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Application for Renewal of Certificate of Compliance 9049 for Model GE-500
	ML20132F583
Person / Time
Site:	07109049
Issue date:	06/27/1985
From:	Irwin H; ADVANCED MEDICAL SYSTEMS, INC.
To:	;
Shared Package
ML20132F582	List: ML20132F578; ML20132F583;
References
	NUDOCS 8507180585
	Download: ML20132F583 (66)
	v • d • e

{{#Wiki_filter:_ Advanced Medical Systems,Inc. O,. r e..., t c. 121 N. Eagle Street d Geneva, Ohio 44041 (216) 4664671 TWX 810 4272183 Consolidated Application for Approval of Packaging for Radioactive Material 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 Prepared and Submitted by. s[ 4.,' 'Ifowa rd R. Irwin Manager, Regulatory Affairs June 27, 1985 O 0507180505 050627 PDR ADOCK 07109049 C PDR

1.0 General Information \\_/ 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 1.1.2 Packaging The model GE-500 shipping cask basically consists of the cask, a base, and a protective jacket. It has a gross weight of 8100 lbs (the cask weights 6300 lbs). Reference drawing 106D3870 in Appendix 1.3 for a view of the complete package. 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 h inch stainless steel plate. The cavity is shielded by 10 inches of lead on the sides and bottom, and 11 inches of lead on top. ,7- 'J 8 The cavity is penetrated by a inch 0.D. x 0.065 inch wall stainless steel tube gravity drain 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 \\NPT hex head brass pipe plug, or a solid stainless steel plug. 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 3 posed lif ting cars welded to the side of the casi. The cask lid is a lead filled flanged, stainless steel plug. It consists of two right cylinders of 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, h 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 assemaly. A silicone rubber gasket bonded to an 1-1 L

i aluminum back up plate provides a seal between (N the cask and its lid. Reference drawing 129D4690 \\' in Appendix 1.3 for a detailed view of this seal. b) The base is a hollow cylindrical steel weldment with a h inch square bottom plate on an I beam frame. Overall it is approximately 47h inches square by 7 inches high. The cylindrical collar is 29-k 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. c) The protective jacket is a steel weldment, basically a right circular cylinder with open bottom 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 air gap between walls. Overall it is 33-3/4 inches outside diameter, 40-3/4 inches wide by 38-7/8 inches high across the box section. A steel flange (OS is welded to the outer wall of the open bottom. There are four gussets welded to the flange and outer wall. There are two rectangular lifting loops located on the top of the box section at the corners. These loops are of welded construction. There are two 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 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 loops to allow air circulation for cooling purposes. Reference drawing 706E790 in Appendix 1.3 for a detailed view of the jacket assembly. 1.2.2 Operational Features Not applicable.* 1.2.3 Contents of Packaging rS By product material meeting the requirements of (J special form, maximum decay heat load 780 watts. 1-2 . ~ _ _ - _

1.3 Appendix a~ The'following items may be found in this appendix: Drawings Originator Number-Revision GE 106D3870 - 11 'GE 106D3855 - 4 GE 706E790 - 4 GE 212E246 - 7 GE 129D4690 - 1 O O 1-3

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'..E*' , />,e /..#~~ . t 'g N g NUM6E R AND CA*E. s s \\ ' s. N s. f s. x- + x. -,' 4 \\ u /.. N. N u . s __J s9..- c yN.:.,. O /.,i ... s /, / , /' \\. .O 9,O. - sP \\ ' ge,L.C E , tve. ..msowwaso].\\':,.".. \\ x,: l' NeTE / i t \\ l". -I O / Ape'rture Card \\' / A t /i \\j/ ~ s- ~ /x . / j B N.;' DB t} .s cs no L- ___.f._.s a i x <s i o-a s. .TI R . _ _ L _. _.!,I -J-1+ JAPERTURE n F. - -l \\ \\..\\ i ;,gggo, f, i \\,. .K I .,s 4 (0,\\. g. s 1 O / s. \\ w' e q,,. / t ',k \\ d.. ' N. \\ h l .2 '.;/ - ?~5 ',0 s /y a/ y \\,.3 -. - V. . < Q. 3 \\ i ./ -/ tso 75 \\?..,*c*\\- v 6 , //c i yyp ivP.. ' - / ,~ f ., f, ' e. .O . O. l N., ~. t, ' /,- (-LEW.rN%.e.-_z ,,,/#- m o Typ / .19 De A. PUNOH .,231 T.. ~ 86 PLACES A6 6HowN

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e 2.0 Structural Evaluation p, 2.1 Structural Design 2.1.1 Discussion The principal structural members of the package are the protective jacket, the cask, and the base. 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. "W a.

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2.1.2 Design Criteria ) 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 For the model CE 500 cask, the following data is applicabic: Weight of jacket, covers and bolts 1150 lbs. Weight of base 650 lbs. Weight of cask and lid 6300 lbs. (lid weighs 400 lbs.) 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. L If;%.40.' R

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s i 2.3 Mechanical properties of Materials I () A242 Steel i Reference Shear Strength 67,000 psi 1 Yield Strength 46,000 psi 1 C1020 Steel l l Shear Strength 75,000 psi 1 Yield Strength 48,000 psi 1 302 Stainless Steel i Shear Strength 90,000 psi 1 l Yield Strength 40,000 psi 1 ( l Carbon Steel Bolts i 2"-4h" UNC Grade 5 Cross Sectional area 2.5 in 2 I 2 l l Minimum tensile 90,000 psi 2 strength () Yield strength 58,000 psi 2 j i References t i

1. Materials Selector 1974 L

Reinhold Publishing Co. Inc. i

2. Fastener Standards, 5th Edition, 1980 l

Industrial Tastener Institute l 1 i i 2-3 1h '? I

2.4 General Standards for All Packages 2.4.1 Chemical and Galvanic Reactions k_s) There are no components of the packaging or its contents which are subject to chemical or galvanic reaction. The package construction is of steel and stainless steel. The only chemical material in use is exterior paint. 2.4.2 Positive Closure The package closure system consists of a 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 to the cask cavity. 2.4.3 Lifting Devices Attached to the protective jacket is a pair of Ilfting loops. 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 lif t the entire package or for tie down purposes, and are rendered inaccessabic during transit by re-movabic covers. ~(T In normal practice, the package is moved with a fork lift truck. In the event that an overhead pickup was necessary, the tie down cars could be utilized for lif ting the entire package. These cars are located on opposite sides of the jacket, approximately 7 inches below the top surface. They are 6"H x 3h 'W x 2" thick with a lh inch hole. Reference drawing 706E790 in Appendix 1.3. The following calculation will demonstrate that these cars have been designed with a minimum safety factor of three. 2-4 i

IS" ,G H 's./ / o () 6" L o p-3'/[H Figure 3 S=P where S = unit stress in psi A P = load in Ibs. (total package weight) A = net area at cross segtion con-z taining the hole (in ) S= 8100 lbs (3.5-1.5-)(2)= 2025 psi Yield strength for ASTM C-1020 Carbon Steel - 48000 psi () Safety factor = yield strength (psi) stress (psis SF = 48000 = 23.7 2050 The welds used to attach the ears to the jacket will next be analyzed. The ears are attached to the jacket with two 6 inch x inch fillet welds Each weld' throat 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, each weld can withstand a load of 23,933 lbs 2 l (11,300 psi x 2.118 in ), and each ear can withstand a load of 47,867 lbs. The safety factor is 5.9 for each ear. l l l 2-5 { c-e .,mr ,_m --,v,,-,m., ,y~,r,ee-,-,,-,,-%,,.~ .__r..._ ..,,.r.,.,.,___~%-

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/p j] ',,, .. t g 2.4.4 Tie down : devices (U~N 'j There are, s's two tie down ears attached to the jacket, previously described in 2.4.3. The following anal withysis Will demonstrate that these ears will comply the requirements. % t 'The tie down earn have been designed so that failure 4 r/ s ;i of the ear underJexcessive load would not impair ~, f i the ability of the package to meet the other require- 'O ments of' $0CFR71. This feature has been achieved by ) using a.less' strong carbon steel (C-1020) for the \\ [ 3 ears than that used for the jacket shell (A242). f 7 sTherefore, damages should be confined to the ears. OO.$ The following assumptions are made for the analysis: 'i I s (refer to figure.4) ,};'/'(i / ,I tJ '.,. (, 7 1. The 10g, longitudinal load is supported by tie d6wn lines 3 and 4. s gr, e' t 2. The 5g transverse load is supported only by ~ + '$ lines, 1 and 4 since lines 2 and 3 will not g support compression. ( 3 s 2*/OS O n kl \\ i 1 29 r .W4 h D' + A 0 Q ( ) C w S3

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3. The 2g vertical load will be supported by lines 1 and 4. U -4. Each tie-down device shall be capable of supporting the following loads: Sg = longitudinal direction 5g = transverse direction 5g = vertical direction .f f 26- / Es L / s N 5+ p l 1 I (a) (a) O I t ~ i f (b) (c) Figure 5 5. Assume weld is weaker than steel. 6. The forces are considered to act through ps the center of the drilled hole (figure 5). G 2-7

The resultant force on the tie-down device g was broken down into its component parts and then the weld stresses were found. &~ d' _t P f[ \\ r L ) %,,,, j th,*,, Q.'. ~ " % 4ss'N 4';>%/ s o (a) (b) ? 1 %.d: 1, ' ' '6'ib/ 6 (c) Figure 6 C' 2-8

a) Bending stress due to the longitudinal /~3 force-(Refer to fig.6b) V S = 3TPL B 2 2 1h (3T -6Th + 4h ) T - 2.0 P = 5 x 8100 lb = 40,500 lb L = 1.5 in 1 = 6 in h = 0.5 in S = 3(2)(40500)(1.5) B 6(0.5)[3(2)2 - ' 6 ( 2 )(0. 5 ) + 4(0.5)2] S = 17,357 psi B b) Shear stress due to the longitudinal force (Refer to fig. 6b) O S =P S 2h1 S = 40,500 S 2(6)(0.5) S = 6750 psi S-c) Tensile stress due to transverse force (Refer to fig. 6c) S =P T (h1 + h Il 2 P = 5 x 81,00 = 40500 lb by=h2 = 0.5 1 = 6 in O 2-9 i i

S = 40,500 T pj (0.5 + 0.5)(6) S = 6750 psi T d) Bending stress due to vertical force (Refer to fig. 6d) S = 3PL B y P = 2 X 8100 = 16,200 L = 1.5 in. h = 0.5 in. 1 = 6 in. S = 3(16,200)(1.5) B (0.5) (6) S = 4050 psi e) Shear stress due to vertical force (Refer to Fig. 6c) S = P -. S 2h1 S = 16,200 3 2(0.5)(.6) S = 2700 psi S O 2-10

A free-body isometric diagram of the tie-down device shows the following stresses: C l O l 17357 psi J4 f @a 6750 psi 6750 psi 5G h Y w x 4050 psi 2700, psi s', SS l / BAk 'A P e g Figure 7 A unit cube near point A, the location of the highest stresses, shows the total stresses and their direction. K N/ l \\ 3.1 Discussion The Model GE 500 package is basically a trans-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 noraml and hypothetical accident conditions. The maximum decay heat load shall not exceed 780 watts. 3.2 Summary of Thermal Properties of Materials Melting point Carbon steel 2750 F. Lead 670 F. () Stainless Steel (302) 2550 F. 0 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 of jacket 139 F. Outer shell of jacket 99 F. Ambient 80 F. () The GE Model 1500 package is larger, but of the 3-1 l

same design as the Model 500 package. The ~ cask outer surface-to-cavity distance is ']^) comparable, being only 1 1/8 inches greater v .for the Model 1500. The Surface Area for heat dissipation in the Model 500 is approximately 55% of the area available in the Model 1500; how-ever, the watt loading for the Model 500 is 25% of the loading for the Model 1500. _Therefore, it is anticipated that equilibrium temperatures for the Model 500 cask with an internal heat load of 780 watts would be approximately the same as those for the model 1500 cask. 3.4.6 Evaluation of Package performance It is expected that under the Heat Conditions 6 2 -(ambient air at 100 7 and insolation of 800 g cal /cm 2 on top, 400 g cal /cm on sides), the package surface temperature will rise, but that the cask temperatures, and certainly the temperature of the contents will not change significantly. -Likgwise, under the cold conditions (ambient air of -40 F in still air and shade) the package surface temperature will drop, but the temperature of the contents will not change significantly. Since the contents are in special form, there are-no internal pressures to consider. Thermal stress is t hs . minimal due to the materials of construction. 3.5 Hypothetical Accident Thermal Evaluation 3.5.1 Thermal Model The Thermal Model used was GE Model 1500 cask (Reference Certificate of Compliance 5939). That package was assemed using the General Electric Transient Heat Transfer Computer Program Version D-(THTD), which allows the analysis of the general transient problem; involving conduction, convection, and radiation. The program allows the thermal properties of the materials to be entered as a function of temperature -and the boundary conditions to be entered as a function of time. l The significant assumptions, approximations, and boundary conditions used for the analysis are listed below: 1. Fire temperature 1472 F. 2. Effective Fire Esmissivity 0.9 l~ (])' 3. Fire shield surface Emissivity and constant with temperature 0.8 I 3-2 w ---e .en+. n. ,-,~~v, ~r---- ,, + - ~ - ~ - n

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4. Emissivity of other surfaces 0.8 () and constant with temperature. 5. There is intimate contact between the lead shielding and the stainless steel shell 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 protective jacket. 7. There is negligible heat transfer by convection between the two shields of the protective jacket and between the cask and first shield of the protective jacket. 8. There is an internal heat load of 3,120 watts with a temperature profile as outlined in 3.4.1. Conditions 1 through 3 above are specified in 10CFR71. Condition 4 is quite conservative particularly for the stainless steel shell of the cask. Condition 5 is conservative since for most () 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-sulate the lead thus reducing its temperature rise. Conditions 6 and 7 are not conservative but rough calculations indicate that the effect of these assumptions may increase the temperature rise of the shielded cask only 10% t o 15%. Also, they are more than compensated for by the conservatism of condition 4, which may overestimate the temper-ature rise by as much as 60% depending on the condition of the surfaces. Condition 8 lists thermocouple recordings from a 3028 thermal watt internal load. T.he thermal properties other than emissivity were used as functions of temperature. 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 outer stainless steel shell of the cask was divided into two nodes. The lead was divided into several nodes. Finally, the cask cavity wall (stainless steel) was considered a node. (~') s_- 3-3 L..,
U ~ -3.5.2 Package' Conditions and Environment '() It is expected that-the package will sustain ~ minor' damage to_the protective jacket.during the free drop and puncture tests, and that the containment vessel will be virtually undsmaged. .Therefore, it is reasonable to. consider the resultant package, for purposes of thermal resistance, as ' essentially undamaged. 3.5.3 Package Temperatures The computer program calculations were run for a'30 minute fire. The_calcugationsindicateamaximum temperature of. less L than - 390 F for the lead af ter 30 minutes and no lead melting could be' expected. Al-though a. coast-up. analysis was not performed on this container,.the resulting maximum lead temperature, after equilibgating for forty minutes, is expected not to exceed 470 F. These results, obtained from an analysis _of a GE .Model 1500 container, will hold true for the Model 500 package. Appendix 3.6 contains a writeup of the analysis performed on a GE Model 100 package. It contains a graph _of temperature rise during the thermal tests and also a coast up analysis of temperature N-(?(d during the cool down period immediately following the test.: The Model GE 500 package is expected to perform in a similar manner, though at higher temperature. 3.5.4 Maximum Internal pressures Not applicable. -3.5.5 Maximum Thermal Stresses Not applicable. 3.5.6' Evaluation of package performance The package will not incur structural damage, breach of containment or loss of shielding as a result of the hypothetical accident thermal conditions. lhe temperatures reached by the lead are not high enough to cause the lead to melt - therefore shielding is unaffected. The steel components of the package do not reach temperatures high enough to cause damage. 3.6 Ippendix. Predicted Thermal Response of General Electric Shielded Containers during the 10CFR71 Standard Fire. 3-4 m
~~O 2~~
i EXHIBIT A [ I e f PREDICTED THERMAL RESPONSE OF 1 I GENERAL ELECTRIC SHIELDED i CONTAINERS DURING THE 10CFR71 !o W STANDARD FIRE l i i I 4 [ i I l l l 4 e 4 l i i I ._-. _ ___ _ _ _,..._.. ~, _ _ _
Introductir:n end Prebtsm Dafinition The following the*rmal analysis of the General Electric shielded shipping con. tainers w'as performed in accordance with 10CFR71.36, as described in Appendix B (3) to 10CFR71. The conditions of 10CFR71.3': do not preclude melting of the shleiding material but rather limit the dose rate allowable after the accident. The hypothetical accident involves a sequence of conditions involving: 1) A free drop through,a distance of 30 feet onto a flat essentially unyielding sur-face. 2) A free drop through a distance of 40. inches onto a verticle steel cylinder 6 inches in diameter and 8 inches or more long. 3) Exposure for 30 minutes within a source of radiant heat having a temperature of 1475'F and an emissivity coefficient of 0.9, or equivalent. For calculational purposes, 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.~~
o V The General Electric approach to this problem was to protect the shielded cask for future use while meeting the requirements of Appendix B to 10CFR71. Two primary design criteria were established for the protective jacket. 1) Provide maximum protection for the shielded cask during the required impact tests with a high confidence of zero cask weld damage as an objective, and 2) provide maximum protection for the shielded cask during the 30 minute fire with zero mclting as an objective, yet maintain compatibility with the internal heating load which must b'e dissipated from the cask during normal transport. Several methods of protecting the shielded cask during the drop and during the fire have been devised by other designers..The protection generally has been constructed of wood or combinations of wood and metal. Two objections to the general use of these deigns have been noted. First, while the wooden i^] ( Jacket does an execllont job ot protecting the ahielded can from the stru and i L-s. .s .. gs,ha <$jg( hene, No;, 70.'754-fhj,h)f,RQR '?-?.S O,5 D. ^ A,- w, g E x h ibit ' A * /- *.
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satisfactorily protects it during the drop, unfortunately, it also insulates the shielded cask during normal operating conditions. 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 become contaminated. Proposed Solution The design selecttd for the protective jacket consists of two steel enclosures which serve as thermal radiation shields during the fire transient as well as " crash" shields during the drop. The internal heat load can be dissipated to the ambient air by providing a path for natural air circulation through the pro-tective jacket during normal transport. The protective jacket analyzed is. shown in Figure 6. Heat Analysis Q The analysis was performed using the General Electric transient heat transfer computer program (THTD) which allows the analysis of the general transient problems involving conduction, convection, and radiation. The THT D computer-P It allows the thermal-program uses the implicit finite difference technique. properties of the materials to be entered as a function of temperature and the boundary conditions to be general functions of time. ~ The significant assumptions approximations, and boundary conditions used for - the analysis are listed below. .1. Fire temperature,1472 *F = 800*C, 2. Effective fire emiss tvity. 0. 9. 3. Fire shleid surface emissivity, 0.8 and constant with temperatureg, 4. Emissivitics of other surfaces, 0.8 and constant with temperature. 6' 5. Intimate contact between the lead shleiding and the stainless 2, teel b cask shell.-
1.. -

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Negligibla hatt trcnofer by conduction through the pipas used as 6. spaders between the cask and the first shield and between the ~' 7-)l ( shields. Negligible heat transfer by convection between the two shie '/ 7. between the first shield and the cask. Internal heat load of 400 watts with recorded temperatures as out. 8. lined,in Section 5.1. 2 (e). i Conditions 1 through 3 above are specified in Appendix B. Condition h k. Cond' tion conservative particularly for the stainless steel shell of t e cas d to the 5 is conservative since for niost shielded casks the lead The presence of a small gap between the lead and the stee outer steel shell. is e. Conditions would tend to insulate the lead thus reducing its temperature r 6 and 7 are not conservative but rough calculations indicate that f the shielded cask only these assumptions may increase the temperature rise o i f 10% to 15% Als'o, they are more than compensated for by the cons ,e by as much as 60% V condition 4, which may overestimate the temperature rise 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-symmetric con For the analysis using THTD, the packaging was divided radiation solution. The nodes into 15 nodes or regions as shown schematically on Figure 7. gradient becoming were made smaller in the region of the maximum temperature The protective jacket shields were each progressively larger near the center. The outside stainless steel shell of the shielded divided into two nodes. The first two lead nodes at the outside surface was divided into two nodes. h li. The remaining <g of the cask were made the same thickness as the ca. k s e a V L lead was. divided into six nodes of equal thickness... ..' P'oi.N . Decket No.' _ ' 70 74' - Q.15d 1:Mo'.INhiS't AJ x..*: q;. yyi iW Appe, 4 Lit.D gy.',
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Shieldad Cack and Protective Jacket Dimensions A typichl General Electric Shielded Container-Model 100 was used m. (~'b for the thermal analysis. Shielded Cask Dimensions Inside Diameter 7 5/8 inches Steel Thickness 1/3 inch Lead Thickness 5 7/8 inches Steel Thickness 1/4 Inch Outside Diameter 201/4 inches Protective Jacket Dimensi'ons First Shield O st t Tatc* t/4 t=ca Outside Diameter 221/4 inches Second Shield Steel Thickness 1/4 inch Outside Diameter 251/4 inches Results and Conclusions ~ The results of the analysis are shown on Figure S. 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 cmissivities), the design provides a large margin of safety duriag the pro- -x j posed fire accident. Since no lead melting will occur the snielding wculd net . -J '3 '. 5 'A License No. - i SNM 960 -: ".. Doch At No. 70 '754 ' P - . y,' Sect.le! EihibiEk * py' '+ s -, ~. =,. : _ ;. ~.. ; 5: y v - r.
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_ _ _ _. - _ _ = ba reduced end maximum safety would be maintained. The 220*F temperature rise was based on axi-synnetric geometry and O boundary conditions. For the two dimensional problem (represen:ed by a single package) a simplifying idealization applying superposition was made to arrive at the maximum lead temperature rise of 440*F. This is a conser. ative estimate of the package performance during the specified fire. Again, since no lead melting will occur, the shielding will not be reduced even in the event of sheath rupture and maximum safety will be maintained. O l 5 V Decket No. 70 754 '- ' s.c,. k,'Ek hlb t_t A - _?./pfgi3 License No. SNM 960 tembe r 16,3 ~':68,: ;*s.. '%,.s:.,; ppendIx, *l;,,,. _.*glg:6- . l. . :e '. :' l-s. i>
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. o.. c ~ O Novec.ber 13, 1968 ^ . e 1:r. Blaka Brown Irradiated Fuals Branch Diviston of Haterials I.icensing U. S. Atomic Energy Ccanissica Washington. D.C. 20545 0-
~~Dear Blake:~~
~~The enclosed data', including 1) a siatariaU propertime table, ')~~
2) a physical model,of the container with noda locations,

3) tha 'results of a coast-up analysis, and 4) a stacament
~ ~' ' v-explaining the choice of'the radial. direction for the bact analysis, ars submitted in accor:!ance with the telecon batuaan ?!azars.'. Don Brown, Walt King, and your= elf. ..}.,... . ~... If additions 1 data or details are requirdd,' please let ca. know.. - ~ 5incerely. - .7... . g;... Walter H. King ~ ..~ W fafierator-L.ic.en.sius.....'. .c;... ....... ~ Cy.. . m... c,... s..,.'.,.- ... 3,.
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L93tfrJd~ l5 tis &FiTRl. Atzmis psw:r Eq11pmost D1pt. EN21NEERINS CALCULA710N SHEET DATE ~ ~~ SHOP ORDER NO. E'CoAE iA W +>^Eu? 3(' SU8 JECT SY .SHEE1___ _ OF__. , SutELtEh Cebmium-nelic-2 4 TMT Fmc% Ce-1:n Am s ts mAmom' MBbE h w Micks.*F Tmt: bmna, ' Timt = 3.c msu, 'hc c loc 945 M56 '~ No %54 556 436 '953 -- 434 gsq ~ 3tt 39t \\% 334 .O a6 O ~ 334 - \\ st 335 \\to 3% 6 r - nS SSl et q4 3 64 \\u 3M i t TM 33 t. . \\ p.. .zy yss- .c L l ? tu' . 9o1 8 M3 4c6 'I i I ' l3l (6 b9 460 c,?' \\3o 16 bel g 34 \\3M .i k. .s, . \\ s M....... i.. . WS. . j; : :- :: s ..,t
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i l t y- ~. - - - 3. General 21cetric shielded container - Model 100, liurber 104 Cash Ta=paraturs Comet-Un after Fire Transient ~ Using the temperature distribution at the end of the fire fro = the TET firs transient run, tha 104 cask was allowed to equilibrata for forty minut.es, usin, assin the TNT computer code. h resultant temperaturas in various parts of the cask versus time are sho.:n in rigures 1 and 2. The significant sarc=ption.: and approximations are: 1. Ambiant (sink) ' temperstare. 130*r Effoetive sink enh.ssivity. 2. 0.9 3. Fire shield surface emissivity. 0.8 and constant with temperatura. ~ 4. E=issivities of othat sursaces. 0.8 and constant with te=perature. 5. Intimata cont =cti hetween tha lead shisiding and the stainless staal cask shall. 6. Nogligible heat ersasfer by conduction through the pipes used as spacers betusen the cask and the first shield and between the tuo shields. (O 7. h slistal heat transist 67 conv etion set enn the t o v shields ar.d between the first shield and the cask. 3. Iuternal heat load of 400 watts with tamperature distributica as calculated by T:IT computer code at the and of the 30 micuts fire. Condition: 3, 4 and 5 are not co:nrervative for the coast-up, but thess aonditions. vere imposed and vera conservative for the fire transient, since the temperaturen' actsined at the end of the fire would have becc consid:rchly lower wi:h lowc; i caissivities. Also, natural convectien from the outside fire shield was not - allowed bat,would in fact occur to some extent, n=d is conscrvative. In order to determine the emeperatura distribution in the 10L cask under normal' transport ecoditions, a test'was run using a Co660 source. The ca:rk waa. - .J i instru=cuted with 5 chtsrel-alumel stainless stcol cisd therracoupins W.ich isra. : taped to and sprung' against the surfaces to ha otazured. A si:,cch thermoccuple was used to censurs a=hiont air teapersturn. A Co-60 source was placed in the cash cavity with s. lead lince, and thi. 25,003.C2. syzt.:s '~ was allowed to equilibrata for a'ppronizataly 5 days. The terperatures obtaincd j." were as followst. " ', l J '. .V ; } s n q- . L ': -.a..
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t=ternal shall of cask, bottes 156*F Protective,)acket, outside surface, top 99'F Protective jacknt, outsida surface, side 95'F hr.biant ta=perature 76*F 4. Choice of T:sdial Directica for Meat.a.nn!vsis In reply to the question as to why the TUT fire ersnsion: anclysis couaidared the radial direction rather than the top or bottom of the ca:h: This uns done principally to allow consideration of the lead liner, which would not be included if the cask were analyzed throu,$ the top or bottom. Also, the di. stances involved are somewhat comparable; the sadial distance bein; the chortest by about two inches. I l l. .) l ^ I \\ t I l .f,. \\ r. l ,. ~ <... -., :;. _...n... ~- .. " - c, A y-,.a,.,:;. p'.. '..*. :7.; ; J.- l.-
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~4.0 Containment g4.1 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-design specifications are summarized on Drawing 2123246: in Appendix 1.3. 4.1.2 Containment Penetrations The cavity is penetrated by a h inch 0 D.x 0.065 inch wall. stainless steel tube gravity ' drain 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. 4.1.3 Seals'and Welds A silicone rubber gasket bonded'to an aluminum . backup plate provides a seal between the cask and its lid. Reference drawing 129D4690 in Appendix 1.3. - ()F Cask welds are specified on drawing 212E246, . Appendix 1.3. 4.1.4 Closure The closure-devices used for the containment vessel are 6 equally spaced 1 x 8 UNC 2A steel bolts. 4.2 Requirements for Norma 11 Conditions 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 Pressurization within the containment vessel cannot occur. The radioactive material being trans-ported is in special form. 4-1
E J4.2.3-Coolant Contamination .- y Not applicable. -J 4.2.4 Coolant Loss Not applicable. T 4'. 3. - Containment Requirements for the Hypothetical Accident Conditions 4.3.1: Fission Gas Products Not applicable. -4.3.2 Releases of Contents There will be no release of radioactive material from the containment vessel. d 4-2
m-5.0 Shielding Evaluations c 5.1 Discussion and Results d. The Model GE 500 package is designed to 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 removable shielding is in the cask lid. TABLE 5.1
~~SUMMARY~~
OF MAXIMUM DOSE RATES (mR/hr) 3 feet from Package Surface Surtace of Package Side Top Bottom Side Top Bottom Normal Conditions Gamma 60 60 60 7 7 7 ~ ,^\\ Neutron .V Total 60 60 60 7 7 7 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 O 5-1
5.2 Source Specification L7 5.2.1 Gamma 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 as a point source with an output of 1.35 RHM/ curies. 5.2.2 Neutron Source Not applicable 5.3.3 Model Specification 5.3.1 Description of the Radial and Axial Shielding Configuration i m m j m /oW /I' F O O e to" ~ K a llY1" /0 if \\ U l Figure 10 e O Q) 5-2
r 5.3.2-_ Shield Regional Densities () Not applicable. 5.4 Shielding Evaluation There are ru) 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. before acceptance. A Victoreen 491 survey meter is used. -Readings are taken at the package surface and 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 gy 45,200 curies 55 mR 6.0 mR v 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 below the limits of 10CFR71. O 5-3 i t
6.0 Criticality Evaluation
~~O Not applicable.~~
I l I 4 S l i. O d l !O 6-1 i t .._.-.._.----...-..._-._.m..,-_.,-_
3 7.0 Operating Procedures \\ ~' 7.1-7.2 Procedures for Loading / Unloading the Package The following general procedure is used in the handling of the package. a. Survey the package dose rate in accordance j with internal procedures to assure the levels j do not exceed acceptable limits. L i b. Use appropriate capacity material handling equipment to transfer the package assembly to a clean area. The total package assembly weight is 8100 lbs. Remove the wire security seal (item 6) located c. at the base of the jacket. d. Remove the six bolts (item 7) from the base of the jacket. c. 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 lugs (item 3) and appropriately rated slings. g. Place the jacket in a clean area. h. Survey the external cask surfaces for radioactive contamination. If smearabic contamination is detected, follow appropriate internal procedures for contamination control. 1. Lift the cask from the jacket base using the cask lifting cars (item 8). Transfer it to the shielded facility (hot cell) designated for dry loading / unloading operations. J. Remove the cask lid bolts (item 9) and store to irevent loss, contamination, or damage. The aolts are required for reassembly. k. Monitor the, cask dose rate and carefully remove the lid from the cask using the cask lid lifting eye (item 1). (D m 7-1
1. Inspect the seat 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. m. Transfer the radioactive materials and associated 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 prescribed limits. p. Install and tighten all lid bolts to assure a good lid seal. q. Remove all old labels from cask. Apply new " FULL" or " EMPTY" label, as is appropriate. Tape the interface between the cask lid and cask r. body with fabric-backed adhesive tape for contami-r^T nation control. U Survey the external cask surfaces for removable s. contamination. Decontaminate to reduce smearable contamination Icvels to below DOT limits. t. Return the cask to the protective jacket storage area. u. Inspect the protective jacket, base, and bolts for damage. Notify AMS if any damage requiring repair or replacement of parts is observed. v. Place the cask on the jacket base, w. Align the cask on the base so the fireshield will position over the cask lifting cars and align with the bolt holes in the base assembly. x. Position protective Jacket on Jacket base. y. Install the jacket bolts and tighten. z. Fasten anti-tiedown covers to jacket lifting n eyes. Y] 7-2
aa. Remove all old labels. Attach appropriate 7_() shipping labels and security seal. The container label contains two descriptions of contents, as follows: Radioactive Material, Special Form n.o.s. or Radioacitve 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) and complete shipping papers as required by applicable internal procedures and government regulations. 7.3. Preparation of an Empty Package for Transport The following general procedure is used in pre-paring empty package for transport, a. Survey the external cask surfaces for removable contamination. Decontaminate to reduce wipable s (_ contamination levels to below DOT limits. b. Verify that the cask lid, gasket and bolts are all in place. Apply an ' Empty' label to the cask. c. d. Inspect the base and bolts for damage. protective jacket, c. Assemble the package. f.- Fasten anti-tiedown covers to jacket lifting eyes. g. Remove all old labels. Attach appropriate shipping
~~labels, h.~~
Mask out the words ' Radioactive Material, Special Form n.o.s.' on the container label. ! ($) l 7-3 i i I L
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 performed on an as-needed basis. .8'.2.1 Structural and Pressure Tests -None required. -8.2.2 Leak Tests None required. 8.2.3 Subsystems Maintenance (n-) 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. 8.2.5 Shielding i Not applicable. Routine surveys in accordance with transportation requirements are adequate. 8.2.6 Thermal 'Nxe required. Thermal degradation does not occur. l 8-1 t ._}}

ML20132F583

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Dear Blake:

SUMMARY

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