RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 15, Accident Analyses
Text
640 630 lOCUS OF CONOmONS WHERE ONBR:: ONBR UMrT 620 610 600 590 580., , ,*25 1---....l.---I.._.L.---i----I..l...-...lI---J:_..L..---W---.l._..l.---.l.....J-570 OTOT TRIP UNES (INCLUDING MAXIMUM", 35 INSTRUMENT ERRORS)....AT INDICATED PRESSUFlES
", 30 80_,__., 75 70 ,40 65 , ,\, 2000PSIA 2250PSlA",\60 i\/-u..0)55 Q)c-....I 50=-CD c 45 Average Temperature (Oeg.F)SOlJ1'l-4 CAROUNA ELECTRIC&GAS CO.VlRGIL C.SUMMER NUCL.EAR STATION Overtemperature and Overpower Delta-T Protection Figure 15.1-1 AMENDMENT 96-02 July 1996 u u..,....-----------------
.......-......,.-.__,r__"-.,.....L...-.
.......-_-...,J U AMENDMENT6 AUGUST,1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Rod Position vs.Time On Reactor Trip Figure 15.1*2 AMENDMENT6 AUGUST.1990 OJ u 0., 12 u..,.--------------------,.
OJ OJ 0.1 U I I I SOUTH CAROLINA ELECTRIC&GAS COo VIRGIL Co SUMMER NUCLEAR STATION Normali;zed RCCA Reactivity Worth VSo Percent Insertion Figure 15.1-3 11 OJ OJ4-....-;=:::::;:=-...,,--,..--,.-L-,---.......----J U u t.D..,.----------------..,....-----, 17 11 1.1 AMENDMENT 6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Normalized RCCA Bank Worth vs.Time After Trip Figure 15.1-4 100 NOTE 2: "I..OWER CURVELEAST NESA TIVE'DOPPI..ER OM., Y POWER DEFECT--0.
A K NOTE 1: "UPPER CURVEIrfOST NEGATIVE lJfJPFIt.ER I'JCJPPLER ONL Y POWER OEFECT.. 0 6S A K-20-11-16 E-14 III0 L..-12 z III u-10 E III L E-I ill I.1 u-I L-"-2 0 0 AMENDMENT 6 AUGUST.1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGILC.SUMMER NUCLEAR STATION Doppler Power Coefficient Used In Accident Analysis Figure 15.1-5
,ott**..Z TOTAL lUI'L WAT (w.Ttl"S fDO_)10*'**W 2*=*FIlS'.",DUCT KU't:..*Z;;0-AL FlSSIOIS t:_TDM I 10.'**1-231 CAPT.lt ,rta,..'#,.10°2....10'2..,"0 2 2 TIME anu SIIUTOO" (SECOIDS)AMENDMENT 6 AUGUST.1990 II*'103 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGILC.SUMMER NUCLEAR STATION Residual Decay Heat Figure 15.1-6 10 0 10°TIME AFTER SHUTDOWN (SECONDS)AMENDMENT6 AUGUST,1990.SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION 1979 ANS Decay Heat figure 15.1-7 N+1 1+1 ,.-----....-I"., FILM CLAD AMENDMENT 6 AUGUST, 1990 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGILC.SUMMER NUCLEAR STATION Fuel Rod Cross Section Figure 15.1*8
10;------------------------------
0.01 0.003:E 3 o Z u.o z Q 0.3 l-0:: 0.1!:!::-0:: w 0.030-...J o::>z 25 20 10 15 11M£: (SeCONDS)5 0.001 I.-_......__.....--&_-'-__......__...l-__......_......:'---l o 0.5:::r0.4 0 Z u.0 Z 0 0.3 i=!:!::-x 02::>...J u.w:I: 0.1 w 0:: 0 0 0 0 5 10 15 11t.E (SECONDS)20 25 30 AMENDMENT 96-02 JULY 1996 SOUTH CAROUNA ELECiRIC&GAS co.VIRGIl.C.SUMMER NUCLEAR STATION Uncon1rolec:t RCCA WlthdI'3WaI from SUbc:l11ICaI:
Nuclear Power and core HlIat Flux va.1'IIlIe 3.500 Fuel Centerline 3.000 2.500 u:-*d w e.Fuel Average W a: 2.000:;)a: w a..:E w I-1.500 1.000 Fuel Clad 500 o 5 10 15 TIME (SECONDS)20 25 SOUTH CAROUNA aEC1RIC&.GAS co.VIRGiL C.SUMMER NUCLEAR STATION Uncontrolled RCCA trom SUbcItlcal:
FUlIl Centllrtlne.
Ayerage, lIIld C1lId TtmpenltUre vs.TInIe AMENDMENT 96-02 JULy 1996 SOUTH CAROLJIIA aECTRIC&\GAS CO.VIRGIL C.SUMMER NUC\.fAR STAnON AMENDMENT 96-02 JULy 1996 SOUTH CAROLINA aECTRIC..GAS co.VIlGIL C.SUMMER NUCLEAR STJmON AMENDMENT 96-02 JULY 1996 300 2SO 150 TIME (sec),.I , 150 200 250 300 E (sec)150 200 250 3ClO UE<_>TIM" 100 100 50 1.2 i'0:z: II.0 o 0.8<II:!!:;.II: 0.6 w!: 0 a..0.4 II:<w...0.2 0:::>:z: 0 0 1.2:IE 0:z: II.0 0.8c::!:!:-x 0.6::>.......!C....0.<&:::: 0.2 0<&3.5 3 II: II:l:z: Q 2.5 2 1.5 0 SOUTH CAROLINA ELEcnuc&.GAS co.\llRGIL C.SUMMER NUCI.EAR STATION UftconIraIIed Rod WithdraWIII From 100%'-Tenllil.tICI by OWl_I.......AT"&ip NucHar'-'.H_t Flax 8Ild DNBR va.TIme.....16.2*6 AMENDMENT 96-02 JULY 1996 SOUTH CAROLINA EJ.ECTRIC 6.GAS co.VIRGIL C.
NUa.EAR STATION UncomraIIed Rod*..\lItlldla_1 From 100%Pvwwby o-umpllnltU'e'1iipand Watw Volume...sTwg va T_Figure 16.2-6 AMENDMENT 96-02 JULY 1996 1.95 HI Fl.UX TRIP 1.9/, 1.85 OTSTRIP a::: CD z 1.8 c:E::::>:E 1.75 z:E 1.7 1.65 1.6 0.5 1 2 5 10 20 50 100 REACTIVITY INSERTION RATE (pcmIsec)Min.Fee:Il:a:k MIll<FeecI:8ck SOUTH CAROLINA aECTRlC 6.GAS co.VIRGIL C.SUMMER NUa.EAR sanON EffIlCt of Ruc:tivity IMW1ion Ra1e on MiniIlIum DNBR for a Rod WI1hdrawIlI A.c:cident at 100%"-FlgIn 1&.2-7 AMENDMENT 96-02 JULY 1996 25 10 20 REACTIVITY INSERTION RATE (pcmIseC)2.3 2.2 2.1 0:: tIl Z 2 0::aE:;:)::aE 1.9 Z::aE 1.8 1.7 1.6 0.5 OTti.TTRIP
\SG SAFETY VALVES OPEN BEFORE TRIP...1 SG SAFETY VALVES II OPEN BEFORE TRiP......HI FLUX TRIP 50 100 SOUTH CAROLINA ELECTRIC,.
GAS co.VIRGIL C.
NUCI.EAR STATION Eff.ct of RaM::tivity
........Re.on-...-DN8R for a Rod WllhdnwaI Accid_at 6O'J(, P-.F'igwe 16.2-8 AMENDMENT 96-02 JULY 1996 100 HI FLUX TRIP25 10 20*50 REACTIVITY INSERTION RATE (pcmlsec)OW TRIP SG SAFEiY VALVES/
1 3 2.8 2.6 c::: CD Z 2.4 0::!E::>2.2::!E z::!E 2 1.8 1.6 0.5 SOtml CAROLINA ELEC1'RIC Ir.GAS CO.VIRGIl.C.SUMMER NUCl.EAR STATION EffKt of RucIivity m-1ion Rat.on Minimum DNBR tor a RodAcc:id_at FiguN 15.2-9 AMENDMENT 96-02 nTTV 1001=.
- _.ID.,...---------"'t**ID_ID 10 SIO.ID..saID_.ID.....--:o--"!!---"!!---l II*I*i!!1 i::;...:*:!....".....--;**,..., iaLO ,..,.,-.0-......-.0 I*..It I I I!I I SOUTH CAROUNA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STAnON Transient Response 10 A Dropped RCCA.T_vg anc:t Pressurizer Pressure vs.Time FigYre15.2-11 A..."l{ENDMENT 96-02 JULY 1996 1.1:E1--u..0 0.9 Z 0 i=0.8-()<: a: u..-07.0...I 0.6 u.....I W CIl CIl 0.5 w>a: g 0.4w 0.3 a: a 2 4 6 8 10 TIME (SECONDS)1.1:?:E 0 0.9 z u..0 0.8 Z Q I-0.7 a:!60.6...I u..0.5 Q.0 0 0.4....0.3 0 2 4 6 8 10 Tlt..£(SECONDS)SOUTH CAROL!NA ELEClRIC&GAS CO.VIRGIl..C.SUMMER NUeu:AR STAncH FIgure 15.2-12 AMENDMl."NT 96-02 JULY 1996 SOUTH CAROLINA EI.ECTRIC&.GAS CO.VIRGIl.c.SUMlER NUCLEAR STA'TlON All I.oops Operating, One Loop CoMtIng Down: Nua-and COre HMt FhD: w.l1me FIgunl15.2-13 AMENDMENT 96-02 JULY 1996 3 2.6 2.e c::: 24 CJ Z 0 2.2:2*8,6 0 2 4 6 B 10 TIM: (SECONDS)SOUTH CAROUNA ELECTRIC&GAS CO.VIRGIL C.SUMlER NUCLEAR STAnON AD Loops 0pera1Ing, One I.oop CoaIIUng Down: DNBR¥s.11me FIgurlI15.2.14 AMENDMENT 96-02 JULy 1996 Figures 15.2-15 Through 15.2-18 Deleted by Amendment 99-01
1.4 1.2o z u.oa::: 0.8!:!:;.a::: lJJ0.6 Q.*0.4 u:::l Z 0.2 TIME (SEC)60 80 100 4.5 4 3.5 a::: a:l 3 z Q 2.5 2 1.5 0 20 40 eo 80 100 llME(SEC)SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION LOSS OF LOAOITURBINE TRIP WITH AUTO PRESSURE CONTROL MINIMUM FEEDBACK (SOL)NUCl..EAR POWER AND ONBR VS.TIME FIGURE 15.2*19 AMENDMENT 96-02 JULY H96 100 80 60 40 1.800.....-----....------.L.-----_-I-l.--1 o 20 2.8002.600 en e:.w a:2.400 en UJ Cl: Q.Cl: UJ!:::1 2.200 Cl:::>en en UJ g: 2.000 TIME (SEC)1,300 w::E::>1,100-J 0>a:1,000ffi N a: 900::>(fl (fl w a: Q.800 700 0 60 80 100 l1ME(SEC)SOUTH CAROUNA ELECTRIC&.GAS CO.VIRGIL C.SUMMER NUCLEAR STATION LOSS OF LOAOITURBINE TRIP WITH AUTO PRESSURE CONlROL MINIMUM FEEDBACK (BOLl PRESSURIZER PRESSURE AND WATER VOLUME VS.TIME FIGURE 15.2-20 AMENDMENT 96-02 JULY 1996 620 1 i:i:" 610 m s..g600-J W en en w>590 a: o ti<t W a: 580 80 60 40 20 570'--...l..--J..;.....J...
....l.--.!o TIME (SEC)1,400 1.300<<a;e:..w 1,200 It:::l (0 til W!t 1.100:E<W fo-til 1.000 SOC 0 20 40 60 80 100 TIME (SEC)SOUTH CAROUNA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION LOSS OF LOADII1JRB1NE TRIP WITH AUTO PRESSURE CONTROL M1Nlt.AUM FEEOBACK (BOL)REACiOR VESSEL TAVG AND STEAM PRESSURE VS.TIME FIGURE 15.2*21 AMENDMENT 96-02 TInv 1 Figures 15.2-22 Through 15.2-24 Deleted per RN 03-042 RN 03-042
.........J<<1.2 z0 z--'" u..0 z.8 0 j::: (.)<<.6 0:: u......., 0::...W:;r;0 0-.2 0::..:(W..J U 0::>0 20.(0 60 80\00 z TIME (SEC)RN 03-042 October 2003 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Loss Of LoadlTurbine Trip With No Pressure Control Minimum Feedback (SOL)Nuclear Power and DNSR Vs.Time Figure 15.2-25 2700.......<<iii 2600 0..'-" w 2500 a:::::>If)If)2-400.....a:: 0..a:: 2lOO w N2200:::>If)If)2100.....a:: 0..2000 80 100 0 40 60 TIME (SEC).-..1100 I")t'-" w 1050:J::::>....I 0 RN>1000 a:: 03-042 w I-<<950 a:: w!:::!a:: 900:::>If)If)w a:: 0..850 20 40 60 100 TIME (SEC)RN 03-042 October 2003 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Loss Of LoadlTurbine Trip With No Pressure Control Minimum Feedback (BOL)Pressurizer Pressure and Water Volume Vs.Time Figure 15.2-26 600........lI..Cl 595 w 0'-'Cl 590><0(..-...J 585 w (I)(I)W>580 0:: 0 I-515 u<<w 0:: 570 0.w 60 80 100 TIME (SEC)1400........:::;!;1300 (I).......w 1200 0::::>RN (I)(I)03-042 w 0:: 1100 Q..:;,:<<w 1000..-(I)900 0.w 60 100 TIME (SEC)RN 03-042 October 2003 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Loss Of LoadlTurbine Trip With No Pressure Control Minimum Feedback (SOL)Reactor Vessel T AVG And Steam Pressure Vs.Time Figure 15.2-27 Figures 15.2-28 Through 15.2-30 Deleted per RN 03-042 RN 03-042 650.0-Ctl.O LEG---HOT LEG 1 640.0/i/I 630.0./I/'---------...-I 620.0 I I;:;: I (:l 610.0 I....S\600.0\i I'"\!J...590.0 Q.\!J Q\/.Cl580.0....../......_--"""'" 570.0 560.0 550.0 1.0 10.0 100.0 1000.0 10000.0 LOOPS 1&3 1..0£+05 1.20E+05%1.00E+05 CD::::!en BOOOO.O en c:lit....60000.0 c cz:!w Co:':lit 40000.0....'" 20000.0 0.0 1.0 10.0 LOOP 2 100.0 mE (SECI 1000.0 10000.0 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUIRIER NUCLEAR STAllONof NorINII Feedwa1Ilr LDopS'-" Generator Water.....__TIme FIgm.15.2-31 AMENDMENT 96-02 JULY 1996 I*12 I 0 Z'"\:;CI: oaoQ...5 0.60':>z 0.40 0.20 00 1.0 10.0 100.0 1000.0 0 i!OOO.0 llIIlOO 1600.0......1<<10.0!=i5 1200.0 ,.a:1000.0 c'" a: 1IIlO.0§600.0'"'" It!...<100.0 200.0 0.0 10 10.0 200.0 1000.0
.0 2IlIlO.0 2600.0 C;;;e.2<100.0'"....2200.0""...a:i!OOO.0'"'"...a::....1900.0 1600.0 1.0 10.0 100.0 1000.0 0 1I1E!SEC)SOU1H CAROLINA EI.ECTRtC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Loa of NclnnaII Feedwater Nuclllar""'urtZllr' Waw YoIume and Fl9'" 15.242 AMENDMENT 96-02 JULy 1996
SOUTH CAROLINA ELECTRIC.GAS co.VIRGIL C.SUMIISl NUCLEAR STATION be I I'LolIdWiD e-.oI.IMIini&IIlwn
......NuI::*r'--
and F9n 15..2*36 AMENDMENT 96-02 JULY 1996 I 2.5 640 E 620 w c:::::l 600 t;: c:: w-580 ww 560 Sf c:: w540 w c:: 0 520 u 500 0 50 100 150 200 250 300 TIME (SECONDS)3 c:: m S 2 1.5 300 250 200 150 TIME (SECONDS)100 50 1L.-...l-l--...l-......;-"-..-J o SOUTH CAROLINA ELECTRIC..GAS CO.VIRGIL C.SUMMERSTAnON e-iMt LMd Inc:ruM wJo Conwal.Minimum FeedIMck Con Awrege'1'empw_Md DNBR w.*-Figure 15.2*36 AMENDMENT 96-02 JULY 1996 SOUTH CAROLINA aECTRIC 6.GAS CO.VIRGIL C.SUMMS\NUCLEAR EX:.I lilM LoecIwlo ComrDl.Mallilllum Feedback NudNr Poww end"'-....va.Tn.Figure 16.2-37 AMENDMENT 9 6-02 JULY 1996 ,
640 t 620 w 0::::>600-0:: W Cl..580:=w...w 5600:: W?i 540 w 0:: 0 520 u SOD 0 50 100 150 TIME (SECONDS)200 250 300 3r---------------------------.
252""----------------------1 1.5 300 250 200 150 nME (SECONOS)100 50 11.-.-:...:..--'-..:.....-'----J o AMENDMENT 96-02 JULY 1996 SOU1'H CAROUNA B.ECTRIC..GAS co.VIRGIL c.SUMMER NUCUSAR STAnON e_Loed lnc:nMe w/o e-.oI..........FeHbKIt e-A_..Tetnpw........DNBR w.T_Figur.16.2-38 1 1.4;j Z1.2 0:z-u.1 I/'0 z 0 i=0.80: u.-06 0:.W0.4 c.300 250 200 100 50 OL....---------------------------.....J od 0.2::::l z 2,600 r-------------------------...,-----.........._-,..,..---
....._-"."'--.....--300 250 200 150 11ME (SECONDS)1.800 L--l----'....:......J-;....-__--..I o 50 100 AMENDMENT 96-02 JULY 1996 SOUTH CARCUNA EL£CTRIC&.GAS co.VIRGIL C.SUMMS NUCLEAR STAnON e-.M l.alIIIwI Comral, 1MininHmI..................
ra-and Pnnca;;nr ,......va.r_F91r-16.2-39 a::;(---1l 640 E 620 w a::::;, 600a:: w c..580::E w I-W 56Ca:: w540 w a:: 0 520 to)0 50100150 200 250 300 TIME (SECONDS)3 300 250 200 150 TIME (SECONDS)100 50 11.--'-...........:.....:...'""---1 o AMENDMENT 96-02 JULY 1996 SOUTH CAROUNA EL£C1'RIC..GAS co.VIRGIL C.
NUCLfAR STATION e-.M Loed Inc:r_wi Comrol.Minimum FeedNdt Con
.......-..DNBRw.T_Figure 15.2-40 1.4z:E 1.2 0 z 1V l.I..0:2 0 i=0.80: l.I..;-0.6 w0.4 c.0.2-'u:::>z a 0 50 100 150 200 250 300 TIME (seCONDS)2.600*w:'2.400 w 0::::>en en I-w 0: 2.200 c.0: W N c::::>en en 2.000 w 0: c.1,800 0 50 100 150 200 250 300 TIME (seCONDS)AMENDMENT'96-02 JULY 1996 SOUTH CAROLINA ElECTRIC.GAS CO.VIRGIL C.SUMM8'NUCLEAR STATION Ell:***LDlId mc:r-wi Comrol**-.un F.dIllIck Nude.-'-'end PNnwiar va.T_Figwe 1&.2..-1 1 640 fi='620 w Cl:::J 600Cl: w a..580::i: w I-W 560Cl: W540 w Cl: 0 520 u 500 0 50.100 150 llME (SECONDS)200 250 300 3r--------------------------, 300 250 200 150 TIME (SECONDS)100 50 11.--"-"'----'-"'-----1 o 2 1.5 25 AMENDMENT 96-02 JULY 1996 SOUTH CARQUNA aECTRIC..GAS co.VIRGIL C.SWllMS NUCI.EAR S'mTlON e:.:-ailM t.o.I...._wI eo....ai.Mam-FeMbac:lc Core A-..
....T_Figure 16.2-42 1.2 I-..1.1...JSE 0:z 0.9....0 0.8:z:2 0.71-c::;:§0.6 e.i c::-'3: 0.:-c:: 0.:3-<""-...z......-.....'I ,", 10 20 30 40 50 60 TIME (SECONDS), I t-640-630...620...S-f I...6 lOl-a:: I:::l600r,590=....580 I.::><a:: 570....560 is u 550 540 0 10 20 30 40 TIME (SECONDS)50-60 SOUTH CAROUNA EL.ECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Accidental Depressurization of the Reactor Coolam System Nuclear Power and Core Average Temperature YS.Time Figure 15.2-43 AMENDMENT 96-02 JULY 1996 14-00--t;:;1300 WJ w.f:2 Cl:l 1200:::l (.)......WJ:::E:::l is>a:: WJ:(3: a:: WJ N 800;::::l III III 700 WJ a:: a.600 0 10 20 30 40 SO 60 mAE (SECONDS)SOUTH CAROUNA El.ECTRIC&GAS CO.VIRGIL C.SUMMER NUCI.EAR STATION Accidental Depressurization of the Reactor Coolant System Pressurizer Pressure and Water Volume ys.Time Figure 15.2-44 AMENDMENT 96-02 JULY 1996 5 4.5 4-3.5 Q....<I: Cl:: 3 l%l Z Q 2.5 2 1.5'0 10 20 30 40 50 60 TIME (SECONDS)SOUTH CAROL!NA ELECTRIC&.GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Accidental Depressurization of the Reactor Coolant System ONBR vs.Time Figure 15.2-45 AMENDMENT 96-02 JULY 1996
Amendment 00-01 December 2000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Main Steam Depressurization Variation of Keff With Core Temperature FIGURE 15.2-46 1.1 1.081.06...0....(J lU lL.1.04 c.2 i1.02:::l:a zero power, 1150 psia.end of life rodded core with one RCCA full out.98 600 550 500 450 400 350 300 250.96 200 Core Average Temperature (F) 3000.....,...-----
--..........0 en 2000 0-'-"" Q)I-en en Q)l-ll..(fJ 1000 U er::: 500 100 200 300 400 Safety Injection Flow Cgpm)From One Centrifugal Charging Pump O-+---.----....--...,...
__
........
o AMENDMENT 96-02 JULY 1996 SOUTH CAROLIlA ELECTNC...GAS co.VIRGIL c.SUMMER NUCLEAR STAllON 2500 T--------------------------....., 2000-..:::<on=-1500.......c:r::::::><on<on......c:a::: 1000=-......c:a::: c:::>SOO 0 0 200 400 aoo 800 800 550.....-.....c:a::: 500:::>--e: c:a:::.....450=-:::=-.....-.....400 c.::>-e: c:a::.....::0-350..c:......Qc:: c:::>300 250 0 200 400 600 BOO TI""E (SEC)AMENDMENT 96-02 JULY 1996 SOUTH CAROUNA ELECTRIC&GAS CO.VIRGIl.C.SUMMER NUCLEAR STATION T-*it R..,onA for a St8Ml LIne BI'lIIIk Equmlent to 2S5 IbItIec: at 1100 psla wton.lte Power Available 300 2!S0-200=-CL..CL..-1!S0::z: c::>ClI:: c::>100 c:::I:l......ClC c::>C",:l!SO 0-!SO 2 0 4 0 e 0 a 0 1000 0=-c..:>CL..->---1000=---c...:>...::.....ClI::-2000 o 200 600 800 TIME (SEC)AMENDMENT 96-02 JULY 1996 SOUTH CAROUNA ELECTRIC&GAS co.VIRGIL C.SUMMER NUCLEAR STAnON for a a-n Une BNIIk EquMIlent To 25S IbItIec at 1100 p8Ia wJOfflllleAvallabkl SOUTH CAROUNA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUClEAR STATION Spurious Actuation Of The Safety Injection System Nuclear Power, Steam Flow and Core Tavg vs.Time Figure 15.2-50 AMENDMENT 96-02 JULY 1996 1,200<>>E1,000 g-........LI..800 0 15...0 600-...en en 400<>>...Q.200 0 100 200 300 400 500 600 Time (sec.)2,600<>>2,400...en en e 2,200 Q.-...<>>cn.!::!Q.2,000:s-en (I)e 1,800 Q.1,600 0 100 200 300 400 500 600*Time (Sec.)SOUTH CAROUNA ELECTRIC&GAS CO.VIRGil C.SUMMER NUClEAR STA ilON Spurious Actuation Of The Safety Injection System Pressurizer Water Volume and Pressurizer Pressure vs.Time Figure'5.2-51 AMENDMENT 96-02 JULY 1996
3000 2500 1 000 1500 2000 Pressure (psia)500 Broken Loop 51 Flow-Intact Loop 51 Flow o-l--'--'-..J.-..1-+-..L-..L-.L-.L-+-.L-.L-.L-.L.-t-L--L--L...-J'---li--'---'---'---'-f---L---L---L--I.--1 o 10 40 50..,-----------------------------, SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Pumped Safety Injection Flow Rate Faulted Loop Injects to ReS Pressure2-4 inch Breaks Figure 15.3-la Page 10 of 39 Broken Intact Loop SI Loop SI F low F low 50-,-----------------------------,""'"-"-"-"-""-"-""""-""-"-" 40 10\\\\\3000 2500 1000 1500 2000 Pressure (psia)soo o-l--L..-L..-L..-L..-1-...l-...l-..1-..1--f-..t.--'---'--..t.--f--'---'---'---'--i-
.................
""=-"'---i-"'---"--"--"--j o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STA nON Pumped Safety Injection Flow Rate Faulted Loop Injects to Containment Pressure (0 psig)6 inch Break Figure 15.3-1 b Page II of 39 14...,------------------------------.., 12 10--..::>t::.8---.....CI>3=0 Cl........6 c CI>c:::..:::i 4 2 12 10 468 Core Elevation (ft)2 o-l---'---'-J..-+---'---'_J..-+---'---'_.L.-+---'---'_.L.--1---'----L_.L.--+---L.---L_L-....j o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Peak Rod Axial Power Shape Figure 15.3-2 Page 12 of 39 CAROUNA ELECTRIC&GAS CO.C.SUMMER NUCLEARSTATlON 15.3-3 AMENDMENT 96-02 JULy 1996 2500 2000 i--i: 1500. i a...i::: U)U)i: 1000 0-500 o o 500 Westinghouse Proprietary Class 210001500 Time (5)200 2500 3000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Reactor Coolant System Pressure (2.75-inch break)
Figure 15.3-4 Page 13 of 39 Westinghouse Proprietary Class 2 2500..,-------------------------------, 2000 I----.I::'1500*00 c...---e:::::s (I')(I')e: 1000 0-500 3000 2500 2000 1500 Time (s)1000 500 o-f-...L-..J-...L-..L-i-1.-.JI......I---L-t---'---'---J-...L-+-...L-..L-.L.-I........1I--'---L--L---'--!---J-...L-...L-...I-...i o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Reactor Coolant System Pressure (2.75-inch break)Figure 15.3-4 Page 13 of 39 "Top of Core-21.7446 35-r----------------------------, 30 2---25 e:::s.........x===20 3000 2500 2000 1500 TIme (s)1000 500 15-1-..L-..L-.l..-.I.......lc---l-..L-J..-I.--+-..L-..L-..L-.l..-.f-lc---l--L-J..-f--'-...I.-..I-.A--f-lL...--.1---L--L-I o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Core Mixture Height (2.75-inch break)Figure 15.3-5 Page 14 of 39 2000 1800 1600..1400 l.--e::..1200 e Cl c.E~1000/800/600 J 400 500 1000 Westinghouse Proprietary Class 2 1500 )2000 Time (5 2500 3000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST AnON Clad Temperature Transient at Peak Temperature Elevation (2.75-inch break)
Figure 15.3-6 Page 15 of 39 Westinghouse Proprietary Class 2 2000 1800 1600..--.1400......--e::::s---1200Cl>c...E1000 800 600 400 500 1000 1500)2000 2500 3000 Time (5 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STA nON Clad Temperature Transient at Peak Temperature Elevation (2.75-inch break)Figure 15.3-6 Page 15 of 39
--800 en-.E...: c:..0 600 e::l 0 i: en en 0 400:: Westinghouse Proprietary Class 2 1200 1000 200 o I o 500~-10001500 Time (s)200 2500 300 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST AnON Steam Mass Flow Rate Out Top of Core (2.75-inch break)
Figure 15.3-7 Page 16 of 39 Westinghouse Proprietary Class 2 1200...,....-----------------------------,I-1000----800-en..............
E...c:::l.::::::::;...
<J.>........0 600-0::::t:: 0 l.:L: en en 0 400-:::::=: I I 200-f I.j flY.,.,."" o I 0 5001000150020002500 3000 Time (s)SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST AnON Steam Mass Flow Rate Out Top of Core (2.75-inch break)Figure 15.3-7 Page 16 of 39 5 10'G i s: '+I i--=~104..co--:: Q.o c: i- 3~10 en i:~to..o Q.:: 6 10 2 10 1 10 500 ri I i L 1000 Westinghouse Proprietary Class 2 1500 (5)2000 Time 2500 300 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Clad Surface Heat Transfer Coeffcient at Peak Temperature Elevation (2.75-inch break)
Figure 15.3-8 Page 17 of 39 Westinghouse Proprietary Class 2 6 10-=------------------------------, 2 10:::=Q)o<:...:>"-310-en c::.........o Q)::c l-3000 2500 1500 (5)2000 Time 1000 1 10+--'----'---'---'-j--'---'--'----'--+--'-'---'---'---+----L...---L--'_'--+--'----'----L...---L-i 500 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Clad Surface Heat Transfer Coefficient at Peak Temperature Elevation (2.75-inch break)Figure 15.3-8 Page 17 of 39 2000 1800 1600'G 1400..~::..1200:: Q.c.E~1000 800 600 J~-l 400 500 1000 Westinghouse Proprietary Class 2 1500 (5)2000 Time 2500 300 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Fluid Temperature at Peak Clad Temperature Elevation (2.75-inch break)
Figure 15.3-9 Page 18 of 39 2000 1800 1600'G:.'1400...........:::::J.........1200::2 Q.)c..E1000 800 600400 500 1000 Westinghouse Proprietary Class 2 1500 (5)2000 Time 2500 3000 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Fluid Temperature at Peak Clad Temperature Elevation (2.75-inch break)Figure 15.3-9 Page 18 of 39 Westinghouse Proprietary Clas 2 2400 2200 2000 1800..c:. i c: 1600--~:: cr 1400 cr~0.1200 1000 800 600 0 100020003000 4000 5000 6000 Time (5)SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Reactor Coolant System Pressure (2-inch break)
Figure 153-lOa Page 19 of 39 Westinghouse Proprietary Class 2 2400 2200 2000 1800..--..0*en c..1600--;::, (/)1400 (/)0....1200 1000 800 600 0 1000 2000 3000 4000 5000 6000 Time (5)SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Reactor Coolant System Pressure (2-inch break)Figure 15.3-lOa Page 19 of 39
'" Top of Core-21.7446 34 32 30 28---.......----Ci3 26>-..324::;,.......><:::iE 22 20 18 16 0 1000 2000 3000 4000 5000 6000 Time (8)SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Core Mixture Height (2-inch break)Figure 15.3-10b Pags 20 of 39 Westinghouse Proprietary Class 2 1400 1200 ('G 1000--/~='..e l Q.c: E 800 Q.i-600 400 2000 3000 4000 Time (5)500 6000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation (2-ineh break)
Figure i 5.3- lOe Page 21 of 39 Westinghouse Proprietary Class 2 14oo-r-----------------------------, 1200'G:" 1000---::;:,......e Q,)Q..E 800 Q,)I-600 400+--l-..1.---L.-I--f----'-_..L.--'----lL---f--..L_J..--L..--l_-f---L._I-....L...--l-----1 2000 3000 4000 5000 6000 Time (5)SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation (2-inch break)Figure 15.3-lOc Page 21 of 39 2500 2000 ,.-o. i a.--~ 1500:=(I en~CL 1000 500 o 1000 Westinghouse Proprietary Class 2 2000 3000 Time (s)400 5000 600 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST AnON Reactor Coolant System Pressure (2.25-inch break)
Figure 15.3-1 la Page 22 of 39 Westinghouse Proprietary Class 2 2500..,.....-----------------------------, 20001500:::::s (I)(I)0..1000 6000 5000 4000 3000 Time (s)2000 1000 500-+-....&..-..L--'---'--t--'L......J---L--L-+-'---I---'-....&..-+--'---'--.L..-L-j:....-L--L--'--'--+--'-....L.......&..--,-!
o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Reactor Coolant System Pressure (2.25-inch break)Figure 15.3-11a Page 22 of 39 Top of Core-21.7446 34 32 30 28-:::;:::;--
-...........
Ci.5 26>-e 24::;,........x:::.::=20 18 6000 5000 4000 3000 Time (s)2000 1000 16-!--l--l-...I.-...I.-+-...l.-...l.-.l-..l-.+-'--'--'--'--!-JL.-JL.-J'--l--l--'--'--'--...L-+--L--L--L-J..--l o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Core Mixture Height (2.25-inch break)Figure 15.3-11b Page 23 of 39 1600 1400 1200-c--~:=--1000 I~(I a.E~800!600 I 400 1000 Westinghouse Proprietary Class 2 2000 3000 (5)4000 Time 500 6000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Clad Temperature Transient at Peak Temperature Elevation (2.2S-inch break)
Figure lS.3-11c Page 24 of 39 Westinghouse Proprietary Class 2 1600....-----------------------------, 1400 1200-c:-----:=J--1000 ICI.>a..E800!600 I 6000 5000 3000 (5)4000 Time 2000 400-1---'---'---'---'--t--l.--1----'--t-..L-..L.---'--j---'---'---'---'--t--l.--1----'---i 1000 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Clad Temperature Transient at Peak Temperature Elevation (2.25-inch break)Figure 15.3-11c Page 24 of 39 2500 2000..o. i c:--e 1500:: en en e Cl 1000 500 o Westinghouse Proprietary Class 2
\~\1000 2000 300 Time (5)400 5000 600 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Reactor Coolant System Pressure (2.S-inch break)
Figure lS.3-12a Page 25 of 39 Westinghouse Proprietary Class 2 2500...-----------------------------, 2000-I::'.(;5 c...--e 1500-:::l en en e Cl...1000\\1000 2000 3000 Time (5)4000 5000 6000 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STA nON Reactor Coolant System Pressure (2.5-inch break)Figure 15.3-12a Page 25 of 39 Top of Core-21.7446 35-.------------..,..------------------, 30-........0.+--Ci3:>-..5 25 e;:::,........x::E 20 6000 5000 4000 3000 Time (5)2000 1000 15 o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Core Mixture Height (2.5-inch break)Figure 15.3-12b Page 26 of 39 1800 1600 140-c--1200~::--~Q.c.1000 E~800 600 I 400 o Westinghouse Proprietary Class 2 1000 2000 3000 Time (s)400 5000 6000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Clad Temperature Transient at Peak Temperature Elevation (2.5-inch break)
Figure 15.3-12c Page 27 of 39 Westinghouse Proprietary Class 2 1800-.---------------------------, 1600 1400-c;::----1200::::::l..-.Q.)c..1000 E800 600 I 6000 5000 4000 3000 Time (s)2000 1000 400+--'---'--"--'--!--L
........-'--'--;--'--"--
........-+........-'--'--'--+-"--
........--L-+-'--'--'---'--i o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Clad Temperature Transient at Peak Temperature Elevation (2.5-inch break)Figure 15.3-12c Page 27 of 39 2500 2000..0 1500'nc:--~:: en en~1000 Cl 500 o o 500 Westinghouse Proprietary Class 2 1000 1500 Time (5)200 2500 3000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Reactor Coolant System Pressure (3.0-inch break)
Figure 15.3-13a Page 28 of 39 Westinghouse Proprietary Class 2 25oo-r------------------------------, 2000---0 1500'00 c..--::::s en en<J.)1000 a..500 3000 2500 2000 1500 Time (5)1000 500 o+--'--...l...-..L..-.L-f-lI.-..L
.......--'--+.........--'--'--'--+-..L..-.L-L......J'---t
.......--'---..L.
.........-t--'--'---'---'-l o SOUTH CAROLINA ELECTRIC&GAS CO, VIRGIL C.SUMMER NUCLEAR STATION Reactor Coolant System Pressure (3.0-inch break)Figure 15.3-13a Page 28 of 39 Westinghouse Proprietary Class 2 35 Top of Core = 21,7446 30 i..~--1i~~25~::--x\::\20 15 o 50010001500 Time (5)2000 2500 3000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Core Mixture Height (3.G-inch break)
Figure 15.3-13b Page 29 of 39 Westinghouse Proprietary Class 2 Top of Core=21.7446 35.,-------------------------------, 30----------<i3:>25\::;:,---x:::iE-."-20 3000 2500 2000 1500 Time (5)1000 500 15+--'--...L......L.-..I..-+-.l...-L..-L.-.JL........j.......J........J.-.L--L.-+-1...-1......J.........L-+--'--...L......L.-..I..-+-.l...-L..-L.-.JL........j o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST AnON Core Mixture Height (3.G-inch break)Figure 15.3-13b Page 29 of 39 Westinghouse Proprietary Class 2 2000 1800 1600'G--1400 /'200 ~':: /600 J~::..e Q.Cl E~400 500 1000 1500 (S)2000 Time 2500 3000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation C3.0-inch break)
Figure 15.3-l3c Page 30 of 39 Westinghouse Proprietary Class 2 2000..,.-----------------------------, 1800 1600 1400 1200 1000/800 3000 2500 1500 (S)20oo Time 1000 400+-L.-..L.--J.-.J_!--.1..-..L--'--'--f--..L.--J.-.J_L...-+-..L--'--'--L.-+--J.-.J_L...-,,--!
500 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation C3.0-inch break)Figure 15.3-13c Page 30 of 39
..0 1500. ei c.--~:: en en~1000 0-Westinghouse Proprietary Class 2 2500 2000 500 o o 50010001500 Time (5)2000 2500 300 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST AnON Reactor Coolant System Pressure (3.25-inch break)
Figure 15.3-14a Page 31 of 39 Westinghouse Proprietary Class 2 25oo-r-----------------------------, 2000 I.--..0 1500'en CL............;::, en en<l.>.....1000 0....500 3000 2500 2000 1500 Time (5)1000 500 0+--'--...L.-J..-L-f-l--L-l..--L.-+--L-....1...-'--'--+-J..-L-L.-.I-f-l..--L.--L.--L--1--'--'---'---,-!
o SOUTH CAROLINA ELECTRIC&GAS CO, VIRGIL C.SUMMER NUCLEAR STATION Reactor Coolant System Pressure (3.25-inch break)Figure 15.3-14a Page 31 of 39 3000 2500 2000 Core Mixture Height (3.25-inch break)Figure 15.3-14b SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION 1500 Time (s)1000 500Top of Core-21.7446 15-I-..J.-..L-..L-l..-j--L-J...--I..-.L.-1-..J...:....L-..L-..L-I--J--L-J...--I..-I-....I-..J.-..L-..L-J--..l--L--l.-J...-1 o 20 35.....-----------------------------, 30..--::::::::----Ci3:>-..3 25 e:;::l........x::::E Page 32 of 39 Westinghouse Proprietary Class 2 1800 1600 1400-c--1200~=:..~~(l Cl 1000 E~/800 i J 600 400 o 500 1000 1500 Time (s)2000 2500 300 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation (3.25-inch break)
Figure 15.3-14c Page 33 of 39 Westinghouse Proprietary Class 2 18oo-r-------------------------------, 1600 1400-c;::-----1200:::s........((1)Cl..E 1000800 J 600 3000 2500 2000 1500 Time (s)1000 500 400-f--'--..L..-
..........
'-t--'--'--'--'-+-..L..-
..........
'--I.-+-'--'--'--'--+-
..........
'--I.--'--t--'--'--'--.L-.j o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation (3.25-inch break)Figure 15,3-14c Page 33 of 39
~.~ 1500 c:..~:: en en~0- 1000 Westinghouse Proprietary Class 2 2500 2000 500\\~o o 500 1000 1500 Time (s)200 2500 3000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Reactor Coolant System Pressure (4.0-inch break)
Figure 15.3-15a Page 34 of 39 Westinghouse Proprietary Class 2 2500.,----------------------------, 20001500 c...............::;, en en0-1000 500 3000 2500 2000 1500 Time (s)1000 500 o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Reactor Coolant System Pressure (4.0-inch break)Figure 15.3-15a Page 34 of 39 35...,.-------------------------------, 3000 2500 2000 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION 1500 TIme (5)1000 500'" Top of Core-21.7446 30 15 10-I-....I-....I-..I-..I-4-...L-...L-..L-..L-+-.l-.l-.l-.l-i-.L..-.L..-'---'---1t---J
........................
--i--L--L--I.--I......, o Core Mixture Height (4.0-inch break)Figure 15.3-15b Pag8 35 of 39 1600 1400 1200-c-~::..1000~(l c.E~800 Westinghouse Proprietary Class 2 600 lJ 400 o 500 1000 Time (s)1500 2000 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation (4.0-inch break)
Figure 15.3-15c Page 36 of 39 Westinghouse Proprietary Class 2 1600.....---------------------------, 1400 1200 a::;::-"--":::::3--1000(l)c..E800 600 2000 1500 1000 Time (s)500 400-f---L_.l...--J....--L_.j--J....--L_.l...--J....-+_.l...--J....--L_.l...--I---L_.l...--J....--L----1 o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Clad Temperature Transient at Peak Temperature Elevation (4.0-inch break)Figure 15.3-15c Page 36 of 39 Westinghouse Proprietary Class 2 2500 2000..0 1500.üS Q.--~:: en en~1000 a.\500~0 0 500 1000 1500 200 Time (5)SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR ST A nON Reactor Coolant System Pressure (6.0-inch break)
Figure 15.3-16a Page 37 of 39 Westinghouse Proprietary Class 2 2500...,.-----------------------------, 2000............
0 1500*US Q..----::::I en en1000 a...500I-2000 1500 1000 Time (5)500 o-t----'--""----'--------t---'--'--'----'-;---'--'---'----'--'i---'----"'---'----'---i o SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Reactor Coolant System Pressure (6.0-inch break)Figure 15.3-16a Page 37 of 39 2000 1500 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR ST A nON Core Mixture Height (6.0-inch break)Figure 15.3-16b 1000 Time (5)500 Top of Core-21.7446 10+---L_.1..-....I----L_+--'---1_-'----I.._/--...I--..I.._.l...-....I--+_.1..--'---1_-'---I o 15 30 35....------------------------------.
Page 38 of 39 1000 900 II 800'G--700 e::..0..(1 Cl 600~E i2 500 400 300 o Westinghouse Proprietary Class 2 500 1000 Time (s)1500 200 SOUTH CAROLINA ELECTRIC & GAS CO.
VIRGIL C. SUMMER NUCLEAR STATION Clad Temperature Transient at Peak Temperature Elevation (6.0-inch break)
Figure lS.3-16c Page 39 of 39 Westinghouse Proprietary Class 2 1000.------------------------------, 900 800"G:"...---700 e...::::s---0.......<U r-0..600+Et-ee 3-10............L&.I o (,,)1 d c::: L&.I......en z-<C:::.1 t-10-<L&.I::c:I-II-.---.......-::---III******II**IIIIIIIIIIII 0 1000 1500 2000 2500 3000 3500 40 00 TIME (S)t.SOUTH CAROUNA ELECTRIC It GAS CO.VIRGIL C.SUMMER NUCLEAR STAnON Clad Surface Heat Transfer Coefficient at Peak Temperature Elevation (3-inch break)Figure 15.3*20 AMENDMENT 96-02 JULY 1996\\
,-----------------------------------------
00 1800 1600 1400-U--UJ 1200 0::::::;)I-<0:: 1000 UJ c..:::::E UJ I-800 600 400 5 l-t I-\l-I v\.A..l-I-I ,...........'\l-I-I\I--U ,-I....-l-I l-I-I, I*II*I 010001500 2000 2500 3000 3500 40.",'.J t J.TIME (5)SOUTH CAROUNA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Fluid Temperature at Peak Clad Temperature Elevation (3-inch break)Figure 15.3-21 AMENDMENT 96-02 JULY 1996 10 8 4 6 TIt.£: (SECONDS)2:::l 1.1 1-------------------------------:E g LL.o 5 i=0.9ct LL.i 0.8 g LL.ill 0.7 en enct 0.6w ct 1.2 r----------------------------.
j:E g LL.o 0.8 S0.6!:!:.x:::l it 0.4w J:0.2 o u o........1."--....J-"----J o 2 4 6 8 10 Tlt.E (SECONDS)AMENDMENT 96-02 JULY 1996 soutH CARQUNA ELECTRIC..GAS co.VIRGIL C.SUMMER NUCLEAR STATION 1 12:E 0:z I.l..0:z 0.8 Q....0.6 a:!:!::.a: w0.4 Q.a: L5 02.....C,,):::J:z 0 0 2 4 6 8 10 T1tJE (SECONDS)2.4 22 2 a: 18 a:l:z 0 16 14 1.2 1 0 2 4 6 8 10 T1tJE (SECONDS)AMENDMENT 96-02-JULY 1996 SOUTH CAROLINA ELECTRIC&.GAS<:0.VIRGIL C.SUMMER NUCLEAR STATION
~
RN 06-040 July 2009 BLOWDOWN 0 second BREAK OCCURS REACTOR TRIP PUMPED SI SIGNAL (PRESSURIZER PRESSURE)
ACCUMULATOR INJECTION BEGINS PUMPED ECCS INJECTION BEGINS (ASSUMING OFFSITE POWER AVAILABLE) 20-30 seconds CONTAINMENT HEAT REMOVAL SYSTEM STARTS (ASSUMING OFFSITE POWER AVAILABLE)
END OF BYPASS REFILL END OF BLOWDOWN 30-40 seconds BOTTOM OF CORE RECOVERY REFLOOD ACCUMULATOR EMPTY 10 minutes CORE QUENCHED LONG TERM COOLING 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SWITCH TO COLD LEG RECIRCULATION ON RWST LOW LEVEL ALARM SWITCH TO HOT LEG/COLD LEG RECIRCULATION
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Typical Time Sequence of Events for the Virgil C. Summer Nuclear Station BELOCA Analysis Figure 15.4-1a
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Peak Cladding Temperature for Reference Transient Figure 15.4-1b RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Break Flow on Vessel Side of Broken Cold Leg for Reference Transient Figure 15.4-1c RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Break Flow on Loop Side of Broken Cold Leg for Reference Transient Figure 15.4-1d RN 06-040 July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Void Fraction at the Intact and Broken Loop Pump Inlet for Reference Transient Figure 15.4-1e RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Vapor Flow Rate at Midcore in Channels 11 and 13 During Blowdown for Reference Transient Figure 15.4-1f RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Collapsed Liquid Level in Lower Plenum for Reference Transient Figure 15.4-1g RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION One Intact Loop Accumulator Mass Flow Rate for Reference Transient Figure 15.4-1h RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION One Intact Loop Safety Injection Mass Flow Rate for Reference Transient Figure 15.4-1i RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Collapsed Liquid Level in Core for Reference Transient Figure 15.4-1j RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Collapsed Liquid Level in Downcomer for Reference Transient Figure 15.4-1k RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Vessel Fluid Mass for Reference Transient Figure 15.4-1l RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Peak Cladding Temperature Location for Reference Transient Figure 15.4-1m RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Peak Cladding Temperature Comparison for Five Rods for Reference Transient Figure 15.4-1n RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION Lower Bound Containment Pressure for Best Estimate Large Break LOCA Figure 15.4-1o RN 06-040
July 2009
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION 28 Core Peripheral Assembly Locations Figure 15.4-1p RN 06-040
July 2009 PMID0.250.300.350.400.450.50 PBOT 0.15 0.20 0.25 0.30 0.35 0.40 0.45(0.30, 0.43)(0.30, 0.315)(0.30, 0.28)(0.3325, 0.2575)(0.365, 0.20)(0.43, 0.20)(0.44, 0.21)(0.44, 0.315)(0.44, 0.36)(0.43, 0.375)(0.365, 0.43)
Note: MONTEC sampling range indicated by dashed line is Analysis Limit. Associated WCOBRA/TRAC response surface range is indicated by solid line.
SOUTH CAROLINA ELECTRIC & GAS CO. VIRGIL C. SUMMER NUCLEAR STATION PBOT/PMID Core Design Limit Figure 15.4-1q RN 06-040 July 2009
RN 06-040 Figures 15.4-2 Through 15.4-67 Deleted per RN 06-040
10*3
...................................
-:..'""..10 oS..*********.**********
- .*
,***..*....*.******....
- ..**..**************
- ..****************.***
- .**...**....**.*.....
Hydrogen Generation SCM/SEC*M 2 r........::..:...:.:.2.5 3.0 3.5 10001T (OK)AMENDMENT96-03 SEPTEMBER 1996 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Hydrogen.Generation from Aluminum Corrosion' ANS 56.1 Figure 15.4-68 10*s
........................
- ........................
- j..*.10'" 10.8:-:-.*...::::*...*...*...::::*...*...*...*.*.*.*.*.*.*.*.*.Hydrogen Generation SCM/SEC-M 2 10.9 2.0 2.5 3.0 3.5 AMENDMENT 96-03 SEPTEMBER 1996 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGil C.SUMMER NUCLEAR STATION Hydrogen Generation from Zinc Corrosion-ANS 56.1 Figure 15.4-69 HYDROGEN PRODUCTION RATE - NO RECOMBINER 0 1 2 3 4
5 6 70102030405060708090100TIME FOLLOWING LOCA (DAYS)
HYDROGEN PRODUCTION RATE (SCFM) .
TOTALRADIOLYSISAl + Zn CORROSION
RN 03-005 June 2003 SOUTH CAROLINA ELECTRIC & GAS CO VIRGIL C. SUMMER NUCLEAR STATION Hydrogen Production Rate No Recombiner Figure 15.4-71 RN 03-005 HYDROGEN ACCUMULATION - NO RECOMBINER0.0E+002.0E+044.0E+046.0E+048.0E+041.0E+051.2E+051.4E+05 1.6E+051.8E+052.0E+052.2E+052.4E+050102030405060708090100TIME FOLLOWING LOCA (DAYS)
HYDROGEN ACCUMULATION (SCF) .TOTALRADIOLYSIS Al + Zn CORROSION ZIRC-WATER
RN 03-005 June 2003 SOUTH CAROLINA ELECTRIC & GAS CO VIRGIL C. SUMMER NUCLEAR STATION Hydrogen Accumulation No Recombiner Figure 15.4-72 RN 03-005 VOLUME PERCENT HYDROGEN 0 1 2
3 4
5 6 7 8
9 100102030405060708090100TIME FOLLOWING LOCA (DAYS)
VOLUME PERCENT HYDROGEN .NO RECOMBINERRECOMBINER STARTS AT T=1 DAY
RN 03-005 June 2003 SOUTH CAROLINA ELECTRIC & GAS CO VIRGIL C. SUMMER NUCLEAR STATION Volume Percent Hydrogen In Containment Figure 15.4-73 RN 03-005
0.4 0.1 0.2 0.3 POWER (FRACTION OF NOMINAL) 0.0....J<{a::: o WZZ W U c: L...W o U a::: 1000 w.....l Q..C:..o o u..o Si'2000....---------------------_----, u Q...........SOUTH CAROLINA ELEC1'R1C&GAS co.VIRGIL C.SUMMER NUCLEAR STAlION v.tdaft of A.etIYIty WIth Pow.-At ConaDnt COre."..T_.,.atunI figure 15.4-75 Amendment 96-02 July 1996
.3C3=*E.25<:::>=<5.2=<:::>:.=<..>.15><=.1=<::><1.>=.5E-Ol e<:::><...:>0 0 100 200 300 400 Time (seconds)500 600 2500 2000.S:?en=-1500=en<n e 1000 CL e<:::><..>500 0 0 100 200 300 400 Time (seconds)500 600 RN 01-125 600 500 200 300 400 Time (seconds)100 o w-en<1.>e='3 500 e..a400 ERN 01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Transient Response to a Steam Line Break Double Ended Rupture With Offsite Power Available (Case A)Figure 15.4-76 3500<:><L>3000 en--E-=2500-=--S 0 2000=:::;0:=1500 c;:: en en 0 1000===E 0 500-S C/)0 0 100 Intact SGs Faulted SG 200 300 400 Time (seconds)500 400 300 E=-200=e=co 100=<...:>0-100 0 100 200 300 400 500 600 Time (seconds)RN 01-125 2000 1000 E<->r--2='0 f0<L>=:::-1000-2000 0 100 200 300 400 500 600 Time (seconds)RN 01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Transient Response to a Steam Line Break Double Ended Rupture With Offsite Power Available (Case A)Figure 15.4-77
- a.-.a.i--..*a*--.:::..***i------*.=-.....V*s.*c-o.0.0.ao*ao.....******-****\:=.£*****--i:-"-.5**************a**********-***---***--:;-Ii***---***---;:***-...=aoo...a**TIME (SEC)**AMENDMENT 99-01 JUNE 1999 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Transient Response To A Steam Line Break Double Ended Rupture Without Offsite Power Available (Case B)Figure 15.4-78
,.s W*..!.-.I-.!!F"AUlTED s;;:;*a**'II***a**i" ao.-,..I 10.I.0*-..**ao**..,..------_:--
-, 1000=*+-+..;;;:=----------------------i
- -:::---a***
TIMe caec)AMENDMENT 99-01 JUNE 1999 SOUTH CAROLINA ELECTRIC&GAS CO.VIRGIL C.SUMMER NUCLEAR STATION Transient Response To A Steam Line Break Double Ended Rupture Without Offsite Power Available (Case B)Figure 15.4-79 Figures 15.4-80 Through 15.4-82 Have Been Deleted Amendment 96-02 July 1996 1.4 0 (c E 1.2 0 c"-0 c 0.B:.;:::;u 0'-"-.6------'-Q):;:: 0.4 0-'-0 Q).2 u::::J:z 0 0 1 2 3 4 5 10 10 10 10 10 10 Time (seconds)1.4,---------------------------, RN 01-125 o 1 2 3 4 5 10 10 10 10 10 10 Time (seconds).4.2-+-'o Q)::r::: Q)o o g/"E 1.2r-------/o c o:.;:::;.8 u o'-"-------.6 x::::J Lt...RN 01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture With Offsite Power Nuclear Power and Core Heat Flux VS.Time Figure 15.4-83 2600.------------------------,.......-.-
o2400------Q)::J en en2200-t------1800 o I 2 3 4 5 10 10 10 10 10 10 Time (seconds).......-.-
1600-+-'Q)Q)'+-.S2 1400...0::J<..>------Q)E 1200::J 0>-'-Q)1000-+-'0 3='-Q)N 800-;:::::J en en Q)'-CL 600 0 1 10 10 2 3 10 10 Time (seconds)4 10 5 10 RN01-125 May 2002 RN 01-125 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture With Offsite Power Pressurizer Pressure and Water Volume vs.Time Figure 15.4-84 Hot Leg Cold Leg----------, I I I I-c=--660 UJ640.....en Q)3620 UJ Q).......3 600Q)CL E 580 Q)I-g-560-.3-g 540:::t=::::J520;---JL......J-l-L.J.J..l.lf--...L-..L-L...L.l...u..L.j--l--L.L.L..ll.JJ4---I.--l....L..J..J..J.J-4-_l.-J'--L.L..J.J..J.J..I o 1 2 3*5 10 10 10 10 10 10 Time (seconds)RN 01-125 5 10*10 2 3 10 10 Time (seconds)I 10 Hot Leg Cold Leg 520;----I---l...J-l..J....LJ-4----J'--L-WLU..l4-_L...J-Lw..L.llJ-_L...JL...l...w..L.llJ-_L...JL..I-.J..J.J..J.J..I o 10.........540 u o.........c C'660
'-'-Saturation UJ640.....en Q)3620 UJ Q)600.........o.....Q)E 580 Q)I-CL 560 o o---.J RN 01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture With Offsite Power Faulted and Intact loop Coolant Temperature vs.Time Figure 15.4-85 14000*u:;1200 I 0------I Intact Q>I'-1000::;, I UJ r/UJ.....I\",--'Q>-'\\'-800 0-,f'-I 0.......600 0'-Q>C Q>400 Faulted<.:)E 0 200 Q>.......if)0 0 1 2 3 4 5 10 10 10 10 10 10 Time (seconds)120000 FaultedE 100000------..Q-----UJ UJ 80000 0:::2: '-0 60000.......0'-Q>C Q>40000<.:)E 0 Intact Q>20000.......-------------
if)'\._---0 0 I 2 3 4 5 10 10 10 10 10 10 Time (seconds)RN01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture With Otfsite Power Steam Generator Pressure and Water Mass vs.Time Figure 15.4-86 RN 01-125 1.4......--..
(<::>c E 1.2 0 c'+-0 c 0.8:;:::;<.><::>.....'+-.6'--'.....Q)3: 0.4 0........<::>Q).2<.>::::s:z 0 0 I 2 3 4 5 10 10 10 10 10 10 Time (seconds)......--..
1.4<::>(c E 1.2 RN 0 c 01-125'+-<::>c 0:;:::;.B<.><::>.....4-'--'.6 x::::s l..L-.......4<::>Q)::I:.2 Q).....0<..,)0 I 0 I 2 3 4 5 10 10 10 10 10 10 Time (seconds)RN 01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture Without Offsite Power Nuclear Power and Core Heat Flux VS.Time Figure 15.4-87 2600 en 0..'--'Q.)2400'-;:)en en Q.)2300'-0...'-Q.)N 2200'C;:)en en Q.)'-2100 0...2000 0 1 10 10--..1600-+-'Q.)Q.)'->-(.):.0 1400;:)(.)'--'Q.)E 1200;:)0::>'-Q.)1000-+-'0:5: '-Q.)N 800'C;:)en en Q.)'-0...600 0 1 10 10 2 3 10 10 Time (seconds)2 3 10 10 Time (seconds)4 10 4 10 5 10 5 10 RN 01-125 May 2002 RN 01-125 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture Without Offsite Power Pressurizer Pressure and Water Volume vs.Time Figure 15.4-88
..-...660 u...Saturation U>......Hot Leg c:n/Q)/620----------, , I U>I Q)I/......-3 600 ,/0 , I......Q)I Q...E 580 Q)I--g-560 Cold Leg 0--l-0 540 Q)=:::::::J 0 u...520 0 1 2 3 4 5 10 10 10 10 10 10 Time (seconds)RN 01-125 5 10 4 10 2 3 10 10 Time (seconds)1 10 Hot Leg Cold Leg 520+---'--..l....J...J...J..J..Llf---J.--l......l-l...l...U.lf----l--'-....l-l...J..U.lf----l--J....l-Ju..L.Uf-_J..-'--l...J..J.J...&..y o 10 U>Q)::;600.......o......Q)Q...580 E Q)I--Q...560 o o--l.......540 (J o.......c:-c.;::::--
660 U>640......c:n Q) RN 01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture Without Offsite Power Faulted and Intact loop Coolant Temperature vs.Time Figure 15.4-89 1400...--...0"c:n 1200 f 0-f Inta<{t------f<J.)1000 f'-::J'\I (I)(I)I\/<J.)-,.,,--'-800\/0-V'-0-+-'600 0'-<J.)c Faulted<J.)400 0 E 0 200<J.)-+-'(/)0 0 1 2 3 4 5 10 10 10 10 10 10 Time (seconds)120000 Faulted...--...E 100000..0.;::::...(I)(I)80000 0:::::2: '-0 60000-+-'0'-<J.)c<J.)40000 0 E 0<J.)20000-+-'(/)0 0 1 10 10 I I I I I I f Intact""
'" 2 3 10 10 Time (seconds)4 10 5 10 RN 01-125 May 2002 RN 01-125 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION Main Feedwater Rupture Without Offsite Power Steam Generator Pressure and Water Mass vs.Time Figure 15.4-90
Figures 15.4-92 Through 15.4-94 Have Been Deleted Amendment 96-02 July 1996 0.9c:: '+-0 ,8 c:: 0:.;::;.7<..>0.....'+----....--3:.6 0 LL.(/).5 0 0::: 0.4.......0 I-.3 0 2 4 6 8 10 Time (seconds)1.2..--...0:e RN c:: 01-125'+-0.8 c:: 0:.;::;.6<..>0.....'+-\---....--.4 3: 0 LL..2 Cl..0 0 0...J-0 Q).......-.2::::l 0-LL.'-.4 0 2 4 6 8 10 Time (seconds)RN 01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION All Loops Operating, One Locked Rotor RCS Flow and Faulted Loop Flow vs.Time Figure 15.4-95 1.2.....--...
0 c: E 0 c: '+-0.8 c: 0:;::;<.>0.6'-'+----......-
'-Q)3:=.4 0 0-'-0.2 Q)<.>:;:):z: 0 0 2 4 6 8 10 Time (seconds)1.2 0 RN c: E 01-125 0 c: '+-0 c: 0*8:;::;<.>0'-'+----......-
x.6:;:)u--+-'0 Q).4:I: Q)'-0<...:>.2 0 2 4 6 8 10 Time (seconds)RN01-125 May 2002 SOUTH CAROLINA ELECTRIC&GAS CO VIRGIL C.SUMMER NUCLEAR STATION All Loops Operating, One Locked Rotor Nuclear Power and Core Heat Flux vs.Time Figure 15.4-96A RN 09-017 RN 01-125 RN 01-125 Peak pressure in this figure will increase less than 45 psi
[55] when a more limiting, maximum initial pressurizer level is considered.
RN 09-017 August 2009 SOUTH CAROLINA ELECTRIC & GAS COVIRGIL C. SUMMER NUCLEAR STATION All Loops Operating, One Locked Rotor Maximum RCS Pressure and Hot Spot CladTemperature vs. Time Figure 15.4-96B
Figures 15.4-97 Through 15.4-99 Have Been Deleted Amendment 96-02 July 1996 20 z 1.5 u..0a:::!!:.a:: wQ.a::<w 05-'u;:)z 0 0 2..6 e'0 TlME(sec)6.000 t.$.000 Fuel MeltiDg 49Q()Gf"" a::::::J<4000 Cl:....Q.:::i....3000-u c 2.000 i..J""::::J ,.OCIC...0 0 2 4 6 8 10 TlME(secl SOUTHaECTRIC...GAS co.VIRGIL C.SUMMER Nua.EAR STATION Rod Eiec'don Acc:ident 8CIl H1=P NlId.r'-.Hilt Sll'llt FUlII and aadT..........
w.T_Rpn 16.4-100 Amendment 96-02.July 1996 1 leX)0 Z to....0 (.)<!:.Ll.Ic..<Ll.I 0.1...(.)::l Z 0.01 0 4 6 8 10 TlME{SC)6.000 r-------------------------.
E 5.000 IoU a::::l...4.000 IoU 0..:E l!!3.000....(,,)02.000....IoU: 1.000......_a.._______..10 8 6 4 2 oL-.------:..-----------:..
...l o TIME (sec)Amendment 96-02 July 1996 RoO EiecDDn Accident 80L HZPPaw..Hot SIlOt FUIII and Qed T........."..T_Re-1&.4-101 Figures 15.4-102 Through 15.4-104 Have Been Deleted Amendment 96-02 July 1996
RN06 040Figures 15.4-105 Through 15.4-122 Deleted per RN 06-040 June 2009
Figures 15.4-123 Through 15.4-142 Deleted per Amendment 96-02 Amendment 96-02 July 1996