ML19221A559

Analysis of Natural Circulation at TMI-2 Following Main Reactor Coolant Pump Trip

ML19221A559
Person / Time
Site:	Crane
Issue date:	03/28/1979
From:	Office of Nuclear Reactor Regulation
To:
References
OLS-790328, NUDOCS 7905230191
Download: ML19221A559 (45)

Text

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"5" ste pne r..tc r is isolated cnd its level is 95~ of operating 164 216 t

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_ Transient RC punp 2A is tripped and flow transitien to natural circulation is t

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examin e d.

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f CASE 2 This cas is identical to Case 1 with the exception that both the "A" f

and "B" s ca: generators are active and solid with 100cF, 3000 GP" iecdvater flaving f rc the tain feedvater header through the s: car.line.

i This is the initial conditica when RC pump 2A is tripped.

C AS E 3 Initihl Steady State EC purp 2A cperating.

0 Fritar; systa= tc peratura at 200 F, "A" stec= generator solid, 100 F, 3000 CP."

F,'.

"B" stea= generr tor idcntical to "A" but isolated.

6 Transicnt

[.

I RC purp 2A tri;;c.d and natural circulatien established.

':ev !ritial St a nd:. S t ate i,

e'

atural circulation flew at atcve cenditiens.

___cv T r a r s i.:

_t_

Tcn rineten af ter m.cv c teady st:te is est;blished, "L" ste_= p_narctor f

I is vt 1 red into crcrati:n.

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164 217

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. t..t c.'.S L 4

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Initial Steadv State _

{

RC pu p 1A operating 1

Primary tc perature at 250 F.

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"A" sten generator steaming at 95% operating range level.

g "3" stes: generctor solid with OSC F feeCuster at 1275 GE:'.

Transient

.6 I

" /s ' stece ;cnerctor valved out.

"2" stes: generator f eedvater ra: ped to 3003 GP:' in 5 minutes 0

.-ith 230 F vater.

F.C purp 2A tripped of f and transitien te n:tur:1 circulaticn i

,s 4

ex: ited.

CAS: 5 Initial Stead.- Etste RC pump 1A operating Pricary tcaperature at 200 F.

"A" sten: generater stecting at 95% cptrating r:rge Icvel.

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"3" stes: generator isolated at 95% operating range ?evel.

g Pc scr level = 7 852 'G't decay beat Transient i

T.0 pump la is tripped 2n-1 trt.citica to c.atural circulaticn is c..;;;ned.

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Identical to Case 1 cxecpt that t he "i' s e c a: ;cncrator feedwater fiev rate ir, 1003 GP'! instead of 3000 GP".

l t

L,,2 :.-

t Identical to Case 1 except that the initial core bypass fiev f

I fractier was increased frc 5.4% to 257..

i s.

I The c; tails of thc.ie cnalyses with respect to the ecdel used cnd the key i

l i:. p u t censidera:.icns vill be discussed in the foilsvir.g secticns.

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c,.

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3.

"J.A'.TS IS "ET.40DCI.OJY i <.- 2 ?' '.

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g p,

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The analysis was perforted with the FITFjd: syste= snclysis cede deve'cred by ll En2rgy In:crporated under ccatract to EPRI.

The : del used ves previously

(

4 develarec specifically for ~'!1 and thus includes all plcnt gecretric detcil.

I f

The develcptent required appre <icately. nine ran-:.nti t This codel accou.ts i

for cass, energy and r:tentu: cc.sercation ced is thus well suited for i

I a:tural circulction calculaticns of this type cnd han been successfully used I

I for t'is pur;cse PIcviously.

7 e ':.:ic

.cd:li:3tien sc..ene for each of th2 c

.;-^c is 25-v: in the attached e

j T:; re 1.

A s c e_, be fecn, this is a hf;hly Cctafled 7 dal::c. tion s-bc.2 and t' e p.'

-t is reprc :nted in its entiret/ vith t'c Icy s, inc!m!!rg the fcur ?.C i

i

-.:ps c.d cel! Icas, the t*. o h a t 'eds cr'1 tb2 a cc ;;uri.-< r.

T1.c

1tipic Eat f

leg - ading c: veil s the seven rede ccre retica ware.. deled 21:b t',e purpcre 164 219

E ar.e 5

/s of sinalating the actual TMI-2 accident;.chavior and were raintained in this analysis for ext:di acy.

Such an intensive nedalization arrangcrent is not required for this c.alysis.

Tae reactor vessel codel includes a cultinede

,s a;ici care, a ccre bypass region, and upper plcnun, outlec plenu: and upper i.ead regions.

De recctor vessel do.mcocer and 10.er plenu: are also Tc p re:ie n t C 0.

Tae four rc;ctar cociar.: cu ps are simulated with the built-in Einch:2 -'unp l

"c.ie l in E' F ' '..

Tnese pu. p characteristics have not becn cc psred against the actual.:~-2 Cin;;hr: Furp four cuadrcnt curves.

,7 a

t 3

-" e e tc

ncrcte r is 20 deled with twelve er.ual pri

ary to seccndary heat I

s f

F tr ncicr nedet.

Inis modal ccnfiguration has been danenstrated in previcus a

verificctic s cgainst cetual plant data to be quite adequate in the representa-(

a tica of the cetur.1 prinary/seccndary transicnt heat transfer prccccsec.

l t

h For the purpescs of the natural circulation analyses in which the CT3C is f

4 I

s eca--ing and isolated, the cecondary side of the OT50 has been reduced to a p

.I-

r.. m - -..

.. - --.... ing. _ lu e;-have also been ei :cin a t e+ since.

n

-e--

'f single node.

~52 fcec.ater pip vc f.c : r:..iry side is not erhibitic;;3r.y signifit r-tr::sien - sehavior,,

.t e

f E-

.Y Tcr there cc:2s.here the OTSC is solid, the lover de.nce:er volu e hcs j

1cca ratiined.

' his sin?lified seccedary side r:presentatica is quite

{

c.d:qu te for there 2nnlyr:s ;ince the se:Ondary side feedrater ir,ut condi-

,s.

. _.-m

' tirns at:. fix d..cith respett to bcth fiev and tct;crcture th:ru;heut the l

7 4 x,.

.n-ira --:ljsis intereal.

Eccendary side ncdal adju trento verc ende cnly "f

to r2 duce tFe run tir.c fer a particular case.

164 220 9

?

.g Pre 6 u

t e-t

• 9

.g II The natural circulation analyses were all acco:plished by initializing the l$

lcr rudel at the conditions indicated for em ;h cf the.atural circulation scenario

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cases and then tripping the pt. p c; sinulating any otner transient initiator l{

frcm this steady state.

he cnalysis is ccepleted when the syste= is re-li ti I

established in a ntecdy state node once cgain under natural circulation i

conditiens if they indecd are predicted to occur.

~~he key syste parameters

(

,a can then be determined.

l I

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(

4.

/SALYSIS DISCUSSIC:;

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(

The initial steady stcte plant confi;;uration for which the n:tural circula-g i

tien cciculations were peric =ed c nsisted cf one reactor coolant pump in j

cperation vitt reverse flow in *ke idle locps.

l L

The normal sys :c: fo:. card for loss ccef ficients were deternined by using the FI!pJJ =cdel in the no =al, full pdwar, full ficv steady state plant 4

operating =cde and obtainin; the re it. ired foro less coef ficients for the s

syste frc: this kne.n ecse.

The for loss coef ficients for the syste= will act change for a given gecret:.y.

h 2 rcvt rte fc = 10:3 Ocef ficicnts for the idle loops. tere detemined by i

I p a-f c raf.; c dditierel TI- ';. p reli._ir.r ry an:lyc es f or one pu p cpcratica e

f with the apprcpriate ficw rrlits cpecified in the :-i "c : tar Cool..r.t Syste:

Specifications (7icu e 0-13) for ore pu -p Oper ti:n.

Sc

'c r ard cnd revc ree.ec.,1._;s c:2Cffcients,are then input to r E!F13 with the crsu cd plent flew dsta for che enis ting ?lant operat ng configura-e tien.

It ses obvious thit tb4r2 was ad!*.ticral core rc;ictarce b.:cause the 164 221

..e

~s

.3 t

e.

a

.b.

puviously cstablished loss coefficients were shhtantially laa,er for this I

t.ca flow ccnditicn. Core flow losses were incrc2 sed until cther systen lesses

[

P conforccd to their nattal values.

This shewed cxcessi e core fIcw resistance.

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t t

, Af ter a ccering with En' at 1.ynchburg, care excet flow and core pressure drop (t.

+

1

egt.irerents were cbtained for the plant in its present configuratica.

The I

J care resistance uns adjusted to provide a pressure dr:p of 17.96 psi f rca 1

,1 the vcscel downcorer thrcugh the cere to the upper plenu: and the apprcpriate q

Icop ficvs were used.

Cases I thrcugh 7, excluding Ccse 5, were run en this 5

Y hcsis.

Ccsc 5 was ran with the systen ficw and ccre pressurc dr:p data which j

i cs dcternin:d prior to the recting with EE*.i.

s i

initici ccnditiens provided by B&h' cre shewn in the cttcched Figure 2 l

~~ae t.nd cccc:paaying data in Table 1.

The initial conciti:ns uscd in the FITFAN 1

analyces are provided in Table 3 for each case cnclycec.

4

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1l 3.

r. _- 2 L.,. S--

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5.1 CENE?>l. DISCUSSION i

i The results of the calculctiens for six of the seven c2ses cre su criced in 1

~'in table provides the eclues cf the 1 pertant systc tc:perctures N

Table 2.

and

cc flav r-tes at a tire 2600 reconds ir'.o the trcnsitica ta r tural

,. -11 L. sufficient to apprea:h ciNulction, e:c ce p t for Ccre 5.

Tais ti:2..;.'.".

t ^ n,. stcte temperatures cnd f ~cvs in tb. Eatural circul.,tica : ode.

The i

f, het i n tcrperctures are these in the firr,t hot leg ned s in ihc "A" and "Ts" le.ps.

The terperature differenc2 across the core cra ae deter.ined fre i

the t'

ercture at. the tcp of the core and the icwcr plemun terpernure.

164 222 i

Page 8

t. discussien of the nature of each of the cases is discussed in Section 2.

,11 cases were run with a decay heat of 5 L't, e.xcer

Case 5 which used 7.S621"'.

l l

The sus of the two hot leg flow rates is equal to the tot'l flav thrcugh the l

core and the core bypass.

In this canner, the bypass flow can be deternined.

D: cept for Cases 4 and 7, the bypcss fleu was initially assured to be 5. 4'l:.

Ccscs 4 and 7 assurad a 25% bypass flev.

Fin'e the pre cnt : ore pc ct:f.

is.c : kncus, the core bypass flaw is also not dc:a min 2ble. It. i s 'ael,ieved i

na: 25" is conservation.~

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The results f or each ccse are illustrc:cd in the attached Figures 3 through

'.s cca be seen by a revicv of the figures fcr ach case,.2tural circulati.n flow is shcun to be estchlished in..the ccre after the purp is tripped.

The cc e fice reaches a. ir.icu= value when the 7t=p cocs:s devn af ter cbcut 30 ceconds cnd th2n increcses cs nctural circula:{an begins.

The flev escillates initially but settics doen to its steady s:cte vclue sf:er chout C000 seconds.

This behavior is c?sracteristic of all cases cs ccn be seen by a revicv of

,i -

)

^[ the core flev as e functica of ti=2.

The tc perature transier in the core i

1 1

and upper plenun !aring the transi:icn to n: m l circulction chcus 2n v

,a l

initial rc?id increase, then pecking and decr<

g wi f, n-..: cr two subsc-euen: ascillcticna cf =uch s aller 22 nitude than th2 initial peck until a rc.'ctivcly stable regien tc:perature is reac.hed.

This e?. ticr is 'gtin 6

es: ntf all;- ch:rcctcrf stic of all ::r:s n.aly : d :s ccn ;c r ac n by a reviev cf the upper 7.nue, het leg and top cf core

_ p reter tre.sient during 1

the t: r31 icn to 6 2 :-n.tural ci rcui n:ic a t;de.

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