Information Notices - 1997
| 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 |
Page Last Reviewed/Updated Thursday, March 29, 2012
