ML20024C657

Evaluates Areas of Concern Following 780423 Reactor Trip/ Cooldown Incident.Areas Discussed Include Reactor Coolant Pumps,Control Rod Drive Mechanisms,Fuel Components,Rcs Water Chemistry,Transient Results & Reactor Coolant Piping

ML20024C657
Person / Time
Site:	Crane
Issue date:	05/02/1978
From:	Rogers L BABCOCK & WILCOX CO.
To:	Geoffrey Miller METROPOLITAN EDISON CO.
References
TASK-*, TASK-GB GPU-2047, SOM-II-140, NUDOCS 8307120931
Download: ML20024C657 (8)

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Post Office Boz L50 M1(*1etov=, PA 17C57 Suhject Eeacter nip /.5./Cooldsv: :=eide=1 cf 23 A;ril 1978 1

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$4". 73 I= secorda.=e with ycur req =est for.he eva.1.:atics of specific areas of cc=cera fo'.lovir.g the suhjec. ;1a.==. trassie=, 3av has ec=;1eted a pre.

'* *- y review c* the effects c* -he su;;1*ed data. The findugs c=,. -

cer.-1=g the remeter coelas ;c;s, the cer.:::1 r=4 drive =echt=1s=s, fuel co=pe=s=ts, the R ea=.cr Coolt= Syste vue che=1stry C*S3 trs=siet resvits, reictor ve=sel trassia=:

results, a=1 reae:ce cocia=;i;1=g, 2'

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Reseter Coela.=t 7.

,.s r.

4 Zuri=g the first 22 =1=vtes of this tes=sie=., ti:r'ee ;=;s were operati=g,

.tvo 1= "3" loe; and one 1= "A" loc;. The v=rs ce=iitics, frc= a= :Piz sta=dpoi=t, Wuld have m.ffected the s'=gie ;_- ; is the "A" Icep.

'"*is pc=; vas flovi=g a,,..zisately 117,00C g;= at.he ti=e cf the i==ide=

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and veuld have required a =i *-- =ys.c presr.:re of thc== $60 ;sig te prever. cavita:!c= = the i=; slier at a ecid leg tcpercu.re of LF.*T.

As the ir.ficcic= is the the..ys.c presr.:re c=1y dr.,;;ed to J

752 ;sig, we da===. helieve the ;=;s c;eated c= der esi' ati=g ec=11tio=s.

Ve acte the.t after 2 =1=utes, s* =;* e

,__f c;eratio= 1: each loop vas i=itiated, however,1y this ti=e sie *.es :cr Cc=1a=2 Syste presr= o va.s bach up o 2110 psig, which ve::14

..ide ader.:a.:e 275: available to the p=ys.

2"rcz: vet =1.chservations, we u= der:ta=4 that i=je: tic: vater was =ai=-

I.

7 tained and there was no,=oted ch.u.ge '= shaft vihra:!=s. Ve wuld like

• .,j to get additio=al i=fsr=ation, su:2 a.s see.1 esvity pressure res;onse e.

.amd seal ler.1=ce during th's.resie:S to fur-har our c.sviedge a.s to o.

4 how these semis respond to such pla=t tra=siasts.

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to the effect et leng-ter= fatigue 11*e os the ;=; casi g and ecver.

j These transiests would have to be evaluated by the Xecha ics Reses ch

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=stitute, ne consulta=. that perfer=ed the stress azalysis c= these

• j yi=ps. We recently citahed a quotation "cr SS.CCD for a shilar analysis on the % 3 7.:=ys. If we are advised to y.roceed vist this

• a=alysis, we vill p. sve obtablig a new g.actatica for,ne 2C 2 pungs.

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. ;I 3r V reco==am's ec=ti=ued operation of t$e reactor cocia=i. p.:i:;s.

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Sta.rtu; and pver escalati== data pertahim; to the teamsce cocia=t y=; seals aad p.:=p vitratics data sh:uld.be chtained and cc=pstod vith ta.seline refeeste data.. This data shculd he fervarted e Zav s

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for t hal rocc==estatic s and cer. fir =atics c' cur asses =:e=t. 'Ve wr.id recc==e:4 pursuis the analysis descritei abcve, h=vever, this

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woul.1 set delay ce pese: cperatioc cf these pu=ps.

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Cc_ff.r=atio= is reg:erted that the safe:y reds which were.vithdraws s

durug the transie=t were d. rives. :nt trd.; ped, ha:h i=to ;1 ace.

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' Imaad or the above, a=d the shilari-ies of this t.rassie= to the rece=tly asalyset 27.;: trs siert (.'?a.rch 20, 1974), we do not feel,

the:s are s y sigsifitant ess=erts regardi=g *.c=g-te = da=a.ge t.o.

t.he C.::t's c'r the'.: thility to es=ti=ue to ;erra.~ as desissed.

-2 y*- ? cale..lations to su; port these f*-'*- s are a=tici;s.ted 1 7

Juse 1, 1974.

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• = additio=, the tor =al drive ve: ting proced=e==st be,followed j

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3 11=it/Precautica C=rve 1.C. C5.2 was viciated by as =u=h as 250 ; sis

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d=i=g the accidestal depress =isatic=.

Z:vever, cis 11=1: re;rese=:s-

-.j a worst case envelope ar.d does =st realistically reflect the e==diti:..s

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encou= ered in 'the :1C-2 trar.siest. A specific a a2ysi cf the *::C-2

- 4 ecoditions ush the su;;11ed reactor..cocla= ta=petture/ pressure i=for=r. tion and the TACC code (Ya.rsion 18) i=ficates that in act:.miity

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1 C. P. Miller 3

• gy the fuel rod cladding =ever experie=ced a te=sile force.

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• cc==e. va:ive a.=aly=1s and all i=fcr=a:Los 8

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, Although the li=1ts/precar.ic= c=ve was viciated, a tra=ste=t specific U

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l a=alysis bitcates t.he fuel desic= criteria was =ot; the efo.-o, E*i N

does not feel there is any ec=cers rega.r,ti=g the ahill:y of :the fuel j

j to co=tinue sa perform as desi;=ed.

m All of the akve findings are hased e= the i=fer=atio: ;rovid.e4 fros

, l

/

the site to Z=gi=espi=g through N==les.r Sevi=es.

17 ROS Nater Chemist-v

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'. ' l A review has bee: =ade of the c)erati=g a :". chs=istry da.a associa. ed

+

y; vith.she chieride co=ta=1=stic= cf the Rea=:=r Coela= Systes c:

M 23 A;ril, 'a=d it is our 's;i=ic= that the 1135 chierides ' vill have no

.]

deletaricus effect c= the s :.:= :ral i=.asrity of the Ken.c.cr Coela=.

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Systc= cr associated systa=s a=4 et=f; e=..

fleref=re, the Zea.c.or Coela=. Sys:c= rc al=s,aeee; ahle fer ec=ti==ed ope. asfc=,(heatu; and startu;). This letter cesstite.es the required e=gineeri=g -

eval =at'om i= acco.-da ce with 71a= Te^ ' al !;ecificatio= (1/k L-17).

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• j This eva'auatic= is based o= the f=novi=g ec=iisio=s.

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..l Chloridas 3.O ;;u (=a=.)

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as '-'* ested by che=istry a=alysis Sodium

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a=4 the Resater Coola=t Systa= a: Eat *

-'hy Cc=11tioEs.

This e ahatic= is specifier.*ly t= sed o= the h. sic ;E associs ted with the sodiu= tydr= ride co=ta=hasio= a=1 ?.he ;rese=ce c*

ov ozyges levels.

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.L-3/2/78

, j ;

g 3'":", a=d ausillary erstens s$d ;f;1=g cc=.ashatica., ne Reacter

?

.,, y

,. Cocis=t Systs codi::s*1evels =ust be redu=ed'hclev 2 ;;m ;rior ta

j g

. achiev1=g criticality i= the reacter with ch.lcrides as Icv as pos-

,, j sille, a=d because of the cierest plant =ahte a=ce verk, a*1 ec= trol rod drive nec' -'s=s v1.11 require full ve=ti=g before retwa to cperations. It =st be stressed, however, that Met-Id should e swe.

that sodim lev'els are below 10 ;. is the ce=:rol rod drive =e^ 'st t

ec=;o=e=tm he.ri=; these vesti=g opera-ic=s, with chlorides s'-'* -ly i

5 rotated.

...s'.,

De 3*.Tl' shocid have all of the costa =i=a=ts redu=ed to the lavest

.5 achievat.le clea==.; ec=ditic=st 51g=ifies.= th.shi=5 c;eratio=s c.

j all of the i= tere.=r.secth: ;f;hg shec.14 he a. cc=;11shed to eli=i= ate d

, ce=ta=hation..h Ocse a eas.

Y.

Cr.ce S. och 5:es= te=ceters i -

3a*=* Mt. Ye=':= sectic= has reviewed the data se=t ce=:ershg she' rapid cocidews which oerurred a. '::C-2 c: 23 A,..'1..

2a. sed *ce the i=ter..a.1o=

received by tele,.hsr.e a=d tele==;y, it a;; ears the het les reacter 0

cocis=t ta=;cature d.rc;;ed fic= $F2*T to 160*T is 3-1/2 =i=u.es;a=4 -

the -'."== te=; erat== cf L5k'T us rea.:hed C-1/2 =i=:tes after ne

t. rip. *The reacter esclast sc=;estre 're=ahed relatively ec=sta=t

'i at this ta=peature, fer at least 3 hou s, hefere a gradual ecoldsva d

vas hittated. *: is co=servative te ass.=e that the -= *'--- tube

• j t

t.o she.11 ta=; erat =e dif*ere= e is egual to the - *-- ta= erat =e drop of 135'T.

1l 2.is is less shar' the 17 'T tube to.shell sc=pe: atre differe=:e that was a=aly:cd fer the rapid escidev= s..*?.3 i= Ear =h a=4 hased.'o= tha, a=41 s's is acce;tahle.

7 r

J The rapid te=,4. rat =.re decrease vill cause local ther=al stresses which vill havg to be evaluated in order to descr=.ise.he effect si this trassie:S on ste fatigue life of the vessel. 29e= thr.:Ch this trs=sie=t was==re ra;id ths.= the 5:1:3 coeldci.s in l' arch, ne t=tal ta=;eratre drop us sig:ifica:tly less; a=d 3&V feels the =et effect of the OC-2 1

cocidevs vill te less scvera tha= the.91:3 eo=1dev. eurres ly bei=g a=alyzed. -

~

Attached is s' graph shevi=g the te=perat=e distributies in the sup

• s

.1 shirt dri:g the critical tra=sie=t ti=es considered is ce Cf!3 stress

.:..d Report. 51=:e the react.cr coelt t te=;ersture did act dec; telov LS.*F

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d=i=c the initial ecoldeva, nis transie:. should act produ:e a te..;;er-

..e ature gradica: ar.y scr e s ever e "- a the cc:41tica s=clysed "is ne stress

. *..,. R report. Therefore, the effect ot* this tr==stest, os the support skirt l

~.~,f wuld he the same at a 1CC*T/hr cocidova.

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3ased es he af=rme=tio ed it'es. 3&V feels cat he s.rnet=sa integrity of de '::C-2 generaters is ac ey:4tle for res=.1=g =ce..a1 1.4 P a:t e?araties.

l a

Y1.. Resetar Tessel

. A p.* *- y review of de tsjid coc14=v= transiest talece;ies to e

C 1

3&v Mt. Ver=.;= sectis has bes: reviewed a=4 fenad to Se necey:ahle.

The t 14capied' c=ves of cis trs=.sie=t were difficuh to read; cere-il fore, the tra.=ste=t a=alyzed.*rs= a fracture r.ec'*

8cs

.asspoi== is described belows

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1751) 22co c.o c.o 575

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..W 15 0 22:o 115.o taco ce=pse=t 7.=si=ecri=g is.s rete'vec the e,.ar yri= mut of the fracture a

mee. -* cs amm* 7sf.s fcr ce c=re regi== s.=4 the cu.let====le-sc= ale s

beh region. 2a s=:ress 1=:e=sity facters far cis trs=s".a=t' vers le~ss tha.= t2=se ex, erie== et hy E*C3 d:= i=g a :syid cocid=v=. Pr ' * * -*7 eraluatica c' ce s.=airsis *-d'=ates.tia= cis area is of me comrass W

be. sed as the tra=sie=t data.

a

'j A det.aI*.ed ;ri=a:7 ;1_s se==-d"h a=4 suhset===t fa*ig e amm1 sis was 7

i mot perfor=ed. Se 65ces ti=e t=atics of the trassie=t reraits la pes.k ski = stresses cr. the inside s=fszes and :=all dises=t'- 'tr

. ' t *-

..E stresses (;ii=r 7 a.r.d seco '. 7). Usi=g a.= u;;er be.:.=4 peak skis st ess. equatio= vtich ass.=:es a= i= finite f11= coefficiest ami E-

's.ey down 1: :1=i4 c;ersi=e. ne rershi=g ski = stress far thi,s r* c tiassie=t is a,,

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cerzal stres's a.=4 ;;tessure stress lu=;ed with the =asi=s= swass E

rest.lti=g f.as - a1 sserati=g trassie=.s vill have a= i=s's=ifica=t q.h.C.*:. ",, l..

effect os ce c.

• .tive fatigue ss' age factors of he reactor vessel

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• A further fatigue justification of this' trassie t is that it 1s * *

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less severe tha.a the 5>lll3 rapid cooldown.

The.9C:D rapid coeldova trassient is is the pecess of bei=g a=slyzed by u-111:1ag si=;11 tied conservative asa. lysis methods.

th's amalysis is in the final stages and increase'in enzsulative factors at the more cri'tical locati

ons,

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, Y:I. Resetor Coetant miu and Pressuriser__

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1 the traastent data shov= in the table below 5as 'been rem.eved f$r pt" '-- y !=;act sa ne operatias life of ne DC-2 reae cr coolant 3,.

1;1=g and pressuriser. The results of Cis refiev show there vould be no sig=ifica=

Partion cf the reacter coola:t piping er pessuriser.it.crsase in the cu ulative

~

7.=vever a detailed analysis w=uld =eed t,o t.e.,,.rter=eg at a later date to doc-1..,e his ory cur.u=e:S this trass' est's ac sal ef"ects for ;..;cses of the ;' nts i

Most of the resesar,s ola5% ;d;1=g has, at pese==, a Nv C1F as does.

the p essuriser. therefore, ne iscrease is C*. F due ta this one time occurrt=g transiest vould =st cause *=y portion of Me reac.ar eoola:t piping er pessuriser *.o have a c'*T greater than a.11ovahle for the life of h e plaat.

o

• hus, there are no know= ecasetzer. es of this sh==rrak tes:st ent e.- the reacter cocla=t ;i;1=g and pressuriser which would pavest s.artup og the ;1a.=". at this time.

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