ML17130A233

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Revision 26 to Updated Final Safety Analysis Report, Section 6.0, Core Standby Cooling Systems, Figures, Part 2 of 2
ML17130A233
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 04/06/2017
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17130A259 List: ... further results
References
Download: ML17130A233 (35)
v • d • e


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

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

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a:

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1000 0.2 ..J CZ:

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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 ~

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~ 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. ...

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c:r

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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 '-

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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 * - ..

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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

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~ 'lO cc.

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> 30

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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!

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1000- -

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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

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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,

.05-SQ FT BREAK FIGURE 6.7.14

2500 .. .

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cc u

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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

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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

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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

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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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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----------------..-------......------...-------.------.,-------..,-----.......

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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

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