ML21278A277
| ML21278A277 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/07/2021 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21278A102 | List:
|
| References | |
| NEI 99-04 | |
| Download: ML21278A277 (20) | |
Text
CHAPTER 14 SAFETY ANALYSIS TABLE OF CONTENTS PAGE 14.0 SAFETY ANALYSIS 14.1-1 14.1 ORGANIZATION AND METHODOLOGY 14.1-1 14.1.1 CLASSIFICATION OF TRANSIENTS AND ACCIDENTS 14.1-1 14.1.1.1 Categorization 14.1-1 14.1.1.2 Acceptance Criteria 14.1-2 14.1.1.3 Section Numbering 14.1-3 14.1.2 PLANT CHARACTERISTICS CONSIDERED IN SAFETY 14.1-3 ANALYSIS 14.1.2.1 Initial Conditions 14.1-3 14.1.2.2 Input Parameters 14.1-3 14.1.3 ASSUMED PROTECTION SYSTEM ACTIONS 14.1-5 14.1.3.1 Sequence of Events and Systems Operation 14.1-5 14.1.3.2 Protection System Setpoints 14.1-5 14.1.3.3 Control System Operational Status 14.1-6 14.1.4 CORE AND SYSTEM PERFORMANCE 14.1-6 14.1.4.1 Mathematical Models 14.1-6 14.1.4.2 Operator Action Requirement 14.1-14 14.1.4.3 Activity Release Methodology 14.1-15 14.1.4.4 Fuel Performance Models and Acceptance Criteria 14.1-17 14.
1.5 REFERENCES
14.1-19 14.2 CONTROL ELEMENT ASSEMBLY WITHDRAWAL EVENT 14.2-1 14.2.1 IDENTIFICATION OF EVENT AND CAUSE 14.2-1 14.2.2 SEQUENCE OF EVENTS 14.2-1 14.2.2.1 Zero Power Case 14.2-2 14.2.2.2 Full Power Case 14.2-3 14.2.3 CORE AND SYSTEM PERFORMANCE 14.2-4 14.2.3.1 Mathematical Models 14.2-4 14.2.3.2 Input Parameters and Initial Conditions 14.2-4 14.2.3.3 Results 14.2-5 14.
2.4 CONCLUSION
S 14.2-6 14.
2.5 REFERENCES
14.2-6 14.3 BORON DILUTION EVENT 14.3-1 14.3.1 IDENTIFICATION OF EVENT AND CAUSE 14.3-1 14.3.2 SEQUENCE OF EVENTS 14.3-1 14.3.2.1 Power Operation and Startup 14.3-2 14.3.2.2 Hot Standby, Hot Shutdown 14.3-2 14.3.2.3 Cold Shutdown 14.3-2 14.3.2.4 Refueling 14.3-2 CALVERT CLIFFS UFSAR 14-i Rev. 52
CHAPTER 14 SAFETY ANALYSIS TABLE OF CONTENTS PAGE 14.3.3 CORE AND SYSTEM PERFORMANCE 14.3-3 14.3.3.1 Mathematical Models 14.3-3 14.3.3.2 Input Parameters and Initial Conditions 14.3-3 14.3.3.3 Results 14.3-4 14.
3.4 CONCLUSION
14.3-4 14.3.5 NRC ACCEPTANCE LIMIT 14.3-4 14.
3.6 REFERENCES
14.3-4 14.4 EXCESS LOAD EVENT 14.4-1 14.4.1 IDENTIFICATION OF EVENT AND CAUSE 14.4-1 14.4.2 SEQUENCE OF EVENTS 14.4-1 14.4.2.1 Zero Power Case 14.4-1 14.4.2.2 Full Power Case 14.4-3 14.4.3 CORE AND SYSTEM PERFORMANCE 14.4-4 14.4.3.1 Mathematical Models 14.4-4 14.4.3.2 Input Parameters and Initial Conditions 14.4-4 14.4.3.3 Results 14.4-5 14.
4.4 CONCLUSION
14.4-6 14.
4.5 REFERENCES
14.4-6 14.5 LOSS OF LOAD EVENT 14.5-1 14.5.1 IDENTIFICATION OF EVENT AND CAUSE 14.5-1 14.5.2 SEQUENCE OF EVENTS 14.5-1 14.5.3 CORE AND SYSTEM PERFORMANCE 14.5-2 14.5.3.1 Mathematical Models 14.5-2 14.5.3.2 Input Parameters and Initial Conditions 14.5-2 14.5.3.3 Results 14.5-2 14.
5.4 CONCLUSION
S 14.5-3 14.6 LOSS OF FEEDWATER FLOW EVENT 14.6-1 14.6.1 IDENTIFICATION OF EVENT AND CAUSE 14.6-1 14.6.2 SEQUENCE OF EVENTS 14.6-1 14.6.3 CORE AND SYSTEM PERFORMANCE 14.6-2 14.6.3.1 Mathematical Models 14.6-2 14.6.3.2 Input Parameters and Initial Conditions 14.6-3 14.6.3.3 Results 14.6-3 14.
6.4 CONCLUSION
S 14.6-4 14.7 EXCESS FEEDWATER HEAT REMOVAL EVENT 14.7-1 14.
7.1 INTRODUCTION
14.7-1 14.7.2 PHYSICAL DESCRIPTION OF EVENT 14.7-1 14.7.3 METHODOLOGY 14.7-1 14.7.4 INPUTS AND ASSUMPTIONS 14.7-2 CALVERT CLIFFS UFSAR 14-ii Rev. 52
CHAPTER 14 SAFETY ANALYSIS TABLE OF CONTENTS PAGE 14.7.5 RESULTS 14.7-2 14.
7.6 CONCLUSION
S 14.7-2 14.8 REACTOR COOLANT SYSTEM DEPRESSURIZATION 14.8-1 14.8.1 IDENTIFICATION OF EVENT AND CAUSE 14.8-1 14.8.2 SEQUENCE OF EVENTS 14.8-1 14.8.3 CORE AND SYSTEM PERFORMANCE 14.8-2 14.8.3.1 Mathematical Models 14.8-2 14.8.3.2 Input Parameters and Initial Conditions 14.8-2 14.8.3.3 Results 14.8-2 14.
8.4 CONCLUSION
14.8-2 14.
8.5 REFERENCES
14.8-3 14.9 LOSS-OF-COOLANT FLOW EVENT 14.9-1 14.9.1 IDENTIFICATION OF EVENT AND CAUSE 14.9-1 14.9.2 SEQUENCE OF EVENTS 14.9-1 14.9.3 CORE AND SYSTEM PERFORMANCE 14.9-2 14.9.3.1 Mathematical Models 14.9-2 14.9.3.2 Input Parameters and Initial Conditions 14.9-2 14.9.3.3 Results 14.9-2 14.
9.4 CONCLUSION
14.9-3 14.
9.5 REFERENCES
14.9-3 14.10 LOSS-OF-NON-EMERGENCY AC POWER 14.10-1 14.10.1 IDENTIFICATION OF EVENT AND CAUSE 14.10-1 14.10.2 SEQUENCE OF EVENTS 14.10-1 14.10.3 CORE AND SYSTEM PERFORMANCE 14.10-2 14.10.3.1 Mathematical Models 14.10-2 14.10.3.2 Input Parameters and Initial Conditions 14.10-3 14.10.3.3 Results 14.10-3 14.
10.4 CONCLUSION
14.10-3 14.11 CONTROL ELEMENT ASSEMBLY DROP EVENT 14.11-1 14.11.1 IDENTIFICATION OF EVENT AND CAUSE 14.11-1 14.11.2 SEQUENCE OF EVENTS 14.11-1 14.11.3 CORE AND SYSTEM PERFORMANCE 14.11-2 14.11.3.1 Mathematical Models 14.11-2 14.11.3.2 Input Parameters and Initial Conditions 14.11-2 14.11.3.3 Results 14.11-3 14.
11.4 CONCLUSION
14.11-3 14.
11.5 REFERENCES
14.11-3 14.12 ASYMMETRIC STEAM GENERATOR EVENT 14.12-1 14.12.1 IDENTIFICATION OF EVENT AND CAUSE 14.12-1 CALVERT CLIFFS UFSAR 14-iii Rev. 52
CHAPTER 14 SAFETY ANALYSIS TABLE OF CONTENTS PAGE 14.12.2 SEQUENCE OF EVENTS 14.12-1 14.12.2.1 Asymmetric Excess Feedwater 14.12-1 14.12.2.2 Asymmetric Loss of Feedwater 14.12-1 14.12.2.3 Asymmetric Excess Load 14.12-2 14.12.2.4 Asymmetric Loss of Load 14.12-2 14.12.3 CORE AND SYSTEM PERFORMANCE 14.12-3 14.12.3.1 Mathematical Models 14.12-3 14.12.3.2 Input Parameters and Initial Conditions 14.12-3 14.12.3.3 Results 14.12-3 14.
12.4 CONCLUSION
14.12-4 14.
12.5 REFERENCES
14.12-4 14.13 CONTROL ELEMENT ASSEMBLY EJECTION 14.13-1 14.13.1 IDENTIFICATION OF EVENT AND CAUSE 14.13-1 14.13.2 SEQUENCE OF EVENTS 14.13-1 14.13.2.1 Zero Power Case 14.13-1 14.13.2.2 Full Power Case 14.13-1 14.13.3 CORE AND SYSTEM PERFORMANCE 14.13-2 14.13.3.1 Mathematical Models 14.13-2 14.13.3.2 Input Parameters and Initial Conditions 14.13-3 14.13.3.3 Results 14.13-3 14.13.4 DOSE ANALYSIS 14.13-4 14.
13.5 CONCLUSION
14.13-5 14.
13.6 REFERENCES
14.13-6 14.14 STEAM LINE BREAK EVENT 14.14-1 14.14.1 IDENTIFICATION OF EVENT AND CAUSE 14.14-1 14.14.2 DISCUSSION OF MAIN STEAM ISOLATION VALVE TESTING 14.14-1 14.14.3 SEQUENCE OF EVENTS 14.14-3 14.14.4 CORE AND SYSTEM PERFORMANCE 14.14-5 14.14.4.1 Mathematical Models 14.14-5 14.14.4.2 Input Parameters and Initial Conditions 14.14-5 14.14.4.3 Results 14.14-9 14.
14.5 CONCLUSION
S 14.14-10 14.
14.6 REFERENCES
14.14-10 14.15 STEAM GENERATOR TUBE RUPTURE EVENT 14.15-1 14.15.1 IDENTIFICATION OF EVENT AND CAUSES 14.15-1 14.15.2 SEQUENCE OF EVENTS AND SYSTEMS OPERATION 14.15-2 14.15.3 ANALYSIS OF EFFECTS AND CONSEQUENCES 14.15-4 14.15.3.1 Core and System Performance 14.15-4 14.15.3.2 Radiological Consequences 14.15-6 CALVERT CLIFFS UFSAR 14-iv Rev. 52
CHAPTER 14 SAFETY ANALYSIS TABLE OF CONTENTS PAGE 14.
15.4 CONCLUSION
14.15-9 14.
15.5 REFERENCES
14.15-9 14.16 SEIZED ROTOR EVENT 14.16-1 14.16.1 IDENTIFICATION OF EVENT AND CAUSE 14.16-1 14.16.2 SEQUENCE OF EVENTS 14.16-1 14.16.3 CORE AND SYSTEM PERFORMANCE 14.16-2 14.16.3.1 Mathematical Models 14.16-2 14.16.3.2 Input Parameters and Initial Conditions 14.16-2 14.16.3.3 Results 14.16-2 14.16.4 DOSE ANALYSIS 14.16-3 14.
16.5 CONCLUSION
14.16-4 14.
16.6 REFERENCES
14.16-4 14.17 LOSS-OF-COOLANT ACCIDENT 14.17-1 14.
17.1 INTRODUCTION
AND
SUMMARY
14.17-1 14.17.2 LARGE BREAK LOCA ANALYSIS 14.17-2 14.17.2.1 Event Description 14.17-3 14.17.2.2 Evaluation Model 14.17-4 14.17.2.3 Plant Description and Summary of Analysis 14.17-7 Parameters 14.17.2.4 Analysis of Results 14.17-8 14.17.2.5 Conclusions 14.17-9 14.17.3 SMALL BREAK LOCA ANALYSIS 14.17-9 14.17.3.1 Event Description 14.17-10 14.17.3.2 Evaluation Model 14.17-10 14.17.3.3 Plant Description and Summary of Analysis 14.17-11 Parameters 14.17.3.4 Results of the Small Break Analysis 14.17-12 14.17.3.5 Conclusions 14.17-13 14.17.4 CURRENT CYCLE ANALYSES 14.17-13 14.17.4.1 Unit 1 14.17-13 14.17.4.2 Unit 2 14.17-13 14.
17.5 REFERENCES
14.17-13 14.18 FUEL HANDLING INCIDENT 14.18-1 14.18.1 GENERAL 14.18-1 14.18.2 METHOD OF ANALYSIS 14.18-2 14.18.3 RESULTS 14.18-4 14.18.3.1 Fuel Handling Incident in Containment 14.18-4 14.18.3.2 Fuel Handling Incident in the Spent Fuel Pool Area 14.18-4 14.
18.4 CONCLUSION
14.18-5 CALVERT CLIFFS UFSAR 14-v Rev. 52
CHAPTER 14 SAFETY ANALYSIS TABLE OF CONTENTS PAGE 14.
18.5 REFERENCES
14.18-5 14.19 TURBINE-GENERATOR OVERSPEED INCIDENT 14.19-1 14.20 CONTAINMENT RESPONSE 14.20-1 14.
20.1 INTRODUCTION
14.20-1 14.20.2 LOSS-OF-COOLANT ACCIDENT 14.20-1 14.20.2.1 Description of Event 14.20-1 14.20.2.2 Mass and Energy Release 14.20-3 14.20.2.3 Containment Response Analysis 14.20-4 14.20.2.4 Inputs and Assumptions 14.20-12 14.20.2.5 Results 14.20-14 14.20.2.6 Summary of LOCA Analysis and Effect of the RSGs 14.20-15 14.20.3 MAIN STEAM LINE BREAK 14.20-15 14.20.3.1 Description of Event 14.20-15 14.20.3.2 Mass and Energy Release Methodology 14.20-17 14.20.3.3 Containment Response Analysis Methodology 14.20-17 14.20.3.4 Inputs and Assumptions 14.20-18 14.20.3.5 Analysis Results 14.20-21 14.20.3.6 Summary of MSLB Analysis 14.20-21 14.20.4 SUBCOMPARTMENT ANALYSIS 14.20-22 14.20.4.1 Methodology 14.20-22 14.20.4.2 Inputs and Assumptions 14.20-22 14.20.4.3 Containment Internal Structure Evaluation Results 14.20-23 14.
20.5 CONCLUSION
S 14.20-24 14.
20.6 REFERENCES
14.20-24 14.21 DELETED 14.21-1 14.22 WASTE GAS INCIDENT 14.22-1 14.22.1 GENERAL 14.22-1 14.22.2 METHOD OF ANALYSIS 14.22-1 14.22.3 RESULTS 14.22-1 14.
22.4 CONCLUSION
S 14.22-1 14.
22.5 REFERENCES
14.22-1 14.23 WASTE PROCESSING SYSTEM INCIDENT 14.23-1 14.23.1 GENERAL 14.23-1 14.23.2 METHOD OF ANALYSIS 14.23-1 14.23.3 ASSUMPTIONS 14.23-1 14.23.4 RESULTS 14.23-2 14.
23.5 CONCLUSION
S 14.23-2 14.
23.6 REFERENCES
14.23-2 CALVERT CLIFFS UFSAR 14-vi Rev. 52
CHAPTER 14 SAFETY ANALYSIS TABLE OF CONTENTS PAGE 14.24 MAXIMUM HYPOTHETICAL ACCIDENT 14.24-1 14.24.1 GENERAL 14.24-1 14.24.2 METHOD OF ANALYSIS 14.24-1 14.24.2.1 Control Room 14.24-1 14.24.2.2 Source Terms 14.24-1 14.24.2.3 Containment Pathway 14.24-2 14.24.2.4 Ventilation Stack Pathway 14.24-3 14.24.2.5 Hydrogen Purge Line Pathway 14.24-4 14.24.2.6 Refueling Water Tank Pathway 14.24-4 14.24.2.7 Containment Shine 14.24-5 14.24.2.8 Plume Shine 14.24-5 14.24.2.9 Control Room Filter Shine 14.24-6 14.24.3 RESULTS 14.24-6 14.
24.4 REFERENCES
14.24-7 14.25 EXCESSIVE CHARGING EVENT 14.25-1 14.25.1 IDENTIFICATION OF EVENT AND CAUSE 14.25-1 14.25.2 CORE AND SYSTEM PERFORMANCE 14.25-1 14.25.2.1 Mathematical Models 14.25-1 14.25.2.2 Input Parameters and Initial Conditions 14.25-1 14.25.2.3 Results 14.25-1 14.
25.3 CONCLUSION
S 14.25-1 14.26 FEEDLINE BREAK EVENT 14.26-1 14.26.1 IDENTIFICATION OF EVENT AND CAUSE 14.26-1 14.26.2 SEQUENCE OF EVENTS 14.26-1 14.26.3 CORE AND SYSTEM PERFORMANCE 14.26-2 14.26.3.1 Mathematical Models 14.26-2 14.26.3.2 Input Parameters and Initial Conditions 14.26-2 14.26.3.3 Results 14.26-3 14.
26.4 CONCLUSION
14.26-4 14.
26.5 REFERENCES
14.26-4 CALVERT CLIFFS UFSAR 14-vii Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF TABLES TITLE PAGE 14.1-1 DESIGN BASIS EVENTS 14.1-22 14.1-2 SAFETY ANALYSIS VALVE AND PUMP ASSUMPTIONS 14.1-23 14.1-3 DECONTAMINATION FACTORS USED IN OFFSITE DOSE 14.1-24 CALCULATIONS 14.2-1 INITIAL CONDITIONS AND INPUT PARAMETERS - CEAW 14.2-7 EVENT 14.2-2 SEQUENCE OF EVENTS FOR ZERO POWER CEAW EVENT 14.2-8 14.2-3 SEQUENCE OF EVENTS FOR FULL POWER CEAW EVENT 14.2-9 14.3-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.3-5 BORON DILUTION EVENT 14.3-2 RESULTS OF BORON DILUTION EVENT 14.3-6 14.4-1 INITIAL CONDITIONS AND INPUT PARAMETERS TO 14.4-7 DETERMINE APPROACH TO SAFDLs FOR THE EXCESS LOAD EVENT 14.4-2 SEQUENCE OF EVENTS FOR THE ZERO POWER EXCESS 14.4-8 LOAD CONDITIONS TO CALCULATE MAXIMUM LHR 14.4-3 SEQUENCE OF EVENTS FOR APPROACH TO SAFDLs FOR 14.4-9 THE FULL POWER EXCESS LOAD EVENT 14.5-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.5-4 LOSS OF LOAD EVENT TO CALCULATE MAXIMUM RCS PRESSURE 14.5-2 SEQUENCE OF EVENTS FOR LOSS OF LOAD EVENT TO 14.5-5 MAXIMIZE CALCULATED RCS PEAK PRESSURE 14.5-3 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.5-6 LOSS OF LOAD EVENT TO CALCULATE MAXIMUM SECONDARY PRESSURE 14.5-4 SEQUENCE OF EVENTS FOR LOSS OF LOAD EVENT TO 14.5-7 MAXIMIZE CALCULATED SECONDARY PEAK PRESSURE 14.6-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.6-5 LOFW EVENT TO MAXIMIZE CALCULATED PEAK PRESSURE 14.6-2 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.6-6 LOFW EVENT TO MAXIMIZE SG INVENTORY DEPLETION 14.6-3 SEQUENCE OF EVENTS FOR LOFW EVENT TO MAXIMIZE 14.6-7 CALCULATED PEAK RCS PRESSURE 14.6-4 SEQUENCE OF EVENTS FOR THE LOFW EVENT TO 14.6-8 MAXIMIZE CALCULATED PEAK SECONDARY PRESSURE 14.6-5 SEQUENCE OF EVENTS FOR THE LOFW EVENT TO 14.6-9 MAXIMIZE STEAM GENERATOR INVENTORY DEPLETION 14.7-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.7-3 EXCESS FEEDWATER HEAT REMOVAL EVENT 14.7-2 SEQUENCE OF EVENTS FOR THE EXCESS FEEDWATER 14.7-4 HEAT REMOVAL EVENT CALVERT CLIFFS UFSAR 14-viii Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF TABLES TITLE PAGE 14.8-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR RCS 14.8-4 DEPRESSURIZATION EVENT 14.8-2 SEQUENCE OF EVENTS FOR THE RCS DEPRESSURIZATION 14.8-5 EVENT 14.9-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR LOSS- 14.9-4 OF-COOLANT FLOW EVENT 14.9-2 SEQUENCE OF EVENTS FOR LOSS-OF-COOLANT FLOW 14.9-5 EVENT 14.10-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR LOSS- 14.10-4 OF-NON-EMERGENCY AC POWER EVENT 14.10-2 SEQUENCE OF EVENTS FOR LOSS-OF-NON-EMERGENCY AC 14.10-5 POWER EVENT 14.10-3 RADIOLOGICAL ASSUMPTIONS AND RESULTS FOR LOSS- 14.10-6 OF-NON-EMERGENCY AC POWER EVENT 14.11-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR CEA 14.11-4 DROP EVENT 14.11-2 SEQUENCE OF EVENTS FOR THE CEA DROP EVENT 14.11-5 14.12-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.12-5 LOSS OF LOAD TO ONE STEAM GENERATOR 14.12-2 SEQUENCE OF EVENTS FOR THE LOSS OF LOAD TO ONE 14.12-6 STEAM GENERATOR 14.13-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.13-7 CEA EJECTION EVENT 14.13-2 CEA EJECTION EVENT RESULTS 14.13-8 14.13-3 ASSUMPTIONS FOR RADIOLOGICAL CONSEQUENCES OF 14.13-9 THE CEA EJECTION EVENT 14.14-1 INITIAL CONDITIONS AND INPUT PARAMETERS ASSUMED 14.14-12 FOR THE POST-TRIP SLB EVENT INITIATED FROM FULL POWER 14.14-2 INITIAL CONDITIONS AND INPUT PARAMETERS ASSUMED 14.14-13 FOR THE PRE-TRIP SLB EVENT INITIATED FROM FULL POWER 14.14-3 ASSUMPTIONS FOR THE RADIOLOGICAL EVALUATION FOR 14.14-14 THE SLB EVENT 14.14-4 SEQUENCE OF EVENTS FOR THE POST-TRIP SLB EVENT 14.14-15 14.14-5 SEQUENCE OF EVENTS FOR PRE-TRIP SLB EVENT WITH 14.14-16 LOOP ON TURBINE TRIP INITIATED FROM FULL POWER 14.15-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR THE 14.15-11 STEAM GENERATOR TUBE RUPTURE EVENT 14.15-2 SEQUENCE OF EVENTS FOR THE STEAM GENERATOR TUBE 14.15-12 RUPTURE EVENT 14.15-3 ASSUMPTIONS FOR RADIOLOGICAL CONSEQUENCES OF 14.15-13 THE STEAM GENERATOR TUBE RUPTURE EVENT CALVERT CLIFFS UFSAR 14-ix Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF TABLES TITLE PAGE 14.16-1 INITIAL CONDITIONS AND INPUT PARAMETERS FOR SEIZED 14.16-5 ROTOR EVENT 14.16-2 SEQUENCE OF EVENTS FOR SEIZED ROTOR EVENT 14.16-6 14.16-3 ASSUMPTIONS FOR SEIZED ROTOR DOSE CALCULATION 14.16-7 14.17-1 SAMPLED LARGE BREAK LOCA PARAMETERS 14.17-15 14.17-2 PLANT OPERATING RANGE SUPPORTED BY THE LOCA 14.17-16 ANALYSIS 14.17-3 STATISTICAL DISTRIBUTIONS USED FOR PROCESS 14.17-18 PARAMETERS 14.17-4
SUMMARY
OF MAJOR PARAMETERS FOR THE LIMITING PCT 14.17-19 CASE 14.17-5
SUMMARY
OF HOT ROD LIMITING PCT RESULTS 14.17-20 14.17-6 CALCULATED EVENT TIMES FOR THE LIMITING PCT CASE 14.17-21 14.17-7 CONTAINMENT HEAT SINK DATA 14.17-22 14.17-8 CONTAINMENT INITIAL AND BOUNDARY CONDITIONS 14.17-23 14.17-9 SMALL BREAK LOCA ANALYSIS ECCS PERFORMANCE 14.17-24 14.17-10 SMALL BREAK LOCA ANALYSIS ECCS PERFORMANCE 14.17-25 14.17-11 SMALL BREAK LOCA ANALYSIS ECCS PERFORMANCE` 14.17-26 14.17-12 SMALL BREAK LOCA ECCS PERFORMANCE ANALYSIS 14.17-27 14.18-1 SOURCE TERM FOR FUEL HANDLING ACCIDENT IN 14.18-7 CONTAINMENT OR SPENT FUEL POOL BASED UPON ALTERNATIVE SOURCE TERM METHODOLOGY 14.18-2 OFFSITE AND CONTROL ROOM DOSES FOR A FUEL 14.18-8 HANDLING ACCIDENT IN CONTAINMENT OR SPENT FUEL POOL BASED UPON ALTERNATIVE SOURCE TERM METHODOLOGY 14.20-1
SUMMARY
OF SIGNIFICANT ASSUMPTIONS FOR LOSS-OF- 14.20-28 COOLANT ACCIDENT MASS and ENERGY RELEASE METHODOLOGY 14.20-2 INITIAL CONDITIONS AND KEY ASSUMPTIONS FOR MASS 14.20-30 AND ENERGY RELEASE ANALYSIS OF LOSS-OF-COOLANT ACCIDENT 14.20-3 CONTAINMENT PARAMETERS 14.20-31 14.20-4 CONTAINMENT HEAT SINK THERMODYNAMIC DATA 14.20-32 14.20-5 CONTAINMENT HEAT SINKS 14.20-33 14.20-6 ENGINEERED SAFETY FEATURES PERFORMANCE FOR 14.20-38 LOSS-OF-COOLANT ACCIDENT CONTAINMENT ANALYSES 14.20-7 SEQUENCE OF EVENTS FOR DOUBLE-ENDED DISCHARGE 14.20-40 LEG MINIMUM SI LOSS-OF-COOLANT ACCIDENT 14.20-8
SUMMARY
OF SIGNIFICANT ASSUMPTIONS FOR MAIN 14.20-41 STEAM LINE BREAK MASS and ENERGY RELEASE CALCULATIONS CALVERT CLIFFS UFSAR 14-x Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF TABLES TITLE PAGE 14.20-9 INITIAL CONDITIONS AND KEY ASSUMPTIONS FOR 14.20-42 ANALYSIS OF MASS AND ENERGY RELEASE FOR MAIN STEAM LINE BREAK 14.20-10 INITIAL CONDITIONS AND KEY ASSUMPTIONS FOR 14.20-44 ANALYSIS OF CONTAINMENT RESPONSE TO MAIN STEAM LINE BREAK 14.20-11 ENGINEERED SAFETY FEATURE PERFORMANCE 14.20-45 PARAMETERS USED FOR CONTAINMENT ANALYSIS FOR MAIN STEAM LINE BREAK 14.20-12 SEQUENCE OF EVENTS FOR MAIN STEAM LINE BREAK 14.20-46 INSIDE CONTAINMENT 14.20-13 INPUT PARAMETERS COMPARTMENT PRESSURIZATION 14.20-47 ANALYSIS 14.23-1
SUMMARY
OF COMPONENT DECONTAMINATION FACTORS 14.23-3 AND AMOUNT OF PRIOR PROCESSING CREDITED FOR EACH WASTE PROCESSING SYSTEM COMPONENT 14.25-1 EXCESSIVE CHARGING EVENT - CORE AND SYSTEM 14.25-2 PERFORMANCE FOR CHARGING FLOW AND LETDOWN FLOW 14.26-1 INITIAL CONDITIONS AND INPUT PARAMETERS ASSUMED IN 14.26-5 THE FEEDWATER LINE BREAK EVENT 14.26-2 ASSUMPTIONS FOR THE RADIOLOGICAL EVALUATION FOR 14.26-6 THE FEEDLINE BREAK EVENT 14.26-3 SEQUENCE OF EVENTS FOR FEEDWATER LINE BREAK WITH 14.26-7 LOAC FOLLOWING REACTOR TRIP CALVERT CLIFFS UFSAR 14-xi Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF FIGURES FIGURE 14.2-1 CEAW EVENT - HZP CORE POWER VS TIME 14.2-2 CEAW EVENT - HZP CORE HEAT FLUX VS TIME 14.2-3 CEAW EVENT - HZP RCS TEMPERATURES VS TIME 14.2-4 CEAW EVENT - HZP RCS PRESSURE VS TIME 14.2-5 CEAW EVENT - HFP CORE POWER VS TIME 14.2-6 CEAW EVENT - HFP CORE HEAT FLUX VS TIME 14.2-7 CEAW EVENT - HFP RCS TEMPERATURES VS TIME 14.2-8 CEAW EVENT - HFP RCS PRESSURE VS TIME 14.4-1 EXCESS LOAD EVENT - CORE POWER VS TIME (HFP) 14.4-2 EXCESS LOAD EVENT - CORE HEAT FLUX VS TIME (HFP) 14.4-3 EXCESS LOAD EVENT - RCS TEMPERATURES VS TIME (HFP) 14.4-4 EXCESS LOAD EVENT - PRESSURIZER PRESSURE VS TIME (HFP) 14.4-5 EXCESS LOAD EVENT - REACTIVITIES VS TIME (HFP) 14.4-6 EXCESS LOAD EVENT - SG PRESSURES VS TIME (HFP) 14.4-7 EXCESS LOAD EVENT - CORE POWER VS TIME (HZP) 14.4-8 EXCESS LOAD EVENT - CORE HEAT FLUX VS TIME (HZP) 14.4-9 EXCESS LOAD EVENT - RCS TEMPERATURES VS TIME (HZP) 14.4-10 EXCESS LOAD EVENT - PRESSURIZER PRESSURE VS TIME (HZP) 14.4-11 EXCESS LOAD EVENT - REACTIVITIES VS TIME (HZP) 14.4-12 EXCESS LOAD EVENT - SG PRESSURES VS TIME (HZP) 14.5-1 LOSS OF LOAD EVENT CORE POWER VS TIME 14.5-2 LOSS OF LOAD EVENT CORE AVERAGE HEAT FLUX VS TIME 14.5-3 LOSS OF LOAD EVENT RCS PRESSURE VS TIME 14.5-4 LOSS OF LOAD EVENT RCS TEMPERATURES VS TIME 14.5-5 LOSS OF LOAD EVENT STEAM GENERATOR PRESSURE VS TIME 14.5-6 LOSS OF LOAD EVENT PRESSURIZER WATER VOLUME VS TIME 14.6-1 LOSS OF FEEDWATER FLOW EVENT MAXIMUM RCS PEAK PRESSURE CORE POWER VS TIME 14.6-2 LOSS OF FEEDWATER FLOW EVENT MAXIMUM RCS PEAK PRESSURE RCS TEMPERATURES VS TIME 14.6-3 LOSS OF FEEDWATER FLOW EVENT MAXIMUM RCS PEAK PRESSURE RCS PRESSURE VS TIME 14.6-4 LOSS OF FEEDWATER FLOW EVENT MAXIMUM RCS PEAK PRESSURE STEAM GENERATOR PRESSURE VS TIME 14.6-5 LOSS OF FEEDWATER FLOW EVENT MAXIMUM SECONDARY PEAK PRESSURE CORE POWER VS TIME 14.6-6 LOSS OF FEEDWATER FLOW EVENT MAXIMUM SECONDARY PEAK PRESSURE RCS TEMPERATURES VS TIME 14.6-7 LOSS OF FEEDWATER FLOW EVENT MAXIMUM SECONDARY PEAK PRESSURE PRESSURIZER PRESSURE VS TIME CALVERT CLIFFS UFSAR 14-xii Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF FIGURES FIGURE 14.6-8 LOSS OF FEEDWATER FLOW EVENT MAXIMUM SECONDARY PEAK PRESSURE STEAM GENERATOR PRESSURE VS TIME 14.6-9 LOSS OF FEEDWATER FLOW EVENT MAXIMUM STEAM GENERATOR INVENTORY DEPLETION CORE POWER VS TIME 14.6-10 LOSS OF FEEDWATER FLOW EVENT MAXIMUM STEAM GENERATOR INVENTORY DEPLETION RCS TEMPERATURES VS TIME 14.6-11 LOSS OF FEEDWATER FLOW EVENT MAXIMUM STEAM GENERATOR INVENTORY DEPLETION PRESSURIZER PRESSURE VS TIME 14.6-12 LOSS OF FEEDWATER FLOW EVENT MAXIMUM STEAM GENERATOR INVENTORY DEPLETION STEAM GENERATOR PRESSURE VS TIME 14.6-13 LOSS OF FEEDWATER FLOW EVENT MAXIMUM STEAM GENERATOR INVENTORY DEPLETION STEAM GENERATOR INVENTORY VS TIME 14.7-1 EXCESS FEEDWATER HEAT REMOVAL EVENT, CORE POWER VERSUS TIME 14.7-2 EXCESS FEEDWATER HEAT REMOVAL EVENT, CORE HEAT FLUX VERSUS TIME 14.7-3 EXCESS FEEDWATER HEAT REMOVAL EVENT, RCS TEMPERATURES VERSUS TIME 14.7-4 EXCESS FEEDWATER HEAT REMOVAL EVENT, RCS PRESSURE VERSUS TIME 14.7-5 EXCESS FEEDWATER HEAT REMOVAL EVENT, STEAM GENERATOR PRESSURES VERSUS TIME 14.7-6 EXCESS FEEDWATER HEAT REMOVAL EVENT, STEAM GENERATOR TEMPERATURE VERSUS TIME 14.8-1 RCS DEPRESSURIZATION EVENT CORE POWER VS TIME 14.8-2 RCS DEPRESSURIZATION EVENT CORE AVERAGE HEAT FLUX VS TIME 14.8-3 RCS DEPRESSURIZATION EVENT RCS TEMPERATURES VS TIME 14.8-4 RCS DEPRESSURIZATION EVENT RCS PRESSURE VS TIME 14.9-1 LOSS OF COOLANT FLOW EVENT CORE FLOW FRACTION VS TIME 14.9-2 LOSS OF COOLANT FLOW EVENT CORE POWER VS TIME 14.9-3 LOSS OF COOLANT FLOW EVENT CORE HEAT FLUX VS TIME 14.9-4 LOSS OF COOLANT FLOW EVENT RCS TEMPERATURES VS TIME 14.9-5 LOSS OF COOLANT FLOW EVENT RCS PRESSURE VS TIME 14.10-1 LOSS OF ALL NON-EMERGENCY AC POWER EVENT CORE POWER VS TIME 14.10-2 LOSS OF ALL NON-EMERGENCY AC POWER EVENT CORE AVERAGE HEAT FLUX VS TIME 14.10-3 LOSS OF ALL NON-EMERGENCY AC POWER EVENT REACTOR COOLANT SYSTEM TEMPERATURE VS TIME 14.10-4 LOSS OF ALL NON-EMERGENCY AC POWER EVENT REACTOR COOLANT SYSTEM PRESSURE VS TIME CALVERT CLIFFS UFSAR 14-xiii Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF FIGURES FIGURE 14.10-5 LOSS OF ALL NON-EMERGENCY AC POWER EVENT STEAM GENERATOR PRESSURE VS TIME 14.11-1 FULL LENGTH CEA DROP CORE POWER VERSUS TIME 14.11-2 FULL LENGTH CEA DROP CORE HEAT FLUX VERSUS TIME 14.11-3 FULL LENGTH CEA DROP RCS TEMPERATURES VERSUS TIME 14.11-4 FULL LENGTH CEA DROP RCS PRESSURE VERSUS TIME 14.12-1 LOSS OF LOAD /1 STEAM GENERATOR EVENT RADIAL DISTORTION FACTOR VS CORE INLET TEMPERATURE ASYMMETRY 14.12-2 LOSS OF LOAD/1 SG EVENT CORE POWER VS TIME 14.12-3 LOSS OF LOAD/1 SG EVENT CORE HEAT FLUX VS TIME 14.12-4 LOSS OF LOAD/1 SG EVENT RCS TEMPERATURES VS TIME 14.12-5 LOSS OF LOAD/1 SG EVENT PRESSURIZER PRESSURE VS TIME 14.12-6 LOSS OF LOAD/1 SG EVENT SG PRESSURES VS TIME 14.13-1 CEA EJECTION EVENT HOT FULL POWER CORE POWER VS TIME 14.13-2 CEA EJECTION EVENT HOT ZERO POWER CORE POWER VS TIME 14.14-1 SLB EVENT POST TRIP MODERATOR REACTIVITY VS MODERATOR DENSITY 14.14-2 SLB EVENT POST-TRIP CORE POWER VS TIME 14.14-3 SLB EVENT POST-TRIP CORE HEAT FLUX VS TIME 14.14-4 SLB EVENT POST-TRIP PRESSURIZER PRESSURE VS TIME 14.14-5 SLB EVENT POST-TRIP RCS TEMPERATURES VS TIME 14.14-6 SLB EVENT POST-TRIP REACTIVITIES VS TIME 14.14-7 SLB EVENT POST-TRIP SG PRESSURE VS TIME 14.14-8 SLB EVENT PRE-TRIP CORE POWER VS TIME 14.14-9 SLB EVENT PRE-TRIP CORE HEAT FLUX VS TIME 14.14-10 SLB EVENT PRE-TRIP PRESSURIZER PRESSURE VS TIME 14.14-11 SLB EVENT PRE-TRIP RCS TEMPERATURES VS TIME 14.14-12 SLB EVENT PRE-TRIP REACTIVITIES VS TIME 14.14-13 SLB EVENT PRE-TRIP SG PRESSURES VS TIME 14.15-1 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-1 sh 2 ACTIONS CORE POWER VS TIME 14.15-2 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-2 sh 2 ACTIONS REACTOR COOLANT SYSTEM PRESSURE VS TIME 14.15-3 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-3 sh 2 ACTIONS CORE COOLANT TEMPERATURE VS TIME 14.15-3 sh 3 Deleted 14.15-4 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-4 sh 2 ACTIONS PRESSURIZER WATER VOLUME VS TIME CALVERT CLIFFS UFSAR 14-xiv Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF FIGURES FIGURE 14.15-5 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-5 sh 2 ACTIONS UPPER HEAD VOID FRACTION VS TIME 14.15-6 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-6 sh 2 ACTIONS RCS LIQUID MASS VS TIME 14.15-7 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-7 sh 2 ACTIONS STEAM GENERATOR PRESSURE VS TIME 14.15-8 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-8 sh 2 ACTIONS TUBE LEAK RATE VS TIME 14.15-9 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-9 sh 2 ACTIONS INTEGRATED LEAK FLOW VS TIME 14.15-10 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR ACTIONS FLASHING FRACTION VS TIME 14.15-11 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-11 sh 2 ACTIONS STEAM GENERATOR MASS VS TIME 14.15-11 sh 3 Deleted 14.15-12 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-12 sh 2 ACTIONS INTEGRATED SAFETY INJECTION FLOW VS TIME 14.15-13 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-13 sh 2 ACTIONS AUXILIARY FEEDWATER FLOW VS TIME 14.15-14 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR ACTIONS STEAM GENERATOR SAFETY VALVE FLOW VS TIME 14.15-15 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-15 sh 2 ACTIONS INTEGRATED MSSV FLOW VS TIME 14.15-16 sh 1 STEAM GENERATOR TUBE RUPTURE WITH EOP BASED OPERATOR 14.15-16 sh 2 ACTIONS HOT LEG SUBCOOLING VS TIME 14.16-1 SEIZED ROTOR EVENT CORE POWER VS TIME 14.16-2 SEIZED ROTOR EVENT CORE AVERAGE HEAT FLUX VS TIME 14.16-3 SEIZED ROTOR EVENT REACTOR COOLANT SYSTEM TEMPERATURES VS TIME 14.16-4 SEIZED ROTOR EVENT REACTOR COOLANT SYSTEM PRESSURE VS TIME 14.17-1 SCATTER PLOT OF OPERATIONAL PARAMETERS (Sheet 1) 14.17-1 SCATTER PLOT OF OPERATIONAL PARAMETERS (Sheet 2) 14.17-2 PCT VERSUS PCT TIME - SCATTER PLOT FROM 59 CALCULATIONS 14.17-3 PCT VERSUS BREAK SIZE - SCATTER PLOT FROM 59 CALCULATIONS 14.17-4 MAXIMUM OXIDATION VERSUS PCT - SCATTER PLOT FROM 59 CALCULATIONS 14.17-5 TOTAL OXIDATION VERSUS PCT - SCATTER PLOT FROM 59 CALCULATIONS CALVERT CLIFFS UFSAR 14-xv Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF FIGURES FIGURE 14.17-6 PEAK CLADDING TEMPERATURE (INDEPENDENT OF ELEVATION)
FOR THE LIMITING CASE 14.17-7 BREAK FLOW FOR THE LIMITING CASE 14.17-8 CORE INLET MASS FLUX FOR THE LIMITING CASE 14.17-9 CORE OUTLET MASS FLUX FOR THE LIMITING CASE 14.17-10 VOID FRACTION AT RCS PUMPS FOR THE LIMITING CASE 14.17-11 ECCS FLOWS (INCLUDES SIT, LPSI, AND HPSI) FOR THE LIMITING CASE 14.17-12 UPPER PLENUM PRESSURE FOR THE LIMITING CASE 14.17-13 COLLAPSED LIQUID LEVEL IN THE DOWNCOMER FOR THE LIMITING CASE 14.17-14 COLLAPSED LIQUID LEVEL IN THE LOWER PLENUM FOR THE LIMITING CASE 14.17-15 COLLAPSED LIQUID LEVEL IN THE CORE FOR THE LIMITING CASE 14.17-16 CONTAINMENT LOOP PRESSURES FOR THE LIMITING CASE 14.17-17 LOOP VERSUS NO-LOOP CASES 14.17-18 SMALL BREAK LOCA - ECCS PERFORMANCE ANALYSIS FOR THE LIMITING CASE - REACTOR POWER 14.17-19 SMALL BREAK LOCA - ECCS PERFORMANCE ANALYSIS FOR THE LIMITING CASE - PRIMARY AND SECONDARY PRESSURE 14.17-20 SMALL BREAK LOCA - ECCS PERFORMANCE ANALYSIS FOR THE LIMITING CASE - BREAK FLOW RATE 14.17-21 SMALL BREAK LOCA - ECCS PERFORMANCE ANALYSIS FOR THE LIMITING CASE - CORE INLET FLOW RATE 14.17-22 SMALL BREAK LOCA - ECCS PERFORMANCE ANALYSIS FOR THE LIMITING CASE - HOT ASSEMBLY MIXTURE 14.17-23 SMALL BREAK LOCA - ECCS PERFORMANCE ANALYSIS FOR THE LIMITING CASE - CLADDING TEMPERATURE AT HOT SPOT 14.20-1 CONTAINMENT AIR COOLER CAPABILITY 14.20-2 COLD LEG DISCHARGE LOCA - MAXIMUM SI, CONTAINMENT PRESSURE AND TEMPERATURE AND CONTAINMENT SUMP TEMPERATURE VERSUS TIME 14.20-3 MAIN STEAM LINE BREAK, CONTAINMENT PRESSURE AND TEMPERATURE VERSUS TIME 14.21-1 Deleted 14.21-2 Deleted 14.21-3 Deleted 14.21-4 Deleted 14.21-5 Deleted 14.21-6 Deleted 14.21-7 Deleted CALVERT CLIFFS UFSAR 14-xvi Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF FIGURES FIGURE 14.26-1 FEEDLINE BREAK EVENT WITH LOAC FOLLOWING REACTOR TRIP RCS PEAK PRESSURE VS BREAK SIZE 14.26-2 FEEDLINE BREAK EVENT WITH LOAC FOLLOWING REACTOR TRIP CORE POWER VS TIME 14.26-3 FEEDLINE BREAK EVENT WITH LOAC FOLLOWING REACTOR TRIP CORE AVERAGE HEAT FLUX VS TIME 14.26-4 FEEDLINE BREAK EVENT WITH LOAC FOLLOWING REACTOR TRIP RCS TEMPERATURES VS TIME 14.26-5 FEEDLINE BREAK EVENT WITH LOAC FOLLOWING REACTOR TRIP RCS PRESSURE VS TIME 14.26-6 FEEDLINE BREAK EVENT WITH NO LOAC FOLLOWING REACTOR TRIP STEAM GENERATOR PRESSURE VS TIME 14.26-7 FEEDLINE BREAK EVENT WITH NO LOAC FOLLOWING REACTOR TRIP STEAM GENERATOR INVENTORY VS TIME 14.26-8 FEEDLINE BREAK EVENT WITH NO LOAC FOLLOWING REACTOR TRIP AUXILIARY FEEDWATER FLOW VS TIME 14.26-9 FEEDLINE BREAK EVENT WITH NO LOAC FOLLOWING REACTOR TRIP INTEGRATED BREAK FLOW VS TIME 14.26-10 FEEDLINE BREAK EVENT WITH NO LOAC FOLLOWING REACTOR TRIP BREAK FLOW VS TIME 14.26-11 Deleted CALVERT CLIFFS UFSAR 14-xvii Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF ACRONYMS ABB Asea Brown Boveri ADV Atmospheric Dump Valve AEC Atomic Energy Commission AFAS Auxiliary Feedwater Actuation System AFW Auxiliary Feedwater ANS American Nuclear Society AOO Anticipated Operational Occurrence AOR Analysis of Record ASGPT Asymmetric Steam Generator Protection Trip ASI Axial Shape Index AST Alternative Source Term BOC Beginning of Cycle CAC Containment Air Cooler CBP Condensate Booster Pump CE Combustion Engineering, Inc.
CEA Control Element Assembly CEAW Control Element Assembly Withdrawal CEDM Control Element Drive Mechanism CHF Critical Heat Flux CIS Concurrent Iodine Spike CSAS Containment Spray Actuation Signal CTM Centerline Temperature Melt CVCS Chemical and Volume Control System DBA Design Basis Accident DBE Design Basis Event DEG Double-Ended Guillotine DEG/PD Double-Ended Guillotine at Pump Discharge DEQ Dose Equivalent Curies DES/PD Double-Ended Slot at Pump Discharge DNB Departure from Nucleate Boiling DNBR Departure from Nucleate Boiling Ratio EAB Exclusion Area Boundary ECCS Emergency Core Cooling System EOC End of Cycle EOP Emergency Operating Procedures ESF Engineered Safety Feature ESFAS Engineered Safety Feature Actuation System FCM Fuel Centerline Melt FHI Fuel Handling Incident FLB Feedline Break FSAR Final Safety Analysis Report FTC Fuel Temperature Coefficient FTI Framatome Technologies, Inc.
GIS Generated Iodine Spike HDP Heater Drain Pump HEPA High Efficiency Particulate Air HFP Hot Full Power HPSI High Pressure Safety Injection CALVERT CLIFFS UFSAR 14-xviii Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF ACRONYMS HPT High Power Trip HTP High Thermal Performance HZP Hot Zero Power ICI Incore Instrumentation IFBA Integral Fuel Burnable Absorber LCO Limiting Conditions for Operation LHGR Linear Heat Generation Rate LHR Linear Heat Rate LOAC Loss-of-Non-Emergency AC Power LOCA Loss-of-Coolant Accident LOFW Loss of Feedwater LOOP Loss of Offsite Power LPD Local Power Density LPSI Low Pressure Safety Injection LPZ Low Population Zone LSSS Limiting Safety System Setting MDNBR Minimum Departure from Nucleate Boiling Ratio MFIV Main Feedwater Isolation Valve MFW Main Feedwater MSIV Main Steam Isolation Valve MSLB Main Steam Line Break MSS Main Steam System MSSV Main Steam Safety Valves MTC Moderator Temperature Coefficient NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System OSG Original Steam Generator PCT Peak Clad Temperature PD Pump Discharge PDIL Power Dependent Insertion Limit PIS Preaccident Iodine Spike PLCEA Part-Length Control Element Assembly PLCS Pressurizer Level Control System PLHGR Peak Linear Heat Generation Rate PORV Power-Operated Relief Valve PPCS Pressurizer Pressure Control System PSV Pressurizer Safety Valves PWR Pressurized Water Reactor RAS Recirculation Actuation Signal RCP Reactor Coolant Pump RCS Reactor Coolant System RPS Reactor Protective System RRS Reactor Regulating System RSG Replacement Steam Generator RTD Resistance Temperature Detector RTP Rated Thermal Power RWT Refueling Water Tank SAFDL Specified Acceptable Fuel Design Limit CALVERT CLIFFS UFSAR 14-xix Rev. 52
CHAPTER 14 SAFETY ANALYSIS LIST OF ACRONYMS SDBS Steam Dump and Bypass System SDC Shutdown Cooling SDCHX Shutdown Cooling Heat Exchanger SER Safety Evaluation Report SFP Spent Fuel Pool SFPEVS Spent Fuel Pool Exhaust Ventilation System SG Steam Generator SGFP Steam Generator Feedwater Pump SGIS Steam Generator Isolation Signal SGTR Steam Generator Tube Rupture SI Safety Injection SIAS Safety Injection Actuation Signal SIT Safety Injection Tank SLB Steam Line Break SRP Standard Review Plan TBV Turbine Bypass Valve TEDE Total Effective Dose Equivalent TID Technical Information Document TM/LP Thermal Margin/Low Pressure UFSAR Updated Final Safety Analysis Report VAP Value Added Pellet VHPT Variable High Power Trip WBD Whole Body Dose ZrB2 Zirc Diboride CALVERT CLIFFS UFSAR 14-xx Rev. 52