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HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsStaff ReportsNUREG 0933

#                     Resolution of Generic Safety Issues: Section 3. New Generic Issues ( NUREG-0933, Main Report with Supplements 1–35 )                

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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 (Rev. 2)   
                  -  Issue 3: Set Point Drift in Instrumentation (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 7: Failures Due to Flow-Induced Vibrations (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters   
                  -  Issue 14: PWR Pipe Cracks (Rev. 2)   
                  -  Issue 15: Radiation Effects on Reactor Vessel Supports (Rev. 3)   
                  -  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 (Rev. 1)   
                  -  Issue 21: Vibration Qualification of Equipment (Rev. 2)   
                  -  Issue 22: Inadvertent Boron Dilution Events (Rev. 2)   
                  -  Issue 23: Reactor Coolant Pump Seal Failures (Rev. 1)   
                  -  Issue 24: Automatic ECCS Switchover to Recirculation (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 35: Degradation of Internal Appurtenances in LWRs (Rev. 2)   
                  -  Issue 36: Loss of Service Water (Rev. 3)   
                  -  Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown (Rev. 1)   
                  -  Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris (Rev. 2)   
                  -  Issue 39: Potential for Unacceptable Interaction Between the CRD System and Non-Essential Control Air System (Rev. 1)   
                  -  Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Rev. 1)   
                  -  Issue 41: BWR Scram Discharge Volume Systems   
                  -  Issue 42: Combination Primary/Secondary System LOCA (Rev. 1)   
                  -  Issue 43: Reliability of Air Systems (Rev. 2)   
                  -  Issue 44: Failure of Saltwater Cooling System (Rev. 1)   
                  -  Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather (Rev. 2)   
                  -  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 (Rev. 1)   
                  -  Issue 49: Interlocks and LCOs for Class 1E Tie-Breakers (Rev. 3)   
                  -  Issue 50: Reactor Vessel Level Instrumentation in BWRs (Rev. 1)   
                  -  Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water System (Rev. 1)   
                  -  Issue 52: SSW Flow Blockage by Blue Mussels   
                  -  Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR (Rev. 1)   
                  -  Issue 54: Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980 (Rev. 1)   
                  -  Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand (Rev. 2)   
                  -  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 (Rev. 3)   
                  -  Issue 58: Containment Flooding   
                  -  Issue 59: Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown Is Degraded or Inoperable (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 62: Reactor Systems Bolting Applications (Rev. 1)   
                  -  Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis (Rev. 1)   
                  -  Issue 64: Identification of Protection System Instrument Sensing Lines   
                  -  Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures (Rev. 1)   
                  -  Issue 66: Steam Generator Requirements (Rev. 2)   
                  -  Issue 67: Steam Generator Staff Actions (Rev. 5)   
                  -  Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture (Rev. 3)   
                  -  Issue 69: Make-Up Nozzle Cracking in B&W Plants (Rev. 11)   
                  -  Issue 70: PORV and Block Valve Reliability (Rev. 3)   
                  -  Issue 71: Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety (Rev. 3)   
                  -  Issue 72: Control Rod Drive Guide Tube Support Pin Failures (Rev. 1)   
                  -  Issue 73: Detached Thermal Sleeves (Rev. 3)   
                  -  Issue 74: Reactor Coolant Activity Limits for Operating Reactors (Rev. 1)   
                  -  Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant (Rev. 1)   
                  -  Issue 76: Instrumentation and Control Power Interactions (Rev. 3)   
                  -  Issue 77: Flooding of Safety Equipment Compartments by Backflow Through Floor Drains (Rev. 1)   
                  -  Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System (Rev. 3)   
                  -  Issue 79: Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown (Rev. 3)   
                  -  Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments (Rev. 4)   
                  -  Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety (Rev. 5)   
                  -  Issue 82: Beyond Design Basis Accidents in Spent Fuel Pools (Rev. 3)   
                  -  Issue 83: Control Room Habitability (Rev. 3)   
                  -  Issue 84: CE PORVs (Rev. 2)   
                  -  Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments (Rev. 2)   
                  -  Issue 86: Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping (Rev. 1)   
                  -  Issue 87: Failure of HPCI Steam Line Without Isolation (Rev. 2)   
                  -  Issue 88: Earthquakes and Emergency Planning   
                  -  Issue 89: Stiff Pipe Clamps (Rev. 2)   
                  -  Issue 90: Technical Specifications for Anticipatory Trips (Rev. 2)   
                  -  Issue 91: Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators (Rev. 1)   
                  -  Issue 92: Fuel Crumbling During LOCA (Rev. 1)   
                  -  Issue 93: Steam Binding of Auxiliary Feedwater Pumps (Rev. 1)   
                  -  Issue 94: Additional Low Temperature Overpressure Protection for Light Water Reactors (Rev. 1)   
                  -  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 PWRs (Rev. 3)   
                  -  Issue 100: Once-Through Steam Generator Level (Rev. 1)   
                  -  Issue 101: BWR Water Level Redundancy (Rev. 1)   
                  -  Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train (Rev. 2)   
                  -  Issue 103: Design for Probable Maximum Precipitation (Rev. 1)   
                  -  Issue 104: Reduction of Boron Dilution Requirements   
                  -  Issue 105: Interfacing Systems LOCA at LWRs (Rev. 4)   
                  -  Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas (Rev. 2)   
                  -  Issue 107: Main Transformer Failures (Rev. 3)   
                  -  Issue 108: BWR Suppression Pool Temperature Limits   
                  -  Issue 109: Reactor Vessel Closure Failure   
                  -  Issue 110: Equipment Protective Devices on Engineered Safety Features (Rev. 1)   
                  -  Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments (Rev. 2)   
                  -  Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times   
                  -  Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers (Rev. 2)   
                  -  Issue 114: Seismic-Induced Relay Chatter (Rev. 1)   
                  -  Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System (Rev. 2)   
                  -  Issue 116: Accident Management   
                  -  Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages   
                  -  Issue 118: Tendon Anchor Head Failure (Rev. 1)   
                  -  Issue 119: Piping Review Committee Recommendations (Rev. 4)   
                  -  Issue 120: On-Line Testability of Protection Systems (Rev. 2)   
                  -  Issue 121: Hydrogen Control for Large, Dry PWR Containments (Rev. 2)   
                  -  Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Short-Term Actions (Rev. 4)   
                  -  Issue 123: Deficiencies in the Regulations Governing DBA and Failure Criterion Suggested by the Davis-Besse Incident of June 9, 1985 (Rev. 1)   
                  -  Issue 124: Auxiliary Feedwater System Reliability (Rev. 3)   
                  -  Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Long-Term Actions (Rev. 7)   
                  -  Issue 126: Reliability of PWR Main Steam Safety Valves   
                  -  Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems (Rev. 1)   
                  -  Issue 128: Electrical Power Reliability (Rev. 2)   
                  -  Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling   
                  -  Issue 130: Essential Service Water Pump Failures at Multiplant Sites (Rev. 2)   
                  -  Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants (Rev. 1)   
                  -  Issue 132: RHR System Inside Containment (Rev. 1)   
                  -  Issue 133: Update Policy Statement on Nuclear Plant Staff Working Hours (Rev. 1)   
                  -  Issue 134: Rule on Degree and Experience Requirement (Rev. 1)   
                  -  Issue 135: Steam Generator and Steam Line Overfill (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 139: Thinning of Carbon Steel Piping in LWRs (Rev. 1)   
                  -  Issue 140: Fission Product Removal Systems   
                  -  Issue 141: Large Break LOCA with Consequential SGTR   
                  -  Issue 142: Leakage Through Electrical Isolators in Instrumentation Circuits (Rev. 4)   
                  -  Issue 143: Availability of Chilled Water Systems and Room Cooling (Rev. 2)   
                  -  Issue 144: Scram Without a Turbine/Generator Trip (Rev. 2)   
                  -  Issue 145: Actions to Reduce Common Cause Failures (Rev. 3)   
                  -  Issue 146: Support Flexibility of Equipment and Components (Rev. 2)   
                  -  Issue 147: Fire-Induced Alternate Shutdown/control Room Panel Interactions (Rev. 1)   
                  -  Issue 148: Smoke Control and Manual Fire-fighting Effectiveness 
                  -  Issue 149: Adequacy of Fire Barriers (Rev. 2)   
                  -  Issue 150: Overpressurization of Containment Penetrations (Rev. 1)   
                  -  Issue 151: Reliability of Anticipated Transient Without Scram Recirculatlon Pump Trip in BWRs (Rev. 2)   
                  -  Issue 152: Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads (Rev. 3)   
                  -  Issue 153: Loss of Essential Service Water in LWRs (Rev. 2)   
                  -  Issue 154: Adequacy of Emergency and Essential Lighting (Rev. 2)   
                  -  Issue 155: Generic Concerns Arising from TMI-2 Cleanup (Rev. 3)   
                  -  Issue 156: Systematic Evaluation Program (Rev. 8)   
                  -  Issue 157: Containment Performance (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 160: Spurious Actuations of Instrumentation upon Restoration of Power (Rev. 1)   
                  -  Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits (Rev. 1)   
                  -  Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit is Shut Down (Rev. 1)   
                  -  Issue 163: Multiple Steam Generator Tube Leakage   
                  -  Issue 164: Neutron Fluence in Reactor Vessel (Rev. 1)   
                  -  Issue 165: Spring-Actuated Safety and Relief Valve Reliability (Rev. 2)   
                  -  Issue 166: Adequacy of Fatigue Life of Metal Components (Rev. 2)   
                  -  Issue 167: Hydrogen Storage Facility Separation (Rev. 2)   
                  -  Issue 168: Environmental Qualification of Electrical Equipment (Rev. 3)   
                  -  Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure (Rev. 1)   
                  -  Issue 170: Fuel Damage Criteria for High Burnup Fuel (Rev. 2)   
                  -  Issue 171: ESF Failure from Loop Subsequent to a LOCA (Rev. 1)   
                  -  Issue 172: Multiple System Responses Program (Rev. 2)   
                  -  Issue 173: Spent Fuel Storage Pool (Rev. 4)   
                  -  Issue 174: Fastener Gaging Practices (Rev. 1)   
                  -  Issue 175: Nuclear Power Plant Shift Staffing (Rev. 1)   
                  -  Issue 176: Loss of Fill-Oil in Rosemount Transmitters (Rev. 1)   
                  -  Issue 177: Vehicle Intrusion at TMI   
                  -  Issue 178: Effect of Hurricane Andrew on Turkey Point (Rev. 2)   
                  -  Issue 179: Core Performance   
                  -  Issue 180: Notice of Enforcement Discretion (Rev. 1)   
                  -  Issue 181: Fire Protection (Rev. 2)   
                  -  Issue 182: General Electric Extended Power Uprate (Rev. 1)   
                  -  Issue 183: Cycle-Specific Parameter Limits in Technical Specifications (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 191: Assessment of Debris Accumulation on PWR Sump Performance 
                  -  Issue 192: Secondary Containment Drawdown Time   
                  -  Issue 193: BWR ECCS Suction Concerns Description   
                  -  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   
                  -  ISSUE 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES 

**Contents**                  -  Issue 1: Failures in Air-Monitoring, Air-Cleaning, and Ventilating Systems   
                  -  Issue 2: Failure of Protective Devices on Essential Equipment (Rev. 2)   
                  -  Issue 3: Set Point Drift in Instrumentation (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 7: Failures Due to Flow-Induced Vibrations (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters   
                  -  Issue 14: PWR Pipe Cracks (Rev. 2)   
                  -  Issue 15: Radiation Effects on Reactor Vessel Supports (Rev. 3)   
                  -  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 (Rev. 1)   
                  -  Issue 21: Vibration Qualification of Equipment (Rev. 2)   
                  -  Issue 22: Inadvertent Boron Dilution Events (Rev. 2)   
                  -  Issue 23: Reactor Coolant Pump Seal Failures (Rev. 1)   
                  -  Issue 24: Automatic ECCS Switchover to Recirculation (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 35: Degradation of Internal Appurtenances in LWRs (Rev. 2)   
                  -  Issue 36: Loss of Service Water (Rev. 3)   
                  -  Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown (Rev. 1)   
                  -  Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris (Rev. 2)   
                  -  Issue 39: Potential for Unacceptable Interaction Between the CRD System and Non-Essential Control Air System (Rev. 1)   
                  -  Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Rev. 1)   
                  -  Issue 41: BWR Scram Discharge Volume Systems   
                  -  Issue 42: Combination Primary/Secondary System LOCA (Rev. 1)   
                  -  Issue 43: Reliability of Air Systems (Rev. 2)   
                  -  Issue 44: Failure of Saltwater Cooling System (Rev. 1)   
                  -  Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather (Rev. 2)   
                  -  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 (Rev. 1)   
                  -  Issue 49: Interlocks and LCOs for Class 1E Tie-Breakers (Rev. 3)   
                  -  Issue 50: Reactor Vessel Level Instrumentation in BWRs (Rev. 1)   
                  -  Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water System (Rev. 1)   
                  -  Issue 52: SSW Flow Blockage by Blue Mussels   
                  -  Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR (Rev. 1)   
                  -  Issue 54: Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980 (Rev. 1)   
                  -  Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand (Rev. 2)   
                  -  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 (Rev. 3)   
                  -  Issue 58: Containment Flooding   
                  -  Issue 59: Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown Is Degraded or Inoperable (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 62: Reactor Systems Bolting Applications (Rev. 1)   
                  -  Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis (Rev. 1)   
                  -  Issue 64: Identification of Protection System Instrument Sensing Lines   
                  -  Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures (Rev. 1)   
                  -  Issue 66: Steam Generator Requirements (Rev. 2)   
                  -  Issue 67: Steam Generator Staff Actions (Rev. 5)   
                  -  Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture (Rev. 3)   
                  -  Issue 69: Make-Up Nozzle Cracking in B&W Plants (Rev. 11)   
                  -  Issue 70: PORV and Block Valve Reliability (Rev. 3)   
                  -  Issue 71: Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety (Rev. 3)   
                  -  Issue 72: Control Rod Drive Guide Tube Support Pin Failures (Rev. 1)   
                  -  Issue 73: Detached Thermal Sleeves (Rev. 3)   
                  -  Issue 74: Reactor Coolant Activity Limits for Operating Reactors (Rev. 1)   
                  -  Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant (Rev. 1)   
                  -  Issue 76: Instrumentation and Control Power Interactions (Rev. 3)   
                  -  Issue 77: Flooding of Safety Equipment Compartments by Backflow Through Floor Drains (Rev. 1)   
                  -  Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System (Rev. 3)   
                  -  Issue 79: Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown (Rev. 3)   
                  -  Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments (Rev. 4)   
                  -  Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety (Rev. 5)   
                  -  Issue 82: Beyond Design Basis Accidents in Spent Fuel Pools (Rev. 3)   
                  -  Issue 83: Control Room Habitability (Rev. 3)   
                  -  Issue 84: CE PORVs (Rev. 2)   
                  -  Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments (Rev. 2)   
                  -  Issue 86: Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping (Rev. 1)   
                  -  Issue 87: Failure of HPCI Steam Line Without Isolation (Rev. 2)   
                  -  Issue 88: Earthquakes and Emergency Planning   
                  -  Issue 89: Stiff Pipe Clamps (Rev. 2)   
                  -  Issue 90: Technical Specifications for Anticipatory Trips (Rev. 2)   
                  -  Issue 91: Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators (Rev. 1)   
                  -  Issue 92: Fuel Crumbling During LOCA (Rev. 1)   
                  -  Issue 93: Steam Binding of Auxiliary Feedwater Pumps (Rev. 1)   
                  -  Issue 94: Additional Low Temperature Overpressure Protection for Light Water Reactors (Rev. 1)   
                  -  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 PWRs (Rev. 3)   
                  -  Issue 100: Once-Through Steam Generator Level (Rev. 1)   
                  -  Issue 101: BWR Water Level Redundancy (Rev. 1)   
                  -  Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train (Rev. 2)   
                  -  Issue 103: Design for Probable Maximum Precipitation (Rev. 1)   
                  -  Issue 104: Reduction of Boron Dilution Requirements   
                  -  Issue 105: Interfacing Systems LOCA at LWRs (Rev. 4)   
                  -  Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas (Rev. 2)   
                  -  Issue 107: Main Transformer Failures (Rev. 3)   
                  -  Issue 108: BWR Suppression Pool Temperature Limits   
                  -  Issue 109: Reactor Vessel Closure Failure   
                  -  Issue 110: Equipment Protective Devices on Engineered Safety Features (Rev. 1)   
                  -  Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments (Rev. 2)   
                  -  Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times   
                  -  Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers (Rev. 2)   
                  -  Issue 114: Seismic-Induced Relay Chatter (Rev. 1)   
                  -  Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System (Rev. 2)   
                  -  Issue 116: Accident Management   
                  -  Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages   
                  -  Issue 118: Tendon Anchor Head Failure (Rev. 1)   
                  -  Issue 119: Piping Review Committee Recommendations (Rev. 4)   
                  -  Issue 120: On-Line Testability of Protection Systems (Rev. 2)   
                  -  Issue 121: Hydrogen Control for Large, Dry PWR Containments (Rev. 2)   
                  -  Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Short-Term Actions (Rev. 4)   
                  -  Issue 123: Deficiencies in the Regulations Governing DBA and Failure Criterion Suggested by the Davis-Besse Incident of June 9, 1985 (Rev. 1)   
                  -  Issue 124: Auxiliary Feedwater System Reliability (Rev. 3)   
                  -  Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Long-Term Actions (Rev. 7)   
                  -  Issue 126: Reliability of PWR Main Steam Safety Valves   
                  -  Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems (Rev. 1)   
                  -  Issue 128: Electrical Power Reliability (Rev. 2)   
                  -  Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling   
                  -  Issue 130: Essential Service Water Pump Failures at Multiplant Sites (Rev. 2)   
                  -  Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants (Rev. 1)   
                  -  Issue 132: RHR System Inside Containment (Rev. 1)   
                  -  Issue 133: Update Policy Statement on Nuclear Plant Staff Working Hours (Rev. 1)   
                  -  Issue 134: Rule on Degree and Experience Requirement (Rev. 1)   
                  -  Issue 135: Steam Generator and Steam Line Overfill (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 139: Thinning of Carbon Steel Piping in LWRs (Rev. 1)   
                  -  Issue 140: Fission Product Removal Systems   
                  -  Issue 141: Large Break LOCA with Consequential SGTR   
                  -  Issue 142: Leakage Through Electrical Isolators in Instrumentation Circuits (Rev. 4)   
                  -  Issue 143: Availability of Chilled Water Systems and Room Cooling (Rev. 2)   
                  -  Issue 144: Scram Without a Turbine/Generator Trip (Rev. 2)   
                  -  Issue 145: Actions to Reduce Common Cause Failures (Rev. 3)   
                  -  Issue 146: Support Flexibility of Equipment and Components (Rev. 2)   
                  -  Issue 147: Fire-Induced Alternate Shutdown/control Room Panel Interactions (Rev. 1)   
                  -  Issue 148: Smoke Control and Manual Fire-fighting Effectiveness 
                  -  Issue 149: Adequacy of Fire Barriers (Rev. 2)   
                  -  Issue 150: Overpressurization of Containment Penetrations (Rev. 1)   
                  -  Issue 151: Reliability of Anticipated Transient Without Scram Recirculatlon Pump Trip in BWRs (Rev. 2)   
                  -  Issue 152: Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads (Rev. 3)   
                  -  Issue 153: Loss of Essential Service Water in LWRs (Rev. 2)   
                  -  Issue 154: Adequacy of Emergency and Essential Lighting (Rev. 2)   
                  -  Issue 155: Generic Concerns Arising from TMI-2 Cleanup (Rev. 3)   
                  -  Issue 156: Systematic Evaluation Program (Rev. 8)   
                  -  Issue 157: Containment Performance (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 160: Spurious Actuations of Instrumentation upon Restoration of Power (Rev. 1)   
                  -  Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits (Rev. 1)   
                  -  Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit is Shut Down (Rev. 1)   
                  -  Issue 163: Multiple Steam Generator Tube Leakage   
                  -  Issue 164: Neutron Fluence in Reactor Vessel (Rev. 1)   
                  -  Issue 165: Spring-Actuated Safety and Relief Valve Reliability (Rev. 2)   
                  -  Issue 166: Adequacy of Fatigue Life of Metal Components (Rev. 2)   
                  -  Issue 167: Hydrogen Storage Facility Separation (Rev. 2)   
                  -  Issue 168: Environmental Qualification of Electrical Equipment (Rev. 3)   
                  -  Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure (Rev. 1)   
                  -  Issue 170: Fuel Damage Criteria for High Burnup Fuel (Rev. 2)   
                  -  Issue 171: ESF Failure from Loop Subsequent to a LOCA (Rev. 1)   
                  -  Issue 172: Multiple System Responses Program (Rev. 2)   
                  -  Issue 173: Spent Fuel Storage Pool (Rev. 4)   
                  -  Issue 174: Fastener Gaging Practices (Rev. 1)   
                  -  Issue 175: Nuclear Power Plant Shift Staffing (Rev. 1)   
                  -  Issue 176: Loss of Fill-Oil in Rosemount Transmitters (Rev. 1)   
                  -  Issue 177: Vehicle Intrusion at TMI   
                  -  Issue 178: Effect of Hurricane Andrew on Turkey Point (Rev. 2)   
                  -  Issue 179: Core Performance   
                  -  Issue 180: Notice of Enforcement Discretion (Rev. 1)   
                  -  Issue 181: Fire Protection (Rev. 2)   
                  -  Issue 182: General Electric Extended Power Uprate (Rev. 1)   
                  -  Issue 183: Cycle-Specific Parameter Limits in Technical Specifications (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 191: Assessment of Debris Accumulation on PWR Sump Performance 
                  -  Issue 192: Secondary Containment Drawdown Time   
                  -  Issue 193: BWR ECCS Suction Concerns Description   
                  -  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   
                  -  ISSUE 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES 

**Contents**                  -  Issue 1: Failures in Air-Monitoring, Air-Cleaning, and Ventilating Systems   
                  -  Issue 2: Failure of Protective Devices on Essential Equipment (Rev. 2)   
                  -  Issue 3: Set Point Drift in Instrumentation (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 7: Failures Due to Flow-Induced Vibrations (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters   
                  -  Issue 14: PWR Pipe Cracks (Rev. 2)   
                  -  Issue 15: Radiation Effects on Reactor Vessel Supports (Rev. 3)   
                  -  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 (Rev. 1)   
                  -  Issue 21: Vibration Qualification of Equipment (Rev. 2)   
                  -  Issue 22: Inadvertent Boron Dilution Events (Rev. 2)   
                  -  Issue 23: Reactor Coolant Pump Seal Failures (Rev. 1)   
                  -  Issue 24: Automatic ECCS Switchover to Recirculation (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 35: Degradation of Internal Appurtenances in LWRs (Rev. 2)   
                  -  Issue 36: Loss of Service Water (Rev. 3)   
                  -  Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown (Rev. 1)   
                  -  Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris (Rev. 2)   
                  -  Issue 39: Potential for Unacceptable Interaction Between the CRD System and Non-Essential Control Air System (Rev. 1)   
                  -  Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Rev. 1)   
                  -  Issue 41: BWR Scram Discharge Volume Systems   
                  -  Issue 42: Combination Primary/Secondary System LOCA (Rev. 1)   
                  -  Issue 43: Reliability of Air Systems (Rev. 2)   
                  -  Issue 44: Failure of Saltwater Cooling System (Rev. 1)   
                  -  Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather (Rev. 2)   
                  -  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 (Rev. 1)   
                  -  Issue 49: Interlocks and LCOs for Class 1E Tie-Breakers (Rev. 3)   
                  -  Issue 50: Reactor Vessel Level Instrumentation in BWRs (Rev. 1)   
                  -  Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water System (Rev. 1)   
                  -  Issue 52: SSW Flow Blockage by Blue Mussels   
                  -  Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR (Rev. 1)   
                  -  Issue 54: Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980 (Rev. 1)   
                  -  Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand (Rev. 2)   
                  -  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 (Rev. 3)   
                  -  Issue 58: Containment Flooding   
                  -  Issue 59: Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown Is Degraded or Inoperable (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 62: Reactor Systems Bolting Applications (Rev. 1)   
                  -  Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis (Rev. 1)   
                  -  Issue 64: Identification of Protection System Instrument Sensing Lines   
                  -  Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures (Rev. 1)   
                  -  Issue 66: Steam Generator Requirements (Rev. 2)   
                  -  Issue 67: Steam Generator Staff Actions (Rev. 5)   
                  -  Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture (Rev. 3)   
                  -  Issue 69: Make-Up Nozzle Cracking in B&W Plants (Rev. 11)   
                  -  Issue 70: PORV and Block Valve Reliability (Rev. 3)   
                  -  Issue 71: Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety (Rev. 3)   
                  -  Issue 72: Control Rod Drive Guide Tube Support Pin Failures (Rev. 1)   
                  -  Issue 73: Detached Thermal Sleeves (Rev. 3)   
                  -  Issue 74: Reactor Coolant Activity Limits for Operating Reactors (Rev. 1)   
                  -  Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant (Rev. 1)   
                  -  Issue 76: Instrumentation and Control Power Interactions (Rev. 3)   
                  -  Issue 77: Flooding of Safety Equipment Compartments by Backflow Through Floor Drains (Rev. 1)   
                  -  Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System (Rev. 3)   
                  -  Issue 79: Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown (Rev. 3)   
                  -  Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments (Rev. 4)   
                  -  Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety (Rev. 5)   
                  -  Issue 82: Beyond Design Basis Accidents in Spent Fuel Pools (Rev. 3)   
                  -  Issue 83: Control Room Habitability (Rev. 3)   
                  -  Issue 84: CE PORVs (Rev. 2)   
                  -  Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments (Rev. 2)   
                  -  Issue 86: Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping (Rev. 1)   
                  -  Issue 87: Failure of HPCI Steam Line Without Isolation (Rev. 2)   
                  -  Issue 88: Earthquakes and Emergency Planning   
                  -  Issue 89: Stiff Pipe Clamps (Rev. 2)   
                  -  Issue 90: Technical Specifications for Anticipatory Trips (Rev. 2)   
                  -  Issue 91: Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators (Rev. 1)   
                  -  Issue 92: Fuel Crumbling During LOCA (Rev. 1)   
                  -  Issue 93: Steam Binding of Auxiliary Feedwater Pumps (Rev. 1)   
                  -  Issue 94: Additional Low Temperature Overpressure Protection for Light Water Reactors (Rev. 1)   
                  -  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 PWRs (Rev. 3)   
                  -  Issue 100: Once-Through Steam Generator Level (Rev. 1)   
                  -  Issue 101: BWR Water Level Redundancy (Rev. 1)   
                  -  Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train (Rev. 2)   
                  -  Issue 103: Design for Probable Maximum Precipitation (Rev. 1)   
                  -  Issue 104: Reduction of Boron Dilution Requirements   
                  -  Issue 105: Interfacing Systems LOCA at LWRs (Rev. 4)   
                  -  Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas (Rev. 2)   
                  -  Issue 107: Main Transformer Failures (Rev. 3)   
                  -  Issue 108: BWR Suppression Pool Temperature Limits   
                  -  Issue 109: Reactor Vessel Closure Failure   
                  -  Issue 110: Equipment Protective Devices on Engineered Safety Features (Rev. 1)   
                  -  Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments (Rev. 2)   
                  -  Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times   
                  -  Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers (Rev. 2)   
                  -  Issue 114: Seismic-Induced Relay Chatter (Rev. 1)   
                  -  Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System (Rev. 2)   
                  -  Issue 116: Accident Management   
                  -  Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages   
                  -  Issue 118: Tendon Anchor Head Failure (Rev. 1)   
                  -  Issue 119: Piping Review Committee Recommendations (Rev. 4)   
                  -  Issue 120: On-Line Testability of Protection Systems (Rev. 2)   
                  -  Issue 121: Hydrogen Control for Large, Dry PWR Containments (Rev. 2)   
                  -  Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Short-Term Actions (Rev. 4)   
                  -  Issue 123: Deficiencies in the Regulations Governing DBA and Failure Criterion Suggested by the Davis-Besse Incident of June 9, 1985 (Rev. 1)   
                  -  Issue 124: Auxiliary Feedwater System Reliability (Rev. 3)   
                  -  Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Long-Term Actions (Rev. 7)   
                  -  Issue 126: Reliability of PWR Main Steam Safety Valves   
                  -  Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems (Rev. 1)   
                  -  Issue 128: Electrical Power Reliability (Rev. 2)   
                  -  Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling   
                  -  Issue 130: Essential Service Water Pump Failures at Multiplant Sites (Rev. 2)   
                  -  Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants (Rev. 1)   
                  -  Issue 132: RHR System Inside Containment (Rev. 1)   
                  -  Issue 133: Update Policy Statement on Nuclear Plant Staff Working Hours (Rev. 1)   
                  -  Issue 134: Rule on Degree and Experience Requirement (Rev. 1)   
                  -  Issue 135: Steam Generator and Steam Line Overfill (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 139: Thinning of Carbon Steel Piping in LWRs (Rev. 1)   
                  -  Issue 140: Fission Product Removal Systems   
                  -  Issue 141: Large Break LOCA with Consequential SGTR   
                  -  Issue 142: Leakage Through Electrical Isolators in Instrumentation Circuits (Rev. 4)   
                  -  Issue 143: Availability of Chilled Water Systems and Room Cooling (Rev. 2)   
                  -  Issue 144: Scram Without a Turbine/Generator Trip (Rev. 2)   
                  -  Issue 145: Actions to Reduce Common Cause Failures (Rev. 3)   
                  -  Issue 146: Support Flexibility of Equipment and Components (Rev. 2)   
                  -  Issue 147: Fire-Induced Alternate Shutdown/control Room Panel Interactions (Rev. 1)   
                  -  Issue 148: Smoke Control and Manual Fire-fighting Effectiveness 
                  -  Issue 149: Adequacy of Fire Barriers (Rev. 2)   
                  -  Issue 150: Overpressurization of Containment Penetrations (Rev. 1)   
                  -  Issue 151: Reliability of Anticipated Transient Without Scram Recirculatlon Pump Trip in BWRs (Rev. 2)   
                  -  Issue 152: Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads (Rev. 3)   
                  -  Issue 153: Loss of Essential Service Water in LWRs (Rev. 2)   
                  -  Issue 154: Adequacy of Emergency and Essential Lighting (Rev. 2)   
                  -  Issue 155: Generic Concerns Arising from TMI-2 Cleanup (Rev. 3)   
                  -  Issue 156: Systematic Evaluation Program (Rev. 8)   
                  -  Issue 157: Containment Performance (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 160: Spurious Actuations of Instrumentation upon Restoration of Power (Rev. 1)   
                  -  Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits (Rev. 1)   
                  -  Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit is Shut Down (Rev. 1)   
                  -  Issue 163: Multiple Steam Generator Tube Leakage   
                  -  Issue 164: Neutron Fluence in Reactor Vessel (Rev. 1)   
                  -  Issue 165: Spring-Actuated Safety and Relief Valve Reliability (Rev. 2)   
                  -  Issue 166: Adequacy of Fatigue Life of Metal Components (Rev. 2)   
                  -  Issue 167: Hydrogen Storage Facility Separation (Rev. 2)   
                  -  Issue 168: Environmental Qualification of Electrical Equipment (Rev. 3)   
                  -  Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure (Rev. 1)   
                  -  Issue 170: Fuel Damage Criteria for High Burnup Fuel (Rev. 2)   
                  -  Issue 171: ESF Failure from Loop Subsequent to a LOCA (Rev. 1)   
                  -  Issue 172: Multiple System Responses Program (Rev. 2)   
                  -  Issue 173: Spent Fuel Storage Pool (Rev. 4)   
                  -  Issue 174: Fastener Gaging Practices (Rev. 1)   
                  -  Issue 175: Nuclear Power Plant Shift Staffing (Rev. 1)   
                  -  Issue 176: Loss of Fill-Oil in Rosemount Transmitters (Rev. 1)   
                  -  Issue 177: Vehicle Intrusion at TMI   
                  -  Issue 178: Effect of Hurricane Andrew on Turkey Point (Rev. 2)   
                  -  Issue 179: Core Performance   
                  -  Issue 180: Notice of Enforcement Discretion (Rev. 1)   
                  -  Issue 181: Fire Protection (Rev. 2)   
                  -  Issue 182: General Electric Extended Power Uprate (Rev. 1)   
                  -  Issue 183: Cycle-Specific Parameter Limits in Technical Specifications (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 191: Assessment of Debris Accumulation on PWR Sump Performance 
                  -  Issue 192: Secondary Containment Drawdown Time   
                  -  Issue 193: BWR ECCS Suction Concerns Description   
                  -  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   
                  -  ISSUE 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES 

**Contents**                  -  Issue 1: Failures in Air-Monitoring, Air-Cleaning, and Ventilating Systems   
                  -  Issue 2: Failure of Protective Devices on Essential Equipment (Rev. 2)   
                  -  Issue 3: Set Point Drift in Instrumentation (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 7: Failures Due to Flow-Induced Vibrations (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters   
                  -  Issue 14: PWR Pipe Cracks (Rev. 2)   
                  -  Issue 15: Radiation Effects on Reactor Vessel Supports (Rev. 3)   
                  -  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 (Rev. 1)   
                  -  Issue 21: Vibration Qualification of Equipment (Rev. 2)   
                  -  Issue 22: Inadvertent Boron Dilution Events (Rev. 2)   
                  -  Issue 23: Reactor Coolant Pump Seal Failures (Rev. 1)   
                  -  Issue 24: Automatic ECCS Switchover to Recirculation (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 35: Degradation of Internal Appurtenances in LWRs (Rev. 2)   
                  -  Issue 36: Loss of Service Water (Rev. 3)   
                  -  Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown (Rev. 1)   
                  -  Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris (Rev. 2)   
                  -  Issue 39: Potential for Unacceptable Interaction Between the CRD System and Non-Essential Control Air System (Rev. 1)   
                  -  Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Rev. 1)   
                  -  Issue 41: BWR Scram Discharge Volume Systems   
                  -  Issue 42: Combination Primary/Secondary System LOCA (Rev. 1)   
                  -  Issue 43: Reliability of Air Systems (Rev. 2)   
                  -  Issue 44: Failure of Saltwater Cooling System (Rev. 1)   
                  -  Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather (Rev. 2)   
                  -  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 (Rev. 1)   
                  -  Issue 49: Interlocks and LCOs for Class 1E Tie-Breakers (Rev. 3)   
                  -  Issue 50: Reactor Vessel Level Instrumentation in BWRs (Rev. 1)   
                  -  Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water System (Rev. 1)   
                  -  Issue 52: SSW Flow Blockage by Blue Mussels   
                  -  Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR (Rev. 1)   
                  -  Issue 54: Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980 (Rev. 1)   
                  -  Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand (Rev. 2)   
                  -  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 (Rev. 3)   
                  -  Issue 58: Containment Flooding   
                  -  Issue 59: Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown Is Degraded or Inoperable (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 62: Reactor Systems Bolting Applications (Rev. 1)   
                  -  Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis (Rev. 1)   
                  -  Issue 64: Identification of Protection System Instrument Sensing Lines   
                  -  Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures (Rev. 1)   
                  -  Issue 66: Steam Generator Requirements (Rev. 2)   
                  -  Issue 67: Steam Generator Staff Actions (Rev. 5)   
                  -  Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture (Rev. 3)   
                  -  Issue 69: Make-Up Nozzle Cracking in B&W Plants (Rev. 11)   
                  -  Issue 70: PORV and Block Valve Reliability (Rev. 3)   
                  -  Issue 71: Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety (Rev. 3)   
                  -  Issue 72: Control Rod Drive Guide Tube Support Pin Failures (Rev. 1)   
                  -  Issue 73: Detached Thermal Sleeves (Rev. 3)   
                  -  Issue 74: Reactor Coolant Activity Limits for Operating Reactors (Rev. 1)   
                  -  Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant (Rev. 1)   
                  -  Issue 76: Instrumentation and Control Power Interactions (Rev. 3)   
                  -  Issue 77: Flooding of Safety Equipment Compartments by Backflow Through Floor Drains (Rev. 1)   
                  -  Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System (Rev. 3)   
                  -  Issue 79: Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown (Rev. 3)   
                  -  Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments (Rev. 4)   
                  -  Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety (Rev. 5)   
                  -  Issue 82: Beyond Design Basis Accidents in Spent Fuel Pools (Rev. 3)   
                  -  Issue 83: Control Room Habitability (Rev. 3)   
                  -  Issue 84: CE PORVs (Rev. 2)   
                  -  Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments (Rev. 2)   
                  -  Issue 86: Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping (Rev. 1)   
                  -  Issue 87: Failure of HPCI Steam Line Without Isolation (Rev. 2)   
                  -  Issue 88: Earthquakes and Emergency Planning   
                  -  Issue 89: Stiff Pipe Clamps (Rev. 2)   
                  -  Issue 90: Technical Specifications for Anticipatory Trips (Rev. 2)   
                  -  Issue 91: Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators (Rev. 1)   
                  -  Issue 92: Fuel Crumbling During LOCA (Rev. 1)   
                  -  Issue 93: Steam Binding of Auxiliary Feedwater Pumps (Rev. 1)   
                  -  Issue 94: Additional Low Temperature Overpressure Protection for Light Water Reactors (Rev. 1)   
                  -  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 PWRs (Rev. 3)   
                  -  Issue 100: Once-Through Steam Generator Level (Rev. 1)   
                  -  Issue 101: BWR Water Level Redundancy (Rev. 1)   
                  -  Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train (Rev. 2)   
                  -  Issue 103: Design for Probable Maximum Precipitation (Rev. 1)   
                  -  Issue 104: Reduction of Boron Dilution Requirements   
                  -  Issue 105: Interfacing Systems LOCA at LWRs (Rev. 4)   
                  -  Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas (Rev. 2)   
                  -  Issue 107: Main Transformer Failures (Rev. 3)   
                  -  Issue 108: BWR Suppression Pool Temperature Limits   
                  -  Issue 109: Reactor Vessel Closure Failure   
                  -  Issue 110: Equipment Protective Devices on Engineered Safety Features (Rev. 1)   
                  -  Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments (Rev. 2)   
                  -  Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times   
                  -  Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers (Rev. 2)   
                  -  Issue 114: Seismic-Induced Relay Chatter (Rev. 1)   
                  -  Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System (Rev. 2)   
                  -  Issue 116: Accident Management   
                  -  Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages   
                  -  Issue 118: Tendon Anchor Head Failure (Rev. 1)   
                  -  Issue 119: Piping Review Committee Recommendations (Rev. 4)   
                  -  Issue 120: On-Line Testability of Protection Systems (Rev. 2)   
                  -  Issue 121: Hydrogen Control for Large, Dry PWR Containments (Rev. 2)   
                  -  Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Short-Term Actions (Rev. 4)   
                  -  Issue 123: Deficiencies in the Regulations Governing DBA and Failure Criterion Suggested by the Davis-Besse Incident of June 9, 1985 (Rev. 1)   
                  -  Issue 124: Auxiliary Feedwater System Reliability (Rev. 3)   
                  -  Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Long-Term Actions (Rev. 7)   
                  -  Issue 126: Reliability of PWR Main Steam Safety Valves   
                  -  Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems (Rev. 1)   
                  -  Issue 128: Electrical Power Reliability (Rev. 2)   
                  -  Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling   
                  -  Issue 130: Essential Service Water Pump Failures at Multiplant Sites (Rev. 2)   
                  -  Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants (Rev. 1)   
                  -  Issue 132: RHR System Inside Containment (Rev. 1)   
                  -  Issue 133: Update Policy Statement on Nuclear Plant Staff Working Hours (Rev. 1)   
                  -  Issue 134: Rule on Degree and Experience Requirement (Rev. 1)   
                  -  Issue 135: Steam Generator and Steam Line Overfill (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 139: Thinning of Carbon Steel Piping in LWRs (Rev. 1)   
                  -  Issue 140: Fission Product Removal Systems   
                  -  Issue 141: Large Break LOCA with Consequential SGTR   
                  -  Issue 142: Leakage Through Electrical Isolators in Instrumentation Circuits (Rev. 4)   
                  -  Issue 143: Availability of Chilled Water Systems and Room Cooling (Rev. 2)   
                  -  Issue 144: Scram Without a Turbine/Generator Trip (Rev. 2)   
                  -  Issue 145: Actions to Reduce Common Cause Failures (Rev. 3)   
                  -  Issue 146: Support Flexibility of Equipment and Components (Rev. 2)   
                  -  Issue 147: Fire-Induced Alternate Shutdown/control Room Panel Interactions (Rev. 1)   
                  -  Issue 148: Smoke Control and Manual Fire-fighting Effectiveness 
                  -  Issue 149: Adequacy of Fire Barriers (Rev. 2)   
                  -  Issue 150: Overpressurization of Containment Penetrations (Rev. 1)   
                  -  Issue 151: Reliability of Anticipated Transient Without Scram Recirculatlon Pump Trip in BWRs (Rev. 2)   
                  -  Issue 152: Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads (Rev. 3)   
                  -  Issue 153: Loss of Essential Service Water in LWRs (Rev. 2)   
                  -  Issue 154: Adequacy of Emergency and Essential Lighting (Rev. 2)   
                  -  Issue 155: Generic Concerns Arising from TMI-2 Cleanup (Rev. 3)   
                  -  Issue 156: Systematic Evaluation Program (Rev. 8)   
                  -  Issue 157: Containment Performance (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 160: Spurious Actuations of Instrumentation upon Restoration of Power (Rev. 1)   
                  -  Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits (Rev. 1)   
                  -  Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit is Shut Down (Rev. 1)   
                  -  Issue 163: Multiple Steam Generator Tube Leakage   
                  -  Issue 164: Neutron Fluence in Reactor Vessel (Rev. 1)   
                  -  Issue 165: Spring-Actuated Safety and Relief Valve Reliability (Rev. 2)   
                  -  Issue 166: Adequacy of Fatigue Life of Metal Components (Rev. 2)   
                  -  Issue 167: Hydrogen Storage Facility Separation (Rev. 2)   
                  -  Issue 168: Environmental Qualification of Electrical Equipment (Rev. 3)   
                  -  Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure (Rev. 1)   
                  -  Issue 170: Fuel Damage Criteria for High Burnup Fuel (Rev. 2)   
                  -  Issue 171: ESF Failure from Loop Subsequent to a LOCA (Rev. 1)   
                  -  Issue 172: Multiple System Responses Program (Rev. 2)   
                  -  Issue 173: Spent Fuel Storage Pool (Rev. 4)   
                  -  Issue 174: Fastener Gaging Practices (Rev. 1)   
                  -  Issue 175: Nuclear Power Plant Shift Staffing (Rev. 1)   
                  -  Issue 176: Loss of Fill-Oil in Rosemount Transmitters (Rev. 1)   
                  -  Issue 177: Vehicle Intrusion at TMI   
                  -  Issue 178: Effect of Hurricane Andrew on Turkey Point (Rev. 2)   
                  -  Issue 179: Core Performance   
                  -  Issue 180: Notice of Enforcement Discretion (Rev. 1)   
                  -  Issue 181: Fire Protection (Rev. 2)   
                  -  Issue 182: General Electric Extended Power Uprate (Rev. 1)   
                  -  Issue 183: Cycle-Specific Parameter Limits in Technical Specifications (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 191: Assessment of Debris Accumulation on PWR Sump Performance 
                  -  Issue 192: Secondary Containment Drawdown Time   
                  -  Issue 193: BWR ECCS Suction Concerns Description   
                  -  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   
                  -  ISSUE 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES 

**Contents**                  -  Issue 1: Failures in Air-Monitoring, Air-Cleaning, and Ventilating Systems   
                  -  Issue 2: Failure of Protective Devices on Essential Equipment (Rev. 2)   
                  -  Issue 3: Set Point Drift in Instrumentation (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 7: Failures Due to Flow-Induced Vibrations (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters   
                  -  Issue 14: PWR Pipe Cracks (Rev. 2)   
                  -  Issue 15: Radiation Effects on Reactor Vessel Supports (Rev. 3)   
                  -  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 (Rev. 1)   
                  -  Issue 21: Vibration Qualification of Equipment (Rev. 2)   
                  -  Issue 22: Inadvertent Boron Dilution Events (Rev. 2)   
                  -  Issue 23: Reactor Coolant Pump Seal Failures (Rev. 1)   
                  -  Issue 24: Automatic ECCS Switchover to Recirculation (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 35: Degradation of Internal Appurtenances in LWRs (Rev. 2)   
                  -  Issue 36: Loss of Service Water (Rev. 3)   
                  -  Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown (Rev. 1)   
                  -  Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris (Rev. 2)   
                  -  Issue 39: Potential for Unacceptable Interaction Between the CRD System and Non-Essential Control Air System (Rev. 1)   
                  -  Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Rev. 1)   
                  -  Issue 41: BWR Scram Discharge Volume Systems   
                  -  Issue 42: Combination Primary/Secondary System LOCA (Rev. 1)   
                  -  Issue 43: Reliability of Air Systems (Rev. 2)   
                  -  Issue 44: Failure of Saltwater Cooling System (Rev. 1)   
                  -  Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather (Rev. 2)   
                  -  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 (Rev. 1)   
                  -  Issue 49: Interlocks and LCOs for Class 1E Tie-Breakers (Rev. 3)   
                  -  Issue 50: Reactor Vessel Level Instrumentation in BWRs (Rev. 1)   
                  -  Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water System (Rev. 1)   
                  -  Issue 52: SSW Flow Blockage by Blue Mussels   
                  -  Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR (Rev. 1)   
                  -  Issue 54: Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980 (Rev. 1)   
                  -  Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand (Rev. 2)   
                  -  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 (Rev. 3)   
                  -  Issue 58: Containment Flooding   
                  -  Issue 59: Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown Is Degraded or Inoperable (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 62: Reactor Systems Bolting Applications (Rev. 1)   
                  -  Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis (Rev. 1)   
                  -  Issue 64: Identification of Protection System Instrument Sensing Lines   
                  -  Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures (Rev. 1)   
                  -  Issue 66: Steam Generator Requirements (Rev. 2)   
                  -  Issue 67: Steam Generator Staff Actions (Rev. 5)   
                  -  Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture (Rev. 3)   
                  -  Issue 69: Make-Up Nozzle Cracking in B&W Plants (Rev. 11)   
                  -  Issue 70: PORV and Block Valve Reliability (Rev. 3)   
                  -  Issue 71: Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety (Rev. 3)   
                  -  Issue 72: Control Rod Drive Guide Tube Support Pin Failures (Rev. 1)   
                  -  Issue 73: Detached Thermal Sleeves (Rev. 3)   
                  -  Issue 74: Reactor Coolant Activity Limits for Operating Reactors (Rev. 1)   
                  -  Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant (Rev. 1)   
                  -  Issue 76: Instrumentation and Control Power Interactions (Rev. 3)   
                  -  Issue 77: Flooding of Safety Equipment Compartments by Backflow Through Floor Drains (Rev. 1)   
                  -  Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System (Rev. 3)   
                  -  Issue 79: Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown (Rev. 3)   
                  -  Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments (Rev. 4)   
                  -  Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety (Rev. 5)   
                  -  Issue 82: Beyond Design Basis Accidents in Spent Fuel Pools (Rev. 3)   
                  -  Issue 83: Control Room Habitability (Rev. 3)   
                  -  Issue 84: CE PORVs (Rev. 2)   
                  -  Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments (Rev. 2)   
                  -  Issue 86: Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping (Rev. 1)   
                  -  Issue 87: Failure of HPCI Steam Line Without Isolation (Rev. 2)   
                  -  Issue 88: Earthquakes and Emergency Planning   
                  -  Issue 89: Stiff Pipe Clamps (Rev. 2)   
                  -  Issue 90: Technical Specifications for Anticipatory Trips (Rev. 2)   
                  -  Issue 91: Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators (Rev. 1)   
                  -  Issue 92: Fuel Crumbling During LOCA (Rev. 1)   
                  -  Issue 93: Steam Binding of Auxiliary Feedwater Pumps (Rev. 1)   
                  -  Issue 94: Additional Low Temperature Overpressure Protection for Light Water Reactors (Rev. 1)   
                  -  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 PWRs (Rev. 3)   
                  -  Issue 100: Once-Through Steam Generator Level (Rev. 1)   
                  -  Issue 101: BWR Water Level Redundancy (Rev. 1)   
                  -  Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train (Rev. 2)   
                  -  Issue 103: Design for Probable Maximum Precipitation (Rev. 1)   
                  -  Issue 104: Reduction of Boron Dilution Requirements   
                  -  Issue 105: Interfacing Systems LOCA at LWRs (Rev. 4)   
                  -  Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas (Rev. 2)   
                  -  Issue 107: Main Transformer Failures (Rev. 3)   
                  -  Issue 108: BWR Suppression Pool Temperature Limits   
                  -  Issue 109: Reactor Vessel Closure Failure   
                  -  Issue 110: Equipment Protective Devices on Engineered Safety Features (Rev. 1)   
                  -  Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments (Rev. 2)   
                  -  Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times   
                  -  Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers (Rev. 2)   
                  -  Issue 114: Seismic-Induced Relay Chatter (Rev. 1)   
                  -  Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System (Rev. 2)   
                  -  Issue 116: Accident Management   
                  -  Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages   
                  -  Issue 118: Tendon Anchor Head Failure (Rev. 1)   
                  -  Issue 119: Piping Review Committee Recommendations (Rev. 4)   
                  -  Issue 120: On-Line Testability of Protection Systems (Rev. 2)   
                  -  Issue 121: Hydrogen Control for Large, Dry PWR Containments (Rev. 2)   
                  -  Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Short-Term Actions (Rev. 4)   
                  -  Issue 123: Deficiencies in the Regulations Governing DBA and Failure Criterion Suggested by the Davis-Besse Incident of June 9, 1985 (Rev. 1)   
                  -  Issue 124: Auxiliary Feedwater System Reliability (Rev. 3)   
                  -  Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Long-Term Actions (Rev. 7)   
                  -  Issue 126: Reliability of PWR Main Steam Safety Valves   
                  -  Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems (Rev. 1)   
                  -  Issue 128: Electrical Power Reliability (Rev. 2)   
                  -  Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling   
                  -  Issue 130: Essential Service Water Pump Failures at Multiplant Sites (Rev. 2)   
                  -  Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants (Rev. 1)   
                  -  Issue 132: RHR System Inside Containment (Rev. 1)   
                  -  Issue 133: Update Policy Statement on Nuclear Plant Staff Working Hours (Rev. 1)   
                  -  Issue 134: Rule on Degree and Experience Requirement (Rev. 1)   
                  -  Issue 135: Steam Generator and Steam Line Overfill (Rev. 3)   
                  -  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 (Rev. 2)   
                  -  Issue 139: Thinning of Carbon Steel Piping in LWRs (Rev. 1)   
                  -  Issue 140: Fission Product Removal Systems   
                  -  Issue 141: Large Break LOCA with Consequential SGTR   
                  -  Issue 142: Leakage Through Electrical Isolators in Instrumentation Circuits (Rev. 4)   
                  -  Issue 143: Availability of Chilled Water Systems and Room Cooling (Rev. 2)   
                  -  Issue 144: Scram Without a Turbine/Generator Trip (Rev. 2)   
                  -  Issue 145: Actions to Reduce Common Cause Failures (Rev. 3)   
                  -  Issue 146: Support Flexibility of Equipment and Components (Rev. 2)   
                  -  Issue 147: Fire-Induced Alternate Shutdown/control Room Panel Interactions (Rev. 1)   
                  -  Issue 148: Smoke Control and Manual Fire-fighting Effectiveness 
                  -  Issue 149: Adequacy of Fire Barriers (Rev. 2)   
                  -  Issue 150: Overpressurization of Containment Penetrations (Rev. 1)   
                  -  Issue 151: Reliability of Anticipated Transient Without Scram Recirculatlon Pump Trip in BWRs (Rev. 2)   
                  -  Issue 152: Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads (Rev. 3)   
                  -  Issue 153: Loss of Essential Service Water in LWRs (Rev. 2)   
                  -  Issue 154: Adequacy of Emergency and Essential Lighting (Rev. 2)   
                  -  Issue 155: Generic Concerns Arising from TMI-2 Cleanup (Rev. 3)   
                  -  Issue 156: Systematic Evaluation Program (Rev. 8)   
                  -  Issue 157: Containment Performance (Rev. 1)   
                  -  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 (Rev. 1)   
                  -  Issue 160: Spurious Actuations of Instrumentation upon Restoration of Power (Rev. 1)   
                  -  Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits (Rev. 1)   
                  -  Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit is Shut Down (Rev. 1)   
                  -  Issue 163: Multiple Steam Generator Tube Leakage   
                  -  Issue 164: Neutron Fluence in Reactor Vessel (Rev. 1)   
                  -  Issue 165: Spring-Actuated Safety and Relief Valve Reliability (Rev. 2)   
                  -  Issue 166: Adequacy of Fatigue Life of Metal Components (Rev. 2)   
                  -  Issue 167: Hydrogen Storage Facility Separation (Rev. 2)   
                  -  Issue 168: Environmental Qualification of Electrical Equipment (Rev. 3)   
                  -  Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure (Rev. 1)   
                  -  Issue 170: Fuel Damage Criteria for High Burnup Fuel (Rev. 2)   
                  -  Issue 171: ESF Failure from Loop Subsequent to a LOCA (Rev. 1)   
                  -  Issue 172: Multiple System Responses Program (Rev. 2)   
                  -  Issue 173: Spent Fuel Storage Pool (Rev. 4)   
                  -  Issue 174: Fastener Gaging Practices (Rev. 1)   
                  -  Issue 175: Nuclear Power Plant Shift Staffing (Rev. 1)   
                  -  Issue 176: Loss of Fill-Oil in Rosemount Transmitters (Rev. 1)   
                  -  Issue 177: Vehicle Intrusion at TMI   
                  -  Issue 178: Effect of Hurricane Andrew on Turkey Point (Rev. 2)   
                  -  Issue 179: Core Performance   
                  -  Issue 180: Notice of Enforcement Discretion (Rev. 1)   
                  -  Issue 181: Fire Protection (Rev. 2)   
                  -  Issue 182: General Electric Extended Power Uprate (Rev. 1)   
                  -  Issue 183: Cycle-Specific Parameter Limits in Technical Specifications (Rev. 2)   
                  -  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 (Rev. 2)   
                  -  Issue 191: Assessment of Debris Accumulation on PWR Sump Performance 
                  -  Issue 192: Secondary Containment Drawdown Time   
                  -  Issue 193: BWR ECCS Suction Concerns Description   
                  -  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   
                  -  ISSUE 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES 

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