ML23173A052

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9 to Updated Final Safety Analysis Report, Appendix J, Figures - Redacted
ML23173A052
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 04/10/2023
From:
Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML23172A253 List:
References
EPID: L-2023-LRO-0038
Download: ML23173A052 (1)


Text

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ROO DROI' ACCIDENT MAXIMUM CONTROL RDO WORTH WITH SINGLE O,ERATOft ERROR FOft VARIOUSOl'ERATING STATES AT BEGINNING OF LIFE WITH ROD SEQUENCE CONTROL SYSTEM ROO SELECTION ERROR ROD WITHDRAWAL ERROR 50% ROD DENSITY

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20 40 60 100 AVERAGE MODERATOR DENSITY lgm/ccl CORE AVERAGE POWER 11'1 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD DROP ACCIDENT MAXIMUM CONTROL ROD WORTH WITH SINGLE OPERATOR ERROR AT SOL WITH RSCS FIGURE J.4.1

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0.016 ROO OROP ACCIDENT MAX IMUM CONTROL ROD WORTH WITH SINGLE OPERATOR ERROJI FOR VARIOUS OPERATING STA TES AT THE MOST REACTIVE POINT IN CORE LIFE (8600 MWd(TI WITH ROO SEQUENCE CONTROL SYSTEM

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ROD WITHDRAWAL ERROR o.oos 50% ROD DENSITY 0 ________ ___. ______.......-............... ____..___., _

20 AVERAGE MODERATOR DENSITY (gm/eel 40 60 80 100 CORE AVERAGE POWER (%1 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD DROP ACCIDENT MAXIMUM CONTROL ROD WORTH WITH SINGLE OPERATOR ERROR AT MOST REACTIVE POINT IN CORE LIFE (6500 MWd/ T) WITH RSCS FIGURE J.4.2

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CORE DISPLAY 185 ROD POSITIONS

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PHILADELPHIA EL::~R POWER STATION BOTTOM ATO PEACH UNITS 2 AND 3 S REPORT IC COMPANY UPDATED FINAL SAFETY ANALYSI CK DIAGRAM OF SCHEMATIC BLgRE EXPOSURE RSCS F~:s~o MWd/ T FIGURE J.4.4a

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CORE DISPLAY 185 ROD POSITIONS

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SEQUENCE WITHDRAWAL/

INSERTION SELECT Al A2 81 82 TO MANUAL 1--+- CRO CONTROL SYS PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT RSCS BLOCK DIAGRAM FOR CORE EXPOSURE >6500 MWd/T FIGURE J.4.4b

Security-Related Information Withheld under 10 CFR 2.390

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Security-Related Information Withheld under 1 o CFR 2.390

Security-Related Information Withheld under 10 CFR 2.390

PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND3 UPDATED FINAL SAFETY ANALYSIS REPORT OFF-SITE EFFECT OF ROD DROP ACCIDENT FIGURE J.4.8