ML20155A857

Forwards Applications for Licenses to Export 24.604 Kg U & 0.302 Kg of Pu to Canada for post-irradiation Exam to Evaluate Performance of Commercial PWR Fuel Irradiated to High Burnup.Ltr of Assurance Required

ML20155A857
Person / Time
Issue date:	09/27/1988
From:	Peterson M NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA)
To:	Thorne C STATE, DEPT. OF, BUREAU OF OCEANS & INTL. ENVIRONMENT
References
NUDOCS 8810060099
Download: ML20155A857 (1)

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AEP 2 71989 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.

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Dear Mr. Thorne:

Enclosed are two applications for the export of special nuclear material (XSNM02402) and reactor components (XCOM1018). The special nuclear material, 24.604 kilograms of uranium and 0.302 kilograms of plutonium, is contained in irradiated fuel elements; the components consist of one reactor control rod assembly, one non-fueled rod and one fuel element assembly cage. The irradiated fuel and components will be exported to the Atomic Energy of Canada (AECL) Chalk River Nuclear Laboratories for post-irradiation examination to evaluate the performance of comercial PWR fuel irradiated to high burnup.

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, C

/) ml a'rvin IG Ye'tirson, Assistant Director for Internatfor'al Security Office of Governnental and Public Affairs

Enclosure:

Appis, dtd. 9/16/88 (XSNM02402and XCOM1018 - Canada) cc w/

Enclosure:

T. Hart, DOE M. Rosenthal, ADCA G. Oplinger, 000 N. Martin. 00E R. DeLaBarre, DOS 8810060099 UGO927 PDR XPDMT PNU XSNM-U40p

f NRC ' FORM y u3. MUCLE AQ CEGULATORY COMM'$$10N APPMVED SY OMS (1241l 3154 0027 to cFR 110-APPLICATION FOR LICENSE TO EXPORT NUCLEAR EXPIRES 123147 MATERIAL AND EQUIPMENT /Seeinstructionson Reverse /

1. APPLICANT'S ls D ate OF AePLIC ATION D. APhtC ANT'S RIPERENCE 2.NRC

)DOCKEThO. O/

X CdM l o / 7 e LICENSE No.

ust

16 september 1988 eP2905 2 ust

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3. APPLIC ANT'S N AME AND ADDRESS l RIS

4. SUPPLIER *S NAME AND ADDRES$

M (Complete of apoiwt us not neoter of matwall g

Copeuttion Engineering, Inc.

1 STRitT ADDR8:5 s.NAWE 1000 Prospect Mitt Road saltimore Ces & Electric Compeny

s. CIT Y STATE ZIP CODE

b. STRIET ADDR$$$

Windsor CT

'.',6 0 9 5 Calvert Cliffs nuclear Power Plant

s. f t L& P MON E NVW a t m (4rea Coor - humoer - f atwuen/

s. CIT Y STATE ZIP CODE (203) 2f!5 5200 (Mr.

4. E. Scherer) tusby WD 2M57

_6. FIR $7 8HIPMENT I

5. FIN AL 5HIPMENT F. APPLICANT'$ CONTRACTUAL 8. PROPOSED LICENSE

9. US. DEPARTMENT OF ENERGY S4,H E DU L E D SCHEDULEO DELIVERY DATE EX>IR ATION DATE CONTR ACT NO. fit Knonn)

December, 1988 af. A.

W.A.

December, 1989 N.A.

10. ULTIMATE cONsicNE E l Ris

19. ULTIM ATE (ND USE b_

,u,yy unctwoo piant nr facaoty trw)

Atcmic Energy of Canada, Limited (aECL) tesearch and Development a sTmatT ADDatss Post Irradiation Enamination Chalk River nuclear Laboratories

t. CIT Y - ST Af t - CovNT R Y Chalk River, Ontario, anada lis. EST. OATE OF FIRST USE

12. INTERMEDI ATE CONSIGNE E l Als

13. INTERMEDI ATE END U$E l

a N Aut JrompgavertClr alloa M e ent rans Lusby, Maryland, USA kuclear Assurance Corporation fot Chalk River Nuclear Laboratories CPath River,

o. sTma:T ADDntss Ontario, Canada 6251 Crooked Creek Road

s. cst v - sT ATE - CovNT m v Method of Transport: Mo'.or vehicle Woreroes, Georgia, 014 dAf Ar$ D OF F R t E la. INTE,RMEDI ATE CONSIGNEE l R16

. 15. INTERMEDI ATE END U$E l

a NAME D. STREET ADDMi$s

s. CIT Y - ST AT E - COUNTR y 1Es. EST. DATE OF PtRST USE 14.

17. DESCRIPTION

18. M AX. ELEMENT 19. M AX. 20. M AX 21.

NRC fineaver caemc4 ead pWe' form of nuctar marr#, pre oow ealue of VvEIGHT WT.%

ISOTOPE WT.

UNIT I

USE nurdee<eo n w ear r o com m y w A) Special kuclear materlat A) Uranium 82.0 U/ U 233.00002 g

12 Each Irradiates Fuel Elements Total 24604g Total U 235 72.7 g

Stated tods Containing $ctic hormal Form 'Wts.

Plutonium Pu 238 12.7 e

of Uranlue and Daugeiter Sroducts 302 e 1.0 Pu/ Pu 239 135.0 e

fotal Pu 240 75.8 g

B) By Product Materiet 5 (VSD)

Pu 241 45.8 g

Irradiated huclear Reactor Components

5) Principal Ag 108m 4220 Cl 1 Each teactor control Rod Assembly 25,000 Isotopes As 109m 2640 Cl 1 Each hon Fueled Rod 1,000 Cd 109 2640 Cl 1 Each Fuel Etement Asseebtv tage 25,000 Fe 55 2610 Ci

22. COUNTRY OF OR40tN -

l

23. COUNTRY OF ORIGIN 4NM l

J 24. COUNTRIES WHICH ATTACH l

SOURCE MATERI AL WHERE ENRICHED OR PRODUCED SAF E GU ARDS (if KapanJ USA USA USA, Canada

25. ADDITION AL INFORM ATION Ine scoe are s^eet sf neceswr>

A) Detailed Neavy Metals Inventoty, See fable 1 B) Detailud Isotopic Inventory 01 By P'sduct Materlat, $ee table 2

,26. The eeplac,ent eertif.es that the soplication es p<epared en conformity /

wnh Tatie 10. Code et Pede*al Ree4atens, and that ett enformaten in this application as servoet to the best of hdor sewwnede,e A

27. AUTHOMt2ED OFFICIAL

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TABLE 2 IRRADIATED NUCLEAR REACTOR COMPONENTS CURIES OF BY-PRODUCT MATERIALS REACTOR CONTROL NON FUEL ROD ASSEMBLY ISOTOPE ROD ASSEMBLY CAGE TOTALS 1

H3 1.94E 05 2.27E 04 1.06E 04 3.52E-04 2

BE-10 7.76E 09 2.77E-04 3.80E 08 2.77E-04 3

C-14 2.49E 07 1.50E 06 1.50E-06 3.25E 06 4

SI 32 2.14E-10 1.47E 09 5.35E-09 7.03E-00 5

P-32 2.14E-10 1.47E-09 1.llE 02 1.llE-02 6

P-33 3.26E-13 8.45E-06 0.45E 06 7

S 35 1.15E 04 5.29E-06 7.87E-02 7.88E-02 8

CL-36 1.39E-08 1.41E 07 1.50E-07 3.05E-07 9

AR-37 1.28E-16 5.24E-Il 5.24E-11 10 AR-39 3.61E-13 5.70E-12 3.98E-12 1.00E-Il 11 AR 42 3.65E-16 1.84E-15 1.26E-16 2.13E-15 12 K-42 1.65E-16 1.84E 15 1.26E-16 2.13E-15 13 CA 45 7.93E 05 3.17E-05 5.37E-04 6.48E-04 14 CA-47 4.94E-15 4.94E-15 15 SC-46 6.13E-04 2.24E-05 3.50E-02 3.56E 02 16 SC-47 3.98E-14 3.98E-14 17 V 50 9.84E-16 5.29E-15 2.91E-15 9.18E-15 18 CR 51 1.19E-04 3.07E-10 2.09E+02 2.09E+02 19 MN-54 1.40E+00 1.53E+00 2.98E+02 3.01E+02 20 FE 55 6.76E+01 2.llE+02 2.33E+03 2.61E+03 21 FE-59 2.08E 04 1.88E-07 1.46E+01 1.46E401 22 CO 58 1.22E+00 1.75E 02 2.38E+02 2.40E+02 23 CO 60 3.01E+01 2.20E+02 4.58E+01 2.96E+02 24 NI-59 8.27E 01 4.27E+00 9.03E-01 6.00E+00 25 NI 63 1.37E+02 7.74E+02 1.52E+02 1.06E+03 26 ZN 65 7.74E-05 2.91E-04 4.05E 04 7.74E-04 27 GE-71 2.08E-16 2.08E-16 28 SR 89 1.45E 05 1.35E-12 6.47E 01 6.47E 01 29 ZR 89 6.22E-16 6.22E-16 30 SR 90 1.37E-05 5.98E 08 4.46E-04 4.60E-04 31 Y-89m 6.23E-16 6.23E 16 32 Y 90 1.37E-05 5.98E 08 4.46E 04 4.60E 04 33 Y-91 1.30E 04 2.37E-12 2.13E+00 2.13E+00 34 NB 92 1.23E-04 1.23E 04 3 $-

IR 93 6.90E-04 2.18E-06 2.llE-02 2.18E 02 36 ZR-95 1.12E 01 3.21E-07 1.08E+03 1.08E+03 37 NB 93m 1.24E-04 5.84E 07 2.55E 03 2.68E-03 38 MO 93 2.18E-02 1.32E 01 1.55E 02 1.69E 01 39 NB 94 3.33E-05 1.89E-04 2.37E-05

- 2.46E-04 40 NB 95 2.49E 01 7.12E-07 2.02E+03 2.02E+03 41 NB-95m 8.34E-04 2.38E 09 7.99E+00 7.99E+00 i

42 TC-98 7.08E-10 6.54E-09 5.16E-10 7.76E-09 43 MO 99 8.36E-14 8.36E-14 1

TABLE 2 (CONT.)

REACTOR CONTROL NON FUEL ROD ASSEMBLY ISOTOPE ROD ASSEMBLY CAGE TOTAL 3 44 TC-99 8.84E 04 4.65E-03 6.27E 04 6,16E 03 45 RH 102 4.18E 09 6.75E-08 4.51E-09 7.61E-08 46 RU-103 8.98E 07 4.65E-10 7.84E-03 7.84E 03 47 RU 106 8.0E-13 4.lE-08 1.7E-12 4.15E-08 48 RH 106 8.0E-13 4 lE 08 1.7E-12 4.15E-08 49 PD 107 3.lE-16 1.3E-04 2.6E-16 1.27E-04 50 AG-108 3.80E+02 3.80E+02 51 AG-108m 4.27E+03 4.27E+03 52 AG-109m 2.64E+03 2.64E+03 53 CD 109 2.64E+03 2.64E+03 54 AG-110 2.41E-17 1.86E+01 9.26E 17 1.86E+01 55 AG-110m 1.81E-15 1.40E+03 6.96E-15 1.40E+03 56 IN-114 3.44E-04 3.44E-04 57 IN 114m 3.59E-04 3.59E-04 i

58 CD 115m 4.61E-06 4.61E-06 4

59 IN ll5 9.29E-13 9.29E-13 60 SN 119m 7.13E 01 7.13E-01 61 SN 121m 4.38E-08 4.38E-08 62 SN-123 5.30E-13 5.30E-13 63 TE 123m 2.29E-10 2.29E-10 64 5B 124 6.80E-18 6.80E-18 65 58 125 3.00E-15 3.00E-15 66 TE-125m 7.43E-16 7.43E-16 67 TE 127 5.05E-18 5.05E-18 68 TE-127m 5.16E-18 5.16E-18 TOTALS 2.38E+02 1.26E+04 6.40E+03 1.92E+04 l

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SONIBU5 TION ENGINEERING

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1:

September 19, 1988 LD-88-092 Mr. Marvin R. Peterson Assistant Director For International Security Office of Governmental and Public Affairs U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Application for License To Export Nuclear Materials and Equipment

Dear Mr. Peterson:

Combustion Engineering, the Electric Power Research Institute (EPRI) and Baltimore Gas and Electric Company (BG&E) are jointly undertaking a research and development program to evaluate the performance of commercial PWR fuel irradiated to high burnup.

Post-irradiation examination of nuclear materials and equipment used in this research program will be exported to research facilities located in Canada for evaluation. As such, Combustion Engineering is submitting the enclosed appilcation for a License To Export Nuclear Materials and Equipment (NRC Form 7) pursuant to 10 CFR 110.30 and 110.31, and supporting documentation.

The research program, EPRI RP2905-02, is entitled, "Hot-Cell Examination of Extended Burnup Fuel From Calvert Cliffs-1". As the title suggests, the subject fuel was irradiated in the BG&E, Calvert Cliffs Unit i reactor for up to five reload fuel cycles.

The fuel was removed from the reactor in April, 1988.

The workscope of EPRI RP2905-02 specifies detailed post-irradiation examinations utilizing both destructive and nondestructive test techniques.

These examinations will be performed in the hot cells located at the Chalk River Nuclear Laboratories, Ontario, Canada. The Chalk River facility is operated by Atomic Energy of Canada, Limited.

Atomic Energy of Canada will be responsible for the long tcrm disposition of the subject nuclear materials and equipment. The material will be disposed of by burial at the Chalk River Nuclear laboratories following completion of the examinatilon workscope.

The goal of EPRI RP2905-02 is to obtain performance data on twelve (12) fuel elements (rods), one (1) non-fueled rod, one (1) reactor control rod asseratly and one (1) fuel assembly cage.

The average burnups of the fuel Power Systems 1000 Prospect HJI Road (203) 688 1911 Combusbon Ergneenng. Inc.

Post Offce Box 500 Telex: 99297 Wn:tsor, Connectcut 06095-0500 e

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Mr. Marvin R. P:t:rson LD-88-092 Sept cber 16, 1988 Page 2 rods range from 47.9 to 59.0 GV.'d/MtU. The initial fissile content of the fuel rods was:

30.1 kg Total UO, Enrichef U 26.5 kg 235 Ikotal 3.65 to 4.00 wt% U Enrichment 985 g Total U 235 The transport of the subject nuclear materials and equipment will be managed by Nuclear Assurance Corporation of Norcross, Georgia.

The fuel rods, non-fueled rod, and control rod assembly will reside within a Combustion Engineering designed 14x14 fuel assembly cage. These items will be transported to Chalk River in an NLI-1/2 shipping cask (Certificate of Compliance No. 9010). A firm shipping date has not yet been established because the dates when a shipping cask will be available have not been firmly established. The tentative schedule is to ship the fuel and components from Calvert Cliffs Unit 1 to Chalk River Nuclear Laboratories in February or May,1989. A December,1988 shipping date may, however, be achievable should a cask be.come available.

If you have questions or require additional information to process this application, please do not hesitate to call me, Mr. Charles M. Molnar of my staff at (203) 285-5205.

Very truly yours, COMBUSTION ENGINEERING, INC.

k ADj

'. d cherer A

Director Nuclear Licensing AES/dmb

Enclosure:

As Stated

U.S. NuCLEA") GE ULATORY COMMIT $lON APPZVt 3 BY OMS CRC FORM /

3164 0027 (12 41) lo cm 110 APPLICATION FOR LICENSE TO EXPORT NUCLEAR expires 12 31 s?

MATERI AL AND EQUIPMENT /see Imtructiom on Reesel

1. AFPLICANT4 lo. D ATE OF APPLIC ATION D. APPL 6C ANT's ptPintNCE 2.NRC aPOCKETNO.

D. I.lC E NS E N O.

ust

-.1 to sept aber 1988 RP2905 2 ust ---o ff/)6 y/4 0 XSN4f 6M44 35 APPLIC ANT'S NAM 1 AND ADDRESS l RIS

4. SUPPLitR'S NAME AND ADDRESS lRIS (Comp;9te of appbcent it n0t aw&O!4r Of Aaretra?/

1 NAME Ceeitust ion E ngineering, Inc.

b STmtETACORESS e NAME 1000 Prospect Mitt Road saltimore Gas & Electric Company

s. CIT Y STATE RIP CODE e STREET ADQmtSS Windsor CT 06095 Calvert Cliffs Wuclear Po er Plant

e. T t 6t PMONL NuMat m #Aree Cove - hwmoer - f a rensos/

e CIT Y STATE 2IP CODE (203) 285 5200 (Mr. A. t, scherer)

Lusby Me 20657

5. FIR $T SHIPMENT

4. FIN AL $HIPMENT 7. APPLIC ANT'S CONTRACTUAL'8. PROPOSED LICENSE

9. US.DEP ARTMENT OP ENERGY SCHt DUL E D SCHE DUL E D DELIVERY DATE EXPlR ATION DATE CONTR ACT NO. (if raoen/

0*ccecer, 1938 N.A.

W.A.

December, 1989 k.A.

10. ULTIM ATE CON 51GNtt l Als it. ULTIMATE END U$t l

Umwe piant er fac,4rr na nel

, g,yg Atoals Energy of Canada, Limited (AECL)

Research and Development Post Irradiation inomination

b. STmt E T A00mtS5 Chalk River nuclear Laboratories

s. CIT Y - ST ATE - CouNTm v Chalk eiver Ontario, Canada 11a. EST.DATE OF FIRST U$t

12. INTERMEDI ATE CONSIGNtt l Als

13. INTERMEDI ATE END U$t l

h!N C5!f!

Lusby, Maryland, US A nuclear Assurance Corporation p

et Simitt ADDmtss 6251 Crooked Creek Road Method of fransporti Motor Vehicle

s. Cli v - ST AT L - COUNT m v 1AIA Certificate of Compliance Package USA /9010/D[ If horcross, Georgia, USA 13a EST. D ATE OF FIRST USE

14. INTERMEDI ATE CONSIGNit l R86

15. INTERMEDI ATE END U$t l

e NAME

o. STmtif ADomtSS

s. CITY - ST ATL - COUNimy 15e IST. DATE OF FIRST U$t

14. '

17. DE SCRIPTION

18. MAN. ELEME NT 19. M AX.

20. M AX 21.

NRC fivwe c Aem. cat ew p*,sget tam ef awcw matmai. p+e pouar ine ef gggggy WT.%

ISOTOPE WT.

UNIT USE ave w eweer e*e m jyriers>

A) $pecial hwetear Material A) Uranium 82.0 U/ U 233.00002 g

12 tech Irradiated f uel Elements Total 24604g Total U 235 72.7 g

Stated tods Containing $olid hormal form 'wts.

Plutonium Pw 238 12.7 g

of Urantue and Dawanter Proowets 302 g 1.0 Pu/ Pu 239 135.0 g

d total Pu 240 ?5.8 g

B) By Product Material

$ (V$0}

Pu 241 45.8 g

Irradiated twctear teactor Components I) Prir.:1 pat Ag 108m 4270 Cl 1 fach teactor Control tod Asse*bly 2$,000 Isotopes As 100m 2640 Ci i tach hen Fueled tod 1,000 Cd 109 2640 C1 1 fach twet flement Asse*bly Cage 25,000 Fe 55 2610 Ci 22 COUNTRY OF ORIGIN.-

l

23 COUNTRY OF ORIGIN-$NM l

l 24. COUNTRIES WHICH ATTACH l

SOURCE MATERI AL WHERE ENRICHED OR PRODUCED SAFIGU ARDS tif ra0*al USA USA U$A, CanaCa

25. ADDITIONAL INFORM ATION tune sepa ere svenf rwesw,;

4) Cetailed Meavy Metals Invento y, see table 1 l

B) Detailed isotepic Inventory of ly Fred ct Material, See fable 2 en> T rtie 10. CenJe et Federal Regutatena, erwl that all informaten in this

26. The epohcaat certifies that the septic. tion is prepared in conf ormitv/

opphcetion a correct to tha t>est of h.0er knowleden j

27. AU THORI2ED OFFICIAL

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o TABLE 2 IRRADIATED NUCLEAR REACTOR COMPONENTS CURIES OF 8Y PRODUCT MATERIALS REACTOR CONTROL NON FUEL ROD ASSEMBLY ISOTOPE ROD ASSEMBLY CAGE TOTALS 1

H-3 1.94E 05 2.27E-04 1.06E 04 3.52E-04 2

BE 10 7.76E 09 2.77E 04 3.80E 08 2.77E-04 3

C-14 2.49E 07 1.50E 06 1.50E 06 3.25E-06 4

SI 32 2.14E-10 1.47E 09 5.35E 09 7.03E-09 5

P 32 2.14E 10 1.47E-09 1.llE-02 1.llE-02 6

P 33 3.26E-13 8.45E 06 8.45E-06 7

S-35 1.15E-04 5.29E-06 7.87E 02 7.88E-02 8

CL-36 1.39E 08 1.41E-07 1.50E-07 3.05E 07 9

AR-37 1.28E-16 5.24E-11 5.24E 11 10 AR-39 3.61E-13 5.70E-12 3.98E-12 1.00E-Il 11 AR 42 1.65E-16 1.84E 15 1.26E 16 2.13E-15 12 K 42 1.65E-16 1.84E-15 1.26E 16 2.13E-15 13 CA 45 7.93E-05 3.17E 05 5.37E 04 6.48E-04 14 CA 47 4.94E-15 4.94E-15 15 SC-46 6.13E-04 2.24E 05 3.50E-02 3.56E 02 16 SC 47 3.98E 14 3.98E 14 17 V-50 9.84E 16 5.29E-15 2.91E 15 9.18E-15 18 CR 51 1.19E 04 3.07E-10 2.09E+02 2.09E+02 19 MN 54 1.40E+00 1.53E+00 2.98E402 3.01E+02 20 FE-55 6.76E+01 2.11E402 2.33E+03 2.61E+03 21 FE-59 2.08E 04 1.8SE 07 1.46E+01 1.46E+01 22 CO 58 1.22E+00 1.75E-02 2.38E402 2.40E+02 23 CO 60 3.01E+01 2.20E+02 4.58E+01 2.96E+02 24 NI-59 8.27E-01 4.27E+00 9.03E 01 6.00E+00 25 N1 C3 1.37E+02 7.74E+02 1.52E+02 1.06E+03 26 ZN 65 7.74E 05 2.91E 04 4.05E 04 7.74E 04 27 GE-71 2.08E-16 2.08E 16 l

25 SR 89 1.45E 05 1.35E 12 6.47E 01 6.47E-01 29 ZR 89 6.22E-16 6.22E-16 30 SR 90 1.37E 05 5.98E 08 4.46E 04 4.60E 04 31 Y 89m 6.23E 16 6.23E 16 32 Y 90 1.37E-05 5.98E 08 4.46E 04 4.60E 04 33 Y-91 1.30E-04 2.37E 12 2.13E+00 2.13E+00 34 NB 92 1.23E 04 1.23E 04 35 ZR 93 6.90E 04 2.18E-06 2.llE 02 2.18E 02 36 ZR 95 1.12E 01 3.21E 07 1.08E+03 1.08E+03 37 NB 93m 1.24E 04 5.84E 07 2.55E-03 2.68E 03 38 MO 93 2.18E 02 1.32E 01 1.55E 02 1.69E 01 39 NB-94 3.33E-05 1.89E 04 2.37E 05

- 2.46E 04 40 NB 95 2.49E 01 7.12E-07 2.02E+03 2.02E+03 41 NB 95m 8.34E-04 2.38E-09 7.99E+00 7.99E+00 42 TC-98 7.08E-10 6.54E 09 5.16E-10 7.76E-09 43 MO 99 8.36E-14 8.36E-14

TABLE 2 (CONT.)

REACTOR CONTROL NON FUEL R00 ASSEMBLY ISOTOPE ROD ASSEMBLY CAGE TOTALS 44 TC 99 8.84E-04 4.65E 03 6.27E 04 6.16E 03 45 RH 102 4.18E-09 6.75E 08 4.51E 09 7.61E 08 46 RU 103 8.98E-07 4.65E-10 7.84E 03 7.84E 03 47 RU 106 8.0E-13 4.1E 08 1.7E 12 4.15E 08 48 RH 106 8.0E-13 4.lE 08 1.7E-12 4.15E 08 49 PD-107 3.lE-16 1.3E 04 2.6E-16 1.27E 04 50 AG 108 3.80E+02 3.80E+02 51 AG 108m 4.27E,03 4.27E+03 52 AG-109m 2.64E+03 2.64E+03 51 CD 109 2.64E+03 2.64E+03 54 AG llo 2.41E-17 1.86E+01 9.26E-17 1.86E+01 55 AG 110m 1.81E-15 1.40E+03 6.96E-15 1.40E+03 56 IN ll4

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3.44E 04 3.44E 04 57 IN 114m 3.59E 04 3.59E 04 58 CD-ll!m 4.61E 06 4.61E 06 59 IN 115 9.29E 13 9.29E 13 60 SN 119m 7.13E 01 7.13E 01 61 SN 121m 4.38E-08 4.38E-08 62

$N 123 5.30E-13 5.30E 13 63 TE-123m 2.29E-10 2.29E 10 64 SB 124 6.80E 18 6.80E-18 65 SB-125 3.00E-15 3.00E 15 66 TE-125m 7.43E-16 7.43E-16

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67 TE-127 5.05E-18 5.05E 18 68 TE 127m 5.16E 18 5.16E-18 TOTALS 2.38E+02 1.26E+04 6.40E+03 1.92E+04 1

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September 16, 1988 LD-88-092 Mr. Marvin R. Peterson Assistant Director For International Security Office of Governmental and Public Affairs U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Application for License To Export Nuclear Materials and Equipment

Dear Mr. Potorson:

Combustion Engineering, the Electric Power Research Institute (EPRI) and Baltimore Gas and Electric Company (BGkE) are jointly undertaking a research and development program to evaluate the performance of commercial PWR fuel irradiated to high burnup. Post-irradiation examination of nuclear materials and equipment used in this research p*ogram will be exported to research facilities located in Canada for evaluatien.

As such, Combustion Engineering is submitting the enclosed application for a License To Export Nuclear Materials and Equipment (NRC Form 7) pursuant to 10 CFR 110.30 and 110.31, and supporting documentation.

The research program, EPRI kP2905-02, is entitled, "liot-Cell Examination of Extended Burnup Fuel From Calvert Cliffs-1". As the title suggests, the subject fuel was irradiated in the BG&E, Calvert Cliffs Unit I reactor for up te five reload fuel cycles. The fuel was removed from the reactor in April, 1988, The workscope of EPRI RP2905-02 specifies detailed post-irradiation examinations utilizing both destructive and nondestructive test techniques. These examinations will be performed in the hot cells located at the Chalk River Nuclear Laboratories, Ontario, Canada.

The Chalk River facility is operated by Atomic Energy of Canada, Limited.

Atomic Energy of Canada will be responsible for the long term disposition of the subject nuclear materials and equipment.

The material will be disposed of by burial at the Chalk River Nuclear Laboratories following completion of the examinatilon workscope.

The goal of EPRI RP2905-02 is to obtain performance data on twelve (12) fuel elements (rods), one (1) non-fueled rod, one (1) reactor control rod assembly and one (1) fuel assembly cage.

The average burnups of the fuel Power Systems 1000 Prospect Hal Road (203) 688 1911 Cornbuston Ervneenng. Inc.

Post CMtce Box 500 Te:er 99297 Windsor, Connectcut 06095-0500

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Mr. Marvin R. Paterson LD-88-092 Septr ber 16, 1988 P:ge 2 rods range from 47.9 to 50.0 GWd/MtU.

The initial fissile content of the fuel rods was:

Total UQ 30.1 kg Enrichef U 26.5 kg 3.65 to 4.00 wt% U235 Iketal Enrichment l

Total U 985 g 235 The transport of the subject nuclear materials and equipment will be managed by Nuclear Assurance Corporation of Norcross, Georgia. The fuel rods, non-fueled rod, and control rod assembly will reside within a Combustion Engineering designed 14x14 fuel assembly cage. These items will be transported to Chalk River in an NLI-1/2 shipping cask (Certificate of Compliance No. 9010). A firm shipping date has r.ot yet been established because the dates when a shipping cask will be available have not been I

firmly established.

The tentative schedule is to ship the fuel and components from Calvert Cliffs Unit 1 to Chalk River Nuclear Laboratories in February or May,1989.

A December,1988 shipping date may, however, be achievable should a cask become available.

If you have questions or require additional information to process this application, please do not hesitate to call me, Mr. Charles M. McInar of my staff at (203) 285-5205.

Very truly yours, COMBUSTION ENGINEERING, INC.

k 229 j

A. dcherer

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Director Nuclear Licensing AES/dmb

Enclosure:

As Stated i

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