ML19322C157

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Cycle 2 Reload Rept, Revision 1
ML19322C157
Person / Time
Site: Oconee 
Issue date: 04/30/1976
From:
BABCOCK & WILCOX CO.
To:
References
BAW-1425, NUDOCS 8001090567
Download: ML19322C157 (50)
v • d • e


Text

cd06 E BAW-1425, Rev 1 l

April 1976 l

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OCOhr.E UNIT 2, CYCLE 2

- Reload Report -

Revision 1 l

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8001090$[7-

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"n*-! ?.2 5, 2ev 1 April 1976 OCONEE L' NIT 2, CYCfA 2

- Reload Report -- '

Revision 1 BAPCOCK & WILCov Power Generatfor

.oup Nuclear Power Generat ton Division P. O. Box 1260 Lynchburg, Vir;; inia 24505 Babcock t.Wilcox

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P.t ce

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INTD JCT!s.?. AND St?J*.iRY.

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. ri egy

-$_ t 3

1.

.rNO.il. Dr.4GIPTIt1N 3-1 4N! SYS TFJ: XSIGN.

'. - 1

.meably....w hanical Desi.n 4s ruet

'.2.

Fue! ?.J Pesign 4-1

-. 2.1.

r!ad4!ing Collapse 4-1 2...

cisddine Stress 4-2

". 2. 3.

Fuel Pellet Irr.ediatien Swelling 4-2 4

. yher it..iesign s

4-3 1.1.

Power Spike Model..................

4-3 3.2.

Fuel 'iv perature Analysis 4-3 a.

>*a t er i 41 Pesign 4 - /*

..).

0; era t,.ng 1.xper.,ence 5.

NCC',. EAR DESIGN..........................

5-1 t.I.

Physics Characti.ristics 5-1 3.1.

Analytical Input.

5-2

~.3.

Chaneer in Nuclear Design 5-2 c.

T Hi*C'.A1.-11YD.ul't.lc DESIGN 6-1 n.;.

Ther=al-liydrauli. De.4 tan Calculat ions

'6-1

  • >.1.1

.ntroduction of Mark L-4 Asse-blies 6-1 6.1.2.

Increased RC Systen Flow.

6-1 6.1.3.

MW DNB Correlat ten 6-2 6.2.

DNBR Analysis 6-2 7.

ACCIDENT AND TRANSIE.'.T ANAt.YSIS 7-1 7.I.

General Safety Analysis 7-1 7..'. Red Ulthdrawal Accidents 7-1

7. 5.

MeJerator Dilution Accident 7-2

?.4 Cold Water- (Pum;i Startup) Accident 7-3 7.3. -I.oss of Coolant Flov.

7-3 J

7.6 Stuck.7ut. ' Stuck-In. ur Drs;';.-d Control Rod '

7-4

~

'7.7.

l.oss of Electric Power.

7-4

-l 7.9.

Stean Line Failure-.

'7-5 7.4

.Stean Generator Tube Failure...

<. -. ~.........

7-5

- 7.10.. Fuel Handl ing Accident 7-5

'l 7.11. Rod Elcetion Accident 7..

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Page

'.12.

'!axi,n litpathetical Accident 7-6

'. I 1.

  • a.. t - C is T.:nk Rupture 7-6

'.l..

!/AA Analysis.

7-6 i.

'FOPOSED !Pulf1CAI!ON:3 10 TECli';!CA*. SPr.CIFICMION3.

8-1 a.

STARit'P PROGRAM.........................

9-1 L

L h

R1.FE5'ENCES A-1 l

1

.f e

I_i.s_t__o_.t' T_a_b_.l_e_s

- lable 4-1.

Fuel Design Parameters.

4-5 4-2.

Fuel Re.1 Dinensions 4-5

- 3.

I n;>u t Sur. nary f or C;..dd ing Creep t'ollapse C alculations.

4-6 4-4 Fuel Thermal Acalysis Para.teters

'6 j-5-I.

O.ence 2. Cycle 2 Phy les 'arameters.

.5-3 1

5-2.

Shutde a Orgin Calculat ion - Oconee 2, Cycle 2 5-5 6-!.

Cycle i at:J J."a>:lena Design Cond it ions 6-4 7-1.

Compariwa of F.ey Parameters for A,:cident Analysis 7........

1 4

1 I.ist of Figurg i

Figure 3-1.

Oconee 2. Cycle 2 - Core Leading Diagram.

l 3-2.

0. onee 2 Enrich.ent. and Burnup Dist ribution for Cycle 2 -

'3-3 3....

3-3.

Ocence 2. Cyc le 2 -- Con trol Rod '.I.ocat ions

........-.n.

3-5 4-;.

!!a.s.inun C.ip Size Vs Axial Position - Oconee 2. Cvele 2.

4-7

- - 2.

Pow r' Spike Factor V.* Axial Pos it ion - Ocenee 2., Cycle 2.....

4-8 5-!.

I;Ot" t ! EFPD), Cycle 2 Two-Dicensional Relat ive Power Distribution Ful l I'ower. Equ i l i br inn y,enen. ';orma!

l<od Po* l t ions tdroupy 7 and d Inserted) 5-6 5-1.. Oconee-2.' Cvele 2 - Core Protection Safety 1.inits

'8..'..... -

s-2.

Oconee 2. Cycle 2 Core - Protec t ion Sa f ety 1.imit s =.~....

S-3

- s-L Oconee '2.

Cveleil - Corell'retect ion Saf ety I.f r.it i

'. L.

8-4

' 8-4

Oconce Cycle 21-Protective Sy tem M.ixitus Allowable

~

4 Setpoints:

8-5 s-i. ;Geonce 2,'.CycIs~2 i Protes.t ive Syr, tem.**.ix f run Allowable t

Setroints 8-6 cN

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T a

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Eevision 1 (4/3s/2o)

Pigures (Cont'd) i Pa,e Fi.;ure 8-6.

Deenec 2. Cycle 2 - Rod Positica. 1.inits t er Feur-Pump operatien Fron O to 150 (:10) EFPD.

3-7 5-7.

Oconee 2. Cycle 2 - Rod Positien Ei=its : r Four-Pu=p O eratten Fron 150 (110) to 261 (:10) EFF3 S-S P

8

.4.

Oconee 2. Cycle 2 -- Rod Por.it f en Limits f er Four-Purp Operat ion Af ter 26 7 (

  • 10) EFPD 5-9 6-4 Oconee 2. Cvcle 2 -- Rod Posit t en 1.init s :Or T.o-and Three-Pu-p sp. rat ion Fron 0 te l'U (t10) EFPD 3-10 g

8-10.

Oconee 2. Cvcle 2 -- Rod Posit ten I.init s ::t Two-and three-Po~ Operation Fren 1 30 (-10) to 242 (*10) EFF3

!-11 3-11.

Oconee 2. Cycle 2 - Red Pos it ten 1.in i t s fcr Two-and Thr ee-Pu ;

  • T;*. rett i.'n Af te r M 7 ( ' 0) E FP.n 6-i~

l 8-12.

Oconee 2, Cycle 2 Operation.i; Pew. r : h: lance Envelope for Opern ien From 0 to 150 (*10) EFPD.............

2-13 R-13.

Oconee 2. Cycle 2 Opera t ion.. I "ower I:-l'... n c e Envelope for Opera:!cn From 150 ( 10) to 2 t>7 ( 10) EFPD.........

S - l '.

3-10 Oconec 2. Cvele 2 Operattonal Power Inhilanc e Envelope for Oper.i:ien After 267 (210) EFPD.

8-15 l

l l

Babcock 8.Wilcox

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IURODUCTN!. 2;D Sat \\RY This r. P.>rt j us t a t' les the operation ef the sect nd ey:1-t' ente Nuclea r Sta-s tloa, Unit 2, at the ra t ed cor. ;: owe r o-

.'A9 W.

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t! e required

.ina l sea out!!ned 1 :.. iie US E C doeure--t s i d i r.. e i : ':. m.d I... r we A.,e n d -

Felat ing te Ref ueling," dated

,. 1975.

To.

.ents r

de 2 eperation

?f Ocanee Unit 2, this report ep10vs.in.ilytical t.

iquss nj.b ign b..ses es t.ib i l ihed in reports t !.a t have been subnitted 2nd

..e ited by the LSSRC (we reterences).

Cy.le 1 and.' re a.' t o r p.t rane t e rs re : et.d to pm.;er c..

bi' t-are..=rirized bri.ily in seetion 5.

/d I the aceident, a n a ly. icd i r. -hs FS?G :t rce been re-vie.ed for cycle 2 operation.

In casss where cycle - -har ae:crist ic > preved to 5. 0nservat ive vi: h re spec t to these analy d for - cle ; cperation, ao n c.-. ice t.len t.inaly+cs were perforned.

The Teebaical Spe:1ficatians have be e:' reviewed, and

. red if icm t i:ns re-quirad ter cycls-2 operation are justified in this r port.

Based o.

the an2174es p( r fo rr.ed, whicii take inte ace;;nt the postulated ef-f ecta o f f uel densificatica and thc Final Acceptance Crite ri.: for E ergency Core roa!Iag Systems, it has been concluded that Occr-' 2, cfcle 2, can be operate 1 afely at the rated core level of 2%S Vit.

l 1-1 Babcock & Wilcox

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cien 1 (;/ 3 /76) 2.

OPERAT!!;G !!1 STORY Unit 2 ci the Oconee !;acle.ar Station achieved init ial c rit icality en ';even.ber 11, 19 7 3. and power cc.ila t ion ce= enced on Dec-nw r

'873.

The ICC" pw er le.el e+ 2 569 mit was rea ia d on Juni-19, 197L.

- :ontrol r._ interchance was perforr.ed at 248 effective full-power days (EEPD). The fucI cycle w.u l

t errif r.at ed on Apr il 7, 1976, after 440 EFPD. The first cycle involved no operatine, anomlics that vould adversely affe ft.el performance during the second cycle.

Operation of cycle 2 is scheduled to begin in early. lune 197e. The design cycle length is 306 EFPD, and no control rod interchanc.es are planned.

l1 I

2-1 Babcock s.Wilcox

1 C.~.NEML D'.SC?. IPI IC';

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'c. w e aut : reactor core is described in le: il in Ch.pter 3 c: t he Unit 2

i FM.

TN c.r l.' c e r t cens:sts or l'7

.c la

'11".

'7' whic h are e

15 5

~ a r r.sy cmita in ing 208 t uel rod.4, i' "tra!

.:.;u:Je t bes, and one u t r un n. g,a id e tube.

The foei r ai

. W i 4.-

is a l 1-verk._ I

?. i rea lt e. -

4 m

4 i;h e O? :

0. 30 inch and.. vall t hi. knv.ss 3.

2t3.

h.

2e fuel c a n i., t., of dierJ-end, cy!!ndrical pelleti : uriniu-- Cie:sice whic s ne 0.709

n c c. In !enctl. an.1 1.370 i m-h in diameter.

". 5 e s

!.3,le t '. - 1 a n d '. - for addi-tior.a! data.)

The other two f ue l a s.ie.T.h l i e s in eecle 2 are i:eron.2 ration 17 h l'

'.rk s fuel auc-blics.

All fuel ac.. Mies in c.c'.

2. xceat the 17 hv 17 d..

o:.s t ra

  • ca a s s e.-b l i e
  • raintain a constan:. neri,. : :: -1 l e..d ia.; of M 3. 6 kg 0: u ra r. ; un.

The undensified nominal act!.s fue' t e.u : h s and (teor._tical dvn-

i. c5 2 r.

he.,e e n N t c hes, bewecer, an.1 t r. sc i.2es arc

...n in Iables

.-i i n u,

, -z.

FIN re 3'

ic the core inaci ang di inram fer i:onee ini-2, ele 2.

The ini-tea! enr hnents of batches 2 ar.d 3 were

.'.'5 and

't.0,

.t ur1nirt-213, re-

u t ice v.

Tatch 1 it enriched to 2.6'. vt u r a a i r.-; 3 5

.u l tne batch I u s. 0. i e s t11 de discharged at the end of cycle i.

Te batch 2.*ni 3 as-sd::s.ili he =.huffled te nev locations.

The u te - as.cebiles will oc-ce;

ri ar
!- the ;:cr iphe rv ef the core and eigt! I r.tions in its interior.

F1 ;nt e :_ ts an eighth-core r.ap showing the

1. sc=bly burnup and enr ienment diitr ihtien at ne be. ginning of cycle 2.

Lattivit, control is supplied by 61 ful1-lergt h A:;-In-C.i cont rol rods and T o l u'a l e boroa

r. h i.,.

In addition to the iull-ene.tn s.ntrol rods, e i,:h t par-t ia l-Ics-t h ax 2ai pever shaping rods (APSRs) are prwe. wd lir auditi na! ce.n-trat oi utal power dist r ibution. The cvele.' locati^,s of the 69 c ontrol rods a n.! the group designations are indicated in FI:;ure 3-3.

The cere loca-tions er t r;e total pattera 69 control rods) for cycle 2 are ident ical to those c: the refsrecce cyele indicated in C5 eter 3 c: t i.e FSAP.. I

!awever, 3-1 Babcock & Wilcox l

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c.r e u; J.'s ! gacit ion,,1 i. : er Lt.een cyc !.

2 a r.d i h.

r.

. r. i;c

.cle e nint-tice p wer re.iking

' t.hrr u..r t r... ' rcJ ir.: cre rui,. nr

.:n;ible pai-mn rods ti r e r.( c e ss.a r v f or cyc le 2.

The no.i n.il s stem p r e w : r..

i 2 2f,9 p.;i s,.u d t he. ore

.-r.- densitied r.cni-

/

tu l neat re.-

i.; 5. 7 4 k *i ' ' *...t th.'

ra:ed nre pos. r o f -

s %t.

This hea:

rat + is sli.d.t!y hi>;he r t2iin that of cyc I - I bec.tuse of sherter stack he i >i t ot b. itch 4.

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Ocone.- 2. Cvcle Co D.,d i r : Di i tra.

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Fi:, tre 3-2.

Oconee 2 Er.r ichment aa,1"Ecrnup Distri/nica for Cycle 2 8

9 10 11

!?

13 14 15 2.75 2.75 2.75 2.75

. 3
3.,,5 3,o5
, <,4 d

11,9 %

16,711 IG,2d2 Iti,941

11. A0 li,9 -

10,695 a

r l'

l 3.05 3.05 f

i P

e.,,

a.64 2.73 2.75

2. *i4 11, % 9

!2.001 13 '494 0

14.451 14,137 0

i

2. 7 's 2.75
3. r,3 2.75 2.64 2.64 f

16,941 37,203 11.233 14,631 l 0 G

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3.03 3.05 3.05 2.64 l

  1. 31.3 10.267 78o4 0

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2.73 3.03 2.64 i

+4 l

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7323 o-t I

g 2.64 0

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R xxx Initial Enrichrent' xxu ECC Eurnup, ::'?d/ntU 3-4

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,e 4.' FCEL Sh a TESIGN i

'.. l. Titel A2.se9 1v Mechanical Desien

~ Pertinent fuel design paraneters.re lis:cd In Table 4-1.

All it:e1 assemblies are - echanic illy interchanceable. 5 z: the Nirk C Jenonst rat lea asseslies can-

c. t 1e located in 1 rodded locatien.

. ;.e

,- new M. irk ~-a fuel a<<en31ies incor -

a f

4-

. perate minor nadit icat tens to the end ' t: tines, prinaril-to reduce it:el assen-4 b; prem:re..!rer and increase holdde., arcin. -Two ef the 5'. N r k 5 4 reload fue. asse-Skies were especi slly censt ru :ef :a exa:-ine :- e ef fect en rod bow of ; a1:ioning t e inel. red : 0.6 inch a'e x :he fneI aos r.51-de::ec c;i11.ege.

N TSis reposittening of the fuel with respre: o the lews:.nd fit:in. aficets echirical operating parameters with : % possible exespriea of red bow, ne i

.tich nar he itecreased.

In addit ien, rse ~::ienine the :uel <!:h:n :'re two f t.e : assc hlies :.ill not dect. ass-fu.

a - W. v inteeri:v a.srin.: acetdent con-di: i nns.

4tandird :* ark S fuel rods are u"

. ar.d the

're and fune:icn ef these t wo i nc t a s-tenblies ts:ain identic_. :s ibe sta:Jard "ar( E. feel as-se 9 '.tes.

The tra denonstration 17 * - !' 5 ri C furl. m rblies e.re described-in re fe re:'re '.

P i

a j

Til othsr results i, resented in the FSAR fue a s.ser:b l y neehanical discussion are applicable t.- the rele d fuel assenblie$.

4.d.

ruel Rod Desien J

Pertinent fuel i ed di: ensions for residua! 2.nd new fuel are listed in Table 4-d.

The mechant al evaluation of the fuel rod is discus ed belev.

4

..d.:.

: ad d i t,.

co l l. alls _e.

Creep.cellapse utalys.9 wer e performed fer three-ey.1 ' tuer.hiv rowe r - $i. tories -

for econec 2.

table 4.i is a tur:.arv c: :k Sat ch e

1. asd *. - f uel red de--

sic t.. The fuel'..ssenhiv power histor ies f.cc.inalyze J. and t he e.est limiting j '

shiateries were de:ernined.. Specific asser5:r power histeries were use! in th'e Lanalyses of batei.es-2 and '1.

Batch a was a.r.lvred.usinc a. conservative phwer histery envelepe.

'.',etual ;cerat ine h! ite-v..a.: used wSe-available. :: hts

- i 21

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+

c e

s 3

t 8

w h visica 1 G/30/76) i cli: led the initial pc.cr operiri -

  • 40 ani S? c

. ore v.er.

The predicted e -er.bly power hi.tcrv ter t !.e :-,:.1:-i t in; a us.-bly v..

,cd *.o det rnine t'e vn t liriting cellapwe tinc. a<

fe. crib.d

.n T.L'-l

. T TS. 2dOO-heu-.icns if ie st. sn as st p:ic a descrii s u i n re r s. ; e-- e 3 us used in

e analyni" -ince it rerelents the

,w t

..e t r e condi-i..

.te con 4e rva t isns in he ana ly : c al p roc e.it.re.a re 4 ;-- s r i ::. d be l.'w.

I.

W.%0V e":t er s oJe ev sed to predict t!'c ti.e to collapse; CF conuervi:

c'.

rr : ;, collame r I:rea. 3 2.

';4 :redit i-

  • Jen f or ; e; Nn p.is r lc.ip.

T' ref re. the r.et J;

' n t i.. i

.utes

-.4 d i. t h.

a 1.ilvsis

..r.

-erva:ive;y hir.h.

.m s.'

1.n h! i..

ti t 4! w-i ; :%.

.. c r t o l. r ex.; limit C.!L) of e rm s

L is -b. i l t -

a g en:.

IEe in.. 1 cvalIt.

t he c lad.* in.: wied was t ':-.

on.-

.. r.4 : c e. : m.i 10 T:. ) e: :ne a : il: cas ure-vnt s.

Ti.< %

v.i l ae s

..Je t Ren :' r.

  • a s t a t i-: ! c a l

-ir' I l et the.-? adding.

a.

A e rnre rv.it i.

.er his:

r.

envele t.c t s n.ed :n : e bitch fuel ann:vs;s.

The

.w li.ittne..:

e.o, t'

und

' h.w e 1 liapse t:rc creater

?.an the r i <;r u proi., s e t hrt s le !itst! e of 2 '.. a l.'. f f e:- t i. c :::I T power 5.virs l1 (v

Ta ', ;. '. - :.

it is

. was sn,.rferned : - i c ;- the r-r-- t ions on densi-i::en de.er: ed m rs :es n e 3.

". 1..

(_.i d_1_._

. t r_e_s_4 S; e,

he bat.. 2 ar.d 4 i's the ce

? i m i t :.- f r em a t-!x iiu strt" point

.f

..v eio te :Fe 1, w.n cre;rer.wrici icn and '

-deanit.. -te ca lcul ations

.-- t ed in t e we:me uell aemili c at ion Feart. SL-11 U, " represented

  • ..: I I-i t : n -

c e-.

i Noace 2. cycle 2.

Iue:

!!ct ! r

..i t I, i Swe 111 :-

a ibe - o l (* i si m c r i t e r i.i (.ity a li-it of 1. en claddic-,1 cunf erent ial plc

.- 'trair.

P:o pe!!c' d.

it:n is

ch thu : e tila s t i - e!aldin: strain is I c., 4 :nsn 1:

e.

3,000 ' C1 ' t r The

.II" wine - :w rva t i a ere used in this anal:..is:

i The ex:no,,~

l a: icat ien v ilar fer th tel pellet lia eter was used.

i 2.

The

c. i r. m ~ ; e.. : icatien v.1;e fer : % :ue! pt!!e: de u i t y wa s used.

l The c : add ine I!'

.e ! was :Fe..wes :

p..- :i t :cd,nv ir i 'at ion, tole rance.

4

'lhe iximum o.r.s - ? three-c'.c!c local at Ilet ?n n : - is less ti2n

%.0

. %.i/et t Babcock s. Wilcox

___-_-__-J

  • . 3.

(hern al Design, f.e cure loading for cycle 2 operation is shown in Figure 3-1.

There are %

f re<.h (batch 4) fuel asseribiles and 121 once-burned (batches 2 and 3) assen-blies.

Two of the freah assenblies are Mark C. 17 by 17 demonstratien fuel:

these were not considered in the thernal design analysis since the core een-figurat ion would be r: ore linit ing it' they were not present.

t he t her:ul de-i sign of t he two Mark C denonst rat ion assenblics 15 described in a separate repart.? The two Mark B-4 IIfted rod demonstratica fuel.scemblies are ther-1 nally identical to the otner 52 Mark 3-4.nssemblies and da net require 8e;'arate a.u l y ne s. The latch 4 fuel has a hir.her initial theeret ical density (TP) ni 3

f a cerre.ipondingly higher linear heat rate capability (Jn.15 Y.s 19.8 k2/ft) t5m the Nat--h 2 and 3 fuel.

The.<e linear heat rate linfratiens were established n+ine the TAFY-3 coele 5 with full fuel densificatien peralties.

1

5. ll.1.

l'ever Spike Model The power spike nodel used in this analvsis is identical to that presented in El.%-LOO W except f or two nodif icatien4: t he nodifications have been applied t c. F and F. as described in reference 7.

These probabilities have been g

i chane.d to reflect addit ienal data f rem operating reaeters that. support a A.ernat dif f erent appreach and yie!J ls.s severe ;>ena l t i e < due ta pever 4; :id.

j F wa. i !:anged f rom 1.0 to 0.5.

Fk was cha:tged : rnn a daussi.m - to a !!near g

d! 4t ribut ion, which ref lect s a decreasinr, frequency wit h increasing gap size.

We axic".m gap size versus axial positten is sho.n in Figure 4-1, and the pu cr spike facter versus axial position is shown in Figure 4-2.

The calculated pct.cr spike and gap si.te were based on an initial theoretical density cf 92.5; and an enrichnent of 3.0 wt 2 uraniu :-235.

The correspending values for the b itch 4 Mark 11-4 and Mark C demonstratien fuel would be scalier becat..re of the increased depsity and lower enrichnent of this fuel.

4.1.2.

Fuel Tenperature Analvsis Therrut analvsis of the fuel rods assuned in-reactor fatel densifleat ton to 9h.E.10.

The basis fer the analysis is.;1ven in references 5 and 6 with the j

fo!! ewing nodifications:

1.

The cede. opt ten for no restructuring of fuel has been used in this analysis in accordance with the NRC's interin svaluatIon of TAFY.

-3 Babcock & Wilcox

2.

The calculated cap conJuctance was rsducc.! Sy 25*. in accordance with t he ';F.C 's interin evaluation ci !AM.

During cycle 2 operation the hip,Sest relative asse-3::. power levels occur in batch ) fuel (see r i r.ur e s 3-1 an.f 5-1 ).

":e fuel t.mperature analytis fer this fuel doeurented in t he Oconec 2 rael Den 41: f ca:Ien % por t '* is a;'plicable for cycle.'

d is based on 1initing 30C con if t f on. (cers burnup), as shewn in Table '.. Although batch a fuel 1.as a rehiced.ictive fuel l e:'.,t h and a cor-res; send !. ly hir,her ave rage linea r f. eat rate, tne

.ni:,un pred ic t ed. enter !Ine tenperattre of this fuel is lo cr than that of batch I f':el, even *.ith the

s. a.~e pea-in? f.ntors ipplied.

this 14 due to t ne hic :..r initial den +1t'.

of 5

the b.ttc.2 '. fne1.

?'m.ria! D :i.'u The, ae n '.

.J. c.cpat i bi l l t '. of a ll possil' h

'uc l-c i.id.: i-n-c eola n t -a ssenbly inter act. :ns fer t'.e batch. fuel.i. c.-b:!cs is id.'.n t i ca l to t. h. i t of the pre.s-ent fuel.

.. i..- -.0.:.c.r.a.t.i c a E:<ro r i em e a

'he " ark 3.

'..e 4ms i l. s and N rk ' de e i 4 t : at ion a ih '.l ie. do not co...Itute a d.partu:~e from past eb si.:n ;+il.sepice, t h.

ade ;uac: o f U t h h is 'r.+cn der.,n-r

,trated

- t !.e o; er..t ion of six I?7-f'i.I a se.5 '. pl.nts.

4.

Pabcock s. Wilcox

Re e is t os. 1 (;/30.'76)

Table 4-1.

ruel Desien Firanaters Re.41 dual f e.1 a s s e-b li e s

.;e fue.. asse=blies Batch 2 Bitc5 3 Satch 4 ruel asser.bly type Mark 3-3

".rk 3-3

" ark E-;

Mark-C

?;o. ef assenblies 61 6) 54 2

Initial feel enrica, wt !. I SU 2.75 3.05 2.64 2.64 Initial fuel density, 2 TD 92.5 92.5 93.5 94.0 Initial fil!,;as pressure, psig (a)

(a)

(a)

(a)

Batch Surnup. 50C, "Wd/ctt 16.11) 10,11;.

0 0

l1 Cladding collapse time. ETPl!

25.000

\\ 2 5. :.0 y 5

'25.CC0

'25,000 Des!.;n life, EFPH 17 '3 0 +

21.9*2 21,160 21.300 l1 (a)Preprietary.

(h);.nch 1 is ecst limit tne,.

Table 4-2.

Ful h3 Di ensiens

  • w fuel. Sir:S 4 Residual :.ael.

bateSes 2, 1

!! irk E '.

"ari C dero Fuel rod OD, in.

0.430 0.430 0.379 ruel rod ID, In.

0.377 0.377 0.332 ruel pellet OD. tn.

O.370 0.370 1.32;

)

Fuel pellet density.

TD 92.5 43.5 41.0 Undensified active fuel length, in.

144.0 1*2.6 143.0 type of flexible spacces Corrugated Spring Spring Solid sp.icer natorial

Zr0, Zr-4 Zr-4 4-5 Babcock a. Wilcox

T.6 : e '. - 3.

ut su narv for Clad!!r - Cn er C,1:a-ce Ca lcula t ter.s Mark C demo fuel 3a:r' es 2.

3 lutch 4 asserblies PelIet P.'

(rean sa c i fied), in.

J.17'O 0.3700 e.3240 Pellet d.nsity (..m specif f ed),, TD L'. 5 93.5 94.0 Densifie-J pel:et C?, in.

').1450

0. 3t>6 3 0.3213 Claditi n : ID (ne;n pecificJ), in.

'37' O.377 0.312 Cladd!ne iva l i r :. (*JTI.). in.

C la.!d i n.; : h i.:* ns % tiTL), in.

prepren nie (-inimun.gecified), p.sla

=

Post -den 4 i f ic.t ien nrer rem:ure (cold), p,ia Reactor

-vete-p re < < u rer, psia 22 0 2200 2200 Stack he.:ht tuadensteted), in.

I ; '.. C 142.6 143.0 O l' rop r i e t a r y.

Td : e '. - 4.

l'uel Therr.a t 6 1 414. a r ire t e r:;

J,tShes 2 3 E.atch 4 E ntr.22 l i r e.. r S a t rate, kW/ft 5.77 5.80 l'en-:;ised acti u (u. l length, in.

111.1 1".0.5 I. i n. a t heat rate (153) to central fuel nelt, kW/ft 19.5 20.15

!!ot e5 anne: f actor en lilR 1.014

1. 01 *.

Initia: TD

  • 92.5 93.5 Initial furt pellet 03, in.

0.370 0.370 Avg f ue l t i.,' d neninal I.liR F 1335 1311

) 110L "). F SC30 5080 I

l'uel centerlire ne t t i n,-

t e rap (a)At zero burnup.

e.- 8 Babcock a.Wilcox

R m-N O

G

  • " N m

eg

    • A C

Pd C

C O

C t

C e

me

=

  • 2l t

C a;

A

~

C C

==

m C

o

=

2 C

4 TD

.e.d 2

Q N

A C

==

Y.

Q

,0

~

C=

st

,~2 G.

Ey o

N

-r m

i st NNN L

sn.@. O C

h.

CN

=

wem w

a N

A L==

  • s a=

t* H I

e i

g C.

C.

C.

C.

O m

N

. w ss iteu urui n u saipu i 4-7 Babcock & Wilcox

O<

ee G

teh O

U e4 te 1

b N

~

O I

_ c

~

=

.4 ese

't O

C~

.a.

Q C

sue

. cr.

~

x

~e e

  • r C

0

  • e

~-

?

  • J 4

f c

L 1

A x

  • 7W
  • C b

i D

L O

4 Fe s

s N, N

\\

=

C.

.O l

SA e

e.

T Tr O

~

M n s a

  • - y

=

u w

P.

.O i ~ i*

I t

t 1

o r

e o

e C.

O.

C.

2..pta.m pts.ia.ed

.. a Babcock r.Wilcox 1

5.

Sl'CLE\\R DESIGN i.1.

Ph esics Characterist ics

.abic 5-1 compares the core physics paraneters of cycles 1 and 2.

The values-for both cycles were generated using PDQd7 3ince the core has cot yet reached

..n o;uil ibr ium cycle, ? :f t erences in cere.. ~ I t., para. tera are te be expected between the cycles.

The shorter cycle 7 will produce a snaller cycle dif ferential burnu? than that for cycle 1.

The accu =ulated average core burn.p w111 be higher in cycle 2 than in cycle 1 because of the presence of the once-burned batch 2 : 3 3 fuel.

Figure 5-l illustrates 2 representative rciative pcwer distributice for the beginning of the second cycle at f ull power with equilibriun xenon ind nor=al rad p;sitions.

T:ic critical baron concentrations for cycle 2 are lower in all cases than for l

cycle 1.

As indicated in Table 5-2, the control rrd worths are sufficient to caintain the required irutdown cargir..

liovever, dye to changes is isotopics

. tad the radial flux distribution, the BOC hot, full power control rod worths are generally less than those for cycle 1.

The cycle 2 ejected red worths for i

the sa=e nu:ber of ra;;ulating banks inserted are lower than those in cy l c e 1.

it is difficult to comp tre values between cycles or between red patterns since neither the rod patterr.4 from which the CRA is assened to be ejected nor the tsaturic distributions are identisal.

Calculated ejected rod worths and their adherence to criteria are considered at all times in life and at all pcwer 1cvels In the developeunt of the rod insertion linits presented in section S.

The naxitun stuck rod w rths for cycle 2 ate less than those in cycle 1..

The ada.;uacy ot the shutdown margin with cycle 2 stuck rod worths is den:nstrated in Taote 3-2.

The fo11 ewing conservatisns were applied for the shutdown cal-culations:

.l.

Poison nateria: depletten allevance.

-2.

101 uncertatutv on net rod worth.

3.

Flux redistrIM' %n penalty.

5-1 Babcock a Wilcox

-' elsion 1

(.* M/76) r.Ite.tr.but;un was accounted for Flux slace the shutdeva ar it ysis w as calcu-lat e d u s i r;; a t wc-di s. ns f or.a t no.!el.

The :,hu:dewn calcc; 2: Icn at t' e end of cycl. 2 I-a. a ; y: n. at approxtr.ste]y 267 ErP3.

This la :he latest tine I

(i 10 days.* in ccr. 1110 at which the transient baak 1. near. fully inserted.

t After r'3, : '. e transient bank will be ainost fully withirawn, thus in:reas-

.n i ny, tna r.- ::a tae 1.uteava cargin. The r e f e r,. n. e t ue l c:.c !. shutdo t rarp,in i s ;ireacat -i i c. :.e 3:once 1. 2. and 3 F$/a. Tele 3-5.

The r>cle 2 ;;w.er deficits f rcn het zero power to hot full p.reer are sinilar to but uhtis ". :. h e r than those for cycle 1.

Ooppler :sefficient.4, -elerator cociticicn S,

.r

.s r a n we r t h s a re similar for the tw c::les. The litfcren-tial 1. orc, wert,
r cycle 2 are lower t han
:use for cycle i due to lepletion of t:. f i.e l rd
  • . e saciated buildup of fissi.:n products.

The effective delayed c ;;rca ations for ho t ;-. cycles sh ce t l acre.-

41.

burnap.

?

5.2.

1.na i": i : i ; in ut the cycl 2 i v. r u.etsarenent ci!colation cen,:.m at - used :or conputing core power i t u r i aut i.n : w e r.1 prepared in the sare ar.ne r ar. fr the reference cycle.

i. 3.

Caa. s in !..-Isar Desien T1.ere are. ur a ;;st r n ien fuel assenblies in batch 4 The tw 17 by L7

! ark C ac.cnstrat
c. ?act assenblics have been shown to have at-significant effect

'n :. nuc b ir leaiga of cycle 2.2 The rotenti2; f ~ r e. s i rafued fuel rods (0.6 inch above the lower cod fitting prilla;c) cn tcc

..; car lest.;n and safety analysis of Oco.ee 3, cycle 2 Fas t,ee n r e. i s..u.

_i._e en t:. twa fuel issen5!ies v:th raised fus i rods are being inserted in

h._ c te ac part of batch 4, the inpact on th cverall nuclear p.i r.ine t e r s is ne,-11;ible, and no addit ional analysis is repirei. Further-more, no al ditien ti restricticns on the placenent of these assenblies in the cote are ncc2ssirv.

The same calcalatia al re: hods and design infer:ution were ; sed to obtain th inportant 12: 1 ar dc:

e 4ipn ;iarancters for cycles 1 and 2 In acdition, there are no ri.;ni f icacit c;erational procedure changes fron the reference cycle with regard to avial or rc e i :1 power shape control, >.enon cont rol, or tilt er,ntrol.

Tne opera tional 1:ni: s iIcebnical Specifications c t.a nge s ) fer the reload cycle are shown in <ectinn 3.

5-2 Babcock & Wilcox

Revisien 1 (;/30/76)

Table 3-1.

Oconec 2 Cvele 1 and 2 Phvsics Para ners Cycle 1(d)

Cycle 2 *)

I Cycle lun4th, IFPD 460 306 Cycle burr.up, Mk'd/mtU 14.396 9582 Average core burnup - EOC, Mk'd/=tU 14,396 18,606 Initial care loading, atU 82.1 82.1 i

Critical beren - BOC, ppo (no Xc) il2P(a), a:: rods out 1634 1445

!!i'P. group 2 7 and S inscreed 1494 1330 l

liFP. grenpa 7 and S inserted 1332 1140 Critical horcn - ECC, pre (eq Xe) i H2P, all r^ds cut 480 434 lirP, group 5 (37.5% Vd. eq Xe) 180 87 Con:rol rod verths - liFP(s), BOC, %ak/k 1

~j Group 6 1.58 1.20 Group 7 0.99 0.96 4

Group 8 (37.5% Vd) 0.44 0.54 Cont rol rod varths -- !!FP, EOC, tak/k j

Group 7 1.37 1.33 1

Group 8 (37.5% vd) 0.26 0.51 "2x ejected rod worth - liZP, 1*.k/k 30C 0.4S(C) 0.59(b) 1 EOC

0. 72 (c) 0.5S(b)

Max stuck red worth - ItZP %Ak/k BOC 4.27 2.16 EOC 2.69 2.22 i

Power deficit, Ii2P to !!TP, %2k/k SOC 1.32 1.65 EOC 2.10 2.49 Dcppler coeff - 50C, 10-5 (ak/k/"F) 100% power (0 Xe)

-1.51

-1.51 Doppler coef f - EOC,10-5 (ak/k/*F) 103Z power (eq Xc)

-1.67

-1.55 j

"oderator coef f - IIFP,10~~ (ak/k/*F) l 000 (0 Xe, 1000 ppm, groups 7. 8 ins)

-0.23

-1.03 4

4 EOC (eq Xe.'17 ppm, group 8 ins)

--2.70

-2.60

&?rsn wartii - ETP. ppat iak/k j

40C (1000 p;=)

98 109 i

F.0C '(17.pps) 95' 101 i

1 i

5-3 Babcock & Wilcox.

~'V 4

9 W

w V

P,eeision 1 (4 /30/76)

Table 5.1-1.

(Cont'd)

I

_Cyc!c 1 Cycle 2 *)

Xen 2n wor t h ~ IIFP.

,1.'.k / k 1

a ECC (4 daye) 2.71 2.60 E 0 (equilibrium) 2.65 2.66 Effective delayed neutrcn f ract ion - IIFP ECC EOC 0.00690 0.00577 0.00514 0.00316 (a)!!!P:

hot zero pcwer; liFP: hot full power.

(b) Ejected rod value for groups 5

6. 7, and 5 ir.scrted.

(c) Ejected red value t'or groups 6, 7, and 8 iiserted.

(d)For cycle I length of 460 EFPD.

Based on cvele ! length of 440 EFPD.

l

. I 5-4 Babcock s. Wilcox

Revision 1 (4/30/76)

Tele 5-2.

C...t dawn !L1r: in C.ilcu' n f ra - Occ-.e - 2, Cycle 2 N.- 1. thl e-Rod *.irth ICC, * *k/k ECC(3), * 'k/k Tot ; rod wrth. !!/PU2) 9.77 9.80 I

'.Jo r i reluction d_e to burnup of

-0.19

-0.30

;.' s-en r.at e r i al

a x. - -... t u c k r o d, P.2 P

-2.16

-2.22

e t wrth 7.42 7.28 i

1.e s s.31 uncertainty

-0.74

-0.73,

~;t.21 avail.;Lle wortn

6. 6 /s 6.55 g

P e : f it d Po.1 k*o rth Pa. :- r deficit, !!FP t o IIZP 1.65 2.49

a x 1;1cvab!c inserted red worth 1.07 1.27 l

F1:c r;-lictribution 0.40 1__00

.t:.

required worth 3.12 4.76

..... _ _....3T[gQ To.. '. v. ail... orth - total req. vorth 3.56 1.79 i

i l

!!jta: f.equircJ shutdown margin is 1.00:..k/k.

l 1

1 (a)7.! v.:utde.a.argin calculations, this is defined as approxi:.ately

- I:iD, th.. latest time in core life at which the transient bank I

is nearly full-in.

(b)*ZF: hot zero paver; itFP: het full ; o.cr.

55 Babcock a. Wilcox I

k

.e v i s i.m. L. ' N/ 76; Fir re 5-1.

i,0C (4 EFP::), Cycle 2 Tse-Ji: enutet.21 : elative I: er

istributica - Fall toser, i'q a i11 b. F.caon ' or:.11 RJJ Ponitiens (Orcups 7 and e Inn r: elf 8

9 10 11 12 13 14 15 I

il

'.-0 1.27 1.22 1.17 1.M 0.8' O.77 0.60 i

N-s-K N

i.27 u

. 23 1.23 0.57

'*

  • 9
a. i9 L

l N8 I

l L

I

\\

2 1.U x

. 11

.12 o.v

0.c3 ri. 5 2 t

l f

n 1.17 1.23 il

'.13 1.29

1. ; '.

0.92 I

j NJ l

1 l

1.23

,i N

.2.

,7; 1.29

.lo 3,,4 9, % -

1 i

1 l

l N7i o

l o.37 c.

j

..e, i.2 t.o9 o.72 e

i P

o, ;

o,.,o 3,.,,

c,,92 o, g I

l R

0. *v 0. '> 4 0, 52 1

l

\\ x Inserted Rod Group ::o.

\\

x.xx Relativ.s Poser Dans!ty

.l 5-6

)

/

o.

I t!E L".it-iY;h'.VJ t..

_% d 6._1_._

' '. e - a l - i P.e.d.r.a.a.l_i.c..L.e_ _i__c n_.C.a.l. u t.a t.i_o_n_s_

hcrrsi-hedr.. 1;c de.t:.a alco!..tleas fer

. p.:: et.. cts J.,periti.a. : 11 1.:cd 1 1..

.ci..-

.c:h.:.!..t a.- eite.i in re:c e ah :! t.ns e

.. c -

.e t

ei.n t :er

..e int ro ; set ism at

  • ri w cr'.Ii.. i' b..t c a

.. : i+

.r the -int..- actual re.ic:er ci..

-s:.-

'. x ra:e i.,

pured d ir tr

  • ti ele cretatien. an.1 to a t ce: ;>er i. - ::s

's.' JH F e e r r e !. :

'a in

'. a.

t paeviously m,c!..

a,

.erre at on.

... (.:. cor rel i;.e t bas u *.c '

'i

.usi.c econee 1. cycle 2.

  • i.'.

.h:

_.t.i.on..e.t..M_a_r_k._i.n..'..i s s_ _r..b. l i.e._s.

.. ~

-,s t on se t ism

.1 the "tri E '.

as-.-'.is, l t t' t e t f ro:- t he "a rk B-1 s.

,4c 2 ;.

m ariis in *he end i i t t i n.:s.

.ic

. : e rc :c e,:au :e. a ili.: re-
  • 1.. re 1 : nce.:
  • h.

h '. i*

s--..es.

e.

t h. P '.

. r hi ic t i :

ite I arily c: t: s

,'e r -

th v.

15.

.te i h i.":. -..i r )

. a n-i b cc

.nd 5-1 i.

..s...-.

.de te c. -- :r rva t s..

.ccount i

i m.

of t v. ":a r k C ra..e-

.. - s 51c ' ' e r n 1-h d t.n l i. nod e l etsti

.. +-

,4 l.!

.-. cont i r.u r.it ion and rs t t :rr.

the 3-5 ass.nblic, in tae a t ion.

ai,ac.u ptiaa i nc e.e.e - :1:e cc servat isn of the 5 2

.a%

r. hac ir the cincula vd hot w e : 1.

t tev rate.

Far : 8.

two

" ark " - I t t e :-re 1 !rnen < t ra t i. n a:;.. blies. t ':s

.sse-b!-

fern losu will be 1er i.e: * :.c

  • aik h-1 : :.-l.

Irene.. the is- ! e ~t-b!).il;.still hr.e t i.e t i c '., s t a.d r a.;! t e le ses nd wi1i be

a-f1o.

'i-ited, n.!

2.

.t a s e t t:c v.e s t en. _. F.l.o_w l'eas t e t ceIan* t 1.v d it a ebt a ine.1 d':r ing cy.-l.

' c; er.it iet:

i f ical ti.a t the ss3 '.

- was crea:er t'.ei tb d e i.- n t l aw.

~'

r c.r.u re !

i uas 1 : 1. 5..

.: t w

. i cu flow.

ler tw c s. l..' ' Se r a l 'cc a r. ! i. desiea.inalv;;.. the i r c r e.. s e in

-s,ter. tie w e.

s en-c'.at ivel. c:

u, n to

'c 10 '. *. os.fes!..

6-1 Babcock & Wilcox

6_.1 t.

W

...?_.2 _'_'a_.D. i r. r.e..l.a.t _ !. --

'Ls

...' - ! r.3

.t r e l.it t ea, a :e nlist i< pre-lictiu.

- . '.;rneut l'he na c. i. ' '

  • has t. en re- :i..

.ind.i; prove;..r u -

5 t!:. ".i' i

.m.en!' l. l e.. c:1.

=

I't'-

a; p1 it.it. m et thi.

e.

r....

. -. i : en..s Ie 2 ore...e nodi-i s c.:

v': t c '- '. es. a l.,e }.c.

i a :.;,1 i d.. t he '? : - i.

J.

ind Ocot: e '..

ve'c m es.. rc. Sci a ti..t : :i. : t.i :

1.

'. l i m i t : tu,.!csfra :)N'M. ' l. G - 14 tsed.

r. Ps.

n:

c a O! ceaf tds :ee 1.

e1 'r c o, : 1..: i

-1

r et e.

te.

II.e *i-it

-- of 1. L'. w ?..

'+ca t e.

t).

... : ic - a t.re.. m:.: -

u: sen, re

r. -

a.

9J or.

pretc

' N. han;.;e i-n-

cM:

. ra.: s ! - ; t.e. : ice a:-

no-s t.1: i.'i..

rd.a.W. IItssi I /
!:
.iesic
. M 'A

. i se.

. e;

  • e.j h-

'~

it a
id the '. ' D.

2.

'esu

? i ",:.

iipl.

.'le

.a co re. t ia N.

stend d '. :-

r. -.

) to I.. ' ; s :.e.

~

,t

0 :

..cd i

r.

i. w.* *

^!

CHF

' t !.a

'.s e c o 41

,T.

.+uic

- i sw.'. !

1p

..e. s-...

Upws t h. - :he

. err >*

-clea..

O l '.

'.jicts ! !.e.!.? :.: ir I '. i. Ta u f,e.

E-this r: el t: is o +

,e an-

a. t er. w i t ' inc r. s.

.<:en f!vw ar c

ar t ! :i, tr :ic t.

it tr a:n *.".: i,

'r th.an ni: een t r..'.

Or

.t

...te

...c r.. :. e a, a:. a.n i t.

. Sit 6..

_.2.

'.9.A..n s i.c a.t_.;

..c:

t.

t - J i si. - sc.* abece, the r'a
. i nt. t

-. Onditions

'. - t,

G r: : u. 2

,,,e-bl.

.. e.

e r.

. s ed.. i ::a t-i ;-

r-b..

.ai a w. r.

..uce i n t...s e c o.in t.

hi-resalted ir a :.ini::un D.W e:
1. a - **

. ;ew

..t uni ea:. i t i. d ! uel.

P.

c

s 0:

m i f..itien ta:4 5e d1cided into two c a t e r.* r i es :

(1) t he re-

..s2 -. i he i.::i: inJ (2) :L* re-er spike resultini, fren Jensification-in iu,.cd.:a;ss i:t :Le t'ne l ce l e.

n.

He a.:t ive lenrth w as c.deulated to be G l.1 in hes. a r..wt ie:

ren :he nuJensif f ed leai;t b of IJ.1.0 inches. Dese den-i: i. : and una, sit ied lenr.Ss.<re ba<cd en f uel batches 2 and 1

  • tI:e 11 = -

it i tut;bcs in gcle. '. as e i: eed in see t ica 4. L 1.

Be axi..; tlux sha;.e t h.s t pre h:eed t he -.axinun change in D'3R f rom the ori inal desi.:a value w.s.- an out!ct reak vtth a cere offset of +11.5'.

The spike r:.:i:ni-tudt and t he max t=:n v.ap s ize are diseitwed in scet f or. 4. 3 and the values s.+

Babcock 8. Wilcox M

used in the analysis are 1.087 and 3.10 it.ches, respictively. The remalts of the t.e et f ec t o.a re -1. 88 and - L.0V. ch in,:e in the mini.un S.et channel li?;3R

.iad pc.Aing narcin, respectively. The changes in tl.ese nirgins are sunnirleed in Tabit 6-1. wh h h inc ludes compar is.ui, c' ot her pert inent cycle 1 a r.d.' da t a.

The D!.YR analyr.1i has been based on a core confic.ur.it ion eensist ing of 177 Stsrk R : ael asse:-bl tes.

The incorpor.it ie:n of t -e " ark t' denen-s t r.it ion fuel a+te+1.es i n ba t c h J. in place et t i.o Sh rk B as.. 911e3, r e:,u l t s 12 an increase in

'ic. -. e r a l l a rr,in t e !)?;':. a s.!!:;c u:;-ed in t ference 2.

o Channe fren undensified values.

These are actually an irprover.cnt over cycle i densified conditie.is.

6-3 Babcock & Wilcox

i iS t e-- e-1.

r cte I e d.' " i. i m.- - - - i c. c.r.* i-i e.s

---. ;e i l C v.- l e 2

le d i.n power I.T ei,

M'.*t 25-8 2%S 3" ster presssrr, p iia 22:0 2200 ne.w t r c ou i eit

.e..

, de.i.n ilow t

,0 6

ga.e....

t, n l e t n.....

t er:per it oire, g

,,J.

....r.

F

..>2

.o

..> >,>. 9 t e. :.c r.it ure,

.cs... mit c-c.. mt

lir, r ewe r, f

-J

  • 02.2 Ret..!c.i>*,n ra.fi.2 - weel rewer Pc 6 f.ic t e r
1..' -

1.H 6e

...s i. e,. :ru s a.. p.-

,,tne

..:,ces.ne 3

.L t '

nel lenct!. in.

i m !e.

'. l. I i! m.)
  • . c.-

it !!nx.

p.wer.

-a t u.,. t t

.u

.,.. n, s >

...4.

  • ix 'a-p.wer.
< t a, n.

(;.t.'.. c. s c.ilc )

. 6,,,,.,.,n.

i HF. + r. l..t i on

'4- :

55'.i-2 DN F r:

.t x les i..n con !i t i m.

l.'

1. 9 Ci u '.

1 * ; c.; )

c...

1.

..- r i F.it i.me i 'i.rets

' * :.ilp: rHe 1.0:1 1.011 H..t I' l u x 1.014 1.014 t 1. v a i,..

O ;-

0.95 Pen. t...itien etIcete.

1..:n..a r a; i n.

-n. A.

- 1. Ly

..a n c e tr t ?.n r.e i t. p. m..r pe.sk i ng, ma r g in,

-2.

-1.06 1

i 1

1 1

6-4 Babcock s.Wilcox

~.

a. L. p.s :....,

s.

......>.t..~.

u.

,.. L... e _.s:.a a >. s

.'.1.

c.. n.e r, ;.. -.. -.c.t..

'_in a 1.v.s. i s af L un FStal efarat analys!< has 'n en es t-ir ca v; r -ree:

.r.e e s in cycle

.' p.e r.i.e t e r i. to ;et er.in.' T*m ef fec t s

.;v c c;c

-1 al Li -

en care t 'la t

.'t:

.. }.*!.Inanct.. It J..' r.3ded du.

.4

.T

.t:. s'.11 : r&

-[.nts.

I w. c. re trn:..! ;a:...ters uJ in tim - I V.

.:. : c c. :..il.4i>

- e r.- ' e s t.:a ar. ra: 1..

a1 e.

.,a.. e.: en.ala.lattJ va; s

. 1-

.-..-r-in:. 4 yi. i e 1.2tues tF-

.i l ue-f :.

.ar< t.w: r.il ira.e t e r

. N r...::. :. :u ica ;n t;w c.el-a a. t.'.i s 1.

able 6-1.

T1.e s e par 2 ster: ne. r.en to ill of the sect-

d....

c.1.

p r.

.c n t, ;. z e i r.. Fe r c..-

lis:u4sien r.. :

L.

part et.rs.i re p re.- i dt d.

.- ; t r i o n t ;..e

..s ?.

pari:etsrs cee

a te...

.1 ir...

f r.C a! : e r rs se... c.:.

.c

r. :;. vi: ::w accieen:

... : 4.

s,

- ic 2:: w r. 2: ;

i:

tal c..;; '.

.n: ire :.t.n. : :

. ii-.. tiv ii i.

t..s c:

  • s

.....: -.le.t; fen en :

re.* ::

i ree been ev al-s

.su i:: 2

.t r.-

r,.p ::t.

a W '. M.

  • 3. c. ;. _v:22 2

.1 8 ';e! u.:e 511ea

e r,.

.e; x4 w4ne aosetic.11.'en-it:.

is iar r ; :a t..Ose.snsidered

.c retiren.x a the uenc'ssions derived in t ut rsi.rei.e ar.= still v. slid.

. a, a.., a t : oaa.. ux.n., we s in..,

r e t ac., ; :or e.e e

a n. y e s ren.atn eOnnstent vi:P : we u :e 2 : e r t..e F S.ik.

.idditienal 'nR

._n.:in is shewn for cycle 2 h c aa.,e :.:e !!.%-J Chf correlation va4 use.1 ins:ca:1 cf the **-3.

.No new d, se e sleu'.aticas were perf orned f or Int reload report.

The dose een-siderati.ns in the PS.'d were ba.ted on rc txt ca-. p.-akin;; and burnup f or all core

\\

eyc h s; Gereisre, the dose censiderations ire.ndepeadant et the relca.3 ba:ch.

7.2.

t'_e.1 W i t 'i J r w :' A eidents Tai. accident is de:ined as an uacontrolica reactivity additien to the core 2 t.e t e wi t hdr av.21 e f control to.ls durine. + tar:up tonditiens or f ro 2 rated power eenditions.

"oth types of incidents were analyzed in the FSAR.-

7-1 Babcock a.Wilcox

P.evi,L an 1 t./ 30/ 76)

/

The f pe t a:.t p ir :- :. r s dur!nc a red withdrxsal ac..i

are Taepple-coeffi-cient, m.cr st or : en:. ratt.re coef f icient,

n L '.:e r.::=

1 which reactivity is a JdN to t i.e orm

<11'.

t.iph pre.sure aa'

,.h-: 1u. t:ir-arc asecun:cd for in t'

. a:. i t --

'. i t a 3.

  • r titip; il a rm, i.: rb'eks. am' trips thn

_ill, pr.u : ;v t h i-; t yps c: Inc i.!ea t.

Fcr pe,i:ive reacri city addi-iea..nl;c at ive

t ese event,,

!.e na.: x en re w'.:

>ccur ter 9.. coa-df:'

e F.: A. e d.. e., ef ti,

.~ e.

IU

....,.. c r. - : ::

.. id i t ie:.c vere -1.17

  • r

...e Papler erefficient. 0.;

IT-k/k : er t he xdera-

.e

-- - :.rc

.s.

is : a.:

reup w. : :;u, e r :e.

ine la ! in.:.i 10%

' k ';

r-at-

  • er;;.r nic _ rie 2 p.u tre e r:c il:-> are -1. M 10d

./r t'..

-*..: a c: 1.

c. :,

-l...

1F'

'F) ir n.adera-ter

'3;ere _ s s

..'ent, and a..a x t :.um r -J 1.x;

.r e f 9. i. *k/k.

"cle. ; a.

.. : e t, are saaled 1.s Jr:.. - s :1 - <. w: c.! for the F C /6 a c.,

s.

sc.. f or. m r 'd i: hd r.r. ti :

a..s : ent s.

. e e ns cueaces will ts a

..e ve r e : sic. those p re,..-is a in t; TD. For :w re! viihdrwal fic p: er.

t r..n f er.: een..equ nce - ru f. w o. :- severe t::an t hose p re... ;

cation e.* pert.

7. 1.

.. r

.._:.n.

iceident in re

or n x :ic a id 14
111.c.i
en rol,.-

,- re ::t ivity.

i..e

  • c

--. ;r t :.t ;. '

> riacter cesiin; is ; ric ;c..;.

er
r. duced :.* ;0:pensate

. rnu; an t r in le :: >cnoa Mfe.ts v.

h li: *:

n tat er 8.;p 11c-1 by t 'w

2.

e

.r.

. tion

,yeter..

The d.: r e d

.a* r ter dil. ten traasients consi-s-

, c.p

., e r w i:O r -1:5 ere ao r _ r. co:.. ;t r t:ien fron the r.ncup

. I.

.*i.;s r Got'..l i t i on% Qi f'111 pOVer e;cta'.i. ', Jat S h*1: lO*.*n, and r.* :

1. l k.

.i r.tr.e te r $ in :,11 an.n l y,1 ;. arc th= sni*ial bCrOn (.enCCn tratte.,

t_ r ei reac t ivit y worth, ar.1 codera t or cer.; 2r tt ur-escifielent for peaer c ue.

For pomi. ive rent h it:. addition et this type, the os: se cere results occur fer IE aaditions.

W FS?.R values of the k.. para..etera f or P.0!. condit ions were 1.'

p p.. f o r t.~ Init ial ba ro:t 20ncent r t: Ien, 7 p p n ' ; *. (.*k/k) toren reactivit..ortu aam

  • C. %

1.) - 'kik/'F for :Se :a 8 ttei.nr.

e rat e r te"pe ra tu re coe f-Compar.ble c yc le 2 :1ues are lit.o pyr. for the initial bor,rn concentration S'. pps/1. (J,/k) boren reactivity w:rth and -1. 33 20

('.k/k)/*F for the 7-2 Babcock & Wilcox I

n

evis,ica 1 ( *./ 30/ M) nede r-.t ar tenperat ure cetific ient.

Se FSAR < hews th.t the cere and Ta'5 are ade;a.,;elv pratee:cd durin this event.

%fficient tine for operatar a :fon La : rninete t :. i s t rans ient is also C.c.3 in the

- nd n i n :n in :.a bu t do-::

FSAR, even ith.axtrum dilu-tica na r.;i n.

Th, inpce t inte to predic:ed cycle 2 para etric e.ilues of

. -.a leratcr lilut t :n tranier.:

Are bounded.

the F<A7. Jeatgn va l u. 5

- h is, tho anaLy:4is in t he FSA.. is ealid.

7 '..

-r!.

.: it e -

- - - r.

..n.."- S t a r t. :, n a c c i d e a t_

8

,atre are ao check ur...Tation v.=lves in t.te reacter esalant. pipins:: there-fore. :.e cia-sie cold v.

>r accident i.s :ot ;;s ibi..

Hewever, when the re se t. - i-c; erat ed t. i ta :n er nore p

.p 8 n 2: r r.n i n t., and t he:. i nes<.

tura.

.e increasel le. ra:e vi;;

.re sause :1. reeer 1 :e decrea cere : perature to th naderstar ic.? rature c:efficien:

1., ne.ative, : hen retcti-vtt

'. - 212ed to th2 ce re e

and a p o wer ri :<.111 occur.

E rc :,.. :. v.

terleeks and precedures pre. at c ar t i.; i.lle p :nps if the r. actor pov2r. abere.'2*.

Ifeve r, ti.sse rc; r:etions were anered, and two pump sta-;.-

ran

,. I aver was

.t taly cd a s

!.e

-.e s :

xtere tra sient.

la

..-ize re ;t:vity ailitian, the 7 -Ic.

inilys;, a s.e_re a t he._ s : nec2:ive ned r. : r :e.ceratare cea:ti: a::

c:

-1.

- la -

.'</L p ? and lea +t neg n i...

DeppI<r. e:.eien: o: - 1. - )

IC 'a...

L reder a:er tenper. t are currespandin: est c.e;;a t ive ce_::icien; and is_ : ne.,.: :ve b..ppler coe:ficient 3.4c t m.

er eyee. are

..u C an:' -1.21 pre-

~ -

~~'

_' e -

( '. '.,' ' )./ *,

Sinc. :

r:ect tc v

r eyc'e l ralerstar respectively.

'1 tenperature coet :1cient is less ne;a:ive and ti

.ccpler ce <ficien:. is rore ne;nivu thin the talu a used in the FSAR, the tr n.icat results wou l. *:e les t han these reper e.1 1: the FSAR.

.+ c re re of Cenlant Flev

-=

rae re a e :.: ecolaat tlov rate daereases if one or sore of the reacto panps tail.

A punping failure can be caused by =echanical failures r cool. int at < 1ee:rical pe.cr.

or a loss With four independent pu.ps available, a neehanical itil-uve in :ne pu: p t. ill not,sficet the opern ion ot others.

  • il t : t !.e reactor at p owe r,

..e e: ect ot loss of coolant flew is a rapid increase in ecolant te=-

perature

-ue to ti e reduction of heat rencval capability.

~his increase cosid re ul: :n

'.3 it a

correct.ive ae :en were taken i-nediately.

The key para-net ce 7.c r s ::: feur-pu;p coattdown or a locked-rotor incident are the flow rate, fAov coaa:di wn charaetorI luppler ; eificion:, noderator tenperature

.cs.

7-3 Babcock s. Wilcox I

Sevision 1 ( /30/76) coef t'i.:! cat,

a...!

22:

.n e ; >. i' pea kin;; fae: cts.

T.:e - : ~ t e enser vat ivc initial condit:ons were.i. red fcr :

dcasificarica :<pc ::

JA.1 valucq of flow and coastdc-a,

-1.l'.

1r'

!..kel*- ;' opp;c r. c. : f f e u.

.-s.,

.0-*

( ' k,' k i /

wit :i has t f ied c e ?

.eer
p:ke a.:d pe.sking.

~ 1.t ro ; 21: s

.e.cd -.: t o.e 3.':LR ri aa f:.e t.: b yce 1.1 W-1 l 'r :.;e f our ; urp cuantdown, and tt e : t e:.laldtag ter; rature r e.i i c.i 5.uisw criteri. linits ter the l oc '. d-
t e
Lt usient.

.be prediit.i v ira 1:.; valu.s for cycle 2

.re -1. 11

'.,- F

/D /*P 20ppler !g cees f :,:. cat.

-L.

i

. ' - t <.,1) / ' F : o !c ra:Or.. nr

.:.:.2 oe:1ielent, and tsakit.

. tar..;

.w.

in iar,le 6-L.

s in u : he p r. d ic: -d cycle 2 ealt;e9 are 50 :. sd 1,.

2 a d in t're.!ene f l en t.:n : epo::, -

  • resclts o*

trat analv.!< te;ter.ea: :. e rest,.. ve r e. censequ nces trer. a loss of tiet incident.

7. 3.

a.. my_.L. 3-xO3;;;..d --ant ni :<a d It a. e:.. r s t r.;

': - g ! Into the e re ile it wa 4 eperit ing.i rapid decrea..e

.. i n. u : -. x..- r we..: ;ccur, accance d ed

. a.. e re sw-ir the cere a c.-r e c. * ;..u:

er; - ra t.re.

E.t pewer : b. : r ;'2ct ior. nL:h: be.' i s t o r t ed due te i

.t c.t : ol rc;

. 3rn, r
'er which ;: :itfen.

i tt; urn 10 f all pc ;er

-t.hi ta I c..i ' :

.t

-A r k n.i:its an.! hest t:.ws.. x -(:-s of des ign

! ! - i t a *.. -

Ihe ke. ;..r.ce er-t..- transient are ed.crator : rperatars coefrici(nt, ir ar pv.

a rt

. :.il pe.G ing f act m 3.

ihe ! 1AR analy 5: s was 'oase d

.i, e.

rc; e'rtas with a nelerator t.rper.tura c:. efficient of

- 1. 0 iT* ( i. <. i.

Fer cveic 2, the na.xi.u i

  • or:h rol at pcwer is 0. 2 0.

..,.,. an.

- > c e :.. :.r

mra are coef f ie.,en:., :

1 -. t..y.:)/..

1 s.

r ince s

the p r.... ::s a re ; w ;: :'a is le.sa pcsitive ar..i the r:odcrat::r terperature coef f t-c r e: t 1...cre ro21:i., the consequences et this tra:..icn: are lens severe than tF.v to auit. ; r..: r. t ec in the PSAR.

~

' :.e - -:. a - - Of T.I. :: r_!._Pe e r Ivo types ot power lo3 ;es vera considi.ced in tha FS.*J::

(1) a loss of losi j

cc:idit ion caused by separ ition of the unit t're:: the transnissica syr. ten and (D a hypot het ica; con.:1tien ri.sulting in a co plete loss of all systen and unit power except that fren the unit batteries.

The FSN.i aaal/ sis evalua:ed the lo.s of loal with and without : urb!nc runback.

k*aen t he e 1. ne runea k.

ra..ctor trip occura on hich reactor coolar.t pressure 7_4 Babcock 8. Wilcox

Revision 1 (4/30/76) or temperature. This ease results in a non-li=iting accident. The largest offsite dose occurs far the second case.

i.e.,

less of all electrical power cxcept unit batterics, and assu= lag operation with failed fuel' and steam gene-rator tube leakage. These results are indepenient et cere loading; therefore, i

theresultsoftheFS$Rareapplicabicforanyreload.

7.8.

Stean L,ine Failure A steam line failure is defined as a rupture af say of the steam lines from the stca: genorators. Upon initiation of the rupture, Lath stean generators start te blev down, ca aing a suJdon decrease In the primary systen tempera-ture, pressure, and presuurizer 1cvel. The tv 7. rature r edaction leads to -

positive reactivity insertion, and the reactor : rips on high flux or low RC pressure. The FSAR ltas identified a double ended rupture of the staan line between the steam generator and steam stop valve as the vor:At-case situation.

l l

at end-of-life conditions.

The key para eter for the core response is the referator temperature coeffi-cient.

  • hich was assured in the FSAR to be -3.
  • 10 ' ( k/k)/*F. The cycle 2 predicted value of =aderator te=perature coeffi: font is -2.60 10-* (ak/k)/

'l

  • F.

This value is bounded by those used in t..e FIAR ana."ysis; hence, the re-sul., in the FSAR represent t!.e verst situation.

7. 4 St.- c- <;enerat or Tube Failure A rupture or leak in a steam generator tube allevs reacter coolant and avlo-clated activity to pass to the secondary systc=.

The F5AR analysis is based on conplete severance of a stean generator tube.

The primary concern :cr this incident is the potential radiological release, which is independent of core loading.

lienee, the FSAR results are applicable to this reload.

7.10.

Fuel !!andline Accident The ciechanical da= age accident is considerc ? the =aximun potential source of activity release during fuel handling activities. The primary concern is radiolocical releases that are independent of c:re losling; therefore, the FSAR results are applicabic to all reloads.

7.11.

Mod Ejection Accident For reactivity to be added to the core more rapidly than by uncontrolled rod withdrawal, physical fai)* e of a pressure barrier conponent in the centrol 7-5

- Babcock & Wilcox

The tabulat ion belew shows the bounding values for alle chle LOCA peak linear heat for Occ> nee 2, cycle 2 fuel.

rates Core Allowable peak elevation, linear heat ft ra h _kk'/ft_

2 13.5 4

16.6 6

18.0 8

17.0 10 16.0 The !! ark C 17 by 17 denenstration as.sembly will be locatec en the periphery of the core.

Because of it s location, the r.aximum line..r :.est rate within the asseeb1;. will be a; p o u inat e l 10 kk'/it.

Operation at tuts low linear heat rate will ; re.ent clelding, rupture during blewlevn should a 1.OCA occur.

Since rupture daring blowdovn causes the highest pea *< claddin; terperature, ti;e con +

the LJCA should be less severe for the :! ark C 17 by 17 demonstra-sequences c:

tion fuel.

In addition, the low linear heat rate provides substantial nargin relative te the LeCA linits calculated in !a'.!-10103.1" Theref ore, eccpliance with the acceptance criteria of 10 CFR 50.46 is ensured.

7-7 Babcock & \\Vilcox f'

F.evision 1 (4/23/76) rod drive assenbly cust occur.

tial to act Such a fallare could cause a pressure differen-en a control rod assembly and rapidly eject the assenbly fre the core region. This incident represents the =ost can be reasonably postulated.

rapid reactivity insertica that The values used in the F6AR and densificatien report at 30L conditions. -1.17 a 10-5 (ak/k)/*F Deppler coefficient

-0.5 =

10-" (ak/k)/*F coderator tenperature cacfficient, and an ejected rod worth of 0.65% *k/k, represent the maxi um possibic transient.

The corresponding cycle 2 parametric values of -1 51

  • 10-5 (ak/k)/'F Doppler. -1.03 = 10-" (Li/k)/*F noderator temperature coefficient l1 (both more negative ence 4), and a maxie.u:

t!.an those used in refer-predicted ejected rol vorth of 0.13',J.k/k ensure that the results vill be less severe than those presented in the ESAR I and the den-sification report."

7.12.

Esti.un Hypothe_ti_ cal Accident There is no pastulated ecch..ntsm wher by this accident can occur since it veuld require a tuttitude of failures in the engineered safeguards.

The hypothetical accident is based solely on a gross release of radioactivity to tl building.

e reaeter The consequences of this accident are independent of core loiding;

hence, the results reported in the FSAR are applicabic fcr all rel oads.

7.11.

"aste Gas Tank punture

)

The

..<ste gas tank was assuced to contain the gaseous activity evolved fre=

h r.a uin2 all of the reactor coolant f ollovi..:

Rupture of the tank would result operation with 1'. defective fuel.

in the release of its radioactive contents to the plant ventilation systen and to the st=csphere threcch the unit vent The consecuences of this incident are independent of core loading; therefore, the results reported in the FSAR are applicable to any r l e oad.

7. ! !.. LOCA Analysts z

a generic LOCA analysis for B&W's 177-FA, lowered-loop SSS (category I plant) t.as been perforced using the Final Acceptance Criteria ECCS Ev l a uation Model.IE That analysis is generic since limiting values of key paraceters for all plants in this category were used.

The average fuel te=perature as a function of linear heat rate and lifetime pin pressure data used in the BAW-19103IOlLOCA li=its analysis are conservative conpared to those calculated for thi Therefore, s reload.

the analysis and the LOCA limits reported in RA'.*-10103 pr

- 8 ovide conservative results for the operation of the c:onee 2, cycle 2 fuel 7-6 Babcock & Wilcox

Revision 1 (4/30/76)

Table 7-1.

Co=parison of Key Parameiers for

!ccident Analysis 9

FSAF., densif Predicted Parameter value cycle 2 value BOL Doppler coeff, 10'! (.*.k/k)/

  • F

-1.17 (a)

-1.51 ECL Doppler coeff, 10~5 (ik/k)/*F

-1.33

-1.55 30L roJerator coef f,10-" (ik/k)/*F

+0.5(h)

-1.03 EOL coderator coef f,10'" (ak/k)/*F

-3.0

-2.60 I

All rol bank worth (IIZP), ! 4k/k 10.0 9.8 laitial boron canc (IIFP), ppm 1430 1140 30ron reactivity wortt (70F),

75 84 pr=/1; 7.k/k

    • ax ejected rod worth (liFP),

Ak/k 0.65 0.18 Drepped red worth (IlFP), % ak/k O.46 0.20 I" (-1.2 10-5.*.k/k/F) was used for steam line failure analysis.

(-1. 3 - 10 *- ?.k/k/F) was used for cold water an.nlysis.

(40.94 10-' Lk/k/F) was used for the.noderator dilution accident.

1 I

l l

7-8 Babcock a.Wilcox -

s V

i

8.

PROPOSED MODIFICATIO!;S TO TIClifi!CAI, SPEC:FICATIO!:S l

l The Technical Specifications have been revised fc,r cycle 2 :peration.

l Changes were the results of the following:

i

+

1.

I' sing the fi&W-2 Cl!F correlation rather than k"-3, as :15 cussed in seetion 6.1.

j 2.

(l sing a 95/95 confidence level rather than 99/9i 3s discussed in seetton 6.1.

1 j

3.

t~ sing 107.6* of design flow rather than 100':. as cisc-a =e3 in 1

section 6.1.

4.

tising the Final Acceptance Criteria 1.0CA Ar.alysis for restricting

[

peans during operation, as discussed in section 7.1*..

i l

S.

Revising the assumpt ions on which the flux flew RPS +et;>oint is baced.

This netpoint now account s for signal noise on the -b.t = is of data accienulated f ro: operat ing fi&W reactor.s.

6.

An analysis incorporating the ef fects of fuel rod Ece.- m core paraneters.

Based on the Technical Specifications derived from the analvses presented in this report, the Final Acceptance Criteria ECCS li:-Its vill not be excee fed, nor will the thermal design criteria he violate:. Figures S-1 through d-14 illustrate revisiona to previous Technical 5;ecification safety limits.

1 i

i k

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2.

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END MICR0 PHOTOGRAPHER _s,~

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MICROFILM SECTION N AVY PUBLICATIONS AND PRINTING Sr 9VICE 08FICE BUILDsNG 157 2. WASHINGTON NAw / YAAD WASHINGTON. D C, 20374

..

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