ML20059N116

Application for Renewal of Certificate of Compliance 9049 for Model GE-500

ML20059N116
Person / Time
Site:	07109049
Issue date:	09/28/1990
From:	Stein S ADVANCED MEDICAL SYSTEMS, INC.
To:
Shared Package
ML20059N093	List: ML20059N092 ML20059N116
References
NUDOCS 9010100122
Download: ML20059N116 (59)

Text

{{#Wiki_filter:, ! 'r$dvanced MedicalSystems,Inc. 121 North Eagle Street Geneva, Ohio 44041 l G16) 466-4671. TWX 4332135 ATC UI FAX (216) 466-0186 ? Consolidated Application for Renewal of Approval of Packaging for j Radioactive Material L Docket 71-9049 for o U.S. Nuclear Regulatory Commission Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Washington, D.C. 20555 l t \\f Submitted by f, SherryJ.'/tein Direc or Regulatory Affairs 1 September 28, 1990 i i 9010100122 900028 PDR ADOCK 07 : *049 C '?DC 5

49 ~ i 1.0 General Information -1 1.1 Introduction The model GE-500 shielded shipping cask is designed for use as a type a package for radio-active material shipments. 1.2 Package Description 6 1.1.2 Packaging The model GE-500 shipping cask basically I consists of the cask, a base, and a protective jacket. It has a jtross weight of 8100 lbs (the cask weights 6300 '.bs). Reference drawing 106D3870 in Appendix 1.3 for a view of the complete package. l a) The Cask is 28 inches in diameter by 29-3/8 inches high. It is a lead filled stainless steel weldment. The outer shell is constructed of k inch stainless steel plate, with a % inch bottom plate and a 1 inch top flange. The cavity is 7 inches in diameter by 7 inches deep. It is constructed of t inch stainless steel plate. The cavity is shielded by 10 inches of lead on the sides and bottom, and 11 inches of lead on cdp. q The cavity is penetrated by a inch 0.D. x 0.065 inch wall stainless steel tube gravity drain s line, running from the center of the cavity bottom to the side of the outer shell near the cask bottom. It is closed with either a fusible lead cored hNPT hex head brass pipe plug, or a solid stainless steel plug. s NOTE: Advanced Medical Systems may, at its discretion, permanently close and seal the drain line for this container with no interference to its structural properties. There are two diametrically o aposed lif ting ears welded to the side of the casc. .I The cask lid is a lead filled flanged, stainless' steel plug. It consists of two right cylinders of H decreasing diameter, one 12 inches ~in diameter by 6-5/8 inches high, the other 9-3/8 inches in diameter by 4-3/8 inches high. A lifting loop, i inch in diameter, is located in the center of the lid top. The lid is held to the cask by six equally spaced 1 inch-8-UNC-2A steel bolts. Reference drawing 212E246 (, in Apaendix 1.3 for a detailed view of the cask assem>1y. A silicone rubber gasket bonded to an e 1-1

i 'ik. e aluminumbackupfid. late provides a seal between the cask and its Reference drawing 129D4690 l i in Appendix 1.3 for a detailed view of this seal. b) The base is a hollow cylindrical steel weldment ] with a \\ inch square bottom plate on an I beam frame. j Overall it is approximately 47\\ inches square by 7 inches high. The cylindrical collar is 29-t inches in diameter by 3 inches high. It houses two sets of 1-h inch steel angles separated by a 5/16 inch steel mid plate. The cask rests on these angles. There are two diametrically opposed tie blocks welded to the base, designed to accept the jacket attachment bolts.

• Reference drawing 106D3855 in Appendix 1.3 for a detailed view of the base assembly.

t c) The protective jacket is a steel weldment, basically a right circular cylinder with open bottom i ~ and with a protruding box section diametrically across the top and vertically down the sides. It is double 5/16 inch wall construction, with a 1 inch-i air gap between walls. Overall it is 33-3/4 inches outside diameter, 40-3/4 inches wide by 38-7/8 l inches high across the box section.i>A steel flange is welded to the outer wall of the'open bottom. i There are four gussets welded to the flange and outer wall. There are two rectangular lifting loops j located on the top of the box section at the corners. l These loops are of welded construction. There are two 1 i tie.down ears welded to the sides of the box section. These are diametrically opposed, 2 inch thick, with a 1-inch diameter hole. The protective jacket is bolted through its

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flange to the base using six 2 inch bolts. The jacket'has slots along its bottom periphery and in the box section under the lifting loo allow air circulation for cooling purposes. ps to Reference drawing 706E790 in Appendix 1.3 for a detailed view of the jacket assembly. 7 1.2.2 Operational Features Not applicable.

• 1.2.3 Contents of Packaging

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.o ? 2.0. Structural Evaluation j 2.1 Structural Design 2.1.1 Discussion The principal structural members of the ?ackage are the protective jacket, the cask, and the aase. + The jacket and base are steel weldments. The cask is a lead filled stainless-steel weldment. These components are held together by bolts. A cross sectional view of the package may be seen in figure 1. ) NW/l [ ] \\ / l %= =. ./ n ll l l C ll ) j u 4 I 11 a 1 ll 3 n e il li n i; r i a,-n,, ni~n3igogn,,,uginnun////om m,no m n.e3 w,,..I 5!. F 3. Figure 1 .e 2-1

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x e. o..... A 2.1.2 Design Criteria I l' The design criteria considered for the structural evaluation of the package are those that meet the requirements of 10CFR71. 2.2 Weights and Centers of Gravity i For the-model GE 500 cask, the following data is applicable: Weight of jacket, covers and bolts 1150 lbs.. Weight of base 650 lbs. Weight of cask and lid 6300 lbs. (lid weighs 400 lbs.) ..ic ,j Total 8100 lbs. The center of gravity of the. complete package is located 24 13/16 inches from the bottom of the package, or just above dimensional center. h '- "~ - s /, I

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2.3 Mechanical properties of Materials ~- A242 Steel A 1 Reference I 4 Shear Strength 67,000 psi 1 I Yield Strength 46,000 psi 1 j C1020 Steel Shear Strength 75,000 psi 1 Yield Strength 48,000 psi 1 i 302 Stainless Steel Shear Strength 90,000 psi 1 Yield Strength 40,000 psi 1 1 i Carbon Steel Bolts 2"-4h" UNC Grade'5 2 Cross Sectional area ?. 5 ' in 2 Minimum tensile 90,000 psi-2 strength tr ~( Yield strength 58,000 psi 2 References , ;. f ' f

1. Materials Selector 1974 Reinhold Publishing Co. Inc.

2. Fastener Standards, 5th Edition, 1980 i

Industrial Fastener Institute .j

i Y

ll 2-3 L [ ,...4 m..

2+ c - 2.4 Gnn7ral Standcrds for All Packegas, i 2.4.1 Chemical and Galvanic Reactions 1 y There are no components of'the packaging or its contents-which are subject to chemical or i galvanic reaction. The package construction is of steel and stainless steel. The only chemical 3 material in use is exterior paint.. i 2.4.2 Positive Closure i f1 The package closure system consists of a j series of bolts that must be removed before the Protective jacket can be removed. A second series of bolts must be removed in order to gain access I to the cask cavity.. 1 2.4.3 Lifting Devices Attached to the protective jacket is a pair of lifting looas. These are designed to enable a fork lift truc< to pick the jacket off the base and cask. They are not intended for use to-lift i the entire package or for tie down purposes, and l are rendered inaccessable during transit by re-movable covers. ( In normal practice, the package is moved with a fork lift truck. In the event that an overhead pickup was necessary, the tie down ears could be utilized for lifting the entire package. These. ears are located on opposite sides.of the jacket, approximately 7 inches below the top surface. They are 6"H x 3i'W x 2" thick with a lh inch hole. Reference drawing 706E790 in Appendix 1.3. The t 3 j_ .following calculation will demonstrate that these ears have been designed with a minimum safety factor of three. h O i l m 2-4 p-m.,,..,,. e... - - v ~..._

l Ji" H ^ f 1 6' P 3'/[-H Figure 3 ~ S=P where S = unit stress in psi A- .P = load in 1bs. (total package weight) A = net area at cross segtion con- ? taining the hole (in ) z i S= 8100 lbs ( 3.5-1. 5-) ( 2 ) = 2025 psi L 1 Yield strength for ASTM C-1020rCarbon Steel = 48000 psij k Safety factor =. yield strent;th (psi) 4 stress-(psi, j SF = 48000 3.7 2050 = i

3 The welds used to attach the ears to the jacket will next be analyzed.

The ears are attached.co the jacket with two'6-inch x h-inch fillet welds. Each weld throat l' diameter is 0.353 in.2 (he effective weld area T ? is therefore 2.118'in 6 in. x 0.355 in) per weld. The standard working stress for fillet welds is 11,300 psi (Ref. American Welding Society code for Fusion Welding). Therefore, 1 each weld can withstand a load of 23,933 lbs 2 l (11,300 psi x 2.118 in ), and each ear can 3 1 withstand a load of 47,867 lbs. The safety factor is 5.9 for each ear. i 1 2-5 1'. I.l - f-] a t

[l [_ af ' Il .a v \\, o z.; ',h 2.4.4 Tie down devices I! There:;are two tie down ears' attached.to the jacket, previously-described in 2.4.3. The following i analysis'will= demonstrate that these. ears.will comply; with the requirements. =The tie'down ears have been designed so.that' failure-l 1 -of the ear ~under excessive load:would not impair-1 the ability'of the' package to meet the'other require-, ments of 10CFR71. This feature has been achieved by: using a less-strong carbon steel (C-1020) for the ' ~ ~ ears than that used for the jacket shell-(A242). Therefore, damages should be confined to the ears.- 1 i y The following assumptions are made for-the analy' sis:- i (refer to figure 4) 4 1. .The 10g longitudinal load is supported-by. ~ tie down lines 3 and 4.

)

2. Thec5g transverse loa'd is supported only by lines-1 and 4 since lines 2 and 3 will not l -I -support compression, d .1 r> . /% I-1 \\ [ .f m 29 r-- I 1 h T .g O r fy i e z a e a I 4 / (a) (b) Figure 4 E-4 1 2-6 4

+ 1 E E 4 J l } '49.- xw -1 3. The 2g vertical' load will'.beLsupported l ' 7~ by ' lines :. l' and 4., -l 3 ci ) r - 4. Each tie-down device.shall be capable ofi supporting the following loads: 1 Sg - longitudinal direction, 5g = transverse: direction. -o Sg = vertical direction -i 1 =i n n -hl) hf-z, }f c 2s L / '.s. r 39 56' I E '(a) (d) ( 3 t Y .i ~ 6 ., = s G. (b) (c) 1 i Figure 5 o. 5. Assume weld is weaker than steel. 6. The forces.are considered to act.through the center of the drilled hole (figure 5). t k. i I: 2-7 e y'- 'i 4 l-6- e

I a t . ; ;ec g' The resul. tant' force on the tie-dcwn device - was broken down into its: component parts and'then the weld stresses were found. / M ] .. ~ ~ 2 ~ / N / L ~ t i.h g,. :,....,s'.? N / i: .g.. - i % g h g N ,/,Q N \\ w R s s w -( 4 4 j '(a) (b)- l [ I a -i z / / W . vf*,y / \\ ? ~ Y dl/, ' ' f ' " g ..u l -( ^l (c) Figure 6 k, ~,. Y.. 2-8 l x a

+ 3, + j l a) : Bending stress due to'the longitudinal force-(Refer to fig.6b) i f-S - 3TPL-m >B z .1 2

h (3T -6Th + 4h )

i-T - 2.0 f 1 P = 5 x 8100 lb = 40,500 lb L =11.5 in 1 = 6 in I h =-0.5 in S = 3(2)(40500)(1.5) B 6(0.5)[3(2)2 6 ( 2 )(0. 5 ) ~ t '4(0.5)2]- S ' - 17,357 psi B _t m b)' Shear stress due to the lorfgitudinal force (Refer to fig. 6b) (- -) S = P, ') 8 2h1 [ S = 40,500 8 I 2(6)(0,5) S = 6750 psi 3 c) Tensile stress due to transverse force (Refer to fig. 64) S =P T (h1 + h I1 2 P = 5 x 81,00 - 40500 lb h1=h2 = 0.5 1 - 6 in Y 2-9 .... ~. -....- -. -.

A g e !.I ~..* t l j.'<e/ti: l / 40,500 y ..S = t. t 'T a (0.5 + 0.5)(6)- 1 .i S -.= 6750 psi-9, -: T + i e m d) Bending stress due'to: vertical force: (Refer-to fig '64)' 4 S' - 3PL r B 2 e bl. D',',' P 1 2 X 8100 = 16,200 = 1.5 in. 6 L = V;, h 0.5 in. = 1 6 in. = 3(16,200)(1.5) S c 3; B (0.5).-(6)2 t., e> t S = 4050 psi S. B' 1 e) Shear stress due to vertical force (Refer to Fig. 6c) S =P l 3 n 2h1 \\;L S - 16,200 S 2(0,5)(.6) 4, I.: S = 2700 psi 'b i, S ? -i l-O i.

e.

p. 8 2-10 in; Ie 1 e d l '.m v h.f,,/[i, ! . i: 5 m.-pe co,o me-em e * = " + - - i

x , ' y _,4 ' - .._..'.t','+' l " 1..- A free-body isometric diagram of~the tie-down. ~" ..i device shows-the-following stresses: e l-D' .g. \\ @l 17357 psi 1- ')(r Q 6750' psi .f 5G' j j5 6750 psi ,Y 4050 psi-w x ~ 2700, psi i,, F. W l 1 4; 3,,en G H .g Figure 7. A unit cube near point.A, the location of the-. highest stresses, shows the toep,1 stresses and' their. direction. h.Sy .] i .SF l \\ j / i p-Figure 8 h The stresses from Figure'7 are: S = @ = 6750 psi l X 1 S = @ = 2700 psi 8 Y S =@+@+@=28,157 psi' ( The cube is loaded with normal stress (S ) e ; 2-11 T,.. t i 4l t i_

j..v a v e andishearing stress (S ) in one plane and a shearingstress-(S)oX1yinaplaneatright i y angles'to-the first plane. When considering the plane of the shearing stress-it can be shown.that the resultant shearing .9450. psi.g) acting on the face of the plane-.is-stress (S i ,1,. L 675*p ~ 4; J7er1< =. y' L hn ' ll, s i yP

• w a

~ a my-Figure 9 d f) Maximum and minimum principal ~ stresses 4

y

.in the tie down device 1 Maximum -{ S "'8 8 ' S 1 Z + B + S 1 I 2 3 . w g 28,157 psi-j S .S Sy+SX = 9450 psi 14,080 + [(14,080)2 + (9450)2) h j{ = 3 S = 1 8 8.93 x 10 )b-7 14,080 + (1.-98 x '10 u S = + 1 14,080 + (2.873 x 10 )h 8 S = 1 u,;, 14,080 + 16,950 S = 1 31,030 psi S = 1 L y> 4;

• 2-12 i.

t I r1- ,1

c:

y l

s .g*..

t A/

Minimum I (S )2]I l S

• SE

'I + ~ 2-S $2 '2- .c 3 7.. 2 - 14,080 - 16,950 'I S: .S = -3870 psi 2 Factor of safety-(weld) = 43,000(185)* 31;030 F.S. = 1.18 I <e

• (.85 = weld - joint.: efficiency) 6 It may be seen from the above that'the welds-

't j. attaching the ears:to the; jacket will withstand. l the static force requirement. It'wss shown-in 4 2.4.3 that the ear itself would witustand much ~- greater forces. Therefore the tie down devices; meet the requirements of 10CFR. 1 2.5 Standards for Type B and Large Quantity' Packaging 2.5.1 ' Load Resistance 9) .( '(' The following analysis will show that the' package, if regarded as a simple beam supported at its: ends ~' L along.any major axis, can support a. uniformly-dis-j. tributed lo.ad equal, to five times :its fully loaded weight.- For the purpose of this analysis,,we will consider the package as an open ended cylinder,- L neglecting any interior supports. ) To calculate the load resistance, the maximum load per unit length is determined by. dividing the shortest side'by the total package' weight. For this package, the worse case load would be the'- package load distributed along.'the height of the jacket outer shell. l 3 ~ l Load = 8100 lb = 231 lb/in 35 in R For 5 times the load we have 231-lb/ inch x 5 or 1155 lb/ inch. Calculating the bending stress on the jacket for uniform loading: j h 2 Mmax = WL 8 L where Mmax = bending moment (inch - lbs) { e y 3 2-13 u. 'l C. [ 3 ~. .. = -. ~.

+c riiN4 a a

~"*

~ W = load-(1bs/ inch)

x?

o L = length (inches) i

Reference:

. Design of-Weldments - James F. i Lincoln-Arc Welc;ing Foundation 1968 page 7.: 1 y Mmax = 1155 lb/in'(351n')2-176,860 inch-lbs 8 t The stress due to bending 11s: d S = _M_C. i 4 : I where 1 ?. M = bending moment (in-lbs) o 4 ~ I = moment.of inertia of section~(in ) . C = distance from neutral axis (in) 'l

Reference:

Design of Weldments - James F. ~! Lincoln _ Arc Welding Foundation 1968 pag 2.6-1 \\ r> (, C for a cylinder is.32D I p )i (D" - d")- 1 where D = 33.125 t m d =.32.625 C - 1060 1060 1 ~ r I 3.14(1203,992-1,132,927) 3.14(71065)=.00475. L L S - 176,860 X.00475 - 840 psi P.- L This stress is well below the yield' strength (. of the steel in the shell (40,000 psi)~. p l ~ l-L ([ p 2-14 er s w e ~

• ?

.t.

~ .r ~. 1:.f

• L

. 2. 5. 2-External Pressure-For this package, the containment:yessel is. the I shielded: cask.. The following analysis will show-that the cask would suffer.no loss of-contents if; it were subjected tolan external pressure of 25psig.- For a-cylindrical shell, the maximum allow-able working pressure may be. computed. from the following formula P, = B Do/t I where P, = maximum working. pressure.(psi) B = a factor for. the' specific material! l being used j. Do = shell outside diameter (inches) t.= shell. thickness (inches) Reference ASME Boiler and' Pressure Vessel Code Section VIII 1965 pgs'10 & 202

{.

For the outer shell' of the cask:r B = 14,000 Do = 28 inches 1 t = 0.25 inches Therefore P = 14000. 125 psig a = 28/0.25-Disregarding any bracing and internal ~ support,.the cask outer shell itself will resistLa pressure of 'five times the requirement. "' ~ j H G l ki '- 2-15 s-1 l -,e,,j-.-- E -! ' 7;."~ "M L' t -, f --.----------1-----

4 'O. 2.6! 'Normni conditions ofETransport . Heat' d 2;.6.1 37 Package components, constructed of steel,1 I stainless steel and-lead, are unaffected by the H heat condition <(ambient air at 1000F. and insolation l loads of 800 g-cal /cmZ'on top,.400'g-cal /cm2 on ,j sides). The package surface temperature will-in-crease,:but.the interior cask and its contents should remain unaffected. The amount of expansion 1 and stress induced in the jacket-as a: result of -l this temperature rise will be nominal.. 'i 2'.6.2 Cold

g IJnder the cold conditions (ambient air at.-40 F.<

"I f in still. air'and shade), the package operation will" be unaffected. There are no liquids or gases in-

volved.- The materials of construction will not

be

.i adversely;affected. 2.6.3 Pressure 1 The package will withstand an. external-pressure of 0.5 standard. atmospheric pressure, h <d 2.6l4 Vibration te t Inspection of the package after shipments over a period.of two. years has shown no evidence of. damage aus a result of vibration normally_ incident to: transport. 2.6;5 Water' spray The package, constructed-entirely of metal, would' suffer. no damage as a-result of: the water spray test. 2;6.6" Free Drop

t

.A drop through a distance of 1.2 meters would. have only superficial' effects on the package. r There would be no loss of containment fromosuch a-drop. 2.6.7 Corner Drop o r Not applicable. 2-16 b \\ g L. s

i 9;i. ?" l 1 'g 2.6.8 Panstratione T'l. -le There'wouldlbe no significant damage to the l protective jacket from the impact.of a 1% inch'. diameter by.13cib. mass _ dropped from a height of 'j 1 meter.- 2.6.9 Compression-1 The package is capable of. withstanding a compressive load equal'to five times its weight. This requirement is analyzed in 2.5.1. o 2.7 Hypothetical Accident Conditions 2.7.1 ' Free Drop 1 /c The design and* construction of the GE model-500 protective jacket was based upon extrapolation of 1 the proven data generated during the design and construction of the GE model 100 cask and also upon the-results of' cask drop experiments by C.B. Clifford -(1) (2) and H.G. Clarke, Jr. (3). The laws' of similitude were'used in an analytical ~ evaluation'(3)(4) i to determine the protective jacket wall thickness that would withstand the test conditions of 49CFR173 an'd 10CFR71 without breaching the integrity of the ] c model 500 cask. The increased' weigh 4 and dimensions f. of the model 500 container over the model 100 container 4 necessitated a protective jacket wall of 5/16 inch steel compared to a 1/4 inch wall for the mode 11100. ,1 (1) C.B. _ Clifford, The Design, Fabrication and Testing of a Quarter Scale of the Demonstration Uranium ( Fuel Element Shipping Cask, KY-546, (June 10.1968). 3 (2) C.B. Clifford, Demonstration Fuel element Shipping-Cask from Laminated Uranium Metal-Testing Program, Proceedings of the Second International Symposium on Packaging and Transportation of Radioactive Materials, Oct.114-18, 1968, pp. 521-556. (3) H.G. Clarke, Jr., Some Studies of Structural Response of Casks to-Impact, Proceedings of the Second International Symposium of Packaging and' 4 Transportation of Radioactive Materials, Oct. 14-18,. 1968, pp. 373-398. (4) J.K. Vennard, Elementary Fluid Mechanics, Wiley and Sons, New York, 1962 pp. 256-Z59. '{. 2-17 e' _......m.-

eu a 13: T The iatent of the design-forjthe?GE model 500-h"i[ is, during accident conditions',fto sustain' damage.to M.- the. packaging not reater than-the damage sustained 1 by.the GE model.10 during itscaccident condition-i ,4 tests. (Reference application for model'100 cask,. 4,[ ' ' Cert!ficate of Compliance 5926)..The modell100' cask' was dropped onto a 10' x 8'.x 3 inch steel 1 plate. :The j orientacion was onto:the upperJedge of the. protective ll -jacket, where the lifting and. tie down devices are located. The results were that-the protective jacket sustained all damaps. The-cask < lid remained secure- -and there was no loss of' contents lfrom the containment J s vessel. i It is ex>ected;that damage not exceeding that r suffered by t.se GE;model.100.will result if the GE-- 3 1 model'500 is subjected to the 30 foot drop test;. 5 ..0 Basically the contaf.1 ment vessel is a solid-mass with no' moving marts, protected by a steel Jacket which. l will absor) the energy of impact.- r 2.7.2 Puncture The protective outer jacket will ~ sustain all damages resulting froIIL the puncture test. It is expected that there;will be some de'f'ormation of the j -(-' ollowing caluclation will demonstrate that'the acket, but that the cask will remain unharmed. The j jacket will not be punctured. Li The energy developed in the; drop (E ) is equal'to' D the weight (W) ' times the drop height (d). l .ED = Wd = 8100:1bs ('40'in)'= 324,000 in-lb The energy necessary to shear the. steel jacket may be calculated. E = Shear Force (F ) times the thickness (t). - s s F, = Area of Shear (A) times shear _ strength -(S). i Es " ^ ISIICI 1r(6" DIAM)(t)(67,000 psi)(t) = E = 1,262,,280 (t2) s The thickness of steel necessary to resist; puncture may be determined by setting the energy necessary to shear (E ) equal-to E ' s D 10 2-18 g q.. _g ss 9+ w i ' ' * " ~

f ~ ~~ ~ ~ r 'N, * .1,262,280 (t)2 = 324,000 2 o" 2 t =.257 %a t=.057 inches 4' Th2' minimum thickness ~of steel necessary to j{ resist-puncture is;0.507. inches.. ,s The protective jacket is designed with a-double wall of.3125' inch steel ~plateLseparated-by 1 m . inch air space. The combined wall thickness ~ "4 of 625' inches will therefore resist: puncture-1 (, and damage to the cask.. 'I q 2.7.4 Water Immersion-q f[^ ..The'model GE 500 package is a solid, rigid

p"

' package that will resist an external pressure of water of 21 psi. The protective jacket has openings-1 designed for air circulation whf.ch will a? low water j n pressure to equalize on all sides of the jacket. 'In. '2.5.2Ean analysis was performed to show that the cask would support an external load of 25 psi.. ] The materials of construction would'not'stffer - 4"3 ~any significant damage.from. contact gith' water.- J ,.1 d 2.7.5. Summary of Damage j 4 q .As a result of the hypothetical accident test sequence, the package will have sustained some cf damage to the outer protective jacket,.but the ij containment vessel and its contents will have remained intact. The protective jacket will be crushed but 4 not penetrated in the areas of. impact:from the free 'l drop and the puncture t,est.. All bolts will be in y' place and secured. The containment vessel will have suffered no loss of shielding and therefore-the package-j will be as safe after the tests as it was before the l tests. I i 2.8 Special Form a Not applicable, aq 2.9 Fuel Rods 4 1 Not applicable. l 2.10 Appendix d i 2-19 4 y - ~.Qs e.-~..--x-- _ rr+

• r ".

.....' #5

l'?' 3.0- . Thermal'. Evaluation 3 3.1-Discussion TheLHodel'GE 500 package is basically'a trans- $,1 portation package. There are no. subsystems involved.- ? .The: primary thermal design feature. is in the steel protective jacket, with a double wall to insulate from external thermal sources, and also designed to allow air circulation for package cooling necessary. from internal thermal sources.; Analyses. performed on : similar packages. demonstrates that the package will prevent structural: damage, breach of containment, and loss of-shielding under-the norami and hypothetical - t accident conditions, s The maximum decay' heat load shall not exceed'780 I watts. 3.2 Summary ~of Thermal Properties of Materials Melting point- -Carbon. s t' eel 2750 F. Lead 1670 F. i b 0 Stainles s: Steel - ( 302 )- 2550 F. i 3.3 _ Technical Specifications of Components Not applicable. 3.4 Thermal Evaluation-for Normal Conditions of Transport 3.4.1 Thermal Model. Equilibrium temperature recordings for the GE Model 1500. cask (Reference Certificate of Compliance 5939) were taken.- The package was loaded to 3028 watts-(97% capacity), which resulted in the-following data. Cavity-wall -307 F. Maximum-lead temp 307 F. Inner shell ofojacket 139 F. Outer shell of jacket 99 F.. Ambient 80 F. k. The GE Hodel 1500 package is larger, but of the 3-1 s-..,.. =. = m

y m 3.w ..I

a. m samn design as.ths Model 500 package.

Th2-J UT' L, cask outer surface-to-cavit comparable, being only 1;1/y distance is

t. W 8 inches greater J

for the Model'1500.: The-Surface Area for-heat dissipation.in the Mo& 1 500>is approximately 55% of:the area available in the Model 1500;-how-- 1 P ever, the watt loading-for the Model 500 is: 257. of the loading for ' the Model 1500.. Therefore,. 1 it is anticipated that' equilibrium temperatures: t for the Model 500 cask with an internal heat 0-load of'780 watts would be approximately the 47 same as those for the,model 1500 cask.. 3.4.6 Evaluation of Package performance 3 It is expected that under the Heat Conditions 6 (ambient air at 100 F and insolation of 800 g cal /cm7 2 ? on top, 400 g cal /cm on sides), the package surface a T 1 temperature will rise, but that the cask temperatures, ch and certainly the temperature of the contents-will' .j. L not change significantly. Likgwise, under the cold. 2' conditions (ambient air of -40 F in still air and' shade) j + 'i the package surface temperature will drop, but the: temperature of the contents will not change significant!1y. 3E .Since the contents are in cpecial form, there are} + no internal pressures to consider. Thermal stress is 14 o y -(. minimal.due to the materials-of construction. j ll[lU1 n' 3.5 Hypothetical Accident Thermal Evaluation t 1 v, J, -3.5.1 Thermal Model m ?!- The Thermal Model used was GE Model 1500 cask (Reference Certificate of Compliance 5939). ,1 g That package was assessed using the General Electric: y Transient Heat Transfer, Computer Program Version:D' y (THTD), which allows the analysis of the general; transient i problems involving conduction, convection, and radiation. ?,' The program allows the thermal properties of the b,, materials to be entered as a function of temperature LN and the boundary conditions to be~ entered as a function F of time. ~1; J [% The'significant assumptions, approximations, and-1 gi bo'undary conditions used for the analysis are listed rj 9 below: E m,g 1. Fire temperature 1472 F. y [ 2. Effective Fire Esmissivity 0.9 m ! !. (, 3. Fire shield surface p Emissivity and constant 1 with temperature 0.8 e y 3-2 3 m, - *y;i t 7 ]M-~f'[E y E Tl. "Y ,e

Q*. 4 f.* a - p 4. i hf- _ Emissivity'of.other' surfaces 0.8 andLconstant with temperature. E' 5. There isLintimate contact between the lead-c shielding and the-stainless steel'shell1 of the' cask.

6. - There is negligible - heat transfer by.

conduction through the pipes used as-spacers' between the cask and the first: shield and between the two shields of the u l ' protective jacket. 7. There is negligible heat transfer by; l convection between the two shields of the i 4 i protective jacket and between the cask and 4 first shield of the protective jacket. y 1 8. There is an internal heat load of 3,120 R wrtts with a-temperature profile as outlined-a:~. in 3.4.1. Ccnditions 1 through 3 above are specified in d 10CFR71. Condition 4 is-quite conservative particularly :for-the stainless steel shell lof the= j 3 cask. Condition-5 is conservative since for most i l shielded casks the lead is not bonded to the ' outer steel.shell. The presence of a.small gap. between the lead and the steel would tend.to in-4 sulate the lead thus reducing its temperature rise.- Conditions 6 and 7 are not conservative but rough calculations indicate that the effect-of a these assumptions may increase the-tem of the shielded cask enly 10% t o' 15%. perature rise Also they are more'than compensated for by the conserv,atism of condition 4, wh1ch may-overestimate-the temper-o ature rise by'as m,uch as 60% depending on the y condition of the surfaces. Condition 8 lists thermocouple recordings from a 3028 thermal watt 1 internal load. T.he thermal properties other than q emissivity were used as functions of temperature, 3 i With these assumptions, the problem yields to an axi-symmetric conduction-radiation solution. -For-the analysis using THTD, the packaging was divided into nodes or regions. The two protective jacket shields were each divided into two nodes. The-y outer stainless steel shell of the cask was divided L into two nodes. The lead was divided into several nodes. Finally, the cask cavity wall (arainless steel) was considered a node. k 3-3 i 1

h, h' t lit c '325,2-Psckaga Conditions and Environmnnt e ,1 n; p It is expected that.;the package will sustain. minor damage t_o the-protective-Jacket during'the free drop and puncture tests,-and that the containment vessel will be virtually undamaged. Therefore',L it 1 t W -is' reasonable to consider the resultant package, [ "y m for purposes of thermal resistance, as ' essentially undamaged. '3.5.3 Package Temperatures The computer program calculations were run'for' i ,3 a.30 minute fire. Thecalcugations<indicateamaximum. t temperature of less than 390 F for the 1e'ad~after 30 (' minutes and no lead-melting:could.be' expected. >Al-though a coast-up analysis-was: not. performed on -this j container, the resulting maximum lead temperature, -[ c after equilibgating for forty minutes.,-is expected not t U to exceed 470 F. j I i 1 These results, obtained from an analysis of a GE Model-1500 container,.will hold true for the Model 500l package. Appendix 3.6 contains a writeur of the 1 analysis performed on a GE Model 100 package. It-4 e L contains a graph of temperature. rise during the thermal L tests and also a coast up-analysis g{ temperature L lp',. during the cool down period immediately following thel test. The-Model GE-500 package is expected:to' perform -) in a similar manner, though at higher temperature. p 3.5.4 Maximum Internal pr.essures' L' p Not applicable. s 3.5.5 Maximum Thermal Stresses "yL Not applicable. 't ['" 3.5.6 Evaluation of package performance t. E The package will not incur structural damage,. i L breach of. containment or loss of. shielding as a result of the hypothetical accident - thermal conditions. 'Ihe temperatures reached by the lead are not high enough to cause the lead to melt - therefore shielding is q unaffected. The steel components of the package do not } reach temperatures high enough'to cause damage. L 3.6 1ppendix J Predicted Thermal Response of General Electric E.C'.- Shielded Containers during the 10CFR71 StandardLFire. 1 b' 3-4 r b; h'% -.an- ~

w , \\y. 1L, ,, s. *. + 1,y; :s. 'J ; :, u, f,.'. ,sy r .-[, f et - r, J't f EXHIBIT A - o a i . I PREDICTED THERMAL RESPONSE' ~ l' ' .0

.y

. 7 ' t! f v 0F-4 4 GENERAL ELECTRIC SHIELDED .i i CONTAINEx DURING THE 10CFR71-ti (:. t STANDARD FIRE j '. I i ~ + + A i t l '. ) . + i e ) 'I l 8 +), w .y44 4 +%...-- - [* $* c p,l >,,

'esv- . WI[. lhtreductica t'nd Preblom D finitian l 4.. ; n

Tha' following tha'rmal analysis of ths Genarel Electric shialded shipping con.

tainers was. performed in accordance with 10CFR71.36, 'as described in Appendu l 3,,,,,. .B (3) to 10CFR71. The conditions of 10CFR71.36.do not preclude melting of the ,{ 3 . shielding material but rather limit the dose rate allowable after the' accident.. P The hypothetical accident involves a sequence of conditions involving: '1) L A ' distance of 30/ feet onto a flat essentially unyleiding sur. free drop through f i face. ~ 2). A free drop through a distance of 40. inches onto a verticle steel n cylinder 6 inches in diamete and 8 inches or more long. 3) Exposure for-i.. I 30 minutes within a ' source of radiant heat having a temperature of 1475'F and. i 1 an emissivity ccefficient of 0.9, or equivalent. For calculational purposes, h' j it shall be assumed that the package has an absorption coefficient of 0.8. The) package shall not be cooled' artificially until after the 30 minute test period-has.espired and the temperature at the center of the package has begun to fall.

4) Immersion in water for 24 hours to.a depth of at least 3 feet.

l . (). The General Electric approach to this problem was to nrutect the shleided cask i Two for future use while meeting the, requirements of Appendix B to 10CFR71. - primary design criteria were established for the protective jacket. 1) Provide maximum protection for the shielded cask during the required impact tes.ts i with a high confidence of zero cask weld damage as an objective, and 2). provide t E maximum protection for the shleided cask during the 30 minute fire with zero-k molting as an objective, yet' maintain compatibility with the internal heating, ~ I load which must'b'e dissipated from the cask during normal transport. Several methods of protecting the shleided cask during the drop and during l the fire have been devised by other dusigners..The protection generally has been constructed of wood or combinations of wood and metal. Two objections to the general use of these designs have been noted. First, while the wooden Jacket,does,an exec 11unt job of protecthyg the ahielded., cask,from tho'itru.an.d ) ...........,s ,e ,3.. ..s,. .p. ,;. -........ Exhibit ' A. 5 e .pfN - .,1,"1.leense 44" ENO.~466 ~ NAQ%ee, He.,.g 10.754.'Lgg.- g, .:......<. 4;. 4.ct, e. i 3

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f ',, , 7.' s... =i h 7 ?* sctisfactorily. protects it during tho drop, 'unfortunctaly, it clso'tnsutetas ths-y'; f, g shielded cask during norinal operating conditions 2 Thus, the cask operates at- . ( ' unnecessarily high temperatures if the transported material generates signif. icant amounts of decay heat. Second, wooden jackets cannot be readily decon. taminated in the event that they should becotae contaminated. t Proposed Solution. - The design select %d for the protective jacket consists of two steel enclosures i which serve as thermal radiation shleids during the fire transient as well as,. Y. - " crash" shields during the drop. '.The internal heat l load can be dissipated to. the' ambient air by providing a path for natural air circulation through the, pro. l-tective jacket during normal transport. The protective jacket analyzed is.. shown in Figure 6. t 1 Heat Analysis r ( The analysis was performed using the General Electric transient heat transfer l ,t , computer program (TNTD) which allows the analysis of the general transient problems involving conduction, convection, and radiation. --The THTD computer "t program uses the impl.icit finite difference technique.. It allows-the th.ermal - 'j properties of the ma'terials to be entered as a function of temperature and the 1 boundary conditions to be general functions of time. - The significant assumptions approximations, and boundary conditions used for,- the analysis are listed below.

3

~. .w;. ~ { 1. Fire tempe ratu' e,14*l2 *F = 800*C. - r 2. Effective fire emissivity. 0.9. F 3; ' Fire shleid surface emissivity. 0.8 and. constant with temperature., Emissivitles of other surfaces, 0.2 and constart with temperatt[r2 4. 5. Intimate cor, tact between the 1 cad shielding and the stainless t.tegl (. cask shell., .. 17... ; .:,.... ;,..;j;.; q y. 3,4 ;..,u';-(5,g

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7. --Neg11gible heat transfer by convection between the two shi P

between the first shield 'and.the cask. 8.. Internal heat load of 400 watts with recorded temperatures as out. lined,in Section 5.1.2 (e). 4; Conditions 1.through.3 above are specified in: Appendix B. Condition 4 e Condition ! -i conservative particularly for the, stainless steel shell of the cask. .K ! 5 is conservative since for most shielded casks the lead ," 1 ~ d .l h lead and the:stef1 outer steel shell. The presence of a small gap between t e . Conditions would tend to insulate the lead thus reducing its temperature rise. h ffec't of 6' and 7 are not conservative but rough calculations indicate that t e e i hielded cask'only these assumptions may increase the temperature rise of the s 10% to 15%. Al's'o, they are more than compensated for $y the co 60%- condition 4, which may overestimate the temperature rise by as much as Condition 8 lists thermocouple record depending on the condition of the' surfaces. The thermal properties other ings from a 400 thermal watt internal load. than emissivity were used as functions of temperature. i ' With these assumptions, the problem yields to an axi.syrnmetric cond For the analys'is using THTD, the' packaging was dtvided s radiation solution. The nodes Into 15 nodes or regions ais shown schematically _on Figure 7. dient becoming

g..

were made smaller in the region of the maximum temperature gra l-F The protective jacket shields were each progressively larger near the i: enter. The outside stainless steel shell of the shielded ca i divided into two nodes. The first two lead nodes at th'e outside surface was divided into two nodes. y) The remaining of the cask were made the same thickness as the cask sheti.

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,j, .'1ead was divided into 'six n' odes of equal thickness..., .a. - -.. g..,. s c,- .;. 9 .,..,..;,......s.., $.. '. },f. %e, E; '70.'7W ' " d*_SitN(i.MIEiI' Al "" E. M 'k * .ncs.,.. j. 3 b I.1 k(Lies se No." "# "sNM. q C ',fe.,.1.,'p t, yQ j.,n;q:,,q.;g :Qy:y.!;y,..; ppegtg@y%g.q f-4 .g. ,; g ~ ~. A

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_.w_. - - - - - - - = = - - - - - - - - - - - - - - - }[lg, + y ^ Shioldod Cask and Protoctivo Jschot Dimonsions A typicht General Electric Sh'ielded Container-Model 100 was used dx for the thermal analysis. m; r* i ' ' 4 =i . Shielded Cask Dimensions i l 1 Ins ide~ Diameter 7 5/8 inches - S Steel Thickness 1/8 inch 1 . Lead Thickness. 5 7/8 Inches: l Steel Thickness-1/4 ' inch - gm s; Outside' Diamete r 201/4 inches t 64 n l Protective Jseket Dimensi'ons 1 First Shield 'A k. Steel Thickness 1/4 inch Outside Diameter 221/4 inches e Second Shield -t 1 Steel Thickness 1/4 inch ' Outside Diameter 251/4 inches _Results and Conclusions The results of the analysis are shown on Figure 8. The calculations indicate a maximum temperature rise of 220*F for the lead after 30 minutes. Thus, considering the conservatism of the analysis (due to the choice of 0.8 for all g.y cmissivities), the design provides a large margin of safety during the pro-posed fire accident. Since no lead melting will occur,,the shielding. we.uld net ?.. qg -

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%y to arrive'at the maximum lead temperatur# rise of 440'F. This is a conser. 1 [7 ative estimate-of the package performance during the.specified fire. Again. since no lead melting will occur, the shleiding will not be reduced even In' ,m . the event of sheath rupture and maximum safety will be maintained. d. i br .. (. ~ 7 i '). 'i 3 i '( 1 l 1 v 1 \\ { I u l 1 y o a i t j y j ), 3: -i. si d + u ig t 1' qux J- -L' ..i s e,}~.TEkhli>iE Ai ' '.: .4 pjh) i. i Licene. W. SNM-960 ,. Decket.No. 70 754 - ~ w

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.i 1 November.13, 1968 N.J- +... ~ ~ '., s... 1 J .ll ..\\ \\ Mr. Blaka Brava Irradiated Fuals. Branch .I Divisica of Haterials 1.icensing U. S. Atomic Ener37 Cennissisa Washington, D.C. 20545 ,s. 3 Dear Blakes- ~ the enclosed data', including 1) a material' proper #das table. ('s _

2) ai physical andal,of the sootniner with anda locations,

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3) the 'resulta"of a ~eoast'-op ' analysis, and 4) a statsnaat i

'~ "'" ' i explaining the aboice of'the radial.dirsation for the beat. ~ analysis,' ara submitted. in accordanes with the.telecca L batvean Massrs." Don Broun, Walt King, and yourself. . j.... . t,......s

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'.3 ..a 5 h 3. General Elastrie shielded Container - !?odel 100, liur.ber 1% Cash Tamperatura comet-Un after ytre 'transione Ustag* the temperature distribution at the end of the fire fron the TE: firs transient rua, ths 1M sask was allowed to equilibrata for forty stastas, estag . -,1 agnia the TET coupstar code. 'R.e resultant temperaturas in various parts of the seek versus. time are shoun in rigures 1 and 1. The significant asm-.ptieaa and approximations are: .130'F. 1. Ambiant (siak) temperatsi:s. ~ 2. Effective sink emissivity. 0.9 ' 3. Fire shield surface amissivity. O.8 1 and constant with temperstare. 4. Emissivities of other sur8 aces. 0.8 and constaat with temperature. Intiasta centset' batveen tha lead shielding and t.ha stainless staal task shell. 6. Negligible heat transfer by conduction through the pipes used as spacers betvun the sask and the first shtald and between the rao shields., ((, 7. Wesligible heat transfer by eaavention between the two V shtalds and betooen the first shield and the eask. 3. Iuternal heat load of.400 watts with tamperature distributica .c as calculated by 22 esaputar code at the and of the 30 minuts' fire. 4 Condition: 3, 4 and 3 are not co:nrervativa for the coast-sp. but these conditions.. vere imposed and were conservative for the fire stanstant, since the temperaturea'. attained at the end of the fire would have been considerably lower with lower ~ emissivitism. Also, natural convectica from the outsida fire shield was not - allowed but,would in fact ecsar to some extcat, a=4 La esaservativa. In order to determine the taeparatura distributtaa is the 1% sask moder neraal: transport conditions, a test was run usin5 a Ca660 sourca. The navk waa.'. /.4 - O i c =< ith 5 ste et-1 t ete< 1e o ei sted ta ce-e evi e *ics ve=> :- taped to and sprung agatast.'.the surfaces to be measured. r n ~ A sixth ther.moccuple was used to taasurs ambient air tauperstars. A.25.003.ca., Co.60 source ?.sas placed in the cask cavity with s'laad linee, and the'svatza ' was allovad to equilibrata for s'pproximataly > days..The ta=peratures s. tined

• 4" titre as followes.

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t m.., i 4 m m.m g...., i n - [; +; < Shialdad eask savity 8 440 y t .4 W taternal shell of saak, side 8 173 7 ) + e,' Esterasi shell of sask, top 165'r 1 1., tutornal shall of cask, hattam '156*F Protective jacket, entside surface, top pp'y . h' Protactive Jackat, outside surface, sida 95'F ~ m iant i r - na t 4. Choice of P dial Direction for Meat.*.nnivsis J x In reply to the qucation as to vby the 23r fire transient snelysis cassidated l the radial direction rather than the top or bottaa of the cask: This was does "r i principally ta allow seasideration of the lead liner, which would not be . Laciuded if the task were analysed thesa$ the top or bottan. Also, the c '!- dLstancas involved are somewhat comparable; the sadial distance being the f chartsst by about two inches. 1* v: a .. i

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fii . ) 1 Nf[ + J 4.0 Containment i 4.1 Containment boundary 4.1.1 Containment Vessel The containment vessel for this package is the cask which contains a cavity 7" DIAM x 7"H. The J design specifications are summarized on Drawing 212E246 in Appendix 1.3. 4.1.2 Containment Penetrations i; ' The cavity is penetrated by a inch r 0 D x 0.065 inch wall stainless steel tube gravity { drain line, running from the center of the cavity r bottom to the side of the outer shell near the cask bottom. It is closed with either a fusible lead h cored NPT hex head brass pipe plug, or a solid stainless steel plug. 4.1.3 Seals and Welds 1 A silicone rubber gasket bonded to an aluminum backup plate provides a seal between the cask and e its lid. Reference drawing 129D469Q,in Appendix 1.3. - ( Cask welds are specified on drawing 212E246,- Appendix 1.3. 4.1.4 Closure i The closure devices used for the containment 1 vessel-are 6 equally spaced 1 x 8 UNC 2A steel bolts. 4.2 Requirements for Normal Conditf.ons of Transport 4.2.1 Release of Radioactive Material There will be no release of radioactive material from the containment vessel. The protective outer jacket completely protects the containment vessel. 4.2.2 Pressurization of Containment Vessel Pressurizet'.on within the containment vessel cannot occur. Tne radioactive material being trans-ported 'is in sp<scial form. (g. 4-1 -p

• ~ = ~

z.2 - r-a n

4 ", i ' 4.2.3 Coninne centecin9tien ~ i Not applicable. 4.2.4 Coolant Loss Not applicable.- 4 3. Containment Requirements for the Hypothetical Accident Conditions 4.3.1 Fission Gas Products. 2 s Not applicable. .l~ 4.3.2 Releases of Contents There will be no release of radioactive ~ material from the co'ntainment vessel. I h 8 b O e L 4-2 ? ,F"***N# ~* I

• 1. f**8,

5.0 .Shiniding E"aluations 5.1 Discussior, and Results c i The Model.GE 500 package is designed to j provide a. nominal 10 inches of lead on all sides, top and bottom, of the cask cavity. All of the shielding is in the cask itself. The only rerovable shielding u is in the cask lid. TABLE 5.1

SUMMARY

OF MAXIMUM DOSE RATES I (mR/hr) i i 3 feet from Package Surface Surtace of Package Side Top Bottom Side Top Bottom Normal Conditions Gamma 60 60 60 7 7 7 !) Neutron Total 60 60 60 7 7 7 t Hypothetical Accident Conditions Gamma 60 60 60 7 7 7 Neutron Total 60 60 60 7 7 7 10CFR Part 71 Limit 1000 1000 1000 l ~%s I r 5-1 (I 1; .-.,,.. _ _ - _ _ - _ _ _ _ _ - _ - +.. ., - - < - " - - - ~ ~ -

i ,.s 5.2 Sourco-Spacification i 5.2.1 Camma Source The maximum quantity of radioactive material to be shipped by Advanced Medical Systems in this package is 50,000 curies of Cobalt 60. For the shielding analysis, this material was considered d as a point source with an output of 1.35 RHM/ curies, u 5.2.2 Neutron Source Not applicable 5.3.3 Model Specification \\. 1 l ~ 5.3.1 Description of the Radial and Axial Shiel_d_ing i configuratl.on l-I [ m 1 i /OW It' i j O O L ' g. e /0, - i .\\ J " 'l: gg" b-. /o fy" l y p 1 Figure 10 1 b t t I 5-2 F IIk wt- + m .w, wg Vg__-g9-,. q py 9 + -my 7 e,- y--i 9 peg -r

= -. i l'. 5.3.2 Shield Regional Densities A Not applicable. 5.4 Shielding Evaluation There are no differences between normal conditions and accident conditions of transport, as 'the outer jacket is designed to protect the contain-ment vessel from damage and loss of shielding. The basic method used to determine the gamma-dose rates at selected points outside the package was by actual measurement. Incoming shipments of Cobalt 60 in special form are routinely surveyed 1, before acceptance. A Victoreen 491 survey meterris used. Readings are'taken at the package surface and e at points three feet from the surface. A summary of the highest readings recorded follows: Quantity. Surface Reading 3' Reading. 28,300 curies 40 mR -4.8 mR 35,300 curies 45 mR 5.0 mR 45,200 curies 55 mR 6.0 mR Plotting.this data on a graph and extrapolating to a maximum quantity of 50,000 curies results in a maximum surface reading of 60 mR/hr. This value is confirmed by calculations. In practice the maximum dose rates are well i below the limits of 10CFR71. e 0 s 1 5-3 b ,_s

<~ 6.0 Criticality Evaluation +: l Not applicable. . i 9 i e f s l i [ l 1 k I 4 - j a 1 h .h r ' l i V e j i e t } 6-1 e ~ r i B b

• T Y '^ ~

m

• " ' ' ~ ~

^ ^ ~ ~~ ~ r e 1

~ ] ,o , o* I 7.0 Operating Procedures 7.1-7.2 Procedures for Loading /Unicading the Package Note: The requirements of 10CFR20.205 are [ applicable when receiving or unloading the container.' i The following general procedure is used in the I handling of the package. 1 a. Survey the package dose rate in accordance with internal procedures to assure the levels do not exceed the limits of 10CFR71.47. p i b. Use appropriate capacity material handling Lq.- equipment to transfer the package assembly to a clean area. The total package assembly weight is 8100 lbs. I 1 c. Remove the wire security seal (item 6) located at - L the base of the jacket. d. Remove the six bolts (item 7) from the base of the jacket. r> ( e. Open the anti-tiedown covers (item 4)..Use care not to damage the covers or lose the bolts.- f. Carefully lift,the jacket off the cask, either by using the rectangular lifting eyes (item 2) [ on top of the jacket, or by using the tiedown i lugs (item 3) and appropriately rated slings. i g. Place the jacket in a clean area. i j h. Wipe the external cask surfaces for radioactive contamination. If removable contagination above the limits of 10CFR71.87 (22dpm/cm or. 20,446dpm/SF) is detected, follow appropriate i internal procedures for contamination control.' q 1. Lift the cask from the jacket base using the cask lifting ears (item 8). Transfer it to the shielded facility (hot cell) designated V for dry loading / unloading operations. j. Remove the cask lid boler (item 9) and store to i arevent loss, contamination, or damage. The solts are required for reassembly. ) w. 3 i 7-1 Change 1 Oct. 15, 1985 2

t. + a k. Monitor the cask dose rate and carefully remove-the lid from the cask using the cask lid lifting eye (item 1). 1. Inspect the seal gasket (item 11), the lid seal area, and the lid bolts-for damage which could affect the integrity of the closure seal. This inspection should be conducted prior to. loading. material into the empty cask cavity, or after the cask contents have been removed and safely stored. If any' damage is observed, notify AMS. Transfer the radioactive materials and associated m. internal hardware into or out of the cask cavity.- Check the seal gasket for proper positioning and n. install the cask lid. Use care not to displace the gasket. o. Monitor the cask dose rate to assure that the dose rates are within the limits of 10CFR71.47. p. Install and tighten all lid bolts to assure a good lid seal (100 ft-lbs torque). ) ( s q. Remove all old labels from cask. Apply new " FULL" or " EMPTY" label, as is appropriate. Wipe the exter'al cask surfaces for removable ~ s. n contamination. Decontaminate to reduce removable contamination levels to below the limits of'10CFR71.87, t. Return the cask to the protective jacket storaget area. Inspect the for damage. protective jackec, base and boltsNotify AMS u. repair or replacement of parts is observed. Place the cask on the jacket base. v. w. Align the cask on the base so the fireshield will position over the cask lifting ears and align with the bolt holes in the base assembly.- Position protective jacket on jacket base. x. l 7-2 Change 1 Oct. 15, 1985,, p .]

{h Install' the jacket bolts and tighten (600 f t-lbs tonym)l y. z. Fasten anti-tiedown covers to jacket lifting eyes. aa. Remove all old labels from the jacket. Attach appropriate-shipsing labels and security seal. In addition to tse proper shipping labels, the container ID label contains two descriptions of contents, as follows: Radioactive Material, Special Form n.o.s. or i Radioactive Material, Empty Package Mask out the one which does not apply. bb. Perform' final radiation survey of assembled package;(including smear check of external jacket surfaces) to insure the limits of 10CFR71.47 and 71.87.are not exceeded. Complete shipping papers as required by-applicable internal procedures and government' ^ regulations. ( l i l 1 k%s 7-3 Change 1 Oct. 15, 1985 i e me7

"j ' Ji i a o' y 84 "O - 7.3 Preparation of an Empty Package for Transport ir Note: The requirements of'49CFR173.427 are applicable',' g I The following general procedure is used in pre-paring empty package for transport. a. Wipe the external cask for removable contamination. Decontaminate to reduce removable contamination -l levels to below limits of 10CFR71.87. j b. Verify that the cask lid,. gasket and bolts are ] eh .all in place. .I b c. Apply an ' Empty' label (49CFR172.450) to the cask. l-t d. Inspect the protective jacket, base and bolts for damage. u e. Assemble the package. f. Fasten anti-tiedown covers to jacket lifting. eyes. 3 g. Remove all old labels. Attach appropriate shipping labels. h. Mask out the words ' Radioactive Material, Special- -{ li Form n.o.son the container ID label. ? t (- 7-4 Change 1 Oct. 15, 1985 l 1

i 1 er s

• r; 8.0 Acceptance Tests and Maintenance program

( 8.1 Acceptance Tests At present, Advanced Medical Systems Inc. has no intention'of constructing any new Model GE 500 packages. Should the need for new packages arise, they-will be constructed under approved QA Program 0354. 8.2 Maintenance Program-Prior to each shipment, the package components are thoroughly inspected. All defects are corrected before releasing for shipment. Replacement and repair of components is pdrformed on an as-needed basis. 8.2.1 Structural and Pressure Tests q None required. 8.2.2 Leak Tests None required. 8.2.3 Subsystems Maintenance _ i 't Not applicable. 8.2.4 Valves, Rupture Discs, and Gaskets on Containment Vessel The gasket used between the cask and cask lid is-inspected prior to each shipment. It is replaced when inspection shows any defects or when it becomes contami-nated. b 8.2.5 Shielding l Not applicable. Routine surveys in accordance with i transportation requirements are adequate. 1

[

8.2.6 Thermal None required. Thermal degradation does not occur. s 1 - (, 8-1 ,, j h l' 1 .. j

a h a @*0%, UNITED STATES, ,g NUCLEAR REGULATORY COMMISSION 3,, w j' tj wa$mucTow, o.c. asse f l \\..v.../ j E i FCTC:CEW ggg g g gg$ 71-9049 Advanced Medical Systems, Inc. ATTN: Mr. Howard R. Intin s L 5463 Horning Road + Pittsburgh, PA 15236 Gentlemen: Enclosed is Certificate of Compliance. No. 9049, Revision No. 6. for the Model No. GE-500 shipping package., This certificate supersedes, in its entirety, Certificate of Compliance No. 9049, Revision No. 5, dated December 24, 1985. Changes made to the enclosed certificate are indicated by vertical lines in the margin. Advanced Medical Systems, Inc. and the Department of Energy have been registered as users of this package under the general license provisions of 10 CFR 971.12 or 49 CFR 6173.471. r> ( This approval constitutes authority to use this package for shipment of radioactive material and for the package to be shipped in accordance with the provisions of 49 CFR 6173.471. Sincerely, \\V k / r // Charles . MacDonald, Chief ' Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS

Enclosures:

1. Certificate of Compliance No. 9049, Rev. 6 2. Approval Record cc w/encis: Mr. Richard R. Rawl -Department of Transportation Department of Energy ATTN: Mr. Roy F. Garrison f DP-122.2 ( Washington, DC 20545 J* O vg4+trw4hf 1

i me eene se u.a. wuctsAn narutaroav osumissen CERTIFICATE CF COMPLIANCE CC 8" POR RADCACTWE CATERIALS PACKAGES l,,'camixicAia avuesa e at m o" * "*ta

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i 1 r 9049 6-IS A/9049/B( ) 1 2 l a emSAMBL4 b a The certificase e neouse to certify shot the secheeeng one contente seecrimes en hem $ ho6ow. meets the sopiscegue setot, oleneeres set torin in title 10. Cose j of Feeeral Roeuteleens. Port 71. 'Paceaeen0 ene fransportetson of Aeoeometr.o hoseereL*' [ n the coroneme ages not re e m cone.enor trem compi.ence ita ear eeouement of the reevietions of ine u s 0.oortment of Trenosories.cn or einer ( e es.e,ee mory seenc,se. incio.n, = e erami of any couniry tarovea or eato -a.ca ine pacieve..a os ironsoones J j{f j_ a v ses,c, gICA ON TMg oA&al Of a SAFETY AsnALysis,as, gnogs l $ $$UE T om iCA SON {j i Advanced Medical Systems, Inc. Advanced Medical Systems, Inc. application 5463 Horning Road dated June 27, 1985, as supplemented. j{ Pittsburgh, PA 15436 .. ooe=7 aumesa 71-9049 e CDeeDrie0ssE i[ The certificase es conertepnel upon fulfelleng the reeuwemente 6f to CFR Port 71, es eposecas.o. ene the cenentione specifies Deoow. s (a ) Packaging ( (1) Model No.: GC 500 J 1 (2) Desc ription 1 -l Steel encased lead shielded shipping cask. A double-walled steel l cylinder protective jacket encloses the cask during transport. It is i bolted to a steel pallet. The cask is closed by a lead-fi.' led flanged I plug fitted with a silicone rubber gasket and bolted closura. The I 1 cavity drain line is closed by either a stainless steel or 1'usible l l plug (melting point 500*F). The physical description is as follows: l l Cask height, in 29.0 l Cask diameter, in 28.0 g I Cavity height, in 7.0 il I Cavity diameter, in 7.0 il l Lead shielding, in 10.0 /l g Protective jacket height, in 38.9 l g Protective iacket width, in 40.75 l Packaging weight, Ib C,100 lll l lq f (3) Drawings l t ji l The packaging is constructed in accordance with the following General ili l l Electric Company Orawing Nos.: I 1 1 212E246, Rev. 7 106D3855, Rev, 4 I l 106D3870, Rev. 11 129n4690, Rev. O I l l i 706E740, Rev. 4 l i i j l l 4 I i li I. l I I I I i l i,l 1 a 1 \\g Cg guysopt

q g,,....,... r y y y., y,.r3..mx ryrrt,- e r. u v er v r u. err.str-rX +> 1 l ctuom us cc:ntonven l l 1 t-f *Page 2 - Certificate No. 9049 - Revision No. 6,- Docket No. 71-9049 [j tt ) Ilj 5. (b) Contents l (1) Type and fom of caterial !j i 1, l (1) Bvoroduct naterial neeting the requirements of special fom I radioactive material. 1 (2) Maxinum quantity of naterial per package .(J t g. Radioactive decay heat not to exceed 780 watts. t t 6. Shoring rust be provided to nininize novement of contents during accident I conditions of transport. l g 7. Package contents rust be delivered to a carrier dry. t i 8. Prior to each shipnent the silicone rubber lid gasket rust be inspected. This f d gasket rust he replaced if inspection shows any defects or every 12 nonths, I i whichever occurs first. Cavity drain line rust be sealed with appropriate l f' l sealant applied to threads of pipe plug. g g 9. Fabrication of additional packagings is not authorized. I j i t ll t 10. The package authorized by this certificate is hereby approved for use under the-l l l l general license provisions of 10 CFR 671.12. g j i i 11. Expiration date: December 31, 1990. - t l l 4 REFERENCES I 1I. Supplement dated: October 29, 1985. 1 I Advanced Medical Systens, Inc. application dated June 27, 1985. l 1 l .I l FOR THE tl.S. MJCLEAR REOULATORY COWISSION I L, l LI ,i I k l Charles E. t'ac onald, Chief. .I n l Transportation Certification Pranch = l li Oivision of Fuel Cycle and I i l Material Safety, tt'SS jy Datei DEC 8 0 885 j 1 ,1 -l l j l .,1 i I I g /'

?i', [ T / 78, UNITED $TATES . =.. p '! c( NUCLEAR REGULATORY COMMISSION' g-s. waamecrow, o. c. rosas i t I t Transportation Certificatinn 9 ranch ADproval-ReCnrd Model No. GE-500 Package Docket No. 71 0094 .l 2'1 Certificate of Compliance No. 9049_ for the H~jel No. GE-500 nackage has been revised to correct an error in.the expiration date. / 4e b ! ll'c '. L Charles E. PacDon"hid, Chief Transportation Certification Branch Oivision of Fuel Cycle and i Material Safety, '.HSS ~ I 'j Date: gge t e M l i i q t b A ,.4 b y -i i t L -}}