ML19312A330

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Safety Analysis Rept for Packaging:Ornl Tungsten-Shielded Cask, Addendum 1
ML19312A330
Person / Time
Site: 07105597
Issue date: 02/28/1979
From: Jonathan Evans, Mouring R
OAK RIDGE NATIONAL LABORATORY
To:
Shared Package
ML19312A332 List:
References
ORNL-ENG-TM-03, ORNL-ENG-TM-03-ADD-1, ORNL-ENG-TM-3, ORNL-ENG-TM-3-ADD-1, NUDOCS 8003210227
Download: ML19312A330 (29)
v • d • e


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SAFETY ANALYSIS REPORT FOR PACKAGING:

in THE ORNL TUNGSTEN-SHIELDED CASK ADDENDUM 1 e

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J. H. Evans R. W. Mouring x.

Date Published: February, 1979 e

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' ABSTRACT?.:.

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GENERAL.INFORMATION....

l' 10.1-~ Introduction.. ;..:...-.................

1

.0.2. Package Desertiption 2

0.2.1.

Container description and modifications.

2 2

0.2.2'LOperational^ features....~.......-.....

2

'O.2.3 ~ Contents

[

0.2.4. Materials'of the modifications 2

'1.'

STRUCTURAL EVAi,UATION.

4 4

' 2.

THERMAL EVALU.ATION..

3.---CONTAINMENT. '..~.....

7 4.

SHIELDING..

7

-5.

- CRITICALITf.~.. -..

8 6.

QUALITY ASSURANCE...

8 REFERENCES...'.'......

9

APPENDIX A - Approval Docum2nts 11 APPENDIX B - As-Built Drawings.

15

' APPENDIX C -LTesting-o'f' Tungsten-Shielded Cask with Personnel

- Shield c.

21 APPENDIX.D - Certificate-of Compliance.. '

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BIl o.As-bu'ilt drawing'offthe'ORNL tungsten-shielded cask-i

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- As-built drawing of the personnel shield for the ORNL tungsten-shielded ~ cask........

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B.3-As-built drawing of'the shipping' pallet for the ORNL

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. SAFETY ANALYSIS REPORT FOR PACKAGING:

THE ORNL TUNGSTEN-SHIELDED CASK-ADDENDL3 1 J. H.-Evans-R. W. Mouring ABSTRACT Described here are the modifications of the Oak Ridge

, National Laboratory (ORNL) tungsten-shielded cask necessary when the cask is used to: transport materials of greater activity-and, heat load than those specified in the original Safety' Analysis Report for Packaging.(SARP) for the cask.

Also included are the data and do~cumentation to demonstrate that the cask complies with the regulations governing con-tainers in which radioactive and fissile materials are transported,'even under the previously stated circumstances.

1 0.

GENERAL INF0FJ!ATION 0.1 Introduction The ORNL tungsten-shielded cask was developed at the Oak Ridge National Laboratory (ORhl) in 1967; 12 casks were built and are currently in use. The design was analy::ed, and a Safety Analysis Report for Packagingr(SARP)l.was published in 1977 to demonstrate compliance with t

the regulations' governing containers in which radioactive and fissile materials are transported.2-4 It' has'become necessary to use the cask to transport contents :(Type B and large-qu' ntity radioactive materials) a which emit more gamma radiation and have higher heat-generation rates than those content's specified;in the original SARP. JCalculations, s

engineering-logic test results, packtging modifications or additions, aitd all related documents that demonstrate compliance _with the regulations

~

are presented in subsequent sections of this _ addendum.. Copies ~of the

' approval ~ documents'.are pr'esented in Appendix A.

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[0.2 ~ Package Description 0.2.1;'.' Container description and modifications EachLeask as described.in the-SARP has been modified only by the

! addition of'a 1-in. pipe welded ~to the lid to ensure position of the

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c contents. Also,'a tungsten' insert to provide. additional shielding, a

personnel heat sh'ield to' reduce. accessible. surface temperature, and a iskid to facilitate' handling'have been added. The package is illustrated in Fig. 0.1, and as-built ' fabrication drawings are in Appendix B.

The

weight.of the cask and insert is 404 lb.

The weight of the total

-assembly is-565.lb; that of the basic cask remains 381 lb.

The tungsten

. insert weighs 23:1b,.the heat shield 70 lb', and the skid 91 lb.

The c' enter of gravity remains essentially at its original location.

s0.2i2 Operational features

. Operational features of the cask remain unchanged except that the heat shield renders the four 3/4-in.-diam holes in the gusset plates inaccessible for lif ting or tie-down during transit.. The skid has pro-L

visions for forklif t-handling -of the package. -

0.2.3: Contents F

In addit' ion to-the contents specified in the original SARP, the f eask with insert, heat shield, and skid in ~ place will be used to ship

~

nonfissi1e radioisotopes in solid form with a maximum internal heat

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l'

' load of;50 W.

lThe radioactive materials will also be.1.imited by com-pliance with the external radiation levels specified its Department of.

L ff T'ransportation (DOT). regulations'. JAll radioactive materials will be in dM'

'special. form. containers, as described in the'SARP.

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. 0.2.4,'. Materials of the modifications

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Modifications;to the' cask include the addition to.the lid of a.

'l'.-1'n.. 'schP40,j stainless steel pipe capped;with a 1/8-in.-thick stainless

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s ste'el plate w'elded all around. LThe-tungsten insert is of'18.6 special

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grade' tungsten' alloy pressed and sintered

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.specified in Y-12 Technical Data Sheet No. 2.6.4..

The 1lx 1 x 1/8 in.' rectangular tubing and 16-gauge expanded sheet added -to' the personnel: shield are of carbon steel. The bolts,Jalso iof carbon steel, are' 1/2-13 UNC-2, 2-1/4-in.-long bolts.

All. components of ' the skid,1the ' plates, channels, spacers, clamps,

nuts, and bolts are of low carbon steel. The bolts are 1/2-13 UNC-2, 1-3/4-in.-long bolts.

1.

STRUCTURAL EVALUATION

For the purpose of structural' evaluation, the effects-of the per-

, sonnel shield and' skid will. be neglected, except as outlined in the following discussion. This represents a conservative approach because these components protect the cask and would have a cushioning effect in

any ' impact. The tungsten: insert and the effects of the weight increase attributable to it are. considered.- The original evaluations affected-are recalculated'in Table 1.1.and are referenced to section and page number.in the SARP.- All. stresses,' etc., are below the acceptable limits.

The impact' calculations were also made using the increased weight.

The changes.in cask' response are presented in Table 1.2.

Changes are small'and do not alter the conclusion reached in the SARP. The personnel

. shield makes the lifting lugs inaccessible for the tie-down; hence, this calculation was not made.-1When~in transit, the cask is secured by the

same techniques as conventional cargo without lifting lugs.

~

'2.

THERMAL EVALUATION

. The' increase in internaltheat load would cause the surface of.the

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cask proper, witho'ut. the personnel / shield, to approach lar slightly
exceed l the. normal _ operat'ional limit of 122*F specified in the, regulations."

. With.the personnel shieldL in place,J ehe shield becomes - the accessible.

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(surface,'and. temperatures are'well below the operating limits. During the{first week of October 1978, ~ testing was. cenducted' on a modified.

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. tungsten cask with insert, personnel shield, and skid in place

~ (Appendix C).. The. testing was conducted indoors with an ambient tempera-1:

ture of;71*F. :The cask'was loaded with a'47.4-W 1921 source and allowed to. reach equilibrium. The-temperatures. corrected for a 50-W source and

.100'F smbient temperature' are 110'F at the top of the personnel shield, 110*F at:the side of the personnel shield, and 115'F at the bottom of the personnel shield. Because the temperatures were too-low for signifi-

cant radiation heat transfer, the temperature corrections were made on

'th'e basis of' free convection alone. The corrected temperatures of'the contents are well below the special form test. temperature.2,3 The additional internal' heat load.would not significantly affect

-the results of the thermal accident (fire)2,3 because..as described in the original'SARP.I the cask approaches the fire temperature of 1475*F.

As a result of its small weight, the cask has little heat capacity.

3.

CONTAINMENT

. The containment boundaries for the package are not altered or affected.by these modifications.

4.

SHIELDING The shielding outlined in the SARP.is supplemented by the tungsten insert.. Radiation readings were taken on a tungsten-shielded cask loaded with a 47.4-W 1921 source (Appendix C).

The radiation. readings extrapolated for a 50-W source are 36 millirems /hr at the. cop of the

' personnel shield,. 25. millirems /hr at the side of. the personnel shield, and 5.3 millirems /hr at the bottom of the pers'onnel shield. The highest ra'iation reading at'a distance of 1 m was 2.1 millirems /hr. These-d creadings are well within the allowableLradiation dese-rate limitations

, of'the DOT 4

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CRITICALITY

1 Criticality evaluation;is not necessary because no fissile materials

~

-are to be transported in'this' cask'.

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' 6., QUALITY - ASSUlVLNCE s

[

. Engineering quality assurance procedures established by Union-

Carbide. Corporation, Nuclear din sion (UCC-ND), which comply with the guidelines' described?in Chap. OR.IMD 02XX'of the' DOE Manual,5 were used to

~

ensure the quality of the addition to the-package. The necessary modifi-cations to the' cask as well as the inspections needed to ensure compliance

~

..with'these specified modifications are outlined on the drawings in Appen' ix B.

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' REFERENCES.

~

A

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4 l1.

J. H. Evans ' D'. L. Le. vine, and R. - A.' Just, Safety Analysio Report fox' Packaging: The CRE hngsten-Shielded Cash, ORNL/ENGlTM-3 c

'(October 1977).

i.

2.. Code of Fedeml Regulations, Title 10, Part 71, " Transport of Licensed Materials;"'see'al'so. Fed. Aegier. 31, 9941-49 (July 1966).

~

3. T AEC Ahnual, vol. 0000, Pt. 0500, Chap. 0529, U.S omic Energy Commission,' Aug. 22, 1966.

7

~

4.-

Code of FedemL Regulations, Title 49, Part 173,' " Transportation";

-see also Fed. Regist. 33, 14920-31 (October 1968).

~

4

5. - DOE Nanual, vol'. - 0'000, Pt. 0200,- Chap. OR IMD 02XX (supersedes Chap. 0R IMD,0820), TN 0200-1, U.S. Department of Energy, Oak

- Ridge Operations Office, Oak. Ridge,_Tenn., Jan. 30, 1978.

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1 Appendix A APPROVAL DOCL'MENTS I

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TC.78-1 INTRA LABORATORY.CORRESP.ONDENCE.

OAK RIDGE NATIONAL LABORATORY June 13,'1978

~ Tos:

J. H. Evans

~ Subjects : Approval of Safety. Analysis Report.for Packaging: - The ORNL Tungsten-Shielded Cask,: Addendum 1 The draf t '(received' June 1,1978) of' the subject SARP has been -

reviewed by the Transportation Comittee. The SARP is approved for technical

. content and approach - for submission to DOE.- Comments from' individual

. members'.of the Committee 1have been forwarded for consideration.

$. IN. Ysts E. M. King Transportation Committee cc: - Commib't'ee ' Members ~:~

G.'H.

Burger

- J. A. Cox J.-H. Evans R. W.'Schalch1

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4r i s 6 I r ? Appendix C t .( e. TESTING OF TUNGSTEN-SHIELDED CASK WITH PERSONNEL o.'IELD x 4. 3 -f: a L/ - 9# h hI ~ i G 6 - L F n l, 4w {... 4 h ('. L: j' };o 3 k' p-A d . p-;. 4, - j',.- -m

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'n?- y a g + ,4 w;,,. ' 23-n 4.g C + ~ n i.lNTRA L'ABORATORYE CORRESPONDENCE: 'I ~ OAK' RiDGC NATIUH AL L ABORATORY LO. ~ ? N: s h ~ w \\ John'. Evans ( .Date: October'9, 1978 1To: ~ ' ' Te

x'

.From:E'

R.J Ex Schalch

' ::4 c

Subject:

-. TESTING: 0F. TUNCSTEL SilID.DED CASK WITH PERSONNEL SHIELD-D p .e, ' ~ ' LALTungsten Shielded Cask lwith_a~ tungsten insert was loaded with 8,320 euriesi(47.4 watts) of iridium-192 to determine radiation and tempera-l ture'measurementsLon~the personnel shield:(see ateached). n E . Tl'a radiation' measurements were made by Health Physics persont;el using ~ ~ .a calibrated-(9/6/78) Victorcen'Model 440. ~ . Reading Position Radiation, mrem /hr Top of personnel shicid= 34 e g . Side of; personnel snield. 24.

2 -

~

Bottom'of personnel $hield 5

l _ Highest 7rcading @;1_ meter 2 Thel temperature measurements'vero.made by R. E Schaich using three cali- - ~ ',

brated thermocouples andlSimpl1 trol Temperature meters at various points-on the personnel' shield after=the1 cask temperatures reached equilibrium.

+ $'g Reading Position'? Temperature, *F- [ 2 Top of3p'ersonnel shield: -75 t

Side of, personnel shield.

75: tBottom_of personnel shield 80. -.iAmbient temperature-71- ~, ,f. bb, j : l N -R. E <Schaich v.- M' 3RWSidtv .;? v i,,, ~ 2 - 'm.?,-., iAttichmentS r 2, %, i.O v. g 3s# y ~ y _, 4 / - Y a '. k[: r [ s, t w. 5 v~ ,.,.-b***- 4 z q A.* r g f,;, ,ev -..,. ,.[

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.a to. Cetamie Nwreer. j le. Re t.oa N. is suuos ioeatdatea No - l16. Page No. g ee Tota. No. Paget - 5 5597' l 2 USA /5597/BL(DOE-OR) -l 1 1 -2

2. PR$ AWOLE '

2a.. TMis cartitsave es se.,es to notistv secteas t 73 393a.173.394. I73J06. and 173 306 o' the oeoeremeat o8 Treanoortat oa Mareroown patews Res.coas t49 CP R 170-1991. 2b. x The secmaging ans coatears anscrbed en tem 6 neese raset's tne safety staaderes set forth *a Suecert C of T se 10. Code of Feoest Reev eteas. Part 71.-Pacnag.ng of Rad.oset.ve Meteres for Transport sad Teaanporteten of Radeact.w Meree a6 Wacer Corte4a ' n Coaditeas!* 2c. in.s sert +este does not ret. eve tne seas gaer from comsmence ve.th aay regaareereat of tne vaewatens of ane U S. Deporteneat of . Treasoorision or etwr son case reewater, seeas.n.. ace e.ae ene sowrarreat et ea, cowarry inrouen er.ato en.cn ene pecesee D ' e.14 he treaecorted. a:

3. Tn.s cert.e.cm.e ss.ee en ene on.s o# a wei,.

,s.: resort of tne neckage on.ea or son. atma-(3) Date: (1) Prepared Dy Miente and addsysst 121 T. tie saa ident.t.cateca of reoort or sooncaten a) Safety Analysis, Report for the ORNL a) Oct. 1977 Oak Ridge National Laboratory Tungsten-Shielded Cask, Report. Post Of fice Box X No. ORNL/ M /TM-3' . Oak Ridge'. Tennessee - 37830 - ~ b) Safety Analysis Report for the ORNL b) March 1979 Tungsten-Shielded Cask. Addendum 1, 4 coNotfioNS . eport

o. : 0WMM-3.. Addendum 1.

Th.s cert +f.cate 4 coao tiones vaca sne Mfene ol sne reew.esawars o' 5 cs. set 0 of to CFR 71 as soss.camie and tw cono e oas nn.f as a tem 5 te+on s S. Descr prica of Paceepas sas Author see Comeats, Yode % racer. F we Class, Ct'wr Caac.nor+s. saa Reesteaces. a. Packaging: . Tungsten-Shielded Cask 1 2(1) J Model:. (2)'

Description:

.^ - The packaging consists of a right circ'ular evlinder with a hemispherical bottom. It has a maximum outside diameter of 16-in. at the base. _ The cask itself has .an outside. diameter of 8-in. The overall height-is 15-1/4-in. -Inner cavity dimensions are-3.120-int diam. by.6-1/2-in.chigh. Shielding is composed of a 2" thickness' ol. isostatically 1 pressed and sintered tungsten alloy containing -~ 95: tungsten,3.57. nickel, and 1.5%. tron..with'a 1/4-in. type 304L stainless steel: cladding outside and a 1/8-in. type.304L stainless steel cladding inside. The gasketed lid consists'of a 150-lb. flange to which the top shield plug is ' attached'and is held in place by eight 5/8-in. studs and bolts..A capped 1-in.

pipe is welded to the underside of the cask lid to position the contents. The

.' gross weight of the basic. cask is 381 lbs. .. ~ 1 A tangsten insert, heat shield, and-skid are utilized for' shipping radioactive - ' materials having higher internal. heat loads and external radiation levels. -The gross weight of the' cask.~ insert, heat shield and skid is 565'1b. 2 se osia se nousace 'AM Z 5 & s - l en s.o.,at.oa os - FOR THE U.$.ofPARTVENT 07 SNGRGY - .is Addveen(of 00f tssi no tr*M pg 3.go.,,,,, um y,w g, gg g,% pf, U.-S. Department of' Energy ph %7e ,n'& 6 ' Post-Of fice Box E - i William H. Travis, Direct 3r 0ak Ridge. Tennessee 37830 ~ Safety and Environmental Control' Division 3 ~. 1 y 9" ',s. ~~(. ~ jy ' ~ f 3

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e r r .s ~ T(3)1-11.Deswings: ~ x, l."E s .,., n. . n.-, s, , *,-.A_ . i.. g 9 < The packaging-islas de' scribe'd and. fabricated.in accordance with4 X0ak Ridge National. Laboratory Drawings 'No.^ M-11575-Df-001-E- ~' ~ ..-g Rev.f2.jX3D11575-002,.and.X3D-11575-003-Rev. 3. - , ~ " L. cont,ents: e .. ~ A-i. -si (b[ Type.andFormofMaterials ~ ~ - x.- . tn I-Non-fissile [ radioactive materials.as solid"and 'in special fora.- ms ,. a.c ~ r '

(2)'. Maximum quantity -of material per' package may be a.large quantity

-. andJnot' to. exceed. 25 watts (of thermal decay energy without. the :

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~ insert heat shieldL and skid,and not to' exceed 50 watts of thermal ~- decay energy with the". insert, heat shield. and skid.. The radioactive ? contents will be'further limited by authorized external radiation s ' levels'specified in Department of-Transportation (DOT) Regulations. ~ m y.

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10. ;H. C. Claiborne 34.

J. N. Robinson 11.' R. L. Clark. 35-36. R. W. Schaich

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62. - W. A.' Brobst, DOE, Division of Waste Management and: Transportation,-

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64. ~R.EI. Elder, Chicago Operations office,'~9800 South Cass Avenue,

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A'.;W./Grella,=U.S. Department of. Transportation, 6th and D' Street, SW,~ Washington, D.C. 120590. .67.' C. L.EHanson, Lawrence Livermore Laboratory,'-University of~ 4 jCalifornia,:P_ost Office Box 808,iLivermore,' California 94550. 68s R. E.. Harris,'.-DOE,~0RO.- .69. R.-~J. Hart,' DOE,EORO. -70. ::J.;U._Langhaar,L E. 'I; du -Pont. de Nemours & Company, Wilmington, Delaware 419898.. 71.. Assistant Manager,.l Energy Research and. Development,' DOE-ORO . E. C.-Lusk,1Battelle Memorial' Institute, 505 King Avenue', Columbus, ,72. - c,' zChtol43201. .n 1 i 3~. .m,_y.,_y_._. ._e y - g. m .- +.,

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..9 H + i g,y ~ 130: 4 17'3._-jW.iGT O'Quinn,.-DOE,f Savannah' River Operations Office, Post ji ; EF ... l Office Box A, Aiken,-South Carolina 29801. 3 j742 R.;H.' Odegaarden,;NRC, 0ffice'of: Regulation, Washington,'D.C. "20545. -i75L IR.-W.GPeterson,UAlliedLCeneral Ndelear4 Services, Post Office: ..... Box 847,TBarnwell', South' Carolina ^29812.

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80-92.:-l Safety and Health Protection Branch,' DOE.10RO.-

~93-263. Transportation of Property' and Nuclear' Materials (25 copies -- -NTIS). ~ ' } J 4 a O [ ,I I 1 g ^- ,j' 2;J e x ? b 15., !)j il e s 'J. a 3 ;., y + ~.; n .. s ,}}

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