ML16257A132

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Revision 309 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Section 15.4, Figures 15.4-1 Through 15.4-99
ML16257A132
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/25/2016
From:
Entergy Operations
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16256A115 List: ... further results
References
W3F1-2016-0053
Download: ML16257A132 (114)


Text

Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical Core Power vs. Time Figure 15.4-1 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical Core Heat Flux vs. Time Figure 15.4-2 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical Reactor Coolant System Temperatures vs. Time Figure 15.4-3 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical Reactor Coolant System Pressure vs. Time Figure 15.4-4 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical Steam Generator Pressure vs. Time Figure 15.4-5 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical Reactivity vs. Time Figure 15.4-6 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical Peak Linear Heat Rate vs. Time Figure 15.4-7

Revision 304 (06/10)Waterford Steam Electric Station #3 CEA Withdrawal from Subcritical DNBR vs. Time Figure 15.4-7a Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power Core Power vs. Time Figure 15.4-8 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power Core Heat Flux vs. Time Figure 15.4-9 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power Reactor Coolant System Temperatures vs. Time Figure15.4-10 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power Reactor Coolant System Pressure vs. Time Figure15.4-11 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power Steam Generator Pressure vs. Time Figure15.4-11a Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power Reactivity vs. Time Figure15.4-11b Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power Peak Linear Heat Rate vs. Time Figure15.4-11c

Revision 304 (06/10)Waterford Steam Electric Station #3 CEA Withdrawal at Low Power DNBR vs. Time Figure 15.4-11d WSES-FSAR-UNIT-3 Revision 14 (12/05)(DRN 05-543, R14)

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Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Core Heat Flux vs. Time Figure15.4-25 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Peak Linear Heat Generation Rate vs. Time Figure15.4-26 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Reactor Coolant System Pressure vs. Time Figure15.4-27 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Core Power vs. Time Figure15.4-28

Revision 304 (06/10)Waterford Steam Electric Station #3 CEA Withdrawal at Power Minimum DNBR vs. Time Figure 15.4-29 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Reactor Coolant Temperatures vs. Time Figure15.4-30 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Pressurizer Water Volume vs. Time Figure15.4-31 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Steam Generator Pressure vs. Time Figure15.4-32 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Steam Flow vs. Time Figure15.4-33 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Feedwater Flow vs. Time Figure15.4-34 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Feedwater Enthalpy vs. Time Figure15.4-35 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Steam Generator Liquid Mass vs. Time Figure15.4-36 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Withdrawal at Power Secondary Safety Valve Flow vs. Time Figure15.4-37 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop Core Power vs. Time Figure15.4-38 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop Core Average Heat Flux vs. Time Figure15.4-39 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop Reactivities vs. Time Figure15.4-40 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop RCS Temperature vs. Time Figure15.4-41 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop System Pressure vs. Time Figure15.4-42 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop Steam Generator Pressure vs. Time Figure15.4-43 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop Pressurizer Level vs. Time Figure15.4-44 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop Steam Generator Level vs. Time Figure15.4-44a

Revision 304 (06/10)Waterford Steam Electric Station #3 CEA Misoperation, Single CEA Drop DNBR vs. Time Figure 15.4-44b WSES-FSAR-UNIT-3 Revision 12 (10/02)(DRN 02-1479)

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0.00%20.00%40.00%60.00%80.00%100.00%

120.00%140.00%160.00%180.00%200.00%012345TIME, SECONDSCORE POWER, PERCENT OF FULL POWER

Revision 15 (03/07)Waterford Steam Electric Station #3 HFP CEA Ejection Core Power vs. Time Figure 15.4-67

0.00%100.00%200.00%300.00%400.00%500.00%600.00%700.00%800.00%012345TIME, SECONDSPEAK CORE POWER, PERCENT OF FULL POWER

Revision 15 (03/07)Waterford Steam Electric Station #3 HFP CEA Ejection Peak Core Power vs. Time Figure 15.4-68

0.00%20.00%40.00%

60.00%80.00%100.00%120.00%

140.00%012345TIME, SECONDSCORE HEAT FLUX, PERCENT OF AVERAGE HEA TFLUX AT FULL POWER

Revision 15 (03/07)Waterford Steam Electric Station #3 HFP CEA Ejection Core Heat Flux vs. Time Figure 15.4-69

0.00%50.00%100.00%150.00%200.00%

250.00%

300.00%

350.00%400.00%450.00%

500.00%012345TIME, SECONDSPEAK CORE HEAT FLUX, PERCENT OF AVERAGE HEAT FLU XAT FULL POWER

Revision 15 (03/07)Waterford Steam Electric Station #3 HFP CEA Ejection Peak Core Heat Flux vs. Time Figure 15.4-70

0.00500.001000.001500.002000.002500.003000.003500.004000.004500.005000.00012345TIME, SECONDSTEMPERATURE, o FFUEL CENTERLINE - HOT CHANNELFUEL RADIAL AVG - AVG CHANNELFUEL CENTERLINE - AVG CHANNELFUEL RADIAL AVG - HOT CHANNELCLAD SURFACE - HOT CHANNELCLAD SURFACE - AVG CHANNEL

Revision 15 (03/07)Waterford Steam Electric Station #3 HFP CEA Ejection Hot and Average Channel Fuel & Clad Temperatures vs. Time Figure 15.4-71

-6%-5%-4%-3%

-2%-1%0%1%012345TIME, SECONDSREACTIVITY, %drhoEJECTED CEATOTALCEAs AFTER SCRAMDOPPLERMODERATOR

Revision 15 (03/07)Waterford Steam Electric Station #3 HFP CEA Ejection Reactivity Components vs. Time Figure 15.4-72 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Ejection RCS Pressure vs. Time for Peak RCS Pressure Figure15.4-73 Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Ejection Core Power vs. Time for Peak RCS Pressure Figure15.4-73a Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Ejection Core Heat Flux vs. Time for Peak RCS Pressure Figure15.4-73b Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Ejection Core Coolant Temperatures vs. Time for Peak RCS Pressure Figure15.4-73c Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Ejection Steam Generator Pressure vs. Time for Peak RCS Pressure Figure15.4-73d Revision 14 (12/05)Waterford Steam Electric Station #3 CEA Ejection Reactivity Components vs. Time for Peak RCS Pressure Figure15.4-73e WSES-FSAR-UNIT-3 Revision 14 (12/05)(DRN 05-543, R14)

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LOUISIANA POWER 8 LIGHT CO.Waterford Steam Statlon FIGURE HAS BEEN INTENTIONALLY DELETED WSES-FSAR-UNIT-3 Revision 14 (12/05)(DRN 05-543, R14)

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Figure 15.4-97 has been deleted. (DRN 05-543, R14) 005 01 006 007 02 008 009 03 010 011 04 012 013 05 015 016 017 018 019 020 021 022 023 014 024 027 07 028 029 08 030 031 09 032 033 10 034 035 11 026 036 025 06 037 12 041 042 043 044 045 0 4 6 047 048 049 040 050 039 166 052 056 14 057 058 15 059 060 16 061 062 17 063 064 18 055 065 054 13 066 19 053 067 169 170 171 172 173 174 175 176 177 168 178 167 051 180 071 072 073 074 075 076 077 078 079 070 080 069 081 068 082 088 23 089 090 24 091 092 25 093 094 26 095 096 27 087 097 086 22 098 28 085 099 179 151 154 39 155 156 40 157 158 41 159 160 42 161 162 43 153 163 152 38 136 165 139 140 141 142 143 144 145 146 147 138 148 137 164 44 119 150 122 30 123 124 31 125 126 32 127 128 33 129 130 34 121 131 120 29 149 102 133 106 107 108 109 110 111 112 113 114 105 132 35 104 115 103 116 038 183 46 184 185 47 186 187 48 188 189 49 190 191 50 182 192 181 45 193 51 195 196 197 198 199 200 201 202 203 194 204 205 52 206 207 53 208 209 54 210 211 55 212 213 56 214 215 216 217 083 20 100 117 134 36 084 21 101 118 135 37 001 002 003 004 XXX YYXXX-Fuel Assembly No.YY-Incore Instrument No.

Revision 304 (06/10)

Waterford Steam Electric Station #3 Locations of Incore Neutron DetectorsFigure 15.4-98NOTE:THEREARENOINCORENEUTRONDETECTORSATLOCATIONS9,11AND30 X3X8X8X3 0.48 0.610.610.48 0.22 0.320.320.22X2X6Y8Z2Z3Z2Y8X6X20.430.64 0.961.421.40 1.42 0.950.640.440.180.35 0.611.101.16 1.10 0.610.340.18X2Y6Z2Z3Z6Y6Z6Z3X2Y6Z2 0.630.911.33 1.441.481.14 1.48 1.431.651.75 1.84 0.290.611.07 1.281.381.10 1.38 1.271.631.76 1.89X2Z2Z3Y8Y3Y7Z6Y7Y3Y8Z3Z2X2 0.63 1.371.431.10 1.191.201.54 1.18 1.161.071.41 1.36 0.62 0.29 0.991.241.00 1.071.111.45 1.10 1.050.981.23 0.98 0.28X2Y6Z3Y2Z7Y3Z7Y3Z7Y3Z7Y2Z3Y6X2 0.44 0.91 1.431.391.57 1.311.611.35 1.56 1.241.491.35 1.410.900.43 0.18 0.60 1.241.211.44 1.181.491.25 1.45 1.121.381.19 1.230.600.18X6Z2Y8Z7Y8Z8Y7Z8Y7Z8Y8Z7Y8Z2X6 0.63 1.31 1.091.561.33 1.811.351.63 1.22 1.571.181.49 1.071.320.64 0.34 1.06 0.991.421.22 1.641.261.53 1.18 1.471.131.38 0.981.060.34Y8Z3Y3Y3Z8Z6Z8Y2Z8Y2Z8Y3Y3Z3Y8 0.92 1.37 1.141.281.80 1.861.811.35 1.57 1.381.561.24 1.161.420.96X30.59 1.24 1.031.151.62 1.781.641.25 1.48 1.271.461.12 1.051.270.61X30.46Z2Z6Y7Z7Y7Z8Y2Y2Y2Z8Y7Z7Y7Z6Z2 0.480.211.35 1.37 1.081.561.34 1.811.511.17 1.33 1.561.201.54 1.171.471.42 0.22X81.05 1.29 1.021.411.23 1.631.241.09 1.15 1.461.161.44 1.101.371.10X80.58Z3Y6Y2Y3Z8Y2Y2S4Y2Y2Z8Y3Z6Y6Z3 0.610.311.32 1.03 1.141.291.59 1.301.200.88 1.13 1.271.551.31 1.521.141.40 0.32X81.10 0.99 1.051.141.48 1.241.090.84 1.06 1.191.471.22 1.431.091.16X80.58Z2Z6Y7Z7Y7Z8Y2Y2Y2Z8Y7Z7Y7Z6Z2 0.610.311.34 1.36 1.061.491.19 1.561.331.13 1.32 1.551.201.54 1.171.471.42 0.32X31.05 1.28 1.001.361.15 1.471.151.06 1.14 1.461.161.43 1.101.371.10X30.46Y8Z3Y3Y3Z8Y2Z8Y2Z8Y2Z8Y3Y3Z3Y8 0.480.210.92 1.36 1.111.211.55 1.371.561.27 1.56 1.371.561.24 1.161.430.96 0.22 0.59 1.22 1.011.101.45 1.261.461.19 1.46 1.261.461.12 1.051.270.61X6Z2Y8Z7Y8Z8Y7Z8Y7Z8Y8Z7Y8Z2X6 0.62 1.29 1.061.481.18 1.561.201.55 1.20 1.561.181.49 1.071.320.64 0.34 1.04 0.971.371.13 1.461.161.47 1.16 1.461.131.38 0.991.070.34X2Y6Z3Y2Z7Y3Z7Y3Z7Y3Z7Y2Z3Y6X2 0.43 0.89 1.401.341.48 1.241.541.31 1.54 1.241.491.35 1.410.900.44 0.18 0.59 1.221.191.38 1.121.441.22 1.44 1.121.381.19 1.230.600.18X2Z2Z3Y8Y3Y7Z6Y7Y3Y8Z3Z2X2 0.62 1.361.411.07 1.161.181.52 1.18 1.161.071.41 1.36 0.63 0.28 0.981.230.99 1.051.101.44 1.10 1.050.991.23 0.98 0.29X2Y6Z2Z3Z6Y6Z6Z3Z2Y6X2 0.630.911.32 1.431.471.14 1.47 1.431.320.90 0.62 0.290.601.07 1.271.381.09 1.38 1.271.070.60 0.28X2X6Y8Z2Z3Z2Y8X6X20.440.64 0.961.421.40 1.42 0.960.640.430.180.34 0.611.101.17 1.10 0.610.340.18X3X8X8X3 0.48 0.610.610.48 0.22 0.320.320.22##Assembly TypeDenotes position of Misloaded Assemblies

  1. .##Max Rod Power
  1. .##Assembly Power Revision 13 (04/04)

Waterford SteamElectric Station #3 Power Distribution for Representative Worst Case Undetectable MisloadFigure 15.4-99