ML17130A233: Difference between revisions
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| number = ML17130A233 | | number = ML17130A233 | ||
| issue date = 04/06/2017 | | issue date = 04/06/2017 | ||
| title = | | title = Revision 26 to Updated Final Safety Analysis Report, Section 6.0, Core Standby Cooling Systems, Figures, Part 2 of 2 | ||
| author name = | | author name = | ||
| author affiliation = Exelon Generation Co, LLC | | author affiliation = Exelon Generation Co, LLC | ||
Line 13: | Line 13: | ||
| document type = Drawing, Updated Final Safety Analysis Report (UFSAR) | | document type = Drawing, Updated Final Safety Analysis Report (UFSAR) | ||
| page count = 35 | | page count = 35 | ||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:\ | |||
\ | |||
\ | |||
) | |||
I STEAM BREAKS | |||
..,.._____________________________________ I | |||
~-----*------DEPRESSURIZATION AUTOMATIC | |||
!t'~ MAXIMUM STEAM LINE BREAK HPCI I | |||
--- ------.----------------------------------------.....I | |||
....._ _ _ _ _ _ _ _ _ _..... LPCI D F I-t---------------------__.I | |||
~ | |||
B CORESPRAY I | |||
II I | |||
I I | |||
I LIQUID BREAKS I | |||
....,_______________________ AUTOMATIC I | |||
~ - - - - - _ _ _ _ DEPRESSURIZATION '~MAXIMUMRECIRCULATION LINE BREAK t-------,.*. _--_-------_- HPCI I | |||
---------...-----------------------------------------------------~ | |||
E c t-----------------------.. 1 LPCI | |||
---- - --...-----------------------------------------------11111 t-------------------* | |||
A 1 | |||
CORE SPRAY I | |||
I I I I I I I I 0 0.1 0.2 1.0 2.0 3.0 4.0 5.0 6.0 | |||
~ | |||
SCALE CHANGES BREAK AREA Ctt2) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CSCS'S PERFORMANCE J CAPABILITY CHART FIGURE 6.3.1 | |||
PBAPS UFSAR Figure 6.4.1 thru 6.4.2 Deleted | |||
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Peak Cladding Temperature, UNITS 2 AND 3 Maximum Recirculation Suction Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, PEAK CLADDING TEMPERATURE VERSUS TIME Appendix K Assumptions DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.1 REV. 26 04/17 | |||
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Water Level in Hot and Average Channels, UPDATED FINAL SAFETY ANALYSIS REPORT Maximum Recirculation Suction Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, WATER LEVELIN HOT AND AVERAGE CHANNEL VS. | |||
Appendix K Assumptions TIME, DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.2 REV. 26 04/17 | |||
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Reactor Vessel Pressure, UNITS 2 AND 3 Maximum Recirculation Suction Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, REACTOR PRESSURE VERSUS TIME Appendix K Assumptions DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.3 REV. 26 04/17 | |||
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Heat Transfer Coefficients, UNITS 2 AND 3 Maximum Recirculation Suction Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions HEAT TRANSFER COEFFICIENTS, MAXIMUM RECIRCULATION SUCTION LINE BREAK FIGURE 6.5.4 REV. 26 04/17 | |||
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Peak Cladding Temperature, UNITS 2 AND 3 0.05 ft2 Recirculation Discharge Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, PEAK CLADDING TEMPERATURE Appendix K Assumptions 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.5 REV. 26 04/17 | |||
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Water Level in Hot and Average Channels, UPDATED FINAL SAFETY ANALYSIS REPORT 0.05 ft2 Recirculation Discharge Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, WATER LEVEL IN HOT AND AVERAGE CHANNELS Appendix K Assumptions 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.6 REV. 26 04/17 | |||
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Reactor Vessel Pressure, UNITS 2 AND 3 0.05 ft2 Recirculation Discharge Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions REACTOR VESSEL PRESSURE 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.7 REV. 26 04/17 | |||
PBAPS UFSAR Heat Transfer Coefficients, PEACH BOTTOM ATOMIC POWER STATION 2 | |||
0.05 ft Recirculation Discharge Line Break, UNITS 2 AND 3 Battery Failure, EPU Power / MELLLA+ Core Flow, UPDATED FINAL SAFETY ANALYSIS REPORT Appendix K Assumptions HEAT TRANSFER COEFFICIENTS 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.8 REV. 26 04/17 | |||
PBAPS UFSAR FIGURE 6.5.9 DELETED REV. 26 04/17 | |||
PBAPS UFSAR FIGURE 6.5.10 DELETED REV. 26 04/17 | |||
PBAPS UFSAR FIGURE 6.5.11 DELETED REV. 26 04/17 | |||
PBAPS UFSAR FIGURE 6.5.12 DELETED REV. 26 04/17 | |||
2500 z | |||
0 t 2000 llDIST IllTDllEDIATE -~7 .._ | |||
u m ~ a: | |||
LLJ 0 FAILURE d 1500 ~ | |||
LI.I | |||
~ | |||
a: | |||
~ | |||
1000 0.2 ..J CZ: | |||
LU | |||
~ | |||
500 0.1 t-z w | |||
u 0-+--------------------------------------------------------'-o "~ | |||
IJJ | |||
\0 .. 10.. \0 * \0 ' | |||
BREAK AREA< SQ fTl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS BREAK AREA, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS FIGURE 6. 7 .1 | |||
2500 u: 2000 L | |||
~ CORE REFLOODED CORE SPRAY INITIATED | |||
-8 | |||
~ 1500 a: | |||
d 1000 500 0-+------------------..------.~----...---------------~--~~~ | |||
0 100 200 300 'lOO 500 600 700 BOO 900 TJHE (SECONDS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CLADDING TEMPERATURE VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .02-SQ FT BREAK FIGURE 6. 7 .2 | |||
2500 | |||
: u. 2000 CORE REFLOODED | |||
~ CORE SPRAY INITIATED ' | |||
~ | |||
z 1500 | |||
~ | |||
1000 500 0-+-----........------------------~-------------------------------.. | |||
0 100 200 soc '100 500 800 ?00 800 TJrtE CSECt'HlSl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CLADDING TEMPERATURE VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUf\;tPTIONS, .05-SQ FT BREAK FIGURE 6. 7.3 | |||
2500 r CORE REFLOODED COAE SPRAY INITIATED ~ | |||
-8 | |||
~ 1500 a: | |||
d 1000 500 0-+-~---------------------------~----~---~~~~--~~---'- | |||
10 0 10 I 10 2 10 I TJME CSECrJNOSJ PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN BASIS ACCIDENT, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS FIGURE 6.7.4 | |||
.a | |||
.2 0-1------------------.-------------------------------------P-o s 10 lS TJHE (SECONDS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CORE FLOW FOLLOWING DESIGN BASIS ACCIDENT VERSUS TIME FIGURE 6.7.5 | |||
I I I I f I f f 10 I | |||
: 10. ... | |||
~ | |||
0 I | |||
...= | |||
d 10 *- | |||
en I | |||
c:r | |||
~ | |||
....m u.... 10 J- .... | |||
~ | |||
10 ,_ ... | |||
10 0 I l I I I 1 I I 0 100 200 300 llOO 500 600 700 600 900 TIME (SECONDS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT HEAT TRANSFER COEFFICIENT VERSUS TIME, TWO CORE SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .02*SQ FT BREAK FIGURE 6. 7 .6 | |||
I I I I I I I 10 I '- | |||
10' ... | |||
LL' 0 | |||
I | |||
~ | |||
0 U> | |||
I 10 *- - | |||
a: | |||
'J: | |||
~ | |||
u m | |||
~ | |||
'J: 10 1- ... | |||
10 ' - ... | |||
10 D I I I I I 0 100 I | |||
200 300' "00 500 600 700 800 TIME(SECONOS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT HEAT TRANSFER COEFFICIENT VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, | |||
.05-SQ FT BREAK FIGURE 6. 7. 7 | |||
I t 10 I r----___ | |||
to * - .. | |||
0 u.. | |||
I | |||
~ | |||
u.. | |||
0Cf) | |||
I to 1- .. | |||
a: | |||
~ | |||
t- | |||
- m u | |||
t-to - | |||
~ | |||
2-t0 I* .. | |||
\0 D-'----------------------,-------------------.-,-------------------+- | |||
10 0 10 I 10 2 10 I TIME(SECONOS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT HEAT TRANSFER COEFFICIENT VERSUS TIME, TWO CORE SYSTEMS, AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6.7.8 | |||
60 so Tll' | |||
&: ~ ------~~---------- | |||
20 Ill' 10 r CORE SPRAY INITIATED o---------------------------------------------------------- o lOO 200 500 600 700 BOO 900 TIME(SECONOS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR PRESSURE VESSEL WATER LEVEL VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .02-SQ FT BREAK FIGURE 6. 7 .9 | |||
60 | |||
.!:-.. so id | |||
~ 'lO cc. | |||
~ | |||
> 30 | |||
~ | |||
20 10 r CORE SPRAY llllTIATED 0-+-------------...------.----------------------------------~ | |||
0 100 200 1&00 500 600 100 BOO TIME (SECONDS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH aonoM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR PRESSURE VESSEL WATER LEVEL VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .05-SQ FT BREAK FIGURE 6.7.10 | |||
60 so to--- | |||
'10 | |||
~ | |||
fAf 20 BAf 10 O+-------------...-......----------...-----------------------~-----+ | |||
0 so 100 150 200 TIME (SECONDS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR PRESSURE VESSEL WATER LEVEL VERSUS TIME, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6.7.11 | |||
3 l | |||
0-+-------------------------------------------------~--~~~._J.. | |||
0 s 10 ts TIME (SECONDS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT MINIMUM CRITICAL HEAT FLUX RATIO VERSUS TIME FOLLOWING A DESIGN BASIS ACCIDENT FIGURE 6.7.12 | |||
2500 .. | |||
* IL 0 | |||
2000* | |||
r CORE REFLOODED i-I! | |||
I!:! | |||
0 CORE SPRAY INITIATED 5u tSOO* | |||
* ll:: | |||
~ | |||
1000- - | |||
500 .. - | |||
0 I I I I I I I 0 100 200 900 '100 500 800 ?00 BOO TJHE *CSECrNlSl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS TIME, | |||
-- 1,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, | |||
.05-SQ FT BREAK FIGURE 6.7.13 | |||
I | |||
* * | |||
* I I t 2500- .. | |||
--a: | |||
0 u.. 2000-r CORE REFLOODED CORE SPRAY INITIATED | |||
~ | |||
c cc ,. | |||
--~ tSOO* | |||
u | |||
~ | |||
a: | |||
~ | |||
1000- i-500- ,. | |||
0 I I I I I I I 0 100 200 soo 'lOO 500 600 ?00 800 TJHE (SECCHJS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS TIME, 10,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, | |||
.05-SQ FT BREAK FIGURE 6.7.14 | |||
2500 .. . | |||
u.. 2000-r CORE REFLOODED i: | |||
~ | |||
CORE SPRAY INITIATED 0 | |||
cc u | |||
~ | |||
tSOO- - | |||
cc | |||
~ | |||
1000- .. | |||
soo- ... | |||
0 I I I I I I I 0 100 200 900 'lOO 500 600 ?OD 800 TJHE rSECM>Sl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS TIME, 25,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, | |||
.05-SQ FT BREAK FIGURE 6. 7.15 | |||
~ CORE REFLOODED u: 2000 | |||
°- | |||
: n. CORE SPRAY INITIATED s:: | |||
~ | |||
0 5u 1500 | |||
~ | |||
a: | |||
~ | |||
1000 500 0-+----------------------------~----~~--~~------------ 10 0 10 ' 10 I 10. | |||
TJHE f'SECrH>Sl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS TIME, 1,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6.7.16 | |||
2500 | |||
+-CORE REFLOODED | |||
&L: 2000 | |||
~ | |||
~ | |||
~ | |||
CORE SPRAY INITIATED c | |||
5u 1500 | |||
~ | |||
a: | |||
H:! | |||
1000 500 a10......0----------------------------------------------------_.. | |||
10' 10. 10 I TJHE tSECIN>Sl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS TIME, 10,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6.7.17 | |||
2500 r CORE REFLOODED IL 11.. | |||
2000 ' | |||
2: | |||
CORE SPRAY INITIATED | |||
~ | |||
0 5u 1500 lt': | |||
u:. | |||
le 1000 500 0-+------------------------------------------------------- 10 0 10 ' 10. 10. | |||
TIHE CSECfNlSJ PHILADILPHIA ILICTRIC COMPANY PIACH BOTTOM ATOMIC POWIR STATION UNITS 2 AND 3 UPDATED FINAL SAPITY ANALYSIS RIPORT PEAK CLAD TEMPERATURE VERSUS TIME, 25,000 MWd/T EXPOSURE, TWO CORESPRAY SYSTEMS,AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6. 7.18 | |||
2SOO- | |||
~ | |||
l | |||
~ 2000'- \:"'"" l. PESIGN -- | |||
8'9S/$ #ICC/DENT | |||
~ | |||
~ | |||
1 | |||
~ 1.soo ... | |||
Ll!lllJC llNTe~N'J~Dl4TE - ~GAi( | |||
~ | |||
~ | |||
~ | |||
Q /000 - | |||
Q | |||
~ | |||
._J (J | |||
~ .soo - | |||
~ | |||
Q. | |||
0 I I 0 10000 20000 36600 FUEL BUNDLE EXPOS/JR£ - MWD/r PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAPITY ANALYSIS REPORT PEAKING FACTOR STUDY, EFFECT OF EXPOSURE ON MAXIMUM CLADDING TEMPERATURE FOR PEACH BOTTOM UNITS 2 AND 3 PIGURI 6.7.18a | |||
0.001 ~-------------------------------------------------------------....i..--------------- | |||
0.06 1.0 10 100 1,000 TIME AFTER ACCIDENT (SECONDS) | |||
POWER GENERATION FOLLOWING A DESIGN BASIS LOCA ACCIDENT PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT POWER GENERATION FOLLOWING A DESIGN BASIS LOCA FIGURE 6.7.19 | |||
1.0----------------..-------......------...-------.------.,-------..,-----....... | |||
0.8 | |||
\ | |||
\ | |||
0.6 \ | |||
)-i 8 | |||
\ | |||
H \ | |||
H \ | |||
~ | |||
()I 0.4 0.2 CHANNEL INLET QUALITY 0 | |||
0 2 4 6 8 10 12 14 16 TIME AFTER ACCIDENT ... (SECONDS) | |||
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT QUALITY VERSUS TIME FOR THE DESIGN BASIS ACCIDENT FIGURE 6. 7 .20}} |
Latest revision as of 18:19, 4 February 2020
Text
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I STEAM BREAKS
..,.._____________________________________ I
~-----*------DEPRESSURIZATION AUTOMATIC
!t'~ MAXIMUM STEAM LINE BREAK HPCI I
--- ------.----------------------------------------.....I
....._ _ _ _ _ _ _ _ _ _..... LPCI D F I-t---------------------__.I
~
B CORESPRAY I
II I
I I
I LIQUID BREAKS I
....,_______________________ AUTOMATIC I
~ - - - - - _ _ _ _ DEPRESSURIZATION '~MAXIMUMRECIRCULATION LINE BREAK t-------,.*. _--_-------_- HPCI I
...-----------------------------------------------------~
E c t-----------------------.. 1 LPCI
- --...-----------------------------------------------11111 t-------------------*
A 1
I I I I I I I I 0 0.1 0.2 1.0 2.0 3.0 4.0 5.0 6.0
~
SCALE CHANGES BREAK AREA Ctt2)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CSCS'S PERFORMANCE J CAPABILITY CHART FIGURE 6.3.1
PBAPS UFSAR Figure 6.4.1 thru 6.4.2 Deleted
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Peak Cladding Temperature, UNITS 2 AND 3 Maximum Recirculation Suction Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, PEAK CLADDING TEMPERATURE VERSUS TIME Appendix K Assumptions DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.1 REV. 26 04/17
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Water Level in Hot and Average Channels, UPDATED FINAL SAFETY ANALYSIS REPORT Maximum Recirculation Suction Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, WATER LEVELIN HOT AND AVERAGE CHANNEL VS.
Appendix K Assumptions TIME, DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.2 REV. 26 04/17
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Reactor Vessel Pressure, UNITS 2 AND 3 Maximum Recirculation Suction Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, REACTOR PRESSURE VERSUS TIME Appendix K Assumptions DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.3 REV. 26 04/17
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Heat Transfer Coefficients, UNITS 2 AND 3 Maximum Recirculation Suction Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions HEAT TRANSFER COEFFICIENTS, MAXIMUM RECIRCULATION SUCTION LINE BREAK FIGURE 6.5.4 REV. 26 04/17
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Peak Cladding Temperature, UNITS 2 AND 3 0.05 ft2 Recirculation Discharge Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, PEAK CLADDING TEMPERATURE Appendix K Assumptions 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.5 REV. 26 04/17
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 Water Level in Hot and Average Channels, UPDATED FINAL SAFETY ANALYSIS REPORT 0.05 ft2 Recirculation Discharge Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, WATER LEVEL IN HOT AND AVERAGE CHANNELS Appendix K Assumptions 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.6 REV. 26 04/17
PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION Reactor Vessel Pressure, UNITS 2 AND 3 0.05 ft2 Recirculation Discharge Line Break, UPDATED FINAL SAFETY ANALYSIS REPORT Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions REACTOR VESSEL PRESSURE 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.7 REV. 26 04/17
PBAPS UFSAR Heat Transfer Coefficients, PEACH BOTTOM ATOMIC POWER STATION 2
0.05 ft Recirculation Discharge Line Break, UNITS 2 AND 3 Battery Failure, EPU Power / MELLLA+ Core Flow, UPDATED FINAL SAFETY ANALYSIS REPORT Appendix K Assumptions HEAT TRANSFER COEFFICIENTS 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.8 REV. 26 04/17
PBAPS UFSAR FIGURE 6.5.9 DELETED REV. 26 04/17
PBAPS UFSAR FIGURE 6.5.10 DELETED REV. 26 04/17
PBAPS UFSAR FIGURE 6.5.11 DELETED REV. 26 04/17
PBAPS UFSAR FIGURE 6.5.12 DELETED REV. 26 04/17
2500 z
0 t 2000 llDIST IllTDllEDIATE -~7 .._
u m ~ a:
LLJ 0 FAILURE d 1500 ~
LI.I
~
a:
~
1000 0.2 ..J CZ:
LU
~
500 0.1 t-z w
u 0-+--------------------------------------------------------'-o "~
IJJ
\0 .. 10.. \0 * \0 '
BREAK AREA< SQ fTl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS BREAK AREA, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS FIGURE 6. 7 .1
2500 u: 2000 L
~ CORE REFLOODED CORE SPRAY INITIATED
-8
~ 1500 a:
d 1000 500 0-+------------------..------.~----...---------------~--~~~
0 100 200 300 'lOO 500 600 700 BOO 900 TJHE (SECONDS)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CLADDING TEMPERATURE VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .02-SQ FT BREAK FIGURE 6. 7 .2
2500
- u. 2000 CORE REFLOODED
~ CORE SPRAY INITIATED '
~
z 1500
~
1000 500 0-+-----........------------------~-------------------------------..
0 100 200 soc '100 500 800 ?00 800 TJrtE CSECt'HlSl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CLADDING TEMPERATURE VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUf\;tPTIONS, .05-SQ FT BREAK FIGURE 6. 7.3
2500 r CORE REFLOODED COAE SPRAY INITIATED ~
-8
~ 1500 a:
d 1000 500 0-+-~---------------------------~----~---~~~~--~~---'-
10 0 10 I 10 2 10 I TJME CSECrJNOSJ PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT DESIGN BASIS ACCIDENT, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS FIGURE 6.7.4
.a
.2 0-1------------------.-------------------------------------P-o s 10 lS TJHE (SECONDS)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CORE FLOW FOLLOWING DESIGN BASIS ACCIDENT VERSUS TIME FIGURE 6.7.5
I I I I f I f f 10 I
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT HEAT TRANSFER COEFFICIENT VERSUS TIME, TWO CORE SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .02*SQ FT BREAK FIGURE 6. 7 .6
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT HEAT TRANSFER COEFFICIENT VERSUS TIME, TWO CORE SYSTEMS, AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6.7.8
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR PRESSURE VESSEL WATER LEVEL VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .02-SQ FT BREAK FIGURE 6. 7 .9
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PHILADELPHIA ELECTRIC COMPANY PEACH aonoM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR PRESSURE VESSEL WATER LEVEL VERSUS TIME, TWO CORE SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS, .05-SQ FT BREAK FIGURE 6.7.10
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR PRESSURE VESSEL WATER LEVEL VERSUS TIME, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6.7.11
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT MINIMUM CRITICAL HEAT FLUX RATIO VERSUS TIME FOLLOWING A DESIGN BASIS ACCIDENT FIGURE 6.7.12
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS TIME, 10,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS,
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TJHE f'SECrH>Sl PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PEAK CLAD TEMPERATURE VERSUS TIME, 1,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6.7.16
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TIHE CSECfNlSJ PHILADILPHIA ILICTRIC COMPANY PIACH BOTTOM ATOMIC POWIR STATION UNITS 2 AND 3 UPDATED FINAL SAPITY ANALYSIS RIPORT PEAK CLAD TEMPERATURE VERSUS TIME, 25,000 MWd/T EXPOSURE, TWO CORESPRAY SYSTEMS,AEC/NRC ASSUMPTIONS, DESIGN BASIS ACCIDENT FIGURE 6. 7.18
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POWER GENERATION FOLLOWING A DESIGN BASIS LOCA ACCIDENT PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT POWER GENERATION FOLLOWING A DESIGN BASIS LOCA FIGURE 6.7.19
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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT QUALITY VERSUS TIME FOR THE DESIGN BASIS ACCIDENT FIGURE 6. 7 .20