| File Name |
Date |
Description |
| in97015s1 |
04/23/1999 |
Reporting of Errors and Changes
in Large-Break/ Small-Break Loss-of- Coolant Evaluation Models of Fuel Vendors
and Compliance with 10 CFR 50.46(a)(3) |
| in97091s1 |
08/10/1998 |
Recent Failures of Control
Cables Used on Amersham Model 660 Posilock Radiography Systems |
| in97063s1 |
05/07/1998 |
Status of NRC Staff's Review
of BWRVIP-05 |
| in97045s1 |
02/17/1998 |
Environmental Qualification
Deficiency for Cables and Containment Penetration Pigtails |
| in97091 |
12/31/1997 |
Recent Failures of Control Cables Used on
Amersham Model 660 Posilock Radiography Systems |
| in97090 |
12/30/1997 |
Use of Nonconservative Acceptance Criteria
in Safety-Related Pump Surveillance Tests |
| in97089 |
12/29/1997 |
Distribution of Sources and Devices
Without Authorization |
| in97088 |
12/16/1997 |
Experiences During Recent Steam Generator
Inspections |
| in97087 |
12/12/1997 |
Second Retrofit to Industrial Nuclear Company
IR100 Radiography Camera, to Correct Inconsistency in 10 CFR Part 34 Compatibility |
| in97086 |
12/12/1997 |
Additional Controls for Transport
of the Amersham Model No. 660 Series Radiographic Exposure Devices |
| in97085 |
12/11/1997 |
Effects of Crud Buildup and Boron Deposition
on Power Distribution and Shutdown Margin |
| in97084 |
12/11/1997 |
Rupture in Extraction Steam
Piping as a Result of Flow-Accelerated Corrosion |
| in97083 |
12/05/1997 |
Recent Events Involving Reactor Coolant
System Inventory Control During Shutdown |
| in97082 |
11/28/1997 |
Inadvertent Control Room Halon Actuation
Due to a Camera Flash |
| in97081 |
11/24/1997 |
Deficiencies in Failure Modes and Effects
Analyses for Instrumentation and Control Systems |
| in97080 |
11/21/1997 |
Licensee Technical Specifications Interpretations |
| in97079 |
11/20/1997 |
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 |
| in97076 |
10/30/1997 |
Degraded Throttle Valves in Emergency Core
Cooling System Resulting From Cavitation-Induced Erosion During a Loss-of-coolant
Accident |
| in97078 |
10/23/1997 |
Crediting of Operator Actions in Place of
Automatic Actions and Modifications of Operator Actions, Including Response
Times |
| in97077 |
10/10/1997 |
Exemptions From the Requirements of Section
70.24 of Title 10 of The Code of Federal Regulations |
| in97075 |
09/24/1997 |
Enforcement Sanctions Issued as a Result
of Deliberate Violations of NRC Requirements |
| in97074 |
09/24/1997 |
Inadequate Oversight of Contractors During
Sealant Injection Activities |
| in97073 |
09/23/1997 |
Fire Hazard in the Use of a Leak Sealant |
| in97072 |
09/22/1997 |
Potential for Failure of the Omega Series
Sprinkler Heads |
| in97071 |
09/22/1997 |
Inappropriate Use of 10 CFR 50.59 Regarding
Reduced Seismic Criteria for Temporary Conditions |
| in97070 |
09/19/1997 |
Potential Problems with Fire Barrier Penetration
Seals |
| in97069 |
09/19/1997 |
Reactor Trip Breakers and Surveillance Testing
of Auxiliary Contacts |
| in97068 |
09/03/1997 |
Loss of Control of Diver in a Spent Fuel
Storage Pool |
| in97067 |
08/21/1997 |
Failure to Satisfy the Requirements for Significant Manipulation of the
Controls for Power Reactor Operator Licensing |
| in97066 |
08/20/1997 |
Failure to Provide Special Lenses For Operators
Using Respirator or Self-Contained Breathing Apparatus During Emergency
Operations |
| in97065 |
08/15/1997 |
Failures of High-Dose-Rate Remote Afterloading
(HDR) Device Source Guide Tubes, Catheters, and Applicators |
| in97064 |
08/13/1997 |
Potential Problems Associated With Loss of Electrical Power in Certain
Teletherapy Units |
| in97063 |
08/07/1997 |
Status of NRC Staff's Review of BWRVIP-05 |
| in97062 |
08/06/1997 |
Unrecognized Reactivity Addition During Plant Shutdown |
| in97061 |
08/06/1997 |
U.S. Department of Health and Human Services Letter, to Medical Device
Manufacturers, on the Year 2000 Problem |
| in97060 |
08/01/1997 |
Incorrect Unreviewed Safety Question Determination Related to Emergency
Core Cooling System Swapover From the Injection Mode to The Recirculation
Mode |
| in97059 |
08/01/1997 |
Fire Endurance Test Results of Versawrap Fire Barriers |
| in97058 |
07/31/1997 |
Mechanical Integrity of In-Situ Leach Injection Wells And Piping |
| in97057 |
07/30/1997 |
Leak Testing F Packaging Used in The Transport of Radioactive Material |
| in97056 |
07/28/1997 |
Possession Limits for Special Nuclear Material at the Environcare of Utah Low-Level Radioactive Material |
| in97055 |
07/23/1997 |
Calculation of Surface Activity for Contaminated Equipment and Material |
| in97054 |
07/18/1997 |
NRC Licensed Operators at Six Non-power Reactor Facilities Allow Their Operator License to Expire |
| in97053 |
07/18/1997 |
Circuit Breakers Left Racked Out in Nonseismic- Ally Qualified Positions |
| in97052 |
07/17/1997 |
Inadvertent Loss of Capability for Emergency Core Cooling System Motors |
| in97051 |
07/11/1997 |
Problems Experienced Loading and Unloading Spent Nuclear Fuel Storage and Transportation Casks |
| in97050 |
07/10/1997 |
Contaminated Lead Products |
| in97049 |
07/10/1997 |
B&W; Once-through Steam Generator Tube Inspection Findings |
| in97048 |
07/09/1997 |
Inadequate or Inappropriate Interim Fire Protect- Ion Compensatory Measures |
| in97046 |
07/09/1997 |
Unisolable Crack in High-Pressure Injection Piping |
| in97045 |
07/02/1997 |
Environmental Qualification Deficiency For Cables and Containment Penetration Pigtails |
| in97044 |
07/01/1997 |
Failures of Gamma Metrics Wide-range Linear Neutron Flux Channels |
| in97043 |
07/01/1997 |
License Condition Compliance |
| in97047 |
06/27/1997 |
Inadequate Puncture Tests For Type B Packages Under 10 CFR 71.73(c)(3) |
| in97042 |
06/27/1997 |
Management Weaknesses Resulting in Failure to Comply With Shipping Requirements for Special Nuclear Material |
| in97041 |
06/27/1997 |
Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers |
| in97040 |
06/26/1997 |
Potential Nitrogen Accumulation Resulting From Backleakage From Safety Injection Tanks |
| in97039 |
06/26/1997 |
Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations |
| in97038 |
06/24/1997 |
Level-Sensing System Initiates Common-Mode Failure of High-Pressure-Injection
Pumps |
| in97037 |
06/20/1997 |
Main Transformer Fault With Ensuing Oil Spill Into Turbine Building |
| in97036 |
06/20/1997 |
Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials
And External Exposure Due to Inadequate Control of Work |
| in97035 |
06/18/1997 |
Retrofit to Industrial Nuclear Company (Inc) Ir100 Radiography Camera
to Correct Inconsistency in 10 Cfr 50 Part 34 Compatibility |
| in97034 |
06/12/1997 |
Deficiensees in Licensee Submittals Regarding Termonology For Radiological
Emergency Action Levels in Accordance With The New Part 20 |
| in97033 |
06/11/1997 |
Unanticipated Effect of Ventilation System on Tank Level Indications And
Engineering Safety Features Actuation System Setpoint |
| in97032 |
06/10/1997 |
Defective Worm Shaft Clutch Gears in Limitorque Motor-operated Valve Actuators |
| in97031 |
06/03/1997 |
Failures of Reactor Coolant Pump Thermal Barriers and Check Valves at
Foreign Plants |
| in97030 |
06/03/1997 |
Control of Licensed Material During Reorg- Anizations, Employee-Management
Disagreements, And Financial Crises |
| in97029 |
05/30/1997 |
Containment Inspection Rule |
| in97028 |
05/30/1997 |
Elimination of Instrument Response Time Testing Under The Requirements
of 10 CFR 50.59 |
| in97027 |
05/16/1997 |
Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction
Head |
| in97026 |
05/19/1997 |
Degradation in Small-Radius U-bend Regions of Steam Generator Tubes |
| in97025 |
05/09/1997 |
Dynamic Range Uncertainties in Reactor Vessel Level Instrumentation |
| in97024 |
05/08/1997 |
Failure of Packing Nuts on One-inch Uranium Hexafluoride Cylinder Valves |
| in97023 |
05/07/1997 |
Evaluation and Reporting of Fires And Unplanned Chemical Reactor Events
at Fuel Cycle Facilities |
| in97022 |
04/24/1997 |
Failure of Welded-Steel Moment-Resisting Frames During The Nothridge Earthquake |
| in97021 |
04/18/1997 |
Availability of Alternate AC Power Source Designed for Station Blackout
Event |
| in97020 |
04/17/1997 |
Identification of Certain Uranium Hexafluoride Cylinders that Do Not Comply
With ANSI N14.1 Fabrication Standards |
| in97019 |
04/18/1997 |
Safety Injection System Weld Flaw at Sequoyah Nuclear Power Plant, Unit
2 |
| in97018 |
04/14/1997 |
Problems Identified During Maintenance Rule Base- Line Inspections |
| in97017 |
04/04/1997 |
Cracking of Vertical Welds in The Core Shroud and Degraded Repair |
| in97016 |
04/04/1997 |
Preconditioning of Plant Structures, Systems, and Components Before ASME
Code Inservice Testing or Technical Specification Surveillance Testing |
| in97015 |
04/04/1997 |
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) |
| in97014 |
03/28/1997 |
Assessment of Spent Fuel Pool Cooling |
| in97013 |
03/24/1997 |
Deficient Conditions Associated With Protective Coatings at Nuclear Power
Plants |
| in97012 |
03/24/1997 |
Potential Armature Binding in General Electric Type HGA Relays |
| in97011 |
03/21/1997 |
Cement Erosion From Containment Subfoundations at Nuclear Power Plants |
| in97010 |
03/13/1997 |
Liner Plate Corrosion in Concrete Containments |
| in97009 |
03/12/1997 |
Inadequate Main Steam Safety Valve (MSSV) Set- Point and Performance Issues
Associated With Long MSSV Inlet Piping |
| in97008 |
03/12/1997 |
Potential Failures of General Electric Magne- Blast Circuit Breaker Subcomponents |
| in97007 |
03/06/1997 |
Problems Identified During Generic Letter 89-10 Closeout Inspections |
| in97006 |
03/04/1997 |
Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling
the Secondary Side of Once-Through Steam Generators |
| in97005 |
02/27/1997 |
Offsite Notification Capabilities |
| in97004 |
02/24/1997 |
Implementation of a New Constraint on Radioactive Air Effluents |
| in97003 |
02/20/1997 |
Defacing Labels to Comply With 10 CFR 20.1904(b) |
| in97002 |
02/06/1997 |
Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors |
| in97001 |
01/08/1997 |
Improper Electrical Grounding Results in Simultaneous Fires in The Control
Room And The Safe- Shutdown Equipment Room |
