Text

7 to Updated Final Safety Analysis Report, Chapter 6, Figures
	ML19114A141
Person / Time
Site:	Peach Bottom
Issue date:	04/08/2019
From:	; Exelon Generation Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML19114A265	List: ML19114A123; ML19114A124; ML19114A125; ML19114A126; ML19114A130; ML19114A131; ML19114A132; ML19114A133; ML19114A136; ML19114A137; ML19114A139; ML19114A140; ML19114A141; ML19114A142; ML19114A143; ML19114A144; ML19114A146; ML19114A147; ML19114A149; ML19114A150; ML19114A152; ML19114A153; ML19114A155; ML19114A156; ML19114A157; ML19114A158; ML19114A159; ML19114A161; ML19114A162; ML19114A163; ML19114A164; ML19114A165; ML19114A166; ML19114A167; ML19114A168; ML19114A170; ML19114A171; ML19114A172; ML19114A173; ML19114A175; ML19114A176; ML19114A177; ML19114A178; ML19114A179; ML19114A181; ML19114A184; ML19114A185; ML19114A186; ML19114A187; ML19114A190; ... further results
References
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PBAPS UFSAR Figure 6.4.1 thru 6.4.2 Deleted

PBAPS UFSAR PEAK CLADDING TEMPERATURE VERSUS TIME DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.1 REV. 26 04/17 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Peak Cladding Temperature, Maximum Recirculation Suction Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT WATER LEVELIN HOT AND AVERAGE CHANNEL VS.

TIME, DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.2 REV. 26 04/17 Water Level in Hot and Average Channels, Maximum Recirculation Suction Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

PBAPS UFSAR REACTOR PRESSURE VERSUS TIME DESIGN BASIS ACCIDENT BREAK FIGURE 6.5.3 REV. 26 04/17 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Reactor Vessel Pressure, Maximum Recirculation Suction Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

PBAPS UFSAR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT HEAT TRANSFER COEFFICIENTS, MAXIMUM RECIRCULATION SUCTION LINE BREAK FIGURE 6.5.4 REV. 26 04/17 Heat Transfer Coefficients, Maximum Recirculation Suction Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

PBAPS UFSAR PEAK CLADDING TEMPERATURE 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.5 REV. 26 04/17 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Peak Cladding Temperature, 0.05 ft2 Recirculation Discharge Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

PBAPS UFSAR WATER LEVEL IN HOT AND AVERAGE CHANNELS 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.6 REV. 26 04/17 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Water Level in Hot and Average Channels, 0.05 ft2 Recirculation Discharge Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

PBAPS UFSAR REACTOR VESSEL PRESSURE 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.7 REV. 26 04/17 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Reactor Vessel Pressure, 0.05 ft2 Recirculation Discharge Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

PBAPS UFSAR HEAT TRANSFER COEFFICIENTS 0.05 FT2 RECIRCULATION DISCHARGE LINE BREAK FIGURE 6.5.8 REV. 26 04/17 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT Heat Transfer Coefficients, 0.05 ft2 Recirculation Discharge Line Break, Battery Failure, EPU Power / MELLLA+ Core Flow, Appendix K Assumptions

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

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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

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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 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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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

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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

ML19114A141

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