ML20134J180

Informs of Impending Shipment of Spent Nuclear Fuel by Iowa State Univ.Info Required by 10CFR73.72 Encl

ML20134J180
Person / Time
Site:	University of Iowa
Issue date:	10/30/1996
From:	Wendt S IOWA STATE UNIV., AMES, IA
To:	Haughney C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9611150038
Download: ML20134J180 (10)

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IOWA STATE UNIVERSITY '""*8"""~""'"""'"'

OF SCIENCE AN D T ECH NOLOGY Nudcar Engmccring Prograrn 107 Nudear Engineenng I2h Arr.es,lowa Soot p224 515 294-584 0 FAX Sn5 294-7224 October 30,1996

5'o -//(o Charles J. Haughney )

Spent Fuel Project Ofice NMSS

' US Nuclear Regulatory Commission  !

Washington, DC 20555 Dr. Mr. Haughney: l 1 l This letter is to inform you of an impending shipment of spent nuclear fuel by lowa State l University. The information required by 10CFR73.72 is attached. The governor's designess 1 in the states in which the shipment will pass will be notified in writing per 71.97(c) and (d).

I Please feel free to contact me (515) 294-0539 !f you have any questions.

l Sincerely,

~$ h l Scott E. Wendt Reactor Manager SEW:bs j i

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150009 9611150038 961030

~ 4 PDR ADOCK 05000116 P PDR .

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• Shipment identification 0: R59-090196 NOTIFICATION OF SPENT FUEL SHIPMENT i

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Shipper Carrier  ;

l Mechanical Engineering Dept. Tri-State Motor Transit Co.

lowa State University P.O. Box 113 1 Joplin, MO 64802-0113 l Ames, IA 50011 800-641-7500 l

Contact:

Scott E. Wendt 107 Nuclear Engr. Lab.

515-294-0539 )

Fax: 515-294-7224 Receiver Westinghouse Savannah River This notification is being furnished in l Savannah River Site, Bldg 244-H compliance with NRC regulations to Part 73 Aiken, SC 29808

Contact:

Matt Beckum 803-557-9642 l

l DESCRIPTION Radioactive Material, fisslie, n.o.s., UN2918 ADDITIONAL INFORMATION FOR A PART 73 SHIPMENT OF SPENT FUEL The street address of the point of origin is:

112A Nuclear Engineering Laboratory lowa State University Ames, IA 50011 and the route to be used within that state is:

Bissell Road to Union Drive.

Union Drive to Sheldon Avenue.

Sheldon Avenue to Lincoln Way.

Lincoln Way to Elwood Drive.

Elwood Drive to US 30.

US-30 to 1-35.

1-35 to I-80.

1-80 to I-280.

1-280 to lowa/ Illinois border.

Page 1 of 3 Notification of Spent Fuel Shipment

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Shipment identification #: R59-090196 The shipment is scheduled to be transported through (or into) the following additional states using the routes indicated:

lltinois:

1-280 to I-74 l-74 to I-474 l-474 to I-74 l-74 to I-55 l-55 to I-74 1-74 to l-57 l-57 to I-24 l-24 to Illinois / Kentucky border Kentucky:

1-24 to Kentucky / Tennessee border Tennessee: 1-24 to Tennessee /G,eorgia border Georgia: 1-75 to 1-285 l-285 to I-20 1-20 to Georgia / South Carolina border South Carolina 1-20 to SC-19 SC-19 to Savannah River Site Schedule information is attached as a separate seated item. It must be protected against unauthorized disclosure until ri-74-% .

This notification is being provided by:

Organization: Mechancial Engineering Department By: Scott Wendt, Reactor Manager lowa State University 107 Nuclear Enginering Laboratory '

d~hid d Ames, IA 50011 (Signature)

Tel: 515-294-0539 Fax: 515-294-7224 Shipment identification number: MI-NOIN A /

d#3 ddd IDSo%

Shipment Today's Date Mo/ Day / Year

7. Schedule Information for a Part 73 Shipment of Spent Fuel is provided in a separate enclosed envelope marked " Safeguards information." The contents must be protected against unauthorized disclosure until January 1,1997.

Notification of Spent Fuel Shipment Page 2 of 3

Physical Description of shipment:

The shipment will consist of 72 aluminum clad plates from the Iowa State University UTR-10 i reactor (Argonaut type). Each plate is three inches wide,26 inches tall and .125 inches thick.

The fuel material is UAlx with U-235 enriched to approximately 93%. The average mass of U-235 per plate is approximately 22g.

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' ULd States Department of Energy Unitid States of America -

DOESRAA-96-006 Rev.0 APPENDIX A AGREEMENT SPENT NUCLEAR FUEL ACCEPTANCE CRITERIA UNDER CONTRACT NO. DE-FG02 87ER75360 No.

Iowa State University WITH

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! THIS AGREEMENT, entered into this _1 st_ day of _ September _,1987_, constitutes an agreement by the U.S.

Department of Energy (hereinafter called DOE) to receive under the terms and conditions of Contract FG02-87ER75360. the specification material described herein. This agreement provides a detailed descrip material.to be delivered to DOE in accordance with this contract and also enumerates the specifications and requirements which the Customer must meet. Failure of the material debehd hereunder to co l

j specifications and requirements given in this agreementwi11' result in the material being non-spe separate Appendix A Agreement will be required for each element, subassembly, or assembly wh Descriptiort All dimensions must be given in meters or centimeters and all weights in grams or kilograms.

A. Definitions The following definitions are applied to the Specification Materialdescribed in this Agreement:

The Fuel Element -The smallest integral unit of clad fuel (or blanket) containing source or special nuclear material (e.g., plate, tube, rod, disc, etc.). i l

F j Subassembly - If used, is a group of elements. combined in a structural unit, which is grouped with other 1 l

subassemblies to form the larger unit called the assembly. )

Assembly - A group of elements or subassemblies combined in a structural unit. The assembly is usu l fuel structure which is removed from the reactor as an individual unit.  ;

B. Form and Composition of Specification Material

1. Drawing Identification The following drawing (s), four (4) copies of which are attached and which are incorporated thereto, constituce(s) a comprehensive illustration of the fuel elements. subassemblies, and a f delivered under this Contract as charged to the reactor, in sufficient detail and accuracy under t Drawing No./ English Title Drawing No./ English Title R1-C-121. Fullload fuel olate f R1-C-122. Halfload fuel plate i

) ISU-NE-96-01. ISU Fuel Plate Holder Rev. ) (t/96)

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United States Department of Eh..gy DOESRAA 96 006 Rev.O Page 2 0f 7 Appendix A Agreement

2. Material Description l

The following summarizes the description of fuel elements, subassemblies, assemblies and a after discharge. Where dimensions am required, the nominaldimensions, as charged to the rea used and the best estimate of the maximum change in these dimensions because of iltadiation m Weights must be dry, unitradiated weights with the expected range of weights also to be inc isotopic weights of SNM are required, tolerances shall be specified.

l (a) Fuel ' Element' Description I Plate Fuel element type (plate, disc, rod. tube, etc.)

66.04 x 7.62 x 0.203 Nominal dimensions (include clad and bond, cm) 60.96 y ,

Activelength of fuelelement(cm)

Fullload = 291.50 Nominal total weight of fuel element (g) I Halfload = 282.46 Quaner load = 278.00 Fullload = 23.9083 Nominal weight of SNM before irradiation (g) l Halfload = 11.6500 "

Quaner load = 5.8550 j l

Full load = 23.9083 0.3617 Total U (g g uncenainty)

Halfload = 11.6500 0.1697 Ouanerload =5.8550 0.1202 Full load = 22.2900:0.3300 U-235 (g g uncertainty)

Halfload = 10.8700 0.1697 Quanerload = 5.465 io.1061  !

Full load = 0.0 2.7e- 10 TotalPu (g g uncertainty)

Halfload = 0.0 1.4e-10 Quanerload = 0.0 6.Se-11  :

Full load = 0.0 2.7e-10 Pu-239 (g g uncertainty)

Halfload = 0.0 :1.4e 10 Quaner load = 0.0 6.8e 1I Full load = 5.55e 14 : 1.le.14 Thorium (g i g uncertainty) r{alfload=2.77e 14:5.55e 15

, Our eter load = 1.38e 14 t 2.78e 15 UA14

[ Chemical form of SNM (e.g., UO2, U Alx-alloy, UC, etc.)

i Rev. 3 (It96)

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' DOESRAA 96-006 Rev.O Unitid States Department of Enw gy _

Page 3 of 7 Appendix A Agreement Fullload = 34.660 I Weight of SNM (g)

Halfload = 16.995 Quarter load = 8.541 Homogeneous intermetalic Fabricated form of SNM (pellets, slugs, ribbons) fuel meat Aluminum Alloy or dispersing material (A1, SS, etc.)

Fullload = 95.85 Alloy or dispersing material weight (g)

Halfload = 47,92 l l

Quarter load = 23.94 Cadding material (A1, SS, etc.) & method of sealing Aluminum Metallurgical solid phase bond Cad thickness (cm), weight (g) 0.0508 cm 0.0127 cm l

Fullload = 161.46 1

Half load = 217.54 Quarter load =245.51 l N/A Bonding material,if any (Na, Al-Si, etc.)

Bond thickness (cm), weight (g) N/A N/A Spacers, inactive material (MgO, SS, etc.)

N/A Spacer dimensions (cm), weight (g)

N/A Other materials contained in the fuel element:

(include dimensions and weights)

Rev, J 0%

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• DOESRAA-96-006 Rev. O

United States Department of EL.gy .

Page 4 of 7 Appendix A Agreement M ' Subassembly' Description Number of elements- N/A Over-all subassembly dimensions (cm) N/A Total subassembly weight (g) N/A Casing Material (Zr, A1, etc.) N/A Casing dimensions (cm), weight (g) N/A Side plate material N/A Side plate dimensions (cm), weight (g) N/A Spacer material N/A -

Spacer dimensions (cm), weight (g) N/A End box material N/A E .*

End box dimensions (cm), weight (g) N/A Bmze or weld material N/A B mze or weld dimensions (cm), weight (g) N/A Other structural material contained in N/A subassembly (include dimensions and weight)

(c) Full ' Assembly' Description Number of subassemblies / elements l 6 or 7 Over alldimensions (cm) 8.255 x 8.255 x 86.6775 l

Over-all weight (g) 3106 or 3444 Casing Material (Zr, A1, etc.) - Al6065 8.255 OD x 87 00,1078 l Casing dimensions (cm), weight (g)

Side plate material N/A Side plate dimensions (cm), weight (g)* N/A Spacer material N/A _

NA, N A Spacer dimensions (cm), weight (g)

End box material N/A i

End box dimensions (cm), weight (g) N/A Braze or weld material Al4043 Braze or weld dimensions (cm), weight (g) 0.7 x 11,70 Other structural material in assembly N/A (include dimensions and weight)

• Side plate weight shall account for any slot volume (s),

Do the fuel elements cuntain Sodium (Na)?

Yes G Nok Rev.3 036)

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- DOESRAA-96-006 Rev. 0 United States Department of Er. gy 1 Page 5 of 7 Appendix A Agreement C. FuelIdentification Each separately removable unit in a shipment batch must be identified by a durable tag or by embo Idendfication of the Units to be delivered under this Appendix A Agreement are as follows (NOTE: Custom shall list actual assembly identification numbers):

The fuel has been disassembled into individual plates. Each plate has a uniaue serial number engrav inch numerals. The plates will be placed in aluminum tubes (6 or 7 per cant Each aluminmn tube has a uniaue serial number encraved and painted in 2 inch letters and numerals.

D. FuelIrradiation Specifications g.

1- FuelIrradiation History GeneralSummary The fuel was in the core for a period of 11231.5 davs. Of that time. the reactor was critical for a 8673.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Durine the time critical, the fuel experienced a total bumun of 87.7 mwd /MTU. This b consumed a total of 396.2 millierams of U-235.

2. Post Irradiation Specifications The average and maximum SNM content post-irradiation is to be specified in grams per a available value should be given and the uncenainty stated. The irradiation history for each a provided according to Section F.

Maximum (g) Uncertainty SNM Material Average (g)

(t g or : %)

24.2674 10 %

Total U 23.1673 2.702e-10 20 %

Total Pu 2.702e-10 2.0785e-11 20 %

Total Np 2.0785e-1 I 3435e 12 20 %

Total Th l 3.435e 12 6.686e-16 20 %

U-232 6.686e-16 5.612e-15 :20%

U-233 5.612e-15 22.620 10 %

U-235 21.6311 5.825e-06 20 %

U-236 5.825e-06 2.695e-10 20 %

Pu-239 2.695e-10 9.207e-16 20 %

Pu-241 9.207e-16 no.mm

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United States Department of En'e.g

(, DOESRAA 96-006 Rev.0 'i l

Page 6 of 7 .

. Appendix A Agreemer.t

3. Specifications for Failed / Warped Fuel Units <

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1. Fuel elements or assemblies distoned beyond specified dimensionallimits must be considen:d on an :

i individual basis. 'Ihe Customer should provide DOE with complete dimensionalirJonnadon for each j

failed / warped unit atleast 60 days before delivery.

2 If material nonnally removed from the element or subassembly by the Customer cannot be removed d

. fuel failure, warpage, or other reasons, the Customer must notify DOE at least 60 days before d l l i d by j . complete dimensional, material, and weight information. Detailed structural drawings are a so requ re 1

i DOE.

t E. Correspondence (_

l. Customer Contact

! l Laboratory / Research Iowa State University

Center / University .

I Reactor Name UTR-10 City, State, Country Ames, Iowa, USA f

l Customer Name Scott E. Wendt Mdd l Customer Signature i Reactor Manager Title Phone Number (515) 294-0539 Fax Number (515) 294-7224 Date July 24,1996 l

) 2. Depamnent of Energy Contact All correspondence or inquiries regarding this document and the information

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to:

U.S. Department of Energy Savannah River Operations Office Reactors &. Spent FuelDivision i P.O. Box A i Aiken.SC 29801 Phone and facsimile inquiries may be made to:

Phone: (803)-557-3759 l' Fax: (803)-557-3763 1

Rev, J (tS61 t

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