ML16257A127

09 to Final Safety Analysis Report, Chapter 15, Accident Analyses, Section 15.1, Figures 15.1-1 Through 15.1-94

ML16257A127
Person / Time
Site:	Waterford
Issue date:	08/25/2016
From:	Entergy Operations
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16256A115	List: ML16256A120 ML16256A121 ML16256A122 ML16256A123 ML16256A124 ML16256A126 ML16256A127 ML16256A128 ML16256A129 ML16256A131 ML16256A132 ML16256A136 ML16256A137 ML16256A138 ML16256A144 ML16256A145 ML16256A150 ML16256A153 ML16256A154 ML16256A155 ML16256A156 ML16256A157 ML16256A159 ML16256A160 ML16256A161 ML16256A162 ML16256A163 ML16256A164 ML16256A165 ML16256A167 ML16256A170 ML16256A171 ML16256A172 ML16256A174 ML16256A175 ML16256A181 ML16256A182 ML16256A183 ML16256A184 ML16256A185 ML16256A186 ML16256A188 ML16256A189 ML16256A190 ML16256A191 ML16256A192 ML16256A193 ML16256A194 ML16256A195 ML16256A196 ... further results
References
W3F1-2016-0053
Download: ML16257A127 (128)

Text

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Core Power vs. Time Figure 15.1-1

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Core Average Heat Flux vs. Time Figure 15.1-2

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Reactor Coolant System Pressure vs. Time Figure 15.1-3

Revision 304 (06/10)

Waterford Steam Electric Station #3 Increased Main Steam Flow Minimum DNBR vs. Time Figure 15.1-4

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Reactor Coolant System Temperatures vs. Time Figure 15.1-5

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Pressurizer Level vs. Time Figure 15.1-6

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Steam Generator Pressure vs. Time Figure 15.1-7

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Total Steam Flow vs. Time Figure 15.1-8

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Feedwater Flow vs. Time Figure 15.1-9

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Feedwater Enthalpy vs. Time Figure 15.1-10

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow Steam Generator Liquid Mass vs. Time Figure 15.1-11

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve Core Power vs. Time Figure 15.1-12

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve Core Heat Flux vs. Time Figure 15.1-13

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve RCS Pressure vs. Time Figure 15.1-14

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve Reactor Coolant Temperature vs. Time Figure 15.1-15

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve Pressurizer Water Volume vs. Time Figure 15.1-16

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve Steam Generator Pressure vs. Time Figure 15.1-17

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve Total Main Steam Flow vs. Time Figure 15.1-18

Revision 14 (12/05)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve Steam Generator Fluid Mass vs. Time Figure 15.1-19

Revision 304 (06/10)

Waterford Steam Electric Station #3 Inadvertent Opening of a Steam Generator Atmospheric Dump Valve DNBR vs. Time Figure 15.1-19a

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Core Power vs. Time (Typical NSSS Response)

Figure 15.1-20

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increase Steam Flow with Concurrent Single Failure Core Heat Flux vs. Time (Typical NSSS Response)

Figure 15.1-21

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure RCS Pressure vs. Time (Typical NSSS Response)

Figure 15.1-22

Revision 309 (06/16)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Minimum Hot Channel DNBR vs. Time Figure 15.1-23

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Reactor Coolant Temperature vs. Time (Typical NSSS Response)

Figure 15.1-24

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Pressurizer Liquid Volume vs. Time (Typical NSSS Response)

Figure 15.1-25

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Steam Generator Pressure vs. Time (Typical NSSS Response)

Figure 15.1-26

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Main Steam Flow vs. Time (Typical NSSS Response)

Figure 15.1-27

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Feedwater Flow vs. Time (Typical NSSS Response)

Figure 15.1-28

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Feedwater Enthalpy vs. Time (Typical NSSS Response)

Figure 15.1-29

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Steam Generator Liquid Mass vs. Time (Typical NSSS Response)

Figure 15.1-30

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-31 has been intentionally deleted.

(DRN 05-543, R14)

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Total Integrated Safety Valve Flow vs. Time (Typical NSSS Response)

Figure 15.1-31a

Revision 14 (12/05)

Waterford Steam Electric Station #3 Increased Main Steam Flow with Concurrent Single Failure Core Flow vs. Time (Typical NSSS Response)

Figure 15.1-32

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Core Power vs. Time Figure 15.1-32a

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Core Heat Flux vs. Time Figure 15.1-32b

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power RCS Pressure vs. Time Figure 15.1-32c

Revision 304 (06/10)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Minimum Hot Channel DNBR vs. Time Figure 15.1-32d

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Reactor Coolant Temperature vs. Time Figure 15.1-32e

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Pressurizer Liquid Volume vs. Time Figure 15.1-32f

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Steam Generator Pressure vs. Time Figure 15.1-32g

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Main Steam Flow vs. Time Figure 15.1-32h

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Feedwater Flow vs. Time Figure 15.1-32i

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Feedwater Enthalpy vs. Time Figure 15.1-32j

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Steam Generator Liquid Mass vs. Time Figure 15.1-32k

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening of an Atmospheric Dump Valve With a Concurrent Loss of AC Power Total Integrated Safety Valve Flow vs. Time Figure 15.1-32l

Revision 14 (12/05)

Waterford Steam Electric Station #3 HFP Inadvertent Opening in an Atmospheric Dump Valve With a Concurrent Loss of AC Power Core Flow vs. Time Figure 15.1-32m

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Core Power vs. Time Figure 15.1-33

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Core Heat Flux vs. Time Figure 15.1-34

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Pressurizer Pressure vs. Time Figure 15.1-35

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Reactor Coolant System Temperature vs. Time Figure 15.1-36

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Steam Generator Pressure vs. Time Figure 15.1-37

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Reactivity vs. Time Figure 15.1-38

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Pressurizer Level vs. Time Figure 15.1-38a

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Steam Flow vs. Time Figure 15.1-38b

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Feedwater Flow vs. Time Figure 15.1-38c

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Steam Generator Mass vs. Time Figure 15.1-38d

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Integrated Safety Injection Flow vs. Time Figure 15.1-38e

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power Reactor Vessel Level vs. Time Figure 15.1-38f

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, Loss of Offsite Power DNBR vs. Time Figure 15.1-38g

T H R O U G H H A V E B E E N I N T E N T I O N A L L Y D E L E T E D

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Core Power vs. Time Figure 15.1-47

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Core Heat Flux vs. Time Figure 15.1-48

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Pressurizer Pressure vs. Time Figure 15.1-49

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-50 has been intentionally deleted.

(DRN 05-543, R14)

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Reactor Coolant System Temperatures vs. Time Figure 15.1-51

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-52 has been intentionally deleted.

(DRN 05-543, R14)

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Steam Generator Pressure vs. Time Figure 15.1-53

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Steam Flow vs. Time Figure 15.1-54

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Feedwater Flow vs. Time Figure 15.1-55

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-56 has been intentionally deleted.

(DRN 05-543, R14)

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Steam Generator Mass vs. Time Figure 15.1-57

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Reactivity vs. Time Figure 15.1-58

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Pressurizer Level vs. Time Figure 15.1-58a

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Integrated Safety Injection Flow vs. Time Figure 15.1-58b

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Full Power, No Loss of Offsite Power Reactor Vessel Upper Head Level vs. Time Figure 15.1-58c

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-59 has been intentionally deleted.

(DRN 05-543, R14)

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-60 has been intentionally deleted.

(DRN 05-543, R14)

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Core Power vs. Time Figure 15.1-61

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Core Heat Flux vs. Time Figure 15.1-62

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Pressurizer Pressure vs. Time Figure 15.1-63

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Reactor Coolant System Temperature vs. Time Figure 15.1-64

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Pressurizer Level vs. Time Figure 15.1-65

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Steam Generator Pressure vs. Time Figure 15.1-66

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Steam Flow vs. Time Figure 15.1-67

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Feedwater Flow vs. Time Figure 15.1-68

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-69 has been intentionally deleted.

(DRN 05-543, R14)

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Steam Generator Mass vs. Time Figure 15.1-70

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Reactivity vs. Time Figure 15.1-71

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-72 has been intentionally deleted.

(DRN 05-543, R14)

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Integrated Safety Injection Flow vs. Time Figure 15.1-72a

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power Reactor Vessel Level vs. Time Figure 15.1-72b

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, Loss of Offsite Power DNBR vs. Time Figure 15.1-72c

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Core Power vs. Time Figure 15.1-72d

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Core Heat Flux vs. Time Figure 15.1-72e

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Pressurizer Pressure vs. Time Figure 15.1-72f

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Reactor Coolant System Temperatures vs. Time Figure 15.1-72g

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Steam Generator Pressure vs. Time Figure 15.1-72h

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Reactivity vs. Time Figure 15.1-72i

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Pressurizer Level vs. Time Figure 15.1-72j

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Steam Flow vs. Time Figure 15.1-72k

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Feedwater Flow vs. Time Figure 15.1-72l

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Steam Generator Mass vs. Time Figure 15.1-72m

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Integrated Safety Injection Flow vs. Time Figure 15.1-72n

Revision 307 (07/13)

Waterford Steam Electric Station #3 Return to Power Steam Line Break Inside Containment, Hot Zero Power, No Loss of Offsite Power Reactor Vessel Upper Head Level vs. Time Figure 15.1-72o

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-73 has been intentionally deleted.

(DRN 05-543, R14)

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-74 has been intentionally deleted.

(DRN 05-543, R14)

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-75 has been intentionally deleted.

(DRN 05-543, R14)

WSES-FSAR-UNIT-3 Revision 14 (12/05)

(DRN 05-543, R14)

Figure 15.1-75a has been intentionally deleted.

(DRN 05-543, R14)

I l o o -

s 8

I I

I 32 144 216 288 360 SECONDS REVISION 10 (10199)

LOUISIANA POWER LIGHT CO.

MAIN STEAM LINE BREAK MODES 4 Steam Figure WITH LOSS OF ACPOWER Electrical Station 15.1-76 CORE POWER VS. TIME

1600 1200 800 400 t

t 1

REVISION 10 (10199) 72 144 216 280 36G TIME, SECONDS POWER LIGHT CO.

Steam Electric Station REACTOR COOLANT SYSTEM PRESSURE VS. TIME 77 MAIN STEAM LINE BREAK MODES 3 & 4 I

WITH LOSS OF AC POWER

700 600' 200

'CORE INLETCOOLANT TEMPERATURE I

72 144 288 360

TIME, SECONDS REVISION 10 (10199)

LOUISIANA POWER LIGHT CO.

MAIN STEAM LINE BREAK MODES 3 4 WITH LOSS OF AC POWER REACTOR COOLANT TEMPERATURE VS. TIME

1 8 0 0 200 ISOLATED STEAM GENERATOR STEAM GENERATOR WITH RUPTURED LINE 72 144 216 288 36 0

TIME, SECONDS REVISION 10 (10199)

LOU POWER LIGHT CO.

Electric MAIN STEAM LINE BREAK MODES 3 4 I

WITH LOSS OF AC POWER STEAM GENERATOR PRESSURE VS. TIME

10000 800C 2000 P O W E R MAIN STEAM LINE BREAK MODES 3 i-4 WITH LOSS OF AC POWER STEAM MASS RELEASE FROM BREAK VS. TIME I

I STEAMGENERATORWITH RUPTUREDLINE ISOLATED STEAMGENERATOR I

I I

72 216 288 TIME, SECONDS REVISION

I I

I 72 144 216 288 360 TIME, SECONDS REVISION 10 (10199)

ANA MAIN STEAM LINE BREAK MODES 3 8 4 WITH LOSS OF AC POWER FEEDWATER FLOW VS. TIME

7 2 144 2 1 6 TIME, SECONDS MAIN STEAM LINE BREAK MODES 3 & 4 Figure WITH LOSS OF AC POWER FEEDWATER ENTHALPY VS. TIME REVISION 10 (10199)

300000 72 ANA MAIN STEAM LINE BREAK MODES 3 4 WITH LOSS OF AC POWER STEAM GENERATOR LIQUID INVENTORY VS. TIME Uric I

I 144 216 TIME, SECONDS 288 360 REVISION 10

3 DOPPLER SAFETY INJECTION TOTAL S -3 9

I I

I I

MODERATOR 6

-6 CEA

-9 I

I I

I 72 144 216 288 TIME, SECONDS REVISION 10 (1 MAIN STEAM LINE BREAK MODES 3 4 WITH LOSS OF AC POWER REACTIVITY VS. TIME

350000 300000 150000 100000 50000 TIME, SECONDS REVISION 10 (10199)

MAIN STEAM LINE BREAK MODES 3 8 4 WITH LOSS OF AC POWER INTEGRATED STEAM MASS RELEASE FROM BREAK VS. TIME

Revision 307 (07/13)

Waterford Steam Electric Station #3 Inside Containment Steam Line Break Pre-Trip Power Excursion Core Power vs. Time Figure 15.1-87

Revision 307 (07/13)

Waterford Steam Electric Station #3 Inside Containment Steam Line Break Pre-Trip Power Excursion Core Heat Flux vs. Time Figure 15.1-88

Revision 307 (07/13)

Waterford Steam Electric Station #3 Inside Containment Steam Line Break Pre-Trip Power Excursion Reactor Coolant System Temperatures vs. Time Figure 15.1-89

Revision 307 (07/13)

Waterford Steam Electric Station #3 Inside Containment Steam Line Break Pre-Trip Power Excursion Reactor Coolant System Pressure vs. Time Figure 15.1-90

Revision 307 (07/13)

Waterford Steam Electric Station #3 Inside Containment Steam Line Break Pre-Trip Power Excursion Reactivity vs. Time Figure 15.1-91

Revision 307 (07/13)

Waterford Steam Electric Station #3 Inside Containment Steam Line Break Pre-Trip Power Excursion Steam Generator Pressure vs. Time Figure 15.1-92

Revision 307 (07/13)

Waterford Steam Electric Station #3 Inside Containment Steam Line Break Pre-Trip Power Excursion DNBR vs. Time Figure 15.1-93

WSES-FSAR-UNIT-3 Revision 307 (07/13)

(EC-8458, R307)

Figure 15.1-94 has been Intentionally Deleted.

(EC-8458, R307)