Spotlight
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 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 | -- |
Page Last Reviewed/Updated Monday, March 03, 2025
Page Last Reviewed/Updated Monday, March 03, 2025