General 10-CFR Code of Federal Regulations -- Energy Index of All NRC Generic Communications Bulletins 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 Circulars CR77007  Short Period During Reactor Startup CR77012  Dropped Fuel Assemblies at BWR Facilities CR79007  Unexpected Speed Increase of Reactor Recirculation MG Set Resulted in Reactor Power Increase CR80002  Nuclear Power Plant Staff Work Hours Generic Letters 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 Information Notices 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

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