ML20024C724

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Forwards 780508 Memo & LC Rogers Re Rapid Cooldown Transient of 780423
ML20024C724
Person / Time
Site: Crane  Constellation icon.png
Issue date: 05/09/1978
From: Wandling G
BABCOCK & WILCOX CO.
To: Rogers L
BABCOCK & WILCOX CO.
References
TASK-*, TASK-GB GPU-0366, GPU-366, NUDOCS 8307130122
Download: ML20024C724 (18)
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M:"E IN372UCTION NO. U2*- I .4 s-TME5(SCDCK& WILCO 2 COMPANY D M 6 0N-( .E .] @ERCt!!ERI.710!sGROUP e ILESPONSE GQ'D Fi107.! 4 4 + % I L. C. Aegers - $lte Operations Manager. Three MiMg*gg""$n.3.,e_ (.4f i lh _C~~ ~ r-Ir**

8. E. Wand (ing. Startup Task Engineer (T.st. 2034) i ll.

5 k71-:A 'm j r Cost. g ~ Iil' #8."33*0 .t er Bef. 73.5 I 3. 9 '3waj. Capid Caeldoui Transient of 4/2.1/;g Date gay 3,1g73 .j jf a .'i I

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gm. . = - g g g The fellering is a prelfeinary evaluation of the subject transfent es requested by the customer. Specific areas of c:rt:ern are f acivic4411y addressed with j recommendations made where necessary. The evaluations s:ade are based upon data .i I.q received from the site in the fere cf slant para etar grapes reactimeter data. RC5 chemistry analysts results, and me sessen:e cf events during the transient. ([ F-6* . o Reactor Coolant Pimes ,. w.: IL G t-

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During the first 22 einstes c" cis treasient. three purps were operating, two i-M. F. f. in *S* Loop and one in *A* 1.sc.

    • e -:-s: concitton. from an NP5H standpoint

'T would have affectes ce stagle :.r: 1i t*e *A* Loco. This puso was flowing r.$.f kN d4 appresimately 117.000 GM et !?.e stre cf t~e in:1 cent and would have required p

  • j a siniseas systas pres:ca cf asc.: 5C *1:1 ts cre<ent cavitation in the f;

n ispeller at a cold leg teeArat.re c' a!4 F. As me Indication is that the s '. ~7 system pressure caly cr:: red :.*!I **;*. we do not believe the ptssps operated it," -t imider cavitating condittent. .e 'm:te t'.at after 22 minutes, single pts, p.. 4 ?-i operation in escn Ice: mas trittster, a.wtvar. ty this time the RC3 pressure ' %j was back up to 2140 P213. =*.1m e.fc src<1se aceluate NP3M available to the k* f. pumps. .q" .9..r V Tram vertial observatices we umrt-* t : tr.at 'efeetten water was risintained 0, ' 'd +2 and there was no noted =teFe t't. ***'t attratten. We would Ifke to get [

  • additional information, su:. as seal ca.tts tres:ure response and seal leakage

'j L during this transient to f:.rt:e* :p ir sledge as to how these seals respond M. 3 to seen plant traastents. t, - As this was a very evich tergt-ature a== pressure rarp.12$ F in 3 minutes, l.C 1448 P51 in 3 minutes..e :am-:: r6 an l3 . term fatigue life en t'te p>.;m= castn; a-:y statare t as to the affect of long. ,t-c:ver. These transients would have esear.r. Institute. Se c=r.sultant that performed [,. j to be evaluated by Meer.anics r the stress analysis an these pa:=s.

  • 'e recently ontained a quotation for S8E g

E for a sistlar analysis en the $C = r:t. If t.e are advised to with .-G this analysis, we will pursue catair.fr.; a new quotation for the -2 pumps. h .1 b

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  • su recomends continued operetton of the reactor coolant pi.scs.

power escalation data pertaining to R:P seals and pump vibration data'should "g kl.*'.,,. This data should be he ottained and coat.ared with baseline reference data. forwarded to EG for final recasiendations and confirmation of our assessment. 1 kg

  • Ide would reconeend pursuing the ar.alysis descrited adeve, homever, this would

) [".i-s. not delay the,present operation cf these pw:ps. [ 4A-g d:f,, [b'.:.;- !!. M ff Confirmation was received from the sita office that the safety rods whlch were { 't 3 j withdraw during the transier.1 were driven, not tripped. back into place. re f/.,. . I' r%.... .e ReCoBreadatiens ( Q5 t-Based on the above, and the sir:ilarttfes of this transtant to the recently 7 analyzed 9t:D transiest (3/:*.c.'t). we do not feel t. Sere are any significant J[C,... concerns regarding long. tera Carage to the CC't's or thef r 43flity to con- '.J l tinee to perform as desig.ed. Final calculations to support these findings . f.F. : -*' are anticipated by 6/1/72. .j j O,** In addition. the norcal crite ver. ting ;rocedust must' be followed prior to

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returning the C2Jt s te service. d.R.m'.; w 111. [ee1,, m_, -.- i. It appears that the er.ol:M lirit for 80:. clad cocpression found in 1.isrits/ g 6 '.- Precautions curve 1.0-03.2.At vt:latte sy as such as 250 PSIG during the f;?.- N-evee. tats Ifeit represents a worst case ~ '; accidental depressurt:ation. r envelope and goes not reells;ttally earlett the canditions encountered in A toect'tt ar alysis of the Tri-2 conditions using the y (J.;.'- '. 4 the TMI-2 transient. tr.*er atten and the TAto code (Version 18) supplied RC teeperature/scr*.s. t indicates that in actualta:r tw d.el rot clas:Ing never esperienced a ten. $,y 4

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This concli.sice !$ teset en a cre.servattve analysts and all sile force. T,ir.%er ar.alysis detaf fs can be found fa (;p,. information available to date. p.. calculational file 3*.SC7:.0:. w.- Recoeuwadatieas i h .s.- Although the lirits/tre:autite.s ::.ru was victated, a transtent specific . b-analysis indicates the fuel :esip cetteris was not, therefore. BW does b-" not feel therv.is any cencem resareteg the attif ty of the feel to con-tifhat to perfort, as ces1 ped. i.. . t.. Q'.. .. p.. L.. r L i ,L, e s t ) V h 1 n j l. I e f is'. L. d ~. L '% u ~~ ~ fO9 0 a_ 5 9.;. e ~ e

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-2 m y a,1sra IV. ~0 54's f 0755 Eagineerfing Unit. Mt. Yernon, has reviewed *be data sent concera.f ag the e sa6 ject rapid cooldown. Eased on the inforv:atica received. it a : ears the het leg RC tegerature crepped free 15 F ta AC F in 31/2 efnu.as and the f sinfeum *sr,*.orature of a54 F was reamed 6-1/2 min'.tes after *.he *.rfs..We .[ isodersta-d the RC tarporature remained relatively constant at this tasserature for at least three hours before a gragsal coole:W1 was initiated.. !! is con-C. servative to ass:ane that the nazirass tube to she11 tarporature effference is. ) 'yp'

  • equal ta the maximum toeperature drop of 138 T.

1y This is less than the 173 r tube to s% ell temerature difference that was .- ( analyted for the rapid cocidown at SP.'Q.In March and based on that analysis is acceptable. t The rapid tarverstore decrease will cause' local thermal stresses which wf11 a have to be evaluated in orcer ta determine the affe: of this transiest as the fatigue Itfe of the vessel. Even thougn this transient was sore rapid J than the SN'3 cooldown in.* arch, the t:tal temerature drop was significantly less and we feel the net affect cf t.e TMI-2 c=cicawn will be less severv ~ I

  • y than the SPLC coclean currently t,eirs analyzed.

e Attached (See Attachment 1) is a gra:> showing the tasseraturv distributtos-fa the support skirt durfr.g t*e critical transient tires considered la the _D 820-CCCE-55 Stress Recert. Stace the RC tacpersture afd not drop belor 454 F r y ..S') 'g gradient anysere severe tt.ae tr,e c=rd:sfon analy.e s in the stress report. O during the initial cact:mma, this treatie it shsaid not produce a tecperature 3 Therefore,100 T/hr coolema.the affect of tr.ts trar.:le. on the su; port skirt would be the J R same as a F l Based en the above ttams. 354 fetis that the strw-tural fategrity of the t TMI-2 generata-s is a:ceptat*a f=r rss.sta; n: mal plant operation. 0 y . ~y .*.g i Y. Reactor Yessel ,i

  • 4 1 V A preliminary review of the re:+c ce=*::.= trar.sfent telecopied to 2&v. Mt.

t F Vernen has been reviewed a-c fr.r: te t.e acce;.tante. The telecopied curves F of this transient were esffi:al read; toersfare, the transient analyted - / from a fracture =caanics st.-tocir.t is oe:crited helm: {. e.. m k. v t- ..g e t. 6 e a e b. p. <e s -- 3 g ,_:...w..~, -s-E-f0T O 8 6 O.f. -1 = .r l

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i .] 115.0 2200 'f[ Component Engfreering has received the cas : ster printout of the fracture 'o, mechanics analysis for the care reglen and ue cutlet nozzle-nea:1e belt region. The stress inter.st:y facters fer snis tran; fen: were less than those E experienced by."."O dr. ring a resid coc!down. Preliminary evaluaticus of the ?

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transient from a fracture mecPanics star.sacint indicates that this is r.st am 1 : P j area of concern and tr,e transient is acceptable. e ,,Q A dotatted primary plus secondary and subseovent fatigue analysis tsas not (. N performed. 7te sac-t tiee dorati:n =f tne trar.sfent results in peat skin E 9 stresses on the inside surfaces and sat 11 discontinuity stresses (prfaary

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.d and secondary). Using an u;per to;nt. reak skin stress assuation w4fch assuses F an infinite film coefficie-and a ster esan. in fluid terperature, the re. [ ) ' w ~, 4 smiting skin striass for this transient is at:rssitately 26,000 F51. One [ cycle of this 25.0CT, PS: t=er.at stress anc pressure stress Turped trith the 4 1 maalaus stress resslting f r s nor al c:arsting transients will have an insig-af ficant affect art t?.e c:ssalative fati2ue usage factors of the reactor vessel [; [E g components. .p b .E. snef tats :-sestant is that it is fess severe f L- ,A A further fatf;w justifigs: 8 9 than the.N.! rapid coeldr e.

  • he *..::: rapid cooldoun transient is in the

[ process of being a*ely:ed by t!18:te7 tirJ1tfled conservative analysis 4

  • ?.3 methods. This analysis is in tr.e firal st ges and the increase in cumulative F.

?c factors at the more critical fccatises are small, b 1 U. ~~ l1 Y!. Reactor Coofas P4=fas a d ?ms 1-4 er

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1 y 2 The transient data sureart:ed in :se ta:Te beter has been reviewed for pre-e Ifminary impact en the caeratfr.c if fe e' me ??'!-2 reactor coolant piping and i.. pressurizer. "he results cf :*.is eview s*.=w mere would be no significant facrease.sn the e s;1attv .s re fae::r f:r a.,g portton of the Pr pipiag or p us.ever, a.4etailed a.aalysts acued need to be perfor:ed at a pressurfrer. .a g later date ta 4::sent tP.fs transient's act.a1 effects for purposes of the g plant's life his.ory C::F. 7 t: I Most of the ft: piping has, at present, a low C;T as does the pressurfree. {. Therefore. :ne increase in ::? sue.t: mis cae time oc:arring transient would not cause any portion of the RC sisteg or pressurizer to have a CUF g greater than tne alls.atie for :Me 1tfe of :se plant. ,:p. r ~ 3 .i k. f ,P a e o ~ '[- P g.h y" L _. G d"" - *1 f' - '. f ?

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There are four observattens cr calculations which can be drawn to ascertain' l [ y /. f.5 meether or not the prv.s: art:er.s.'rge line e Stied during the transient. Each I f \\ .,7 of these suggests that. in fact. ne staan butble was drawn into the RCS proper \\ 4 from the pressurizer er f:rties src:: tare :. sly during the depressurization. [ . *'. 4 . Calculations were made besed se Se setsured F.CS parameters to determine the .. f t n / 7 - 5 rate of and amount of *:1 :cotant s--fr.kage tring the first two minutes of the transient which faci. noes rest af t.e peried wnen pressurizer level was f. low-eff. scale. These ca*calet*e-: c:n tr.ered the effects of the Makeup j !. .9 Systs and the operatcc Ir.f tf at - t t* HFI. esti.v.ations of the effects of [y; d temperati.re measurwea.: errs =s. ar.4 flat. sing and subsequent cooltag of "= e$ Ifquid in the press trize es 16e grassure repidly dropped. Using conservative .I .. + estinatas for these effects, tre calca,*ation shcued that the pressurizer steen l P. bedrble reached the upsee sectica cf t'e sur e flee i.e.. the pressurizer did t-empty. but the bubble di: not reach :::e het leg. [: The second itas of 'r.ste is t*st tMt R ! pers:ure was a smoothly varying f. 'parametae throu;*.out t*e tesnsit-t. In >suse. codes (e.g.. TRAP 2) have shone ~J that following pretsuriter suale if-e e*ptyfeg. RCS pressure promptly fTattens } k. t as het legs flash to stear, in.s esf taintes the RC3 at saturation pressure for the highest torperat:; e in tre k73. This sort of phenorenon did not ) eccur at 7y.12 as can be seen from the loop RC pressure tracas. t 't The third indication that no huhtte was drawn in the RCS is that the hotter f; .y of the two RC3 hot legs (Lc=0 "A*) rever got within 2C F of saturation taspera- -O ture as the R:s pressure felt. At ne 3 minute rartcarter reactor trip. the' y pressure turned sharply up ard and this as ect of t'.e ;rchlea ceased to be a [' f .a m,. n I

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s4? ~.,. ~.%.,.,..,,..,.., . y:yo.: m,q..,._, 4.y,, t.. g..., y.,..., ...uyp.f., g.; s. ... f .. m _ g.',...., g.,.:.z. -p. .,1 3 .;,44.;m y yy.:. c m...,..,.,... '--... : v.~.?.e. ~. . ;. ~., e :~. l.,;,., _ r,; E-}:.Q j.1--. :Q:.;-lj .'..'..: w... '. ' ?.'. '.l ;.....:.:. ~ _. 9 y_., ~ . ~ ^ ' - ~ _ -._ :.Oc t , c. -. : ;:.y ..a j. :- s.., w g... ed f- .L C.' Angers -4 nay 8. 1973 i.,. r. p. ?..' x ". '.j*% The. fourth itms is a qualitative agreement based on the reactisiete.c data from. M the site. For purposes of esplanation, the plot of pressurt:er level. RC1 's 7 pressure-and pressurizer tec;,eratuta are attached (See Attactment 2). Accord-ing to site sources. 43 seter.ds af ter reacte.c trip. the HPI isolation valves t. were scened and. tae second r.akave puca was sta'rtec. This' point is s.arked with [ ,EP Aj an *I* en the pressurl:er leve4.-plot. Design stroke time for the Hpt valves V. is 10 secondst design start.a.:t. ins-for the s.teus pur;s is 6 seconds. There-t e. fore. It seems reasonable ts* assure that full tipi flow was achieved well before the 1 e:inute mark. Stace the.sateve pumps are centrifugal pis:ps, their 8 3 level trace that when.it cr.ees back ce scale (t = 2.2 minutes) pressurizer flow rate increases as RCS pressure decreases, listice on the . Its slope is .I F relatively lineae for about nait a minute.. t.: t = 2.5 minutes, the operators i 4-throttled dcwn Hp! flow. P.ctics that. at that time, the slope decreased'as t, E~' one would err,ect. liow lost at the dashed curve which covers that range in t p-time when level was off. scale. for the level ta have behaved in this way. h makeup flow rate wculd have had to decrease so stice before level came back en scale. Sface RC3 press re was centic.cssly decreasing throughout this time. h.. g r and the MPI valves we o at a fised pesttion, this conclusion does not sees physically realtrable. Tr.e only curve shape wnich meets the physical conditions 6 .t line. This alternative is shown as a dotted h is a concave curve, or strat~II:w vs. RCS pressare curves put out by Component line. According ta tr.e i= I , e.. Esgineering. the NPI flew este sh:uld be c:ntinuously tr. creasing as the RCS ' ;:g.'. 'i pressure falls, thus a c:. cave curve snase ser-s rest logical. The conclusion 1 from this line of reesce.9rg it t!.st pressart:er level could not have dropped

, pp/

very far belas the 1<.a.or levet to: when hP1 tun.ed the Icvel decrease around. g q '9 The curves.suggest thst the 1e,e1 suyed within two feet of the lower level l m .../ - g c. tap. . ' 'f. - ~ .? ?._ 3 Based on the argurar.ts aec a.:se-vatter.s out1'ned above. the B&W conclusion is %. E. that the pressuM2er mes re,ee e?: tied. It af, pears that only the operator's timely initiation of E-! =mt-te: 9:: fr:c oc6urring. but the data seems i 4 to support sur cententic- '. st tre ;.ressurizer mas never entirely drained.

  • j D It 17.K:

p$. Technical 53eefficattr.n 5 rv.ww Y111. i .,e g The preliminary evaluati:*5 ;e-f - cc t: date have specifically addressed vio-F -l* 2 14tions of Plant Technical 7; Ws:ati:n tets 3.4.9.1 (b).and 3.4.g.2 (a). V,. N These preliminary evaluatic~. ts:1:a:e es ce:eterious effecu on the kC3 loop L pressure boundary (inciver; :-e:SuHte* aae surge line) that would prevent continued plant operatier. is 41 evaluation of the above noted transient p'r. will be perforced to sur:ert..me atsve state:ents in the near future. =. F.F II. RCS Cheoistry l A review has been cada cf t*'il:erattry and chanistr/ data associated with the,. 5 - $c,. . chloHde contacinatica of t=.e RCS en.a/23 ar.d it is our opinion that the high [g"- ] chlorides will have no deleteHous ef fect en t e structural integHty of the RC3 or associated syste:s and equf ~ent. Therefore. the RC5 remains acceptable. t e for continued eperatic.* (~ eat.: anc start.:). This cr.nstitutes the required l / M/ ) engineering evaluation is accerect.ca with Plant Technical Specification (3/4 4-17). 4 I,,;e... ' ~ ~ R,.. 2 , f:t t '. s - ,i. c --- y -. a. w : w ; = %-fo9 o a q at A. -l" O. ..

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3._ .: :.. y~a. s..... j 1 l ~ '. May 8,1978 ( - e.~, L. C. Rogers 7 ( p, i i r .A This' evaluation is based on the following conditions: I 'f- ,,] g- .,) l .[ .- Chlorides 3.0 pga (max.) as indicated by chemical analyses .h- {.', . Oxygen 0.0 pga Sodium + 130 pps E. E and the RCS at Hot Standby Canditions. g This evaluation is Specif13iiy sasee on the sasic,* associated with the I 9 sodium hydroxide contaefeation and the presence of low ozygen levels. .] .i "J Recompendations for contamination cleanup have already been forwarded to the j g site via Site Ir.struction 6/200. g- { If there are any questions, please contact me. 2 GEM:RF i fc.. [ Attachments .e .J cc: V. N. Spangler P.C & A. Baker ,;?. L. R. Flethe RO.'tEY.:ZD FOR ACCU.".ACY E C *'" **s* G- @"' 1os4. A e.J t l. m.r"/g'I' ' ~~ E- ^ l D. E. Liennart 7 J. N. Nicks M ,i, ? 'E S. A. Meyer w '-- / M_..M 12 A~g D?t:3.:M*b c t g,y,gg313, 7;- i ). $ .s g V. J. vest g

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R. A. Coe a. a a R. A. Wal11e T. A. Brandsberg re-f' C. W. Bruny. Mt. Vernon If y,,. P. A. S <! c. J. n. hortpurne .r.eu t m e< A. D. McKim. Mt. Vernon g R. R. Schaefer Mt. Terr.ca. - / l. w(,- T. E. Geer ru J. R. Burris 6 ..J.i C. E. Harris M-C. V. Tally h." ^ J. R. Bonart ,e,. .i M. E. Pe:4ts $r Central Files b.c b. 1- . ~.

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= d',: Based on st's aMvt. a... tm sta:.htr* tf e=. cf u.is tras est to the t, f. recently masay a :::.1 t re .tr.- .:::.e::. 23. mi), we e ast feel 't L..i there are any s'c.ith: t .a. rar. rett.. :.er.:-scr= damage to 0 ' h the Ch:n's or their arsht, t: c. t.*.it..e tc pstform as desicsed. p Flaal calesisticas te.:;;;rt *.:.s:.e fisdla.ca are antici;s.e4 ty } p ".t..f

  • i 6 June 1.1973.

py. la addities, the s.cr e:.1 tirl.c vd-r.tr. yotel:are aust te followed' Ga .. h. ; yrfor to returnu;; ::., et.ca ta. cerv 1==. [ j. f.- a a III. f.3.!il.* [y (( I It appears that tas sc:22:v: Ibit fr.- IC*. el:4 coe:yression found in f.-.. Llalt/freesuti:n C:.. * :.f. %. v.s. v::4 stet by as 2::23 as 200 T81C ..l durf ac ce me:11= ta 14.;rwis 2.-i :.;;cs. h:w. rte.t. tal: limit rescvstets f:

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