ML23062A422

8 to Updated Final Safety Analysis Report, Appendix J, Figures J.4.1 Through J.4.8 (Redacted)

ML23062A422
Person / Time
Site:	Peach Bottom
Issue date:	03/03/2023
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML23062A422 (1)

Text

0.020 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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 0.016 ROO SELECTION ERROR I-i 8a:

_, 0 .010 0

a:

1-z 8

ROD WITHDRAWAL ERROR 0.005 50% ROD DENSITY 0

~ ~

0

~

0

~

0

~

0

~

0

e 0

0 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

0.020 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . .

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

r i - ROD SELECTION ERROR

~ 0 .010

.J 0

z 8

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

20 40 60 80 100 AVERAGE MODERATOR DENSITY (gm/eel 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

17:..

'"" Of Jut,.t..* OUt' f'Ul..i..** ..

i-T co..

~

I

• 6 \IS (TY* )

---L i .. ' ' --

,u& ... ; -. - - -- *- I (IIOU"°"" T C.0trr,TA(.T$}

1---it-,

COMPANY PHILADELPHIA EL~~R~~WER STATION TOMATO PEACH BOT UNITS 2 A~:!L YSIS REPORT UPDATED FINAL SAFETY CK DIAGRAM OF SCHEMATIC BLgRE EXPOSURE RSCS F~=s~o MWd/T

)

FIGURE J .4.3a

)

POSITION 185 ROD POSITIONS LIGHT PROBE ISOLATOR - TYP OF

& Al.ARM STATUS 185 RPI CAB i

CORE DISPLAY EE 4 ROD DISPLAY BYPASS SWITCH

• ~--Power Permissive Signal LIGHTS 185/4 APPROXIMATELY

~----..;;;;;..;;;;;..;.;..;;...;;.;;=.;..;..;.;...;...;.;.;;.;..;.;;.;.;;..;.;..;;;..;;..;.._ _ _ _---f, tr--

L_______

____LOGIC -

RSC

..,.,.--Power Alarm Signal

, - - - - - - - - - - - - - - - - - - - - - ' : i--

.-----------------......f: 1-- SEQUENCE

,, ,-------------------4: i---

1 WITHDRAWAU INSERTION SELECT 185 WIRES SELECT Al RELAY I MODULES I TO I I A2 MANUAL ~ CRD r CONTROL Bl SYS I I I I I I 82 PHILADELPHIA ELECTRIC COMPANY I

• C: PEACH aonoM ATOMIC POWER STATION t I UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD SELECT PANEL RSCS BLOCK DIAGRAM FOR CORE EXPOSURE <6500 MWd/T FIGURE J.4.3b

)

---... - ---...... IIIIOW.--TO..Ha 1~11.>H Alo.'-* IUf

~1.-,

• .:J=-c=I ~ ~

1 ...-

J

._L i .. .. I 1----,

.. ~ - 1

=r-* I ---- (.llOU ..MWT t OMTACTJ)

~:!!!..;= - - , , -~

I.I ..... .... - -~ ..

.,,.....,$). !.fW*'"':-

• • • t:e---'TTPf:

IC COMPANY PHILADELPHIA EL::~RPOWER STATION BOTTOM ATO PEACH UNITS 2 AND 3 S REPORT UPDATED FINAL SAFETY ANALYSI CK DIAGRAM OF SCHEMATIC BLgRE EXPOSURE RSCS F~:s~o MWd / T FIGURE J.4. 4 a

)

POSITION 185 ROD POSITIONS LIGHT PROBE ISOLATOR TYP OF

& ALARM STATUS 185 RPI CAB i

EE BYPASS SWITCH CORE DISPLAY 4 ROD DISPLAY

• ----Power Permissive Signal i

LOGIC-RSC

_ _ _ _ _ _L;;:,;1..;;;GH...;.T.;,.;Sc..1;;..;;8.;.:5/'-'4...;.A.;.;;.P..;..PR~OX...;.l...;.MA;;..;;T.;..;E;;;..;L;;;..;Y'-------......i' ~

- - - - - - - - - - - - - - - - - - ~ ~ !--

---

~ -:--Power Alarm Signal

- - - - - - - - - - - - - - - - ~ - . r--- SEQUENCE

---

1~ r- WITHDRAWAL/

INSERTION t ' SELECT 185 WIRES -

~

SELECT RELAY I t I Al MODULES I I TO A2 MANUAL 1--+- CRO I I I CONTROL 81 SYS I I I I I I 82 PHILADELPHIA ELECTRIC COMPANY I I PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT I

ROD SELECT PANEL RSCS BLOCK DIAGRAM FOR CORE EXPOSURE >6500 MWd/T FIGURE J.4.4b

Security Related Information Withheld under 10 CFR 2.390

)

/

) ) )

Security Related Information Withheld under 10 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