United States Nuclear Regulatory Commission - Protecting People and the Environment

Information Notices - 1997

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 --
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 --
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 --
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 --
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