ML16180A183
| ML16180A183 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/05/2016 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16180A174 | List:
|
| References | |
| Download: ML16180A183 (147) | |
Text
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.0-1 Core Limits and Overpower-Overtemperature Delta T Setpoints (Tref =
576.0qF)
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.0-2 Reactivity Coefficients Used in Non-LOCA Safety Analysis
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.0-3 Reactivity Insertion Scram Curves
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-1 Feedwater Flow Increase at Full Power, Nuclear Power and Loop Average Temperature Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-2 Feedwater Flow Increase at Full Power, Pressurizer Pressure and Steam Gen-erator Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-3 Feedwater Flow Increase at Full Power, Steam Generator Mass Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-4 Steam Line Rupture, Multiplication Factor Versus Core Average Temperature (Calculated at 1050 psia)
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-5 Steam Line Rupture, Integrated Doppler Defect Versus Fraction of Power
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-6 Steam Line Rupture, 1.4ft2 Break with Power, Two Loops in Service, Core Heat Flux and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-7 Steam Line Rupture, 1.4ft2 Break with Power, Two Loops in Service, Pressurizer Water Volume and Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-8 Steam Line Rupture, 1.4ft2 Break with Power, Two Loops in Service, Loop TAVG and Cold Leg Loop Temperature Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-9 Steam Line Rupture, 1.4ft2 Break with Power, Two Loops in Service, Faulted Loop Steam Flow and Total Feedwater Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-10 Steam Line Rupture, 1.4ft2 Break with Power, Two Loops in Service, Core Aver-aged Boron and Reactivity Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-11 Steam Line Rupture, 1.4ft2 Break Without Power, Two Loops in Service, Core Heat Flux and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-12 Steam Line Rupture, 1.4ft2 Break Without Power, Two Loops in Service, Pres-surizer Water Volume and Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-13 Steam Line Rupture, 1.4ft2 Break Without Power, Two Loops in Service, Loop TAVG and Cold Leg Loop Temperatures Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-14 Steam Line Rupture, 1.4ft2 Break Without Power, Two Loops in Service, Faulted Loop Steam Flow and Total Feedwater Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-15 Steam Line Rupture, 1.4ft2 Break without Power, Two Loops in Service, Core Averaged Boron and Reactivity Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-16 Steam Line Rupture, 1.4ft2 Break with Power, One Loop in Service, Core Heat Flux and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-17 Steam Line Rupture, 1.4ft2 Break with Power, One Loop in Service, Pressurizer Water Volume and Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-18 Steam Line Rupture, 1.4ft2 Break with Power, One Loop in Service, Loop TAVG and Cold Leg Loop Temperatures Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-19 Steam Line Rupture, 1.4ft2 Break with Power, One Loop in Service, Faulted Loop Steam Flow and Total Feedwater Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-20 Steam Line Rupture, 1.4ft2 Break with Power, One Loop in Service, Core Aver-aged Boron and Reactivity Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-21 Combined Atmospheric Relief Valve and Main Feedwater Regulating Valve Failure, Nuclear Power and Core Heat Flux Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-22 Combined Atmospheric Relief Valve and Main Feedwater Regulating Valve Failure, Loop Average Temperature and Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.1-23 Combined Atmospheric Relief Valve and Main Feedwater Regulating Valve Failure, DNBR Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.1-24 Combined Atmospheric Relief Valve and Main Feedwater Regulating Valve Failure, Steam Generator Level and Steam Generator Mass Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.2-1 Loss of Load, with Automatic Pressure Control, Nuclear Power and DNBR Ver-sus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.2-2 Loss of Load, with Automatic Pressure Control, RCS Average Temperature and Pressurizer Water Volume Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-3 Loss of Load, with Automatic Pressure Control, Steam Generator Pressure and Pressurizer Pressure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-4 Loss of Load, Without Pressure Control, Nuclear Power Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-5 Loss of Load, Without Pressure Control, RCS Average Temperature and Pres-surizer Water Volume Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-6 Loss of Load, Without Pressure Control, Steam Generator Pressure and Reactor Coolant System Pressures Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-7 Loss of Load, Peak MSS Pressure Case, Nuclear Power Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-8 Loss of Load, Peak MSS Pressure Case, RCS Average Temperature and Pres-surizer Water Volume Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-9 Loss of Load, Peak MSS Pressure Case, Steam Generator Pressure and Pressur-izer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.2-10 Figure Deleted
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.2-11 Figure Deleted
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.2-12 Figure Deleted
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-13 Loss of Offsite Alternating Current Power to the Station Auxiliaries, Nuclear Power and Pressurizer Pressure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-14 Loss of Offsite Alternating Current Power to the Station Auxiliaries, Pressurizer Water Volume and Pressurizer Steam Relief Rate Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-15 Loss of Offsite Alternating Current Power to the Station Auxiliaries, Reactor Coolant Flow and Core Inlet/Outlet Temperatures Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-16 Loss of Offsite Alternating Current Power to the Station Auxiliaries, Steam Gen-erator Mass and Steam Generator Pressure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-17 Loss of Normal Feedwater With Power, Nuclear Power and Pressurizer Pres-sure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-18 Loss of Normal Feedwater With Power, Pressurizer Water Volume and Pressur-izer Steam Relief Rate Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-19 Loss of Normal Feedwater With Power, Reactor Coolant Flow and Core Inlet/
Outlet Temperatures Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-20 Loss of Normal Feedwater With Power, Steam Generator Mass and Steam Gen-erator Pressure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-21 Feedline Break With Offsite Power; Nuclear Power and Pressurizer Pressure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-22 Feedline Break With Offsite Power; Pressurizer Water Volume and Pressurizer Steam Relief Rate Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-23 Feedline Break With Offsite Power; Cold Leg, Hot Leg and Saturation Tem-peratures Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-24 Feedline Break With Offsite Power; Steam Generator Mass and Steam Genera-tor Pressure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-25 Feedline Break With Offsite Power; Feedwater Mass Flow Rates Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-26 Feedline Break Without Offsite Power; Nuclear Power and Pressurizer Pres-sure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-27 Feedline Break Without Offsite Power; Pressurizer Water Volume and Pressur-izer Steam Relief Rate Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-28 Feedline Break Without Offsite Power; Cold Leg, Hot Leg and Saturation Tem-peratures Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-29 Feedline Break Without Offsite Power; Steam Generator Mass and Steam Gen-erator Pressure Versus Time
GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Revision 26 5/2016 Figure 15.2-30 Feedline Break Without Offsite Power; Feedwater Mass Flow Rates Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-1 Full Loss of Flow (Undervoltage), Nuclear Power and RCS Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-1a Full Loss of Flow (Underfrequency), Nuclear Power and RCS Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-2 Full Loss of Flow (Undervoltage), Core Average and Hot Channel Heat Flux Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-2a Full Loss of Flow (Underfrequency), Core Average and Hot Channel Heat Flux Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-3 Full Loss of Flow (Undervoltage), RCS Pressures and DNBR Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-3a Full Loss of Flow (Underfrequency), DNBR and Reactor Coolant System Pres-sures Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-4 Partial Loss of Flow, Nuclear Power and RCS Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-5 Partial Loss of Flow, RCS Pressures and RCS Loop Flows Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-6 Partial Loss of Flow, Core Average and Hot Channel Heat Flux Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-7 Partial Loss of Flow, DNBR Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-8 Locked Rotor, RCS Pressures and RCS Loop Flows Versus Time
Revision 26 5/2016 GINNA/UFSAR CHAPTER 15 ACCIDENT ANALYSIS Figure 15.3-9 Locked Rotor, Nuclear Power and RCS Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.3-10 Locked Rotor, Core Average Heat Flux and Cladding Inside Temperature Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-1 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal From Subcritical Conditions, Heat Flux and Nuclear Power Versus Time (422V+Fuel)
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-2 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal From Subcritical Conditions, Clad Inside and Fuel Average Temperature Versus Time(422V+Fuel)
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-3 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, Mini-mum Feedback, 100 pcm/sec, Nuclear Power and Heat Flux Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-4 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, Mini-mum Feedback, 100 pcm/sec, Pressurizer Pressure and Pressurizer Water Vol-ume Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-5 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, Mini-mum Feedback, 100 pcm/sec, Tavg and DNBR Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-6 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, Maxi-mum Feedback, 5 pcm/sec, Nuclear Power and Heat Flux Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-7 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, Maxi-mum Feedback, 5 pcm/sec, Pressurizer Water Volume and Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-8 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, Maxi-mum Feedback, 5 pcm/sec, TAVG and DNBR Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-9 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, Mini-mum and Maximum Feedback, DNBR Versus Reactivity Insertion Rate
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-10 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from 60% Power, Minimum and Maximum Feedback, DNBR Versus Reactivity Insertion Rate
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-11 Uncontrolled Rod Cluster Control Assembly Bank Withdrawal from 10% Power, Minimum and Maximum Feedback, DNBR Versus Reactivity Insertion Rate
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-12 Startup of an Inactive Coolant Loop, Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-13 Startup of an Inactive Coolant Loop, TAVG Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-14 Startup of an Inactive Coolant Loop, Core Inlet Temperature Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-15 Startup of an Inactive Coolant Loop, Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-16 Rod Cluster Control Assembly Ejection Beginning-of-Life, Full Power, Fuel and Clad Temperature and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-16aRod Cluster Control Assembly Ejection, Beginning of Life, Full Power, Fuel and Clad Temperature and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-16bRod Cluster Control Assembly Ejection, Beginning of Life, Zero Power, Fuel and Clad Temperature and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-17 Rod Cluster Control Assembly Ejection Beginning-of-Life, Zero Power, Fuel and Clad Temperature and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-17aRod Cluster Control Assembly Ejection, End of Life, Full Power, Fuel and Clad Temperature and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-17bRod Cluster Control Assembly Ejection, End of Life, Zero Power, Fuel and Clad Temperature and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-18 Rod Cluster Control Assembly Drop Heat Flux and Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-19 Rod Cluster Control Assembly Drop Pressurizer Pressure and Core Average Temperature Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-20 Uncontrolled Rod Cluster Control Assembly Bank Withdrawl from 8% Power (RCS Pressure Case), Minimum Feedback, 55 pcm/sec, Nuclear Power and Heat Flux Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.4-21 Uncontrolled Rod Cluster Control Assembly Bank Withdrawl from 8% Power (RCS Pressure Case), Minimum Feedback, 55 pcm/sec, Pressurizer Pressure and Tavg Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-1 Steam Generator Tube Rupture (Overfill), Maximum Safety Injection Flow Ver-sus Pressure
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-1a RCS Depressurization, Nuclear Power Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-1b RCS Pressurization, Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-1c RCS Depressurization, Indicated Loop Average Temperature Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-1d RCS Depressurization, DNBR Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-2 SGTR (Overfill), Pressurizer Level and Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-3 SGTR (Overfill), Secondary Pressure and Steam Generator Liquid Mass Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-4 SGTR (Overfill), Hot and Cold Leg Temperatures for Intact and Ruptured Steam Generators Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-5 SGTR (Overfill), Total Primary to Secondary Leakage and Total Integrated Pri-mary to Secondary Leakage Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-6 SGTR (Overfill), Steam Generator Relief Flow and Integrated Steam Generator Relief Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-7 SGTR (Overfill), Steam Generator Water Volume Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-8 SGTR (Dose), Pressurizer Level and Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-9 SGTR (Dose), Secondary Pressure and Steam Generator Liquid Mass Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-10 SGTR (Dose), Hot and Cold Leg Temperatures for Intact and Ruptured Steam Generators Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-11 SGTR (Dose), Total Primary to Secondary Leakage and Total Integrated Pri-mary to Secondary Leakage Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-12 SGTR (Dose), Steam Generator Relief Flow and Integrated Steam Generator Relief Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-13 SGTR (Dose), Steam Generator Water Volume Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-14 SGTR (Dose), Tube Rupture Flow Flashing Fraction and Integrated Flashed Break Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-15 Small Break LOCA Inch Break, Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-16 Small Break LOCA Inch Break, Core Mixture Level Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-17 Small Break LOCA Inch High Break, Peak Cladding Temperature at PCT Elevation Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-18 Small Break LOCA Inch High Break, Core Exit Vapor Flow Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-19 Small Break LOCA Inch Break, Hot Rod Heat Transfer Coefficient at PCT Elevation Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-20 Small Break LOCA Inch Break, Fluid Temperature at PCT Elevation Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-21 Small Break LOCA - Axial Power Distribution, Heat Rate Versus Core Eleva-tion
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-22 Small Break LOCA - 1.5-Inch Break, Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-23 Small Break LOCA Inch High Break, Pressurizer Pressure Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-24 Small Break LOCA - 1.5-Inch Break, Core Mixture Level Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-25 Small Break LOCA Inch Break, Core Mixture Level Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-26 Small Break LOCA - 1.5-Inch Break, Peal Cladding Temperature at PCT Eleva-tion Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-27 Small Break LOCA Inch Break, Peak Cladding Temperature at PCT Eleva-tion Versus Time
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-28 Figure Deleted
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-29 Figure Deleted
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-30 Figure Deleted
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-31 R.E. Ginna Vessel Model Noding Diagram1
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-32 R.E. Ginna Loop Model Noding Diagram
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-33 R.E. Ginna Initial Transient Axial Power Distributions
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-34 Containment Pressure Used for the R.E. Ginna Best-Estimate Large Break LOCA Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-35 Peak Clad Temperature of the 5 rods for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-36 Split Break Flow for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-37 Total Flow at the Bottom of the Core for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-38 Accumulator Injection Flow for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-39 High Head Safety Injection Flow for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-40 Low Head Safety Injection Flow for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-41 Average Collapsed Liquid Level in the Downcomer for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-42 Lower Plenum Collapsed Liquid Level for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-43 Core Collapsed Liquid Levels for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-44 Vessel Liquid Mass for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-45 Pressurizer Pressure for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-46 Hot Rod Peak Clad Temperature and Elevation for the Initial Transient
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-47 R.E. Ginna PBOT/PMID Analysis and Operating Limits
Revision 26 5/2016 GINNA/UFSAR Chapter 15 ACCIDENT ANALYSES Figure 15.6-48 Lower Bound Containment Pressure for R.E. Ginna Analysis