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Resolution of Generic Safety Issues: NUREG-0933: Footnote 2068 ( NUREG-0933, Main Report with Supplements 1–35 )

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Section 1 TMI Action Plan Items (52)

Task I.A: Operating Personnel (Rev. 3) (7)

Task I.A.2: Training and Qualifications of Operating Personnel (Rev. 6) (85)

Task I.A.3: Licensing and Requalification of Operating Personnel (Rev. 6) (36)

Task I.A.4: Simulator Use and Development (Rev. 6) (29)

Task I.B: Support Personnel (Rev. 4) (Rev. 1) (32)

Task I.B.2: Inspection of Operating Reactors (Rev. 1) (7)

Task I.C: Operating Procedures (Rev. 4) (35)

Task I.D: Control Room Design (Rev. 8) (61)

Task I.E: Analysis and Dissemination of Operating Experience (Rev. 3) (21)

Task I.F: Quality Assurance (Rev. 5) (29)

Task I.G: Preoperational and Low-Power Testing (Rev. 3) (15)

Task II.A: Siting (Rev. 2) (11)

Task II.B: Consideration of Degraded or Melted Cores in Safety Review (Rev. 5) (64)

Task II.C: Reliability Engineering and Risk Assessment (Rev. 3) (40)

Task II.D: Reactor Coolant System Relief and Safety Valves (Rev. 3) (21)

Task II.E: System Design (Rev. 2) (6)

Task II.E.2: Emergency Core Cooling System (Rev. 3) (35)

Task II.E.3: Decay Heat Removal (Rev. 2) (15)

Task II.E.4: Containment Design (Rev. 2) (36)

Task II.E.5: Design Sensitivity of B&W Reactors (Rev. 2) (12)

Task II.E.6: In Situ Testing of Valves (Rev. 2) (17)

Task II.F: Instrumentation and Controls (Rev. 3) (29)

Task II.G: Electrical Power (Rev. 1) (3)

Task II.H: TMI-2 Cleanup and Examination (Rev. 3) (13)

Task II.J: General Implications of TMI for Design and Construction Activities (Rev. 1) (34)

Task II.J.2: Construction Inspection Program (Rev. 1) (9)

Task II.J.3: Management for Design and Construction (Rev. 1) (6)

Task II.J.4: Revise Deficiency Reporting Requirements (Rev. 3) (3)

Task II.K: Measures to Mitigate Small-Break Loss-Of-Coolant Accidents and Loss-Of-Feedwater Accidents ( 2) (332)

Task III.A: Emergency Preparedness and Radiation Effects (26)

Task III.A.2: Improving Licensee Emergency Preparedness - Long-Term (10)

Task III.A.3: Improving NRC Emergency Preparedness (37)

Task III.B: Emergency Preparedness of State and Local Governments (6)

Task III.C: Public Information (11)

Task III.D: Radiation Protection (44)

Task III.D.2: Public Radiation Protection Improvement (Rev. 4) (59)

Task III.D.3: Worker Radiation Protection Improvement (Rev. 3) (38)

Task IV.A: Strengthen Enforcement Process (4)

Task IV.B: Issuance of Instructions and Information to Licensees (3)

Task IV.C: Extend Lessons Learned to Licensed Activities Other than Power Reactors (3)

Task IV.D: NRC Staff Training (3)

Task IV.E: Safety Decision-Making (Rev. 3) (27)

Task IV.F: Financial Disincentives to Safety (11)

Task IV.G: Improve Safety Rulemaking Procedures (12)

Task IV.H: NRC Participation in the Radiation Policy Council (3)

Task V.A: Development of Safety Policy (3)

Task V.B: Possible Elimination of Non-Safety Responsibilities (3)

Task V.C: Advisory Committees (8)

Task V.D: Licensing Process (Rev. 1) (17)

Task V.E: Legislative Needs (Rev. 1) (3)

Task V.F: Organization and Management (21)

Task V.G: Consolidation of NRC Locations (6)

Section 2 Task Action Plan Items (142)

Item A-1: Water Hammer (Rev. 2) (1)

Item A-2: Asymmetric Blowdown Loads on Reactor Primary Coolant Systems (Rev. 2) (4)

Item A-3: Westinghouse Steam Generator Tube Integrity (Rev. 2) (3)

Item A-4: CE Steam Generator Tube Integrity (Rev. 2) (2)

Item A-5: B&W Steam Generator Tube Integrity (Rev. 2) (2)

Item A-6: MARK I Short-Term Program (Rev. 2) (2)

Item A-7: MARK I Long-Term Program (Rev. 2) (2)

Item A-8: MARK II Containment Pool Dynamic Loads Long-Term Program (Rev. 2) (2)

Item A-9: ATWS (Rev. 2) (2)

Item A-10: BWR Feedwater Nozzle Cracking (Rev. 2) (2)

Item A-11: Reactor Vessel Materials Toughness (Rev. 2) (2)

Item A-12: Fracture Toughness of Steam Generator and Reactor Coolant Pump Supports (Rev. 2) (2)

Item A-13: Snubber Operability Assurance (Rev. 2) (5)

Item A-14: Flaw Detection (Rev. 1) (5)

Item A-15: Primary Coolant System Decontamination and Steam Generator Chemical Cleaning (Rev. 1) (5)

Item A-16: Steam Effects on BWR Core Spray Distribution (Rev. 1) (5)

Item A-17: Systems Interactions in Nuclear Power Plants (Rev. 2) (2)

Item A-18: Pipe Rupture Design Criteria (Rev. 1) (9)

Item A-19: Digital Computer Protection System (Rev. 3) (2)

Item A-20: Impacts of the Coal Fuel Cycle Description (Rev. 2) (2)

Item A-21: Main Steam Line Break Inside Containment - Evaluation of Environmental Conditions for Equipment Qualification (Rev. 1) (11)

Item A-22: PWR Main Steam Line Break - Core, Reactor Vessel, and Containment Building Response (13)

Item A-23: Containment Leak Testing (Rev. 1) (9)

Item A-24: Qualification of Class 1E Safety-Related Equipment (Rev. 2) (2)

Item A-25: Non-Safety Loads on Class 1E Power Sources (5)

Item A-26: Reactor Vessel Pressure Transient Protection (Rev. 2) (2)

Item A-27: Reload Applications (Rev. 1) (2)

Item A-28: Increase in Spent Fuel Pool Storage Capacity (5)

Item A-29: Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage (Rev. 1) (9)

Item A-30: Adequacy of Safety-Related DC Power Supplies (Rev. 1) (11)

Item A-31: RHR Shutdown Requirements (Rev. 1) (2)

Item A-32: Missile Effects (5)

Item A-33: NEPA Review of Accident Risks (2)

Item A-34: Instruments for Monitoring Radiation and Process Variables During Accidents (2)

Item A-35: Adequacy of Offsite Power Systems (Rev. 1) (2)

Item A-36: Control of Heavy Loads near Spent Fuel (Rev. 2) (2)

Item A-37: Turbine Missiles ( 2) (13)

Item A-38: Tornado Missiles (Rev. 3) (15)

Item A-39: Determination of Safety Relief Valve Pool Dynamic Loads and Temperature Limits (Rev. 1) (Rev. 3) (2)

Item A-40: Seismic Design Criteria (Rev. 1) (2)

Item A-41: Long-Term Seismic Program (Rev. 1) (4)

Item A-42: Pipe Cracks in Boiling Water Reactors (Rev. 2) (2)

Item A-43: Containment Emergency Sump Performance (Rev. 1) (3)

Item A-44: Station Blackout (Rev. 1) (2)

Item A-45: Shutdown Decay Heat Removal Requirements (Rev. 1) (2)

Item A-46: Seismic Qualification of Equipment in Operating Plants (Rev. 2) (2)

Item A-47: Safety Implications of Control Systems (Rev. 1) (2)

Item A-48: Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment (Rev. 1) (2)

Item A-49: Pressurized Thermal Shock (Rev. 1) (2)

Item B-1: Environmental Technical Specifications ( 2) (2)

Item B-2: Forecasting Electricity Demand (2)

Item B-3: Event Categorization (2)

Item B-4: ECCS Reliability (2)

Item B-5: Ductility of Two-Way Slabs and Shells and Buckling Behavior of Steel Containments (Rev. 1) (20)

Item B-6: Loads, Load Combinations, Stress Limits (12)

Item B-7: Secondary Accident Consequence Modeling (2)

Item B-8: Locking out of ECCS Power-Operated Valves (Rev. 1) (15)

Item B-9: Electrical Cable Penetrations of Containment (2)

Item B-10: Behavior of BWR MARK III Containments (Rev. 1) (11)

Item B-11: Subcompartment Standard Problems (Rev. 1) (2)

Item B-12: Containment Cooling Requirements (Non-LOCA) (Rev. 1) (2)

Item B-13: Marviken Test Data Evaluation (Rev. 1) (2)

Item B-14: Study of Hydrogen Mixing Capability in Containment Post-LOCA (2)

Item B-15: Contempt Computer Code Maintenance (2)

Item B-16: Protection Against Postulated Piping Failures in Fluid Systems Outside Containment (5)

Item B-17: Criteria for Safety-Related Operator Actions (14)

Item B-18: Vortex Suppression Requirements for Containment Sumps (2)

Item B-19: Thermal-Hydraulic Stability (Rev. 1) (5)

Item B-20: Standard Problem Analysis (Rev. 1) (2)

Item B-21: Core Physics (2)

Item B-22: LWR Fuel (Rev. 2) ( 2) (16)

Item B-23: LMFBR Fuel (2)

Item B-24: Seismic Qualification of Electrical and Mechanical Equipment (2)

Item B-25: Piping Benchmark Problems (Rev. 1) (2)

Item B-26: Structural Integrity of Containment Penetrations (Rev. 1) (14)

Item B-27: Implementation and Use of Subsection NF (Rev. 1) (2)

Item B-28: Radionuclide/Sediment Transport Program (2)

Item B-29: Effectiveness of Ultimate Heat Sinks (2)

Item B-30: Design Basis Floods and Probability (Rev. 1) (2)

Item B-31: Dam Failure Model (Rev. 1) (5)

Item B-32: Ice Effects on Safety-Related Water Supplies (Rev. 1) (4)

Item B-33: Dose Assessment Methodology (2)

Item B-34: Occupational Radiation Exposure Reduction (2)

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 (Rev. 1) (2)

Item B-36: Develop Design, Testing, and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems (2)

Item B-37: Chemical Discharges to Receiving Waters (4)

Item B-38: Reconnaissance Level Investigations (2)

Item B-39: Transmission Lines (2)

Item B-40: Effects of Power Plant Entrainment on Plankton (2)

Item B-41: Impacts on Fisheries (3)

Item B-42: Socioeconomic Environmental Impacts (2)

Item B-43: Value of Aerial Photographs for Site Evaluation

Item B-44: Forecasts of Generating Costs of Coal and Nuclear Plants (2)

Item B-45: Need for Power-Energy Conservation (2)

Item B-46: Costs of Alternatives in Environmental Design (2)

Item B-47: Inservice Inspection of Supports - Classes 1, 2, 3, and MC Components ( 2) (2)

Item B-48: BWR Control Rod Drive Mechanical Failures (2)

Item B-49: Inservice Inspection Criteria and Corrosion Prevention Criteria for Containments (Rev. 1) (2)

Item B-50: Post-Operating Basis Earthquake Inspection (Rev. 1) (8)

Item B-51: Assessment of Inelastic Analysis Techniques for Equipment and Components (2)

Item B-52: Fuel Assembly Seismic and LOCA Responses (2)

Item B-53: Load Break Switch (4)

Item B-54: Ice Condenser Containments (Rev. 1) (14)

Item B-55: Improved Reliability of Target Rock Safety Relief Valves (Rev. 1) (10)

Item B-56: Diesel Reliability (Rev. 2) (13)

Item B-57: Station Blackout (2)

Item B-58: Passive Mechanical Failures (Rev. 1) (10)

Item B-59: (N-1) Loop Operation in BWRs and PWRs (Rev. 1)

Item B-60: Loose Parts Monitoring Systems (Rev. 1) (2)

Item B-61: Allowable ECCS Equipment Outage Periods (Rev. 1) (15)

Item B-62: Reexamination of Technical Bases for Establishing SLs, LSSSs, and Reactor Protection System Trip Functions (2)

Item B-63: Isolation of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary (2)

Item B-64: Decommissioning of Reactors (Rev. 2) (2)

Item B-65: Iodine Spiking (Rev. 2) (12)

Item B-66: Control Room Infiltration Measurements (2)

Item B-67: Effluent and Process Monitoring Instrumentation (2)

Item B-68: Pump Overspeed During LOCA (14)

Item B-69: ECCS Leakage Ex-Containment (2)

Item B-70: Power Grid Frequency Degradation and Effect on Primary Coolant Pumps (2)

Item B-71: Incident Response (2)

Item B-72: Health Effects and Life-Shortening from Uranium and Coal Fuel Cycles (Rev. 1) (2)

Item B-73: Monitoring for Excessive Vibration Inside the Reactor Pressure Vessel (5)

Item C-1: Assurance of Continuous Long-Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment (5)

Item C-2: Study of Containment Depressurization by Inadvertent Spray Operation to Determine Adequacy of Containment External Design Pressure (2)

Item C-3: Insulation Usage Within Containment (Rev. 1) (2)

Item C-4: Statistical Methods for ECCS Analysis (Rev. 1) (4)

Item C-5: Decay Heat Update (Rev. 1) (4)

Item C-6: LOCA Heat Sources (Rev. 1) (4)

Item C-7: PWR System Piping (2)

Item C-8: Main Steam Line Leakage Control Systems (Rev. 1) (21)

Item C-9: RHR Heat Exchanger Tube Failures (12)

Item C-10: Effective Operation of Containment Sprays in a LOCA (2)

Item C-11: Assessment of Failure and Reliability of Pumps and Valves (Rev. 1) (14)

Item C-12: Primary System Vibration Assessment (5)

Item C-13: Non-Random Failures (Rev. 1) (2)

Item C-14: Storm Surge Model for Coastal Sites (Rev. 1) (2)

Item C-15: NUREG Report for Liquid Tank Failure Analysis (2)

Item C-16: Assessment of Agricultural Land in Relation to Power Plant Siting and Cooling System Selection ( 2) (2)

Item C-17: Interim Acceptance Criteria for Solidification Agents for Radioactive Solid Wastes (2)

Item D-1: Advisability of a Seismic Scram (Rev. 1) (20)

Item D-2: Emergency Core Cooling System Capability for Future Plants (Rev. 1) (2)

Item D-3: Control Rod Drop Accident (2)

Section 3 New Generic Issues (204)

Issue 1: Failures in Air-Monitoring, Air-Cleaning, and Ventilating Systems (15)

Issue 2: Failure of Protective Devices on Essential Equipment (Rev. 2) (6)

Issue 3: Set Point Drift in Instrumentation (Rev. 1) (5)

Issue 4: End-of-Life and Maintenance Criteria (5)

Issue 5: Design Check and Audit of Balance-of-Plant Equipment (2)

Issue 6: Separation of Control Rod from its Drive and BWR High Rod Worth Events (Rev. 1) (2)

Issue 7: Failures Due to Flow-Induced Vibrations (Rev. 1) (15)

Issue 8: Inadvertent Actuation of Safety Injection in PWRs (7)

Issue 9: Reevaluation of Reactor Coolant Pump Trip Criteria (2)

Issue 10: Surveillance and Maintenance of Tip Isolation Valves and Squib Charges (25)

Issue 11: Turbine Disc Cracking (2)

Issue 12: BWR Jet Pump Integrity (Rev. 1) (15)

Issue 13: Small-Break LOCA from Extended Overheating of Pressurizer Heaters (10)

Issue 14: PWR Pipe Cracks (Rev. 2) (4)

Issue 15: Radiation Effects on Reactor Vessel Supports (Rev. 3) (13)

Issue 16: BWR Main Steam Isolation Valve Leakage Control Systems (2)

Issue 17: Loss of Offsite Power Subsequent to a LOCA (12)

Issue 18: Steam-Line Break with Consequential Small LOCA (5)

Issue 19: Safety Implications of Non-Safety Instrument and Control Power Supply Bus (2)

Issue 20: Effects of Electromagnetic Pulse on Nuclear Power Plants (Rev. 1) (5)

Issue 21: Vibration Qualification of Equipment (Rev. 2) (2)

Issue 22: Inadvertent Boron Dilution Events (Rev. 2) (14)

Issue 23: Reactor Coolant Pump Seal Failures (Rev. 1) (20)

Issue 24: Automatic ECCS Switchover to Recirculation (Rev. 3) (15)

Issue 25: Automatic Air Header Dump on BWR Scram System (2)

Issue 26: Diesel Generator Loading Problems Related to SIS Reset on Loss of Offsite Power (2)

Issue 27: Manual vs. Automated Actions (2)

Issue 28: Pressurized Thermal Shock (2)

Issue 29: Bolting Degradation or Failure in Nuclear Power Plants (Rev. 2) (14)

Issue 30: Potential Generator Missiles - Generator Rotor Retaining Rings (Rev. 1) (13)

Issue 31: Natural Circulation Cooldown (5)

Issue 32: Flow Blockage in Essential Equipment Caused by Corbicula (2)

Issue 33: Correcting Atmospheric Dump Valve Opening upon Loss of Integrated Control System Power (2)

Issue 34: RCS Leak (Rev. 1) (6)

Issue 35: Degradation of Internal Appurtenances in LWRs (Rev. 2) (21)

Issue 36: Loss of Service Water (Rev. 3) (20)

Issue 37: Steam Generator Overfill and Combined Primary and Secondary Blowdown (Rev. 1) (2)

Issue 38: Potential Recirculation System Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris (Rev. 2) (5)

Issue 39: Potential for Unacceptable Interaction Between the CRD System and Non-Essential Control Air System (Rev. 1) (2)

Issue 40: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Rev. 1) (5)

Issue 41: BWR Scram Discharge Volume Systems (5)

Issue 42: Combination Primary/Secondary System LOCA (Rev. 1) (2)

Issue 43: Reliability of Air Systems (Rev. 2) (13)

Issue 44: Failure of Saltwater Cooling System (Rev. 1) (2)

Issue 45: Inoperability of Instrumentation Due to Extreme Cold Weather (Rev. 2) (2)

Issue 46: Loss of 125 Volt DC Bus (4)

Issue 47: The Loss of Offsite Power (8)

Issue 48: LCO for Class 1E Vital Instrument Buses in Operating Reactors (Rev. 1) (2)

Issue 49: Interlocks and LCOs for Class 1E Tie-Breakers (Rev. 3) (11)

Issue 50: Reactor Vessel Level Instrumentation in BWRs (Rev. 1) (5)

Issue 51: Proposed Requirements for Improving the Reliability of Open Cycle Service Water System (Rev. 1) (15)

Issue 52: SSW Flow Blockage by Blue Mussels (2)

Issue 53: Consequences of a Postulated Flow Blockage Incident in a BWR (Rev. 1) (12)

Issue 54: Survey of Valve Operator-Related Events Occurring During 1978, 1979, and 1980 (Rev. 1) (5)

Issue 55: Failure of Class 1E Safety-Related Switchgear Circuit Breakers to Close on Demand (Rev. 2) (14)

Issue 56: Abnormal Transient Operating Guidelines as Applied to a Steam Generator Overfill Event (2)

Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (Rev. 3) (17)

Issue 58: Containment Flooding (12)

Issue 59: Technical Specification Requirements for Plant Shutdown When Equipment for Safe Shutdown Is Degraded or Inoperable (Rev. 2) (11)

Issue 60: Lamellar Tearing of Reactor Systems Structural Supports (2)

Issue 61: SRV Line Break Inside the BWR Wetwell Airspace of Mark I and II Containments (Rev. 2) (20)

Issue 62: Reactor Systems Bolting Applications (Rev. 1) (2)

Issue 63: Use of Equipment Not Classified as Essential to Safety in BWR Transient Analysis (Rev. 1) (14)

Issue 64: Identification of Protection System Instrument Sensing Lines (5)

Issue 65: Probability of Core-Melt Due to Component Cooling Water System Failures (Rev. 1) (11)

Issue 66: Steam Generator Requirements (Rev. 2) (6)

Issue 67: Steam Generator Staff Actions (Rev. 5) (113)

Issue 68: Postulated Loss of Auxiliary Feedwater System Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture (Rev. 3) (13)

Issue 69: Make-Up Nozzle Cracking in B&W Plants (Rev. 11) (5)

Issue 70: PORV and Block Valve Reliability (Rev. 3) (45)

Issue 71: Failure of Resin Demineralizer Systems and Their Effects on Nuclear Power Plant Safety (Rev. 3) (18)

Issue 72: Control Rod Drive Guide Tube Support Pin Failures (Rev. 1) (8)

Issue 73: Detached Thermal Sleeves (Rev. 3) (11)

Issue 74: Reactor Coolant Activity Limits for Operating Reactors (Rev. 1) (9)

Issue 75: Generic Implications of ATWS Events at the Salem Nuclear Plant (Rev. 1) (38)

Issue 76: Instrumentation and Control Power Interactions (Rev. 3) (21)

Issue 77: Flooding of Safety Equipment Compartments by Backflow Through Floor Drains (Rev. 1) (11)

Issue 78: Monitoring of Fatigue Transient Limits for Reactor Coolant System (Rev. 3) (12)

Issue 79: Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown (Rev. 3) (10)

Issue 80: Pipe Break Effects on Control Rod Drive Hydraulic Lines in the Drywells of BWR Mark I and II Containments (Rev. 4) (49)

Issue 81: Impact of Locked Doors and Barriers on Plant and Personnel Safety (Rev. 5) (17)

Issue 82: Beyond Design Basis Accidents in Spent Fuel Pools (Rev. 3) (12)

Issue 83: Control Room Habitability (Rev. 3) (5)

Issue 84: CE PORVs (Rev. 2) (4)

Issue 85: Reliability of Vacuum Breakers Connected to Steam Discharge Lines Inside BWR Containments (Rev. 2) (13)

Issue 86: Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping (Rev. 1) (5)

Issue 87: Failure of HPCI Steam Line Without Isolation (Rev. 2) (14)

Issue 88: Earthquakes and Emergency Planning (5)

Issue 89: Stiff Pipe Clamps (Rev. 2) (25)

Issue 90: Technical Specifications for Anticipatory Trips (Rev. 2) (27)

Issue 91: Main Crankshaft Failures in Transamerica Delaval Emergency Diesel Generators (Rev. 1) (5)

Issue 92: Fuel Crumbling During LOCA (Rev. 1) (12)

Issue 93: Steam Binding of Auxiliary Feedwater Pumps (Rev. 1) (13)

Issue 94: Additional Low Temperature Overpressure Protection for Light Water Reactors (Rev. 1) (11)

Issue 95: Loss of Effective Volume for Containment Recirculation Spray (15)

Issue 96: RHR Suction Valve Testing (15)

Issue 97: PWR Reactor Cavity Uncontrolled Exposures (12)

Issue 98: CRD Accumulator Check Valve Leakage (10)

Issue 99: RCS/RHR Suction Line Valve Interlock on PWRs (Rev. 3) (17)

Issue 100: Once-Through Steam Generator Level (Rev. 1) (15)

Issue 101: BWR Water Level Redundancy (Rev. 1)

Issue 102: Human Error in Events Involving Wrong Unit or Wrong Train (Rev. 2) (7)

Issue 103: Design for Probable Maximum Precipitation (Rev. 1) (6)

Issue 104: Reduction of Boron Dilution Requirements (2)

Issue 105: Interfacing Systems LOCA at LWRs (Rev. 4) (14)

Issue 106: Piping and the Use of Highly Combustible Gases in Vital Areas (Rev. 2) (16)

Issue 107: Main Transformer Failures (Rev. 3) (14)

Issue 108: BWR Suppression Pool Temperature Limits (10)

Issue 109: Reactor Vessel Closure Failure (5)

Issue 110: Equipment Protective Devices on Engineered Safety Features (Rev. 1) (16)

Issue 111: Stress Corrosion Cracking of Pressure Boundary Ferritic Steels in Selected Environments (Rev. 2) (24)

Issue 112: Westinghouse RPS Surveillance Frequencies and Out-of-Service Times (10)

Issue 113: Dynamic Qualification Testing of Large Bore Hydraulic Snubbers (Rev. 2) (19)

Issue 114: Seismic-Induced Relay Chatter (Rev. 1) (5)

Issue 115: Enhancement of the Reliability of Westinghouse Solid State Protection System (Rev. 2) (29)

Issue 116: Accident Management (13)

Issue 117: Allowable Time for Diverse Simultaneous Equipment Outages (13)

Issue 118: Tendon Anchor Head Failure (Rev. 1) (6)

Issue 119: Piping Review Committee Recommendations (Rev. 4) (17)

Issue 120: On-Line Testability of Protection Systems (Rev. 2) (14)

Issue 121: Hydrogen Control for Large, Dry PWR Containments (Rev. 2) (2)

Issue 122: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Short-Term Actions (Rev. 4) (77)

Issue 123: Deficiencies in the Regulations Governing DBA and Failure Criterion Suggested by the Davis-Besse Incident of June 9, 1985 (Rev. 1) (6)

Issue 124: Auxiliary Feedwater System Reliability (Rev. 3) (3)

Issue 125: Davis-Besse Loss of All Feedwater Event of June 9, 1985 - Long-Term Actions (Rev. 7) (256)

Issue 126: Reliability of PWR Main Steam Safety Valves (26)

Issue 127: Maintenance and Testing of Manual Valves in Safety-Related Systems (Rev. 1) (11)

Issue 128: Electrical Power Reliability (Rev. 2) (2)

Issue 129: Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling (19)

Issue 130: Essential Service Water Pump Failures at Multiplant Sites (Rev. 2) (18)

Issue 131: Potential Seismic Interaction Involving the Movable In-Core Flux Mapping System Used in Westinghouse-Designed Plants (Rev. 1) (22)

Issue 132: RHR System Inside Containment (Rev. 1) (21)

Issue 133: Update Policy Statement on Nuclear Plant Staff Working Hours (Rev. 1) (3)

Issue 134: Rule on Degree and Experience Requirement (Rev. 1) (2)

Issue 135: Steam Generator and Steam Line Overfill (Rev. 3) (2)

Issue 136: Storage and Use of Large Quantities of Cryogenic Combustibles on Site (5)

Issue 137: Refueling Cavity Seal Failure (13)

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) (18)

Issue 139: Thinning of Carbon Steel Piping in LWRs (Rev. 1) (24)

Issue 140: Fission Product Removal Systems (2)

Issue 141: Large Break LOCA with Consequential SGTR (14)

Issue 142: Leakage Through Electrical Isolators in Instrumentation Circuits (Rev. 4)

Issue 143: Availability of Chilled Water Systems and Room Cooling (Rev. 2) (15)

Issue 144: Scram Without a Turbine/Generator Trip (Rev. 2) (16)

Issue 145: Actions to Reduce Common Cause Failures (Rev. 3) (18)

Issue 146: Support Flexibility of Equipment and Components (Rev. 2) (33)

Issue 147: Fire-Induced Alternate Shutdown/control Room Panel Interactions (Rev. 1) (14)

Issue 148: Smoke Control and Manual Fire-fighting Effectiveness (17)

Issue 149: Adequacy of Fire Barriers (Rev. 2) (15)

Issue 150: Overpressurization of Containment Penetrations (Rev. 1) (15)

Issue 151: Reliability of Anticipated Transient Without Scram Recirculatlon Pump Trip in BWRs (Rev. 2) (14)

Issue 152: Design Basis for Valves That Might Be Subjected to Significant Blowdown Loads (Rev. 3) (15)

Issue 153: Loss of Essential Service Water in LWRs (Rev. 2) (14)

Issue 154: Adequacy of Emergency and Essential Lighting (Rev. 2) (16)

Issue 155: Generic Concerns Arising from TMI-2 Cleanup (Rev. 3) (23)

Issue 156: Systematic Evaluation Program (Rev. 8) (115)

Issue 157: Containment Performance (Rev. 1) (39)

Issue 158: Performance of Safety-Related Power-Operated Valves under Design Basis Conditions (17)

Issue 159: Qualification of Safety-Related Pumps While Running on Minimum Flow (Rev. 1) (6)

Issue 160: Spurious Actuations of Instrumentation upon Restoration of Power (Rev. 1) (15)

Issue 161: Use of Non-Safety-Related Power Supplies in Safety-Related Circuits (Rev. 1) (2)

Issue 162: Inadequate Technical Specifications for Shared Systems at Multiplant Sites When One Unit is Shut Down (Rev. 1) (3)

Issue 163: Multiple Steam Generator Tube Leakage (16)

Issue 164: Neutron Fluence in Reactor Vessel (Rev. 1) (4)

Issue 165: Spring-Actuated Safety and Relief Valve Reliability (Rev. 2) (19)

Issue 166: Adequacy of Fatigue Life of Metal Components (Rev. 2) (2)

Issue 167: Hydrogen Storage Facility Separation (Rev. 2) (13)

Issue 168: Environmental Qualification of Electrical Equipment (Rev. 3) (2)

Issue 169: BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure (Rev. 1) (17)

Issue 170: Fuel Damage Criteria for High Burnup Fuel (Rev. 2) (9)

Issue 171: ESF Failure from Loop Subsequent to a LOCA (Rev. 1) (17)

Issue 172: Multiple System Responses Program (Rev. 2) (66)

Issue 173: Spent Fuel Storage Pool (Rev. 4) (11)

Issue 174: Fastener Gaging Practices (Rev. 1) (10)

Issue 175: Nuclear Power Plant Shift Staffing (Rev. 1) (5)

Issue 176: Loss of Fill-Oil in Rosemount Transmitters (Rev. 1) (5)

Issue 177: Vehicle Intrusion at TMI (5)

Issue 178: Effect of Hurricane Andrew on Turkey Point (Rev. 2) (2)

Issue 179: Core Performance (2)

Issue 180: Notice of Enforcement Discretion (Rev. 1) (2)

Issue 181: Fire Protection (Rev. 2) (2)

Issue 182: General Electric Extended Power Uprate (Rev. 1) (3)

Issue 183: Cycle-Specific Parameter Limits in Technical Specifications (Rev. 2) (2)

Issue 184: Endangered Species (3)

Issue 185: Control of Recriticality Following Small-Break LOCAs in PWRs (19)

Issue 186: Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants (10)

Issue 187: The Potential Impact of Postulated Cesium Concentration on Equipment Qualification (2)

Issue 188: Steam Generator Tube Leaks or Ruptures, Concurrent with Containment Bypass from Main Steam Line or Feedwater Line Breaches (12)

Issue 189: Susceptibility of Ice Condenser And Mark III Containments to Early Failure From Hydrogen Combustion During a Severe Accident (36)

Issue 190: Fatigue Evaluation of Metal Components for 60-Year Plant Life (Rev. 2) (2)

Issue 191: Assessment of Debris Accumulation on PWR Sump Performance (1)

Issue 192: Secondary Containment Drawdown Time (17)

Issue 193: BWR ECCS Suction Concerns Description (36)

Issue 194: Implications of Updated Probabilistic Seismic Hazard Estimates (9)

Issue 195: Hydrogen Combustion in BWR Piping

Issue 196: Boral Degradation (13)

Issue 197: Iodine Spiking Phenomena (48)

Issue 198: Hydrogen Combustion in PWR Piping (15)

Issue 199: Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern U.S. for Existing Plants (8)

Issue 200: Tin Whiskers (5)

Issue 201: Small-Break LOCA and Loss of Offsite Power (9)

Issue 202: Spent Fuel Pool Leakage Impacts (9)

Issue 203: Potential Safety Issues with Cranes That Lift Spent Fuel Casks (3)

ISSUE 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES (2)

Section 5 Chernobyl Issues (6)

Task CH1: Administrative Controls and Operational Practices (Rev. 1) (40)

Task CH2: Design (Rev. 1) (26)

Task CH3: Containment (Rev. 1) (7)

Task CH4: Emergency Planning (Rev. 1) (17)

Task CH5: Severe Accident Phenomena (Rev. 1) (14)

Task CH6: Graphite-Moderated Reactors (10)

Section 6. Nuclear Material Safety and Safeguards Issues (22)

NMSS-0001. Door Interlock Failure Resulting from Faulty Microselectron High Dose Rate Remote Afterloader (2)

NMSS-0002. Significant Quantities of Fixed Contamination Remain in Krypton-85 Leak-Detection Devices after Venting (2)

NMSS-0003. Corrosion of Sealed Sources Caused by Sensitization of Stainless Steel Source Capsules During Shipment (2)

NMSS-0004. Overexposures Caused by Sources Stolen from Facility of Bankrupt Licensee (2)

NMSS-0005. Potential for Erroneous Calibration, Dose Rate, or Radiation Exposure Measurements with Victoreen Electrometers (2)

NMSS-0006. Criticality in Low-Level Waste (Rev. 1) (2)

NMSS-0007. Criticality Benchmarks Greater than 5% Enrichment (Rev. 2) (4)

NMSS-0008. Year 2000 Computer Problem - Non-Reactor Licensees (Rev. 1) (2)

NMSS-0009. Amersham Radiography Source Cable Failures (2)

NMSS-0010. Troxler Gauge Source Rod Weld Failures (Rev. 1) (2)

NMSS-0011. Spent Fuel Dry Cask Weld Cracks (2)

NMSS-0012. Inadequate Transportation Packaging Puncture Tests (Rev. 1) (2)

NMSS-0013. Use of Different Dose Equivalent Models to Show Compliance (Rev. 1) (2)

NMSS-0014. Surety Estimates for Groundwater Restoration at in Situ Leach Facilities (Rev. 1) (2)

NMSS-0015. Adequacy of 10 CFR 150 Criticality Requirements (Rev. 1) (2)

NMSS-0016. Adequacy of 0.05 Weight Percent Limit in 10 CFR 40 (Rev. 1) (2)

NMSS-0017. Misleading Marketing Information to General Licensees (2)

NMSS-0018. Problems Encountered When Manually Editing Treatment Planning Data on Nucletron Microselectron-HDR Model 105.999 (2)

Resolution of Generic Safety Issues: NMSS-0019. Control Unit Failures of Classic Nucletron HDR Units (2)

NMSS-0020. Leaking Pools (2)

NMSS-0021. Unlikely Events (2)

NMSS-0022. Gamma Stereotactic Radiosurgery (2)

Section 7 Fukushima Issues (2)

Issue 199: Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern U.S. for Existing Plants (9)

ISSUE 204: FLOODING OF NUCLEAR POWER PLANT SITES FOLLOWING UPSTREAM DAM FAILURES (2)

Appendix A: Releases from Containment

Appendix B: Generic Issues requiring licensees review in applications for design certification and combined licenses

Appendix C: Priority Ranking Numerical Thresholds Used in Prioritizations Completed Before June 30, 1993 (1)

Appendix D: Related Generic Activities (22)

Appendix E: Generic Communication and Compliance Activities (747)

Appendix F: Nuclear Material Safety and Safeguards GSIs (Rev. 6)

Appendix G: Generic Issues Program Current and Historical Procedures (49)

Revision History

2068.

Point Beach Nuclear Plant, Units 1 and 2 - Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident. [ML18200A181]

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