ML17130A233

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Peach Bottom Atomic Power Station, Units 2 & 3, 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)
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Text

) J I I STEAM BREAKS AUTOMATIC ..,.. ____________________________________ _ ! MAXIMUM STEAM t' LINE BREAK HPCI .... ___________________________ .... _____ __ I I D F ---------.----------------------------------------..... -..... __________ ..... LPCI I B I ----.------------------------------------------------...

  • t---------------------__.I CORESPRAY I I I I I I I LIQUID BREAKS I ...., _______________________ AUTOMATIC -----____ DEPRESSURIZATION RECIRCULATION LINE BREAK t-------,.* .. _--_-------_-HPCI I E c ---------... t-----------------------.. 1 LPCI A -------... -----------------------------------------------11111 t-------------------*1 CORE SPRAY I I I I I I I I 0 0.1 0.2 1.0 2.0 3.0 4.0 BREAK AREA Ctt2) SCALE CHANGES I 5.0 6.0 \ \ \ PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT CSCS'S PERFORMANCE CAPABILITY CHART FIGURE 6.3.1 PBAPS UFSAR

Figure 6.4.1 thru 6.4.2 Deleted

2500 t 2000 llDIST IllTDllEDIATE m 0 d 1500 FAILURE 1000 500 z 0 .._ u a: LLJ << LI.I ..... a: 0.2 ..J CZ: .... LU 0.1 z w u " IJJ 0-+--------------------------------------------------------'-o \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 1500 -8 a: d 1000 500 CORE REFLOODED CORE SPRAY INITIATED 0 100 200 300 'lOO 500 TJHE (SECONDS) 600 700 BOO 900 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

-u. * -z -2500 2000 CORE REFLOODED ' CORE SPRAY INITIATED 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 1500 -8 a: d 1000 500 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 -----------------.-------------------------------------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 10 I I I I I f I f f 10. ... 0 I ...= "-10 *-... d 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 10 I I I I I I I I ' -10' ... LL' 0 I .,..: 0 10 *--U> I a: 'J: ....... :::> m -u 10 1-... 'J: 10 ' -... 10 D I I ' I I I I 0 100 200 300 "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

-u.. 0 I u.. 0 Cf) I a: % ........ t-m -u t-% 10 I I t r----___ to * -.. to 1-.. 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 CORE SPRAY r 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

-... !: id > cc. .... ... > 60 so 'lO 30 20 CORE SPRAY 10 r llllTIATED 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 TIME (SECONDS) 150 200 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 s TIME (SECONDS) 10 ts 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 2000* i-0 r CORE REFLOODED -I! I!:! 0 CORE SPRAY INITIATED 5 tSOO*

  • u 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-.. -2000-.. u.. 0 r CORE REFLOODED -a: 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 .. .. -2000--u.. r CORE REFLOODED * -i: 0 CORE SPRAY INITIATED cc tSOO--_, u 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 u: 2000 °-n. s:: 0 5 1500 u a: 1000 500 CORE REFLOODED CORE SPRAY INITIATED 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 &L: 2000 * -c 5 1500 u a: H:! 1000 500 +-CORE REFLOODED CORE SPRAY INITIATED a ...... ----------------------------------------------------_.. 10 0 10' TJHE tSECIN>Sl 10. 10 I 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 IL 2000 * -11.. 2: 0 5 1500 u lt': u:. le 1000 500 CORE SPRAY INITIATED r CORE REFLOODED ' 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'--1.soo ... " ... /000 -Q Q ._J (J .soo -Q. 0 0 \:"'"" 1 L l!lllJC I 10000 FUEL BUNDLE l. PESIGN 8'9S/$ --#ICC/DENT -I 36600 20000 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 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

)-i 8 H H :::> ()I 1.0----------------..-------...... ------...-------.------.,-------..,-----....... 0.8 0.6 0.4 0.2 0 0 2 4 \ \ \ \ \ 6 8 \ CHANNEL INLET QUALITY 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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