ML19308B529

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Cycle 4 Reload Rept.
ML19308B529
Person / Time
Site: Oconee Duke energy icon.png
Issue date: 05/31/1978
From:
BABCOCK & WILCOX CO.
To:
References
BAW-1486, NUDOCS 8001090531
Download: ML19308B529 (40)
v • d • e


Text

!

EAW-14 6 May 1978 9 e.'

N( [

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OCONEE WIT 3. CYCLE 4

- RELOAD REPORT -

4

Babcock &Wilcox

' =- . . .

8001ogof3j

Pr.'- 14 6 6 "ty

. 19,'S OCo?;EE L* NIT 3. CYCLE 4

- Relo.2d Feport -

ca s

F BABCOCK & VILCOX Power Generation Group Nucicar Power Generation Division P. O. Box 1260 1.ynchburg, Virginia 24505 Babcock & Wilcox

CONTEN19 P s,*,c

1. INTRODCC flON A*;D SOC 1.\ltY .

. . . . . . . . . . . . . . . ..... 1-1

2. Ofr u TI:b; Hl.i10RY , . . . . .

. . . . . . . . . . . . ..... 2-1 1 GIALLAL DESCRIPTION . . . . . . . . . . . . . . .,. . . ..... 3-1 4 Ft'F.I. C.YSTI;I DESIGN .

. . . . . . . . . . . . . . . . . . ..... 4-1

..l. Fuel A.sembly Hechanical Design . . . . . . . . . ..... 4-1 4.J. Fuel Rod Dc irn . . . . . . . . . . . . . . . . . ..... 4-1 4.2.1. Cl. add ar g C.)ll pne: . . .. . . . . . . . . . ..... 4-1 4.2.2. Claddin.g Stress. . . . . . . . . . . . . . ..... 4-1

4. /. 1. Cladding Strain . . . . . . . . . . . . . ..... 4-1 4 . 1. Therm.nl Desirn . . . . . . . . . . . . . . . . . . .....

4.4.

4-2 M.s t e r i a l Deh i r.n . . . . . . . . . . . . . . . . ..... 4-2 4.5 Opciating I:xperience .

. . . . . . . . . . . . . . ..... 4-2

's . NLrt. EAR DLSidN . .. . . . . . . . . . . . . . . . . . . ..... >-1 5.1. Plan it as Ch.:acteristica . . . . . . . . . . . . . ..... 5-1 5.J. Anil)tiral Input

5. 3. Ct.inges in Nuc Ic.sr De=Ip;n

. . . . . . . . . . . . . . . . . ..... 5-2

. . . . . . . . . . . . ..... "2 - 2

h. 1HrA'ttl.-ItYDRAt!LIC DESIGN . . . . . . . . . . . . . . . . ..... b-1
7. ACCIDFA T AND TRANS!LNT ANA!.TSIS . . . . . . . . . . . . ..... 7-l 7.t. Ocneral Safety An.nlysin . . . . . . . . . . . . . . .... 7-1 1.2. Ac e l .'en t Evaluation . . . . . . . . . . . . . . . . .... 1-1 M.

PROPOSED MODIFICATIONS TO TECitNICAL SPECIFICATIONS . . . . .... 3-1 I-9 STARit;P PROCKAM - PliYSICS TES11NC . . . . . . . . . . . . .... 'J - 1 REFFit!3CES . ... . . . . . . . . . . . . . . . . . . . . ....

A-1 l

List of Tables i T.shle 4-1. Fuel Dentgn Parameters and Dimensions . . . . . . . . . ....

4-)

4-2. Fuel Thercul Analyula Parameters . . . . . . . . . . . . .... 4-4 i

i

.gg(. Babcock & Wilcox

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7, i,b ty,g p .r.t*d),

Tab!e P s .;c S-l. 0.once 1 i :iy e l e P.. r...> t . r s - G . c l es. I and 4 . . .. . . . . . 1-1 5-2. *ibutdwn M.tr u t 1 a. s ic ul at ten f o r oc o.i. e J. Cveic a

. ....... S-)

ei- l . M.is t:: ut Ns t ra L. r.l a t ions for t.clov ) aaJ ; . . . . . . . . . ts - 3 7-1. Can;>ar in.n o: F.n P : . n.e t e r .e f.r b cluent Ana'vsin . . . . . . . 7-3 1-2, th.un.t t ns: *a!ne4

. for Alto-ahle Lara re.iic l.ir.ca r !!c it ita t c - . . . 1- 3

3. . : M r i .u. re..

Ityure 1-1. Co re v. .d i n e DI.wi c.s f or Ocon a c 3. C> ele 4 . . ........

. 1' a-2. 1.n r ii; tua. n t and Eu rn*: 5 D1:st r ibet ion f or Oco' ice 3. Cycle 4 . . . 5- 3 3-3. ( o:s t rol sto Locat ion = f or ecor.ce 3. Cycle . . . ........ F.

5-1. POC C/cle 4 Tw,-teleenis ton si Rel t lve. 8 sover Distribution -

Full Powes . f>.ut i t hrlism Xenon. :sor 2sl Rud Pesit iones. Groupis 1 and tt insertcJ . . . .. . . . . . . . . . . ........ lr-te 8-l. Had Po* i t ion 1.t.u it s f or Four-P.s:.p Ope r.it ion F rem 0 to 100 ?

10 f.FI'D Oconce 1 Cvele *. . . . . . . . . . . ........ 5 .'

r.- 2 . ko.1 Po . i t

  • an Lira s t tos roor-t.mp Oper.s t ton i ren 100
  • 10 to . 3 's IO l>Pa - 0.ortoe J. escle 4 . . . . . ........ e-)

M- 3. pe.d Po s t t ! a 1.t rat . . l or f ou r-i sta Ope rat ion At t e r 2 3 5

  • 10 171!' w on. e ;. Qcle 4 . . . . . . . . . . . ........ 5~

76 - 4 Ar4 Po.s a t is.n 1.1 il t s to: Ivo- and ihree-Pump u;>cr.st ton t ros O to !% i 1 0 t.fi D - 0. oric e J. Cyc!c 4 . . . . ........ 3-5 8-5. Mod 4 os t t ion 1.irait s tor No .er.d Tint ce-remp Opes at ion Fren 104

  • IP to 21)
  • 10 LFe'D Oci;nce J. C.cle 4 . ........ n - 'i h - e. . lio 1 l'ur. s e a . n I.f r.i t r. tr r Na= ati.1 Ilarce-Pomp Operation Af ter

.'l$

  • 10 6.e l p - ocosiec 3, Lyele . . . . . . . ........ h-7 ri- 7. o,ic a a t ion n ! P> av. r Inb.ilance Envelope f or Oper.at ion From O
  • to l't0 -

10 FFFD - Oeence 3. Cvele 4 . . . . . ........ n *3 b - et . Ope r a t i . in.e l Power 1r balance !.nvelope for 0;>crat ion From .*

190 - 10 t o 2 3 ') 3 10 EFI D Geonre 1. Cycle 4. ........ s-v 3-9. Op. e at sonal Power Irr.h.elance t.nvelope Ior OPeratton Atter 235 + 10 !.rpa ..iconee .3, tycle 4 . . . , . . . .,....,. 3-10

.M-lo. APSR Posit len 1.imit as for Operation From 0 to 100 l'J 1: PPD - oeence 1. a.vele 4 . . . . . . . . . . . ........ 3-11 dall. APSk Poait ion 1.Init: tor Og erat ion Fres 100 r 10 to 4 .

.'35 - 10 ETPD -- 0.:once 1. t.) . I r 4 . . . . . . . ........ 8-12 3 8-12. A PMt Position LDs6ts ~ for Preration After 235 : 10 iFPu Ocetier 3. C,.cle . . . . . . . . . . . ........ 6-13

. g,.. Babcock s.Wilcox -

11

,t,

1.  !?;tep3tTTION A!.D 5t?tJtARY This re port justifice the oper.sttoi ;f the fourth cycle of econce Nuclear Sta-ttun. Cnit
1. .a t the rated core roser of 15 6 8 5.".*t . Included are the required

.in.alpes as oatlined in the US?sEC document "r.old.ance for Proposed Licenne A.wnlw nts R(latir.g to Fetuc!!ng." fune 1975.

In support i:vele 4 operat ion of econce t' nit 1. t his report cr ploys analyt ical t rf.niques .ani design b.sacu retablisfeel in report s that were prevloessly us5-matto trad 4creptc<l by tt.c L!S'ikC and its predece ssor (sce ref erences s .

A brief nammary of cyc!c 1..nJ 4 reactor p.ir.ineters related to powr cap. ability i s inc !'ade-J an r.ect ion 5 of t hi s report. All of t he accidene n analyred in the t SAR h. ave been reviewed for tyc!c 4 oper.it is,n. In those c.asens where eyele 4

. twar.screristics wrc conservat ive comp.ored to t hose analyred f or previous cy-c!cs. no ru.r acci.'ent an.nlyses scre perforced.

The Teshniasl Specifications f. ave been revarved, and the modificatioc.s required f or ' cycle 4 operation Src justified in this re; or t .

8. ased on t he analyses p..r t ortwJ. v*ilch take into account the pontulated effects ut luci densitication a<id the Final Acceptance criteri.: for Emergency Cere Cool-In,t Syste m.

It tis been enneluded that Oconce Cnit 1. Cycle '. can be operated i

e..ii e l y .it the rated power icvel ot' J 5 % ?%'t .

1-1 Babcock & Welcox

I

2. UPFRATING lilSTORY The ref ere nt.-
uct cycle for the nuclear and thersal-hydr.culte analynca of the Oconce Nuclear Station. Unit i, is the currently operating cycle 1 C cl 2 was terminated at ter 259 EFTD of operation. Cycle 3 achieved init ial critical-it y on Den:enber 1.1977, awJ power em< alat ion coepenced on December 12. 1977.

T he-1001 power level of 2568 ff.'t i.as reached on December 20 1977.. The fuel cys:le desirn length for cycle !. - 2s0 EFFD - is based upon a planned cycle 3 length of 169 E.rPD.

ne danign cycle length of cycle 3 in 277 EFPD. No oper-at ing anom.ilies occurred during cyc!c 3 operation titst would advernely af fect f uel performnce in cycle 4.

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1 2-1 Babcock & Wilcox l 1

l I

I 1 .1 M.RA!. ! c G IPT1.d l The Oconee !* nit i reactor core im Jescrited in detail in Crupter 1 of the FSAR.*

T he cycle 4 core sonstats of 177 fael assenb!!cs, each r,f w+sich is a 15 t . 15 array r unt ainin,r 2',8 f uel ro ts. 1 +2 control rod guide tubes. and one incere in-strinent ruide tube. The fuel r>l claiding a s cold-i.ork.-d Tirc.alcy-4 wit h an 03 4,1 0. 4'1G i nc h .and .i w.s ! ! t hic kne ss of 0.02f5 inch. The fuel ren= fats cf dished-end, cflinJric.at pellets of uranium dioxide which are 0. lt>95 inch in diancter. (See Table 4-1 for additional d.it.s.) All s ue! . sew-b t les in cycle 4 saintain .a rt,n= tant nasiinal fuel loadinr et 461.6 kg of urantua. The unden.il-(ted nonical active fuel lent:ths and theoret ic.sl densit ica vary between batchen.

.ert these value= .ere gisen in Talle 4-1.

Fir.ure I-I is the care to.edlag diagra:s for oconce 1. evele 4. Al l t he tu t e ti 1 a ceblic will be divharged at t he end of cycle 1. Twentv-nine once-burned b.stch ! asurnhile,.. with . . initial enric'-ment of 2.01 wt : ' ' ' t'. w i l l be re-lu. de.1 fi.t a t he cent ral port ion of t he core. hatches 4 4A. .and 5 wi t h ini-ttil enrich vnt.s ut 2.55, 2.64, and 1.02 wt T " l' . respectivelv - wiII be shuffled t.: new loc tions. Ita t c h b. with an initial enrichsent of 2.9 7 wt :

  • '* t' will occu;iy prin.ar t iv t he ccre peripher) . Figure 3-2 is .in eight h-core re.ap nhowing t he .isacc51y burnup an.1 a nriclesenc dist ribut ton .at the twginning of cycle 4.

Re.sctivit y cont rol in r.upplied by 61 fual-length Ag-In-Cd cont rol roJs and solisti!c horon phin.

In .iddit ten to the full-length control rods. eight partial-Icog'h axlat power abaping rods 1AT5Rs) are provided for additional control of n l.a1 power distr 15utien. Tho cycle 4 locations o f t he to con t r ol rod e .ind t he group designattens are indicated in Figarc J-3. The core locations of the to-t.a1 pattern (t>9 cont rol roda) for cycle 4 .are ident ical to thome of the rc'cr-ence o cle indlemted in Chapter 1 of the FSAR.I llowever, the group desis satinns riay dif fer betwen cycle 4 and the reference cycle to minintre power peaking.

Nettber cont rol rod interchange nor turnable poinon rods .are necess.sry for cycle 4.

3-1 Babcock a. Wilcou

h Figure 1-1, d o r. I o.ad i u M.w rens t .> r ( ,* r ...: 3. Cvele I.

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I17.4fc l-2. Ir.rish ent .in : %rnt.s O!.tr1tutIon ior

%;ne c J. Cyc!c *.

g 3 9 90 11 12 13 14 15

.I N. ' 2.Cl l 2. 01 J.Of 2.01 3. C2 2. G1 2.33 3.C2 14.215 16.2E4 7.283 17.460 i

1.437 18.031 13.736 3.833 3.C2 2.$J 3.02 2.53

, 3.C2 l 2.63 2.97 1

4.831 '

1s.4: 14.496 6.021 11. 757 0 i 3l 4.331 l 2.64 ,

l l 2.63 2.53 2.$3 i

3. 02 2.97 3

13.945 13 497 12.112 14.939 4.136 l  !

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J. 2. 01 3.C2 l e

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2.Cl 2.97 g 17.679 6. 74 3 14.640 0 I

2. Cl 3. 02 2.97 N

17.768 4.296 0 2.97 0l e

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00.033 900 BURNUP, una ufu 3-3 Babcock a. Wilco n

rieur., 1-3.

Co :t r';l ' o ! Lo .s t i r.g ?ct ', rce 1 Cycle a 1

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-sw I Ii 12!3(4 b, 5(1 8l9 10illi12jl3 k

14 15 i CS etrP NO.Cf RODS FUN 0fifN 1

12 SAFETY 2 8 5AFEff 3 S 4

SAFETT 8

SAFETT 5 3 CCNTACL 5 8 CONTROL i 8 C0hTROL 8 h AFSR$

TOTAL 69 l

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Babcock a Wilco -

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4 ii.vt. :tste Lt. sics 4.*. Tew i .b se ntil **-4 nr.n l e .s i de . l g ',i 1he type = r,f ?6.cl

.r .sA>!!c- and ferttnent f uel de v i en ;>a r net er.e an.3 diwn-stone f or t:re.nev .. cy fc k arc !!sted in T.able 4-1. All fuel asse mlf em are identteal in r..ncept sad are r:cch anic.sily interchaneciasc. All rc=ults. rei-cec *cen. at4 ident ifie d o nservat t .ts presented in me. t ian 4.1 of ttw previous ornnce +

i load rep.rt* are applicabic to the cycle 4 reload core.

4 .2 *_ . J..I A!8 .?Y a 'E 4.2.1. t.l.i,ese .sna l) .c.

here : cr ioraxd f air three-c)r!c ammerbly pcwer"hinto-t te i. Tbc ha t c h 1 f6el 8 c, . r e limitin,t than the other batthem due to its

.irevsoas i m ure- .: pimura tie.e and the .assaned fa.cl densiti. tion behavior out-lined an r.terence J. it.e b..t ch 4 ammcably power histories were an al ysed .ind t he c.a n t t l'el t l ag a gt.e ,al v .tet ermined.

i.

cons.c 's it ive ..ssembl . vwe r !?i st ory nvelopint i t.c wa r II::it ing assezoly' pir.t r t.i m t orv v.s h u r..I t o calcu!.it e the fa.<t neutron !!ux invel sur r % en'rgy ran /c e.>ove 1 HeV.

f.rce : colla;u s tire was determined to 1,c raire thas 3f>.000 LFPet (c! t ect ive tull-p wer h.,srn). %telcin is lun,te r t h an it.c rse simuss e s t i ma t ed i t.co r e residence tie.' See la%le 4-l). Tne creep collspne ana!yhem were per-f o r rw .t b.sved cr. tl.e s en si t ions act forth in retcrences 2 .sied 4

.r

  • . 2.2. fl.idter Stre<s lhe 'Acccc ! a.t ra se parJN t erse .tr.*

enveloped by a con .crvat ive f uel rc 2 st ream anse lys ts.

ine reault s presented in iccti.m 4.2.2 of the previous Oconee 3 re-l o.a.t resor t# are applac.s.lc. 6

4. 2.1. C1.edd i nLS,t_r_43 The f uel de e l ga c r i t er l.a espec i f y a !!mit of 1.0% on cladding pl. ant ic c irc um--

ferenti ! atrain. The pellet dee+18.n in est.ablished for plastic cladding str. sin 41 Babcock s, Wilcox

m _

of Icts th.in'11 at v.ilu s of xtrem des ta ; 1 al r. Ilet 1urnup a-3 he.it /.c n -

eration rate. which are .saderataly 1.ig5cr th-en t h v ai acn tne ucen.e 3 fuel i s r a p.:< t . d ' t o sec. Tht*. -211 result an =at ,q1: t h.s t 13 even er<. iter than the an aly m t m de.%n s t r .a t ( 4. The st r.si n anal . sis 1. a l s. s based en !!c t h i ..us Specif iut tun v. slue f.sr 't... fus.1 acitet Jiau t o r an.: ..-n s i t s .in.s t r..: tuwest

'pctnitted Crc:stt. it ten r ule r.r.re i t'r t he el.4ddin c 10.

._  !. . ) . TT.c r ea l ' *)c s lyry, All fuel.anses, ica tre ti.t> urc ..rc t: r= 11v =1 mil.ar. the f r es ta b.s t e t 6

,' ac t 1:strted fo c:..le <r>-ration Intr. cures, no s i gn i t t e.tn t differences in l uc t 15erratl .r cr t urr ance rr!4ttee t., the otner fu.1 renaaning in ti.e core.

The .lv s i v:l mi n ica.a l i nt a r he.it r.s t e (l.hP ) car 25111 t y .and the .sve r vc fuel t reaper at ure. f or c.w h b it ch ' in . vr ie are s a:r.n in Taale 4-2. LIR capa5111-t i cs .i r. . tsa scet n tunter!a..e f.e! x ic and .ere c4tabits.ntd uwinr the I Al~i- 1 tu.le' 1,;i t a.1 riensi f 1. at sea to %. iI of tbeenetIc.11 dens 1Lv.

4 . ?. . ** s r . t 1.s l_ ?ns 133 Th.* b.s t 4 6 f ..e l .i s ariat> ! !c . re not nos in c.,n c;t. nur do thrv ut(lize lif-

!trent cetiron nt titerl.el .  !!ceciose. t h e- c h n t a l <<mp.st i;. l i s t y .51 .a l l pow 1hle t +:v. . l ...sd t n g- c.m l .ent . s.:r.ts l y ir.t c r.a t t i. nu for the t .it r te ri t oel .ss-

.v ta' l i r a. ts i t.. s t t t .s i t e. ti.-c of the present fuel.

' . . ' . . e b.c rat in. f y >* in ys .

ft.b c . .. t t 'd : 1. a ,

e, . r .a t t n e u v + r l < c. . . sith the 't.o r k t5 15 15 rse! .sn embly h.,

vtri! leo tnw a icqu.i. v - of it. Je s a ;n. A= . t i ets r u.e r y .! s . IWd. t t.c : o l lewin,;

e s p. t ie n. lis i t. e n .ec. u .a l.... d for s he e s 4ht ope r.s t in,; 44'4 1/8-t et a seably

-plante. ... . si g t '.e Ma t h I. ~..c ; is se sts t y :

- e. - 2 Babcock & Wilct):

f.-

N xinus .essenbiv Current ""P' ' ' -

Cu @ tive net Rea: t or ~cyele electrical eutput.

11cere D ischa rged Wh Oconce i 27,200 25.3M 20. 3d 5.249 Oconee 2 .) 26.700 .'d.800 15.2'.d 595 Oconce 3 3 27.140 27.200 19.182.513 TMI-1 3 31.720 25. eta 18.430.506 ANO-1 2 2F.2"O 17.050 1*.575.320 k.incho seco 2 2.' 300 17.170 13.297.637 Cryst.rl River 3 1 10.430 --

4.'*30.412 Daviu-Arnse 1 1 2.460 --

1. N9.741 7.jSi n4-A. Fuct yar.ign_ Parameters and_ Dimensions Twice- Fresh burned FAs. Onec-burned FAs FAs.

Batch 4/GA Mtch IC hatch 5 Mtch o FA type Nrk 64 Nrk B3 N r k E '. Nrk b'.

W. of FAs- 52/4 29 56 30 FueI rod 03 to. O . *. 3 0 0.430 0.430 0.*30 Fuct rod ID. in. O. 177 0.377 0. 177 ~ 0.377 Flex. sp.ies r s . type Spring Spring Spring Spring Rigid spaceri. type Zr-4 Zr-4 Zr-4 Zr-4 l'ud en

  • 1 ( . active fuel 142.2 141.0 length (nos.nal). in. 142.2 142.2 Fue' pellet Initla1 94.0 density (nos). I TD' 95.5(d) 94.0 94.0 l'uct pellet OD (nean 0.3o95 apeci(). in. 0.5edO(d) 0.3695 O.3695 Initial fuel enrich.

wt Z;M' t 2.53/2.64 2.01 3.02 2.97 BOC burnup (avg). 13.865/13.975 Wd /mt t- 16.557 5.318 0 Cladding collapse >30.000 time. EFMI >30.000 $30,000 >30.000 i Estimated residence 17.952 l$ 192 l time (rtx). EFPil 18.024 20.736  !

(a) Nominal v.alues af ter reslutering.

i 4-3 Babcock a Wilcox l

iW Table 4-2. I'ue 1 Thernal Anslysis Parameters '

Batch IC Batch 4/4A 3. arch 5 tiatch e

'4). of assemblies 29 32f. 56 36 Initi.nl den 44ty. 2 TD I c5. 5 '*I 94.0 9. 0 44.0 PelIct dian.? t e r . in. O.165 0 ("I C.3:95 0.3e45 O. h9 5 Stack height, in. 141.0 Id) 172.2 1-2.2 142.2

_ Dens t f i rd Fuel P.a raw t_e_r.s.

Pellet' diam *tes, in. G.3649 G . It>4 6 ' O.3640 0.3646 Fuel stack height. 19.  :,s .2 140.5 140.5 140.5 )

Nominal linear ha at rate i

5.3> 5.50 5.50 5.80

@ 25M MVt. kW/ft Avi* rag.* fur t te.mperat ure 13:C 1320 1320 a', u',raincl utR. F 1320 Linear. heat r.a t e 20.15 20.15 20.15 20.15 capabilltv (center 1tne fuel aeltJ. LW/ft

- f a)Notinal value .af ter resinterine'.

(b)Densifisation to 96.5: ID assun.J.

l l

1 4.c Babcock a,Wilcox

5. 'ot;CI. EAR :s!.5 IGN i.l. Phv4fes Ch.t r se t e r i s t d e r.

. Table 5-1 con.p ires t;ie c..re s hs sic . ; ara s ters of design cycles 3 and 4; the h

values for both cycic4 were onerated using PDJ07. Since the core h.as not vet reached an equilibrium cv?le, differences in tore ;'hysics P.ir.imeters are to be espected between cl.e cycles.

The shorter cycle 4 will produce a sta.siler evele daitcrenttal burne.:n f h.n t hat for the design cycle 3. The acennulated

.sver.ine core burnu;> will in ;u.:Ser its the design cycle 3 than in* cycle 4 be-cause of t ric presen(e of the once-burned batch 1, 4, 4A. and 5 t uel .ind the use of L W 5:FPD for the planned cycle 3 length. F gure 5-1 illustr.stes a representative relat ive' power dist ribut ion for the bes;ir.ning of the fourth cycle at f ull p.wer wit h e psilibr f un xenon and nos mal rod posit ions.

The tratical boren cencentrations for cycle 3 are higher than for cycle 4 be-

. a u a.c ot .i higher t' red enrichment ditierent r.adial power distribut ion. etc.

As l ad i c.a t e.; in a-abic 5-2, the sontrol rod worths are sutfielent to maint. sin the tr4p:a red shutdow rur.*!: . The eyele 4 ejected rod worths are lower than those in eve!c 1 ic r t ne s. nae nutber or r egulat ing, banks inserted. Ca lcul.it ed e lec t ed ro.! wor t h 6 und their adherence to criteria are considered at all titres it: 1i t e and .st a!! power levels in t he develo; ccat of . .ac rod in:,ert ion 1 inmit a present ed in :wt t ion 3.

The maximun stuck rod wrths for cycle 4 are less than those in cycle 3. 'the a fecuacy of the shutdown rurgin with cycle 4 stuck rod worths is demon *trated in T. sole 3-2. The following conserv.atisms were applled for t!.e shutdown calcul.atIons:

1. Poison tr.ateri.nl deplet ion . allowance.
1. 10% uncertainty on net rod worth.
3. Flsax redist r ibut ton penalt y.

Flux redistribution'was .iccounted for since the shutdown . analysis was calcu-la t ed us in g .a t wo-d t mens t en.n l ex del . The shutdewn calculation at the end of cycle 4 is .inalyred at approxica.itely 235 EFPD, This is the latest time 5t Babcock & Wilcox

(1 10 days) in core lite at which the transient bank is ne.arly fully inserted.

After 235 1.FPD. the transient bank will be almost fully withdrawn, thus in-creasing the avail. Ole shutdown rurgin. Tae reference fuei eyele shutdo.n n.nrgin is presented :n reference 2. Tibic S-1.

The cycle 4 puser detic1Ls frem hot sero pm.er to het tull power are s iri l.ir to those for cycle 3. Doppler evelficients. =>Jerator coef f icient s, an'd xenon wort hs are also sisillar f or - the twa cycle s. The dif ferential boron worths for cycle 4 are approxitutely equal to those for cycle 3. The effecttye delayed neutron f ractions f or both cycles 4how a decre.ase with burviup.

5 2 2. Analytical in; ut_

The cvele 4 incere inessurement calculation constants used to compute core power distribution. vere pre >ared in the same manner as for the reference cycle.

5. 3. Cha n n.= s. In Nac! car Design The saac calculational :aethods and design informat ion were used to hbtain the lepirtant nialear design parac.eters for eteles 3 .ind 4 In addition, there are no signiiisaat e;er at tenal pri cedure changes t rots the reterence cycle with rex..rd to a:: lit or radial ; wer chap. cont rol. xenon control, or tilt control.

The operattonil 1fr.it3 (Technical Speeifleation changes) for the tOload cycle are shown in scetion 8.

A fuel .,el; 11 nit or 20.15 kW'/ft has been employed in calculating the reactor proteetten i,) sten setpcints and is tl.e same as in previous cycles. The batch h fuel a a n.blies will Se lo.ided as shown in Figure 3-1. Two batch 5 assen-tit les hr.e been as ir ied a ::.axic ou linear paver rating of 19.74 k'd/ft based on as-!:uilt data. These assembl4es will be placed in non-limiting loc.at ions during their entire core residence. For cycle 4 investigation has determined t h.i t if these .in....511es are placed in locations C-9 and 0-7. they will not experience ;ineat ;e.e rates bl.: tier than 19.15 k'd/ft.

o 5-2 Babcock & Wilcox

T.~e h l e 5-1. oconee 3 P h sics P.1 era eters - Cveles 1 and 4 Cvele 3 Cvele 4 Cycle n eut h. FFPD 277 270 Cycle burnup. INd/catU #4668 8450 Average core burnup, t'OC. E.'dictt 18.921 17.233 Initial c..re li .id ing. et L' 82.1 82.1 Cr it ical Saron - tm (no xenen) . ;;m '

s HZP. r,roup a iti < rted 1261 1230 it3P grou; s 7 .ind 8 ins.c r t ed 1168 1170 liFP gros.pr. 7 .an.1 h inserted 1000 978 Crit it.at inran - E84 (equil senon), ppa H2P. gros.p S 17.5% vd. equil menon 288 304

!!FP nr.)::- 8 37.52 vd. equil xenon 35 41 Con t rs:1 rt d wort hs -- liFP. SOC, I ak/k Group t> 1.03 1.00 Crou;i 7 0.77 0.37 Croup ti 37.5% wd 0.40 0.35 Control rod =orthe - HFP. 2i5 EFPD. Ak/k Croup 7 1.05 1.12 Croup 3 37.5% ud 0.44 0.40 LA e lec t e st rod worth - ilZP. I akti IWC. groupa 3-8 inserted 0.73 0.44 25i EFI'D. graupg 5-8 inserted 0.61 0.50 Nx stuck rod worti. - !!ZP. ; ak/k PJ 5C 2.54 1.80 235 EFP3 2.24 1.85 Powe r de t' i c i t . !!2D to HFP. I ik/k BOC 1,55 1.30 235 EFPD 1.98 2.12 Doppler ces:t t - BOC. 10-S(Ak/i *F)

.1002 power (equll xenon) -1.43 -1.48 Doppler ceet f - EOC. 10-5(ai/k *F)

.1002 ptver (equi t xenon) -1.56 -1.61 5-3 Babcock a Wilecx q

Table $-1. (Cont'd) i Cycle Cycle 4 Mederator coef f - liFP, 10-4 (Ak/k *F)

LOC.(0 xenon. 1070 ppe, group 8 ins.) -0.53 Id) -0.70 LOC (equ11 menen. 17 fra. group 3 ins.) -2.55 -2.57 Boron worth - HFP. pps/2 !.k/k i' BOC (1150 pra) 10$E *) 106 EOC (17 ppas 95 95 Xenon worth - HrP. % l.k/k 90C (4 days) 2.66 LOC (equi 1*brium) 2.64 2.75 2.75 ,

F.f f delayed neut ron f raction - HFP i LGC 0.00594 0.00583 EOC o.00522 0.00522 (a)For coaditions applicable to these values refer to EAW-1453 2 (b)the dyatrq cycle 3 lenett. is 277 1FPD. The danseed cycle 3 length 14 109 LFPD.

i I l

- t I

I I

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4 a

34 Babcock & Wilcox i

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4 Is-..

.- p .

Table 5_-2. Shutd.vn Margin Cal _cula_ tion for (cence 3. Cycle 4 P.CC ,

I 2k/k-  : E0C.

.k/k IN Available Rod Worth Total rod worth. HZP 8.18 8.52 Warth red'n due to poison burnup -0.05 -0.33 Maxt:nsu s. tuck rod, il2P -1.60 -1.85 Net werth 6.13 6.34 Less 102 uncertainty -0. o 1__

-0. 61, Total av.al ble wort h 3.52 5.71 Fequired Fed *.* orth Power deficit, HFP to HZP 1.30 2.12 Ma x a t :cw.ible inserted rod wrth 1 06 1.31 Flux redistributte.n 0. I. 7 0.87 Totest required wosth 2.83 4,30 Shidown M.srgin Total . avail worth - total req'd worth 2.69 1.41 Required shutdown turgin = 1.00: ik/k (a)For shutdir n m rgin calculstions, this is defined as au mt 233 Lil3 the 1.s t e s t tise in core life at which ele transient bank in nearly fully inserted.

i i

i 1

l 5-5 Babcock & Wilcox l 1

-4 I

Fis;ure 5-1.

30C (4 EFPD) Cycle 4 Two-Pir2cnslenal Relative Power Distribution - Full Power. Equilibrium .%enon. W r-

.21 Rud Positions, Croups 7 .ind 8 Inserted S 9 10 11 12 13 14 15 H 1 C. 8 9 0.96 f.38 1.02 1.36 0.83 0.52 0.69 R

1.34 1.37 1.09 l 1.03 1.26 0. 92 0.81 1

5 L

0.61 3. 91  ; 0.91 1. 01 1.22 0.75 i 1 W

0.77 1.16 0.91 1.09 M i 0.87 l 1.18 0.73 0

0.88 1

?

R INSERIED R::3 GROUP NC.

0.00 RELATIVE FCsER DEhSiff

]

5-6 Babcock a. Welcom

6 THDWJs!.-liYDPAl'LIC DES!CN Thr-thermal-hydraulic design evalustien . supporting cycle e c;eration ut Alize1 .

the w.ethods .ind ridcle described in references 1, 2, and 3.

batch 6 fuel 19 The incommt cycle hydrau!!c .lly .and r.co rtrie. ally initar to batch 5 fuel. The 3 and 4 ruxatum desir.n udit ions and minnificant parameters Jre.mnown i n T.ib le 's-1.

The niniu s DNtut shown at the dust,n over m er is unch.acJ;cd for cycle 4 .and is bawd on 106.5I of desim reactor coolant flow and the Mark B- 4 fuel assent,1y and includen tt.e ef fects of incore fuel densification.

The po:enti.nl ef fect of fuct rod bow n DNS8t was considered by incorporatin g suit.able margins into PNd-limited core safety lintts and RPh *ctpoints . The maximum rod bow san calcul.ated f rom the equstica U

c, S 9. ut.*, e 0.o'J1449 .E where s !.C = ri:d bev rugnit udo, nila, C,,

  • I n i t i a l c.4p ( 1 M s i l s ) .

MU = ux tsum arrumbly burnep KJd/st'J.

The fue I cycle desi;;n calcult.tluns show that the r_aximum radi.al-local peak during cycle 4 in alw. syn loc.a t ed eum burnup. in the batch 5 fuel assembly with the m.axi-Thir. ruv isma p.vL (1. 512)

En credit is 18* below the 1.7s reference i peak.

is cl,eir.ed for the dif ference between c.alculated cycle 4 peaking and the reference ! peaking used for analysis.

in.; f or JNER an.41ysis, Since this fuel assembly is limit-to cycle . operation.

c:.e rod bow penalty associated with batch 5 is ap; lied This tu.thod nor calculating the raximum core rod how pe alty t.as been revicued and approved for acceptability by the NRC 7 Tt4-Oconee 3. cycle 4 calculated rod bow penalty is 8.91 based on the maxim um burnup in b.atch 5. Id 450 M'Jd/stU.

An '1.2% rim low penalty based on an . assumed naulmum burnup of 3 3.000 KJdintU to conservatively .appiled to all n.alysem c;d to design transients. that deline plant operating 11atts 6-1 Ba W &W Icox g.'

- 2,4

~

The flux / flow trap setpoint was <1etermined by. analyzing an assumed two-pop coastdown starting from an initial power 1cvel (indicated) of 1021. A flux /

flow trip setpoint of 1.055 is catablished for cycle 4 and is baw d on 4 mini-cun DNhR of. I.3 plus a suitable cargin to of fset the DNER reduction due to rod bow.

A thermal margin credit equivalent to 1% LN3R to of fset the projected fuel rod bow penalty has been u. sed as a result of the flow area (ritch) reductJon factor included in all the thertui-hydrat.lic analyses. For trie flux / flow trip .

setpoint analyJis, an .sdditional thersal r.argin credit equivalent to 12 ex-cess flow has been .spplied. The II flow credit is claimed on the basis that 106.5% of RC design fluw was used for safety analysis and an RC flow in ex-cess of 110% of design has been proved in the plant. The specific DNER cred-its used to offset the rod bow penalty in the flux / flow analysis are as fol-lows:

DNBR Credit for flow .irca red'n 1.0
f. actor in analysis Credit for 12 excen= ltC flow 2.5

( 3. 5 6 .sva i l .ib l e )

Net rod bow pen.nlty applied 1.J, in uslysis To6.il credits 11.2 1

l i

j I

l 92 Babeeck & Wilcox l

l

I Table 6-1_. 2ximism Design ConQt iens for Cycles 3 and 4 C.cle 3 Cvele a D. sir,n power level. MWL 2Ms 2%S Svat.a pressure. psia 2200 2200 Reactor coolant fIcw. I design 106.5 106.5 Ves:.el inlet /oot tet coolant t emp a t 555.6/602.4 555.6/602.s 100% p >wer. F Ref design radial-lecal puwer 1.76 1.76 peakinic f.setor Reef design axial flux shape 1.5 cosine 1. 5 cosine ilot ch.ennel factors: Enthalpy rise 1.011 1.011 Heat flux 1.014 1.014 e low area 0.98 0. O A(ttve fuel length. In. 140.2 140.2 Avg heat flux at 1001 power. Btu /h-ft2 I*I 175 a ~103 175 103 lfa x heca t flux .it 1007. power, !!tu/h-ft2 468 108 468 = 103 CHF correlatton BAW-2 BAW-2 Hin DNBR (I p.2wer) 1.90 (112) 1.90 (112)

(a )liea t flux w.as b.ssed on densified length (in hottest caire location).

th) Lased on average heat flux with retcrence peaking, a

6-3 Babcock & Wilcox

I.

7 AerIDENT A';D TPANSIENT ANA1.YSIS 7.1. General Safc*v A9419 sis Each FSARA accident ar.alysie has been esamined with raspe t to changes in cycle 4 parameters to dercrnice t he e f f e c t of c cycle 4 seloaa and to ensure t ha t thersal performance during hypathetical transients is not degraded. The effects of fuel densification on the FSAR accident results have been evaluated and are reported in reference 3.

Since batch 6 reload fuel assemblies contain fuel rods with a theoretical density hir,her than those considered in reference 3, the con-clusions in that reference are still valfd.

No new dose calculat ions were perf ormed f or the reload report. The dose con-siderations in t he } SAM bure bau-d on maximum peaking and burnup for all core

~

cycles; ther.iore, the do w con %i m :stions are independent of the reload b.ttch.

7.2. Acc i.f. .t rvalu.a t f or.

the sey par w ters that have tie greatest- effect on determining the outcone of a t r.sn sien t can t ypic21Lv te etav ifled in three major areas: core thermal parameters, therm.1-hydraulic p.arrxt ers, and kinet ics paraext ers, including the react ivit y f eedb.ick ceri f icients arid cont rol rod worths.

Core t he:ral propert ies us-d in t he FSAR 4ccident analysis were design operat-it.g values basco on calculat ion 41 valces plus unecrtaint ies. Coeparisons of fir.t core values (ISAR values) of wre thern.s1 p.arameters a sd n shmequent fuct batches to p<stomercra unvJ in cycle 4 analyses are given in Table 4-2. Tabic o-1 conparem t he cycle 4 thermal-bycraulic euxieun design condit ions to the previous cycle i valuen. These parameters are com9un to all t he accidents connidered in t his report. Table 7-1 compares the key kinet ics par.iaeters from the FSAR and cycle 4 A gercric LOCA analysis has been perforr.ed f or t he B&W 177-FA lowered-loop Nss using the Final Acceptance Criteria ECCS evalua-tion model reported in referenec 6. This analysis is generic in nature since the Itniting values of the key parascrcrs for all plants in thlm category were used. Furthernore, the conbinaticn of t he average f uel tesserature as a 7,3 Babcock & VVilcox

iunction of ' linear heat rate an-1 the lifetime pin p. essure data used in the LOCA limits analysis'- is conservat ive compared to those calculated for t hi*

reload. Th:s s , the analy<.is and the LDCA lisits reported in reference 7 pro.

vided conservative resalt s fur (b: operation of oconec 3 cycle 4 fuel. A tabulation showing tre Lounding values f ar allowable LOCA reak Li!Rs for Oconee

3. cycle 4 fuct are prov!Jed in Table 7-2.

From the exasin stion of cycle 4 core thornal properties and kinetics prcperties with re= rect to acceptable nrevious c>:lc values, it is concluded that t !' t a core reload will not adversely affect the safe cperation of the Oconee 3 plant during cycle 4  !

Considering t he- previousif acceptcd design Lavin used in the I j

FSAR and subsequent cycles, the t ransient svaluation of cyc!c 4 is censidered to be bounded by previous y accepted analyses. The initial conditions of the t ransients in cycle i are bounded by the FSAR and/cr the fuel densification

[

report' and/cr subacquent cycle analyr.cs. ]

7-2 Babcock s, Wdcox

7

-m

~

Table'7-1. Compari son of Ec y I'a rame t e r s f or Accident Analysis I'SAR and denatf'n Predicted Parameter report evele 4

.i Osppler coe f f , (l.k/k)/*F

. P,0C -1.17 10

  • I'I -1.t.8 = 10-1 rCC' -1.33 10 * -1.61 10-I Mederator cceff. (l.k / k ) /
  • F Pd:C +0. 5 10 '* M -0.70 10-'

LOC 1.0 - 10 * -2.57 -

10--

All rod grcup worth, SZP. I 10.0 S.18

.k/k Initi.sl tsoron cone, HF P. pre 1400 1070

f. oram react ivi ty wort h .st 75 74 10F, ppn/II /k/k

% ejected rc4 worth, HFP 0. t 5 0.55

  • ?.k / k Dropped red vosth tJP. I O.46 0. .?O lk/k

() -1.2 - :T.' (t.i/ k ' /

  • F w.i s used for the ste.as line f.niture analy-sis, an-1 -1.3 10 '- (t.k/..)/*F was used for the cold water .acci-den,t an.n l y s i s, t s.j +0. 91, 10-' (l.k/k)/* sag used f or the raiderator dilution .accia dent a na l y s l e..

T able- 7-2. I,ounding Values for Allowable LOCA Peak !.1. ear H. sat Rates Allewable peak linear rore .levation g _tes_t rite, kil/f t 2 15.S 4 16.6

~6 18.0 8 17.0 10 16.0

- ~

73 Babcock & WilCOM

'u S. PR0 POSED N DITICATIONS TO TECl!NICA!.

$PT.CIFICATIONS I

The Tectitcal Specifications have been revised for cycle 4 operation to account for minor changes in power peaking and control rod worths inherent with non-equilibrium cycles. In cddition. the allowable quadrant tilt limit for cycle 4 has been ,:hangedto 5.0%. A pewr caking penalty (1.075) appropriate for this quadrant tilt limit was used to set != balance and rod insertion limits.

Based on the Technical Specifications derived f rom the analyses presented ir.

this report. The Final Acceptance criteria ECCS limits will not be exceeded, nor will the therral design criteria be violated. Figures 8-1 through 8-12 are revisions to ptevious Technical Specification limits.

)

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8-1 Babcock & Wilcox

~..

'Le

Figure 8-1. RM Positien Limits f or Four-Pu .p Ope rat ion Fre .

O to 100 : 10 EFPD - Ocence' 3. Cycle 4.

.l!0 (82'i i 2' (t T4* t

  • t 02) i, ,,(212.E.802) 100 -

RESTRICTED OPER AT IOk3 REGIC%

90 - h0i (174.1.90) , , (212.6.90)

ALLD8ED TRICTED / (251.4.80)

'tEGION POWER LEVEL 80 -

161.2.80) CUIDFF SW50CsN

= 10 uARGIN tl51.4.70)

(3CD.70)

$ Lly:T

" 60 -

h 50 -

J' (29.50)

PERiflSSIBLE 40 -

OPERA T ING REGION 30 -

20 1

(0.15 l 10 - l J

0 '!I i i . , , .'

f f I f I t t 0 20 40 GO 80 100 120 140 150 180 200 220 240 260 280 300 Roa Ir.:es. - setneraen

  • ' ' ' t i t , , ,

0 25 50 15 100 0 25 50 75 100 Grcup 5 Grcup i l I I t g 2 25 50 75 1c3 Grcup 6 1

i i

8 Babcock s.Wilcox 1

l l

F!gure 3-2. Rod Po sition"1.Imits f or Four-Pu- p operation Fron 100 - 10 to'235 10 FFPD -- oconec 3. Cycle 4 J'

110 (154.9.102) ( 174.1.1 C2 ) (232. l C2 )

' 0 ICO -

> RE51RICTED REG 104 OPERATION IN TH' (222.90) 90 REGl:4 'S h0i ALLteEO ),(174.1.90) ' %PC8ER LEVEL CUT 0FF 80 1C

.[< (161.2.80) a5i.4.80, (1 1.4.70) (300.70)

SHUT 0084 uaRGig 3 CO _ Liuti -

C i 50 (80.501 PERul5SIBLE OPERATI%G REGIDst I 40 -

a.

30 -

20 - ( 0.13 )

30.15) 10 ~

PESTRICTED GEGICN 0,

O 'f t , , j , , , , t , , , ,

0 20 4C 60 6 103 120 140 160 180 200 220 240 250 280 300  ;

Roa Inden. , Estnoraen I I I I I e f , t 1 0 25 50 15 lCD 0 25 50 75 i30 Gscup 5 Greup 7 I e e i t 0 25 50 15 ICO Stoun 6 l

l l

2 8-3 Babcock s. Wilcox

1 Figure 8-3.

Rod Positlen 1.imits for Tour-Pump Operation Af ter 235

  • 10 EFPD - Oconee 3. Cycle 4 110 (ISI.7.102) (251 4.102)

' ~

CPER AT1341% Tetl5 RE;l0N 'PCIE81 LEVEL

%0T AltC8EC CUTOFF RESTRICTED SD -

/ 1 REGION H251 4.90) 80 -

(248.9.63)

, S4sTD28% uitGIN .I!0 6.70)

= ~

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"a 50 '

110.5C)

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20 -

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c 20 40 ED 63 1C0 123 140 160 133 20C 223 242 250 222 300 Rec Inses, '. Estr.craen I

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C 25 $0 15 100 '

Cscup 5 Grca 7 t t , , ,

a 25 50 75 lt:

Grcup 6

- :. rm i

l 8-4 Babcock s Wilcox l

______________ _ _ i

I I

Figure 8-4 Rod Posi t ion Limit s f or Two .ind Three-Pu=p Oper.ttien From 0 to 100 t 10 EFPD - Oconee 3. Cycle 4 110 OPERATICV 14 II 'I*' I * #

100 - INi$ REGION NOT (2EI I 3 02I ALLCt!3 RESTRICTED REGICg FOR RESTRICTIQ FOR 3 PuuPS E

90 .

(l $1,4,33,7 ) (300,93.2) 3 PtlWP j SHUT 0094 OPER.

80 WARGIN %

u b - Lluli

%? 70

- (50.10) o PERulSSIBLE OPERaithG G0 .

REGIC% \

0 ,

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$0 -

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a 30 -

RESTRICIE0 FC4 h 3 puvP OPERATION L* 2G 40.155 10 -

(0.0:

0I i ' i > > > i i e e i r e i 0 20 40 63 100 120 80 140 160 180 200 220 240 260 280 300 Rod inces, S Witnataan i t f A 3 g e f a 3 0 25 SD 75 ICO 0 25 $0 th ICO Cteup 5 Gr:up 7 r t f e 0 2h $0 75 100 Group 6 8-5 Babcock s. Wilcox l

Figur F-5. Rod Position Limits for Tw- and Three-Pump Operatico From 100 ? 10 to 235 t 10 EFFD - Oconee 3. Cycle 4 110 (164.9 IC2) (259.9.102) 100 -

CPERAT104 tN THIS REGIGg RESTRICTED FOR 3 E l$ 407 ALLCeED W W ERATION

- 10 -

(300.91.,

E a

f 80 -

?

~

1" 10 SwJT00sg utsGIN LlulT - PERutSSIBLE OFEttil4G l REGION 3 60 -

3 50 -

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20 (0,13;

33 15) to - RESTRICIED FOR 283 PLNP OPERAfl0N (2.01 O t i e i t i , , , , , , , ,

0 20 40 63 f0 100 120 140 160 150 20 220 240 260 280 3:0 Ro3 Inces, 5 Estnaraon L t t t . g g , , ,

0 25 50 75 . 100 0 25 50 75 ICO Groco $ Group 7 i i , , ,

0 25 50 75 100 Group 6 l

l I

8-6 Babcock a Wilcox; i

1 1

l l

Figure 8-6.

R4 Position I.intts f a r 190- .and Three-Pump t'ptr tlen After 235 s 10 trPD - ceo:.ce 3 Cvrie 4 110 -

RESTRicito FC4 213 PUWP OPf 8Afith 100 -

(191.2.102) / (218.5.102) e

]. 90 -

(180.6.33.7) 2_

{ 80 -

OrtaAil0N IN THl3 R[Gi m

", 15 NOT Atttet0 y 70 -

bl 60 -

.l r PfRNIS$18L[

a 50 -

OPERATING

= REGION (110,50)

40 -

t 30 .

b

} E 20 -

(48.15) 10 jo.79 (0.0) RESTRICit0 FCR 2 & 3 O , , PUWP OPE, R ,A T ICN 0

20 40 60 80 100 123 140 150 180 200 220 240 260 280 300 Rc3 inces, t, Witnataan I I I I I t t t 0 25 50 75 t 3 100 0 Group 5 25 50 75 100 Gtcup 7 I f f f e

0 25 50 75 ICD Group 6 87 Babcock a, Wilcox 5'

Figure 6-7. Operational Power Imbalance Envelope for Operation Fren 0 to 100 - 10 ETPD -

Occcee 3 Cycic 4 Pc.er, i of 2568 Nut RESTRICTED REEL 04

-19,802 -

- 100

^ 15.102

-22.5.90 - - 90 > 2 0. 90 30.80( -- 80 < > 2 0. 80 70 l

60 i

l 50 40 PERutSSIBLE --

0 OPERATING AEGIGN 20 10 e i e i e i i

  • 50 -40 30 -20 -10 0 10 20 30 40 50 A al Peeer imbalance 5 8-8 Bab<xcic t iVilcox

Figure 5-8. Operational Power ichalance Envelope for Operation From 100 10 to 235 ? 10

, EFPD - Oconee 3 Cycf.c 4 Poser, s of 2568 ust RESTRICTED REGION

-22.102 -

- 15.102

-30.90 - - 90 p 20.90

-38.80 < . . 80 o 20.80 70 60

-- 50 PERN!SSIBLE OPERA TING 40 REGION 30

- - 20 10 l

t t t t e l n t t t 50 40 -30 \

20 -10 0 10 20 30 40 50 j Areal Power imoalance, S '

i 89 Babcock & VWicor

Figure 8-9. Operational Power Inbalance Envelope for operation Af ter 2 32 : 10 EFPD - Oconee 3, Cycle 1 Poser 5 of 2568 Mt RESTRICIE0 REGION

-26.102

^

- - 100

^

39.90 r -

90 > 25.90

-39,80 0 - -

80 0 25.80

- c 10

- 60 PERNISSIBLE OPERATING REGION

- 50

- 40

- 30

- 20 10 I 1 9 f f f f f f 3

-50 -40 30 -20 10 0 10 20 30 40 50 Axial Poser leoalance, i

(

8-10 Babcock s. Wilcox

l 1

i Figure 8-10. APSR Position L1::its f or Operation Frcs O to 100 : 10 EFPD - Oconee 3 Cycle 4

" i io2 Res:Ricuo REGION I, 90 - 19.1.90 80 - l l

1 0 100,70 j

3 g 60 -

O

$0 -

PERMl1Sl8LE d OPERATING

$ 40 - REGION l

30 -

l 20 -

t 0

10 -

e e i 0 i e i i i i 0 10 20 30 40 50 60 70 80 90 100 APSR 5 Witt.oraan 8 tt Babcock a. Wilcox

N i

I Figure 8-11.

APSR Positfon Lie.its for Oper.ation From 100 - 10 to 235

  • 10 UPD -. Nonoce 3 cvele 4 l

23.102 100 -

1 RESTRICTED 90 - 25.5.90 REGICM l 80 - 45.80 l

70 -

l 100.70 l E

g 50 -

2 E 50 -

40 -

O PERiflSSIBLE 30 . OPER AT ING REGION 20 -

10 -

0 '

  • t i e s i i 0 10 20 30 40 50 60 70 80 90 100 APSR, S Witnaraen l

s-12 Babcock s. Wilcox

Figure 8-12. APSR Posit ica Limits for Operation After 235 10 EFPD - Oconec 3, Cycle 4 25.5.102 100 -

RESTRICTED REGION i gg _ 33.90 t

80 -

64.4.80 h 70 -

. 100.70 M -

60 _

'a

,; 50 -

40 -

PERNISSIBLE OPERATING 30 - REGION 20 -

10 -

0 t I t t i e 't i 10 0 20 30 40 50 60 70 80 90 '100 APSR, i vitneraen f

i 1 1

8-13 Babcock a.W Icox a

t

~%

4 9

9. STARTUP PkOGRA.'t -- P!!YSICS TESTING The planned Startup Test Program associated with core performance as outlined below. These tests verify that core performance is within the assumptions of ~

j the safety analysis and provide the necessary data for continued safe opera-tlon.

Procritical. Tests

1. Control rod trip test.

Zero Power. Physics Tests

1. Critical boron concentration.
2. T.+perature react tvity coetficient.
a. All rods out, groua 8 in.
b. Croups 5 through 8 inserted, groups I throc es 4 out.

1 Control rod group retactivity worth.

4. t.jected control rod reactivity worth.

P_ oyer Tests

1. C. ire power distribution verification at approxir.ately 40, 75. and 1301 f ull power with normal control rod v.roup configuration.

2.

Incore versus out-of-core detector imb.slaace correlation verificat t.on at less than full power.

l

3. Power Doppler reactivity coefficient at approximately 100% FP.

4 Temperature reactivity co(f ficient at approximateJy 100I FP.

l

)

4.-._..,.._

, REFERENCES 3

Oconee Nuclear Station Units 1, 2, and 3 Final Safety Analysis Repert, Docket Nos. 50-269, 50-270, and $0-287, Duke Power Company.

2 Oconee Unit 3. Cycle 3 Reload Report, BAW-1453, Babcock & Wilcox, Lynchburg, Virginia August 1977.

3 Oconee 3 Fuel Densification Report, _BAV-1399, Babcock & Wilccx, Lynchburg, Virginia, November 1973.

Program to Determine In-Reactor Performance of B&W Fuels - Cladding Creep Collapse. BAV-In084, Rev. 1, Babcock & Wilcox, Lynchburg, Virginia, Novem-ber 1976.

C. D. Morgan and H. S. F.ao tan * - Fuel Pin Temperature and C s Pressura Analysis, BAW-10044 Babcock & Wilcox, Lynchburg, Virginia, May 1972.

ECCS Analysis of Bau's 177-Fuel Assembly, Lowered-Loop NSS, BAV-10103, Babcock & Wilcox, Lynchburg, Virginia, June 1975.

7 Safety Lvaluation by the Office of Nuclear Reactor Regulation Supporting Amt.ndrvat No. 14 to Facility Operating License No. DPR-54, Sacramento Munic-1,41 Utility District, Rancho Seco Nuclear Cencration Station Docket No.

50-312.

A-1 BabC0ck & Wilcox e

i

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