| Document Number |
Title |
Revision |
Publish Date |
Reviewed Date |
| IN-97-91 |
Recent Failures of Control Cables Used on Amersham Model 660 Posilock Radiography Systems |
S1 |
08/10/1998 |
-- |
| -- |
12/31/1997 |
-- |
| IN-97-90 |
Use of Nonconservative Acceptance Criteria in Safety-Related Pump Surveillance Tests |
-- |
12/30/1997 |
-- |
| IN-97-89 |
Distribution of Sources and Devices Without Authorization |
-- |
12/29/1997 |
-- |
| IN-97-88 |
Experiences During Recent Steam Generator Inspections |
-- |
12/16/1997 A 12/16/1997 B |
-- |
| IN-97-87 |
Second Retrofit to Industrial Nuclear Company IR100 Radiography Camera, to Correct Inconsistency in 10 CFR Part 34 Compatibility |
-- |
12/12/1997 |
-- |
| IN-97-86 |
Additional Controls for Transport of the Amersham Model No. 660 Series Radiographic Exposure Devices |
-- |
12/12/1997 |
-- |
| IN-97-85 |
Effects of Crud Buildup and Boron Deposition on Power Distribution and Shutdown Margin |
-- |
12/11/1997 |
-- |
| IN-97-84 |
Rupture in Extraction Steam Piping as a Result of Flow-Accelerated Corrosion |
-- |
12/11/1997 |
-- |
| IN-97-83 |
Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
-- |
12/05/1997 |
-- |
| IN-97-82 |
Inadvertent Control Room Halon Actuation Due to a Camera Flash |
-- |
11/28/1997 |
-- |
| IN-97-81 |
Deficiencies in Failure Modes and Effects Analyses for Instrumentation and Control Systems |
-- |
11/24/1997 |
-- |
| IN-97-80 |
Licensee Technical Specifications Interpretations |
-- |
11/21/1997 |
-- |
| IN-97-79 |
Potential Inconsistency in the Assessment of the Radiological Consequences of a Main Steam Line Break Associated with the Implementation of Steam Generator Tube Voltage-based Repair Criteria |
-- |
11/20/1997 |
-- |
| IN-97-78 |
Crediting of Operator Actions in Place of Automatic Actions and Modifications of Operator Actions, Including Response Times |
-- |
10/23/1997 |
-- |
| IN-97-77 |
Exemptions From the Requirements of Section 70.24 of Title 10 of The Code of Federal Regulations |
-- |
10/10/1997 A 10/10/1997 B |
-- |
| IN-97-76 |
Degraded Throttle Valves in Emergency Core Cooling System Resulting From Cavitation-Induced Erosion During a Loss-of-coolant Accident |
-- |
10/30/1997 |
-- |
| IN-97-75 |
Enforcement Sanctions Issued as a Result of Deliberate Violations of NRC Requirements |
-- |
09/24/1997 |
-- |
| IN-97-74 |
Inadequate Oversight of Contractors During Sealant Injection Activities |
-- |
09/24/1997 |
-- |
| IN-97-73 |
Fire Hazard in the Use of a Leak Sealant |
-- |
09/23/1997 |
-- |
| IN-97-72 |
Potential for Failure of the Omega Series Sprinkler Heads |
-- |
09/22/1997 |
-- |
| IN-97-71 |
Inappropriate Use of 10 CFR 50.59 Regarding Reduced Seismic Criteria for Temporary Conditions |
-- |
09/22/1997 |
-- |
| IN-97-70 |
Potential Problems with Fire Barrier Penetration Seals |
-- |
09/19/1997 |
-- |
| IN-97-69 |
Reactor Trip Breakers and Surveillance Testing of Auxiliary Contacts |
-- |
09/19/1997 |
-- |
| IN-97-68 |
Loss of Control of Diver in a Spent Fuel Storage Pool |
-- |
09/03/1997 |
-- |
| IN-97-67 |
Failure to Satisfy the Requirements for Significant Manipulation of the Controls for Power Reactor Operator Licensing |
-- |
08/21/1997 A 08/21/1997 B |
-- |
| IN-97-66 |
Failure to Provide Special Lenses for Operators Using Respirator or Self-Contained Breathing Apparatus During Emergency Operations |
-- |
08/20/1997 |
-- |
| IN-97-65 |
Failures of High-Dose-Rate Remote Afterloading (HDR) Device Source Guide Tubes, Catheters, and Applicators |
-- |
08/15/1997 |
-- |
| IN-97-64 |
Potential Problems Associated with Loss of Electrical Power in Certain Teletherapy Units |
-- |
08/13/1997 |
-- |
| IN-97-63 |
Status of NRC Staff's Review of BWRVIP-05 |
S1 |
05/07/1998 |
-- |
| -- |
08/07/1997 |
-- |
| IN-97-62 |
Unrecognized Reactivity Addition During Plant Shutdown |
-- |
08/06/1997 |
-- |
| IN-97-61 |
U.S. Department of Health and Human Services Letter, to Medical Device Manufacturers, on the Year 2000 Problem |
-- |
08/06/1997 |
-- |
| IN-97-60 |
Incorrect Unreviewed Safety Question Determination Related to Emergency Core Cooling System Swapover From the Injection Mode to The Recirculation Mode |
-- |
08/01/1997 |
-- |
| IN-97-59 |
Fire Endurance Test Results of Versawrap Fire Barriers |
-- |
08/01/1997 |
-- |
| IN-97-58 |
Mechanical Integrity of In-Situ Leach Injection Wells and Piping |
-- |
07/31/1997 |
-- |
| IN-97-57 |
Leak Testing F Packaging Used in The Transport of Radioactive Material |
-- |
07/30/1997 |
-- |
| IN-97-56 |
Possession Limits for Special Nuclear Material at the Environcare of Utah Low-Level Radioactive Material |
-- |
07/28/1997 |
-- |
| IN-97-55 |
Calculation of Surface Activity for Contaminated Equipment and Material |
-- |
07/23/1997 |
-- |
| IN-97-54 |
NRC Licensed Operators at Six Non-power Reactor Facilities Allow Their Operator License to Expire |
-- |
07/18/1997 |
-- |
| IN-97-53 |
Circuit Breakers Left Racked Out in Nonseismic- Ally Qualified Positions |
-- |
07/18/1997 |
-- |
| IN-97-52 |
Inadvertent Loss of Capability for Emergency Core Cooling System Motors |
-- |
07/17/1997 |
-- |
| IN-97-51 |
Problems Experienced Loading and Unloading Spent Nuclear Fuel Storage and Transportation Casks |
-- |
07/11/1997 |
-- |
| IN-97-50 |
Contaminated Lead Products |
-- |
07/10/1997 |
-- |
| IN-97-49 |
B&W; Once-through Steam Generator Tube Inspection Findings |
-- |
07/10/1997 |
-- |
| IN-97-48 |
Inadequate or Inappropriate Interim Fire Protection Compensatory Measures |
-- |
07/09/1997 |
-- |
| IN-97-47 |
Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) |
-- |
06/27/1997 |
-- |
| IN-97-46 |
Unisolable Crack in High-Pressure Injection Piping |
-- |
07/09/1997 |
-- |
| IN-97-45 |
Environmental Qualification Deficiency for Cables and Containment Penetration Pigtails |
S1 |
02/17/1998 |
-- |
| -- |
07/02/1997 |
-- |
| IN-97-44 |
Failures of Gamma Metrics Wide-range Linear Neutron Flux Channels |
-- |
07/01/1997 |
-- |
| IN-97-43 |
License Condition Compliance |
-- |
07/01/1997 |
-- |
| IN-97-42 |
Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material |
-- |
06/27/1997 |
-- |
| IN-97-41 |
Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers |
-- |
06/27/1997 |
-- |
| IN-97-40 |
Potential Nitrogen Accumulation Resulting From Backleakage From Safety Injection Tanks |
-- |
06/26/1997 |
-- |
| IN-97-39 |
Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations |
-- |
06/26/1997 |
-- |
| IN-97-38 |
Level-Sensing System Initiates Common-Mode Failure of High-Pressure-Injection Pumps |
-- |
06/24/1997 |
-- |
| IN-97-37 |
Main Transformer Fault with Ensuing Oil Spill Into Turbine Building |
-- |
06/20/1997 |
-- |
| IN-97-36 |
Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work |
-- |
06/20/1997 |
-- |
| IN-97-35 |
Retrofit to Industrial Nuclear Company (Inc.) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR 50 Part 34 Compatibility |
-- |
06/18/1997 |
-- |
| IN-97-34 |
Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with The New Part 20 |
-- |
06/12/1997 |
-- |
| IN-97-33 |
Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint |
-- |
06/11/1997 |
-- |
| IN-97-32 |
Defective Worm Shaft Clutch Gears in Limitorque Motor-operated Valve Actuators |
-- |
06/10/1997 |
-- |
| IN-97-31 |
Failures of Reactor Coolant Pump Thermal Barriers and Check Valves at Foreign Plants |
-- |
06/03/1997 |
-- |
| IN-97-30 |
Control of Licensed Material During Reorg- Anizations, Employee-Management Disagreements, and Financial Crises |
-- |
06/03/1997 |
-- |
| IN-97-29 |
Containment Inspection Rule |
-- |
05/30/1997 |
-- |
| IN-97-28 |
Elimination of Instrument Response Time Testing Under The Requirements of 10 CFR 50.59 |
-- |
05/30/1997 |
-- |
| IN-97-27 |
Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head |
-- |
05/16/1997 |
-- |
| IN-97-26 |
Degradation in Small-Radius U-bend Regions of Steam Generator Tubes |
-- |
05/19/1997 |
-- |
| IN-97-25 |
Dynamic Range Uncertainties in Reactor Vessel Level Instrumentation |
-- |
05/09/1997 |
-- |
| IN-97-24 |
Failure of Packing Nuts on One-inch Uranium Hexafluoride Cylinder Valves |
-- |
05/08/1997 |
-- |
| IN-97-23 |
Evaluation and Reporting of Fires and Unplanned Chemical Reactor Events at Fuel Cycle Facilities |
-- |
05/07/1997 |
-- |
| IN-97-22 |
Failure of Welded-Steel Moment-Resisting Frames During The Northridge Earthquake |
-- |
04/24/1997 |
-- |
| IN-97-21 |
Availability of Alternate AC Power Source Designed for Station Blackout Event |
-- |
04/18/1997 |
-- |
| IN-97-20 |
Identification of Certain Uranium Hexafluoride Cylinders that Do Not Comply with ANSI N14.1 Fabrication Standards |
-- |
04/17/1997 |
-- |
| IN-97-19 |
Safety Injection System Weld Flaw at Sequoyah Nuclear Power Plant, Unit 2 |
-- |
04/18/1997 |
-- |
| IN-97-18 |
Problems Identified During Maintenance Rule Base- Line Inspections |
-- |
04/14/1997 |
-- |
| IN-97-17 |
Cracking of Vertical Welds in The Core Shroud and Degraded Repair |
-- |
04/04/1997 |
-- |
| IN-97-16 |
Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing |
-- |
04/04/1997 |
-- |
| IN-97-15 |
Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50.46a(3) |
S1 |
04/23/1999 |
-- |
| -- |
04/04/1997 |
-- |
| IN-97-14 |
Assessment of Spent Fuel Pool Cooling |
-- |
03/28/1997 |
-- |
| IN-97-13 |
Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants |
-- |
03/24/1997 |
-- |
| IN-97-12 |
Potential Armature Binding in General Electric Type HGA Relays |
-- |
03/24/1997 |
-- |
| IN-97-11 |
Cement Erosion From Containment Subfoundations at Nuclear Power Plants |
-- |
03/21/1997 |
-- |
| IN-97-10 |
Liner Plate Corrosion in Concrete Containments |
-- |
03/13/1997 |
-- |
| IN-97-09 |
Inadequate Main Steam Safety Valve (MSSV) Set- Point and Performance Issues Associated with Long MSSV Inlet Piping |
-- |
03/12/1997 |
-- |
| IN-97-08 |
Potential Failures of General Electric Magne- Blast Circuit Breaker Subcomponents |
-- |
03/12/1997 |
-- |
| IN-97-07 |
Problems Identified During Generic Letter 89-10 Closeout Inspections |
-- |
03/06/1997 |
-- |
| IN-97-06 |
Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Once-Through Steam Generators |
-- |
03/04/1997 |
-- |
| IN-97-05 |
Offsite Notification Capabilities |
-- |
02/27/1997 |
-- |
| IN-97-04 |
Implementation of a New Constraint on Radioactive Air Effluents |
-- |
02/24/1997 |
-- |
| IN-97-03 |
Defacing Labels to Comply with 10 CFR 20.1904(b) |
-- |
02/20/1997 |
-- |
| IN-97-02 |
Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors |
-- |
02/06/1997 |
-- |
| IN-97-01 |
Improper Electrical Grounding Results in Simultaneous Fires in The Control Room and The Safe- Shutdown Equipment Room |
-- |
01/08/1997 |
-- |