Text

Requests Executive Branch Opinion Re Transnuclear,Inc Application to Export 51.054 Kg U-235,enriched to 93.45% U-235,to France
	ML20247R689
Person / Time
Issue date:	04/04/1989
From:	Peterson M; NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA)
To:	Thorne C; STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT
References
	NUDOCS 8904100034
	Download: ML20247R689 (1)
	v • d • e

.

b 9,-

UNITEC' $TATES l[

n-

- NUCLEAR REGULETORY COMMISSION

(

j WASHINGTON D. C. 20655 s

~

....+

APR 4 1999 e

--n,.

Mr. Carlton E. Thorne, Director Office of Nuclear Export and Import Control Bureau of Oceans and International' Environmental and Scientific Affairs.

U.S. Department of State Washington,'D.C. 20520

Dear Mr. Thorne:

Enclosed is an application from Transnuclear, Inc. for the export of 51.054 kilograms of uranium, enriched to 93.45-percent uranium-235, for use as fuel in the BR-2 reactor in Belgium. The material will be converted and fabricated at CERCA in Romans, France.

Before taking action on this request, we would appreciate your views, in accordance with established procedures and from the overall perspective of the Executive Branch, as to whether the proposed export meets the applicable criteria in the Atomic Energy Act of 1954 as amended by the Nuclear

. Nonproliferation Act of 1978.

Sincerely,

.k

~

v y

.arvin. Pe'tEson, Assistant Director for International Security International Programs Office of Governmental and Public Affairs

Enclosure:

Appl. dtd 3/29/89 (XSMN02444-Belgium) n.-

cc w/

Enclosure:

T. Hart, DOE R. DeLaBarre, DOS N. Martin, DOE M. Rosenthal, ACDA G. Oplinger, D0D 3

N,,f 904100034 890404 DR XPORT PDC SNM-2444 i

1

T nnu pc4 u.a.tuCLEAa CEtuLAToRY COMMISSION

/'okFbth APPIOVED BY CAD APPLICATION FOR LICENSE TO EXPORT NUCLEAR m 22s m ae21

.i l

MATERIAL AND'EQUlFMENT (see /mtruction on amnel 1 '

. l1. APPLICANT'S le. DATE OF APPLICAT10N

b. APPUCANT'S REFERENCE

2. NRC

] e DOCKET e60.1 tJLICENSE NO.

USE March 29, 1981 NUK-495 USE

- ///) At// 66

)(I ?/ h @ O l/ ////

'PLICANT'S NAME AND ADDRESS l RIS

4. SUPPLIER'S NAME AND ADDRNSS lRIS (Complete if applocant es not suppher of matersall Tr'ansnuclear, Inc.

U.S.D.O.E.

b. ST RE ET ADDRESS e NAME Two Skv11ne Drive e/o' Martin Marietta Energy Systems, Inc.

c. ClTY STATE ZIP CODE

b. STREET ADDRESS Hawthorne, NY 10532

d. T E LE PHONE NUMsE R (Arme Cooe - humber - Estemen/

c. CITY STATE ZIP CODE c1 M _7 a7_ S U E vve 7ntA nak R4Mnn TN 17R30

5. FIRE T SHIPMENT

6. FINAL SHIPMENT 7. APPLICANT *S CONTR ACTUAL B. PROPOSED LICENSE

9. US. DEPARTMENT OF ENERGY SCHE DULE D SCHEDULED DELIVERY DATE EXPlR ATION DATE CONTR ACT NO. fif Known/

Three years from ASAP N/A Same as item 5 date of issuance Tn be determined

10. ULTIMATE CONSIGNEE l Als l 11. ULTIMATE END USE l

,y,yy (include plant or facility name)

Centre d' Etude de L'Energie Nucleaire Will be used as fuel for the BR-2 reactor

b. STREET AcoRESs in MOL, Belgium (See attached end use Boeretang 200 B-2400 MOL statement and checklis't).

L CIT Y - ST ATE - COUNTRY Belqium 11a. EST. DATE oF FIRST USE

12. INTERMEDIATE CONSIGNEE l RIS

13. INTERMEDIATE END USE l

I e.NAME CERCA For conversion and fabrication of fuel

b. ST RE E T Aconts5 elements.

c. CITY - ST ATE - COUNTRY Romans, France 13a EST. DATE oF FIRST USE

, INTERMEDI ATE CONSIGNEE l Als

15. INTERMEDIATE END USE l

DAME mennennnlonivn. n a-For transport purposes only

b. STRE ET ADDRESS 11 bis rue Christophe Colomb

s. CITY - ST ATE - COUNTRY 75008 Paris, France 15e. EST. DATE OF FIRST USE 15.

l

17. DESCRIPTION

18. MAX. ELEMENT 19. M A X, 20. MAX 21.

NRC_

(Irelude chemicalsnetchysicol torm of nuclese rnsteros!. gove dotter velur of USE nuetror rouipment and components)

WEIGHT WT.%

ISOTOPE WT.

UNIT (U)

(U235)

Uranium in the form of metal, enriched to 51.054 93.45 47.710 KGS 93.45 w/o maximum.

4y hy_ J. a

b. If & -(( }

. COUNTRY OF ORIGIN.-

[' 9 U1'1 23. COUNTRY OF ORIGINr$NM

24. COUNTRIES WHICH ATTACH D-SOURCE MATERI AL WHERE ENRICHED OR PRODUCED SAFEGUARDS (/f Knosws)

USA Euratom

25. ADDITIONAL INFORMATION /use seperete sheet t/necessaryf

At this time it is unknown whether there will be any Australian or Canadian origin material, however, Transnuclear, Inc. will advise NRC if such is the case.

the applicant eartifie. that thli oppiimtion 1. prope7sd eonforseky e iPFinne 10, Code of Federal Regulations and that allinforenetion in this

~

application is correct to the best of his'her knowledge, y \\( \\

f 27 AUTHORIZ ED OFFICIAL

s. SIGNATURE

?,

b. TITLE hh ' 0

b.

-3

[..

[ /

(

o s

neg riory

(

h TRANSNUCLEAR,INC.

March 30, 1989 United States Nuclear Regulatory Commission One White-Flint North Mail Stop 3-H-5

{

Washington, DC 20555 l

Attn:

Mrs. Betty Wright i

I Re:

Export License Application TNY Ref:

NUK-495 t

Dear Betty:

.m Enclosed is an export license application, the end use statement and reactor checklist, for your handling of the following:

i 47.710 Kgs U235, contained in 51.054 Kgs Uranium, in the form of metal, enriched to 93.45 w/o maximum.

Please call me if you have any questions.-

i 1

Very trul

yours, l

N 1

~

(L aih "N

' Patricia B. Quain Traffic Coordinator PBQ:dmr: 05 81 D Enclosure

p..

)

i

(;

Y TWO SKYLINE DRIVE

HAWTHORNE, NEW YORK 10532-2120 TELEPHONE: 914 347 2345

FAX: 914 347 2346

TELEX: 681-8082

~f$0h

NMu j

.8

l l

l r

'1 Boeretang 200 ' B-2400 MOL (Belgium)

TEL (014)31.68.71 - 31.18.01 TFX (014)3i.50.21 f

a TLX 31922 l

TLG Centratom Mol L

.)

To whc:a it may concern l

END USE STATEMENT l

The undersigned certify.that the following marimum quantities, i.e.

'50.800 kg of uranium 93.30 w/o U-235 enriched 47.396 kg of U-235 content in the form of mets.'

will be furnished to us under a Short-Term, Fixed-Commitment Contract -

held =between EURATOM on behalf of NUKEM GmbH and US-DOE - and will be used as fuel-in the BR-2 reactor at CEN, Moi, Belgium.

CERCA, Romans, France shall perform the manufacturing of ' the fuel elements.

We authorize Transnuclear, Inc., Hawthorne, N.Y.,

USA, to apply for the

'U.S. export license.

h. h Date :

Signature :

p. Spae n DeputybeneralDirec tor Scientific Departner.ts

,N,;

""' *** *ad * " *' 8'"d*" ""' #^ **""". s-u 6 Bru i. (s.igium)

TEL (02)661.08.11 TFX (02)660.75.63 TLX 22.718 TLG Centratom Brussels 3

e

R 0461 m,i *f 1 1-q-~

CHECKLIST FOR USE'IN REVIEW OF REQUESTS FOR HEU TO DETERMINE TECHNICAL AND ECONOMIC JUSTIFICATION BR2 REQUEST I

i

1. Nace of reactor and facility : BR2

2. Location':. Belgian Nuclear Research Centre (C.E.N./S.C.K.)

i B-2400 MOL - BELGIUM

3. Quantity of uranium requested (kg U) : 50.8 kg U

4. Enrichment in the isotope U-235 : 93.3 %

5. Quantity of uranium requested (kg U-235) : 47.396 kg

6. Type of fuel element and form of uranium :

Assemblies of concentric cylindrical tubes,'where'the fuel is under the s

form of UA1 powder (x z 3), 1.27 gU/cm, mixed with aluminium and burnable poisons added as powder.

7. Current reactor power level (MW th) :

Current reactor power : 60 to 100 MWth depending on the experimental loading.

Maximal reactor power : 125 MWth Current maximal heat flux : 470 W/cm2 Maximal nominal heat flux : 600 W/cm2

8. Duty factor : see appendix 1.

Average burn-up : a) of a load, end of cycle if 6 to 7 $ of experiments : 37 %

b) of eliminated fuel elements : 54 i 4 %

9. a) Current core loading (kg U-235) :

8 to 12 kg U-235, depending on the experimental loading fI b) Amount of fuel per element (kg U-235) :

I 400 g U-235 for a standard fuel element V

c) Number of elements in core :

27 to 40, depending on the experimental load ammsemeyexnosas*mos*- awnan********YRT** mm

1 R 0461 d) Average core life : One fuel element serves for 10 running weeks, i.e. 5 cycles of 2 weeks e) Active core and reflector dimensions :

height 914 mm diameter 1100 mm hexagonal lattice 96.44 mm pitch fuel active height 726 mm f) Neutron flux :

"Y NE

NE K

LG.JE c s ?ht V U

1 a

9 10 " n/cm s 1

2 1.4 10 " n/cm,

Central Be plug 1

2 5 7 10 " n/cm's l

3.8 10 " n/cm s 1

Standard fuel element 5 7 10 " n/cm,

j 1

2 Driver fuel element (0 200 mm)

10. Annual fuel usage (kg U-235) :

Routinely, 75 fuel elements type vin, or 30 kg U-235.

In case of development of the safety programme for fast reactor :

1 fuel element 200 mm or - 2 kg U-235.

In case of starting of the fusion programme :

20 fuel elements type Vn or 7,2 kg U-235.

11. Annual spare fuel requirement (kg U-235) : 30 kg U-235 minimum.

12. Plans to increase, decrease reactor power level :

We continuously optimize the reactor performances : specific and total power, energy produced, number of fresh fuel elements to be used for an imposed cycle length, taking into account the experimental loading. The present trend is to increase the available fast flux and consequently the specific

power, maintaining the maximum thermohydraulic characteristics of the reactor.

13. Estimated annual supply of current fuel request : 30 kg U-235.

14. Required manufacture's working stock, if any, included in this request

Existing manufacture's working stocks are not included in this request; the manufacture's working stock will be zero on December 1989.I*)

15. Fabricat' ion loss, if any, included in this request (kg U-235). (**}

The ordered Spanish fuel is not yet available.

(

5 % for fabrication and scraps and 3 kg for completion of a current fuel element fabrication (100 FE).

)

l lWr; germ.-~.._ _ ______ ___ ___ _ __ __ ___ _ _ _ ___

a

3 Lh R 0461 E :.,,. # -

s l

16. Names of convertor : US-DOE Oak-Ridge Tennessee USA COGEMA BP-4 F-78141 Velizy France

17. Fabricator of fuel : CERCA Romans-sur-Issre, France-

18. Inventory on December 31, 1988.

The complete ' inventory is given at appendir. 2. Find here the detailed items of this inventory concerning available fuel for the reactor BR2.

Localisation U

U-235 Enrictment Remark got

[kg]

[%]

CERCA (Romans) fabrication process 39.172 36.321 92.72 e usable fuel to be recovered 22.643 20.733 91.56 b to be recovered ordered Spanish fuel (,)

24.326 21.874 89.92 a to be recovered DOE (USA) 0 0

BR2 (CEN/SCK) fresh fuel elements 46 standard type 19.760 18.343 92.83 b usable-18 special type 4.542 4.084 89.92 b not usable 36 for experiments 9.957 9.167 92.06 b not usable 210 usable spent fuel element 61.942 53.073 85.68 d

Remarks : a) Scraps.

b) fabricated unitradiated stored fuel.

c) unirradiated non-fabricated fuel.

d) spent fuel stored.

19. Date at which the available and usable inventory will be expended :

end 1991 Date at which current inventory, including a, b, c (usable), will be expended : end 1991.

20. Date current requested fuel will be needed at reactor :

Sept. 1990 (or mid 1991)I*).

(*) Preliminary data

the ordered Spaninh fuel is not yet available ;

there is now no guarantee that the Spanish fuel will be available in December 1989.

J l

i l

3 0461

')

w

.; }

+

h

)

i l,'

21. Date. current requested fuel will be needed by convertor and fabricator :

end 1989..

~h I

22. a) Time taken for shipment from USA to convertor / fabricator : six months.

b) Lead time for ordering in USA : six months

23. Date et which current requested fuel will be expended i.e.,

when a further HEU supply will be needed at reactor : begin 1993-The current date sheduled for the replacement of the Beryllium matrix is January 1995, which will cause one year shut-down.

24. Dates at which reactor could be converted to 45 % fuel; to 20 % fuel, including time required for licensing procedure :

No date is fixed yet for BR2; in routine, it will not be before several years,,as for other high flux reactors : ATR, HFIR, HFR in Grenoble...

From what. we know, tests of fue) - plates U Si -Al G 4.8 g U/cmD.~are 3 g satisfying and the industrialization of the process is in under way.

For the future (at a time still to be defined), it would be possible, if requested, to use MEU (45 % enrichment) at the BR2, reactor. The ' time -

required ' for licensing procedure is equal to a successful irradiation campaign and post-irradiation examination of prototype fuel. elements, increased by six months for reports, when the reprocessing of this fuel-has been demonstrated feasible technically and economically. The use of hEU in BR2 demands the availability of fuel plates containing U Si -Al-3 y 8

( 2: 7.1 g U/cm ). No prevision can be given concerning the reliability of this fuel, which is required in order to attain the density level of LEU required for the BR2-reactor.

25. History and dates of previous HEU supplies by the U.S. : Continuously, t

since June 08 1959, has U.S. supplied HEU for the reactors BR2, BR02 and third parties.

The last delivery of 39.824 kg U-235 (contract Ag 2218) was shipped at 0:.tober 21, 1988 to CERCA : the appendix 3a, 3b and 3c give the details concerning respectively the deliveries of U-235, transfer of fuel for reprocessing and supply to third parties.

p 4.

4/.U2.09

'l

'L R 0461 f :,,, ~ '

~S-L L

l l

26. Amount of fuel of.' U.S.-origin previously consumed during operation of-1 i

reactor :

l l

l The total amount of uranium received up to Oct. 21, 1988 is : 1,147.332 kg U-235 including ordered Spanish fuel (see appendix 3c)

The total amount-of uranium burnt to Dec.

31, 1988 is 1.24 g U-235/ mwd x 340,130 mwd x 0.97 = 409,108 kg U-235.

The appendix 3d gives the total balance of highly enriched uranium received at BR2.

27. Status of cooperation between reactor operator and Argonne National Laboratory in reduced enrichment program (RERTR) :

We have maintained the contact with the ANL repres entatives,

for collaboration in the RERTR program, although there is some delay in the testing of very high density fuel plates We cooperate. -also closely with the. fuel fabricators mainly on the performances of our fuel elements (fission products release.

corrosion,

cladding, behaviour,...).

28. Status of agreement between reactor operator and ANL to reduce enrichment :

Agreements and commitments for a joint study between the Belgian.

Nuclear Research Centre and the Argonne National Laboratory (RERTR progt tm) on the utilization of LEU fuel elements in the BR2 reactor are effective : contract signed January 22, 1985. The first phase of the program has demonstrated the theoretical feasibility for irradiation of a LEU fuel element test in the BR2 core and-has been terminated with the first appreval by the Safety Authorities, by the presentation of the Safety Analysis Report at 8th March 1988. The research on technical feasibility is in progress. The analysis of this test will assess the modification in the performances and in the safety, with corresponding economic implications. The - schedule for BR2 test elements is given at mpendix 4.

29. Status of cooperation between reactor operator and IAEA reduced program : The Belgian Nuclear Research Centre as reactor operator participates regularly at the consultant's meeting organized by the 1AEA for the reduced enrichment program.

_________.___-_-__m-_------_

R 0461 4

APPENDIX 1

$ 8. Actual and foreseen duty factor.

(

i ACTUAL FORESEEN 1987 1988 1989 and 1990 (2)

Minimum required date begin 18 Dec. 86 16 Dec. 87 12 cycles of 14 days date end 16 Dec. 87 15 Dec. 88

+

end of cycle 13/87A 13/88A 1 special campaign time of the year (1) [ day]

362.7 365.3 365 operating time

[ day]

180.2 167.6 182 duty factor 0.50 0.46 0.50 energy produced

[ mwd ]

11,898.2 10,958

- 12000 number of fresh fuel elements loaded 75 68

- 75 mass of fresh U-235 [kg]

28.1 26.9

. 30 Remarks :

1

1. The operating time is defined to be the time when the reactor has a power

> 80 % nominal power for normal cycle and > 1 % nominal power for special campaign.

2. The required operation han to produce radioisotopes with a sheduled programme determined by a minimum of 12 cycles / year, each with a minimum energy produced of 900 mwd. At least, one special irradiation campaign will complete the normal irradiation progracme of each year 1989 and 1990; in the year 1989 the special compaign MOL 70 vill be equivalent to a routine cycle and in the year 1990 the special compaign PAHR will occur during a long foreseen shut-down.

R 0461.-

L g ^

APPENDIX 2

$ 18 : Inventory on October 21, 1988 (end of cycle 13/88 A)

Localisation U

U-235 Enrichment Remark tot

[ kg ]

[%]

CERCA (Romans) fabrication process 39.172 36.321 92.72

c. usable fuel to be recovered

'22.643 20.733 91.56

b. to be recovered ordered Spanish fuel ***

24.326 21.874 89.92

a. to be recovered DOE (USA) 0 0

d. reprocessed CEN/SCK (Mol-Belgium)

LABO : Physics department 0.243 0.222 91.36

a. for experiments at BR1

.BR02 61 fresh fuel elements 20.130 18.102 89.93

b. usable only at BR02 BR2 18 fresh fuel el. type Alloy $n 4.542 4.084 89.92

b. not isable*

18 fresh fuel el, type S 3 S 2.897 2.600 89.75

b. fo experiments 18 fresh fuel el. type Cerset $n 7.060 6.567 93.02

b. for experiments 46 fresh fuel el. type Standard 6n 19.760 18.343 92.83

b. usable 208 partially burnt fuel el. 9 84 mm 59.766 51.119 85.53

d. usable **

2 partially burnt ATR 65 6 200 mm 2.176 1.954 89.79

d. usable 1 low burnt AIR 10S W 200 mm 1.931 1.742 90.18

d. to recover 658 totally burnt spent fuel 160.367 119.254 74.36

d. not usable Remarks : a. scraps,

b. fabricated unirradiated stored fuel.

c. unirradiated non fabricated fuel.

d. spent fuel stored.

only useable, to restart the reactor after a prolongated shut-down to compensate the antireactivity of the beryllium poisoning.

- 56 partially burnt less than 30 % and reactive fuel elements permitting to produce 4982 Wd.

158 partially burnt (30 % < 8 < 50 %) less reactive fuel elements permitting to produce 4315 Wd.

- - preliminary data ; there is presently no piarantee that this fuel will be available in December 1989.

C 1

m,ceoce, y

l R 0461 1

'J i

er

(

APPENDIX 2 (continued)

Usable partially burnt fuel elements at BR2 The partially burnt fuel elements are considered usable at BR2 when the fuel elemants aren't damaged or don't release fission products and when Uranium content is higher than 200 g U-235 per fuel cell; this latter condition means that a fuel element containing less than 200 g U-235 is less reactive than a Beryllium plug in a cell neighboring the core configuration of 30 fuel elements routinely used. The listed " mwd usable" is the difference of residual U-235 and 200 g U-235 per fuel element, divided by 1,24 g U-235/ mwd.

l First and second batchs of partially burnt fuel elements are more reactive than fresh fuel elements containing burnable poisons; the actual stock of these fuel elements is less than the minimum required for a good management because of shortage in fresh fuel deliveries.

Accumulation of fuel elements burnt at 40 % is due to

1) not sufficient stock of reactive fuel elements.

2) small core configuration doesn't permit to irradiate all 40 % burnt fuel elements.

3) irradiation conditions of experiments positionned in the neighboring

cells, burn-up type n

U-tot U-235 U-235 U-235 mwd fresh fresh burnt usable usable

<13 % 6n,61 20 8633.63 8007.13 820.59 3186.54 2569.79 Sn 4

1571.81 1456.58 164.46 492.12 396.87

<30 % 6n,61 13 5590.23 5153.33 1188.17 1364.94 1100.76 Sn 15 5944.35 5503.90 1369.62 1134.28 914.74 j

l

<40 % 6n,61 58 25031.90 21136.25 8307.92 3228.48 2603.61 f~

Sn 19 7434.99 6911.11 2337.46 773.59 623.86 k-

<50 % 6n,61 79 34158.94 31549.42 14401.34 1348.08 1087.16 i

I total 208 88365.85 79717.82 28598.56 11528.03 9296.80

2 7

7 0

6 0

0

+

E' 5

6 0

0 7

5 8

6 4

5 2

5 9

5 7

2 7

0 7

7 7

0 6,

7, 9,

7, 3

5, 3

1 1

2 3

6 9

9 9

9 2

8 1(

3 3

1 1

1 4

0 0

2 3

5 0

0 0

1 g

/

1 8

7 8

9 1

5 4

9 0

6 5

3 7

5 4

0, 2,

2, 2,

2, 8,

7, 4,

R O

U 4

0 4

1 2

0 3

9 T

4 4

2 2

1 1

C AE R

2 R

n B

o 9

9 2

3 4

4 4

3 4

4 8

9 4

5 5 - 6 6

6 6

6 i

R et O

t p 6

0 o0 2 o6 8 o9 1

5 o9 o7 9

1 0

.t0

0. t 0

0. t 0 0

F ae 1 t 1 1

1 D c M

e 8

0 6

3 5

6 0

6 3

8 1

1 4

U R

0 3

2 2

3 2

2 2

0 0

0 T

N A

R U

D E

)

i N

N l

C M

E I

e M

C R

cM

(

N nO 1

E eT

/

a h

c d

e o

f l

rA 2

2 2

2 i

eR 9

0 0

0 G

f U 1

1 1

1 I

eE I

R G

C C

G G

C I

A A

F O

Y.

2 T

0 P

R P

B 1

t S

r 3

4 2

4 1

3 r

o 9

9 9

2 3

6 3

e t

?

2 2

2 3

d c

5 r

a X

X K

X 6

X O

e B

B B

B 9

B r

ro f

A 2

6 1

8 t

2 4

2 1

c

/

a 4

3 3

1 3

3 3

r 7

/

t L

L L

n E

M M

M o

B

/

C E

U U

S B

E E

P 1

2 3

4 5

6 7

8 E

R

0 4

0 0

0 6

0 0

E 7

8 7

9 0

7 7

1 5

1 0

6 6

4 2

0 5

9, 2,

7, 0,

5 9,

7, 5,

3 2

U 0

3 6

8 3

9 8

0 4

1 4

1 1

5 0

2 0

0 0

1 g

/

0 2

0 6

7 5

6 5

0 9

9 8

9 7

5, 6,

0, 9,

0, 6,

4, 1

R O

S 4

2 8

5 2

9 6

I I

T 4

1 5

1 2

5 C

A E

R 2

R n

B o

4 5

5 6

6 7

7 7

8 9

6 6

i R

et O

t p 9

5 o9 3 o4 2 o3 7

2 2

F ae 0

0. t 0

0. t 0 0

0 0

D c M

e 4

1 9

3 3

6 3

7 4

3 U

R 0

3 0

2 1

0 1

0 2

0 I

NA R

U l'

DE l

iC I

R

'e 2

N cM g

h 1

j k

k 1

E nO 2

2 2

eT 0

0 0

l i

rA 1

1 1

C eR I

G G

G I

f I A

A A

I eE I

R F

O X

I s

6 P

i 0

P b

0 r

r U

8 2

/

2 e 2 e 9

S r

3 0

1 a

1 t 1

t 9

e 3

0 0

a 0 -

0 -

0 d

3 1

1

/

1 2 1 2 r

N

/R

/R 6

O X

a s

O sB sB 6

R a

a C

aN aN 8

6 4

5 1

3 8

4 1

t 4

4 5

6 7

9 1

c a

3 3

3 r

/

t L

L L

n M

M M

o

/

C U

U U

E E

E n

P 9

0 1

2 3

4 5

E 1

1 1

1 R

0 0

E 0

9 3

3 9

5 9

9 0

5 8

7 3

2 5

2 4

6 4

5 2,

8 4,

9, 8,

6, 3

1 1

2 U

2 6

4 7

3 5

9 9

3 1

3 4

4 4

1 0

0 0

0 g

/

4 4

0 7

5 0

3 4

2 8

8 0

9 4

0 9

7 4

9, 9,

6, 9,

8 4,

0, 1

5 R

U 3

6 4

1 3

0 5

6 4

O 1

4 5

5 6

T 1

C AE R

2 R

n B

o 9

9 9

9 2

1 0

2 3

6 6

7 7

7 i

R et O

t p 7

7 9

2 1

8 9

5 1

F a e 0

0 0

0 1

D c I

e 2

2 1

1 1

2 2

6 1

R R

0 0

1 3

0 0

1 2

0 I

I N

A RU DE I

IC I

R e

N cM m

n p

q r

s t

E nO 2

2 2

eT 0

0 0

l i

rA 1

1 1

G eR T

f U G

G G

l eE A

A A

l R

F O

YL P

P U

7 3

2 6

1 8

0 9

S r

9 0

1 7

6 2

5 7

e 2

4 6

9 9

5 9

0 d

r 5

5 5

6 O

6 6

9 9

1 1

0 1

B 1

4 1

3 3

0 1

5

)

l t

1 1

2 2

47 45 l

c 1 1 1 3 a

3 3

3 9

/

9 r

/

/.

/

9U 9U

/

L L

4E 4E L

t L

I n

M M

(/

M o

/

/ /

/

S S

/

C U

U U

U TE TE U

E E

AU AU E

m, P

6 7

8 9

0 1

2 3

4 E

1 1

2 2

2 R

0 0

1 1

0 2

4 4

2 E

0 0

5 1

6 5

7 2

2 7

2 8

4, 9,

9, 2,

3, 8,

8, 3,

5 3

2 2

0 0

0 5

1 9

1 7

1 9

9 7

0 5

3 2

4 U

1 1

1 0

0 0

0 g

3 6

0 3

0 4

4 6

0

/

8 8

5 2

8 5

4 2

0 0,

6, 0,

0, 7,

3 7,

2 1

9 4

7 7

6 3

5 2

4 8

U 1

9 9

7 1

5 4

2 5

R 1

2 O

T 1

CAE R

2 R

n B

o 3

3 4

7 0

6 8

3 u

7 7

8 8

8 i

L R

et O

t p 7

2 2

7 0

2 0

c A

1 1

e T

F a e 0

0 0

d O

D c M

e 1

0 9

5 3

8 1

T U

R 0

2 1

1 2

2 2

T NA RU DE i

t C

T 5

R e

0 N

cM 1

E nO u

/

1 eT 2

1 4

l rA 0

0 0

i

/

2 C

eR 1

II f U T

eE G

C G

I R

A A

A F

O YL I

P P

U 7

S r

5 e

4 d

r 5

O 6

3

)

h n si i g ni ar 1

5 4

1 po t

2 0

4 5

S c

7 1

1 1

S a

3

/

8

/

8 dU r

/

U U

U 1

e(

t L

E E

E 4

E 2

r n

M

/

1

/

2 el o

/

S S

d e C

U E

E E

G E

G ru E

U U

U A

of Or.

PE S

6 7

8 9

0 1

2 R

?

2 2

3 3

3 1

9 4

0 2

9 0

5 8

9 4

8 7

6 9

8 9,

2, 5,

8, 5,

6, t

1 t s oe 4

8 4

6 3

9 9

t R 2

2 0

5 2

1 2

1 E

7 0

58620 00 1

9 5

h 7

0 9431 8 6 3 7

5 4

8, 5,

9,2,5,0, 3, 9, 0,

5, 8,

5 s 1

3 e 2 r 8

4 41 234 53 9

3 8

F 2

3 21 323 33 2

2 3

J1 g

3 2

1 7342 76 7

3 8

8532 60 6

5 0

/ h 3

7 1

2 2

3, 9, 2, 8, 9, 9, 3, 8, 3,

s 1

e r

2 8

63557 97 2

6 3

U F 3

3 21 32 3 33 3

2 4

G N

I S

S E

CO R

g P

n c

c ccccc cc c

c c

E i

i i

iiiii ii i

i i

R s

m m

mmmmm mm m

m m

st e

e e ee e e e e e

e e

T en h

h hhhhh hh h

h h

O ca c

c c cc c c cc c

c c

H ol o

o ooooo oo o

o o

rP r

r r r rrr rr r

r r

N p

u u

uuuuu uu u

u u

I e

E E

EEEEE EE E

E E

R LE UF m

l E

re f

bf o 5

4 00000 00 0

0 0

mo 2

4 05505 55 5

0 5

u l

1 1

1 1 1 1 1 1 1

1 1

N eu F

~

r 8

89999 01 2

2 3

6 66666 77 7

7 7

e f e 7

st 6

3 21 230 02 7

0 6

0 0001 0

0 0

na 9

1 1

1 ad 1

r 7

667 01 02 1

3 8

T 2

01 220 31 0

1 2

t j

. r p

1 2

3 4

5 6

7 e

R

0 0

1 0

0 1

1 2

0 6

1 6

8 4

3 0

t 1

5, 3,

2, 3,

6, 3

5 t s oe 7

8 9

0 7

8 9

7 t R 3

3 1

3 3

2 8

4 5

4 6

3 2

3 7

3 E

0 3

9 0

1 9

6 2

i 8,

9, 9,

9, 4,

2, 6,

1 t

5 s 3 e 9

3 7

2 6

3 4

8 2 r 4

5 2

4 5

4 1

3 U F 6

5 1

9 1

0 5

8 2

g 7

8 3

1 3

1 6

3

/ i 3,

9, 6,

9, 4,

6,.

1 7

ts e

5 9

1 7

5 8

r 5

5 3

4 6

4 1

0 U

7 G

N T

S SE CO R

g t

t t

P n

c n

n n

o E

i i

a a

a h

R s

m e

e hl hl hl a

s e

l l

aP aP aP d

T e

h u

u n

n n

I O

c c

o o

nr nr nr H

o o

c c

ae a e a e P

r r

vv vv vv P

N p

u a

a ai ai ai C

I e

E M

M SR SR SR I

R L

EUF m

l E

re f

b o

0 0

5 4

4 8

6 m

5 5

7 4

4 0

3 u

l 1

1 1

N eu F

r 4

5 5

9 90 0

2 2

e 8

7 7

78 8

8 fs' 2

1 2

m mm m

m 1

n*

0 0

1 e

e e e oe 1

a s

ss st s r

5 4

1 4

T 0

2 3

I 2I 2

1 2

O;

.p 8

9 0

1 2

3 4

e 1

1 1

R

g 0

2 4

7 3

9 0

5 8

/

0 2

3 9

8 1

0 8

8 4

0, 0,

6 8,

8, 2

3 2

2 1

3 1

6 U

1 1

2 8

SE I

1 T

4 56 66 0

R 7

77 77 A

44 1

P 77 3

1 4 1 2 2

0 0

00 9

01 5

79 1

D 77 38 7

5 7

77 00 0

62 91 0

R I

92 2

9 71 00 01 3

3 5

H e

00 72 0

00 0

T c

01 R

RK U

7 1

n 43 K

6 55 DU UC 8

A 9

O e

22 E

C 1

01 KE ES 2

1 T

r R.

S U

t C.

K NA AA K

k n

e I

A C

C a

i 2

f R

R e

UM

+ F.

M S AM Mi S

r I

C E /D E

ED

/

t t

B R

EE K

KB F

K NK KK KK N

n n

M GU C

B U

EU CU UU E

o e

O AN SF F

N CN SN NN C

K l

R F

M U

I NARU

)r F

e O

su Y

(

L g

P 3

i e

P 2

e h

U 1

w u

S h

r r

3 c

e

)

s e

/

s i

I l

m L

E n

E g

E D

r o

M R

u R

r R

K a

t

/

I a

I u

I U

K s

U r

l N

u E

B l

M

(

C C

a E

7 M

B t

K 3

L R

T e

U R

O F

P M

N B

M 5

4 t

1 5

0 4

c 7

3 1

7 7

1

]+

a 9

/

8 1

r U

U U

U 1

4 t

L E

E E

E 4

0 n

M

/

1 2

(

o

/

S S

C U

E E

G G

E U

U U

U A

A

7" Jt 0461 22.,.

,. 4'. n _

.c

-A P P E N.D I I 3d.

Total balance of highly enriched Uranium.from Inventory dated December 31, 1988.

U-235 [kg]

Total fresh supply US origin 1147.332 (see appendix 3a) i Stock (see appendix 2) i 1

available at CERCA 78.928 useable fresh fuel 18.343 fresh fuel special type 4.084 fresh fuel not. standard 9.167 spent fuel 174.069' BR02 18.102 scraps at BR1

'O.222 Sub-total of stock 302.915 Hot reprocessed (see appendix 3b) 377.565 Supply to third parties (see appendix 3c) 34.161 Burnt : 340,130 mwd x 1.24 g/ mwd x 0,97 =

409.108 Fabrication losses according to the declaration 16.704 of the fabricators until Dec 23, 1988.

Total 1140.453 The difference between the 2 totals appears to be 6.879 kg, which is less than 2 % of the mass corresponding to the energy produced and fabrication

(~-

losses.

f R 0661

, ;. '.l * '.

C',

APPENDIX 4

$ 28. Approximate schedule for BR2 test elements at September 1988.-

a Approximate.tice Approximate codpletion required (months) date

1. First approval of Safety Report.

1-3 8th March 1988

2. Fabrication Feasibility Reports 1-3 June 1989 from CERCA.

3. Finalize detailed specification 3

Second approval of safety Report.

December 1989

4. Fabricate test fuel elements.

12 December 1990

5. Reactivity and flux measurements in BR02 Critical Facility 3

January 1991 Third approval of Safety Report.

March 1991

6. Irradiation in BR2 18 July 1992

7. Cool irradiated elements.

4 September 1992

8. Post-irradiation-examination 3

January 1993 9

The key uncertainties in this schedule are the dates for finalization of the specifications by CERCA and the dates by which CERCA will be able to deliver the finished elements to BR2.

\\

- _

ML20247R689

Contents

Text

Dear Mr. Thorne:

Enclosure:

Enclosure:

Dear Betty:

Navigation menu

ML20247R689

Text

Dear Mr. Thorne:

Enclosure:

Enclosure:

Dear Betty:

Navigation menu

Search