ML16127A476
Text
{{#Wiki_filter:',,-80 Neutron 60 Power.I 40"0 200C1*60 Thuma I 40 Power.I 20 0....-/Fue I Temper atur e Chanal.F 400 300 200 100 o l-4 Sec-J 12 Aver aal Cor I Moder Itor 8 TempIra ture Chana'.F 4 0 2600 Reactor 2500 Srstlm 2400 Pressurl.-4.*ps IIca::l 3: 2300 a DI c:..'1:t-2200 c:en n f>!:!.:.Z CIaa.,.. I C n...n -Daa a I C;a.51aCt..c:*'1:t c.a::::z:=_.DI ca-:rC'D."a...." CD QI c: C'D.."....cE'C'D c: "a-a........I>>-.........,...m-CO*N... CI CI 1ft CI----CI CI PI-CI 1ft PI N CI CI*-CI CI CI CI CI-CI CI CI CI PI-til**ca.a;:IU-.-.--a-*c*.;*-...--a....:-..-*a I!:I=E-*..-*--*til-:*ca.c-*ca.c u-M:I**.....*E....M**aa:I*..a**--z ca.-ca.-u c*-U IIIC M ca.Update-1 7/82 lffil!]Nuclear 1MI Unit-1 Startup Accident from 10-9 Rated Power using all Rods with a Worth of 10 1/.AK/K;High Flux Reactor Trip is Actuated)p.14.FIG-2 Fig.14.1-2 ..c M CI....-0Z-0 M 0_--IlIA:--t-----.0+---- .......-----1 e'" c..J_-- .-...............,ji.-.................0\J o 0::: ClI....p.14.FIG-3't**TherMal Pftwer , Peak Thermal Power vs.Rod Withdrawal Rate for a Startup Acciden t from 10-9 Rated Power CAD FILE: 6555R14.DWG CIt UPDATE-14 4/98 FIG 14.1-3 ('"')I o Q....-C Q CL (,,)Q U....-CJIC'C-Q U"" CK 0*""'-..-.-"-.-*-U-,.CK ,.*,.....'C.c--*'C a czI 0 Peak Neutron POler,\0]!]Nuclear TMI Unit-1 Peak Neutron Power vs.Rod Withdrawal Rate for a Startup Accident from 10-9 Rated Power p.14.FIG-4 Update-1 7/82 Fig.14.1-4 '-'\i\\\\\-...c:-*0*1\\\=*..*..-**-****..**..**N t-&-Z*W U LL LL W 0 0 u-a:::: 0 t-<<N a:::: w*0*0::E..***-*-**-.'I" Ttt"***'***r, , UPDATE-14 04/98 p.14.FIG-5-CAD FILE: 6556R14.DWG FIG 14.1-5 , J I)-..c-*0 z J-V I/*"" 10 JC M....'-...,.-..'-...,...--c:: N U-U---U 0...u 8: 0 C2IQ IQ I CIt.....CIt*Q'" Gil!]Nucle.r TMI Unit 1 Peak Thermal Power Versus Doppler Coefficient for a Startup Accident Using a 1.50/0 flKlK Rod Group at 1.09 X10-4(flKlK)/S From 10.9 Rated Power Update*8R 3/90 Fig.14.1-6 p.14.FIG-e ,'---,)v j-fa c:*0 z I J/CD'"***It)I M 0 X N-*C Q)*u:.;:-Q)0 U L Q)0.0.0 a e::t-p.)4.FIG-7 (crPii UNIT I NUCL.A.Peak Thermal Power vs.Doppler Coefficient for a Startup Accident Rods at 7.25 x 10-4 Ak/k)S from 10-9 Rated Power TITLE LINE 2 CAD FILE: 6557R14.DWG UPDATE-14 04/98 FIG 14.1-7 \ \i 1--------+---- \\\Pell Ther**1 Po.er, I N-+Q..-+CD Q+CD a+*la M*'-..a-+'-..4--N-C Q u+u--u Q 0 U Q...0-......U N0 Q*I*Q , CD Q ,-a I Q M p.]4.FIG-8[[il!J Nuclear TMI Unit-l Peak Thermal Power vs.Moderator Coefficient for a Startup Accident Using all Rods at 7.25 X 10-4 From 10-9 Rated Power Update-1 7/82 Fig.14.1-8 IIll1t ,..'111', I 110 ThUI 100"-rOil', I eo"-ID 70 I I I I I Fill're8,,, It 1111 CllIn." F h"'.1 c",*...".t., T..,.,.tII,.CIlU.I, F".ct., S,lt..r'II...II,'I" 80 40 2038 2.5 2.8 15 1.8 8.5*.* ......_-"--_.......__....TI.., Sic p.14.FIG-9 0:W!J Nuclear TMI Unit-1 Rod Withdrawal from Rated Power Using a 1.5%6K/K Rod Group at 1.09 X 10-4 (6K/K)/S;High F lux Reactor Trip is Actuated Update-1 7/82 Fig.14.1-9 2500 A II Rolls'0*4 hd l,thclrlUI lUI, (A.kjK)/SE.C 2200 HOC ,......,-........c-..'C Sinale Control...!toll'roup 2300 ,,-..0:iX!I Nucle.r TMI Unit 1 Peak Pressure ys.Rod Withdrawal Rate for a Rod Withdrawal Accident from Rated Power Update*SR 3/90 p.14.FIG-10 Fig.14.1*10 ..-ca Q.." U U Q us-u II.-:>>ootQ U Q C1....., I:'N Q Q Q CI CI CI Q Q.., N Q..,..,..,..,.., N N N N N Pe.k Pressure.psia P.14.FIG-ll Gil!J Nuclear 1MI Unit-l Peak Pressure vs.Trip Delay Time For a Rod Withdrawal Accident from Rated Power Using a 1.5%...:JK/K Rod Group Update-1 7/82 Fig.14.1-11 2400 I."..--2390 2380 2370 2360en 2350 Cl.Q,):J 2340 en en Q,)CL 2330cu CL 2320 2310 2300 2290 2280 2270 J//V J//v J , JNominal/V/V-0.8-I.0-I.2-I.4*1.6 Update-1 7/82 p.14.FIG-12 Do PP Ie reoef fie i ent, (A k/k)'Fx1 0 5 0]!J Nuclear 1MI Unit-1 Peak Pressure vs.Doppler Coefficient fo.a Rod Withdrawal Accident from Rated Power Using a 1.S D/D 6K/K Rod Group Fig.14.1-12 2380 2360V>>C.cu 2340...::::s V>>V>>cu...23202300 2280'"'\"'" Nominal-..............-0.6-0.4-0.2 0.0*0.2.0.4.0.6.0.8 Mocerator Coefficient. (6k/k)/F x 10 4 BE Nuclear TMI Unit-1 Update-1 7/82 p.14.FIG-13 Peak Pressure vs.Moderator Coefficient for a Rod Withdrawal Accident from Rated Powr Using a 1.5%6K/I(Rod Group Fig.14.1-13 120 I 10 laxlmum Neutron Pow.r....100&l*0 CL'CI&l-...ex 90-0..--....&l*0 CL80...&l CL IUI.u.Ther.11 Power 70 60 25 50 75 Initial Pow.r, , of tlt.d Pow.r BimNuclear 1MI Unit-1 Maximum Neutron and Thermal Power for an All-Rod Withdrawal Accident from Various Initial Power Levels IDa Update-1 7/82 Fig.14.1-14 3000 2800Ii)2600....<<JIi)c.E 2400 Ii)....cuE 1600E M<<1*1400 1200 10001/Maximum Temperature in Hottest Fue I Rod At The Hot Spot<-//aXlmum Average FuelTemperature t ,.......a 20 40 60 80100120----------.---.--..-_.Initial Power, , of Rated Power TMI Unit-l Peak Fuel Temperature in Average Rod and Hot Spot for an AII-Rod Withdrawal Accident from Various Initial Power Levels p.14.FIG-15 Update-1 7/82 Fig.14.1-15 --80 70 Neutron"'0 Power,%60.....50a I 110.....0"-30 65 Thermal 60 Power55 50 0.0*I-5.0 II L------------------------.I +5.0 I Change In Average Moderator T_p.rature,F -10.0 , , , , , , , , Reactor Coolant 2350 Pr."ure,p,ia enim, cc*"C:I C_I=C:I Z c:_."C:I ,..5-I....c a-en I c...-a 0 I CD..I>>:::I Q."" c: cP'"C a.-I>>ora.......,..-............ CI)I co I-en N..21100 2300 2250 2200 o ,*2 II 6 Tillie, Sec I 10 12 III 100 80---*a.......,80*a a ua...., u*,--u-=40 20 i\\r I*70,000 Ib-ft 2'"""'lIlllil '"'-......, a o 4 8 Tilll, SIC 12 16-p.14.FIG-17 0i!l Nuclear TMI Unite'Percent Reactor Coolant Flow as a Function of Time After Loss of Pump Power Update-1 7/82 Fig.14.1-17 2.0 18 c*1.6 0'CIIon ca 0 Co.)42'at C-...1.4:::I Q a: 51 flol loss a:a z (Vent Valve Stuck Open)Q E:::I*.-1.2 c.-*1.0 100 102 104 106 108 110 112 114 Overpoler at Inicn Coastaoln Blains., Iai!lNuclear TMI Unit-1 Update-1 7/82 p.14.FIG-18 Minimum DNBR Which Occurs During Coastdown From Various Initial Power Levels Fig.14.1-18 2.0 I.8 0 1.6.-+J.., GI: CD Z Q u c 1.4 c.., J::(.)+J 0%I.2 I.0 0.0 0.4 0.8 1.2 1.6 2.0 ,/-Time Seconds 0i!J Nuclear TMI Unit-1 Update-1 7/82 p.14.FIG-19 DNB Ratio Versus Time for a Locked Rotor Accident from 102%of Rated Power Fig.14.1-1 9 -'.......... ---......-'110 100 THEII4Al 90 POWER l 80 70 60 50 1&0 30--10010 It EUf ROil 10 POWER l 70 60 50 1&0.....-rja I N o"'C AVERAGE COlE MODERATOR T04PERATURE. f 586 581&582 580 578 576 571&572 I>>0 im c*omC::I Z:a.......::;'0&=:a I c:r"o...-:.rc I ,.....o Q-a 01_..0...*:3 c:a eta I>>a ,..I>>eta=a.a.-o-'0=-CIt CN'"&a en-a::.'-::r'" AI oI=It ,..-" CD.CO I N N...,0-2280 2260 REACTOR SYSTEM 22l1O PRESSURE ,Ii.2220 2200 2180 2160 21'10 0 5 10 15 20 25 30 TIME.SEC ),If I J J/I*o N o o o..o*"" o o"""" o"""" N o.."""" o.."""" o*"" N o o.., N......1ft......1ft*....1ft o*1ft N*1ft ,.,*1ft..*lit***olit o 1ft o*o....o*o fa o o o o*o....o*o a-o o o)*o-.....,......"'0...p.14.FIG-21..,...., oc.,)_=-0'"..,...C oc_c_...-.."'OZ>0'" CZ'"...-oz=--...-c.,).c...........Bi!J Nuclear TMI Unit-1 0.36'1. Rod Drop from Rated Power with Automatic Runback to 60°/, Demand in 12$Update-1 7/82 Fig.14.1-21 650.0 4000.0 .......-HIIU"--CClId lAg 600.0-*:J'0550.0 EQ, o o..J!500.0:;.!!c-------3000.0**o EL 2000.0 c: e'S*z 450.0 1000.0 Time (s)100.0 80.0 60.0 0.0 .........--.........----L--------.J 0.0 20.0 40.0 400.0 L..-____...L..____'____.....L_........._____'_____J.._I 0.0 20.0 40.0 60.0 80.0 100.0 Time (s)2500.0 650.0 r---....----,.---.....---....,-------......,..-.---.-----r------.------HIlt....--CeId lAg 2000.0-';;..e*III c: 0 Q, III., 1500.0;:)III III*0: 1000.0-........--, HIIt....--UrIouIled Hat lit 60().0 S III;:)'0550.0 Q, EQ, o o..J 500.0:;D".....-..._-_...--------450.0 100.0 80.0 Time (S)400.0 1:--_"'--_ ........---L---------'-----a..--..J 0.0 20.0 40.0 60.0 500.0 L...-__'"--__.A--__..o...-__..I.--L..--L.__--a..__--J 0.0 20.0 40.0 60.0 80.0 100.0 Time (s)AmerGen TMI-UNIT 1 UPDATE-15 4/00 DOUBLE-ENDED RUPTURE OF 24 IN.STEAM LINE BETWEEN STEAM GENERATOR AND STEAM STOP VALVE (WITH FEED WATER ISOLATION) p.14.FIG-22A CAD FILE: 6710R15.DWG Fig.14.1-22A 1500.0 5000.0 __4000.0 Faulted SG'--............. SG1000.0 ,------------I---0---'iii------------...3000.0--------........1!::J..*0 CD Q:C)V)Lo..2000.0 500.0 1000.0 ,......SG 0.0 0.0 0.0 20.0 40.0 60.0 80.0 100.0 0.0 20.0 40.0 60.0 80.0 100.0 Time (s)Time (s)&0000.0 r------.-----,.-----------r---...---""T"'------..,.---......-----. UPDATE-15 4/00 AmerGen TMI-UNIT 1 100.0 80.0 """"""""" 0.0 .......... --...L------..a......--"""---J 0.0 20.0 40.0 60.0 20000.0 40000.0o:I (,)V)Time (s)DOUBLE-ENDED RUPTURE OF 24 IN.STEAM LINE BETWEEN STEAM GENERATOR AND STEAM STOP VALVE (WITH FEED WATER ISOLATION) p.14.FIG-22B CAD FILE: 6713R15.DWG Fig.14.1-22B 1500.0 1000.0 500.0 2000.0--IL....._ ___L___I.__L.__A..__'0.0 2600.0 -c'iii2400.0::J en en cuQ.ao.!:!'0:z: CI)2200.0 0 ,..--Q: Time (s)AmerGen TMI-UNIT 1 UPDATE-15 4/00 ,"-'-RCS HOT LEG PRESSURE (psia)RESPONSE FOR LOSS OF ALL AC POWER (STATION BLACKOUT)p.14.FIG-23 CAD FILE: 6705R15.DWG Fig.14.1-23 TMIUFSAR Figure 14.1-24 Dropped Rod wI Bayonet Failure-ReS Pressure Response (NOTE 1)NOTES: 1.CVOL 110-4 and 210-4 represent hot leg pressures. CVOL 352-1 represents the core exit pressure.TMI-UNIT 1 REV.19, APRIL 2008 p.14.FIG-23A Dropped Rod wi Bayonet Failure ReS Pressure Response FIGURE.14.1-24 TMIUFSAR Figure 14.1-25 Dropped Rod wi Bayonet Failure-Reactor Power Response TMI-UNIT 1 REV.19, APRIL 2008 p.14.FIG-23B Dropped Rod wI Bayonet Failure Reactor Power Response FIGURE.14.1-25 TMIUFSAR t If:!.Jj: 80 F**:**.::..****':***,'**'.;;;:
- .'1'" 70 1*,*******0;**,
- ,*:**,:,*;**,****,**
..*******..,*:* ..,:";;*..::::::t', ,***,.*****..***H*::*'Figure 14.1-26 Dropped Rod wI Bayonet Failure-Primary Temperature Response TMI-UNIT 1 REV.19, APRIL 2008 p.14.FIG-23C Dropped Rod wi Bayonet Failure Primary Temperature Response FIGURE.14.1-26 10-3 Rated Power ,Hal 10-3 Rated Power,EOl Nominal No Xenon Nominal I,th Xenon Rated POler, EOl Rated Paler I Hal 100 1000 c: o+-':::J III Z)Control Rod lorth, , l.\k/k 10 o 0.2 0.3 0.4 0.5 0.6 o 1 o 8 0]!]Nuclear TMI Unit-1 Update-1 7/82)Peak Neutron Power Variation With Ejected Control Rod Worth Fig.14.2-1 1000 Nominal 11th Xenon 100 Rated POler, EOL Hllh Pressure;;T rip*0 1110.1 na I A..IQ E I., 10.3 Rated z::.....¥IQ., A..No.'na I 10 Hllh Hllh Pressure Flul Trtp T rip o I 0.2 0.3 0.4 0.5 0.1 o 7 o 8 Control Aod lorth,\6k/k BE Nuclear 1M I Unit-1 Update-1 7/82 Peak Thermal Power as a Function of Ejected Control Rod Worth p.14.FIG-24 Fig.14.2-2 240 E"-.C'Q Rated Power,BOl u 200"C (;)Nominal a: lith eu Xenon:J 160 u......Rated Power ,EDl In........120 (;)Nominal%....No llnon (;)u..Hiah Prlssure Tr--Hlah Flux Trip>.80 ,-.NO.lnal CQ 10-3 Rated Power,BOl.&:....10.3 Rated Power, EOl c='\40 CQHiah Pressure 0 0.2 0.3 0.4 0.5 0.&0.1 0.8 Control Rod lorth, , 6k/k raE Nuclear TMI Unit-1 Update-1 7/82 Peak Enthalpy of Hottest Fuel Rod Versus Ejected Control Rod Worth p.14.FIG-25 Fig.14.2-3 10.3 RJted Power.EOl.Rat.d Pow.r, BOl Rated POlar.EOl 100 1000 10.3 Rued Pour.BOl (Hllh Pr.ssur.Trip)*2 2-2.°.I.1.1.1.4.1.2.I.D-0*10 Doppler Co.fflclent, (Ak/k):F I 10 5 Fig.14.2-4 Update-1 7/82 1MI Unit-l Effect on Peak Neutron Power of Varying the Doppler Coefficient for an Ejected Rod Worth of 0.56%6K/K at 10-3 Rated Power and 0.46%6K/K at Rated Power p.14.FIG-26 lla 140 Nominal L Rated Paler.SOL-120 1 I Nominal Rated POler.EOl 100--u*10 a a....Eu.c....60-'-'-...U A.- 10-3 Rated Paler ,lOL-I(Hilh Pressure Trip)--+_Na.ina'7 I 40 20 o-0.1-1.0-I.2-I.4 10-3 Rated Po.er.EOl I I-1.1-1.1-2.0 Do p pierC oe f fiei*nt, (Aklk)I F I 1 0 5 Update-1 7/82 Bi[J Nuclear TMI Unit-l Effect on Peak Thermal Power of Varying the Doppler Coefficient for an Ejected Rod Worth of 0.56% at 10-3 Rated Power and 0.46%6K/K at Rated Power p.14.FIG-27'--F_ig_. -lOOO a, ted'ow.,.EDl 10.3"t.d',**f.IOL tM'I-',.sIur.,r,p)*3.*2 a'11 a.a.1 a Moderator coefficient@lF x 10-4*f I.0 10 taO..*o&.c a...:2 I*......UPDATE-14 04/98 Effect on Peak Neutron Power of Varying the Moderator Coefficient for an Ejected Rod Worth of 0.56% at 10-3 Rated Power and 0.46%Akk at Rated Power p.14.FIG..28 CAD FILE: 6558R14.DWG FIG 14.2-6 140 1 I 120 Rated io,er, EOl'-Noml na I Nominal_I..--Rated POler,BOl 100.......cu*0 80CQ E....cu.c60.., cu-40 20 I-o NaIll na I 1 I 10.3 Rated POler,BOl V (H1ih Pressure Trip) I---4.0-3.0-2.0-1.0 0.0+1.0+2.0+3.0 Moderator Coefficilnt,(Ak/k)/F x 1Ii 4 Update-1 7/82 Fig.14.2-7 G]!]Nuclear TMI Unit-1 Effect on Peak Thermal Power of Varying the Moderator Coefficient for an Eiected Rod Worth of 0.56%6K/K at 10-3 Rated Power and 0.46%6K/K at Rated Power p-14.FIG-29 140 120 100..-.*0 80 ICL."I E60"I-,-...ICL.40 20 o.I , Rated POler,BOl-:L No_inal---Rated
10.3 Rated Paler, BOl (Hilh Pr'essure Trip),\I , ,\...-No.inalNo.ina I-':J 10.3 Rated POler I EOl 1 0.0 0.2 0.4 0.6 0.*1.0 Trip Delay Ti.e, Sec 0:ir!]Nuclear TMI Unit-1 Update-1 7/82 Fig.14.2-8 p.14.FIG-30 Effect on Peak Thermal Power of Varying the Trip Delay Time for an Ejected Rod Worth of 0.56%oK/K at 10-3 Rated Power and 0.46%6K/K at Rated Power 6.0 5.0 m z Q4.0 u c: cu...cu CL)oC 3.0 u.I cu...0 u2.0 1.0 0.0 0.2 0.3 0.4 0.5 0.6 0.7 Control Rod Worth, S6k/k I:ai!l Nuclear TMI Unit-l Percent Core Experiencing0NB as a Function of Ejected Control Rod Worth at Rated Power, BOL p.14.FIG-31 Update-1 7/82 Fig.14.2-9
.-INITIAL RCS AND CORE PARAMETERS o<TIME<EOB EOB*END OF.LOWDOWN EOAH*END OF ADiAIIA nc HEA TUP EOE*END OF EVENT MASS AND ENERGY RELEASE 0<TIME<EOE CORE STORED ENERGY SYSTEM MASS AND ENERGY ACCUMULATOR MASS AND ENERGY STEAM GENERATOR MASS AND ENERGY MASS AND ENERGY RELEASE REFLOD3B EOB<TIME<EOE CONTAINMENT PRESSURE FLOODING RATE UPPER PLENUM PRESSURE CORE INLET TEMPERATURE EOBCOREPARAMETERS",," BEACH ,.(RELAP5IMOD2-B&W) EOB<TIME<EOE W METAL WATER REAcnON HOT PIN THERMAL RESPONSE PEAK CLADDING TEMPERATURE UPDATE-14 4/98 LARGE BREAK ANALYSIS CODE INTERFACES p.14.FIG-32 CAD FILE: 6573R14.DWG FIG 14.2-10 3200 2800 2400 0Q)2000::J 20 8tu/hr F t2-F...euQ)Q.e G>.-1600 u eu u...0 Q.h V).....1200 0%:800 400 50 140 30 20 10......l................"""'_.._...o Time After Rupture.Sec p.14.FIG-33 Bi[I Nuclear TMI Unit-1 Hot Spot Clad Temperature V5.Time for a 36 in.10, Double-Ended, Hot Leg Pipe Rupture and Variable Quench Coefficient Update-1 7/82 Fig.14.2-11 28 24 20 16 12 8 4-------------------------....&.0 32TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL)-REACTOR VESSEL UPPER PLENUM PRESSURE p.14.FIG-34 CAD FILE: 6574R15.DWG FIG 14.2-12 x10*xl0*10 LEGEND RV Side 4 8------Pump Side re 36 e"i4 20....en en en 2 1 CI')i<--_.".".."_."."""............. 0 32 28 241216 20 TIME, SECONDS 8 4 o Am er Gen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL)-BREAK MASS FLOW RATE p.14.FIG-35 CAD FILE: 6575R15.DWG FIG 14.2-13 2400 500 w 1000 Ii i7501250 1500----Fuel, Seg 6_._-_.Clad, Seg 6 2000 1.", 1600 (\/ Y..'v\wi.a::'\,1200*.,I, 800*\I 400\ 240 200 160 120 TIME, SECONDS 80 40 o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-2.506-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-36 CAD FILE: 6576R15.DWG FIG 14.2-14 2400...-----------------.....----- LE""""'G!""""'E..,..ND...,...-----. 2000 1600 u.1 1200.800 400----Fuel, Seg 10---._.Clad, Seg 10 1500 12501000i 750500 240 200 160 120 TIME.SECONDS 80 40 o Jo..--------I o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (SOL-4.264-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-37 CAD FILE: 6577R15.DWG FIG 14.2-15 - 2000 1600..Ii\,I'": I V.i 1200*800----Fuel, SeQ 13----_.Clad, Seg 13 1500 1250 400 500 240 200 160.120 TIME, SECONDS 80 40 0.......------------------------1 o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-6.021-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-38 CAD FILE: 6578R15.DWG FIG 14.2-16 ,,- 2000 800----Fuel, Seg 18----_.Clad, Seg 16 1500 12501000i 750!400 500 240 200 80 120 1eO TIME, SECONDS 40 o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-7.779-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-39 CAD FILE: 6579R15.DWG FIG 14.2-17 -2400 2000 1600 u.H!1200'I 800 400----Fuel, Seg 16------Clad, SeQ 16 1500 12501000760 i 500 ,,,-01..-------------------------4 o 40 80 120 160 200 240 TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-9.536-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-40 CAD FILE: 6580R15.DWG FIG 14.2-18 2400----Fuel, Seg 7--_._.Clad, Seg 7 2000 1600 Y.I"I::>>....1200*800 400\\"'-_"",\., , I , , 1.L....._.1500 12501000750500 240 200 160 120 TIME, SECONDS 80 40 O..a....----------------------- .....o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-2.506-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-41 CAD FILE: 6581 R15.DWG FIG 14.2-19 2400----Fuel, Seg 9_._-_.Clad, Seg 9 2000 1600*"-I'.:::>>...1200 I i 800 400\.\..,.r-......,.-,-\"\i I\I , I L. 1500 1250W 1000i 750500 240 200 160 120 TIME.SECONDS 80 40 0""'----------------------- .....o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-4.264-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION p.14.FIG-42 CAD FILE: 6582R15.DWG FIG 14.2-20 2400 2000 400----Fuel, Seg 12---_.Clad, Seg 12 1500 12501000i750500 240 200 1ao 120 TIME.SECONDS 80 40 0-'------------------------ .....o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-6.021-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION p.14.FIG-43 CAD FILE: 6583R15.DWG FIG 14.2-21
1500 12501000750400 40 80 120 TIME.SECONDS ,---.....
Fuel.Seg'5----_.Clad.Seg,5 160 200 240 Am er 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 p.14.FIG-44 CAD FILE: 6584R15.DWG FIG 14.2-22----,---_.."-------------
2400-ro-----------------------......., 2000!, 600.""./": I'J.I 1200*i 800 1500'2S0 400 .....500----Fuel, Seg'8----_.Clad, Seg 18 160 200 240 120 TIME.SECONDS 80 40 0.......--------------- .......----------1 o-Am er 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 p.14.FIG-45 CAD FILE: 6585R15.DWG FIG 14.2-23
_._._.2.508 It----..4.264ft---8.021ft***************7.77Ift ---9.531ft 2.0 It:: oU c(1.5 II.It:: WGo1.00.5 12 10 8 4 2 o_.UPDATE-14 4/98 LOCA LIMIT AXIAL POWER SHAPES p.14.FIG-46 CAD FILE: 6586R14.DWG FIG 14.2-24 2400...... 160'""-----------t 80----0.01-FT2, CLPD SBLOCA----_.O.03-FT2, CLPO SBLOCA-------_._. 0.04-FT2, CLPD SBLOCA....._..-----0.05-FT2, CLPD SBlOCA**_-_.__.-0.06-"2, CLPD SBLOCA 120'-'"\,°0,,'\"\\\'\.\\\"-\',...\\.'."...\"...,...,"'-...., e,._...___.._.....'---'-",,-- ....."--'"-------..-,..-..--..----'...."""................. ...., -.'-.................................-.-........................--..__..40............ ..---. ..--.................................
- -....._--...._-.........................
._---.-.-.800 400 2000 16001200 I o 1000 2000 3000 4000 5000 6000 TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.01-0.06 FT 2 BREAKS)p.14.FIG-47 CAD FILE: 6587R15.DWG FIG 14.2-25 2400..... 160 2000 i Ii 1200 I----O.07-FT2, CLPD SBLOCA------O.08-FT2, CLPD SBLOCA----O.09-FT2, CLPD SBLOCA...--**----O.10-FT2, CLPO salOCA.'--------------...120 80 40 0.1.------------------------60 o'000 2000 3000 4000 6000 6000 TIME.SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.07-0.10 FT 2 BREAKS)p.14.FIG-48 CAD FILE: 6588R15.DWG FIG 14.2-26 2000 2400.....
0.lS-FT2, CLPO SBLOCA--_._.O.30-FT2, CLPD SBLOCA-**-----.0.50-FT2, CLPD SBLOCA............ CLPD SBLOCA 120 16001%00\\fI)en ,.\\\800*\*\.\\\\, 400 ,'."'\"\\"" ,..........
" 80 40, ,-0"'-----------------------.-.0 o 250 500 750 1000 1250 1500 1750 2000 TIME, SECONDS..AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.15-0.75 FT 2 BREAKS)p.14.FIG-49 CAD FILE: 6589R15.DWG FIG 14.2-27 10 2 Q 5 o5000 LEGEND----O.Ol.fT2.SBLOCA-.._---O.03.fT2 S8l0CA____,I O.04-FT2 SBlOCA********** O.05-FT2 SBlOCA 8*..-..._.-O.06.fT2 SBLOCA 2000 3000 4000 TIME.SECONDS-----------------------..--100 6000 35 30 I 26*1\.t:2016::J 10 6 0 0 1000 AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.01-0.06 FT 2 BREAKS)p.14.FIG-50 CAD FILE: 6605R15.DWG FIG 14.2-28 AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.07-0.10 FT 2 BREAKS)p.14.FIG-51 CAD FILE: 6606R15.DWG FIG 14.2-29 f 35 LEGEND 10 O.'5-FT2 SBLOCA 30------O.30-FT2 SBLOCA-----O.&O-FT2 SBLOCA********** O.7f5.fT2 SBLOCA 8 t::&60a 4:::a:I 10 2 o 250 500 750 1000 12&0 1600 1760 2000 nME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.15-0.75 FT 2 BREAKS)p.14.FIG-52 CAD FILE: 6607R15.DWG FIG 14.2-30 2000 p-.-------- ...... 1200 500 1500 1750----0.01-FT2, CLPD SBLOCA, Seg 18----_.O.03*FT2, CLPD SBLOCA, Seg 19_._**_._....O.04..FT2, CLPD SBLOCA, Seg 20..---------0.OS*FT2, CLPO SBLOCA, Seg 20.....-.-__*0.08*FT2, CLPD SBLOCA, Seg 19 ,-,--------------t !......."",*....-*..----, 1 000!u.1250 J**...)ti".,.....: ',"'"..,,"'..\,.."'i: ,...v/.. /"../"","" ,-,\"...#11\;1' \1000/,/r/I" V\\/(*\.'\800*, I Jf r\-...a:: j:\: '..,'" III 750 I Iii\,".: I Ii::*(.r.f:1.:;::-':'::::: __J'.'-j'1'600**I'....... ..: L ,--0 ..****** ._.250 400 7000 6000 5000 3000 4000 TIME, SECONDS 2000 1000 0.-.--------------------------.. o 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 2000..... .....----0.07.fTZ, CLPD SBLOCA, Sea 19--_._.O.08-FT2, CLPD SBLOCA, S_, 19 1200---,-O.09.fT2, CLPD SBlOCA, Seg 19****--......O.10.fT2, CLPD SBlOCA.Seg 19 1750 1500 i 1250 i 1000 i 750 500 'I,*!tv';fi j I:1.:I:**.,.., I**---"-I*...AJ*:.,.,."'...........,........:lO'Il= ..aP.lIl1Jl...-r. ........... 1000Ll S800 i*800 400 1000 2000 3000 4000 TIME.SECONDS 6000 6000 AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF PEAK CLAD TEMPERATURES (0.07-0.10 FT 2 BREAKS)p.14.FIG-54 CAD FILE: 6590R15.DWG FIG 14.2-32 ..-- 600 LEGEND----0.16-FT2, CLPD SBLOCA, Se;20----_.0.30-FT2, CLPO SBLOCA, SeQ 20 1200--------.0.50-FT2, CLPO SBLOCA, SeQ 19---------- 0.75-FT2, CLPD SBLOCA, SeQ 17 1000ii S 800 Ie400 2000 1750 1500 750 1000 1250 TlME, SECONDS 500 250 2000'750'500 I:: 750 500 250 0 0 ,,--.'AmerGen 1\41-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF PEAK CLAD TEMPERATURES (0.15-0.75 FT 2 BREAKS)p.14.FIG-55 CAD FILE: 6591 R15.DWG FIG 14.2-33 2400 ,..------------ ..... 160 2000----HotLeg------Intact SG Secondary----_._-._-_. Broken SG Secondary------_... eFT 80 40..._--.._---_._----_._---------_.----_ .**-** oL_-===================:d o o 500 1000 1500 2000 2500 3000 3500 4000 TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 eFT LINE BREAK SYSTEM PRESSURE p.14.FIG-56 CAD FILE: 6592R15.DWG FIG 14.2-34 Am er Gen TMI-UNIT 1 UPDATE-15 4/00 CFT LINE BREAK COLLAPSED LIQUID LEVELS p.14.FIG-57 CAD FILE: 6593R15.DWG FIG 14.2-35 20.0 LEGEND Hot Channel 5.6 17.5-----.Average Channel 4.8 15.0 t: 4.0:E12.53.2 H!10.0 II!7.5 2.4:I 2 5.0 1.8 2.&0.8 0.0 0.0 0 1000 2000 3000 4000 5000.6000 7000 8000 nME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 eFT LINE BREAK MIXTURE LEVELS p.14.FIG-58 CAD FILE: 6594R15.DWG FIG 14.2-36 400 600 1000i 800I 1200 4000 3500 3000'500 2000 2600 TIME, SECONDS 1000 SOD LEGEND Se;21,11.2*12.0 FT----_.Seer 20, 10.4*11.2 FT_**_**_**_**.Seg 19, 9.6*10.4 FT_.--_...--.Seg 18, 8.8*9.6 FT.......... -........SeQ 17, 8.0*8.8 FT 1Ai.'..250 o a 500 1750 1500 2000": 1250 H!i,ooo!750 AmerGen TMI-UNIT 1 UPDATE-15 4/00 CFT LINE BREAK HOT CHANNEL CLAD TEMPERATURES p.14.FIG-59 CAD FILE: 6S9SR15.DWG FIG 14.2-37 2400 160 2000 16001200 I/)i 800 400----HotLeg----_.Intact SG Secondary_**--_**__.Broken SG Secondary-----..----eFT 80-
- -----.-****----**--.-.-...40 o 1000 2000 3000 400d 5000 6000 7000 8000 TlME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK SYSTEM PRESSURE (OPERATOR ACTION)p.14.FIG-60 CAD FILE: 6596R15.DWG FIG 14.2-38 2$LEGEND 8.0 Downcomet 24---_._.Core Composite 7.2 6.4 20 t: 5.6:!Ed 16 4.8 af0 4.0 g 5 12§g 3.2 8 2.4-1.8 4 0.8 0 0.0 0 1000 2000 3000 4000 5000 6000 7000 8000 TtUI:
AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK COLLAPSED LIQUID LEVELS (OPERATOR ACTION)p.14.FIG-61 CAD FILE: 6597R15.DWG FIG 14.2-39 20.0 LEGEND Hot Channel 5.6 17.5--_.-.Average Chlnne(4.8 15.0 t: 4.0 212.53.2 10.0 I!!e 7.&2.4 i:i 5.0 1.8 2.5 0.8 0.0 0.0 0 1000 2000 3000 4000 5000 6000 7000 8000 TIME, SECONDS ,-AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK MIXTURE LEVELS (OPERATOR ACTION)p.14.FIG-62 CAD FILE: 6598R15.DWG FIG 14.2-40 1000 2000 3000.4000 5000 6000 7000 8000 TlME.SECONDS 400 1000 1200 LEGEND----Seg21,'1.2-12.0 FT----_.Seg 20, 10.4*11.2 FT-.._*.-.*--Seg 19, 9.6-10.4 FT---**-----Seg 18, 8.8*9.6 FT*.***_.-*.*_-Seg 17, 8.0*8.8 FT ,"-1750 1500 1250 u.l1000750 I 500 250 0 0 AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK HOT CHANNEL CLAD TEMPERATURES (OPERATOR ACTION)p.14.FIG-63 CAD FILE: 6599R15.DWG FIG 14.2-41 ,--2400 160 2000 16001200 i 800----HotLe;------Intact SG Secondary_**_-------.. Broken SG Secondary--*---*---eFT 1...--+120 80 400**-----********--------------
- ---**----***--****-----_.--_
- 40 001-------------------------
.....0 a 1000 2000 3000 4000 5000 6000 7000 8000 TlME.SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK SYSTEM PRESSURE (NO OPERA TOR ACTION)p.14.FIG-64 CAD FILE: 6600R15.DWG FIG 14.2-42 28 LEGEND 8.0 Downcomer 24------Cote Composite 7.2 6.4 20 t: 5.6 2:16..4.8...0....4.0 g 12-------_.a::I 3.2:1 8 2.4 1.8 4 0.8 0 0.0 0 1000 2000 3000 4000 5000.6000 7000 8000 TIME, SecONDS Am er Gen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK COLLAPSED LIQUID LEVELS (NO OPERATOR ACTION)p.14.FIG-65 CAD FILE: 6609R15.DWG FIG 14.2-43 20.0 LEGEND Hot Channel 5.6 17.5----_.Average Chamel 4.8 15.0 ti: 4.0 S12.5 g 3.2 10.0It!7.&2.4:I:i 5.0 1.8 2.&0.8 0.0 0.0 0 1000 2000 3000 4000 5000 8000 7000 8000 TIME.SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK MIXTURE LEVELS (NO OPERATOR ACTION)p.14.FIG-66 CAD FILE: 6610R15.DWG FIG 14.2-44 LEGEND 400 1000 1200 800060007000----Seg21.1'.2-12.0FT
_.Seg 20.10.4*11.2 FT_**_-._.SeQ 19.9.8-10.4 FT*****---..Seg 18.8.8-9.8 FT****
eo 17.8.0*8.8 FTr.3000 4000 5000 TIME, SECONDS 2000 10001750 1500 1250 u.f1000 I 760 500 250 0 0 AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK HOT CHANNEL CLAD TEMPERATURES (NO OPERATOR ACTION)p.14.FIG-67 CAD FILE: 6611R15.DWG FIG 14.2-45 TMI-1 UFSAR Summary of SBLOCA PCT Spectrum-Limiting Break Range I'->J-----t.I I I.**.1._.*__,._,., 11 I I 1 I I I ,.-1-*.,.-----'-MI-'---------I I I I----_...:..' ---.I , I I I I I ,.,.,-,., ,.I I I I I I I*,-.._,.,.r ,.,.-...,.,..,..i-,.,.-,..,.,.,..-1 II I j I*1 L ,.*____,.*_, I I I I , I I I
1**----
I I I , I 1;_.__,.L J , , I*I*\_______*L__
- , 1 I I I:: 1444F::.WM t I I 1600 1500 1400 1300 12001100 1000 900 800 700 0.12 0.10 0.08 0.08 Break StH (tt)0.04 0.02 GOO+,------i------....I-I--"""-----+---'----+-_---l._--1!--
"'"--"-.........0.00 TMI-1 Updated Final Safety Analysis Report SBLOCASPECTRUM-PCTVERSUS BREAK SIZE Figure 14.2-68 Rev.20, 04/10 p.14.FIG-68 o CFT 21 3 15 4 14 2@-@17@6 23 16@@@3 11@LP1 Node No.Identification Path No.Identification Additional Data Not Shown on Diagram are: Node 22 Is Containment Node 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 o 1 2 3 4,14 5,15 6,16 7,17 8,18 9,11,19 10,12,20 13 21 22 23 Note: Downcomer 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 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 p.14.FIG-69 Core Hot Leg Piping Hot Leg,Upper SG Tubes SG Lower Head Core Bypass Cold Leg Piping Pumps Cold Leg Piping Downcomer LPI Upper Downcomer Pressurizer Vent Valve Leak&Return Path HPI Containment Sprays Craft 2 Noding Diagram for Small Break CADD fS1B,SKM,OO.0341,OOO-,14OO Update-14 4/98 Fig.14.2-47 loa***-***..............***..::...._.._...."-0-"..',..........-0..0..-0...0--0_,-..: '"....---..: I"/\ I 10: 0......,;.'I/..........:0"***""": 'I..,.,'.....:...."/'.: 4:.0 ,....!\.".... ...y ,:+i J I..t J I//.--.--.-./...\ eo/'&t'I/.,./----..---.0//.*.2G.;"-.---I%100 zaaa llaa Izaa laG*'-.a-.__.............._I.....__..*.Ila, IIC UPDATE-14 4/98 BREAK SPECTRUM-AVERAGE SYSTEM VOID FRACTION WITH THE RC PUMPS OPERATIVE AND 2 HPI PUMPS CAD FILE: 6602R14.DWG FIG 14.2-48 p.14.FIG-70 PRESSURE VS TIME*SIAlL BREAKS 11TH AUXILIARY FEEOIATER 3500 4DOO 1500 2000 2500 3000 1000 100 ..... .....__ ....*500 2500.,,-----\tl!"1';, 2000 ,,-', ,I', lit, II.,.AI 1500\..*lit\M*\..a-1000 ,-Tt_, IIC UPDATE-14 4/98 p.14.FIG-71 CAD FILE: 6603R14.DWG FIG 14.2-49 PRESSURIZER LEVEL VS TIIE*S.ALL BREAKS 11TH AUXILIARY FEEDlaTER 100 I I 10 ,)I-I..,,..,.....10/I*//....I-..::a/.I WI lilt/,....*I.-I 2D I I*(,-*SOD 1000 1500 2000 2500 3000 3500 11M.SIC UPDATE-14 4/98 PRESSURE LEVEL VS TIME-SMALL BREAKS WITH EMERGENCY FEED WATER p.14.FIG-72 CAD FILE: 6604R14.DWG FIG 14.2-50 'IESSUIllE_ LEVEL IS TIM[FOR SMAll IR£AI IN'IrSSUIIZER .-*-**...75.._.**-.....*...-..*.1....*..*.-IDDD 100 II'481 I.D I.... .....__....._....._--*n*.DC" UPDATE-14 4/98 PRESSURIZER LEVEL VS.TIME-SMALL BREAK IN PRESSURIZER p.14.FIG-73 CAD FILE: 6626R14.DWG FIG 14.2-51 2400 22DO..2000-M.u..:I M M U..1800 L 1100 1400 1200 o 500 tODD 1500 TI**(SIC)2000 2500 UPDATE-14 4/98 p.14.FIG-74 0.01 FT2 COLD LEG BREAK WITH NO EFW Sa STUCK PORV AT 20 MIN-NODE 14 PRESSURE VS.TIME CAD FILE: 6627R14.DWG FIG 14.2-52 2000\000 TI**(Sit)SOD OL-Jc=::::....l- __-1-----L----..L----1 D 10.000*20.000 50.000 60.000..---40.DOD-uu...a-::a 30.000 f:I'...UPDATE-14 4/98 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPI'S a STUCK PORV AT 20PRESSURIZER LIQUID LEVEL CAD FILE: 6628R14.DWG FIG 14.2-53 p.14.FIG-75 2500 2000 Tt**(SIC)1000 500 2.000 ____a....L...L...o 1.000 4.000 1.000 14.000 18.000 r--------------------. 11.000.......12.000""" u...u...a::a 10.000 D'-'UPDATE-14 4/98 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPl's Sa STUCK PORV AT 20 MIN-UPPER PLENUM LIQUID LEVEL CAD FILE: 6629R14.DWG FIG 14.2-54 p.14.FIG-76 2500 2000 1500 1000.soa D""----.....---.....-...... o 10.000 20.000 50.000 40.000 30.000 60.000 ,..--------------------- ...Tt**(sec)UPDATE-14 4/98 0.01 FT2 COLD LEG BREAK WITH NO EFW 2 HPI's&STUCK PORV AT 20 MIN-PORV LEAK FLOW CAD FILE: 6613R14.DWG FIG 14.2-55 p.14.FIG-77 1.200.------------------ 1.000.800......--..a u Q,.100-...400.200 o D 5DO loaa 1500 TI**(SIC)2QOO UPDATE-14 4/98 2500 p.14.FIG-78 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPI's&STUCK PORV AT 20 MIN-PORV LEAK FLOW QUALITY CAD FILE: 6614R14.DWG FIG 14.2-56 2500 35.000 30.000\25.000 I-"'""-a-M 20.000.....,u u WI**D"-15.00010.000-lllj.....5.000__WI...-o.....-""-I"'--I J-..'J.-I...J o SOD 10DD 1500 2000 TI**(SIC)UPDATE-14 4/98 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPI's&STUCK PORV AT 20 MIN-COLD LEG BREAK FLOW CAD FILE: 6615R14.DWG FIG 14.2-57 p.14.FIG-79 -"(I!J": ,f:1 I:1 1 , c,'..I'i frl I;Iii I'pl*!, I;1':'/t Ii'!i\...11 1t 1.!'1"'1 1: i ':11 I Ir'I.II.il-lPf:1" a':I'r-f'I 1!" , I A , I ,-1.200 1.000.800--..::a c::r*Q,-.600...400.200 D*0 5GO lOGO 150D TI**(SIC)2000 UPDATE-14 4/98 2500 p.14.FIG-80 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: 6616R14.DWG FIG 14.2-58 -2500 2DOO III*1500.*-*III IIIIDOD*sao 3500 4000 lOGO IGO 0.........__....__..._.............._.....a--UPDATE-14 4/98 SYSTEM PRESSURE VS.TIME-SMALL BREAKS W/O EMERGENCY FEEDWATER p.14.FIG-81 CAD FILE: 6617R14.DWG FIG 14.2-59 ,-1....._......_....-.a....L.-_..._..L..._...L._...I._-.I D IGG laao tSDI ZDGI Isaa 3000 3500 4000 21 1 ao-..10.....--.....10-...*ONLY Fa.SMALL CLASS 3.......1£AlS...*40..TI.,.Ie UPDATE-14 4/98 PRESSURIZER LEVEL VS.TIME-CLASS 3 BREAKS W/O EMERGENCY FEEDWATER p.14.FIG-82 CAD FILE: 6618R14.DWG FIG 14.2-60 loaa 5**4DDD 3DDD 2000 loaD£Iclusion 10°D,stinci I*I at-I 10-, at.,.0 30-DI'OOSI a c I-Hour Dosl 0-2-Hour OOSI Ie-a 10-2..-=-y at-CI 10-3 Distinci Fraa Edll If allcto, luildinl.ft.UPDATE-14 4/98 INTEGRATED DIRECT DOSE FOLLOWING MHA WITH 3-1/2 FT.REACTOR BUILDING WALL THICKNESS p.14-.FIG-83 CAD FILE: 6619R14.DWG FIG 14.2-61 TMI UFSAR
Figure 14.2-62 Deleted
FROM RC PUMPS RC-V1 RC-V3 RC-T-2 DH-V62 DH-V63 NOTES 1.VALVES ARE SHO'MII IN TYPICAl POST LOCA POSITION 2.ARROWS WiN INDICATE 1WO ACTIVE FLOW PATHS FOR RV BORON CONCENTRATION CONTROl.2 DH-V64 DH-V69 DH-V22A DH-V4A DH--V19A I, DH-V38A DH-V38B BWST DH-V22B DH-V4B DH-V19B UPDATE-14 4/98 SHEET I OF I FIG 14.2-63 CAD FILE: 6550RO.DWG POST LOCA BORON CONCENTRATION CONTROL FLOW PATHS DH-P-18 DH-P-1A 2 DH-V128 iu BS-v.lB DH-V12A DH-V3 DH-V6A DH-V6B BS-V3A REAC.BLDG.SUMP p.14.FIG-85) ',,-80 Neutron 60 Power.I 40"0 200C1*60 Thuma I 40 Power.I 20 0....-/Fue I Temper atur e Chanal.F 400 300 200 100 o l-4 Sec-J 12 Aver aal Cor I Moder Itor 8 TempIra ture Chana'.F 4 0 2600 Reactor 2500 Srstlm 2400 Pressurl.-4.*ps IIca::l 3: 2300 a DI c:..'1:t-2200 c:en n f>!:!.:.Z CIaa.,.. I C n...n -Daa a I C;a.51aCt..c:*'1:t c.a::::z:=_.DI ca-:rC'D."a...." CD QI c: C'D.."....cE'C'D c: "a-a........I>>-.........,...m-CO*N... CI CI 1ft CI----CI CI PI-CI 1ft PI N CI CI*-CI CI CI CI CI-CI CI CI CI PI-til**ca.a;:IU-.-.--a-*c*.;*-...--a....:-..-*a I!:I=E-*..-*--*til-:*ca.c-*ca.c u-M:I**.....*E....M**aa:I*..a**--z ca.-ca.-u c*-U IIIC M ca.Update-1 7/82 lffil!]Nuclear 1MI Unit-1 Startup Accident from 10-9 Rated Power using all Rods with a Worth of 10 1/.AK/K;High Flux Reactor Trip is Actuated)p.14.FIG-2 Fig.14.1-2 ..c M CI....-0Z-0 M 0_--IlIA:--t-----.0+---- .......-----1 e'" c..J_-- .-...............,ji.-.................0\J o 0::: ClI....p.14.FIG-3't**TherMal Pftwer , Peak Thermal Power vs.Rod Withdrawal Rate for a Startup Acciden t from 10-9 Rated Power CAD FILE: 6555R14.DWG CIt UPDATE-14 4/98 FIG 14.1-3 ('"')I o Q....-C Q CL (,,)Q U....-CJIC'C-Q U"" CK 0*""'-..-.-"-.-*-U-,.CK ,.*,.....'C.c--*'C a czI 0 Peak Neutron POler,\0]!]Nuclear TMI Unit-1 Peak Neutron Power vs.Rod Withdrawal Rate for a Startup Accident from 10-9 Rated Power p.14.FIG-4 Update-1 7/82 Fig.14.1-4 '-'\i\\\\\-...c:-*0*1\\\=*..*..-**-****..**..**N t-&-Z*W U LL LL W 0 0 u-a:::: 0 t-<<N a:::: w*0*0::E..***-*-**-.'I" Ttt"***'***r, , UPDATE-14 04/98 p.14.FIG-5-CAD FILE: 6556R14.DWG FIG 14.1-5 , J I)-..c-*0 z J-V I/*"" 10 JC M....'-...,.-..'-...,...--c:: N U-U---U 0...u 8: 0 C2IQ IQ I CIt.....CIt*Q'" Gil!]Nucle.r TMI Unit 1 Peak Thermal Power Versus Doppler Coefficient for a Startup Accident Using a 1.50/0 flKlK Rod Group at 1.09 X10-4(flKlK)/S From 10.9 Rated Power Update*8R 3/90 Fig.14.1-6 p.14.FIG-e ,'---,)v j-fa c:*0 z I J/CD'"***It)I M 0 X N-*C Q)*u:.;:-Q)0 U L Q)0.0.0 a e::t-p.)4.FIG-7 (crPii UNIT I NUCL.A.Peak Thermal Power vs.Doppler Coefficient for a Startup Accident Rods at 7.25 x 10-4 Ak/k)S from 10-9 Rated Power TITLE LINE 2 CAD FILE: 6557R14.DWG UPDATE-14 04/98 FIG 14.1-7 \ \i 1--------+---- \\\Pell Ther**1 Po.er, I N-+Q..-+CD Q+CD a+*la M*'-..a-+'-..4--N-C Q u+u--u Q 0 U Q...0-......U N0 Q*I*Q , CD Q ,-a I Q M p.]4.FIG-8[[il!J Nuclear TMI Unit-l Peak Thermal Power vs.Moderator Coefficient for a Startup Accident Using all Rods at 7.25 X 10-4 From 10-9 Rated Power Update-1 7/82 Fig.14.1-8 IIll1t ,..'111', I 110 ThUI 100"-rOil', I eo"-ID 70 I I I I I Fill're8,,, It 1111 CllIn." F h"'.1 c",*...".t., T..,.,.tII,.CIlU.I, F".ct., S,lt..r'II...II,'I" 80 40 2038 2.5 2.8 15 1.8 8.5*.* ......_-"--_.......__....TI.., Sic p.14.FIG-9 0:W!J Nuclear TMI Unit-1 Rod Withdrawal from Rated Power Using a 1.5%6K/K Rod Group at 1.09 X 10-4 (6K/K)/S;High F lux Reactor Trip is Actuated Update-1 7/82 Fig.14.1-9 2500 A II Rolls'0*4 hd l,thclrlUI lUI, (A.kjK)/SE.C 2200 HOC ,......,-........c-..'C Sinale Control...!toll'roup 2300 ,,-..0:iX!I Nucle.r TMI Unit 1 Peak Pressure ys.Rod Withdrawal Rate for a Rod Withdrawal Accident from Rated Power Update*SR 3/90 p.14.FIG-10 Fig.14.1*10 ..-ca Q.." U U Q us-u II.-:>>ootQ U Q C1....., I:'N Q Q Q CI CI CI Q Q.., N Q..,..,..,..,.., N N N N N Pe.k Pressure.psia P.14.FIG-ll Gil!J Nuclear 1MI Unit-l Peak Pressure vs.Trip Delay Time For a Rod Withdrawal Accident from Rated Power Using a 1.5%...:JK/K Rod Group Update-1 7/82 Fig.14.1-11 2400 I."..--2390 2380 2370 2360en 2350 Cl.Q,):J 2340 en en Q,)CL 2330cu CL 2320 2310 2300 2290 2280 2270 J//V J//v J , JNominal/V/V-0.8-I.0-I.2-I.4*1.6 Update-1 7/82 p.14.FIG-12 Do PP Ie reoef fie i ent, (A k/k)'Fx1 0 5 0]!J Nuclear 1MI Unit-1 Peak Pressure vs.Doppler Coefficient fo.a Rod Withdrawal Accident from Rated Power Using a 1.S D/D 6K/K Rod Group Fig.14.1-12 2380 2360V>>C.cu 2340...::::s V>>V>>cu...23202300 2280'"'\"'" Nominal-..............-0.6-0.4-0.2 0.0*0.2.0.4.0.6.0.8 Mocerator Coefficient. (6k/k)/F x 10 4 BE Nuclear TMI Unit-1 Update-1 7/82 p.14.FIG-13 Peak Pressure vs.Moderator Coefficient for a Rod Withdrawal Accident from Rated Powr Using a 1.5%6K/I(Rod Group Fig.14.1-13 120 I 10 laxlmum Neutron Pow.r....100&l*0 CL'CI&l-...ex 90-0..--....&l*0 CL80...&l CL IUI.u.Ther.11 Power 70 60 25 50 75 Initial Pow.r, , of tlt.d Pow.r BimNuclear 1MI Unit-1 Maximum Neutron and Thermal Power for an All-Rod Withdrawal Accident from Various Initial Power Levels IDa Update-1 7/82 Fig.14.1-14 3000 2800Ii)2600....<<JIi)c.E 2400 Ii)....cuE 1600E M<<1*1400 1200 10001/Maximum Temperature in Hottest Fue I Rod At The Hot Spot<-//aXlmum Average FuelTemperature t ,.......a 20 40 60 80100120----------.---.--..-_.Initial Power, , of Rated Power TMI Unit-l Peak Fuel Temperature in Average Rod and Hot Spot for an AII-Rod Withdrawal Accident from Various Initial Power Levels p.14.FIG-15 Update-1 7/82 Fig.14.1-15 --80 70 Neutron"'0 Power,%60.....50a I 110.....0"-30 65 Thermal 60 Power55 50 0.0*I-5.0 II L------------------------.I +5.0 I Change In Average Moderator T_p.rature,F -10.0 , , , , , , , , Reactor Coolant 2350 Pr."ure,p,ia enim, cc*"C:I C_I=C:I Z c:_."C:I ,..5-I....c a-en I c...-a 0 I CD..I>>:::I Q."" c: cP'"C a.-I>>ora.......,..-............ CI)I co I-en N..21100 2300 2250 2200 o ,*2 II 6 Tillie, Sec I 10 12 III 100 80---*a.......,80*a a ua...., u*,--u-=40 20 i\\r I*70,000 Ib-ft 2'"""'lIlllil '"'-......, a o 4 8 Tilll, SIC 12 16-p.14.FIG-17 0i!l Nuclear TMI Unite'Percent Reactor Coolant Flow as a Function of Time After Loss of Pump Power Update-1 7/82 Fig.14.1-17 2.0 18 c*1.6 0'CIIon ca 0 Co.)42'at C-...1.4:::I Q a: 51 flol loss a:a z (Vent Valve Stuck Open)Q E:::I*.-1.2 c.-*1.0 100 102 104 106 108 110 112 114 Overpoler at Inicn Coastaoln Blains., Iai!lNuclear TMI Unit-1 Update-1 7/82 p.14.FIG-18 Minimum DNBR Which Occurs During Coastdown From Various Initial Power Levels Fig.14.1-18 2.0 I.8 0 1.6.-+J.., GI: CD Z Q u c 1.4 c.., J::(.)+J 0%I.2 I.0 0.0 0.4 0.8 1.2 1.6 2.0 ,/-Time Seconds 0i!J Nuclear TMI Unit-1 Update-1 7/82 p.14.FIG-19 DNB Ratio Versus Time for a Locked Rotor Accident from 102%of Rated Power Fig.14.1-1 9 -'.......... ---......-'110 100 THEII4Al 90 POWER l 80 70 60 50 1&0 30--10010 It EUf ROil 10 POWER l 70 60 50 1&0.....-rja I N o"'C AVERAGE COlE MODERATOR T04PERATURE. f 586 581&582 580 578 576 571&572 I>>0 im c*omC::I Z:a.......::;'0&=:a I c:r"o...-:.rc I ,.....o Q-a 01_..0...*:3 c:a eta I>>a ,..I>>eta=a.a.-o-'0=-CIt CN'"&a en-a::.'-::r'" AI oI=It ,..-" CD.CO I N N...,0-2280 2260 REACTOR SYSTEM 22l1O PRESSURE ,Ii.2220 2200 2180 2160 21'10 0 5 10 15 20 25 30 TIME.SEC ),If I J J/I*o N o o o..o*"" o o"""" o"""" N o.."""" o.."""" o*"" N o o.., N......1ft......1ft*....1ft o*1ft N*1ft ,.,*1ft..*lit***olit o 1ft o*o....o*o fa o o o o*o....o*o a-o o o)*o-.....,......"'0...p.14.FIG-21..,...., oc.,)_=-0'"..,...C oc_c_...-.."'OZ>0'" CZ'"...-oz=--...-c.,).c...........Bi!J Nuclear TMI Unit-1 0.36'1. Rod Drop from Rated Power with Automatic Runback to 60°/, Demand in 12$Update-1 7/82 Fig.14.1-21 650.0 4000.0 .......-HIIU"--CClId lAg 600.0-*:J'0550.0 EQ, o o..J!500.0:;.!!c-------3000.0**o EL 2000.0 c: e'S*z 450.0 1000.0 Time (s)100.0 80.0 60.0 0.0 .........--.........----L--------.J 0.0 20.0 40.0 400.0 L..-____...L..____'____.....L_........._____'_____J.._I 0.0 20.0 40.0 60.0 80.0 100.0 Time (s)2500.0 650.0 r---....----,.---.....---....,-------......,..-.---.-----r------.------HIlt....--CeId lAg 2000.0-';;..e*III c: 0 Q, III., 1500.0;:)III III*0: 1000.0-........--, HIIt....--UrIouIled Hat lit 60().0 S III;:)'0550.0 Q, EQ, o o..J 500.0:;D".....-..._-_...--------450.0 100.0 80.0 Time (S)400.0 1:--_"'--_ ........---L---------'-----a..--..J 0.0 20.0 40.0 60.0 500.0 L...-__'"--__.A--__..o...-__..I.--L..--L.__--a..__--J 0.0 20.0 40.0 60.0 80.0 100.0 Time (s)AmerGen TMI-UNIT 1 UPDATE-15 4/00 DOUBLE-ENDED RUPTURE OF 24 IN.STEAM LINE BETWEEN STEAM GENERATOR AND STEAM STOP VALVE (WITH FEED WATER ISOLATION) p.14.FIG-22A CAD FILE: 6710R15.DWG Fig.14.1-22A 1500.0 5000.0 __4000.0 Faulted SG'--............. SG1000.0 ,------------I---0---'iii------------...3000.0--------........1!::J..*0 CD Q:C)V)Lo..2000.0 500.0 1000.0 ,......SG 0.0 0.0 0.0 20.0 40.0 60.0 80.0 100.0 0.0 20.0 40.0 60.0 80.0 100.0 Time (s)Time (s)&0000.0 r------.-----,.-----------r---...---""T"'------..,.---......-----. UPDATE-15 4/00 AmerGen TMI-UNIT 1 100.0 80.0 """"""""" 0.0 .......... --...L------..a......--"""---J 0.0 20.0 40.0 60.0 20000.0 40000.0o:I (,)V)Time (s)DOUBLE-ENDED RUPTURE OF 24 IN.STEAM LINE BETWEEN STEAM GENERATOR AND STEAM STOP VALVE (WITH FEED WATER ISOLATION) p.14.FIG-22B CAD FILE: 6713R15.DWG Fig.14.1-22B 1500.0 1000.0 500.0 2000.0--IL....._ ___L___I.__L.__A..__'0.0 2600.0 -c'iii2400.0::J en en cuQ.ao.!:!'0:z: CI)2200.0 0 ,..--Q: Time (s)AmerGen TMI-UNIT 1 UPDATE-15 4/00 ,"-'-RCS HOT LEG PRESSURE (psia)RESPONSE FOR LOSS OF ALL AC POWER (STATION BLACKOUT)p.14.FIG-23 CAD FILE: 6705R15.DWG Fig.14.1-23 TMIUFSAR Figure 14.1-24 Dropped Rod wI Bayonet Failure-ReS Pressure Response (NOTE 1)NOTES: 1.CVOL 110-4 and 210-4 represent hot leg pressures. CVOL 352-1 represents the core exit pressure.TMI-UNIT 1 REV.19, APRIL 2008 p.14.FIG-23A Dropped Rod wi Bayonet Failure ReS Pressure Response FIGURE.14.1-24 TMIUFSAR Figure 14.1-25 Dropped Rod wi Bayonet Failure-Reactor Power Response TMI-UNIT 1 REV.19, APRIL 2008 p.14.FIG-23B Dropped Rod wI Bayonet Failure Reactor Power Response FIGURE.14.1-25 TMIUFSAR t If:!.Jj: 80 F**:**.::..****':***,'**'.;;;:
- .'1'" 70 1*,*******0;**,
- ,*:**,:,*;**,****,**
..*******..,*:* ..,:";;*..::::::t', ,***,.*****..***H*::*'Figure 14.1-26 Dropped Rod wI Bayonet Failure-Primary Temperature Response TMI-UNIT 1 REV.19, APRIL 2008 p.14.FIG-23C Dropped Rod wi Bayonet Failure Primary Temperature Response FIGURE.14.1-26 10-3 Rated Power ,Hal 10-3 Rated Power,EOl Nominal No Xenon Nominal I,th Xenon Rated POler, EOl Rated Paler I Hal 100 1000 c: o+-':::J III Z)Control Rod lorth, , l.\k/k 10 o 0.2 0.3 0.4 0.5 0.6 o 1 o 8 0]!]Nuclear TMI Unit-1 Update-1 7/82)Peak Neutron Power Variation With Ejected Control Rod Worth Fig.14.2-1 1000 Nominal 11th Xenon 100 Rated POler, EOL Hllh Pressure;;T rip*0 1110.1 na I A..IQ E I., 10.3 Rated z::.....¥IQ., A..No.'na I 10 Hllh Hllh Pressure Flul Trtp T rip o I 0.2 0.3 0.4 0.5 0.1 o 7 o 8 Control Aod lorth,\6k/k BE Nuclear 1M I Unit-1 Update-1 7/82 Peak Thermal Power as a Function of Ejected Control Rod Worth p.14.FIG-24 Fig.14.2-2 240 E"-.C'Q Rated Power,BOl u 200"C (;)Nominal a: lith eu Xenon:J 160 u......Rated Power ,EDl In........120 (;)Nominal%....No llnon (;)u..Hiah Prlssure Tr--Hlah Flux Trip>.80 ,-.NO.lnal CQ 10-3 Rated Power,BOl.&:....10.3 Rated Power, EOl c='\40 CQHiah Pressure 0 0.2 0.3 0.4 0.5 0.&0.1 0.8 Control Rod lorth, , 6k/k raE Nuclear TMI Unit-1 Update-1 7/82 Peak Enthalpy of Hottest Fuel Rod Versus Ejected Control Rod Worth p.14.FIG-25 Fig.14.2-3 10.3 RJted Power.EOl.Rat.d Pow.r, BOl Rated POlar.EOl 100 1000 10.3 Rued Pour.BOl (Hllh Pr.ssur.Trip)*2 2-2.°.I.1.1.1.4.1.2.I.D-0*10 Doppler Co.fflclent, (Ak/k):F I 10 5 Fig.14.2-4 Update-1 7/82 1MI Unit-l Effect on Peak Neutron Power of Varying the Doppler Coefficient for an Ejected Rod Worth of 0.56%6K/K at 10-3 Rated Power and 0.46%6K/K at Rated Power p.14.FIG-26 lla 140 Nominal L Rated Paler.SOL-120 1 I Nominal Rated POler.EOl 100--u*10 a a....Eu.c....60-'-'-...U A.- 10-3 Rated Paler ,lOL-I(Hilh Pressure Trip)--+_Na.ina'7 I 40 20 o-0.1-1.0-I.2-I.4 10-3 Rated Po.er.EOl I I-1.1-1.1-2.0 Do p pierC oe f fiei*nt, (Aklk)I F I 1 0 5 Update-1 7/82 Bi[J Nuclear TMI Unit-l Effect on Peak Thermal Power of Varying the Doppler Coefficient for an Ejected Rod Worth of 0.56% at 10-3 Rated Power and 0.46%6K/K at Rated Power p.14.FIG-27'--F_ig_. -lOOO a, ted'ow.,.EDl 10.3"t.d',**f.IOL tM'I-',.sIur.,r,p)*3.*2 a'11 a.a.1 a Moderator coefficient@lF x 10-4*f I.0 10 taO..*o&.c a...:2 I*......UPDATE-14 04/98 Effect on Peak Neutron Power of Varying the Moderator Coefficient for an Ejected Rod Worth of 0.56% at 10-3 Rated Power and 0.46%Akk at Rated Power p.14.FIG..28 CAD FILE: 6558R14.DWG FIG 14.2-6 140 1 I 120 Rated io,er, EOl'-Noml na I Nominal_I..--Rated POler,BOl 100.......cu*0 80CQ E....cu.c60.., cu-40 20 I-o NaIll na I 1 I 10.3 Rated POler,BOl V (H1ih Pressure Trip) I---4.0-3.0-2.0-1.0 0.0+1.0+2.0+3.0 Moderator Coefficilnt,(Ak/k)/F x 1Ii 4 Update-1 7/82 Fig.14.2-7 G]!]Nuclear TMI Unit-1 Effect on Peak Thermal Power of Varying the Moderator Coefficient for an Eiected Rod Worth of 0.56%6K/K at 10-3 Rated Power and 0.46%6K/K at Rated Power p-14.FIG-29 140 120 100..-.*0 80 ICL."I E60"I-,-...ICL.40 20 o.I , Rated POler,BOl-:L No_inal---Rated
10.3 Rated Paler, BOl (Hilh Pr'essure Trip),\I , ,\...-No.inalNo.ina I-':J 10.3 Rated POler I EOl 1 0.0 0.2 0.4 0.6 0.*1.0 Trip Delay Ti.e, Sec 0:ir!]Nuclear TMI Unit-1 Update-1 7/82 Fig.14.2-8 p.14.FIG-30 Effect on Peak Thermal Power of Varying the Trip Delay Time for an Ejected Rod Worth of 0.56%oK/K at 10-3 Rated Power and 0.46%6K/K at Rated Power 6.0 5.0 m z Q4.0 u c: cu...cu CL)oC 3.0 u.I cu...0 u2.0 1.0 0.0 0.2 0.3 0.4 0.5 0.6 0.7 Control Rod Worth, S6k/k I:ai!l Nuclear TMI Unit-l Percent Core Experiencing0NB as a Function of Ejected Control Rod Worth at Rated Power, BOL p.14.FIG-31 Update-1 7/82 Fig.14.2-9
.-INITIAL RCS AND CORE PARAMETERS o<TIME<EOB EOB*END OF.LOWDOWN EOAH*END OF ADiAIIA nc HEA TUP EOE*END OF EVENT MASS AND ENERGY RELEASE 0<TIME<EOE CORE STORED ENERGY SYSTEM MASS AND ENERGY ACCUMULATOR MASS AND ENERGY STEAM GENERATOR MASS AND ENERGY MASS AND ENERGY RELEASE REFLOD3B EOB<TIME<EOE CONTAINMENT PRESSURE FLOODING RATE UPPER PLENUM PRESSURE CORE INLET TEMPERATURE EOBCOREPARAMETERS",," BEACH ,.(RELAP5IMOD2-B&W) EOB<TIME<EOE W METAL WATER REAcnON HOT PIN THERMAL RESPONSE PEAK CLADDING TEMPERATURE UPDATE-14 4/98 LARGE BREAK ANALYSIS CODE INTERFACES p.14.FIG-32 CAD FILE: 6573R14.DWG FIG 14.2-10 3200 2800 2400 0Q)2000::J 20 8tu/hr F t2-F...euQ)Q.e G>.-1600 u eu u...0 Q.h V).....1200 0%:800 400 50 140 30 20 10......l................"""'_.._...o Time After Rupture.Sec p.14.FIG-33 Bi[I Nuclear TMI Unit-1 Hot Spot Clad Temperature V5.Time for a 36 in.10, Double-Ended, Hot Leg Pipe Rupture and Variable Quench Coefficient Update-1 7/82 Fig.14.2-11 28 24 20 16 12 8 4-------------------------....&.0 32TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL)-REACTOR VESSEL UPPER PLENUM PRESSURE p.14.FIG-34 CAD FILE: 6574R15.DWG FIG 14.2-12 x10*xl0*10 LEGEND RV Side 4 8------Pump Side re 36 e"i4 20....en en en 2 1 CI')i<--_.".".."_."."""............. 0 32 28 241216 20 TIME, SECONDS 8 4 o Am er Gen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL)-BREAK MASS FLOW RATE p.14.FIG-35 CAD FILE: 6575R15.DWG FIG 14.2-13 2400 500 w 1000 Ii i7501250 1500----Fuel, Seg 6_._-_.Clad, Seg 6 2000 1.", 1600 (\/ Y..'v\wi.a::'\,1200*.,I, 800*\I 400\ 240 200 160 120 TIME, SECONDS 80 40 o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-2.506-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-36 CAD FILE: 6576R15.DWG FIG 14.2-14 2400...-----------------.....----- LE""""'G!""""'E..,..ND...,...-----. 2000 1600 u.1 1200.800 400----Fuel, Seg 10---._.Clad, Seg 10 1500 12501000i 750500 240 200 160 120 TIME.SECONDS 80 40 o Jo..--------I o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (SOL-4.264-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-37 CAD FILE: 6577R15.DWG FIG 14.2-15 - 2000 1600..Ii\,I'": I V.i 1200*800----Fuel, SeQ 13----_.Clad, Seg 13 1500 1250 400 500 240 200 160.120 TIME, SECONDS 80 40 0.......------------------------1 o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-6.021-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-38 CAD FILE: 6578R15.DWG FIG 14.2-16 ,,- 2000 800----Fuel, Seg 18----_.Clad, Seg 16 1500 12501000i 750!400 500 240 200 80 120 1eO TIME, SECONDS 40 o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-7.779-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-39 CAD FILE: 6579R15.DWG FIG 14.2-17 -2400 2000 1600 u.H!1200'I 800 400----Fuel, Seg 16------Clad, SeQ 16 1500 12501000760 i 500 ,,,-01..-------------------------4 o 40 80 120 160 200 240 TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-9.536-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-40 CAD FILE: 6580R15.DWG FIG 14.2-18 2400----Fuel, Seg 7--_._.Clad, Seg 7 2000 1600 Y.I"I::>>....1200*800 400\\"'-_"",\., , I , , 1.L....._.1500 12501000750500 240 200 160 120 TIME, SECONDS 80 40 O..a....----------------------- .....o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-2.506-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK UNRUPTURED LOCATION p.14.FIG-41 CAD FILE: 6581 R15.DWG FIG 14.2-19 2400----Fuel, Seg 9_._-_.Clad, Seg 9 2000 1600*"-I'.:::>>...1200 I i 800 400\.\..,.r-......,.-,-\"\i I\I , I L. 1500 1250W 1000i 750500 240 200 160 120 TIME.SECONDS 80 40 0""'----------------------- .....o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-4.264-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION p.14.FIG-42 CAD FILE: 6582R15.DWG FIG 14.2-20 2400 2000 400----Fuel, Seg 12---_.Clad, Seg 12 1500 12501000i750500 240 200 1ao 120 TIME.SECONDS 80 40 0-'------------------------ .....o AmerGen TMI-UNIT 1 UPDATE-15 4/00 LBLOCA LIMIT CASE (BOL-6.021-FT)HOT CHANNEL FUEL AND CLAD TEMPERATURE AT PEAK RUPTURED LOCATION p.14.FIG-43 CAD FILE: 6583R15.DWG FIG 14.2-21
1500 12501000750400 40 80 120 TIME.SECONDS ,---.....
Fuel.Seg'5----_.Clad.Seg,5 160 200 240 Am er 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 p.14.FIG-44 CAD FILE: 6584R15.DWG FIG 14.2-22----,---_.."-------------
2400-ro-----------------------......., 2000!, 600.""./": I'J.I 1200*i 800 1500'2S0 400 .....500----Fuel, Seg'8----_.Clad, Seg 18 160 200 240 120 TIME.SECONDS 80 40 0.......--------------- .......----------1 o-Am er 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 p.14.FIG-45 CAD FILE: 6585R15.DWG FIG 14.2-23
_._._.2.508 It----..4.264ft---8.021ft***************7.77Ift ---9.531ft 2.0 It:: oU c(1.5 II.It:: WGo1.00.5 12 10 8 4 2 o_.UPDATE-14 4/98 LOCA LIMIT AXIAL POWER SHAPES p.14.FIG-46 CAD FILE: 6586R14.DWG FIG 14.2-24 2400...... 160'""-----------t 80----0.01-FT2, CLPD SBLOCA----_.O.03-FT2, CLPO SBLOCA-------_._. 0.04-FT2, CLPD SBLOCA....._..-----0.05-FT2, CLPD SBlOCA**_-_.__.-0.06-"2, CLPD SBLOCA 120'-'"\,°0,,'\"\\\'\.\\\"-\',...\\.'."...\"...,...,"'-...., e,._...___.._.....'---'-",,-- ....."--'"-------..-,..-..--..----'...."""................. ...., -.'-.................................-.-........................--..__..40............ ..---. ..--.................................
- -....._--...._-.........................
._---.-.-.800 400 2000 16001200 I o 1000 2000 3000 4000 5000 6000 TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.01-0.06 FT 2 BREAKS)p.14.FIG-47 CAD FILE: 6587R15.DWG FIG 14.2-25 2400..... 160 2000 i Ii 1200 I----O.07-FT2, CLPD SBLOCA------O.08-FT2, CLPD SBLOCA----O.09-FT2, CLPD SBLOCA...--**----O.10-FT2, CLPO salOCA.'--------------...120 80 40 0.1.------------------------60 o'000 2000 3000 4000 6000 6000 TIME.SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.07-0.10 FT 2 BREAKS)p.14.FIG-48 CAD FILE: 6588R15.DWG FIG 14.2-26 2000 2400.....
0.lS-FT2, CLPO SBLOCA--_._.O.30-FT2, CLPD SBLOCA-**-----.0.50-FT2, CLPD SBLOCA............ CLPD SBLOCA 120 16001%00\\fI)en ,.\\\800*\*\.\\\\, 400 ,'."'\"\\"" ,..........
" 80 40, ,-0"'-----------------------.-.0 o 250 500 750 1000 1250 1500 1750 2000 TIME, SECONDS..AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF RCS PRESSURE (0.15-0.75 FT 2 BREAKS)p.14.FIG-49 CAD FILE: 6589R15.DWG FIG 14.2-27 10 2 Q 5 o5000 LEGEND----O.Ol.fT2.SBLOCA-.._---O.03.fT2 S8l0CA____,I O.04-FT2 SBlOCA********** O.05-FT2 SBlOCA 8*..-..._.-O.06.fT2 SBLOCA 2000 3000 4000 TIME.SECONDS-----------------------..--100 6000 35 30 I 26*1\.t:2016::J 10 6 0 0 1000 AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.01-0.06 FT 2 BREAKS)p.14.FIG-50 CAD FILE: 6605R15.DWG FIG 14.2-28 AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.07-0.10 FT 2 BREAKS)p.14.FIG-51 CAD FILE: 6606R15.DWG FIG 14.2-29 f 35 LEGEND 10 O.'5-FT2 SBLOCA 30------O.30-FT2 SBLOCA-----O.&O-FT2 SBLOCA********** O.7f5.fT2 SBLOCA 8 t::&60a 4:::a:I 10 2 o 250 500 750 1000 12&0 1600 1760 2000 nME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF REACTOR VESSEL COLLAPSED LIQUID LEVEL (0.15-0.75 FT 2 BREAKS)p.14.FIG-52 CAD FILE: 6607R15.DWG FIG 14.2-30 2000 p-.-------- ...... 1200 500 1500 1750----0.01-FT2, CLPD SBLOCA, Seg 18----_.O.03*FT2, CLPD SBLOCA, Seg 19_._**_._....O.04..FT2, CLPD SBLOCA, Seg 20..---------0.OS*FT2, CLPO SBLOCA, Seg 20.....-.-__*0.08*FT2, CLPD SBLOCA, Seg 19 ,-,--------------t !......."",*....-*..----, 1 000!u.1250 J**...)ti".,.....: ',"'"..,,"'..\,.."'i: ,...v/.. /"../"","" ,-,\"...#11\;1' \1000/,/r/I" V\\/(*\.'\800*, I Jf r\-...a:: j:\: '..,'" III 750 I Iii\,".: I Ii::*(.r.f:1.:;::-':'::::: __J'.'-j'1'600**I'....... ..: L ,--0 ..****** ._.250 400 7000 6000 5000 3000 4000 TIME, SECONDS 2000 1000 0.-.--------------------------.. o 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 2000..... .....----0.07.fTZ, CLPD SBLOCA, Sea 19--_._.O.08-FT2, CLPD SBLOCA, S_, 19 1200---,-O.09.fT2, CLPD SBlOCA, Seg 19****--......O.10.fT2, CLPD SBlOCA.Seg 19 1750 1500 i 1250 i 1000 i 750 500 'I,*!tv';fi j I:1.:I:**.,.., I**---"-I*...AJ*:.,.,."'...........,........:lO'Il= ..aP.lIl1Jl...-r. ........... 1000Ll S800 i*800 400 1000 2000 3000 4000 TIME.SECONDS 6000 6000 AmerGen TMI-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF PEAK CLAD TEMPERATURES (0.07-0.10 FT 2 BREAKS)p.14.FIG-54 CAD FILE: 6590R15.DWG FIG 14.2-32 ..-- 600 LEGEND----0.16-FT2, CLPD SBLOCA, Se;20----_.0.30-FT2, CLPO SBLOCA, SeQ 20 1200--------.0.50-FT2, CLPO SBLOCA, SeQ 19---------- 0.75-FT2, CLPD SBLOCA, SeQ 17 1000ii S 800 Ie400 2000 1750 1500 750 1000 1250 TlME, SECONDS 500 250 2000'750'500 I:: 750 500 250 0 0 ,,--.'AmerGen 1\41-UNIT 1 UPDATE-15 4/00 SBLOCA COMPARISON OF PEAK CLAD TEMPERATURES (0.15-0.75 FT 2 BREAKS)p.14.FIG-55 CAD FILE: 6591 R15.DWG FIG 14.2-33 2400 ,..------------ ..... 160 2000----HotLeg------Intact SG Secondary----_._-._-_. Broken SG Secondary------_... eFT 80 40..._--.._---_._----_._---------_.----_ .**-** oL_-===================:d o o 500 1000 1500 2000 2500 3000 3500 4000 TIME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 eFT LINE BREAK SYSTEM PRESSURE p.14.FIG-56 CAD FILE: 6592R15.DWG FIG 14.2-34 Am er Gen TMI-UNIT 1 UPDATE-15 4/00 CFT LINE BREAK COLLAPSED LIQUID LEVELS p.14.FIG-57 CAD FILE: 6593R15.DWG FIG 14.2-35 20.0 LEGEND Hot Channel 5.6 17.5-----.Average Channel 4.8 15.0 t: 4.0:E12.53.2 H!10.0 II!7.5 2.4:I 2 5.0 1.8 2.&0.8 0.0 0.0 0 1000 2000 3000 4000 5000.6000 7000 8000 nME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 eFT LINE BREAK MIXTURE LEVELS p.14.FIG-58 CAD FILE: 6594R15.DWG FIG 14.2-36 400 600 1000i 800I 1200 4000 3500 3000'500 2000 2600 TIME, SECONDS 1000 SOD LEGEND Se;21,11.2*12.0 FT----_.Seer 20, 10.4*11.2 FT_**_**_**_**.Seg 19, 9.6*10.4 FT_.--_...--.Seg 18, 8.8*9.6 FT.......... -........SeQ 17, 8.0*8.8 FT 1Ai.'..250 o a 500 1750 1500 2000": 1250 H!i,ooo!750 AmerGen TMI-UNIT 1 UPDATE-15 4/00 CFT LINE BREAK HOT CHANNEL CLAD TEMPERATURES p.14.FIG-59 CAD FILE: 6S9SR15.DWG FIG 14.2-37 2400 160 2000 16001200 I/)i 800 400----HotLeg----_.Intact SG Secondary_**--_**__.Broken SG Secondary-----..----eFT 80-
- -----.-****----**--.-.-...40 o 1000 2000 3000 400d 5000 6000 7000 8000 TlME, SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK SYSTEM PRESSURE (OPERATOR ACTION)p.14.FIG-60 CAD FILE: 6596R15.DWG FIG 14.2-38 2$LEGEND 8.0 Downcomet 24---_._.Core Composite 7.2 6.4 20 t: 5.6:!Ed 16 4.8 af0 4.0 g 5 12§g 3.2 8 2.4-1.8 4 0.8 0 0.0 0 1000 2000 3000 4000 5000 6000 7000 8000 TtUI:
AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK COLLAPSED LIQUID LEVELS (OPERATOR ACTION)p.14.FIG-61 CAD FILE: 6597R15.DWG FIG 14.2-39 20.0 LEGEND Hot Channel 5.6 17.5--_.-.Average Chlnne(4.8 15.0 t: 4.0 212.53.2 10.0 I!!e 7.&2.4 i:i 5.0 1.8 2.5 0.8 0.0 0.0 0 1000 2000 3000 4000 5000 6000 7000 8000 TIME, SECONDS ,-AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK MIXTURE LEVELS (OPERATOR ACTION)p.14.FIG-62 CAD FILE: 6598R15.DWG FIG 14.2-40 1000 2000 3000.4000 5000 6000 7000 8000 TlME.SECONDS 400 1000 1200 LEGEND----Seg21,'1.2-12.0 FT----_.Seg 20, 10.4*11.2 FT-.._*.-.*--Seg 19, 9.6-10.4 FT---**-----Seg 18, 8.8*9.6 FT*.***_.-*.*_-Seg 17, 8.0*8.8 FT ,"-1750 1500 1250 u.l1000750 I 500 250 0 0 AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK HOT CHANNEL CLAD TEMPERATURES (OPERATOR ACTION)p.14.FIG-63 CAD FILE: 6599R15.DWG FIG 14.2-41 ,--2400 160 2000 16001200 i 800----HotLe;------Intact SG Secondary_**_-------.. Broken SG Secondary--*---*---eFT 1...--+120 80 400**-----********--------------
- ---**----***--****-----_.--_
- 40 001-------------------------
.....0 a 1000 2000 3000 4000 5000 6000 7000 8000 TlME.SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK SYSTEM PRESSURE (NO OPERA TOR ACTION)p.14.FIG-64 CAD FILE: 6600R15.DWG FIG 14.2-42 28 LEGEND 8.0 Downcomer 24------Cote Composite 7.2 6.4 20 t: 5.6 2:16..4.8...0....4.0 g 12-------_.a::I 3.2:1 8 2.4 1.8 4 0.8 0 0.0 0 1000 2000 3000 4000 5000.6000 7000 8000 TIME, SecONDS Am er Gen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK COLLAPSED LIQUID LEVELS (NO OPERATOR ACTION)p.14.FIG-65 CAD FILE: 6609R15.DWG FIG 14.2-43 20.0 LEGEND Hot Channel 5.6 17.5----_.Average Chamel 4.8 15.0 ti: 4.0 S12.5 g 3.2 10.0It!7.&2.4:I:i 5.0 1.8 2.&0.8 0.0 0.0 0 1000 2000 3000 4000 5000 8000 7000 8000 TIME.SECONDS AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK MIXTURE LEVELS (NO OPERATOR ACTION)p.14.FIG-66 CAD FILE: 6610R15.DWG FIG 14.2-44 LEGEND 400 1000 1200 800060007000----Seg21.1'.2-12.0FT
_.Seg 20.10.4*11.2 FT_**_-._.SeQ 19.9.8-10.4 FT*****---..Seg 18.8.8-9.8 FT****
eo 17.8.0*8.8 FTr.3000 4000 5000 TIME, SECONDS 2000 10001750 1500 1250 u.f1000 I 760 500 250 0 0 AmerGen TMI-UNIT 1 UPDATE-15 4/00 HPI LINE BREAK HOT CHANNEL CLAD TEMPERATURES (NO OPERATOR ACTION)p.14.FIG-67 CAD FILE: 6611R15.DWG FIG 14.2-45 TMI-1 UFSAR Summary of SBLOCA PCT Spectrum-Limiting Break Range I'->J-----t.I I I.**.1._.*__,._,., 11 I I 1 I I I ,.-1-*.,.-----'-MI-'---------I I I I----_...:..' ---.I , I I I I I ,.,.,-,., ,.I I I I I I I*,-.._,.,.r ,.,.-...,.,..,..i-,.,.-,..,.,.,..-1 II I j I*1 L ,.*____,.*_, I I I I , I I I
1**----
I I I , I 1;_.__,.L J , , I*I*\_______*L__
- , 1 I I I:: 1444F::.WM t I I 1600 1500 1400 1300 12001100 1000 900 800 700 0.12 0.10 0.08 0.08 Break StH (tt)0.04 0.02 GOO+,------i------....I-I--"""-----+---'----+-_---l._--1!--
"'"--"-.........0.00 TMI-1 Updated Final Safety Analysis Report SBLOCASPECTRUM-PCTVERSUS BREAK SIZE Figure 14.2-68 Rev.20, 04/10 p.14.FIG-68 o CFT 21 3 15 4 14 2@-@17@6 23 16@@@3 11@LP1 Node No.Identification Path No.Identification Additional Data Not Shown on Diagram are: Node 22 Is Containment Node 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 o 1 2 3 4,14 5,15 6,16 7,17 8,18 9,11,19 10,12,20 13 21 22 23 Note: Downcomer 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 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 p.14.FIG-69 Core Hot Leg Piping Hot Leg,Upper SG Tubes SG Lower Head Core Bypass Cold Leg Piping Pumps Cold Leg Piping Downcomer LPI Upper Downcomer Pressurizer Vent Valve Leak&Return Path HPI Containment Sprays Craft 2 Noding Diagram for Small Break CADD fS1B,SKM,OO.0341,OOO-,14OO Update-14 4/98 Fig.14.2-47 loa***-***..............***..::...._.._...."-0-"..',..........-0..0..-0...0--0_,-..: '"....---..: I"/\ I 10: 0......,;.'I/..........:0"***""": 'I..,.,'.....:...."/'.: 4:.0 ,....!\.".... ...y ,:+i J I..t J I//.--.--.-./...\ eo/'&t'I/.,./----..---.0//.*.2G.;"-.---I%100 zaaa llaa Izaa laG*'-.a-.__.............._I.....__..*.Ila, IIC UPDATE-14 4/98 BREAK SPECTRUM-AVERAGE SYSTEM VOID FRACTION WITH THE RC PUMPS OPERATIVE AND 2 HPI PUMPS CAD FILE: 6602R14.DWG FIG 14.2-48 p.14.FIG-70 PRESSURE VS TIME*SIAlL BREAKS 11TH AUXILIARY FEEOIATER 3500 4DOO 1500 2000 2500 3000 1000 100 ..... .....__ ....*500 2500.,,-----\tl!"1';, 2000 ,,-', ,I', lit, II.,.AI 1500\..*lit\M*\..a-1000 ,-Tt_, IIC UPDATE-14 4/98 p.14.FIG-71 CAD FILE: 6603R14.DWG FIG 14.2-49 PRESSURIZER LEVEL VS TIIE*S.ALL BREAKS 11TH AUXILIARY FEEDlaTER 100 I I 10 ,)I-I..,,..,.....10/I*//....I-..::a/.I WI lilt/,....*I.-I 2D I I*(,-*SOD 1000 1500 2000 2500 3000 3500 11M.SIC UPDATE-14 4/98 PRESSURE LEVEL VS TIME-SMALL BREAKS WITH EMERGENCY FEED WATER p.14.FIG-72 CAD FILE: 6604R14.DWG FIG 14.2-50 'IESSUIllE_ LEVEL IS TIM[FOR SMAll IR£AI IN'IrSSUIIZER .-*-**...75.._.**-.....*...-..*.1....*..*.-IDDD 100 II'481 I.D I.... .....__....._....._--*n*.DC" UPDATE-14 4/98 PRESSURIZER LEVEL VS.TIME-SMALL BREAK IN PRESSURIZER p.14.FIG-73 CAD FILE: 6626R14.DWG FIG 14.2-51 2400 22DO..2000-M.u..:I M M U..1800 L 1100 1400 1200 o 500 tODD 1500 TI**(SIC)2000 2500 UPDATE-14 4/98 p.14.FIG-74 0.01 FT2 COLD LEG BREAK WITH NO EFW Sa STUCK PORV AT 20 MIN-NODE 14 PRESSURE VS.TIME CAD FILE: 6627R14.DWG FIG 14.2-52 2000\000 TI**(Sit)SOD OL-Jc=::::....l- __-1-----L----..L----1 D 10.000*20.000 50.000 60.000..---40.DOD-uu...a-::a 30.000 f:I'...UPDATE-14 4/98 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPI'S a STUCK PORV AT 20PRESSURIZER LIQUID LEVEL CAD FILE: 6628R14.DWG FIG 14.2-53 p.14.FIG-75 2500 2000 Tt**(SIC)1000 500 2.000 ____a....L...L...o 1.000 4.000 1.000 14.000 18.000 r--------------------. 11.000.......12.000""" u...u...a::a 10.000 D'-'UPDATE-14 4/98 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPl's Sa STUCK PORV AT 20 MIN-UPPER PLENUM LIQUID LEVEL CAD FILE: 6629R14.DWG FIG 14.2-54 p.14.FIG-76 2500 2000 1500 1000.soa D""----.....---.....-...... o 10.000 20.000 50.000 40.000 30.000 60.000 ,..--------------------- ...Tt**(sec)UPDATE-14 4/98 0.01 FT2 COLD LEG BREAK WITH NO EFW 2 HPI's&STUCK PORV AT 20 MIN-PORV LEAK FLOW CAD FILE: 6613R14.DWG FIG 14.2-55 p.14.FIG-77 1.200.------------------ 1.000.800......--..a u Q,.100-...400.200 o D 5DO loaa 1500 TI**(SIC)2QOO UPDATE-14 4/98 2500 p.14.FIG-78 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPI's&STUCK PORV AT 20 MIN-PORV LEAK FLOW QUALITY CAD FILE: 6614R14.DWG FIG 14.2-56 2500 35.000 30.000\25.000 I-"'""-a-M 20.000.....,u u WI**D"-15.00010.000-lllj.....5.000__WI...-o.....-""-I"'--I J-..'J.-I...J o SOD 10DD 1500 2000 TI**(SIC)UPDATE-14 4/98 0.01 FT 2 COLD LEG BREAK WITH NO EFW 2 HPI's&STUCK PORV AT 20 MIN-COLD LEG BREAK FLOW CAD FILE: 6615R14.DWG FIG 14.2-57 p.14.FIG-79 -"(I!J": ,f:1 I:1 1 , c,'..I'i frl I;Iii I'pl*!, I;1':'/t Ii'!i\...11 1t 1.!'1"'1 1: i ':11 I Ir'I.II.il-lPf:1" a':I'r-f'I 1!" , I A , I ,-1.200 1.000.800--..::a c::r*Q,-.600...400.200 D*0 5GO lOGO 150D TI**(SIC)2000 UPDATE-14 4/98 2500 p.14.FIG-80 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: 6616R14.DWG FIG 14.2-58 -2500 2DOO III*1500.*-*III IIIIDOD*sao 3500 4000 lOGO IGO 0.........__....__..._.............._.....a--UPDATE-14 4/98 SYSTEM PRESSURE VS.TIME-SMALL BREAKS W/O EMERGENCY FEEDWATER p.14.FIG-81 CAD FILE: 6617R14.DWG FIG 14.2-59 ,-1....._......_....-.a....L.-_..._..L..._...L._...I._-.I D IGG laao tSDI ZDGI Isaa 3000 3500 4000 21 1 ao-..10.....--.....10-...*ONLY Fa.SMALL CLASS 3.......1£AlS...*40..TI.,.Ie UPDATE-14 4/98 PRESSURIZER LEVEL VS.TIME-CLASS 3 BREAKS W/O EMERGENCY FEEDWATER p.14.FIG-82 CAD FILE: 6618R14.DWG FIG 14.2-60 loaa 5**4DDD 3DDD 2000 loaD£Iclusion 10°D,stinci I*I at-I 10-, at.,.0 30-DI'OOSI a c I-Hour Dosl 0-2-Hour OOSI Ie-a 10-2..-=-y at-CI 10-3 Distinci Fraa Edll If allcto, luildinl.ft.UPDATE-14 4/98 INTEGRATED DIRECT DOSE FOLLOWING MHA WITH 3-1/2 FT.REACTOR BUILDING WALL THICKNESS p.14-.FIG-83 CAD FILE: 6619R14.DWG FIG 14.2-61 TMI UFSAR
Figure 14.2-62 Deleted
FROM RC PUMPS RC-V1 RC-V3 RC-T-2 DH-V62 DH-V63 NOTES 1.VALVES ARE SHO'MII IN TYPICAl POST LOCA POSITION 2.ARROWS WiN INDICATE 1WO ACTIVE FLOW PATHS FOR RV BORON CONCENTRATION CONTROl.2 DH-V64 DH-V69 DH-V22A DH-V4A DH--V19A I, DH-V38A DH-V38B BWST DH-V22B DH-V4B DH-V19B UPDATE-14 4/98 SHEET I OF I FIG 14.2-63 CAD FILE: 6550RO.DWG POST LOCA BORON CONCENTRATION CONTROL FLOW PATHS DH-P-18 DH-P-1A 2 DH-V128 iu BS-v.lB DH-V12A DH-V3 DH-V6A DH-V6B BS-V3A REAC.BLDG.SUMP p.14.FIG-85)}}