ML20236A065

Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days

ML20236A065
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/15/1975
From:	Butler W Office of Nuclear Reactor Regulation
To:	Williams J PORTLAND GENERAL ELECTRIC CO.
References
TAC-06596, TAC-6596, NUDOCS 8710210378
Download: ML20236A065 (13)

Text

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INCLU UI'E O

STATDM!r CF TIE FFOElfM l

Jn the un}ikely cwnt cf a IW primary coo 30nt nyc t ern pi r:e t upt u re in t he l

irrediate vicini ty of t h" react or vesw), transient Jen& oticinatina fro.T three principa.1 causes will le c>:erted on the reactor verrel suppert systcr?.

There are:

3: B]owdown iet fotcer at the location of the r upture freaction forces),.

2. Transient diffctrutial'pressuren in the annular rcaien between the veccel and the rhicld, rod -

3. Trancient' di f fc i ent ia] prcrcurce actorn the core Fert e.1 within the' reacter VCGre].

The blenlown vt lcr ec t are eda!uat ely understoc-0 cnd derjon preceriot er cre avai)chio to acccunt f cr t her'. I?oth of thc "diffcrcntic) prercure" forcec, houtver, are threr-Sirc.nciona] and tire dependent and troujre rephisticatcd ana)yt ical precWrc 5 to trcns) ate than into .lo 9r actina en t h., t eactor vermi ruppert-< 'tc r. 111 of the 10:e are rcr~j st ed 1 y th inertic rnd by the nuj port r o:! o r coS rentraints or otha co;;ponente of the primary coolDill CyS t 01: jrJ3udi!d tht rei,Clor J>Fer ';ure \ CCre) D'll'er t S .

O The trennient dif ferert ial .premrure r.ctira externally en ll., reactor verre) in a rero)t of !);c f 3cv of the b]cwM : effluent in (bc reect or cavi t.y. 'lh e rrcor i t ufo enM tI c t i: ' dep.ndonce cf the terultina forca deren^ on tfe nat ure ind tbc o;' of the pij r rupt ure, the clearener l eh:cc n the ,ver rel aid the rhield m t!r ria cod locet ien of tl.e vent r;rniras )cadina frer Ll e cavity to t!.c centeitrent er a whole. Fot reme t ir e i c f. ired enc lyt ica L rret hcds have I ccn evai li ble ior calculet ino t.hese trei-rient. di f f crent j a) prerCurrO (rul l i-r f'N' rnial vres) . 'iPe result s of ruch envlyrcr' irdiccre t hP t' tlO COP 0 eG Uc n t 1D2'S en ll.e venFPl Support CyHtcU c03 Cull't.Dd l'y 3 cro sophisticated netFu rcy not 'e c as cencervative cP orioirolly inten& d for earlier deninnc. 7ttechrert 1 to this enclosure previder Ier ycur inforrraticn a lirt of infor M icP IT oucrte for which rcrponrer cou]d tx reedcd fer a proper essencrent cf the inpact of the cevity dif ferentiel prercure en the desion tocauccy cf the vencel support cysten for a pov:er plant.

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for derien purpocer, however, ePrect in typical caser O . 9he to rccontrolliry tne cere sorrci.

1c000 '<s th the soterno, airecroot ie1 nrrvcorec ecr o=r

<>to=e c rociet<a ne irterne11y ce,ceree<a 3ccdn ere due to e cocentery diffCrent10} preErcrr UhiC!! Ir Ca.lCulOlCd to 0XiCl OCTOEU t.l.e Core l'ar rel I when t he orernure in t.he reactor annular reoion betreen ti e core l'arre]

and verrel vall ir, the vicinity of tJw ruptured pipe ir rFruved to rapidly decrerne to th: Faturation pressort of the pritrary cco.1/nt due to the outf]ow of water. Althcunh tl e deprccrurization vo /c trave.1D repidJy croond the eOre 10rre], llRre 1:. P f j ni l.D periO3 ef tire during WhiCll thO pref'Eure in i thr enrolar r< cier er r:o:ite the ! rerd: JocalJon .ic actuacd to rercin at, or. 1 nChr, lho Or$0inal rCTCtcr Operality! p ref:Su l e . Th u'3, t rFurient PflyrT5etriCf.)

for ces el e everted en the core berrel tnd the versel we)) which ult ie ntely reru.l t in ttanniert ]ccdr co the ':Urport syct ers. Thece are t.he load which WCI C urderefit iF O!( O Fy t h*.' 3 5 C(!nrOO Or50$nUl.ly repOlliFO lhiD ]lehler iPd whj ch r ay l e undore:~.t iret ed in ot.her cener . They are therefore cf cencric .

Concerft to {hD f(F((. /!L6titt:nt' 2 to lh.iS enClerDre l'rr.Y.idC0 for your .

inforimt. ion a lict of jr(ortwtien recuertn f er which rcrperror wou]d le nceded for a prerer cerer rrent of the inpcct that the versel ir t erre) differential precrure, in conieretier eith lie ather concurrent Joa?r, could have on the d lan cdcou<cy of tFe rulfort cyc t ei%

3D t h ?l there Die CChrideralilD di f f erer:CC in th> reDCtCL DU[ port CYSLUF dcGinriE for VPricU: ficililitr ppd prCdfihly jn (le [frion UProiUr proVid(d -

hy { }'e (US j aPel; r f ( s } dt. t fECilitiOr, lhO ut.derefitiral.i(P cf t l' Ore "di f f er--

Cut 503 pit" u r P " l f. . ' ' r " C ' ' 01 ray not te"u.lt in O det er'; j rct iOP t!'Ot {he Pd( Our ?y of lia V( ! E t } r:. EO) t r \Ti & Ior a fl.cGifjC Il Ci l ii y iU OutfliCP-O Ed 1 } O . Si nt.N .l eC /r l. IL j lui UG jn Ll<e . reel r , , Or t l IruJh Fr p3artiC defCrFDt.iOP) du not rccernariiv Jet to the f ailure of th; reimper t: rn cn jntecra.1 syctc'r, ll!UJ t rN li re: * ]if i!i < rCrclot vcCre] tot ien pr c'?j(C d t het ro f ur t.hc r significant cen. o vr ecc. Uou]d erm an:1 t h> ernroercy c/ ie coolir,a rycters (IT( u ) v: u]d l e ch i c t e ; f r for r t hei r c'c':.ico f unct ionn . '

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ATTAC;i.1ENT 1 CONTAINMENT SYSTEMS BRN;0! -

,P1 QUEST FOR ADDITIONAL INFORMATION In the unlikely event of a pipe rupture.inside major component subccmpartuents, the initial blowdown transient would lead to non-uniform pressure loadings on both the structures and enclosed compcnents. To assure the integrity of those design features, we, re, quest that you perforn a compartment multi-node pressure response analysis to provide the following information: ,

(a) The results of analysen of the dif ferential pressures resulting from hr;l leg and cold leg (pump suction and discharge) recciar cos>lant system pipe ruptures within the reactor cavity and_ pipe penetrations.

(b) D2 scribe the nodali7.ation sensitivity study performed to determine the minimum number of volu.te nodes required to conservatively O pre m t tne a -imum nrossure wiu,in the reactor cavity. The nc kliation sensitivity study should include consideration of spatial pressure variation; e.g., pressure variations circumferentially, axially and radially within the reactor cavity.

(c) Provida e schematic drawing showing the nodalization of the reactor cavity. Provide a tabulaLion of the nodal net free volumes and interconnecting flud path areas.

(d) Provide sufficiently detailed plan and section drawings for several views showing the arrangement of the reactor cavity structure, reactor vessel, piping, and other major obstructions, and vent areas, to pernit verification of the reactor cavity n,odalization and vent l oca tions . -

O w rrovide and su8tify tne hreaa type end area used in each anclysis.

. . t (

gy' O (f) Provide and Justify va1ues or vont loss coefficients and/or triction factors used to calculate flow between nodal volunos. When a loss coefficient consists of more than one component, identify each component, its value and the flow area at which the loss coefficient c

applies.

(

(g)

Discuss the manner in which movable obstructions to vent flow (such as insulation, ducting, plugs, and seals) were treeted. Provide analytical justification for the removal of such items to obtain vent  ;

area. Provide justification that vent areas will not be partially or cc:apletely plugged by displaced objects.

(h) Provide a table of bicadci:n mass flow rate arid energy release rate as a function of time for the reactor cavity design basis accident.

(i) Graphically <.how the pressure (psin) and differential pressure (psi) rc<; > ues as functions o't tinu for each' node. Discuss the basis for estehluhing the di f f erential pressures.

(j) Provi& the pech calculated differential pressure and tine of pech pressure for each node, and the design differential pressure (s) for the reactor cavi ty. Discuss whether the design differential pressure is uniformly applied to the reactor cavity or whether it is spatially varied. (Standard Review Plan 6.2.1.2, Subcompartn.ent Analysis attached, provides additional guidance in establishing acceptable design values, for determining the acceptability of the calculated results. )

i O .

1 U.S. MUCLEAR REGULATORY C0uiMISG10N rehnnry, INS

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l SF.LTION 6.2.1.2 SLBCOT/6T'W ANAL.YS!$

.m_._.l_b f_P E S P_O N S I C l u_T I E S_ ,

I Primry - Containvnt Systus f! ranch (CSB)

Secondary - Mechanical hgineerira Branch (ts)

Core Perfor. ance f; ranch (Cf B)

Auxiliery nd Pow tr Ccnver; ion Syste% f ranch (MCSB)

I. AWAS Of REVID.

The CS', revion the infore stion Drct,0ntec by the applic arit in the saf ety caly31s report concerning the d :terrin.ition of the dni;n dif f orc nt ia l ;te ,sure vc Net, i caouira :nt %. ,

compart. Nots. A wtcon.partmat is d fined as any ful!:, er partially orclostd volure within the priary co-tairmert tha t hNses high cnergy piping v.f wenld limit tb flyI of fluid to th y rain conta f r. cant volwe in the ev0nt of a postull t(c pipe rupturo within thi<. valu y l ' fr.t., . m ., r - puis ,tsid <

s'. 11 ; . 9. i' > < 'ts-

., feik q a pin ropture .a thir. thn vala:,a 1his prr so'< tr,msi n t pro ' s ., i prem differential a c ru s U'e wa l l s o f t he sukog arte mt .iich reaches * , p iir.m valur tewrally within tM f irst secon ' o f ter ble@,in be pins The i. g nituda of W reak value b = function of v:veral para A rs, .thich inM blwd in ra s s a nd es ;;j relene ra te , s M.cerb 'n t scitc< not a rf 3, inf vont flca i;;;havior. A transi'ot Li f f erc n t ial p*x ' wr e rc 'fm ma l) :-. ,haa l d , arm id s fcr ,eco sau ca m rtment or croup of sub paments that r :ts t h <- + defritien, ihr l'i i v ws 1 m. l u es the i m e i n ',.. h i c h t h e Em,5  : nd enorgy icleisc cate into the laa t

( F;..r! t .,t t.ece det tr.> ind. ' Aal ia tion of sLbc0N art a ts , sute p r tra t , cr.t f lm, behwin ,

'.nd wt w ;.a r tr.cnt dcs ip pru sure r argins. Inis includ", a car dirated revica effori P th" CFB. it c CW ii respnsible for the ad0gnty of the blc..h3 r:odel.

Ita CSS ,eviS of i k r-ns anJ energv releese rates inclu h s the tasis for the selectico of .

the pip.- Meak s ilt and location within cach subcorpartn.nt containiro > high cnergy lir.e and the calytic al procedure for predittir.9 the short-te r mass.and enn gy releJSc rates.

The I'W miew of t e subcccparta nt medcl includes the tasis for the no::ali7ation sitbin each .'

mpartc.nt, tM initial therr:J.,0c. tic conditicm within cach surep:rtNot, the ne'ure of each ve. t f lce.; path tensidcred, cod th( ex ten t of en trait,:, r,t M wed in the w.nt flow >ixture, rh? revicw Uy also include an analysis ei thti dyna ,ic W rac teri!,t ics o f cm p nc its, such e s decrs, lilevout panels, or san'i plugs , tha t r.ust mn cr le rrowd to USNBC STANDACD DEViEW PL A!J p

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provide a vent fic.i path, and the n ethods an i results of corpontnts tr sts _perfon ed to demnstrate the velidity cf these analyses. The culytical procedure to determine the loss coefficicots for cach vent flow path and to i redict the vent wss flow rates, including flow correlation , uwd to cc rpute sonic and sute.onic flow ccoditions within a vent, is re-viewed. The dr.ign prese.ure chosen (cr cach subcci/psrtecnt is also reviewed. On r eques t f rom the AFC59, the CSB evaluate.; or perfccms pressure response u.alysos for sub;omp3rtments outside centa in.m:n t.

lhe MEB is respansib h fc, .evicaing the acceptability of the brak locations chosen and of the desic;n criteria and prs isicas, and rethods trployed to Jubtify liriited pipe ration f or brech ps!.tulatt d to occur ws: Sin sub:ccpart:nants (See Standu d Review plan 3.6.2),

r J!. ACCEPf W E CR;iE.U A

1. Tne r.ub~ m;a rt .L analysis sWld inw;cra to the follrair,g anu9ticos: >

e. Creak locatice ar.d types J.mid b: chosen ncordirc to TZgulatory Guide 1.45 for e

H ' r '- w. t s i rd, i dn c: 1 3irc:;Pt mi tn L< mc5 Te(I nical Pcsitic* 'd8 3-1 (3rt ni. s * '+ m<h d P_, H. 3. 6. ?) t r. %. x. irteents w isid! cnM a ir.c i e An actcpuble al terra t e p acedure is to postulate a circraferential double-endeel rupture of each high pressre systtm pir4 in the subtownrtmnt.

b. Of se,eral brc:b patulettd en the basis of a, above, th ' br.uk seltcled as the refer < < ;e tese f or sud ;Nrte ent analysis should yield tha 1.ighest r: ass and encrgy release retu., consis tent with the criterie for establishing the tireak O - - " -

ine initial pi':nt epera tir-p con iitions, such as pressure, tecperatt;re, eter in.cntcry, and p; er le,11, shauld be selected to yield the r eirtu a blaa k.in

( nodi t icn a IN sel& ted 0, ?ratire ce ditions will L' acceptoble if it can La m.n tM t a th um of each rarar ater wald n esult in c less severe t lo th.,n profi!.

2. fue analyt tr al pprmch used t'o cocpute the crass and etercy release profile will be a n e; te ; i f to th t hi. (c e;,ater progrmi and voluo radir.g of the piping sys tnt ar; s i d iar to nne of an apprce cd n ergen;y core coaling syste.c, (ECCS) analysis. The n nfe, e.a.ir cr that are cuo ently attertel>1e include MTAN-VI (Ref N), CRAri-li c t . 23), Ll' T LM& O (Re f. 2 5), u e RLLN3 (rnf. Pl), urun a fica r:ultiplier of 1.0 is used ith the 0;mliable choke.' fit , correl a ti on. An altern ue apprm ch, uhh.h is also acceptaMe, is la rssume a (cr6 tent blNdmin ptofile v3ir.g the initial ce sdi tit t , oith an ciccptchie cWid fica correle. tion, ' 'n f EI AP-4 is accepted t,y t he s ta f f a s a op;raticul ECL5 Mcad7.m rode, it will b> mptable for s' ucempart-c'ent an alyses.

3. The initial a t ospherir conditiers within ' " ' e c "p3 rtan t should be selec ted to rm.-

imize (Le i siultant dificrential pressure. /n acceptMe whl ..culd be to assuro air a t th5 m ie.c allo.>iable temperc ture, uin hu a Osolute pres sure, ,'d zero percent rel-if the asttme) ini t ici c tma;pOric con h t ions di f fer fro these, the O

alive hualdi ty, selected values shoald b; jm.tif ied.

6.2.1,?-?

Another rJ>de) that is ulso actg t Sle, for a restriet<.d cle ci rub m artr'mt s , i n.

volves siglifying tha t ir , otl o. tlined < tove, i or Mi s Mc'el , t he ini tial e';.os-l' O phere within the sutrc0 y r t&nt l', r 3 doled ds a. hwc3 "29us mier-s tew: mi/ ture i.,i th an vuc e nsity edit elent to the dry nir nodM This a mroeb shcaid b trited te svLtompartuents th? t have cFei:e1 f ly.; within the vents. lia.ev e r , the idM;uicy o f this sii<plified r:a ial fcr 5ubco w rt nts havirig prir arily suhaic flow through the vr.nts hn rat been citablishet 4

Subcocar t~en t not'aliza tico sche s thould be chosen such that there is na substantial prenure w adic , m thin a roh,' i .e. , the radali n tion schea, should be verified by c sens iti /i ty s t udy it.J t inclui's inc reas int. the r,w ber of nada., ontil the pech cul-cola ted f rmsures comers to st all resul tan t c har, ius ,

f 5, if vent fla pitm m ~d d ich a e t.at ir din f ely cvailable a t th: tim of r i p. >

ro;, ' ' 4 , th? follcalm; cri'"rta apply

• If, y(n' u re,- ., ) ;

• t ,ty ;tj, 3 r i

, , , , 7 t. g j .; p g,. y .. , .g ) g i 6; e  ! i c, -

ilj'i i

of ira 7., W ,Jrl'u ' ,e s.,, u p m to pip rup tm M t) ,

lh" validi ty o f th enaly:.is sh9;1d L:r supporud by experit.Nntal da tc or o

M t i rG pr g ra (

' w l'f ti pr01 osed c t th 2 canitruction perrit '.ta p that' vill

<,,;r* t h i ', 6

l f;i s

( ,

efterte of itinilts W t say L. pnN oted duri@ (M N,m .imt GM d n

^ "'

O ~ " ~ "

6. fica u u m ro p ajj f}c, path within tbc rabli2td t o partwnt i edd

+

1 ' a t- m , r . t m e i r, thrr.a1 equilibrice ,i:ith the euu wtien 0: *o na > a i: r. t . o eddition, the 'ciectrJ sent critical floa cor relation sr 't-m , f rv o i . d th resg.c t to evailable experir ntal data. Currently accept-sJ ,

itit: cal flw terrelations a n thu "frict ionless ru.>df uith a cultiplier of 0I rm > r-ste-

r. i:s t u re t , and the therm 1 howtnPaus equilibrium nadel for a i r- s t - atm mix tui es

7. M r corstrx tion pcn it sty, a f actor of 1.4 she.uld b9 applice to th2 peh diffa tntia rrMsur e tel'ulated in a r arner fourJ u tertable to th" C59 for (F Sbh r s urb mt. Thc calculc %d r res vi e r ui tiplied tiy 1.4 shnid 1.0 considJrad th; dciign tre "ra. li t the cparatirg licen?-0 sta;;e, th7 pJ3k cultul A ld dif f orential pren urr Could not e'" 11 th< Gsica pre Mur' It is expected that tha p d calev-la ted d if f er en t-in l P reO 'o i-!Ill ral W substcotially dif ferent h am tha t of' the cons t r u( t ich H9rit st1 Hosevt r , ir;revec :nts in the enalytice1 ; chl5 or charms in in es.b;ilt sotw urtc.cnt ' Af af fect thz availnt,lo urgi III. REVi!W fe.; i L'Jf:E 5 i

lhe procedur< s dc scribed belo<: a re f ol icacd f or the wbcoc uru.cnt cnalysis rcvic.-f &

reviev"! 5 elect (

and c,phisizes r aterial fra these procd'em 's ray b ; propria te f or 6.2.1.2-3

, ~

l a pnt iculer case. Portiens of the reviet r.uy Li carried out on a generic Lacis or by adoptin the result! of previc is re.iews of plants with essentially the same subcompartrent and high prenure cipinj design, lhe CSB reviews the initial conditions selected for determining the rm s and crargy rclease rate to the subcotpn taents. Thc se valuu are cur;ared to the spectrw of allo,;able opera-ting conditions for tP plent. The (33 will asctrtain the adeluccy of tM assu. M conditicm, based cn this rr view.

The CSB confir, . With the EC the validity of the applicant's enalysis cf subce,rgettsants containing high energy line; and po..tule ted pip: tri '

locatiom, using elevation and plan c'rmdny, of the containt at sScaing the routin] of lines cenicinin; hir,h energy fluids. The CSC Ntterines that an arcpriate refeience case for sobrpartn 'at analysis ,

hcs t>cen identified. In tho event a pipe bred. other then a double-ended pipe rupture is postblittd by th0 applicant, th2 fG aill evaluate th: applicant 's jus ti fica tivo f or ds strnir.1 e lir,itred displacc.:snt pipe Lreg ,

The C% r y/ geforn ccW ir ratory draly , ,, of the blo.my. n ras and enyt.;, profiles within e sub o partcent. Th; analysis is d:"e using the 6 tim con uter progr (See b ference 21 f or a c'ncript ir e of thi; cc 4: parpose of tu analysis is to c :nfirn the predic-tion, t o: mv end ensern release ra t es 4; earir; in the safety onelnis report, ard to ccofi- >!

an e propriao Latak lc,.3 tion has (".cn conside ed ir this a.alysis lhe v,e of h * 'll cetim util tn ; !! ly; co puter cH W. Leen approe^d l y ilm s t a f f as O an v N7 'o' At th) tic , th" (SU uill repince ut u 3 with M /,p; for all i !  ; 1y:,e s The i th,

.nri v ncy cf th: in f orr e t ich i n t b. :,Jfety analysis report ryprding su h 't \ 01; ,

61nt creas, cnd vent resistencts, I f a s ,t.ca pb ro ant mus t rely on dso N ,.nl p els , ar Waival .nt d:vius to inc reat0 Vent breas, tne CSS revie.,s the eniiy3 s

,wa tes t t ry ;'rops that snLst an tiate thei r use, lhe CW reciews the 1,adaliid tion of each sub:cmpart&nt to deter:aine the edequacy of the calculatiaal ci.Jel. As n?cessary, C50 perform iterathe rodalization studies fod sub.

Comparto w c to confirm that sufficient nod:s ha e licen included in thu 'dcl.

The a n (ocpM es the initial sun or, a tent air pressum, temperature, c:ci humidity condi..

t i o m. t o t h>

triteria of 11, abMa, to c scre that conurvative ccr.ditier.s v:ere selected, Ihe CSis revices the baws, correintions, and cwnutei ccdes uicd ta predict subsonic and sonic vent floa t.ehnior and tM capability of the c0/e ta '7 del c; 7rc>nfole and un-coa.pressible f loa, lha bases should include cenarisons of' the correlations to bsth experimental data and recogniycd alterr. ate correlatie ,s that hwe l'eDn accepted by the staff, O

6.2,1, ? 4 1

( Usira the nodall/a tion of tath subce:n,2arO unt es specified in the saf ety enalysis report, t!,o CSB perforrs an91yses usir.] cne of several evai h.ble c'r puter pecyec ^. to e ternine the edequacy of the calculated ptuk dif fereati&l pressure. The coi;rfer prege r.m used will cyar.d upoa '.h set,cas a r to ,1t ui '-:r ra ! , e s , all .M thi fle., r _

a it tt '

p r( s tite, tht two progru , und b;' th:' CSB cre ret /-P3 (i.ef. 21) cr.J C0iIft PI-LT (W fs. 7, 8, and 9). A rulti-valo:e ersputer cadu is currcntly und.r develop rot. ,

At tht Construction permit stcy , the C50 will ascertain tha t the subcompartcent d; sign '

pressures in W H ep;u npriato rargins etove the calculated values, as given in II, abov d

IV. fVllt;MIC1 FIrijitm lhe tcnclusicns reached en r.c pletion of the t evies of this section ere : Tsented in Standatd P> vies ilen ' 0,?,1, V. .R. E_F,.D. .i el s The refen na for this plan ert thase listed in $t'andard Revica Plan 6,?.1, togetber with fa ..m ,

la. Pogula tory Gu ido 1.%, " Pro tec t ion /G; inst pip. Whip f re;ide t.cntairemnt,"

23, bl e- . <d h vic Pli n 3. 6. 7, % te n ,, o.a t i nn o f {,reak l ocation- and Djnv ic f.f t ect s

/v ' .d wi t h t he h.s t ulo ted Pu;,ture of Piping,' cro at tached i;ranc h h chnir.a l s P-

• , , ' iU 3- 1, "I o;,t ol n ie d Cree k and l < mgy t ou tion" in i-luit! S;.s t en Piping O' O. u.ta ir ,,t t

O 6.?,1.F-5

. . - . . . . . ... . . . . - - . - - - - - --,,-u,

\

i . .. .v y

.I i l 7 ATTAC M QT 2. . - - -

t s .b.E_C H Y._!.I.C__/t__E U.._C f il E F R I NG B P /J!CH 7

O 4 x

, Tw su rea imrm mmes

.s L I t n i \ i

% g i Pecer L enelyses have shm;n (r ht react.c pressure vessel sppports rany be ,3 subje:kd tet. previNpl[ undern s t, a t >d lateral loat's cader the coaditions h

.thatycZd exist if 'an instan tr.neous double ended break is poS L ' lated in i

5 t h e re <.n .ttor vessel told 1eg pipe at the vessel nozzle. It is therefore i

heces pry to reasv :s the cgNh ilit/ of the reactor conhnt systent whports M; td ]imit the calculated jatio, ci the rcmctor vessel during a phtalet,ed cold I

!On J,ru'.

1 x s

'11 lh T!! h0'in@. n .: r:C $ ' ' / t o U !. c. U r 0 hi .N Dr'Jwhili {'/ ih 3 L i ? qw"I

- 4 t

reUClOr COulci he brought S '1f(.ly tr a 'cul d r.i4t h; a n condi tj em ,

• 1 The follhilj i n f o ni;i t ion . recpiped rop par gg of g jgg (gg gg , ,

rense u or tnc rem <am'.a supports- .

1 0 l., m , % % d m.on , or m re m or supyor1 ys tm u r ts cien to U t he ge: 'try of all principle cle; an ts. rnd in terials of ri.in-6 b 'h. f} n

2. hec l j th0 dOtuil dOSign lODds used in the original desiC,D InalySCS Of

'd.e l ead or c.upnaris giving risgnia.de, direction of application and the

\ , ,

bDSin f or edrh lDi'd. /ilSO pr0V'ide Ch? Cal CUl) j/2d 'IraXiM'M S tre,s in ed1 pr in C i pl 0 CleD?nt Of 1,he support nvs 's and 't's.e corresponding allonable i

StreS'e . '

g f.

3. Provide the in fon:ttion rC4uested in 2 Acefu. the D supports con- .

9 sidering a pastulated -r bred at the cold lef Snzle In cl u'k a s ui ma ry a ss g

b e bnd y .iCO) D ' h #)(l [' C h. J 'g G}f]d g q d s' rj n ; jgg} r, 4 p g. . .{

g # --

short term prbssvr< differential, acQs j the core barrel i \doJbination ./

'l c'1 3

\ I

,j 1 ,

( .

V-

\

f ,

, a f A >

1. \

. l,i . ' i)

(

7 -,

O with all external loadings calculated to result from the required par. tu l a t e . This enaly5ir, should consid.r.

(0) limited displacement break areas where applicable (b) considera tion of fluid s tructure interactio.

(c) use of actual time dependent i'orcing function (d) reactor support s tiffness.

4. If the results of the anclyres required by 3 abv/e indicates loads leading to inelastic action in the reactor supports or displacements 5 exce:rdin<j previous da ;ign luiits oro ide an esaluatica of th:> folles;r y (a) Vield _ behavior (effeci:; of possible strain energy buildup) of the mterial used in the reactor support design and the effect on the load:,

5 t

!<onsmitted to thc reactor coolcut sys taa nnd the backup

'h uttures to which th? reactor coolcnt system supports are attached.

.p (b) adequacy of the reactor coolant systui pipir,9, control rod is's, steam generator and pump supports structurer surrounding the reactor coolant system, reactor internals and ECCS piping -

to assure that the reactor can be safely brought to cold shutdc in.

3 t

O

.