ML20037A953

Application to Amend License DPR-2,App A,Allowing Modified Type 3 Fuel Design Operation

ML20037A953
Person / Time
Site:	Dresden
Issue date:	12/24/1964
From:	Bower D COMMONWEALTH EDISON CO.
To:
References
NUDOCS 8008250836
Download: ML20037A953 (18)

Text

'

e

~

A C05tMONWEALTH EDISON COMPANY f4 December 2 4, 1964 4

w

.% 4 Dr.

P..

L. Doan, Director Division of Reactor Licensing

.5 f

~

[.

• G f.:

,f U.S. Ato' sic Enerav Commissiorr-

. if M

C' Nashington, D.C. 20545 Ml

.p'

'F{

,(.

^

' ~ _ -A.;* l; 7ockat: 50-10 + -a..g -

...h m

Subject:

\\- end ant of Ap7cadix

%, 997-2 to,crnit

< $,_ y '. - T.

oneration vith Tyne III : Pie l

~

Dear Dr. Doan:

Pursuant to 10 CF't 50. 59 and "1r1;',raph 3. 2. ( 1) of Licen se DPR-2, as anended ("DPR-2"), Commonwealth Edison Company requests that.Apoendix "A" of DP'l-2 be anended to allow the operation of nodified fuel design, designated Type III P fuel, in the Dresden re,ctor.

The anendments proposed are as follows:

Amendment No. 1 Anend itet "2.

' hic lear Care" o f section

"'t.

M.3 :CN FEj r!!PT.7' o t

..pp e n u fE " A" t o 0 !' '.. : to reau in its ent:rety:

"2

'hicicar Core

"'faximum core diameter (circumscribed circle) 129 in.

'taximum active fuel length - cold 112 in.

Blaximum number of fuel assemblics by types:

Type I 263 Type II 102 Type III 192 Type-III-F 104 Type PF-10 and PF-11 (one each) 2 Type SA-1 1

Maximum total number of fuel assemblies 438 "The fuel assemblies may be located in any position of the reector, provided that fuel assemblies Type PF-10 and PF-11 are each separated from the other by at least four Type I, Type II, Type III, or Type III-F ' fuel assemblics.

D*

lD lD 3 h

WW W3 ~.MdMJl)h p

.s o o s u o L 5765

Page 2 Decembac 2 ~4, 1964 Dr. R. L. Doan-

"The reactor may be operated at any power up to and including rated power with any configuration of the various types of fuel assemblies installed, provided the maximum number and location are within the limits specified above."

Amendment No. 2 Amend the second paragraph of itea "3.

Fuel" of section "3.

DESIGN FEATUPES" of Apoendix "A" to DPR-2 to reac in its entirety:

"3.

Fuel "The nominal fuel pellet density averaged over a fuel sea-is 94.3% of theoretical for all fuel assemblies except ment Tene III-F assemblies which contain vibrator" compacted t:n "03 powder with a nominal lensity of 13) of theoretical.

\\ mend,ent 30 3

Amend item "3.

Jeternination of unxinun 7e,ctor i< K

'iri."w

~

Power" of acetion D.

Anmendix "3" to DP'i-2 to reaa ia its e?tirety:

ocactor Fower "3.

Jetermination of aximum "The rated uower of the re.tetor shall be limited to a maximum steady st1te value of 700 u4(t),

"The maximum allowable stendv state heat flux limits etoressed in units of '.tu/ (h'r) (f t2) shall never exceed the 911owing value;:

Fuel Ty,e I 350,000 Fuel Type II 419,000 Fuel Type III 360,000 Fuel Type III-F 360,000 Fuel Type PF-10 and PF-11 510,000 Fuel Type SA-1 425,000 "The reactor shall be operated within the above limits such that a minimum burnout ratio of at least 1.5, evaluated at 125 percent of rated power, will be maintained in each type to burnout in.the hottest channel in tcc of fuel closest core based on a uniform steam quality over the cross section This burnout ratio shall be based upon the of the ci.annel.

correlation in Edison's " Recommended Curves of Burnout Linit for Design and Operation of Boiling 'Jater Reactors," dated January 5, 1962.

The reactor,shall be operated always well within the bounds of stability, as evidenced by the operation itself and any experimental data produced."

Amend Appendix "A" to 3PR-2 by deleting TABLE II Ameriment No. 4 (re"ised 6-15-63) attached thereto and substituting TAILE II (revised 11-13-64) attached herewith.

D*"')D

]D

' 9F N M

.o o M o Ju. )] kird a

r-

,3.

Dr. R. L. Doan Page 3 December 24, 1964 Pursuant to 10 CFR 50.59 and 3.a(4) of DPR-2, a Description and Hazards Evaluation Report in support of the proposed amendments to appendix "A" is attached hereto as "EXIIISIT I".

In our opinion the data in this document indicates that operation of Type III-F fuel in the Dresden reactor will not involve hazards of significant proportion to prohibit operation of the Type III-F fuel.

Analyses of hazards different from or greater than those previously considered by the Commission in authorizing license DFR-2 as amended are included in Section V of Exhibit I.

Very truly yours, CD'NONUEALTH EDISON COMPANY 3y G/d C L - =,

Treasurer a

Subscribed and sworn to before me this 24th day of Decenber, 1964

(

t r2Y tozarv Puolic q,/'

Attachments:

Table II and U;hibit I L._

x,

'f.'***

j

• g

(

D LI 4J m

3 J 4

%.hUa t

n pg)

-s + 5.e; f%

51 8 I

l' D4/

g

-s90

' 9(

j A

h,

. m.,'. '

.h "i

+

, Q.

Q.

m.

).

1,f s c e

O 4

O O+

)

f i

-ew M. -

a'9-l

'., g

'.4

%.s w

c 9

. 3 w.,

.h 1+9t

.m

• t *,;

Jg 4

A Q

"* $ (*

O N.

N.

A b.

5

. n.

+9

,.$,I 3

g m

%g

-s.

.=

.a w

O

[a C'

/4

,Q

)

l I

ifh f

l 6

s a

f d,-

.J f

.x

~

~

nu o

e 3 **

y f ;,, f-t d

s" M

p

'C1 c

g N.

O..%

O iJ*%'

I hO.

. va QA fJ o'c' N y

.s q e

.e

9. a.

-e

-e a

,p S

.N

\\3

-4 LT

',.5 0.j, f

(

a

'7,

. g y

a

'sg g

l 43,.

g.,, ~ *

?

O 4

Q

.?

lA.

1 Kf I v

r g

i ns A.*t i C

l 1'

0

--6 i

l f

o j*N g

a

.) ]

.g j

g.

[

)

O.

PJ A'

J C4 9

Q 3

fre G e

~,,.

h.

i

.l5 6

t

-a t 3

l 3

3.

3.

'_g 3,

)

O.

O.

[

o.

'.1 b.,

• J Q

J a gg n

A.s al e

- I O Lh'1 3

t hM S *M.

i a "-f e

I 7%

N b

^

a o

.o -

.9

• 1.

2 h" h a.o o

o 4;

e

.o

-J J

ei J-

-d.

, ni ej.

ej d

c.

< ir*r.7 m

,.r.

' I t-

.A '.M (is"gW 4 4 r

?2 "#..- -

~.

3 7 ',

. f -_.,_G_)

- L.4 4

7

.WK%t; e L t

-wk

.A.

-.s

.~

m

,==.

v=,

6 M'

e*1

' 4r)

., wy,& m. 4";&, e 3

. y yr

, 4

• @ M r3W))

h

' ~

D J

J I

O

- q

-d

.J

. =

N

-s Al zjo'l.y A,

• ~

4 -** y [ . }

g m

"J %.-

~

-QT n.-

so. n,

.. df.

-3. a

_5 m

Q

-.4 A

eT

• ea6 a.)

S3=

.% s 34

$* 3 us, Ja '.'

o 7 b.'.,

..4 s

+

,.J-.

,, _-9

,..--4..-

._]..

. o.

3 so

--.4 4-%-g 9j

'3

.j.

y.

j.c.

. g c.

3..

._3

_3

-f 1

7 j 1 4

.*)

eg w-c4 se:.

w A

A N

w

p js; 7~.

i

,9~

g

• l..

~

r a_ m

,,. vapt.r-pus k

i. Ja a

f f

3,

m.. M..

a.

.J. ^.** g.. _)

• 1

-. S Q -

c 4

c T) m 5

• "'** -[*bt

j *<.i

=

w w

w ee '

W W

w Q

3 4

9 n

D H

3M

^

1

.., +4

~9 l

, yfs t wa oyn

-s

~ 3 d' o

n A

A A

(J

' " 1 -[

a ay e

-e n

A n

c) t2 Q

3...

3.

O.

7 O>.

o 3

3 O

O l'"'-

0 O.

s.

3 s== ;

. g:

3 3

3 ;)

,,~

co w

.2 4.l,1 e

G s

A n

-a we 9

'=

s"

- CA N

A 9

4. ;n

-.s

.s.

2

.s. '

4

-LY' c2 ae Q

c L

o.a

.1, 4 4

s 3

0 3

o O

O O

O o

w e

..'. C.e%,

} -*

g,-

o 3x,

..m a

g j

u c,

c, a

e, a

a n

s

.~

N s'.

b d

b G6

' *""m j

a

,n u

u u

a u

u p

ugu

-..d 3s

'g I"

3 C.

a, E.f. r8 -

n >. -:.

W t

i& G

-8 s.

.M H

u

-3 a

p.

eg.

-e M

N M

ei.e M

Ehe

=

b

s.. -. -.a g

.f*W h,* Q.. f m

ee e

.. ~.* 4$

N '.. ?.."

-.a--.

~ E- -

-. a-c t

N, e + e,$

...,g.,,,,.

.g-,..-,

. y.1-

e..

.2..

,,,.,,,,,_,m,,.,

y

.i.

~.,._y.

f

,.. a.3; s.

s<...

%e -'&.

g 4 ~-

-t*d,,

p,,

e y,

9 w.

1. . u m.. ~..... ~. e.~,.-.

m.w. -

.--w-*

% 4,...*.w e m

.a....~...

..,...-m.

L5 \\*.t ? LTa.in.'. T _

.. ~...

s_.

m;,,

.- e d

2

.e

,. ~.,a.

..z.

s..

-..a.%.

ruei and Co:s

. U.i!O:I._'.

ti n c a r C a.w > e r:r.i.:s 01.ne

~

.~,d2,...'"..

C." a m. ' ' ' '-4 s " '.'s

- %.,.,,a.-_

3.. m,

... c.;

k.?

~u..,,,3./

.a t.et

..v h,.a.a c :.

w g:

/

4

-*r.

G Inic reprt ;rovidec technical inforraCon in capport of the attached i

yplication for amendment of Dresden ' Opera *.ing !,1cence DPR-2, as e.:e nded.

It is not, intended that;the raterial 20ntained herein con-

• re ca.sa. o.'

• ...e.r,1 ".. n 3 i.e.g N.3 y * ~. 4. '. ' ' a *.' o ". b-a.4..,.e5

. o., s., 4 a l.

e

.2 44

+

,c o,

e,p.

4..,t.-

. cs. 0,6 ).

.v.. u..

4.., n.

( - Q mn.,. x3,.

e.

m v

4

'k j

G e

e es

!IOVe.d.er L*i, L'hA I

t

' - SECTION I. DESCRIPPION OF' PROPOSED NEUDMENTS TO APPENDIX "A? TO DPR-2.

These roar amencments are proposed primarily for the purpose of outaining authority to utilize Type 'III-F fuel assesclies in the Dresden mactor.

Current plans are to 1 cad up to 9e5 additional Type ' III and_104 Type III-F

[.

fuel assencliec -ia tu? Dmsma reactor during tne refueling.at the end of.

. operating cycle No. 3 The r.nysical, thermal hydraulic, and naclear pmporties of tae Type III-F fuel and.the effect of using this fuel in a :r.1xed com-am l

cove n d in Sections II throuen V of tais report.

. The sforementior.ed smendment s also provice sn up-to-date listing of the fuel l

sscemelies avaim;me for the next reft e11rg, ' F;?L assemblies FF 3, 9, and 12 were::9.mo ted f rom -J.e core st. tne laat ref eling and were tr.23 not in the" core during cycle No. 3 P

9-4

\\

.mmmme

-*_w4..---*==-

w.

~

_s.

SECTION II PHYSICAL CHAS.AC"'ERL*1'ICS OF THE PEICAD FUEL TYPE III-F FUEL

.It is proposed to relost tne maetor with 1C4 Type III-F f ael accemblies. The Type III-F ft.el consista or cix rova of alx "irealoy-2 clad fuel rods as sucwn in Figure 1.

Each of tr.e 104 assemblies contain one segmented pellet fuel rod which connects and positions five doucle vim apring upacers. The spacers are essentially tue saae as for the Type'III fael and am designed to minimize -

defie^tica a:ri vierstion of ne reda 1:. the sese.tly.

Eaen of the 1Ch assemblies contain six faei roda vitn icwcr enriennen:, vnicr. are placed in corner Locations to recice loca pc er peaci:g. Zaen or ;ne ich accenolies contain one re:nevsble -

tur- ;cie poisen r:1.

'sinety-four of tc.e aa ent,ile; contain ;inteNi CQ,re;NL :.e.

and ten ccatain tit ra *.o r/- :c::1paenel '.00 pc we..

Zignty-ei.;nt a:.te 4 pellet fuei ascenclies ani e2:n cf the en pc nor arce

.ics ?:ntain La:- m _e poi;cn P.e fc = c f Gd 0,:- Ale,.0.: M L ie *.

T*e n.ainin. six r.eilet. fuei sioser.ciiec viii each con- -

2 tain one re :c tat.e experimenta. ceg tentet: poicon roc. TP.ece rcds con *.ain Gd C23 l

Ocncentrstions of 0.i;3 rd?- *nd '.272 g-/:e in the farm of either Gd C3-Al20-3 2

or Gz03 r.02 The p'trpose or cne six experimental turnacle poiaon rods 1s to

.)

Onfi m the anaracterictie; cf mie_.-UOc as a potential c anan.e poison.

~t 4

is p:arnea to reccie some or ::.e apezia poiaan roda af ter one 2,/cie for analysis-witn A-2 3 cr :.anaari poison roda. The rect of One experi:sental and.-eplace tue 0

poicon reds will re ;ain in the : ore to cct.ain additional expcsun.

(G.fyj L.. 4.ani:.a (.bcy j we re ;n: W a as....e.

yo.ini.a::.aineOxn2 n.2 ournab.e poisen veriaa., ueca%e or

..eir cortculen asi N e anu irradiaticn1 3tabliity.

N, 1

~

o A

,.*K g.

SECfION III HUCEAR CHAPACTERISTICS OF THE FWL AND CORE The basic physics lattice data for the Type I, Type III and Type III-F fuel assemblies are au.:narized in Table 1.

Thece data vem used to evallate the nuclear characteriat.ies of ceveral scat te r fuel icadirgs for Dresden fuel Cycles 4 and 5 Two typical scattered core loadings am shown in Figum 2.

The :esults of tnese studies are given in the following paragrapns.

A.

Power Distritation The predicted.;roca core pcVer ciu'.rit.tions are not signifi:an.ly different from inat precined for the Type III fuel loacing in Cycle 3 Ihe ma ;nitude::

ne io;al : :e; acsest 2y power peak is esse..tially _na.:anged f:~:s ?ype I!! :.el, but the rever Ci ~ ri:ution vitnin an assently is 11fferant te2aase of tne pneence c1

.e 'curna:.ie poison ro: (?!. pre 3 ).

3.

Temuerv are anc 'loid 00efficien s Temperature and voic coeffielents tecome less negative vita exposure in the Dresden reactor.

"hus, the limiting Iclerator coeffiaienta occur at the end of.:.e f el _jcie.

Predicted moderator Ocefficients represe: ;ing typical loacings of Type I, Type III and "ype III-F fuel at -he end of the fourth snu fif th cycles are listeu in Table 2.

Af ter re elirg is

ompleted and refore ne reactor is :.ro unt to c;erating power levela,

.e u=perat m zeffi:ieu

.a ceau.re 2.

C.

Reactivity control The fuel assemo ty lattice data presented in Table 1 indicates that =aterial.

buckling deemases and the control strength increases as the temperature and void fraction increases. Also, tne effective reactivity level of the mixed com containing these fel assemelies will decrease with exposure.

Thus, the most reactive state of the core vill be at ambient te=persture at the beginning of the fuel cycle. The reactivity of Type III-F fuel has been designed such that kerr 4 0.9) in the most reactive mixed core With one red stuck out of the com.

Detailed calculations performed using tne maximum reactivity Type III-F and Type III loading configurstien of j

Figure 2 indicate tnat the reactivity level is lover than thst of the initial Dresden core. This assures an adequate snutdown margin for.he proposed configurations. Any other scattered loading configuration containin6 a unifor 2 mixture of ?/ pes I.,

III and III-F fuel vould be less reactive.

.w D.

Burnable Poison Behavior Q

Type III-F fuel utilizes gadolinia as the burnable poison in place of erbia vnich was used in the Type III fuel. The gadolinia which is a self-shiel& d poison is contained in a sir.gle, re.novable ru<1 having t e same dimensicos 5

as a fuel rod. The gadolinia is carried in an alumina taatrix and has a concentration within the :natrix of 4.7 v/o. This concentration and geometric configurstion cf gadoJ '.ia is designed to be effectively depleted in the

s.-

.-em*.

m

f A

.es high cross section isotopes, Gd-155 and Gd-157, after 3000 WD/T exposure, g'

As shown in Table 1, the reactivity wor +h of gadolinia is ~6% dk at 68'F.

Because the proposed loading pattern is a five baten scatter, the effective poisoning of the core is enly ~1.23 ok., Eroia depletion chameteristics in Type III fuel provide assurance tnat tae beginning of fuel cycle reactivity is tne :naximum. Evaluation of the gadolinia burnup in Type III-F fuel indicates that with the proposed loading the core vill still have urimum reactivity at the beginning of the cycle. Possible uncertainties in predicting self-shielding in tne gadolinia are recognized and considered in the fuel design. To acco:nmodate any possible increase in the cold mactivity level of the core from a too rapid depletion of gadolinia, the Ty;e III-F fuel reactivity was adjusted to provide additional shutdown margin (snutdown keff = 0.W 3). Tnus, even if the gadolinia is assu:aed to deplete instantaneously, the core kerf with one control rod out of the core would be only ~0.c45 The depletia:. behavior of ercia in tne ?/pe III f.el is :naffected by the presence of gadolinia and is the sare as described in the Ty;e III license a:aencment s.

E.

Special Assemblies 1.

Six of tne pellet fuel Ty;c III-F asse:clies vill be loaded vita regrentec poison rods containin,;; gadolinia-urania and gadolinia-al mina mixtures. The similarit'. of these poison rods to the stancard poison rods is suen tha*. gross core ;cver distrilutions, moderator msponce, and gress iepletion characteristics vill te unaffected.

Ten bundles of me Type III-F desi.Tn vill :ontain compacted powder fuel. The small difference in fuel density vill not cha.spr any of the Type III-F nuclear chara.:teristics.

'A 3

The SA-1 and FF assemblies now in the coze will similarly not affect core performance.

ei

?-

m.,

s.,

[

-\\

,~,.,,..-

~

,r SECTION IV THEINAL AND HYDRAULIC CHARAcrERISTICS

-..a.s. :e t v, %v.r Because the typical core power distribat. ions involving Type III-F fuel are essentially the sa:ne as those previoasly analyzed for Type III fuel and becauce of the physical similarity between TyIe III-F and Type III fuels,

. vw j :

there are no significant diffemnces in their the: ml and hydraalic charse--

teristics. Hence, operation of the zwactor with Type III-F fuel vill not y

appreciably chang the performance of the reactor and vill pe:mit the

.Itactor to o;erste within the heat, flux and minimum critical heat flux ratic license-limits.

'he p. eder fuel una a cwer therna. condu:tivity than dces the pellet fuel because of its ic er lensity. The ic er thernal :enauctivity has the effect

^-C

'or a Of raisir4 tr.e ;.cwder f.et te ;eratum note. tant for i.e.le*

giren ':est fin.

n ae Ty;e I !-F f ae-,

25 percen'. cf the steady state neat flux cerract.cula to an, 'Elt of G.a :G/ f t.

Tne FF-d and FF-9 powder t 4/f*. n 25 ;:ercer.t of the steady asseno des..icenced

• o an

'Elt state heat flux, nave oremi.ed in tne L:esdon co:t ;o-exposu:ts exceeding

' it.1o st f si. a.

9CO) AO:

N

• I# '.',,,

'~~

~n,...

9 h-m-

m a

4m4..d e

_qn.e w,w e q-

SECIIGN V SAMY 'dVALUATION Former and potential operating hazardas nave been reviewed with respect to the Type III-F fuel. The Type III-F fuel hus tcen found to be suffit lently similAr to previous Dresden fuel so as to caus,c no additions or cignificant ehsnges in the hazards evaluation except for the one indicated below.

Fuel Loading Accident.

Becauce the Type III-F fuci bundle rea.it.ivity is greater than for previous Dresden fuel, t.he reft.ciind accident hus teen re-exeined.

0 e secident poetulated is the Lovering of a fuel tiund'e at. t.hc :mimum design hotut rste into a negr-crit.ical core during ref aeling. The nfucling accident hats been hypothesized from a number of procedure violatis.g circu 2 stances and represents an acci tent of ext.remely low pret, ability. Coaservative assumptions for this analysis are as follows:

1.

Two control r0du, next to Oc fuel position to be leaded, have inAivertently been vitbirawn to give a near critical 2 x k fuel element array with one center fuel element missing, rhe refueling operstors fail to note thst theGe two rods art withdrawn and start to load a fuel Clement into the vacsnt position.

The loading pro:edures recuire verification that the reactor is safely subcritical by withdrawing and re-inserting a control rod before and after each loading step.

2.

The control room operstor fails to notii:e the indications frc n his instru-ments that the control rods are out and that the reactor is near critical prior to loading. Procedures require him to observe this instru::entation and to te in communication with the refueling oprutor durin6 all fuel losding operations.

3 The bundle is incerted inte the vacant. fuel position at the maximum design rste of the hoist (~12 in/ ace).

4.

Th'e period scram circuity fails.

5 The fuel bundle reactivity worth is 19% A k.

Analysis indicates that this is the maximum potential reactivity worth for Type III-F fuel in the assured s

array. For the worth to be this high, the cort area bein6 loaded must con-tain fuel with a relatively lov irradiation exposure.

6.

The initial fuel and modegtor tempersturv is 68'F. The power level at initial criticality is 10 times rsted.

Based on the above assumptions, the calculations indicate that the asximum fuel tempersture would be $200*F which corresponds to a peak fuel enthalpy rise of 230 cal /gn. There may be a small amount: of cladding burnout but no explosive fuel red rupture. The accident is terminated by the negative Doppler reactivity

-due to the, fuel tempersture rise and the r esctor is subsequently brought sub-

. critical by the scruta system which is actuated when the flux spike of the transient passes a level correspondin6 to 125% of rated power.

t

,s'.

,q.

b TABE 1.

ASSEMBLt AVEFAGE LATTICE DATA WIRRADIATED TYIS 'I, III AND HI-F FGT.

(Inciading ti.e effects or c.ructumi :csponents) i Fuel Type I

I I

III IH III IH-F IH-F IU-F Tem; erst.ae (*?)

t2 5-o-54 66

-54 i6 6a

' 5L6 5L6:

~

a o 20 void Frs::ica o

s. 2 v.

v o

G. 2

v v

Une:n.m..ed 1..;2

_._?;

> l.1T.

1. n;

. 15' :.210 1.201 1 197

'..s x, controlled 0.9L6 o.Sak c.352 c.970 c.9ch o.D3 1.0c9 o.927 0 902 control worth (4k/k) 0.164 0.232 0.256 0.159 0.221 0.241 0.166 o.232..o.2h6 8

39.8 63 5 75.4

'38.8 61 9 74.1 39 0 61 7 77 0 0.055 o.okd Bumatie Poison Worth

.(ak/k)

.m-.

,. nw e m mes e

---

____.__,,__m,____

--,m_.-9,-

A

/'

3 TAME 3 MODEFATOR REACTIVITY COEFFICIENTS FCR FUIL COPE MIXED IAITICE Sir.gle Satened, End-of-Cyeie 5:

TE!UERATCFE CCEFFICIE:fr T':mpsrs'.ute C0efficlent Te=oerar.2m (*F)

(l.k/k/*F)

~_

x... 3

+).;

s 20 0

54

~a.2 x LO~)

VCO C*EF'IC2!.""

V0il F m *ti:1.

Void C efficient (Interior

• .o Fiev Channe ;)

Te rp. (*F)

(Z.k/k/E Void)

'I d6

-1.5x10~f 0

63

- 2.1.: i;~"

Macle Sa*.ened, End-of-Cycle TEMPEFATLRE CCEFFIC'EITT Temperature Ccefficient Temperature (*F)

(Z.k/k/*F) r

~

68

+4.9 x 10-3 h15 o

Sh6

-5 5 x 10-5 VOID CCEFFICIEFT Void Fraction Void Coefficient (Interior to Flow Channel)

Temp. (*F)

(4.k/k/% Void) o 68

-1.6 x 10-4 10 68

-2.4 x 10~"

b y i--

'C-

to w

y t

1 i

f e%g

m. : \\

s.

I e M

[b *

./

y.

f

.N

\\

r T

g*

4

.a t

w

• • b

.' s f

5 g

=

i P

1*

1 4 E.

.E

~ N ' 9 " % 9.K.'

l

. u-

- ~

.b

' T. M M

Ig U

i 4

P e.g

_.a 58

=

a 1

m

~

o : > e n

(.

i j m,

o 6 e a I

t T

l.].

e l

w e..=d Y E E'- w 1

n s

f.

$I b E

s=g l

y e

a o w a

?

e w

w

_ o 2

g e e-6 l.

4 a

0

> M I b 4_

t 4

4

• r c

s I

_*8 '...

M g

i

./.

p Y:

=

7_

, e 4

-e

_m-

-)

m e

% ' 'V* *,r

, n r. s ' s t

,a+

=

W c--

2-

• t I

_e*-

v*

L-a ": -

{fy

... Q-

%e p

y p' 5-G '> z -

e.

s.

L

~

~ 1 y g N

,/ m.,: =j c

• A m

<ww ~,

7,

,... ~._ - -' -...

3

.b

.,_.%_.,?' U.. %_ ~' w &. N5 E

?

s m.

b', W;,V.:w% : -7 gj E

q.

L i.

.s k

4.___!

I L'K d Z v 3,b.9 ' If.

E t

n m=x-wee w

3

\\

C 4

_J Z

C s

W W \\

L' t____

iL 5

C, I

J

-t. "h.' -i. -- =.

r 4

(

G' J,

f 8

w

.a, 6

t

-s

- I-.%

W' ed*' m.f.

=:-

W M

!a g :(%j.

,g-gj ;t g

rt'J

~

L#*h

~

W Ef s _, [_ ' > - - r-- %.07.Oi.

t' u rgdi d+ di N.-

.e

{ _p[ r

. C' i

=

p

~

s L.

- -, -., } j.

i I

g,",,,,,'._g_'_-,{.

xnexs x-e H

m 'Mc 4; L.y e

. e 1

m ik 8.

.y c:,

. p"I

.w' i

~

-=

I

. ;6

, f

% # %,.m v.:x. s,.r>

l 6;

s

.m ks

• ~

s y

s.

_' v, e

~ '.

p

'g -,.. _4g/- I *,'; i

,. i N i i.

w w

L d

'i

\\

]j 4 '

e

k J'I f..

[p$ %

q.

.nk&y:. w )l~'

?,s _j. *,

+

r w% g:]b 30.3

.o o;-

• r j,,_--

.y~y*5<1.,

t

. I

-5 g

,b.',.1ild; Je W.h N

e 3r v 9

.~ - -

N ew 3-n,

,n 3.., 'ts 1-u4

'A i,,

A.

,g e.~.. 4. : 2 :

wt / -.. f,g

-6 e

T e si

/M[Cs y;

/

N q.v.. - a n%.m

.L t.

.. n. g s.

f, t...

On.m ^6 i,.

4. y5(bld %g k r

'y 1 * ;, vj.

i t6 v

i ;-j *', s q % p ;

t m56 s ::$ "

' I f

'l[s, S.in e

g r. ; ; r,.,3,L gr 4.

J +4 E..p.-$

i S,,_..n'}.., f,

?

s a

c O'u m'[*

m

..9

{~g

~

. dm y

~1-F., Mi V

=

f 1 ira.

E.

j

i. (

lp 7 j e.3, :

v, v-j.5 e

3 l

l l i

y z g y gat 0 o-c r

-'l-

.e

=!

,j twt, %s,,t $,

f 4,,n

.I ry'tng' Q.n

• 2 =

r---L

y

, F,e' [b,,, -y' A t

1 l--,,.

- o

.c i

. - - ~.

g,. g a

y : -

o ea,,...* '

e.1.)~

s a

w t

c e

,.-U:s% Q g

39+

g

.x' Egs n ?

. n w. -s u 3

- -.- c e 4,q e p. ;n.r,.f. c E

E L

l a.

,s p g. q..,.. A..

'z. s......d ? ' *1. *

+k b.y

^

e r s <

(p l

i^f A' a

-)-

I,5 A 6 I

g

/

~f

v,'.? rd.Mh k,'s' M

s

^

[.

i

.J mw% -

4 g k',-va y,e p

< $ e a o ', J.,. A f

.w. %g,.

f tts m &.

W y ; W':(p

~

.; ; LYS s

e yy-

~

t' 2

) K. n.~3..E W

f

• ,)

g

' s Jyd

• A,; ' <

M

1

..'q$ ?*

• U ;.

,,g,,u,r-h....-A,,

u.

.n,

• .,Mg

'/

.t[.

g4

's*B

.m r*n..

,'[^,

I,.,

m'

_ f n.,,., y *._,

s e

~

~

T,..es,*,e e,,, ' c w

i3

.L.

%, e --

s-

' j M N+* ' ~ % ',t 2

'w.

m j

g

, f

, m[

w, m.

3

[.

-I.

a u

s g

s.

P

< * %.,y' t.e. c.

e.

V;-;N.,..m'.

F

.. -. be 1, 3 q-gr,

. yf,e,c m,

g-

- s 3__

• e..-.

,r y < w< %' ' r d'.,. %,,

• ~

l----'^-

? -

e 7, q,,, ~. ~~,,

U 1.._-

y C

v c

sr.

a g

?h

,' m} - dW$

tc'

~,, - *, *,,,; f _,4 __f-met'-

a x

e l y i<

3

. %,,:g,e. ' 7%

n ___

_s-5 N

C s

f. * - ~ -

s oQh

[

~

'b

=h s If ? < T j' l

y

- # v.

fp'y. W

?

s

'm.

r.,-_

g LJ y.><>q f

c

=

%3

,1.t -:

i e

r

-r-i

,'. 4 b M*'3.'l44 sI f.

t J M

f e,,.

f1 s

lf?*Av. v,:+

s-I

^

1.N-Y '- %

• i

~

- -... x i

g. *?.>>

.e/k 1

l k h'.

d l

~u:v y'14* I.

1' y h y; '- C' p ~q ' I 9'4- $ w.it; e

1 we

=

',$ T.,

f1 3,d.4, vu..

L y-c ge U ~,pd.,.

+-

. *z (,1 J a*

$d t

e

~,. -

r_ mN..

.r.,

[-..,t d,%@ f.

n. s b,,, i_ *, ; + : -,

.,

• 1,..

.4 A

.~ c

. A 2

--s, g

} ;C g -y,

t; y

g _

==

.~, Lp:.,

. y 7

,-O,-

,j%

-

=,

. g c.,

,,,E

N _,.&.,d. A I...

3,.,

j,'.

A e-t % 1,.

g h [--

e

,x,.. 4'.w;g.'.

E 4O j

-y g

,I

. ty M * /

>l

.. v'.

>.,.,.,-~.A.h.

\\_

a y _ ~; -,,' -.,

y g g

r.

c y.,.

., - y.-

i

,g'.

.. _h b 1.Jg '..T +

j, [,'

y,11

• 'M 3

( T *w,'.9* g;.,

, g'-

L V V, /1 m

8

~~

A f%w.

( ? {s O.* t r w l

f ik l '.

v, O/A.

.. %.;*j

• • g.

/g -

sk D,. * /,..

e-"

y

~1 3

1

/Jl'

,L f

.,g y ; r it -

h m-. s *

.7.

g S.

f

]y w ),;

.g t,........,(

" ['

w y, ; ). m; t y&.. ;y.17,

}

- ~,

/

-w.

n.

v.

uq.

s

? 4 ? f,.f s.

N..h

.q

.9 2,.

~

3 1*

.- %p

• ie*

v p }x;

~

ri

~

N

,,3 e '

7tISDET TJOIJA.9 *WZ9 S'"ATIO3

!Y?IOAL ft!L A.9'tAY "9

'I*:3L! A"3 D7J31,': SA"Of LOA 0! ': tY FtJIL "'YPt 25 1

1 1

1 1

1 24 1

1 1

3 t

3 1

3 1

1 1

1 23 2r 1

3r 3*

3r 3'

't 3*

3r 3+

3r 1

3r 1

3r 10 g- - <

3 f:

22 1

3 1

3 1

g3 1

3 1

3 1 I 3'

1

?

I 1

1 s

21 1

3

'a

'r 3'

i 3r 2*

3r P

3r 3*

3r P

3r 3*l-- -

l

?r 2*

?r i

9 l3 h,_1__

l1 20 1

3 1

n 3 1

3 1

3 1

3 1

3 1

g i 1

1 1 i g--

-- 1 3r l 3* 1 =rl 3 wlsein

,- l 3*

19 1

3*

3r t'

3r

?*

'e

,e

,e w

3r 8

l3

'p - -l 3 l*

-g 18 il ya 1

3 1

1 3

1 3

1 1

1 h1

?

1 3rf:*'t P I 3r f ?

3r l ?"l 3f 17 1

3r 3'

Tr 1r if P

3*

't 3'

'f "l

i 1 gf[

l? l1

-y l3 l1 l1

• lt f3 l1 l2 16 1

3 3

1 !83 1

i 1

3 1

t 3rlP 1r ! P ir l 3*

?? f P ar l " 3r 3* l ir 3* Y,r 15 1

P 3r 3+

3r P

'r

,a 1

6-g4 I;

le l

1 3

i st i 1

3 1

?

I 1

3 1

3' 1

3 1

3 1

1 le t v l 'r l P l1r ! P ! 'r l "l +r l 'r 13 1

3r

" 3r P

1r 1r P

y ar P

3r a

i fl 3 f3

!1 fl 3 I2 1

3 1

3 1

3 1

1 3

1 3

1 3

1 3

1 1

1 3

1 3! Pl, 3 r ; P ' :r l 2+

3r l P 3rf"l?r 3r f 3*

, P I[' ?r 3r P

3r P

't P

4-

~~

{1 l1 l3 10 1

3 1

3 l1 1 3

1 3

1 3

1 3

1 1

3 1

?

l 4

t 3rfP!3r 09 3*

3r 3*

3r 3*

3r 3'

3r 3'

't 3'

':t 3* 3fj 3*

3r 1

1 3*

3 i

08 1

1 3

i 33 1

3 1

3 1

3 1

3 1

3 1

3 l'

1 1

3 i

t.., _

-J i

07 1

3r 3*

3r IP 3r P

3r 3*

3r P

3r

• t y

3r' 3'

3r 3r

i. -

- -.J 2

f3 06 1

L' a.1..y 1

1 3

1 3

1 3

1 3

1 1

1 3

1 i

3* l' P l5l 3rP st 3r 05 1r P

3r 3*

3r 1

1 1

3r 3

3r I

l 04 3

3 1

3 1

3 1

3 1

7 1

1 1

7 l

1 1

l l 3r l

03 1

3r ' 1 2r P

3r P

3r P

3r 1

I l

O2 t

t 1

i i

t i

1 j

l l

l I

I A

B C

0 E

F G

H J

K 51 52 53 54 55 56 57 58 59 60 6: 62 63 64 65 66 67 68 69 70 71 72 73 74

<e,.

?:r ? Wie sten (Cycle h1 P ta.dicstes unirradiata W !!! ruel ror Cinale Jaten (7 cle $) 3 4":d P toth i M ienta irr9diat ed ?fpe !*! rs*1 7

3-r indicates ? pe I!!-F tv-1

/

1 indicates ?/pe ! ruel FITJ?? ?

g f Pg e; g- +^ -

geW a=p..,.

> armersep wr-m pq' A

kb *, $

s

[ A.%h

,N

%.% ~

,f

.)

~~$

[

M

-a Ae.%W.

W' s1 w8.

i w+ a -n. Wm-Fr ?- tm?m P.-r~.W FN.

.3,y w.

• N~".

... my.:.- - -

,s -- -,e. um.s dub...

u.aw s >=.-t.. M,an,.

. -t--

.--3dwhA, v @.- - -

-...s

~,.

ar.e' "'

o *-.%-.s %. - w# N.4 m

1.-~,, 4 g

m

- v.4.e e-s.e

~..

• ',.y

.., x.

.m a,,,

wme w

-... ; ~ :v,,

m=...%w,

w w. #,.fah,. e,.w ;p.

. c.

n<en.

4. -

. ~.

,-www v>w 1-:

.H:KR, 4.t.

^ '

L

. c

• w.www _ ~ A L ' # '* -

,, owe = s 4 ^ *;,

4 4

,., i k 94 $@*

y.

...~m-

+ ~ ean ov

-.=.-ese r, s, e hf' MD -

'%-W W

4#

b I-A"e[

• h s.

.g'

.o.

_/

,.o*

- se e---

N-

- - + = =,

m*-

.wm-

. ame

.s

,y=m-.

w %e.

g

.asr e

==m-

-~~-.m

, wa i

w-1 f

I I

/, ' *,

I 3

i y.

.y.

5 i s

Agg. o f

,.s..%

1, l

2. m.

.w j

i

- +9. 4 -

.~ __

l

,'.' w' 's.

4 1

t

\\

t Q% 2 i

\\

,". G.

l

-W:w:

s me.

j

-4 l

.[4?.? '

g.; /..J..

w e f,* Yv -

,_=

1r 4

p 9

s M '

we f.

• M1'-

7 we t

-wt

~.r.V.,,

.kg..

'6 f

~s _.y.,

. s ',s.se.a

(

^

'g 7,_q h i.n. 7.1. *M.j,;{2gl!N" l

r

t..

m._-.<...;-

q pc,- x -,

s a w. w'c M m.._ v ~,. '

• a r

'g J

-.,,.4$

4.v ag,,a*g5

,A.a

-. ryr. : p. v., :,wfr',. %Qwxgp,3

, e y

g gg

.gs z.

~

. -. <m.. c, _

.~_.,w.x,,,,m e

n._

2M %h Ed

(

W W. 5. S fe r'/

a

m.,

,-Mf57 P9 48798e4 OFFICE: B964 739 435-

• M.,,,

o.re necemo (-

1 l rec. 4m ggg g can osoccu en, No D. R. W 5h, LIa.

natano.

eeooms-CTHea:

I to, cetG; CCa O T HE R.

l h

z(3) 19 onaformed cys.

ACTION NECESSARY S

CONCutetNCE C

y ANSWE9ED e

r40 act1ON NECE55 A8Y [

Ccew &NT S Y.

j CLA55.F4 8057 C5F'CI lF'LE CODE 4 DCCKI.T $0-10 /

g eco No

tSCli;PTIONi Mvs 5. Undantes, a(F{RGED fo l O A!! I effElvtD tv i Ca't Ltr. requseting that Appar=44v #A' of i

0"1-2 be acended to allow the oraratice of acyds 12-28 de::ignated a;Mifj*ed fuel design, den reactcr' Dr w/all exma--A,..'l MI:.N p M h y g ge Dres s

e.~Cic ss ts-(22 cys) l 2r. Nan (w/ info cy) i L'E" I' i.evised 11-1.Mh)

I I

i mI'n 1 =Tesden mie ar der tah I

i 2:.crip;,len and '.3:.arca ava.t.at.i.n acecrt of me II:' 4 hel,i dtd l

l-11-i.7-eh (no or4 ef anc1s?

I e

i i

t a - <5

istribution:

1 - roral rue

. - sucp1 ril. \\ /j i

i i

1-Mc nt

/

s 1-E I

5 7 " '

- ii. ST.eele 2 - Gesplianos j

j

v. s. arce.c (NencY cc-s5 c" Mall CONTROL FORM Feau.wi anc. m s l

i i