ML19343B140

Submits Data Re Cesium Source Capsule in Connection W/Request to Amend Certificate of Compliance 5796,changing Cs-137 to Normal Form.Supporting Documentation Encl

ML19343B140
Person / Time
Site:	07105796
Issue date:	01/04/1980
From:	Pengov C PICKER INTERNATIONAL, INC.
To:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML19343B137	List: ML19343B136 ML19343B138 ML19343B139 ML19343B140
References
17930, NUDOCS 8012110391
Download: ML19343B140 (86)

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PICKER CORPORATi3N 6671 BETA DRIVE / CENT. BLDG. MAYFIELD VILLAGE. OHIO 44143 i i wJ January 4,1980 Charles E. MacDonald Transportation Branch United States Nuclear Regulatory Commission Washington D C 20555

Dear Mr. MacDonald,

I have been in communications with Mr. Dick Odegaarden relevant to our request for amending Certificate of Compliance No. 5796 changing Ceslum-137 to normal form and submit the following data concerning the construction of the Cesium Source Capsule. 1. All Cesium Sources were fabricated by O.R. N. L. (Oak Itidge National Labs.) using capsule parts supplied by Picker. 2. The Cesium source material was encapsulated in two scaled stainless steel shells then put into the tungsten source holder. See the attached draviing for construction. ,C), 3. The inner and outer containers were constructed of type 316 LC stainless steel. The wall thickness is.0G25 inches thick except for the window which is.020 inches thick. The covers are type 316 LC stainless steel.002 inches thick, IIell-arced welded to the container. ~ 4. All welds were made by O.R. N. L. 5. Leak and wipe tests were made by O. R. N. L. in accordance with the AEC/NRC regulations in effect at the time of construction. G. Picker had also performed wipe tests. The Picker wipe test consisted of wiping all the external surfaces of the sealed sources using absorbant paper which was moistened with water. The wipe was placed in a well counter and counted against a standard. All sources were found to be within the regulation requirements in effect at the time of the wipe. All records currently reviewed indicate wipe results less than.005 uc. Some of the present isotope facility personnel believe the regulations at one time may have required.05 uc or less of removable contamination. l(i 8012110 J . P.I C.. K.... E,R... t_ ~

January 4,1980 Pzge 2 Prior to future shipments of the Cesium Sources, wipe tests will be conducted on each source in the following manner. 1. The Cesium Source will be removed from the Cesium head and place in the source exchange container. 2. The source cavity where the source has been installed since installation will have all the surfaces which the source *vas in contact with wiped with moistened absorbant paper. 3. The activity of the wipe will be counted and compared to a standard using equipment which is capable of detecting less than,05 te of contamination. 4. Shipment will be made only if the wipe results are less than.05 uc of contamination. Your expeditious handling of this matter will be greatly appreciated. Sincerely yours, W h)f AM.engbh Safety Officer Special Systems Division Picker Corporation cc: R. Arndt - AMS W. Ashby D. Churchill K. Draggman N. Kelbicy - AMS R. Locker W. Mog J. Stickney l l ba

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. _ _.. __~ s. l' arch 20,1979 Picier Cerperation (671 4 :a Drive Clevel. sed, OM 44143 StT.YE CT_: Uater Spray Test Conducted en Two (2) Cobalt Overpack Shirping Centainers g: Ficker Corporation P.O. No. L67670 Perron Laboratory Project No. L 4020 Over the period 7 February 1979 through 9 February 1979, two (2) ceFalt overpsck shipping containers, asse-bly nt:.ber D-181361, serial nu *.er 107 and assembly nu ber D-181375, serial nun 5er 315, vere subjected to vater spray testing in accordance with paragraph 711, section VII of IAEA Safety Standards, dated 1973. b TEST E0rIT:'ENT The veight of the two cobalt overpack shipping containers vas nene...ed with a system consisting of a Le Bcv, nodel 3124, serial nutber 714, load cell, with a 5000 lb. capacity cnd a BLH Electronic, Inc., redel 120 C strain indicator. The Icad cell and strain indicator systen were calibrated to ir.dicate lead in pounds. Calibration was perforr.ed on a Ealdwin-Tate-Encry electro-rechanical universal te= ting rachine, type BTE-64, serial no. (401264, with a 5000 lb. capacity. Ecad-out incorporated in r.tchine is a Tate-Er. cry indien tor with four re..ges of 50, 2'*0, 1000, and 5930 lb. res;.ectively, with N.B.S. traceshle accuracy of + 0.5% of reading.

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'n.c v.-ter spray t est was cendt'eted in accordance with paragraph 711, wetion VII of I/.EA Safety Stendards as follo.*s: I ( C \\ _..._ _ 3 _. .d4 iglyd' h( j / lll.'RRON. ll 5IING l \\!M 1R \\1ORil 5, INC y a u. w w.n.. v. .........<.m.i..i..... a. N a c* ~ *. * ? lt t% s ',e. T i, 'a

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• March 20, 1979 pb 1.

Lead cell was connected r>etween overhead crane and test sanple. Farple was If f ted conpletely off the ground with the cranc su:h that the entire weight of the sample was supported through the load cell. The strain in the load cell was monitored on the strain indicator and the weight was read from the calibration data and recorded. 2. ' spray nozzle vcs attach'ed to the outlet of the water .71.e to disperse the vater cpproritately uniformly ever the entire surface of the sc=ple. The spray ner:le was then positioned so that the water spray i: pinges upon the specimen at an angle of approxinately 45* from the horizontal. 3. %e water was turned en and the water spray was collected and censured. The water flev ves adjusted until the ar.ount of water collected per unit of ground area was approxirately equivalent to a rainfall rate of 5 cm. per hour. 4 Subsequently, tanple ves pesitioned under the water spray and oriented s i:h that the greatest arount of surface O area was a: posed to direct water spray, as illustrated O. in Tigure 1,1.ppendix I. 5. Le conditiens d< scribed in procedure steps 2 threur,h 4, above, were rsintained stcady state for a tir..e period of at least one hour. 6. Subsequently, water spray was turned off and the exterior of the overpack shipping container vcs.!ried vith com-pressed air and paper tcr.:els. i 7. I cediately after exterior drying, the shipping container vas reveighed using er.actly the same tiethod described l in procedu;e step 1. This final weight was compared l vith the original veight of the container in procedure l step i to cc te in the ar ount veight gained due to . ater absorpt 'on. 8 Prc.cedure steps 1 through 7, above, were rer ated three coditionni tires so that. ich shipping cent.iner was a:pesed to ti e test paramtcrs tvice. Le resulting bernses in weight were averaged for each shipping rentainer. o. P00HRlagt I11 RRON 11 SIING I AR('R \\l()Ril S, INC 7 p'. ,. u n w... m.i n a.v.....-..,. m n o n.-

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1 1 Structural Evaluation. 2.0 2.1 Structural Design. Discussion. 2.1.1 The basic structure of both Overpacks consists of a welded steel framework composed of steel angle iron covering all Between these a laticework of steel edges and corners. strap material stiffens the frame and protects the contents by preventing entrance of any foreign protruding object 6" This entire framework is lined with in diameter or larger.

1. 16 gauge sheet steel which will absorb energy from any impact as well as be.ing a deterent in case of a flash fire.

A cubical liner composed of 2" x 4" hardwood maple blocks bolted together with tie-bolts to form panels, lines the entire case to form an impact and heat barrier. The source capsule then is mounted and secured within this In case of structure and within its own carrying container. the 181375 pachage this container is the Irradiator Machine Head which acts as the carrier as well as a shield for radi-In the #181361 ation and is an approved and licensed vehicle. package the shipping and exchange container head serves the same purpose and also is licensed for carrying source capules. [ )# Both of these internal carriers contain tungsten and large \\-- amounts of lead which are contained within a steel or brass shell and completely surround the source capsule. Design Criteria. 2.1.2 Calculated design a:talysis to follow will show that under normal conditions of transport there would be no release of ( There are no gases stored within these radioactive material. containers and no coolents are used to cause leakage and damage to the package nor contents. The heat dissipating qualities of the contalusrc era sufficient to radiate off would be received to maintain a temperature more heat than well below the 180 limit under normal conditions of 130 F and full sunlight. Calculations to follow show that hold down devices within there packages will withstand 10g forces with a safety factor The steel angle-iron framework, without the of 1.01 and 1.3. j l added suoport of the steel straps and wood liner, will with-stand a 5g load with a safety factor of 1.9. An external pressure of 25 psi on the Overpack would be re 'sted Construction of the overpack will with a safety factor of 9.4. allow for expansion and contraction well beyond the limits of Two Overpack Containers were water spray normal conditions. tested by an independent testing laboratory in 1979 and shown (T to comply with the 1973 I.A.E.A. safety standards. The tests (\\_ l substantiated that packages loaded with radioactive contents were certified by the National Campetent Authority of the f 7 i

O Unitied States as meeting the regulatory requirements for type 3" packaging radioactive materials as prescribed inI.A.E.A.regula51nsandSS49CFR173.393 band 173.394 (c) (2) of the USA regulations for the transport of radio-active materials. Calculations for a 3C foot drop test reveal that the basic carton would survive in-tact. In the case of a 45 angle drop on top, the pick up eyes weald be damaged and probably would break-off. The most important requirement of any such designed package is to retain structural integrity and contain shielding and radioactive material in their respective places for both normal and accident conditions. Accident conditions could include an impact which will be later discussed concerning a 30 foot free fall of the package to an unyielding flat surface. The package maybe subjected to fire and this is discussed later with calculations for heat absorbtion when subjected to a 1475 F fire for 1/2" fall of the packages with its total weight upon the end of a 6" Dia steel bar. 2.2 Weights and Center of Gravity The weights of the individual components and total for the packages may be found at # 1.2.1.1.9 for #181375 and # 1.2.1.2.6 for package # 181361. Center of gravity cf # 181361 overpack and contents is 26.3" bove the floor. Center of gravity of

1. 181375 Overpack and contents is above the floor.

Weights and Centers of Gravity for weights refer to sections I 1.2.1.9 and 1.2.1.1.5. For centers of gravity l l 181373 Package 181361 Package l -K- -A h- +e-t-74 [eh:2 [+] ce C9___ --- y 4 28 g 9 2'1, I 8 l Jf I I v /s/ -,/s a r/a e an 8

e .o 3 - t Screw and Bolt Sheer Areas P Coef ficient Coefficient Tenelle field Thermal of Radiant Heat Heat Modulus Pbdulus Melt Crush Thread Sise Shear Ares Material Strength Strength Linear Heat Fais. Transfer Absorbtion of of Point Resist. 7 2 BTU-In. BTU /Lb. f* Ruptive Elasticity F" LB Perin Am. Std. IM In./f*/In. Ft.{Hr. Hr.-Ft.{I Expanoton BW PSI PSI /f* L4 Perin E 1/4 - 20 .0318 5/16 - 18 .0524 a 3/8 - 16 .0775 6 1/2 - 13 .1419 3/4 - 10 .334 ( A.I.S.I. -6 1020 Steel 65,000 43,000 6.3x10 65 31n .11 BTU 30x10 2550 { 6 A.I.S.I. 30x10 2550 i e 1045 Steel 59.000 6.3x10-6 65 n E. Sheer Arese Tartoes Articlee 7 Est Rolled 28 to Structural 30x106 2550 Article Sheer Area 4 65 4 Steet

l Crede #1 1 1/2" die.

1.23 I solte 60,000 55,000 tie bolt o* 1/4 x 3 x 3 1.44 I Soc. Need ansle Bolte 110,000 85,000 14 to Besse 20,000 0.1x10 715 09 17 10 1650 { 6 4 6 031 1x10 620 Lead 10.200 6 1.58x10' 1.8x10 parattet Wood 2.8x10-6 '1.2 .6 Maple Merd to arain thod 2.8xtu 'O Yellow Pine 1.162 .171 Air flW per FT. Hr. (Dez.Renkin)' 2 Stefan - Boltzmann Law (Radiant Heat Trennminston) = q = CAT ; where c = 0.I 71 x 10-8 4 460" Renkin = # Fahrenheit 4

\\ 2.4 General Standards for All Packages. The general standards for all packages, as specified in 10CFR 71 71.31, are complied with as demonstrated in the following paragraphs. 2.4.1 Chemical and Galvanic Reactions. Since the primary materials of construction for the overpack con-tainers is mild steel and hardwood maple there would be no signifi-cant galvanic nor chemical reaction among the packaging components. 2.4.2 Positive Closure. Both Overpacks (#181361 and #181375) have positive closures which require the removal of screws and nuts respectively in order to separate the cover from its pallet base. These details are described more fully in sections # 1.2.1.1.6 and 1.2.1 ?.5 of the application. 2.4.3 Lifting Devices. Both Overpack covers are equipped with lif ting ears which are designed for lif ting the entire packages weight or just the cover itself as for packaging or unpackaging. Skid runners are previded under both Over-pack pallets to faculate. See reference drawing #181361 and #181375. 2.4.3.1 Lifting Devices for #181375 Overpack Container. The container is provided with four lifting ears at the top, one being for each side. Their location provides a balanced and stable load when the empty or full container is b2ing lifted. l l l 2.4.3.1.1 Calculation for " factor of safety" using only one of four pickup l ears #181375. l l The followingcalculation was made to show that a large factor of safety was built into their construction. Should one inadvertently pickup the entire load using only one of these lifting ears, the load and operator would be safe. Assumptions: 1). One Ear lifts all the weight. 2). Ignore the 3" x 5" triangular gusset for this analysis.

• (o
• 2 3/4" Dia.

t L l [ In A l A7 __\\ Where: S = Unit Stress in Pounds Per Square Inch. 3_, P = Load (or in this case the total 6 et + 3

• package weight in pounds)

A = Cross Sections Area g,,,,,,, y,,,,,, of Metal in Lifting Ear; Section A-A l 3325 Lb. = 2728Lb. S = P 3325 - Lb. = (6.00-2.75)(.375) (3.25) (3.75) 10

35,000 PSI

• Yield strength for 1020 Hr. Steel

= 12.82 35.000 PSI Safety Factor = = 2728 This exceeds the "Three Times Yield Strength" as specified in U.S.N.R.C. 71.31 C-1. In addition the Side guskets will provide additional strength and the unit is normally transported by four of these ears instead of using only one. 2.4.3.2 Lifting Devices for # 181361 overpack Contair.er This container is also provided with four lifting ears at the top. Two of these ears are at two opposite sides 2.4.3.2.1 Calculation for " factor of safety" using only one of the four pick-up ears 181361. The following calculation will show that this con-struction has a large built-in factor of safety. Should only one lifting ear be inadvertently used, both the load and operator would be safe.

• 4 7 'Z,'Ds A.

,f / 1). One Ear Lifts all the Weight. 9': 2). Ignore the 3" x 5" Triangular I i weld ',.. set for this analysis. k_ 4_.-. W ~ 3" 5* i E= 4000 Lb. 5,333 PSI A-A = A (4-2)in. (.375) in. 59,000 PSI * [ Yield strength for AISI 1045 Steel = T/fffA VGffA 11.06 l _59.000 Safety Factory = 5,333 l This exceeds the "Three Times Yield Strength" as specified in U.S.N.R.C. 71.31C-1. In addition the welded side gussets will provide additional strength and the unit is normally transported by four ears rather than using only one. Ryerson " Stocks & Services" Data Book, Copyright 1976, Page 83. 1 b 11

2.4.3.3 General Strength of Lifting Devices. Paragraph 71.31 G2 is satisfied for both Overpacks #181361 and

1. 181375 by calculations in part 2.4.3.1 and 2.4.3.2.

Paragraph 71.31 C31;oes Not Apply. The lift ear's cross section as co= pared to the vertical supports total cross section of the bulk package are in a Ratio of: 6 in/ .166 For #181375 is 36 in = 4 in/ .108 For #181361 is 37 in = Therefore the overpacks is at least 6 and 9 ti=es as strong respect-ively as the lifting ears of respective Overpacks # 181375 and

1. 181361.

2.4.4 Tie Down Devices. 2.4.4.1 Tie down devices for #181375 overpack container (Contain=ent for shielded irradiator eaching head). The shielded irradiator =achine head and its co=ponents represent the =ost weight in this package (2125 pound). Thus the brackets which secure this device will be subjected to the most severe stress under abnormal conditions. The =ost severe case would be when an end force of 10G is applied as shown. F-The brackets would pivot and apply M~-87?~~ ~ a tensile force on two of the 3/4-10 Hold Down Bolts (one of the bolts & se --e-e-- -E from each bracket). G '*/ 'y/4 //// g Where: e 'Jp 2125 lbs. Wt. of Container & Contents f' Fg = 10 g (F ) F = 10 (2125 = 21,250 Lb. = Tension of (2) Bolts + (9) in (21,250 Lb.) = 25,500 Lb. 7 1/2 in. Where: .302 in.2 Area of polt at Thread Root Dia, is 42,219 PSI ST = 7 = 25.500 = (2).302 in.2 Mini =u= tensile strength ot Grade #1 Bolt is 55,000 PSI

• The Safety Factor for A 10 Times gravitational load is:

1.303 S.F. (10G) = 55,000 = 42/219

• j Marks Handbook, 4th Edition, Table 32, Page 909.

Industrial Engineering Institute. 12

2.4.4.2 Tie Down Devices for #181361 Overpack Container. Containment for Shipping / Exchange Container F The Shipping / Exchange and its components + represent the greatest weight in this + 7 package (3000 pounds). Thus brackets which hold this container and its 4" fasterners are subjected to the most servere stress under normal conditions. ( g, g' 7 The most servere case would be a side force) i. i. 3 of 10G applies as shown. id d } The entire load would tend to pivot the brackets and apply a tensile force of the two 3/4-10 Hold Down Bolts. 2924 Lbs. F = H FH (10) g F = 29,240 Lbs. 2924 (10) F = = 35,987 Lb. 29,240 Lb. (16)1n. Tension on Bolts = = 13 In. Where: Design strength area of A 3/4-10 Bolt is.334 In. 2 Bolts (.334 In.2)53,872 PSI 35,987 Lb P S = = = A Minimum Tensile strength of Grade il Bolt is 55,000 PSI. The Safety Factor for A 10 times Gravitational Load is: 1.02 or will withstand up to A 10.2 G Load .F. 55,000 10G = = 53,872 In addition two 1 1/4" Dia. Steel Threaded Rods pass through both the Top and Bottom sections of the Overpack and through Both I-Beam of the Shipping / Replacement Container # 3320 AR Base. 2.5 Standards fet. Type "B" and large quantity packaging. The standatds for type "B" and large quantity packaging, specified in paragraph 71.32, are complied with, as demonstrated in the following paragraphs. Gross 2.5.1 Load Resistance: Overpack i Dimensions Weight Overall Including Box Only without Pick-up Eyes & Sitds Skids & Pick-up Eyes k 1423gide 4000 H

1. 181361 39"gx 39.5"yx 48"H

Gross Weight O

1. 181375 37'y X 40'yX 41'{

32" x 41 x 28.5"H 1168 3325# Weight /In. Length

1. 181361 W = 4000' 39" 102.6 / In.

= 1

81. d / In.

1. 181375 W5" Since both Overpack Perimeters are constructed using 1/4" x 3 x 3 Structural Steel Angles, Only the mose servere case of #181361 will be anagyzed for 5 x Load "W".

513 /In. 5 x 102.6 SW, = = 2 WL Where: M max = j g 8 = 97,534 / in. 97,534 Msix = 513d/in x 39 in. x 39 in. = = 8 3*** I (1/4" x 3" x 3" Angu) 1.2 in. = Load Resistange: 175,561 / In. Smax = 97,534 3" .84") = Where: (2) Angles 3 (1/4" x 4" Straps) are on each long side 87,781 / In.2 (Considering 175,561 /In. S=ax = = ^"I ** 7 (2) Angles & (3) Straps Where: Yield Str. (Low Carbon Steel) = 35,000 PSI S.F. (5) = 35,000 x 5 = 1.99 87,781 Safety Factor Ryerson Steel Data Book, Copyright 1975, Page 88. Marks Engineering Handbook, 4th Edition, Page 456. Marks Engineering Handbook, 4th Edition, Page 460. l Load Resistance: Ne two angles at least two straps (1/4" x 4"# 1045) In addition - j plus a pa: ' eauge steel provide additional strength as well as 3 1/2 inch.. maple lining. O 14

O 2.5.2 External Pressure (25 PSI G) Since both Overpacks are made using the same type of construction only the most severe situation need be analyzed. OVERPACK MAX. AREA @ F (25 PSI G)

1. 181375 40 x 41 + 1640 In. 2 41,000 Lb.
2. 181361 39.5 x 36.5 = 1442 In.2 36,050 Lb.

Assume 25 PSI G Pressure 7 on one side and resisted f ff ffff g., by a Rigid plane welded // / / / / / / .to four 1/4" x 3 x 3 l [ 3 angle legs. v H39.5 i f Wl6Gnsn. Where cross sectignal area of a 1/4 x 3" x 3" 3,, angle is 1.44 in 5.76 In. \\ lk A Legs = 4 (1.44 In. ) = 2 f=47,4005.76 In.3 8,230 PSI on 1/4 x 3 x 3 An 'S = O, g p4. STRAPS Column Load wherg modolus of elasticity for steel is 30 x 10 PSI lhu MAPLE. 0 7E= 3.14 x 30 x 10 og = Pc = 3'280'000 PSI = A (L/c) (48/0.52) Therefore we have a safety factor of 9.4 and no buckling would occur. 2.6 Normal Conditions of Transport The package, when subjected to the normal conditions to transport specified in Appendix A to 10 CFR, Part 71, meets the standards specified in paragraph 71.35 of 10 CFR 71, as demonstrated in the following paragraphs. 2.6.1 Heat Thermal evaluation for the heat test is reported in Section 3.4 2.6.1.1 Summary of Pressures and Temperatures-Pressures would have no detrimental *ifect on these (Packages since they are not saaled. Normal external temperatures of 130 and subsequent internal temperatures of 167 F due to Solar heat and decay heat would have no effect. f')

9 2.6.1.2 Differential Thermal Expansion. Expansion of Overpack due to Heat of Sun & Decay, considering the expansion of steel frame and wood liner of Overpack. -6 Coefficient of linear expansion of steel = 6.3 x 10 in. per F. Coef ficient; of linear expansion of wood = Basically Zero. Expansion of fra=e from temperature manufacture assuming mfg. temp. = 75 F. -6 (167 F Skin Temp. - 75 F) x 39" length x 6.3 x 10 = +.0226/ expansion in 39" length. Expansion of wood liner from mfg. temp. = (167 F - 75 F) x 39" x 0 = 0/ expansion la 39" length. This difference would cause an additional loosness of.022 or.011 per side which is inconsequencial. A cold-hot and bubble test were performed at Herron Laboratories under file #M-5125, on Source Capsules. The capsules successfully passed tests of -40 F to 194 F and 203 F without leakage. There is no cooling system and therefore no pipes nor radiators to break nor liquid to escape due to thermal changes. 2.6.1.3 Stress Calculations Based on calculatxons in Sections 2.51 and 2.52, and past history of no adverse results due to fatique and no deformaties observed, no additional calculations are necessary. 2.6.1.4 Comparison with Allowable Stresses. Under normal conditions of transport there would be no release of radioactive material under Section 71.35-1, since a temperature of only 130 F and conditions in paragraph 3.4 would not have any deterimental effects. Also, thermal expansion and contraction under paragraphs 2.6.1.2 would basically have no effset on the capsule nor containers. 2.6.2 Cold Two source capsules were subjected to an actual test of -40 F and si=ulated still air and in shade. 3 tis temperature was maintained for (20) minutes af ter samples had reached stabili-zation. At completion of test these samples were allowed to return to ambient temperature. They then were subjected to a bubble leak test in water at 194 F and 203 F, see Herron Test file #M-5125, and passed successfully. There is no cooling system and thus there are no pipes nor radiator to break nor liquid to escape due to thermal changes. Contraction of Overpack steel frame due to -40 F. Expansion or Contraction = Temp. Diff. x Length x Coefficient of Therm. Exp. Assuming a manufacturing temperature of 75F. Contraction of Overpack steel fgame due to -40 F temperature = (75F -(40F ) x 39" x 6.3 x 10- =.028". ~ ~ 16

i O Contractionofwoodlinerdueto-40Ftemperature=(75F-40F x 39" x 0 =.0". Contraction due to this low temperature would" produce a negidgeable effect since the Overpack is a built up s ructure with a minimum air gap between the outer steel frame and wood liner. This temperature would have no effect on the operation of the package in view of the above. The inner package is normalized at indoor ambient temperature of the about 23C for about (24) hours prior to normal usage. Also, these packages are not normally used at these extremes of temperature. 2.6.3 Pressure. These centainers are not pressure vesseis and no seals are present to restrict equalization of inside and outside pressures. Source capsules were pressure tested for this requirement by Herron Laboratories under file fM-5125 and passed successfully. 2.6.4 Vibration Shipments made by the Picker Corporation over the past ten years have 2hown no ill effects due to vibration incident to transport. Source capsules were tested for this requirement by Herron Lab-s, oratoriec under file #M5125 and passed successfully. 2.6.5 Water Spray. Water Spray tests were performed on the package by Herron Lab-oratories under project L-4920 and passed successfully. 2.6.6 Free Drop of Forty-Eight Inches. This requirement is covered by a more stringent free drop of 30' under section 2.7. I ( 2.6.7 Corner Drop. Not applicable. This requirement is covered by the more stringent l requirement of a 30' corner drop under section 2.7. 2.6.8 Penetration. A (13) pound 1 k" diameter rod dropped from 40" would have no serious effect on the package considering the 1/16" thi'ck steel jacket and 3 5/8" thickness of hardwood maple. Refer to section 2.7.2 which has been calculated for a 40" drop of the Overpack and its entire weight onto the end of a 6" diameter steel bar. 2.6.9 Compression. This requirement is covered by a theoretical 5g load under section 2.5.1. [ T 2.7 Hypotetical Accident Condition. I'\\- / The package, when subjected to hypothetical accident conditions as 17

O specified in appendix "B" of 10CTR 71, =eets the standards in paragraph 71.36 of 10CFR 71, as de=onstrated in the following paragraphs. This application is a consolidated application for both Overpacks

1. 181361 and i 181375. Since these overpacks exhibit close si=ilarities in construction many of the foregoing analysis are applicable to both.

The following analysis concerns the differences which are unique to the #181361 Overpack. 2.7.1 Free Drop of (30) Feet. 2.7.1.0.1 Velocity and "G" Load Developed by a 30' fall. ~ v (velocity at i= pact) = N2gh height = N2 x 32.2 x 30' 44 f t. per second at time of i= pact = ) a3 unifor= declaration of the assu=irg a 3" defor=atijn (k ft. d 3632 ft. per sec. 44 ft. total = ass a= v = = 2h 2 x k ft. 3632 ft. persec.k= 1132 00 g loa g load a_ = = g 32.2 ft. per sec.' Therefore we will assu=e a 100g load to cover this require =ent. 2.7.1.0.2 Stress on-Hold Down Belts and Tie Bars. Since a 30' free fall will produce a 100g load caused by the Shipping / Exchange #3320AR container on its h61 ding devices would be: 'a'100g 0 (2924) = 292,400f load. = Considering shear stress on the (4) 3/4-10 bolts securing Shipping / Exchange container to its base. 'a'here a 3/4-10 bolt has a design strength of 110,000 psi. F S+ "A 218,862 Psi. 292,400 lb, = = 4 (.334 in.') Therefore these (4) bolts would break. Considering this shear stress on the (2) I k" dia=eter tie bars: 'alere these tie bars have a cross sectional area of 1.23 in,2 and were =ade fro = #1020 steel with a strength of 65,000 psi. These bars hold each end. F 292,400 lb. = 59,600 psi S A = = 4 (1.25)' T 4 Therefore these tie bars would hold and in turn would restrict I motion of the Shipping / Exchange container to within the clearance between tie bars and their clearance holes in skid, or within 1/16". 18 l

O Considering shear stress on the (20) 1/2-13 bolts securing top to skid on #181375 overpack: Where a 1/2-13 bolt has a designer area of.1419 in.2 per bolt and are made from material with a st.rength of 110,000 psi. 87,000 psi. 332,500 S = = = 20 x (.1419) Therefore these bolts would not shear. 2.7.1.0.3 Stress on Skids and Bottom Panel. Drop of 30' with the Entire Load on the Skid Runners at Impact Bottom area of (2) Skids for Impact. (37) Length (3.75) Width x (2) 277.5 in.2 A = 7,800 psi. parallel to grain 31" S Stress = F = SA = 7,800 (277.5) = 2,164,500 lb. M v Therefore the skids would survive this drop of [i 30' and resulting load of 292,400 pounds. "Ig,,, m f 3 Deformation of Skid at 100g Load

• 34 PL

= b E = _100 (4000, Pound)(7.5 Skid, Depth)Lb. - In. .006 In. = i 277.5 In.' (1.8 x 10" ~ 'In.') Therefore the screws which hold skid to frame and screws which l hold the head and hold down devices will have very little relative l motion and would survive this 30' drop. i Impact Load Transferred frem runners to bottom panel. The grain lay of maple wood laminationa is paralled to the lay of l l the skids. However, the bottom weldment is constructed of four 3/8" x 3" x 3" angles and six internal straps of 1/4 inch x 4 inch ) which form a " Basket Weave Affect". In addition, the 16 gauge steel plate is welded to the straps and angles. This construction is illustrated in Ref. Document 17 of original application. If 100g load is distributed over the (2) skid areas then load per In.2 1440Lb./In.2 100(4000} is: W = = 277 In Therefore the bottom panel will withstand this load. Since the bottom Feldment is more rigiditly constructed than the top, the top will be analyzed as a simple supported beam with resistance at the extreme n. ends and the relative head motion will be taken into consideration. [ The previous calculation shows the bottom construction will with-stand the distrubuted load of the skids. 19 ., _. -~

2.7.1.0.4 Relative }btion of Cobalt Head (Upside Down Drop) Nominal clearance between top of head and lower-inside surface of top Overpack is 20,375 - 19.188 = 1.187 in (1 3/161n.) where head height is 19.188". Therefore, there should be no collision between Overpack and top of head if top deflects k inch. The head casting wall is 5/16 (.312 in.) thick. go g Assume section A-A is a ring g_, 8 in, diameter. Assume section B-B is a ring 20 in, diameter ^A-A = D -D ( M-%.4) = O g 2 = 7.54 in 2 E ( 400-375)= 19.61n A = B-B 4 SAE 40 Brass Yield = 20,000 psi 40,000 psi Ult. = F =S (A) = 7.56 (20,000) = 151,100 :b. (^ F BB" y Therefore head can take a large external load prior to any permanent distortion. p 9 20

/^ In 30 ft. (Upside down) drop the machir.e irradiator head would hit the top panel. 90uMER nu l' f DOTTOM } ' it TTjl. ' I / 1 d I" 1%!!Ii. I d E -\\O 4 W HEA Ho.SCR. E-sy5+2' 8 -f E Hex.W sc.e.. E 1 L., ) ( f IjTole 5 j ' ll 1 3 ( la i O The inertia load of head will put a tensile strain on the four 3/4 - 10 x 6" hex bolts and 3/8 - 16 x 3/4 utuds. 3/4 - 10 Screw-Stress area = 0.334 in.2 each 3/8 - 16 x 5 3/4" Stud-Stress area = 0.0773 in.2 each l Total Screw-Stress Area is: l- = 4 (.334) + 4 (0.0773) = 1.336 + 309 = 1.64511n.2 F = 2800 (100) = 280,000 Lb.s 100G F yield = SY (A) = 55,000 (1.654) in = 89,375 Lb. Assume 4 inch working length of screw for deflection length calculations. l b = PL = 89,375 lb. (4 in), AE

1. 64 5 in' x 30 x 10 Lb. / in.'

= 7244 x 10-6 =.0072 in. Energy used = F ( d) = 89,375 (.0072) = 643 in.-lb. Unused Energy = 2800 (100)(12) = 3,360,000 in-lb.-0 l If the head breaks the tie down bolts, the head l will move 1.316 inch before it contacts with the hard 21

maple wood liner, which is backed up by the cover back weldment. From Page 49 it can be seen that the head has a high resistence to deformation based on shell rigidity and ignoring that lead fill will offer additional resistence. Assuming the contact area of head and wood is an 8 inch diameter circle: Then crush resistence of the hard maple panel will be: Fc=S (A) = ( 10,200 lb. _)( 8 TT )in.2 = 512,448 lb. in.4 4 The resulting deformation would be: d = PL = 512,448 (3.625) =.00121 in. [4 / 8'- T 30x10-6 AE \\ Energy used = 512,448 (.0012) = 620 in.-lb. 2.7.1.0.5 Energy absorbed by Overpack top if Cobalt head were to break loose (Upside-Down Drop). Assuming the wood lining in top would act as a simply supported beam. S=Mc 1 / \\ / / / I = bh3 = (36.25 (3.625)3. ,/ ,/ / 12 12 4 / / = 143 in 3 _] o 4 o O 4 29 L 3k ', [ 7 Beam formula for load concentrated at center M= g = P (32.875) = 8.219 (P) in. 4 4 c= 3. 625/ 2 = 1. 812 2 i l S = Modulus of rupture is 15,800 lb./in. for hard wood maple l 15,800 Lb. = (8.219) (P In.) (1.812 In.) l 143 in 4 l lb. ,,P = 15,800 in 2 (143 in') = 151,710 lb. (8.219) (1.812) in' Maximum deflection (Load @ Center) kW = PL = (151,710) (32,875)3 = 436,276 g 10-6 in. 48EI 48 (1.8 x 10") (143) i O 22

x Energy Usued = 151,710 (.436) = 66,145 in-lb. l Assu=ing the steel weldsent acts as a simple supported .s bea=: k x 3" x 3" Angle Iron cross section area = 1.44 in.2 I = 1.24 in' xx l-x4 STett. 4 MEAD h 3 WRD VLAPLE L x313 y i ' [y fuw wu 11-1, 'l j I i i \\ti 3 7~4 a 16 G A. STL. _847. T 'Ir l. Neutral axis of weldment from T-T. b 2 QUAN. SYM. AREA IN. t . : r -T (2) 2 x 1.44 = 2.88 .842 2.42 l (2) w 2 x 11.750 x.250- 5.88 .125 .74 (4) C 4 x.250 = 1 .125 .125 16 ca. 37(.062)= 2.29 = 2 12.051n .281 .64 3 3.92 = 0.32 3.92 N.A. = Mt-t = A 12.05 23 l

Deter ine Ina 2 2 SYM. 122 A d d M ,., ~ 1.n. .6 .45 ...ca . m 1., 6 e# C .37 5.38 .32.12=.20 . C#. .235 .62 1.00 .20 .C4 . Gl. _16 GA .01 2.29 . 01 .002 .004 2.24 a.wu 2.2!. e 1.03 = 3.27 in' I = ca M = PL = P (37.250) = 9.312 P S = 65,000 PSI L~1ti= ate Strength of Strue: ural Steel 5 = _Me I 65,000 = 9,312 P (3.00 - 0.32) 3.2712.' F = 65,000 (3,27) = S516 Lb. 9.312 (2.6S) .v2xi=u= Def1eeti = b M = PL3 =E516(37.25}} =.093 in. 45E I 43 ( 30 x 10') (3.27 in.') Energy U:: sed = 3516 lb. (.093 in.) = 792 In-Lb. O 69

Summation of energy absorbed on impact if the Overpack top acts as a simple supported beam and with the irradiator machine head acting as a concentrated load at center, and the resistance reactions are at the two outer edges of the top. MEMBER _ FORCE bDEF. ENERGY Tie Down Bolts 89,375 lb. .0072 in. 643 in.-lb. Wood Crush Resistance 512,448 lb. .00121 620 in.-lb. Wood As A Beam In Rupture 151,710 lb. .436 66,145 in.-lb. Weldment 8,516 lb. .093 792 in.-lb. 762,049 lb. 68,200 in.-lb. 30 Ft. Fall would cause a 100g Head Load 100g Force of Head = 280,000 lb. Since 762,049 lb. y 280,000 lb. It is unlikely that the head would penetrate the top. If it should, a force of 151,000 lb. would be required to damage the head casting near the top. The head may squash slighly -[ but the source wheel will remain in its relative position to the center of head. 2.7.1.0.6 Stress on Shutter Plug Components Due to Drop Normal to Shutter Plug Azis. This treatment will analyze the relative motion, within Overpack #181375, between the Head and Rotor Assembly and subsequent possible damage and possible reposition of the source. The shutter plug & rotor assemblies weigh approximately 250 lbs. The shutter plug & rotor assembly is held in the Head Assembly primarily by four 5/16 - 18 Hex. Cap Screws which are on a 41s inch Bolt Circle. Force on 4 bolts due to 30 f t. fall would cause a 100 load q from Shutter Plug & Rotor Fg = 100 (250#) = 25,000 pounds er 5/16 - 18 Bolt =.052 in.2 Stress Area v 25 2 S={=4

2) = 120,200 lb./m In.

O p' Therefore, breakage will likely occur on the four 5/16 - 18 Bolts. 25

However the front cover is fastened to the Head Casting, which adds further restrictions to a loose shutter plug. ( Clearance between the front cover and pulley which rotates the rotor is k inch. The front cover is held on with four k - 20 socket head bolts. Stress area per k - 20 Bolt =.031 in.2 "4 2 +.031) '( ) 083) Socket head bolts have a strength of 110,000 PSI. Therefore, the total travel of the plug & rotor assembly is approxi=ately k inch. The rotor locking device has a 5/8 inch engage =ent with the rotor locking bar. Therefore, the rotor locking bar will not allow the source wheel to rotate. 2.7.1.0.7 Stress on Mounting Devices and Side Move =ent of Cobalt Head due to side drop paralled to Rotor and Shutter Plug Centerline. c = Clearance between Head & Side 1 [ Box - 33.250 in. ~ ^ Steel Panel (2) .125 in. i Wood Panel (2) 7.250 in. Head - 21.468 in. -,i ic. Hold Downs (2) 1.000 in. Total Clearance 3.407 in. 3.407/2 = 1.703 in. clearance per side Hardware: Soc. Hd. Scr. HT =.500 (2) = 1.000 in. Lock Washers

.125 (2)

.250 in. Total space taken up by haedvare = 1.250 in. Per Side = 1.250/2 .625 in. = Clearance between wood interior & Screw Head is: 1.703 .625 = 1.078 in. which equals approximat21y 1.00 inch Deflection of Head Hold Dom Brackets ~ due to impact on side parallel to (,, g Rotor & Plug Center lines. g,ggg 5 I at 5 inch Height p i- -, bh' 5 (.5)3 f I=F =.052 12 26

i I 0.5 Inch Height AT N. A. Axis calculation SYM A X )( (" 4 l 2(2.25)(.5)=2.25 1.375 3.09 se l 5 5 x (.5) = 2.50 (.25) .63 4.75 3.72 1 % + N.A. = 5.M = 3.72 = 0.78 + y 4.75 l 1A N m. I N.A. 2 Quan. SYM. Ic.G. A d d2 Ad .5(2.25)3=.47 2.25 .78.25=.53 0.28 .63 i i 2 12 ] 5(.5)3 .05 2.50 1.37.78=.59 0.35 .88 1 12 l .52 -1.51 4 I = 2.03 In. N.A. S At 5 inch Height 2800 (100)(3.96)(.25) = 5,330,769 Psi S = Mc = T .052 S At 8 inch Height S = Mc = (2800)(100)(8.96)(2.5.78) = 2,125,682 Psi l I 2.03 f Therefore, c'eflection will cske place at the five inch height. D 1 27

Force required to reach yield point of structural steel straps: Sy = 43,000 Psi for 1020 H.R. steel 43,000 = P (.396) (.25) .052 22,580 Lb. P = 43,000 (.052) = .396 (.25) Reflection O = PI = 22,580 (3.96)3 =.300 inch 3EI 3 (30 x 10 ) (.052) Energy used to deflect hold down 1.00 inch 2 (1.00) (22.580) = 45,160 In.-Lb. Additional resistance is provided in the base of the Overpack which is weldment B16530. The steel weldment consists of a cylinder 13 1/8 diaceter x 2 1/2 Inch high which,, l is filled with lead for radiation protection. e g,6 This steel weldment is' held to the bottom skid by the four 3/8 x 16 x 5 3/4 Lg. Studs. / The 13 1/8 diameter Pilots into the /. 13 5/16 diameter bore which is located i at the bottom of the irradiator machine head. This leaves a nominal clearance of 3/32 (.092 in.) between the weldment and brass head casting. Structual Rigidity of Side Panel The Overpack side construction is very similar to the top, except that there are no lif ting ears on the side. Hence, the side should not have to be analyzed as a simple l supported beam. From the summary in Section 2.7.1 and l table on page , the top construction and similar side construction can with stand the impact load. There-I fore no further treatment of side or top of the Overpack is required for this report. 2.7.1.1 End Drop Since the ends are shorter and more rigid than the longer sides. Refer to calculations for a side drop in following section 2.7.1.2 1 O 28

kn 1,687,500 Lb Per Ear 3.375.000 lb. = I - Section for #181375 Lifting Ear. i Neutral Axis from Y-Axis d i I - Section for lifting ear on #181375 Overpack Determine (NA) Neutral Axis 6" from Y Axis. 1.03

SYM. AREA X Ky 1.125 1.875 2.109 l 1.125 1.875 2.109 f w O 2.250 p.1875 .421 .__ L igalfMat'1. Thick) b ( 4.500 In 4.639 In. d t=.375 (NA) Neutral Axis + f. My = 4.639 = 1.03 IN. f A t.L.2 4 5 EA 4,500 Determine Ig, [ SYM. h A d d Ad .843 1.125 1.5x.375-1.03 .714 .803 .843 1.125 .803 ~ ~ " [ .026 2.25' 1.03 -.1875 .709 1.595 1.712 3.201 4,913 In. 1.712 + 3.101 = = I NA -"3 /' If the entire impae; load produces a moment o-ear the resultant be..' ding h stress would be: MC Where I = 4913 In. 1 S = "I '#/ ff 00' Y 1 I k 4000 Lb. (100g)(5In.)1 03) In. = 4.913 In.' 419,235 Psi. = is si si, Therefore che ear would break off for this type of impact logd as angle increases to 90 tM bending load *becomes load beenmes a ( compression load. { Yield streggth for 1020 Er. Steel = 43,000 Psi. Force (P ) required to distort ears to yield T point. "A I Y = (6)(.375)(43,000) = 96,750 Lb. for (2) Ears. ~

O 2.7.1.2 Side Drop Since construction of sides and top of Overpack are similar (reference calculaticrs for stress on Top # 2.7.1.2.1) on side analysis is required for Overpack or Head damage. Analysis on # 181375 Top shows that unit will survive impact load. From previous analysis the bold-down bolts of Overpack #181375 and tie bars of #181361 will withstand a 100 force in a direction 8 normal to the tie bars. When the 100 force is paralled to the Tie Bars, the hold down bolts will shear. As pointed out in the previous treatment and original applications, the tie bars will withstand a sliding force of 10. g The impact would be absored primarily by the lower supporting structure since its extremities extend slightly beyond the steel sphere. The steel sphere will withstand its portion of the impact I force since it was demonstrated that the brass head casting of similar thickness will withstand the total impact force.

2..1.2.1 Stress on Top (Upside Down-Drop)

Free 30 ft. drop with container turned Upside Down & Landinggl l on Overpack # 181375 Top. 15c.TTt M Assume: Intial contact is -i n-

• ade at two points "I &R2 after 1/4 inch de-i l-flection. The remaining load j

is also absorbed Y#* F by lifting devices ~_ R and R 3 4, g Load = 100 for 30 f t. Drop from rreviou s gg g% L analysis #2.7.1.0.1 R R = (g L ad) (W) = (100)(4000), 200,000 Lb. 3, t g 2 2 2 4"s -= =- F = Force required. i g Force required for 1/4 inch i 5 compression on edge of ear. i F 4,Def." i View of Lift Ear 0 l =(.250 in.)(6 in.)(.375)30 x 10 lby = 3,375,000 Lb. Total i 5 In. 30

o 193,500 Lb. 2F = 96,750 (2) = ReeditingDeflection = 96,750 ( 5 In.) = 0.007 Deflection = = AE 6 (.375 In.) (30 x 10"Lb./In. Energy used in reaching yield point. 2 (F ) = 193,500 (.007) = 1345 In-Lb. E = Sit ((ethebalanceoftheenergyisusedincompressingthetwo T ears k inch and then compressing the other two ears, the resulting force is distribued over the upper veldment and the hard maple l super structure. If the assumption is made that all energy is absorbed in the upper veldment then: I l The upper veldment has eight j supporting columns (4) k x 3 x 3 h 0 angles; (4) 3/8 x 6" Straps. The energy absorbing length is 25 3/8 Inch. 1 ,_Jl CROSS 6ECT, ELJkdT l8l.%9 The total steel cross-section area is: A = 4 (6)(.250) + 4 (6) (.275) = 6 + 8.1 = 14.1 In. 7 i(. Force required to reach yield point F*= AS = 14.1 7 (43,000) = 606,300 Lb. Resulting Deflection h = l FL .036 In. Deflection 606,300 (25.375) = = AE 14.1 ( LJ a 10") l Energy used in reaching yield point l Eyp = Ft (6) = 606,300 Lb. (.036) = 21,826 In.-Lb. Total energy absorbed in steel reaching yield point T E = E ears + E (Top Weldment) = 1345 + 21,826 = 23,171 In.-Lb. Resistance to deformation on wood-hard maple area of wood cross l sect on for four sides. A= 3 5/8 in. x (291/8 2+ (3 5/8 x'32 7/8) 2 I I i r (Con't) 30A . ~..

// / / // / / / if / / 3 5/8" ,,,,,f TYP. 2 + = 211 + 238 = 449 in Maximum crush strength parallel to grain 10,200 psi Maximum force on wood: F = A Sc = 449 (10,200 psi) = 4,579,800 Lb. Resulting DeflectLon d =FL = 4,579,800 Lb. (25 in) =.141 in deflection A.E 449 in' (1.8) x 10 Energy used = 4,379,800 Lb. (.141) in = 645,751 in -Lb. Unused energy = 4000 Lb. (30 ft.) (12 in/f t.)- 645.751 in-Lb. - 23.171 in - Lb. = 1,440,000 - 645,751 - 23.171 O = 771,078 in-Lb. Assuming elasticity continues beyond yield point until unused energy is dissipated, the final deformation AF will be: l For 1020 steel L = 25.375 _ =.059 x 166 ~ 0 l AE (14.1) (30 x 10 ) Hard Maple L_ = 25 =.030 x 106 AE (449) (1.8x10 ) Since.059 = 2, the wood deflection is that for the steel .030 weldment, for same force if steel weldment continues to deflect to wood compression (.141 in). The force required to accomplish this is half that required for the wood. F(,147) _ 4,579,800 Lb. 2 Additional energy used = 4,579,800 (.141 .036) = 240,439 in - Lb. 2 \\' O 31

Unused energy = 771,078 - 240,439 = 530,639 in - Lb. Energy will be dissipated beyond.141 deflection 530.639 in - Lb. = P (4 p) P=AE L 530,639 in - Lo. = 4 A E (d p) L Where: Ap=4 6 6 530,639 in - Lb. = '(14.1) (30 x 10 ) + (449) (1.8 x 10 ) ( ) 25.375 25 = b6.7 x 106=32.3x10](gp)2 6 6 (49 x 10 ) o 2 = p 10829 x 10-6 = 6 2 p 104 x 10-3 =4 p i I .104

4y Total deflection, =.104 +.141 =.245 in or

inch deflection 2.7.1.3 Most severe cast of a 45 corner drop on top for overpack 181361 2 = (4000)2 = (4 x 10 )2(ZO)k-t5 Soc % 4 COO L 3 2x 6 f, = 16 x 10 6 x = 8 x 10 x = 2828 Lb. J_

7) CARRY

/ 2. Lono x E 141 Lb. N# For 181875 overpack (f.) CAte.y D I Stress on = 13 une cap screws five on a side: - 13 screw shear area = 0.1.19 in Strength of material in socket head screws = 110,000 psi Assuming (10) of the (20) screws carry the load S = P_ = (100) (1414 Lb.) _= 100,354 psi f.g A (10) (.1419 in)# 1 Therefore, these bolts would not shear. 32

2.7.1.4 Obliqu2 Drop Likewise as a corner drop, the load will be supported by the container corners. Where as in the corner drop t a sides were involved to absorb the shock, an oblique drop will involve three sides. Thus, the sr.ess for each will be less than would be experienced by the corner drop. Therefore, no calculation is necessary for this section over and above that already calculated for section # 2.7.1.3. 2.7.1.5 Summary Under hypothetical accident conditions of a 30' Drop, the containers and contents vould reach a speed of 44 ft. per second and would be subjected to stress caused by a 100g load. (Reference section 2.7.1.0.1). Under these conditions and with an upside down drop of Overpack

1. 181361, the two Ik inch diameter tie bars would hold and resist motion of shipping / exchange container #3320AR. This motion would be restricted to within limits of loosness (1/16) inches between these bars and the container.

Such a drop would cause the (4) 3/4-10 bolts, which secure the shipping / exchange container to its pallet to break loose. However, it would still be restricted to within the Overpack cavity and would not in itself be damaged nor break looce. Using the scme conditions on overpack #181375, the (20) -13 bolts cacuriag top to pallet would hold and prevent the irradiator machine head from escaping. However, the (4) 3/4-10 x 6 inch bolts securing hold down brackets to pallet and (4) 3/8-16 x 5 3/4 inch bolts securing irradiator machine head directly to pallet would break. the irradiator machine head would still be restricted within the Over pack cavity and could not escape. Calculstions show that if the Irradiator Machine Head were to break loose, in an upside down drop, it would substain some. damage by squashing slightly but would still retain the source wheel and source ia a safe "Off" and locked position. If the load Instead had landed on the bottom skids, they would have resisted d is load and remained in tact. This load then transmitted to the Overpack bottom panel would have been resisted by the strength of this panel and its weldment. In the case of either Overpacks the Irradiator Machine Head and Shipping / Exchange Containers would have been restricted within their Overpacks and in a safe condition. 2.7.2 Puncture calculation for a 40 inch fall of #181361 Overpack on the end of a 6 inch diameter steel bar. For Overpacks # 181361 and 181375 the most severe damage would be encountered if the maximum overpack weight of 4000# were to fall 40 in. onto the end of a 6 in. diameter bar. Shear area in 16 gauge steel sheet = A, = F 7 As= 6 (.062 r2.) = 1.18 in 33

l O As (Shear Stress) Shear Force = Fs = = (1.18) (77,000) (.75) 68,145 Lb. + 4" e = Average energy = 68,145 (.062)= 2212 In.-Lb. 2 Energy. developed in drop = 4000 (12) = 48,000 In.--Lb. Energy needed to shear thru 4" thick hardwood maple panel Shear force =Fs=As ( Shear Stress) 6 T (4) (2140 Psi.) = 161,270 Lbs. = _161270 (4) = 80635 in.-lb. Average Energy = 2 80,635 In.-Lb. Resistar.ce of Hard wood maple panel is greater than 48,000 In.-Lb. potential ener?,y available. Therefore the hard wood maple panel would resist this stress. 1.68 Factor of Safety is 80,635 = 48,000 Additional resistance to impact is provided by the h; x 4" steel straps which were added to prevent the access of a 6" diameter pin. 2.7.3 Thermal calculation for Overpack subjected to flames Assume the Overpack is a cube \\\\\\ 4476 //// 40 inches on a side with 16 N e / gauge steel skin over the 3 5/8 g g gaf M hard maple liner. Temperature / at normal transporting con- / gggggNN ditions is 100 F or 560 Rankin. / First analysis is in one dimesion. Radiation heat transfer from i flames @ 1475 F. 1475 F = 1935 R T = 4 2 2 -8) (0.8) = QA=((19.35 x 0 )8 (0.g)-983x1hx(0.173x10 (5.60 x 10 ) (0.173 x 10, ) (0.8) Q 40,200 x 10 17,327 BTU /HR FT = Heat per side for 30 minutes. Qs = Qa (A) (t) = 17,327 (40)2 ( ) = 96,200 BTU 12 If all is transfered to 16 gauge steel skln the f'.nal temperature would be: '.""C-WTIC TI) C W (TF Q = =

• TF = Q + W TIC

= WC W=p V=.289 3 (40In.) (.062) = 28 Lb. 0.11 Steel = WA

{ O l t Q + W TIC TF = WC i BTU F) 96,200 BTU + 28 Lb. (100 F)(0.11 Lb. l = (0.11) I - F 28 Lb. BTU L ~ 31,333 F = Melting Point of Steel is 2550 F, therefore steel would melt I if all heat is contained in steel, however some heat is transferred to the Hard Maple Liner. The steel plate transfers the following quantity of heat 0 assuming wood is initially at 100 F. KA A T (+) = 310 (BTU)(In) = (1475-100)0F(.5 Hr.)(h)2Ft.2 Q = A X Hr-Ft' = EO .062 In. 38,194,000 BTU = Since 38,194,000 BTU heat transferred is greater than the l 96,200 BTU received per side, it can be assumed that most of the heat is transferred to the wood even though some heat will be retained in the steel plate and welded frame and raise the temperature of the steel. i l Heat transferred through the hardwood maple panel is: KA 4T (t)=1.2(N)2 (1375) (.5) 2528 BTU I Q = = d X 3.625 If the balance of the heat is contained in the wood, then the final temperature of the wood would be: W =p V=(62.4)(0.63)(h) ( T = Q + W Tic y 132 lb. We = = 96,200-25 28 + 132 (100 (0.6) = 1 . f3 132 (0.6) T Appcoaches the ignition temperature of hard maple wood. p However, this wood is not exposed to the atmosphere and oxygen is not readily available to support combustion. If the inside of the steel reaches an average temperature of 500 F a more realistic approach is: 35 l.

Where the wood panels weigh 132 lbs.: W(six wood panels) = 6 (132) = 792 lbs. T 800 lbs. Remaining steel weight is = 1200 - 800 = 400 lbs. W, (weight of steel perside) = 400 = 70 lb. per side of steel 6 Then, the heat absorbed in wood and steel is as follows: Where coefficie..c of heat absorbtion for steel is 0.11 BTU per pound per F. Q Steel = W, C (A T) = 70 lb. (0.11) BTU-lb. (1450-500) F OF = 7315 B.T.U. Heat transferred through the wood is Q =KxA4T(+)=1.2(N) (400 (.5) y oX 3.625 = 735 BTU Then final temp. of wood would be: T = 96,200-7315-735 + 132 (100) (0.6) = 1213 F y 132 (.6) Since 1213 1* 7 1282 E then the inner' surface temperature i of steel and would is not too significant. Volume of Overpack inner ca ity = (27.0) (27.25) (20.375) 3 =8.6Ft.gch = 14990 i l Volume of Head (Assuming a 20 inch Dia. sphere) i = 4_1r R = 4_ fr (20)3 3351 In.3 2 3 3 = 1.9 Ft.3 Volume of Air = 8.6 - 1.9 = 6.7 Ft. Weight of Air WRT P V = W=n RT 36

O (R ) Ft.-Lb 2 144 h x (14.7 lb ) (6.7) Ft.3 - W (53.34)(560) R = 0.474 Lb. Heat absorbed from (2) thru tie rods (page 30H) is 146 x 2 = 292 BTU Since heat transferred through the wood is 735 BTU per "*.de. Total energy absorbed to the inner cavity is: (735) = 4410 BTU The final temp. of enclosed air would then be: U=C (T -T ) M y p g T = U + C,, T_ M = 4410 +.171 (560) (.474) F CM~ .171 (.474) y = 54968 R Obviously, the interior temperature would not go above the 0 equilibrium point of 1475 F unless oxygen were allowed to enter and combustion occured in the hardwood maple. Then, additional heat would be given of f.

4) Thermal Determine heat conducted along tie bard 14750

{1475 i h_ _ .D [100F ~ Q = KA A T (t) X (1.25)2 2 = (310 BTU) (in) 12 W Ft (1375 F) (.5Hr) HR (F() ( y) 4 (20 in) = 73.55 B.T.U. from each end However, as the midpoint temperature rises, the rate of heat transfer decreases. Hence,146 BTU is unrealistic. However, if this heat were transferred to the steel shell, it will increase the temperatura by f a T = (2) = 2 (146) = 4.8 F WQ 500 (.12) 37

'j The energy required for the internal air to reach 1475 would be: U1475 - C M (6 T) y .171 BTU (.474 Lb) (1475-100) = WF = 111 BTU The unused heat energy remaining within the inner cavity would be the total amount received less that used: 4410 BTU - 111 BTU = 4299 BTU in excess The brass casting of the containment vessel weicht 330 Lbs. the heat consumed to raise the temperature from 100 F to 1475 is Ubrass - M C AT (.09 h ) (1375) = 334 Lb = 41,335 BTU O Since only 4299 BTU is lef t the final temperature of the brass could only reach C T brass - U + MCT y MC = 4299 + 330 (.09) (100) 330 (.09) = 245 F The amount of lead in the brass containment vessel is approximately 1400 Lbs. The source and depleted uranium shielding are in the approximate center of the brass casting and Isad envelope. The amount of heat required to bring this lead to its melting point of 620 F is: Qt = M C A T = 1400 (.031) (620-100) = 21,840 BTU The latent heat required to melt the lead would be: Qg = MC = 1400 (10) = 14,000 BTU Heat required to melt all the lead is 21,8QO BTU + 14,000 iO = 35,840 BTU. 38

S Total time required to raise brass container to 245 F is Steel .00013 Wood .50000 Air .00543 Brass .00116 Total .50672 Hours Since the heat radiation source is applied for 0.5 hour and then re=oved, a reverse heat transfer would gradually occur. In order to =elt the lead it would require an additional 35,840 BTU. Therefore, it is safe to conclude the lead would not =elt under these conditions. Ti=e required for heat transfer through the steel jacket. T =Q x KA 6 T Syggy STFA7 NooD 8 \\ Ain 7315 BTU (.062)In. = ROTCR 310 (BTU-In) (40,)' (1450-500) + Hr.-F'" F 12 f H75* E 9 f' =.00013 Er. i Ti=e required for heat transfer WD through the wood: ), s v=735 BTU (3.625) In f BRn.55 s 1.. (BTU-In.-(40)' (500-100) Hr.-FT' F" 12 Tve. Cco Ls sect. f 0.] Hr. / I j T1=e required for heat transfer through one inch of air space DisT ALA C E. t air = 111 BTU x 1 In. 1.362 BTU (40)' (1450-100)F HrF -F g O ^ 39

i l I l .00543 Hr. = Time required for heat transfer through the brass. l l .0016 Hr. 4299 BTU (312 In.) = = br l 715 BTU 40' (245"-100 F" 0 -2 Hr.F oF 12 2.7.3.1 Summary of Pressures and Temperatures There would be no pressures developed by the 245 F maximum reaching the lead through the brass casting since the melting point of the I lead is 620 F. I I The package will pass the Heat Test. l t j 2.7.3.2 Differential Thermal Expansion There will be no deformations or stresses resulting from thermal expansion. This is further detailed in 2.6.1.2. 2.7.3.3 Stress Calculations No stresses are developed which will cause a malfunction of the package. See also Sections 2.51, 2.52. and 2.6.1.3. 2.7.3.4 Comparison with Allowable Stresses. The capsules were tested, e.nd passed, all tests for special form. Tests were also done to ANSI N542 1977. The results of these tests are included with this application. No damage to the to the containment vessel results. 2.7.4 Water Immersion. This is not a fissile package. Not applicable. 2.7.5 Summary of Damage. 2.7.5.1 overpack #181375. 2.7.5.1.1 Free 30 Ft. Drop on Top of Overpack. a). The lifting ears will deform. b). If the box hits the horizontal resistance at an angle the lifting ear will be torn off. c). Most of the strain-energy is consumed in the wood because of it's large surface area. d). If the top surface hits the horizontial surface paralled the' deformation should be approximately 1/4 inch. e). Top deformation of wood panel will not cause a collision from Irradiator Machine Head since 1/4 inch deflection is less than the 1 3/16 inch clearance. O f). Head can withstand 100g loading (28,000 lb) without any lJh appreciable distortion. g). If the head were to break loose from its tie down bolts, the I head would strike the hard wood maple liner. The crush resistance of Maple hard wood will withstand a 512,448 lb. force, which is greater than the 100g (2800) = 280,000 lb.

' hen the top asse:bly is treated as a si= ply supported h). bea= the total resistant force of the dev: bolts, wood, and veld = ant is: 89,375 + 151,710 + 3516 = 249,601 lb. This is in the range of 100g head lead. SL :e it is =cre than si= ply supported and additic al force is required to distort the ears, it is unlikely the head will penetrate the tcp. it is unlikely the head vill penetrate the tcp. 2.7.5.1.2 Free 30 Ft. Drop c Side Paralled to Roter and Plug Centerline a). Hold dev: brackets vill defor= at five-inch height. The balance of the i= pact vill be absorbed by the wood a 1 veld:ent which vill suppert the 1 cad, as shavn 1: Part 1, since the vall ec structicas are very si=ilar to the top but without lift ears. Additic:al resistance to head =ove- =ent is supplied by the steel veld:ent which is bolted to the base of the everpack. 2.7.5.1.3 Free 30 Ft. Drop c Side Nor=al to Plug and Re:c Centerline. a). No further analysis on structural require =ents for drop side. b). If rotor and plug asse=bly can =ove h inch the rotor lock har vill not disengage and act allev the scurce rotor to rotate. 2.7.5.1.4 Free 10 Ft. Drep c Ecttc= of Overpack. a). Skids will withstand i= pact because of large surface. Defor=ation is.006 inch. The hold devn bolts vill have very little : otic. b). Botte= asse:bly vill withstand i= pact Icad. 2.7.5.1.5 Ther:al, a). The hard =aple wood is the pri=ary insulater. b). The brass shell ef,ccatain=ent vessel vill reach a te=perature of 215* 7 after 0.5 hour. c). An excess of 35,000 3!t would be required in order to get the lead to =elt. d). After c e half hour the heat transfer vill reverse, e). In K.V. Eaff's paper " Radioisotope Shipping Cc::ainer Develeprent" =aple was exposed to a fla=e of a pressurized kerosene burner for cae hour at an external te=perature of 900 C. The renetratics was 2 inches in that test. The - o or' calculated terjerature for this analysis was 1252 -1213 therefore sc=e exter=al charing =ay occur at outer edges and corners but penetratice vould be slight - Eaf f's paper is part of original applicatics. l l 41 1 J

2.7.5.2 Overpack #181361. 2.7.5.2.1 Free 30 Ft. Drop on Top of Overpack. a). Top will withstand 30 ft drop. b). No relative motion between container and overpack is likely. c). Ne> damage to container is likely. 2.7.5.2.2 Free 30 Ft. Drop on Sides. a). Sides will withstand 30 ft drop. I b). Tie down bolts and tie bars will restrict any relative motion { when impact force is normal to tie bars. c). Tie down bolts will shear when impact is paralled to tie bars. Container will slide along the tie bars and contact the side. No s rious damage will occur to either container or overpack because of large impact area. 2.7.5.2.3 Free 30 Ft. Drop on Bottom. a). Skids will survive impact. 2.7.5.2.4 Thermal a). Heat transfer through the tie rods is insignificant. It will cause the shell temperature of containment vessel to rise less than 5 F. l 2.8 Special Form l The material meets special form requirements given in paragraph 71.4 (0) when subjected to the applicable test conditions of Appendix D to 10 CFR Part 71, as demonstrated in the following paragraphs. 2.8.1 thru 2.8.6 These tests were performed by an independent testing labora tory. All the tests were acceptable. Copies of the test results are included in 2.10 Appendix. 2.9 Fuel Rods This is not a reactor. Not applicable. 2.10 Appendix .i ~ 4 2

3.0 Ther:al Evaluatics

3.1 Discussic

The :.aximu= heat lead under n r=al cenditices d:es not exceed a =axt=== air te=perature of 130*F in bright s = light j and with a==x*-- decay heat lead of 200 W::s. here is no ther:al cooling syste= =cr expansics tanks, etc. Ther:al consideratices are =i *-=1. 3.2 S->ry of ther:a1 properties of materials Previcusly covered under Sectics 2.7.3. 3.3 Technical specifications of cc penents Previously ecvered c:: der Sectie: 1.0. 3.. Ther.a1 Evaluatire fer Nor:al C cditices of Transper: Refer :: Appendi.x "A" to 10CII Part 71. Ass =ing a constant air te=perature of 130 7 and with the package setting in the sus in still air at latitude 42. Radiated heat frc: the su: vill vary fre: :ero to maxir= and back :o :ero vithis e.e day. Af ter the package te=perature -' frc: days in the su vi:h the axirm bec =es stabili Q* decay lead of 200 vat:s and s lar radiatics, internal C balt the surface te=perature vill be equalized by external radiatics 10 all directic s. Due to the large sass involved, it vill be ass =ed the centainer surface te=perature is unifer: over a 21 5:ur peried aad does n:t vary frc: side to side ::: ::p to be::::. The a: cunt of s.:lar radiatics received c a clear day with the sus at its zenith vill be: - sw/ t,1..ead at 42 Latitude is 34! 5 EC/Ft.- Oay er Solar Eea* l 1r. r nr.

• Cak Ridge Nati::al latera: ries, Cask Oesigners Guide.
• CRSI.-NSIC-63, UC-50 Eeacter Technol:gy p' ages 129-130, 134 Figure 5.3, Page 130, 142-113.

SC/Er. = A l p1 T-

2) - A 7,E, l

1 1 q Heat Radiated out frc: C ::ainer Eeat fro: Sun Decay Eeat r a ~ q-A[py (T* - Ip pi E s y 1 s v e 43

Where: 2 h, (solar heat) = 144 BTU average per ft hr h, (decay heat) = 200 Watts = 682 BTU per hr Ty = Maximum temperature to which Container will rise T2 = 130 F Air temperature + 460 = 590 Renkin p1 =.065 (Coefficient of heat absorbtion for steel sheet covering) A = 66 ft2 (Total surface area of overpack box) y 'A2 = 10.7 ft2 (Top surface area of overpack box) 6 = 0.173 x 10-8 ( constant) 2 2 q (144 BTU per f t -hr x 10.7 f t ) + 682 BTU = 2223 BTU per hr = q =A[p Tf - A 8p1 d-A y y 2 2 Py H, - Hy A8p Tf=q+A[pyd+A2 p1 H, + H y y y Therefore: T =q+Aygp T2+A2 P Hs+H y y y A g p1 y = 2223 + C66 x 0.173 x 10-8x0.65x590] 4 + (10.7 x 0.65 x 144) + 682 66 x 0.173 x 10-5 x 0.65 8 = 1738 x 10 Ty = 645 Penkin - 4 60 = 185 F Thus the container and its contents will equalize in temgeraturewhenthecontainersi.rfacetemperaturereaches 185 F, sine'e. the container can,ithstand this temperature, no further calculation should oe needed.

• Introduction to Heat Transfer by A. I. Brown (Professor of Heating & Ventilating @ Ohio State Univ.) Virst Edition, l

McGraw-Hill Book Company, Inc. Page 62 3.4.1 Thermal Model 3.4.1.1 Analytical Edel We have assumed as analytical model as a 40" cubical package with a #16 gauge cheet steel skin, over a 3 5/8 inch thick Q liner of laminated hard maple. This analytical model was fs/ used to represent the overpacks as described in section #1.0. 44

3.4.1.2 Test Model We are using an analytical model. Not applicable 3.4.2 Maximum Temperatures Maximum air temperature was 130 F and with bright sunlight and a maximum decay heat load of 200 watts, the contents reached an equalization temperature of 185 F. 3.4.3 Minimum Temperatures The capsule was actually tested to -40 F and passed successfully. The package would withstand -40 F as calculated. l 3.4.4 Maximum Internal Pressures l We do not have a sealed container except for the capsule and this passed all tests successfully. l 3.4.5 Maximum Thermal Stresses l, Not applicable for our package and contents l 3.4.6 Evaluation of Package Performance for Normal Conditions of Transport O This package will perform all its required functions and all systems will remain in tact and in working order under all normal conditions of cemperature, pressure, sunlight, shade, decay heat load, etc. l 3.5 Hypothetical Accident Thermal Evaluation Not Applicable. This is a redundancy and repeat of questions under section 2.7.5 which were previously answered. l l l l 4 O l l l 45

s g 4.0 Containment 7Q 4.1 Containment Boundry This is the source capsule vessel 4.1.1 Containment Vessel A containment capsule was provided to meet all test requirements which are specified by domestic and international regularitory authorities. A double encapsulated package was selected to meet these requirements. 4.1.2 Containment Penetration Nothing penetrates the primary containment. Not applicable. 4.1.3 Seals and Welds The inner capsule is a stainless steel cup, the open end of which is capped and innert gas heli-arc welded closed. This cup is then placed in another cup which is capped and again innert gas heli-arc welded shut. Tbese two welds provided the seals for the containment package leaks, testing is performed following each weld operation. 4.1.4 Closure This is a completely welded vessel and not requiring any additional closures. Not applicable. O ' \\-- 4.2 Requirements For Normal Conditions of Transport 4.2.1 Re? tase of Radioactive Material It aas been shown that there would be no release of radioactive material. See Herron Laboraties testing in Appendix # 4.4 4.2.2 Pressurization of Containment Vessel There would be no. gases released. l Not Applicable. 4.2.3 Coolant Contamination There is no coolant present and therefore no such contamination. Not Applicable. 4.2.4 Coolant Loss There is no coolant to be lost. l Not Applicable. 1 4.3 Containment Requirements for the Hypothetical Accident Conditions. 4.3.1 Fission Gas Products 'N There are no fission gas products. i; x Not Applicable. 4.3.2 Releases of Contents i M

See Herron Laboratories test report in Section 4.4 which g shows compliance to 10 CFR 71, Appendix "B". 4.4 Appendix. 5.0 Shielding Evaluation 5.1 Discussion and Results. Lead, depleated uranium, tungsten and brass are all used as shielding in various combinations. TABLE 5.1 SUMMR Y OF MAXIMUM DOSE RATES (MR/HR.) PACKAGE SURFACE 3' FROM SURFACE OF PACKAGE SIDE TOP BOTTOM SIDE TOP BOTTOM NORMAL CONDITIONS GAMMA 25 64 11 2.1 4.6 0.8 NEUTRON NA NA NA NA NA NA TOTAL HYPOTHETICAL ACCIDENT CONDITIONS GAMMA 25 64 11 2.1 4.6 0.8 NEUTRON NA NA NA NA NA NA TOTAL 10 CFR Part 71 Limit 1000 1000 1000 The Irradiator Machine Head and Shipping / Exchange containers were designed to meet requirements of 10 CFR 71 IAEA safety series #6 and 49 CFR chapters 173.24, 173.393 and 173.394. In adaition the Irradiator Head meets requirements of NCRP Report #33. There are no spent fuels involved with this packaging. 5.2 Source Specification. 5.2.1 Gamma Source. The maximgg quantity of radioactive material is 13,600 curies of Cobalt or 2200 curries of Cesium 137. 0 Cobalt metal is purchased from suppliers preassayed. The number of curies per gram is known and only the number of grams, required to meet a particular source specification, need be determined. Each source is measured for Rhm output before shipment. 47

~O L REPORT OF r TEST OPERATION CONDUCTED ON TWO (2)' PROTOTYPE GAltfA TELETHERAPY SEALED ~ SOURCES (NON-RADI0 ACTIVE) i w P 1 For E E O ADVANCED MEDICAL SYSTEMS, INC. Cleveland, Ohio B 22 October 1979 Herron File M-5125 E g Abhj?$~ik(kbkY.hhh? ANUT~~ R '.? '&R ,?. &___.. T?.. gO 1 I HERRON TESTING LABORATORIES,-INC. 9, W

sv(J REPORT OF TEST OPERATION CONDUCTED UN TWO (2) PROTOTYPE GAhNA TELETilERAPY SEALED SOURCES (NON-RADIOACTIVE) FOR ADVANCED MEDICAL SYSTEMS, INCORPORATED CLEVELAND, OHIO 22 OCTOBER 1979 11 ERR 0N FILE NO. M 5125 i I ) ./ ~ HERRON TESTING LABORATORIES, INC. 5405 SCH AAF ROAD

• CLEVELAND, OHIO 44131 716/52414W CONSULTATION AND TESTING SINCE 1911

f i ' O 4 22 October 1979 Advanced Medical Systems, Incorporated 1020 London Road Cleveland, 011 44110

SUBJECT:

Tes t Operation Conducted on Two (2) Prototype Gamma Teletherapy Scaled i Sources (Non-Radioactive) RE Advanced Medical Systems P.O. No.: 010 lierron Laboratory Project No. M 5125 Two (2) prototype gamma teletherapy scaled sources, non-radioactive, supplied for test by Advanced Medical Systems, Incorporated, Cleveland, Ohio, were subjected to test parameters specified in American National Standard N542; N " Sealed Radioactive Sources, Classification" dated July 1978, further identified National Bureau of Standards llandbook No. 126. All test operations were performed using the seal source classification designa tion of ANSI 77C53524. This number was employed to determine which tests would be applicabic from Table I of the above specification as follows: ? I TEST CLASS PARAMETERS Temperature 5 -40 C (20 Min) +600 C (1h) and Thermal Shock j 600 C to 20 C 2 External Pressure 3 25 KN/m abs. to 2 M N/m2 (290 1h./in.2) abs. 1 i i ( f HERRON TESTING LABORATORIES, INC. 54ft5 5CHA Af ROAD

• Cll\\ ti AND, Of110 44111
• 11h/52414V) t (ONSULT AflON AND If 5flNG SINCf 1911

lie rron l're ji i i thi. M !. I,". 22 October 1979 l' age, 1 LO TEST CLASS PARAMETERS l Impact 5 5 kg (11 Ilt) from 1 m Vibration 2 30 min. 25 to 500 11: at 5 g peak amp. i' Puncture 4 50g (1.76 oz.) from 1 m For each required Icak test, Section A 2.2.2 "llot Liquid Bubbic Test," of Appendix A, attached to the above specification was employed. SUBMITTED SAMPLES The two (2) submitted samples were identified by the following etched numbers: PX 20 1 These two numbers were utilized throughout the test program 4 as the Sample Number. Operations were conducted in both i units as assembled in Figure 2, Appendix I. Figure 2, Appendix I, illustrates those items comprising a completc 1 source assembly. - I TEST EQUIPMENT The following list of equipment was used in the perform-ance of the above stated test program: - Temperature / Vacuum Test Chamber, Tenney Enginecr- !l ing Company, Model 8ST-85, S/N 2491 I Temperature Range: -1100 F. to +2100 F., control i l tolerance of +10 F. i O li HERRON TESTING LABORATORIES, INC. l l s.os soi4=e no*n. onuwo. onw> uin a,m = l cossuo4tios Aso ustisc sisct ran L

. _ ~ _ llerron l'i oj n I i.o. 61 !. l i '. 22 October 1979 Pu y.e - TEST l!QUIPMENT Vacuum Range: Atmospheric to 0.1 inches of mercury absolute. 3 - lilectric Furnace, Blue-M lilectric Company, Model 8640C-3, S/N LVA1247 Temperature Range: Ambient to 2000 C. - Pressure Vessel, lierron Testing Laboratories, Incorporated, 2-1/2" x 14" with U.S. Solfrunt Pressure Gauge, O to 600 ?SI - Impact Tester, The Chandler Machine Company - Vibration S'ystem, Calidyne Corporation, consisting of: 4 - Shaker, Model 58, S/N 69, Ampli tudes of +0.375 inches at 1200 force-pound - Console and Power Supply, Model 45A, S/N 18 - Vibration Meter, MB Electronics, Model N524, S/N 9401646 - Accelerome ter, B 6 K Ins truments, Model MB304, i S/N 182021 - Ilammer and Pin, lierron Testing Laboratories, Incorporated fabrication TEST PROCEDURE The followi w test procedures were used in the performance of all test vrations: A. TEMPERATURE TEST was conducted per Section 7.2 as follows: 1 1. Both sampics were installed within the temperature / vacuum test chamber. 1 2. The chamber was closed and se t to control at -40 C. (-40 F.) i o h O 4 HERRON T ESTING l.ABORATORIES, INC. 54fn SCH A Al RO AD

• CLI4iL AND, OHIO 44111
• 21h.'$1414W CON %ULI AflON AND 11%11NL SINCt 1911

_ = _ - - - lle t t osi l'i o,s i i i toi. M !. l. *, l ' ' Oc t obe r 1979 F l':i g e ; L0 l k' TEST PROCEDURE l 3. Temperature condition was maintained for l 20 minutes af ter samples had ic:ched thermal stabilization. 1 i 4. At the completion of test, samples were I allowed to return to ambient temperature. 1 5. Bubble leak test was performet in water at 90 - 95 C. (194 - 203 F.). I 6. Sampics were placed in the test furnace. t i l' 7 Furnace was closed and set to control at l! +6000 C. (11120 F.). t I 8. Temperature condition was maintained for one hour. t 9. Step 4, above, was repeated. j-10. Steps 5, 6, 7, and 8, above, were repeated except that temperature was maintained for one hour fifteen minutes. 11. At the completion of test, samples were quickly removed from the furnace and placed in a 10 gallon container of water at a temperature of 200 C. (68 F.) and allowed to remain until cooled. II 12. Step 5, above, was repeated. B. EXTERNAL PRESSURE TEST was conducted per Section 7.3 as follows: i' 1. Both samples were placed-in the vacuum chamber. 1 2. Temperature / vacuum test chamber was closed ~ and scaled. t I i 3. A vacuum of 25 KN/m2 (7.37" lig abs. )' was developed within the chamber. i JO HERRON TESTING LABORATORIES, INC. 54)$ 5CH A Al ROAD e (((b[t AND, OHN)44191 + 2%Q414*d) CONSULTAllON AND TI5flNG 5tNCE 1911 ~. _ _...,,. _, _ _..., _. -. _ _.. _ - _. _ _..., _ -,, -.. -. -,, -

lle r i o n l'i oj e. I f.o. M !. l.* !. 22 October 1999 Pn yy, -4 TEST PROCEDURE (Continued) 4. Condition was held for five minutes. 5. Chamber valve was opened and internal pressure allowed to return to atmospheric pressure. 6. Steps 3 and 4 were repeated for a total of two (2) cycles. 7. Sampics were placed in pressure vessel and filled with water. 2 absolute ^ 8. System was.pressuri:cd to 2 MN/m (27 PSIG) and held for five minutes. 9. Pressure vessel valve was opened system allowed to return to atmospheric pressure. 10. Steps 8 and 9 were repeated for a total of i two (2) cycles. 11. At the completion of both tests, the sampics were bubble Icak tested. l C. IMPACT TEST was conducted per Section 7.4 as follows on both sampics: i 1. The sampic was placed on the anvil such that the impact hammer would strike the source on the window end. ll 2. The hammer assembly weighing 5 kg (11 lbs.) was raised to height of one meter (3.28 f t.) l and allowed to drop. I 3. The sample was bubble leak tested at the i completion of the test. Figure 4, Appendix I, illustrates the t i orientation of the sample in impact tester I af ter first drop (Sample PX 15). Figure 5, Appendix I, illustrates the effect of the l impact test on both samples. i f g t O HERRON TESTING LABORATORIES, INC. 5405 5(H A Af ROAD. O thtt AND. OHN) 441 st 2m/12414% f CONSULTAtlON AND 1E5tlNG SINCE 1911

M l Ilerron l'rojec t No. M 'i l 2 5 1 22 October 1979 p.. .._g,. i i. TEST Pit 0CEDUllE (Continued) i D. VIBRATION TEST was conducted per Section 7.5 { Figure 6, Appendix I, shows Sample PX 15 as mounted to the platform for vibration along the "Y" axis. For the "X" axis the sample was placed on its side and clamped in the same manner as illustrated in Figure 6, Appendix I. i 1. The sampic was vibrated with peak accelera-i tion icvel maintained at +5g, with sinusoidal frequency swept from 25 llz to 500 liz to 25 llz in ten (10) minute sweeps. I 2. Step 1, above, was repeated for a total of three (3) sweeps in nn effort to determine a resonant frequency. 3. At each resonant frequency, a 30 minute dwell was performed. 4. At the completion of vibration, the sample was rotated to the "X" axis and Steps 1, 2, and 3 were repeated. 5. The sampic was then bubble Icak tested. I Sample PX 20 vibrated to the same procedure as stated above. E. PUNCTURE TEST was conducted on both samples per Section 7.6. 1-The hammer employed had a total mass of 50g

i (1.76 oz.) equipped with a hemispherical end pin 3mm in diameter with a 6mm free height and

!l a hardness of 55 Rockwell C. l1 1. Sampic was placed on a steel anvil. l l 2. A glass guide tube was positioned over the l center of the sample. O HERRON TESTING LABORATORIES, INC. 5405 5CH A Af RO AD

• Cll%It AND.05110 44111 + /lfi 52414V)

CON %Ut1 AllON AND 11%11NG SMt 19t#

lierrun l'r oj ee t No. M S1/S 5 '2 October 1979 l' age, TEST PROCEDURE (Continued) l 3. The hammer was loca ted, pin downward, in the tube and adjusted to a height of one meter (3.28 f t.) and dropped to impact the test sampic on its window end. 4. The sample was bubble leak tested at the completion of the test. RESULTS OF TEST OPERATION The following results are those developed by the appli-cation of the above stated procedure: RESULTS OF TEST OPERATIONS TEST SAMPLE PERFORMED COMMENTS PX 15 and PX 20 Temperature No Leakage i Met Spec. Requirements

i PX 15 and PX 20 External No Leakage j

Pressure Met Spec. Requirements PX 15 and PX 20 Impact No Leakage Met Spec. Requirements PX 15 Vibration No Leakage Apparent Met Spec. Requirements l Resonances .i 400 ilz and 475 liz in "Y" Axis, 403 liz and 477 IIz "X" i Axis PX 20 Vibration No Leakage Apparent Met Spec. Requirements Resonance at 402 IIz in both "X" and "Y" axes PX 15 and PX 20 Puncture Test No Leakage Met Spec. Requirements i k ' HERRON TESTING LABORATORIES, INC. 5405 SCHA4f Rott) Cit %tt AND OHto44111 2th 514 is vi (ONSUt14TKJN ANO f t%IING SINCE 1911 1

1, _..~__ . _. _ _ - -... _ _. _.. _._.. _. ~.-_ _.._ Ilerron I'roject No. M 5125 p. 22 Octoher 1979 l' age 3 t jf I' 4 h 4 i' F F It is judged that both submitted prototype ;;amma teletherapy scaled sources complied with all appropriate i. test requirements associated with scaled source classi-fication designation ANSI 77C53524. -l i llERR0N TESTING LABORATORIES, I "C. D. L. Endle, I.C.E.T. 20029 Engineering Technician it l1 4, . h b /, k n e 1 !L K. J. Wolf, P.E. j Reliability Engineering Manager 4 ': /dvu 4

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m. i 6 I I l l l FIGURl! 1 Illustrates the Samples as Assembled for Test. f I 1 'i I i i f i HERRON TESIING LABORATORIES, INC. h s n son.: no.n. un n isn. oino uni. v.,:m uw o,.,o.,,0~.sn,,s,~.sm a,,, (

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O FIGURE 2 Illustrates the Parts Going Into Assembled Samples. I I I I 0 1 ypD HERRON TESTING LABORATORIES, INC. ll Ws s,s v nau no o. < mn so. onio uin. w su im , o_,,.,,os so m, ~. s s<,,,, l t I a. - -, - -,,.. -,. -. -. - - - - - - - - - - - -

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..n. I 5t l Ia i k FIGURE 3 'lO Shows the Effect of liigh Temperature es Sa I'X 15 o n Le f t, Sample F l. I i 1 Ii HERRON T ESTING LABORATORIES, INC. g w,s scnur no is. nnit4Nii. o.nci nin 2,.su ico g (()N%Ut I4fl()N ANI) Il$llN(, $1Ns1 1911 e ... _, _.. - - -.. - _. ~.. _.,m.,

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... _.. _.. -... _ =. _ _. -.. i O i l l 4 I I t l, FIGURI! 4 Illustrates Sample PX 15 at the Completion of the Impact Tcst. I l l HERRON TESTING LABORA. 3 RIES, INC. 546 M H A Af lif) All * ((lb ll AND OHlf 8 44'11 = 1183,51414M (()N5titI AllON AND ll%IING SINf t l'811 .,_.__....__._._.m_ _ _ _.. _,,, _. _. -.. _ _ _....,,. ~..,,, _ _

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i e 1 i 4 I ( l i-r i l, i s FIGURE 5 Shows the Effect of the Impact and Puncture Tests. A i L l' l i l1 t i l HERRON TESTING LABORATORIES, INC. S&$ SCH A AF ROAD (if Vil AND. f N f tO 441l1 = lih 51414V) (ONSUl14f 80N AND fl5flNG $1NCE 1911 1

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i t i l l i FIGURE 6 .i Illustrates Sample PX 15 as Mounted for Vibration in the "Y" Axis. l l l l l l i 1; HERRON TESTING LARORATORIES, INC. SWM 5CH A AF ROAll Cl(VEL AN!) ()tlin 44111 2m/5141471 l ~: CONsULTAT10N AND f t511NG 5INCE 1911 1l.--_..~-,-....__.-.__.-_-.

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~ _ _. i D.i t,, 22 April 1980 7)k-HERRON l LS~llNG LAlb 1RAIORll.S, INC. 1 1 w, s< n44, msn. o n n u > oino.ni n. i,.rin im e, a o >Nsus i ANON AND 11%IING slM i l'#n V Pr. No. 0-2030-2 TEST CERTIFICATE P.O No. 0368 ADVANCED MEDICAL SYSTEMS, INC. V ACUUM TEST HUMIDITY TEST 1020 London Road ~ ELECTRICAL TEST ARTIFICIAL WEATHERING Cleveland, Ohio 44110 F LOW TEST TEMPER ATURE TEST Helium Pressure PRESSURE TEST X Bubble Test QUANTITY PART NUMBER DEsCRIPTlON RESULTS 2 PX 15 Radioactive Source Capsules Meets spec requirements PX 20 (Non-Radioactive for Test) ANSI N542, A2.2.3 Two (2) source capsules were subjected to the test parameters setforth in American Standard N542, Appendix A, Section A2.2.3 Helium Pressurization Bubble Test. l These sources are the design of Advanced Medical Systems, Inc. and Picker Corporation and were fabricated by Advanced Medical Systems, Inc. The Helium Pressurization Bubble Test was performed in a pressure vessel, 2-1/2" dia. x 14" long, manufactured by Herron Testing Laboratories, Inc. and employing a U.S. Solfrunt pressure gauge, 0-600 PSI. De-ionized water was used as the leak test fluid. After pressurization the samples were submerged in the test fluid and observed for bubbles for a period of two (2) minutes. No bubbles were observed and the sample sources are considered to be leak free. All samples were returned to Advanced Medical Systems, Inc, l r j --.-e---.- --.r. The foregoing is empressly limeteil to Ote f s n hone *t upon mater @, enformation, and/or specifications furntshetf ijy Client and excludes any eRpre55 o WTfr6ftt#6145 to the fitnell Of the mate:f 8JI JOejaf)f PrOCell 50 Sublected to examination and/or analyl85 for any particular purpose or use. ~D. L. Endle, I.C.E.T. 20029 Engineering Technician SWORN AND SUBSCRIBED TO ME THIS U E DAY OF ,19 i j NANCY L onwr Notary Pubisc Notary PuMic state of Ch!c Cuya. Cty i ElfE

o,,, 26 September 1980 HERRON TESTING LABORATORIES, INC. I s40s st n Aal Rom. ru vn e.o. OHin 44i H. fiv,14 saw Page of rONSUI1 AHON ANL) M SUN (, %1N(l 14H P-002 Pro. No. TEST CEllTIFICATE P.O.No. ADVANCED MEDICAL SYSTEMS, INC. VACUUM TEST HUMIDITY TEST 1020 London Road ELECTRICAL TEST T RtJG Cleveland, Ohio 44110 F LOW TEST TEMPER ATURE TEST PRESSURE TEST QUANTITY PART NUMBER DESCRIPTION RESULTS 1 PX 15 Prototype Gamma Teletherapy Sealed Source (Non-radioactive) 1 PX 20 Prototype Gamma Teletherapy Sealed Source (Non-radioactive) Over the period from 16 September 1980 to 19 September 1980, two (2) Prototype Gamma Teletherapy Sealed Sources (non-radioactive), identified PX 15 and PX 20 were subjected to free drop, heating and immersion testing as specified in tests 1, 3 and 4, Appendix D " Tests For Special Fom O Licensed Material", Part 71 " Packaging of Radioactive Material for Transport" of United States National Regulatory Conmission (USNRC) regulations. Free drop tests were performed on each of the two test samples by allowing them to free fall through a distance of 30 feet and strike a nominal 4 foot by 4 foot, 3/4 inch steel plate. Heating tests were performed on each test sample by placing them inside a Hevi Duty Electric Co., type HDT-5610-CU, Serial No. 72041 electric furnace for a minimum of 10 minutes at a temperature of 1,475 F. Immersion tests were conducted on both samples by immersing them in de-ionized water having pH6 and pH8 and a maximum conductivity of 0.2 micromhos per centimeter at ambient temperature for 24 hours. The foregoing it empressly limited to findings based upon ruaierial, mformation. and/or spacif. cations furnished i;y client and euciudes any empress or implied W9'fa91iel at 10 the Isthell Of the material and/Or prOCell 50 lubjected 10 examination and/or analytil for any particular purp059 Or use. h_ Alan N. Reitenbach (O Engineering Technologist \\j 26th September ,is 80 DAY OF SWORN AND SUBSCRIBED TO ME TH,tS .htf* Notary Publ+c N ANOYJ. OOOuS Motary Pubfit. !! ate el ohis Cuys, Cty My Commission Empires Jan. 16, 1985

.. =.. Date 26 September 1980 /g HERRON TESTING LABORATORIES, INC. l 54tri Stil AAI R() AI). CilVil ANI). (lillt ) 44111 216/524 149) Page of r()N%UI1 Allt IN ANI) 11%IING %lN(l l'ill pro, no, P-002 l TEST CEltTIFICATE P.O.No, i After each of the three tests described above, a hot liquid bubble test was conducted on each source to check for leakage. Hot liauid bubble test was conducted in accordance with Section A2.2.2., Appendix A, " Leak Test Methods", of American National Standard N542; " Sealed Radioactive Sources, Classification" dated July 1978. No leakage was detected from either source af ter any of the three tests. Subsequently, both prototype gamma teletherapy sealed sources were returned to Advanced Medical Systems, Inc. for further evaluation. ) v i i t ~ O l'

Cesium sources are not intended to be manufactured by Advanced Medical Systems. 5.2.2. Neutron Source. 5.3 Model Specification m del 3320 AR container contain.ng The catalog 181361 overpack with 80 a 2.5 cm diameter 5219 Rhm Cobalt source of about 4559 curies was used by Picker in the evaluation. This was reported in Picker Corporation application dated October 17, 1975 on pages 40, 41 and 42. Copies of this data is included in 5.5 appendix. The irradiator heads will be much lower in leakage as they must comply with NCRP report 33 (less than 10 Mr/Hr. at 1 meter on any spot and the average over 26 points must be less than 2 Mr/Hr.) 5.3.1 Description of the Radial and Axial Shielding Configuration. (' ' The radial shielding is steel and lead, In the axial direction lead, steel, tungsten, brass and depleted uranium are used. 4 This is because the source window end is pointed up in the stored position inside the containers. There are no differences for normal conditions and the accident conditions. 5.3.2 Shield Regional Densities. 99% pure lead is used and certifications are required. 17 density tungsten is used. Calculations were not done. Data was based upon actual measurements. 5.4 Shielding Evaluation A G M Survey meter was used to measure the gamma dose rates at the selected points outside the package. 5.5 Appendix Gp. 48

6.0 Not applicable. 7.0 Operating Procedures. 7.1 Procedures for Loading the Package. The following procedure is used by Advanced Medical Systems before the #181375 and #181361 Overpack boxes are used for shipment. A. A visual inspection of all Overpacks is perfor=ed for possible defects. B. A check is made to insure that the Overpack functions mechanically. C. The cobalt heads and replacement shipping containers are internally wiped for contamination and cleaned if necessary. D. The cobalt heads and replacement shipping container are reloaded and wire sealed. E. The specific containers are wipe tested on the outside and findings recorded. F. The specific containers are put in the overpack. G. A radiation survey is performed. H. Form is co=pleted and kept on file. (A copy of this form appears in section 7.4 of th~is report). I. Records are kept of all shipments to and from t destination with respect to source size, carrier, bill of lading, and source serial number. See Also Q.A. 1014A Procedure, In 7.4 (Appendix _. l l l 7.2 Procedures for Unioading. INSTRUCTIONS FOR HANDLING LOADED COBALT TELETHERAPY OR CYCLOPS HEAD _. l Package Part Number 181375 The cobalt head described in the attached letter or contained l in the package this notice is affixed to, should be handled l in the following manner: l 1. Before removal from the delivery truck, the package must be checked with a radiation survey meter to make sure that no point at a meter from the surface of the package has a leakage of more than 10 milli-roentgens per hour. 49

P * * " ^ 2-4)lO66efhtq 5339O /9 /T - // C- /)qt f?_pnbrucs O A) SRpAce = - - - [ ~ paeor 3 [ O T' DP .2 6 /o /2 L %-froH $~ l 9 y* O-i 1 ,So u act Pr eti2ct

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.tr ,3a ra., n..,- i \\G f. TC < 1f 1B ) ,\\ g, 4' 'i i .I1 a.t 4 ~ *ll 25 ' t c ~,, s. x cra re n '8 .CC 47 1 p.* a r-pp ! Y%( TerraA .as .se 6 sr l sj j l 3* l . V s,. i , 41 8, S o vice. e Pf AI5L9 9 5 c n 3r n. D /9 RUM S/r5/15 l HSS1 C {t /w guRIp b E- -- -- (N

O 2. Remove from the delivery truck with lifting equipment of adequate capacity to handle the package weight of 4000 pounds. 3. The wooden a d steel protective cover may be removed in a con-venient area outside the building. Remove the 20 socket-head cap screws around the base and lift off the cover which weights approximately 800 pounds. CAUTION: DO NOT REMOVE THE HEAD FROM THE WOODEN BASE. 4. The head and bace may now be moved into the room in which it is to be installed. NOTE: No further work may be done with the head except in the presence of the licensed individual named on the red tag affixed to the front of the head or in the service man's instructions accompanying the shipment. In case of accident or emergency, call the ADVANCED MEDICAL SYSTEMS, INC., (216) 692-3268, or out of the state of Ohio 1-800/ 321-5803 or 5804. I~}.3 Preparing an Empty Package for Transport. k-See Following Procedures: i INSTRUCTIONS FOR RETURN OF SHIPPING BOX PART NUMBER 181375 1. Bolt the metal braces from the head back to the skid, l 2. Repla<q the cover using the colored lines for orientation, put back all the bolts. 3. The " Radioactive Material" lettering on the top of the box must be covered (masking tape may be used). 4. The " Caution Radioactive Material" marks on the box must be covered ( masking tape may be used). 5. The Diamond Labels must be removed and " Empty" Lebels applied. l 6. The box Tmpty Weight is 1200 pounds or 544 kilograms. 7. Use the return lables provided. Ship To: Advanced Medical Systems, Incorporated 1020 London Road fT Cleveland, Ohio 44110 k) 50

7*3 PREPARATION OF EMPTY CONTAINER FOR SHIPMENT PART NUMBER 181361 WITH 3320 AR A. Make wet smear contamination check on the outside on the container. B. The SOURCE EXCHANGE CONTAINER must bear two (2) labels. C. The top flange cover and drawer cover must be sealed with wire and lead seals. D. Assemble the EXCHANGE CONTAINER with the source in t% outer package as follows: 1. Lift container and remove casters. 2. Lower container on wooden base using colored index markings for orientation. 3. Insert "THRU-ROL3" as a check for align =ent. Install four (4) Hex nuts and bolts to fasten container to wooden base. Remove " M U-RODS". 4. Lower wooden cover over container using colored index markings for orientation. 5. Insert "TERU-RODS" and asse=ble hex nuts on "THRU-RODS". 6. Seal wire cover to base. E. Apply two (2) EMPTY labels to the outer package. F. The carrier must be advised of the containers content and the Bill of Lading marked as follows: 1. Container Radioactive Materials - EMPTY, RVNX.40 per lb. 2. This is to certify that the above named materials are properly classified, described, packaged, marked and labeled and are in proper condition for transportation according to the applicable regulations of the Dept. of Transportation. 3. Shipping weight is the full gross weight. (A source only weighs about 2 pounds.) O 51

8.0 Acceptance Tests and Maintenance Program. 8.1 Acceptance Tests. The tests to be performed prior to the first use of the package are as detailed in the following paragraphs. 8.1.1 Visual Inspection. A. Visual mechanical inspection of the components parts required in the manufacture of the package and contain-ment vessel to assure compliance to the drawings. Acceptance is upon compliance or acceptance by a material review committee consisting of a representative from Quality Assurance, Engineering and Inventory Control. Items of non compliance are presented to the material review committee who decides to scrap, rework or deviate for use as is. pection of the sub-assemblies to assure B. Inprocess Visual proper manufacture to the assembly drawings. Acceptance /h and rejections are the same as in "A" above. Yl C. Final Inspection of the assembled products to assure proper function and safety. All items are brought into full compliance before release for use. The material review committee meets to decide the disposition of non-conforming material. 8.1.2 Structural and Pressure Tests. l A. Structural Tests As determined from the drawings tests are made on the welds by X-Ray, magnetic particle or dye penetrant tests. The requirements for acceptance of these tests are detailed on the drawings where the tests are required. Calculations indicate compliance of the design. B. Pressure tests are not performed since calculation indicate complete compliance. 8.1.3 Leak Tests. l Leak tests are performed on each source, as detailed in ANSI N542-1977 A 2.2.2, at the time of manufacture by Advanced Medical Systems, Inc. A certificate of this test is provided. Any source not meeting this requirement is not released for shipment. The source is the con-O tainment vessel. 52

g S.I.4 Cc=pc ent Test. A. Visual rechanical tests as detailed in 5.1.1-A are perfc =ed. 3. Material Certificatics a:d/or testing zay be perferred, if required by the drawings. C=pliance to the drawings is :.anda: cry. The :aterial reviev =ittee handles dispcsitics of :::-cc=fc=1 g ce:penets. 5.1.4.1 Not Applicable. S.1.4.2 Gaskets. Gaskets, even though used, are =c: necessary for the prepar per-for._ance of the package. They are a carry ever frc: when the containers were shipped without an overpa-k. S.I.t.3 Net Applicable. 5.1.5 Tests for Shielding 1::egrity. A radiatics survey of each new package is cade. Readings are taken at a dis:as:e of 1 se:er frc: the source and c the surface of this package. These readings are of the package. (Tele:herapy head er shipping container) at the 26 points as described i: N.C.R.P. report no. 33

4. 2. 2 (a).

The readi=gs obtained are extrapolated to the design axi = capacity, if the scurce used for the readings is less than the design maxi =u: seurce si:e. he readings when extrapolated to the design._aximu= source si:e =ust be less than 10=r/hr. at any point at 1 =eter and less tha: 200 :r/hr. c the surface. When place 1 in the everpack these readings vill be reduced further due to the greater dis:ance of the outer surface frc: the scur e and the shielding of the overpack zaterials. No ec::ainer is released for use if readi=gs are in excess of the above li=its. S.I.6 Ther al Acceptance Tests. So special ther a1 tests are cade. The axi-- heat generated by decay is less than 200 Vat:s. Whe: contained in the overpack the temperature of the container rises to abeu 50 C at an a:hiest temperture of 22 C. G ~ 53

t 1 i O 8.2 Maintenance Program Before each use the nackage is thoroughly inspected. All defects are corrected before releasing for shipment. The maintenance program is therefore, a continuous program. Replacement of a package is not anticipated since repairs are continually made and normal life expectancy is in excess of 20 years under these conditions. Repairs are made so that the repaired area is no less stronger than the original package. Exact replacement parts are used in all cases. ' Shielding tests which are made prior to each use, at 1 meter and on the surface and the tests detailed in section 7.1 are the tests to be made. 1 O t t

• $ 64 54

All Values Used In This Analysis Were Taken From: 1. Materials Selector, 75-A Reinhold Publication. 2. Machinery Handbook, Industrial Press. 3. ' Air conditioning and refridgeration B. Jenny & S. Leivis, 4th Edition, International Textbook Company. 4. Marks Handbook. 5. Oak Ridge National Laboratories, Cash Designers Guide. 6. ORNL-NSIC-68, UC-80 Reactor Technology, Pages 129-130, 134,142-143, figure 5.3. 7. Introduction To Heat Transfer, A.J. Brown (Professor of Heating & Veutilating, Ohio State University) ist. Edition, McGraw Hill Book Company, Inc. Page 62. 8. Fastener Standards, Industrial Fasteners Institute, 5th Edition, Pages N20, N 34. O / / O 4 SS ~ ~ 7.}}