ML19322D164

Evaluation of Transient Behavior & Small RCS Breaks in 177 Fuel Assembly Plant,Vol II Apps

ML19322D164
Person / Time
Site:	Crane
Issue date:	05/07/1979
From:	BABCOCK & WILCOX CO.
To:
References
TASK-TF, TASK-TMR NUDOCS 8002100001
Download: ML19322D164 (59)

Text

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Dr. F.un ::aturc; Cir:ulstier Tes:

Af:er :ne fuel assen': lier were 1:aded bu: prier :: ini:ial criticcli:y a:

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3:enee *Jni: 1, EEW and Duke Powcr 00 pany condu::ed a simulated natural cir:u-la:icn :es: en May 1, 1973.

With the cere in place but wi:h ne power his: cry to produce decay hea:, :wo tests were condue:ed and were successful in developing-sufff:1en: na: ural circula:1en flow rate.

1c3 firs: :es: induced na: ural circulation flow in both reacter ecolant syste: loops by rapidly levering the stear generator stear pressure to lower l

he :e:pera:ure ef the rea::cr coelan: ex:ernal to :he reae:cr vessel. A decrease in s:ca pressure fre: !!3 psig te 730 psig in approx 1:a:ely :wo minutes was a::ceplished wi:h :he :urbine bypass valves. This caused a 13 to 20F decrease ir reld les temperatures, which =ain ained a natural circulation flow rate fer 10 minu:es or 20re.

A large chance in the indicated water levels of bcth stea t

cenera:crs occurred in the same two-minute depressurization time.

The final level was 310 inches above the lower tubesheet, whereas the initial level was i

373 inches.

The reason fer rapidly creating a 207 decrease in the cold leg i

tempera:ure was te use the transport time between the ccid leg temperature probe l

and the h:: leg temperature probe to calculate the natural c'irculation flow rate.

I y:I :he se:end tes: initif. operating conditiens were reestablishe'd several neurs la:er, and after securip :he las: twe RC pu=ps, :he OTSG water levels were rapidly increased to coel down the cold leg tecperatures discharging froc both steam generators. Main feedwater flow was used to increase the initial wa:er level cf 310 inches to approximately 390 inches in seven minutes.

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presen:ed in Figures 1 through f.

Figure 1 is a sche =atic' of the S&W 177-fue".

asserbiv. lowered-loor. alant.

The lecation of the instrumentation used to =easure r

the behavior of :he reactor ecclan: syste durinc natural circulation is shown in Figure 1.

Figure : displays-loep B het leg and. cold leg RC temperatures during the firs: tes: described above.

RC pressure and pressuricer leve* are sh:wn in he lower graph.

RC pressure varied t 60 psi abeu: the ner:a'. operating vs.ue c:.

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ps,g.

Figure 2 shows the loop A 'no: les and cold le; tempera:ures.

The lower fi:ure disrlays a comparison of *he'h'~ hest he: 'eg temperature and the RC sys:e sa:ura:icn :e:pera:ure. Approxima:el; 1107 subcooling existed in the RC sys:e during this simulated test.

Ficure i dis lays the rapid change in stear generator pressure and steam generater wa:er levels as the tureine bypass valves were used te cool the celd leg te=pera:ures 15 to 20F.

Figure 5 shows a co:parisen of a cel' leg temperature s'i:h the saturation

e:pera:ure within the stear genere:cr. These data show : hat the :ine' delay for

+

l Ocid leg :e:peratur.* te be al:ered by changing steam pressure is approximately two minutes.

Test data fro: the second test, natural circulation by raising water level, are presented in Figures 6 through C.

Figure 6 shows ho: leg and ccid les

enpa stures in loop A.

The lower graph displays RC pressure and pressurizer lev wi:'r changes nearly ec.ua'. :t the firs: tes:.

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Figure 7 displays le:p I hr: and :c'd le; :e:peratures.

The lever praph sr.:ws. cs bef:re. :he arrun: ef subco:~ in; is grea er than 110F fer the se:end

ss: in: :ing a na urcl circula: ion f1:w ra:c.

Figure S shows the change in

P s:ean genera::: pressures and water level indications.

2 Figure 9 dis;'ays a :: psrisen of loca A cold le.: terr.erature anf :he r

satura:icn e:perature corresponding te loop A s: eat pressure.

Nete again the sher:

ine delay Of 2h =inutes for the cold leg temperature to fellow steam.

pressure.

1.

Firs: Natural Circulatien Test with Decar Hea:

On :::vember

. 1973. Duke Power Compan. condue:ed a less-ef-effsite-pever tes: a: 0:enee Uni: 1.

The oni:. da:a available are shown in Figure 10.

Loop A and S h:: and cel: 1ec temperatures are very well catched, and the cere :e:perature difference is ab: : 317.

The taxi =u: value of ho: leg te=perature was only 360F.

3.

Se:end Natural Circula:1er test vith De:av Hea:

On May 1, 197, Duke Power Cc=pa perferred ane:her natural circulatiob.

tes: on Oconee Uni: 1.

B&k' and Duke determined that if the natural circulation tes: could be cer;1eted within one hour after reae:cr shutdown, decay heat greater than l'. rated power would be available due te the previous power history.

The natural circulation test was successful, and after 37 minutes of unpowered fler. the RC pumps were restarted.

Fijure 11 displays :he Icep A and I cold leg and ho leg temperatures.

The core :e=perature difference on loep E is slightly larger than tha: on loop A - 13F compared to 12F..The highest hot leg temperature was only 556F.

Figure il shows a co:parisen of the hiches: ho: leg temperature with the saturatier temperature of the RC sys:er. Minitut subcooling was appronizately

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the grid by erroneous a::1er.s in the 130-kV sw1:chyard.

~he reae:cr : ripped en either high RC pressure (2355 psig) or punp conitors and both feedwa:er pu=ps were shu: down.

~he emergen:v feedwa:er system was delayed in suap2ying water t

c the stea generators for approximately 7 =inutes.

Ins:rumen: air pressure reduced :o a value below 50 psi until a diesel-powered backup cc: presser was a.. c.'.',* s *. a. *. e.'

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r feecwa:er sys:e: began :c fill the stec: generaters te 05% on :he Operate Range 1evel indica: ice ('.375 inches above the tubeshee:).

Control roce opera:::s took e

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=anual control of :he startup valves in an effer: :: redu:e the :oeldewr rate 3,u

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.r Figure 14 shows the rapid decrease in the, cold leg te=perature without the

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concurrent reduction in RC pressure and pressur':er level.

This was due te the I

operator's use of High Pressure Inje::icn, as recuired, te =cintain RC pressure and pressuri:er level.

Figure 15 displays RC syste: :e:peratures and the saturation te erature

crrespending to the RC pressure during this ::currence of natural circula:icn.

Figure 16 shows recerded stear generater parame:ers that were available f::

this unplanned natural circulation occurrence. When the emergency feedwater was supplied to the loop A steam genera:or, it automatically filled the generator to c51 on the operate level.

This se:pcin: has been changed to 50% on cli 3&W

.owered-loop plants subsecuen: :e this incident.

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Na urt'_ Circulati durin: Less ef Offsite pever Tes: at TM:-:

Me:r:p:litcr Ediser 00 pany ::ndu::sf a su::essful less Of effsite power

es: cr April 22,1~75 f ren an ini:ial pcwer leve; of 15L.

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he rea:::: trip.

The energency feedvater sys:e star:ed a supply of water ::

he stear generators at apprcximately one minute, but the final level was.abou 401 in :he Operate Range rather :han SOL.

Figure 23 displays the loop E core temperature dif.ference of 35F er more and the sinul:anecus change in EC pressure and pressuri:er level during the natura; circulation flow condition.

Figure 21 shows ether R systen :e:pera:ures and indicates nearly ecual lo;; A and loop E perf:rnance. The highest he leg :e:perature is more than 100F below :he sa:uratien tenc. era:ure for the RC sys:et.

Figure 25, which shows steer genera:or conditions fc11oving the rea::cr trip, revesis :ha: the normal fill rate fer the emergency feedwater system has drastically reduced steam pressure te 700 psis.

A review of previous case power his: cry showed tha: :he core had only 0.f EFF days at the time of :his test.

Figure 26 compares the loves: cold leg te=perature with the steam generator sa:uration curve.

Unrianned Natural Circu'atier 00:urrence a: Dacis-Sesse 1 On :: eve =ber 29, 1977, Toledo Edison Co=pany experienced an inadvertent loss of offsite power incident which unpowered the four RC pumps and resulted in na: ural circulation flow rate conditions in the RC system. -The initial reactor s

power was 4GL.

The inciden was initiated by unre=oved ele :rical tes: ju=pers uni:r causef :he rea:::: power :: increase unti; i: tripped er everpower a: 50%.

The rea:::r : rip initia:ed a tur':ine trip which caused :he Operater : cper the A7 O

main :ir:ui: brcakers.

ne s:stier experienced a 7-se:Ond bla:hou:.

After

~

.-( tinutes. :ne RC pumps were restarted.

Tigure ~ displays the rapid :hange in icer

1d lec :e:pera:ure.

The

1down ef the RC syster was severe enough :: cause the pressurizer "evel :o d::p belew ere indicatien.

Figure 23 shows a similar rapid cocidown cf the loop 1 cold le; temperature.

A~ s shown is the arount of subcooling cf the loop 2 ho: leg below the RC syste:

4 satura: ion temperature.

The minimum value is greater than a 40F =argin.

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Firure 29 displays :he variation in s: ear generator water level indica: ion and pressures durin; the :1:e the energency feedwater syster was supplying water

the s:ea genera:crs.

The loop 2 generater was filled firs: to the s'e:pein of 10 feet en :he startup level.

The loop 1 genera::: was filled a sher: time lah. and the operator took control of valves te reduce the cooldown rate on

hi F.C system.

The second genera:c ~was only filled te the 6-foot level.

50: ice

he recevery cf s ear pressure af:er :erminatin; the fill cf :he loep l's:ca '

generator.

Figure 30 shows the usual relationship of cold leg temperatt e to the stea:

4 genera *er satura:1on te:pera:ure during na: ural circula: ion conditions.

rigure 31 displays the calculated core decay heat profile based on the i

power history of Davis-Besse 1 orier to the reac:or trip.

i 3.

Natural Circulation at Daris-Lesse 1 durin; Flanned Less of Offsite Power Tes:

!clede Edison Company performed a loss of offsite power test on January 15, 1979, te evaluate the alility of the Davis-Besse 1 plant te withstand this transient.

Since the previous occurrence, control room operators had demenstrated tha:

2 3 er - feet of level in both stea: genera: ors veuld adecuately control the cocidown

f :he R: systen.

Alsc, a special natural circula:10r tes; was conducted a few i

e d -b O

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4

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veeks e:rlier and 1: verified :nc: the : Ore flow rate was adequate with water c.c....

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presented i

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Tipure 3" shews the 1::; I he: le; and ::1d le; tempe:a:ures and :h+ E:

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pressure and pressuri:er ' eve; ressurerents during the na: ural circulation fiev c:ndi:i:ns. ~his was a su :essful tes: and the cooldown if the RC sys:e was contrelled verv well with the lover se:pein for the emergency feedwater syster.

Figure 23 displays the loop 1 cere differential temperature and a 60F.

cargin of subcooling between hot leg temperature and saturation temperature.

Figure 3-shows stear genera:cr c nditions during natural circulation and Oper : ion of the emergency feedwa:er systen.

Af:er 200 seconds when the cpera:er canua.;y ra,.sec :ne eve. Oc apprcx.,cately. feet, a signi:.icant reduction in s: ear pressure resul:ed.

The rate of fill appears to cuen:h stea generation nc-,,n; a constant. eve. coes n::.

.au:

nreuen s: eat genera:crs, the

or ence-:.

fill rate needs tc be 22::hed wi:h :he decay hea: and the desired coelfowr ra:e.

Figure 35 shows a comparison of the lowest cold leg temperature and the steam cenerator saturation :e:perature. The action taken by the operator at 200 seconds reduced :he usual temperature difference of 20? te nearly zero.

Figure 36 presents the calculated core decay heat profile for Davis-Sesse 1 c'lowine the reactor trip on January 15, 1979.

~

F.

Nc: ural Circula: ion Tes: a: Pever a: Davis-5 esse 1 On Dece ber 3, 197S, Tolede Edison Co:pany conducted a special :est on natural circulation with the core at a constant power level of 4%.

A few days earlier testing was co=pleted that provided the neutron flux-cold leg temperature corree:icn factors so that cere power would be accura:ely known durinc the natura; cir:ulation flev rate test.

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-s steadv-s:ste c.a:a was c::aine:.

en a2,, six leve,s were estar,,she, rang.,ng :. rom Sh feet to 13 fee: and :he calcula:ed natural circulation flow rates show

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d Ficure 37 disc.la.vs the loor E steadv-state :erc.erature difference be: een

he.,0:.

. cc2c.,e; :e peratures.

.ne tower craph shows the change in R, u

_eg an:

pre:sure and pressurizer level during this special natural circulation test.

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Of subcooling be: ween he: les temperature and saturation te=perature of SOF.

71rure 3C resen:s the c.uasi-steadv.-state conditions of both s: eat.cenera:::s r

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3 flow rate at a water level of 13 feet.

This fluctuation in emergency feedwater

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-3 Figure 40 displays :he reasured cold leg temperatures for loops A and 3 and the calculated saturation temperatures based on the ceasured steam pressures f: loop A and E stea: generators.

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Rea::cr cociant flow during natural circulation occu.: nces, to date, at epera:ing L&W plan;s is sum =arized in Figure-41 and the associated table.

The flow ra:es were calculated based on observed core iTs and calculated decay

.es: power levels usin; a simple hea; balance method.

In :he-sin cases fred.

he Sa aral Cir:ula:icn a: ? ewer es: a: Davis-Lesse 1, reactor power, measured y.. u.

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,5:: ural Circu'a:10: a: Cvvs:s'. Eiver ? On Less of Offsite power Tes:

On e.pril 11, is 7, 71:rida 1:ver 0:rt::ctie: :endu::e: a su:cessful less 6

Of effsite pewer :es: and icn:ns::a:ed th:: sa:isf a:::::' :entr:1 ef the plan:

was a:hieved under sicula:ed sta:ier bla:icu: c nditiens.

The reactor was tripped fro 151 power and all four RC pumps were shu d ewr..

Coe emergency ~

diesel genera:cr was left operating :o power a rakeup pump, coeling va:er pu ps, an ins:rument air compressor, and some pressuri:er heaters, in ene cinute the n

energency feedwater pump was opera:ing and supplying feedwater to both stea:

genera:crs.

Operators tried to.use both stea:-driven and cc:or-driven emergency feedwater pu=ps to evenly and simul:aneously supply'wa:er to beth steam generaters.

One steam generater received too li::le feedwater and boiled dry until -the filling Operation of the other stear genera:c: was cceple:ed.

This resulted in unnatched loop A and B het and cold leg tempera:ures.

Figure 15 shows RC sys:e= parameters durin.: na: ural circulation a: Crvs:a1 F.iver 3.

Loop A indicates a core :e:perature difference ei nearly 50Fe Figure 19 shows several other RC system temperatures during the same time.

The largest core temperature difference recorded for loop B was 35F, whereas

he targin of subco: ling exceeded 60F.

Figure 20 displays the un=atched filling operation and resulting unequal systen pressures for loop A and B s:eam generators.

Figure 21 shows the close relationship of ecid leg te:pera:ure of.each loop with the saturation :e:pera:ure fer each stear generator. The time delay is approxi=ately equal to two minutes as noted earlier for Oconee Unit I tests.

1 Figure 22 displays the calculated core decay heat at the time natural 1

l circulation flow ra:e existed a: Crys'tal River 3.

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1. a subcocled s:ste (minimum cf J.f 7 subcocling) and head transfer has beer.

established fro

he core via the stea: genera:crs te the secondary system.

Thus, it is concluded that natural circulation is a reliable, effective =eans e f c c re coc.~ <.nc..

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6 AD L \\u Se

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Lis: ef "irures ns:rumen:c: ion Used for Na: ural Cir:ula:10n Flow Ra:e Measure:ents a:

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Br.: 177-Fuel Asse=':1:. Plan:s 2.

RC Sys:e Parace ers During Depressuri:a:ien-Induce ~d Natural Circula:icn a: 0:enee Unit 1 3.

RC Sys:e Temperatures and Sa:cratier Te pera:ure During Depressuri:ctien-Induced Natural Circula:1cn a 0:enee Uni: 1 Steat Generater Conditions During Depressuri:a: ion-Induced Natural Circula: ion at 0:enee Uni: 1 5.

Steam Genera:or Outle; and Saturation Temperatures During Depressuri:atien-Induced Na: ural Circulation at Oconee Uni: 1 c.

RC Sys:en ?arace:ers Durine Level Increase-Induced Natural Circulation a: 0:enee b.1: 1 7.

RC Syste: Te peratures and Saturation Temperature During Level Increase-Induced Na: ural Circulation a: 0:enee Unit 1 S.

5:ea Generater Ccaditions During Level Increase-Induced Natural Circulation a: 0:enee Unit-1--

i.

5:e : Genera:cr Condi:icns Durin; Level 'ncrease-Incueed Na: ural' Circulation at 0:enee Uni: 1 10.

Loop A and 3 RC Te=peratures During Natural Circulation at Oconee Unit 1 11.

Loep A and E RC Te peratures During Flanned Tes: of Na: ural Circula:1cn a: 0:enee Uni: 1 12.

RC Syste Paraceters During Planned Test of Na: ural Circulation at Oconee Uni: 1 11.

Stea: Genera:cr Conditions During Planned Test of Natural Circulation at 0:enee Uni: 1 1.

RC Syste Parace:ers During Unplanned 00 urrence of Na: ural Circulation at Oconee Uni: 2 15.

RC Systet Te peratures and Saturation Temperature During Unplanned Occurrence of Natural Circulation at Oconee Unit 2 16.

S: eat Genera:cr Conditions During Unplanned Occurrence of Natural Circulatic at 0:enee Unit 2 l'.

Calculated C:re De:ay Hea During Unplanned 0:currence of Na: ural Circula:icn a: 0:enes Uni: 1 O

O w

Lis; ef 7f;ures icon:'d) 1:.

1: Eys:e-Pa ;te:ers Lurin;

ss cf Cffsi:c Power !es Li:h Sa:cra'.

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R: Syster Parace:ers During Loss of Off si:e Power Test With Natural es...,

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RC Syste: Temperatures and Satura:1en Te:perature During Loss of'Offiste

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Steam Genera:cr Conditions During Unplanned Less of Offsite Power Event With Natural Circulation a: Davis-Sesse 1 30.

5:ea= Generater Outle: and Satura:1cn Tempera:ures During Unplanned Loss ef Of f site Power Even: With. Natural Circulation at Davis-Besse 1 31.

Calcula:ed Cere Decay Hea: During Unplanned Less cf Offsite Power Even:

With Satural Circulation a: Davis-Lesse 1 32.

RC Syster Parameters During Loss of Offsite Power Test With Natural Circulation at Davis-Besse 1 33.

RC Syster Temperatures and Saturation Te:perature During Loss of Offsite Power Tes: With Sa: ural Circulation at Davis-3 esse i 4

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