ML19323F855

Slide Presentation Entitled Agenda for ACRS Presentation

ML19323F855
Person / Time
Site:	Crane
Issue date:	05/10/1979
From:	Burchill W, Daleas R, Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:
Shared Package
ML19323F848	List: ML19323F846 ML19323F855
References
TASK-TF, TASK-TMR ACRS-CE-210, NUDOCS 8005290547
Download: ML19323F855 (57)

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{{#Wiki_filter:x O' vn x o, 55 AGENDA FOR e o ACRS PRESENTATION S a MAY 10, 1979 Co N""2 I. INTRODUCTION - A. E. SCHERER Z (A' )g w n ~ ~ n 4B n t,, o r8 II. DESIGN FEATURES OF C-E NSSS ? 8 - W. E. BURCHILL r+(d/3 $ g ga, m h (C3 -III. C-E NSSS RESPONSE d$ 3 El$

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=] %.r + p$ 2 @ 23! A. NATURAL CIRCULATION s - R. S. DALEAS (D C '~J. E, i T W1 B. SMALL BREAK LOCA - J. LONGO 2 "" $C C 'T C. LOSS OF FEEDWATER FLOW AND PORV MALFUNCTION - C. KLING $ "f~TJ ] N IV. C-E PLANT EXPERIENCE - W. R. CORCORAN om OBSERVATIONS ON 18E BULLETINS AND ACRS RECOMMENDATIONS 4 V. CONCLUSIONS - F. M. STERN A \\' 1 nW1 A D % S& ?~ X

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d* NSSS GENERAL ARRANGEMENT ~ e p \\ / s' '/ A4' %.) A_ $, 3 6 ,k* ?,' Et U w 29' / 9F

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= s IMPACT OF NSSS LAYOUT j t O NSSS ELEVA' TION LAYOUT OF MAJOR COMPONENTS t ENHANCES RCS NATURAL CIRCULATION i C A P A BILITY ALLOWS ONLY 20 - 25% OF RCS INVENTORY 'IO COVER REACTOR CORE e I i 1

g i STEAM GENER ATOR DESIGN I M M M 4 M M M M M M M M M M M M / N fy w s

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x\\;'n: x\\h\\:: ^ l l FULL POWER TRIP SETPOINT l

L i, b ~ IMPACT OF STEAM GENERATOR DESIGN l i SECONDARY WATER INVENTORY AND REACTOR TRIP ON LOW SECONDARY WATER LEVEL n NORMALLY PRECLUDE OPENING PRESSURIZER RELIEFIS AFETY VALVES FOLLOWING LOSS OF FEEDWATER ALLOW SUFFICIENT TIME FOR ESTABLISHING AUXILIARY OR EMERGENCY FEEDWATER l ~ k ~ o t-l 1 { F" b 4 g e .e a ee, .gp e ,,.ese e e's .g g e

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L = 9 s > QUENCH TANK o RTD o RTD g-S A w ns ~ X n SAMPLE < X X O SYSTEM g SUMP 4-Cx0" PRESSURIZER ~ I 1 = i e f% t PRESSURIZER POWER OPER ATED RELIEF V ALVES CONFIGUR ATION 4 s. s ~;-.-..--*-~ , c ...

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.l i i IMPACT OF PRESSURIZER POWER OPERATED RELIEF VALVE l CONFIGURATION DESIGN n DUAL POWER' OPERATED RELIEF VALVES AND 1 J RTDs IN THE VALVE DISCHARGE LINES ALLOW CONTROLLED PRESSURE RELIEF WITH ONE' VALVE BLOCKED OUT ALLOW COMPARIS0N.0F VALVES' DISCHARGE ^ LINES TEMPERATURES ' ,e. .i .h N$G;- L'q;r.. :.:; 9.':

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i HIGH PRESSURE COOLANT INJECTION SYSTEM PUMP DELIVERY CHARACTERISTICS i 3000 m TYPICAL ONE CHARGING PUMP 2500 t i 2000 RCS

PRESSURE, PSIA 1500 1000 TYPICAL HPSI -

~ s PUMP 500 0 i 200 400 600 800 DELIVERY RATE, GPMIPUMP l 0 i T-60 F e t 6.! ... ;.c.;jjj. z. ;;:.;. g ...; _..rf.g..: F. d c. z.. s,. yp_.;p. E. ." g.'.-gl. :.~ i

,q g.,es.ow. 6 o* A O ,o IMP ACT OF HPSI PUMP DELIVERY CHARACTERISTICS 4 G-1 HPSI SHUT 0FF HEAD IS BELOW THE NORMAL REACTOR OPERATING PRESSURE WHICH ALLOWS HPSI TO BE LEFT INJECTING ~ AS LONG AS NECESSARY WITHOUT OPENING P.RESSURIZER RELIEF OR SAFETY VALVES 9 ,..e g O* l 1 ctzgyg.gQ. };..... .. f4 ,e:;pg.,jygi .a... ja.g >;.... ~ !:9... ..,...... ~,.

L' .s l' CONTROL SYSTEMS' DESIGN PHILOSOPHY MINIMIZE CHALLENGES TO THE REACTOR PROTECTION SYSTEM (RPS) DUE TO CONTR0L' O SYSTEMS' FAILURES AVOID INHIBITING RPS REACTION TO TRANSIENTS WHICH REQUIRE REACTOR PROTECTION (NOTE: PRESSURIZER, LEVEL IS USED ONLY IN CONTROL SYSTEM, NOT IN ANY S AFETY SYSTEM ACTUATION. ) t l e' i 1 i / 1*. (,*.c?;-} y

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( ( NATURAL CIRCULATION ~ DESIGN FEATURES FIELD TESTS - POWER AS:ENSION TEST PROGRAM FIELD EVENTS INVOLVING llATURAL CIRCULATION j 1 S h

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STEAu \\ ,I OU TL E T l 1** tNIT RuatioT N0ZZLE 's.

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s DEFLECTOR TCP (*. HEAD D !!5 STEAM [0RYERS .. GOD C,C_C,Q C,C O / jib i? \\ i 22STEAu i 1** L E V EL caYEa Da AlN$ YJ ,5NDICATION n g u; NQZ2LE agwgy 144 STEAM $4 A KC'OI M AN DMO L E gg ggq.o

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h SECONDARY D (2 REO*D) ~ t P RIM ART RET ggyLgy SRACCET NARY P pozztg (2 REC *D) ' (2 REQ *D) \\ FEE ER "{' ; L qs g"C E,EL I n~ T T / ;_cd i ig 8,*" l-y 1[ gg gyg g BRACCET sNDICAT;ON { NDZILES l l 1** L EV EL 1 INDICATlCN -{ ff g NOZ LE i D .lNSTRUMENT ,l l (4 REQ *D) NO:zLEs ',yjt b e. sis-s/**co t s Twsts e 1;g 743** f 1** L EV EL g 'i* (NDICAT!CN ld NO.ZZLES f ^ ~'- i i P R!m ART 8NLET 3 C~ ' ~ BO TT0a4 N0ZILE

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il MOZILE OURET _ g ;g g, g gj g yggw g g 333. 0.D. j g ;t, gl l h.- - SLOWDOWN & DR AIN NO2ZLE l l l 1 i f.'7,' 80TToa

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82 885**) lL .A @ EUE.N .4! I i l & DR A!N i N ZM V pg;yggy ,Kg7,g,gM7 C 4' MEAD -NoIILE I (4 REQ *D) PalMARY e MANWAY g (2 AEQ'D) i f{ f q'. D4YlDER PLATE NLET ,OgTLg; H02ZLE ND :LE \\. SUPPORT (2 REQ *D) ' w' '., s sgggy A A SECTION 8 8 'n STEAM GENERATOR t

( i 3 2-4 1 5 o I i H C REACTOR COOLANT SYSTEM TEMPERATURES 1 5 IH \\ \\ s 2 3 4 4-i T SAT C T T TUBE LENGTH PRIMARY TEMPERATURE SECONDARY TEMPERATURE y,i ry J6w w P

at. _1. ._._m O l g "l i STEAM DUMP STEAM DUMP t t s. p.o .me. 8 n. f 7 I u- \\ y, ,. s. ,s .( 25.2 FT o m T T M n l x +g g 13.7 FT ( p, \\ ~, L pl J 11.5'FT m, T T v C C \\ hL. vG g mul. 6 ---- g

'( i j FLOW C0ASTD0$ AND NATURAL CIRCULATION POWER ASCENSION TEST ~ INITIAL CONDITIONS: 40% POWER liSSSCONTROLSINAUTOMATICMODE r SEQUENCE OF EVENTS: TRIP RCPs MANUALLY RPS TRIPS REACTOR AllD TUPSINE OPERATOR SLOWLY RESTORES SG WATER i LEVELS USING AUXILIARY FEEDWATER OPERATOR TERMINATES AUXILIARY FEEDWATER AND SGs " STEAM DOWN" FOR 1-2 HOURS EVALUATI0il: CORE DECAY HEAT IS DERIVED FROM MEASURED SG WATER LEVEL CHANGES AND CORRESPONDING I:lVEllTORY j DEPLETI0il RCS FLOW IS DERIVED FROM MEASURED T, T AND DERIVED CORE DECAY HEAT H C i RESULTS: CORE DECAY HEAT 0.53% RCS FLOW 2.2% i ~ w

~ l ~ RCS LOOP TEMPERATURES 555< i i

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o"- 550 f o: 545 j E a LOOP 12 T 5 540 V k E o 2 a_ o a h535o-hh[~ LOOP 11 TH0T E g DOWN LOOP 128 TCOLD a 530 / a* [K 00P llB TCOLD 0 20 40 60 80 100 120 140 TIME, MINUTES i

.1 t i l NATUR AL CIRCULATION TEST A P RI L 1, 1975 EPT APPENDIX PPD n-40 i i i i 35 % AT POWER 5 3 30 l ~ 2 START 11A RCP- $ 25 j -SECURED 20 ED ~ --START ST AE M DOWN 15 $0 100 120 140 0 20 4O 6O 1 TIME, MINUTES l s. f

T r i i CHANGE IN THERM 0 COUPLE TEMPERATURE vs TIME AFTER FOUR PUMPi LOSS OF FLOW 10 HOT LEG TEMPERATURE 8 --- THERMOCOUPLE NUMBER 14 6

---

THERMOCOUPLE. NUMBER 26

--- THERMOCOUPLE NUMBER 35 W~ 4 2 p-m I O f ? ) ) i, V g hh -2 f j.7'.f' \\j ~~--- y / 2 H -4 f 'l f ,s' j 'j -6

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REACTOR TRIP NUMBER 26 RCS COOLANT TEMPERATURES 600 - FIELD DATA ~ 580 ANALYTICAL DATA 560 - O O O 540 o g* 520 - ) 4 O i u_ 500 - o i-or l y480 4 o i 5 i o-460 a t

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.T HOT b! a nz 440 a C O O f o o o o 420 t m o o T 400 COLD o ~ O 380 a. 360 O 340 o O 320 i O e 300 0 1 2 3 4 5 6 7 8 9 TIME, HOURS () )

REACTOR TRIP NUMBER 26 PRESSURIZER PRESSURE 2500 i 2400 < 2300

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l i m 2200 g{ o ~ 5 2100 O e 0 o-2000 o 5 d 1900 g vi O 0 1800 x a. ~ 1700 o 1600 "0 1500 0 1 2 3 4 5 6 TIME, HOURS

i PRESSURIZER C00LDOWN TO HOT LEG SATURATION TEMPERATURE 24 CURVE A: PRESSURIZER HEAT LOSS BASED ON PRE-OPERATIONAL TEST ACCEPTANCE 20 CRITERIA O, CURVE B: 50 PERCENT OF CURVE "A" PRESSURIZER HEAT LOSS 16 s D i S2 "B" 1 Y p 8 "A " 4 0 0 2 4 6 8 10 12 14 16 18 RCS LEAKAGE ANDl0R BLEED 0FF RAE GPM

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SUMMARY

'1. NATURAL CIRCULATIO!1 IS VERIFIED IN EVERY C-E PLANT. 2. IIATURAL CIRCULATION C00LDOWN CAPABILITY OF C-E PLA!!T HAS BEEN VERIFIED. 3. SEVERAL IllDICATIONS OF ADEQUATE NATURAL CIRCULATION ARE AVAILABLE lil THE PLAtlT. A. SUBC00 LING INDICATED BY PRESSURIZER PRESSURE 1 AND I CONDITIONS. g B. IH (AND dI POWER) " TURNS-0VER" WITHIN 5-10 MINUTES OF SECURING RCPS. C. CORE EXIT THERMOCOUPLES TRACK T. g D. T-T INDICATION LESS THAN FULL POWER VALUE H g ALSO Al POWER INDICATION IS LESS THAN 100%. E. T CONTROLLABLE BY SECONDARY HEAT SINK. C ,m W 9 A

t (_ / \\ r 1600.') i i i 7 1 1400.0 1200.0 O l s 1000.0 -30 y JY.c w a. h s 800.0 O PUMP DISCHARGE LEG ~ O TOP OF PRESSURIZER 600.0 O REANALYSIS WITH 100% ANS 400.0 ~ ~~ 0 0.1 0.2 0.3 0'. 4 0.5 2 BREAK AREA', FT r 4 8 d[?ds, // /, "S"'" I 'l ' MAXIMUM HOT SPOT CLAD TEMPERATURE 6 3 3 3- '\\ h4 vsBREAKSfZE 7 x i ~l.C..

,8 i i \\'. r-s) t +- j j SYSTEM 80 2400 i i i V 2000 j H ~ d t e 1600 I w a. ) E -\\ m w m g: 1200 0'.02 FT2 W ~ ~ .td 0.05 FT2 w m .w S3 800 z z 't e.- 400 0'l2FT2 0l5FT2 I I I 0 O 600 , 1200 1800 2400 3000 l TIME, SEC l '~

g I,- _( 9 SYSTEM 80 10PSV - ENERGY MLANCE, RCS 03 FT2 HL 10 10 = = 1 CORE \\ =3 r / co 109 STEAM" GENERATOR _f g w

== 7 ~ / [ 108 l w W 5 E 5 Z EXITING SYSTEM 2 [.' --- ENTERING SYSTEM ~ ~ e 7 l f 30 O 1200 2400 3600 4800 6000 TIME, SEC I y O y I a t i E l \\

't SYSTEM 80 2 '~ 0.02 FT DISCHARGE LEG BREAK LOOP 2 1 LOOP 1 j ( \\ SG SG PRZ o' BREAK OCCURS AT~. = --~ .~ n 2250 PSIA \\ Q // \\O FULL POWER CONDITIONS. ^ 653 F RCP i NORMAL \\ pl.EVEL RV N-4 p i } ( Q %) ) h ? djl_ ( gA l ' 'JAh 622 r-s j O C ^' ' l .O O LS i RCP CORE RCP U 565 F i T=0 1 SUBC00 LED FORCED CONVECTION ~

g-r n, SYSTEM 80 2 0.02 FT DISCHARGE LEG BREAK 1 LOOP 2 l LOOP 1 i i ( \\ ( SG SG 'l PRZ p

• RV UPPER PLENUM

~ 1900 PSIA SATyRATES kQ//. RCP O' ^ 628 r l -li-f DECREASIb ~ s- ~~ l r. 4 i. %.) 4 i. m \\ ) %I 628 *r - ( l* , CL i HL l. 9 LEAK C o ( ~. LS j RCP CORE RCP . i, o ses F .+ T = 100 SECS ~ FORCED C0fWECTION - ~:

SYSTBi 80 2 '~ 0.02 FT DISCHARGE LEG BREAK ~ LOOP 2 ~ i LOOP 1 ~ l f l SG SG PRZ p e PRZ EMPTY 1350 PSIA-SIAS., TRIP H PPENED RCP O \\ e U 583 F ,.e RCP OFF/C0ASTDOWN-SG TUBES START TO DRAIN, p l e SG SECONDARY ISOLATED J 1 583 F t j q' l kd i "J EAK C -O v / LS .i p [ RCP CORE RCP ~ 582 F I T = 500 SECS l e TRANSITI0li FR0il FORCED CONVECTION TO POOL BOILING ~ 8

SYSTD1 80 ~ ~ 2 0.02 FT DISCHARGE LEG BREAK LOOP 2 u LOOP 1 SAFETY ( SG PRZ e SG SECONDARY RELIEF O 1350. PSIA VALVES OPENED 582 F A SG. TUBES DRAINING-pp e g

• STEAM BUBBLES UP R

\\_ j ~ ^ FROM RV TO SG'S

• RCP C0ASTDOWN TO 582 F

<5% SPEED d t 1 V ~ q nd [ PAW ; Q c'e %^ 6 i c 9 LEAK L LS RCP CORE Ce I 581 F 4 ~ T = 600 SECS 4 TRANSITI0ll FR0il FORCED C0iWECTI0il TO P0OL BOILING

t I SYSTB4 80 \\ 2 0,02 FT DISCHARGE LEG BREAK [ LOOP 2-LOOP 1 1 p SAFETY Q t { SG SG PRZ e SG TUBES EMPTY O 1350 PSIA CORE FLOW hLM0ST.ZERO ' 589 F O. i p N" av U 0 589 F sp } b2 q nd \\ >' b 7AF s i k c( 4"I ~ V 9 LEAK C I LS CORE RCP RCP k j ~ 505 F T = 1200 SECS ,l I q POOLBdILhlGCORE,CONDEllSATION'INSG'S j

~ s' ~ ~. : SYSTEM 80. 2 0.02 FT DISCHARGE LEG BREAK .1.. LOOP 2 LOOP 1 SAFETY { SG ~. SG PRZ ll p n=w

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• HOT LEGS EMPTY 1350 PSIA

'e COLD LEGS EMPTY. 580 "F \\9 RCP G . e-LOOP SEALS EMPTY m e 580 F 1 v ) ) ) t* 1 2 r. ~_ .s 7Ah i hA[ - ~ sm 1. i-9 LEAK C '~ LS 1 u-CORE p o 515 F T = 1800 SECS '.-

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s e r .I - c / P0OL B0ILIiiG CORE,-CONDENSATION IN SG'S e

i ~ SYSTEM 80. ~ 2 ~ ' 0,02 FT DIScilARGE LEG BREAK \\ LOOP 2.- j' LOOP 1 l ATM DUMP. i i 1 SG SG PRZ b 1350. PSIA o START PROCEDURE TO ~ ^ ^ - = ESTABLISH 1.0NG TERM 578 F ~ o g ]n q O COOLING - l \\ _c R u i 0 i-578 F 3o s t a ) l ( -i C-ay flL CL h,. 9 LEAK C '~ LS 1 HPSI CORE 562 F \\ ./. T = l il00R L ~ SG C00LDOWll liIITIATED-

i SYSTEM 80. 2 .02 FT DISCHARGE LEG BREAK ~ 0 i LOOP 1 LOOP 2 ATM DUMP, b SG SG I

• HPSI > LEAKFl.0W 4 e

_~ 1 20 PSIA

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e INITIATE HOT SIDE / COLD. SIDE HPSIP INJECTION ' \\ 506 F RCP \\- i R ~ ~ i D C i } N-3k ha d 9 L K C 2 n i 2 1/2 HPSI-LS j v (99g T = 2 HOURS IllITIATE HOT / COLD SIDE INJECTION ~

u (* ' (y i ? ~. 1 STEAM GEllERATOR 70 - O N O PRESSURIZER 1 / 3*/ol S 60 - u J C 0 e J 13 50 - I f .N [ 0 c i .g c _ z O q ~ 8 49 - i D k# /' g RCS (d 5 tg # F PUMP

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-t )P\\ ( HOT LEG f E 30 - y 3 l l Y i. o D o -l '- - - - - .o_ LEAK- . '20 - COLD LEG // 3 e c' q y / o ACTIVE .x 10 --hATERLEVELRISESINH0 LEG kS A STTkF ED UWER. C0f!DENSATE DRAIM-BACK PLUS ECC INJECTED INTO HOT LEG FLOW INTO TOP 0F CORc $.w. ~~ ~ -m o m e- "*w

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( "i n. T.. STEAM GENERATOR ~ . - y-: ' 70 -- O N PRESSURIZER .\\(7)'l, T ~*'w.- ~60 - ~ g .., 3 <,, g,,', - O

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tD 50 - ~ \\ g D 0 l I e o E LIO ( ~ e o P RCS h j j f PUMP w 1. $ 30 - g h HOT LEG Il I y u, g k (~) LEAK 20 COLD LEG // f

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~ k J [ eACTIVE DURING THE TIME OF CORE BOILING THE STEAM LEAVIflGO' CORE THE UPPER PLENUM WILL FLOW THROUGH THE HOT LEGS AS [.i 10 A STRATIFIED FLOW. IF THE PATH IS MOMEllTARILY BLOCKED BY WATER BRIDGING THE PIPE, THE CORE PRESSURE WILL liiCREASE (5-6 PSI /SEC). THE PRESSURE INCREASE WILL SUPPRESS THE BOILIllG AS WELL AS 0 RE-0PEil THE STEAM PATH. SINCE THE MASS OF FLUID BRIDGING THE PIPE IS INSIGNIFICANT COMPARED TO THE MASS OF FLUID FILLING THE REACTOR VESSEL AND COLD LEGS, THE LEVEL OF WATER IN THE CORE WILL ll0T CHANGE SIGNIFICANTLY DURING THESE PRESSURE FLUCTUATIONS. -me.====-..e

.n. ~. i " :.' '(J .. ' ' '.i 'Y v ( ' ~, .n . J, ; ~; - .p. . ;:. _.:.. y, ;. _..... : n.. . y :. STEAM ' " !. ~ l ;$:I. ~ ~' '~ GENERATOR ,'"?.b 7 " ~ 70 - ._ j; n ..z.. ~ o-O PRESSURIZER i o (&, c ' ......,..:p.:. g -;i.. ' : 60 _ w-. ~ y c o . l. :; ' ;.: l o .. :.. :.7:.[: :.; c - h3 50 - .... :..... :) - i-s W LL. b o 3 i z o o S 40 - W u 0 Q) a RCS g; e y PUMP t;-j w LE 30 - r-h ( HOT LEG Il _ p. a ( w m ~ ~ o- ) LEAK y 20 - COLD LEG [/ a 'r ,r .o.. ~ x ACTIVE CORE WHEN THE WATER LEVEL.0N THE INLET SIDE OF THE / STEAM GENERATOR REACHES THE TOP 0F THE LOWER /A ~~ U-TUBES THE WATER WILL DRAlil INTO THE COLD SIDE d 0F THE STEAM GENERATOR. IN ORDER TO MAINTAIN ~ 0 _ THE HYDROSTATIC PRESSURE' BALANCE THE WATER IN THE COLD LEG WILL FLOW TOWARD THE ANNULUS WITH INCREASING FLOW RATE. THIS IS THE BEGIllNI!1G OF NATURAL CIRCULATION. y '7'

~. q, 1 100,000 ~ ~. hB EDjgRjg 10,000 I A Ib c. ~ W 80 INTERMITTENT G .0PERATING POINT AT 2h hrs. FLOW REGIMES ~ ~ Y Ap (SLUG & PLUG y FLOWS) ~ 1,000 SEGREGATED E 5 5 FLOW REGIMES (STRATIFIED & WAVY FLOW)

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' ' ' ' ' ", 0 0 0 100 10 O.1 1.0 10 100 1000 ~ ..W.. g Y12 p /e /['" A Y g swMg/4-FLO'W REGIME MAP. OPERATING POINT IN HOT LEG , y p) DURING REFILL PHASE OF A SMALL' BREAK LOCA. gg fpg/ j

p J SYSTEM 80 2 O.02 FT DISCHARGE LEG BREAK LOOP 1 LOOP 2 1 i ATM DUMP' ( h Q ~ SG SG PRZ n J 180 PSIA 373 F O p .\\ - R .? i 1 G ~ =- t--. KA ( ) 1 )h HL , CL 9 LK V O tg CORE T = li 0 HOURS .~

1 J

RCS REFILLING

l. SYSTEM 80 2 -0.02 FT DISCHARGE LEG BREAK LOOP 1 LOOP 2 g @ ATM DUMP' SG PRZ O o SUBC00' LED ~ 280 PSIA SOLIDSYbTEM o I' 350 F p Q .o tiPSI.= LEAKFLOW' p a. ~ '\\9 r i S d START NATURAL CIRCULA. TION ~ 1 V %l ( ) 1 ~~) Ah C3-( dA ,j HL , CL 6> l O 9 LK C LS CORE T = II.3 HOURS 1 1.' RCS REFILLED

SYSTEM 80 2 - 0.02 FT DISCHARGE LEG BREAK 7 LOOP 2 LOOP 1 i ,e.... ~ ATM DUMP' j, p Q l SG Sro PRZ N A o RCS IN NATURAL 280 PSIA CIRCULATION 350 F A n o . PREPARE TO STARTUP p RCP m ' '... o \\ Ii-SOCS u l,-

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i i i s. v -qj A& QU C A .HL . CL I 9 .'.J h; . (-) LS u cogg u e SDHX LPSIP E i 4 'T = 8 HOURS O 9" i CCW INITIATE.SiiUTDOWN COOLING.SYSTEl1S. t

( o u I TYPICAL COMPLETErLOSS OF FEEDWATER SEQUENCE FOR A C-E OPERATING PLANT TYPICAL STUCK PRESSURIZER RELIEF VALVE SEQUENCE FOR A C-E OPERATING PLANT IF i i-f'l

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I C O TYPICAL COMPLETE LOSS OF FEEDWATER SE00ENCE FOR A C-E OPERATING PLANT TIME (SEC) EVENT TERM,fHATION OF MAIN FEEDWATER FLOW RESULTING IN 0 DECREASING STEAM GENERATOR WATER LEVEL 20 PRE-TRIP ALARM ON L0ll STEAM GENERATOR WATER LEVEL 25 REACTOR TRIP ON L0ll STEAM GENERATOR WATER LEVEL 30 PEAK PRESSURIZER PRESSURE < PORV SETPOINT (2400 PSIA) (PORV DOES NOT OPEN) 30+ STEAM DUMP, BYPASS, AND PRESSURIZER CONTROL SYSTEMS REGULATE TO HOT STANDBY CONDITIONS 120 MINIMUM PRESSURIZER PRESSURE ~1800 PSIA (N0 SIAS) 780 - 900 FROM THE CONTROL ROOM THE OPERATOR MANUALLY STARTS AUXILIARY FEEDWATER PUMPS AND OPENS VALVES TO THE STEAM GENERATORS BEFORE RCS PRESSURE RISES TO PORV SETPOINT (2400 PSIA) l

C O TYPIC AL COMPLETE LOS S OF FEEDW ATER FOR A C-E OPER ATING PLANT PRESSURIZER PRESSURE vs TIME 6 1 1 I 2400 r 1 2300 5 E N 2200 5 W E 2100 g r-8 O E 2000 1900 1800 l 1 1 I 0 5 10 15 20 25 TIME, MINUTES

C C TYPIC AL COMPLETE LOSS OF FEEDW ATER FOR A C-E OPERATING PLANT PRES SURIZER LEVEL vs TIME 100 i i i i 80 d 60' B a !E 5 12g 40 c. 20 0 i i i i .0 5 10 15 20 25 TIME, MINUTES y w-ee * -

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([ (' ) ~ TYPICAL STUCK PRESSURIZER RELIEF VALVE SEQUENCE FOR A C-E OPERATIt1G PLAllT TIME (SEC) EVEtlT ~ PORV OPENS RESULTING IN RAPID DEPRESSURIZATION 0 0F'RCS 0+ OPERATOR RECEIVES INDICATION AND ALARMS FROM RTD IN PORV PIPING, AS WELL AS, QUENCH TANK TEMPERATURE, PRESSURE, AND LEVEL 0+ PRESSURIZER CONTROL SYSTEMS AND CVCS RESPOND TO DEPRESSURIZATION 5 TM/LP PRE-TRIP ALARM 7 TM/LP TRIP DN LOW THERMAL MARGIN 22 SIAS AT APPROXIMATELY 1600 PSIA AUTOMATICALLY STARTS HPSI PUMPS 30 QUENCH TANK RELIEF VALVE OPENS RELEASING STEAM TO CONTAINMENT 30+ OPERATOR RECEIVES ALARMS AND INDICATION OF INCREASING CONTAINMENT PRESSURE, TEMPERATURE, AND POSSIBLY ACTIVITY 50 Fluid EXPANSION AND SUBSEQUENT FLASHING IN RCS RESULT IN INCREASING PRESSURIZER LEVEL 240 HOT LEG RTDs INDICATE RCS IS APPROACHING SATURATION CollDITI0 tis

C C) ~ TYPICAL STUCK PRESSURIZER RELIEF VALVE SEQUENCE FOR A C-E OPERATING PLANT (CONTINUED) TIME (SEC) EVENT 260 FliLINGOFPRESSURIZERRESULTINGINTWO-PHASE RELIEF THROUGil PORV 300 OPENING QUENCH TANK RUPTURE DISK RESULTING IN FLUID RELEASE TO THE CONTAINMENT 300+ STEAM DUMP AND BYPASS REGULATE RCS TO HOT STANDBY TEMPERATURE 300+ RCS PRESSURE STABILIZES AT +1100 PSIA WITH HPSI FLOW MATCHING PORV FLOW [ 600 - 900 AUXILIARY FEEDWATER MANUALLY INITIATED TO STEAM l GENERATORS, IF MAIN FEEDWATER WAS LOST 900 - 1800 OPERATOR CLOSES PRESSURIZER BLOCK VALVE TERMINATING UNCONTROLLED RCS FLUID RELEASE 1800+ RCS PRESSURE STABILIZES AT HPSI SHUT 0FF HEAD 5400 PRESSURIZER HEATERS RE-ESTABLISH BUBBLE IN (1.5 HRS) PRESSURIZER

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=+6 PRESSURIZER PRESSURE, PSIA o w w to N m o 8 8 8 a o t-I m -1 C O X T M m g AT1 "O g M c ~o i V w ^N \\ Cm M M e-e l W Nm. 5 m m m ~ Z r-i O H S a m r1 Z g C m< -4 m> J m m g f x <m m ~ m ~ u < o x > 5 O m .I m O ro O o m M> -4 H Z f I c-) T r-> Z --4 O )

- t TYPIC AL STUCK PRESSURIZER RELIEF VALVE FOR A C-E OPER ATING PLANT: PRESSURIZER LEVEL vs TIME 100 i 80 n e d i 60 5ds w if) 40 !E 20 ~ f 0 i i i i 0 5 10 15 20 TIME, MINUTES -m-m - =

.~ PORV OPERATION 4 2 DEMAND VALVE OPENINGS n, 0 FAILURE TO CLOSE 2 INADVERTENT ACTUATION 1 FAILURE TO CLOSE 4 e 4 w

~ : P.0RV ACTUATION DEMAND VALVE OPENINGS FAIL TO OPEN CLOSE HIGH PRESSURE TRIP DURING SPURIOUS ~ r~'- TURBINE RUNBACK AT POWER 1 0 HIGH PRESSURE TRIP DURING LOSS OF ~ LOAD - POWER ASCENSION TEST - 1 0 INADVERTENT ACTUATION RPS MAINTENANCE - SPURIOUS OPEN SIGNAL - ' ~ ' PRE POWER TESTING AT HOT SHUTDOWN - 1 1 ~ ~ PORV MAINTENANCE - SPURIOUS OPEN SIGNAL - COLD SHUTDOWN - 1 0 08

p. i k .i ECCS OPERATION n DEMAND ECCS OPERATION 6 ~ FAILURE TO OPERATE 0 INADVERTENT ACTUATION 3 0' FAILURE TO OPERATE ,m 'O

ECCS OPERATION FAIL TO DEMAND OPERATE DEMAND ECCS OPERATION PORV OPENING 1 0 POST-TRIP EXCESS FW ,3 0 FW BYPASS VALVES STUCK OPEN 1 0 UNBLOCKED SIGNAL DURING C00LDOWN 1 0 INADVERTENT ECCS ACTUATION RPS/ESFAS TESTING 3 0 9

AUXILIARY FEEDWATER OPERATION TIMES FAILED TO USED OPERATE AS EMERGENCY FEEDWATER LOSS OF FEEDWATER 2 0 LOSS OF 0FFSITE POWER 9 0 LOSS OF CONDENSER VACUUM 7 0 4 r e 5 g 9 9'

COMBUSTION ENGINEERING PROCESSING 0F OPERATING INFORMATION OTHER LERs SOURCES 1r AVAILABILITY CORRECTIVE DATA ACTI0ilS PROGRAM PROGRAM (ADP) (CAP) ir y CUSTOMERS C-E MANAGEMENT 1 M

EXAMPLE OF LER PROCESSING CALIBRATION ERROR IN INJECTION TANK LEVEL TRANSMITTER EVENT DATE FUTilRE 1-10-78 DESIGNS A s t CUSTOMER LER OPERATING C-E ENGli1EFRING COMMUNICATION 1-24-78 PLANTS RESOLUTION 11 f1-78 A o CAP ACTION TELECOM TO INITIATED ADP CAP OPERATING PLANTS 1-24-78 JANUARY 1978 v v ADP REPORT TO CAP REPORT TO CUSTOMERS WITH C-E MANAGEMENT RECOMMENDATION APRIL 1978 APRIL 1978 e

EXAMPLE OF INFORMATION EXCHANGE NOBLE GAS DOSE ACCOUNTABILITY DURING REFUELING COMPLIANCE illTH 10 CFR 20 CUSTOMER PROBLEM RESOLVED IDENTIFIES WITH NRC 18E BRANCH PROBLEM 10-27-78 7 C-E NOTIFIED OF PROBLEM AND RESOLUTION 11-28-78 u ADP t ADP REPORT TO CUSTOMERS JANilARY 1979 w-- m}}