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Auxiliary Feedwater
Chemistry, Chemical Engineering
Containment (leakage, degradation, cooling system performance)
Cyber Security
ECCS
Electrical Power Systems
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Fuels
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Health Physics
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Physical Security
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Abstract
Abbreviations
Introduction
Section 1 TMI Action Plan Items
Section 2 Task Action Plan Items
Section 3 New Generic Issues
Section 4 Human Factor Issues
Section 5 Chernobyl Issues
Section 6 Nuclear Material Safety and Safeguards Issues
Section 7 Fukushima Issues
Appendices
Revision History
Abstract
Abbreviations
Introduction
Section 1. TMI Action Plan Items ( )
Description
Task I.A: OPERATING PERSONNEL: Operating Personnel and Staffing: Shift Technical Advisor
Task I.A.2: OPERATING PERSONNEL: Training and Qualifications of Operating Personnel: Immediate Upgrading of Operator and Senior Operator Training and Qualifications: Qualifications - Experience
Task I.A.3: OPERATING PERSONNEL: Licensing and Requalification of Operating Personnel: Revise Scope of Criteria for Licensing Examinations
Task I.A.4: OPERATING PERSONNEL: Initial Simulator Improvement: Short-Term Study of Training Simulators
Task I.B: SUPPORT PERSONNEL: Management for Operations: Organization and Management Long-Term Improvements: Prepare Draft Criteria
Task I.B.2: SUPPORT PERSONNEL: Inspection of Operating Reactors: Revise OIE Inspection Program: Verify the Adequacy of Management and Proced
Task I.C: OPERATING PROCEDURES: Short-Term Accident Analysis and Procedures Revision: Small Break LOCAs
Task I.D: CONTROL ROOM DESIGN: Control Room Design Reviews
Task I.E: ANALYSIS AND DISSEMINATION OF OPERATING EXPERIENCE: Office for Analysis and Evaluation of Operational Data
Task I.F: QUALITY ASSURANCE: Expand QA List
Task I.G: PREOPERATIONAL AND LOW-POWER TESTING: Training Requirements
Task II.A: SITING: Siting Policy Reformulation
Task II.B: CONSIDERATION OF DEGRADED OR MELTED CORES IN SAFETY REVIEW: Plant Shielding to Provide Access to Vital Areas and Protect Safety Equipment for Post-Accident Operation
Task II.C: RELIABILITY ENGINEERING AND RISK ASSESSMENT: Interim Reliability Evaluation Program
Task II.D: REACTOR COOLANT SYSTEM RELIEF AND SAFETY VALVES: Testing Requirements
Task II.E: SYSTEM DESIGN: Auxiliary Feedwater System: Auxiliary Feedwater System Evaluation
Task II.E.2: SYSTEM DESIGN: Emergency Core Cooling System: Reliance on ECCS
Task II.E.3: SYSTEM DESIGN: Decay Heat Removal: Reliability of Power Supplies for Natural Circulation
Task II.E.4: SYSTEM DESIGN: Containment Design: Dedicated Penetrations
Task II.E.5: SYSTEM DESIGN: Design Sensitivity of B&W Reactors: Design Evaluation
Task II.E.6: SYSTEM DESIGN: In Situ Testing of Valves: Test Adequacy Study
Task II.F: INSTRUMENTATION AND CONTROLS: Additional Accident Monitoring Instrumentation
Task II.G: ELECTRICAL POWER: Power Supplies for Pressurizer Relief Valves, Block Valves, and Level Indicators
Task II.H: TMI-2 CLEANUP AND EXAMINATION: Maintain Safety of TMI-2 and Minimize Environmental Impact
Task II.J: GENERAL IMPLICATIONS OF TMI FOR DESIGN AND CONSTRUCTION ACTIVITIES: Vendor Inspection Program: Establish a Priority System for C
Task II.J.2: GENERAL IMPLICATIONS OF TMI FOR DESIGN AND CONSTRUCTION ACTIVITIES: Construction Inspection Program: Reorient Construction Inspe
Task II.J.3: GENERAL IMPLICATIONS OF TMI FOR DESIGN AND CONSTRUCTION ACTIVITIES: Construction Inspection Program: Assign Resident Inspectors to All Construction Sites
Task II.J.4: GENERAL IMPLICATIONS OF TMI FOR DESIGN AND CONSTRUCTION ACTIVITIES: Revise Deficiency Reporting Requirements: Revise Deficiency Reporting Requirements
Task II.K: MEASURES TO MITIGATE SMALL-BREAK LOSS-OF-COOLANT ACCIDENTS AND LOSS-OF-FEEDWATER ACCIDENTS: IE Bulletins: Review TMI-2 PNs and D
Task III.A: EMERGENCY PREPAREDNESS AND RADIATION EFFECTS: Improve Licensee Emergency Preparedness - Short-Term: Upgrade Emergency Preparedness: Implement Action Plan Requirements for Promptly Improving Licensee Emergency Preparedness
Task III.A.2: EMERGENCY PREPAREDNESS AND RADIATION EFFECTS: Improving Licensee Emergency Preparedness - Long-Term: Amend 10 CFR 50 and 10 CFR
Task III.A.3: EMERGENCY PREPAREDNESS AND RADIATION EFFECTS: Improving NRC Emergency Preparedness: NRC Role in Responding to Nuclear Emergencie
Task III.B: EMERGENCY PREPAREDNESS OF STATE AND LOCAL GOVERNMENTS: Transfer of Responsibilities to FEMA
Task III.C: PUBLIC INFORMATION: Have Information Available for the News Media and the Public: Review Publicly Available Documents
Task III.D: RADIATION PROTECTION: Radiation Source Control: Primary Coolant Sources Outside the Containment Structure: Review Information Su
Task III.D.2: RADIATION PROTECTION: Public Radiation Protection Improvement: Radiological Monitoring of Effluents: Evaluate the Feasibility and Perform a Value-Impact Analysis of Modifying Effluent-Monitoring Design Criteria
Task III.D.3: RADIATION PROTECTION: Worker Radiation Protection Improvement: Radiation Protection Plans
Task IV.A: STRENGTHEN ENFORCEMENT PROCESS: Seek Legislative Authority
Task IV.B: ISSUANCE OF INSTRUCTIONS AND INFORMATION TO LICENSEES: Revise Practices for Issuance of Instructions and Information to Licensees
Task IV.C: EXTEND LESSONS LEARNED TO LICENSED ACTIVITIES OTHER THAN POWER REACTORS: Extend Lessons Learned from TMI to Other NRC Programs
Task IV.D: NRC STAFF TRAINING: NRC Staff Training
Task IV.E: SAFETY DECISION-MAKING: Expand Research on Quantification of Safety Decision-Making
Task IV.F: FINANCIAL DISINCENTIVES TO SAFETY: Increased OIE Scrutiny of the Power-Ascension Test Program
Task IV.G: IMPROVE SAFETY RULEMAKING PROCEDURES: Develop a Public Agenda for Rulemaking
Task IV.H: NRC PARTICIPATION IN THE RADIATION POLICY COUNCIL: NRC Participation in the Radiation Policy Council
Task V.A: DEVELOPMENT OF SAFETY POLICY: Develop NRC Policy Statement on Safety
Task V.B: POSSIBLE ELIMINATION OF NONSAFETY RESPONSIBILITIES: Study and Recommend, as Appropriate, Elimination of Nonsafety Responsibiliti
Task V.C: ADVISORY COMMITTEES: Strengthen the Role of Advisory Committee on Reactor Safeguards
Task V.D: LICENSING PROCESS: Improve Public and Intervenor Participation in the Hearing Process
Task V.E: LEGISLATIVE NEEDS: Study the Need for TMI-Related Legislation
Task V.F: ORGANIZATION AND MANAGEMENT: Study NRC Top Management Structure and Process
Task V.G: CONSOLIDATION OF NRC LOCATIONS: Achieve Single Location, Long-Term
Section 2. Task Action Plan Items ( )
Description
Item A-1: Water Hammer (former USI)
Item A-2: Asymmetric Blowdown Loads on Reactor Primary Coolant Systems (former USI)
Item A-3: Westinghouse Steam Generator Tube Integrity (former USI)
Item A-4: CE Steam Generator Tube Integrity (former USI)
Item A-7: Mark I Long-Term Program (former USI)
Item A-6: Mark I Short-Term Program (former USI)
Item A-7: Mark I Long-Term Program (former USI)
Item A-8: Mark II Containment Pool Dynamic Loads Long-Term Program (former USI)
Item A-9: ATWS (former USI)
Item A-10: BWR Feedwater Nozzle Cracking (former USI)
Item A-11: Reactor Vessel Materials Toughness (former USI)
Item A-12: Fracture Toughness of Steam Generator and Reactor Coolant Pump Supports (former USI)
Item A-13: Snubber Operability Assurance
Item A-14: Flaw Detection
Item A-15: Primary Coolant System Decontamination and Steam Generator Chemical Cleaning
Item A-16: Steam Effects on BWR Core Spray Distribution
Item A-17: Systems Interactions in Nuclear Power Plants (former USI)
Item A-18: Pipe Rupture Design Criteria
Item A-19: Digital Computer Protection System
Item A-20: Impacts of the Coal Fuel Cycle
Item A-21: Main Steamline Break Inside Containment - Evaluation of Environmental Conditions for Equipment Qualification
Item A-22: PWR Main Steamline Break - Core, Reactor Vessel and Containment Building Response
Item A-23: Containment Leak Testing
Item A-24: Qualification of Class 1E Safety-Related Equipment (former USI)
Item A-25: Non-Safety Loads on Class 1E Power Sources
Item A-27: Reload Applications
Item A-28: Increase in Spent Fuel Pool Storage Capacity
Item A-29: Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage
Item A-30: Adequacy of Safety-Related DC Power Supplies
Item A-31: RHR Shutdown Requirements (former USI)
Item A-32: Missile Effects
Item A-33: NEPA Review of Accident Risks
Item A-34: Instruments for Monitoring Radiation and Process Variables During Accidents
Item A-35: Adequacy of Offsite Power Systems
Item A-36: Control of Heavy Loads Near Spent Fuel (former USI)
Item A-37: Turbine Missiles
Item A-38: Tornado Missiles
Item A-39: Determination of Safety Relief Valve Pool Dynamic Loads and Temperature Limits (former USI)
Item A-40: Seismic Design Criteria (former USI)
Item A-41: Long-Term Seismic Program
Item A-42: Pipe Cracks in Boiling Water Reactors (former USI)
Item A-43: Containment Emergency Sump Performance (former USI)
Item A-44: Station Blackout (former USI)
Item A-45: Shutdown Decay Heat Removal Requirements (former USI)
Item A-46: Seismic Qualification of Equipment in Operating Plants (former USI)
Item A-47: Safety Implications of Control Systems (former USI)
Item A-48: Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment
Item A-49: Pressurized Thermal Shock (former USI)
Item B-1: Environmental Technical Specifications
Item B-3: Event Categorization
Item B-4: ECCS Reliability
Item B-5: Ductility of Two-Way Slabs and Shells and Buckling Behavior of Steel Containments
Item B-6: Loads, Load Combinations, Stress Limits
Item B-7: Secondary Accident Consequence Modeling
Item B-8: Locking Out of ECCS Power Operated Valves
Item B-9: Electrical Cable Penetrations of Containment
Item B-10: Behavior of BWR Mark III Containments
Item B-11: Subcompartment Standard Problems
Item B-12: Containment Cooling Requirements (Non-LOCA)
Item B-13: Marviken Test Data Evaluation
Item B-14: Study of Hydrogen Mixing Capability in Containment Post-LOCA
Item B-15: CONTEMPT Computer Code Maintenance
Item B-16: Protection Against Postulated Piping Failures in Fluid Systems Outside Containment
Item B-17: Criteria for Safety-Related Operator Actions
Item B-18: Vortex Suppression Requirements for Containment Sumps
Item B-19: Thermal-Hydraulic Stability
Item B-20: Standard Problem Analysis
Item B-21: Core Physics
Item B-22: LWR Fuel
Item B-23: LMFBR Fuel
Item B-121: Seismic Qualification of Electrical and Mechanical Equipment
Item B-25: Piping Benchmark Problems
Item B-26: Structural Integrity of Containment Penetrations
Item B-27: Implementation and Use of Subsection NF
Item B-28: Radionuclide/Sediment Transport Program
Item B-29: Effectiveness of Ultimate Heat Sinks
Item B-30: Design Basis Floods and Probability
Item B-31: Dam Failure Model
Item B-32: Ice Effects on Safety-Related Water Supplies
Item B-33: Dose Assessment Methodology
Item B-34: Occupational Radiation Exposure Reduction
Item B-35: Confirmation of Appendix I Models for Calculations of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light Water Cooled Power Reactors
Item B-36: Develop Design, Testing, and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineer
Item B-37: Chemical Discharges to Receiving Waters
Item B-38: Reconnaissance Level Investigations
Item B-142: Transmission Lines
Item B-40: Effects of Power Plant Entrainment on Plankton
Item B-41: Impacts on Fisheries
Item B-42: Socioeconomic Environmental Impacts
Item B-43: Value of Aerial Photographs for Site Evaluation
Item B-44: Forecasts of Generating Costs of Coal and Nuclear Plants
Item B-45: Need for Power - Energy Conservation
Item B-46: Cost of Alternatives in Environmental Design
Item B-47: Inservice Inspection of Supports-Classes 1, 2, 3, and MC Components
Item B-48: BWR Control Rod Drive Mechanical Failures
Item B-49: Inservice Inspection Criteria and Corrosion Prevention Criteria for Containments
Item B-50: Post-Operating Basis Earthquake Inspection
Item B-51: Assessment of Inelastic Analysis Techniques for Equipment and Components
Item B-52: Fuel Assembly Seismic and LOCA Responses
Item B-53: Load Break Switch
Item B-54: Ice Condenser Containments
Item B-55: Improved Reliability of Target Rock Safety Relief Valves
Item B-56: Diesel Reliability
Item B-57: Station Blackout
Item B-58: Passive Mechanical Failures
Item B-59: (N-1) Loop Operation in BWRs and PWRs
Item B-60: Loose Parts Monitoring Systems
Item B-61: Allowable ECCS Equipment Outage Periods
Item B-62: Reexamination of Technical Bases for Establishing SLs, LSSSs, and Reactor Protection System Trip Functions
Item B-63: Isolation of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary
Item B-64: Decommissioning of Reactors
Item B-65: Iodine Spiking
Item B-66: Control Room Infiltration Measurements
Item B-67: Effluent and Process Monitoring Instrumentation
Item B-68: Pump Overspeed During LOCA
Item B-69: ECCS Leakage Ex-Containment
Item B-70: Power Grid Frequency Degradation and Effect on Primary Coolant Pumps
Item B-71: Incident Response
Item B-72: Health Effects and Life Shortening from Uranium and Coal Fuel Cycles
Item B-73: Monitoring for Excessive Vibration Inside the Reactor Pressure Vessel
Item C-1: Assurance of Continuous Long-Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment
Item C-2: Study of Containment Depressurization by Inadvertent Spray Operation to Determine Adequacy of Containment External Design Pressu
Item C-3: Insulation Usage Within Containment
Item C-4: Statistical Methods for ECCS Analysis
Item C-5: Decay Heat Update
Item C-6: LOCA Heat Sources
Item C-7: PWR System Piping
Item C-8: Main Steam Line Leakage Control Systems
Item C-9: RHR Heat Exchanger Tube Failures
Item C-10: Effective Operation of Containment Sprays in a LOCA
Item C-11: Assessment of Failure and Reliability of Pumps and Valves
Item C-12: Primary System Vibration Assessment
Item C-13: Non-Random Failures
Item C-14: Storm Surge Model for Coastal Sites
Item C-15: NUREG Report for Liquid Tank Failure Analysis
Item C-16: Assessment of Agricultural Land in Relation to Power Plant Siting and Cooling System Selection
Item C-17: Interim Acceptance Criteria for Solidification Agents for Radioactive Solid Wastes
Item D-1: Advisability of a Seismic Scram
Item D-2: Emergency Core Cooling System Capability for Future Plants
Item D-3: Control Rod Drop Accident
Section 3. New Generic Issues ( )
Description
Issue 1: Failures in Air-Monitoring, Air-Cleaning, and Ventilating Systems
Issue 2: Failure of Protective Devices on Essential Equipment
Issue 3: Set Point Drift in Instrumentation
Issue 4: End-of-Life and Maintenance Criteria
Issue 5: Design Check and Audit of Balance-of-Plant Equipment
Issue 6: Separation of Control Rod from Its Drive and BWR High Rod Worth Events
Issue 7: Failures Due to Flow-Induced Vibrations
Issue 8: Inadvertent Actuation of Safety Injection in PWRs
Issue 9: Reevaluation of Reactor Coolant Pump Trip Criteria
Issue 10: Surveillance and Maintenance of TIP Isolation Valves and Squib Charges
Issue 11: Turbine Disc Cracking
Issue 12: BWR Jet Pump Integrity
Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters
Issue 14: PWR Pipe Cracks
Issue 15: Radiation Effects on Reactor Vessel Supports
Issue 16: BWR Main Steam Isolation Valve Leakage Control Systems
Issue 17: Loss of Offsite Power Subsequent to a LOCA
Issue 18: Steam Line Break with Consequential Small LOCA
Issue 19: Safety Implications of Nonsafety Instrument and Control Power Supply Bus
Issue 20: Effects of Electromagnetic Pulse on Nuclear Power Plants
Issue 21: Vibration Qualification of Equipment
Issue 22: Inadvertent Boron Dilution Events
Issue 23: Reactor Coolant Pump Seal Failures
Issue 24: Automatic ECCS Switchover to Recirculation
Issue 25: Automatic Air Header Dump on BWR Scram System
Issue 26: Diesel Generator Loading Problems Related to SIS Reset on Loss of Offsite Power
Issue 27: Manual vs. Automated Actions
Issue 28: Pressurized Thermal Shock
Issue 29: Bolting Degradation or Failure in Nuclear Power Plants
Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings
Issue 31: Natural Circulation Cooldown
Issue 32: Flow Blockage in Essential Equipment Caused by Corbicula
Issue 33: Correcting Atmospheric Dump Valve Opening Upon Loss of Integrated Control System Power
Issue 34: RCS Leak
Issue 35: Degradation of Internal Appurtenances in LWRs
Issue 36: Loss of Service Water
Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown
Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris
Issue 39: Potential for Unacceptable Interaction Between the CRD System and Non-Essential Control Air System
Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System
Issue 41: BWR Scram Discharge Volume Systems
Issue 42: Combination Primary/Secondary System LOCA
Issue 43: Reliability of Air Systems
Issue 44: Failure of Saltwater Cooling System
Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather
Issue 46: Loss of 125 Volt DC Bus
Issue 47: Loss of Offsite Power
Issue 48: LCO for Class 1E Vital Instrument Buses in Operating Reactors
Issue 49: Interlocks and LCOs for Redundant Class 1E Tie-Breakers
Issue 50: Reactor Vessel Level Instrumentation in BWRs
Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water Systems
Issue 52: SSW Flow Blockage by Blue Mussels
Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR
Issue 54: Valve Operator-Related Events Occurring During 1978, 1979, and 1980
Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand
Issue 56: Abnormal Transient Operating Guidelines as Applied to a Steam Generator Overfill Event
Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment
Issue 58: Inadvertent Containment Flooding
Issue 59: Technical Specification Requirements for Plant Shutdown when Equipment for Safe Shutdown is Degraded or Inoperable
Issue 60: Lamellar Tearing of Reactor Systems Structural Supports
Issue 61: SRV Line Break Inside the BWR Wetwell Airspace of Mark I and II Containments
Issue 62: Reactor Systems Bolting Applications
Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis
Issue 64: Identification of Protection System Instrument Sensing Lines
Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures
Issue 66: Steam Generator Requirements
Issue 67: Steam Generator Staff Actions: Integrity of Steam Generator Tube Sleeves
Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture
Issue 69: Make-Up Nozzle Cracking in B&W Plants MTEB
Issue 70: PORV and Block Valve Reliability
Issue 71: Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety
Issue 72: Control Rod Drive Guide Tube Support Pin Failures
Issue 73: Detached Thermal Sleeves
Issue 74: Reactor Coolant Activity Limits for Operating Reactors
Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant
Issue 76: Instrumentation and Control Power Interactions
Issue 77: Flooding of Safety Equipment Compartments by Back-Flow Through Floor Drains
Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System
Issue 79: Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown
Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments
Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety
Issue 82: Beyond Design-Basis Accidents in Spent Fuel Pools
Issue 83: Control Room Habitability
Issue 84: CE PORVs
Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments
Issue 86: Long-Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping
Issue 87: Failure of HPCI Steam Line Without Isolation
Issue 88: Earthquakes and Emergency Planning
Issue 89: Stiff Pipe Clamps
Issue 90: Technical Specifications for Anticipatory Trips ICSB
Issue 91: Main Crankshaft Failures in Transamerica DeLaval Emergency Diesel Generators
Issue 92: Fuel Crumbling During LOCA
Issue 93: Steam Binding of Auxiliary Feedwater Pumps
Issue 94: Additional Low Temperature Overpressure Protection for Light-Water Reactors
Issue 95: Loss of Effective Volume for Containment Recirculation Spray
Issue 96: RHR Suction Valve Testing
Issue 97: PWR Reactor Cavity Uncontrolled Exposures
Issue 98: CRD Accumulator Check Valve Leakage
Issue 99: RCS/RHR Suction Line Valve Interlock on PWRs
Issue 100: Once-Through Steam Generator Level
Issue 101: BWR Water Level Redundancy
Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train
Issue 103: Design for Probable Maximum Precipitation
Issue 104: Reduction of Boron Dilution Requirements
Issue 105: Interfacing Systems LOCA at LWRs
Issue 106: Piping and Use of Highly Combustible Gases in Vital Areas
Issue 107: Main Transformer Failures
Issue 108: BWR Suppression Pool Temperature Limits
Issue 109: Reactor Vessel Closure Failure
Issue 110: Equipment Protective Devices on Engineered Safety Features
Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments
Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times
Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers
Issue 114: Seismic-Induced Relay Chatter
Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System
Issue 116: Accident Management
Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages
Issue 118: Tendon Anchorage Failure
Issue 119: Piping Review Committee Recommendations: Piping Rupture Requirements and Decoupling of Seismic and LOCA Loads
Issue 120: On-Line Testability of Protection Systems
Issue 121: Hydrogen Control for Large, Dry PWR Containments
Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985: Short-Term Actions: Potential Inability to Remove Reactor Decay Heat: F
Issue 123: Deficiencies in the Regulations Governing DBA and Single-Failure Criteria Suggested by the Davis-Besse Event of June 9, 1985
Issue 124: Auxiliary Feedwater System Reliability
Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985: Long-Term Actions: Availability of the Shift Technical Advisor
Issue 126: Reliability of PWR Main Steam Safety Valves
Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems
Issue 128: Electrical Power Reliability
Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling
Issue 130: Essential Service Water Pump Failures at Multiplant Sites
Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants
Issue 132: RHR System Inside Containment
Issue 133: Update Policy Statement on Nuclear Plant Staff Working Hours
Issue 134: Rule on Degree and Experience Requirement
Issue 135: Steam Generator and Steam Line Overfill
Issue 136: Storage and Use of Large Quantities of Cryogenic Combustibles On Site
Issue 137: Refueling Cavity Seal Failure
Issue 138: Deinerting of BWR Mark I and II Containments During Power Operations Upon Discovery of RCS Leakage or a Train of a Safety System
Issue 139: Thinning of Carbon Steel Piping in LWRs
Issue 140: Fission Product Removal Systems
Issue 141: Large-Break LOCA With Consequential SGTR
Issue 142: Leakage Through Electrical Isolators in Instrumentation Circuits
Issue 143: Availability of Chilled Water Systems and Room Cooling
Issue 144: Scram Without a Turbine/Generator Trip
Issue 145: Actions to Reduce Common Cause Failures
Issue 146: Support Flexibility of Equipment and Components
Issue 147: Fire-Induced Alternate Shutdown/Control Room Panel Interactions
Issue 148: Smoke Control and Manual Fire-Fighting Effectiveness
Issue 149: Adequacy of Fire Barriers
Issue 150: Overpressurization of Containment Penetrations
Issue 151: Reliability of Anticipated Transient Without SCRAM Recirculation Pump Trip in BWRs
Issue 152: Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads
Issue 153: Loss of Essential Service Water in LWRs
Issue 154: Adequacy of Emergency and Essential Lighting
Issue 155: More Realistic Source Term Assumptions
Issue 156: Systematic Evaluation Program: Settlement of Foundations and Buried Equipment
Issue 157: Containment Performance
Issue 158: Performance of Power-Operated Valves Under Design Basis Conditions
Issue 159: Qualification of Safety-Related Pumps While Running on Minimum Flow
Issue 160: Spurious Actions of Instrumentation Upon Restoration of Power
Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits
Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit Is Shut Down
Issue 163: Multiple Steam Generator Tube Leakage
Issue 164: Neutron Fluence in Reactor Vessel
Issue 165: Safety and Safety/Relief Valve Reliability
Issue 166: Adequacy of Fatigue Life of Metal Components
Issue 167: Hydrogen Storage Facility Separation
Issue 168: Environmental Qualification of Electrical Equipment
Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure
Issue 170: Fuel Damage Criteria for High Burnup Fuel
Issue 171: ESF Failure from LOOP Subsequent to a LOCA
Issue 172: Multiple System Responses Program
Issue 173: Spent Fuel Storage Pool: Operating Facilities
Issue 174: Fastener Gaging Practices: SONGS Employees' Concern
Issue 175: Nuclear Power Plant Shift Staffing
Issue 176: Loss of Fill-Oil in Rosemount Transmitters
Issue 177: Vehicle Intrusion at TMI
Issue 178: Effect of Hurricane Andrew on Turkey Point
Issue 179: Core Performance
Issue 180: Notice of Enforcement Discretion
Issue 181: Fire Protection
Issue 182: General Electric Extended Power Uprate
Issue 183: Cycle-Specific Parameter Limits in Technical Specifications
Issue 184: Endangered Species
Issue 185: Control of Recriticality Following Small-Break LOCA In PWRs
Issue 186: Potential Risk and Consequences of Heavy Load Drops
Issue 187: The Potential Impact of Postulated Cesium Concentration on Equipment Qualification in the Containment Sump in Nuclear Power Plan
Issue 188: Steam Generator Tube Leaks/Ruptures Concurrent with Containment Bypass
Issue 189: Susceptibility of Ice Condenser Containments to Early Failure from Hydogen Combustion During A Severe Accident
Issue 190: Fatigue Evaluation of Metal Components for 60-Year Plant Life
Issue 191: Assessment of Debris Accumulation on PWR Sump Performance
Issue 192: Secondary Containment Drawdown Time
Issue 193: BWR ECCS Suction Concerns
Issue 194: Implications of Updated Probabilistic Seismic Hazard Estimates
Issue 195: Hydrogen Combustion in Foreign 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 United States
Issue 200: Tin Whiskers
Issue 201: Small-Break LOCA and Loss of Offsite Power Scenario
Issue 202: Spent Fuel Pool Leakage Limits
Issue 203: Potential Safety Issues with Cranes that Lift Spent Fuel Casks
Issue 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES
Section 4. Human Factors Issues ( )
Description
Task HF1: STAFFING AND QUALIFICATIONS: Shift Staffing
Task HF2: TRAINING: Evaluate Industry Training
Task HF3: OPERATOR LICENSING EXAMINATIONS: Develop Job Knowledge Catalog
Task HF4: PROCEDURES: Inspection Procedure for Upgraded Emergency Operating Procedures
Task HF5: MAN-MACHINE INTERFACE: Local Control Stations
Task HF6: MANAGEMENT AND ORGANIZATION: Develop Regulatory Position on Management and Organization
Task HF7: HUMAN RELIABILITY: Human Error Data Acquisition
Task HF8: Maintenance and Surveillance Program
Section 5. Chernobyl Issues ( )
Description
Task CH1: ADMINISTRATIVE CONTROLS AND OPERATIONAL PRACTICES: Administrative Controls to Ensure That Procedures Are Followed and That Procedures Are Adequate: Symptom-Based EOPs
Task CH2: DESIGN: Reactivity Accidents: Reactivity Transients
Task CH3: CONTAINMENT: Containment Performance During Severe Accidents: Containment Performance
Task CH4: EMERGENCY PLANNING: Size of the Emergency Planning Zones
Task CH5: SEVERE ACCIDENT PHENOMENA: Source Term: Mechanical Dispersal in Fission Product Release
Task CH6: GRAPHITE-MODERATED REACTORS: Graphite-Moderated Reactors: The Fort St. Vrain Reactor and the Modular HTGR
Section 6. Nuclear Material Safety and Safeguards GSIs ( )
Description
NMSS-0001: Door Interlock Failure Resulting from Faulty Microselectron High Dose Rate Remote Afterloader
NMSS-0002: Significant Quantities of Fixed Contamination Remain in Krypton-85 Leak-Detection Devices after Venting
NMSS-0003: Corrosion of Sealed Sources Caused by Sensitization of Stainless Steel Source Capsules During Shipment
NMSS-0004: Overexposures Caused by Sources Stolen from Facility of Bankrupt Licensee
NMSS-0005: Potential for Erroneous Calibration, Dose Rate, or Radiation Exposure Measurements with Victoreen Electrometers
NMSS-0006: Criticality in Low-Level Waste
NMSS-0007: Criticality Benchmarks Greater than 5% Enrichment
NMSS-0008: Year 2000 Computer Problem - Non-Reactor Licensees
NMSS-0009: Amersham Radiography Source Cable Failures
NMSS-0010: Troxler Gauge Source Rod Weld Failures
NMSS-0011: Spent Fuel Dry Cask Weld Cracks
NMSS-0012: Inadequate Transportation Packaging Puncture Tests
NMSS-0013: Use of Different Dose Equivalent Models to Show Compliance
NMSS-0014: Surety Estimates for Groundwater Restoration at in Situ Leach Facilities
NMSS-0015: Adequacy of 10 CFR 150 Criticality Requirements
NMSS-0016: Adequacy of 0.05 Weight Percent Limit in 10 CFR 40
NMSS-0017: Misleading Marketing Information to General Licensees
NMSS-0018: Problems Encountered When Manually Editing Treatment Planning Data on Nucletron Microselectron-HDR Model 105.999
NMSS-0019: Control Unit Failures of Classic Nucletron HDR Units
NMSS-0020: Leaking Pools
NMSS-0021: Unlikely Events
NMSS-0022: Gamma Stereotactic Radiosurgery
Section 7. Fukushima Issues ( )
Description
Issue 199: Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States
Issue 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES
Tables ( )
Description
TABLE II: LIST OF ALL THREE MILE ISLAND NUCLEAR PLANT ACTION PLAN ITEMS, TASK ACTION PLAN ITEMS, NEW GENERIC ISSUES, HUMAN FACT
Table III: SUMMARY OF THE STATUS OF ALL GENERIC SAFETY ISSUES
TABLE IV: LISTING OF AEOD REPORTS AND RELATED GENERIC ISSUES
TABLE V: SUMMARY OF CONSOLIDATED GENERIC ISSUES
Appendices ( )
Description
Appendix A: Releases from Containment
Appendix B: Applicability of NUREG-0933 Issues to Operating and Future Reactor Plants
Appendix C: Priority Ranking Numerical Thresholds Used in Prioritizations Completed Before June 30, 1993
Appendix D: Related Generic Activities
Appendix E: Generic Communication and Compliance Activities
Appendix F: Nuclear Material Safety and Safeguards GSIs
Appendix G: Generic Issues Program Current and Historical Procedures
NUREG 0933: Revision History
Description
Page Last Reviewed/Updated 06/24/2025
