 | BL73005
Manufacturing Defects in Boiling Water Reactor Control Rods |
| BL73006
Inadvertent Criticality in a Boiling Water Reactor |
| BL78014
Deterioration of Buna-N Components in ASCO Solenoids |
| BL79026
Boron Loss from BWR Control Blades |
| BL79026R1
Boron Loss from BWR Control Blades |
| BL80007
BWR Jet Pump Assembly Failure |
| BL80017
Failure of 76 of 185 Control Rods to Fully Insert During a
Scram at a BWR |
| BL8007S1
BWR Jet Pump Assembly Failure |
| BL8017S1
Failure of 76 of 185 Control Rods to Fully Insert During a
Scram at a BWR |
| BL8017S2
Failures Revealed by Testing Subsequent to Failure of Control
Rods to Insert During a Scram at a BWR |
| BL8017S3
Failures Revealed by Testing Subsequent to Failure of Control
Rods to Insert During a Scram at a BWR |
| BL8017S4
Failure of Control Rods to Insert During a Scram at a BWR |
| BL8017S5
Failure of Control Rods to Insert During a Scram at a BWR |
| BL88007
Power Oscillations in Boiling Water Reactors (BWRs) |
| BL8807S1
Power Oscillations in Boiling Water Reactors (BWRs) |
| BL96001
Control Rod Insertion Problems |
| BL96002
MOVEMENT OF HEAVY LOADS OVER SPENT FUEL, OVER FUEL IN THE
REACTOR CORE, OR OVER SAFETY-RELATED EQUIPMENT |
| GL79058
ECCS Calculations On Fuel Cladding |
| GL80003
BWR Control Rod Failures |
| GL80063
IEB 80-17 Failure Of Control Rods To Insert During A Scram At
A BWR |
| GL80066
IEB 80-17 Supplement 1 Failure Of Control Rods To Insert
During A Scram At A BWR |
| GL80067
Scram Discharge Volume |
| GL80068
IEB 80-17 Supplement 2 Failures Revealed By Testing Subsequent
To Failure Of Control Rods To Insert During A Scram At A BWR |
| GL80079
IEB 80-17 Supplement 3 Failures Revealed By Testing Subsequent
To Failure Of Control Rods To Insert During A Scram At A BWR |
| GL80084
BWR Scram System |
| GL80107
BWR Scram Discharge System |
| GL81009
BWR Scram Discharge System |
| GL81018
BWR Scram Discharge System-Clarification of Diverse
Instrumentation Requirements |
| GL81020
Safety Concerns Associated With Pipe Breaks in The BWR Scram
System |
| GL81024
Multi-Plant Issue B-56 Control Rods Fail To Fully Insert |
| GL81030
Safety Concerns Associated With Pipe Breaks in the BWR Scram
System |
| GL81034
Safety Concerns Associated With Pipe Breaks in the BWR Scram
System |
| GL81035
Safety Concerns Associated With Pipe Breaks in the BWR Scram
System |
| GL82003
High Burnup MAPLHGR Limits |
| GL82012
Nuclear Power Plant Staff Working Hours |
| GL86002
Technical Resolution of Generic Issue B-19 -Thermal Hydraulic
Stability |
| GL86003
Applications For License Amendments |
| GL86004
Policy Statement On Engineering Expertise On Shift |
| GL88011
NRC Position on Radiation Embrittlement Of Reactor Vessel
Materials And Its Impact On Plant Operations |
| GL94002
Long-Term Solutions and Upgrade of Interim Operating
Recommendations for Thermal-Hydraulic Instabilities in BWRs |
| GL94003
Intergranular Stress Corrosion Cracking of Core Shrouds in
Boiling Water Reactors |
| GL96004
BORAFLEX DEGRADATION IN SPENT FUEL POOL STORAGE RACKS |
| GL97001
Degradation of Control Rod Drive Mechanism Nozzle and Other
Vessel Closure Head Penetrations |
| GL99001
NRC Generic Letter 99-01: Recent Nuclear Material Safety and
Safeguards Decision on Bundling Exempt Quantities |
| IN80001
Fuel Handling Events |
| IN80002
8X8R Water Rod Lower End Plug Wear |
| IN80004
BWR Fuel Exposure in Excess of Limits |
| IN80030
Potential for Unacceptable Interaction between Control Rod
Drive Scram...and Non-Essential Control Air at GE BWRs |
| IN80045
Potential Failure of BWR Backup Manual Scram Capability |
| IN81011
Alternate Rod Insertion for BWR Scram Represents a Potential
Path for Loss of Primary Coolant |
| IN81012
Guidance on Order Issued January 9, 1981 Regarding Automatic
Control Rod Insertion on Low Control Air Pressure |
| IN81016
Control Rod Drive System Malfunctions |
| IN81023
Fuel Assembly Damaged Due to Improper Positioning of Handling
Equipment |
| IN82027
Fuel Rod Degradation Resulting from Baffle Water-Jet
Impingement |
| IN83029
Fuel Binding Caused by Fuel Rack Deformation |
| IN83075
Improper Control Rod Manipulation |
| IN84021
Inadequate Shutdown Margin |
| IN84079
Failure to Properly Install Steam Separator at Vermont Yankee |
| IN85012
Recent Fuel Handling Events |
| IN85014
Failure of Heavy Control Rod (B4C) Drive Assembly to Insert a
Trip Signal |
| IN86058
Dropped Fuel Assembly |
| IN86068
Stuck Control Rod |
| IN86075
Incorrect Maintenance Procedure on Traversing Incore Probe
Lines |
| IN86089
Uncontrolled Rod Withdrawal Because of a Single Failure |
| IN86109
Diaphragm Failure in Scram Outlet Valve Causing Rod Insertion |
| IN86110
Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR
Plants |
| IN87056
Improper Hydraulic Control Unit Installation at BWR Plants |
| IN88021
Inadvertent Criticality Events at Oskarshamn and at U.S.
Nuclear Power Plants |
| IN88034
Nuclear Material Control and Accountability of Non-Fuel
Special Nuclear Material at Power Reactors |
| IN88039
LaSalle Unit 2 Loss of Recirculation Pumps with Power
Oscillation Event |
| IN89009
Credit for Control Rods Without Scram Capability in the
Calculation of the Shutdown Margin |
| IN89024
Nuclear Criticality Safety |
| IN89031
Swelling and Cracking of Hafnium Control Rods |
| IN90063
Management Attention to the Establishment and Maintenance of a
Nuclear Criticality Safety Program |
| IN90077
Inadvertent Removal of Fuel Assemblies From the Reactor Core |
| IN90078
Previously Unidentified Release Path From Boiling Water
Reactor Control Rod Hydraulic Units |
| IN9077S1
Inadvertent Removal of Fuel Assemblies From the Reactor Core |
| IN91036
Nuclear Plant Staff Working Hours |
| IN92021
Spent Fuel Pool Reactivity Calculations |
| IN92039
Unplanned Return to Criticality During Reactor Shutdown |
| IN92074
Power Oscillations at Washington Nuclear Power Unit 2 |
| IN9221S1
Spent Fuel Pool Reactivity Calculations |
| IN93070
Degradation of Boraflex Neutron Absorber Coupons |
| IN93077
Human Errors That Result in Inadvertent Transfers of Special
Nuclear Material at Fuel Cycle Facilities |
| IN93079
Core Shroud Cracking at Beltline Region Welds in Boiling-Water
Reactors |
| IN93082
Recent Fuel and Core Performance Problems in Operating
Reactors |
| IN93101
Jet Pump Hold-Down Beam Failure |
| IN94013
Unanticipated & Unintended Movement - Fuel Assemblies
& Other Components Due - Improper Operation of Refueling
Equipment |
| IN94042
Cracking in the Lower Region of the Core Shroud in
Boiling-Water Reactors |
| IN94064
Reactivity Insertion Transient and Accident Limits for High
Burnup Fuel |
| IN9413S1
Unanticipated & Unintended Movement - Fuel Assemblies
& Other Components Due - Improper Operation of Refueling
Equipment |
| IN9442S1
Cracking in the Lower Region of the Core Shroud in
Boiling-Water Reactors |
| IN9464S1
Reactivity Insertion Transient and Accident Limits For High
Burnup Fuel |
| IN95008
Inaccurate Data Obtained With Clamp-on Ultrasonic Flow
Measurement Instruments |
| IN95016
Vibration Caused by Increased Recirculation Flow in a Boiling
Water Reactor |
| IN95017
Reactor Vessel Top Guide and Core Plate Cracking |
| IN95038
Degradation of Boraflex Neutron Absorber in Spent Fuel Storage
Racks |
| IN95051
Recent Incidents Involving Potential Loss of Control of
Licensed Material |
| IN95056
Shielding Deficiency in Spent Fuel Transfer Canal at a
Boiling-Water Reactor |
| IN95057
Risk Impact Study Regarding Maintenance During Low-Power
Operation and Shutdown |
| IN96007
SLOW FIVE PERCENT SCRAM INSERTION TIMES CAUSED BY VITON
DIAPHRAGMS IN SCRAM SOLENOID PILOT VALVES |
| IN96012
Control Rod Insertion Problems |
| IN96016
BWR Operation With Indicated Flow Less Than Natural
Circulation |
| IN96017
Reactor Operation Inconsistent With the Updated Final Safety
Analysis Report |
| IN96025
Traversing In-Core Probe Over withdrawn at LaSalle County
Station, Unit 1 |
| IN96039
ESTIMATES OF DECAY HEAT USING ANS 5.1 DECAY HEAT STANDARD MAY
VARY SIGNIFICANTLY |
| IN96041
EFFECTS OF A DECREASE IN FEEDWATER TEMPERATURE ON NUCLEAR
INSTRUMENTATION |
| IN96069
OPERATOR ACTIONS AFFECTING REACTIVITY |
| IN97002
CRACKS FOUND IN JET PUMP RISER ASSEMBLY ELBOWS AT BOILING
WATER REACTORS |
| IN97013
Assessment of Spent Fuel Pool Cooling |
| IN97015
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) |
| IN97017
Cracking of Vertical Welds in The Core Shroud and Degraded
Repair |
| IN97030
Control of Licensed Material During Reorganizations,
Employee-Management Disagreements, And Financial Crises |
| IN97039
Inadequate 10 CFR 72.48 Safety Evaluations of Independent
Spent Fuel Storage Installations |
| IN97042
Management Weaknesses Resulting in Failure to Comply With
Shipping Requirements for Special Nuclear Material |
| IN97051
Problems Experienced Loading and Unloading Spent Nuclear Fuel
Storage and Transportation Casks |
| IN97062
Unrecognized Reactivity Addition During Plant Shutdown |
| IN97077
Exemptions From the Requirements of Section 70.24 of Title 10
of The Code of Federal Regulations |
| IN97085
Effects of Crud Buildup and Boron Deposition on Power
Distribution and Shutdown Margin |
| IN98029
NRC Information Notice 98-29: Predicted Increase in Fuel Rod
Cladding Oxidation |
| IN99031
Operational Controls to Guard Against Inadvertent Nuclear
Criticality |
| IN00001
Operational Issues Identified in Boiling Water Reactor Trip
and Transient |
