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Section 3. New Generic Issues

This section contains a compilation of issues that are not listed in any single report. these issues have surfaced since publication of NUREG-0371,2 NUREG-0471,3 and NUREG-0660.48

the first 27 of these issues were transmitted23 from the Generic Issues Branch (GIB) to SPEB on September 30, 1981 for prioritization by SPEB. This transmittal provided the basis for the formation of this group of New Generic Issues.

Several of the first 27 issues had origins in reports published by ACRS, some of which were important enough to be considered as Candidate USIs. This group has been expanded to include new issues that have been raised by the NRR staff as well as those forwarded to NRR from other offices such as AEOD. It will continue to expand to include new safety issues as they arise. the lead responsibility and a summary of the findings for each issue listed in this section can be found in Table II of the Introduction.


Contents
Issue 1: Failures in Air-Monitoring, Air-Cleaning, and Ventilating Systems
Issue 2: Failure of Protective Devices on Essential Equipment
Issue 3: Set Point Drift in Instrumentation
Issue 4: End-of-Life and Maintenance Criteria
Issue 5: Design Check and Audit of Balance-of-Plant Equipment
Issue 6: Separation of Control Rod from its Drive and BWR High Rod Worth Events
Issue 7: Failures Due to Flow-Induced Vibrations
Issue 8: Inadvertent Actuation of Safety Injection in PWRs
Issue 9: Reevaluation of Reactor Coolant Pump Trip Criteria
Issue 10: Surveillance and Maintenance of Tip Isolation Valves and Squib Charges
Issue 11: Turbine Disc Cracking
Issue 12: BWR Jet Pump Integrity
Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters
Issue 14: PWR Pipe Cracks
Issue 15: Radiation Effects on Reactor Vessel Supports
Issue 16: BWR Main Steam Isolation Valve Leakage Control Systems
Issue 17: Loss of Offsite Power Subsequent to a LOCA
Issue 18: Steam-Line Break with Consequential Small LOCA
Issue 19: Safety Implications of Non-safety Instrument and Control Power Supply Bus
Issue 20: Effects of Electromagnetic Pulse on Nuclear Power Plants
Issue 21: Vibration Qualification of Equipment
Issue 22: Inadvertent Boron Dilution Events
Issue 23: Reactor Coolant Pump Seal Failures
Issue 24: Automatic ECCS Switchover to Recirculation
Issue 25: Automatic Air Header Dump on BWR Scram System
Issue 26: Diesel Generator Loading Problems Related to SIS Reset on Loss of Offsite Power
Issue 27: Manual vs. Automated Actions
Issue 28: Pressurized thermal Shock
Issue 29: Bolting Degradation or Failure in Nuclear Power Plants
Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings
Issue 31: Natural Circulation Cooldown
Issue 32: Flow Blockage in Essential Equipment Caused by Corbicula
Issue 33: Correcting Atmospheric Dump Valve Opening upon Loss of Integrated Control System Power
Issue 34: RCS Leak
Issue 35: Degradation of Internal Appurtenances in LWR's
Issue 36: Loss of Service Water
Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown
Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris
Issue 39: Potential for Unacceptable Interaction between the CRD System and Non-Essential Control Air System
Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System
Issue 41: BWR Scram Discharge Volume Systems
Issue 42: Combination Primary/Secondary System LOCA
Issue 43: Reliability of Air Systems
Issue 44: Failure of Saltwater Cooling System
Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather
Issue 46: Loss of 125 Volt DC Bus
Issue 47: the Loss of Offsite Power
Issue 48: LCO for Class 1E Vital Instrument Buses in Operating Reactors
Issue 49: Interlocks and LCO's for Class 1E Tie-Breakers
Issue 50: Reactor Vessel Level Instrumentation in BWRs
Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water System
Issue 52: SSW Flow Blockage by Blue Mussels
Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR
Issue 54: Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980
Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand
Issue 56: Abnormal Transient Operating Guidelines as Applied to a Steam Generator Overfill Event
Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment
Issue 58: Containment Flooding
Issue 59: Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown Is Degraded or Inoperable
Issue 60: Lamellar Tearing of Reactor Systems Structural Supports
Issue 61: SRV Line Break Inside the BWR Wetwell Airspace of Mark I and II Containments
Issue 62: Reactor Systems Bolting Applications
Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis
Issue 64: Identification of Protection System Instrument Sensing Lines
Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures
Issue 66: Steam Generator Requirements
Issue 67: Steam Generator Staff Actions
Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture
Issue 69: Make-Up Nozzle Cracking in B&W Plants
Issue 70: PORV and Block Valve Reliability
Issue 71: Failure of Resin Demineralizer Systems and their Effects on Nuclear Power Plant Safety
Issue 72: Control Rod Drive Guide Tube Support Pin Failures
Issue 73: Detached thermal Sleeves
Issue 74: Reactor Coolant Activity Limits for Operating Reactors
Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant
Issue 76: Instrumentation and Control Power Interactions
Issue 77: Flooding of Safety Equipment Compartments by Backflow through Floor Drains
Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System
Issue 79: Unanalyzed Reactor Vessel thermal Stress During Natural Convection Cooldown
Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments
Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety
Issue 82: Beyond Design Basis Accidents in Spent Fuel Pools
Issue 83: Control Room Habitability
Issue 84: CE PORVs
Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments
Issue 86: Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping
Issue 87: Failure of HPCI Steam Line without Isolation
Issue 88: Earthquakes and Emergency Planning
Issue 89: Stiff Pipe Clamps
Issue 90: Technical Specifications for Anticipatory Trips
Issue 91: Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators
Issue 92: Fuel Crumbling During LOCA
Issue 93: Steam Binding of Auxiliary Feedwater Pumps
Issue 94: Additional Temperature Overpressure Protection for Light Water Reactors
Issue 95: Loss of Effective Volume for Containment Recirculation Spray
Issue 96: RHR Suction Valve Testing
Issue 97: PWR Reactor Cavity Uncontrolled Exposures
Issue 98: CRD Accumulator Check Valve Leakage
Issue 99: RCS/RHR Suction Line Valve Interlock on PWR's
Issue 100: Once-Through Steam Generator Level
Issue 101: BWR Water Level Redundancy
Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train
Issue 103: Design for Probable Maximum Precipitation
Issue 104: Reduction of Boron Dilution Requirements
Issue 105: Interfacing Systems LOCA at LWR's
Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas
Issue 107: Main Transformer Failures
Issue 108: BWR Suppression Pool Temperature Limits
Issue 109: Reactor Vessel Closure Failure
Issue 110: Equipment Protective Devices on Engineered Safety Features
Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments
Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times
Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers
Issue 114: Seismic-Induced Relay Chatter
Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System
Issue 116: Accident Management
Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages
Issue 118: Tendon Anchor Head Failure
Issue 119: Piping Review Committee Recommendations
Issue 120: On-Line Testability of Protection Systems
Issue 121: Hydrogen Control for Large, Dry PWR Containments
Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985 -- Short-Term
Issue 123: Deficiencies in the Regulations Governing DBA and Failure Criterion
Issue 124: Auxiliary Feedwater System Reliability
Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985 -- Long-Term Actions
Issue 126: Reliability of PWR Main Steam Safety Valves
Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems
Issue 128: Electrical Power Reliability
Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling
Issue 130: Essential Service Water Pump Failures at Multiplant Sites
Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants
Issue 132: RHR System Inside Containment
Issue 133: Update Policy Statement -- Nuclear Plant Staff Working Hours
Issue 134: Rule on Degree and Experience Requirement
Issue 135: Steam Generator and Steam Line Overfill
Issue 136: Storage and Use of Large Quantities of Cryogenic Combustibles on site
Issue 137: Refueling Cavity Seal Failure
Issue 138: Deinerting of BWR Mark I and Mark II Containments During Power Operations upon Discovery of RCS Leakage or a Train of a Safety System Inoperable
Issue 139: Thinning of Carbon Steel Piping in LWRs
Issue 140: Fission Product Removal Systems
Issue 141: Large Break LOCA with Consequential SGTR
Issue 142: Leakage through Electrical Isolators in Instrumentation Circuits
Issue 143: Availability of Chilled Water Systems and Room Cooling
Issue 144: Scram without a Turbine/Generator Trip
Issue 145: Actions to Reduce Common Cause Failures
Issue 146: Support Flexibility of Equipment and Components
Issue 147: Fire-Induced Alternate Shutdown/Control Room Panel Interactions
Issue 148: Smoke Control and Manual Fire-Fighting Effectiveness
Issue 149: Adequacy of Fire Barriers
Issue 150: Overpressurization of Containment Penetrations
Issue 151: Reliability of Anticipated Transient without Scram Recirculation Pump Trip in BWRs
Issue 152: Design Basis for Valves that Might be Subjected to Significant Blowdown Loads
Issue 153: Loss of Essential Service Water in LWRs
Issue 154: Adequacy of Emergency and Essential Lighting
Issue 155: Generic Concerns Arising from TMI-2 Cleanup
Issue 156: Systematic Evaluation Program
Issue 157: Containment Performance
Issue 158: Performance of Safety-Related Power-Operated Valves under Design Basis Conditions
Issue 159: Qualification of Safety-Related Pumps While Running on Minimum Flow
Issue 160: Spurious Actuations of Instrumentation upon Restoration of Power
Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits
Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit Is Shutdown
Issue 163: Multiple Steam Generator Tube Leakage
Issue 164: Neutron Fluence in Reactor Vessel
Issue 165: Spring-Actuated Safety and Relief Valve Reliability
Issue 166: Adequacy of Fatigue Life of Metal Components
Issue 167: Hydrogen Storage Facility Separation
Issue 168: Environmental Qualification of Electrical Equipment
Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure
Issue 170: Fuel Damage Criteria for High Burnup Fuel
Issue 171: ESF Failure from Loop Subsequent to a LOCA
Issue 172: Multiple System Responses Program
Issue 173: Spent Fuel Storage Pool
Issue 174: Fastener Gaging Practices
Issue 175: Nuclear Power Plant Shift Staffing
Issue 176: Loss of Fill-Oil in Rosemount Transmitters
Issue 177: Vehicle Intrusion at TMI
Issue 178: Effect of Hurricane andrew on Turkey Point
Issue 179: Core Performance
Issue 180: Notice of Enforcement Discretion
Issue 181: Fire Protection
Issue 182: General Electric Extended Power Uprate
Issue 183: Cycle-Specific Parameter Limits in Technical Specifications
Issue 184: Endangered Species
Issue 185: Control of Recriticality Following Small-Break LOCAs in PWRs
Issue 186: Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants
Issue 187: The Potential Impact of Postulated Cesium Concentration on Equipment Qualification
Issue 188: Steam Generator Tube Leaks or Ruptures, Concurrent with Containment Bypass from Main Steam Line or Feedwater Line Breaches
Issue 189: Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion During a Severe Accident
Issue 190: Fatigue Evaluation of Metal Components for 60-Year Plant Life
Issue 191: Assessment of Debris Accumulation on PWR Sump Performance
Issue 192: Secondary Containment Drawdown Time
Issue 193: BWR ECCS Suction Concerns
Issue 194: Implications of Updated Probabilistic Seismic Hazard Estimates
Issue 195: Hydrogen Combustion in BWR Piping
Issue 196: Boral Degradation
Issue 197: Iodine Spiking Phenomena
Issue 198: Hydrogen Combustion in PWR Piping
Issue 199: Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern U.S. for Existing Plants
Issue 200: Tin Whiskers
Issue 201: Small-Break Loca and Loss of Offsite Power
Issue 202: Spent Fuel Pool Leakage Impacts
Issue 203: Potential Safety Issues with Cranes That Lift Spent Fuel Casks


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Tuesday, August 26, 2008