ML17130A233

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
Issue date:	04/06/2017
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17130A259	List: ML17108A393 ML17130A208 ML17130A211 ML17130A216 ML17130A218 ML17130A220 ML17130A222 ML17130A224 ML17130A227 ML17130A231 ML17130A233 ML17130A235 ML17130A241 ML17130A245 ML17130A247 ML17130A249 ML17130A254 ML17130A256 ML17130A258 ML17130A263 ML17130A266 ML17130A268 ML17130A270 ML17130A273 ML17130A277 ML17130A279 ML17130A281 ML17130A284 ML17130A286 ML17130A288 ML17130A290 ML17130A292 ML17130A294 ML17130A301 ML17130A303 ML17130A306 ML17130A308 ML17130A310 ML17130A313 ML17130A317 ML17130A319 ML17130A321 ML17130A324 ML17130A326 ML17130A328 ML17130A330 ML17130A332 ML17130A486 ML17130A488 ML17130A493 ... further results
References
Download: ML17130A233 (35)

Text

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I STEAM BREAKS

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~-----*------DEPRESSURIZATION AUTOMATIC

!t'~ MAXIMUM STEAM LINE BREAK HPCI I

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....._ _ _ _ _ _ _ _ _ _..... LPCI D F I-t---------------------__.I

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B CORESPRAY I

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....,_______________________ AUTOMATIC I

~ - - - - - _ _ _ _ DEPRESSURIZATION '~MAXIMUMRECIRCULATION LINE BREAK t-------,.*. _--_-------_- HPCI I

---

...-----------------------------------------------------~

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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

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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

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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

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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

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z 1500

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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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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 SPRAY SYSTEMS PLUS ADS, AEC/NRC ASSUMPTIONS,

.05-SQ FT BREAK FIGURE 6. 7. 7

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to * - ..

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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

60 so Tll'

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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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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---

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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

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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 ..

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-- 1,000 MWd/T EXPOSURE, TWO CORE SPRAY SYSTEMS, AEC/NRC ASSUMPTIONS,

.05-SQ FT BREAK FIGURE 6.7.13

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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 .. .

u.. 2000-r CORE REFLOODED i:

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CORE SPRAY INITIATED 0

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..

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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

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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