Text

Redacted Braidwood Station, Units 1 & 2 and Byron Station, Units 1 & 2, Revision 17 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis
	ML19170A347
Person / Time
Site:	Byron, Braidwood
Issue date:	06/20/2019
From:	Mahesh Chawla; Plant Licensing Branch III
To:	; Exelon Generation Co
	Chawla M
Shared Package
ML18355A456	List: ML19168A119; ML19168A216; ML19169A023; ML19169A113; ML19170A007; ML19170A012; ML19170A311; ML19170A336; ML19170A347; ML19170A384; ML19170A387; RS-18-144, Amendment 28 to Fire Protection Report, Chapter 4, Fire Protection Program;
References
	Download: ML19170A347 (739)
	v • d • e

B/B-UFSAR REVISION 1 - DECEMBER 1989

Attachment 15B h as been deleted intentionally.

80 70 60 30 20 560 rfl\T tpotnts: '* \ \ \ \ \ \ \

580 \ \ \ \ \ \ \ REVISION 15 DECEMBER 2014 600 620 640 660 Tavg (Deg-F) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.0-1 ILLUSTRATION OF OVERTEMPERATURE AND OVERPOWER PROTECTION 10 -9 LI.

i 8 -7 c CD i 6 8 ! 5 i !-4 3 I 2 1 REVISION 6 DECEMBER 1996 0 "-""'._...

................................................

.--...-. ...............

..-. ....................................

0 10 20 30 40 50 60 70 80 90 100 Power (Percent power) BYRON/BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 1-5.0-2 MODERATOR TEMPERATURE COEF'FICIENT USED IN ANALYSIS 0 *? 6 0 ..a I:\, '#. ::10 -12 Cl Ill -16 *18 . .. 20 0 RBVls10N *:.9* !-. DECEMaeR NOTE J .. "UPPER ClJRVE" LEAST Nt:GATlVE JlOPPLER ONLY UEf'.ECT .o.78 llj) (O TO PO'Wj:R) NOTE 2 *LEAST NEGATIVE END*OF*LIFE DOPPLER ONLY POWl!;J.lDEFECT.,.

,.0.91 llp (0 1'0 100% POWEf{} NOTE 3 * "LOWER.CURVE"MOST NJ£GAT1Vtt.bOPPLl!ilt ONLY POWER DEFECT'"' .J.6 Ap (0 TO 100% POWER) 10 20 30 40 50 60 70 80 90 100 o/o POWER BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE is.o-3 DOPPLER POWER COEFFICIENT USED IN ACCIDENT ANALYSIS

""t ... .. Q w .. >,_ _, a: U'? _,w ... ::>Cl) -L\, I-,_ 0 Cl. .. :c :c <"? fl) <( Q .. Q LI. &L. 0 ""t 0 a. .. Q. 0 e I-"": .. WO I-q 1-w .. CS! a: .... Q13. 0 QC oq wa: NO 0 -'UJ ""z "": <(_ :Ee> 0 a:w om Za. 0 0 a: Lt> Q d a: l&J * .... u. 0 <( CW) w d :& t=: -N d ... d 0 -. co ..... in * "' N ... 0 ... ... d d d 0 d d d d d U.OdHS'VO dO! O.L 3:>N'V.LSI0/03ddOYO 3:>N'V.LSIQ)

NOIJ.ISOd VOOl:f 03Zl1VWl:f0N BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15,0-4 RCCA POSITION VERSUS TIME TODASHPOT 1.0 . 0.9 0.8 % ... a: 0.7 0 I: > !:: 0.6 > ;: (,.) c( 0.5 w a: Q w 0.4 _, ct :e 0.3 a: 0 z 0.2 0.1 0 0 0.2 0.4 0.6 0.8 1.0 ROD POSITION (FRACTION INSERTED)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.0*5 NORMALIZED ROD WORTH VERSUS PERCENT INSERtED cc i 0.8 t -> -t-0.6 w cc c 8 0.4 cc Q w !::f ""' c 0.2 :& cc i 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 . TIME AFTER DROP BEGINS NORMALIZED ROD DROP TIME TIME TO TOP OF DASHPOT BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.0-6 NORMALIZED RCCABANK REACTIVITY WORTH VS. NORMALIZED DROP TIME ABBREVIATlOMS

VS'ED: AFwS ... AQXJLIARY fEE , DWA1'ER svgEM eves -* CHEMICAL.*At4o 'V , OLllME cotli'ROL.

SYSTEM ESFAS. -ENGINEERED ACTUATION SYSTEM .FW "'FEEOWATER RTS .. REACTOR. TR Ip SYSTEM SIS "" SAFETY INJECTION SYSTEM SI ** SAFETY i NJE'Cr foN '* .* RT -REACTOR tRIP CS -CONTA .SP.RAY NOTES:

-

C()RE

HL *

HOT 'LEG .CL

COLD LEG

-COMPONENT COOUNG WATER * * : svs'TEM * ** .* * * * *** RCS .. ftEAnoR COOL.A"T SY.STEM : s.Ws -SERY I CE WATER *;s_vs t b f . HP I "' HlGft PRESSURE INJtCllOH LP I .. LOW . PRESSURE ' I NJEC T lON c1 .. coNTAINMENf 1soLhi'oN ..

GENERATQR I.

INlTIAllON AHO SAFETY SYSTEM MµLTlPLE SIGNALS ARE SHOWN 'eut ONLY A s rN.Gl.E Si GNA{ : 1 s REQU I REI). THE ARE BACKUPS. . . 2. HO tJM{ffG SEQUENCE IS 8.Y POSIT OF VAR10US REFER TO EVENT '*Tl'MING SEQOENCE*s IN FORM iM PERTINENT ANALYSIS SECTION OF CHAPTER 15.0 OF THE FSAR. DIAGRAM SYMBOLS: c* )

EVENT TITLE <> ' BRANCH POINT FOR DIFFtRENT PLANt CONOITIONS I ,. -SAF.EJY SYSTEM ( ) .. SAF.ETY ACTION -SYSTEM REQUIRED TO MEET SINGLE-FAILURE CRITERIA .... -, I P I -MANUAL ACTION REQUIRED DUR I NG SYSTEM OPERATION

\.._,,, BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.0*7 . SVMEiPLS USED IN ACCiOENT SEQUENCES

..,, fTl (Tl x rrJ (") OrrJ :E (/) )> (/) -I 1--1 (Tl< :;:o rrJ (/) :::c (Tl 31: *3;: -rt> :z ()0 -IC: 1-t fTl 0 :Z...; t/) 0 ..,, 1-t G') c ;o m -(.11 CS> I CXl c "ti 0 (Tl m 0-( :::0 ..,,o -z r-CD :::0

..,, 0 0 )>0 z )> (./) (/) ..... -(1')0 z ;o (/) trj 0 :::0 ...; EXCESSIVE HEAT REMOVAL DUE TO FEEOWATER SYSTEM MALFUNCTIONS HIGH NEUTRON FLUX POWER RANGE 2/4 RTSJ. 1 ovER POWER t.T 2/4 " REACTOR TRIP BREAKERS 'Slf) " CONTROL RODS GRAVllY INSERTION PASSIVE CONTROL ROD CON1ROt. OVER TEMPERATURE AT 2/4 Sl SIGNAL STEAM GENERATOR SAFETY VALVES PASSIVE W£1Y VALVES OPEH.10 REI.ml£ . S'SEU .. PRESSURE . HIGH-HIGH SG (EVELIN ANY SG MAIN SOl.ATION/TURBINEI TRIP . . Cl.OS£ MAJN I'll' ISOLATION o;;o rrlP'J*****.

(")< :r:rl""" mO ;:oz. "°.,..... *s O')

omrowu iT 2/11 liviilffilPEiAtuat

- 6t. ' PCIWH U.llGE lllUTROil . i' ,, , ' I 'liUctciii . TitiP

-;. , , v FJ '"' ciili1iloL liallil ** q*'Y 1rv

l'AIStn .PASSIVE ,$.WJ'f l/Al.VES . Of.'Et:I TC), RELIEVE. <RCS PRESSURE 1. 1 il1s 01loalM to*oŽ MAliUAL AllUUTOidTIC COllTIOL llOiiU. . . 2. roil r-u**tllT.

.. OTlCTiOll SYlfbl FililCTIOllS ARE AllUMEO To 1.£ OPEmlYI. liit .. HACTOR TR IP I I !lot Emmo.

T .. * . **. CitNEAATQR

.SAFEN. 'ff;.l..VES . ..

SAFEf'fVALV£S

- - ..

PEN TO A£m:v£ S£CONOAR'f SYSTEM PRESSURE . . . . . . BYR()N/lflAIQW()OD STATIONS . UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.0*9 EXCESSIVE LOAD INCREASE y,;N ... ;1 ... i I Ii .. ;; i ;;; .. ':°' 11 .. ..... "' Ya** ... =-*

'-'!i' * * .*,. ' ji.; §1!1' '.;J ...

... *;*.** a!l1 """""'

I *1s"'l1 S .. li::* ....... * *.. :a: ...*. 1'l .... * ** *.* ........ . .. .. . , .. ! 1""w"' i:: 1.** .. * ...*.* :::* .. *$.**.ii 1it 1 .. S 11 ts 6 1alii 1!.* §c:!atltl!:e EIYAC)N/BRAIDWOOD .

UPDATEO FINAL SAFETY ANALVSISREP08T FIGURE 15.0"'10 DEPAESSURf%ATjON OF MAIN STEAM SYSTEM

.HIGH . PtUSUI IZ £Ii PAISSUAE ovfrllNPliOiJRE t.T RYS tEACTOI UIP e*mt*s .. ,,. ts r\ *conm 'i>>s . GRAVllY . . .INSlRTION PASSIVE. CONTROL ROD REACTIVITY pil£sluilim suin P&SSIYl SUETT OPEli m IJVE Res. mssuu RE\/lStQN . 11 DECEMBER 2006 . : lflAM GUE UT.QA YA.LYES PlSSln SAfrtY OPhTO *wm StSUli Patssuu

BYRON/BRAIDWOOD STAnONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.0*11 LOSS OF EXTERNAL LOAD s .. ..; ! ! I!. ... !.., .. ; .. ; :: ...... " t=; .. .,,._,, "" .... ' "'"!.-R*.E*.*.*v**.*.IS*s*r*

.a ...... N*****. 1*.**1*

2006 IYRON/BftAIDWOOD STA 110NS UPDATED ANALYSIS R90ftt. FIGURE 15.0-12 LOSS OF OFFSITE POWER TO STATION AUXILLi\AIES

"' ... i .. i ... :::! .ii .,; * -12 B en . -I a ""' -... w ...... 1 .. -._, -.. . .. .. e: !E . i5g REVISION 11 PECE:MaE:R 200.P BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFm ANALYSIS REPORT FfGURE 15.0*13 LOSS OF NORMAL FEEDWATER

.. N' *s !

UPDATED FINAL SAFm AHALYSJS REPORT *: ,**---*; ,_ ..

FIGURE 15.0-14 .

OF A MAlN , FEt:DWATER LINE

0 0 ;::::! ..., >.,, ...... o-.,>o ooze o :;oo ::o

1"11 z 0 n ...... ........ 0{Jl ...,, ::0 r rrt "'O I ..... ::EO-iUl dfTlo :::o, 0 c -u 0 2/3 lOW RCS now IN. 274 LOOPS

...,, ::0 ..... 0 Zz f!ri:J >,.... .,,0

>o zO > (,/)

(/) ....... ..........

<no z ::0 (J) f'T1 ,, 0 RE"ACTOR lRIP* BREAKERS CONTROL RODS GRAVITY INSERTION PASSIVE CCNJRQl. llOO REM:IMlY CONnlOl LOSS OF FORCED* REACTOR COOLANT FlO' .NO PROTECno:

REQUIRED p, STEAM GENERATOR SAFETY VALVES PASSM: SAfEIY v..._YES DPfH 1D llEU£VE SElXllilWn' S'ISIBI PR£5SUllE P7 UNDER FREQUENCY 2}4 .REACTOR TRIP BREAKERS CONTROL *ROos GRAYm INSERTION PASSIVE COtmilX. -R£ACl1VIrr CCN1lml. S1EAM GENERATOR SAFETY VALVES PASS'iVE OPDflO 0:::0 f'l'll;-J mo csi-$ O)'.

LOW .RCS .FLOW 2/3 lN ONE LOOP REACTOR TRIP BREAKERS CONTROL RODS GRAVITY INSERTION PASSIVE CONTROL ROD R£ACTIVlTY CONTROL REVISloN 11 DECEMBER 2006 REACTOR COOLANT PUMP SHAFT SEIZURE {l..OCKED ROTOR) (FULL POWER) RESSURIZER SAFETY VALVES PASSIVE SAFETY VALVES OPEN TO RELIEVE RCS PRESSURE stEAM GENERAfdR SAFFJ'Y VALVES PASSIVE SAFETY VALVES OPEN TO .RELIEVE SECONDARY SYSTEM PRESSURE BYRON/BRAIDWOOD STATIONS UPDATE FINAL SAFElY ANALYSIS REPORT FIGURE 15.0-15b REACTOR COOLANT PUMP SHAFT SELlURE (LOCKED ROTOR) 8 l:;z cn-t m :JJ S:*O UJF ,...r--<m CDC "o :en _r-: 5!i o-1 :um >;g l8 r-"Tl i5 c :u m -OI 0 . ..& Cl) SIUKE-RbGE Rl&I llf.OTllOI FlUI. I /Z PafEll IAl&E lllGll IEUllOll FWI. Ullf. 2/'1 c: g nlm a< ,.:a -0 zz r-CD :a C'I>> 1:i6 rn=: -c> UJ::! (iO z: ,. 0 ::u -ti REACTOR. TRIP .Sl'STOf '1' 's * ' ' I IHCTDR Jiii' m*lm ... ls r* ' CGllHll llGO$ Gllltlif US[HIClll PISSIYE COIHROL ROii IOCOVllf COllllOl.

IJUUTIGLLEO Ila> cwSTEI CGllHL &SS0181.Y 1111 wnllilltu&t. . SlllCIU I IC&l 1'11£SSUl1l£1 WHY IJLW£S P&SSIWE S&Ftn 'fauu mu ro 1tu£;£ lC$ PIEsSulf * " PCllffl SIG StFHT VALY£S P&SSl'IE 2/4 . "9u 11111&1 **Gil llEUHm Fl.Ill l/. Of11TtMP£UTOU 41r ll* IUGR NtSSUllltl PIESSUll IElCTOI. ...... sYSmt 'f*' u f*' '-. I tttr*. at.uas. **-*** . GRIJIIY Comal PUS.1'1£ c01tloL RGO REKTIJllY C*TIOl 0::0 CDo m :;oZ ...... (SI $ C>

MANUAL REACTOR.TRIP DROPPED ROD CLUSTER CONTROL ASSEMBLY ** BY PROCEDURE REACTOR. TRIP BREAKERS t ' l S F t ' , CONTROL RODS GRAVITY IHSERTIOH PASSIVE CONTROL ROD REACTIVITY CONTROL RESSURIZEA . SAf'ElY VALVES PASSIYE SNEIY VALVES .. OPEN ro REUE.Vt RCS PilESSllRt SttAM GENERATOR SAFETY VAl.VES PASSIVE .* .. ... . SAFETY . ......... *. . OPEN TO REUtllt SECONDAAY' . SYS'(tll

TRIP SEQUENCE OCCURS ONLY IF BY PROCEDURE, IF AN ENTIRE RCCA BANK DROPS, FOR OTHER ROD WORTH, OR FOR MISALIGNMENT, NO AUTOMATIC PROTECTION REQUIRED.

BYRONISRAIDWOOO STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 1s.o.17 DROPPED ROD CLUSTER CONTROL ASSEMBLY OVERTEMPERATURE AT SINGLE ROD CLUSTER CONTROL ASSEM8lY * .WrrHoRAWA

.L it FULL.* POWE*f * ** RE.ACTOR TRIP SYSTEM i' ' I S F I ' I REACTOR TRIP BREAKERS i' ' f S F I '-I CONTROL RODS GRAVITY PASSIVE CONT:lOL ROD REACTIVITY CONTROL BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANAL VSIS REPORT FIGU.RE 15.0*18 SINGLE ROD CLUSTER CONTROL ASSEMBLY WITHDRAWAL AT FULL POWER B/B-UFSAR Figure 15.0-19 has been deleted intentionally.

REVISION 5 -DECEMBER 1994 BYRON/BRAIDWOOD STATIONS . UPDATED FINAL SAFETY ANAL VSIS REPORT FIGURe 1$.0*20 BORON DILUTION ii :I *I'. . I I I Ii: .. i ! I :;

BYRON/BftAIPWOOD STATIONS UPDATED FIN4L. SAFETY ANALYSIS RJPOAT FIGURE 15.0*21 RUPTURE OF CONTROL AOP DRIVE MECHANISM HOUSING BYRON/B8AIDWOQ[) . STATIONS UPOA1E FINAL SAFETY ANALYSIS REPORT FIGURE 15.0-22' INA.DVERTENT ECCS OPERATION AT POWER OYERTEMPERATURE 4T 2/11 R:EVISlON 1* 1 2006 ACCIDENTAL DEPlfESSURllATION OF REACtOR *coot.AMT SYSTEM ,;., ....... * ....... * ... , , ,,,*.,:.-.*

.. ,._ -.... *, .. * .. *,_. FULL PoWER PRUSUR IZER 2/4 RTS POWER > P7 , ' IS F I ' , REA.CTOR TRIP BREAKERS ' f S F ' ' ' CONTROL ROOS GRAVITY IMSERTIOM PASS IV£ CONTROL ROD REACTIVITY CONTROL BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE ACCIDENTAL DEPRESSURIZATfON OF REACTOR COOLANT SYSTEM

I; u ft I 1 11 ff I U

11 i . fl I !I ti 1,* i't *1 ti ii J.,* h It Ii ul I{ I, Ill

I I SYRON/BRAIOWOOD STATIONS UPOATEO F'rNAL SAFETY ANALYSIS REPORT FIGURE 15.0-24 STEAM GENERATOR TUBE RUPTURE LOW PlR PRESSURE 5 II) IJ) I .... 0 .... .,, (/) C'> l !!:: c O)> ::0 Or ITI or

-UI z::o & . , ..., 0 UI n Q .... 0 Pl CONTROi. ROD GRAVITY INSERTION PASSIVE c: 1J "-I .,, ::0 .... o 0 :>0 .... .....

OU> ..., ,, 0 --.--litM:IMlY*

OlltlltOI.

HI-3 CNl.IT (2 PRESSURE LOW PlR PRESS!m£ MAIN fW ISOLAnON OPERATOR ...__...,.

_ _. ComROLS SG l£olEL. --N.. ESFAS (Sl SlCHAI.)

sws sr.m:W5 --S8lOCA 1PERATOR (CI-PHASE A) OPERATOR (CS) HI-3 CHUT PRES. (2/4) LO-LO RWST l.&EL (2/4 -AFTER 6 HRS; COfllt CGDIJlll DECEMBER 2006 WEIYY,llol.WS . Gl'Df ltJ ltEllM *--.: Sl$]Dl*l'llE5$llli£.

OPERATOR ACTION INCLUDES VALVE Al.IGNMENT AND PUMP CONTROL REQUIRED FOR RECIRCULATION.

FOOTNOTE:

SEE TABLE 7.5-1 FOR INDICATORS AND RECORDERS AVAILABLE TO THE OPERATOR FOi.LOWING E.VENT

5 (/J (/) I ...., 0 -0 c :;o OC> 1"1. QM -Ul isl I (.;" N Ul 0 17 -0 P1 c"'O CJ ?;j ""m 0-< zZ 0 >0 z -o U>z :;o Ill .... "'O 0 ::0 -I _,,.,,,. --Ol'ERA10R COHlROl.S SG l.E.VEL. -.._ -*--..mm=. L8LOCA A) -UH..O .. lftiSr 1.£11£1..

AFTER cm*aiiue

OPERATOR ACTION. INCLUOES VALVE ALIGNMENT AND PUMP CONTROL REQUIRED FOR RECIRCULATION.

CONfAIHWENt c:oowc SYSJEM ..

.. OPERATOR ALIGNS SPRAY PUMP SUCTION FOR RECIRCULATION c:oNWNuENr SPRAY' S'IS1EM (JM1.)

SPRAY S'rSJEM . (liB:JRC,)

.r. aaa:..as. _ .. , , __ , __ . -': TO CONTAINMENT RECIRCULATION SUMPS

ON l.O'-'LO RWST l..£VEI..

Al.ARM. ;. F001N01£:

sEE TABLE 7.S""'."1 FoR. INDICATORS

AND RECORDERs AVAltABLE TO lHE OPERATOR F:OUOWINC;*EVENf. .. .& "

w 2300 -0:::: 2200. (/) U1 UJ 2100 a::: a.....--..

a::: . 2000 ,_ LLJ o_ ,.

1900 ' ... a:: :::::> 1800 (./) (/) 1700 w 0.... 1600 0 50 100 TIME (SECONDS) 100 TIME (SECONDS) 150 150 REVISION 15 DECEMBER 2014 200 200 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-10 NUCLEAR POWER TRANSIENT PRESSURIZER PRESSURE TRANSIENT FOR FEEDWATER TEMPERATURE REDUCTION

' 0 50 100 TIME (SECONDS)

' 150 REVISION 15 DECEMBER 2014 I I ; 200 w a:: =::i .... 590"':> .. , M: sso----, "C:" 570--LiJ.!!...-

.... 550-Ct: ,: \ 550-': ------------* ------*-540""

-*-* 0 -(_) 530 , I 1 l ' 1 I I I I ' , * -6 5 Ct:: 4 co :z Cl 3 0 50 100 150 200 TIME (SECONDS) 1.,._ __ ....._ __ _.... _________

...._ ________________

,__ ___ -'-_______ _,. 0 50 100 TIME (SECONDS) 150 200 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -1 b REACTOR COOLANT LOOP flT TRANSIENT CORE AVERAGE TEMPERATURE TRANSIENT AND DNBR TRANSIENT FOR FEEDWATER TEMPERATURE REDUCTION 0-4-.... 0.2--* -t 0 ' 0 50 2300 ,_ . ' 100 TIME (SECONDS) 150 . REVISION 15 DECEMBER 2014 I 200 1100 ......

.........

0 50 100 TIME (SECONDS) 150 200 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-20 NUCLEAR POWER TRANSIENT PRESSIRIZER PRESURE TRANSIENT FOR FEEDWATER CONTROL VALVE MALFUNCTION REVISION 1 5 DECEMBER 2014 80---------------------------------------------. _____ , ___ .. , 1 00->---I i WL-\ 40* 1 a.... \ 0 g 200 w soo----------------------------------------------

0::: .. ::::> < 590-ffi .:* ---------§g 5ao----,\ t:= 'G:' : 570-.. : I, a:: 550-. '-*-, *,, . ..........

- - .. .. ** .. --****-"* .. ***-*-*-*----*-*---*---.. *-550< w a::: 0 u 540-+-_.,__.._..._......_._, ----...i'-"--..--.'""-

' --i..*----.----..:.._...----., 0 50 100 150 TIME (SECONDS) 200

____

0 50 100 TIME {SECONDS) 150 200 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-2b REACTOR COOLANT LOOP DELTA T TRANSIENT CORE AVERAGE TEMPERATURE TRANSIENT AND DNBR TRANSIENT FOR FEEDWATER CONTROL VALVE MALFUNCTION 1.2 ,,........

0 a:: c w*-*. 0.8'"' ... 00 0..Z ..* O! ....... 0.6-::-l5 U+:i 0.4 ... :::> 0 z2 LL.. 0.2-... """"' 0 ' 0 2500 LU a:: 2400 =:. (/) Ul 2300 w a.a 2200 -a:: .iii 2100 0:: 2000 tn .. ff] ** , . ., '" a:: 1900 a... 1800 0 w 1200 ::) _. 1 100 Ct: w 1000 3:!3 900 w N 0:: ::::> 800 en Ul w a:: a.. 700 0 ' J I . . 100 200 100 200 , 100 200 REVISION 15 DECEMBER I I I ** . ' TIME 400 500 600 TIME (affioNDS) 400 500 60 0 TIME 400 500 600 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-3 TEN PERCENT STEP LOAD INCREASE MINIMUM REACTIVITY FEEDBACK MANUAL REACTOR CONTROL 2014 REVISION 15 DECEMBER 2014 610 600 f5 a... 590 W'C" IU w w 570 a::: 0 (..) 560

_________

,._ ________

__ .........

________ 0 120 J 2.a--2.6 .. 2 ....... m z.i--z Q 2 # LB--:-l.6-"' 1.4 I l 0 1 00 240 360 480 600 TIME (SECONDS) f ' I . ' . . I I 200 300 400 500 000 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -4 TEN PERCENT STEP LOAD INCREASE MINIMUM REACTIVITY FEEDBACK MANUAL REACTOR CONTROL 1.2 ,........, 1 c Ct: c: o.s 00 a..Z o.s _, 0 (.J!;j 0.4 ' :::> 0 ze ., 0.2 0 0 2500 : w .* tt 2400-:-::l (/) Ul w 0:: a."O 2200-.... 0::. *-w Ul N8 210Q--er: ;::) 2000-.: Ul (f) w ,... er: 1900"'"" 0... 1800 w 1200 3 0 !100 > 0:: UJ .........

\000 N 900 a= -* 0 ::l .. ei 800 .. Lt.J 0:: 50 100 l\ME

' t t I

I I 50 100 TIME 200 25(} I I . . 200 250 ' REVISION 15 DECEMBER 2014 300 . 300 100-+--------""f-------....,_----

__ ...,..._ ______ -t-______ _.,_ _______ 0 t oo TIME 200 250 300 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-5 TEN PERCENT STEP LOAD INCREASE MAXIMUM REACTIVITY FEEDBACK MANUAL REACTOR CONTROL REVISION 15 DECEMBER 2014 s20-,-. -------------------------

w c:: ::J w wh:' 590--

t-I LLJ 0\ (!) Q) w 570--a:: 0 (..)

550 I t *

I I . . . . 0 50 100 150 200 250 300 TIME (SECONDS) 3.......--------------------------------------------------

a::

0 50 !00 150 200 300 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -6 TEN PERCENT STEP LOAD INCREASE MAXIMUM REACTIVITY FEEDBACK MANUAL REACTOR CONTROL REVISION 15 DECEMBER 2014 t1--------------------------

-*-.....-:*--*--*--+:--------1 O 50 lOO TIME 200 LIJ 2400 (fJ f.:.1 2300 0..0 2200 ffi 'iii 2100 0:: 2000 (/} LU g: 1900 w 3 Q:; 1.cJ 1800 1200 1100 0 1000 -

w 900 N a;: 800 (/) 1.cJ er:: i i : 50 100 TrME 200 700.,._ ______ ....._ ______ ..._ ______ ........., ______ -+-______ _,._ ______ ..,. 0 50 too TIME 200 250 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -7 TEN PERCENT STEP LOAD INCREASE MINIMUM REACTIVITY FEEDBACK AUTOMATIC REACTOR CONTROL REVISION 15 DECEMBER 2014

________________________________________

,,_, 550_..,_ __ __..._._...,!_....

__ .......

0 50 100 150 200 250 300 TIME (SECONDS)

Q:'.* m z 2 o, t5 \-+-__._...

__ .,._ _______ ..,._ _______

.........

0 50 fOO ?50 200 250 300 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -8 TEN PERCENT STEP LOAD INCREASE MINIMUM REACTIVITY FEEDBACK AUTOMATIC REACTOR CONTROL 1.2 -c-c 0:::, c: (t8 oo o...Z 0::: ...... 0.6 0.4 U:p :::-0 :;ze LL 0.2 '-"' 0 0 2500 w 0::: 2400 =i 2300 LtJ 0:: "' o...-2200 ffi 2100 a::: ::::> 2000* U1 tn w a:: \900 a.. 1800 0 w 1200 3 1100--moo-= <..-... . U..I 900"' -N Lr => .* m soo--w er ... 0.. 700 0 50 100 100

I I f 50 100 REVISION 15 DECEMBER 2014 TIME 200 250 300 TlME 200 250 300 f I f . . ' TIME 200 250 JOO BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-9 TEN PERCENT STEP LOAD INCREASE MAXIMUM REACTIVITY FEEDBACK AUTOMATIC REACTOR CONTROL REVISION 15 DECEMBER 2014 610 y--.__ _________________________________________ a{L' 590 ..._ I La.I if 3( w 570 a: 0 <..> 560 550....,_

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BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -10 TEN PERCENT STEP LOAD INCREASE MAXIMUM REACTIVITY FEEDBACK AUTOMATIC REACTOR CONTROL

...__, '-0 ........, <..> c: 0 0 .u 0.. :t=; :s ::E 1.04 1.03 1.02 1.01 1 . 0.99 -0.98 100 REVISION 15 DECEMBER 2014 200 300 400 500 600 Coolant Average T emperoture ( deg-F) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -11 KEFF VS COOLANT AVERAGE TEMPERATURE B/B-UFSAR Figure 15.1-lla has been deleted intentionally.

REVISION 10 -DECEMBER 2004 B/B-UFSAR Figures 15.1-12 and 15.1-13 have been deleted intentionally. REVISION 7 -DECEMBER 1998 REVISION 15 DECEMBER 2014 u 0. '-""' 0 0 10 20 30 40 50 Core Power (%) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -1 4 DOPPLER POWER FEEDBACK B/B-UFSAR Figures 15.1-14a through 15.1-***17 have been deleted intentionally. REVISION 7 -DECEMBER 1998 2 Ci 0 z 0 0.15 c. .Q u 0 0.1 Lt: .._.. x j o.SE-01 u t:' I jsso :!:? 500 3 0 8.450 QJ eJSO cu JOO 50 JOO Time (seconds) 158 200 REVISION 15 DECEMBER 2014 8 0 50 foul ltd Loop ----* Intact I.oops o.8 *i :z °" "'a c: 0 e (;: 0.2 e too Time (seconds)

! 9...-----------------------------.

0 50 100 Time (seconds) 150 200 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-18 1 .4 FT 2 STEAMLINE BREAK OFFSITE POWER AVAILABLE UNIT 2 0 0 50 100 Time (seconds) 150 REVISION 15 DECEMBER 2014 200 o ...... --_.... ....... .__ __ ......------------r------------------------1 0 50 100 Time (seconds) 150 200 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-19 1.4 FT 2 STEAMLINE BREAK OFFSITE POWER AVAILABLE UNIT 2 c:: 0 :.;::; 0 ....., c: Q) CJ c: 0 u c: e 0 CD -E u 0.. ..__,, .c;.. *s; :;J (,.) 0 (I) et::: 0 JOO() 2000 1000 0 -1000 -2000 -3000 50 .. .. 0 50 100 Time (seconds) 100 Time {seconds) l5D 150 REVISION 15 DECEMBER 2014 200 200 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-20 1.4 FT 2 STEAMLINE BREAK OFFSITE POWER AVAILABLE UNIT 2

Figures 15.1-21 through 15.1-26 have been deleted intentionally. REVISION 7 -DECEMBER 1998

_....., 0 c: .E 0 z ...._ 0 .--.. 0 c: .E 0 z 0 c: 0 :.;:::; <..> 0 -l..L. -x :=J G: ....... 0 QJ :c 1.4 1..2 REVISION 15 DECEMBER 2014 Q .......

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_____ ._.. __ ........ ____ 0 5 1.4 1.2 o.a 06 o.4 0.2 0 0 5 w 15 Time (Seconds) 25 10 15 Time (Seconds) 20 25 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-27 STEAM SYSTEM PIPING FAILURE AT FULL POWER -0.95 FT 2 BREAK UNIT 1 2D --.E 2200 fl) Q.. _..... Ql -2100 fl) Q,) -a.. 0 5 5 10 15 20 Time (Seconds) 10 15 20 Time (Seconds) 25 REVISION 15 DECEMBER 2014 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.1-28 STEAM SYSTEM PIPING FAILURE AT FULL POWER -0.95 FT 2 BREAK UNIT 1

--. LI.. O'\ Q) 0 ...........

e ::t -E Q) c.. E Q) ..,.._ Q) 0\ 0 -l 4.> .._ 0 (._) 600 520 500 0 5 10 15 20 Time (Seconds)

REVISION 15 DECEMBER 2014 ---foul led SG -----totoc:C SC --.. 0 *u; a.. -Q.) .._ ::t en UJ Q) -0.. e 2 '--' (.f) 1000 950 900 800 150 700....___...

__ ..._.,,___.___.._._

______ ..,_ ____ .._.. __ __. __ ....... __. __ .........,.

0 5 10 t5 20 Time (Seconds) 25 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15. 1 -29 STEAM SYSTEM PIPING FAILURE AT FULL POWER -0.95 FT 2 BREAK UNIT 1 B/B-UFSAR Figures 15.1 30 through 15.1 32 have been deleted intentionally.

REVISION 7 -DECEMBER 1998

,..... 0 fi a,.Z ol e. \.Z 1 .8 .6 A .2 0 20 --* RCP OuUel Pressure Pnsnurizer Pressatt .co 60 TIME (SECONDS) 80 REVISION 15 DECEMBER 2014 100 2800...--------------------------------------------2600 t: 2CXJO 1800-+-______ _..,._...._..

___ --t _________

.,._ ______ _..., ____ _.... ___ 40 . 80 . 11.£ (SECQNOS)

L&J-22 11DJ-.---------------------------------------------110> 1400 P.irA 12t0 Bo* a::: 1000

a..-. 40 60 80 100 11t.£ (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-1 LOSS OF LOAD/TURBINE TRIP UNIT 1 -RCS PRESSURE CASE 0.8 -c g .... 0.6 CJ 0 0.... lo.. 0 D.4 Q) u ::I z 0.2 0 0 20 40 2500 ,..........

2400 c *u; ..e 2300 d> ""' ::;, U'J 2200 Cl) Q.l .... o_ i; 2100 N *c: ::i Ul 2000 In Cl> d: 1900 1800 0 20 40 1500 g 1400 QJ E ::;, g (5 1200 0 3:: uoo .... O,.l N *c 1000 ::i t/'J en e a.. 900 000 Q 20 40 60 Ttme (s) 60 Time {s) 5G T\me {s) 80 100 120 80 100 120 8(1 100 120 BYRON/BRA!

DWOOD REVISION 15 DECEMBER 2014 STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-10 LOSS OF LOAD/TURBINE TRIP UNIT 1 -MSS PRESSURE CASE REVISION 15 DECEMBER 2014 540 530..._...._...__._.,._

______ __..., ____

20 l1ME (SECONDS) l;! I :

., ik : 570 m :....._ _______ ..,._ _______ -t-_______ _..... ______ ---t..,._

____ --.. 40 60 BO TIME (SECONOS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-2 LOSS OF LOAD/TURBINE TRIP UNIT 1 -RCS PRESSURE CASE

---Tio Tov9 ,,.-......

Li-620 ' ar s10 "'O -E ..z 600 / 0 """" Q) 0... E 590 °§580 0 0 '-' VJ 570 2E ,, \ I \ I I \ ' \ \ \ .. ._,,..,....

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REVISION 15 DECEMBER 2014 560*..,._..._

_______________________________________

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______ _,. 0 20 60 Time (s) 100 120 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-20 LOSS OF LOAD/TURBINE TRIP UNIT 1 -MSS PRESSURE CASE 0.8 ...........

c:: ..... Q.6 cu 0.. 0 0.4 cu u :::I z 0.2 0 0 20 2500 e ::> 2 Cl.. li; 21 N *c :::I 2000 Q) 0: 1900 1800 0 20 1700 g 1600 E ,soo . '::l 0 :: 1400 cu 0 := 1300 ..... tU N "§ 1200 Ul C/'l Cl.. 1100 1000 0 20 40 40 40 60 Time (s) 60 Time {s) 00 Time (s) 80 100 100 00 100 120 120 120 REVISION 15 DECEMBER 2014 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-3 LOSS OF LOAD/TURBINE TRIP UNIT 1 -DNB CASE

---Tin -----Tovg -u... 2' 610 ' "'O -,,. \ I \ I \

,' \ ,B I ' e . / ' cu 590 .. a_ E

-...... ________ ..,._ REVISION 15 DECEMBER 2014 550....-.............

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.........

.................

...._.___.

.......

0 20 -60 Time (s) 100 120 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-4 LOSS OF LOAD/TURBINE TRIP UNIT 1 -DNB CASE 1.2 D ' c: . I 11..Z r .& zf .4 .2 b 0 2100 fl 2&00 D: :t eI uoo 2200 Q,. ...... .,., 2800 u QC 1800 ..........

2"" 1800 1&00 z

"'w 1'00 .j 1200 w NC iiiE 1000 ::lO 133 800 CL-0 20 RCP Outfet Pre111Jre Prenurizer Prnsure 21 0 20 40 60 ID REVISION 15 DECEMBER 2014 IOO TIME (SECONDS)

--

.............. ..... 40 60 80 t 0 TIME (SECONDS) 40 60 80 too TIM£ (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-5 LOSS OF LOAD/TURBINE TRIP RCS PRESSURE CASE UNIT 2 o.a ...........

c: ..£ -..... 0.6 Q.) ir; 0 a.. 0 0.4 IU u ::J :z 0-2 0 0 20 2500 ' 2400 --... 0 2l00 Q,) 5 2200 VJ Cl) ct 2100 .. q) 2000 -::l en fil 1900 . L. CL t800 1700 0 20 -g cu 1400 E :::> 0 ::> '--2 1200 :; 1000 (I) en QJ 0.. eoo 0 20 4{J -40 "° 60 Time (s) 60 Time (s) 60 Time {s) 8C 100 80 100 80 100 120 120 120 REVISION 15 DECEMBER 2014 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-50 LOSS OF LOAD/TURBINE TRIP UNIT 2 -MSS PRESSURE CASE

.... 120 8¥ ::> a 610 a. IOO :&,,,,.., wL&. 590 t-b S!. 580 a; 570 .;.;, 510 = 550 5 no 110 "" a.. 600 wl 590 c°' 580 w-570 _, 560 w en 550 U) !::! w a:: UOD ::J ti 1.300 IL 1200 ai:.-. es 1100 .... -IOOO 900 ::& :i 800 f;; 0 20 0 20 .. 0 20 40 60 TIME (SECONDS) 4' 0 6G TIME (SECONDS)

,0 60 TIME (SECONDS) 10 BO ao REVISION 15 DECEMBER 2014 100 100 110 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-6 LOSS OF LOAD/TURBINE TRIP RCS PRESSURE CASE UNIT 2

---1;f'! Ta v 9 REVISION 15 DECEMBER 2014

-Li... en -8 610 -....... c:: 580 0 0 0 u 570 c.n u a:::: 560 0 1350 -0 tlOO *u; 0.. -f:! l2SO ::i en VJ E !200 ' a. ...... 0 ,.._J e 1150 Q.) c:: QJ (.,!) 1100 E 0 (\) \050 V1 1000 0 I ' I \ I \ \ \ \ ' \ ' 20 40 ............

__ ..__.._,_...., __ _ 60 Time (s) 60 lime (s) BO 80 100 \20 \(JO 120 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-60 LOSS OF LOAD/TURBINE TRIP UNIT 2 -MSS PRESSURE CASE 0.8 ...-c:; Q; Q.6 :&\: 0 a... .... 0.4 0 Q,) u :z 0.2 0 0 2500 . Q) $ 2 cu "-CL a:; 2100 .!::!! 21XXJ c;i '-CL IQOO 1800 0 1700 1600 . ...__ QJ 1500 E =i g 1400 L... ..s 0 3C 1300 L... OJ N 'c:: t200 . :::i tl'I U1 cu ct 1100 1000 D 40 20 40 20 40 60 Time (s) 60 Time (s) 60 Time (s) 80 100 Ir) 100 30 100 120 120 120 REVISION 15 DECEMBER 2014 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-7 LOSS OF LOAD/TURBINE TRIP UNIT 2 -DNB CASE

---t*n -----T ov9 REVISION 15 DECEMBER 2014

,, I \. I \ I \ \ I \ I \ B I 0 .. / '-590 *-E 580 . -c: .. 0 0 570. 0 u 0:::

........

____ ......._ ...................

__. ....... -t CD z 0 0 60 Time {s) 100 1.20 2 0...-------..-------

........

__ __._,, ____ ____ 0 60 Time (s) 80 100 120 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-8 LOSS OF LOAD/TURBINE TRIP UNIT 2 -DNB CASE B/B-UFSAR Figure 15.2-9 has been deleted intentionally.

REVISION 16 -DECEMBER 2016 2800 :i ! 2600 :::> 2400 ffi a: a.. 2200 a: 2000 ::> "' f.3 0:: 1800 El. 1600 G 10 2000 ::i 1800 tJ --w 1600 :E 3 1400 1200 a: w 1000 I-800 a:: w 600 tl! a:: ::;, 400 Cl.I ti.I w 200 a: a. 0 0 10 1 10 , 10 2 3 \0 111 REVISION 16 DECEMBER 2016 4 11l TIME (SECONDS) 2 3

10 10 10 TIME (SECONDS)

BYRON STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-9a PRESSURE AND WATER VOLUME TRANSIENTS FOR LOSS OF OFFSITE POWER 2800 -2600 a.. ............

w 2400 0:::: :::::> LL.I 0:::: 2200 0... a::: w 2000 ::::> (/") r.n LL.I a::: a.. 1800 1600 0 10 2000 -ct 1800 ::i 1600 (..;) ............

w 1400 ::::IE :::::> g 1200 a::: 1000 1..1.J !< 31:: 800 a:::: w N 600 C2 ::> Vl 4{]0 l:fl O:::'. 0... 200 0 0 10 1 10 t 10 2 3 10 10 REVISION 16 DECEMBER 2016 4 10 TIME (SECONDS)

TIME 2 3 4 10 10 10 {SECONDS)

BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-9a PRESSURilER PRESSURE AND WATER VOLUME TRANSIENTS FOR LOSS OF OFFSITE POWER B/B-UFSAR Figure 15.2-10 has been deleted intentionally.

REVISION 16 -DECEMBER 2016 ii:' 680 i> e. 660 w 640 ;) 620 UJ 600 Q. :E 580 w """ ... 560 a. 8 540 ..J 520 500 0 10 1600 ....... ftl 'iii Cl. 1400 ...... w 0:: :::> 1200 w a:: 1000 Cl. ct: g 800 600 w z w (!) 400 :IE 200 en 0 0 10 SAT HOT COLD l 10 1 10 2 3 10 10 REVISION 16 DECEMBER 2016 4 10 TIME (SECONDS) t . 3 4 10 10 10 TIME (SECONDS)

BYRON STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-10a LOOP TEMPERATURES AND STEAM GENERATOR PRESSURE FOR LOSS OF OFFSITE POWER 680 'W:.' s60

""' °" cu e.. 640 LLI D::: 620 REVISION 16 DECEMBER 2016 WOOD JifOT _,, ____ .,, ..

___ ,.,, ... '----------------------,,...,, 0... a5 580 1--560 0... g MO 520 500 () 10 1600 0 1400 .(ii a... .............

w 1200 D::: ::::> U") 1000 D::: 0... a::: 800 0 600 :z LLI (.!) 400 tn 200 0 0 10 OOl.D f 10 I 10 , _______________ _ ( I 2 1 0 TIME (SECONDS) 2 10 J 10 3 10

10

10 TIME (SECONDS)

BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-10a LOOP TEMPERATURES AND STEAM GENERATOR PRESSURE FOR LOSS OF OFFSITE POWER 2600 I 2400 II! I 2200 1-1800 REVISION 10 DECEMBER 2004

__ .........

...._ ...............

.................

.........................

,____._.._........., ......... 1.E-01 1.E+OO 1.E+01 1.E+02 1.e+o3 1.E+04 TJlllE (SECONDS) 1800 1800 1400 1

1200 . m 1000 I I : 400 200 O+.--.._....._......._......_....,_

_ _,_ .........

........................

_

......... 1.E-01 1.E+OO

1.E+01 1.E+02 1.E+03 1.E+04 TIME 18ECOND8J BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-11 PRESSURIZER PRESSURE AND WATER VOLUMETRANSIENTS FOR LOSS OF NORMAL FEEDWA TER 700 880 880 G:' 640 t iii 820 1800 580 .. 9 580 540 1120 800 1.E..01 1200 i 1000 ll! I 800 I 800 m ! 400 200 SAT HOT COLD 1.E+OO 1.E+01 1.E+02 1.E+03 TIME (BECONDS)

REVISION 10 DECEMBER 2004 1.E+04

........

..........

1.E*01 1.E+OO 1.E+01 1.E+02 1.E+04 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-12 LOOP TEMPERATURES AND STEAM GENERATOR PRESSURE FOR LOSS OF NORMAL FEED WATER

-0 IX .c L&J-31: E oo a,.Z IX-o-2 =>u Zf -1 . 4 1 . 2 1 . 8 REVISION 9 DECEMBER 2002

6 .

4 . 2 0 _, 0 1 0 1 0 I 2 1 0 1 0 TIME (SECONDS) 3 1 0 ' 1 0 .6

4 . 2 0 -.2 -.4 -.6

.........

...........

u..u-'+---'---'-...L-L.J...U.Li -I D I 2 3 4 10 10 10 10 10 10 TIME (SECONDS) 1000 ....-----------------------------------------------, 0 -'--------------.

._......._

L&J I -2000 ..J Ill b--3000 ._ -I 1 0 0 1 0 1 2 1 0 1 0 TIME (SECONDS) 3 1 0 ' 1 0 BYRON/BRAIDWOOD STATIONS UPDATED rlNAL SAFE:TY ANALYSIS REPORT FIGURE 15.2-13 NUCLEAR POWER, TOTAL CORE REACTIVITY AND FEEDLINE BREAK FLOW TRANSIENTS FOR MAIN FEEDLINE BREAK WITH OffSITE POWER AVAILABLE

.... 2600 0: ::> 2400 Cl) Cl) .... 0:: 2200 D.-0:: .2 2000 La.I rn N D.. --1800 0: ::> Cl) 1600 fl) La.I 0:: 1400 Q. -I 1 0 1 2 0 Lt.. La.I 100 ::J La.I . o::-c;-80 0: CD La.I rn 60 N ....... 02 E ::> .0 40 en.:::-Cl) 20 La.I 0: a.. 0 -1 1 0 .... ::E 2000 ::> ..... 0 > IX 1500 L&J == !:? 1000 a::-Lo.I N 500 02 ::> Cl) (/) 0 Lo.I IX -1 a.. 1 0 0 1 0 0 1 0 0 1 0 I 2 1 0 1 0 3 1 0 REVISION 9 DECEMBER 2002 ' 1 0 TIME {SECONDS) 1 2 3 4 1 0 1 0 1 0 1 0 TIME {SECONDS)

I 2 3 4 1 0 1 0 1 0 1 0 TIME {SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT rlGURE 15.2-14 PRESSURIZER PRESSURE, PRESSURIZER RELIEF AND PRESSURIZER WATER VOLUME TRANSIENTS FOR MAIN FEEDLINE BREAK WITH OFrSITE POWER AVAILABLE

---Thot ---Tcold -*-*-* Tsot -1 1 0 ---Thot Tcold Tsot 0 1 0 1 2 1 0 1 0 TIME (SECONDS) 3 1 0 REVISION 9 DECEMBER 2_002 ' 1 0 700....------------------------------------------------.

-1 1 0 *-*-*-*-*-*-*-*-*-*-*-*-*-*-*, .._,..,*-..........

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0 1 0 1 2 1 0 1 0 TIME (SECONDS) 3 1 0 ' 1 0 BYRON/BRAIDWOOD STATIONS UPDATED rlNAL SAFETY ANALYSIS REPORT FIGURE 15.2-15 F AULTEO ANO INTACT LOOP COOLANT TEMPERATURE TRANSIENTS FOR MAIN FEEDLINE BREAK WITH OffSITE POWER AVAILABLE 1 . 4 1

2 -'"6 Xe ::>-...J E a.o . 8 ,_z c(.._ LLI 0 ::c

6 c LLI 0 IX:;::: OU oe

4 la. -. 2 0 -t 1 0 FAULTED ---INTACT 1400 LLI 0:: 1 2 0 0 :;) (/) (/') LLI 1000 0:: Q.. a::_ 800 Oo t--c( fl) IX Q. 600 ..... -z LLI (!) 400 c( ..... 200 ..... (/) 0 -1 1 0 0 1 0 0 1 0 REVISION 9 DECEMBER 2002 I 2 3 4 1 0 1 0 1 0 1 0 TIME (SECONDS) r--***** I I / I I 2 3 4 1 0 1 0 1 0 1 0 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED rlNAL SAFETY ANALYSIS REPORT FIGURE 15.2-16 CORE HEAT fLUX AND STEAM GENERATOR PRESSURE TRANSIENTS FOR MAIN FEEDLINE BREAK WITH OFFSITE POWER AVAILABLE REVISION 9 DECEMBER 2002 1 .4

-311:0 o.E -'E .... 0 IX 0 me 0 c-La.lb La.ID ....... ..... ->---X 1 . 2

8 . 6 .4 . 2

6 . 4 . 2 0 -.2 -.4 -.6 .... , U_x-1000 i5 I o::,E -2000 ...J ID c:( 0 b--3000 .... _, 1 0 -I 1 0 0 1 0 0 1 0 I 2 1 0 1 0 TIME {SECONDS)

I 2 1 0 10 TIME {SECONDS) 3 1 0 3 1 0 ' 1 0 4 1 0 -4000 -t 0 I 2 3 4 10 10 10 10 10 10 TIME {SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-17 NUCLEAR POWER, TOTAL CORE REACTIVITY AND FEEDLINE BREAK FLOW TRANSIENTS FOR MAIN FEEDLINE BREAK WITHOUT OFFSITE POWER AVAILABLE

...... 2600 a:: :::> 2400 Cl) Cl) ...... a:: 2200 a..-a:: .2. 2000 ...... 0 Na. --1800 a::: :::> Cl) 1600 Cl) LI.I a:: 1400 a.. -I 10 120 ..... ...... 100 :::; ...... a:::-80 u 0:: CD l&J rn 60 N' -e a:: .a 40 ::> _ en-Cl) 20 LI.I a:: a.. 0 -I 1 0 ...... ::::E 2000 ::> -' 0 > 0:: 1500 ...... I-<-

1000 .._ o::-...... N 500 iX :::> VJ VJ 0 ...... a:: -I ll.. 1 0 D 1 0 D 1 0 0 1 0 I 2 1 0 1 0 REVISION 9 DECEMBER 2002 3 .. 1 0 1 0 TIME (SECONDS)

I 2 3 .. 1 0 1 0 1 0 1 0 TIME. {SECONDS)

I 2 3 4 1 0 1 0 1 0 1 0 TIME {SECONDS)

-BYRON/BRAIDWOOD STATIONS UPDATED f'INAL SAFETY ANALYSIS REPORT FIGURE 15.2-18 PRESSURIZER PRESSURE, PRESSURIZER RELIEF ANO PRESSURIZER WATER VOLUME TRANSIENTS FOR MAIN FEEDLINE BREAK WITHOUT OFFSITE POWER AVAILABLE

...., 0:: ...., ll. ...., .... .,_I Cl ll. GI 0 "tJ o"-' _J .... 0 ---Thot. Tcold Tsot REVISION 9 DECEMBER 2002 650 *-*-*-*-*-*-*-*-*-*-*-*-*-

\. /*-*-*-*-., *-. ,,_ .. *-*--. ..._./ 600 / / -------------

550 _, 1 0 ---Thot ---Tcold -*-*-* Tsot I 2 1 0 1 0 TIME (SECONDS) l 1 0 ' 1 0 650 600 550 -I 1 0 0 1 0 *-*-*-*-\. / ' *...._*-*-.. . ....__/* ,, I 2 1 0 1 0 TIME {SECONDS}

3 1 0 *r** ' 1 0 BYRON/BRAIDWOOD STATIONS UPDATED f'INAL SAF'ETY ANALYSIS REPORT f'IGURE 15.2-19 FAULTED AND INTACT LOOP COOLANT TEMPERATURE TRANSIENTS FOR MAIN FEEDLINE BREAK WITHOUT . OffSITE POWER AVAILABLE 1 . 4 1. 2 . -::::-D >< c :::>-...... E a...o . 8 .,_z ... :::c 0

6 c l.&I 0 a::= OU

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I I I I I / 1 z 3 4 1 0 1 0 1 0 1 0 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.2-20 CORE HEAT FLUX AND STEAM GENERATOR PRESSURE TRANSIENTS FOR MAIN FEEDLINE BREAK WITHOUT OFFSITE POWER AVAILABLE

,--... .E 2350 c.n c... -..._ 2250 . \:: ::l en en Q) ct 2200 REVISION 15 DECEMBER 2014 2150...,_._._

_________________________

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.... _ ----. ------4 6 Time (seconds) 8 to BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.3-1 PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW 1.2 -0 c: .E 0 z '+--0 0.8 c: 0 :.;::::; u 0 o.s L.. I..&-...._... L Q) 3': D.4 0 0.... L.. c (J) 0.2 u => z 0 J 1.5 1 0 2 0 2 4 6 Time {seconds) 3 .. Time (seconds)

B 5 6 REVISION 15 DECEMBER 2014 10 7 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.3-2 PARTIAL LOSS OF FORCED REACTOR COOLANT FLOW c c: *e 0 z -0 c: 0 :.;:::; v 0 ._ l.&-. -3: 0 w:: _,., c: 0 0 0 CJ REVISION 15 DECEMBER 2014 2200....__,__.._...

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0 2 1.2 o.a 0.6 OA 0.2 0 0 2 4 6 Time (seconds) 8 10 4 6 Time {seconds) 8 10 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.3-3 COMPLETE LOSS OF FORCED REACTOR COOLANT FLOW REVISION 15 DECEMBER 2014 1.2 ;..........., 0 c: *e 0 z: -0 o.s c:: 0 :.;::::; (.) 0 Q.6 '-Q) ;: 04 0 a... '-0.2 u ;::, .:z 0 0 2 4 6 Time (seconds) 8 lO J-----------------------------------------------.

c:: 2 0 1.S 1 0 2 3 4 Time (seconds) 5 7 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.3-4 COMPLETE LOSS OF FORCED REACTOR COOLANT FLOW

---Neutron Flux ---Hot Channel Heat Flux -0 c e 0 . 8 ><z ::::> .... ...J 0 L&.c

6 s -u e . 4 ..._ -* 2 0 0 2 2000 La.I 0::: :::> o:::-....,...._

Q.. O> ::E ID 1500 LIJQ ..,.._ Q :s u 1000 0 2 ...... ...... .... ..... .... 4 6 TIME {SECONDS) 4 6 TIME (SECONDS)

.... -REVISION 9 DECEMBER 2002 --8 10 8 1 0 BYRON/BRAIDWOOD STATIONS UPOA TEO flNAL SAFETY ANALYSIS REPORT f"IGURE 15.3-5 SINGLE REACTOR COOLANT PUMP LOCKED ROTOR REVISION 9 DECEMBER 2002 2800 2700 ..... 0::: 2600 ::::>. en en ..... _ 0::: 0 ID..-2500 lll en c. u-0::: 2400 :2 2300 2200 0 2 4 6 8 1 0 TIME (SECONDS)

Core Flow ---f culled Loop flow -c 31= .!: oE _, 0 5 I.&.. z . .___ :z 0 :5 c 0.2 u U e ........ -.5 \ ' 0 -----' ------------------

2 4 6 8 1 0 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.3-6 SINGLE REACTOR COOLANT PUMP LOCKED ROTOR REVISION 9 DECEMBER 2002 BYRON I BRAJDWOOQ STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE JS.4-1 NEUTRON FLUX TRANSIENT FOR UNCONTROllED ROD WITIIDRA WAL FROM A SUBCRITICAL CONDmON

---:---E 0 .J z -0 _....,:. <..> 0 .2 l...L_ ->< :::> _J ....._ 25 .1 ::r: 0 5 10 REVISION 9 DECEMBER 2002 15 20 Time (s) BYRON I BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT AGURE 15.4-2 THERMAL A..UX TRANSIENT FOR UNCONTROLLED ROD WITHDRAW AL FROM A SUBCRITICAL CONDITION 25

'G:' cn 700 Q) Cl -a: ::::.:2: t::=! 650 0::: w ::z: :z: Cl 600 ::s {_) REVISION 9 DECEMBER 2002 550-+-____

.......

0 5 10 15 20 Time (s) BYRON I BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE IS.4-3 FUEL AND CLAD TEMPERATURE FORUNCONTROLLED ROD WITHDRAW AL FROM A SUBCRITICAL CONDffiON (SHEET 1 OF 2)

25 2200 2000 ..--LL-O'l 1800 (l) 0 --: 1600 CL ::;E 1400 LLJ I-LLJ 1200 (.!) <: 0::: LLJ 1000 _J 800 LLJ => LL-600 400 0 5 10 REVISION 9 DECEMBER 2002 15 20 Time (s) BYRON I BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-3 FUEL AND CLAD TEMPERATURE FORUNCONTROLI.ED ROD WITHDRAW AL FROM A SUBCRITICAL CONDITION (SHEET 2 OF 2) 25 REVISION 15 DECEMBER 2014 1.4---------------------------.

.__ 0 c: 0 :_;:j o.s u e u... .._.... 0.6 Q) £ 0.4 . . . . . . . . . . . . . . . . . . . . . . . . . . * . . .... -. -' .

0 2 4 6 Time (s) 10 BYRON/BRAIDWOOD STATIONS UPDA T ED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-4 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVllY FEEDBACK {80 PCM/SEC WITHDRAWAL RATE) (SHEET 1 OF 3)

REVISION 15 DECEMBER 2014 t.4....---------------------------......

-::=--g 1.2 E 0 z c:: 0 1 1:> 0.8 lJ_ ...............

x 0.6 ::3 CL: .,...,_ 0 Q,) 0.4 :c 0.2 ........ ___ ........ .....,. __ _.._........,_.--

_________

-.-__________________

__.. 0 2 4 6 Time (s) 8 10 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-4 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK (80 PCM/SEC WITHDRAWAL RATE) (SHEET 2 OF 3)

REVISION 15 DECEMBER 2014 ...--... 620 .. u.. I . . 610"" ...*..*.... : ............. ' . . . . . . . . . . . . . . . . ............... . ,__ 01 <I) -0 . . . . * ...............

600"' . . * . .. . . . . . ' : . . . . . . . . . . . : . . . . . . . . . . . : . . . . . . . . * . * : . . . . . . . * . . . .:::l : _ _..;.----*-----... : : 15 590--...-.....

............... ............ .......*............. ,__ . . . . . <1) * * -* CL * . . . 580-* ...... 1--Q.) O' .* . . . . 0 570-. . . . . . . . . . . . . . . . . . . . . . . . . . .. -.... --. . . . . . . . . . . . . . . . . . . . . . . . ti.-* * * . (1) " 560-"' ........... : ........... : ........... : . . . . . . . . . . . : .......... . 0 u 0 2 4 6 Time (s) 8 10 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-4 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK {80 PCM/SEC WITHDRAWAL RATE) {SHEET 3 OF 3) 0 2600 REVISION 15 DECEMBER 2014 .. 2400 ........ ' . . . . . . . . . . . . . ' ...... ' . ' ......... ' . . ...... ' ...... . ....__, ,_ (l) N *c:: ::::s (I) 8l 2000 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..........

' a.... 1aoo....---------

.........

.----------..-.-------------------_.

0 2 4 6 8 10 Time {s) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-5 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK (80 PCM/SEC WITHDRAWAL RATE) (SHEET 1 OF 3)

.--.. ..,.._> Q) <J) w... (..) :.0 REVISION 15 DECEMBER 2014

l 1200-.*......... : ........ , ... : . ' ......... : ........... : ..... .... . u .............

Q.) E ...2 .g 1000-""--, ....... , , ..................................

.............. . *c: ::J (/) (./) Q.) 5..-a..

...--:-------...----------1 0 2 4 6 Time (s) 8 10 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-5 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK {80 PCM/SEC WITHDRAWAL RATE) (SHEET 2 OF 3}

a::: REVISION 15 DECEMBER 2014 5------------------------------------------------------..

4 -*************************** .. ************

- - - - -****** 3 ................................... ' ..... -............... . a 1-+-_._ ______ _,_ ______________

..... ______ ..,_ _________ -...... ________ _. 0 2 4 6 Time (s) 8 10 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-5 UNCONTROLLED RCCA BANK WITHDRAWAL FULL POWER WITH MINIMUM REACTIVITY FEEDBACK (80 PCM/SEC W IT HDRAWAL RATE) (SHEET 3 OF 3) 1.2 0 c:: E 1 0 :z "+-0 c: 0.8 0 (..) 0 0.6 '-LI-...__.. '-<l.) 0.4 3= 0 a_ '-0 0.2 <L> (.) ::::> z 0 0 10 20 30 Time (s) 40 REVISION 15 DECEMBER 2014 50 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-6 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK (3.0 PCM/SEC WITHDRAWAL RATE) {SHEET 1 OF 3)

...---.. c c: 1.2 E REVISION 15 DECEMBER 2014 0 :z 1 . ' . . . . . . . . , . . . . . . . . . . . . .....__ 0 c:: 0 .+J o.s (.) 0 ..___... x o.s :::J LL-.........., o.4 * * * * * * * * * * * * * * .. * * * * * * * * , * * * * * * * * * * * * * * * * * * * * * :r:: 0.2..,._.......__......_...__..............,.

____ .......,.

__ --i _ ___,r--......_......_......_...,_....__

_____ ...,. 0 10 20 30 Time (s) 50 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-6 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK (3.0 PCM/SEC WITHDRAWAL RATE) {SHEET 2 OF 3)

..--.. LL. 620 REVISION 15 DECEMBER 2014 t 610 . . . .. . . . . . . . . . . . . . . ' . . . . . . . . . . . . . . . . . . -. . . . . . . . . . . Q) -0 ....__...

<J.) 600 ;;::) 0 __ ___;__.---590-t-..:.*

...........

*...--:"". . . * . . . . * . . * . . . . . . . . . . . . . . * * . . . . . . . .

CL E 500 ....................

........................... . <J.) C°) 570 . . . . . . . -. . -. . . . . . . . . . . . . . . . . . . . . . . . . . . ' . . . . . . . . . . > < 560 ...*............................................. 0 (._) 550-+------------------------.------

...........

.----------1 0 10 20 30 Time (s) 40 50 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-6 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK (3.0 PCM/SEC WITHDRAWAL RATE) {SHEET 3 OF 3)

.....--0 2600 REVISION 15 DECEMBER 2014 . R 2400 * * * * * * * * * * * * * * * * * * * * * * * * * * * * .. * * * * * * * * * -* * * * * * * * * * ...__.-:::J en en cu ct 2200 1aoo------------.---------------------r---------.._..

______ --t 0 10 20 30 Time (s) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-7 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVIlY FEEDBACK (3.0 PCM/SEC WITHDRAWAL RATE) (SHEET 1 OF 3)

_.--.... .........

Q) <J.) LI,_ 1800 u 1600 .0 ::::s u "--"" 1400 Q) E :::s .g 1200 L------------------------REVISION 15 DECEMBER 2014 * * * * .. * ' .. .. .. ... .. ... * * * * * ' * * * * * * "' '. *

4 * * * * * -* * * " .. '

111 ... * .. * " 80() ************************************************* 600 0 10 20 30 Time (s) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-7 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK (3.0 PCM/SEC WITHDRAWAL RATE) (SHEET 2 OF 3) 5 REVISION 15 DECEMBER 2014 4 *********-**********************-***************** . . . .. ...... : ......... : * .......... : ...... *. " . : ... j* .... . .. -....... * : .. : : : :

1 0 10 20 30 Time (s) 40 50 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-7 UNCONTROLLED RCCA BANK WITHDRAWAL FROM FULL POWER WITH MINIMUM REACTIVITY FEEDBACK ( 3.0 PCM/SEC WITHDRAWAL RATE) (SHEET 3 OF 3) a: I

-.-----

tu_,,,.-

..... x .... ,..

... ,..,,k....,-

=--Maximum ResctMty Feedback --...........

Reacti\iy Feedback 1.7 --*--** 16 . ' OTATlrip REVISION 15 DECEMBER 2014 ! 1.5 :& ' z i ' / 1.4 . *\./* 1.3 1.2 ------+--___________

,....__ ____ ____,. 0.1 1 10 100 1000 lnsarlon Ratlt (pcm/ second) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-8 UNCONTROLLED RCCA BANK WITHORAWL FROM 100% POWER MINIMUM DNBR VS REACTIVITY INSERTION RATE REVISION 15 DECEMBER 2014 ****-***----*--*--* .. ------***--****1 2.2

.. SG v.Jves open before trip OTATtrip 1.6 ***--.. _, ...... . ..... 4 ..... --* ___ .. ' igb Flux trip 1.4 ...---------+-

______ _,,,_ ______ ,___ _____ _... 0.1 1 10 100 1000 Insertion Rate (pcm/ second) ' , ___ ...,.,, BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-9 UNCONTROLLED RCCA BANK WITHDRAWAL FROM 60% POWER MINIMUM DNBR VS REACTIVITY INSERTION RATE REVISION 15 DECEMBER 2014 ----------------*1 OT AT trip i SO Valves opeo ! bctm 1r1p ....................

J 2.8 r4 ! 2.2:E I z i 2 -.. -....... *---* *-* .. " . ... -. i ! 1.6 I I I I I J I I 11 ...........,...

--ii.--___,.........,__.__

_ ---=-1 f . ***-.... i ---l l I ::eai;; open \ ..a-_ igh Flux trip J 1.4 0. 1 1 10 100 1000 tnsertlon Rat. (pcm/ second) J .... .. -.... --__ --... -----------------.. ------*-_,_ BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-10 UNCONTROLLED RCCA BANK WITHDRAWAL FROM 100% POWER MINIMUM ONBR VS REACTIVITY INSERTION RATE B/B-UFSAR Figures 15.4-11 and 15.4-12 have been deleted intentionally.

-_, <( w ::E 3=o a: u. <o wz -'o (,,,) -:::> I-zU <( a: u. :::; :J.-_, ::E u.o 1-Z <( u. we ::c wz a:2 ct-(J (J <( a: u. 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 1.2 1.1 1.0 0.9 0.8 0.7 0.6 0.5 0 50 100 150 200 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4*12a TYPICAL TRANSIENT RESPONSE TO A DROPPED RCCA (OR RCCAS) IN AUTOMATIC CONTROL (SHEET 1 OF 2)

.,.._ zu. c:c<2-..J w 0 a: o::::> (,,) .... W<( e,, a: <(W a: a. w::E >W <( .... < -w a: ::::> w a: a. a: w N a: ::::> w a: a. 600 580 560 540 520 500 2400 2300 2200 2100 2000 1900 1800 0 50 100 150 200 TIME (SECONDS)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4*12a TYPICAL TRANSIENT RESPONSE TO A DROPPED RCCA (OR RCCAS) IN AUTOMATIC CONTROL (SHEET 2 OF 2)

B/B-UFSAR Figures 15.4-13 thru 15.4-17 have been deleted intentionally.

REVISION 15 -DECEMBER 2014

'::J" C( c::Z LJ-3: :I! ..... IXO C( !:jZ u2 :::>I-ai::: ..... ........ . 1. 4 1. 2 . 8

6

4

2 D 2 REVISION 9 DECEMBER 2002 4 6 TIME 8 10 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-18 NUCLEAR POWER TRANSIENT.

SOL HFP ROD EJECTION ACCIDENT 3000 2000 I I I 1000 I I 0 FUEL CENTER TEMPERATURE f"UEL AVERAGE TEMPERATURE CLAD OUTER TEMPERATURE

/ / I / / / / .,,,*-*-.........

-*-2 -. -*-*----*-*-*-*-*-*-*-REVISION 9 DECEMBER 2002 *-*-. -*-. 4 6 TIME {SECONDS) 8 1 0 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-19 HOT SPOT FUEL AND CLAD TEMPERATURES VERSUS TIME BOL HFP ROD EJECTION ACCIDENT TIME (SECONDS)

REVISION 9 DECEMBER 2002 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.4-20 NUCLEAR POWER TRANSIENT.

EOL HFP ROD EJECTION ACCIDENT L&J 0::: ::> < a: L&J 0.. ::IE L&J-...........

QC,, u-0 z < -' L&J ::> ...... FUEL CENTER TEMPERATURE ---FUEL AVERAGE TEMPERATURE

-* -* -* CLAD OUTER TEMPERATURE 5000 4000 3000 I I I / / / / ....... ...-*-*-*--.

...... ...... ..... ..... -...... . -. . REVISION *9 DECEMBER 2002 2000 ,,.. -. / -. I 1000 I 0 / / / *2 -*-*----*-*-*-* .. 6 TIME (SECONDS)

-*--*-*--*-. 8 I 0 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFElY ANALYSIS REPORT FIGURE 1 5.4-21 HOT SPOT FUEL AND CLAD TEMPERATURES VERSUS TIME EOL HFP ROD EJECTION ACCIDENT

-1.2 0 c: .E 0 z ....... 0 c ().8 0 +:; (.,1 e Q.6 ...._ \...... <1' OA 3: 0 a.. ._ 0.2 0 Cl) 0 :J :z: 0 580 ;:::) ......, 0 a> 570 a.. E Cl) e 550 Q) 540 0 u 0 100 200 JOO Time( seconds) 400 500 REVISION 15 DECEMBER 2014 600

____________________________________________

_.,. 0 100 200 JOO 400 Time( seconds) 500 600 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.5-1 NUCLEAR POWER TRANSIENT CORE AVERAGE WATER TEMPERATURE TRANSIENT FOR INADVERTENT ACTUATION OF ECCS DURING POWER OPERATION

.............. t: ..__.. <I.> E ::;) 0 > ""-Cb .........

0 3: ,_ Cl> N *c ::::l (I') en (I.) '-0... REVISION 15 DECEMBER 2014 2&00-----------------------------------------------

1600_,_ __________________

..._. ________________________

...... 0 too 2000 1500 1000 500 0 100 200 300 400 Time( seconds) 500 600 200 JOO 400 Time( seconds) 500 600 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.5-2 PRESSURIZER PRESSURE TRANSIENT PRESSURIZER WATER VOLUME TRANSIENT FOR INADVERTENT ACTUATION OF ECCS DURING POWER OPERATION 7 6 5 0:::: 4 CD :z 0 3 2 1 0 0 100 200 JOO 400 Time( seconds) 500 REVISION 15 DECEMBER 2014 600 -1.2------------------------

c; c: *e 0 :z: 'O O.B 0 e ....... -0.6 c: (..) 0.4 E 0.2 0 2 VJ 0---...........

0 100 200 JOO 400 Time{ seconds} 500 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.5-3 DNBR AND STEAM FLOW TRANSIENTS FOR INADVERTENT ACTUATION OF ECCS DURING POWER OPERATION 1-2 ,....... c c: *e 1 0 c: -0 Q.8 c: 0 :.;::::;;

u E 0.6 "'-'" -Q.) :a: (M 0 .... 0 v 0.2 u ::I :z 0 4 a::: 3 0 1 0 0 10 20 10 20 30 Time (seconds) 40 50 REVISION 15 DECEMBER 2014 60 30 "° Time (seconds)

BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFElY ANALYSIS REPORT FIGURE 15.6-1 INADVERTENT OPENING OF A PRESSURIZER SAFETY VALVE REVISION 15 DECEMBER 2014 -c::-1 :E e:? =:II l 580 570 "11 560 :i! 10 20 30 40 Time (seconds) -c;-2200 2000 :I o_ 1800 *c:: 1600 =s G:l-1400 1200 0 10 20 "° -40 Time {seconds) 50 60 l*-f ,_, -J 1400 j -1 *200 a..

_________

0 10 20 30 40 Time (seconds) 50 60 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-2 INADVERTENT OPENING OF A PRESSURIZER SAFETY VALVE t z 0 3= 0 -' II) i .1 -' -' I: w a: I Q 8 -' w a: --' c,, z :::; 8 (,) a: w c,, z 0 -' l BREAK OCCURS REACTOR TRIP (COMPENSATED PRESSURIZER PRESSURE!

PUMPED SAFETY INJECTION SIGNAL (Hf*I CONT. PRESS. OR LO PRESSURIZER PRESS.I PUMPED SAFETY INJECTION BEGINS (ASSUMING OFFSITE POWER AVAILABLE)

ACCUMULATOR INJECTION CONTAINMENT HEAT REMOVAL SYS. INITIATION (ASSUMING OFFSITE POWER AVAIL.) END OF BYPASS END OF SLOWDOWN PUMPED SAFETY INJECTION BEGINS (ASSUMING LOSS OF OFFSITE POWERI BOTTOM OF CORE RECOVERY CONTAINMENT HEAT REMOVAL SYS. INITIATION (ASSUMING LOSS OF OFFSITE POWERI ACCUMULATORS EMPTY CORE QUENCHED SWITCH TO COLD LEG RECIR. ON RWST LOW LEVEL ALARM (SEMI-AUTOMAT I C) SWITCH TO LONG-TERM RECIRCULATION (MANUAL ACTION) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3 SEQUENCE OF EVENTS FOR LARGE BREAK LOCA ANALYSIS

--RCS ----*I ntact SG RsCllVt c d SC ' ... ... .__. ,,,,,.--, REVISION 15 DECEMBER 2014 0 l080 so E .J:J .::::;::.. ,J) cu 15 0::: :it 20 (/) en 0 IO 0 -3T'ame (;)'° BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3A PRESSURIZER AND STEAM GENERATOR PRESSURE AND RUPTURED TUBE FLOW RATE SGTR RESULTS {OFFSITE DOSE CASE)-UNIT 1

REVISION 15 DECEMBER 2014 _____.. ----* Toto* *ntocl SCs -E g 1

2000 : ** *

f I I I ' ' I t ' * *

t ' \ " ., . ' ' ' \ I ..,. .... --* .. ------: -., ,,.., __ -.............

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Time (sJ BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-38 STEAM GENERATOR RELEASE RATES ANO MASS RETAINED SGTR RESULTS {OFFSITE DOSE CASE)-UNIT 1

-**--RCS ----* ! 1st oc; I SG *********

Rup t1H eel Sir r----7 ----... -......... . . \ \ . I I ' 's I ,; .. ... .. '"-*.... \ --... **-..........

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....., 0 REVISION 15 DECEMBER 2014 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3C PRESSURIZER AND STEAM GENERATOR PRESSURE ANO RUPTURED TUBE FLOW RATE SGTR RESULTS {OFFSITE DOSE CASE)-UNIT 2

--R11p&ure4 SG ----* lotiH t11hc:t SCa I * * ' '(ii"

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..........

0 HIGO BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3D STEAM GENERATOR RELEASE RATES AND MASS RETAINED SGTR RESULTS {OffSITE DOSE CASE)-UNIT 2

- -*--.. "s ' .. *****---* 'h'\"*c c *G REVISION 15 DECEMBER 2014 2!i00-------------

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. r ......._ *.1 **. . '\ \. \ l \ l; \ \ i . . "YI. noo JtJIJC 1 11e (S i BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3E PRESSURIZER ANO STEAM GENERATOR PRESSURE AND RUPTURED TUBE FLOW RATE SGTR RESULTS (MARGIN TO OVERFILL CASE)-UNIT 1

J5C .m 7.ie 200 t.1 Q r:;: £ 0 :a t@ 11J $C ". 11t sc:, I * * ; f f ' ' t *' REVISION 15 DECEMBER 2014 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3F STEAM GENERATOR RELEASE RATES AND MASS RETAINED SGTR RESULTS (MARGIN TO OVERFILL CASE)-UNIT

--RCS ----* l*het SG *--*---* 1t11,tur1ti SG \ \ \ \ ... ', _____ .... , °";'*""'"'

',._. __ REVISION 15 DECEMBER 2014 0----............

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0 so I

500 1580 ., fne (sJ -BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3G PRESSURI2ER AND STEAM GENERATOR PRESSURE AND RUPTURED TUBE FLOW RATE SGTR RESULTS (MARGIN TO OVERFILL CASE)-UNIT 2

-*--Ruoluecl SG ----' 1 o t O I I n I act SG s REVISION 15 DECEMBER 2014 0 -' ,, ,, *' I\ I I ' ' \ \ \ \ ' ' \ ' ' .. ' I I I\ t '\ ' ' I '\' I l ' ' I * * * * .. ,-.* lime (SJ -BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3H STEAM GENERATOR RELEASE RATES AND MASS RETAINED SGTR RESULTS (MARGIN TO OVERFILL CASE)-UNIT 2

REVISION 15 DECEMBER 2014 015 e --3COO ... Time (s) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-31 BREAK FLOW FLASHING FRACTION SGTR RESULTS (OffSITE DOSE CASE) -UNIT 1 0-2-----------------

REVISION 15 DECEMBER 2014 c:: 0 :;::::; (,,) 0.1 e ....... oa:-ot o...__.._

__ ...._........_--.....

_______ _... _______ __.......__"'-'

8 .... 5000 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-3J BREAK FLOW FLASHING FRACTION SGTR RESULTS {OFFSITE DOSE CASE) -UNIT 2 B/B-UFSAR Figure 15.6-4 has been deleted intentionally.

REVISION 14 -DECEMBER 2012 N 0 T R u M p M2148.004 07-80 CORE PRESSURE, CORE FLOW, MIXTURE LEVEL, AND FUEL ROD POWER HISTORY 0 <TIME < CORE COVERED ' --L 0 c T A .. REVISION 1 DECEMBER 1989 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-5 CODE INTERFACE DESCRIPTION FOR SMALL BREAK MODEL B/B-UFSAR Figure 15. 6-6 has been deleted intentionally.

REVISION 6 -DECEMBER 1996 B/B-UFSAR Figure 15.6-6a has been deleted intentionally. REVISION 7 -DECEMBER 1998 0.6 0.5 0.4 ; 0.3 0.2 0.1 0.2 0.25 0.3 0.35 PMID 0.4 0.45 .40 .27 0.5 REVISION 14 DECEMBER 2012 PBOT = integrated power fraction In the bottom third of the core PMID = integrated power fraction in the middle third of the core BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-7 Pbot/Pmid OPERATING LIMITS REVISION 14 DECEMBER 2012 1600 1400 1200 1000 800 600+--...:..----,-----'---,-----'-r----,----.:----i o 100 200 300 400 500 After Break (s) 4G5547171 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-80 HOT ROD PEAK CLADDING TEMPERATURE FOR ECCS LB LOCA PCT LIMITING CASE-UNIT

\ '/ '\ f REVISION 14 DECEMBER 2012 60000,----------------------.

50000 40000 10000 .... ,dol o -10000 +-----,.--'--'--.------,'--'--'----,----'---1 o 100 200 300 400 500 After Break (s) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8b BREAK FLOW ON VESSEL SIDE OF BROKEN COLD LEG FOR ECCS LB LOCA PCT LIMITING CASE-UNIT REVISION 14 DECEMBER 2012 30000,..---------------------, 25000 20000 :5000 10000 \ o -5000-1-----,----..,......;----,---'---..,..---:----1 o 50 100 Time After 105547171 200 250 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8c BREAK FLOW ON LOOP SIDE OF BROKEN COLD LEG FOR ECCS LB LOCA PCT LIMITING CASE-UNIT 1 c 14 08 / I 06 I I I I i 04 I 02 r P ,\ ;-A r! REVISION 14 DECEMBER 2012 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8d VOID FRACTION AT THE INTACT AND BROKEN LOOP PUMP INLET FOR ECCS LB LOCA PCT LIMITING CASE-UNIT 1

REVISION 14 DECEMBER 2012 '01TT"-------------------.

41)5547171 25 3G BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8e VAPOR FLOW RATE AT TOP OF CORE AVERAGE CHANNEL DURING BLOWDOWN FOR ECCS LB LOCA PCT LIMITING CASE-UNIT 1

10 o -5 I; 1 '/ A L 1 ; REVISION 14 DECEMBER 2012 4C554?171 25 30 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8f VAPOR FLOW RATE AT TOP OF HOT ASSEMBLY CHANNEL DURING BLOWDOWN FOR ECCS LB LOCA PCT LIMITING CASE-UNIT REVISION 14 DECEMBER 2012 10 -

a 1()O BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8g COLLAPSED LIQUID LEVEL IN LOWER PLENUM FOR ECCS LB LOCA PCT LIMITING CASE-UNIT 1

J;" REVISION 14 DECEMBER 2012 2500...---------------------, r\ 1500 \ \ 1000 i I 500 I \ -500+----..,...-----'-..,...-'-----,.---..,..------!

o 100 400 500 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8h ACCUMULATOR MASS FLOW RATE VAPOR FLOW RATE FOR ECCS LB LOCA PCT LIMITING CASE-UNIT REVISION 14 DECEMBER 2012 1200-r---------------------.

200 o o 100 "'. 400 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 1S.6-8i TOTAL SI MASS FLOW RATE FOR ONE INTACT LOOP FOR ECCS LB LOCA PCT LIMITING CASE-UNIT Ll REVISION 14 DECEMBER 2012 12-r---------------------, 10 o 100 200 300 400 500 Time After Break (s) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8j COLLAPSED LIQUID LEVEL IN CORE AVERAGE CHANNEL FOR ECCS LB LOCA PCT LIMITING CASE-UNIT i \' 1 ! (jWN REVISION 14 DECEMBER 2012 20 15 10 5 o 100 200 400 soc Time After Break 405547171 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8k COLLAPSED LIQUID LEVEL IN DOWNCOMER CHANNEL FOR ECCS LB LOCA PCT LIMITING CASE-UNIT REVISION 14 DECEMBER 2012 250000-r--------------------, LCOOOO 150000 100000 r 50000 o 100 200 400 500 After Break ;;05547171 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-81 VESSEL FLUID MASS FOR ECCS LB LOCA PCT LIMITING CASE-UNIT 1

<J! ! REVISION 14 DECEMBER 2012 12-,...----------.-------------.

JfL-,.--------'r 10 o 100 4-05541171 400 500 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-8m HOT ROD PEAK CLADDING TEMPERATURE LOCATION FOR ECCS LB LOCA PCT LIMITING CASE-UNIT

'.; I _ C REVISION 14 DECEMBER 2012 1800-r-------------------, 1000 600 400 200+-----,----,.------,----'---'--,---'-""'---1 100 200 300 400 500 Time After Break (5) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-90 HOT ROD PEAK CLADDING TEMPERATURE rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

REVISION 14 DECEMBER 2012 60000-.---------------------.

50000 40000 30000 20000 10000 -10000+----'--....,.----'--,-----,.--"""--"-,....----1 o 100 400 500 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9b BREAK FLOW ON VESSEL SIDE OF BROKEN COLD LEG rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

2 L w REVISION 14 DECEMBER 2012 30000,----------------------, 25000 20000 15000 I 10000 -5000+-------,----,----,.------,-----1 o 50 200 250 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9c BREAK FLOW ON LOOP SIDE OF BROKEN COLD LEG rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

14 12 'I '\'1 / I 08 1 04 02 I I I ! REVISION 14 DECEMBER 2012 o 20 1906')l651) 80 100 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9d VOID FRACTION AT THE INTACT AND BROKEN LOOP PUMP INLET rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

L H 1 \ REVISION 14 DECEMBER 2012 o 25 ,,0 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-ge VAPOR FLOW RATE AT TOP OF CORE AVERAGE CHANNEL DURING BLOWDOWN rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

-/ :\ REVISION 14 DECEMBER 2012 v o !O+---.,...---..,.---,...---.,..-'---,-----'--l 25 30 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9f VAPOR FLOW RATE AT TOP OF HOT ASSEMBLY CHANNEL DURING BLOWDOWN rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

1£ 10 o 100 200 Time '; 1 400 500 REVISION 14 DECEMBER 2012 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9g COLLAPSED LIQUID LEVEL IN LOWER PLENUM rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

" r REVISION 14 DECEMBER 2012 1000 I 500 o o iOO 200 400 500 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9h ACCUMULATOR MASS FLOW RATE VAPOR FLOW RATE rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

(/) :,;') 0 2: i r REVISION 14 DECEMBER 2012

.... 1000 800 600 I 400 200 o 100 "90651 ['.511 400 500 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 1S.6-9i TOTAL SI MASS FLOW RATE FOR ONE INTACT LOOP rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

REVISION 14 DECEMBER 2012 --!It,,;T 2 Llc! ')E L! ! l'lt Iq 12-.--------------------, 10 o 100 200 300 400 500 Time After Break (s) BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9j COLLAPSED LIQUID LEVEL IN CORE AVERAGE CHANNEL rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

--UNi t:\;EL I lei ,N A,Cr L REVISION 14 DECEMBER 2012 30-r---------------------, 20 15 10 o 100 200 300 400 500 Time flJter Break (s) "}06'516511 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9k COLLAPSED LIQUID LEVEL IN DOWNCOMER CHANNEL rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

200000 150000 100000 50000 I : U i REVISION 14 DECEMBER 2012 o 100 400 500 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-91 VESSEL FLUID MASS rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

00 1 IL 10 LJJ 8 6 4 a 100 K C L 200 4866 4 576 AT i ,') 1111 300 400 500 REVISION 14 DECEMBER 2012 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.6-9m HOT ROD PEAK CLADDING TEMPERATURE LOCATION rOR ECCS LB LOCA PCT LIMITING CASE-UNIT 2

DECEMBER 2010 BYRON/BRAIDWOOD STATIONS UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15.7-2 SPEN T FUE L STORAGE POO L SECT I ON

ML19170A347

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