |
05/31/1995 |
-- |
| IN-95-25 |
Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit |
-- |
05/11/1995 |
-- |
| IN-95-24 |
Summary of Licensed Operator Requalification Inspection Program Findings |
-- |
04/25/1995 |
-- |
| IN-95-23 |
Control Room Staffing Below Minimum Regulatory Requirements |
-- |
04/24/1995 |
-- |
| IN-95-22 |
Hardened or Contaminated Lubricants Cause Metal- Clad Circuit Breaker Failures |
-- |
04/21/1995 |
-- |
| IN-95-21 |
Unexpected Degradation of Lead Storage Batteries |
-- |
04/20/1995 |
-- |
| IN-95-20 |
Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation into the Sensor Cell |
-- |
03/22/1995 |
-- |
| IN-95-19 |
Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism |
-- |
03/22/1995 |
-- |
| IN-95-18 |
Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves |
S1 |
03/31/1995 |
-- |
| -- |
03/15/1995 |
-- |
| IN-95-17 |
Reactor Vessel Top Guide and Core Plate Cracking |
-- |
03/10/1995 |
-- |
| IN-95-16 |
Vibration Caused by Increased Flow in a Boiling Water Reactor |
-- |
03/09/1995 |
-- |
| IN-95-15 |
Inadequate Logic Testing of Safety-Related Circuits |
-- |
03/07/1995 |
-- |
| IN-95-14 |
Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking |
-- |
02/28/1995 |
-- |
| IN-95-13 |
Potential for Data Collection Equipment to Affect Protection System Performance |
S1 |
11/22/1995 |
-- |
| -- |
02/24/1995 |
-- |
| IN-95-12 |
Potentially Nonconforming Fasteners Supplied by A&G; Engineering II, Inc. |
-- |
02/21/1995 |
-- |
| IN-95-11 |
Failure of Condensate Piping Because of Erosion/ Corrosion at Flow-Straightening Device |
-- |
02/24/1995 |
-- |
| IN-95-10 |
Potential for Loss of Automatic Engineered Safety Features Actuation |
S2 |
08/11/1995 |
-- |
| S1 |
02/10/1995 |
-- |
| -- |
02/03/1995 |
-- |
| IN-95-09 |
Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design |
-- |
01/31/1995 |
-- |
| IN-95-08 |
Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments |
-- |
01/30/1995 |
-- |
| IN-95-07 |
Radiopharmaceutical Vial Breakage During Preparation |
-- |
01/27/1995 |
-- |
| IN-95-06 |
Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment |
-- |
01/25/1995 |
-- |
| IN-95-05 |
Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics |
-- |
01/20/1995 |
-- |
| IN-95-04 |
Excessive Cooldown and Depressurization of the Reactor Coolant System Following a Loss of Offsite Power |
S1 |
10/11/1996 |
-- |
| -- |
01/19/1995 |
-- |
| IN-95-03 |
Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition |
S2 |
07/03/2000 |
-- |
| S1 |
03/25/1996 |
-- |
| -- |
01/18/1995 |
-- |
| IN-95-02 |
Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers |
-- |
01/17/1995 |
-- |
| IN-95-01 |
DOT Safety Advisory: High Pressure Aluminum |
-- |
01/04/1995 |
-- |