ML20058D647

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Irradiation of Four 17x17 Mark-BW Lead Assemblies in Trojan Cycle 13 Design Rept
ML20058D647
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 12/31/1989
From:
BABCOCK & WILCOX CO.
To:
Shared Package
ML20058D639 List:
References
BAW-2098, NUDOCS 9011060193
Download: ML20058D647 (38)
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Page 28 of-65 Page 1 of 38 e N L' [ pe 1 mmmm a mmu, cr_z u -onsign ampart-n 4 1 ff L-u 1 f.. sn m s/ms ~ l .::+':-" B&W FuelCompany An American Company With

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a-i l-l l \\ 9011060193 901029 PDR ADOCK 05000344 i P PDC .ti

-Li - Trojan Nuclear Plant Document Control Desk. Docket 50-344 October 29, 1990 License NPF-l' Attachment TI Page 29 of 65 Page 2 of 38 [1 llNf-2098 h e 1989 i .i. 'c. 4 IRIUGAMX QF FCOR 17x17 MMtK-15f IZhD a.; Asmetrm IN 5t3DN, CYC213 -Design *mr g: -t l, =, t, in-1 h k-' 1-i l l i. BEN IEL CDEhNY g l-P.O.- BcK.10935 1 L Iti h y,.VLeinia 24506-0935 j: 8 \\' t' lI j i I i I 1 l

Trojan Nuclear Plant Document contror Yesl Docket.50-344-' October 29, 1990 License NPF Page 30 p,gp 3,j 33 t;'. . ( Q2MNIS ,L Page i

1. NN 1

l.

2. StMcGE 2

l l.

3. MECHANICAL DESIGN 4

.c 3.1. Ibal A=M1y Design F I; !=. 4 l3 3.2. Pretst:ype ' Dest E, 6 R., 3.3. Ital Assembly namitys Ev=1,wm 7 j, . 3.4. Ibel Assembly TW4*m Wen 10 i 3.5.. Ebel Rcti Design HD 10 3.6. Ibel Rcxi Design Evaltem 2.1. 4 'IEEROJMDIIIADIIC 25L7 29 4.1. Design Evmitem 29 i s .,'l 4.2. Testin:f arzi VMf4% 31. l 5 NOCIZAR DESIGN. 32 l. '6. E7AIIRTIN OF DHTERENCIS 33 1; t l:

7. REFERENCES 34 1,.

1 List of Tablas t l-Thble 1. %Fsc:n of Maric-IN,' W SID arti 0FA Mm 14-1- \\ l 1 :: b, l 1 l l l-e L

Document Control Desk Trojan Nuclear Plant October 29, 1990 Docket.50-344' Attachment [ License'NPF-1= Page 31 of 65 Page 4 of 38 }g.,.; List of Figures . Figure t Figure 1 - naal Assembly outiina.............................. 16 ( Figure 2 - Z1W Irwiata Spcar Grid.................. 17 - i ? .e..e..e...........ee.......... 18 - i. Figure ' 4 - Grid Restraint Systan.............................. 19 b Figura 5 - Top Dxi Spacer Grid................................ 20 Figura 6 - Batt:In Dzi Spacer Grid............................. 21 Figure Typica.t Bettcza Netzle Assembly.................... 22 Figure 8 - Dabris Filtar Bcda Patterns........................ 23 L. Figure 9 - Typical. Top Nozzla Assembly........................ 24 i r Figure 10 -- Guida thinble to 'Ibp Nozzla M+nr+=artt............ 25 h Figura 11 - Guida 34*1= to Bottzan Nozzla AW....... 26 = 7 rigura 12 - amt nai.......................................... 27 c Figure 13.- aml kxi Pauur History, IER vs Burmp............. 28 7 ^ ? e N' h M W I

Document Cont rol Desk i-Trojan Nuclear Plant October 29, 1990 Docket 50-344 Attachment .p License NPF Page 32 of 65 fI Page 5 of 38 ?, 6 .t' 2HIEEDCI' Ear Pbur Max:k-lpt-lead====h14a= - (IAs) w3.1L ba izzadiatai in the '!30T. AN reactor... s -f duritzy foal eyeLas 13,14 and 15. '! bema $2:e leu:$c-sit IAs are standard nj .l eM,=1 leark-Bit fual ad14== with axial blankst fuel reds. '!ba '!30T. AN. reacter is a "I

== designed reactne 7-- a bf Par *M General Electric n

--.f.

'Iba foal i w 47 Az-TH: ann consists of 193 foal

=====h14a=, each with a 17 x 17 astrix af fbaL zuds. '!ba cuzzant foal

=====h14== are tha ~~~ 'i -f== Standard. Iset:icum (STD). Startirty with cycla - 13. tha. fresh foal hatches Iceded. have hai ancial blanhat fuel reds. t '!his w dame-Hban the. Mark-Bit fuel ammeubly desigrr and evaluntas the affects of T---- W '!3C2AN with, four MarkHBt foal me==mh14mm in the STD . 1 cars.. '!ba avaluation concludes that.e ef'mer arsi.r ^ - s will noe 1 ha adversely affected. i e l* .\\ u A I g'& an - g# i N. 4 4 O ~ h: s 1

Document Control Desk Trojan Nuclear Plant Oct ober 29 1990 Docket 50-344 Attachment License NPF-1 g Page 33 of 65 Page 6 of 38 (*) 1 S399Rf [ 'Ihm four 17x17 Mark-E 'ual ="1ias to be insanad in 3CJAN are designed L to be fully emmedble with tbs Westimha== fuel a-li== M compnsa the balanca of the cara. Erf fann:res of the.%rk-N IA can be dividad into thraa groups: (1) fann:res standard an other BWFC-designed faal====*14a=, (2) unique feat =res ir g tad into the Madt-N far c:2:patibility with a cera contaAnang WestirM== designed fuel, and (3) features unique tc the Mark-W. dw fanc: ras that are te 4-M cn cut:ent. pr e v-~ %1 a===*1ima irx:luda: i -Keyable spacer grids [ -Locking cup type.6 top nazrla. i 4 -Zir=alay i r=*4 ata =re=" gr:.ds. -Irr=*4 ata spacer grids not am* to the guida *5i+1as. p. -Axial blankets of nat:ral Uranium cr1 arch and cf tua ac*."1Va fUal Stack. -Annealed Zilusicy guida thimbles. I -Fuel red on lower gr.llaga. -Tap and bott:za plenum spr:gs in fuel red melies ^ otbar featmas have been umru..i d into the Mark-N fuel a==mbly design s for Westirgha== r==r . To a larga extant, thmaa featuras wara adapted for the Mark-N frran the aparating Wanca and *micqy base dev=le m by Nuclear E\\1al Irrtustries (NFI) a SWFC licansaa in supplying reload fuel 3' for MP==-type reactcrs in Jagan. Tbase feat:res irr-itria: -T.maf hm1Mm41 spng -Camig regien in guida thimbles. -Mixing vanas en spacer grids. er gnd farrules. s Soma. feat:.=ws are uniqua to the Mark-s design, but are not raquared for compaedkil dty with Westimhe== etamirjned reactor =:. 'Ihase faauzens are: i -Int,-._-M ata spacer grid rast:alnt systam. -Debns Insistant battan nozrla. Estical strL*" 11 analyses have shown that the Mark-N IAs will aparata in a safe and adequata manner in UCBN cycles 13,14 arzi 15. 'Ita lead 9' a==amh14mm are mmnatible with the balanca of tbn S'ID====hliam ir==. C ad %=a. interfacas and cr:mpatibility witti barxiling =aH=='it bas baan shown by analyses and by hwaticn. 'Iha faal wesely serra M skalaten arxi fuel rrxds will :muntain integrity during all condition I and II y evanes. F.ither a mixed sm/s c=re er an all wn = cars will have MamLata ::rL".;u dur:.ng I.CCA, Seismic or end'ined events. O i 2 im-mmi

Trojan.-Nucicar Plant Document Control Desk Docket.50-344 October 29, 1990 - License-NPF-1 Attachment 1 Page 34 of-65 .. i., Page 7 of 38 ' m cycia 2s aan aparata anfaly with axe m IAs.h-bye-14'" stalysis dameras Armlymus abow that r g-com ptumm drop, hys-14" lift fbrams and 'hm=1 margins are not j-NN of..the IAs. Ikmover, in ca:dar to ensaa that full stardard naal. Asambly aata thmenaleg-_.i4,- m-- _Meulah W the Mast &spheuma STMen:lt-m IA w %<,,i' the M-L c W $2al ely peaking abaald zumain 3 Mwi below the =11,--w1. cza oe peak '**% cycle 13. / - L. e j. 'ma n-1='- *4r analysis abows that the ade-m naal w14-= arm --1,y 44-,ed,--i_ to the. sm assembl.ias tW M1= and have .= l (". My the saem R/tr rat:io. Sm nastzmic d-- t

=*4~ of the Mark-u y and sm ae14== will.ha =4=41=-vith. =14F difemrurca dua to the anrictament credit far usirst zittalay gcdds an the mz$c-W d--4 fi[

and the Region 15 'Mastirsgbausa assemblias are cetwih to be7 'ma IAs h =hla with respect to nuciaer ;- - - - - - 9: .Y k. l4 (, \\f n Y e P 79 L l i o r 3 4

Tvojan Nuclear Plant Document Control Desk Docket 50-344 October 29, 1990 License NPF. 1 Attachment t Page 35 of 65 Page 8 of 38 9

3. WECNANICE WCf b'

3.1. Nel :tssetiv Desic:n "me--it _ien 2a Mark-E faal a==mrely (Figure 1) is a 17x17, stardait lat ica, 7.ircalcy spacer gnd fual====+1y designed for use in Wes :.rryhm== designed

e l

react =rs. 2.a taal aa=+1y irms. stas meny starrint SEC design feat:1res wtule meu.=tsinim ccupa*Niitf vl*.h the Westirmima rence.cr intea als arri resident f.:a1 = eel 4 es. 'Iba basic da=,ejn paramatars of the Mark-54 are Wred to thcasa cf the standard arri CFA West:.I5 a= 17x17 designs (Table 5 i

1). De.Tz les, the nc=le am

--W and the erzi spam grids are based en ;:reven NT.: designs c=rently in apeation in Westirr;5mL==-desigrsd reacters in a w. Se guida thl:tle top sec*% and dai@ diamatars, t.% 'g inst:::*amant sheath diameter, and the fuel :cd cu~sida diamatar are the same as the standard 17x17 Westimm== design. 'Iba faal red design has been developed based =n starxiard NFC ami r.ds applied to the West::.nghcusa starriard cx:tsida <-!= Ming diamatar. Ba unigaa fea* ares of the Mark-N faal assembly design include the 21:=alcy in*=rmM4ata spacer gnd, the spacar gr::.d restr:unt system, arri the use of ?.ircaloy spacar gnds with the standard lattica design. De fuel a==amhly c=nsists of 264 faal ::ds, 24 guida thi:2les, arri crie inst ": mar:: sheath in a 17x17 square array. Da guide thi=cles previda guWnca fcr - d rtri !csertien and are ar '<--M to ne::les at the *wp arxi battrm of the taal====+1y arxi to the bottom erri spacer gnd to form the str" & va.L skalatan. A rene=H diameter sectica at the ucc::n of tha - [~ guida thi=blea deceleratas the c::rr=:e1 red 2-1ia= during tnps. Be L. instrument sheath nr-mpias the carrear lattice ;xasition arri provides guidanca and protect.icn fcr the incere inst =.:montation a===+1ies. ma top nez la assembly c=nts2ns the fuel a===mhly hn1M~n spsgs arri is amM to the guide thi=cles by removable ruts and Iceki xJ cups. De bec:=m nczzle is attached to the guida ~5,eles by 1:cd.ts which are macnarthl'y capr.ared by tack walding. Ma taal red arxi guida rhimble spac:q is maintained alcrxy -l the 1erxJeh of the ammmhly by six 21==ilcy irrW4ata spacar grids. Irrea* wid *ta Teacar Grids 2a Zircalcy inem-4ata spacer grid design shc:wn in Figures 2 and 3 is =4*4 h to the 5fEC 15x15 Mark-E spacer gnd design. With the Marx-E as the design basis, mix:ng vanes were added and the dimensicns were adjustad y to opri'-1 a the hytt::3ulic and mechanical parfcrmarx:a for Westin; house-design a mi % icns. Sa proven da=1nn feat =es of the Mark-E design have been t ihr.u.d.ad into the Mark-E design. ma spacar gnds are kayable allowing 1 fcr sc=st=t free irrartien fcr mest fael reds during faal burrile a==ar~'ly. Generous lead in feat =es together with an i:: groved cc::ner design are en=--M to exhibit W %nt handl.ing charactarr sticc. 2e in'a" mar" n*J spacer gnds are free to fc11cw the fael : ds early in life as they g::w due to 1.%::.cn. Sis feat =e virtually al 4-"natas axul 1:_crien ferces suspected cf wu _.buting to fael :::d bcw. m E 4 E..

_ Trojan Nuclear Plant-Document Control Desk Docket 50-344 October 29, 1990 y License NPP-i; Attachment Page 3 g g5cf 38 f i op . crid 'tann= aint svstam. 2a =pa grid ::cvement is limitmi by a unique c;id :sse:: sine system, which '1 is shcun in sc:bamatic for:o cra Figure 2. me Mr.A-aw irra-=d4=ta =na-

grd.d rast:raint system is identical in functir.2 *w the pzwan Mark-BZ h

. h systam.. ma irr==-44=ta spacer geh are alls 3=d to follcw the c . fuel rexis as they gr:w due to irr=d4=edm until but: sap levels buve significarrely r=1=* the Zircaloy spacar grids. At this bar:32p level, *Ja br===d4=ta spacer grids curreact rigid stops to peuvent furtbar axial

'avument. 2a stcpa are shcrt.h or farrules attachaf to twelve guida 1

tLMlas arxi the inst =ument sheath. Above each ifram=Hiata spacar grid are farrules resistance waldad 'a twelve guida *J22mbles arri the instrument sbaath. x mars is also ana ferrule at*mehad to the instrument sheath balcw e . g,. aach irram=d4=ta spacer grid to prevent dcunward maticrt. 2a :sstraining ' guide thi: la locations =are abcun crt Figurs 4. [,I (

End sn=c=* ar a=.

d 2m top and bott::xn Incanal grids of the Mark-BR 17x17 fuel a===nhly are the H, sama as tha 17x17 Inccnal grids of the standard NFI foal des 2gn. 2a grids' l-

are kayable and empicy the same metbcd of fuel ::td su@cre as the standard l

3GC spacer grids, saa figures 5 arzi 6 for the basic configuration and . method of ae*= ' = m. ,1 W s Fi1*=* k h Nor-la. ~ ~ ' 2a 304L SS bott::xn noz la cz:n1'4r-n+de is shown in Figura 7. To r.a; tha' fuel reds frca damage caused by,*hle debris in the systen, the bottom rxaz=la acts as'a filter. mis debehs resistant bot:2a nozzla sbcwn

in Figure 8 has a large numt:ar of saali halan to allcw for W=w ;====g=.

Sama small bolas - f.iltar cue and r.- p====g= of debris which is larga !z ..ancugh to;baccans w@ by the spacer grids'and cause fretting fantna dua to.ficw-irrhrwi vil:raticri. IL - Ibn Nozzle. li 2a top nc==la shcun in Figure' 9 is d==iM tc matcf2 tha'intarfaces of the-standard y design. 2a matarial, consteru arxi general design - i h configuraticn are based an the NFI 17x17: design.- 2a tcp nozzla prev 2das ccmqsaedki' 4ty with cont =cl +w, fuel harv47 % aq"4==nt an:1the required hniddmn f=r=a to prevent fuel.a===mhly lift.- 2a top noz:la may-mass.ly be rancved tr::m the fual a===nhty by remota t= clin:J to allcw raccnstit:: icn of the fuel a===mbly. 5 1 - - - + -- a w = -n

Trojan Nuclear Plant Document Control Desk Docket 50-344 October 29, 1990 License NPF-1 At t ac hmen t Page 37 of 65 Page 10 of 38 A helddown s;::nn;r set ude up cf four rL. '.J.ade leaf spr.rs;s prev 2/ms the hn1Wt fc::ce. ':he Mi% spws are designed to ac- - Sta t.*a different:al tha'-mi expansicri betwaan the fuel a===mhly and the c'.ra internals and i=sdistian growth. 'Iba M1% spr.n; design is 'acM cn proven NI"I designs in use in Japan. ':he fuel ^===mbly M1hn @x;s provida adeq.2ata holddewn m=hility *m kamp the fuel a==ambi % in ecntact with the 1cuar c=re platt th&-*vsm the design life under all ASME C:rxdition 7. and I" events except pump cw m --i. ':ba *q nc::la providas positive rutarrdm cf the Mihn spx; in casa of the very miik=1y event cf spt:1g bredcacia. Guide '!M bles m.fd _ row.= d. 3:be. y' The dian-ca=s cf the Mark-i54 gtude t!u:tbles are identical to ttx:sa of the Westin;hcusa designs at the upper and dashp::t sections. ':ba material used far the guida and instrument tubes is annealed Zir=alcy-4 alley with mechanical prepa~ies cbcaan to achieve 1cw irradiation gr::wth ratas while maantaulirxy a% *1e stress margins. 1 ~ Miscellanecus Dar s. Atana 6. 'Iha no::le att:ach:nant designs are shewn in Figt ens 10 arxi 11. Tha aW -- J designs are identical to Phnas c 6 r.udy in usa en NFI f.:al f=r Westi. W m,= W plants in Japan. 3.2 oret. me est-A - m A r.-Lype Mar:k-154 fuel====mbly was *aHr-Stai usux; apaem gnds si ad to =4= late the and of life condi+%. A w t-ive *Jst prg ram was enw4w*=d to cham.anza arxi venfy the performance cf the design. Tba fuel a===mbly has been h&1%11y charactari ad by prinssura drop and spacer grid '==mv Deppler v=1+m= tar tasts. 56-1 ct:aractanzat:cn tasting included f.:a1 a===mbly 2nquency and d==49, fuel===amhly st-'*Sess, space.r g=.d stiffness and c.y.L tasts, guida t!nmbla bucklig, and for=a v:s deflec.icn tasts of other mi=~11^nacus mur.-ut=. 'Iba rWst21ts T ua the c"2Lrac*"aW ?>rticn tests have baan liu.a.ru.aL.i into the var.'.'.cus analychl mr-r4=1= used to p fy the design. Design ver"%ti.:n tastury irv-hv4=d envL.w uwd. tastig and cel ro:1 W tasting at the B&W Amance Resear::h Cantar, and a fuel aamambly handling exar sa at the Catawba, Unit 2 sita. The envi ---ui d.*as*dng c=nsistad of av7=4*x; the f.:al a=vambly to reacter c=ndi* dens cf "=T*ntura, pra==:- la arxi flew f=r twe 500 hour W e r4=. React =r CcnditiCns, excerr., iWiSticn, Were si:Lilated di:ll".Ixy tIMt *6. 7A Odal a===mbly exnibitad ne significant m.=icn er trusual weer. 'Ibe results from ex*ansive ::tiumic maaews of the spacar grid wm sites en the fuel r:cis have shown ne r+=s.sive wear after an initial " breaking in" pericd, even With the IElaxed p Otype spaCar gnds. Centr."'1 : d trip tast.ing ebm.rm.-atad that.he tnp *

  • for the Mark-E fuel a===mhl y are

'a= 1 ' within ac

.=1e ! Nts at all c=n11ticns.
'n-reactor, the sr:ubbing charactens-dcc of ex:.sti:x; w.d %=K.s are expected to 1:e the same with the Mark-N f.:al=='-nly as
  • hey are with the Westingncuse SID and CFA designs. Ms expected result is due to the dimensicnal ec=caribility cf 6

Trojan Nuclear Plant. Document Control Desk-Docket-50-344 October 29, 1990 License NPF-1 Attachment sI: Page 38 of 65 Page 11 of 38 ta >p the thre. fuel ama-ety %.

2. tr u w of the = w assemblias in.h Unit 1 suppen:t this

===r-*=d mault. Additionally, the prucceips faal -mbly was exerc:. sed in handling and storace agiipnarm o at the Catswt a, Unit 2 sita, demonstrating compatibflity with d-i*dcal i 127nrfaces. mis exarcise included funt **=1 tests with both a 'ccritrel Itzi

====mbly arsi a *hi n1a pity====mnly. 3 3 4.m1 a====b1v Demicin Evalume% 12e static and dynamic st=uct*xal charac ="4="% of the lead Mark-5f faal

=====h14== have baan datar=u.nsi analytically and exper..mantally and were found to be wi.ihle with the Westirnhm== :==idant fuel====nh14==. Sa ? Jr. Mark-54 lead====+'14== have 1:sen designed to maintain their 'nachanical design integrity emeugh 4 cycles of operatim. 3 Tba chara istics of the :ssident Wese%hm== SID fuel a-lies were d.h aned by tasting and ir-=<--dm. Four SID foal amamenh14mm to be loaded dato T14CLTAN were =h%=d to Sf7Cs LM }tv !aar Fabrication Plant (CNFP)--in Lyncthzrg Viginia.' Flcw tastig described in sectica 4.2 and a detailed dimensicnal-d v dm were ctreluctad. na follow:ng d4=-==im addressas the analysis used to verify tha st=uc,' mal adequacy - of the Mark-54 lead. foal a====hly for design 1*4mm and tha evaluaed~1 of. 'nachanical ccapa*4414ty bet: men the Mark-5f and the Westirnhm== :==4 d-n: fuel====nh1 i==. _, w 2 - P=1 Red crewth Gan 2a axial gaps bet:anen tha'tcp noz la arzi reactor cza:e platas and betuaan Y the top ruw-la arzi fuel rexi conservatively allcw PW4r dant margin to o; ~. i Wata the faal a===mh1y arid fual red gruwth to mar== burnups =-T-3 =d far tha. lead a===mh14==. Sa grewth rata for ttua Zircaloy guide tubes and fual remis will be different fr:m that of Westimbm== fuel an==mbliam. 2a differerx:e in grewth rates is due to tha'different mae=*dal w- =LM thana 1: arts receive as required in'5ffC==="if% ions. t

t. > x, -

wad 4=tice; growth of tha Zirealoy foal assembly and fuelireds was ; 4. cansarvatively estimated'usim both EP5tr and'5fFC Post Tv ad4=edm n Dasmination. (PII) data. Mose growth assumptions have been verified to ba - p* envalopirq. FII data an the Mark-Si IAs in 7t:1111re Unit 1 were used to shcw a that tha growth ratas===wned envelepa the =<-**'=1 measured grewth for both ,r' the foal rods arid the fual===-h11es. M 2 a ,=ri m s are easi i - - - e.a eitf.=ent m e -, expansian between tha fual'a===^1y and the ccra internals arrt 4*4= tion grewth. ta f'.al.====hly holddewn s= rings pr=vida adag:ata M1 damn ,+ .-*=h4'4ty to keep tha 'fual >=e='*r lies in c=ntact with the icwar c=re plata th W. the design life trder all' ASME Ccr diticn I and I'I events with tha I sd E 6

Trojan Nucicar. Plant . Document Control Desk __.____ _ Docket:50-344. October 29, 1990 M cense NPP-1 Attachment i Page 39 of 65 Page 12 of 38 J 9.-* ) i eXCaption of the puup ove, i t::=ansient.. Da h ladrun sc:i:Ep are da=47)ad.c talarata the ~=ih4' 4ty of a danacticri a=M ated with a faal z.c "5 assembly 14 *t,:ff far this condi+%1 arri prende acritact betwaan the taal i .p asaambly arxi the icwer ccra plata fc11cwing this transiant. 2a top nc:::la provides positive recantim of the ha1M~n spri:q in case of the vezy un1.ikely. avant of spring breakage. m t.. . n=1 ned m.xx 'rhere are several featuras af the Mark-N fuel a===hly design that improve its fuel red bcw performana. m ana features includa net rigidly a M m e the irr=v--M=ta g=~r grids to the guide thimbles arzt usi:q a =pame grid ~ y" - design in which :: cst spacar grid calls are kayable. A total of 44 out of 264-fuel rcds will ret be kayed due to the gr:ht restraint system hiryn. 2a net result is that the axial strains b-+=d in the c'uddm are r*+=d which trarm12tas to lower Itzi bow.. Simihrities between the Mark-N arri tha

h,.3 l ctbar NFC fuel designs (Mark-8,-ic,-C) permit the use of the red bow A

prediction correlation as prenantad in the. rett bow tcp,1 cal 6 (BAW-10147, Raf~1). Bis p has baan agreved by the NRC~for licensirq ..m previous SEFC faal. designs. i Stacar Grid t . r' ' The tcp and L m Irx:cnal gr:uis of the Mark-N faal assembly are the sama !es the 17x17 Inc=nal grids of the stardard NFI fuel design. As d 4 e===d in Secticri 3.1 tha. in"Wi=ta Zircaloy spacer grid design is simihe to tha 5fFC 15x15 Mar $c BZ spacer grid damign. 2a results !=czn the e =ria l tastdrq arxi analysis have shown that the Mark-N Zircaloy =pame grid design i, l providas =dS=ta d=iT.nargins.- 2a fuel rect res+--=inig farcas of tbs grid and kayirq +==- '=H.cs are nmarly 4d= *-d=1 to tbcam of the y - MFC Mark BZ desa.gn. Ma structural parfarnance of the grid under =i=4m and I.CCA leadings as dancribact balcw have shown that the Zirtaley =pa<9mv i grid peuvidas adequata design margins. Elevations'of the grid have baan - =lar =d to maxinua axial alignment with the grids of the adjacent fuel i assemblias. t { Pml ned P-et-tiner and want-- .p na Matk-BW faal====mh1y. has baan tasted in.We acw as described in L M dmn:3.2. Sare was nct indication of adversa fruttirxJ wear er pregressive waar'cf fuel.r:ds. l P=1 A=-1v st=.:c.zrs1 In*=m-ity 2a5 aal a==mmhly respensa.:ssultirq f::::m e.aimnic arxi I.CCA Mricanal leads f was analy ad usirg the tiria hist:=ry previdad by Pcrtlarri General Electric . C::Inpany fc:- the T jan plant. It was showri that the faal a===1y m+mical. ] intage_ty 'is mair::sined arri thus a ecclable gecmet=y is assured durrrxJ all l the seismic and T.CCA horizanal loads pos=:lataa fcr the t=jan reacrcr. Se s l ll 8

g-- l Trojan Nucicar Plant Docket 50-344 October 29 1990 l' g,g, ppp_g Attachment Page 40 of 65 s l (, l-Page 13 of 38 , w 4 lL i L' fumi====hly deflectim and grid inpact fcices respesas wrs datamined using the ganarm.1 g wW cutlined in BEW tcpical.w 3AN-10133P, Rev.1

1..

(Raf -2). Sli.s.%t has recaived the NHC ag:ruval for ruferenciq in i ,i licensing agilic:sticns. i-shimim and Man nim f M - l 22e Mark-W 1and fuel a==nhly is designed to :nnimain its dimensional armi struce.:ral int-g.ity when m2jected to rvwm=1 sh4TLM anc! harrilig 1 cads. Tb pr.,melude i== grid crashing failures resulting frcan excmssive -1==tw lands 4=- =4 by the an4Tiq ccrrtalnar, NFC has devole a mact2anical bracket that :matan4-11y limits the i=~M 1 cad.

t...

O: An analysis was parfar:ned to ensure the st::uce.:ral Wey of the Mark-N l ~ IAs undar the fellowig =h4T iq icads, r,

1. '4G' A: cal ac=aleration 2

'6G' Iataral acceleraticzi i

3. A max:. mum e'71m load cf 600 lbs.

i-The results of the analysis showed that the Mark-N fual a=mambly ani its campenerres v411' :naintain thair senacraral intagrity urrier the M4M i g-ah4 mig leads. Crush tasts have been -WM to ensure that the spacar i [ '- grict dimensional stability is saintained dur:ng rw=1 <hirig and handling ccriclitions.- summarias of the results aru providad below. a.ra k6 fuel c=1umn ;~i% and pcuvent the fcrzaticn of axial gaps. D1is L is done by =4e4May a pralcad cm the-fuel stack to czuntar f, accaleraticri Iceds Wtlicti cut occur duzdng ah4 mig ani h=M14g.. 'ma faal a===mbly is very unLikely to mariance the we== axial shipptw accaleration of '4G' used in the analysis. In the unlikaly i; event of a '4G' accelerata.cm, the fuel stack -~in'q arti the t l-praload will be maintained withui tolerancas. 1-l' i j

2. 22e taal :=ct will not slip through the spacar grids under the

( =W== axial ch4mtg loads. i%. l

3. 21s =racat grdds will maintain their senac::aral integrd.ty unsu-p tha =vw= lataral shimig loads, arxi urrier the =rmn cueing-

/ loads. L

4. Spacer grid soft st::ps are designed to maintain acceptable fuel red gr-p for=ms under the most adversa lataral <himig loads. Sia i

'6G' lataral ac=aleraticn used in the analysis is also very cansarvativa with respect to actual shippig c=rriiticns.. P L Mnemicil' tesien C=mtstibility Evaluatien i l~ i L The Mark-m taal ~~ahly design data are given in Table 1. In this table, '"'="4 *.s are :ade between both the Westin:7.cuse SID arxd tha CFA fuel *c 1 1: show design si-4' wties arri diffam. Figure 1 shows a Mark-W D se m mtic view. "he Mark-N fuel amamhly has the same cross-sectional l envalepo as the 17x17 Westingneuse fael a"anly. Matanical intaracticn 9 l

Trojan Nuclear Plant Document Control Desk Docket 50-344 October 29 1990 ,-[ . License NPF-1J Attachment i Page 41 of 65 Page la of 38 .i tm [ s'; batbleen fJai anemnh14mm is c nfined t0 the grid locaticrIs. Una g!"Ni alavaticris of the Mark-W foal assentaly at:21 the 17x17 Westirghause fuel

=====h1 y, mir>4 =i - dm the effe::ts of mechanical ard hydraulic incarmMcn cy bacWann a===nh1 d==. '!ba Mark-N fual assembly is designed to be f.:lly compatible with the standard Westimhm-17x17 Paal====+1y design, reac::ar im:az:nal incarfacas, taal handl.irg sxt w=14g $=-rt, and -r spent taal eh.g racks. Ccapatibility of the existing cent =cl w--h with the Mark-N dam'gn is assured by the simihrity of critical dimensions sucts as guide t"We locaticns with thema used in the Wes-imha== SID arzd ~CFA' designs.- i '!ba casupatibl.lity of the Mark-N foal a===nhly design with the plant intarfaces has baan demonst=ntad by the harxiling and iv-adiation of four i g. Mark-N IAs:in Mc2n.ra Unit 1 cycles 5 and 6. 'lha crzrpaHh414ty of the Mark-W design with r==ddarte SID fual a====h14== has been datarmined by dimensicinal iredm arzi mimimticin. Four raland SID fuel assemblias for '!N17AN wara measured for dimensional data at CNFP. A calculation based on the results of that inspection shcWs that the Mark-N will be ccupatible with tha :1asident S2D a===mh14==. l 3.4.-Fn=1 1==-nb1v Ir-wi4 at4 nn N- +Lrs 1-i '!ha Mark-N IAs in Pt:Glira Unit 1 are ncw in their sacand cycle of [ 4

  • 4=ticn..:A bc' tup of 15,300 Midd/mtc was achieved at the armi of cycle 5,

- the first cycle' of 16. Follow 2.ng the first cycle of 4W4= tion a post 4"-=di=tian examination - (PIE).was azde-=d. - Based at the results abtainact f:tzt.the PIE / the followirg conclimeris are m d. '!be m. I; performance trarmis of the IAs most or are envalaped by the das:Lgn D - - - - 7 % mada in the twiginal mechanical design analysis (rafarance 10.) 4 l '!hus the.criginal design martysns. ara still valid. Eac21 of the areas i = affect:uig perfor=lence is d4=~--! next.. Growth: '!ba grcwth of the fuel a===nh14a= is less than the design curva. l. . Ital rect grewth is less than -~4 Fuel rad growth is-i

E retajbly cn the a
dar of fuel====nhly growth. Spring sat was 1

slightly less than fuel a===*1y g=eweh. 'Ihis 4=14= that burnup i l Wh411 ties given in rufarraca 10' (the mac22anical design *m4=1) p' aru sH W valid arxi that the fuel a===mbly haldda41 force is not dec=mamm ! with avp'="1a. Scw: 'Iha bcw of the four IAs and cne.h Westirghnt= f.:al a===mbly Ii were data==ined. All of the IAs had less ennn how than tha

zuc. mum bcw of the Westinghouse==*-ahly.

In no casa is the bcw c=nsidenci to be larga enetx;h to effect harziling of the f.:a1 a ce-nkl y, nN' i L 10 l-

Document controf w h Trojan Nuc1 car Plant October 29, 1990 Docket 50-344 Attachment License NPF-1 ' p' Page 42 of 65 Page 15 of 38 ch: ids: me oxida thickness amasurmaarres were taken for the face,:ds f:xan casa assembly. Se enn anda +4h= was observed in span six. 'Iba veduas abealued are less than the limitirxy values used in analyses. L-In cycle 6 the IAs are in a:ritral ra:t lccations. Testirq pricar to cycle 6 sta cap V M

  • dad that ccritrel red det:p
  • dams vara within N limits

,U for the Mark-fH IAs, r-3.5 n=1 Mer! n==ien n== 'redm Sa fuel red design consists of cy11Wal- -4m t.t2 pellets contained in ' 'p{"- fuel pallats at anc21 erad cra the fuel stack are unda of natural. uranium, a Zircalcy-4 tube with and caps waldad at and and. A six-inch stack of f creating an ax:.a1 hlankat at each and of the fuel stack. Springs at both ends position tha' fuel stack within the r1=M4T and petwide rwn.ian E against axial gap fornst:.cri dur:rzy =hir45 and bandling. m e fuel red is p evacmanted and than 6**d"=d with h=1k= of high purity at high pressura l prior to seal weldinJ. Se high purity halita assures goed beat transfer across the pallace1=M4m gap. In addition, the high pressure fill gas prevents creep m1'=== of the faal red during the expecemd incera %.r.icri of the faal red.. A m: amantic of the. fuel red design is shown in Figura 12. Di f*arenr== : 1 L. 12e taal red design for the Mark-fN IAs is =4=4'=" to the. tse W== 17 X 17 fuel rad d=4==. Ma sain differences are: n u. A 'Th 4 Am.g r-1 mM4 g B. h1'ae fuel pallat cutsida dianstar j c Use of planum springs at both tzsp arxi bottcza ands (2a W=LedP== da=ign uses artly a top plarum sprim) L Itans A and B are sbcWn an Table 1.. Itam C can be seen cr1 Figure 12. l 3.6 Di=1 *er! Desien Evaluatim A series of analyses were performed an the Mark-fW IA fuel red design to p assure that its A--dcal re c-in-reactor would ba Qw. 2a p areas that were analyzed are: A.M=M4W Stress l 'B. M =M 4 g Strain C. M =M4_g Fatigue D. Crump 61'=== E. naal. rod grewth F. Shipping and haniling L: Items E and' F have been d4=~e==4 in the fuel -bly design evaluation secticn 3.3.- Itams A t.*nr: ugh D are d4=-==d in ~h folleving: 11 l e 1

Document Control Desk Tr'ojan Nucicar Plant' October 29, 1990 -Docket 50-344 Attachment n' License NPF-1-. Page 43 of 65 Page 16 of 38 7 4., ' v. n=1 wed c'=M4m se 'ma fuel rezi m'=M4N ms analyzed far the st= esses irrhrma during c::rsiition I and II operati=n. '!be ASME pressure vassal scrass intensity limits were used as goua1 % s. cansarvative values were used for <-1=ad4% t:hickness, cacida layer 5$4' Ar, external ptissure, incarnal foal reti pressura, differuntial tem.zra and univ -=d4= tad < '=Mdm yiald.6-ys. The analysis results shew that the unan e1= Mig stress intansities are y . within limits undar all leading car:11tions. Stress Analysis 9mmtPy f.\\ (h" Mindr3lE r,waim c::rsiiticn Stress Intansity Limit Margin % p Pri2 nary Ma::brana Sm 31 1-Pri2 nary Membrana + Banding 1.5 Sa 71 Pri2 nary Membrana

  • Banding 3.0 Sa 38

+ Sec&f s Sm as 2/3

  • mini 3:Lrn uni?'"=d4= tad yield aL=gO.

fy Psal Rod E =M4 m st--ain 'Ihm fuel ::ci was analyzact to datarmina the maram transient the fuel Itzi could experr.anca befers the transiant ein limit of it was M.- '!ba transient strain limit uses-<-1=M47 circumferarza d 4-. beform anci aftar-

a. linear beat rata (IER) transiant to deemembas tha strain. '!ba transient inc:rmasa requirai to exceed this limit was fbunci to be 16.8 Md/ft, which is nach greatar than the mamm= transiant the foal red is =-W i to experierx:a.-

l- .'Iha' faal x x:1.was also analyzed to dif-- % the mnv me burnup and transient IRR changa the fuel rtti.could spance witbcut W4N the total strain requL w.. of-1.42 %. -!ba total strain is datarminaci frczn the =num "' =M 4M can:warti ci:.uist...dal charzyn which occ:urs during irzzaru exposure a _ with a sign 4*de-=e raup at the 'ersi of =wrr=ww. At a =vi== rcxi average burnup of 60,000 Mid/mtU a mmmm IER of 19.6 Ma/ft would be required to w exceed the total strain limit. Pini Red c'=aa4 :'aticue '2a fuel reti was analyzed fcir the total fat:u: pia usage fact =r using the ASME pressure vassal c=da as a gn4d=14ria. A mvmn fatigua usage factor of 0.9 'is allowed. A fuel red life of 8 years is====rd. All pe==4kle c=ndition - I & II ever::s "q-N armi cna ccnditicn III ever:t are analy::ad to datar=ina ' the total fatigua' usage fact =r experr.ancaci by tha. t.:al :=ci <-' =M4'xy. conservative inp.I4 in tar::Is of < 1 =M4% thickness, cxide layer bti1* T, ex::arnal pressu:::n, intaznal fuel r:d pressure arxi differential *=merature ac:::ss the ci,M4 x; are assu:na:1. 'Iba results of the fatigue analysis shew a "*"" -fatigua usage fact:r of 0.35 which is <' O.9.

Trojan Nuclear' Plant Document Control Desk Docket 50-344 October 29,'1990 i License NPF-1 Attachment Page44ppf,6p7of38 y. .M N W4 PIlT C M11_ u '. b -{. '!be ftaal 2%Iis warm aralyzed ftr g elly usi2EJ mettacds S*14aart in referuruna-9 ard lo, ttan I-- -tve +=4=1= fte the c: rump ~11=== coda cac7 ard ttaa Mat:k.-Bf mechaniemi desigr1 +=i-=1 Unixxy e 1==w A==4rm iguts, a pause histcay was dar=r=4n=41ddcts enveloped an. past. ftast red ---_- im curaditicais.ftze the Trurjan plants. '!his paume history vitts appropriata c- = 4 *y factacs as abam in riguem u uns inpre:into tas.crapicare:He i TRct22. (Raf. 6) utlictL datazmined.the emuperature, ttaa pressure, ar:L the fast neutrest 21ur laval histney at the arse-se staat rats. Tttis histcay was impre-in cRw usinr ma===vutiva -wim

==nsicris. nm the e ae are the w a creep ~11==== point at the Marsc-ar ftaat reds was decernined to ha grancar-L- than 60,000 lett/metT. '!his burrasp emmeds tha nunciassa hr arxL exposurm , b@ ' ( the Mar $t-!K IAs are aupacted to Wane in '!3GAN, cycles 13,14 and 15. u l -. f ', L \\ _g. L< l. g 1 t 1 t P i k 1 1 9 0 .s l is i- .l I.. + 9- } 1 13 i

Trojan Nuclear Plant Document Control Deck Docket 50-344 October 29, 1990 1.icense NFF-1 Attechnent ap 4 f,pl8 of 38 Shtkla 1 i i j' Waczt of hz$t-5t, y Stzt. arti CFA Design 17x17 BEFC l'- Maz$t-Of 17x17 N 17x17]! l anal Ammautdy standard nml crA naal A-* h4 mt Ammm21y Damian Ammativ Desien i naal Assembly Isrzrth,'in. 159.8 159.8 159.8 naal Rcxi Iangrth, in. 151.500 151.630 151.630 l ll Assamtdy Dwelapa, in. s.425 8.426 8.426 '*-,-i.ible with 0:re Incarnals Yes Yes Yes Maal Raci Pitch, in. .494 .496 .496 [ Number of Maai. Rads / Ass y. 264 264 264 Number of Guida Whlan/Ana'y. 24 24 24 Nunbar of Instesamentaticri 'naba/ Ass'y. 1 2. 1 ~ G-,-i.1hle with Movabla inh: tam Yes. Yes Yes Detectar System Maal Tube Materia.L T4 '= 1== 4 h micy 4 4'a lcy 4 Raal Acx1 ciad 0.D., bz. .3"4 .374 .360 Maal Roct Clad 211ckness, in 0.024 0.0225 0.0225 l Maal/ Clad Gap, mil. 6.5 6.5 6.2 T Maal Pallet Diamatar, in. O.3195 I 0.3225 0.3088 s l g naal Pallet Derasity, % TD 95 95 95 Guida "h4wiki-Mac u ni gigemigy 4 giggal, yg

  • 4maley 4 I

Inner Diamatar of Juida Wielas (uger part), in. 0.450 0.450 0.442 { 0.ttar Dianurter of Guida %ielas (upper part), in. 0.482 0.482 0.474 Inner Diamatar cf Guida 24"ih1== (lower part), in. 0.397 0.397 0.397 14 .. - -.--~.- -. ....,,,n,,

' trojan Nuclear Plant Document Control Desk _ _ _..... _ _. Docket 50-344 October 29. 1990 License NPF-1 Attachment Page 46 of 65 Page 19 of 38 .,9f I N ie 3-1.

% of An r. W std. ard qrA Desim (Cerft'd) 17x17 BEFC Msdt-Bf 17x17 H 17x17 3 Fuel Assembly Stardarti Man.L CFA Tbal W-

' h4m Ammently Danie Asam&lv.Desian Outer Diannstar cd' Gaida Mistdse (lmwar part), in. 0.429 0.429 0.429 Inner Dimmutar of Instrumane mafda 211mbles 0.450 0.450 0.450 ll Cutar Diamstar of Iturt2tamane Slide l

  • 4*1ma, in 0.442 0.482 0.474

--,-

  • m of GFds.

2 Inc.-718 Inc.-718 2 Irr.. -718 Emi Gdds, Erst Grids, 6 Iirtzday-4 6 '.ircalcy-4 Irtmr nadiata Gr!4 h4F, in. 2.244 1.32 2.26 Erzi Grii h4@, irr., 19 6 1.32 1.32 r. 4 Nozzla Mc1dva.m Speirspr 3-laaf 3-Laaf 3-TAst. l l.'.. l 4 6 N-t 1 l..i' 9 15

Trojan Nuclear Plant Document Control Desk Docket 50-344 October 29, 1990 1,1 cense NPI'-l At t ac hment Page 47 of 65 %1 Page 20 of 38 q. _ M gy J ,w =,,y u T 11 Hillll o r=__= kNYUE U ~ ..Abh_; 5' C= g } , =.. - = ma . l.. [.r"TTmTi t.:- 4 TCP VIts in.= w L.- L.J.3 D liTTInTIE i; i l ,.:,gg j i i. v f ;TrrTT[=i1 lin 1 L_IllB I '~ I TiTis_ TT Il

. =

n lllllii_. j yg. IIMlTllI s1.= sur i l; l. L a O.k m ? 31.06 W

y 11
1. < i'l.

.:4g1 5 a " num A M s h7 - v 11 I in i i ! w w ; e w w"I41 '

c: ;. :s. ;' l?U I I 1 6.!D EP

. ?:f:1:-;*:d?!j?t 2.6 W l l"""' I; @@yjM4['j I RikW _atrnt-.:.pl SOTTCM VIEW

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Document Control Desk 'I Trojan Nuclear Plant Docket 50-344 October 29, 1990 License NPT-1 Attachment l Figure 3 Page 49 of 65 Page 2.2 of 38 a' . ['- .d l i V rurasEerrou WE D TAa5 l [/ 2=== y L DIN HEISHT m 016pt.g. F-5 L

  1. w i/

\\ XEYINS WIPOOW 4

' Trojan Nuilear Pi^cni~~~~ ~ ~ ~ ~ ~ ~ ~ ~ ' ' ~ ~ ~~ ^ ^ ~~ ~~~'~ ~~ ~ ife6]iie6't'C6ntiol De sli ~ ^ t ' Docket 50-344 October 29, 1990 License NPF-1 Attachment i Page 50 of 65 I Figtars 4 Page 23 of 3a .l+ @M Rest = mint Systen i - gt I i i i I iI i l I 1 i i 1 1 L" l ip! l l l l e 2 w, 1 I i l i l l 1 1 I I 2 1 :: i l l ,I I 1 r, r, L J L J 4 l I h IA 1 1 4 \\ l \\ \\ 4 l R W RAINING-GUIDE THIMELE LOCATIONS 1 i. l' OENOTED SY @ V p i 1, 1 p l-l l l? 19 l l

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. =... -.. Trojan Nuclect Plat ' Document Control Desk Docket'50-344 October 29, 1990 License NPF-1 Attachment .f.- P!.gure 6 Page 52 of 65 Bot:tta ENd spacer Grid Pago 25 of se I. q + ci Dibibibli A gg i g. i i i i i i i i g i g i f yoturrsra a = W P ' P ' 9P P 5"E gggmaut wrrou L- ~ sr u su::: sT m. n n n e n n n e t! l' l! E" 7 E **" ~~ \\ (~ (kmews, & carws w war \\ d" aCTTOu NOZZUE l 0 V 1 i

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- Trojan Nuclear Plant Document Control Desk - Docket 50-344 October 29. 1990 Attachment l. License HPF-1 Fignate 7 Page 53 of 65 Bettuna 30mmala My Page 26 of 38 {. t t4 seat snaa.sss sim. pun. -1. k .m l p? -{//W/4W ~ 2.80F g l \\ q ! a M v i J S.42E 50 4 + u ) { 'i l l

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DOC ""* "I C "" Trojon Nuclear Plant i October 29, 1990 D 50-344

        • 'I'**"'

License NPF-1 ll Page 55 of 65 FLpars 9 Page 23 of 3a g,, b Tap leazzla Asammhly o-h 1 ) i INCONEL 600 l, C: AMP 150L7 l: LEAF TYPE INCONEL 7I8 HotJ:CCW SPRING j 3

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se4t STAINLE55' STEEL PLATE a /1 QW T l ~ i =~ Nu L i h \\, c V///fA a ? = S.404 l 24

l Trojen Nuclear Plant Document Control Desk Docket 50-344 October 29, 1990 1,1cenroe NPF-1 Attachment '/ Page $6 of 65 @ 10 Page 29 of 33 f GLiide th.uuble to M Mass.la 1N 1 t i al. TCP MINS NUT ANi n i , r'l-U$ uwmm un 3 l. I y [ /[ 4 l [/A T A A f I a~ f l _gy# t. L 1, 5: ,3 f' GUIE EI M l I. 25 1 l i

Trojan Nuclear Plant Document Control Desk Docket $0-344 October 29 1990 't License NPr-1 Attachment @ 11 Page57yggp530 of 25 i Gf f arida thimble to notaan Neuzla ar =r*=m-r i b I I4 GUIDE THIM SOTTOM END PLUS VENT HOLE b SCTTOM NCZZLc

P

{. i amILLAst g h j Y a N x & s s K surer Tsraetc SQLT [ recx e I A j-l i l' t l 26 l

Trojan Nuclear Plant Document Control Desk Docket 50-344 October 29, 1990 License NPF-1 Attachment l Mgurt U PaSe 58 of 65 Pase 31 of 38 UPPER iENO CAP i-af; u h -4 n 'F' UPPER PL N ~ SPRING lip + M 6 DG AXML EEAIGET h 2 hat BC i 6 144.0 R@ O ~ i L ?. n h p,~. i -y v 5.'. LOWER PLENUM 1.s SPRING i isl l o o LCWER ENO PLUG 27

r Trojen Nuclo:r Plant Document Control Desk j Dockst 50-344 October 29, 1990 Licsnse NPF-1 Attachment l Page 59 of 65 Page 32 of 38 i s - q. 1 9% s g -E m n g l. n y a l [ J[ I _g / '{ y i d' h O I i. i 6 i 6 i i i i i e i i e i @' 9 Y9 9 7 " 7! 9 h 9 Tq 9 i O O O O O O O O O O 1 l-l . (OdW) ucanq}4m,c samed Ic!Pohl 28 i-

-~._ Trojan Nuclear Plant Document Control Desk Dock 3t 50-344 October 29, 1990 License NPF-1 At t achment Page 60 of 65 Page 33 of 38 p. v {'

4. "WLWAI.-4&fRMHlc WT 4.1 Desi=1 ivah'stian

':ha tharral and hydraulic caugatibility of fcazr I.and 'mst Ae*11== (us) l with Westi P. SID 17x17 faal in PtrM General Electric C:mpany's a= J Tn:rjan Nuclear Plant, c/cle 13, is d4-~--d in this secreian. ':M analysis considered acre ;:ressen dzty, taal assably lift fareas, thermal Wn ard m i starna ) 'Ibn tharmal ard hydraulic analysis of da IAs was parfar:med using the I2NX1, I2NX2 ard 1220C p.wi_ (rafarances 3, 4 and 5). 'Ihm 12NX1 gw& domines the density, velocit/, enthalw, veid f.raction, are c= tical heat flux on a burdle average basis. ':he I%NX2 rw datamines the thermal v and hydraulic cearactaristics for individual =*=nnals of a fual assant:ly. Both I2HX1 ard I.210C2 ccuprema a dual pass nedal !=r a sutx:mannal analysis. 'l' 'Ihm I210C r+.w is an impreved versien of CCERA1V-1 davaloped at Battalla PW4r Northwest hai ins undar 4..w.ahip cf tM Energy Researt:h ard t Duvaloptuant Administratist and the U.S. Nuclear Regulatcry N4==icri. tL I2NXT is used fcr ci

eisi; reactor cres analyses, in which subchannels, E

groups of =Wnnels, bundles ard grcups of turdles aru ::rdaled in ons l caputar simulation. h '1ha Mark-N ard Westinghcusa SID naal Assably decigns are hydran!*r-ally 7-. s4=4'=" with smal.1 differarcas in pressura drop of the ire===d4=ta spacer ]*. grids (ISG) and the 1cuar ard upper nozzlas. Ifydraulic ;.ettermance of both

====mh1y designs is based cri flow tasts in sfc's 'In..ru. ble Flcw Test l Rig (TF:R) (refaranca 11) in whic:n p:: assure drops of both designs at the j suas ope;;atin;r canditions was measured. 'Ihase rusults havn shcwn that the iy Mark-W fuel assembly has less than a 3 pswt higbar burdla prussure drop than the Westirxp.cusa SID Fuel Assembly. 'Ihm Mark-N design exhs. bits larger FIC's fcr five of the eight ISG's ard ca upper noz:la which results in a hfWr assembly pressura drop ard a diversicr2 of flow to the remaan2n;r L

====mh11as in the care. Siis damnstratas that tM two fuel==ely ' designs are s4me=* in tarms x unracaverable cars pressura drop and that flow will be divertad to the rinnaining a===hl 4== in the ccru with tha insertian of the four IAs. t Ahly and wW-UL hydraulic lift fcross Vill be unaffec ad by the inserticn of the I.As. 32is is due to the s'imi'ar hydraulic perfc=:ance of both foal assembly designs. o IO = 'fhar-=1 marydn design em1mlations aru pai.fs -l to ensure that the minimum. depam f=:m rrmleata boiling ratio (}ENER) is greatar than the design limit fcr all staady-stata cc:rs canditicns. 'ha ther:ml rargin analysis used a ::ar_=um F [3 cf 1.56 in c=rrjuncticn with a 1.55 symmical n:ial flux shape..NocirJL1, icw pressre ard high tamparsture c=re c=nditions (at the ccru safet / 14-4 s) vart evaluatad. Rasults shcw that the Westi.re m e= t SID Fuel Assembly steady-state MINER is trutffectad by the insarrien of the - fcnze I.As. 29 - ~

Trojon Nuclear Plant Document Control Desk Docket 50-344 October 29, 1990 License HPF-1 Attachment Page 61 of 65 Page 3A of 38 j-A stata peine analysis was una:t to detarains wwthar the Mark-E IAs muld pcreantially h limitig during a loss of ficw transient. c=rs flew was re1ucai 20 par-cur. %.+41ng to ficus atmarved at the point of MDiB for the Mad.-W PM assanely exper.ancig this transient. Tcr ecnservatism, reactor power.as maintained at 100 par-mnt for the analysis. ':he :ssults abcw that the MINER far a limiti.N Mark-N IA in a mrt ccr:tainig '{" Westinghouse stardard mal Assemblies is appetacmataly 5 per-cent less than (. that far the 'd-4 ting assembly in a W czzru of s':D assemblias. 1his CNB :nducrica can be cczwarted to an equivalent.Wicn of 3 par-centinFgg. 'Ihm Sc=3 faal ;mrfczmana m. (retarunca 7) was used to evaluata linear heat ratas and red internal pressure as a function of bur:s:p. ':he 3Cc3 program is a best ast.d.mata quasiM stata fual parfar=ance ccda. It ,.S daciudas gap acrzt2 i.4 , foal der =4< % ion and swelling, fuel t Inst::uc :rinJ, M*ng c=usp and daformatica, gap closura and fissica gas release ::cdals. er - h 'he linear heat rata limit for the Mark-W IA vill be the same as that for a the Westireha= Stardard Nel design as bcrth designs have the same radial gap and the fuel diamatars are al--t identical (tr.ble 1). Nel zed W - incarnal pressuru as a furxr.icn of burnap was calculated using the linear heat rata data sbcwn in figure 13 (Given as radial power distd:ution vs burnup fer a ocru average DIR of 5.67 W/ft). ':his red power histerf L reprenants a ccinsarvativa design power histarf. nzrther, the affects of design==-4dation tolerances, densifistian ard power history variations an internal pressure were statistically evaluatad. For average fual rad burnup to appetzci:staly 50,000 MNd/mec, the ac=3 predictisms show that rect i internal pra seura wi.n be less than the nominal systaa pressure of 2,280 !~ psia. Nrtrar, if red linear heat ratas remain below the figure 13 values, j a rod average burnup in excessa of 50,000 )Wd/st3 is achiavable. In sutanary, the Mar:k-E tba -nni-hydraulic analysis d .Latas that the 'ISQM Nacinar Plant cycle 13 can aparata safely with four Mark-W IAs. Analymus shcw that acru pressuru drop, hydraulic lift fertes ard tbammi (. marg 41s are not affected by insertion of the IAs. However, in ordar to anstru that full Westireha= standard Fual Assembly corn thermal-hydraulic h licensig mim1=tions bourd the Westireha== SID/ Mark-N IA configuration, the Marx-w faal====mh1y paa)cn; should runnin 3 par-cent below the 211a=hla cr:re peak during cycle 13. 4 lj: e l, I l 30

Trojan Nuclear Plant Docurnent Control Desk Docket 50-344 October 29, 1990 License WPT-1 Attachment ,]- Page 62 of 65 .t Page 35 of 38 (5 -{ 4.2 M,cr ard vedfiestian Pressure drop tasting of a full-length Mark-IN gJ.wi@a fuel a==ambly has f..- line (acL) test facility. hsting canaists of==eg councnsnt pressure been partez:cmd by SEWS Alliance Anneart:h omntar using the cs:rrt:el :cd dri*m drups over the enths aparating ramps of t-, --i.ars, now and pressure. [, The Gw that ramilts in foal assembly lift is also h %d for various ( cambinations of tamparature and prammura. 'Ibn pressure drap data are used to dotarmine Far:n Imms edr-de (FIC, for the iciar ncezia, upper nenzle and irr*4=ta apamme grids. 'Iha FIC's dotarmined for the Mark-1Bf fuel ammamibly have baan t*d14 ~4 in the IA analysis. Flow tasting of the W= Sm R1al Amasably Design was perfh 7 using Bh7C's Trar%i ble Flow ' Dest Rig (TTIR). ':ba prussure drop results J' frtaa tha test program wart used to detarains fars less coeficients for the r%tva SID Pual congenents. The finiings tres this program indicata F., that the Mark-BW and W= SID Fual designs are hydr ="1%11y [ cnupatible. Immer doppler veloc: instar tasting of the Max:k-ist foal assembly design has u baan performed far the purpena of eining detailmi infor::stica - dng the m*r%nnel flow distr:.butias. Test results iniicata that subchannal FIC's used for the Mark-lpt IA analysis are.Ma and *ht ficw pattarns within the fual an===hly are as =-p-- -a c '!he IMcMV c::d. thal best Cux ccaralation (referenoa 8) has been devmir-d for-fuel ael d== with mixing vana grh and has baan abcun to ba m -14*-=hla to the STD foal design. Critical heat aux. (CT) tasting has baan pertermed at Ctalumbia t2niversity to d=e=mina the app 14'-=h414ty of the 19017 crzrulatican to the Mark-IBi fast ammanbly timmign. 'Itst results show that the IWCMV crztralation w w i.19ely predicts critical heat flux for the Mark-1Bf foal design. 'Ihm BWCMV carrulation was used to ccuputa critical heat flux fcir the IAs. i 4 n l

Trojan Nucicar Plant Document Control Der.k Docket 50-344 October 29, 1990 ~ License NPF-1 Attachment i*- Page 63 of 65 , ' l. i Page 36 of 38 k I

5. MtEZZMt EE.U2f l (r mma mel e riare cycia is win emaise ac m e - starenze lattian manl aumenhldas ad 4 mrse-st Imed w14-= (IAs). ':he Marse-ei ammemb11ms will have 6 hun retural uranium e t hiankees -4=41=- to the Angicra 13,14, ard as "T--f =-

~1 4 = - "he IAs will alma have the suma enrichment (3.60 wet U235) for thm corazal partisrt at the fuel zizi as em P--4,-i is _ '--j- - m14-=. [ '!ba Maz$c-st h14== have a 17x17 nutrix cf. Saal zuds, guide thimbles, arti 4 inmezumere tuba gemete.xmily idsens=1 to the r-;=- thac they ruplaan. '!he fumL rad di-are also the suma tetich results in emmentially the amma Em :stic. 'he Naz$c-Bf ~14= heve zircaloy i l@ fra-d4=ta spense gcids, idasruma the - --? =-- ammamblias have '!he enrictament; credit. for the '4==1T grids is appradastaly.07 wet other than tha gesi asterlat dicemrunas, the neuerenic cmaracteristics oc 1 the two funL ammmmbly designs will ha mini.lar. 'he IAs ard tha @ 15 w.meingnauna = are cesiderud.to ha U- ^1-with w to ranclear ;-- - l, t lI l t 1 s e-e l '. \\ 's f e 0 32

~. - - -. -. - - - - ~ Trojan Nuclear Plant Docent Connol M Docket. $0-344 October 29, 1990 License NPF-1 Attachment Page 64 of 65 Page 37 of 38 y['

6. WAf?'ATmf CF ummfM 2a Mark-N foal a===hly is similar *a the Westf.:sphouse s:D. 2a major f.

difference is-in the use of Circalcy-4 ir***4=ta gr2s. A 5 4 C tianityt featurn of the upw,mv gr.ds is the use of ksys *Aich miM-4 a scratching of nest fuel rods dur.*m===-hiy, arri a spacer gr3 :sstraint systen wMc31 y allows the gr_-ds to fc11cw the taal ro:is early in life. ma spacar grid restraint systam viu allminata ax:.a1 fricticn durixxy assably arti in-c reacter dmudiaticri. In-reactor axial erd"*dm is =vu to contr.bute to fuel red bcw. l' i ) 2a Mark-N fuel rod design is w--- 11y =4=4'=* to the Westinghause STD danign. _ ma use of thickar M*M4M, higher density smallar dianstar fuel pallets, and the use of a double spdng arzi spacer syste are di.fferent frca !!d, bcch the SID and CFA designs. Mame features arn.wtive of the 5fFC Mark-B and Mark-C rimmigris, as wall as the NT!-designed Isload fuel in Japan. 2eam fuel red design featuras have been proven in over 1,000,000 irradiated ? fuel rexts. 2a guide tubes and the M* Mig for the foal rods is produond by Zirectube to sfFCs v".4caticri.W4=ticri grtwth charactarscics than the ma mis matarial vill have different leastirea'-- designs. Differarcas in grcwth have been cumsarvatively accountad fcir in grtwth c=1m1=tions. 2a Mark-W and Westimbouse SID naal Assembly designs aru bydr='14-*11y similar with slignt differences in pressura drup of the ine=*4=ta spoome e gt: ids (ISG) and the icwor and uger r-1==. mis results in a slightly MM assembly prannaws drep arti a diverzicr1 of ficw to the runsLinig a====hliam in the care. Sa Mark-5f mar==1-hyttrau11c analysis dammstratas that the 73nTAN Pv 1=r Plant cycle 13 r:an operata safaly with four Mark-54 IAs. Analyses shcw that cars pressuru drup, by*='ide lift forces and

    • =1 margins are net affect.ad by insertims of the IAs. However, in ordar to erwurn that fall Westirsghause starxiard naal Assably care t5m=1-l hydraulic licensing calculations boursi the WesthPm= S D/ Mark-54 IA 3

configuration, the Mark-59 foal a===phly :==HM sbauld remain 3 i iiwi [ balcw the allcumble cars peak dur_ng cycle 13. e' i Sa Mark-55 fuel mammhlian are gr ucally identical to the SID assemblies they W am arsi have essantially the sums N/U ratio. 2a 1 neutronic charactan.stics of the Mark-5f and SID=====hHan vs.11 be similme L with slight diffurunca due to the enriedmont credit far usig :ircalor grids P? .en the Mark-55 design. me IAs and the angian 15 Westirspbcusa assemblias are considarud to be intarthangeable with.+7 to nuclear perfctmance. Differencas between the Mazi-Si design arri the SIDs will rust have any adverse impact on plant operation. In atrr_butas that affect plant operation, the differences are small arri are covarad by the full SID cera licensim calculations. mesa design features that igac Individual fuel a===mbly performance sucn as faal Itd design arzd spacar grid features have been preven in-:nact:r by bcrh previcus SGC and net designs. l 33 1

Trojan Nuclear Plont Document Control Desk Docket 50-344 October 29 1990 License NPF-1 Attachment Page 65 of ti5 l Page 38 of 38 a 10 t-7,O RI: mtEN:E5 1. BW-10147P, Fuel A:s1 Bcwus; in hhmr* 4 itilctne Fuel Designs, 4-61. 2. BM+-10133P, Rev 1, )taz$c C Fuel Assembly IDCA-4=4-4a Analysam-Rarh 1, 5-79. u.- 3. BM4-10109-A,. I2NX1 anactzr Fual w1y ' thermal-Bydr=$14e Analysis 0:ssa, Rev 0, 7-45. 4. EM4-10130-A, I2NX2 Sutx2annel 'fhanntl Armlysis L, , Rev 0, 7-45.- .l-

5.. BM4-10156-A, I2NXT: Qas Transiert: 'thmal itydr-il 4 e i

- e.,a Ew.-,1%tze".:ary 1986. 6. BMf-10141-A, TnCZ32 7bal Pin Pucfca:mmnom Analysis, Rev 1, 6-43. !l . 7. BM4-10162-P/A, ThCc3: Puni Pin "hmmm1 Analysis Ct:cla, l.. Ncmumber 1989. 8 BM4-10159P, 54t2tV Cactalst x2 of Critdal Heat Fitnc in Mbcing Vana Grid Fuel 1==-h14==, Rev 0, 5-46 9. BAW-10084P-A, Rev 2, L, to Determine In-Ranctez-Parfacmanca of BElf Yuals # d 4% Creep NM ; t; 2, 10-78. .. 10 BM4-1017 P, Pear:k-5f Machanical Danign Aspart July 1988. t

11. Ef7C Dnnmarrt: 32-1173861-00, "fGE Delta-P Test: Data Evaluat&m",

!r T h 5, 1989. L 4 9 i($ 9 t IN-l 34 e s -, - - - -, - - + - ,ar-. ,,-,e-,, s}}

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