ML20006C180

Certificate of Compliance 6003,Rev 12,for Model M-130 Shipping Container

ML20006C180
Person / Time
Site:	07106003
Issue date:	01/31/1990
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20006C179	List: ML20006C178 ML20006C180
References
NUDOCS 9002070039
Download: ML20006C180 (8)

Text

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p u.s. esuctaan maeuLATORY 00tIRAIS$60N CERTIFICATE CF 03MPLlANCE ITi J Jh e'* ?t '

. FOR RADl! ACTIVE CAYERIALS PACKAGES '

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l. to gicata ea)meen 6003 12 USA /6003/B( )F 1

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' of Feeersi megunstions. Port 71J'Pechegmg and Transportation of med.oective Meteral."

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l D This sortificato eoes not foisove the consignor from comptence with any re,ivirovnent of tne reguistions of the U.S Deperiment of Tronoportetto I

appseemas seguestory opences. encluemg one government of any country through or enio which the packepe will.e transponed.

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U.S. Department of Energy-Safety Analysis Report for M-130 shipping I

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l Division of Naval Reactors container dated December 30, 1968, as i

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Washington, DC 20585 supplemented, i

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<oleinmaassa

'71-6003 l

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l ! > %*40'ete..one t.onei n.oi,,ii.ng tas.o iot.e-nio io era een ri. = e.,===. one

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I (a) Packaging m

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(1) Model.No.: M-130 (2)' Description f'

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The Model No. M-130 shipping container,is an upright cy1'inder 84 inches in I

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I diameter by 158' inches overall: height. lThe container walls consist I

L l of a finned'l-inch thick outer shell fabricated from e'ither carbon I

I steel},carbonsteelwithstainlesssteelclad,'orsolidstainless

[,I steel 10 finches of lead, shielding and a 1-inch thick inner pressure i

l vessel (fabricated from carbon steel clad with stainless steel). The r

topof-thecontaineriscostedEithiashieldedclosureheadwhichis

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bolted to the container and seals the press'ure vessel: An access l

l opening with a bolted sh,ield plug is provided in the. closure head for I

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i loading and unloading spent!fu,el.-

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I The pressure vessel has an inside diameter of'55 inches. The central g

I region contains a secondary heat exchanger (not used during shipment) l I

surrounded by 1/2 inch thick carbon steel backup cylinder 29 inches i

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in diameter. The annulus which remains between the backup cylinder I

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and the pressure vessel provides a space 13 inches wide and 130 inches i

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high for spent fuel. The spent fuel is contained in the-annulus by j

l module holders designed for the particular core to be shipped.

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The container has external penetrations to the pressure vessel for l

l l steam and water relief lines and a fill and drain line (which are l

capped during shipment) and a pressure sensing line which remains open I

to a pressure gage during shipment. The container also has penetrations

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I which do not open to the pressure vessel for secondary heat exchanger g

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lines (which are capped during shipment) and a temperature sensing i

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line, b

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I 9002070939 900131 I'

{DR ADOCK 07106003 PDC

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a lI P. age?2-- Certificate No. 6003 - Revision No. 12 - Docket No. 71-6003 I

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(a). - Packaging (cont'd) i I

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I (2) Description (cont'd)

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l For LWBR' spent' fuel shipments, the heat exchanger and' associated l

structures have been removed, external penetrations plugged and seal i

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welded, and an external shield and energy absorber added during l

l modifications.

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ThecontainerissupporteponR's[Eransportvehiclebyan"A" frame I

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structure. Grosp Weightsof*thb loaded container without its support l

i structure is appogximately 228,000 pounds". (,)

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I (3) Drawings-()

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The pack $iing is constructed in accordance with Genpral' Electric l

DrawingJosi4247E209, Sheet 1, Rev. R; Sheet,.2rRev./K;. Sheet 3, Rev.

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and 247E228,.Rev. F.

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' T; Shef t 4, Rev.JlpSheet 5 of 5, Rev. F,/f_f l

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.For i.WBR spent fuelishipmentsfthe container has been modified in I

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I Shest!2 Rev. E an~d'snfeiternal energy \\ absorb)er added irkaccordanc l

accordance with Westinghouse Elect'ric Draitiri 1176J48,' Sheet 1 Rev. G, I

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with Westinghouse? Electric-Driw'inbl525E32 pro. A.

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I (b) ContentsQ,i W

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Type end forin'of,;% be%g{ l,i t d matriafjf l

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i Irradiated fuel assemblies,cact va e corrosion products and structural i

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parts containing'up to;40fgallonssof, residual contaminated water. The l

I fuel assemblies and structural.~ parts are'of the fo116 wing types:

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I (1)

S3N/S4Wfuelsubassembliesofcorec,tNs',2.

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(ii)

S5W fuel modules of core; types 12 or 3.

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4 97 3, i

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SSW corner fuel modu 1~s of core types 2 or 3.

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(iv)

DIG fuel modules of core types 1 or 2.

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(v)

DIG removable fuel assemblies of core types 1 or 2.

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I (vi)

SIC /S2C fuel modules with control rods.

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l (vii)

SIC /S2C peripheral fuel modules.

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(viii)

S3G-3/3A fuel module with or without control rods.

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(ix)

SAD cell.

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3-I 1 Pag)3L-CertificateNo;6003-RevisionNo.12-DocketNo.. 71-6003 l

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(b) Contents (cont'd) l l

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(1)'Typeandformofmaterial(cont'd) l l

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L (x) S3G-3/3A irradiated thermocouples and thermocouple cases, i

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l (xi) S8G full size fuel cell with or without control rod.

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l S8G partial size fuel cel (l f il hy l I

(xii) with or without control rod.

I S5W-4Arecoveglhiadiae d es with control E

(xiii)

rod, e(

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S7G reh(er/

l able irradiated fuel cells.

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I (xiv)

(xv) D2W T il cells with control rods.

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(ifuel with or without c9

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1 (xvii)[ATC fuel modules with 9t;Without/cgntrol rods.

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1 (2) Maxin[mquantity t ial er ackage O

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-fuel dis k

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(ii)()12 fuelis'ssmbli)sias describedVii5 b)(1)(ii) orffuel i

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e assemb1'ies'asldescribedLinl5byl)(i

'and 4 fue1* assemblies l

'asdeseribedjs.5(b)(1)({if)(.,g"Ryd) j '

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6 fue~1-asse~mblie(sias/ escr;ibedxinJ5(b))(1)(iv)(and i

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i (iii) 4fuelp.,fssembliesas"d,escribed"in5(b)(1)(v)h,""

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(iv) 9fuelassembliesasdescribedin5(b)(1)(vi)and l

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8 fuel assemblies as described in 5(b)(1)(vii).

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I (v) 10 fuel assemblies asfde,scribpd.in ~5(b)(1)(viii).

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(vi) 9fuelassembliesasdescribedin5(b)(1)(viii)and j

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one fuel assembly as described in 5(b)(1)(ix).

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(vii) 9 fuel assemblies as described in 5(b)(1)(viii) and I

l one structure as described in 5(b)(1)(x).

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I i-Pag'e_4 - Certificate'No,'6003 - Revision No. 12'- Docket flo. 71-6003 l

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(b)

(2) Contents (cont'd) l 1

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(viii)

4. fuel cells as described in 5(b xi);or l

I 2 fuel cells as described in 5(b xi))and l

l 2 fuel cells as described in 5(b xii.

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(ix)_6.fuelassembliesasdescribedin5(b)(1)(xiii).

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i (x) 8 fuel cells as described in 5(b)(1)(xiv).

(xi) 4 fuel cells a6dIEsc bed (hA(ky)plus n

'2 corner el/ cells or 1 RFA fuel cell. j i

t 4 fuel)modulesasdescribedin5(b)(1)(xv)b (xii)

(xiii) 10 i 1modulesasdescribedin5(b)(1)(xvii.-7 '8 d

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cf, ts shalHhfurther limited by /N)/ quirements as follows:-

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(3) Shipmep/

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i (i)[Shipmentofitontentsspecifiedin5(b~)(II')(iv)andfii(b)(1)(v)and i

I T6fter shutdowniand{$ii) Ahall' b(de' cay?h' eat load not,to exceedl 1.imitedin6(b)'(2) made',no earlier tAap 75 days I

shalj have a I

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(ii)(Shipmentlof. conte".tsfspeciffedtin(5(b)(1)(vi) andl5_(b)(1)(vii) and i

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I limited?in15(b)(2)(iv) tha'11:be'made in a' stainless # steel M-130 I

, container ~andshall:.hav'e'aldecaysheat;1oad~notto* exceed 18,960

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(N Btu /hr periship{mentyQ QMdLr@f ( iii)t 5(b)(1)(ix) a I,

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,g fg uf Shipmentofcontents'specifiehin:5(d)(1))v5(b)(1)(x)andlimitedin'5 i

I (iii) l I

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I shal1<be made at a time hfter shutdown as determined from Bettis l

l Atomic'powerLaboratoryreportWAPD-0P(PP)S;4401datedJune 29, 1979 i

and shall'have,a decay heat load not,to exceed 28,620 Btu /hr for the i

j hr fKthe prototype core.

i shipboardcore}nd.30,000 Btu (n I

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I (iv) Shipmentofcontentsspecifiedin5(b)(1)(i),5(b)(1)(ii)

I shall be made no earlier than 72 days after shutdown and shall l

l have a decay heat load not to exceed 33,500 Btu /hr per shipment, i

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Shipment of contents shecified in 5(b)(1)(xi) or 5(b)(1)(xii)

(v)

I as limited by 5(b)(2)( ii) shall have a fully loaded container heat load not to exceed 15,400 Btu /hr per shipment.

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(vi) Shipmentofcontentsspecifiedin5(b)(1)(xiii)andlimited-in i

5(b)(2)(ix) shall have a heat load not to exceed 23,800 I

Btu /hr and shall be made no earlier than 92 days after shutdown.

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us nucmn nrsudaeny comwom l Annu j

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l Page 5 Certificate No.16003 - Revision No. 12 - Docket No. 71-6003 I

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l So (b) (3) Contents'(cont'd) 1 I

I Shipment of contents specified in 5(b)(1)(xiv) and lim'ited in l

(vii)

I 5(b)(2)(x) shall have a heat load not to exceed 22,400 Btu /hr l

l and shall be made no earlier than 122 days after shutdown.

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(viii)

Shi ment of contents specified in 5(b)(1)(xv) and limited in t !

5(b (P)(xi) shall have a heat load not to exceed 19,100 Btu /hr I

I and shall be made no earlier than 420 days after shutdown.

(ix)

Shimentofc66thts pec id 5(b')(1)(xvi)andlimitedin I

5(b (2)(xiikshall have a heat-loadht,to exceed 6,000 Btu /hr I

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and shal1Je made no earlier than 50 days lafter shutdown.

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I (x)

Ship' ment of contents specified in 5(b)(1)(xv(Is)andlimitedin.

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5(b)(2)(xiii) shall have a heat load not to exceed 27,400 Btu /hr i

ande shall'be made no earlier than 195 days'iftershutdowr..

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FissileClalss(/'Q

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gf (III NR, I

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Maximumnumberofpackageshsp/er shipment:

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l -6.'Forshipmentstinvolvingsthe5 contents-sp"edifieds n5(b)(1)(ii)or5(b)(1)(iii)

I the Model No.I -130 package"shall be inspected'totverify,that boron poison l

-platesarein(themoduleholde~rsWlQ[P]ffh$pMOYhU d'fiM F d

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l Forship(mentsinvolvingthecontents;specified(in5(b)(1)(viii),15(b)(1)(ix)or I

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5(b)(1) x) the thermocouples;and[~thermocoup~le casescif. included or the vacant I

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moduleholdershallbelocatedtinthefmid-positionsofeithercadeandmodule I

i holder assembly, y (",

b G //MQ 4d j/)

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8.. Shipments shall be made in the dry con' ition, except for residual water as l

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limitedin5(b)(1),5(b)(3)(v),and5(b)(3)(vii),

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Container number three (M-1301 ) has been modified by adding two 4-inch thick I

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by 8-inch wide steel plates welded'bstween fins 25 and 50 and between fins 110 I

and 135 at approximately 14.75 inches from the bottom of the container. The l

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-cooling fins in this localized area are removed to permit attachment of i

l the plate directly to the outer shell of the container, i

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ii 11 0. Container number four (M-130-4) has been modified by adding a 2-inch thick I

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by 4-inch wide steel plate welded between fins 32 and 49 at approximately l

I 18.4 inches from the botton of the container. The cooling fins in this j

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' localized area removed to permit attachment of the plate directly to the i

l outer shell of the container.

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iI 11. Containers M-130-4 and M-130-10 may be used for the contents specified in i

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5(b)(1)(viii)and5(b)(1)(x)only.

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l 12. Container M-130-11 may be used for NR-1 shipments only.

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conomous toonunued) l l

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I. Pag'e 6L-Certificatb No. 6003 - Revision.No. 12 - Docket No. 71-6003 l

13. For shipments involvin9 the contents specified in 5(b)(1)(xvii) which do not l

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containafullcomplementoffuelmodules(i.e.onepositionisoccupiedby I

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-either.two flux thimbles or a vacant fuel module holder with pocket shield I

I plug),'that position shall be located in the middle module holder of either i

l half of the cage assembly.

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l 14. Expiration date:

December 31, 1992.

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j REFEREN_CES,

l l Safety analysis report for %139 stDp)n Iton i er

48-703 dated December 30, l

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(

l 1968.-

l 1

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I Supplements: NavalReactor))lettersA#2256datedFebruary 24,4969 and Gi1931 dated I

l I March 3,-1969;' General-Electric Company letter DNP-74520-526 dated April 3, 1972;-

l Naval Reactors letter G#3207 dated April 27, 1972; General Electr'ihtompany letter l

ONP-74520-528 dated April 28L 1972; Naval Reactors letter Gf3250' dated June 6, 1972; i

l General Electric Company letterse0NP-74570-635 dated OctoberJ25,1972j ONP-74570-654 l

i I dated Deceniber 4,1972f ONP-14570 '666sdated December 12,49721 ONP-74570-682 dated l

l I

i l January 12,1973; OhP-74570-698 tdat'ed 'Jpnuarf31,319,73:p0NPf74570-687(dated February 6, I

26;$1973; DLGN-85570 954.Ma~ted September-24,1973;

-.1973; ONP-74390-65' dated Marchdatfdl. January 10;?197(;'/Nava.1 Reattor l

I l DLGN-85570-901 1974; General Electrfc Company letters 0LGN-85570-924, dated' February 15o1974; DLGN--

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l 85570-923 dated MaFch 6, 1974;i DLGN-86570-969 datedHay;24;1974; l

Nava_% Reactors I

1975PGeneralf Electri.c Companyletters[0NP-74340-1 l

letter G#4991 datedgNovemb' d 25 e

I 'JTT-73 dated December 17,1975i,CGN-85570-1145: dathd : September 9,1976;"CGN-85570-I I ;1146 dated September (10,1976f'CGN-85570j1148 datediseptember 14,1976;2 Bettis.

l

~

l ~ Atomic Power Laboratorbletter3APD-R(K)-1378 : dated:Augusti30,1976; WAPD-0P(PF)S-l Naval;Resc' ors, letters 1G#61977 dated July,13,71979; G#7136 I

t 4401 dateu June 29, 1979; l

l dated March 17, 1982; Haval ReactorsYletter' G#7022sdated July 14,(1981 and WAPD-LD-l 4

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(CES)SE-181 dsted September,1981; WAPD-LP(CES)SE-96 ' dated February',1982, WAPD-LP-I l

.(CES)SE-170-dated July 1981';< Naval Peactorstletter G#7160-dated May 18, 1982; Naval I

~P,eactors letter G#7582 datedtSeptember 7,1983; Naval Reactors 31etter G#C87-5692 dated l

l l September 2, 1987; Naval Reactors, letter G#C87-5689 dated September 23; 1987; and i

Naval Reactors letters G#C87-8008 dated January 19, G#C88-5931 dated May 12, and l

i l G#C88-5961 dated July 25, 1988. Naval Reactors letter G#C89-2863 dated i

I August 11, 1989. Naval Reactor letter G#C8962825~ dated March 29, 1989.

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l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

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JMAj7 f/

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Charles E. MacDonald, Chief I

Transportation Branch l

l Division of Safeguards and i

Transportation, NMSS l

i l Date:

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o, UNITED STATES E

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NUCLE AR REGUL ATORY COMMISSION t

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APPROVAL RECORD H-130 Shipping Container Certificate of Compliance No. 6003 Revision No. 12 By application dated March 29, 1989, NavalReactors(NR),U.S.Departmentof Energy, requested an amendment to Certificate of Compliance No. 6003 to permit shipment of ATC irradiated fuel modules in a Model No. M-130 irradiated fuel shipping container.

Because. the maximum loaded package weight for the ATC irradiated fuel modules is less than the maximum weight currently authorized for Model No. M-130' packaging and contents, the review was limited to the evaluation of the ATC irradiated fuel modules during normal and accident conditions of transport.

The application showed that the fuel would not break apart and that there would be no significant rearrangement of the fuel assemblies under normal and accident conditions. The staff agrees with the structural analyses included in the application.-

The applicant performed analysis to establish the subcriticality of the ATC irradiated fuel when transported in the M-130 shipping container. The analysis addressed both normal and hypothetical accident conditions. The Monte Carlo computer program RCP01 was used in this analysis. The neutron cross sections used have successfully calculated relevant naval reactor criticals with the RCP01 program. An axial variation of the fissile content of the fuel was included in the analysis and various conditions of flooding were considered.

The analysis established that under the proposed shipping conditions, the ATC

. fuel modules are subcritical without the benefit of control rods even at the most reactive time in life of the most reactive modules.

In actual shipments, however, most modules will have the control rods secured in place which will increase the margins for subcriticality.

The decay heat load of the contents has been limited to 27,400 Btu /hr for ATC fuel modules. This limitation assures that the maximum package surface temperature does not exceed 180*F (the limit for exclusive use shipment) for normal conditions.

In order to assure that the heat load does not exceed 27.400 Btu /hr, the ATC fuel modules cannot be shipped earlier than 195 days

-after shutdown.

The applicant used a finite element computer code, TRUMP, to predict the package's thermal behavior under accident conditions. There was minimal lead melt and no damage to the ATC fuel. The maximum pressure calculated under accident conditions was approximately 365 psig. This assumed that 40 gallons of residual water was left in the package after loading. The package is designed to withstand 450 psig, and each package is tested to 525 psig.

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' Containment is provided by the Model M-130 package and the cladding of the ATC fuel. The fuel cladding forms the containment boundary for fission products.

-There are no penetrations in :he fuel cladding. The applicant has analyzed the performance of the ATC fuel under normal and accident conditions, and has concluded that there will be no release of fission products if the internal heat load.is limited to 27,4C0 Btu /hr.

Containment for corrosion products and crud is provided by the M-130 package.

The applicant assumed that the M-130 container vent line could be sheared off during a one-foot side drop or during a thirty-foot side drop. The vent line would not be sheared off under a one-foot drop onto the bottom end of the cask, the case for which the lacksge was evaluated for normal conditions of transport.

The staff agrees with tie applicant's conclusion that a one-foot side drop would not be a " normal" cordition for a cask as large as the M-130. Even if the cluded that the release

-ventlineweretobeshearedoff,theapplicanthascog/hrbasedonexperimental rate under normal conditions would be less than A x10~

ventingmeasurementsonthreeloadedM-130contai$ers.

In those tests, the material released was limited to crud and corrosion products adhering to fuel cladding. No fission products were detected in the material released through the vent.

Tests by the applicant on similar fuel cladding indicate that only 0.10 percent of the crud or corrosion adhering to the cladding would be loosened under accident conditions. Since the applicant has demonstrated that the fuel cladding integrity is maintained under accident conditions, any release of material under accident conditions would be less than an A2 quantity.

-With the assistance of the SPAN computer program, the applicant showed that the external radiation dose rate would not exceed the applicable regulatory limits. The shielding analysis included both normal conditions of transport and hypothetical accident configurations. The dose rate results showed the contribution from both gamma rays and neutrons. A comparison of the applicant's results with the representative staff calculations shows the applicant's analytical method to be acceptable.

The NRC staff concludes that the amendment meets the requirements of 10 CFR Part 71.

w CTiaries E.

acDonald, Chief Transportation Branch Division of Safeguards and Transportation, HMSS JAN8119e Date:

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