Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants

목차 (Table of Contents)

• CONTENTS
• SUMMARY AND CONCLUSIONS = ⅴ
• 1. INTRODUCTION = 1-1
• 1.1 Background = 1-1
• 1.2 Bulletins & Orders Task Force = 1-1
• 1.2.1 Charter = 1-3
• 1.2.2 Scope of Activities = 1-3
• 1.2.3 Summary of Activities = 1-5
• 1.3 Conclusions = 1-7
• 2. LICENSING BASES AND REGULATIONS = 1-9
• 3. OFFICE OF INSPECTION AND ENFORCEMENT BULLETINS = 1-10
• 4. GENERAL FINDINGS AND RECOMMENDATIONS = 1-11
• 4.1 Licensing Positions Regarding Implementation of Short-Term Measures = 1-11
• 4.2 Recommendations for Further Improvements in Design, Operation, and Procedures = 1-14
• 4.3 Recommended Implementation Schedule = 1-16
• APPENDIX A GE-BWR PLANT COMPARISON = A-1
• 1. General Features = A-1
• 2. Design Characteristics of Operating and Near-Term OL BWR Plants = A-6
• 2.1 Principal Design Characteristics = A-6
• 2.2 Condensate and Feedwater System = A-6
• 2.3 Reactor Core Isolation Cooling System = A-13
• 2.4 Isolation Condenser = A-15
• 2.5 High Pressure Coolant Injection System = A-18
• 2.6 Low Pressure Coolant Injection System = A-22
• 2.7 Core Spray System = A-24
• 2.8 Safety／Relief Valves = A-30
• 2.9 Automatic Depressurization System = A-32
• 2.10 Reactor Venting = A-34
• 2.11 Containment Spray／Cooling = A-35
• 2.12 Containment Isolation System = A-35
• 2.13 Service Water System = A-38
• 2.14 Reactor Building Closed Cooling Water System = A-39
• 2.15 Instrument Air System = A-39
• 2.16 Control Rod Drive System = A-41
• 2.17 Vessel Level Detection = A-43
• 3. Plant Response to Loss of Feedwater Events = A-66
• 3.1 Steady-State Operation = A-66
• 3.2 Loss of Feedwater Event(Normal Case) = A-67
• 3.3 Loss of Feedwater with Stuck-Open Safety／Relief Valve = A-68
• 3.4 Loss of Feedwater Event with Loss of Offsite Power and Stuck-Open Safety Relief Valve = A-69
• 3.5 Loss of Feedwater Event with Loss of Onsite Power(Total Loss of AC) = A-71
• APPENDIX B BWR PLANT OPERATIONS = B-1
• 1. Survey of Feedwater-Related Events = B-1
• 2. Summary of BWR Experience with Safety／Relief Valves = B-11
• 2.1 Design = B-11
• 2.2 Transients Resulting in Opening of Relief Valves(or SRVs in the Relief Mode) = B-16
• 2.3 Performance = B-22
• 2.4 Valve Discharge Capability = B-24
• 2.5 Alternatives to Increase SRV Reliability = B-25
• 2.5.1 Design Change = B-25
• 2.5.2 Setpoint Modification = B-25
• 2.5.3 Valve Maintenance = B-25
• 2.5.4 Elimination of Relief Function = B-25
• 2.5.5 Reduction in Number of Events = B-27
• 2.5.6 Lessons Learned Task Force Recommendations = B-27
• 2.6 Conclusions and Recommendations = B-27
• 2.7 Final Notes = B-28
• APPENDIX C OPERATOR TRAINING AND OPERATING PROCEDURE CONSIDERATIONS = C-1
• 1. Training = C-1
• 1.1 Findings = C-1
• 1.2 Recommendations = C-1
• 2. Operating Procedures = C-3
• 2.1 Findings = C-3
• 2.2 Recommendations = C-4
• 3.0 Human Factors = C-5
• 3.1 Findings = C-5
• 3.2 Recommendations = C-5
• 4.0 Operator Actions During Recovery From Loss of Feedwater Transient = C-6
• 4.1 Background = C-6
• 4.2 Conclusions = C-6
• APPENDIX D LICENSING BASIS AND REGULATIONS = D-1
• 1. Licensing Overview = D-1
• 2. Final Safety Analysis Reports for Operating BWRs = D-3
• 2.1 Loss of Normal Feedwater = D-3
• 2.2 Loss of Feedwater and HPCI(HPCS) and RCIC Systems = D-3
• 3. Status of Models Used in BWR Safety Analyses = D-4
• 4. Standard Review Plans = D-5
• 5. General Design Criteria = D-6
• 6. References = D-7
• APPENDIX E INSPECTION AND ENFORCEMENT BULLETINS(TMI-2) = E-1
• 1. Introduction = E-1
• 2. Actions Required by IE Bulletins = E-1
• 2.1 Review Actions = E-1
• 2.2 Changes to Plant Design Features and Operating Procedures = E-4
• 3. Evaluation of Licensee Responses to IE Bulletins = E-5
• APPENDIX F ANALYSIS = F-1
• 1. Introduction = F-1
• 2. Summary of Analysis Conclusions and Recommendations = F-3
• 2.1 Small-Break LOCA Model Improvement and Verification = F-3
• 2.2 Conformance of Anlayses to Expected Plant Response = F-4
• 2.3 Availability of HPCI, RCIC, and ADS = F-6
• 2.4 Natural Circulation Under Degraded Conditions = F-6
• 2.5 Safety／Relief Valve Performance = F-7
• 3. Expected Frequency of Small-Break LOCAs = F-8
• 3.1 Introduction = F-8
• 3.2 Date from Operating Reactors = F-8
• 3.3 Evaluation of Anticipated Transients = F-9
• 3.4 Plant Modifications to Prevent Relief Valve Challenges = F-10
• 3.5 Conclusions and Recommendations = F-11
• 3.5.1 Conclusion = F-11
• 3.5.2 Recommendations = F-11
• 4. Small-Break LOCA Analyses = F-12
• 4.1 Introduction = F-12
• 4.2 Analytical Methods = F-12
• 4.2.1 Modifications to the SAFE Code = F-13
• 4.2.2 Counter-Current Flow Limitation = F-14
• 4.2.3 Core Bypass Modeling = F-14
• 4.2.4 Spray Heat Transfer Coefficient = F-15
• 4.2.5 Decay Heat Model = F-15
• 4.2.6 Automatic Depressurization System = F-15
• 4.2.7 Feedwater Flow Modeling = F-15
• 4.2.8 Core Heat Transfer = F-15
• 4.2.9 Reactor Vessel Internal Flows = F-16
• 4.2.10 Conclusions and Recommendations = F-16
• 4.3 Small-Break LOCA Analytical Predictions = F-17
• 4.4 Computer Model Verification = F-30
• 4.4.1 Integral Small-Break Experiments = F-31
• 4.4.2 Modeling Assumptions to be Verified = F-31
• 4.4.3 Limitations of TLTA = F-31
• 4.4.4 Conclusions and Recommendations = F-32
• 4.5 Natural Circulation = F-33
• 4.5.1 Natural Circulation Under Normal Conditions = F-33
• 4.5.2 Natural Circulation Under Degraded Conditions = F-33
• 4.5.3 Natural Circulation for Depressurization = F-35
• 4.6 Michelson Concerns = F-36
• 4.7 Staff Audit Calculation = F-36
• 4.7.1 Introduction = F-36
• 4.7.2 B&OTF Audit Model and Assumptions = F-37
• 4.7.3 Model and Modeling Differences = F-42
• 4.7.4 Audit Analyses Comparisons = F-42
• 4.7.5 Conclusions and Recommendations = F-60
• 5. References = F-64
• APPENDIX G GENERAL CONCLUSIONS, FINDINGS AND RECOMMENDATIONS = G-1
• 1. General Conclusions = G-1
• 2. Plant Design = G-1
• 3. Operations = G-2
• 3.1 Training = G-2
• 3.2 Operating Procedures = G-2
• 3.3 Human Factors = G-3
• 4. Standard Review Plan = G-3
• 5. General Design Criteria = G-3
• APPENDIX H AUDITS OF SMALL-BREAK LOCA EMERGENCY PROCEDURES AND OPERATOR RETRAINING AT SELECTED GE BWR OPERATING PLANTS = H-1
• 1. Introduction = H-1
• 2. Background = H-1
• 3. Plant Audits = H-1
• 4. Findings = H-2
• 5. Simulator Visit = H-5
• 6. Conclusions = H-5
• 7. Recommendations = H-5