ML20189A110
Text
Oconee Nuclear Station UFSAR Appendix 15B. Figures Appendix 15B. Figures
Oconee Nuclear Station UFSAR Figure 15-1 (Page 1 of 1)
(31 DEC 2013)
Figure 15-1. Startup Accident 0
20 40 60 80 100 120 140 160 180 0
10 20 30 40 50 60 70 80 90 100 POWER (% OF 2568 MWth)
TIME (SEC)
Neutron Power Thermal Power
Oconee Nuclear Station UFSAR Figure 15-2 (Page 1 of 1)
(31 DEC 2013)
Figure 15-2. Startup Accident
-2
-1.5
-1
-0.5 0
0.5 1
1.5 0
10 20 30 40 50 60 70 80 90 100 REACTIVITY ($)
TIME (SEC)
Rod Withdrawal Modorator Doppler Total
Oconee Nuclear Station UFSAR Figure 15-3 (Page 1 of 1)
(31 DEC 2013)
Figure 15-3. Startup Accident 530 535 540 545 550 555 560 565 0
10 20 30 40 50 60 70 80 90 100 COLD LEG TEMPERATURE (F)
TIME (SEC)
Oconee Nuclear Station UFSAR Figure 15-4 (Page 1 of 1)
(31 DEC 2013)
Figure 15-4. Startup Accident 530 535 540 545 550 555 560 565 570 575 0
10 20 30 40 50 60 70 80 90 100 HOT LEG TEMPERATURE (F)
TIME (SEC)
Oconee Nuclear Station UFSAR Figure 15-5 (Page 1 of 1)
(31 DEC 2013)
Figure 15-5. Startup Accident 280 290 300 310 320 330 340 350 0
10 20 30 40 50 60 70 80 90 100 PRESSURIZER LEVEL (INCHES)
TIME (SEC)
Oconee Nuclear Station UFSAR Figure 15-6 (Page 1 of 1)
(31 DEC 2013)
Figure 15-6. Startup Accident 2000 2100 2200 2300 2400 2500 2600 2700 2800 0
10 20 30 40 50 60 70 80 90 100 RCS PRESSURE (PSIG)
TIME (SEC)
Oconee Nuclear Station UFSAR Figure 15 15-10 (Page 1 of 1)
(31 DEC 2000)
Figure 15-7. Deleted Per 1998 Update Figure 15-8. Deleted Per 1998 Update Figure 15-9. Deleted Per 1998 Update Figure 15-10. Deleted Per 1998 Update
Oconee Nuclear Station UFSAR Figure 15-11 (Page 1 of 1)
(31 DEC 2003)
Figure 15-11. Rod Withdrawal at Power Accident - Peak RCS Pressure Analysis Power 0
20 40 60 80 100 120 0
5 10 15 20 25 30 35 40 45 50 Time (seconds)
Power (%)
Neutron Power Thermal Power
Oconee Nuclear Station UFSAR Figure 15-12 (Page 1 of 1)
(31 DEC 2003)
Figure 15-12. Rod Withdrawal at Power Accident - Peak RCS Pressure Analysis RCS Temperatures 550 555 560 565 570 575 580 585 590 595 600 605 610 615 0
5 10 15 20 25 30 35 40 45 50 Time (seconds)
RCS Temperature (°F)
Hot Leg Cold Leg
Oconee Nuclear Station UFSAR Figure 15-13 (Page 1 of 1)
(31 DEC 2003)
Figure 15-13. Rod Withdrawal at Power Accident - Peak RCS Pressure Analysis Pressurizer Level 100 125 150 175 200 225 250 275 300 325 0
5 10 15 20 25 30 35 40 45 50 Time (seconds)
Pressurizer Level (Inches)
Oconee Nuclear Station UFSAR Figure 15-14 (Page 1 of 1)
(31 DEC 2003)
Figure 15-14. Rod Withdrawal at Power Accident - Peak RCS Pressure Analysis RCS Pressure 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 0
5 10 15 20 25 30 35 40 45 50 Time (seconds)
RCS Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-15 (Page 1 of 1)
(31 DEC 2003)
Figure 15-15. Rod Withdrawal at Power Accident - Core Cooling Capability Analysis Power 0
20 40 60 80 100 120 0
50 100 150 200 250 Time (seconds)
Power (%)
Neutron Power Thermal Power
Oconee Nuclear Station UFSAR Figure 15-16 (Page 1 of 1)
(31 DEC 2003)
Figure 15-16. Rod Withdrawal at Power Accident - Core Cooling Capability Analysis RCS Temperatures 550 555 560 565 570 575 580 585 590 595 600 605 610 615 620 625 0
50 100 150 200 250 Time (seconds)
RCS Temperatures (°F)
Hot Leg Cold Leg
Oconee Nuclear Station UFSAR Figure 15-17 (Page 1 of 1)
(31 DEC 2003 Figure 15-17. Rod Withdrawal at Power Accident - Core Cooling Capability Analysis Pressurizer Level 100 125 150 175 200 225 250 275 300 325 350 375 0
50 100 150 200 250 Time (seconds)
Pressurizer Level (Inches)
Oconee Nuclear Station UFSAR Figure 15-18 (Page 1 of 1)
(31 DEC 2015)
Figure 15-18. Cold Water Accident - RCS Flow
Oconee Nuclear Station UFSAR Figure 15-19 (Page 1 of 1)
(31 DEC 2008)
Figure 15-19. Loss of Coolant Flow Accidents - Four RCP Coastdown From Four RCP Initial Conditions Analysis - RCS Flow 0
0.2 0.4 0.6 0.8 1
1.2 0
2 4
6 8
10 12 14 16 18 20 Time (seconds)
RCS Flow (Fraction of Initial)
Faulted Loop Faulted Loop Reactor Core
Oconee Nuclear Station UFSAR Figure 15-20 (Page 1 of 1)
(31 DEC 2008)
Figure 15-20. Loss of Coolant Flow Accidents - Four RCP Coastdown From Four RCP Initial Conditions Analysis - Power 0
0.2 0.4 0.6 0.8 1
1.2 0
5 10 15 20 Time (seconds)
Power (Fraction of Initial)
Thermal Power Neutron Power
Oconee Nuclear Station UFSAR Figure 15-21 (Page 1 of 1)
(31 DEC 2008)
Figure 15-21. Loss of Coolant Flow Accidents - Four RCP Coastdown From Four RCP Initial Conditions Analysis - RCS Temperature 550 560 570 580 590 600 610 0
5 10 15 20 Time (seconds)
RCS Temperature (oF)
Loop A Cold Leg - Fauled Loop Loop B Cold Leg - Fauled Loop Loop A Hot Leg - Faulted Loop Loop B Hot Leg - Faulted Loop
Oconee Nuclear Station UFSAR Figure 15-22 (Page 1 of 1)
(31 DEC 2008)
Figure 15-22. Loss of Coolant Flow Accidents - Four RCP Coastdown From Four RCP Initial Conditions Analysis - Pressurizer Level 150 160 170 180 190 200 210 220 0
5 10 15 20 Time (seconds)
Pressurizer Level (Inches)
Oconee Nuclear Station UFSAR Figure 15-23 (Page 1 of 1)
(31 DEC 2008)
Figure 15-23. Loss of Coolant Flow Accidents - Four RCP Coastdown From Four RCP Initial Conditions Analysis - RCS Pressure 2000 2050 2100 2150 2200 2250 2300 0
2 4
6 8
10 12 14 16 18 20 Time (seconds)
RCS Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-24 (Page 1 of 1)
(31 DEC 2013)
Figure 15-24. Loss of Coolant Flow Accidents - Four RCP Coastdown From Four RCP Initial Conditions Analysis - DNBR 1
1.5 2
2.5 3
3.5 0
1 2
3 4
5 6
7 8
DNBR Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-25 (Page 1 of 1)
(31 DEC 2003)
Figure 15-25. Loss of Coolant Flow Accidents - Two RCP Coastdown From Four RC P Initial Conditions Analysis - RCS Flow 0
0.2 0.4 0.6 0.8 1
1.2 0
5 10 15 20 Time (seconds)
RCS Flow (Fraction of Initial)
Faulted Loop Intact Loop Reactor Core
Oconee Nuclear Station UFSAR Figure 15-26 (Page 1 of 1)
(31 DEC 2010)
Figure 15-26. Control Rod Misalignment Accidents - Dropped Rod Analysis - Neutron Power
Oconee Nuclear Station UFSAR Figure 15-27 (Page 1 of 1)
(31 DEC 2010)
Figure 15-27. Control Rod Misalignment Accidents - Dropped Rod Analysis - RCS Temperatures
Oconee Nuclear Station UFSAR Figure 15-28 (Page 1 of 1)
(31 DEC 2010)
Figure 15-28. Control Rod Misalignment Accidents - Dropped Rod Analysis - Pressurizer Level
Oconee Nuclear Station UFSAR Figure 15-29 (Page 1 of 1)
(31 DEC 2013)
Figure 15-29. Rod Ejection Accident - BOC Four RCPs - Power
Oconee Nuclear Station UFSAR Figure 15-30 (Page 1 of 1)
(31 DEC 2013)
Figure 15-30. Rod Ejection Accident - BOC Three RCPs - Power
Oconee Nuclear Station UFSAR Figure 15-31 (Page 1 of 1)
(31 DEC 2013)
Figure 15-31. Rod Ejection Accident - BOC HZP - Power 0
50 100 150 200 250 300 350 400 450 0
0.5 1
1.5 2
2.5 3
3.5 4
4.5 5
Power (% of 2568 MWt)
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-32 (Page 1 of 1)
(31 DEC 2013)
Figure 15-32. Rod Ejection Accident - EOC Four RCPs - Power 0
20 40 60 80 100 120 140 0
1 2
3 4
5 6
7 8
9 10 Power (% of 2568 MWt)
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-33 (Page 1 of 1)
(31 DEC 2013)
Figure 15-33. Rod Ejection Accident - EOC Three RCPs - Power 0
20 40 60 80 100 120 0
1 2
3 4
5 6
7 8
9 10 Power (% of 2568 MWt)
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-34 (Page 1 of 1)
(31 DEC 2013)
Figure 15-34. Rod Ejection Accident - EOC HZP - Power 0
20 40 60 80 100 120 140 160 180 0
0.5 1
1.5 2
2.5 3
3.5 4
4.5 5
Power (% of 2568 MWt)
TIME (SECONDS)
Oconee Nuclear Station UFSAR Figure 15-35 (Page 1 of 1)
(31 DEC 2013)
Figure 15-35. Deleted Per 2013 Update
Oconee Nuclear Station UFSAR Figure 15-36 (Page 1 of 1)
(31 DEC 2013)
Figure 15-36. Rod Ejection Accident - BOC Four RCPs - RCS Pressure 2150 2200 2250 2300 2350 0
0.5 1
1.5 2
2.5 3
3.5 4
4.5 5
RCS Pressure (psig)
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15 15-39 (Page 1 of 1)
(31 DEC 2000)
Figure 15-37. Deleted Per 1999 Update Figure 15-38. Deleted Per 1999 Update Figure 15-39. Deleted Per 1999 Update
Oconee Nuclear Station UFSAR Figure 15-40 (Page 1 of 1)
(31 DEC 2003)
Figure 15-40. Steam Line Break Accident - With Offsite Power - Steam Line Pressure 0
200 400 600 800 1000 1200 0
100 200 300 400 500 600 Time (Seconds)
Steam Line Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-41 (Page 1 of 1)
(31 DEC 2003)
Figure 15-41. Steam Line Break Accident - With Offsite Power - Break Flowrate 0
1000 2000 3000 4000 5000 6000 7000 8000 9000 0
100 200 300 400 500 600 Time (Seconds)
Break flow rate (lbm/sec)
Oconee Nuclear Station UFSAR Figure 15-42 (Page 1 of 1)
(31 DEC 2003)
Figure 15-42. Steam Line Break Accident - With Offsite Power - RCS Temperature 200 250 300 350 400 450 500 550 600 650 0
100 200 300 400 500 600 Time (Seconds)
RCS Temperature (F)
Affected Loop Cold Leg Unaffected Loop Cold Leg Affected Loop Hot Leg Unaffected Loop Hot Leg
Oconee Nuclear Station UFSAR Figure 15-43 (Page 1 of 1)
(31 DEC 2003)
Figure 15-43. Steam Line Break Accident - With Offsite Power - Reactivity
-16.0
-14.0
-12.0
-10.0
-8.0
-6.0
-4.0
-2.0 0.0 2.0 4.0 6.0 8.0 10.0 12.0 14.0 16.0 0
100 200 300 400 500 600 Time (Seconds)
Reactivity ($)
Moderator Doppler Total Boron Control Rods
Oconee Nuclear Station UFSAR Figure 15-44 (Page 1 of 1)
(31 DEC 2000)
Figure 15-44. LOCA - Large Break Analysis Code Interfaces
Oconee Nuclear Station UFSAR Figure 15 15-49 (Page 1 of 1)
(31 DEC 2000)
Figure 15-45. Deleted Per 2000 Update Figure 15-46. Deleted Per 1990 Update Figure 15-47. Deleted Per 1997 Update Figure 15-48. Deleted Per 1997 Update Figure 15-49. Deleted Per 2000 Update
Oconee Nuclear Station UFSAR Figure 15-50 (Page 1 of 1)
(31 DEC 2008)
Figure 15-50. LOCA - Peak Cladding Temperature vs Break Size for LBLOCA Spectrum
Oconee Nuclear Station UFSAR Figure 15 15-79 (Page 1 of 2)
(31 DEC 2000)
Figure 15-51. Deleted Per 1997 Update Figure 15-52. Deleted Per 1995 Update Figure 15-53. Deleted Per 1995 Update Figure 15-54. Deleted Per 1995 Update Figure 15-55. Deleted Per 1995 Update Figure 15-56. Deleted Per 1995 Update Figure 15-57. Deleted Per 1995 Update Figure 15-58. Deleted Per 1995 Update Figure 15-59. Deleted Per 1995 Update Figure 15-60. Deleted Per 1995 Update Figure 15-61. Deleted Per 1995 Update Figure 15-62. Deleted Per 1995 Update Figure 15-63. Deleted Per 1995 Update Figure 15-64. Deleted Per 1995 Update Figure 15-65. Deleted Per 1995 Update Figure 15-66. Deleted Per 1995 Update Figure 15-67. Deleted Per 1995 Update Figure 15-68. Deleted Per 1995 Update
Oconee Nuclear Station UFSAR Figure 15 15-79 (Page 2 of 2)
(31 DEC 2000)
Figure 15-69. Deleted Per 1995 Update Figure 15-70. Deleted Per 1995 Update Figure 15-71. Deleted Per 1995 Update Figure 15-72. Deleted Per 1995 Update Figure 15-73. Deleted Per 1995 Update Figure 15-74. Deleted Per 1995 Update Figure 15-75. Deleted Per 1995 Update Figure 15-76. Deleted Per 1995 Update Figure 15-77. Deleted Per 1995 Update Figure 15-78. Deleted Per 1995 Update Figure 15-79. Deleted Per 1995 Update
Oconee Nuclear Station UFSAR Figure 15-80 (Page 1 of 1)
(31 DEC 2000)
Figure 15-80. MHA - Integrated Direct Dose
Oconee Nuclear Station UFSAR Figure 15 15-88 (Page 1 of 1)
(31 DEC 2000)
Figure 15-81. Deleted Per 1995 Update Figure 15-82. Deleted Per 2000 Update Figure 15-83. Deleted Per 1995 Update Figure 15-84. Deleted Per 2000 Update Figure 15-85. Deleted Per 2000 Update Figure 15-86. Deleted Per 1997 Update Figure 15-87. Deleted Per 2000 Update Figure 15-88. Deleted Per 1995 Update
Oconee Nuclear Station UFSAR Figure 15-89 (Page 1 of 1)
(31 DEC 2003)
Figure 15-89. Post-Accident Hydrogen Control - Reactor Building Arrangement
Oconee Nuclear Station UFSAR Figure 15 15-111 (Page 1 of 2)
(31 DEC 2000)
Figure 15-90. Deleted Per 1995 Update Figure 15-91. Deleted Per 1995 Update Figure 15-92. Deleted Per 1995 Update Figure 15-93. Deleted Per 1995 Update Figure 15-94. Deleted Per 1995 Update Figure 15-95. Deleted Per 1995 Update Figure 15-96. Deleted Per 1995 Update Figure 15-97. Deleted Per 1995 Update Figure 15-98. Deleted Per 1995 Update Figure 15-99. Deleted Per 1995 Update Figure 15-100. Deleted Per 1995 Update Figure 15-101. Deleted Per 1995 Update Figure 15-102. Deleted Per 1995 Update Figure 15-103. Deleted Per 1995 Update Figure 15-104. Deleted Per 1995 Update Figure 15-105. Deleted Per 1995 Update Figure 15-106. Deleted Per 1995 Update Figure 15-107. Deleted Per 1995 Update
Oconee Nuclear Station UFSAR Figure 15 15-111 (Page 2 of 2)
(31 DEC 2000)
Figure 15-108. Deleted Per 1995 Update Figure 15-109. Deleted Per 1995 Update Figure 15-110. Deleted Per 2001 Update Figure 15-111. Deleted Per 2003 Update
Oconee Nuclear Station UFSAR Figure 15-112 (Page 1 of 1)
(31 DEC 2014)
Figure 15-112. Deleted Per 2014 Update
Oconee Nuclear Station UFSAR Figure 15-113 (Page 1 of 1)
(31 DEC 2003)
Figure 15-113. Rod Withdrawal at Power Accident - Core Cooling Capability Analysis RCS Pressure 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 0
50 100 150 200 250 Time (seconds)
RCS Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-114 (Page 1 of 1)
(31 DEC 2013)
Figure 15-114. Rod Withdrawal at Power Accident - Core Cooling Capability Analysis DNBR 1.3 1.5 1.7 1.9 2.1 2.3 2.5 2.7 0
50 100 150 200 250 MDNBR (BHTP CHF CORRELATION)
TIME (SECONDS)
Oconee Nuclear Station UFSAR Figure 15-115 (Page 1 of 1)
(31 DEC 2015)
Figure 15-115. Cold Water Accident - Core Average Temperature
Oconee Nuclear Station UFSAR Figure 15-116 (Page 1 of 1)
(31 DEC 2015)
Figure 15-116. Cold Water Accident - Power
Oconee Nuclear Station UFSAR Figure 15-117 (Page 1 of 1)
(31 DEC 2015)
Figure 15-117. Cold Water Accident - Cold Leg Temperature
Oconee Nuclear Station UFSAR Figure 15-118 (Page 1 of 1)
(31 DEC 2015)
Figure 15-118. Cold Water Accident - RCS Pressure
Oconee Nuclear Station UFSAR Figure 15-119 (Page 1 of 1)
(31 DEC 2003)
Figure 15-119. Loss of Coolant Flow Accidents - Two RCP Coastdown from Four RCP Initial Conditions Analysis - Power 0
0.2 0.4 0.6 0.8 1
1.2 0
5 10 15 20 Time (seconds)
Power (Fraction of Nominal)
Thermal Power Neutron Power
Oconee Nuclear Station UFSAR Figure 15-120 (Page 1 of 1)
(31 DEC 2003)
Figure 15-120. Loss of Coolant Flow Accidents - Two RCP Coastdown from Four RCP Initial Conditions Analysis - RCS Temperature 540 550 560 570 580 590 600 610 620 0
5 10 15 20 Time (seconds)
RCS Temperature (°F)
Cold Leg - Faulted Loop Cold Leg - Intact Loop Hot Leg - Faulted Loop Hot Leg - Intact Loop
Oconee Nuclear Station UFSAR Figure 15-121 (Page 1 of 1)
(31 DEC 2003)
Figure 15-121. Loss of Coolant Flow Accidents - Two RCP Coastdown from Four RCP Initial Conditions Analysis - Pressurizer Level 150 160 170 180 190 200 210 220 0
5 10 15 20 Time (seconds)
Pressurizer Level (inches)
Oconee Nuclear Station UFSAR Figure 15-122 (Page 1 of 1)
(31 DEC 2003)
Figure 15-122. Loss of Coolant Flow Accidents - Two RCP Coastdown from Four RCP Initial Conditions Analysis - RCS Pressure 1800 1900 2000 2100 2200 2300 0
5 10 15 20 Time (seconds)
RCS Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-123 (Page 1 of 1)
(31 DEC 2013)
Figure 15-123. Loss of Coolant Flow Accidents - Two RCP Coastdown from Four RCP Initial Conditions Analysis - DNBR 1
1.5 2
2.5 3
0 1
2 3
4 5
6 7
8 DNBR Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-124 (Page 1 of 1)
(31 DEC 2003)
Figure 15-124. Loss of Coolant Flow Accidents - One RCP Coastdown from Three RCP Initial Conditions Analysis - RCS Flow 0
0.2 0.4 0.6 0.8 1
1.2 0
5 10 15 20 Time (seconds)
RCS Flow (Fraction of Initial)
Intact Loop Faulted Loop Reactor Core
Oconee Nuclear Station UFSAR Figure 15-125 (Page 1 of 1)
(31 DEC 2003)
Figure 15-125. Loss of Coolant Flow Accidents - One RCP Coastdown from Three RCP Initial Conditions Analysis - Power 0
0.2 0.4 0.6 0.8 1
1.2 0
5 10 15 20 Time (seconds)
Power (Fraction of Initial)
Thermal Power Neutron Power
Oconee Nuclear Station UFSAR Figure 15-126 (Page 1 of 1)
(31 DEC 2003)
Figure 15-126. Loss of Coolant Flow Accidents - One RCP Coastdown from Three RCP Initial Conditions Analysis - RCS Temperature 540 550 560 570 580 590 600 610 0
5 10 15 20 Time (seconds)
RCS Temperature (°F)
Cold Leg - Intact loop Cold Leg - Faulted Loop Hot Leg - Intact Loop Hot Leg - Faulted Loop
Oconee Nuclear Station UFSAR Figure 15-127 (Page 1 of 1)
(31 DEC 2003)
Figure 15-127. Loss of Coolant Flow Accidents - One RCP Coastdown from Three RCP Initial Conditions Analysis - Pressurizer Level 150 160 170 180 190 200 210 220 0
5 10 15 20 Time (seconds)
Pressurizer Level (inches)
Oconee Nuclear Station UFSAR Figure 15-128 (Page 1 of 1)
(31 DEC 2003)
Figure 15-128. Loss of Coolant Flow Accidents - One RCP Coastdown from Three RCP Initial Conditions Analysis - RCS Pressure 1900 1950 2000 2050 2100 2150 2200 2250 0
5 10 15 20 Time (seconds)
RCS Pressure (psig)
Loop A - Intact Loop Loop B - Faulted Loop
Oconee Nuclear Station UFSAR Figure 15-129 (Page 1 of 1)
(31 DEC 2013)
Figure 15-129. Loss of Coolant Flow Accidents - One RCP Coastdown from Three RCP Initial Conditions Analysis - DNBR 1
1.5 2
2.5 3
0 1
2 3
4 5
6 7
8 DNBR Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-130 (Page 1 of 1)
(31 DEC 2003)
Figure 15-130. Loss of Coolant Flow Accidents - Locked Rotor From Four RCP Initial Conditions Analysis - RCS Flow
-0.6
-0.4
-0.2 0
0.2 0.4 0.6 0.8 1
1.2 1.4 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
RCS Flow (Fraction of Initial)
Reactor Core Locked Rotor Cold Leg - Loop A1 Other Cold Leg in Locked Rotor Loop - Loop A2 Loop with 2 RCPs Running - Loop B
Oconee Nuclear Station UFSAR Figure 15-131 (Page 1 of 1)
(31 DEC 2003)
Figure 15-131. Loss of Coolant Flow Accidents - Locked Rotor From Four RCP Initial Conditions Analysis - Power 0
0.2 0.4 0.6 0.8 1
1.2 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
Power (Fraction of Initial)
Thermal Power Neutron Power
Oconee Nuclear Station UFSAR Figure 15-132 (Page 1 of 1)
(31 DEC 2003)
Figure 15-132. Loss of Coolant Flow Accidents - Locked Rotor From Four RCP Initial Conditions Analysis - RCS Temperature 550 560 570 580 590 600 610 620 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
RCS Temperature (°F)
Cold Leg - Faulted Loop Cold Leg - Intact Loop Hot Leg - Faulted Loop Hot Leg - Intact Loop
Oconee Nuclear Station UFSAR Figure 15-133 (Page 1 of 1)
(31 DEC 2003)
Figure 15-133. Loss of Coolant Flow Accidents - Locked Rotor From Four RCP Initial Conditions Analysis - Pressurizer Level 180 190 200 210 220 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
Pressurizer Level (inches)
Oconee Nuclear Station UFSAR Figure 15-134 (Page 1 of 1)
(31 DEC 2003)
Figure 15-134. Loss of Coolant Flow Accidents - Locked Rotor From Four RCP Initial Conditions Analysis - RCS Pressure 2000 2050 2100 2150 2200 2250 2300 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
RCS Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-135 (Page 1 of 1)
(31 DEC 2008)
Figure 15-135. Loss of Coolant Flow Accidents - Locked Rotor From Four RCP Initial Conditions Analysis - DNBR 1
1.5 2
2.5 3
3.5 0
1 2
3 4
5 6
7 8
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-136 (Page 1 of 1)
(31 DEC 2008)
Figure 15-136. Loss of Coolant Flow Accidents - Locked Rotor From Three RCP Initial Conditions Analysis - RCS Flow
-0.6
-0.4
-0.2 0
0.2 0.4 0.6 0.8 1
1.2 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
RCS Flow (Fraction of Initial)
Loop with 1 RCP Running - Loop B Reactor Core Locked Rotor Cold Leg - Loop A1 Other Cold Leg in Locked Rotor Loop - Loop A2
Oconee Nuclear Station UFSAR Figure 15-137 (Page 1 of 1)
(31 DEC 2008)
Figure 15-137. Loss of Coolant Flow Accidents - Locked Rotor From Three RCP Initial Conditions Analysis - Power 0
0.2 0.4 0.6 0.8 1
1.2 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
Power (Fraction of Initial)
Thermal Power Neutron Power
Oconee Nuclear Station UFSAR Figure 15-138 (Page 1 of 1)
(31 DEC 2008)
Figure 15-138. Loss of Coolant Flow Accidents - Locked Rotor From Three RCP Initial Conditions Analysis - RCS Temperatures 550 560 570 580 590 600 610 620 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
RCS Temperature (°F)
Cold Leg - Faulted Loop Cold Leg - Intact Loop Hot Leg - Faulted Loop Hot Leg - Intact Loop
Oconee Nuclear Station UFSAR Figure 15-139 (Page 1 of 1)
(31 DEC 2008)
Figure 15-139. Loss of Coolant Flow Accidents - Locked Rotor From Three RCP Initial Conditions Analysis - Pressurizer Level 180 190 200 210 220 230 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
Pressurizer Level (inches)
Oconee Nuclear Station UFSAR Figure 15-140 (Page 1 of 1)
(31 DEC 2008)
Figure 15-140. Loss of Coolant Flow Accidents - Locked Rotor From Three RCP Initial Conditions Analysis - RCS Pressure 2000 2050 2100 2150 2200 2250 2300 0
1 2
3 4
5 6
7 8
9 10 Time (seconds)
RCS Pressure (psig)
Loop A Loop B
Oconee Nuclear Station UFSAR Figure 15-141 (Page 1 of 1)
(31 DEC 2011)
Figure 15-141. Loss of Coolant Flow Accidents - Locked Rotor From Three RCP Initial Conditions Analysis - DNBR
Oconee Nuclear Station UFSAR Figure 15-142 (Page 1 of 1)
(31 DEC 2000)
Figure 15-142. Intentionally Blank
Oconee Nuclear Station UFSAR Figure 15-143 (Page 1 of 1)
(31 DEC 2010)
Figure 15-143. Control Rod Misalignment Accidents - Dropped Rod - RCS Pressure
Oconee Nuclear Station UFSAR Figure 15-144 (Page 1 of 1)
(31 DEC 2013)
Figure 15-144. Control Rod Misalignment Accidents - Dropped Rod - DNBR 1.85 1.9 1.95 2
2.05 2.1 0
10 20 30 40 50 60 70 80 90 MDNBR (B-HTP Correlation)
TIME (SEC)
Oconee Nuclear Station UFSAR Figure 15-145 (Page 1 of 1)
(31 DEC 2013)
Figure 15-145. Turbine Trip Accident - Steam Generator Pressure 800 850 900 950 1000 1050 1100 1150 1200 0
5 10 15 20 25 30 35 40 Steam Generator Pressure (psig)
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-146 (Page 1 of 1)
(31 DEC 2013)
Figure 15-146. Turbine Trip Accident - RCS Temperatures 550 560 570 580 590 600 610 0
5 10 15 20 25 30 35 40 RCS Temperature (°F)
Time (seconds)
Cold Leg Hot Leg
Oconee Nuclear Station UFSAR Figure 15-147 (Page 1 of 1)
(31 DEC 2013)
Figure 15-147. Turbine Trip Accident - Pressurizer Level 200 220 240 260 280 300 320 0
5 10 15 20 25 30 35 40 Pressurizer Level (inches)
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-148 (Page 1 of 1)
(31 DEC 2013)
Figure 15-148. Turbine Trip Accident - RCS Pressure 2000 2100 2200 2300 2400 2500 2600 2700 0
5 10 15 20 25 30 35 40 Peak RCS Pressure (psig)
Time (seconds)
PRESSURE AT THE BOTTOM OF THE REACTOR VESSEL
Oconee Nuclear Station UFSAR Figure 15-149 (Page 1 of 1)
(31 DEC 2013)
Figure 15-149. Turbine Trip Accident - Power 0
20 40 60 80 100 120 0
5 10 15 20 25 30 35 40 Neutron Power (% of 2568 MWt)
Time (seconds)
Oconee Nuclear Station UFSAR Figure 15-150 (Page 1 of 1)
(31 DEC 2011)
Figure 15-150. Steam Generator Tube Rupture - Power
Oconee Nuclear Station UFSAR Figure 15-151 (Page 1 of 1)
(31 DEC 2011)
Figure 15-151. Steam Generator Tube Rupture - Break Flow
Oconee Nuclear Station UFSAR Figure 15-152 (Page 1 of 1)
(31 DEC 2011)
Figure 15-152. Steam Generator Tube Rupture - RCS Pressure
Oconee Nuclear Station UFSAR Figure 15-153 (Page 1 of 1)
(31 DEC 2011)
Figure 15-153. Steam Generator Tube Rupture - Pressurizer Level
Oconee Nuclear Station UFSAR Figure 15-154 (Page 1 of 1)
(31 DEC 2011)
Figure 15-154. Steam Generator Tube Rupture - Steam Generator Pressure
Oconee Nuclear Station UFSAR Figure 15-155 (Page 1 of 1)
(31 DEC 2011)
Figure 15-155. Steam Generator Tube Rupture - Steam Generator Level
Oconee Nuclear Station UFSAR Figure 15-156 (Page 1 of 1)
(31 DEC 2011)
Figure 15-156. Steam Generator Tube Rupture - RCS Temperatures
Oconee Nuclear Station UFSAR Figure 15-157 (Page 1 of 1)
(31 DEC 2003)
Figure 15-157. Steam Line Break Accident - With Offsite Power - Power 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 0
100 200 300 400 500 600 Time (Seconds)
Power (%)
Neutron power Thermal power
Oconee Nuclear Station UFSAR Figure 15-158 (Page 1 of 1)
(31 DEC 2003)
Figure 15-158. Steam Line Break Accident - With Offsite Power - RCS Pressure 0.0 500.0 1000.0 1500.0 2000.0 2500.0 0
100 200 300 400 500 600 Time (Seconds)
RCS Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-159 (Page 1 of 1)
(31 DEC 2003)
Figure 15-159. Steam Line Break Accident - With Offsite Power - Core Inlet Flow 10000.0 12000.0 14000.0 16000.0 18000.0 20000.0 22000.0 24000.0 26000.0 28000.0 30000.0 0
100 200 300 400 500 600 Time (Seconds)
Core Inlet Flow (lbm/sec)
Affected loop Unaffected Loop
Oconee Nuclear Station UFSAR Figure 15-160 (Page 1 of 1)
(31 DEC 2003)
Figure 15-160. Deleted Per 2003 Update
Oconee Nuclear Station UFSAR Figure 15-161 (Page 1 of 1)
(31 DEC 2003)
Figure 15-161. Steam Line Break Accident - Without Offsite Power - Steam Line Pressure 0
200 400 600 800 1000 1200 0
1 2
3 4
5 Time (Seconds)
Steam Line Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-162 (Page 1 of 1)
(31 DEC 2003)
Figure 15-162. Steam Line Break Accident - Without Offsite Power - RCS Temperatures 520 530 540 550 560 570 580 590 600 610 620 0
1 2
3 4
5 Time (seconds)
RCS Temperature (F)
Affected Loop Cold Leg Unaffected Loop Cold Leg Affected Loop Hot Leg Unaffected Loop Hot Leg
Oconee Nuclear Station UFSAR Figure 15-163 (Page 1 of 1)
(31 DEC 2003)
Figure 15-163. Steam Line Break Accident - Without Offsite Power - RCS Flow 80,000 130,000 180,000 230,000 280,000 330,000 380,000 430,000 0
1 2
3 4
5 Time (seconds)
RCS Volumetric Flow (gpm)
Oconee Nuclear Station UFSAR Figure 15-164 (Page 1 of 1)
(31 DEC 2003)
Figure 15-164. Steam Line Break Accident - Without Offsite Power - Reactivity
-4
-3
-2
-1 0
1 2
3 4
0 1
2 3
4 5
Time (seconds)
Reactivity ($)
Total Reactivity Moderator Reactivity Doppler Reactivity Control Reactivity
Oconee Nuclear Station UFSAR Figure 15-165 (Page 1 of 1)
(31 DEC 2003)
Figure 15-165. Steam Line Break Accident - Without Offsite Power - Power 0
10 20 30 40 50 60 70 80 90 100 110 0
1 2
3 4
5 Time (seconds)
Power (% of nominal)
Neutron Power Thermal Power
Oconee Nuclear Station UFSAR Figure 15-166 (Page 1 of 1)
(31 DEC 2003)
Figure 15-166. Steam Line Break Accident - Without Offsite Power - RCS Pressure 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 0
1 2
3 4
5 Time (seconds)
RCS Pressure (psig)
Oconee Nuclear Station UFSAR Figure 15-167 (Page 1 of 1)
(31 DEC 2013)
Figure 15-167. Steam Line Break Accident - Without Offsite Power - DNBR 1.3 1.5 1.7 1.9 2.1 2.3 2.5 0
1 2
3 4
5 MDNBR (BHTP CHF CORRELATION)
TIME (SECONDS)
Oconee Nuclear Station UFSAR Figure 15-168 (Page 1 of 1)
(31 DEC 2016)
Figure 15-168. Small Steam Line Break - Steam Mass Flows
Oconee Nuclear Station UFSAR Figure 15-169 (Page 1 of 1)
(31 DEC 2016)
Figure 15-169. Small Steam Line Break - Steam Line Pressures
Oconee Nuclear Station UFSAR Figure 15-170 (Page 1 of 1)
(31 DEC 2016)
Figure 15-170. Small Steam Line Break - Main Feedwater Mass Flows
Oconee Nuclear Station UFSAR Figure 15-171 (Page 1 of 1)
(31 DEC 2016)
Figure 15-171. Small Steam Line Break - RCS Temperatures
Oconee Nuclear Station UFSAR Figure 15-172 (Page 1 of 1)
(31 DEC 2016)
Figure 15-172. Small Steam Line Break - Core Average Power
Oconee Nuclear Station UFSAR Figure 15-173 (Page 1 of 1)
(31 DEC 2016)
Figure 15-173. Small Steam Line Break - RCS Hot Leg Pressure
Oconee Nuclear Station UFSAR Figure 15-174 (Page 1 of 1)
(31 DEC 2014)
Figure 15-174. Deleted Per 2014 Update
Oconee Nuclear Station UFSAR Figure 15-175 (Page 1 of 1)
(31 DEC 2003)
Figure 15-175. Oconee - No CHRS Flow Oconee - No CHRS Flow 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 0
100 200 300 400 500 600 700 800 TIME (Hours)
H2 Concentration (%)
Oconee Nuclear Station UFSAR Figure 15-176 (Page 1 of 1)
(31 DEC 2001)
Figure 15-176. Deleted per 2001 Update
Oconee Nuclear Station UFSAR Figure 15-177 (Page 1 of 1)
(31 DEC 2003)
Figure 15-177. Lower Bound Containment Pressure Used in Large Break LOCA
Oconee Nuclear Station UFSAR Figure 15-178 212(Page 1 of 2)
(31 DEC 2014)
Figure 15-178. Deleted Per 2014 Update Figure 15-179. Deleted Per 2014 Update Figure 15-180. Deleted Per 2014 Update Figure 15-181. Deleted Per 2014 Update Figure 15-182. Deleted Per 2014 Update Figure 15-183. Deleted Per 2014 Update Figure 15-184. Deleted Per 2014 Update Figure 15-185. Deleted Per 2014 Update Figure 15-186. Deleted Per 2014 Update Figure 15-187. Deleted Per 2014 Update Figure 15-188. Deleted Per 2014 Update Figure 15-189. Deleted Per 2014 Update Figure 15-190. Deleted Per 2014 Update Figure 15-191. Deleted Per 2014 Update Figure 15-192. Deleted Per 2014 Update Figure 15-193. Deleted Per 2014 Update Figure 15-194. Deleted Per 2014 Update Figure 15-195. Deleted Per 2014 Update Figure 15-196. Deleted Per 2014 Update
Oconee Nuclear Station UFSAR Figure 15-178 212(Page 2 of 2)
(31 DEC 2014)
Figure 15-197. Deleted Per 2014 Update Figure 15-198. Deleted Per 2014 Update Figure 15-199. Deleted Per 2014 Update Figure 15-200. Deleted Per 2014 Update Figure 15-201. Deleted Per 2014 Update Figure 15-202. Deleted Per 2014 Update Figure 15-203. Deleted Per 2014 Update Figure 15-204. Deleted Per 2014 Update Figure 15-205. Deleted Per 2014 Update Figure 15-206. Deleted Per 2014 Update Figure 15-207. Deleted Per 2014 Update Figure 15-208. Deleted Per 2014 Update Figure 15-209. Deleted Per 2014 Update Figure 15-210. Deleted Per 2014 Update Figure 15-211. Deleted Per 2014 Update Figure 15-212. Deleted Per 2014 Update
Oconee Nuclear Station UFSAR Figure 15-213(Page 1 of 1)
(31 DEC 2015)
Figure 15-213. 52% of 2568 MWt, Full Core Mark-B-HTP SBLOCA Break Spectrum Analysis
Oconee Nuclear Station UFSAR Figure 15-214(Page 1 of 1)
(31 DEC 2015)
Figure 15-214. 0.072 ft2 CLPD, 52% of 2568 MWt, Full-Core Mark-B-HTP SBLOCA - Pressure
Oconee Nuclear Station UFSAR Figure 15-215(Page 1 of 1)
(31 DEC 2015)
Figure 15-215. 0.072 ft2 CLPD, 52% of 2568 MWt, Full Core Mark-B-HTP SBLOCA - Break and ECCS Mass Flow Rates
Oconee Nuclear Station UFSAR Figure 15-216(Page 1 of 1)
(31 DEC 2015)
Figure 15-216. 0.072 ft2 CLPD, 52% of 2568 MWt, Full Core Mark-B-HTP SBLOCA - RV Collapsed Liquid Level & Hot Channel Mixture Level
Oconee Nuclear Station UFSAR Figure 15-217(Page 1 of 1)
(31 DEC 2015)
Figure 15-217. 0.072 ft2 CLPD, 52% of 2568 MWt, Full Core Mark-B-HTP SBLOCA - Peak Cladding Temperature
Oconee Nuclear Station UFSAR Figure 15-218(Page 1 of 1)
(31 DEC 2015)
Figure 15-218. 0.072 ft2 CLPD, 52% of 2568 MWt, Full Core Mark-B-HTP SBLOCA - Hot Channel Vapor Temperature at Core Exit
Oconee Nuclear Station UFSAR Figure 15-219(Page 1 of 1)
(31 DEC 2011)
Figure 15-219. Mark-B-HTP Full-Core BOL LBLOCA - Reactor Vessel Upper Plenum Pressure
Oconee Nuclear Station UFSAR Figure 15-220(Page 1 of 1)
(31 DEC 2011)
Figure 15-220. Mark-B-HTP Full-Core BOL LBLOCA - Break Mass Flow Rates
Oconee Nuclear Station UFSAR Figure 15-221(Page 1 of 1)
(31 DEC 2011)
Figure 15-221. Mark-B-HTP Full-Core BOL LBLOCA - Hot Channel Mass Flow Rates
Oconee Nuclear Station UFSAR Figure 15-222(Page 1 of 1)
(31 DEC 2011)
Figure 15-222. Mark-B-HTP Full-Core BOL LBLOCA - Core Flooding Rates
Oconee Nuclear Station UFSAR Figure 15-223(Page 1 of 1)
(31 DEC 2011)
Figure 15-223. Mark-B-HTP Full-Core BOL LBLOCA - Hot Pin Fuel & Clad Temperatures at Ruptured Location
Oconee Nuclear Station UFSAR Figure 15-224(Page 1 of 1)
(31 DEC 2011)
Figure 15-224. Mark-B-HTP Full-Core BOL LBLOCA - Hot Pin Fuel & Clad Temperatures at Unruptured Location
Oconee Nuclear Station UFSAR Figure 15-225(Page 1 of 1)
(31 DEC 2011)
Figure 15-225. Mark-B-HTP Full-Core BOL LBLOCA - Quench Front Advancement
Oconee Nuclear Station UFSAR Figure 15-226(Page 1 of 1)
(31 DEC 2011)
Figure 15-226. Mark-B-HTP Full-Core BOL LBLOCA - Hot Pin Heat Transfer Coefficients
Oconee Nuclear Station UFSAR Figure 15-227(Page 1 of 1)
(31 DEC 2011)
Figure 15-227. 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA Break Spectrum Analysis
Oconee Nuclear Station UFSAR Figure 15-228(Page 1 of 1)
(31 DEC 2011)
Figure 15-228. 0.15 ft2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA - Pressure
Oconee Nuclear Station UFSAR Figure 15-229(Page 1 of 1)
(31 DEC 2011)
Figure 15-229. 0.15 ft2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA - Break and ECCS Mass Flow Rates
Oconee Nuclear Station UFSAR Figure 15-230(Page 1 of 1)
(31 DEC 2011)
Figure 15-230. 0.15 ft2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA -
RVCollapsed Liquid Level & Hot Channel Mixture Level
Oconee Nuclear Station UFSAR Figure 15-231(Page 1 of 1)
(31 DEC 2011)
Figure 15-231. 0.15 ft2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA - HotPin Peak Clad Temperature
Oconee Nuclear Station UFSAR Figure 15-232(Page 1 of 1)
(31 DEC 2011)
Figure 15-232. 0.15 ft2 CLPD, 102% of 2568 MWt, Full Core Mark-B-HTP SBLOCA -
HotChannel Vapor Temperature at Core Exit