ANNEX 3
Information Notices
Source: http://www.nrc.gov/reading-rm/doc-collections/gen-comm/info-notices
IN-14-09
Spent Fuel Storage or Transportation System Misloading
IN-14-08
Need For Continuous Monitoring Of Active Systems In Loaded Spent
Fuel Storage Canisters (Including Vacuum Drying Process)
IN-14-07
Degradation of Leak Chase Channel Systems for Floor Welds of
Metal Containment Shell and Concrete Containment Metallic Liner
IN-14-06
Damage Of Industrial Radiographic Equipment Due To Falling
Equipment And Improper Mounting
IN-14-05
Verifying Appropriate Dosimetry Evaluation
IN-14-04
Potential for Teflon® Material Degradation in Containment
Penetrations, Mechanical Seals and Other Components
IN-14-03
Turbine-Driven Auxiliary Feedwater Pump Overspeed Trip
Mechanism Issues
IN-14-02
Failure To Properly Pressure Test Reactor Vessel Flange Leak-Off
Lines
IN-14-01
Fuel Safety Limit Calculation Inputs Were Inconsistent With NRCApproved Correlation Limit Values
IN-13-22
Recent Licensing Submittals Containing Personally Identifiable
Information
IN-13-21
Welding Problems During Fabrication of Reactor Plant Components
IN-13-20
Steam Generator Channel Head and Tubesheet Degradation
IN-13-19
Quasi-Laminar Indications in Reactor Pressure Vessel Forgings
IN-13-18
Refueling Water Storage Tank Degradation
IN-13-17
Significant Plant Transient Induced by Safety-Related Direct Current
Bus Maintenance at Plant
IN-13-16
Importance of Verification of Treatment Parameters for High DoseRate Remote Afterloader Administrations
IN-13-15
Willful Misconduct/Record Falsification and Nuclear Safety Culture
IN-13-14
Potential Design Deficiency in Motor-Operated Valve Control
Circuitry
IN-13-13
Deficiencies With Effluent Radiation Monitoring System
Instrumentation
IN-13-12
Improperly Sloped Instrument Sensing Lines
IN-13-11
Crack-Like Indications At Dents/Dings And In The Freespan Region
Of Thermally Treated Alloy 600 Steam Generator Tubes
IN-13-10
Programs For Monitoring Boiling-Water Reactor Steam Dryer
Integrity
IN-13-09
Compressed Flammable Gas Cylinders and Associated Hazards
IN-13-08
Pending Expiration of the NRC Type B Transportation Package
Certificate for SentinelTM Model 660 Series Radiographic Projectors
on June 30, 2013
IN-13-07
Premature Degradation of Spent Fuel Storage Cask Structures and
Components from Environmental Moisture
IN-13-06
Corrosion In Fire Protection Piping Due To Air And Water Interaction
IN-13-05
Battery Expected Life and Its Potential Impact on Surveillance
Requirements
IN-13-04
Shield Building Concrete Subsurface Laminar Cracking Caused by
Moisture Intrusion and Freezing
IN-13-03
Recent Issue with the Definition of Core Quadrant
IN-13-02
Issues Potentially Affecting Nuclear Facility Fire Safety
IN-13-01
Emergency Action Level Thresholds Outside the Range of Radiation
Monitors
IN-12-25
Performance Issues with Seismic Instrumentation and Associated
Systems for Operating Reactors
IN-12-24
IN-12-23
Recent Radiography Events Resulting In Exposures Exceeding
Regulatory Limits
IN-12-22
Counterfeit, Fraudulent, Suspect Item (CFSI) Training Offerings
IN-12-21
Reactor Vessel Closure Head Studs Remain Detensioned During
Plant Startup
IN-12-20
Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless
Steel and Maintenance of Dry Cask Storage System Canisters
IN-12-19
License Renewal Post-Approval Site Inspection Issues
IN-12-18
Failure to Properly Augment Emergency Response Organizations
IN-12-17
Inappropriate Use of Certified Material Test Report Yield Stress and
Age-Hardened Concrete Compressive Strength in Design
Calculations
IN-12-16
Preconditioning of Pressure Switches Before Surveillance Testing
IN-12-15
Use of Seal Cap Enclosures To Mitigate Leakage From Joints That
Use A-286 Bolts
IN-12-14
Motor-Operated Valve Inoperable Due To Stem-Disc Separation
IN-12-13
Boraflex Degradation Surveillance Programs and Corrective Actions
in the Spent Fuel Pool
IN-12-12
HVAC Design Control Issues Challenge Safety System Function
IN-12-11
Age Related Capacitor Degradation
IN-12-10
Recent Issues Associated With Submittal of NRC Form 396,
Certification on Medical Examination By Facility Licensee, For
Applicants and Licensed Operators at Non-Power Reactors
IN-12-09
Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength
IN-12-08
High Dose-Rate Remote Afterloader (HDR) Physical Presence
Requirements
IN-12-07
Tube-to-Tube Contact Resulting in Wear In Once-Through Steam
Generators
IN-12-06
Ineffective Use of Vendor Technical Recommendations
IN-12-05
Abnormal Releases of Radioactive Water Potentially Resulting in
Groundwater Contamination
IN-12-04
Impacts On Normal Plant Operations Due To Leaks Or Spills Of
Chemicals
IN-12-03
Design Vulnerability in Electric Power System
IN-12-02
Potentially Nonconservative Screening Value for Dam Failure
Frequency in Probabilistic Risk Assessments
IN-12-01
Seismic Considerations – Principally Issues Involving Tanks
IN-11-22
Instrumentation and Control Module Hardware, Configuration, and
Procedure Issues
IN-11-21
Realistic Emergency Core Cooling System Evaluation Model Effects
Resulting From Nuclear Fuel Thermal Conductivity Degradation
IN-11-20
Concrete Degradation by Alkali-Silica Reaction
IN-11-19
Licensee Event Reports Containing Information Pertaining to Defects
to Basic Components
IN-11-18
IN-11-17
Calculation Methodologies For Operability Determinations Of Gas
Voids in Nuclear Power Plant Piping
IN-11-16
IN-11-15
Steel Containment Degradation and Associated License Renewal
Aging Management Issues
IN-11-14
Component Cooling Water System Gas Accumulation and Other
Performance Issues
IN-11-13
Control Rod Blade Cracking Resulting in Reduced Design Lifetime
IN-11-12
Reactor Trips Resulting From Water Intrusion Into Electrical
Equipment
IN-11-11
Reporting Requirement For Heat And Smoke Detector Failures In 10
CFR Part 36 Irradiators
IN-11-10
Thermal Issues Identified During Loading of Spent Fuel Storage
Casks
IN-11-09
Fixed Gauge Shutter Failures Due To Operating In Harsh Working
Environments
IN-11-08
Tohoku-Taiheiyou-Oki Earthquake Effects On Japanese Nuclear
Power Plants – For Fuel Cycle Facilities
IN-11-07
Specific License Required When Exporting To Embargoed
Destinations Listed In 10 CFR 110.28
IN-11-06
Erroneous Criticality Alarm Monitoring Signal Caused By Incorrect
Data Acquisition Module Configuration
IN-11-05
Tohoku-Taiheiyou-Oki Earthquake Effects On Japanese Nuclear
Power Plants
IN-11-04
Contaminants and Stagnant Conditions Affecting Stress Corrosion
Cracking in Stainless Steel Piping Pressurized Water Reactors
IN-11-03
Nonconservative Criticality Safety Analyses for Fuel Storage
IN-11-02
Operator Performance Issues Involving Reactivity Management at
Nuclear Power Plants
IN-11-01
Commercial-Grade Dedication Issues Identified During NRC
Inspections
IN-10-27
Ventilation System Preventive Maintenance And Design Issues
IN-10-26
Submerged Electrical Cables
IN-10-25
Inadequate Electrical Connections
IN-10-24
Notice of Possible Source Leakage During Non-Routine
Maintenance on a Gammacell 40 Irradiator
IN-10-23
Malfunctions of Emergency Diesel Generator Speed Switch Circuits
IN-10-22
Fuel Assemblies Damaged During Refueling Operations Due To
Misalignment
IN-10-21
Crack-Like Indication in the U-Bend Region of a Thermally Treated
Alloy 600 Steam Generator Tube
IN-10-20
Turbine-Driven Auxiliary Feedwater Pump Repetitive Failures
IN-10-19
Updated Probabilistic Seismic Hazard Estimates in Central and
Eastern United States
IN-10-18
Implications of Updated Probabilistic Seismic Hazard Estimates in
Central and Eastern United States on Existing Plants
IN-10-17
Common Cause Failure of Boiling-Water Reactor Recirculation
Pumps with Variable Speed Drives
IN-10-16
Failure To Disable Unsafe Geometry Bandsaw Reservior Results In
Criticality Safety-Related Alert
IN-10-15
Fuel Cycle Facility Configuration Management Errors
IN-10-14
Containment Concrete Surface Condition Examination Frequency
And Acceptance Criteria
IN-10-13
Failure to Ensure that the Post-Fire Shutdown Procedures Can Be
Performed
IN-10-12
Containment Liner Corrosion
IN-10-11
Potential for Steam Voiding Causing Residual Heat Removal System
Inoperability
IN-10-10
Implementation of a Digital Control System Under 10 CFR 50.59
IN-10-09
Importance of Understanding Circuit Breaker Control Panel
Indications
IN-10-08
Welding and Nondestructive Examination Issues
IN-10-07
Welding Defects In Replacement Steam Generators
IN-10-06
Inadvertent Control Rod Withdrawal Event While Shutdown
IN-10-05
Management Of Steam Generator Loose Parts And Automated Eddy
Current Data Analysis
IN-10-04
Diesel Generator Voltage Regulation System Component Due to
Latent Manufacturing Defect
IN-10-03
Failures Of Motor-Operated Valves Due To Degraded Stem
Lubricant
IN-10-02
Construction-Related Experience With Cables, Connectors, And
Junction Boxes
IN-10-01
Pipe Support Anchors Installed Improperly
IN-09-31
Nonpower Reactor Licensee Notifications to the NRC During an
Incident
IN-09-30
Findings From The NRC Initiative To Assess Materials Licensees’
Compliance With The NRC Decommissioning Requirements
IN-09-29
Potential Failure Of Fire Water Supply Pumps To Automatically Start
Due To A Fire
IN-09-28
Summary of Fitness For Duty Program Performance Reports For
Calendar Year 2008
IN-09-27
Revised International Nuclear And Radiological Event Scale User’s
Manual
IN-09-26
Degradation Of Neutron-Absorbing Materials In The Spent Fuel Pool
IN-09-25
Small Arms Firing Range Safety Issues
IN-09-24
Sources of Information Related to Potential Cyber Security
Vulnerabilities
IN-09-23-s1 Nuclear Fuel Thermal Conductivity Degradation
IN-09-23
Nuclear Fuel Thermal Conductivity Degradation
IN-09-22
Recent Human Performance Issues at Nuclear Power Plants
IN-09-21
Incomplete Medical Testing For Licensed Operators
IN-09-20
Degradation of Wire Rope Used in Fuel Handling Applications
IN-09-19
Hostile Action-Based Emergency Preparedness Drills
IN-09-18
Performance Of Required Shutter Checks And Reporting Of Gauge
Shutter Failures
IN-09-17
Reportable Medical Events Involving Treatment Delivery Errors
Caused By Confusion Of Units For The Specification Of
Brachytherapy Sources
IN-09-16
Spurious Relay Actuations Result In Loss Of Power To Safeguards
Buses
IN-09-15
Varian Medical Systems Varisource High Dose-Rate Remote
Afterloader Events: Source Retraction Problems
IN-09-14
Painting Activities and Cleaning Agents Render Emergency Diesel
Generators and other Plant Equipment Inoperable
IN-09-12
Exempt Distribution Licensing Requirements For Irradiated
Gemstones
IN-09-11
Configuration Control Errors
IN-09-10
Transformer Failures - Recent Operating Experience
IN-09-09
Improper Flow Controller Settings Renders Injection Systems
Inoperable And Surveillance Did Not Identify
IN-09-08
NRC Rapid Change Notification of Licensees Following A Physical
Attack Against A Facility
IN-09-07
Withholding of Propriety Information from Public Disclosure
IN-09-06
Construction-Related Experience With Flood Protection Features
IN-09-05
Contamination Events Resulting From Damage To Sealed
Radioactive Sources During Gauge Dismantlement And Non-Routine
Maintenance Operations
IN-09-04
Age-Related Constant Support Degradation
IN-09-03
Solid State Production System Card Failure Results in Spurious
Safety Injection and Reactor Trip
IN-09-02
Biodiesel In Fuel Oil Could Adversely Impact Diesel Engine
Performance
IN-09-01
National Response Framework
IN-08-22
Molybdenum-90 Breakthrough in Molybdenum-99/Technetium-99M
Generators
IN-08-21
Impact Of Non-Safety Electrical Support System Vulnerabilities On
Safety Systems
IN-08-20
Failures of Motor Operated Valve Actuator Motors with Magnesium
Alloy Rotors
IN-08-19
Tamper-Indicating Device Issues
IN-08-18
Loss of a Safety-Related Motor Control Center Caused by a Bus
Fault
IN-08-17
Construction Experience With Concrete Placement
IN-08-16
Summary of Fitness-For-Duty Program Performance Reports for
Calendar Year 2007
IN-08-15
Emergency Response Data System Test Schedule Revised
IN-08-14
Criticality Safety-related Events Resulting from Fissile Material
Operations under Procedures Not Reviewed by Criticality Safety
Staff
IN-08-13
Main Feedwater System Issues and Related 2007 Reactor Trip Data
IN-08-12
Braidwood Unit 1 Reactor Trip Due to Off-Site Power Fluctuation
IN-08-11
Service Water System Degradation at Brunswick Steam Electric
Plant Unit 1
IN-08-10
Response to Indications of Potential Tampering, Vandalism, or
Malicious Mischief
IN-08-09
Turbine-driven Auxiliary Feedwater Pump Bearing Issues
IN-08-08
Maintenance Procedures Compromise Double-Contingency of UO2
Powder-Handling Equipment at Fuel Cycle Facility
IN-08-07
Cracking Indications in Thermally Treated Alloy 600 Steam
Generator Tubes
IN-08-06
Instrument Air System Failure Resulting In Manual Reactor Trip
IN-08-05
Fires Involving Emergency Diesel Generator Exhaust Manifolds
IN-08-04
Counterfeit Parts Supplied to Nuclear Power Plants
IN-08-03
Precautions to take before Sharing Sensitive Security-Related
Information
IN-08-02
Findings Identified During Component Design Bases Inspections
IN-08-01
Designation and Protection Of Safeguards Information
IN-0739
Control of Simulation Software Categorized as Sensitive Unclassified
Nonsafeguards Information
IN-0740
Inadequate Implementation of 10 CFR Part 21 Requirements by
Vendors Who Supply Basic Components To Nuclear Power Plant
Licensees
IN-0738
Ensuring Complete and Accurate Information in the Documentation
of Training and Experience for Individuals Seeking Approval as
Medical Authorized Users
IN-0737
Buildup of Deposits in Steam Generator
IN-0736
Emergency Diesel Generator Voltage Regulator Problems
IN-0735
Varian Medical Systems Varisource HDR Events: Iridium-192 Source
Pulled From Sheilded Position
IN-0734
Operating Experience Regarding Electrical Circuit Breakers
IN-0733
Exposures to Members of the Public Caused by Inadequate Controls
Over Well Logging Sources
IN-0732
Out-of-service Equipment Connected To In-service Process Line
Results in Fissile Solution Spill at Fuel Cycle Facility
IN-0731
U.S. Food and Drug Administration Announcement Related to
Certain Sleep Disorder Drugs
IN-0730
Radiological Controls Create Criticality Safety Accident Scenario for
Fissile Solution Container Transport at Fuel Cycle Facility
IN-0729
Temporary Scaffolding Affects Operability of Safety-related
Equipment
IN-0728
Potential Common Cause Vulnerabilities in Essential Service Water
Systems Due to Inadequate Chemistry Controls
IN-0727
Recurring Events Involving Emergency Diesel Generator Operability
IN-0726
Combustibility of Epoxy Floor Coatings at Commercial Nuclear
Power Plants
IN-0725
Suggestion from the Advisory Committee on the Medical Use of
Isotopes for Consideration to Improve Compliance With Sodium
Iodide I-131 Written Directive Requirements in 10 CFR 35.40 and
Supervision Requirements in 10 CFR 35.27
IN-0724
Summary of Fitness-For-Duty Program Performance Reports for
Calendar Year 2006
IN-0723
Inadvertent Discharge of Halon 1301 Fire-suppression System from
Incorrect and/or Out-of-date Procedures
IN-0722
Recent Hydorgen Fluoride Exposures at Fuel Cycle Facilities
IN-0721
Pipe Wear Due to Interaction of Flow-induced Vibration and
Reflective Metal Insulation
IN-0720
Use of Blank Ammunition
IN-0719
Fire Protection Equipment Recalls and Counterfeit Notices
IN-0718
Operating Experience Regarding Entrainment of Gas or Debris into
Auxiliary Feedwater Systems
IN-0717
Fires at Nuclear Power Plants Involving Inadequate Fire Protection
Administrative and Design Controls
IN-0716
Common Violations of the Increased Controls Requirements and
Related Guidance Documents
IN-0715
Effects of Ethernet-based, Non-safety Related Controls on the Safe
and Continued Operation of Nuclear Power Stations
IN-0714
Loss of Offsite Power and Dual-unit Trip at Catawba Nuclear
Generating Station
IN-0713
Use of As-found Conditions to Evaluate Criticality-related Process
Upsets at Fuel Cycle Facilities
IN-0712
Tactical Communications Interoperability Between Nuclear Power
Reactor Licensees and First Responders
IN-0711
Recent Operator Performance Issues at Nuclear Power Plants
IN-0710
Yttrium-90 Theraspheres® and Sirspheres® Impurities
IN-0709
Equipment Operability under Degraded Voltage Conditions
IN-0708
Potential vulnerabilities of time-reliant computer-based systems due
to change in daylight saving time dates
IN-0707
Potential Failure of All Control Rod Groups to Insert in a Boiling
Water Reactor Due to a Fire
IN-0706
Potential Common Cause Vulnerabilities in Essential Services Water
Systems
IN-0705
Vertical Deep Draft Pump Shaft and Coupling Failures
IN-0704
Construction Experience Related to the Assurance of Quality in the
Construction of Nuclear Facilities
IN-0703
Reportable Medical Events Involving Patients Receiving Dosages of
Sodium Iodide Iodine-131 Less Than the Prescribed Dosage
Because of Capsules Remaining in Vials After Administration.
IN-0702
Failure of Control Rod Drive Mechanism Lead Screw Male Coupling
at a Babcock and Wilcox-designed Facility
IN-0701
Recent Operating Experience Concerning Hydrostatic Barriers
IN-0631
Inadequate Fault Interrupting Rating of Breakers
IN-0630
Summary of Fitness-for-duty Program Performance Reports for
Calendar Years 2004 and 2005
IN-0629
Potential Common Cause Failure of Motor-operated Valves as a
Result of Stem nut Wear
IN-0628
Siren System Failures Due to Erroneous Siren System Signal
IN-0627
Circumferential Cracking in the Stainless Steel Pressurizer Heater
Sleeves of Pressurized Water Reactors
IN-0626
Failure of Magnesium Rotors in Motor-operated Valve Actuators
IN-0625
Lessons Learned From NRC Inspection Of Control And Accounting
Of Special Nuclear Material At Commercial Nuclear Power Reactors
IN-0624
Recent Operating Experience Associated with Pressure and Main
Steam Safety/Relief Valve Lift Setpoints
IN-0623
Events Involving Potential Tampering Or Malfeasance By Persons
Granted Unescorted Access
IN-0622
New Ultra-low-sulfur Diesel Fuel Oil Could Adversely Impact Diesel
Engine Performance
IN-0621
Operating Experience Regarding Entrainment of Air into Emergency
Core Cooling and Containment Spray Systems
IN-0620
Foreign Material Found in the Emergency Core Cooling System
IN-0619
Leaking Fuel Element Causes False Indication of Steam Dryer
Leakage in Boiling-Water Reactor
IN-0618sup1 Significant Loss of Safety-Related Electrical Power at Forsmark, Unit
1, in Sweden
IN-0618
Significant Loss of Safety-Related Electrical Power at Forsmark, Unit
1, in Sweden
IN-0617
Recent Operating Experience of Service Water Systems Due to
External Conditions
IN-0616
Implementing Search Requirements for Personnel, Packages and
Material at NRC-Licensed Facilities
IN-0615
Vibration-Induced Degradtion and Failure of Safety-Related Valves
IN-0614sup1 Potentially Defective External Lead-Wire Connections in Barton
Pressure Transmitters
IN-0614
Potentially Defective External Lead-Wire Connections in Barton
Pressure Transmitters
IN-0613
Ground-Water Contamination Due to Undetected Leakage of
Radioactive Water
IN-0612
Exercising Due Diligence when Transferring Radioactive Materials
IN-0611
Applicability of Patient Intervention in Determining Medical Events for
Gamma Stereotactic Radiosurgery and Other Therapy Procedures
IN-0610
Use of Concentration Control for Criticality Safety
IN-0609
Performance of NRC-Licensed Individuals while on Duty with
Respect to Control Room Attentiveness
IN-0608
Secondary Piping Rupture at the Mihama Power Station in Japan
IN-0607
Inappropriate Use of a Single-Parameter Limit as a Nuclear Criticality
Safety Limit
IN-0606
Loss of Offsite Power and Station Blackout Are More Probable
During Summer Period
IN-0605
Possible Defect in Bussmann KWN-R AND KTN-R Fuses
IN-0604
Design Deficiency in Pressurizer Heaters for Pressurized-Water
Reactors
IN-0603
Motor Starter Failures Due to Mechanical-Interlock Binding
IN-0602
Use of Galvanized Supports and Cable Trays with Meggitt Si 2400
Stainless-Steel-Jacketed Electrical Cables
IN-0601
Torus Cracking in a BWR Mark I Containment
IN-0533
Managing the Safety/Security Interface
IN-0532
Product Alert for Fire Hydrants
IN-0531
Potential Non-Conservative Error in Preparing Problem-Dependent
Cross Sections for Use with the Keno V.A. or Keno-VI Criticality
Code
IN-0530
Safe Shutdown Potentially Challenged by Unanalyzed Internal
Flooding Events and Inadequate Design
IN-0529
Steam Generator Tube and Support Configuration
IN-0528
Inadequate Test Procdures Fails to Detect Inoperable Criticality
Accident Alarm Horns
IN-0527
Low-Dose-Rate Manual Brachytherapy — Equipment-Related
Medical Events
IN-0526s1
Additional Results of Chemical Effects Tests in a Simulated PWR
Sump Pool Environment
IN-0526
Results of Chemical Effects Head Loss Tests in a Simulated PWR
Sump Pool Environment
IN-0525
Inadvertent Reactor Trip and Partial Safety Injection Actuation Due
to Tin Whisker
IN-0524
Nonconservatism in Leakage Detection Sensitivity
IN-0523
Vibration-Induced Degradation of Butterfly Valves
IN-0522
Inadequate Criticality Safety Analysis of Ventilation Systems at Fuel
Cycle Facilities
IN-0521
Plant Trip and Loss of Preferred AC Power from Inadequate
Switchyard Maintenance
IN-0520
Electrical Distribution System Failures Affecting Security Equipment
IN-0519
Effect of Plant Configuration Changes on the Emergency Plan
IN-0518
Summary of Fitness-for-Duty Program Performance Reports for
Calendar Years 2001, 2002 and 2003
IN-0517
Manual Brachytherapy Source Jamming
IN-0516
Outage Planning and Scheduling - Impacts on Risk
IN-0515
Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear
Generating Station
IN-0515
attachment
Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear
Generating Station
IN-0514
Fire Protection Findings on Loss of Seal Cooling to Westinghouse
Reactor Coolant Pumps
IN-0513
Potential Non-Conservative Error in Modeling Geometric Regions in
the Keno-V.a Criticality Code
IN-0512
Excessively Large Criticality Safety Limits Fail to Provide Double
Contingency at Fuel Cycle Facility
IN-0511
Internal Flooding/Spray-Down of Safety-Related Equipment Due to
Unsealed Equipment Hatch Floor Plugs and/or Blocked Floor Drains
IN-0510
Changes to 10 CFR Part 71 Packages
IN-0509
Indications in Thermally Treated Alloy 600 Steam Generator Tubes
and Tube-to-Tubesheet Welds
IN-0508
Monitoring Vibration to Detect Circumferential Cracking of Reactor
Coolant Pump and Reactor Recirculation Pump Shafts
IN-0507
Results of HEMYC Electrical Raceway Fire Barrier System Full
Scale Fire Testing
IN-0506
Failure to Maintain Alert and Notification System Tone Alert Radio
Capability
IN-0505
Improving Material Control and Accountability Interface with
Criticality Safety Activities at Fuel Cycle Facilities
IN-0504
Single-Failure and Fire Vulnerability of Redundant Electrical Safety
Buses
IN-0503
Inadequate Design and Installation of Seismic-Gap Fire Barriers
IN-0502
Pressure Boundary Leakage Identified on Steam Generator Bowl
Drain Welds
IN-0501
Halon Fire-Extinguishing System Piping Incorrectly Connected
IN-04021
Additional Adverse Effect of Boric Acid Leakage: Potential Impact on
Post-Accident Coolant pH
IN-04020
Recent Issues Associated with NRC Medical Requirements for
Licensed Operators
IN-04019
Problems Associated with Back-up Power Supplies to Emergency
Response Facilities and Equipment
IN-04018
Recent Safety-Related Event at Panoramic Wet-Source-Storage
Irradiator
IN-04017
Loose Part Detection and Computerized Eddy Current Data Analysis
in Steam Generators
IN-04016
Tube Leakage due to a Fabrication Flaw in a Replacement Steam
Generator
IN-04015
Dual-Unit Scram at Peach Bottom Units 2 and 3
IN-04014
Use of less than Optimal Bounding Assumptions in Criticality Safety
Analysis at Fuel Cycle Facilities
IN-04013
Registration, Use, and Quality Assurance Requirements for NRCCertified Transportation Packages
IN-04012
Spent Fuel Rod Accountability
IN-04011
Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line
Nozzle
IN-04010
Loose Parts in Steam Generators
IN-04009
Corrosion of Steel Containment and Containment Liner
IN-04008
Reactor Coolant Pressure Boundary Leakage Attributable to
Propagation of Cracking in Reactor Vessel Nozzle Welds
IN-04007
Plugging of Safety Injection Pump Lubrication Oil Coolers With
Lakeweed1
IN-04006
Loss of Feedwater Isokinetic Sampling Probes at Dresden Units 2
and 3
IN-04005
Spent Fuel Pool Leakage to Onsite Groundwater
IN-04004
Fuel Damage During Cleaning at a Foreign Pressurized Water
Reactor
IN-04003
Radiation Exposures to Members of the Public in Excess of
Regulatory Limits Caused by Failures to Perform Appropriate
Radiation Surveys During Well-logging Operations
IN-04002
Strontium-90 Eye Applicators: New Calibration Values and Use
IN-04001
Auxiliary Feedwater Pump Recirculation Line Orifice Fouling Potential Common Cause Failure
IN03022sup1
Heightened Awareness for Patients Containing Detectable Amounts
of Radiation from Medical Administrations, Supplement 1
IN-03022
Heightened Awareness for Patients Containing Detectable Amounts
of Radiation from Medical Administrations
IN-03021
High-Dose-Rate-Remote-Afterloader Equipment Failure
IN-03020
Derating Whiting Cranes Purchased Before 1980
IN-03019
Unanalyzed Condition of Reactor Coolant Pump Seal Leakoff Line
During Postulated Fire Scenarios or Station Blackout
IN-03018
General Electric Type SBM Control Switches with Defective Cam
Followers
IN-03017
Reduced Service Life of Automatic Switch Company (ASCO)
Solenoid Valves with Buna-n Material
IN-03016
Icing Conditions Between Bottom Of Dry Storage System And
Storage Pad
IN-03015
Importance of Follow-up Activities in Resolving Maintenance Issues
IN-03014
Potential Vulnerability of Plant Computer Network to Worm Infection
IN-03013
Steam Generator Tube Degradation at Diablo Canyon
IN-03012
Problems Involved in Monitoring Dose to the Hands Resulting from
the Handling of Radiopharmaceuticals
IN-03011s1
Leakage Found on Bottom-Mounted Instrumentation Nozzles
IN-03011
Leakage Found on Bottom-Mounted Instrumentation Nozzles
IN-03010
Criticality Monitoring System Degradation at BWX Technologies,
Inc., Nuclear Products Division, Lynchburg, VA
IN-03009
Source Positioning Errors and System Malfunctions During
Administration of Intravascular Brachytherapy
IN-03008
Potential Flooding Through Unsealed Concrete Floor Cracks
IN-03007
Water in the Vent Header/Vent Line Spherical Junctions
IN-03006
Failure of Safety-Related Linestarter Relays at San Onofre
NuclearGenerating Station
IN-03005
Failure to Detect Freespan Cracks in PWR Steam Generator Tubes
IN-03004
Summary of Fitness-For-Duty Program Performance Reports for
Calendar Year 2000
IN-03003
Part 21 - Inadequately Staked Capscrew Renders Residual Heat
Removal Pump Inoperable
IN-03002
Recent Experience With Reactor Coolant System Leakage And Boric
Acid Corrosion
IN-03001
Failure of a Boiling Water Reator Target Rock Main Steam
Safety/Relief Valve
IN-02023s1
Unauthorized Administration of Byproduct Material for Medical Use –
Supplement 1
IN-02026s2
Additional Flow-Induced Vibration Failures after a Recent Power
Uprate – Supplement 2
IN-02026s1
Additional Failure of Steam Dryer After a Recent Power Uprate –
Supplement 1
IN-02015s1
Potential Hydrogen Combustion Events in BWR Piping –
Supplement 1
IN-02021s1
Axial Outside-Diameter Cracking Affecting Thermally Treated Alloy
600 Steam Generator Tubing – Supplement 1
IN-02031s1
Potentially Defective UF6 Cylinder Valves (1-inch) – Supplement 1
IN-02036
Incomplete or Inaccurate Information Provided to the Licensee
And/or NRC by Any Contractor or Subcontractor Employee
IN-02035
Changes To 10 CFR Parts 71 AND 72 Quality Assurance Programs
IN-02034
Failure of Safety-Related Circuit Breaker External Auxiliary Switches
at Columbia Generating Station
IN-02033
Notification of Permanent Injunction Against Neutron Products
Incorporated of Dickerson, Maryland
IN-02029er
Recent Design Problems in Safety Functions of Pneumatic Systems
– (ERRATA)
IN-02032
Electromigration on Semiconductor Integrated Circuits
IN-02031
Potentially Defective UF6 Cylinder Valves (1-Inch)
IN-02030
Control And Surveillance of Portable Gauges During Field
Operations
IN-02029
Recent Design Problems in Safety Functions of Pneumatic Systems
IN-02028
Appointment of Radiation Safety Officers and Authorized Users
Under 10 CFR Part 35
IN-02027
Recent Fires at Commercial Nuclear Power Plants in the United
States
IN-02026
Failure of Steam Dryer Cover Plate After a Recent Power Uprate
IN-02025
Challenges to Licensees Ability to Provide Prompt Public Notification
and Information During an Emergency Preparedness Event
IN-02024
Potential Problems with Heat Collectors on Fire Protection Sprinklers
IN-02002s1
Recent Experience With Plugged Steam Generator Tubes –
Supplement 1
IN-02023
Unauthorized Administration of Byproduct Material For Medical Use
IN-02010s1
Diablo Canyon Manual Reactor Trip and Steam Generator Water
Level Setpoint Uncertainties – Supplement 1
IN-02022
Degraded Bearing Surfaces in GM/EMD Emergency Diesel
Generators
IN-02021
Axial Outside-Diameter Cracking Affecting Thermally Treated Alloy
600 Steam Generator Tubing
IN-02020
Microwave Parimeter Intrusion Detection System Installation
IN-02019
Medical Misadministrations Caused by Failure to Properly Perform
Tests on Dose Calibrators for Beta-and-Low Energy Photon-Emitting
Radionuclides
IN-02018
Effect of Adding Gas Into Water Storage Tanks on the Net Positive
Suction Head For Pumps
IN-02017
Medical use of Strontium-90 Eye Applicators: New Requirements for
Calibration and Decay Correction
IN-02016
Intravascular Brachytherapy Misadministrations
IN-02015
Hydrogen Combustion Events in Foreign BWR Piping
IN-02014
Ensuring a Capability to Evacuate Individuals, Including Members of
the Public, from the Owner-Controlled Area
IN-02013
Possible Indicators of Ongoing Reactor Pressure Vessel Head
Degradation
IN-02012
Submerged Safety-Related Electrical Cables
IN-02011
Recent Experience with Degradation of Reactor Pressure Vessel
Head
IN-02010
Nonconservative Water Level Setpoints on Steam Generators
IN-02009
Potential for top Nozzle Separation and Dropping of a Certain Type
of Westinghouse Fuel Assembly
IN-02008
Pump Shaft Damage Due to Excessive Hardness of Shaft Sleeve
IN-02007
Use Of Sodium Hypochlorite For Cleaning Diesel Fuel Oil Supply
Tanks
IN-02006
Design Vulnerability in BWR Reactor Vessel Level Instrumentation
Backfill Modification
IN-02005
Foreign Material in Standby Liquid Control Storage Tanks
IN-02004
Wire Degradation at Breaker Cubicle Door Hinges
IN-02003
Highly Radioactive Particle Control Problems During Spent Fuel Pool
Cleanout
IN-02002
Recent Experience with Plugged Steam Generator Tubes
IN-02001
Metalclad Switchgear Failures and Consequent Losses of Offsite
Power
IN-01019
Improper Maintenance and Reassembly of Automatic Oil Bubblers
IN-01018
Degraded or Failed Automated Electronic Monitoring, Control,
Alarming, Response, and Communications Needed for Safety and
Safeguards
IN-01017
Degraded and Failed Performance of Essential Utilities Needed for
Safety and Safeguards
IN-01016
Recent Foreign and Domestic Experience with Degradation of Steam
Generator Tubes and Internals
IN-01015
Non-Conservative Errors in Minimum Critical Power Ratio Limits
IN-01014
Problems with Incorrectly-Installed Swing-Check Valves
IN-01013
Inadequate Standby Liquid Control System Relief Valve Margin
IN-01012er
Hydrogen Fire at Nuclear Power Station – (ERRATA)
IN-01012
Hydrogen Fire at Nuclear Power Station
IN-01011
Thefts of Portable Gauges
IN-01010
Failure of Central Sprinkler Company Model GB Series Fire Sprinkler
Heads
IN-01009
Main Feedwater System Degradation in Safety-Related ASME Code
Class 2 Piping Inside the Containment of a Pressurized Water
Reactor
IN-01008s1
Update on the Investigation of Patient Deaths in Panama, Following
Radiation Therapy Overexposures – Supplement 1
IN-01008
Treatment Planning System Errors Result in Deaths of Overseas
Radiation Therapy Patients
IN-01007
Unescorted Access Granted on the Basis of Incomplete and/or
Inaccurate Information
IN-01006
Centrifugal Charging Pump Thrust Bearing Damage Not Detected
Due to Inadequate Assessment of Oil Analysis Results and Selection
of Pump Surveillance Points
IN-01005
Through-Wall Circumferential Cracking of Reactor Pressure Vessel
Head Control Rod Drive Mechanism Penetration Nozzles at Oconee
Nuclear Station, Unit 3
IN-01004
Neglected Fire Extinguisher Maintenance Causes Fatality
IN-01003
Incident Reporting Requirements for Radiography Licensees
IN-01002
Summary of Fitness-for-Duty Program Performance Reports for
Calendar Years 1998 and 1999
IN-01001
The Importance of Accurate Inventory Controls to Prevent the
Unauthorized Possession of Radioactive Material
IN-00022
Medical Misadministrations Caused by Human Errors Involving
Gamma Stereotactic Radiosurgery (Gamma Knife)
IN-00021
Detached Check Valve Disc Not Detected by Use of Acoustic and
Magnetic Nonintrusive Test Techniques
IN-00020
Potential Loss of Redundant Safety-Related Equipment Because of
the Lack of High-Energy Line Break Barriers
IN-00019
Implementation of Human Use Research Protocols Involving U.S.
Nuclear Regulatory Commission Regulated Materials
IN-00018
Substandard Material Supplied by Chicago Bullet Proof Systems
IN-00017s2
Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.
C. Summer – Supplement 2
IN-00017s1
Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.
C. Summer – Supplement 1
IN-00017
Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.
C. Summer
IN-00016
Potential Hazards Due to Volatilization of Radionuclides
IN-00015
Recent Events Resulting in Whole Body Exposures Exceeding
Regulatory Limits
IN-00014
Non-Vital Bus Fault Leads to Fire and Loss of Offsite Power
IN-00013
Review of Refueling Outage Risk
IN-00012
Potential Degradation of Firefighter Primary Protective Garments
IN-00011
Licensee Responsibility for Quality Assurance Oversight of
Contractor Activities Regarding Fabrication and Use of Spent Fuel
Storage Cask Systems
IN-00010
Recent Events Resulting in Extremity Exposures Exceeding
Regulatory Limits
IN-00009
Steam Generator Tube Failure at Indian Point Unit 2
IN-00008
Inadequate Assessment of the Effect of Differential Temperatures on
Safety- Related Pumps
IN-00007
National Institute for Occupational Safety and Health Respirator User
Notice: Special Precautions for Using Certain Self-Contained
Breathing Apparatus Air Cylinders
IN-00006
Offsite Power Voltage Inadequacies
IN-00005
Recent Medical Misadministrations Resulting from Inattention to
Detail
IN-00004
1999 Enforcement Sanctions for Deliberate Violations of NRC
Employee Protection Requirements
IN-00003
High-Efficiency Particulate Air Filter Exceeds Mass Limit Before
Reaching Expected Differential Pressure
IN-00002
Failure of Criticality Safety Control to Prevent Uranium Dioxide (Uo2)
Powder Accumulation
IN-00001
Operational Issues Identified in Boiling Water Reactor Trip and
Transient
IN-99003r1
Exothermic Reactions Involving Dried Uranium Oxide Powder
(Yellowcake) - Revision 1
IN-99028s1
Recall of Star Brand Fire Protection Sprinkler Heads – Supplement 1
IN-99034
Potential Fire Hazard in the Use of Polyalphaolefin in Testing of Air
Filters
IN-99033
Management of Wastes Contaminated with Radioactive Materials
IN-99032
The Effect of the Year 2000 Issue on Medical Licensees
IN-99031
Operational Controls to Guard Against Inadvertent Nuclear Criticality
IN-99030
Failure of Double Contingency Based on Administrative Controls
Involving Laboratory Sampling and Spectroscopic Analysis of Wet
Uranium Waste
IN-99029
Authorized Contents of Spent Fuel Casks
IN-99010r1
Degradation of Prestressing Tendon Systems in Prestressed
Concrete Containments – Revision 1
IN-99028
Recall of Star Brand Fire Protection Sprinkler Heads
IN-99027
Malfunction of Source Retraction Mechanism in Cobalt-60
Teletherapy Treatment Units
IN-99026
Safety and Economic Consequences of Misleading Marketing
Information
IN-99025
Year 2000 Contingency Planning Activities
IN-99024
Broad-Scope Licensees' Responsibilities for Reviewing and
Approving Unregistered Sealed Sources and Devices
IN-99023
Safety Concerns Related to Repeated Control Unit Failures of the
Nucletron Classic Model High-Dose-Rate Remote Afterloading
Brachytherapy Devices
IN-99022
10 CFR 34.43 (a) (1); Effective Date for Radiographer Certification
and Plans for Enforcement Discretion
IN-99021
Recent Plant Events Caused by Human Performance Errors
IN-99020
Contingency Planning for the Year 2000 Computer Problem
IN-99019
Rupture of the Shell Side of a Feedwater Heater at the Point Beach
Nuclear Plant
IN-99018
Update on NRC'S Year 2000 Activities for Materials Licensees and
Fuel Cycle Licensees and Certificate Holders
IN-99017
Problems Associated with Post-Fire Safe-Shutdown Circuit Analyses
IN-99016
Federal Bureau of Investigation's Nuclear Site Security Program
IN-99015
Misapplication of 10 CFR Part 71 transportation Shipping Cask
Licensing Basis to 10 CFR Part 50 Design Basis
IN-99014
Unanticipated Reactor Water Draindown at Quad Cities Unit 2,
Arkansas Nuclear One Unit 2, and Fitzpatrick
IN-99013
Insights from NRC Inspections of Low- and Medium-voltage Circuit
Breaker Maintenance Programs
IN-99012
Year 2000 Computer Systems Readiness Audits
IN-99011
Incidents Involving the Use of Radioactive Iodine-131
IN-99010
Degradation of Prestressing Tendon Systems in Prestressed
Concrete Containments
IN-99008
Urine Specimen Adulteration
IN-99009
Problems Encountered When Manually Editing Treatment Data on
the Nucletron Microselectron-HDR (New) Model 105.999
IN-99007
Failed Fire Protection Deluge Valves and Potential Testing
Deficiencies in Preaction Sprinkler Systems
IN-99006
1998 Enforcement Sanctions as a Result of Deliberate Violations of
NRC Employee Protection Requirements
IN-99005
Inadvertent Discharge of Carbon Dioxide Fire Protection System and
Gas Migration
IN-99004
Unplanned Radiation Exposures to Radiographers, Resulting from
Failures to Follow Proper Radiation Safety Procedures
IN-99003
Exothermic Reactions Involving Dried Uranium Oxide Powder
(Yellowcake)
IN-99002
Guidance to Users on the Implementation of a New Single-Source
Dose-Calculation Formalism and Revised Air-Kerma Strength
Standard for Iodine-125 Sealed Sources
IN-99001
Deterioration of High-Efficiency Particulate Air Filters in a
Pressurized Water Reactor Containment Fan Cooler Unit
IN-98045
Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue
Cracking of Pipe Welds
IN-98044
Ten-Year Inservice Inspection (ISI) Program Update for Licensees
That Intend to Implement Risk-Informed ISI of Piping
IN-98043
Leaks in the Emergency Diesel Generator Lubricating Oil and Jacket
Cooling Water Piping
IN-98042
Implementation of 10 CFR 50.55a(g) Inservice Inspection
Requirements
IN-98041
Spurious Shutdown of Emergency Diesel Generators from Design
Oversight
IN-98040
Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive
Suction Head During Design-Basis Accidents
IN-98039
Summary of Fitness-For-Duty Program Performance Reports for
Calendar Years 1996 and 1997
IN-98038
Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC
Inspections
IN-98037
Eligibility of Operator License Applicants
IN-98036
Inadequate or Poorly Controlled, Non-Safety-Related Maintenance
Activities Unnecessarily Challenged Safety Systems
IN-98035
Threat Assessments and Consideration of Heightened Physical
Protection Measures issued
IN-98034
Configuration Control Errors
IN-98033
NRC Regulations Prohibit Agreements That Restrict or Discourage
an Employee from Participating in Protected Activities
IN-98031
Fire Protection System Design Deficiencies and Common-Mode
Flooding of Emergency Core Cooling System Rooms at Washington
Nuclear Project Unit 2
IN-98030
Effect of the Year 2000 Computer Problem on NRC Licensees and
Certificate Holders
IN-98029
Predicted Increase in Fuel Rod Cladding Oxidation
IN-98028
Development of Systematic Sample Plan for Operator Licensing
Examinations
IN-98027
Steam Generator Tube End Cracking
IN-98026
Settlement Monitoring and Inspection of Plant Structures Affected by
Degradation of Porous Concrete Subfoundations
IN-98025
Loss of Inventory from Safety-Related, Closed-Loop Cooling Water
Systems
IN-98024
Stem Binding in Turbine Governor Valves in Reactor Core Isolation
Cooling (RCIC) and Auxiliary Feedwater (AFW) Systems
IN-98023
Crosby Relief Valve Setpoint Drift Problems Caused by Corrosion of
The Guide Ring
IN-98022
Deficiencies Identified During NRC Design Inspections
IN-98021
Potential Deficiency of Electrical Cable/Connection Systems
IN-98020
Problems with Emergency Preparedness Respiratory Protection
Programs
IN-98019
Shaft Binding in General Electric Type SBM Control Switches
IN-98018
Recent Contamination Incidences Resulting from Failure to Perform
Adequate Surveys
IN-98017
Federal Bureau of Investigation's (FBI) Awareness of National
Security Issues and Response (ANSIR) Program
IN-98016
Inadequate Operational Checks of Alarm Ratemeters
IN-98015
Integrity of Operator Licensing Examinations
IN-98014
Undocumented Changes to Non-Power Reactor Safety System
Wiring
IN-98013
Post-Refueling Outage Reactor Pressure Vessel Leak Testing
Before Core Criticality
IN-98012
Licensees' Responsibilities Regarding Reporting and Follow-Up
Requirements for Nuclear-Powered Pacemakers
IN-98011
Cracking of Reactor Vessel Internal Baffle Former Bolts in Foreign
Plants
IN-98010
Probable Misadministrations Occurring During Intravascular
Brachytherapy with the Novoste Beta-Cath System
IN-98009
Collapse of an ISOCAM II, Dual-Headed Nuclear Medicine Gamma
Camera
IN-98008
Information Likely to be Requested if an Emergency is Declared
IN-98007
Offsite Power Reliability Challenges from Industry Deregulation
IN-98006
Unauthorized Use of License to Obtain Radioactive Materials, and its
Implications under the Expanded Title 18 of the U.S. Code
IN-98005
Criminal History Record Information
IN-98004
1997 Enforcement Sanctions for Deliberate Violations of NRC
Employee Protection Requirements
IN-98032
NONE
IN-98003
Inadequate Verification of Overcurrent Trip Setpoints in Metal-Clad,
Low-Voltage Circuit Breakers
IN-98002
Nuclear Power Plant Cold Weather Problems and Protective
Measures
IN-98001
Thefts of Portable Gauges
IN-97015s1
Reporting of Errors and Changes in Large-Break/ Small-Break Lossof- Coolant Evaluation Models of Fuel Vendors and Compliance with
10 CFR 50.46(a)(3) – Supplement 1
IN-97091s1
Recent Failures of Control Cables Used on Amersham Model 660
Posilock Radiography Systems – Supplement 1
IN-97063s1
Status of NRC Staff's Review of BWRVIP-05 – Supplement 1
IN-97045s1
Environmental Qualification Deficiency for Cables and Containment
Penetration Pigtails – Supplement 1
IN-97091
Recent Failures of Control Cables Used on Amersham Model 660
Posilock Radiography Systems
IN-97090
Use of Nonconservative Acceptance Criteria in Safety-Related Pump
Surveillance Tests
IN-97089
Distribution of Sources and Devices Without Authorization
IN-97088
Experiences During Recent Steam Generator Inspections
IN-97087
Second Retrofit to Industrial Nuclear Company IR100 Radiography
Camera, to Correct Inconsistency in 10 CFR Part 34 Compatibility
IN-97086
Additional Controls for Transport of the Amersham Model No. 660
Series Radiographic Exposure Devices
IN-97085
Effects of Crud Buildup and Boron Deposition on Power Distribution
and Shutdown Margin
IN-97084
Rupture in Extraction Steam Piping as a Result of Flow-Accelerated
Corrosion
IN-97083
Recent Events Involving Reactor Coolant System Inventory Control
During Shutdown
IN-97082
Inadvertent Control Room Halon Actuation Due to a Camera Flash
IN-97081
Deficiencies in Failure Modes and Effects Analyses for
Instrumentation and Control Systems
IN-97080
Licensee Technical Specifications Interpretations
IN-97079
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
IN-97076
Degraded Throttle Valves in Emergency Core Cooling System
Resulting From Cavitation-Induced Erosion During a Loss-of-coolant
Accident
IN-97078
Crediting of Operator Actions in Place of Automatic Actions and
Modifications of Operator Actions, Including Response Times
IN-97077
Exemptions From the Requirements of Section 70.24 of Title 10 of
The Code of Federal Regulations
IN-97075
Enforcement Sanctions Issued as a Result of Deliberate Violations of
NRC Requirements
IN-97074
Inadequate Oversight of Contractors During Sealant Injection
Activities
IN-97073
Fire Hazard in the Use of a Leak Sealant
IN-97072
Potential for Failure of the Omega Series Sprinkler Heads
IN-97071
Inappropriate Use of 10 CFR 50.59 Regarding Reduced Seismic
Criteria for Temporary Conditions
IN-97070
Potential Problems with Fire Barrier Penetration Seals
IN-97069
Reactor Trip Breakers and Surveillance Testing of Auxiliary Contacts
IN-97068
Loss of Control of Diver in a Spent Fuel Storage Pool
IN-97067
Failure to Satisfy the Requirements for Significant Manipulation of
the Controls for Power Reactor Operator Licensing
IN-97066
Failure to Provide Special Lenses For Operators Using Respirator or
Self-Contained Breathing Apparatus During Emergency Operations
IN-97065
Failures of High-Dose-Rate Remote Afterloading (HDR) Device
Source Guide Tubes, Catheters, and Applicators
IN-97064
Potential Problems Associated With Loss of Electrical Power in
Certain Teletherapy Units
IN-97063
Status of NRC Staff's Review of BWRVIP-05
IN-97062
Unrecognized Reactivity Addition During Plant Shutdown
IN-97061
U.S. Department of Health and Human Services Letter, to Medical
Device Manufacturers, on the Year 2000 Problem
IN-97060
Incorrect Unreviewed Safety Question Determination Related to
Emergency Core Cooling System Swapover From the Injection Mode
to The Recirculation Mode
IN-97059
Fire Endurance Test Results of Versawrap Fire Barriers
IN-97058
Mechanical Integrity of In-Situ Leach Injection Wells And Piping
IN-97057
Leak Testing F Packaging Used in The Transport of Radioactive
Material
IN-97056
Possession Limits for Special Nuclear Material at the Environcare of
Utah Low-Level Radioactive Material
IN-97055
Calculation of Surface Activity for Contaminated Equipment and
Material
IN-97054
NRC Licensed Operators at Six Non-power Reactor Facilities Allow
Their Operator License to Expire
IN-97053
Circuit Breakers Left Racked Out in Nonseismic- Ally Qualified
Positions
IN-97052
Inadvertent Loss of Capability for Emergency Core Cooling System
Motors
IN-97051
Problems Experienced Loading and Unloading Spent Nuclear Fuel
Storage and Transportation Casks
IN-97050
Contaminated Lead Products
IN-97049
B&W; Once-through Steam Generator Tube Inspection Findings
IN-97048
Inadequate or Inappropriate Interim Fire Protect- Ion Compensatory
Measures
IN-97046
Unisolable Crack in High-Pressure Injection Piping
IN-97045
Environmental Qualification Deficiency For Cables and Containment
Penetration Pigtails
IN-97044
Failures of Gamma Metrics Wide-range Linear Neutron Flux
Channels
IN-97043
License Condition Compliance
IN-97047
Inadequate Puncture Tests For Type B Packages Under 10 CFR
71.73(c)(3)
IN-97042
Management Weaknesses Resulting in Failure to Comply With
Shipping Requirements for Special Nuclear Material
IN-97041
Potentially Undersized Emergency Diesel Generator (EDG) Oil
Coolers
IN-97040
Potential Nitrogen Accumulation Resulting From Backleakage From
Safety Injection Tanks
IN-97039
Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent
Fuel Storage Installations
IN-97038
Level-Sensing System Initiates Common-Mode Failure of HighPressure-Injection Pumps
IN-97037
Main Transformer Fault With Ensuing Oil Spill Into Turbine Building
IN-97036
Unplanned Intakes by Worker of Transuranic Airborne Radioactive
Materials And External Exposure Due to Inadequate Control of Work
IN-97035
Retrofit to Industrial Nuclear Company (Inc) Ir100 Radiography
Camera to Correct Inconsistency in 10 Cfr 50 Part 34 Compatibility
IN-97034
Deficiensees in Licensee Submittals Regarding Termonology For
Radiological Emergency Action Levels in Accordance With The New
Part 20
IN-97033
Unanticipated Effect of Ventilation System on Tank Level Indications
And Engineering Safety Features Actuation System Setpoint
IN-97032
Defective Worm Shaft Clutch Gears in Limitorque Motor-operated
Valve Actuators
IN-97031
Failures of Reactor Coolant Pump Thermal Barriers and Check
Valves at Foreign Plants
IN-97030
Control of Licensed Material During Reorg- Anizations, EmployeeManagement Disagreements, And Financial Crises
IN-97029
Containment Inspection Rule
IN-97028
Elimination of Instrument Response Time Testing Under The
Requirements of 10 CFR 50.59
IN-97027
Effect of Incorrect Strainer Pressure Drop on Available Net Positive
Suction Head
IN-97026
Degradation in Small-Radius U-bend Regions of Steam Generator
Tubes
IN-97025
Dynamic Range Uncertainties in Reactor Vessel Level
Instrumentation
IN-97024
Failure of Packing Nuts on One-inch Uranium Hexafluoride Cylinder
Valves
IN-97023
Evaluation and Reporting of Fires And Unplanned Chemical Reactor
Events at Fuel Cycle Facilities
IN-97022
Failure of Welded-Steel Moment-Resisting Frames During The
Nothridge Earthquake
IN-97021
Availability of Alternate AC Power Source Designed for Station
Blackout Event
IN-97020
Identification of Certain Uranium Hexafluoride Cylinders that Do Not
Comply With ANSI N14.1 Fabrication Standards
IN-97019
Safety Injection System Weld Flaw at Sequoyah Nuclear Power
Plant, Unit 2
IN-97018
Problems Identified During Maintenance Rule Base- Line Inspections
IN-97017
Cracking of Vertical Welds in The Core Shroud and Degraded Repair
IN-97016
Preconditioning of Plant Structures, Systems, and Components
Before ASME Code Inservice Testing or Technical Specification
Surveillance Testing
IN-97015
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)
IN-97014
Assessment of Spent Fuel Pool Cooling
IN-97013
Deficient Conditions Associated With Protective Coatings at Nuclear
Power Plants
IN-97012
Potential Armature Binding in General Electric Type HGA Relays
IN-97011
Cement Erosion From Containment Subfoundations at Nuclear
Power Plants
IN-97010
Liner Plate Corrosion in Concrete Containments
IN-97009
Inadequate Main Steam Safety Valve (MSSV) Set- Point and
Performance Issues Associated With Long MSSV Inlet Piping
IN-97008
Potential Failures of General Electric Magne- Blast Circuit Breaker
Subcomponents
IN-97007
Problems Identified During Generic Letter 89-10 Closeout
Inspections
IN-97006
Weaknesses in Plant-Specific Emergency Operating Procedures for
Refilling the Secondary Side of Once-Through Steam Generators
IN-97005
Offsite Notification Capabilities
IN-97004
Implementation of a New Constraint on Radioactive Air Effluents
IN-97003
Defacing Labels to Comply With 10 CFR 20.1904(b)
IN-97002
Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water
Reactors
IN-97001
Improper Electrical Grounding Results in Simultaneous Fires in The
Control Room And The Safe- Shutdown Equipment Room
IN-96048s1
Motor-Operated Valve Performance Issues – Supplement 1
IN-96044s1
Failure of Reactor Trip Breaker from Cracking of Phenolic Material in
Secondary Contact Assembly – Supplement 1
IN-96053s1
Retrofit to Amersham 660 Posilock Radiography Camera to Correct
Inconsistency in 10 CFR Part 34 Compatibility – Supplement 1
IN-96071
Licensee Response to Indications of Tampering, Vandalism, or
Malicious Mischief
IN-96072
Undetected Failures That May Occur During Patient Treatments with
Teletherapy Devices
IN-96070
Year 2000 Effect on Computer System Software
IN-96069
Operator Actions Affecting Reactivity
IN-96068
Incorrect Effective Diaphragm Area Values in Vendor Manual Result
in Potential Failure of Pneumatic Diapragm Actuators
IN-96067
Vulnerability of Emergency Diesel Generators to Fuel Oil/Lube Oil
Incompatibility
IN-96066
Recent Misadministrations Caused by Incorrect Calibrations of
Strontium-90 Eye Applicators
IN-96065
Undetected Accumulations of Gas in Reactor Coolant System and
Inaccurate Reactor Water Level Indication During Shutdown (with
figure)
IN-96064
Modifications to Containment Blowout Panels Without Appropriate
Design Controls
IN-96063
Potential Safety Issue Regarding the Shipment of Fissile Material
IN-96062
Potential Failure of the Instantaneous Trip Function of General
Electric RMS-9 Programmers
IN-96061
Failure of a Main Steam Safety Valve to Reseat Caused by an
Improperly Installed Release Nut (with figure)
IN-96060
Potential Common-Mode Post-Accident Failure of Residual Heat
Removal Heat Exchangers
IN-96059
Potential Degradation of Post Loss-of-Coolant Re- Circulation
Capability as a Result of Debris
IN-96058
RCP Seal Replacement with Pump on Backseat
IN-96057
Incident-reporting Requirements Involving Intakes During a 24-hour
Period That May Cause a Total Effective Dose Equivalent in Excess
of 0.05 SV (5 rems)
IN-96056
Problems Associated with Testing, Tuning, or Resetting of Digital
Control Systems While at Power
IN-96055
Inadequate Net Positive Suction Head of Emergency Core Cooling
and Containment Heat Removal Pumps under Design Basis
Accident Conditions
IN-96054
Vulnerability of Stainless Steel to Corrosion When Sensitized
IN-96053
Retrofit to Amersham 660 Posilock Radiography Camera to Correct
Inconsistency in 10 CFR Part 34 Compatibility
IN-96040s1
Deficiencies in Material Dedication and Procurement Practices and
in Audits of Vendors – Supplement 1
IN-96052
Cracked Insertion Rods on Troxler Model 3400 Series Portable
Moisture Density Guages
IN-96051
Residual Contamination Remaining in Krypton-85 Handling System
after Venting
IN-96050
Problems with Levering-in Devices in Westinghouse Circuit Breakers
(with figures)
IN-96048
Motor-Operated Valve Performance Issues
IN-96049
Thermally Induced Pressurization of Nuclear Power Facility Piping
IN-96047
Recordkeeping, Decommissioning Notifications for Disposals of
Radioactive Waste by Land Burial Authorized under Former 10 CFR
20.304, 20.302, and Current 20.2002
IN-96046
Zinc Plating of Hardened Metal Parts and Removal of Protective
Coatings in Refurbished Circuit Breakers
IN-96045
Potential Common-Mode Post-Accident Failure of Containment
Coolers
IN-96044
Failure of Reactor Trip Breaker from Cracking of Phenolic Material in
Secondary Contact Assembly
IN-96042
Unexpected Opening of Multiple Safety Relief Valves
IN-96043
Failures of General Electric Magne-Blast Circuit Breakers
IN-96041
Effects of a Decrease in Feedwater Temperature on Nuclear
Instrumentation
IN-96040
Deficiencies in Material Dedication and Procurement Practices and
in Audits of Vendors
IN-96009s1
Damage in Foreign Steam Generator Internals – Supplement 1
IN-96039
Estimates of Decay Heat Using Ans 5.1 Decay Heat Standard May
Vary Significantly
IN-96038
Results of Steam Generator Tube Examinations
IN-96037
Inaccurate Reactor Water Level Indication and Inadvertent
Draindown During Shutdown
IN-96036
Degradation of Cooling Water Systems Due to Icing
IN-96035
Failure of Safety Systems on Self-Shielded Irradiators Because of
Inadequate Maintenance and Training
IN-96032
Implementation of 10 CFR 50.55a(g)(6)(Ii)(A), "Augmented
Examination of Reactor Vessel"
IN-96034
Hydrogen Gas Ignition During Closure Welding of a VSC-24 MultiAssembly Sealed Basket
IN-96033
Erroneous Data from Defective Thermocouple Results in a Fire
IN-96031
Cross-Tied Safety Injection Accumulators
IN-96030
Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly
Valves
IN-96029
Requirements in 10 CFR Part 21 for Reporting and Evaluating
Software Errors
IN-96028
Suggested Guidance Relating to Development and Implementation
of Corrective Action
IN-96027
Potential Clogging of High Pressure Safety Injection Throttle Valves
During Recirculation
IN-96026
Recent Problems with Overhead Cranes
IN-96025
Traversing In-Core Probe Overwithdrawn at Lasalle County Station,
Unit 1
IN-96024
Preconditioning of Molded-Case Circuit Breakers Before Surveillance
Testing
IN-96023
Fires in Emergency Diesel Generators Exciters During Operation
Following Undetected Fuse Blowing
IN-96022
Improper Equipment Settings Due to the Use of NontemperatureCompensated Test Equipment
IN-96021
Safety Concerns Related to the Design of the Door Interlock Circuit
on Nucletron High-Dose Rate and Pulsed Dose Rate Remote
Afterloading Brachytherapy Devices
IN-96020
Demonstration of Associated Equipment Operability
IN-96019
Failure of Tone Alert Radios to Activate When Receiving a
Shortened Activation Signal
IN-96018
Compliance with 10 CFR Part 20 for Airborne Thorium
IN-96017
Reactor Operation Inconsistent with the Updated Final Safety
Analysis Report
IN-96016
Bwr Operation with Indicated Flow less than Natural Circulation
IN-96015
Unexpected Plant Performance During Performance of New
Surveillance Tests
IN-96014
Degradation of Radwaste Facility Equipment at Millstone Nuclear
Power Station, Unit 1
IN-96013
Potential Containment Leak Paths Through Hydrogen Analyzers
IN-96012
Control Rod Insertion Problems
IN-96011
Ingress of Demineralizer Resins Increases Potential for Stress
Corrosion Cracking of Control Rod Drive Mechanism Penetrations
IN-96010
Potential Blockage by Debris of Safety System Piping Which Is Not
Used During Normal Operation or Tested During Surveillances
IN-96009
Damage in Foreign Steam Generator Internals
IN-96008
Thermally Induced Pressure Locking of a High Pressure Coolant
Injection Gate Valve
IN-96007
Slow Five Percent Scram Insertion Times Caused by Viton
Diaphragms in Scram Solenoid Pilot Valves
IN-96006
Design and Testing Deficiencies of Tornado Dampers at Nuclear
Power Plants
IN-96005
Partial Bypass of Shutdown Cooling Flow from the Reactor Vessel
IN-96004
Incident Reporting Requirements for Radiography Licensees
IN-96003
Main Steam Safety Valve Setpoint Variation as a Result of Thermal
Effects
IN-96002
Inoperability of Power-Operated Relief Valves Masked by
Downstream Indications
IN-96001
Potential for High Post-Accident Closed-cycle
IN-95049s1
Seismic Adequacy of Thermo-Lag Panels – Supplement 1
IN-95052s1
NRC Information Notice 95-52, Supplement 1: Fire Endurance Test
Results for Electrical Raceway Fire Barrier Systems Constructed
from 3M Company Interam Fire Barrier Materials – Supplement 1
IN-95036s1
Potential Problem in Post-Fire Emergency Lighting – Supplement 1
IN-95058
10 CFR 34.20; Final Effective Date
IN-95057
Risk Impact Study Regarding Maintenance During Low-Power
Operation and Shutdown
IN-95056
Shielding Deficiency in Spent Fuel Transfer Canal at a Boiling-water
Reactor
IN-95055
Handling Uncontained Yellowcake Outside of a Facility Processing
Circuit
IN-95054
Decay Heat Management Practices During Refueling Outages
IN-95053
Failures of Main Steam Isolation Valves as a Result of Sticking
Solenoid Pilot Valves
IN-95047r1
Unexpected Opening of a Safety/Relief Valve and Complications
Involving Suppression Pool Cooling Strainer Blockage – Revision 1
IN-95013s1
Potential for Data Collection Equipment to Affect Protection System
Performance – Supplement 1
IN-95052
Fire Endurance Test Results for Electrical Raceway Fire Barrier
Systems Constructed From 3M Company Interam Fire Barrier
Materials
IN-95050
Safety Defect in Gammamed 12I Bronchial Catheter Clamping
Adapters
IN-95051
Recent Incidents Involving Potential Loss of Control of Licensed
Material
IN-95049
Seismic Adequacy of Thermo-Lag Panels
IN-95048
Results of Shift Staffing Study
IN-95046
Unplanned, Undetected Release of Radioactivity from the Exhaust
Ventilation System of a Boiling Water Reactor
IN-95045
American Power Service Falsification of American Society of
Nondestructive Testing (ASNT) Certificates
IN-95047
Unexpected Opening of a Safety/Relief Valve and Complications
Involving Suppression Pool Cooling Strainer Blockage
IN-95043
Failure of the Bolt-Locking Device on Reactor Coolant Pump Turning
Vane
IN-95044
Ensuring Compatible Use of Drive Cables Incorporating Use of
Industrial Nuclear Company Ball-Type Male Connectors
IN-95041
Degradation of Ventilation System Charcoal Resulting from Chemical
Cleaning of Steam Generators
IN-95042
Commission Decision on the Resolution of Generic Issue 23,
"Reactor Coolant Pump Seal Failure"
IN-95040
Supplemental Information to Generic Letter 95-03, "Circumferential
Cracking of Steam Generator Tubes"
IN-95039
Brachytherapy Incidents Involving Treatment Planning Errors
IN-95038
Degradation of Boraflex Neutron Absorber in Spent Fuel Pool
Storage Racks
IN-95037
Inadequate Offsite Power Systems Voltages During Design-Basis
Events
IN-95036
Potential Problems with Post-Fire Emergency Lighting
IN-95035
Degraded Ability of Steam Generators to Remove Decay Heat by
Natural Circulation
IN-95034
Air Actuator and Supply Air Regulator Problems in Copes-Vulcan
Pressurizer Power-Operated Relief Valves
IN-95033
Switchgear Fire and Partial Loss of Offsite Power at Waterford
Generating Station, Unit 3
IN-95010s2
Sup 2 for IN 95-10, Potential for Loss of Automatic Engineered
Safety Features Actuation – Supplement 2
IN-95032
Thermo-Lag 330-1 Flame Spread Test Results
IN-95031
Motor-Operated Valve Failure Caused by Stem Protector Pipe
Interference
IN-95030
Susceptibility of Low-Pressure Coolant Injection and Core Spray
Injection Valves to Pressure Locking
IN-95003s2
Loss of Reactor Coolant Inventory and Potential Loss of Emergency
Mitigation Functions While in a Shutdown Condition – Supplement 2
IN-95029
Oversight of Design and Fabrication Activities for Metal Components
Used in Spent Fuel Dry Storage Systems
IN-95028
Emplacement of Support Pads for Spent Fuel Dry Storage
Installations at Reactor Sites
IN-95027
NRC Review of Nuclear Energy Institute, "Thermo- Lag
Combustibility Evaluation Methodology Plant Screening Guide
IN-95026
Valve Failure During Patient Treatment with Gamma Stereotactic
Radiosurgery Unit
IN-95025
Valve Failure During Patient Treatment with Gamma Stereotactic
Radiosurgery Unit
IN-95024
Summary of Licensed Operator Requalification Inspection Program
Findings
IN-95023
Control Room Staffing Below Minimum Regulatory Requirements
IN-95022
Hardened or Contaminated Lubricants Cause Metal- Clad Circuit
Breaker Failures
IN-95021
Unexpected Degradation of Lead Storage Batteries
IN-95003s1
Loss of Reactor Coolant Inventory and Potential Loss of Emergency
Mitigation Functions While in a Shutdown Condition – Supplement 1
IN-95018s1
Sup 1 to IN 95-18, Potential Pressure-locking of Safety-Related
Power-Operated Gate Valves – Supplement 1
IN-95020
Failures in Rosemount Pressure Transmitters Due to Hydrogen
Permeation into the Sensor Cell
IN-95019
Failure of Reactor Trip Breaker to Open Because of Cutoff Switch
Material Lodged in the Trip Latch Mechanism
IN-95018
Potential Pressure-Locking of Safety-Related Power-Operated Gate
Valves
IN-95017
Reactor Vessel Top Guide And Core Plate Cracking
IN-95016
Vibration Caused by Increased Flow in a Boiling Water Reactor
IN-95015
Inadequate Logic Testing of Safety-Related Circuits
IN-95014
Susceptibility of Containment Sump Recirculation Gate Valves to
Pressure Locking
IN-95013
Potential For Data Collection Equipment to Affect Protection System
Performance
IN-95011
Failure of Condensate Piping Because of Erosion/ Corrosion at FlowStraightening Device
IN-95012
Potentially Nonconforming Fasteners Supplied by A&G; Engineering
II, Inc.
IN-95010s1
Potential for Loss of Automatic Engineered Safety Features
Actuation – Supplement 1
IN-95010
Potential For Loss of Automatic Engineered Safety Features
Actuation
IN-95009
Use of Inappropriate Guidelines And Criteria For Nuclear Piping And
Pipe Support Evaluation And Design
IN-95008
Inaccurate Data Obtained With Clamp-On Ultrasonic Flow
Measurement Instruments
IN-95007
Radiopharmaceutical Vial Breakage During Preparation
IN-95006
Potential Blockage of Safety-Related Strainers by Material Brought
Inside Containment
IN-95005
Undervoltage Protection Relay Settings Out of Tolerance Due to
Test Equipment Harmonics
IN-95004s1
Excessive Cooldown and Depressurization of the Reactor Coolant
System Following a Loss of Offsite Power – Supplement 1
IN-95004
Excessive Cooldown and Depressurization of the Reactor Coolant
System Following a Loss of Offsite Power
IN-95003
Loss of Reactor Coolant Inventory And Potential Loss of Emergency
Mitigation Functions While in a Shutdown Condition
IN-95002
Problems With General Electric CR2940 Contact Blocks in MediumVoltage Circuit Breakers
IN-95001
DOT Safety Advisory: High Pressure Aluminum
IN-94086s1
Legal Actions Against Thermal Science, Inc., Manufacturer of
Thermo-Lag
IN-94066s1
Overspeed of Turbine-driven Pumps Caused by Binding in Stems of
Governor Valves
IN-94061s1
Corrosion of William Powell Gate Valve Disc Holders
IN-94064s1
NRC Information Notice 94-64, Supplement 1: Reactivity Insertion
Transient and Accident Limits for High Burnup Fuel
IN-94090
Transient Resulting in a Reactor Trip and Multiple Safety Injection
System Actuations at Salem
IN-94089
Equipment Failures at Irradiator Facilities
IN-94088
Inservice Inspection Deficiencies Result in Severely Degraded
Steam Generator Tubes
IN-94087
Unanticipated Crack in a Particular Heat of Alloy 600 Used for
Westinghouse Mechanical Plugs for Steam Generator Tubes
IN-94086
Legal Actions Against Thermal Science, Inc., Manufacturer of
Thermo-Lag
IN-94084
Air Entrainment in Terry Turbine Lubricating Oil System
IN-94085
Problems with the Latching Mechanism in Potter and Brumfield R10-E3286-2 Relays
IN-94040s1
Failure of a Rod Control Cluster Assembly to Fully Insert Following a
Reactor Trip at Braidwood Unit 2
IN-94083
Reactor Trip Followed by Unexpected Events
IN-94082
Concerns Regarding Essential Chiller Reliability During Periods of
Low Cooling Water Temperature
IN-94013s2
Unanticipated and Unintended Movement of Fuel Assemblies and
Other Components Due to Improper Operation of Refueling
Equipment
IN-94081
Accuracy of Bioassay and Environmental Sampling Results
IN-94080
Inadequate DC Ground Detection in Direct Current Distribution
System
IN-94079
Microbiologically Influenced Corrosion of Emergency Diesel
Generator Service Water Piping
IN-94078
Electrical Component Failure Due to Degradation of Polyvinyl
Chloride Wire Insulation
IN-94077
Malfunction in Main Generator Voltage Regulator Causing
Overvoltage at Safety-related Electrical Equipment
IN-94076
Recent Failures of Charging/safety Injection Pumps
IN-94075
Minimum Temperature for Criticality
IN-94074
Facility Management Responsibilities for Purchased or Contracted
Services for Radiation Therapy Programs
IN-94073
Clarification of Criticality Reporting Criteria
IN-94072
Increased Control Rod Drop Time From Crud Buildup
IN-94071
Degradation of Scram Solenoid Pilot Valve Pressure and Exhaust
Diaphragms
IN-94070
Issues Associated with Use of Strontium-90 and Other Beta Emitting
Radiopharmaceuticals
IN-94069
Potenial Inadequacies in the Prediction of Torque Requirements For
and Torque output of Motor- Operated Butterfly Valves
IN-94068
Safety-Related Equipment Failures Caused by Faulted Indicating
Lamps
IN-94067
Problems with Henry Pratt Motor-Operated Butter- Fly Valves
IN-94066
Overspeed of Turbine-Driven Pumps Caused by Governor Valve
Stem Binding
IN-94065
Potential Error in Manual Brachytherapy Dose Calculations
Generated Using a Computerized Treatment Planning System
IN-94064
Reativity Insertion Transient and Accident Limits for High Burnup
Fuel
IN-94063
Boric Acid Corrosion of Charging Pump Casing Caused by Cladding
Cracks.
IN-94062
Operational Experience on Steam Generator Tube Leaks and Tube
Ruptures
IN-94061
Corrosion of William Powell Gate Valve Disc Holders
IN-94060
Potential Overpressurization of Main Stream System
IN-94030s1
Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear
Station
IN-94059
Accelerated Dealloying of Cast Aluminum-Bronze Valves Caused by
Microbiologically Induced Corrosion
IN-94058
Reactor Coolant Pump Lube Oil Fire
IN-94057
Debris in Containment and the Residual Heat Removal System
IN-94056
Inaccuracy of Safety Valve Set Pressure Determination Using Assist
Devices
IN-94055
Problems with Copes-Vulcan Power-Operated Relief Valves
IN-94054
Failures of General Electric Magne-Blast Circuit Breakers to Latch
Closed
IN-94053
Hydrogen Gas Burn Inside Pressurizer During Welding
IN-94052
Inadvertent Containment Spray and Reactor Vessel Draindown at
Millstone Unit 1
IN-94051
Inappropriate Greasing of Double Shielded Motor Bearings
IN-94050
Failure of General Electric Contactors to Pull in at the Required
Voltage
IN-94049
Failure of Torque Switch Roll Pins
IN-94048
Snubber Lubricant Degradation in High-Temperature Environments
IN-94013s1
Unanticipated & Unintended Movement - Fuel Assemblies & Other
Components Due - Improper Operation of Refueling Equipment
IN-94047
Accuracy of Information Provided to NRC During the Licensing
Process
IN-94046
Nonconservative Reactor Coolant System Leakage Calculation
IN-94045
Potential Common-Mode Failure Mechanism for Large Vertical
Pumps
IN-94044
Main Steam Isolation Valve Failure To Close On Demand Because
Of Inadequate Maintenance And Testing
IN-94043
Determination of Primary-to-Secondary Steam Generator Leak Rate
IN-94042
Cracking in the Lower Region of the Core Shroud in Boiling-water
Reactors
IN-94041
Problems With General Electric Type CR124 Overload Relay
Ambient Compensation
IN-94040
Failure of a Rod Control Cluster Assembly to Fully Insert Following a
Reactor Trip at Braidwood Unit 2
IN-94039
Identified Problems in Gamma Stereotactic Radiosurgery
IN-94038
Results of a Special NRC Inspection at Dresden ... Unit 1 Following
a Rupture of Service Water Inside Containment
IN-94037
Misadministration Caused By a Bent Interstitial Needle During
Brachytherapy Procedure
IN-94036
Undetected Accumulation of Gas in Reactor Coolant System
IN-94035
NIOSH Respirator User Notices, "Inadvertent Separation of the MMR
From the Facepiece of MSA Company MMR SCBA and Status"
IN-94034
Thermo-Lag 330-660 Flexi-Blanket Ampacity Derating Concerns
IN-94033
Capacitor Failures in Westinghouse Eagle 21 Plant Protection
Systems
IN-94032
Revised Seismic Hazard Estimates
IN-94014s1
Failure to Implement Requirements for Biennial Medical
Examinations and Notification to Nrc of Changes in Medical
Condition of Licensed Operators
IN-94031
Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles
IN-94030
Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear
Station
IN-94029
Charging Pump Trip During a Loss-of-Coolant Event Caused by Low
Suction Pressure
IN-94028
Potential Problems With Fire-Barrier Penetration Seals
IN-94027
Facility Operating Concerns Resulting From Local Area Flooding
IN-94026
Personnel Hazards and Other Problems From Smoldering FireRetardant Material in the Drywell of a Boiling-Water Reactor
IN-94025
Failure of Containment Spray Header Valve to Open Due to
Excessive Pressure From Inertial Effects of Water
IN-94024
Inadequate Maintenance of Uninterruptable Power Supplies and
Inverters
IN-94023
Guidance to hazardous, Radioactive and Mixed Waste Generators
on the Elements of a Waste Minimization Program
IN-94021
Regulatory Requirements When No Operations Are Being Performed
IN-94020
Common-Cause Failures Due to Inadequate Design Control and
Dedication
IN-94019
Emergency Diesel Generator Vulnerability to Failure From Cold Fuel
Oil
IN-94022
Fire Endurance and Ampacity Derating Test Results for 3-hour FireRated Thermo-Lag 330-1 Fire Barriers
IN-94018
Accuracy of Motor-Operated Valve Diagnostic Equipment
(Responses to Supplement 5 to Generic Letter 89-10)
IN-94017
Strontium-90 Eye Applicators: Submission of Quality Management
Plan (QMP), Calibration, and Use
IN-94016
Recent Incidents Resulting in Offsite Contamination
IN-94015
Radiation Exposures During an Event Involving a Fixed Nuclear
Gauge
IN-94014
Failure to Implement ... Biennial Medical Examinations & Notification
... Changes in Licened Operator Medical Conditions
IN-94013
Unanticipated & Unintended Movement - Fuel Assemblies & Other
Components Due - Improper Operation of Refueling Equipment
IN-94012
Insights Gained From Resolving Generic Issue 57: Effects of Fire
Protection System Actuation on Safety-Related Equipment
IN-94011
Turbine Overspeed and Reactor Cooldown During Shutdown
Evolution
IN-94010
Failure of Motor-Operated Valve Electric Power Train Due to
Sheared or Dislodged Motor Pinion Gear Key
IN-94009
Release of Patients With Residual Radioactivity From Medical
Treatment and Control Areas ... Revised 10 CFR Part 20
IN-94008
Potential For Surveillance Testing to Fail to Detect an Inoperable
Main Steam Isolation Valve
IN-94007
Solubility Criteria For Liquid Effluent Releases to Sanitary Sewerage
Under the Revised 10 CFR Part 20
IN-94006
Potential Failure of Long-Term Emergency Nitrogen Supply For the
Automatic Depressurization System Valves
IN-94005
Potential Failure of Steam Generator Tubes With Kinetically Welded
Sleeves
IN-94004
Digital Integrated Circuit Sockets With Intermittent Contact
IN-94003
Deficiencies Identified During Service Water System Operational
Performance Inspections
IN-94002
Inoperability of General Electric Magne-blast
IN-94001
Turbine Blade Failure Caused by Torsional Excitation from Electrical
System Disturbance
IN-93100
Reporting Requirements for Bankruptcy
IN-93099
Undervoltage Relay and Thermal Overload Setpoint Problems
IN-93098
Motor Brakes on Valve Actuator Motors
IN-93097
Failures of Yokes Installed on Walworth Gate and Globe Valves
IN-93101
Jet Pump Hold-Down Beam Failure
IN-93096
Improper Reset Causes Emergency Diesel Generator Failures
IN-93095
Storm-Related Loss of Offsite Power Events Due to Salt Buildup on
Switchyard Insulators
IN-93094
Unauthorized Forced Entry Into the Protected Area At Three Mile
Island Unit 1 on February 7, 1993
IN-93093
Inadequate Control of Reactor Coolant System Conditions During
Shutdown
IN-93092
Plant Improvements to Mitigate Common Dependencies in
Component Cooling Water Systems
IN-93091
Misadjustment Between General Electric 4.16-KV Circuit Breakers
and Their Associated Cubicles
IN-93090
Unisolatable Reactor Coolant System Leak Following Repeated
Applications of Leak Sealant
IN-93088
Status of Motor-Operated Valve Performance Prediction Program by
the Electric Power Research Institute
IN-93089
Potential Problems With BWR Level Instrumentation Backfill
Modifications
IN-93087
Fuse Problems With Westinghouse 7300 Printed Circuit Cards
IN-93086
Identification of Isotopes in the Production and Shipment of
Byproduct Material at Non-Power Reactors
IN-93085r1
Problems with X-Relays in DB- and DHB-Type Circuit Breakers
Manufactured by Westinghouse – Revision 1
IN-93085
Problems with X-Relays in DB- and DHB-Type Circuit Breakers
Manufactured by Westinghouse
IN-93084
Determination of Westinghouse Reactor Coolant Pump Seal Failure
IN-93060s1
Reporting Fuel Cycle and Materials Events to the NRC Operations
Center – Supplement 1
IN-93081
Implementation of Engineering Expertise on Shift
IN-93082
Recent Fuel and Core Performance Problems in Operating Reactors
IN-93080
Implementation of the Revised 10 CFR Part 20
IN-93083
Potential Loss of Spent Fuel Pool Cooling Following a Loss of
Coolant Accident (LOCA)
IN-93077
Human Errors That Result in Inadvertent Transfers of Special
Nuclear Material at Fuel Cycle Facilities
IN-93078
Inoperable Safety Systems at a Non-Power Reactor
IN-93079
Core Shroud Cracking at Beltline Region Welds in Boiling-Water
Reactors
IN-93076
Inadequate Control of Paint and Cleaners For Safety-Related
Equipment
IN-93075
Spurious Tripping of Low-Voltage Power Circuit Breakers With GE
RMS-9 Digital Trip Units
IN-93074
High Temperatures Reduce Limitorque AC Motor Operator Torque
IN-93073
Criminal Prosecution of Nuclear Suppliers For Wrongdoing
IN-93072
Observations From Recent Shutdown Risk and Outage Management
Pilot Team Inspections
IN-93071
Fire At Chernobyl Unit 2
IN-93070
Degradation of Boraflex Neutron Absorber Coupons
IN-93069
Radiographic Events At Operating Power Reactors
IN-93068
Failure of Pump Shaft Coupling Caused By Temper Embrittlement
During Manufacture
IN-93083s1
Potential Loss of Spent Fuel Pool Cooling Following a Loss of
Coolant Accident – Supplement 1
IN-93067
Bursting of High Pressure Coolant Injection Steam Line Rupture
Discs Injures Plant Personnel
IN-93066
Switchover to Hot-Leg Injection Following a Loss-Of-Coolant
Accident in Pressurized Water Reactors
IN-93065
Reactor Trips Caused By Breaker Testing With Fault Protection
Bypassed
IN-93064
Periodic Testing and Preventative Maintenance of Molded Case
Circuit Breakers
IN-93063
Improper Use of Soluble Weld Purge Dam Material
IN-93062
Thermal Stratification of Water in BWR Reactor Vessels
IN-93061
Excessive Reactor Coolant Leakage Following a Seal Failure in a
Reactor Coolant Pump or Reactor Recirculation Pump
IN-93060
Reporting Fuel Cycle and Materials Events to the NRC Operations
Center
IN-93059
Unexpected Opening of Both Doors in an Airlock
IN-93058
Nonconservatism in Low-Temperature Overpressure Protection For
Pressurized-Water Reactors
IN-93057
Software Problems Involving Digital Control Console Systems at
Non-Nuclear Reactors
IN-93056
Weakness in Emergency Operating Procedures Found as Result of
Steam Generator Tube Rupture
IN-93055
Potential Problem With Main Steamline Break Analysis for Main
Steam Vaults/Tunnels
IN-93054
Motor-Operated Valve Actuator Thrust Variations Measured With a
Torque Thrust Cell and a Strain Gage
IN-93053
Effect of Hurricane Andrew on Turkey Point Nuclear Generating
Station and Lessons Learned
IN-93052
Draft NUREG-1477, "Voltage-Based Interim Plugging Criteria For
Steam Generator Tubes"
IN-93051
Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater
Pumps
IN-93050
Extended Storage of Sealed Sources
IN-93049
Improper Integration of Software Into Operating Practices
IN-93048
Failure of Turbine-Driven Main Feedwater Pump To Trip Because of
Contaminated Oil
IN-93047
Unrecognized Loss of Control Room Annunciators
IN-93045
Degradation of Shutdown Cooling System Performance
IN-93044
Operational Challenges During a Dual-Unit Transient
IN-93046
Potential Problem With Westinghouse Rod Control System &
Inadvertent Withdrawal of a Single Rod Control Cluster Assembly
IN-93043
Use of Inappropriate Lubrication Oils in Safety-Related Applications
IN-93042
Failure of Anti-Rotation Keys in Motor-Operated Valves
Manufactured by Velan
IN-93041
One Hour Fire Endurance Test Results For ... Kaowool, ... FS-195,
and ... Interam E-50 Fire Fire Barrier Systems
IN-93040
Fire Endurance Test Results for Thermal Ceramics FP-60 Fire
Barrier Material
IN-93039
Radiation Beams From Power Reactor Biological Shields
IN-93038
Inadequate Testing of Engineered Safety Features Actuation
Systems
IN-93037
Eyebolts With Indeterminate Properties Installed in Limitorque Valve
Operator Housing Covers
IN-93036
Notifications, Reports, and Records of Misadministrations
IN-93035
Insights From Common-Cause Failure Events
IN-93034s1
Potential for Loss of Emergency Cooling Function Due to a
Combination of Operational and Post-LOCA Debris in Containment –
Supplement 1
IN-93053s1
Effect of Hurricane Andrew on Turkey Point Nuclear Generating
Station and Lessons Learned – Supplement 1
IN-93033
Potential Deficiency of Certain Class 1E Instrumentation and Control
Cables
IN-93034
Potential For Loss of Emergency Cooling Function Due to a
Combination of Operational and Post-LOCA Debris in Containment
IN-93032
Nonconservative Inputs for Boron Dilution Event Analysis
IN-93031
Training of Nurses Responsible for the Care of Patients With
Brachytherapy Implants
IN-93030
NRC Requirements for Evaluation of Wipe Test Results; Calibration
of Count Rate Survey Instruments
IN-93029
Problems With the Use of Unshielded Test Leads in Reactor
Protection System Circuitry
IN-93028
Failure to Consider Loss of DC Bus in the Emergency Core Cooling
System Evaluation May Lead to Nonconservative Analysis
IN-93027
Level Instrumentation Inaccuracies Observed During Normal Plant
Depressurization
IN-93026
Grease Solidification Causes Molded Case Circuit Breaker Failure to
Close
IN-93025
Electrical Penetration Assembly Degradation
IN-93023
Weschler Instruments Model 252 Switchboard Meters
IN-93024
Distribution of Revision 7 of NUREG-1021, "Operator Licensing
Examiner Standards"
IN-93022
Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to
Support Lever Failure
IN-93021
Summary of ... Observations Compiled During Engineering Audits or
Inspections of Licensee Erosion/Corrosion Programs
IN-93017r1
Safety Systems Response to Loss of Coolant and Loss of Offsite
Power – Revision 1
IN-93020
Thermal Fatigue Cracking of Feedwater Piping to Steam Generators
IN-93019
Slab Hopper Bulging
IN-93018
Portable Moisture-Density Gauge User Responsibilities During Field
Operations
IN-93017
Safety Systems Response to Loss of Coolant and Loss of Offsite
Power
IN-93016
Failures of Nut-Locking Devices in Check Valves
IN-93014
Clarification of 10 CFR 40.22, Small Quantities of Source Material
IN-93015
Failure to Verify the Continuity of Shunt Trip Attachment Contacts in
Manual Safety Injection and Reactor Trip Switches
IN-93013
Undetected Modification of Flow Characteristics in the High Pressure
Safety Injection System
IN-93012
Off-Gassing in Auxiliary Feedwater System Raw Water Sources
IN-93011
Single Failure Vulnerability of Engineered Safety Features Actuation
Systems
IN-93010
Dose Calibrator Quality Control
IN-93009
Failure of Undervoltage Trip Attachment on Westinghouse Model
DB-50 Reactor Trip Breaker
IN-93008
Failure of Residual Heat Removal Pump Bearings Due to High
Thrust Loading
IN-93007
Classification of Transportation Emergencies
IN-93026s1
Grease Solidification Causes Molded-Case Circuit Breaker Failure to
Close – Supplement 1
IN-93006
Potential Bypass Leakage Paths Around Filters Installed in
Ventilation Systems
IN-93005
Locking of Radiography Exposure Devices
IN-93004
Investigation and Reporting of Misadministrations by the Radiation
Safety Officer
IN-93003
Recent Revisions to 10 CFR Part 20 and Change of Implementation
Date to January 1, 1994
IN-93002
Malfunction of a Pressurizer Code Safety Valve
IN-93001
Accuracy of Motor-Operated Valve Diagnostic Equipment
Manufactured by Liberty Technologies
IN-92027s1
Thermally Induced Accelerated Aging and Failure of ITE/GOULD
A.C. Relays Used in Safety-Related Applications – Supplement 1
IN-92068s1
Potentially Substandard Slip-On Welding Neck, and Blind Flanges –
Supplement 1
IN-92051s1
Misapplication and Inadequate Testing of Molded- Case Circuit
Breakers – Supplement 1
IN-92036s1
Intersystem LOCA Outside Containment – Supplement 1
IN-92016s2
Loss of Flow From the Residual Heat Removal Pump During
Refueling Cavity Draindown – Supplement 1
IN-92006s1
Reliability of ATWS Mitigation Systems and Other NRC-Required
Equipment Not Controlled by Plant Technical Specifications –
Supplement 1
IN-92086
Unexpected Restriction to Thermal Growth of Reactor Coolant Piping
IN-92085
Potential Failures of Emergency Core Cooling Systems Caused By
Foreign Material Blockage
IN-92084
Release of Patients Treated With Temporary Implants
IN-92083
Thrust Limits For Limitorque Actuators and Potential Overstressing
of Motor-Operated Valves
IN-92082
Results of Thermo-Lag 330-1 Combustibility Testing
IN-92081
Potential Deficiency of Electrical Cables With Bonded Hypalon
Jackets
IN-92080
Operation With Steam Generator Tubes Seriously Degraded
IN-92079
Non-Power Reactor Emergency Event Response
IN-92078
Piston to Cylinder Liner Tin Smearing on Cooper-Bessemer KSV
Diesel Engines
IN-92077
Questionable Selection and Review to Determine Suitability of
Electropneumatic Relays For Certain Applications
IN-92076
Supp 1 to NUREG-1358, "Lessons Learned ... Inspection Program
For Emergency Operating Procedures (10/88 - 9/91)"
IN-92075
Unplanned Intakes of Airborne Radioactive Material By Individuals at
Nuclear Power Plants
IN-92074
Power Oscillations at Washington Nuclear Power Unit 2
IN-92061s1
Loss of High Head Safety Injection – Supplement 1
IN-92073
Removal of a Fuel Element From a Research Reactor Core While
Critical
IN-92059r1
Horizontally-Installed Motor-Operated Gate Valves – Revision 1
IN-92072
Employee Training and Shipper Registration Requirements for
Transporting Radioactive Materials
IN-92071
Partial Plugging of Suppression Pool Strainers at a Foreign BWR
IN-92070
Westinghouse Motor-Operated Valve Performance Data Supplied to
Nuclear Power Plant Licensees
IN-92069
Water Leakage From Yard Area Through Conduits Into Buildings
IN-92068
Potentially Substandard Slip-On, Welding Neck, and Blind Flanges
IN-92067
Deficiency in Design Modifications to Address Failures of Hiller
Actuators Upon a Gradual Loss of Air Pressure
IN-92065
Safety System Problems Caused By Modifications That Were Not
Adequately Reviewed and Tested
IN-92066
Access Denied to NRC Inspectors at Five Star Products, Inc. and
Construction Products Research, Fairfield, Connecticut
IN-92064
Nozzle Ring Settings in Low Pressure Water-Relief Valves
IN-92063
Cracked Insulators in ASL Dry Type Transformers Manufactured By
Westinghouse Electric Corporation
IN-92062
Emergency Response Information Requirements for Radioactive
Material Shipments
IN-92060
Valve Stem Failure Caused by Embrittlement
IN-92061
Loss of High Head Safety Injection
IN-92059
Horizontally-Installed Motor-Operated Gate Valves
IN-92058
Uranium Hexafluoride Cylinders - Deviations in Coupling Welds
IN-92057
Radial Cracking of Shroud Support Access Hole Cover Welds
IN-92056
Counterfeit Valves in the Commercial Grade Supply System
IN-92053
Potential Failure of Emergency Diesel Generators Due to Excessive
Rate of Loading
IN-92055
Current Fire Endurance Test Results For Thermo-Lag Fire Barrier
Material
IN-92054
Level Instrumentation Inaccuracies Caused by Rapid
Depressurization
IN-92052
Barriers and Seals Between Mild and Harsh Environments
IN-92051
Misapplication and Inadequate Testing of Molded-Case Circuit
Breakers
IN-92050
Cracking of Valves in the Condensate Return Lines of a BWR
Emergency Condenser System
IN-92048
Failure of Exide Batteries
IN-92049
Recent Loss or Severe Degradation of Service Water Systems
IN-92047
Intentional Bypassing of Automatic Actuation of Plant Protective
Features
IN-92046
Thermo-Lag Fire Barrier ... Review Team ... Findings, Current Fire
Endurance Tests, and Ampacity Calculation Errors
IN-92045
Incorrect Relay Used in Emergency Diesel Generator Output
Breaker Control Circuitry
IN-92044
Problems With Westinghouse DS-206 and DSL-206 Type Circuit
Breakers
IN-92043
Defective Molded Phenolic Armature Carriers Found on Elmwood
Contactors
IN-92042
Fraudulent Bolts in Seismically Designed Walls
IN-92041
Consideration of the Stem Rejection Load in Calculation of Required
Valve Thrust
IN-92040
Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry
IN-92039
Unplanned Return to Criticality During Reactor Shutdown
IN-92038
Implementation Date ... Revision ... EPA Manual of Protective Action
Guides and Protective Actions for Nuclear Incidents
IN-92037
Implementation of the Deliberate Misconduct Rule
IN-92036
Intersystem LOCA Outside Containment
IN-92016s1
Loss of Flow From the Residual Heat Removal Pump During
Refueling Cavity Draindown – Supplement 1
IN-92035
Higher ... Erosion/Corrosion in Unisolable Reactor Coolant Pressure
Boundary Piping Inside Containment at a BWR
IN-92034
New Exposures Limits for Airborne Uranium and Thorium
IN-92033
Increased Instrument Response Time When Pressure Dampening
Devices are Installed
IN-92032
Problems ... Emergency Ventilation Systems for Near-Site ...
Emergency Operations Facilities & Technical Support Centers
IN-92031
Electrical Connection Problem in Johnson Yokogawa Corporation
YS-80 Programmable Indicating Controllers
IN-92030
Falsification of Plant Records
IN-92021s1
Spent Fuel Pool Reactivity Calculations – Supplement 1
IN-92029
Potential Breaker Miscoordination Caused by Instantaneous Trip
Circuitry
IN-92028
Inadequate Fire Suppression System Testing
IN-92027
Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C.
Relays Used in Safety-Related Applications
IN-92026
Pressure Locking of Motor-Operated Flexible Wedge Gate Valves
IN-92025
Potential Weakness in Licensee Procedures for a Loss of the
Refueling Cavity Water
IN-92024
Distributor Modification to Certain Commercial-Grade Agastat
Electrical Relays
IN-92023
Results of Validation Testing of Motor-Operated Valve Diagnostic
Equipment
IN-92022
Criminal Prosecution and Conviction of Wrongdoing Committed by a
Commercial-Grade Valve Supplier
IN-92021
Spent Fuel Pool Reactivity Calculations
IN-92020
Inadequate Local Leak Rate Testing
IN-92019
Misapplication of Potter & Brumfield MDR Rotary Relays
IN-92018
Potential for Loss of Remote Shutdown Capability During a Control
Room Fire
IN-92017
NRC Inspections of Programs Being Developed at Nuclear Power
Plants in Response to Generic Letter 89-10
IN-92016
Loss of Flow From the Residual Heat Removal Pump During
Refueling Cavity Draindown
IN-92015
Failure of Primary Compression Fitting
IN-92014
Uranium Oxide Fires at Fuel Cycle Facilities
IN-92013
Inadequate Control Over Vehicular Traffic at Nuclear Power Plant
Sites
IN-92012
Effects of Cable Leakage Currents on Instrument Settings and
Indications
IN-92011
Soil and Water Contamination at Fuel Cycle Facilities
IN-92010
Brachytherapy Incidents Involving Iridium-192 Wire Used in
Endobronchial Treatments
IN-92009
Overloading and Subsequent Lock Out of Electrical Buses During
Accident Conditions
IN-92008
Revised Protective Action Guidance for Nuclear Incidents
IN-92007
Rapid Flow-Induced Erosion/Corrosion of Feedwater Piping
IN-92006
Reliability of ATWS Mitigation System and Other NRC Required
Equipment Not Controlled by Plant Technical Specifications
IN-92005
Potential Coil Insulation Breakdown in ABB RXMH2 Relays
IN-92004
Potter & Brumfield Model MDR Rotary Relay Failures
IN-92003
Remote Trip Function Failures in General Electric F-Frame MoldedCase Circuit Breakers
IN-92002
RELAP5/MOD3 Computer Code Error Associated With the
Conservation of Energy Equation
IN-92001
Cable Damage Caused by Inadequate Cable Installation Procedures
and Controls
IN-91050s1
Water Hammer Events Since 1991 – Supplement 1
IN-91085r1
Potential Failures of Thermostatic Control Valves for Diesel
Generator Jacket Cooling Water – Revision 1
IN-91029s3
Deficiencies Identified During Electrical Distribution System
Functional Inspections – Supplement 3
IN-91029s2
Potential Deficiencies Found During Electrical Distribution System
Functional Inspections – Supplement 2
IN-91079s1
Deficiencies Found in Thermo-Lag Fire Barrier Installation –
Supplement 1
IN-91045s1
Possible Malfunction of Westinghouse ARD, BFD, and NBFD
Relays, and A200 DC and DPC 250 Magnetic Contactors –
Supplement 1
IN-91081s1
Switchyard Problems that Contribute to Loss of Offsite Power –
Supplement 1
IN-91021s1
Inadequate Quality Assurance Program of Vendor Supplying SafetyRelated Equipment – Supplement 1
IN-91064s1
Site Area Emergency Resulting from a Loss of Non-Class 1E
Uninterruptable Power Supplies – Supplement 1
IN-91029s1
Deficiencies Identified During Electrical Distribution System
Functional Inspections – Supplement 1
IN-91052s1
Nonconservative Errors in Overtemperature Delta-Temperature
(OTdT) Setpoint Caused by Improper Gain Setting – Supplement 1
IN-91087
Hydrogen Embrittlement of Raychem Cryofit Couplings
IN-91086
New Reporting Requirements for Contamination Events at Medical
Facilities (10 CFR 30.50)
IN-91085
Potential Failures of Thermostatic Control Valves for Diesel
Generator Jacket Cooling Water
IN-91084
Problems with Criticality Alarm Components/Systems
IN-91083
Solenoid-Operated Valve Failures Resulted in Turbine Overspeed
IN-91018s1
High-Energy Piping Failures Caused by Wall Thinning – Supplement
1
IN-91082
Problems with Diaphragms in Safety-Related Tanks
IN-91081
Switchyard Problems that Contribute to Loss of Offsite Power
IN-91080
Failure of Anchor Head Threads on Post-Tensioning System During
Surveillance Inspection
IN-91079
Deficiencies in the Procedures for Installing Thermo-Lag Fire Barrier
Materials
IN-91078
Status Indication of Control Power for Circuit Breakers Used in
Safety-Related Applications
IN-91077
Shift Staffing at Nuclear Power Plants
IN-91076
10 CFR Parts 21 and 50.55(e) Final Rules
IN-91075
Static Head Corrections Mistakenly Not Included in Pressure
Transmitter Calibration Procedures
IN-91074
Changes in Pressurizer Safety Valve Setpoints Before Installation
IN-91073
Loss of Shutdown Cooling During Disassembly of High Pressure
Safety Injection System Check Valve
IN-91072
Issuance of a Revision to the EPA Manual of Protective Action
Guides and Protective Actions for Nuclear Incidents
IN-91071
Training and Supervision of Individuals Supervised by an Authorized
User
IN-91070
Improper Installation of Instrumentation Modules
IN-91069
Errors in Main Steam Line Break Analyses for Determining
Containment Parameters
IN-91068
Careful Planning Significantly Reduces the Potential Adverse
Impacts of Loss of Offsite Power Events During Shutdown
IN-91067
Problems with the Reliable Detection of Intergranular Attack (IGA) of
Steam Generator Tubing
IN-91066
(1) Erroneous Data in ... NUREG/CR-0095 and (2) Thermal
Scattering Data Limitation ... KENO and SCALE Codes
IN-91065
Emergency Access to Low-Level Radioactive Waste Disposal
Facilities
IN-91064
Site Area Emergency Resulting from a Loss of Non-Class 1E
Uninterruptible Power Supplies
IN-91063
Natural Gas Hazards at Fort St. Vrain Nuclear Generating Station
IN-91062
Diesel Engine Damage Caused by Hydraulic Lockup Resulting from
Fluid Leakage into Cylinders
IN-91061
Preliminary Results of Validation Testing of Motor-Operated Valve
Diagnostic Equipment
IN-91060
False Alarms of Alarm Ratemeters Because of Radiofrequency
Interference
IN-91059
Problems with Access Authorization Programs
IN-91058
Dependency of Offset Disc Butterfly Valve's Operation on Orientation
with Respect to Flow
IN-91057
Operational Experience on Bus Transfers
IN-91056
Potential Radioactive Leakage to Tank Vented to Atmosphere
IN-91055
Failures Caused by an Improperly Adjusted Test Link in 4.16 KV
General Electric Switchgear
IN-91054
Foreign Experience Regarding Boron Dilution
IN-91053
Failure of Remote Shutdown System Instrumentation Because of
Incorrectly Installed Components
IN-91052
Nonconservative Errors in Overtemperature Delta-Temperature
(OTdT) Setpoint Caused by Improper Gain Settings
IN-91051
Inadequate Fuse Control Programs
IN-91050
A Review of Water Hammer Events After 1985
IN-91049
Enforcement of Safety Requirements for Radiographers
IN-91048
False Certificates of Conformance Provided by Westinghouse
Electric Supply Company for Commercial-Grade Circuit Breakers
IN-91047
Failure of Thermo-Lag Fire Barrier Material to Pass Fire Endurance
Test
IN-91046
Degradation of Emergency Diesel Generator Fuel Oil Delivery
Systems
IN-91043
Recent Incidents Involving Rapid Increases in Primary-to-Secondary
Leak Rate
IN-91044
Improper Control of Chemicals in Nuclear Fuel Fabrication
IN-91045
Possible Malfunction of Westinghouse ARD, BFD, and NBFD
Relays, and A200 DC and DPC 250 Magnetic Contactors
IN-91042
Plant Outage Events Involving Poor Coordination Between
Operations and Maintenance Personnel During Valve Testing and
Manipulations
IN-91041
Potential Problems with the Use of Freeze Seals
IN-91040
Contamination of Nonradioactive System and Resulting Possibility
for Unmonitored, Uncontrolled Release to Environment
IN-91039
Compliance with 10 CFR Part 21, "Reporting of Defects and
Noncompliance"
IN-91038
Thermal Stratification in Feedwater System Piping
IN-91037
Compressed Gas Cylinder Missile Hazards
IN-91036
Nuclear Plant Staff Working Hours
IN-91035
Labeling Requirements for Transporting Multi-Hazard Radioactive
Materials
IN-91034
Potential Problems in Identifying Causes of Emergency Diesel
Generator Malfunctions
IN-91033
Reactor Safety Information for States During Exercises and
Emergencies
IN-91032
Possible Flaws in Certain Piping Systems Fabricated by Associated
Piping and Engineering
IN-91031
Nonconforming Magnaflux Magnetic Particle (14AM) Prepared Bath
IN-91030
Inadequate Calibration of TLDs Utilized to Monitor Extremity Dose at
Uranium Processing and Fabrication Facilities
IN-91029
Deficiencies Identified During Electrical Distribution System
Functional Inspections
IN-91028
Cracking in Feedwater System Piping
IN-91027
Incorrect Rotation of Positive Displacement Pump
IN-91026
Potential Nonconservative Errors ... Working Format Hansen-Roach
Cross-Section Set Provided with the KENO and SCALE Codes
IN-91025
Commercial-Grade Structural Framing Components Supplied as
Nuclear Safety-Related Equipment
IN-91024
Recent Operating Experience Involving Reactor Operation Without a
Licensed RO or SRO Present in the Control Room
IN-91023
Accidental Radiation Overexposures to Personnel Due to Industrial
Radiography Accessory Equipment Malfunctions
IN-91022
Four Plant Outage Events Involving Loss of AC Power or Coolant
Spills
IN-91021
Inadequate Quality Assurance Program of Vendor Supplying SafetyRelated Equipment
IN-91021
Inadequate Quality Assurance Program of Vendor Supplying SafetyRelated Equipment
IN-91020
Electrical Wire Insulation Degradation Caused Failure in a Safety-
Related Motor Control Center
IN-91021
Inadequate Quality Assurance Program of Vendor Supplying SafetyRelated Equipment
IN-91019
Steam Generator Feedwater Distribution Piping Damage
IN-91018
High-Energy Piping Failures Caused by Wall Thinning
IN-91017
Fire Safety of Temporary Installations or Services
IN-91016
Unmonitored Release Pathways from Slightly Contaminated Recycle
and Recirculation Water Systems at a Fuel Facility
IN-91015
Incorrect Configuration of Breaker Operating Springs in General
Electric AK-Series Metal-Clad Circuit Breakers
IN-91014
Recent Safety-Related Incidents at Large Irradiators
IN-91013
Inadequate Testing of Emergency Diesel Generators (EDGs)
IN-91011
Inadequate Physical Separation and Electrical Isolation of NonSafety-Related Circuits From RPS Circuits
IN-91012
Potential Loss of Net Positive Suction Head (NPSH) of Standby
Liquid Control System Pumps
IN-91010
Summary of Semiannual Program Performance Reports on Fitnessfor-Duty (FFD) in the Nuclear Industry
IN-91009,
rev. 1
Counterfeiting of Crane Valves
IN-91009
See IN-91009, rev 1
IN-91008
Medical Examination for Licensed Operators
IN-91007
Maintenance Deficiency Associated with General Electric Horizontal
Custom 8000 Induction Motors
IN-91006
Lock-Up of Emergency Diesel Generator and Load Sequencer
Control Circuits Preventing Restart of Tripped EDG
IN-91005
Intergranular Stress Corrosion Cracking in Pressurized Water
Reactor Safety Injection Accumulator Nozzles
IN-91004
Reactor Scram Following Control Rod Withdrawal Associated with
Low Power Turbine Testing
IN-91003
Management of Wastes Contaminated with Radioactive Materials
("Red Bag" Waste and Ordinary Trash)
IN-91002
Brachytherapy Source Management
IN-91001
Supplier of Misrepresented Resistors
IN-90068s1
Stress Corrosion Cracking of Reactor Coolant Pump Bolts –
Supplement 1
IN-90057s1
Substandard, Refurbished Potter & Brumfield Relays Represented
as New – Supplement 1
IN-90051s1
Failures of Voltage-Dropping Resistors in the Power Supply Circuitry
of Electric Governor Systems – Supplement 1
IN-90043s1
Mechanical Interference with Thermal Trip Function in GE MoldedCase Circuit Breakers – Supplement 1
IN-90025s1
Loss of Vital AC Power with Subsequent Reactor Coolant System
Heat-Up – Supplement 1
IN-90077s1
Inadvertent Removal of Fuel Assemblies from the Reactor Core –
Supplement 1
IN-90082
Requirements for Use of NRC-Approved Packages for Shipment of
Type A Quantities of Radioactive Material
IN-90081
Fitness for Duty
IN-90080
Sand Intrusion Resulting in Two Diesel Generators Becoming
Inoperable
IN-90079
Failures of Main Steam Isolation Check Valves Resulting in Disc
Separation
IN-90078
Previously Unidentified Release Path from Boiling Water Reactor
Control Rod Hydraulic Units
IN-90077
Inadvertent Removal of Fuel Assemblies from the Reactor Core
IN-90076
Failure of Turbine Overspeed Trip Mechanism Because of
Inadequate Spring Tension
IN-90075
Denial of Access to Current Low-Level Radioactive Waste Disposal
Facilities
IN-90074
Information on Precursors to Severe Accidents
IN-90073
Corrosion of Valve-to-Torque Tube Keys in Spray Pond Cross
Connect Valves
IN-90072
Testing of Parallel Disc Gate Valves in Europe
IN-90071
Effective Use of Radiation Safety Committees to Exercise Control
over Medical Use Programs
IN-90038s1
License and Fee Requirements for Processing Financial Assurance
Submittals for Decommissioning – Supplement 1
IN-90070
Pump Explosions Involving Ammonium Nitrate
IN-90069
Adequacy of Emergency and Essential Lighting
IN-90068
Stress Corrosion Cracking of Reactor Coolant Pump Bolts
IN-90067
Potential Security Equipment Weaknesses
IN-90066
Incomplete Draining and Drying of Shipping Casks
IN-90065
Recent Orifice Plate Problems
IN-90064
Potential for Common-Mode Failure of HPSI Pumps or Release of
Reactor Coolant Outside Containment During a LOCA
IN-90063
Management Attention to the Establishment and Maintenance of a
Nuclear Criticality Safety Program
IN-90062
Requirements for Import and Distribution of Neutron-Irradiated Gems
IN-90061
Potential for Residual Heat Removal Pump Damage Caused by
Parallel Pump Interaction
IN-90060
Availability of Failure Data in the Government-Industry Data
Exchange Program
IN-90059
Errors in the Use of Radioactive Iodine-131
IN-90058
Improper Handling of Ophthalmic Strontium-90 Beta Radiation
Applicators
IN-90057
Substandard, Refurbished Potter & Brumfield Relays Misrepresented
as New
IN-90056
Inadvertent Shipment of a Radioactive Source in a Container
Thought to Be Empty
IN-90055
Recent Operating Experience on Loss of Reactor Coolant Inventory
While in a Shutdown Condition
IN-90054
Summary of Requalification Program Deficiencies
IN-90053
Potential Failures of Auxiliary Steam Piping and the Possible Effects
on the Operability of Vital Equipment
IN-90052
Retention of Broken Charpy Specimens
IN-90051
Failures of Voltage-Dropping Resistors in the Power Supply Circuitry
of Electric Governor Systems
IN-90050
Minimization of Methane Gas in Plant Systems and Radwaste
Shipping Containers
IN-90049
Stress Corrosion Cracking in PWR Steam Generator Tubes
IN-90048
Enforcement Policy for Hot Particle Exposures
IN-90047
Unplanned Radiation Exposures to Personnel Extremities Due to
Improper Handling of Potentially Highly Radioactive Source
IN-90046
Criminal Prosecution of Wrongdoing Committed by Suppliers of
Molded-Case Circuit Breakers and Related Components
IN-90045
Overspeed of the Turbine-Driven Auxiliary Feedwater Pumps and
Overpressurization of the Associated Piping System
IN-90044
Dose-Rate Instruments Underresponding to the True Radiation
Fields
IN-90043
Mechanical Interference with Thermal Trip Function in GE MoldedCase Circuit Breakers
IN-90042
Failure of Electrical Power Equipment Due to Solar Magnetic
Disturbances
IN-90032s1
Surface Crack and Subsurface Indications in the Weld of a Reactor
Vessel Head – Supplement 1
IN-90041
Potential Failure of General Electric Magne-Blast Circuit Breakers
and AK Circuit Breakers
IN-90040
Results of NRC-Sponsored Testing of Motor-Operated Valves
IN-90039
Recent Problems with Service Water Systems
IN-90038
Requirements for Processing Financial Assurance Submittals for
Decommissioning
IN-90037
Sheared Pinion Gear-to-Shaft Keys in Limitorque Motor Actuators
IN-90036
Apparent Falsification of State of Connecticut Weight Certificates
IN-90035
Transportation of Type A Quantities of Non-Fissile Radioactive
Materials
IN-90034
Response to False Siren Activations
IN-90033
Sources of Unexpected Occupational Radiation Exposures at Spent
Fuel Storage Pools
IN-90032
Surface Crack and Subsurface Indications in the Weld of a Reactor
Vessel Head
IN-90031
Update on Waste Form and High Integrity Container ... Review
Status, Identification of Problems with Cement Solidification ... Waste
Mishaps
IN-90030
Ultrasonic Inspection Techniques for Dissimilar Metal Welds
IN-90029
Cracking of Cladding and its Heat-Affected Zone in the Base Metal of
a Reactor Vessel Head
IN-90028
Potential Error in High Steamline Flow Setpoint
IN-90027
Clarification of ... Regulatory Requirements for Packaging of
Uranium Hexafluoride (UF6) for Transportation
IN-90026
Inadequate Flow of Essential Service Water to Room Coolers and
Heat Exchangers for Engineered Safety-Feature Systems
IN-90025
Loss of Vital AC Power with Subsequent Reactor Coolant System
Heat-Up
IN-90024
Transportation of Model SPEC 2-T Radiographic Exposure Device
IN-90023
Improper Installation of Patel Conduit Seals
IN-90022
Unanticipated Equipment Actuations Following Restoration of Power
to Rosemount Transmitter Trip Units
IN-90020
Personnel Injuries Resulting from Improper Operation of Radwaste
Incinerators
IN-90021
Potential Failure of Motor-Operated Butterfly Valves to Operate
Because Valve Seat Friction Was Underestimated
IN-90019
Potential Loss of Effective Volume for Containment Recirculation
Spray at PWR Facilities
IN-90018
Potential Problems with Crosby Safety Relief Valves Used on Diesel
Generator Air Start Receiver Tanks
IN-90017
Weight and Center of Gravity Discrepancies for Copes-Vulcan
Valves
IN-90016
Compliance with New Decommissioning Rule
IN-90015
Reciprocity: Notification of Agreement State Radiation Control
Directors Before Beginning Work in Agreement States
IN-90014
Accidental Disposal of Radioactive Materials
IN-90013
Importance of Review and Analysis of Safeguards Event Logs
IN-90012
Monitoring or Interruption of Plant Communications
IN-90011
Maintenance Deficiency Associated with Solenoid-Operated Valves
IN-90010
Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600
IN-90009
Extended Interim Storage of Low-Level Radioactive Waste by Fuel
Cycle and Materials Licensees
IN-90008
KR-85 Hazards from Decayed Fuel
IN-90007
New Information Regarding Insulation Material Performance and
Debris Blockage of PWR Containment Sumps
IN-90006
Potential for Loss of Shutdown Cooling While at Low Reactor
Coolant Levels
IN-90005
Inter-System Discharge of Reactor Coolant
IN-90004
Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam
Generators
IN-90003
Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by
Failure of the Swing Arm
IN-90002
Potential Degradation of Secondary Containment
IN-90001
Importance of Proper Response to Self-Identified Violations by
Licensees
IN-8969s1
Shadow Corrosion Resulting in Fuel Channel Bowing – Supplement
1
IN-89025r1
Unauthorized Transfer of Ownership or Control of Licensed Activities
– Revision 1
IN-89077s1
Debris in Containment Emergency Sumps and Incorrect Screen
Configurations – Supplement 1
IN-89090s2
Pressurizer Safety Valve Lift Setpoint Shift – Supplement 2
IN-89056s2
Questionable Certification of Material Supplied to the Defense
Department by Nuclear Suppliers – Supplement 2
IN-89090s1
Pressurizer Safety Valve Lift Setpoint Shift – Supplement 1
IN-89032s1
Surveillance Testing on Low-Temperature Overpressure-Protection
Systems – Supplement 1
IN-89030s1
High Temperature Environments at Nuclear Power Plants –
Supplement 1
IN-89079s1
Degraded Coatings and Corrosion of Steel Containment Vessels –
Supplement 1
IN-89070s1
Possible Indications of Misrepresented Vendor Products –
Supplement 1
IN-89059s2
Suppliers of Potentially Misrepresented Fasteners – Supplement 2
IN-89090
Pressurizer Safety Valve Lift Setpoint Shift
IN-89089
Event Notification Worksheets
IN-89088
Recent NRC-Sponsored Testing of Motor-Operated Valves
IN-89087
Disabling of Emergency Diesel Generators by Their Neutral GroundFault Protection Circuitry
IN-89085
EPA's Interim Final Rule on Medical Waste Tracking and
Management
IN-89086
Type HK Circuit Breakers Missing Close Latch Anti-Shock Springs
IN-89045s2
Metalclad, Low-Voltage Power Circuit Breakers Refurbished with
Substandard Parts – Supplement 2
IN-89084
Failure of Ingersoll Rand Air Start Motors as a Result of Pinion Gear
Assembly Fitting Problems
IN-89083
Sustained Degraded Voltage on the Offsite Grid and Loss of Other
Generating Stations as a Result of a Plant Trip
IN-89082
Recent Safety-Related Incidents at Large Irradiators
IN-89081
Inadequate Control of Temporary Modifications to Safety-Related
Systems
IN-89059s1
Suppliers of Potentially Misrepresented Fasteners – Supplement 1
IN-89080
Potential for Water Hammer, Thermal Stratification, and Steam
Binding in High-Pressure Coolant Injection Piping
IN-89079
Degraded Coatings and Corrosion of Steel Containment Vessels
IN-89078
Failure of Packing Nuts on One-Inch Uranuim Hexafluoride Cylinder
Valves
IN-89056s1
Questionable Certification of Material Supplied to the Defense
Department by Nuclear Suppliers – Supplement 1
IN-89077
Debris in Containment Emergency Sumps and Incorrect Screen
Configurations
IN-89076
Biofouling Agent: Zebra Mussel
IN-89075
Falsification of Welder Qualifications for Contractor Employees
IN-89074
Clarification of Transportation Requirements Applicable to Return of
Spent Radiopharmacy Dosages from Users to Suppliers
IN-89073
Potental Overpressurization of Low Pressure Systems
IN-89072
Failure of Licensed Senior Operators to Classify Emergency Events
Properly
IN-89071
Diversion of the Residual Heat Removal Pump Seal Cooling Water
Flow During Recirculation Operation Following a LOCA
IN-89070
Possible Indications of Misrepresentated Vendor Products
IN-89069
Loss of Thermal Margin Caused by Channel Box Bow
IN-89068
Evaluation of Instrument Setpoints During Modifications
IN-89067
Loss of Residual Heat Removal Caused by Accumulator Nitrogen
Injection
IN-89066
Qualification Life of Solenoid Valves
IN-89065
Potential for Stress Corrosion Cracking in Steam Generator Tube
Plugs Supplied by Babcock and Wilcox
IN-89064
Electrical Bus Bar Failures
IN-89063
Possible Submergence of Electrical Circuits Located Above the
Flood Level Because of Water Intrusion and Lack of Drainage
IN-89062
Malfunction of Borg-Warner Pressure Seal Bonnet Check Valves
Caused by Vertical Misalignment of Disk
IN-89061
Failure of Borg-Warner Gate Valves to Close Against Differential
Pressure
IN-89060
Maintenance of Teletherepy Units
IN-89059
Suppliers of Potentially Misrepresented Fasteners
IN-89058
Disablement of Turbine-Driven Auxiliary Feedwater Pump Due to
Closure of One of the Parrellel Steam Supply Valves
IN-89057
Unqualified Electrical Splices in Vendor-Supplied Environmentally
Qualified Equipment
IN-89056
Questionable Certification of Material Supplied to the Defense
Department by Nuclear Suppliers
IN-89045s1
Metalclad, Low-Voltage Power Circuit Breakers Refurbished with
Substandard Parts – Supplement 1
IN-89055
Degradation of Containment Isolation Capability by a High-Energy
Line Break
IN-89054
Potential Overpressurization of the Component Cooling Water
System
IN-89053
Rupture of Extraction Steam Line on High Pressure Turbine
IN-89052
Potential Fire Damper Operational Problems
IN-89051
Potential Loss of Required Shutdown Margin During Refueling
Operations
IN-89050
Inadequate Emergency Diesel Generator Fuel Supply
IN-89049
Failure to Close Service Water Cross-Connect Isolation Valves
IN-89048
Design Deficiency in the Turbine-Driven Auxiliary Feedwater Pump
Cooling Water System
IN-89047
Potential Problems with Worn or Distorted Hose Clamps on SelfContained Breathing Apparatus
IN-89046
Confidentiality of Exercise Scenarios
IN-89045
Metalclad, Low-Voltage Power Circuit Breakers Refurbished with
Substandard Parts
IN-89043
Permanent Deformation of Torque Switch Helical Springs in
Limitorque SMA-Type Motor Operators
IN-89044
Hydrogen Storage on the Roof of the Control Room
IN-89042
Failure of Rosemount Models 1153 and 1154 Transmitters
IN-89041
Operator Response to Pressurization of Low-Pressure Interfacing
Systems
IN-89040
Unsatisfactory Operator Test Results and Their Effect on the
Requalification Program
IN-89038
Atmospheric Dump Valve Failures at Palo Verde Units 1, 2, and 3
IN-89039
List of Parties Excluded from Federal Procurement or NonProcurement Programs
IN-89037
Proposed Amendments to 40 CFR Part 61, Air Emission Standards
for Radionuclides
IN-89036
Excessive Temperature in Emergency Core Cooling System Piping
Located Outside Containment
IN-89034
Disposal of Americium Well-Logging Sources
IN-89035
Loss and Theft of Unsecured Licensed Material
IN-89033
Potential Failure of Westinghouse Steam Generator Tube
Mechanical Plugs
IN-89032
Surveillance Testing of Low-Temperature Overpressure Protection
Systems
IN-89031
Swelling and Cracking of Hafnium Control Rods
IN-89030
High Temperature Environments at Nuclear Power Plants
IN-89029
Potential Failure of ASEA Brown Boveri Circuit Breakers During
Seismic Event
IN-89028
Weight and Center of Gravity Discrepancies for Copes-Vulcan AirOperated Valves
IN-89027
Limitations on the Use of Waste Forms and High Integrity Containers
for the Disposal of Low-Level Radioactive Waste
IN-89026
Instrument Air Supply to Safety-Related Equipment
IN-89025
Unauthorized Transfer of Ownership or Control of Licensed Activities
IN-89024
Nuclear Criticality Safety
IN-89023
Environmental Qualification of Litton-Veam CIR Series Electrical
Connectors
IN-89022
Questionable Certification of Fasteners
IN-89021
Changes in Performance Characteristics of Molded-Case Circuit
Breakers
IN-89020
Weld Failures in a Pump of Byron-Jackson Design
IN-89018s1
Criminal Prosecution of Wrongdoing Committed by Suppliers of
Nuclear Products or Services – Supplement 1
IN-89018
Criminal Prosecution of Wrongdoing Committed by Suppliers of
Nuclear Products or Services
IN-89017
Contamination and Degradation of Safety-Related Battery Cells
IN-89016
Excessive Voltage Drop in DC Systems
IN-89015
Second Reactor Coolant Pump Shaft Failure at Crystal River
IN-89014
Inadequate Dedication Process for Commercial-Grade Components
which Could Lead to Common Mode Failure of a Safety System
IN-89012
Dose Calibrator Quality Control
IN-89013
Alternate Waste Management Procedures in Case of Denial of
Access to Low-Level Waste Disposal Sites
IN-89011
Failure of DC Motor-Operated Valves to Develop Rated Torque
Because of Improper Cable Sizing
IN-89010
Undetected Installation Errors in Main Steam Line Tunnel Differential
Temperature-Sensing Elements at BWRs
IN-89009
Credit for Control Rods Without Scram Capability in the Calculation
of the Shutdown Margin
IN-89008
Pump Damage Caused by Low-Flow Operation
IN-89007
Failures of Small-Diameter Tubing in Control Air, Fuel Oil, and Lube
Oil Systems Render Emergency Diesels Inoperable
IN-89006
Bent Anchor Bolts in Boiling Water Reactor Torus Supports
IN-89005
Use of Deadly Force by Guards Protecting Nuclear Power Reactors
Against Radiological Sabatoge
IN-89004
Potential Problems from the Use of Space Heaters
IN-89003
Potential Electrical Equipment Problems
IN-89002
Criminal Prosecution of Licensee's Former President for Intentional
Safety Violations
IN-89001
Valve Body Erosion
IN-88023s5
NRC Information Notice 88-23, Supplement 5: Potential for Gas
Binding of High Pressure Safety Injection Pumps During a Loss-ofCoolant Accident – Supplement 5
IN-88064
Reporting Fires in Nuclear Process Systems at Nuclear Power
Plants
IN-88023s4
Potential for Gas Binding of High-Pressure Safety Injection Pumps
During a Design Basis Accident – Supplement 4
IN-88092s1
Potential for Spent Fuel Pool Draindown – Supplement 1
IN-88063s2
High Radiation Hazards From Irradiated Incore Detectors and
Cables – Supplement 2
IN-88023s3
Potential for Gas Binding of High-Pressure Safety Injection Pumps
During a Loss-Of-Coolant Accident – Supplement 3
IN-88063s1
High Radiation Hazards From Irradiated Incore Detectors and
Cables – Supplement 1
IN-88030s1
Target Rock Two-Stage SRV Setpoint Drift Update – Supplement 1
IN-88023s2
Potential for Gas Binding of High-Pressure Safety Injection Pumps
During a Loss-of-Coolant Accident – Supplement 2
IN-88046s4
Licensee Report of Defective Refurbished Circuit Breakers –
Supplement 4
IN-88048s2
Licensee Report of Defective Refurbished Valves – Supplement 2
IN-88082s1
Torus Shells with Corrosion and Degraded Coatings in BWR
Containments – Supplement 1
IN-88097s1
Potential Substandard Valve Replacement Parts – Supplement 1
IN-88075s1
Disabling of Diesel Generator Output Circuit Breakers by Anti-Pump
Circuitry – Supplement 1
IN-88086s1
Operating with Multiple Grounds in Direct Current Distribution
Systems – Supplement 1
IN-88073s1
Direction-Dependent Leak Characteristics of Containment Purge
Valves – Supplement 1
IN-88023s1
Potential for Gas Binding of High-Pressure Safety Injection Pumps
During a Loss-of-Coolant Accident – Supplement 1
IN-88046s2
Licensee Report of Defective Refurbished Circuit Breakers –
Supplement 2
IN-88101
Shipment of Contaminated Equipment Between Nuclear Power
Stations
IN-88100
Memorandum of Understanding Between NRC and OSHA Relating
to NRC-Licensed Facilities (53 FR 43950, October 31, 1988)
IN-88099
Detection and Monitoring of Sudden and/or Rapidly Increasing
Primary-to-Secondary Leakage
IN-88098
Electrical Relay Degradation Caused by Oxidation of Contact
Surfaces
IN-88097
Potentially Substandard Valve Replacement Parts
IN-88096
Electrical Shock Fatalities at Nuclear Power Plants
IN-88095
Inadequate Procurement Requirements Imposed by Licensees on
Vendors
IN-88094
Potentially Undersized Valve Actuators
IN-88093
Teletherapy Events
IN-88092
Potential for Spent Fuel Pool Draindown
IN-88091
Improper Administration and Control of Psychological Tests
IN-88090
Unauthorized Removal of Industrial Nuclear Gauges
IN-88089
Degradation of Kapton Electrical Insulation
IN-88088
Degradation of Westinghouse ARD Relays
IN-88087
Pump Wear and Foreign Objects in Plant Piping Systems
IN-88086
Operating with Multiple Grounds in Direct Current Distribution
Systems
IN-88084
Defective Motor Shaft Keys in Limitorque Motor Actuators
IN-88083
Inadequate Testing of Relay Contacts in Safety-Related Logic
Systems
IN-88085
Broken Retaining Block Studs on Anchor Darling Check Valves
IN-88082
Torus Shells with Corrosion and Degraded Coatings in BWR
Containments
IN-88081
Failure of AMP Window Indent KYNAR Splices and Thomas and
Betts Nylon Wire Caps During EQ Testing
IN-88080
Unexpected Piping Movement Attributed to Thermal Stratification
IN-88079
Misuse of Flashing Lights for High Radiation Area Controls
IN-88069s1
Movable Contact Finger Binding in HFA Relays Manufactured by
General Electric (GE) – Supplement 1
IN-88078
Implementation of Revised NRC-Administered Requalification
Examinations
IN-88077
Inadvertent Reactor Vessel Overfill
IN-88076
Recent Discovery of a Phenomenon Not Previously Considered in
the Design of Secondary Containment Pressure Control
IN-88075
Disabling of Diesel Generator Output Circuit Breakers by Anti-Pump
Circuitry
IN-88074
Potentially Inadequate Performance of ECCS in PWRs During
Recirculation Operation Following a LOCA
IN-88073
Direction-Dependent Leak Characteristics of Containment Purge
Valves
IN-88072
Inadequacies in the Design of DC Motor-Operated Valves
IN-88071
Possible Environ Effect of Reentry of COSMOS 1900 and Request
for Licensee Radioactivity Measurements
IN-88070
Check Valve Inservice Testing Program Deficiencies
IN-88048s1
Licensee Report of Defective Refurbished Valves – Supplement 1
IN-88068
Setpoint Testing of Pressurizer Safety Valves with Filled Loop Seals
Using Hydraulic Assist Devices
IN-88067
PWR Auxiliary Feedwater Pump Turbine Overspeed Trip Failure
IN-88066
Industrial Radiography Inspection and Enforcement
IN-88069
Movable Contact Finger Binding in HFA Relays Manufactured by
General Electric (GE)
IN-88065
Inadvertent Drainages of Spent Fuel Pools
IN-88063
High Radiation Hazards from Irradiated Incore Detectors and Cables
IN-88062
Recent Findings Concerning Implementation of Quality Assurance
Programs by Suppliers of Transport Packages
IN-88061
Control Room Habitability - Recent Reviews of Operating Experience
IN-88060
Inadequate Design and Installation of Watertight Penetration Seals
IN-88059
Main Steam Isolation Valve Guide Rail Failure at Waterford Unit 3
IN-88004s1
Inadequate Qualification and Documentation of Fire Barrier
Penetration Seals – Supplement 1
IN-88058
Potential Problems with ASEA Brown Boveri ITE-51L TimeOvercurrent Relays
IN-88057
Potential Loss of Safe Shutdown Equipment Due to Premature
Silicon Controlled Rectifier Failure
IN-88056
Potential Problems with Silicone Foam Fire Barrier Penetration Seals
IN-88055
Potential Problems Caused by Single Failure of an Engineered
Safety Feature Swing Bus
IN-88054
Failure of Circuit Breaker Following Installation of Amptector Direct
Trip Attachment
IN-88053
Licensee Violations of NRC Regulations, which Led to Medical
Diagnostic Misadministrations
IN-88052
Failure of Intrauterine Tandem of Fletcher Suit Applicator
Brachytherapy Devices During Patient Treatment
IN-88051
Failures of Main Steam Isolation Valves
IN-88050
Effect of Circuit Breaker Capacitance on Availability of Emergency
Power
IN-88049
Marking, Handling, Control, Storage and Destruction of Safeguards
Information
IN-88046s1
Licensee Report of Defective Refurbished Circuit Breakers –
Supplement 1
IN-88048
Licensee Report of Defective Refurbished Valves
IN-88047
Slower-than-Expected Rod-Drop Times
IN-88046
Licensee Report of Defective Refurbished Circuit Breakers
IN-88045
Problems in Protective Relay and Circuit Breaker Coordination
IN-88044
Mechanical Binding of Spring Release Device in Westinghouse Type
DS-416 Circuit Breakers
IN-88043
Solenoid Valve Problems
IN-88042
Circuit Breaker Failures Due to Loose Charging Spring Motor
Mounting Bolts
IN-88041
Physical Protection Weaknesses Identified Through Regulatory
Effectiveness Reviews (RERs)
IN-88040
Examiners' Handbook for Developing Operator Licensing
Examinations
IN-88039
LaSalle Unit 2 Loss of Recirculation Pumps with Power Oscillation
Event
IN-88038
Failure of Undervoltage Trip Attachment on General Electric Circuit
Breakers
IN-88037
Flow Blockage of Cooling Water to Safety System Components
IN-88036
Possible Sudden Loss of RCS Inventory During Low Coolant Level
Operation
IN-88046s3
Licensee Report of Defective Refurbished Circuit Breakers –
Supplement 3
IN-88035
Inadequate Licensee Performed Vendor Audits
IN-88088s1
Degradation of Westinghouse ARD Relays – Supplement 1
IN-88034
Nuclear Material Control and Accountability of Non-Fuel Special
Nuclear Material at Power Reactors
IN-88033
Recent Problems Involving the Model Spec 2-T Radiographic
Exposure Device
IN-88032
Prompt Reporting to NRC of Significant Incidents Involving
Radioactive Material
IN-88031
Steam Generator Tube Rupture Analysis Deficiency
IN-88030
Target Rock Two-Stage SRV Setpoint Drift Update
IN-88029
Deficiencies in Primary Containment Low-Voltage Electrical
Penetration Assemblies
IN-88028
Potential for Loss of Post-LOCA Recirculation Capability Due to
Insulation Debris Blockage
IN-88027
Deficient Electrical Terminations Identified in Safety-Related
Components
IN-88026
Falsified Pre-Employment Screening Records
IN-88025
Minimum Edge Distance for Expansion Anchor Bolts
IN-88024
Failures of Air-Operated Valves Affecting Safety-Related Systems
IN-88023
Potential for Gas Binding of High-Pressure Safety Injection Pumps
During a Loss-of-Coolant Accident
IN-88022
Disposal of Sludge from Onsite Sewage Treatment Facilities at
Nuclear Power Stations
IN-88021
Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear
Power Plants
IN-88020
Unauthorized Individuals Manipulating Controls and Performing
Control Room Activities
IN-88019
Questionable Certification of Class 1E Components
IN-88018
Malfunction of Lockbox on Radiography Device
IN-88017
Summary of Responses to NRC Bulletin 87-01, "Thinning of Pipe
Walls in Nuclear Power Plants"
IN-88016
Identifying Waste Generators in Shipments of Low-Level Waste to
Land Disposal Facilities
IN-88015
Availability of FDA-Approved Potassium Iodide for Use in
Emergencies Involving Radioactive Iodine
IN-88014
Potential Problems with Electrical Relays
IN-88013
Water Hammer and Possible Piping Damage Caused by
Misapplication of Kerotest Packless Metal Diaphragm Globe Valves
IN-88012
Overgreasing of Electric Motor Bearings
IN-88011
Potential Loss of Motor Control Center and/or Switchboard Function
Due to Faulty Tie Bolts
IN-88010
Materials Licensees: Lack of Management Controls over Licensed
Programs
IN-88009
Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps
Caused by Instability of Woodward PG-PL Type Governors
IN-88008
Chemical Reactions with Radioactive Waste Solidification Agents
IN-88007
Inadvertent Transfer of Licensed Material to Uncontrolled Locations
IN-88006
Foreign Objects in Steam Generators
IN-88005
Fire in Annunciator Control Cabinets
IN-88004
Inadequate Qualification and Documentation of Fire Barrier
Penetration Seals
IN-88003
Cracks in Shroud Support Access Hole Cover Welds
IN-88002
Lost or Stolen Gauges
IN-88001
Safety Injection Pipe Failure
IN-87010s1
Potential for Water Hammer During Restart of Residual Heat
Removal Pumps – Supplement 1
IN-87061s1
Failure of Westinghouse W-2-Type Circuit Breaker Cell Switches –
Supplement 1
IN-87044s1
Thimble Tube Thinning in Westinghouse Reactors – Supplement 1
IN-87067
Lessons Learned from Regional Inspections of Licensee Actions in
Response to IE Bulletin 80-11
IN-87066
Inappropriate Application of Commercial-Grade Components
IN-87028s1
Air Systems Problems at U.S. Light Water Reactors – Supplement 1
IN-87065
Plant Operations Beyond Analyzed Conditions
IN-87064
Conviction for Falsification of Security Training Records
IN-87035s1
Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open
on Manual Initiation from the Control Room – Supplement 1
IN-87063
Inadequate Net Positive Suction Head in Low Pressure Safety
Systems
IN-87062
Mechanical Failure of Indicating-Type Fuses
IN-87061
Failure of Westinghouse W-2-Type Circuit Breaker Cell Switches
IN-87060
Depressurization of Reactor Coolant Systems in Pressurized-Water
Reactors
IN-87059
Potential RHR Pump Loss
IN-87058
Continuous Communications Following Emergency Notifications
IN-87057
Loss of Emergency Boration Capability Due to Nitrogen Gas
Intrusion
IN-87056
Improper Hydraulic Control Unit Installation at BWR Plants
IN-87055
Portable Moisture/Density Gauges: Recent Incidents of Portable
Gauges Being Stolen or Lost
IN-87054
Emergency Response Exercises
IN-87053
Auxiliary Feedwater Pump Trips Resulting from Low Suction
Pressure
IN-87052
Insulation Breakdown of Silicone Rubber-Insulated Single Conductor
Cables During High Potential Testing
IN-87051
Failure of Low Pressure Safety Injection Pump Due to Seal Problems
IN-87050
Potential LOCA at High- and Low-Pressure Interfaces from Fire
Damage
IN-87049
Deficiencies in Outside Containment Flooding Protection
IN-87048
Information Concerning the Use of Anaerobic Adhesive/Sealants
IN-87047
Transportation of Radiography Devices
IN-87046
Undetected Loss of Reactor Coolant
IN-87045
Recent Safety-Related Violations of NRC Requirements by Industrial
Radiography Licensees
IN-87044
Thimble Tube Thinning in Westinghouse Reactors
IN-87043
Gaps in Neutron-Absorbing Material in High-Density Spent Fuel
Storage Racks
IN-87042
Diesel Generator Fuse Contacts
IN-87041
Failures of Certain Brown Boveri Electric Circuit Breakers
IN-87040
Backseating Valves Routinely to Prevent Packing Leakage
IN-87039
Control of Hot Particle Contamination at Nuclear Power Plants
IN-87038
Inadequate or Inadvertent Blocking of Valve Movement
IN-87037
Compliance with the General License Provisions of 10 CFR Part 31
IN-87036
Significant Unexpected Erosion of Feedwater Lines
IN-87035
Reactor Trip Breaker, Westing Failed to Open on Manual Initiation
from the Control Room
IN-87034
Single Failures in Auxiliary Feedwater Systems
IN-87033
Applicability of 10 CFR Part 21 to Nonlicensees
IN-87032
Deficiencies in the Testing of Nuclear-Grade Activated Charcoal
IN-87031
Blocking, Bracing, and Securing of Radioactive Materials Packages
in Transportation
IN-87030
Cracking of Surge Ring Brackets in Large General Electric Company
Electric Motors
IN-87029
Recent Safety-Related Incidents at Large Irradiators
IN-87028
Air Systems Problems at U.S. Light Water Reactors
IN-87027
Iranian Official Implies Vague Threat to U.S. Resources
IN-87026
Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders
IN-87025
Potentially Significant Problems Resulting from Human Error
Involving Wrong Unit, Wrong Train, or Wrong Component Events
IN-87024
Operational Experience Involving Losses of Electrical Inverters
IN-87023
Loss of Decay Heat Removal During Low Reactor Coolant Level
Operation
IN-87022
Operator Licensing Requalification Examinations at Nonpower
Reactors
IN-87021
Shutdown Order Issued Because Licensed Operators Asleep While
on Duty
IN-87020
Hydrogen Leak in Auxiliary Building
IN-87019
Perforation and Cracking of Rod Cluster Control Assemblies
IN-87018
Unauthorized Service on Teletherapy Units by Nonlicensed
Maintenance Personnel
IN-87017
Response Time of Scram Instrument Volume Level Detectors
IN-87016
Degradation of Static "O" Ring Pressure Switches
IN-87015
Compliance with the Posting Requirements of Subsection 223B of
the Atomic Energy Act of 1954, as Amended
IN-87014
Actuation of Fire Suppression System Causing Inoperability of
Safety-Related Ventilation Equipment
IN-87013
Potential for High Radiation Fields Following Loss of Water from Fuel
Pool
IN-87012
Potential Problems with Metal Clad Circuit Breakers, General Electric
Type AKF-2-25
IN-87011
Enclosure of Vital Equipment within Designated Vital Areas
IN-87010
Potential for Water Hammer During Restart of Residual Heat
Removal Pumps
IN-87009
Emergency Diesel Generator Room Cooling Design Deficiency
IN-87008
Degraded Motor Leads in Limitorque DC Motor Operators
IN-87007
Quality Control of Onsite Dewatering/Solidification Operations by
Outside Contractors
IN-87006
Loss of Suction to Low-Pressure Service Water System Pumps
Resulting from Loss of Siphon
IN-87005
Miswiring in a Westinghouse Rod Control System
IN-87004
Diesel Generator Fails Test Because of Degraded Fuel
IN-87003
Segregation of Hazardous and Low-Level Radioactive Wastes
IN-87002
Inadequate Seismic Qualification of Diaphragm Valves by
Mathematical Modeling and Analysis
IN-87001
RHR Valve Misalignment Causes Degradation of ECCS in PWRs
IN-86108s3
NRC Information Notice 86-108, Supplement 3: Degradation of
Reactor Coolant System Pressure Boundary Resulting from Boric
Acid Corrosion – Supplement 3
IN-86014s2
Overspeed Trips of AFW, HPCI, and RCIC Turbines – Supplement 2
IN-86021s2
Recognition of American Society of Mechanical Engineers
Accreditation Program for N Stamp Holders – Supplement 2
IN-86099s1
Degradation of Steel Containments – Supplement 1
IN-86081s1
Broken External Closure Springs on Atwood & Morrill Main Steam
Isolation Valves – Supplement 1
IN-86108s2
Degradation of Reactor Coolant System Pressure Boundary
Resulting from Boric Acid Corrosion – Supplement 2
IN-86108s1
Degradation of Reactor Coolant System Pressure Boundary
Resulting from Boric Acid Corrosion – Supplement 1
IN-86064s1
Deficiencies in Upgrade Programs for Plant Emergency Operating
Conditions – Supplement 1
IN-86110
Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR
Plants
IN-86109
Diaphragm Failure in Scram Outlet Valve Causing Rod Insertion
IN-86107
Entry into PWR Cavity with Retractable Incore Detector Thimbles
Withdrawn
IN-86108
Degradation of Reactor Coolant System Pressure Boundary
Resulting from Boric Acid Corrosion
IN-86105
Potential for Loss of Reactor Trip Capability at Intermediate Power
Levels
IN-86014s1
Overspeed Trips of AFW, HPCI, and RCIC Turbines – Supplement 1
IN-86103
Respirator Coupling Nut Assembly Failures
IN-86104
Unqualified Butt Splice Connectors Identified in Qualified
Penetrations
IN-86106s3
Feedwater Line Break – Supplement 3
IN-86106s2
Feedwater Line Break – Supplement 2
IN-86106s1
Feedwater Line Break – Supplement 1
IN-86106
Feedwater Line Break
IN-86102
Repeated Multiple Failures of Steam Generator Hydraulic Snubbers
Due to Control Valve Sensitivity
IN-86101
Loss of Decay Heat Removal Due to Loss of Fluid Levels in Reactor
Coolant System
IN-86100
Loss of Offsite Power to Vital Busses at Salem 2
IN-86099
Degradation of Steel Containments
IN-86021s1
Recognition of American Society of Mechanical Engineers
Accreditation Program for N Stamp Holders – Supplement 1
IN-86098
Offsite Medical Services
IN-86097
Emergency Communications System
IN-86096
Heat Exchanger Fouling Can Cause Inadequate Operability of
Service Water Systems
IN-86095
Leak Testing Iodine-125 Sealed Sources in Lixi, Inc. Imaging
Devices and Bone Mineral Analyzers
IN-86094
Hilti Concrete Expansion Anchor Bolts
IN-86082r1
Failures of Scram Discharge Volume Vent and Drain Valves –
Revision 1
IN-86092
Pressurizer Safety Valve Reliability
IN-86093
IEB 85-03 Evaluation of Motor-Operators Identifies Improper Torque
Switch Settings
IN-86091
Limiting Access Authorizations
IN-86090
Requests to Dispose of Very Low-Level Radioactive Waste Pursuant
to 10 CFR 20.302
IN-86089
Uncontrolled Rod Withdrawal Because of a Single Failure
IN-86005s1
Main Steam Safety Valve Test Failures and Ring Setting
Adjustments – Supplement 1
IN-86025s1
Traceability and Material Control of Material and Equipment,
Particularly Fasteners – Supplement 1
IN-86088
Compensatory Measures for Prolonged Periods of Security System
Failures
IN-86087
Loss of Offsite Power upon an Automatic Bus Transfer
IN-86086
Clarification of Requirements for Fabrication and Export of Certain
Previously Approved Type B Packages
IN-86085
Enforcement Actions Against Medical Licensees for Willfull Failure to
Report Misadministrations
IN-86084
Rupture of Nominal 40-Millicurie Iodine-125 Brachytherapy Seed
Causing Significant Spread of Radioactive Contamination
IN-86083
Underground Pathways into Protected Areas, Vital Areas, Material
Access Areas, and Controlled Access Areas
IN-86082
Failures of Scram Discharge Volume Vent and Drain Valves
IN-86081
Broken Inner-External Closure Springs on Atwood & Morrill Main
Steam Isolation Valves
IN-86080
Unit Startup with Degraded High Pressure Safety Injection System
IN-86079
Degradation or Loss of Charging Systems at PWR Nuclear Power
Plants Using Swing-Pump Design
IN-86078
Scram Solenoid Pilot Valve (SSPV) Rebuild Kit Problems
IN-86077
Computer Program Error Report Handling
IN-86076
Problems Noted in Control Room Emergency Ventilation Systems
IN-86075
Incorrect Maintenance Procedure on Traversing Incore Probe Lines
IN-86074
Reduction of Reactor Coolant Inventory because of Misalignment of
RHR Valves
IN-86073
Recent Emergency Diesel Generator Problems
IN-86072
Failure 17-7 PH Stainless Steel Springs in Valcor Valves Due to
Hydrogen Embrittlement
IN-86071
Recent Identified Problems with Limitorque Motor Operators
IN-86070
Potential Failure of All Emergency Diesel Generators
IN-86069
Spurious System Isolations Caused by the Panalarm Model 86
Thermocouple Monitor
IN-86068
Stuck Control Rod
IN-86067
Portable Moisture/Density Gauges: ... Incidents and Common
Violations of Requirements for Use, Transportation, and Storage
IN-86066
Potential for Failure of Replacement AC Coils ... Westinghouse
Electric ... for ... Class 1E Motor Starters and Contactors
IN-86065
Malfunctions of ITT Barton Model 580 Series Switches During
Requalification Testing
IN-86064
Deficiencies in Upgrade Programs for Plant Emergency Operating
Procedures
IN-86063
Loss of Safety Injection Capability
IN-86013s1
Standby Liquid Control System Squib Valves Failure to Fire –
Supplement 1
IN-86062
Potential Problems in Westinghouse Molded Case Circuit Breakers
Equipped with a Shunt Trip
IN-86061
Failure of Auxiliary Feedwater Manual Isolation Valve
IN-86060
Unanalyzed Post-LOCA Release Paths
IN-86031s1
Unauthorized Transfer and Loss of Control of Industrial Nuclear
Gauges – Supplement 1
IN-86059
Increased Monitoring of ... Patients with Implanted Coratomic, Inc.
Model C-100 and C-101 Nuclear-Powered Cardiac Pacemakers
IN-86058
Dropped Fuel Assembly
IN-86057
Operating Problems with Solenoid Operated Valves at Nuclear
Power Plants
IN-86056
Reliability of Main Steam Safety Valves
IN-86055
Delayed Access to Safety-Related Areas and Equipment During
Plant Emergencies
IN-86054
Criminal Prosecution ... Former Radiation Safety Officer Who ...
Directed an Unqualified Individual to Perform Radiography
IN-86053
Improper Installation of Heat Shrinkable Tubing
IN-86052
Conductor Insulation Degradation on Foxboro Model E Controllers
IN-86051
Excessive Pneumatic Leakage in the Automatic Depressurization
System
IN-86050
Inadequate Testing to Detect Failures of Safety-Related Pneumatic
Components or Systems
IN-86049
Age/Environment Induced Electrical Cable Failures
IN-86048
Inadequate Testing of Boron Solution Concentration in the Standby
Liquid Control System
IN-86047
Erratic Behavior of Static "O" Ring Differential Pressure Switches
IN-86046
Improper Cleaning and Decontamination of Respiratory Protection
Equipment
IN-86045
Potential Falsification of Test Reports on Flanges Manufactured by
Golden Gate Forge and Flange, Inc.
IN-86044
Failure to Follow Procedures when Working in High Radiation Areas
IN-86043
Problems with Silver Zeolite Sampling of Airborne Radioiodine
IN-86042
Improper Maintenance of Radiation Monitoring Systems
IN-86041
Evaluation of Questionable Exposure Readings of Licensee
Personnel Dosimeters
IN-86032s1
Request for Collection of Licensee Radioactivity Measurements
Attributed to the Chernobyl Nuclear Plant Accident – Supplement 1
IN-86040
Degraded Ability to Isolate the Reactor Coolant System from LowPressure Coolant Systems in BWRs
IN-86039
Failures of RHR Pump Motors and Pump Internals
IN-86038
Deficient Operator Actions Following Dual Function Valve Failures
IN-86037
Degradation of Station Batteries
IN-86036
Change in NRC Practice Regarding Issuance of Confirming Letters
to Principal Contractors
IN-86035
Fire in Compressible Material at Dresden Unit 3
IN-86034
Improper Assembly, Material Selection, and Test of Valves and Their
Actuators
IN-86033
Information for Licensee Regarding the Chernobyl Nuclear Plant
Accident
IN-86031
Unauthorized Transfer and Loss of Control of Industrial Nuclear
Gauges
IN-86032
Request for Collection of Licensee Radioactivity Measurements
Attributed to the Chernobyl Nuclear Plant Accident
IN-86030
Design Limitations of Gaseous Effluent Monitoring Systems
IN-86029
Effects of Changing Valve Motor-Operator Switch Settings
IN-86028
Telephone Numbers to the NRC Operations Center and Regional
Offices
IN-86027
Access Control at Nuclear Facilities
IN-86026
Potential Problems in Generators Manufactured by Electrical
Products Incorporated
IN-86025
Traceability and Material Control of Material and Equipment,
Particularly Fasteners
IN-86024
Respirator Users Notice: Increased Inspection Frequency for Certain
Self-Contained Breathing Apparatus Air Cylinders
IN-86023
Excessive Skin Exposures Due to Contamination With Hot Particles
IN-86021
Recognition of American Society of Mechanical Engineers
Accreditation Program for N Stamp Holders
IN-86022
Underresponse of Radiation Survey Instrument to High Radiation
Fields
IN-86020
Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61
IN-86018
NRC On-Scene Response During a Major Emergency
IN-86017
Update of Failure of Automatic Sprinkler System Valves to Operate
IN-86019
Reactor Coolant Pump Shaft Failure at Crystal River
IN-86016
Failures to Identify Containment Leakage Due to Inadequate Local
Testing of BWR Vacuum Relief System Valves
IN-86015
Loss of Offsite Power Caused by Problems in Fiber Optics Systems
IN-86014
PWR Auxiliary Feedwater Pump Turbine Control Problems
IN-86011
Inadequate Service Water Protection Against Core Melt Frequency
IN-86012
Target Rock Two-Stage SRV Setpoint Drift
IN-86013
Standby Liquid Control System Squib Valves Failure to Fire
IN-86010
Safety Parameter Display System Malfunctions
IN-86006
Failure of Lifting Rig Attachment While Lifting the Upper Guide
Structure at St. Lucie Unit 1
IN-86007
Lack of ... Instruction and ... Observance of Precautions During
Maintenance and Testing of Diesel Generator ... Governors
IN-86008
Licensee Event Report (LER) Format Modification
IN-86009
Failure of Check and Stop Check Valves Subjected to Low Flow
Conditions
IN-86004
Transient Due to Loss of Power to Integrated Control System at a
Pressurized Water Reactor Designed by Babcock & Wilcox
IN-86005
Main Steam Safety Valve Test Failures and Ring Setting
Adjustments
IN-86003
Potential Deficiencies in Environmental Qualification of Limitorque
Motor Valve Operator Wiring
IN-86001
Failure of Main Feedwater Check Valves Causes Loss of Feedwater
System Integrity and Water-Hammer Damage
IN-86002
Failure of Valve Operator Motor During Environmental Qualification
Testing
IN-85045
Potential Seismic Interaction Involving the Movable In-Core Flux
Mapping System Used in Westinghouse Designed Plants
IN-85018s1
Failures of Undervoltage Output Circuit Boards in the WestinghouseDesigned Solid State Protection System – Supplement 1
IN-85062
Backup Telephone Numbers to the NRC Operations Center
IN-85041
Scheduling of Pre-Licensing Emergency Preparedness Exercises
IN-85035s1
Failure of Air Check Valves to Seat – Supplement 1
IN-85061s1
Misadministration to Patients Undergoing Thyroid Scans –
Supplement 1
IN-85101
Applicability of 10 CFR 21 to Consulting Firms Providing Training
IN-85100
Rosemount Differential Pressure Transmitter Zero Point Shift
IN-85099
Cracking in Boiling-Water-Reactor Mark I and Mark II Containments
Caused by Failure of the Inerting System
IN-85098
Missing Jumpers from Westinghouse Reactor Protection System
Cards for the Over-Power Delta Temperature Trip Function
IN-85097
Jail Term for Former Contractor Employee Who Intentionally
Falsified Welding Inspection Records
IN-85096
Temporary Strainers Left Installed in Pump Suction Piping
IN-85095
Leak of Reactor Water to Reactor Building Caused by Scram
Solenoid Valve Problem
IN-85094
Potential for Loss of Minimum Flow Paths Leading to ECCS Pump
Damage During a LOCA
IN-85093
Westinghouse Type DS Circuit Breakers, Potential Failure of Electric
Closing ... Because of Broken Spring Release Latch Lever
IN-85092
Surveys of Wastes Before Disposal from Nuclear Reactor Facilities
IN-85091
Load Sequencers for Emergency Diesel Generators
IN-85090
Use of Sealing Compounds in an Operating System
IN-85089
Potential Loss of Solid-State Instrumentation Following Failure of
Control Room Cooling
IN-85058s1
Failure of a General Electric Type AK-2-25 Reactor Trip Breaker –
Supplement 1
IN-85088
Licensee Control of Contracted Services Providing Training
IN-85087
Hazards of Inerting Atmospheres
IN-85086
Lightning Strikes at Nuclear Power Generating Stations
IN-85085
Systems Interaction Event Resulting in Reactor System Safety Relief
Valve Opening Following a Fire-Protection Deluge ...
IN-85084
Inadequate Inservice Testing of Main Steam Isolation Valves
IN-85083
Potential Failures of General Electric PK-2 Test Blocks
IN-85082
Diesel Generator Differential Protection Relay Not Seismically
Qualified
IN-85081
Problems Resulting in Erroneously High Reading with Panasonic
800 Series Thermoluminscent Dosimeters
IN-85080
Timely Declaration of an Emergency Class, Implementation of an
Emergency Plan, and Emergency Notifications
IN-85017s1
Possible Sticking of ASCO Solenoid Valves – Supplement 1
IN-85079
Inadequate Communications Between Maintenance, Operations, and
Security Personnel
IN-85078
Event Notification
IN-85077
Possible Loss of Emergency Notification System Due to Loss of AC
Power
IN-85076
Recent Water Hammer Events
IN-85075
Improperly Installed Instrumentation, Inadequate Quality Control and
Inadequate Postmodification Testing
IN-85074
Station Battery Problems
IN-85073
Emergency Diesel Generator Control Circuit Logic Design Error
IN-85072
Uncontrolled Leakage of Reactor Coolant Outside Containment
IN-85071
Containment Integrated Leak Rate Tests
IN-85070
Teletherapy Unit Full Calibration and Qualified Expert Requirements
(10 CFR 35.23 and 10 CFR 35.24)
IN-85069
Recent Felony Conviction for Cheating on Reactor Operator
Requalification Tests
IN-85068
Diesel Generator Failure at Calvert Cliffs Nuclear Station Unit 1
IN-85042r1
Loose Phosphor in Panasonic 800 Series Badge Thermoluminescent
Dosimeter (TLD) Elements – Revision 1
IN-85067
Valve-Shaft-to-Actuator Key May Fall out of Place when Mounted
Below Horizontal Axis
IN-85066
Discrepancies Between As-Built Construction Drawings and
Equipment Installations
IN-85065
Crack Growth in Steam Generator Girth Welds
IN-85064
BBC Brown Boveri Low-Voltage K-Line Circuit Breakers, with
Deficient Overcurrent Trip Devices Models OD-4 and 5
IN-85063
Potential for Common-Mode Failure of Standby Gas Treatment
System on Loss of Off-Site Power
IN-85061
Misadministrations to Patients Undergoing Thyroid Scans
IN-85060
Defective Negative-Pressure, Air-Purifying, Full Facepiece
Respirators
IN-85059
Valve Stem Corrosion Failures
IN-85058
Failure of a General Electric Type AK-2-25 Reactor Trip Breaker
IN-85057
Lost Iridium-192 Source Resulting in the Death of Eight Persons in
Morocco
IN-85056
Inadequate Environment Control for Components and Systems in
Extended Storage or Layup
IN-85055
Revised Emergency Exercise Frequency Rule
IN-85054
Teletherapy Unit Malfunction
IN-85053
Performance of NRC-Licensed Individuals While on Duty
IN-85052
Errors in Dose Assessment Computer Codes and Reporting
Requirements Under 10 CFR Part 21
IN-85051
Inadvertent Loss or Improper Actuation of Safety-Related Equipment
IN-85050
Complete Loss of Main and Auxiliary Feedwater at a PWR Designed
by Babcock & Wilcox
IN-85049
Relay Calibration Problem
IN-85048
Respirator Users Notice: Defective Self-Contained Breathing
Apparatus Air Cylinders
IN-85047
Potential Effect of Line-Induced Vibration on Certain Target Rock
Solenoid-Operated Valves
IN-85046
Clarification of Several Aspects of Removable Radioactive Surface
Contamination Limits for Transport Packages
IN-85044
Emergency Communication System Monthly Test
IN-85043
Radiography Events at Power Reactors
IN-85042
Loose Phosphor in Panasonic 800 Series Badge Thermoluminescent
Dosimeter (TLD) Elements
IN-85040
Deficiencies in Equipment Qualification Testing and Certification
Process
IN-85039
Auditability of Electrical Equipment Qualification Records at
Licensees' Facilities
IN-85038
Loose Parts Obstruct Control Rod Drive Mechanism
IN-85020s1
Motor-Operated Valve Failures Due to Hammering Effect –
Supplement 1
IN-85037
Chemical Cleaning of Steam Generators at Millstone 2
IN-85036
Malfunction of a Dry-Storage, Panoramic, Gamma Exposure
Irradiator
IN-85035
Failure of Air Check Valves to Seat
IN-85034
Heat Tracing Contributes to Corrosion Failure of Stainless Steel
Piping
IN-85033
Undersized Nozzle-to-Shell Welded Joints in Tanks and Heat
Exchangers Constructed Under the Rules of the ASME Boiler and
Pressure Vessel Code
IN-85032
Recent Engine Failures of Emergency Diesel Generators
IN-85031
Buildup of Enriched Uranium in Ventilation Ducts and Associated
Effluent Treatment Systems
IN-85030
Microbiologically Induced Corrosion of Containment Service Water
System
IN-85029
Use of Unqualified Sources in Well Logging Applications
IN-85003s1
Separation of Primary Reactor Coolant Pump Shaft and Impeller –
Supplement 1
IN-85028
Partial Loss of AC Power and Diesel Generator Degradation
IN-85027
Notifications to the NRC Operations Center and Reporting Events in
Licensee Event Reports
IN-85026
Vacuum Relief System for Boiling Water Reactor Mark I and Mark II
Containments
IN-85025
Consideration of Thermal Conditions of the Design and Installation
for Diesel Generator Exhaust Silencers
IN-85024
Failures of Protective Coatings in Pipes and Heat Exchangers
IN-85023
Inadequate Surveillance and Postmaintenance and Postmodification
System Testing
IN-85022
Failure of Limitorque Motor-Operated Valves Resulting from
Incorrect Installation of Pinion Gear
IN-85021
Main Steam Isolation Valve Closure Logic
IN-85020
Motor-Operated Valve Failures Due to Hammering Effect
IN-85019
Alleged Falsification of Certifications and Alteration of Markings on
Piping, Valves, and Fittings
IN-85010s1
Posttensioned Containment Tendon Anchor Head Failure –
Supplement 1
IN-85018
Failures of Undervoltage Output Circuit Boards in the WestinghouseDesigned Solid State Protection System
IN-85017
Possible Sticking of ASCO Solenoid Valves
IN-85016
Time/Current Trip Curve Discrepancy of ITE/Siemens-Allis Molded
Case Circuit Breaker
IN-85015
Nonconforming Structural Steel for Safety-Related Use
IN-85014
Failure of Heavy Control Rod (B4C) Drive Assembly to Insert a Trip
Signal
IN-85013
Consequences of Using Soluble Dams
IN-85012
Recent Fuel Handling Events
IN-85011
Licensee Programs for Inspection of Electrical Raceway and Cable
Installations
IN-85010
Posttensioned Containment Tendon Anchor Head Failure
IN-85009
Isolation Transfer Switches and Post-Fire Shutdown Capability
IN-85008
Industry Experience on Certain Materials Used in Safety-Related
Equipment
IN-85007
Contaminated Radiography Source Shipments
IN-85006
Contamination of Breathing Air Systems
IN-85005
Pipe Whip Restraints
IN-85004
Inadequate Management of Security Response Drills
IN-85003
Separation of Primary Reactor Coolant Pump Shaft and Impeller
IN-85002
Improper Installation and Testing of Differential Pressure
Transmitters
IN-85001
Continuous Supervision of Irradiators
IN-84069s1
Operation of Emergency Diesel Generators – Supplement 1
IN-84070s1
Reliance on Water Level Instrumentation with a Common Reference
Leg – Supplement 1
IN-84084r1
Deficiencies in Ferro-Resonant Transformers – Revision 1
IN-84055s1
Seal Table Leaks at PWRs – Supplement 1
IN-84052s1
Inadequate Material Procurement Controls on the Part of Licensees
and Vendors – Supplement 1
IN-84094
Reconcentration of Radionuclides Involving Discharges Into Sanitary
Sewage Systems Permitted Under 10 CFR 20.303
IN-84093
Potential For Loss of Water From The Refueling Cavity
IN-84092
Cracking of Flywheels On Cummins Fire Pump Diesel Engines
IN-84048s1
Failures of Rockwell International Globe Valves – Supplement 1
IN-84091
Quality Control Problems of Meteorological Measurements Programs
IN-84090
Main Steam Line Break Effect on Environmental Qualification of
Equipment
IN-84089
Stress Corrosion Cracking in Nonsensitized 316 Stainless Steel
IN-84088
Standby Gas Treatment System Problems
IN-84087
Piping Thermal Deflection Induced by Stratified Flow
IN-84086
Isolation Between Signals of The Protection System and Non-SafetyRelated Equipment
IN-84085
Molybdenum Breakthrough From Technetium-99m Generators
IN-84084
Deficiencies in Ferro-Resonant Transformers
IN-84083
Various Battery Problems
IN-84082
Guidance For Posting Radiation Areas
IN-84081
Inadvertent Reduction in Primary Coolant Inventory in BWRs During
Shutdown and Startup
IN-84080
Plant Transients Induced By Failure of Non-Nuclear Instrumentation
Power
IN-84079
Failure to Properly Install Steam Separator at Vermont Yankee
IN-84078
Underrated Terminal Blocks That May Adversely Affect Operation of
Essential Electrical Equipment
IN-84077
Incident Involving Teletherapy Unit (AECL Eldorado-78)
IN-84076
Loss of All AC Power
IN-84075
Calibration Problems - Eberline Instrument Model 6112B Analog
Teletectors
IN-84074
Isolation of Reactor Coolant System From Low-Pressure Systems
Outside Containment
IN-84073
Downrating of Self-Aligning Ball Bushings Used in Snubbers
IN-84036s1
Loosening of Locking Nut on Limitorque Operator – Supplement 1
IN-84072
Clarification of Conditions For Waste Shipments Subject To
Hydrogen Gas Generation
IN-84071
Graphitic Corrosion of Cast Iron in Salt Water
IN-84070
Reliance On Water Level Instrumentation With a Common
Reference Leg
IN-84069
Operation of Emergency Diesel Generators
IN-84068
Potential Deficiency In Improperly Rated Field Wiring to Solenoid
Valves
IN-84067
Recent Snubber Inservice Testing With High Failure Rates
IN-84066
Undetected Unavailability of The Turbine-Driven Auxiliary Feedwater
Train
IN-84065
Underrated Fuses Which May Adversely Affect Operation of
Essential Electrical Equipment
IN-84064
BWR High-Pressure Coolant Injection (HPCI) Initiation Seal-In and
Indication
IN-84063
Defective RHR Replacement Piping
IN-84062
Therapy Misadministrations To Patients Undergoing Cobalt-60
Teletherapy Treatments
IN-84061
Overexposure of Driver in PWR Refueling Cavity
IN-84060
Failure of Air-Purifying Respirator Filters To Meet Efficiency
Requirement
IN-84059
Deliberate Circumventing of Station Health Physics Procedures
IN-84058
Inadvertent Defeat of Safety Function Caused By Human Error
Involving Wrong Unit, Wrong Train, or Wrong System
IN-84057
Operating Experience Related to Moisture Intrusion in SafetyRelated Electrical Equipment At Commercial Power Plants
IN-84056
Respirator Users Notice For Certain 5-Minute Emergency Escape
Self-Contained Breathing Apparatus
IN-84055
Seal Table Leaks at PWRs
IN-84054
Deficiencies In Design Base Documentation and Calculations
Supporting Nuclear Power Plant Design
IN-84053
Information Concerning the Use of Loctite 242 and Other Anaerobic
Adhesive/Sealants
IN-84052
Inadequate Material Procurement Controls On The Part of Licensees
and Vendors
IN-84051
Independent Verification
IN-84050
Clarification of Scope of Quality Assurance Programs for Transport
Packages Pursuant to 10 CFR 50, Appendix B
IN-84049
Intergranular Stress Corrosion Cracking Leading To Steam
Generator Tube Failure
IN-84048
Failures of Rockwell International Globe Valves
IN-84047
Environmental Qualification Tests of Electrical Terminal Blocks
IN-84046
Circuit Breaker Position Verification
IN-84045
Reversed Differential Pressure Instrument Sensing Lines
IN-84044
Environmental Qualification Testing of Rockbestos Cables
IN-84043
Storage and Handling of Ophthalmic Beta Radiation Applicators
IN-84042
Equipment Availability For Conditions During Outages not Covered
by Technical Specifications
IN-84041
IGSCC in BWR Plants
IN-84040
Emergency Worker Doses
IN-84039
Inadvertent Isolation of Containment Spray Systems
IN-84038
Problems With Design, Maintenance and Operation of Offsite Power
Systems
IN-84037
Use of Lifted Leads and Jumpers During Maintenance or
Surveillance Testing
IN-84036
Loosening of Locking Nut on Limitorque Operator
IN-84035
BWR Post-Scram Drywell Pressurization
IN-84034
Respirator User Warning: Defective Self-Contained Breathing
Apparatus Air Cylinder
IN-84033
Main Steam Safety Valve Failures Caused By Failed Cotter Pins
IN-84032
Auxiliary Feedwater Sparger and Pipe Hanger Damage
IN-84031
Increased Stroking Time of Bettis Actuators Because of Swollen
Ethylene-Propylene Rubber Seals and Seal Set
IN-84030
Discrepancies in Record Keeping and Material Defects in Bahnson
[HVAC] Units
IN-84029
General Electric Magne-Blast Circuit Breaker Problems
IN-84028
Recent Serious Violations of NRC Requirements by Well-Logging
Licensees
IN-84027
Recent Serious Violations of NRC Requirements by Medical
Licensees
IN-84026
Recent Serious Violations of NRC Requirements by Moisture Density
Gauge Licensees
IN-84025
Recent Serious Violations of NRC Requirements by Radiography
Licensees
IN-84024
Physical Qualification of Individuals to Use Respiratory Protective
Devices
IN-84023
Results of The NRC-Sponsored Qualification Methodology Research
Test on ASCO Solenoid Valves
IN-84022
Deficiency in Comsip, Inc. Standard Bed Catalyst
IN-84005r1
Exercise Frequency – Revision 1
IN-84021
Inadequate Shutdown Margin
IN-84020
Service Life of Relays in Safety-Related System
IN-84019
Two Events Involving Unauthorized Entries Into PWR Reactor
Cavities
IN-84018
Stress Corrosion Cracking in PWR Systems
IN-84017
Problems With Liquid Nitrogen Cooling Components Below the Nil
Ductility Temperature
IN-84016
Failure of Automatic Sprinkler System Valves to Operate
IN-84015
Reporting of Radiological Releases
IN-84014
Highlights of Recent Transport Regulatory Revisions By DOT and
NRC
IN-84013
Potential Deficiency In Motor-Operated Valve Control Circuits and
Annunciation
IN-84012
Failure of Soft Seat Valve Seals
IN-84011
Training Program Deficiencies
IN-84010
Motor-Operated Valve Torque Switches Set Below The
Manufacturer's Recommended Value
IN-84009r1
Lessons Learned From NRC Inspections of Fire Protection Safe
Shutdown Systems (10 CFR 50, Appendix R) – Revision 1
IN-84009
Lessons Learned From NRC Inspections of Fire Protection Safe
Shutdown Systems (10 CFR 50, Appendix R)
IN-84008
Employee Protection
IN-84006
Steam Binding of Auxiliary Feedwater Pumps
IN-84004
Failure of Elastomer Seated Butterfly Valves Used Only During Cold
Shutdowns
IN-84003
Compliance With Conditions of License and Notification of Disability
by Licensed Operators
IN-84005
Exercise Frequency
IN-84002
Operating a Nuclear Power Plant at Voltage Levels Lower Than
Analyzed
IN-84001
Excess Lubricant in Electric Cable Sheaths
IN-84007
Design-Basis Threat and Review of Vehicular Access Controls
IN-83044s1
Potential Damage to Redundant Safety Equipment As a Result of
Backflow Through the Equipment and Floor Drain System -
Supplement 1
IN-83070s1
Vibration-Induced Valve Failures - Supplement 1
IN-83066s1
Fatality at Argentine Critical Facility - Supplement 1
IN-83084
Cracked and Broken Piston Rods in Brown Bovery Electric Type
5HK Breakers
IN-83082
Failure of Safety/Relief Valves to Open at BWR - Final Report
IN-83083
Use of Portable Radio Transmitters Inside Nuclear Power Plants
IN-83081
Entry Into High Radiation Areas From Areas Which Are Not Under
Direct Surveillance
IN-83080
Use of Specialized "Stiff" Pipe Clamps
IN-83079
Apparently Improper Use of Commercial Grade Components in
Safety-Related Systems
IN-83078
Apparent Improper Modification of a Component Affecting Plant
Safety
IN-83077
Air/Gas Entrainment Events Resulting in System Failures
IN-83075
Improper Control Rod Manipulation
IN-83074
Rupture of Cesium-137 Source Used in Well-Logging Operations
IN-83076
Reactor Trip Breaker Malfunctions (Undervoltage Trip Devices on
GE Type AK-2-25 Breakers)
IN-83073
Radiation Exposure From Gloves Contaminated With Uranium
Daughter Products
IN-83072
Environmental Qualification Testing Experience
IN-83071
Defects in Load-Bearing Welds on Lifting Devices for Vessel Head
and Internals
IN-83070
Vibration-Induced Valve Failures
IN-83069
Improperly Installed Fire Dampers at Nuclear Power Plants
IN-83068
Respirator User Warning: Defective Self-Contained Breathing
Apparatus Air Cylinders
IN-83067
Emergency-Use Respirator Material Defect Causes Production of
Noxious Gases
IN-83066
Fatality at Argentine Critical Facility
IN-83065
Surveillance of Flow in RTD Bypass Loops Used in Westinghouse
Plants
IN-83064
Lead Shielding Attached to Safety-Related Systems Without 10 CFR
50.59 Evaluations
IN-83063
Potential Failures of Westinghouse Electric Corporation Type SA-1
Differential Relays
IN-83062
Failure of Redundant Toxic Gas Detectors Positioned at Control
Room Ventilation Air Intakes
IN-83061
Alleged Use of Stand-Ins For Welder Qualification Test
IN-83060
Falsification of Test Results For Protective Coatings
IN-83059
Dose Assignment for Workers in Non-Uniform Radiation Fields
IN-83057
Potential Misassembly Problem With Automatic Switch Company
(ASCO) Solenoid Valve Model NP 8316
IN-83058
Transamerica Delaval Diesel Generator Crankshaft Failure
IN-83056
Operability of Required Auxiliary Equipment
IN-83055
Misapplication of Valves by Throttling Beyond Design Range
IN-83054
Common Mode Failure of Main Steam Isolation Nonreturn Check
Valves Valves
IN-83053
Primary Containment Isolation Valve Discrepancies
IN-83052
Radioactive Waste Gas System Events
IN-83051
Diesel Generator Events -
IN-83050
Failures of Class 1E Safety-Related Switchgear Circuit Breakers to
Close on Demand
IN-83049
Sampling and Prevention of Intrusion of Organic Chemicals Into
Reactor Coolant Systems
IN-83048
Gaseous Effluent Releases of Radioactive Iodine-125 and Iodine131 in Excess of Nuclear Regulatory Commission Limits
IN-83047
Failure of Hydraulic Snubbers as a Result of Contaminated Hydraulic
Fluid
IN-83046
Common-Mode Valve Failures Degrade Surry's Recirculation Spray
Subsystem
IN-83045
Environmental Qualification Test of General Electric Company "CR2940" Position Selector Control Switch
IN-83044
Potential Damage to Redundant Safety Equipment as a Result of
Backflow Through The Equipment and Floor Drain System
IN-83043
Improper Settings of Intermediate Range (IR) High Flux Trip
Setpoints
IN-83042
Reactor Mode Switch Malfuctions
IN-83041
Actuation of Fire Suppression System Causing Inoperability of
Safety-Related Equipment
IN-83040
Need to Environmentally Qualify Epoxy Grouts and Sealers
IN-83039
Failure of Safety/Relief Valves to Open at BWR - Interim Report
IN-83038
Defective Heat Sink Adhesive and Seismically Induced Chatter In
Relays Within Printed Circuit Cards
IN-83037
Transformer Failure Resulting From Degraded Internal Connection
Cables
IN-83036
Impact of Security Practices on Safe Operations
IN-83035
Fuel Movement With Control Rods Withdrawn at BWRs
IN-83034
Event Notification Information Worksheet
IN-83033
Nonrepresentative Sampling of Contaminated Oil
IN-83032
Rupture of Americium-241 Source(s) Contained in a Well Logging
Device
IN-83031
Error in The Adlpipe Computer Program
IN-83030
Misapplication of Generic Emergency Operating Procedures (EOP)
Guidelines
IN-83029
Fuel Binding Caused by Fuel Rack Deformation
IN-83028
Criteria for Protective Action Recommendations For General
Emergencies
IN-83027
Operational Response to Events Concerning Deliberate Acts
Directed Against Plant Equipment
IN-83026
Failure of Safety/Relef Valve Discharge Line Vacuum Breakers
IN-83025
Standby Gas Treatment System Heater High Temperature Trip
Setpoint Adjustment
IN-83024
Loose Parts in The Secondary Side of Steam Generators at
Pressurized Water Reactors
IN-83023
Inoperable Containment Atmosphere Sensing Systems
IN-83022
Boiling Water Reactor Safety/Relief Valve Failures
IN-83021
Defective Emergency-Use Respirator
IN-83001s1
Ray Miller, Inc. - Supplement 1
IN-83020
ITT Grinnell Figure 306/307 Mechanical Snubber Attachment
Interference
IN-83019
General Electric Type HFA Relay Contact Gap and Wipe Setting
Adjustments
IN-83018
Failures of The Undervoltage Trip Function of Reactor Trip System
Breakers
IN-83017
Electrical Control Logic Problem Resulting in Inoperable Auto-Start
of Emergency Diesel Generator Units
IN-83016
Contamination of The Auburn Steel Company Property With Cobalt60
IN-83015
Falsified Pre-Employment Screening Records
IN-83014
Dewatered Spent Ion Exchange Resin Susceptibility to Exothermic
Chemical Reaction
IN-83013
Design Misapplication of Bergen-Paterson Standard Strut Restraint
Clamp
IN-83012
Incorrect Boron Standards -
IN-83011
Possible Seismic Vulnerability of Old Lead Storage Batteries
IN-83010
Clarification of Several Aspects Relating to Use of NRC-Certified
Transport Packages
IN-83009
Safety and Security of Irradiators
IN-83008
Component Failures Caused by Elevated DC Control Voltage
IN-83007
Nonconformities With Materials Supplied by Tube Line Corporation
IN-83006
Nonidentical Replacement Parts -
IN-83005
Obtaining Approval for Disposing of Very-Low-Level Radioactive
Waste - 10 CFR Section 20.302
IN-83004
Failure of ELMA Power Supply Units
IN-83003
Calibration of Liquid Level Instruments
IN-83002
Limitorque HOBC, H1BC, H2BC, and H3BC Gearheads
IN-83001
Ray Miller, Inc.
IN-82056
Robertshaw Thermostatic Flow Control Valves
IN-82055
Seismic Qualification of Westinghouse AR Relay with Latch
Attachments Used in Westinghouse Solid State Protection System
IN-82054
Westinghouse NBFD Relay Failures in Reactor Protection Systems
IN-82053
Main Transformer Failures at the North Anna Nuclear Power Station
IN-82052
Equipment Environmental Qualification Testing Experience –
Updating of Test Summaries Previously Published in IN 81-29
IN-82051
Overexposures in PWR Cavities –
IN-82050
Modification of Solid State AC Undervoltage Relays Type ITE-27
IN-82049
Correction for Sample Conditions for Air and Gas Monitoring
IN-82048
Failures of Agastat CR 0095 Relay Sockets
IN-82047
Transportation of Type A Quantities of Non-Fissile Radioactive
Material
IN-82046
Defective and Obsolete Combination Padlocks
IN-82045
PWR Low Temperature Overpressure Protection
IN-82044
Clarification of Emergency Plan Exercise Requirements
IN-82043
Deficiencies in LWR Air Filtration/Ventilation Systems
IN-82042
Defects Observed in Panasonic Model 801 and Model 802
Thermoluminescent Dosimeters
IN-82041
Failure of Safety/Relief Valves to Open at a BWR
IN-82040
Deficiencies in Primary Containment Electrical Penetration
Assemblies
IN-82038
Change in Format and Distribution System for IE Bulletins, Circulars,
and Information Notices
IN-82039
Service Degradation of Thick Wall Stainless Steel Recirculation
System Piping at a BWR Plant
IN-82034r1
Welds in Main Control Panels - Revision 1
IN-82037
Cracking in the Upper Shell to Transition Cone Girth Weld of a
Steam Generator at an Operating PWR
IN-82036
Respirator Users Warning for Certain 5-Minute Emergency Escape
Self-Contained Breathing Apparatus
IN-82035
Failure of Three Check Valves on High Pressure Injection Lines to
Pass Flow
IN-82034
Welds in Main Control Panels
IN-82033
Control of Radiation Levels in Unrestricted Areas Adjacent to
Brachytherapy Patients
IN-82032
Contamination of Reactor Coolant System by Organic Cleaning
Solvents
IN-82027
Fuel Rod Degradation Resulting from Baffle Water-Jet Impingement
IN-82031
Overexposure of Diver During Work in Fuel Storage Pool
IN-82030
Loss of Thermal Sleeves in Reactor Coolant System Piping at
Certain Westinghouse PWR Power Plants
IN-82029
Control Rod Drive (CRD) Guide Tube Support Pin Failures at
Westinghouse PWRs
IN-82028
Hydrogen Explosion while Grinding in the Vicinity of Drained and
Open Reactor Coolant System
IN-82026
RCIC and HPCI Turbine Exhaust Check Valve Failures
IN-82025
Failures of Hiller Actuators upon Gradual Loss of Air Pressure
IN-82024
Water Leaking from Uranium Hexafluoride Overpacks
IN-82023
Main Steam Isolation Valve (MSIV) Leakage
IN-82022
Failures in Turbine Exhaust Lines
IN-82021
Buildup of Enriched Uranium in Effluent Treatment Tanks
IN-82020
Check Valve Problems –
IN-82019
Loss of High Head Safety Injection Emergency Boration and Reactor
Coolant Makeup Capability
IN-82018
Assessment of Intakes of Radioactive Material by Workers
IN-82017
Overpressurization of Reactor Coolant System
IN-82016
HPCI/RCIC High Steam Flow Setpoints
IN-82015
Notification of the Nuclear Regulatory Commission (NRC)
IN-82014
TMI-1 Steam Generator/Reactor Coolant System
Chemistry/Corrosion Problem
IN-82013
Failures of General Electric Type HFA Relays
IN-82012
Surveillance of Hydraulic Snubbers
IN-82011
Potential Inaccuracies in Wide Range Pressure Instruments Used in
Westinghouse Designed Plants
IN-82010
Following Up Symptomatic Repairs to Assure Resolution of the
Problem
IN-82009
Cracking in Piping of Makeup Coolant Lines at B&W Plants
IN-82008
Check Valve Failures on Diesel Generator Engine Cooling System
IN-82007
Inadequate Security Screening Programs
IN-82006
Failure of Steam Generator Primary Side Manway Closure Studs
IN-82005
Increasing Frequency of Drug Related Incidents
IN-82004
Potential Deficiency of Certain Agastat E-7000 Series Time-Delay
Relays
IN-82003
Environmental Tests of Electrical Terminal Blocks
IN-82002
Westinghouse NBFD Relay Failures in Reactor Protection Systems
at Certain Nuclear Power Plants
IN-82001r1
Auxiliary Feedwater Pump Lockout Resulting from Westinghouse W2 Switch Circuit Modification - Revision 1
IN-82001
Auxiliary Feedwater Pump Lockout Resulting from Westinghouse W2 Switch Circuit Modification
IN-81037r1
Unnecessary Radiation Exposures to the Public and Workers During
Events Involving Thickness and Level Measuring Devices
IN-81039
EPA Crosscheck Program – Low Level Radioiodine in Water
Intercomparison Study
IN-81038
Potentially Significant Equipment Failures Resulting from
Contamination of Air-Operated Systems
IN-81037
Unnecessary Radiation Exposures to the Public and Workers During
Events Involving Thickness and Level Measuring Devices
IN-81036
Replacement Diaphragms for Robertshaw Valve (Model No. VC-210)
IN-81035
Check Valve Failures
IN-81030
Velan Swing Check Valves
IN-81029
Equipment Qualification Testing Experience
IN-81028
Failure of Rockwell-Edward Main Steam Isolation Valves
IN-81027
Flammable Gas Mixtures in the Waste Gas Decay Tanks in PWR
Plants
IN-81026
Compilation of Health Physics Related Information Items
IN-81025
Open Equalizing Valve of Differential Pressure Transmitter Causes
Reactor Scram and Loss of Redundant Safety Signals
IN-81024
Auxiliary Feed Pump Turbine Bearing Failures
IN-81023
Fuel Assembly Damaged Due to Improper Positioning of Handling
Equipment
IN-81022
Section 235 and 236 Amendments to the Atomic Energy Act of 1954
IN-81021
Potential Loss of Direct Access to Ultimate Heat Sink
IN-81026s1
Clarification of Placement of Personnel Monitoring Devices for
External Radiation
IN-81020
Test Failures of Electrical Penetration Assemblies
IN-81019
Lost Parts in Primary Coolant System
IN-81018
Excessive Radiation Exposures to the Fingers...During Cleaning and
Wipe Testing of...Sealed Sources at a...Mfg. Facility
IN-81017
INFORMATION NOTICE 81-17 WAS NOT ISSUED
IN-81016
Control Rod Drive System Malfunctions
IN-81015
Degradation of Automatic ECCS Actuation Capability by Isolation of
Instrument Lines
IN-81014
Potential Overstress of Shafts on Fisher Series 9200 Butterfly Valves
with Expandable T Rings
IN-81013
Jammed Source Rack in a Gamma Irradiator
IN-81012
Guidance on Order Issued January 9, 1981 Regarding Automatic
Control Rod Insertion on Low Control Air Pressure
IN-81011
Alternate Rod Insertion for BWR Scram Represents a Potential Path
for Loss of Primary Coolant
IN-81009
Degradation of Residual Heat Removal (RHR) System
IN-81010
Inadvertent Containment Spray Due to Personnel Error
IN-81008
Repetitive Failures of Limitorque Operator SMB-4 Motor-to-Shaft Key
IN-81007
Potential Problem with Water-Soluble Purge Dam Materials Used
During Inert Gas Welding
IN-81006
Failure of ITE Model K-600 Circuit Breaker
IN-81005
Degraded DC System at Palisades
IN-81004
Cracking in Main Steam Lines
IN-81003
Checklist for Licensees Making Notifications of Significant Events in
Accordance with 10 CFR 50.72
IN-81002
Transportation of Radiography Devices
IN-81001
Possible Failures of General Electric Type HFA Relays
IN-80035s1
Leaking and Dislodged Iodine-125 Implant Seeds
IN-80032r1
Clarification of Certain Requirements for Exclusive-Use Shipments of
Radioactive Materials
IN-80045
Potential Failure of BWR Backup Manual Scram Capability
IN-80044
Actuation of ECCS in the Recirculation Mode while in Hot Shutdown
IN-80043
Failures of the Continuous Water Level Monitor for the Scram
Discharge Volume at Dresden Unit No. 2
IN-80029s1
Broken Studs on Terry Turbine Steam Inlet Flange
IN-80042
Effect of Radiation on Hydraulic Snubber Fluid
IN-80041
Failure of Swing Check Valve in the Decay Heat Removal System at
Davis-Besse Unit No. 1
IN-80040
Excessive Nitrogen Supply Pressure Actuates Safety-Relief Valve
Operation to Cause Reactor Depressurization
IN-80039
Malfunctions of Solenoid Valves Manufactured by Valcor
Engineering Corporation
IN-80038
Cracking in Charging Pump Casing Cladding
IN-80037
Containment Cooler Leaks and Reactor Cavity Flooding at Indian
Point Unit 2
IN-80036
Failure of Steam Generator Support Bolting
IN-80035
Leaking and Dislodged Iodine-125 Implant Seeds
IN-80034
Boron Dilution of Reactor Coolant During Steam Generator
Decontamination
IN-80033
Determination of Teletherapy Timer Accuracy
IN-80032
Clarification of Certain Requirements for Exclusive-Use Shipments of
Radioactive Materials
IN-80031
Maloperation of Gould-Brown Boveri 480 Volt Type K-600S and KDON 600S Circuit Breakers
IN-80030
Potential for Unacceptable Interaction between Control Rod Drive
Scram...and Non-Essential Control Air at GE BWRs
IN-80029
Broken Studs on Terry Turbine Steam Inlet Flange
IN-80006s1
Notification of Significant Events at Operating Power Reactor
Facilities
IN-80028
Prompt Reporting of Information in Accordance with 10 CFR
50.55(e)
IN-80027
Degradation of Reactor Coolant Pump Studs
IN-80026
Evaluation of Contractor QA Programs
IN-80025
Transportation of Pyrophoric Uranium
IN-80024
Low-Level Radioactive Waste Burial Criteria
IN-80023
Loss of Suction to Emergency Feedwater Pumps
IN-80022
Breakdowns in Contamination Control Programs
IN-80021
Anchorage and Support of Safety-Related Electrical Equipment
IN-80020
Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 while
in a Refueling Mode
IN-80019
NIOSH Recall of Recirculating-Mode (Closed-Circuit) Self-Contained
Breathing Apparatus (Rebreathers)
IN-80018
Possible Weapons Smuggling Pouch
IN-80017
Potential Hazards Associated with Interchangeable Parts on
Radiographic Equipment
IN-80016
Shaft Seal Packing Causes Binding in Main Steam Swing Disc
Check and Isolation Valves
IN-80015
Axial (Longitudinal) Oriented Cracking in Piping
IN-80014
Safety Suggestions from Employees
IN-80013
General Electric Type SBM Control Switches - Defective Cam
Followers
IN-80012
Instrument Failure Causes Opening of PORV and Block Valve
IN-80011
Generic Problems with ASCO Valves in Nuclear Applications
Including Fire Protection Systems
IN-80010
Partial Loss of Non-Nuclear Instrument System Power Supply During
Operation
IN-80009
Possible Occupational Health Hazard Associated with Closed
Cooling Systems for Operating Power Plants
IN-80008
The States Company Sliding Link Electrical Terminal Block
IN-80007
Pump Shaft Fatigue Cracking
IN-80006
Notification of Significant Events
IN-80005
Chloride Contamination of Safety Related Piping and Components
IN-80004
BWR Fuel Exposure in Excess of Limits
IN-80003
Main Turbine Electro-Hydraulic Control System
IN-80002
8X8R Water Rod Lower End Plug Wear
IN-80001
Fuel Handling Events
IN-79036
Computer Code Defect in Stress Analysis of Piping Elbow
IN-79035
Control of Maintenance and Essential Equipment
IN-79037
Cracking in Low Pressure Turbine Discs
IN-79034
Inadequate Design of Safety-Related Heat Exchangers
IN-79033
Improper Closure of Primary Containment Access Hatches
IN-79032
Separation of Electrical Cables for HPCI and ADS
IN-79031
Use of Incorrect Amplified Response Spectra (ARS)
IN-79030
Reporting of Defects and Noncompliance, 10 CFR Part 21
IN-79029
Loss of Nonsafety-Related Reactor Coolant System Instrumentation
During Operation
IN-79028
Overloading of Structural Elements Due to Pipe Support Loads
IN-79027
Steam Generator Tube Ruptures at Two PWR Facilities
IN-79012a
Attempted Damage to New Fuel Assemblies
IN-79026
Breach of Containment Integrity
IN-79025
Reactor Trips at Turkey Point Units 3 and 4
IN-79023
Emergency Diesel Generator Lube Oil Coolers
IN-79024
Overpressurization of Containment of a PWR Plant after a Main
Steam Line Break
IN-79022
Qualification of Control Systems
IN-79021
Transportation and Commercial Burial of Radioactive Materials
IN-79020r1
NRC Enforcement Policy – NRC Licensed Individuals
IN-79020
NRC Enforcement Policy – NRC Licensed Individuals
IN-79019
Pipe Cracks in Stagnant Borated Water Systems at PWR Plants
IN-79018
Skylab Reentry
IN-79017
Source Holder Assembly Damage from Misfit between Assembly and
Reactor Upper Grid Plate
IN-79016
Nuclear Incident at Three Mile Island
IN-79015
Deficient Procedures –
IN-79014
Safety Classification of Electrical Cable Support Systems
IN-79013
Indication of Low Water Level in the Oyster Creek Reactor
IN-79012
Attempted Damage to New Fuel Assemblies
IN-79011
Lower Reactor Vessel Head Insulation Support Problem
IN-79010
Nonconforming Pipe Support Struts
IN-79009
Spill of Radioactively Contaminated Resin
IN-79008
Interconnection of Contaminated Systems with Service Air Systems
Used as the Source of Breathing Air
IN-79007
Rupture of Radwaste Tanks
IN-79006
Stress Analysis of Safety-Related Piping
IN-79005
Use of Improper Materials in Safety-Related Components
IN-79004
Degradation of Engineered Safety Features
IN-79003
Limitorque Valve Geared Limit Switch Lubricant
IN-79002
Attempted Extortion – Low Enriched Uranium
IN-79001
Bergen-Paterson Hydraulic Shock and Sway Arrestor