Text

Revision 24 to Updated Final Safety Analysis Report, Chapter 14, Figures
	ML18117A432
Person / Time
Site:	Three Mile Island
Issue date:	04/06/2018
From:	; Exelon Generation Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML18117A343	List: ML18117A350; ML18117A352; ML18117A353; ML18117A355; ML18117A359; ML18117A360; ML18117A361; ML18117A362; ML18117A363; ML18117A364; ML18117A366; ML18117A367; ML18117A369; ML18117A370; ML18117A371; ML18117A372; ML18117A374; ML18117A375; ML18117A376; ML18117A377; ML18117A379; ML18117A382; ML18117A383; ML18117A384; ML18117A386; ML18117A387; ML18117A388; ML18117A389; ML18117A390; ML18117A391; ML18117A392; ML18117A393; ML18117A394; ML18117A395; ML18117A396; ML18117A397; ML18117A399; ML18117A400; ML18117A401; ML18117A403; ML18117A404; ML18117A406; ML18117A407; ML18117A408; ML18117A409; ML18117A410; ML18117A411; ML18117A413; ML18117A414; ML18117A415; ... further results
References
	TMI-18-047
	Download: ML18117A432 (90)
	v • d • e

-80 60 Neutron Power. s 40 20 0 ,_. '"!j a I ,_. BO Thuma I 40 Power. I 20 0 400 300 fue I Temperature 200 Chana*. f 100 0 heraae Core 12 Moder at or 8 Temperature Chanae. f 4 0 2600 2500 Reactor 2400 Sr stem Pressure, psi* 2300 =II: en 2200 CD -....

II>> s: Cl II>> t:: -... -t :-J> c:

n ::II z ,, ?> !?. ::::;.* -* a. H Ill :::.-: CD I J> ....... = ..... n :::.-: --=--II: 0 0 I A :I :. C'J -a = .. C: I ,, u:a ::c = -*II>> ca -::r CD A .,, .,, ; 0 "' Ill CD c: ... c: ... ..,, CD r.E' "a c::a. -...... I>> fa ..........

m -co . I -N ....

) g Cl Cl Cl Cl Cl .., -* 0 :I -u .. ..

c .

0 . .. . ; * -E -.. .. -; =

CL c -:I * * ... .. *

Cl -= 0 :I * .c .. z .... -&. --u c ) p. 14.FIG-2 --... :I 0 --* * ... ... *

CL E * * * --. -.. = .. -= u Cl Cl * ... a ... ... ... u *

me Cl Cl .., ... * * -... -... Cl Cl ... Cl -... --... CL -:I ... ... * -.... Id ijl J Nuclear TMI Unit-1 Update -1 7/82 Startup Accident from 1 o-9 Rated Power using all Rods with a Worth of 10 1/o AK/K; High Flux Reactor Trip is Actuated Fig. 14.1-2

..., --------....

.... G -0 iU 0 ---M-: -g __ .,._ ____ ,._ ___ ....., ___ --I a_ "' c..J -.. ._ ______ ..... ______ _. ______ __..._ ______________________

..... .._ ____ __. 0 c -Pt1l Ther*al Pnwer ' Cit ""'O 0 a:: UPDATE -14 4/98 p. 14.FIG-3 Peak Thermal Power vs. Rod Withdrawal Rate for a Startup Accident from 10 -g Rated Power CAD FILE: 6555Rl4.DWG FIG 14.1-3 0 ca Q .... -c Q (.,) ., -c -"' CL Q .... CJI 'a Q CK Peak Neutron Power. \ p. 14.FIG-4 Id ijl I Nuclear TMI Unit-1 Peak Neutron Power vs. Rod Withdrawal Rate for a Startup Accident from 10-9 Rated Power ('"') I 0 0 "" I 0 u * "' '-.. -.-' .-* ., -,. IX ,. * ,. .... i:::I .c ---i:::I 0 IX Update -1 7/82 Fig.14.1-4

= -' '\ I\ \ \ \ -.. \ \ -... c: -* 0 z \ \ \ -.. P11' Tlllr*al Pner. I p.14. FIG-5 -CAD FILE: 6556Rl4.DWG

-* * -* * * * .. * * .. *

N -* 0 -... -. .. -' --. --. r-* z w u LL LL w 0 u a:::: 0 t-<( a:::: w 0 0 :::.;; UPDATE -14 04/98 FIG 14.1-5

__,---. 0 .. p.14.FIG-8 Cl "'

M N -I -Cl I -Cl I "" IQ JC .... '-...,. -.. " .. --c: u -u -u Q ... u 8: Q C2 ,,,, Th1r .. 1 'D*tr. I Gil!] Nuclear TMI Unit 1 Peak Thermal Power Versus Doppler Coefficient for a Startup Accident Using a 1.50/a flK/K Rod Group at 1.09 X10-4(f1K/K)/S From 10*9 Rated Power Update

BR 3/90 Fig. 14.1*6

, . ..--. ,..-p. J 4.FIG-7 -. -. -. ,... N -. c::t -I{) I 0 x @ _µ c: Q) *c::; :.;:::: -Q) 0 u L Q) 0.. 0.. 0 a (crPi; UNIT I NUCL*A* UPDATE -14 04/98 Peak Thermal Power vs. Doppler Coefficient for a Startup Accident Rods at 7.25 x 10 -4 from 10 -9 Rated Power TITLE LINE 2 CAD FILE: 6557Rl4.DWG FIG 14.1-7 PUil Ther** I Power' I p. 14.FIG-8 Id ijl I Nuclear TMI Unit-1 Peak Thermal Power vs. Moderator Coefficient for a Startup Accident Using all Rods at 7.25 X 10-4 bK/K)/S From 1 o-9 Rated Power N + + CD a + ca a +

a + N a + N a I

a ' ca a ' -a I ---c u u --u 0 u ... 0 -... ... u a -Update -1 7/82 Fig. 14.1-8 lllllt , .. "', I Thi ru 1 Pour. I F 111 I TH,111t1111 Cl11n11, F h11111 C111 -h*111ter Tu rature Cll1111, F lucter Sr a tu ,,. .... ,., , ... IH I IN H 110 1 OD ID ID 7D ._ __ __. __

__ .-. __

UH I 2311 2211 22* I 1 D 12 Tiu. SIC ld ijJ I Nuclear TMI Unit-1 Rod Withdrawal Ac..;1dent from Rated Power Using a 1.5% 6K/K Rod Group at 1.09 X 10-4 (61</K)/S; High 14 Update -1 7/82 p. 14.FIG-9 Flux Reactor Trip is Actuated Fig.14.1-9 2500 2'00 , .. .. ... , -.. ... ... c -.. 'C ... 2300 ,,-.. 2200 p .14 I FIG-10 S1n11e Control hll liroup I 0 *4 1toc1 11tnc1r1111 ht*. (A. k/K)/se..c 0:iX!I Nuclear TMI Unit 1 Peak Pressure vs. Rod Withdrawal Rate for a Rod Withdrawal Accident from Rated Power A 11 Rods Update

BR 3/90 Fig. 14.1-10 Cl Cl .., .., .., N N p _ 14.FIG-11 Cl Q Q N Q .., .., .., N N N Puk Pr1ssur1.

psi* [?i ijl J Nuclear TMI Unit-1 Peak Pressure vs. Trip Delay Time For a Rod Withdrawal Accident from Rated Power Using a 1.5% 0K/K Rod Group -..,, Q Q .., = N Q Q Q u u "" -u I! *-..... >.. u = C1 ... ..... Update -1 7/82 Fig.14.1-11 en Cl. Q.) :J en en Q.) CL ca Q.) CL 2400 2390 2380 2370 2360 2350 2340 2330 2320 2310 2300 2290 2280 2270 -0.8 p. 14.FIG-12 Nominal -1 . 0

1 . 2 -1 . 4 Do pp I er Coe ff i c i en t , (A k/ k) , F x 1 fi5 Id ijl I Nuclear TMI Unit-1 Peak Pressure vs. Doppler Coefficient fo:-a Rod Withdrawal Accident from Rated Power Using a 1.5a/a c:iK/K

1 . 6 Update -1 7/82 Rod Group Fig. 14.1 -12 2380 2360 "' ..,, c. cu 2340 :::s ..,, ..,, IU ..... 2320 "' IU 2300 2280 -0.6 Nominal -0.4 -0.2 0.0 + 0. 2 +O. 4 +O. 6 +0.8 Moaerator Coefficient, (t.klk)/f x 104 p. 14.FIG-13 18 ij1 I Nuclear TMI Unit-1 Update -1 7/82 Peak Pressure vs. Moderator Coefficient for a Rod Withdrawal Accident from Rated Powr Using a 1.5% uK/1( Rod Group Fig. 14.1-13 120 I I 0 ,_ 100 &I

0 CL 'Cl &I -... QC 90 -0 .... ,_ &I

0 CL 80 ... &I CL 70 60 25 Maximum Neutron Power lu 1*u* Ther.al Power 50 75 Initial Power, I of lated Power p. 14.FIG-14 18 ijl I Nuclear TMI Unit-1 Maximum Neutron and Thermal Power for an All-Rod Withdrawal Accident from Various Initial Power Levels 100 Update -1 7/82 Fig. 14. 1-14 '-----------------------------------------------------------'

-------*-----------------***--***-"

3000 2800 a.> 2600 ..... <<J a.> a. E 2400 a.> .... cu E 1600 E JIC <<1 -1400 1200 1000 0 ----------*---*--**

--* Maximum Temperature in Hottest Fuel Rod At The Hot Spot Maximum Average Fuel Temperature 20 40 60 BO 100 tnitial Power,' of Rated Power p. 14.FIG-15 Id ijJ I Nuclear TMI Unit-1 Peak Fuel Temperature in Average Rod and Hot Spot for an All-Rod Withdrawal Accident from Various Initial Power Levels 120 Update -1 7/82 Fig. 14.1-15

--...... a I ..... °" Ut -a QI: ... * "'c:::ll * :!? en -c -c: I !: ... :I = -* "'c:::ll ... -I ... ... c 3 Ut Q "$. -a Q C'D ... Al :I A. "" c?' .ra. ..... -............

I co en N Neutron Power, Thermal Power,1. Change In Average Moderator T*perature,F Reactor Coolant Pr111ur1,p1ia z 5 -I .. c: "C Q. C>> ,.. Cl) -80 70 60 50 30 65 60 55 50 21100 2350 2300 2250 2200 0 2 12 111 Ti11e, Sec * '

100 80 ---* a ... ....., 80

a a u a ....., u * ,--u -40 20 0 0 -\ ' \ '.\ "L rl a 70,000 lb-ft2 4 p. 14.FIG-1 7 "' ......... 8 12 Ti 111, sec Id ijl I Nuclear TMI Unit-1 16 Percent Reactor Coolant Flow as a Function of Time After Loss of Pump Power Update -1 7/82 Fig. 14.1-17

,,,,-. 2.0 1. 8 c:

1. 6 0 Cl "' ca 0 (.,) tat c: -... 1.4 ::a Q a: m z Q E ::a * *-1. 2 c *-* 1. 0 100 51 Flow loss dl-' (Vent Valve Stuck Open) 102 104 106 108 110 112 114 Overpower at lnicn Coastaown Beains. s p. 14.FIG-18 Id ijl J Nuclear TMI Unit-1 Update -1 7/82 Minimum DNBR Which Occurs During Coastdown From Various Initial Power Levels Fig. 14.1-18 2.0 I . 8 0 1 . 6 *-+J .., ai: m z Q u c: I. 4 c: .., J:: (..) +J 0 % I . 2 I . 0 ,'-0.0 0.4 p. 14.FIG-19 0.8 1. 2 Time Seconds Id ij) J Nuclear TMI Unit-1 I . 6 DNB Ratio Versus Time for a Locked 2.0 Update -1 7/82 Rotor Accident from 102% of Rated Power Fig. 14. 1-1 9

--100 90 NEUTROM 10 POWER 70 60 50 "° 110 100 THEll4Al 90 POWER x 80 ' """""'--70 ...._,,,__

......,,,.,, 60 -so iio -30 586 511' 582 AVERAGE CORE MODERATOR T04PUATURE.

f 580 578 576 571& 572 2280 2260 HACTOR STSTEM 2211() PRESSURE "Ii a 2220 ):> C) -t m I:

ca en s: a -:Je I>> --e.C> c ::D ....... :I z I: ::;.* = :a I c 1:1"' Q .... 0 ca. -llr"'a I -""' Q Q en -a C) ::;-.. -::!!!. Q .. a Cl ::D CD I>> a -I>> CD = ca. 2200 2180 2160 21 "0 0 s 10 15 20 25 30 TIME, SlC ca. *a = 'i -CD :?? N""' c '!=I en I "a ::.* a. -=-* fa ._... ,.... -...........

rD I co I N 0 N ....

) ) 0 0 0 0 .. 0 -0 .... 0 -0 p. 14.FIG-21 0 0 0 Ot 0 -0 .... 0 -0 "' 0 .. .,, --IO * -.., .. -.,, "' . -"' 0 -u -=-0 .... c *c

C* W .... "'0 z > 0"' ... -.,, 0 -.,, -.... .,, * .... .,, .. .... .,, 0 0 .., " 0 -.... .... 0

N " ... -=-* ., -., . 0 .. N " ..... -0 ... ... N 0 0 ... .. 0 -... 0 -N "' N 0 ... 0 0 Bi!] Nuclear TMI Unit-1 0.36'11 C>K/K Rod Drop from Rated Power with Automatic Runback to 60°/1 Demand in 1 2s Update -1 7/82 fig. 14.1-21

-* 3 -Hiit Ll9 --Cold LllJ 600.0 x. 550.0 E t! 0.. 0 0 ...J ------! 500.0 :; c -"jjj *

c 0 0. ., u 0: e :lJ ., ..

0:.. 450.0 400.0L------------_.._

__________

_._ ____

__ ___.. __ __

0.0 20.0 40.0 60.0 80.0 100.0 Ttme (s) _......,....

2000.0 --, .... Hat .... --Unlauhd Hat .... 1500.0 1000.0 500.0L-----..__

____ .._ __________

_._ ____ _._ ____ ---L ____________

0.0 20.0 40.0 60.0 80.0 100.0 Time (s) p. 14.FIG-22A 3000.0 i' ... *

0 a.. 2000.0 c e :;

z 1000.0 lime (s) 600.0 .. :lJ 0 550.0 0.. E a. 0 0 ...J 500.0 :; D lL. 450.D -----' ...... _______

____ _._ ____ --.1. ____ __......_

____ L-____ ...._ __ __J 0.0 20.0 40.0 60.0 80.0 100.0 lime (s) Amer Gen TMI -UNIT 1 UPDATE -15 4/00 DOUBLE-ENDED RUPTURE OF 24 IN. STEAM LINE BETWEEN STEAM GENERA TOR AND STEAM STOP VALVE (WITH FEED WATER ISOLATION)

CAD FILE: 6710R15.DWG Fig. 14.1-22A

-0 'iii .e ::i .. .. cu .t t!) Ill .. .. 0 :::E " Ill 1500.0 ....------....------.------------.-----.-------

1000.0 , --... I ------------

1 ------------------------... -500.0 FaullwdSC o.o ....._ _ __.. _______ __._ __ ...._ __ ....__ __ .__ _ __. __ -.L __ ......_ _ ___, 0.0 20.0 40.0 60.0 80.0 100.0 Time (s) eoooo.0..-----.---,.---.-----..,.....--_.--..------.--_,.------

40000.0 20000.0 ' ' ' ' ' ' ' ' ...

0.0

_ __. 0.0 20.0 40.0 60.D 80.0 100.0 lime (s) p. 14.FIG-22B 5000.0 ...--------......-------------------------

4000.0 3000.0

0 c;:: ...... 2000.0 1000.0 ' \ ' ' \ 20.0 40.0 60.0 80.0 Time (s) Amer Gen TMI -UNIT 1 100.0 UPDATE -15 4/00 DOUBLE-ENDED RUPTURE OF 24 IN. STEAM LINE BETWEEN STEAM GENERATOR AND STEAM STOP VALVE (WITH FEED WATER ISOLATION)

CAD FILE: 6713R15.DWG Fig. 14.1-228

-tJ *u; :J en en cu Q.. 00 .!:! 0 :z: Cl) 0 ,.--Q: ,,...-.-2400.0 2200.0 p. 14.FIG-23 Time {s) Amer Gen TMI -UNIT 1 UPDATE -15 4/00 RCS HOT LEG PRESSURE (psia) RESPONSE FOR LOSS OF ALL AC POWER (STATION BLACKOUT)

CAD FILE: 6705R15.DWG Fig. 14.1-23 TMIUFSAR Figure 14.1-24 Dropped Rod w/ Bayonet Failure -RCS Pressure Response (NOTE 1) NOTES: 1. CVOL 110-4 and 210-4 represent hot leg pressures.

CVOL 352-1 represents the core exit pressure.

p.14.FIG-23A TMI -UNIT 1 REV. 19, APRIL 2008 Dropped Rod w/ Bayonet Failure RCS Pressure Response FIGURE. 14.1-24

...... . . "" TMIUFSAR .. ICS Delay 608, MTC dlc/k; DRW 0'.22 %dklk 670

.........

..,;-------

Figure 14.1-25 Dropped Rod w/ Bayonet Failure -Reactor Power Response p.14.FIG-238 TMI -UNIT 1 REV. 19, APRIL 2008 Dropped Rod w/ Bayonet Failure Reactor Power Response FIGURE. 14.1-25 TMIUFSAR Figure 14.1-26 Dropped Rod w/ Bayonet Failure -Primary Temperature Response p.14.FIG-23C TMI -UNIT 1 REV. 19, APRIL 2008 Dropped Rod w/ Bayonet Failure Primary Temperature Response FIGURE. 14.1-26

._ cu

0 a... c:: 0 ,_ +-' ::::i ) cu :z ....: o.> a... ) 1000 100 10 0 Nominal No Xenon Nominal 11th Xenon Rated Power, EOL Rated Power, BOL 10-J Rated Power.EOL 0.2 0.3 0.4 0.5 Control Rod lorth, s l\k/k 10-J Rated Power.SOL 0.6 0 1 0 B ld 5Jl I Nuclear TMI Unit-1 Peak Neutron Power Variation With Ejected Control Rod Worth Update -1 7/82 Fig. 14.2-1 1000 100

0 A. IQ E ., z:: .... .¥ IQ ., A. ,,.,-.-10 0. I No*1nal No Xenon Nominal 11th Xenon 0.2 Rated Power, EOL H11h Pressure Tr 1 p ii1a.1nal 10*3 Rated No* 1 na I H11h H11h Pressure f IUI Trip Tr 1 p 0.3 0.4 0.5 0.1 0 7 Control Rod lorth, \4klk p. 14.FIG-24 ld ij) I Nuclear TM I Unit-1 Peak Thermal Power as a Function of Ejected Control Rod Worth High 0 8 Update -1 7/82 Fig. 14.2-2 240 E c:.-"-... -(IQ u 200 "C 0 a: cu => 160 u.. .... "' a) .... .... 120 0 % .... 0 u.. >. 80 ,-. CQ .&: .... c: 40 CQ a) 0 Rated Power, BOL Nominal

i th Xenon Rated Power.EOL Nominal No Xenon Hi&h Pressure Flux Trip Nominal 10-3 Rated Power.SOL 10-3 Rated Power, EOL \ Hi&h Pressure Trip flu1 Trip 0.2 0.3 0.4 0.5 0.6 0. 1 0.8 Control Rod lorth, '6k/k p. 14.FIG-25 Id ijl I Nuclear TMI Unit-1 Peak Enthalpy of Hottest Fuel Rod Versus Ejected Control Rod Worth Update -1 7/82 Fig. 14.2-3 1000 100 I 0 *O I *I. D NoM1nal *I. 2 *I. 4 htld Pntr. EOl Rated Power. BOL 10*3 Rited Power. EOL. 10*3 Rated Pour. BOL (H11h Pressure Trip)

1. I

1.1 -2. 0 . 2 2 Doppler Coeff1c1ent. (Ak/k)*f 1 105 p. 14.FIG-26 Id ijJ J Nuclear TMI Unit-1 Update -1 7/82 Effect on Peak Neutron Power of Varying the Doppler Coefficient for an Ejected Rod Worth of 0.56%6K/K at 1 o-3 Rated Power and 0.46% 6K/K at Rated Power Fig. 14.2-4

. .... u 118 140 120 100

a IO A. ... E .... u .c .... -"' ... u A. 60 40 20 0 *0.1 -1. 0 Nominal Nominal -1. 2 -1. 4 Rated Power, SOL Rated Power, EOL 10*3 Rated Power,IOL (Hi&h Pressure Trip) -1. I

1.1 -2.0 Dopp I er Coefficient I (Ak/k)/f l 1 o5 Bi[) Nuclear TMI Unit-1 Update -1 7/82 Effect on Peak Thermal Power of Varying the Doppler Coefficient for an Ejected Rod Worth of 0.56%

at 1 o-J Rated Power and 0.46% uK/K at Rated Power p. 14.FIG-27

'--------------F-ig_.

_14_.2_-_s

-lOOO ;;

0 &. c:: a ... -:2 I

tOD .. .. .. ,,...--I 0 . D p. 14.FJG .. 28 *f I No*1n11 a1 Ud rower . EDl 10*3 lated ro11r.IOL tM*lft Pr1s5ure Jrtp) *l 1 *2 a *** a.a .1 a Moderator Coefficient@/'F x 10 -4 UPDATE -14 04/98 Effect on Peak Neutron Power of Varying the Moderator Coefficient for an Ejected Rod Worth of 0.563 Ilk at 10 -3 Rated Power and 0.463 A k k at Rated Power CAD FILE: 6558Rl4.DWG FIG 14.2-6

-140 120 100 .... cu

80 CQ E .... cu .c ..... 60 40 20 0 *4. 0 *3. 0 Nominal Nominal 10*3 Rated Po1er,BOL (H1ah Pressure Trip) Rated Power.BOL 10*3 Rated Power ,EOL *2.0 -1.0 0.0 + 1. 0 +2.0 +3.0 Moderator Coeffici1nt,(Ak.1k)/f x 104 p. 14.FIG-29 Id 51P I Nuclear TMI Unit-1 Update -1 7/82 Effect on Peak Thermal Power of Varying the Moderator Coefficient for an Eiected Rod Worth of 0.56% eiK/K at 1 o-J Rated Power and 0.46% eiK/K at Rated Power Fig. 14.2-7 14 0 120 100 ..-. .....

0 80 ICL. t.a E ..... 60 ---ICL. 40 20 0 . I ' Rated Power, BOL \__ Nominal ' Rated --10*3 Rated Power, BOL (Hi &h Pr* es sure Tr i p) 1\ l . ' \__ Nominal Nominal ' 0.0 0.2 I '_/ 10*3 Rated Power, EOL I 0.4 0.6 0.1 Trip Delay Ti*e. Sec Id CIP I Nuclear TMI Unit-1 1. D Update -1 7/82 Effect on Peak Thermal Power of Varying the Trip Delay Time for an E1ected Rod Worth of 0.56% oK/K at 1 o-3 Rated Power and 0.46% e:iK/K at Rated Power p. l 4.FIG-30 Fig. 14.2-8 6.0 5.0 m :z ca 4.0 u c: cu ... cu CL :llC 3.0 LA.I cu ... 0 u ,,,..--2.0 1. 0 0.0 0.2 0.3 0.4 0.5 0.6 Control Rod lorth, S6k/k p. 14.FIG-31 Id ij) I Nuclear TMI Unit-1 Percent Core Experiencing 0 NB as a Function of Ejected Control Rod Worth at Rated Power, BOL 0.7 Update -1 7/82 Fig. 14.2-9

-INITIAL RCS AND CORE PARAMETERS MASS AND ENERGY RELEASE CORE STORED ENERGY EOB *END OF BLOWDOWN EOAH

END OF ADIABA nc HEA TUP EOE

END OF EVENT CONTEMPT O< TIME< EOE SYSTEM MASS AND ENERGY ACCUMULATOR MASS AND ENERGY STEAM GENERATOR MASS AND ENERGY REFLOD3B .,__ ____________

EOB <TIME < EOE FLOODING RA TE MASS AND ENERGY RELEASE CONTAINMENT PRESSURE UPPER PLENUM PRESSURE CORE INLET TEMPERATURE EOBCORE ,,. PARAMETERS

...._ BEACH (RELAP51MOD2-B&W)

EOB < TIME < EOE 'f METAL WATER REACTION HOT PIN THERMAL RESPONSE PEAK CLADDING TEMPERATURE

<'OUUNITI NUCL*A* UPDATE -14 4/98 LARGE BREAK ANALYSIS CODE INTERFACES CAD FILE: 6573Rl4.DWG FIG 14.2-10 p. 14.FIG-32 Q) ..... :> ..... cu ..... Q) Q. e Q) .,_ "O cu u ... 0 Q. V) ..... 0 %: 3 200 2800 2400 0 2000 h 20 Btu/hr F t 2 -F 1600 h I 200 800 0 ----------------------------------------------------------

0 10 p. l 4.FIG-33 20 30 140 Time After Rupture.Sec IZ!il!] Nuclear TMI Unit-1 Hot Spot Clad Temperature vs. Time for a 36 in. ID, Double-Ended, Hot Leg Pipe Rupture and Variable Quench Coefficient 50 Update -1 7/82 Fig. 14.2-11

'-( 2400 2000 1600 !S if ul § 1200 en 800 400 ,,,.,,-. 160 120 al D.. LLi a: 80 :> Cl) Cl) f 40 --------------------------------------------------0 4 8 12 p. 14.FIG-34 16 20 24 28 32 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL) -REACTOR VESSEL UPPER PLENUM PRESSURE CAD FILE: 657 4R15.DWG FIG 14.2-12

,,-. i en en i x10* x10* 10 LEGEND RV Side 4 8 -*-*-* Pump Side 3 6 C> 2 4 0 .... (/) 2 1 Cl) < *2"------------------------------------------..-----1 32 0 4 8 p. 14.FIG-35 12 16 20 24 TIME, SECONDS Amer Gen TMI -UNIT 1 28 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL) -BREAK MASS FLOW RATE CAD FILE: 6575R15.DWG FIG 14.2-13 2 4 00....----------------------------.------L-EG_E_N_D

____ __,. 1500 ----Fuel, Seg 6 2000 -*-*-* Clad, Seo 6 1 -"' 1250 1600 r\ I

""' 'v' \ ur I . . \ 1200' 1, 800 w 1000 i 750 I \ I 400 \ 500 0"----------------------------------------------1 0 40 80 p. 14.FIG-36 120 160 200 TIME, SECONDS AmerGen TMI -UNIT 1 240 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -2.506-FT)

-HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION CAD FILE: 6576R15.DWG FIG 14.2-14 2400-------------------------------------LE_G_E-ND

______ _ 2000 1600 u. 11200. 800 400 ----Fuel, Seg 10 ---*-* Clad, Seg 10 1500 1250 1000 i 750 500 0------------------------------------------------1 0 40 80 p. 14.FIG-37 120 160 200 TIME. SECONDS Amer Gen TMI -UNIT 1 240 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -4.264-FT)

HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION CAD FILE: 6577R15.DWG FIG 14.2-15

-

1500 ----Fuel, Seg 13 2000 -----* Clad, Seg 13 1600 ..* ./\ ,/ ": I v I 1250 i 1200

800 400 500 o------------------------------------------------__.

0 40 80 p. 14.FIG-38 120 160 . 200 TIME, SECONDS Amer Gen TMI -UNIT 1 240 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -6.021-FT)

-HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION CAD FILE: 6578R15.DWG FIG 14.2-16

,'-

..... ----Fuel, Seg 18 2000 -----* Clad, Seg 16 800 400 1500 1250 1000 i 750 ! 500 o..._ ______________

._,. _____________________________

__.. 0 40 80 p. 14.FIG-39 120 TIME, SECONDS 160 200 Amer Gen TMI -UNIT 1 240 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -7. 779-FT) -HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION CAD FILE: 6579R15.DWG FIG 14.2-17

-

2000 1600 u. ti 1200

I 800 400 ----Fuel, Seg 16 -----* Clad, Seg 16 1500 1250 1000 760 i 500 0-------------------------------------------------c 0 40 80 120 160 200 240 p. 14.FIG-40 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -9.536-FT)

-HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION CAD FILE: 6580R15.DWG FIG 14.2-18 2400...------------------------------...------L-EG-E-N-O------

2000 1600 Y. I . I ::> .... '"\ \ "'-*" ----Fuel, Seg 7 -*-*-* Clad, Seg 7 *,, \ 1500 1250 1000 1200 I 750 . 800 ' I ' I 400 1 I L*-*-*---------*-*

500 o-------------------------------------------------

0 40 80 p. 14.FIG-41 120 160 200 TIME, SECONDS Amer Gen TMI -UNIT 1 240 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -2.506-FT)

-HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION CAD FILE: 6581R15.DWG FIG 14.2-19 2 4 00----------------------------------.-------LE_G_E-ND--------.

2000 1600 * "-I . . ::::> .... 1200 I i 800 400 \. \ . .,.,-. . ....._,. .., "\ \ \ i I \ . ' . ----Fuel, Seg 9 -----* Clad, Seg 9 1500 1250 u.i 1000 i 750 500 o--------------------------------------------------

0 40 80 p. 14.FIG-42 120 160 200 TIME, SECONDS Amer Gen TMI -UNIT 1 240 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -4.264-FT)

-HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION CAD FILE: 6582R15.DWG FIG 14.2-20 2400--------------------------------------LE-G-EN_D

____ ___ 2000 400 ----Fuel, Seg 12 *-*-* Clad, Seg 12 1500 1250 1000 i 750 500 0 40 80 p. 14.FIG-43 120 160 200 TIME, SECONDS Amer Gen TMI -UNIT 1 240 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -6.021-FT)

-HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION CAD FILE: 6583R15.DWG FIG 14.2-21

400 1500 1250 1000 750

Fuel, Seg 1 5 -----* Clad. Seg 15 0 40 80 120 160 200 240 p. 14.FIG-44 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -7.779-FT)

HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION CAD FILE: 6584R15.DWG FIG 14.2-22 ----*------*

-2400...-----------------------------------------------., 1500 2000 I l2SO , 600 *" / ": I *J . I 1200. I 800 400 LEGEND ----Fuel, Seg 18 -----* Clad, Seg 18 0------------------------------------------------.....

0 40 80 120 160 200 240 p. 14.FIG-45 TIME. SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 LBLOCA LIMIT CASE (BOL -9.536-FT)

HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION CAD FILE: 6585R15.DWG FIG 14.2-23

-* 2.s .

ct: 0 ... 2.0 u c( 1.5 u. ct: w a. 1.0 0.5 -*-*-* 2.508 ft ----** 4.264ft ---8.021ft *.***********..

7.779ft ---9.531ft 0,0....._

____________________________

_ 0 2 4 ' 8 CORE ELEVATION, FT LOCA LIMIT AXIAL POWER SHAPES CAD FILE: 6586R14.DWG

p. 14.FIG-46 10 UPDATE -14 4/98 FIG 14.2-24 12

-

0.01 *FT2, CLPD SBLOCA 2000 -*-*-* 0.03*FT2, CLPD SBLOCA -**-**-**-*

0.04.fT2, CLPD SBLOCA -* .. -.. --.. -* 0.05*FT2, CLPD SBLOCA 1600 **---*--*-

0.06*FT2, CLPD SBLOCA 12.0 '-"' \' .. ' ' . \" \ \ \ ' \ . 1200 \\ \ ' \' ' ... \ \. .. ' \ \' ... , .._ ________________

--tao I 800 ' .. * .... , *,. ....._ ____ _ ,, ' ..... ..._ ---. . ....._ .........

,... "'-. ..__ . ....._ .. .. .. -*--.. ....._ '* ..... ," ................

-...... . .......__

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

.. ..._ ............... ....... ****.... ... --. -.... -........ ...... ._....____

40 ............

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

-.. *-----*----.....

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

--------........................... . 400 0---------------------------------------------------0 0 1000 2000 3000 4000 5000 6000 p. 14.FIG-47 TJME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.01 -0.06 FT 2 BREAKS) CAD FILE: 6587R15.DWG FIG 14.2-25

0.07-FT2, CLPD SBLOCA 2000 -*-*-* 0.08-FT2, CLPD SBLOCA ----0.09-FT2, CLPD SBLOCA **-***----

0.10-FT2, CLPO SBLOCA . ------------------------..120 1600 i ti 1200 I 80 800 40 400 0"------------------------------------------------0 0 , 000 2000 3000 4000 6000 6000 p. 14.FIG-48 TIME. SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.07 -0.10 FT 2 BREAKS) CAD FILE: 6588R15.DWG FIG 14.2-26

,-

0.15*FT2, CLPO SBLOCA ---*-* 0.30*FT2, CLPD SBLOCA -**-----*

O.SO-FT2, CLPD SBLOCA 2000 -------*--

CLPD SBLOCA 120 1600 uoo \\ fl) en ,. \\ \ 800 * \ * \ ' \ . \ \ \, 400 ' ** " ' \ " 80 40, \ \ ' \ ' ...........

... , 0--------------------------------------------------0 0 250 500 750 1000 1250 1500 1750 2000 p. 14.FIG-49 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.15 -0. 75 FT 2 BREAKS) CAD FILE: 6589R15.DWG FIG 14.2-27 35 t: 20 :J 16 10 6 0 0 1000 2000 p. 14.FIG-50 LEGEND 10 0.01.fT2.

SBLOCA ---*-* 0.03.fT2 SBLOCA 0.04-FT2 SBLOCA -**----*--

0.05-FT2 SBLOCA 8 ***--*-*-0.06-FT2 SBLOCA 8 Q 5 0 :l 2 0 3000 4000 5000 6000 TIME. SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.01 -0.06 FT 2 BREAKS) CAD FILE: 6605R15.DWG FIG 14.2-28

p. 14.FIG-51 AmerGen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.07 -0.10 FT 2 BREAKS) CAD FILE: 6606R15.DWG FIG 14.2-29

,---f t: 0 a :a 35 LEGEND 10 O. 15*FT2 SBLOCA 30 ---*-* 0.30-FT2 SBLOCA ---*-O.&O-FT2 SBLOCA *******-**

0.75.fT2 SBLOCA a :& 6 4 :I 10 2 oL----------------------------------------------0 0 250 500 750 1000 1250 1600 1760 2000 p. 14.FIG-52 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.15 -0. 75 FT 2 BREAKS) CAD FILE: 6607R15.DWG FIG 14.2-30 2000 1750 1500 1250 i 1000 I 750 500 250 0 . . . . . . ;\ . 0 LEGEND ----0.01*FT2, CLPD SBLOCA, Seg 18 . -*---* 0.03*FT2, CLPD SBLOCA, Seg 19 1200 -*-**-*-*..

0.04*FT2, CLPD SBLOCA, Seg 20 *--*----*-

0.05*FT2, CLPO SBLOCA, Seg 20 . ****-*-****--*

0.08*FT2, CLPD SBLOCA, Seg 19

,....... ,' . \ . .--***--*, * , 000 I

.. ,,__,,,...,.!

.. , . i ,' .. v/

...... :.--;,1...-....

.. /. "\ i I/ I -\ .... *"'"*'V.\

> I ,' r-" V'""" ' j : \ : .... , '"\ ., * :;* 1' '-...

'\ . 800 1 : ,. 1 f. I :, I I:. I J: -!!. i : . ( ***G:;.:=.':':::::--J I I j

1 ' 600 ...........

. *. L ' ___ ,__. ............

1000 2000 *400 3000 4000 5000 6000 7000 TIME, SECONDS AmerGen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF PEAK CLAD TEMPERATURES (0.01 -0.06 FT 2 BREAKS) p. 14.FIG-53 CAD FILE: 6608R15.DWG FIG 14.2-31

...... 1750 1500 i 1250 i 1000 i 750 500 1000 p. 14.FIG-54 2000 ----0.07.fTZ.

CLPD SBLOCA, Sea 19 -*-*-* 0.08-FT2.

CLPD SBLOCA, Seg 19 1200 ---,-0.09.fT2, CLPD SBLOCA, Seg 19 ****------

0.10.fT2, CLPD SBLOCA. Seg 19 1000 LI e 800 i

800 400 3000 TIME. SECONDS 4000 6000 6000 Amer Gen TMI -UNIT 1 UPDATE -15 4/00 SBLOCA COMPARISON OF PEAK CLAD TEMPERATURES (0.07 -0.10 FT 2 BREAKS) CAD FILE: 6590R15.DWG FIG 14.2-32 2000 1750 1500 r= 750 500 250 0 0 250 500 ,_--" p. 14.FIG-55 LEG ENO ----0.15-FT2, CLPD SBLOCA, Seg 20 -*---* 0.30-FT2, CLPO SBLOCA, Seg 20 1200 --------*

0.50-FT2, CLPO SBLOCA, Seg 19 -*********

0.75-FT2, CLPD SBLOCA, Seg 17 750 1000 1260 1500 1750 TIME, SECONDS Amer Gen TMI -UNIT 1 1000 ii s 800 600 400 2000 UPDATE -15 4/00 SBLOCA COMPARISON OF PEAK CLAD TEMPERATURES (0.15 -0. 75 FT 2 BREAKS) CAD FILE: 6591R15.DWG FIG 14.2-33 24 00..------------------------------------LE_G_E_N_D

________ __ 160 ----Hotleg 2000 -----* Intact SG Secondary

-**-**-**-***

Broken SG Secondary

--*------

CFT 1600 1200 80 800 40 400 0----------------------------------------------------0 0 500 , 000 1500 2000 2500 3000 3500 4000 p. 14.FIG-56 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 CFT LINE BREAK SYSTEM PRESSURE CAD FILE: 6592R15.DWG FIG 14.2-34

p. 14.FIG-57 Amer Gen TMI -UNIT 1 UPDATE -15 4/00 CFT LINE BREAK COLLAPSED LIQUID LEVELS CAD FILE: 6593R15.DWG FIG 14.2-35 20.0 17.5 15.0 t: 12.5 H! 10.0 7.5 :I 5.0 2.& 0.0 0 1000 2000 p. 14.FIG-58 LEGEND Hot Channel 5.6 ---*-* Average Channel 4.8 4.0 2 3.2 g H! 2.4 2 1.8 0.8 o.o 3000 4000 5000. 6000 7000 8000 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 CFT LINE BREAK MIXTURE LEVELS CAD FILE: 6594R15.DWG FIG 14.2-36

,,-2000 1750 1500 ": 1250 H! i 1000 ! 750 500 250 0 0 500 1000 ,.-p. 14.FIG-59 LEGEND ----Seg 21, 11.2*12.0 FT -*-*-* Seer 20, 10.4

11.2 FT 1200 -**-**-**-***

Seg 19, 9.6

10.4 FT .................

Seg 18, 8.8

9.6 FT *****--*-Se; 17, 8.0

8.8 FT 1000 800 I 600 400 1500 2000 2600 3000 3500 4000 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 CFT LINE BREAK HOT CHANNEL CLAD TEMPERATURES CAD FILE: 6595R15.DWG FIG 14.2-37

2000 1600 1200 "' i 800 400 ----Hotleg -*-*-* Intact SG Secondary

-**---**--*

Brok.en SG Secondary

*----

CFT 80 -

40 o..-.------------------------------------------------_.o 0 1000 2000 3000 400d 5000 6000 7 000 8000 p. 14.FIG-60 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 HPI LINE BREAK SYSTEM PRESSURE (OPERATOR ACTION) CAD FILE: 6596R15.DWG FIG 14.2-38 2$ 24 20 t: ar 16 0 5 12 g 8 4 0 0 1000 2000 p. 14.FIG-61 LEGEND 8.0 Downcomer

---*-* Core Composite 7.2 6.4 5.6 :! 4.8 af 4.0 g 3.2 § 2.4 -1.8 o.a o.o 3000 4000 5000 6000 7000 8000 TtUS:

AmerGen TMI -UNIT 1 UPDATE -15 4/00 HPI LINE BREAK COLLAPSED LIQUID LEVELS (OPERATOR ACTION) CAD FILE: 6597R15.DWG FIG 14.2-39 20.0 17.5 15.0 t: 12.5 10.0 I! e 7.& :& s.o 2.5 o.o 0 1000 2000 ,-p. 14.FIG-62 Hot Channel 5.6 -*-*-* Average et.Mel 4.8 4.0 2 3.2 ! 2.4 i 1.8 o.a o.o 3000 4000 5000 6000 7000 8000 TIME, SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 HPI LINE BREAK MIXTURE LEVELS (OPERATOR ACTION) CAD FILE: 6598R15.DWG FIG 14.2-40

,,,-1750 1500 1250 &&. l 1000 750 I 500 250 0 0 LEGEND 1200 ----Seg 21, 11.2*12.0 FT -*-*-* Seg 20, 10.4

11.2 FT -**-**-**--

Seg 19, 9.6

10.4 FT ---**-----

Seg 1a, a.a. s.s FT 1000 *****-*-***--

Seg 17, 8.0

8.8 FT 400 1000 2000 3000 . 4000 5000 6000 7000 8000 p. 14.FIG-63 TIME. SECONDS AmerGen TMI -UNIT 1 UPDATE -15 4/00 HPI LINE BREAK HOT CHANNEL CLAD TEMPERATURES (OPERATOR ACTION) CAD FILE: 6599R15.DWG FIG 14.2-41

,--

Hotle; 2000 -*-*-* Intact SG Secondary

-**-**-**-***

Brok.en SG Secondary --* ---* -* -CFT 1600 1200 80 i 800 ----------***-----------------------------**-----------------*

40 400 0------------------------------------------------

.... 0 0 1000 2000 3000 4000 5000 6000 7000 8000 p. 14.FIG-64 TIME. SECONDS AmerGen TMI -UNIT 1 UPDATE -15 4/00 HPI LINE BREAK SYSTEM PRESSURE (NO OPERA TOR ACTION) CAD FILE: 6600R15.DWG FIG 14.2-42 28 24 20 t: 16 0 12 :I 8 4 0 0 1000 2000 p. 14.FIG-65 LEGEND 8.0 Downcomer

---*-* Core Composite 7.2 6.4 5.6 2: 4.8 ... .. .. 4.0 g ----*-*-*

a 3.2 :l 2.4 1.8 o.a o.o 3000 4000 5000 . 6000 7000 8000 TIME. SECONDS Amer Gen TMI -UNIT 1 UPDATE -15 4/00 HPI LINE BREAK COLLAPSED LIQUID LEVELS (NO OPERATOR ACTION) CAD FILE: 6609R15.DWG FIG 14.2-43 20.0 17.5 15.0 ti: 12.5 10.0 7.5 :I s.o 2.& o.o 0 1000 2000 p. 14.FIG-66 Hot Channel 5.6 ---*-* Average Chamel 4.8 4.0 :E 3.2 g It! 2.4 :E 1.8 o.a o.o 3000 4000 5000 eooo 7000 8000 TIME. SECONDS AmerGen TMI -UNIT 1 UPDATE -15 4/00 HPI LINE BREAK MIXTURE LEVELS (NO OPERATOR ACTION) CAD FILE: 661OR15.DWG FIG 14.2-44

,,,-1750 1500 1250 u. f 1000 I 760 500 250 0 0 1000 2000 p. 14.FIG-67 LEGEND ----Seg21,11.2*12.0FT

-*-*-* Seg 20, 10.4

11.2 FT -**--*-* Seo 19, 9.8

10.4 FT ********-*

Seg 18, 8.8

9.8 FT eg 17, 8.0

8.8 FT r . 3000 4000 5000 TIME, SECONDS 6000 7000 Amer Gen HAI -UNIT 1 1200 1000 400 8000 UPDATE -15 4/00 HPI LINE BREAK HOT CHANNEL CLAD TEMPERA TURES (NO OPERA TOR ACTION) CAD FILE: 6611R15.DWG FIG 14.2-45 TMl-1 UFSAR Summary of SBLOCA PCT Spectrum -Limiting Break Range 1500 1400 1300 1200 1100 1000 900 800 I I I , I I I I : 1444F: : .,...,., ....................................

.,.i t i ' I I I I -----* -* .* --, ---.* ---*-*-* *-* .*. -r--.**.*. ----** --... --------.. ---,--* -. I I I I I '

I f > ------***

t I I l I ' . 1 I ---------*

... --------1-*. -----**.. ** .. t , -I I ' ' l --,---------*--r-----------, . ' I ;

' ' I -&--'6-8.ffTP wl EOTSG (LOOP) 700

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

__ ..._..._ __

__ _.., ____ ...___.__....--1----

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

--11--..__._

__ _....--4 0.00 0.02 0.04 c.oe Break Size (tr) 0.08 0.10 0.12 TMl-1 Updated Final Safety Analysis Report SBLOCASPECTRUM-PCTVERSUS BREAK SIZE Figure 14.2-68 Rev. 20, 04/10 p. 14.FIG-68 0 0 Node No. 1 2 3 4,14 5,15 6,16 7,17 8,18 9,11,19 10,12,20 13 21 22 23 CFT 3 4 2 ) 13 @ 6 23 @ @ 3 0 CD Identification Down comer Lower Plenum Core Hot Leg Piping SG & Upper Head Steam Generator Tubes Secondary,SG SG Lower Head Cold Leg Piping Cold Leg Piping Upper Downcomer Pressurizer Containment Upper Plenum Note: Additional Data Not Shown on Diagram are: Node 22 Is Containment Node Path No. 1,2 3,4,18, 19 5,20 6,21 7,22 8 9,13,24 10,14,25 11,12,15,16,26,27 17,31 23 28,29 30 32 33,34 35,36 37 Path 33 Is Leak Path From Break Node to Containment Path 34 Is Return Leak Path From Containment to Break Node Path 37 Represents Containment Spray System 2 p. 14.FIG-69 21 @ @ @ @ 20 Identification Core Hot Leg Piping Hot Leg.Upper SG Tubes SG Lower Head Core Bypass Cold Leg Piping Pumps Cold Leg Piping Down comer LPI 14 Upper Downcomer Pressurizer Vent Valve Leak & Return Path HPI Containment Sprays 15 17 16 Craft 2 Noding Diagram for Small Break CADD fS1B,SKM,00,0341,000-, 1400 Update-14 4/98 Fig.14.2-47

.. * * * * ... .. ... ... ... * * * .. 110 ****-**-****

.,-o-,.. *'

,.....--....o-.

o--io-.o--o-*-...

"' /. --------: 1" / \ 6111 ___ ... I \ la : 0 .. .... , -; .* I I

.... "-: 0 ,, *** """ : '1. .,. , ' ... .. : .... "/ , . f 4:ao ,.... !\. ,' .... I0*:11 ... y ' : +

i " I io .. t 'I / -----*-. / ,.,,

o; , & I / ,.'1_-:.-*.....-

.,. / ---*--. 0// .--* 21 .. *--,,-*--I I .._ ____

_____ .._. ____ _... __ _. ..... I ,,, aaa p. 14.FIG-70 1%DD uaa . tla, HC zaaa %100 UPDATE -14 4/98 BREAK SPECTRUM -AVERAGE SYSTEM VOID FRACTION WITH THE RC PUMPS OPERATIVE AND 2 HPI PUMPS CAD FILE: 6602Rl4.DWG FIG 14.2-48 2500 2000 .. .. . .. 1500 .. * .. .. * .. .. 1000 ,-* -PRESSURE VS TIME*Sllll BREAKS llTH AUXILIARY F££01ATER

.,,-----, ""'*'; ' ,,,-' ' ,#" ' ' ' \ \ \ IDD 1000 1500 2000 2500 3000 Tl*, SIC CAD FILE: 6603Rl4.DWG

p. 14.FIG-71 3500 4000 UPDATE -14 4/98 FIG 14.2-49

-.. .. ... .. .. .... .. :a M ... .. .. * .. ,,-PRESSURIZER LEVEL VS TllE*SIALL BREAKS llTH lUllLllRY FEEDIATER 100 10 IO ,0 20 I

SDO p. 14.FIG-72 I ,) , / // / / 1000 1500 2000 2500 11M, HC I I I I I I I . I ' I I I I 3000 3500 UPDATE -14 4/98 PRESSURE LEVEL VS TIME -SMALL BREAKS WITH EMERGENCY FEED WATER CAD FILE: 6604Rl4.DWG FIG 14.2-50

,*---* -* * .... .. --* * -... .. * ... -.. * .. .. * ..

PIESSUllZER LEYtl VS TINE FOi SllAll llEAI IN PIESSUllZER 15 *

21 , ________________

..._ ________ _, I ZDD 411 ... na. aC'* IDD IDDD UPDATE -14 4/98 PRESSURIZER LEVEL VS. TIME -SMALL BREAK IN PRESSURIZER CAD FILE: 6626Rl4.DWG FIG 14.2-51 p. 14.FIG-73 2400 2200 .. -2000 M . u ... :I M M u ... 1800 a.. 1600 1400 1200 0 500 p. 14.FIG-74 tOOD 1500 Tl*1 (SIC) 2000 2500 UPDATE -14 4/98 0. 01 FT2 COLD LEG BREAK WITH NO EFW a STUCK PORV AT 20 MIN-NODE 14 PRESSURE VS. TIME CAD FILE: 6627Rl4.DWG FIG 14.2-52

.,,..._ ..--.. u _, a -::a f:I' _, 60. 000 50.000 40.DOD 30.000 20.000 10. ooo* OL-Jc=:::=:......1-

____ _._ ____

D SOD p. 14.FIG-75

\ODD HaOD Tl** (UC) ('CIPU UNIT I llUCL*All 2000 UPDATE -14 4/98 0.01 FT 2 COLD LEG BREAK WITH NO EFW Z HPl'S a STUCK PORV AT 20 PRESSURIZER LIQUID LEVEL CAD FILE: 6628Rl4.DWG FIG 14.2-53 2:,00

....... """ u ... u _, a ::a D' _, 11. 000 14. 000 12. 000 10.000 I.ODO I.ODO 4.000 2.000 ___ _....._ __ __.. ___ --"-----'-----'

0 500 p. 14.FIG-76 1000 HOO Ti81 (UC) 2000 2500 UPDATE -14 4/98 0.01 FTZ COLD LEG BREAK WITH NO EFW Z HPl'S a STUCK PORV AT 20 MIN-UPPER PLENUM LIQUID LEVEL CAD FILE: 6629Rl4.DWG FIG 14.2-54 SO.DOD 40.000 30.000 20.000 10 .ODO D .SOD p. 14.FIG-77 1000 1500 Tl** (sec) 2000 2500 UPDATE -14 4/98 0.01 FT2 COLD LEG BREAK WITH NO EFW 2 HPl's & STUCK PORV AT 20 MIN-PORV LEAK FLOW CAD FILE: 6613Rl4. DWG FIG 14.2-55

... ... --.. a .. Q, -.. 1. 200 r-------------------

1.000 .800

100 .400 .200 0 D 500 p. 14.FIG-78 1001 1500 Tl** (UC) ('CIPii UNIT I *UCL*A* 2000 UPDATE -14 4/98 0. 01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPl's & STUCK PORV AT 20 MIN-PORV LEAK FLOW QUALITY CAD FILE: 6614Rl4.DWG FIG 14.2-56 2500

"'"" -a -M ....., u u WI *

D ...... 35.0DO 30.000 25.000 i---_ .. 20. 000 -15.000 JO.ODO -Jl,i 1 .. I lt-. .. . 1 5.000

.. Iii .. II g.__ ______ _,,,1 ________

D SOD 1001 1500 2000 2500 p. 14.FIG-79 Tl** (nc)

UCL*All UPDATE -14 4/98 0. 01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPl's & STUCK PORV AT 20 MIN-COLD LEG BREAK FLOW CAD FILE: 6615Rl4.DWG FIG 14.2-57

-.. ::a er

Q. -1. 200 1. 000 -.100 -.&DD -. .400 -.200 -D A

D 500 p. 14.FIG-80 .

IDDD I 1500 Tl** (SIC) I 2000 UPDATE -14 4/98 0. 01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPl's a STUCK PORV AT 20 MIN-COLD LEG BREAK LEAK FLOW QUALITY CAD FILE: 6616Rl4.DWG FIG 14.2-58 2500

--2000 ... .. 1500 . * -* ... ... IDDO

sao / SIALL Q) __ L __ _ a ________________

..... ____ ._ __________________

___ a IGO 1aao p. 14.FIG-81 1saa 2000 2saa 3Daa Tl*. SIC 3500 4000 UPDATE -14 4/98 SYSTEM PRESSURE VS. TIME -SMALL BREAKS W/O EMERGENCY FEEDWATER CAD FILE: 6617Rl4.DWG FIG 14.2-59

,-100 -* 10 * ... -.. ... -10 ... * .. .. * -* 40 .. 21 I D r---11 ZEID" nru I I I I I I I I I I ' I saa 1GDO p. 14.FIG-82 ONLY FOi SllALL CLASS 3 1511 2DGI zsaa Tl*. llC ('CIPU UNIT I *ucL*A* 3000 llUlS HOD 4000 UPDATE -14 4/98 PRESSURIZER LEVEL VS. TIME -CLASS 3 BREAKS W/O EMERGENCY FEEDWATER CAD FILE: 6618Rl4.DWG FIG 14.Z-60 ID' 100 * .. -10.' .. ""' 0 = c 0 -... "a 10*2 .. m: -"' .. -Cl 10*3 hclusion Dasunce I I I lO*Dly Don 2-Hour Dou 10DD 20Da lDGD 4011 5111 HID Distance Fra11 £d11 1t l11ctor luildina.

ft. p. 14-.FIG-83 UPDATE -14 4/98 INTEGRATED DIRECT DOSE FOLLOWING MHA WITH 3-1/2 FT. REACTOR BUILDING WALL THICKNESS CAD FILE: 6619Rl4.DWG FIG 14.2-61 TMI UFSAR

Figure 14.2-62 Deleted

) FROM RC PUMPS FROM CORE FlOOO TANK 18 Cf-V4B Cf-V5B OH-Vl DH-V2 p. 14.FIG-85 RC-V1 RC-VJ RC-T-2 RC-T-1 Cf-VSA Cf-V4A OH-V62 OH-V63 DH-V69 DH-V64 DH-V22A DH-V4A DH-V22B DH-V4B DH-V3 OH-V12A DH-V68 REAC. BLDG. SUMP DH-V6A BS-V3A 2 DH--V19A DH-V38A DH-V388 DH-V198 OH-V128 DH-P-18 2 is SS-VJB DH-P-1A NOTES 1. VALVES ARE SHO'M-1 IN TYPICAL POST LOCA POSl110N 2. ARROWS W//l INOICATE TWO ACTIVE FLOW PATHS FOR RV BORON CONCENTRATION CONTROL BWST UPDATE -14 4/98 POST LOCA BORON CONCENTRATION CONTROL FLOW PATHS CAD FILE: 6550RO.DWG SHEET I OF I FIG 14.2-63

ML18117A432

Text

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