ML19260D478

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Requests Registration as User of Model CE-250-2
ML19260D478
Person / Time
Site: 07109022
Issue date: 01/11/1980
From: Lichtenberger H
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
15226, NUDOCS 8002110113
Download: ML19260D478 (51)
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)/ pgb C-E Power Systems Tel 20316381911 Cort huston Enycenng. :nc Telem 99297 j

1000 Prospect Ms.1 Poad WMC5Cr. Connectcut 06095 cu m POWER 2ns $ SYSTEMS January 11, 1980 U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Mr. Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle & Material Safety Gentlemen:

It is requested that Certificate of Compliance No. 9022 (Model CE-250-2) be renewed for a 5 year period.

Enclosed are ten copies of our renewal applica-tion which is a consolidation of our original application dated July 12, 1974 and all supplements to date.

The CE-250-2 container is presently approved for shipment of dry UO2 enriched to a maximum of 2.0% U235 and for UO2 of unspecified moisture content enriched to a maximum of 3.5% U21s.

It s requested that this container be approved for shipment of uranium oxide with a mt.isture content of 5 wt. 5 or less and enriched to a maximum of 4.1% U22s. A comple+.e criticality safety analysis has been per-formed, the calculations and results of which are incorporated into this renewal application.

If you have any questions regarding the content of this application, please con-tact Mr. G. J. Bakevich of my staff on extension 3150.

Very truly yours, H. V. Lichtenberger Vice Dresident-Muclear Fuel Nuclear Power Systems tianufacturing HVL/GJB/ssb Enclosure 8002110

't 1939 202 25r25

1.0 GEf!ERAL INFORMATION 1.1 Introduction This renewal application is submitted for approval for delivery to a carrier for transport of Combustion Engineering's CE-250-2 shipping container.

The CE-250-2 shipping container is used for the transport of uranium oxide with a measured moisture content of less than 5 wt % and enriched to a maximum of 4.1", U235 This shipping container r.eets the criteria of 10 CFR Part 71.39 for shipping as Fissile Class II, with a maximum of 90 packages per shipment and a t.ansport index of 0.56.

1.2 Package Description 1.2.1 Packaaing The CE-250-2 package consists of a 16 gauge steel inner container 11-5/8" inner diameter by 57-1/4" long with a bolted and gasketed top flange closure and steel welded bottom plate. The inner container is centered within a 22-1/2" I.D. by 68-3/8" long 16 gauge outer steel drum. The inner container is supported by twelve 1/4" diameter steel springs welded to the inner container at the top flange and the bot-tom of the container. The void space between the inner and outer container is filled with vermiculite.

The CE-250-2 package design incorporates two containment boundaries excluding the inner stainless steel can containing the uranium oxide. The secondary contain-ment consists of the bol'ted and gasketed inner container. The primary containment consists of the surrounding 16 gauge steel drum.

Closure of the inner container is maintained by a rubber gasket and (5)1/2" hex head bolts and nuts. These bolts and nuts secure the 1/2" steel inner lid to the package. The outer container is then sealed with a standard 17H 12 gauge nut and bolt ring over the gasketed 16 gauge outer lid.

The weight of the package is approximately 575 lbs. when loaded and is construc-ted in accordance with Combustion Engineering's Drawing No. NFM-E-Z2175 Rev. O dated 6/11/79(Appendix 1.3).

It should be noted that the CE-250-2 package does not contain any valves, sampling ports or protrusions.

1.2.2 Operational Features Not Applicable - The CE-250-2 package is a simple design with no operational features.

1.2.3 Contents of packagina Each package will be limited to four cans of uranium oxide in either powder or pellet form enriched to a maximum of 4.1 w/o U23s and having a measured moisture content of 5 wt ". or less. A spacer will be used to make up the remaining volume within the inner package.

Each can contains a maximum of 30 Kg uranium oxide for a total of 120 Kg uranium oxide per CE-250-2 package. At a maximum of d.1 w/o 35 The weiqht in the isotope U: 35, the package would contain a maximum of 4.5 Kg U:

of the total contents will not exceed 300 lbs. The maximum radioactivity for each container is 0.21 curies with 90 packages per shipment yielding 18.9 curies of radio-activity per Fissile Class II shipment.

}C) 203 l -1

1.3 Appendix Dimensional details of the CE-250-2 shipping container are described in CE Drawing NFM-E-22175 Rev. 00 dated 6/13/79. 1939 204 1-2

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2.0 STRUCTURAL EVALUATION 2.1 Structural Desian 2.1.1 Discussion The secondary containment of the packaqe is the 11-1/2" I.D. x 57-1/4" long 16 gauce steel inner container. The inner co,ntainer closure is achieved by securing a 1/2" steel lid to the inner flange with (f) 1/2" Hex Head Bolts and Nuts tack welded to the flange. The primary containment vessel consists of twc 55-gallon drums which nave been welded together to the following dimensions: 22-1/2" I.D. x 68-3/8" long. The closure of the outer container is assured by a standard 17H 12 gauge ring with 5/8" bolt and nut. See Vsew B on Drawing NFM-E-Z2175 dated 6/13/79 Rev. 00 in Appendix 1.3. 2.1.2 Design Criteria The test results described in Appendix 2.10 support the structural requirements specified in 10 CFR Part 71.35 and 71.36. 2.2 Weights and Centers of Gravity The CE-250-2 container weighs approximately 575 lbs. when loaded. The 4 cans of uranium oxide (30 Kg each) weigh s300 lbs. with the CE-250-2 container weighing s275 lbs. The container is approximately symmetrical; the center of gravity is at the cen-ter of the container. When the cans are loaded inside the inner container, the center of gravity shif ts vertically to a slightly lower point because of the spacer used to make up the remaining volume within the inner package. 2.3 Mechanical Properties of fiaterials Materials of all structural components used in the manufacture of the container have physical and mechanical properties equivalent to or better than 16 gauge steel. 2.4 General Standards for All Packaaina 2.4.1 Chemical and Galvanic Reactions There are no significant chemical, galvanic or other reactions among the pack-aging components and the package contents. The CE-250-2 shipping container is fab-ricated of carbon steel. The contents are: vermiculite for insulation between the outer and inner containers, stainless steel cans containing uranium oxide in either the powder or pellet form and having a moisture content of 5 w/o or less. 2.4.2 Positive Closure Positive closure of the CE-250-2 containers is assured by:

1) The inner con-tainer being gasketed and sealed with 6 Hex Head Bolts and Nuts and 2) the outer container being sealed by a standard 17H 12 gauge ring with a 5/8" bolt and nut.

Both of these closure systems insure that the container cannot be inadvertently opened. 9 2-1

2.4.3 Lifting Devices Both the inner and outer container lids have handles attached. These handles are present for the sole purpose of aiding the operator in positioning of the lids during the closing or opening of the container. They are not for the purpose of lifting the container. No lifting devices are incorporated as a structural part of this container. 2.4.4 Tiedown Devices No tiedown devices are incorporated as a structural part of this container. 2.5 Standards for Type 8 and Larce Guantity Packaaina N/A (Type A quantity per package). 2.6 Normal Conditions of Transport The CE Model 250-2 package is identical to the Westinghouse BB250-2 package except that the overall length is 68-3/8" and the inner container length is 57-1/4" (compared to 74" and 63-1/2" respectively). These packages both utilize design con-cepts which are similar to those used in the design of the NUMEC LA-36 and Pu 10-1 packages. These packages were tested in accordance with the requirements specified in 10 CFR Part 71 Appendix A for normal conditions to assure compliance with the stan-dards outlined in section 71.35. (See Appendix 2.10 for tests performed on the NUMEC Pu 10-1 and LA-36 containers). 2.7 Hypothetical Accident Conditions This section describes the hypothetical accident conditions as specified in Appendix B to 10 CFR Part 71 and meets the standards in 71.36. The inner container of the CE-25C-2 when fully loaded weighs approximately 340 lbs. over a base area of 121 in2 resulting in a vertical loading of 2.8 lbs/in2 The inner container of the NUMEC Pu 10-1 package, when fully loaded, including the neutron moderator weighs 279 lbs. over a base area of 78.54 in2 resulting in a vertical loading of 3.55 lbs/in2 Thus, the tests performed on the latter container are valid for the CE-250-2 package. As a result it is concluded that:

1) The integrity of the package is not affected by the tests. Because the lid is bolted in a minimum of six places around the top of the drum, separation of the lid from the drum does not occur.

In this connection, test experience with the BB250-1 shows that as a result of a top corner drop, the lid and the body are folded together into a tighter closure.

2) The incorporation of five inches of vermiculite is equal to that pro-vided in the NUMEC package, and is sufficient to assure that after the drop and thermal tests, the temperature of the inner container of the CE-250-2 package would not exceed the observed maximum of 500'F. Since the gasket is service rated to 800 F, the closure of the inner container is not compromised.
3) The test series does not result in the addition of noderation to the contained fissile material.

1939 207

4) The dimensions of a damaged package are conservatively taken to be 20" 0.D. x 64-3/8" Lg. This assumes a reduction of 2-1/2" in diameter as the result of a drop test with the package in a hori-plus a reduction of 4" in height as the result of zontal posit' s,

a drop test with the package in a vertical position. No deforma-tions in excess of these values were experienced during the testing of the Pu 10-1 package. (See Appendix 2.10 for 88-250-2 & Pu 10-1 test results). 2.8 Special Form N/A (All radioactove material in the packages is in normal form). 2.9 Fuel Rods N/A (The CE-250-2 package is not used for the shipment of fuel rods). 2.10 Appendix (1) BB-250-2 Test Results - Westinghouse SNM-338 (2) NUf'C Pu 10-1 Test Results (3) NUMEC LA-36 Test Results 1937 208 2-3

APPENDIX 2.10 WESTINGHOUSE LICENSE SNM-338 BB-250-2 TEST RESULTS O O 1939 209

SNM-338 Shipping - NFD ( '. N-16.4 Limits and Controls The Fissile Class II limit, Fissile Class III limit, and the Procedural Controls presented in Sections 4.4, 4.5, and 4.6, respectively, will apply directly to this package, if " Equipment Specification E-676498" is sub-stituted for " Equipment Specification E-676200". 17. NUMEC LA-36 Shinoina Packace The construction, limits on contents, and loading procedures will be in strict complitnce with those given in Amendment 71-1 of License SNM-145, Docket 70-135. 18. BB 250-2 shipoina Packace 18.1 Packaging Descriotion Designation - BB 250-2 \\ _. Gross height - 575 pounds, 1-a iluom a Fabrication - The design and fabrication details for this container are given in Westinghouse sketch

  1. SKA-252 which is attached as Appendix L to this application.

Coolants - Not applicable 18.2 Contents Descriotion Radioactivity - Not applic-ble Identification and enrichment of SNM - The SNM wi).1 be unirradiated uranium enriched to a maximum of 4 w/o in the isotope U-235. f% 1939 210 Docket 70-337 Defo: 11/18/66 Revision No.13 Date: 3/1/68 Face g M e m o

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SNM-338 Shipping - HFD : - 1.?D i .i. _i a_i ?, C..h_i_i.m i_n.- Pa c.h :_~ s:. 23.1 P:e'-:act i ng Dnscrintuon =---- y r.. (.g 9 5 , (..' .. t. & c:riL..I in Part 13. 23.2 Contents Description Radiocctivity - No t apnl icmSic Identification and enrichment of SEM - The S!!:1 will be un m adiated urcnium gnriched i to a maximum of S w/o in the icotope ~"U. Form of S:~21 - The C::M 5:111 be cclid uranium compounds that will not react ch;mically or decompose at temperatures below 750' F. The material uill be encles:d with-in a container constructed of steel having a 24-gage specified minimum thickness. The container will have a maximum ID of 8.5" and a nominal height of 15.375', and will utilize a gasketed lid with bolted leching ring. The container will be constructed in accordance with US Military Standard fis 24347. As an inncr container within the BC-250-2 packaging's inner cylinder, it is considered completely adequate to retain tha SNM un' der the hypo thetical accid _at conditions. A co.npa;;isc.7 between the structural features of this containar and a DOT Spec. 17-H centainer is shown in Table 23.2.1. A maximum of four of these containers will be inserted in cach package. The maximum allcwable H/U ratio, considering all sources of hydrogancus material within the inner cylinde: cf the packaging will not enceed 1.5. A typical arranJement for shipping raaterial in the form of pellets is shown dn Westinghouse Drawing C7103D10, which is enclosed as part of App.endin R. Militar. Standard MS 24347 also is e-nclar;cd as part of Appendix R. Neutron Absorbers, etc. - None Maximum h'eigh t of Fisulle Content - nr

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APPENDIX 2.10 NUMEC LICENSE Snit-414 Pu 10-1 TEST RESULTS 1939 218 7

VI.1 ml:" c Pu 10 T Cnnt'inar VI.1.1, cont.sirce D::crintion Cross Ucicht 400 lbs. (nax.) a. b. !!odel ?!v: ter Pu 10 I ~ Materials of construction, wcichts, dimensions, and =ethods c. of fabrication. 19" or 24" dia cter Outside drum: Salid stainless steel, with flanced, Pregurevessel: gasketed, bolted clocuro Pressure ver,ccl cas!:ct: 1/8"targetorblueasbestos compressed asbcstos chect Polyethylonc gr:nnlcs uith polyester resin Moderator: filling interstices 11 liter polyethylene bottic contained Primary containcr: in two scaled polyvinyl bags More detai1NI design information is provided in the enclosed drawings, and in the follo.ing sections. Identification and maximum radioactivity of radioactive constituents d. 1. Pu 239 154 curies (Transport Group I) 2. U 233 1.71 Curies (Transport Group II) 3 U-235 5 24 x 10-3 (Transport Group III) E Classification of material to be shipped: c. Large source and fissile material Identifica' tion, chenical and physica1 form, and maxinum quantities f. of fissile constituents: Uranyl nitrate colutions having a concentration of U 235 not to 1. execcd 350 grams per liter, provided that (a) the cenbined U 23. and plutoniun content is not more than 1% of the U-235 content, and (b) the mininum free acid is 2 colar. Uranyl nitrate solutions having a concentration of U 233 and 2. U-235 not to execed 250 gra.s per liter, provided that (a) the U 233 content is not r,rcater than 10% of the co.mbined U-233 and ~ U 235 content, and (b) the plutontua content is not mt c than 1% of the com.bined U-233 and U-235 content, and (c) the nininum free acid is 2 nolar. Plutoniun nitrate solution; having a concentration not to execc 3 250 crans.Pu-27) per liter, provided that (a) the Pu 240 conte.n is at Ica?t 3/, of,the total plutonium, and (b) the mini:au.m frc.c acid is 2 colar. l9 11 22 66 VI-1 's

Ten (10) liters' Kuinun quantity of mterial per package: of colution, containing not noro than 2 5 kilograms of 4. fissile isotop:. Extent of reficction, amount and identity of non-fissile neutron ab:orbers in the fi scile constituents, and the atonic ratio of g. moderation to fissile con tituente. The ficsile natcrial is contained in a polyethylen2 bott1'c (0.16" wall thickne:n) tihich is contained in a cadmium wrapped 3/16" thick A 2 inch thick polyethylenc-stainicss stecI prescure vessel. polyceter renin composite currounds the cadmium wrapped pressurc Itcas fl, 2, 3, and 4 above specific veccel. nodcration to.ficcile constituents. 42 pounds including the polyethylene h. Maxinun wcic$t of contents: bottic. For plutonium containing 1 css than Maxinun amount of decay heat: 1 w/o Pu 233, we estinato a 30 F temperature d DtET 1. temperature of 160 F under condition 1 of Appendix A, 10 CFR 71. 0 t 9 1937 220 VI 2 11 22 66

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VI.1.2 contain-r Evalual. inn VI.1.2.1 Cemral_ St.,ndprds 7 Internal Reactions a. All fissile natcrial is contained within a polyethylenc bottic (0.16" wall thickness) which is doubic bagged in 0.012 inch PVC, and contained in a pressure vessel fabri-cated from stainicss stcci, precluding the possibility of intclnal chcaical reactions with the packaging natorial. b. Closurc Clor.ure.of drums consists of a 12 gauge bolted ring with drop forged lugs, one of which is throeded, using a 5/8" bo c. Lifting Devices No lifting devices are incorporated as a structural part of the container or its lid. f s d. Tic doun Devicca No tic down devices arc incorporated as a structural part of this container. Structural Standards for Large Quantity Packaging c. Because the package may contain in execss of 20 curies'of transport Group I natorials, as defined in 10 CFR 71.4(f ), it is evaluated as a large quantity package as well as a fissile r.aterial package. l. Load Resistance Calculations demonstrate that the yield strength 'of the packaging natcrial is not exceeded under the conditions set forth in 10 CFR 7132(a). 2. E'xternal Pressure The contain:ent vessel is equivalent to an ICC 2R container, and is therefore capabic of withstanding an external pressure of 25 psig. Criticality tir.ards for Finnile liatorial Packares VI.1.2.2 Optinun Vater Modcration is a Normal Condition of Ship..cnt. ~ DWT - a. Under this condition, 2 5 kg U 235 is suberitical in a REFutut 5 625" )I.D. cyltraler with full uatcr reficction (F To P-. K-1.2(a Y-1272), and up to 250 gn Pu/ liter is suberitical in an infinite 5 625" I.D. water reflected infinite cylir. der (Figurc J 2.7, Y-1272). 1939 221 "-3 11 22 66 ?

Y All fissile n sterial is contain-d uithin a polyethylene bottle provirk.1 uith a vente.1 can uhich has hecu te::ted toThe bottic is / b. h@g0 [yhich i:: 16 ouncea inteinal pres: tre. l cnclo:r:1 in tuo 12. nil palyvinal scanicus bens, cach of chich op:n at. o ounces t2 Tim enclo::e I r. f has bean r..Oe.1 Ls pr. v n!.1. a'..ini of 31.piiri. ' battle n. placed within L:ic contain.;cnt vesuel which is provided g J, uith a gas':et.:d flanced closure. Eccar.sc this syst.c, provides doubic containnent of the fissile f material in a cuberitical gcon2Lry, and precluGes the leakage o. liquids intn an un;are ccanetry in spite of any singic packagin; crror, the fis::ile content of any single packaginl; cxeceds the nininin critical casa under conditions of optir.tn configuration (sphere) arI ref1cetion. Administrative procedurca detailed in VI.l.2 5 balou are used to verify tho' leak tightness of cach containnont vessel. VI.1.2 3. M1pli.,nfgi_nf)c_P2cic,.yf,, f Noraal Conlitions of Transport a. Er.posure to direct sunlight at an a.bient tenperature of 1. 130 F in still air. 0 The external container is a steel drun inside of which is a verniculite insulated stcol structurc containing a r.cdcrator, a stainic::s stecl pressure vecccl, and the product solution. t dan 2Cc to more scverc thernal con-All are expo::cd with As ditions duzing the rcquired thernal test uith no danage. previously indicated, the solution nay achicyc a tenparature of 160 F, wh'.ch is within the allowabic limits for the ultra-cthylux bottic. Exposure to an anbi ni, tenperature of A0 F. 2. of the steel imd insulating natorial at that Ioss of propertic.: tenperatuio will not occur, and possibic crystallization of the Modcrator ui'il not change its nodcrctin;; properties. The polyethylene bott'e is conposed of " ultra-ethylux-23" as produced by Westlake Plastics Company, or equal, and does not To allow enbritt.le until the tenperature is reduced to -55 F. for exp.ncion of the solution on thawing, at least 107, free space is provided in the bottic. Expasure to atnest eric pressure of 0-5 times standard atnospheric h .3 pressure. The drun lids have no caskets, allowing the equilization of pressure. 4. Vibration .r Each pachace is vibrated for 5 ninutes as a part of the fabri. cat. ion ;,rocedure in order to proncte acttling of the verniculite insulation. 1"9 922 L VI u 11 22 66

l' S. 1.'ater Spray der.lgns (LA '14 with pae:wnen uslain nbtilar druti Erper!..m. S :::-14'i) elenonstrate t. hat e.ywure to heavy llA-10 !!ef: rain for extended Nriods of tine does not result in water inicahage. 6. Frco Drop This test was not performed because the Pu-10-I container does not depend on spacing for nuclear safety. ~ 7 Cornce Drop Because the package is fr.bricated from steel, this test does not apply,' 8. Penetration The druns are fabricated fron 16 Ga. steel, and are sinilar Therefore, the to those used for the I;U;EC LA-36 containers. test results reported in Section Xof S;;M-145 apply. 9 Compression A >2,000 pound load was placed on top of a sample package for a period of 24 hours with no r.casurablo deficction of the drum. Based on the above, uc conclude that requirements set forth t e in 10 CFR 7135(a) (1), (2), (3); (b) (1) and (4) 111 are 10 CFR 71 35(a) (4) and (5) do not apply as there satisfied. aro no coolants in this package. 10 CFR 7135(b) 1 and 3 are discussed in VI.1.2.2 above, and 10 CFR 7135(b) (4), (1) and (II) does not apply as the spacing provided by the package 'does not effect nucicar safety. With regard to 10 CFR 71 35(c), the vent valvc is closed prior to all shipt.cnts. a b. Accident Tent Conditionn Five sanple containers identified in Drawings ASK 1058-D-1, 2, and 3 were subjected to the hccident test conditions reqttired by Theco dra.<ings show direction of inpact for each 10 CFR 71. contain'cr, and indicato naxinun internal tenporatures recorded. Drop tests were conducted in a manner to assure that the lowest point of the container was at least 30 feet above the point of The r:.al impact on an unyiciding surface at tho time of rcicasc. t !!owever, containers numbered 1 and 2 were exposed conditions. to high tenperatees for 36 minutes to compensate for a tc:..perature 1939 223 vr-5 11 22 66

Y / drop in the furnacc ob:crved in.ediately subsequen / [- 1 for the require.d period. Here, the tenparature drop was nininir.cd by additional. pre heating of the furnace to 1600 F. An 11 liter polyethylene bottic cont 2.ining sand for ballast was placed uithin cach container. Container number 5 cuffered inpact on the top corner causing the drun lid to sprind open and release sonc vernicul.' oc. Resulting from this failure, further testing was held in abeyance pending cvaluation of the danage,'and the deternination As finally determined, these nessures of corrective measurcs. consisted of the use of drun lids with a z,ufficient lip to completcIy enc %sc the upper half of the rolled That these neasures were sufficient to assur o closure under accident conditions was denonstrated by contain2r number 3 which The lid renained prop 3rly scated on was also corner dropped. the drun, and no verniculite was lost. Container number 4 was impacted on both its top and botton surfacc. The inpact onto its top surface caused a scan in tre upper drun body to separate slightly, yiciding an opening measuring about !!o ncasu ablo cnount of vernicttlite was lost through 1/8"x1". this opening, and subsequent to the above tests, the drp was impacted froa a height of 40 inches onto a 6 inch diancter by*S inch long bar, as specified by 10 CFR 71 Inpact Althougha1-1/2" occurred on the vcided scan joining the druns. to 2" deep depression resulted, the integrity of the drun and ~ wcld was'not violated. As previously indicated, other tests were performed as illustrated in Figures 1, 2 and 3 of this application. Exanination of the containers subsequent to their renoval f' on r 24 hours of.ir.~.crsion under three feet of water revealed thrco principal facts; (1) no water 1 caked into the containnent vessel, (2) no nodcrator was lost, and (3T tho maxinun tencurature experienced within the containnent vessel was in execss of 1000?, Additionally, the cadmium vrapping of the 0 but 1 css than 150 7. containnent vessel was in no way offected by the test sequence. Fron these findings, we conclude that: No radioactive material will be relc$ced from the packrge ~ 1. under the stated accident conditions. The package will remain suberitical as the material renains 2. confined to a suberitical cconctry, and the geo.2tric forn of the contained natcrial is not altered (10 CFR 71 35 (b)(2). VI 6 1939 224 11 22 66

7

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. isN -,' ( N SU!. A To R ,q,;-. g ,s i i d <-(.,,. ' r -> l;$,, ST^'"'c 5 5 51'3 61-c os pin :n. ve n.n. v N ~. '. .. > ( OU TEP. C Ot4 Th it@.Ps '.. l. ,,'N -2 i t s 6N q.. J, .' -0,.) IG. GA. INtF.R. Cc.yTAINER ss s. IOO'r / o' J,-[~.".- 96. -- rgootag7og C. sk'INkNbi .1937 z 25

19 TAC.E VM. ' 5 :' '

39" ~ O .!00 F O I !'......v > s ; - l,c,.y ' ORUM No._/. w.\\ ?..:. y ~ NUMEC PU I m F t G ~.! SHIPPING CONTAINE Ps SK- 058 I .. - 2 s. G r, C. 5 'i n! I l. ~ - - - t...

'* C O i. j i 'La ; 'i *i. C' *:. :, ;.'.. ~ / 3' / . 'r / y., c,.=, ^ ~ / \\. ~i ./. / 'i '5 ~~? )i :s /,,./. /'6 - <

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(. 1 '; ;,.e ,,4, 4 -- INcuL AToF. M: l .. t y 't. k~N'. 3 ,y .- l -- - STAltit.CS S ST ET L c o w T Air.16r'. V ii.5 0 E L ' j,- \\l h ., -c OUTER. Cot 4TAINER. o..p . fyNs't.';j h.;; - (G G A, INN E R COIE[AINII' , C.) f . Os - u.j i ?. 3 0 r" - l ...i gg.F } o -- MODE R ATo R /- w'N. y s w..... s - kbM,..-.-.h.Nh_) TA.w wmHT 32 22 l DRUtd Ilo. - - FL/st.'6'. CLOC.J..i. [ 1 c .g. 'l '-3l..'~-"-{f' N Stj t A fo g c. fy ] f ' t. .',\\ -f- -- STAtH LE SS S TE E L c c,ia 7 Aig m v c. s s g L j., g .......-4 g}4.c ....g .s ii.p...a - OUTI A. C c9 TAN ER . li s '. <,. 7.s o !, g s[ IG GA. INNER. CONTAINEf( . :..[.'.'. -1* M *E*^'t'cR A hplMi$. 1939 226 TieL'v:.1GHT-350 zz .,'s DE noTis om.2c,..w DRUM NO. lit.V.; T. NUMEC PU I c '> F K'- SHIPPING CONTAINER ASK - 058-D-2.. . - O I-fo S C. SMITM I L_....

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'u t.. : C. *:. C L OD J. '.E.

k / l '\\ }.--....... !.q. _.l i (;....);ng...' ' '%.,' ', %. x.g.

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7 u-. courneraer,. ve.sset <4Nj 4 g . j \\ '. > 09TER Cot 4T ArN E R . N'. .I l '. N. ~! (i '4'. s'.1 ' ic, c,4, mats: couTAisEn. ~ '.',\\ i.. l& l (. s' A Mc30e R ATo R 'Nk- -1 . \\z s c. u- ..,sf .\\ NN fl k\\ T A n,'i V #.t G M T .3'/S i p-::.r.i r_- 88 ~~ " L'O &JC 'f,L E O CPal O.' ! i.M P.'.C T. DRUM No. 5 t-q.,. %. %_.. D._. M. W NN w

j %.

IN SU L A To R ' 's,i;. i.. ,,,I, k i

? y) s7AvNLtss ? yeo 9

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p...

16 GA. INNER. CCNTAINER ,,Q .s 0 'a rtootnAtoR ,,/,..".";Q[",, s 4.,.y3sgqqm~ n,j. 2,.m., 1939 227 '.. a s 'l (NDICAT2s DinscTioM DRUM NO. CF IP'!V.C'j' NUMEC PU. I ~ r ' e' ' ': 3, SH!PPING CONTAINE Ps AS - 058-D-3 l 6 5 C. SMITH

N Double contaitt?.cnt is maintained in that the internal / .3 te.peratures noted during the tests are insufficient to f / comprcaise the i_ntegrity of the polynthylene bottic ~ a. b. thn PVC bagging y T. the pressure, vessel c. It is recogni:cd, ho <cver, the pressure buihiup within the polyethylene bottic may displace gran quanti. tics of solution from the bottle. !!oucver, such material reasins doubly contained within the double PVC bag'and the pressure vessel. 4, No damage uns suffered by any of the conponents or materials .. of const.r.uction due to exposure to the thornal test. VI.l.2.4 Evaluation of an array of Pu-10-I containers In ic:t of the fact that the test conditions did not effect the con-tainment or noderation of the material within the container, we evaluate an array of Pu-10-I containers in both the damaged ar.d undamsgcd condition on the basis of.the follotting conditions: Solution Dianetcr - 5 56" II/X Ratio 44 Cadnivn Thickr. css 0.016" Modcrator Ihickness 2.0" Equivalent Water Thickness - 1.91" hio netheds are considered herein to demonstrate that the cadmium wrapped 5.625" diameter cylinders arc isolated when surrounded by the cquivalent, of 19 inches of water. We consider first an analysis based on neutron ponctration data, and correlated to interacting suberits, as reported in K-1478. .A By this r.cthod, a just critical array is described when K=1.0 ke 1-V where ko = reactivity of suberit V = SLF (1 - UF)(ab) p .O F = fractional solid angle ~ (1-UF) = fast le::kacc probability neutron tenetration. The weighting factor p is (ab)p = set equal to 1.0. To obtain values og gconctric buckling Bg, an appropriate value of f 2 is rcquired. Using the critical height of a cadmium ttrapped water "-7 1939 228 11-22 66

t APPENDIX 2.10 NUMEC LA-36 TEST RESULTS 1939 229

.,. ;.,,.:.,. ', 4.. ; -,,,..... {.' ?

  • i;..-6 D..s{'.,'*.5 4,.4,i -

i .i,,;,. pS- / t 7 1 1:UMEC LA 16 container. , ". O.. >l... QJ... '. C. _.'...>.9.-c...:.e:.'.,.;.... . '... ~ ..s... .,.......n.. v.,..... c u. ....s. '. y, " ' - ( c... E.,.'. ' '.',. J,.. j*. - . '(- ~.. ".1.1 P$ckaae rescrintion ',.:.: ' -:*.. :,.+. ,..,5 '.....,3.; ...,.c'::..... % 'd,...c ~. v .?.w :h:.- s. t.r%::.'.....r. 'O : '.3.-. Gross Vc1ght: 2500. .e. '?

. ' '.'..=' % ' * -l '. -.4,2'y k

.. ' ~.u,..k T.

  • b. Modc1 Uumbcr:

LA-36 ~ s c. Details of Construction: w .s- .. This information is provided in the enclosed drawings (10-D 1167, 'Y.e- -l.,10-D-1168,10 A 214 and 10 A 21'5.). d. Identi 'ication and maxinua radioactivi,ty of radioactive constituents: .c... .:. e....- r 2 curies ~ U-234 + U 235 11.1 x 10 U-233 - 1 3 x 10 2 curies l-Classification of material to be shipped: o. c. Fissile material only.' ~

f. ' Identification', chemical and physical form, and maximum quantities r

e. of fissile constituents: ~ , 1. Dry non-decomposabic forms of uraniun having a maxinum U-235 assay .or.5 0%: .Maximun loadins: 36 kg of material containing no more.than ~ 1 58 kg U 235 .... 'Maximun Uranium Density: Any . Maximum Water Content: 05w/o' 2. 36 kg of hydr'ous decomposabic compounds containing a naxinua of 1.0 kg U 235 The maxinua weight of the uranium bearing ~ naterial shall be 36 kg. Extent of reflection, anount-and identity of non-fissile neutron g. . absorbers in the fissile constituents, and the atomic ratio of . mo'dcrat, ion to fissile constituents: The fissile bearing material is contained in.tuo sca168 5 nallon ICC-17H pails. The above tass limits assut c.that no singic pach:,o ' cont.aln,. critical mass unde'r any credibic conditions of modcration and reficction. Non-fissile neutron absorbers, if present, are negiccted for the purpose ' l 'of evaluation. Actual nodcration ratios are as follous: . 1. Non-decomposabic. forms of uranium: (505w/oH2) 0 - O r ~ U 23.5 A:sav N/X y 14.8 / m7 9 12 2-3 ?.h1 .t 7 J-u 34 4.95 -i 3.? _ 45 v

0.

k. ygt

~ .,.'.".',2. D2conpos'abic forns of uraniun: ... u.. ..... ' ' 5. 7 *,. Optinun hydiogen nodcration is assuned.-. p r ,,, ;, l. ,( 2 .u y* ': 1

  • l'.

h.. Maxinun weight of. contents: ")6 kg. , ~.. ' '. ' %.y.::. ..,,n- . q.v 'l..' -gi'.i,e,.:l), f, i. Maximun anount of decay heat:- Negligible. ,,.{, . ;..,.g.3 -[y,[. p:,iy ;.,; V S E' M d N *~- N.".. 'I h..' ?- 'i ' " ' Y. ' : .:s,"......,,. 142 ' Container W aluation .L. <...:.,,. c .l,. J.,,.,1.2.1 General Standcrds a. .- a. Internal Reactions - ; :.-i..,;. n...r:...y..l.,. Non-decomposable foras of uraniun: .. p.. No internal chenical reactions are co,nsidered credible. ' n '... d :.g. 2. Decomposable forns of uranium: ,. ' All' deconposable forns of uraniun are packaged uithin an inert material, such as polyethylene in the forn of sheet or a bottle in order to preclude chemical reactions between the. Y.n ' *( naterial, and the 5 gallon pails which provide primary ~~ ~ conta.inment. . b. Closure ( . Closure of the diuns consists of a 12 gauge bolted ring uith drop forged lugs, one of which is threaded, using a 5/8" bolt. c., Lifting D2 vices-No lifting devices are incorporated as a structural part of the ,C package or its lid., d. k'ieDoanDavices. ,., No tie doun devices are incorporated as a. structural part, of the

  • package.

Structural Standards' for Large Quantity Packaging. . e. Nst applicable Criticalitv St r.dards for Finsile Material Pac JL.2.2 ~ ~ /

a. '.Each' container is limited to assure that its contents would rc:.ain-suberitical under any condition of water modcration and reficction.

b. Each container is 'further limited to assuro that its contents uould . '. renain' subcritical 'in an o.otinum configuration, with optinun water e t.( f.:, moderation and reflos.t. ion. .,c.

r..

...v. s ..fl . X.1-2, 4 c .r...

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.~ ~ J. '...,. 1 NUMEC I.A '36 Container. c 1.1 Packaec D3scriotion ~ ~ a. Gross Weight: 250#.. ^~

T '.!.-...

' ' ~ " .T' .L ' ' b. liodel number: LA-36 ~ ~ ~ .'~'c. Details of Construction: This information is provided in the enclosed drawings (10 D-1167, ~ 10 D-1168,10 A 214 and 10 A 215). I,dentification and maximun radioactivi,ty of radioactive constituents: - d. -2 U-234 + U 235 11.1 x 10 curies U-233 - 1 3 x 10 2 curies Classification of material to be shipped: c. Fissile natorial only. f. Identification', chenical ard physical form, and naiinua quantities of fissile constituents: 1. Dry non deconposabic forns of uranlun liaving a maxinu1 U-235 assay .of50%: .Maxinun Loading: 36 kg of natorial containing no r. ore.than 1 58 kg U 235 . 'Haximun Uranium Density: Any . Maxinun Uater Content: 05w/o~ 2. 36 kg of hydr ~ous deconposabic compounds ~ containing a nacinun of 1.0 kg U 235 The maxinun weight of the uranium bearing' natorial shall bc 36 kg. Extent of reflection, ar.ount and identity of non-fissile neutron g. absorbers in the fissile constituents, and the atonic ratio of moderation to fissile constituents: The fissile bearinj; naterial is contained in tuo scaled 5 gallon ICC-17H pails. The above mass linits assure.that no singic package 'contains a critical nass under any credibic conditions of nederation and ref1cetion. Non-fissile neutron absorbers, if present, are negiccted for the purpose of cvaluation. Actual nodcrc. tion ratios are as follct:s:

1. ' Non$decomposabic forms of uraniun:

H O) ( 50 5 w/v 2 U 235 Ans..7 H/X 12 14.8 2-3 7.h1 ~ .U ~.j:7 .1933 232

.. ;?

.., : - ; R. t. *...., 5 j. '.c.._.:....~.:.

3.,. ; ~i
y ':. r...

.....,,.:.n..... ..,;.;p .. c., .. s...-. -, - r........:.;.. u r .. p. - ~ z., i- ~. p ..z.., ~- . l . c. n:c- .: s .~-.: ... '.. -.' ' '~' ',.2. Decomposabic forms of uranium: - r ,., ', ' Optinun hydiogen moderation is assuned.- ~ . Maximun weight' of. contents: _36 kg. h. ~.-.. --T - Maximun.anount,.of dccay heat: Negligible W. -[i. - / :.'.. ~. - ~r. - i. 4. S. hc 1 '--?".';. ~1.2 ' Container Evaluation 1.2.1 Gener al Standa2 ds .s. - a. Internal Reactions Non-decomposabicfornsofura$iun: ~ 1. No internal chemical reactions are considered credible. 2. Deconpasabic forns of uraniun: Al1~deconposabic forms of uranlun are pacitaged uithin an inert material, such as polyethylene in the forn of sheet or a . bottle in order to preclude chemical reactions betueen the material, and the 5 gallon pails which provide primary containment. b. Closure Closure of the diuns consists of a 12 gauge bolted ring uith drop forged lugs, one of which is threaded, using a 5/8" bolt. c. Lifting Davices No lifting devices are incorporated as a structural part of the package or its lid. d. Tie Doun Davices , No tie doun devices are incorporated as a. structural part of the - package. Structural Standards" for Large Quantity Packagin'g. .c. Not applicable .1.2.2 Criticality Str.nd rds_ for Ficsile '!aterial. Packa es

a. 'Each' container is linited to assure that its contents would renain.

suberitical under ar.y endition of water nodcration and reflection. b. Each container is further linited to assure that its contents uould . rc:nin subcritical 'in an o.ntinu t configuration, with optinu t uater ' modcratio.1 and reficet.icn. 1939 233 ~ X.1 2

. l..~-;' ._......,z..-

~.-
  • .O:.-.:;...j.

c .. f W.. ' y "..'. .... 1,2 3 Evalu ition of a Sinele Package ~ .z ~,... ... ~ .s. Normal.G..ondition of Transport a. g... Exp*osure to direct sunlight at an ambient temperature of 1. ~ ~~ s. 130 F in still air. ~ r. The external container is a steel _drtin inside of which is a ~ ep. 3 1 * 'O veralculito insulated steel sleeve uhich contains two ICC-17H 'All are exposed without danage to more severe thermal .,...f.. - , pails. ..c, conditions during the required thermal test. - 7. '2. 5xposu-e to an anbient temperature of 40 F - M ~ Exposure to 40 F will not affect the structural materials, which .c steel, or the insulating material, which is ver .ulite. '}. Exposure to atnespheric pressure of 0 5 times standard atmospheric pressure.. Tho' drun lids have no gasket, allowing equilization of pressure. 4. Vibrat' ion Each package is vibrated for 5 ninutes as a part of the fabri-cation procedure in order to promote settling of the vermiculite insulation. .5. water-spray A' number of containers have been expos $d to heavy rain storns Such l for extended periods of time, with no water,inicatage.

  • cxposure exceeds the requirements of the unter spray test.

6. Free Drop Two sanple packages were dropped from a height of 4 feet onto-One package was dropped botton end doun, an unyiciding surface. and experienced a less than 5$ loss of apacing and reduction of The other was dropped in~ a hoiizontal position, and volume. also experienced, a less than 5% loss of 3 pacing and reduction - of volumc. 7 Penetration Bot.h sampic packarcs'were subjected to a penetratio t test as .specified in Appendix A of 10 CFR 71. - The resulting dents did. not cxeced a depth of 3/16 inch. 8. Compecasion . A '1275 pound load uns placco on top.of a sa,pic packcce for a period of ~24 hburs uith no neasurable deficction of the drun. Baccd on the above, uc conclude'that the requit cments sat for'th in 10.CFR 7135 are satisfi,cd to the extent' that they are portinent.. x.1-, 1939 234 ~ 11/22/66

'. ' '. '. '.. Wr~.'. O -~.'d-l.*.* :R:t ' ~ -:'.*:T *'.. : u 9 '* ' . ?1-Q. _. . 7. m-y- y..

3.;.~

19 ~ b. Accident Test Conditions .. f ' '.. Two sa.iple packages, each containing at least 36 kg of dry brick ?

~

mortar,and designated as Drums J1 and J2, were subjected to the ' ' ^ ',. ' *.

  • ' accident test. conditions, as set forth in Appendix A,10 CFR 71.

3

1. ' Impact.

- l, J. - dro'pped at a 45 angle fron a height of 30.. y feet on its cov'er. ~ The drum cavcd inuard several inches at ...c. the point of inpact. The ring and cover ucro not dislodged. Dru:1 number '2 was dropped fmn a teight of 30 feet so as to ~ strike flat on its side. Impact occurred approxinately half way betueen the spacer rods. This drvt uns then dropted 30 feet in a vertical position, suffering inpact on its bottoa surface. '2. Puncture ' Drum number 1 was dropped through a distance of 40'.nches onto

a 6 inch dic
.eter cylindrical target.

A dent approx. iately 1-1/8 inches deep resulted. 3 Thornal Both druns were placed within a furnace heated in excess of 1500 F prior t'o insertion of the druns, and naintained at 1475.F for 1/2 hour subsequent to' the, insertion of the drums. 4. Immersion' ~ . Both druns were innersed under three feet of water for a period of 24 hours. 5 Containcy Disnantling and Insrection The two sanple druns were disnantled, inspected and neasured- ~ .to deternine the loss of spacing suffered during the.inpact tests, and the extent of water inicakage into the 5 gallon pails. 51 Weightchecis All pails were weighed before the tests con.enccd, and again, on the sane scale, on conpletion of the tests. Thecc wei hts are tabulated belo r, and denonstrate that C no r.cacurabic inlcahage of unter into the pails had oCCuricd. .;939 9g. X.1 4 11/22ll:

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. W..

...,a. ... c., ".. ' A'.*; ~;'~ ;. - X. '.y .n....s,; 'a. ~^l. :.. :~.,, ;. :- . ~c".. a * ':. r. y.:.: v :. ;. r )* 1 '.. ' Z.'.%9+'Y.':.%- ~ F. ' ' # ~ ~ ', 'i 'J' ......-l* );y.,.. l....; WIGHTS OF PAILS ... s. '. : r... p

v. :.

. r..,.. - ORGDP . ORGDP ~. E, ' -1. Y,.* " - . - _(before testsl (before tests) (after tests), IMEC .J '. '. [ f . y',,.... ', .......u + ?,.;. number i

n..

Top Pail' 22,470 22,470 22,470 Botte Pai3' 20,470 20,440 20,.440 Number 2 Top Pail 20,510 20,490 20,490 ~ Bottom Pail , 20,450 20,44o 20,440 '5 2 Inspection checks ~ 5 2.1 Dru:t number 1 experienced a maximum temperature of 500 F ~ 1 on the cover plate. Removal of the cover and the pails revealed that uater had entered, but only half filled the inner container. The inner container had shifted approximately 1/4 inch as 'a result of the impact. s Both pails experiencodi.aximun tenparatures.of from 200 to 300 F, and appeared to have suffered little damage.. 0 When opened, dryness of the contents was confirned. 5 2.2 Drun nunber 2 also experienece a maxinun teeparature of 5000F on tha cover plate. As with drun nunbar 1, water had entered, but only half filled the inner container. ~ The r inner container had shifted approximately 7/8 inch as a result,of the impact. In addition, the drun had caved in at the point of impact, yie'ld'ing a total loss of.21/2 inches spacing betueen the center of the inner container, and the nearest point on the outer container. The upper pail experienced a maximum tenper$ture of 325 F. Pieces of the, gasket pulled-loose uhen the lid uas renoved as a result of the adherence to the side of the pail. The botton pail experienced deformation on its rolling hoop', sufferingalossof1to1-1/2inchesinoverallheight. However, the gasket had not deteriorated ' appreciably, and maintained its scal. A. strip of sec=ingly.ca':cd pouder 3/8 inches. t. Icby3/4incheslongby1/64inchthichunsfound near the t.op'of t% pail. l'o.other indications of cat:ed material uns notcc. Attempts to brush this material fron. .the pail uith light pressure uere unsuccessful, but sini]a.- - attempts uith finger nail pressure indicatcd that it may not' have been completely reacted. No o?.hcr attengt had been made to identify the nature of this caking. However, in i f the cen:ral tendency of. hygroscopic powdered natcrir.1 -)i A..; b' .v c:t oto~ fora locali:.ed odhonions on nan) apptrcntly dry sucrc :cs, 7 77 /. the calvre of the nilligran qun iti. tics _of cat:ej pyan observed cannot be, acc:.clain:S uith any de rce of cr ct"nt. nts It is, therefore, on thc.bTsis of recorded ucicht n:ar. thit hadcratica cont:al is chined. v~ tM

,,. :-? v.*.;:g: ~ p.'; ~ -:.. e,,.. . ' '.... 'g.' 5.,; l

  • m

...g., g....... ;.... -..,.,,...g.. a.,, ~ . y. i. ..y .. ~.. -. ~ A series of additional tests has b'cen carried out wherein ....., ~ ,.~, a ~ "...J f,,.. -,' pairs of pails have been dropped together uithout ben 2 fit of the surrounding,dru.n st.ructure, exposed to' temperatures , ' f. '., *].. e ", ', .,. ' '. '... ' typical of those recorded above,.nd im.ersed under three . " %. !. c '..,*[J,;..l..,. [ ' fee t of water for 24 hours. The results confirn thoso .. reported above. Included in these tests.were pails uhich ., J..?. U...., ..l.. were equipped with lids identical to the standard 17-H lids, cxcept, that the closure device is a' lever loc!: ring formed of. 032 stcol sheet, ~in place of the standard lid closurc .,, 7 ~.. y-lugs. The lids are identical in all other respects. ~ ~. Based on the above tests, we concl1ide that: '~~ 1. The individual package -renains subcritical under all conditions by virtue of _the mass lirtit, 2. The ability to exclude water fron the material being ~ i shipped provides the basis for evaluating an array of packages on the basis of dryness of the material. 12.!i Evalu? tion of an Arrav of LA '36 Containers s _1.2.4.1 Drv Concounds In vicu of the proven ability to.cxclude water moderation, uc consider that all, material bping shiipad contains'a maxinu.n of 0 5 w/o uater. l a. Undamaged .Because this naterial is essentially unmoderated (H/US 0.$), ~

criticality cannot be achieve'd with any finite mass. ' Accordingly, an infinite number of containers is safe.
b.. Damaged The rtinimun voluna occupied by the LA-36 container in a close packed hexagonal array is 3 46 R H = 3 46 (.835)2 (3 16) = 7.6 ft3.

2 ~ 2 (93% U-235) }feb = Critical nass.of an unreflected sr.iere of UO Because the nederation ratio noy be as high as 14.8 for 1.00 . enriched uraniun, ue detornine,the value of.Mcb fron F gure 10 i of LA-3366. 5." nile the value of Mcb thus obtained represents a. carbon-::ater-uraniun systen, it yicids slightly conservative results, as seen in Figurc 9 of IA-3366. Thus,, McB = 25 kg U 235 Thedensityfo=17gn/cc. The a~ verr.gc uraniun density [for the systen is g = 3 3.s..e.s-m = *

  • cn/ =

,9w o37 215 liter I x.1 6 n/22/G5

3.0 THERMAL EVALUATI0ff Materials of all structural components used in the manufacture of the con-tainer have physical and mechanical properties equivalent to or better than mild steel throughout a temperature range of -40*F to 1500*F. (See Appendix 2.10 page (VI-7) of NU!4EC Pu 10-1 tests "No damage was suffered by any of the cor"ponents or materials of construction due to exposure to the thermal test".) 1939 238 3-1

4.0 CONTAINMEfiT 4.1 Containment Boundary The primary containment of the CE-250-2 package is the outer 16 gauge 55-gallon drums which have been welded together (22-1/2" I.D. x 68-d8" long). The secondary containment boundary is tne 16 gauge steel inner container,11-5/8" inner diameter x 57-1/4" long. As a result of the tests performed on the Westing-house BB 250-2 and the NUMEC Pu 10-1 containers, it was determined that the in-tegrity of the CE-250-2 package would not be affected by the test conditions. 4.1.1 Containment Vessel The outer shell of the CE-250-2 package is composed of two 55-gallon drums made of 16 gauge steel welded together. 4.1.2 Containment Penetrations There are no penetrations into the primary containment. 4.1.3 Seals and Welds All seals and welds are specified in Drawing NFM-E-Z2175 Rev. O dated 6/13/79. 4.1.4 Closure Closure of the outer container is achieved by using a standard 55-gallon 12 gauge Nut and Bolt ring securing the gasketed 16 gauge outer lid. The closure of the inner container is maintained by a gasket and 6 Hex Head Bolts (1/2" 13 UNC-2A x l-3/4" Lg and nuts (1/2" 13 UNC-28). These two closure devices provide posi-tive sealing of the container. 4.2 Requirements for Normal Conditions of Transport It is concluded that under normal conditions of transport (as specified in 10 CFR Part 71, Appendix A) the tests results described in Section 2.6 of this applica-tion indicate the following:

1) There will be no release of radioactive material from the containment vessel.
2) The effectiveness of the packaging will not be reduced.

} N 9

3) There will be no mixture of gases or vapors in the container which could, through any credible increase of pressure or an explosion, significantly reduce the effectiveness of the package.
4) The package is so designed and constructed, and its contents so limited, that under the normal conditions of transport specified in Appendix A of 10 CFR Part 71:

(a) ihe package will be subtritical. Criticality safety calcula-tions are presented in Section 6 of this application. 4-1

(b) The geometric form of the package contents will not be substantially altered. (c) There will be no substantial reduco.an in -he effective-ness of the packaging, including: (i) Reduction by more than 5 per. cent in the total effective volume of the packaging on which nuclear safety is assessed; (ii) Reduction by more than 5 per cent in the effec-tive spacing on which nuclear safety is assessed, between the center of the containment vessel and the outer surface of the packaging, or; (iii) Occurrence of any aperture in the outer surface of the packaging large enough to permit the entry of a 4" cube. 1939 240 4-2

4.3 Contain. ment Requirements for the Hypothetical Accident Conditions The effect on the loaded CE-250-2 container of conditions hypothesized to occur in an accident was assessed during the testing of a loaded NUMEC Pu 10-1 container. Two 30-foot free drop tests and puncture tests as specified in Appen-dix B of 10 CFR Part 71 were conductet. These tests demonstrated that no radioactive material would be released. The thermal tests performed on the NUMEC' Pu 10-1 container demonstrated that no damage was suffered by any of the components or materials of construction during the thermal test. Examination of the containers subsequent to their removal from 24 hours of immersion under three feet of water revealed that no water leaked into the contain-ment vessel. It was evident from the above tests that the package would remain subcritical because the material remains confined to a subcritical geometry and the geometric form of the contained material is not altered. 1939 24I 4-3

5.0 SHIELDING EVALUATI0t! N/A (The packages are used for the shipment of uranium oxide in pellet or powder form in stainless steel cans which are then placed in the container. External dose rates are less than 1 mR/hr S y at the surface of the CE-250-2 package.) 9 9 1939 242 5-1

6.0 CRITICALITY SAFETY EVALUATION 6.1 Discussion and Results The CE 250-2 shipping drum design incorporates a steel inner cylinder which can hold up to 4 fuel-bearing stainless steel cans. The void between the outer drum and the inner steel cylinder is filled with vermiculite. It has been shown that the hypothetical accident conditions do not compromise the leak-tight feature of the container. The inner cylinder design thus provides an added margin of criti-cality safety by maintaining a greater separation distance between fuel-bearing con-tainers and by excluding moderator from this region. A summary of the criticality evaluation (as Fissile Class II) is presented as follows: NORMAL CONDITI0flS Number of undamaged packages calculated to be subcritical (closely reflected by water) 448 3 Package size, cm 444,333.03 ACCIDENT CONDITIONS Number of damaged packages calculated to be subcritical with optimum interspersed hydro-geneous moderation and full water reflection 180 3 Package size, cm 330,485.36 Transport Index 0.56 6.2 Package Fuel Loading All material to be shipped in the CE-250-2 package will meet one of the 'following two restrictions:

1) The material to be shipped will be homogeneous and sampled to verify that the moisture content is less than 5 wt %.

or

2) The material to be shipped will be heated to at least 600 C in a moist atmosphere for at least one hour to assure dryness.

In addition, a maximum of 30 kg of uranium oxide per can will be allowed. (Four cans maximum per package). }g}} 243 6.3 Model Specification ~6.3.1 Description of Calculational Model The calculational model (Figure 6.1) is nearly identical to the actual package dimensions. The following conservative assumptions were incorporated in the model:

1) Each stainless steel can was assumed to be packed full with UO2 at a bulk density of 3.5 gm UO2/cc. This translates to over 46 kg U02 per container. A maximum of 30 kg uranium oxide is allowed.

6-1

2) The fuel was assumed to contain 7 wt % H 0.

The limit is 5 wt % 2 verified by analysis.

3) The package was assumed to contain the maximum number of cans (4) all at the maximum allowable enrichment of 4.1% U235
4) A 1 foot thick external water reflector was assumed for each case.
5) For the array cases, the actual triangular pitch was converted to a square pitch, resulting in tighter packing of the drums than is physically possible.
6) For the accident case, it was assumed that the drums were reduced

? 1/2" in diameter and 4" in height. These reductions were obtained fecm the previously referenced test results.

7) Optimum interspersed hydrogeneous moderation was assumed for the accident case.

6.3.2 Package Regional Densities Fuel Composition U235 .00032418 x 1024 atoms / barn - cm U238 .00748708 x 1024 a Hydrogen .01763005 x 102i. n Oxygen .02443744 x 1024 6.4 Criticality Calculations The KENO-IV Code with 16 group Hansen-Roach cross section sets was used to determine the reactivity of the CE-250-2 drums under normal conditions of transport and under hypothetical accident conditions. The following results were obtained: Normal Conditions of Transoort K Description eff Isolated package 1 ft. H 0 2 reflector 7% H O in fuel 0.4409 0.0046 2 Same as above with 15% H O 2 in fuel 0.7392 0.0046 8x8x7 array,1 ft. thick ex-ternal H O reflector, 7% H O 2 2 in fuel 0.8421 0.0048 Hypothetical Accident Conditions }g}} 2kk K Description eff Isolated package 1 ft. H 0 2 reflector 75 H O in fuel 0.4555 0.0056 2 Same as above with 15% H O 2 in fuel 0.7545 0.0073 6x6x5 array, 1 ft. thick ex-ternal H 0 reflector, 7% H O 2 2 in fuel 0.8676 0.0048 6-2

The last case was the highest reactivity calculated in a parametric study of an array of damaqed packages under various external mist densities. Results of this study are shown in Figure 6.2. 6.5 Code Validation The XEtt0 Code with 16 group Hansen-Roach cross sections was validated in an Oak Ridge report entitled " Validation of the "KEfl0" Code for fluclear Criticality-Safety Calculations of Moderated, Low-Enriched Uranium Systems" by G. R. Handley and C. M. Hopper, Y-1948, issued June 13, 1974 In the study, the Monte Carlo computer code, KE!10, was employed to calculate 40 critical experiments with uranium enrichments in the U235 isotope of 5'; or less. A variety of geometries and materials were considered. The code input parameters and the 16 energy-group-cross sections were included. It was concluded that the code and cross sections are adeouate and that reliable criticalit'y safety calculations may be made for systems of general interest. 1939 245 6-3

1 FIGURE 6.1 CE-250-2 SHIPPING CONTAINER KENO-IE MODEL I4.605 CELL BOUNDARY N.66 VERMICULITE MIST N ySTAINLESS STEEL \\l ( d y 3 \\/ 28.575 NORMAL CASE l\\ N (25.4) ACCIDENT CASE / / r2.2555 g i\\ p CARBON STEELj \\ 28.63 NORMAL CASE tJO -HgO (25.955) ACCIDENTCASE L 2 r-f.27 4 VOID .i397 eVERMICULITE s l h,dh. N 'p,i ( i, [/h! } i,Uo :HgO,l 27.8003 r p , /" l [, )g', ,g799 )' 1397 j N3.8275 A'l 173.2155 NORMAL CASE ,' ' '/ j l12.3188 ' '/ (E3.OSS3) ACCIDENT CASE f' .i397 N / / l l -CARBON STEEL / / i' ! o o l '--3175 }} STAINLESS STEEL i 10.63625 NORMAL CASE (5.55625) ACCIDENT CASE NOTE:ALL DIMENSIONS ARE NOMINAL AND ARE IN CENTIMETERS =- . "P""

1'lt;Ul:C 6. 2

o 1 CE-250-2 SilIPPING DRUMS, llYPOTilCTICAL ACCIDENT (IIA)

~ REACTIVITY OF 6x6x5 ARRAY I' { .90 .I i a l l 'l j i T T I ~. J ^ INT M i i i-1 s 1 1 N 'NT.N j l i 1 i 1 's s. ' N' i i i 'i T. -l .80 s l N\\ 's-s .l K 's, i eff s i i 1 j .N A \\ t T i .70' i 1 1 T l 1 i W us W r,J A t N .60, .10 .20 .30 .40 .50 .60 .70 .80 .90 1.0 Dry External Mist Density (Bert een Driins), em/cc lion

7.0 OPERATIflG PROCEDURES 7.1 Procedures for Loading the Packace A member of the Nuclear Licensing, Safety, and Accountability staff must be present to witness loading of the CE-250-2 packages. A packaging check list is then filled out after inspection of the following:

1) Each package must be in serviceable condition with no damage which

~could compromise its integrity.

2) Condition and placing of gasket
3) Proper seating of gasket to assure leak tightness
4) Proper closure of flange bolts 5)

Inclusion of spacer can

6) Proper placement ard tightening of ring seal or cover bolts 7.2 Procedures for Unloadina the Packace Manufacturing has a specific operating procedure for unloading the CE-250-2 shipping containers. This procedure outlines the proper order and methods for un-loading the package with instructions to notify Health Physics of any problems en-countered.

M39 248 7-1

~ 8.0 MAfflTEflAfiCE TESTS Afl0 MAINTEf!AfiCE PROGRAM 8.1 Acceptance Tests All containers to be fabricated will be constructed in accordance with CE Drawing flFM-E-Z2175 Rev. O dated 6/13/79 and shall be source i'nspected prior to leaving the vendor's facility. Changes to the design of the con-tainer which fall outside of the safety envelope specified in this application will be submitted to NRC for approval. This may include retesting of the con-tainer if analytical results are not capable of demonstratino that the 'est sequence previously performed would be applicable to the changes made. 8.2 Maintenance Prooram Health Physics personnel determine during the loading inspections when any repair or replacement of material is required. 1939 249 8-1 --}}

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