ML20148L641

From kanterella
Jump to navigation Jump to search
Safety Analysis Rept,Tech/Ops Model 850 Type B Package
ML20148L641
Person / Time
Site: 07109147
Issue date: 10/30/1980
From:
TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:
Shared Package
ML20148L633 List:
References
17813, NUDOCS 8012100672
Download: ML20148L641 (65)
v • d • e


Text

{{#Wiki_filter:. Tech, Ops [ 3,{- "lrr.-[;; 7 L .) b q,n t!!, t !.;9,. ' m

w.. : ~2 ne-*:_

Rc J J'icn ProfuCts Di/5 ion 40 Nodh Avenue So::.ng:on Massuhusetts 01803 Tekph0*,3 l617) 272-2000 SAFETY ANALYSIS REPORT TECH /0PS !<0 DEL 350 TYPE 3 PACD.GE ~ l l 3032100(#74

v 1. General lnformation Introduction Tech / Ops Model 850!is designed. for use as a source changer and ship-- . ping container.for Type B quantities of radioactive mate +1c1 in special form. JThe Model 850 conforms lto the criteria for Type B. packaging in.accordance with 10CFR71'and satisfies the criteria for Type B (U) packaging in accordance with IAEA Safety Serics No. 6, 1973 Revised EDITION. 1.2. Package Description 1.2.1 . Packaging i .The Model 850 is' 10.4 inches (264mm) high, 8.5 inches (216mm) wide and 8.8 inches (224 mm) de-p. The gross vaight ef-the package is 77 poundF (35kg). The radioactive source assemblies are housed in R itanium "d" tubes. The tube has an outside diameter of 0.56 inch (14.3mm) and a wall thickness of 0.03 inch (0.8mm). A source stop is installed in one side of the "U" tube to provide positive positioning of the source assembly at the appropriate storage location. The source tubes are surrounded by depicted uranium metal for shield-ing.. The uranium metal is cast around th9 titanium source tubes. The weight of the uranium shield is 49 pounds (22kg). The uranium shield. assembly is encased in a stainless steel housing. The shield assembly is' supported an the bottcm by a stainless steel support. plate which is attached to the package housing. The shield assembly is supported on the top by the lock asremblies. Horizontal novement of the shield assembly is restrained by the studs which mount the support, late to the housing. Rotation of the shield assembly is prevented by engagement of the titenium "U" tubes with the lock assemblies. Copper separators are used to prevent iron-uranium interfaces. The void space between the uranium shield assembly and the staini~ss steel housing is filled with a castable rigid polyurethane foam. Mounted on the top of the package in the lock plate weldments are the lock assemblies. Thesa irck assemblies are used to secure the radio-active source assemblies in n-proper shielded position during trans-port. Cover plates, fabricated frca stainless steel, are installed on the package to provide protection of the locking ascemblies. Tamperproof seals are provided during shipment of these packaget. Two vent holes in the package provide passageways for the escape of any 1-1 Revisita 0 30 Octcler 1980 4 7 3 e s a,,-~.m n.w-y, w-.,,-u ,,w.-,.- ,4w ,-,,,.mn <,,-,.-~.w-a m--m.,,e

4 gas generated fron the decompositio'n of the polyurethane foam in the event that the source changer is involved in a fire accident. The outer packaging is d signed to avoid the collection and rotention of water. The package has a smooth stainless steel finish to provide for ecsy decontamination. The radioactive material is scaled inside a stainless steel source capsule. The capsule acts as the containment vessel for the radio-active material. 1.2.2 Operational Features The source assemblies are secured in the proper storage position by means of the locking assemblies. The lock slide engages an under-cut in the source assembly preventing movement. The lock slide is secured in position by maans of a key operated plunger lock. 1.2.3 Contents of the Package The Model 850 is designed for the transport of iridium-192 in quantities up to 240 curies as Tech / Ops source assembly Model 90003. This source assembly contains either a !fodel 90004 or Model 90005 source capsule. These capsules satisy the criteria for special form radioactive material in accordance with 10CFR71 and IAEA Safety Series No. 6, 1973 Editien (Sectic'a 2.8). l l l 1-2 l Revision 0 30 October 1980

l I 1,3 Appendix Drawing 85090 sheets 1 - 5 Descriptive Assemb,1y Drawing 85092 Label Drawing 20091 Source Assembly ~ 1-J F.evision 0 30 October 1980 v ..-yy

l

  • * ~ ~ ' " '

6 % 901 l '" l '" ! TAFETV WlRED WITH TAMPER PROOF 9AL p \\b / a' 7 -N e >V ~ A / A I i i. 4 3 g o 'm ' :D s %3N% 'N-p y \\ / s. s t ,s M l 3.Q s TJTAL VVflGHT: 75 L85 (?>.KG) ~' AS NOTED En" mal "a"*Y552((5359*" -, ~ ,,,,,y f. MODEL 350 SOUR.E CHANCdR

.u..%., -i ;"*" ':~" ~--~

C.=5CRPiIVE A%5MKY sc 7 .a n_

~..

/ IC l 35090 Is 1.~. ~34 . s.m ,3 I-6'

. W 90l 10 ')2 PAN HD SCR. (d) (STEEL) SAFETY WIRE i j. (.030 DIA ST.STL) HAnttR (2) (3/8 DlA 3C4 STSTL) EMLL DETENT PLUNGER (2) (VpER 88 S38W12N) I r L I t' ) () 1 _____._{_..__ .. -- /- [ ROLL RN - t/8 DrA (2) (STEEL) I k L cf", j D [(CCRBI.4 LOCX,MoDir;ED / I

  1. 02290)

I / r-; [ y r- 'y ,. -- SCTTOM PLATE (2) /! w~ . [ (* i ^ 'l / (1/4 COLD pr@wrf STEEL)

  • 'Q

/@' y l s s s N; l n

  • I Ja.

i

  1. (20 HCX HD S 5
  • c,

! s . - }" l ' / L--. ;.. )T p p' 9 A / A '*g;e-l r g bl+ d I l 8.9 i I m Er. A ]#n untat<ED I~,Tsl i cocr.o l \\ N'/ J 6, lc ___________._w=_t.__ _____.--I LOCKihG SUDE (2) f (1/4 TWX RAT GROUNDSTEEL) (> t) ( LOCK PLATE WELClf V / TOP VIEW L V 'np (LCCX C[CR R. ATE

  • REMCVE~>)

o \\ $ WELL (REF) (13 ( 090) GA %4 3T STL-TYP) REF _. g,a J ~ " ~ AS NCTED C

  1. Yi$',i{o*y,3'$=~

MODEL 850 SOUFCE CHArCf_R S c:;4...-W" ~."-" ~ _ CERPTivE ASSEMaY mv .s r s ICl 65090 l0 s .E.. s - n. +m 7 o, 5 l - 5~

MO901 ! "' ' " i e Lock C0VER(2) SOURCE 5TDP ASS 1'(2) (11G4 (.l20) 304 ST.STL) (4 UMlNUM) B wq t / w t y (TYP \\ . $1 r r; ) ~ u /: / [ p/ / NLOCK PLATE VVEldT [/, $ m Lbi l '~ (13 GA,5/16 & I/4T* 30d sTSTL) / /; s s s - r- .f/ M y, r /' // e '/// 4 w S Axxs s s xxxx xx s x 1 x s

Jy us

,s N!// f/ /,/ j' /T .22 -- M"3 ?'4 g _C Nl / (_ l NC LAMP RING l2) REF. s / m N s 1 y jN i p// l '\\ . %90GRCE TUBE (2) REF. I C,.4 I 2 Pn 7 / x /: l \\ / N-$ WIELD A55Y / ) / /h, _ Q _ y._y'f. / (SEE SHT

  • 7) s s s

~ // /// j j SICE PLATE (1) k' (13 GA(.090) 004 ST.57L-) N -CDTER OF PADIDACTNE Source MB cECTION A-f' ZAM FILL M (l' DIA - 2 HOLE 5) --WLTAFCAM 16-L-t03 OR EQUIV. COPPER $HIM (RtGID FOL1'UPETWJ1E roam) (.03 THK) As NorED Ed a***[ E 5 9. 9 *" '~ $CURCE HCLDER ASSY ~NODEL 69J $0URCE CHAf1GE We* we.n=., DESCFJPTIVE A'sSEMBLY ~- b .s p".._._ * (-~~~,,~,tl^'65090 10 w. 4-, n 3 <,, ! **M... . -, - - -. ~ - - - +

85390l ~' ~ s - NEX HP BCtl~,5[6-18(O (sT. sn.) ~NFEADED ADAPTER (2)- It0. I-IS THO (3M ST STL) n m u.s 1 ITT1 304 ST STt. <a d ' / 2 "- y LOCKING SLICE (REF,. &l~ f l

/

lN LOCKED P3SITION L base ,/: ru m : ct _.h1 ro - a s, p'.xxx SHIELD SUPPCRT F'.O (2) psx pj xxx s ,y ' " lI/ ua M. j f I L c -.1 / l I

-#{fg'fg I,

!/ 1 /ll' P / /l l /. t i i / /. I. l l 'il I '12 - TYP x~ a~ g NTUEE GUAPD(2) (1/2 0.D. r 1/32 WE CC,PPER) N i /i / - D2:== f ' /- / 3 A ( 90) 304 $7 STL) / s. \\ \\ .N-SIDE PLATE REF 1/ 8 g^ 9ECTION B-B so m u etaTe (f 1C-4(.m) 3C4 ST STL) } SHIELD SUPPGRT WE'dT ( 3/16TWK HOT R0ttTTEEL) l 49 r1CTED E2 o?a'[;{ $ @,"'[g[soa ,[ l[5 DEL 850 SOUFG CHANGER,; m.., a :-~n-cesemya mwas 3 lo... u m, ._,d,im_,69090 ~,,,I ..~...,; i-s.r e ,3 b~5-

650901 i r- = 6.l2 a,77 CLAMP RING (21 .,_ '97 pg7_ 'CCM.PL'RE TITAnivM) i. ,. /, I,/ / l-(co) _;n / A / l. l 1 4.730 ,/ /,, ',/l/ / ,/ / i s / 7.79 /, 1.ww -'/ ~~ s ,/ WI ' (, / -s / ,ll \\ j \\ 1 + '- 3HIEi.D ^0URCE TLEEl2) ,I f, f, (CEP E'ED LP/-hlL'A) 9/16 C.D < l/2 f.D t (C;Mt,'-IuALLY P.55 T'#f.M) i i I t i I, 3.90 I f

t 5H?_C AH_
VELY

~ l i gl I vvEfC0 49 ; - (72.2 E-) I 2,38 ~~~ ~ ' i .i (,?s_/ D:A \\ h0T TOP 4 J I f i / A9 r1CED E Ea*[532/El'@Y9' s esAde .- l. 79 m frlu '.tCCEL 3'O SOJRCE >ANGEF n (=" ';-" ~, c y cp.p m z pgeg,.aggy f g an was<:s,m e,_0 9 9 l '.< <_ ~.: !Cl ra./ 07 .c,. +m 3.* 5 /- El

efj R EV. CATC CESCRIPTION

rea J$/l Vs l

i 3-plGH l6 l.. H G4 .4 L o 0 DAN ~,ER a y,eu IO woort.5f0 g. [ssa. no. "",). isoT:Pr ! A !92'y cap 4c ay 2COCl' 3~ H ~,,_M j l ~M y

  • HIGH RACl0ACTf/E mal RIAL" 1

MISM 7 4 c.r F E,OECIAL FORM ; 71.0.9 U6,A b(U)_I YPE & %1 mea 2 3 49 L3 22 KG b ~ HIGM P4CIO'-CTIVE SHIELCITIG UF/-JllVM35 HS #r g3 TOTAL WIC-wT' 77L3 7I f Y,'#'iC;LOTi:17:.tj:"C.Ai;14 c.'N F4'S c3 DIV. l 0 f!.* RTH l Ehu'. E. :u n5:~. 1 MMS 3 usa - C / / 2 ? NIGN J . -_ _ -[ 3__ R E V ($G'OS' l.N.L C 7;f C 2:25,.ca,cimN Swect f ec ETwo imo ',h','i Ps:$ CCj *.W1 Dik:; ), ein:r's FG3;:e:C PA'riC G.b'w * \\?5n FE, =C. ?*3,595 J, sIE,"/3 Tic S CE l P47iIiC Vj.?f,7/. l7;4 *. E:.% FJ t~*b. E ' y

  • ' ' AT E T.lALS

, w., TECHNICAL OPER ATIONS INC. ' "g 'Y'l[g 7O CL 'NTI$N RADIAT!ON PRODUCTS DIVISIC N i => r,:-

m. Lh" B U R Li r4 G TO N, MA 01003
  • W. /

' ilNISH OWG TITLE ~.. 5, J. 3 i-c / 1 :.? l /1l { M yl f /r

- 4,v3 sy e tess orscawiss s i=rico vouai~ cts iac

/

,. < j.

/ e,.., -e n .x Ag . a..a h Size C/G. N O.,,, Acg3 sy .xx ct, '.SincAT ICN AEY. q ,xxx C b) 1.b C. E 3 SY ( As;g,gs 3 FEAcT:CNS g SCALE N,?;E l SHEET I 0F i

ggq j m l :.. l ~... 10.6% CAP 5UtE P1 DER .C94 DtA rcd. PIN (300 *IR, sT.sTt) .5TEnE.D SH:ELNfG REAR COUPunG(2) (W") (*" ") {DETAllA {CETAll8 FrTr;;SHIELDNG ^ (WfGSTEti) I i / } 4/ s ) ( ll64 2 fib l@lp oM:3 W.:J A CJ lo I .J74CtA L.3,,oiA (250 DIA 1 CE.'ii R $HIELDING cGT CO.PJNS (3) Rc)R SHIELDitG SOURCE EXTEN90N ~ (7JNGSTEN) (?00SERIE$ SI *TL) (TUrG$7Erf) (T'#657EN) SOURCE ASSY PSLLE AS5Y 90CC4 cR 9000f _. [ k,,k^.. l ![Q3 an

  • f DETAll A luteri(srsrt)

FEMALE CG1NECTCR Scu 2:1 . (4130 (C8.D DPNrti STEEL) CAPSULE R)_ DER A$$Y MALE SOURCE CCMECTS } POLLPld CONP. "PR'.NG (%EL) (\\LSIC W!EE 5 EEL) } - - / _.. / /,,,3 $)Y%%\\%.4 FredMV G,. q f-[j /v(/ ,.N .7x p } .' -{ r

r.,

,\\ a 1 26 D:A - CEiilL 8 -SLEEVE scat 4:: (460 C.D STEEL) 5OURCE CONNECTOR A55Y w~ N.- s i ~ nno LO ~25?}.0T&.'s% 33g ga DW W fG MF"fP DE T R; Tid A$5a%.Y T l".c. n _.w. d wu 9 X 91 l -- wes-i. t t.w. ,.m ,: e ss,, n...

4 2.0 Structural Evaluation 2.1 Structural Design 2.1.1 Discussion Structurally, the Model 850 consists of four components: A source capsule, shield assembly, outer houring and locking assembly. The source capsule is the primary containment vessel. It satisfies the criteria for special form radioactive material. The shield assembly fulfills two functicas. It provides shielding for the radioactive material and, together with the lock assembly, assures proper posi-tioning of the radioactive source. The outer housing is fabricated from 13 gauge (0.09 inch or 2.3mm thick) stainless steel. The housing provides the structural strength of the package. The cover plates protect the lock assemblies. The lock assemblies secure the radioactive source assemblies in the proper shielded positian in the package and assures positive closure. 2.1.2 Design Criteria lhe Model 850 is designed to comply with the requirements of 10CFR71 and IAEA Safety Series No. 6, 1973 Edition. The device is simple in design. There are no design criteria which r annat he evaluated by a straightforward application of t'ae appropriate section of 10CFR71 or IAEA Safety Series No. 6. 2.2 Weights and Centers of Gravity The Model 850 weighs 77 pounds (35 Kilo 3 rams). The shield assembly contains 49 pounds ( 22 kg) of depleted uranium. The center of gravity was located experirentally. It is located along the vertical axis at a distance of 4.3 inches (110m.m) above the bottea surf ace. 2.3 Mechanical Properties of Materials, t The Model 850 housing is f abricated from Type 304 stainess steel. This material has a yield strength of 35,000 pounds per square inch 2 (241MN/m ). (Ref: Metals Handbook, Vol. 1, Eighth Edition). Drawings of the source capsules used in conjunction with the Model 850 are enclosed in section 2.10 These source capsules are f abricated from Type 304 or Type 304L stainess steel. The capsules are sealed by tungsten inert gas welding. 2.4 General Standards for All packages i 2-1 i Revision 0 30 October 1980 1

l i 2.4.1 Chemical and ' Galvanic Reactions The materials used in the. construction of the Model 850 are uranium metal,' steel, titanium, bronze and copper. There will.be no signif-icant chemical or galvanic action between any of these components. The possibility of the formation of the cutectic-alloy-iron-uranium .at temperatures below the melting temperatures.of the indidivual metals has.been' considered. The iron-uranium eutectic = alloy tem - peratures is approximabely 1337 F (725 C). However, vacuum condi-ditions and extreme cleanliness of the surfaces are nececsary to produce the alloy at this low temperature.. Due to the conditions under which the shields are mounted, sufficient contact.for this effect.does.not exist. In support of this conclusion, the following test results are pre-sented. A thermal test of a sample of bare depleted uranium metal indicat' d that the was. performed by Nuclear Metals, Inc. The test e uranium sample oxidized suchLthat the radial dimension was reduced by 1/32 inch (0.8mn)..A sulaequent test was performed in which a sample of bare depleted uranium metal was placed on a steel plate and subjected to the thermal test conditions. The test showed no melt-ing or alloying characteristics in the sample, and the degree of oxi-dation was the same as evidenced in the first test. Copies of the test reports are included in Section 2.10. Notwithstanding these test results, copper shims are used as -sep-arators at all iron-uranium interfaces to prevent contact and to pre-clude the possibility of the formation of this eutectic alloy. 2.4.2 Positive Closure The source assemblics in the Model 850 cannot be exposed without open-t i ing a key operated lock. Access to the lock requires removal of the cover plate. The cover plate is seal wired with a tamperproof seal. 2. 4.3 Lifting Devices, The Model 850 is designed to be lif ted by two handles fabricated from 0.38in (9.5mm) diameter staineless steel. These handles are attached to the package by means of 0.09 inch (2.3mm) fillet welds around the entire diameter of the handle on each end. Thus, the stress area of (56.8mm*). The yield strength of the weld is 2 each weld is 0.038 in 2 assumed to be 35,v00 pout.ds per square inch Q41 MN/m ). Therefore, each weld can suppcre 3080 pounds or forty times the wei ht of the 3 package without exceeding the yield strength of the material. 2.4.4 Tiedown Devices The lif ting handles of the Model 850 are also used as tiedown devices. 2 2 Revision 0 20 October 1980 -,. _.._ _ _._ _ ~ _. .. ~..

7 _u _, y ( n + i As demonstrated in Section12.4.3, the weld at each.endLer each handle can support :. forty - times: the' weight of the package without-generating ' stress:in excess of the yield strength of the material. 2.5 Standards for Type B and-Large Quantity Packages 2.5'1I Load Resistance i Considerng the' package as a-simple beam supported on both ends with a uniform load of five times the package weight evenly distributed along its ;1ength, the maximum stress can.be computed from: l, o-19; 8Z ? Where: c: Maximum Stress F: Total Load -1:. Length of the. Beam-Z: Section Modulus-1 (Ref: Machinery's Handbook, 21st Edition, P404)- 3 The Load is assumed-to be-385 pounds. The package is assumed to be a rectangular shell 8.5 inches (216mm)~ wide, 8.8 inches (224mm) deep and a wall thickness of 0.09 inch (2.3mm). Consequently, the cection 3 8 modulus is 8.78. in (183,858mm ). The length of the beam is assumad to be 10.4 inches (254mm). Therefore, the maximum stress generated in the beam is 57 pounds per square' inch (393 kN/m ) which is less than 0.2% of the yield strength 2 of the material. i 2.5.2 External Pressure. l The Nodel 850 is open to the atmosphere. Therefore, there will be no- { differential pressure acting on it. The collapsing pressure of the source capsule is calculated assuming that the capsule is a thin wall l tube with a wall thickness equal to the, minimum depth of weld pene-i tration (0.020 inch; 0.5mm). The collapsing pressure is calculated j from: P: 86,670 t - 1386-d Where: P: Collapsing Prescure t: Wall Thickness d: Outside Diameter (Ref: Machinery's Handbook 21st Edition, P440) 3 l l 2-3 Revision 0 30 October 1980 i 1

~ 7 VL o The collapsing pressure of the source capsule is calcolated to' be 2 7070 pounds per square inch l(49MN/m ). Therefore, the. source capsules . can. withstand-an external prr.e.sure of 25 psis. 2.6_ Normal Conditions of Transport ' 2.6.1 Heat' + . The thermal eyaluation of the-Model'850 is performed in Chapter 3.. From this evalvation, it can be concluded that the Model 850 can with-stand the normal he,at t:Snsport condition. i J 2.6.2 ' Cold v The' metals used in.the' manufacture of the Model 850 can all withstand . a temperature of -40 C. ' The ' lower operating limit ' of the polyureth-0 0 ane foam is -100 F (-73 C). Thus, it.is concluded that the Model 850 will withs.cand-the normal transport cold conditions. 2.6.3 Pressure The Model 850 is open to the atmosphere: thus, there will be no diff-erential pressure acting on the package. In Section 3.5.4,-it'is demonstrated that the source capsules are able to withstand an external 2 pressure reduction of 0.5 atmosphere- (50.7 kN/m ), 2.6.4 Vibration The Model 850 is basically a welded package. The locking assemblies are siedlar in principal to the locking assembly of the Model 900 (USA /9141/B). The Model 900 was subjected to a vibration test. The package was 2 vibrated for seventy minutes with a maximum acceleration of 9.8m/s at each of the following frequencies: 5, 8, 12, 20, 32 and 80 Hz. At the conclusion of this test, the source assembly remained secured in the proper storage position. There was no reduction in.the shielding .) efficiency or structural integrity of the package. l On the basis of the Model 900 vibration test result and the similar-ity of the locking assemblies of the Model 900 and Model 850, it is I concluded that the Model 850 will withstand the vibration normally incident to transport. 2.6.5 Water Spray Test The water spray test was not actually performed on the Model 850. We contend that the materials used in construction of the Model 850 ar+. all highly water resistant cod that exposure to water will not reduce t 2-4 Revision 0 30 October 1980 -.s. .a u m. b----..A ,* - + > -.......,.-wri, y-.--w.m-w m m y,, -,,,g-,w,mc.,., --v w 3 f y,,,,,-.y-p-,.-m.--u y,,g-pww.w_...,,,,,,,,,,chy p,,,,

1 1 4 i 1 4 . l thm shielding or affect the structural integrity lof the package. l ~ l 2.6.6' ' Free Drop 1' The drop analysis performed in Section'2.7.1 is sufficient to satisfy' the requirements of the normal transport free drop condition.' On this basis, we conclude that the Model 850 will withstand the free drop without loss of shielding effectiveness'or loss of package integrity. j t 2.6.7 Corner Drop Not Applicable 2.6.8' LPenetration r A penetration test of the Model 850 was performed. There was'no' loss' of shielding or loss of structural integrity as a result of this test. A copy of the test report appears in Section 2.10. 2.6.9 Compression The gross weight of.the Model 850 is 77 pounds (35kg). The maximum cross sectional area of the package is 42 in (0.06m ).- Thus, five i 2 2 times.the weight of the package' (3851bs; 1715 newtons) is greater than two pounds.per squape' inch multiplied by the. maximum cross sectional j crea (184 pounds; 820 newtons). ) i The Model 850 was subjected to the conditions of the compression test. [ A load of 459 pounds <1044 newtons) was applied uniformly to the top and bottom of the pt or 68 hours. As a result of this test, j there was no loss of _ ing effectiveness nor loss of structural i integrity. A copy of the test report is included in Section 2.10. i 2,7 Hypothetical Accident Conditions i 2.7.1 Fr,ee Drop [ The Model 850 was subjected to a drop te'st through a distance of 30 { feet onto a steel plate. There was no loss of shielding efficiency nor loss of structural integrity as a result of this test. A copy of the test report is included in Section 2.10. l 2.7.2 Puncture The Modc1850 was subjected to the puncture test of 10CFR71. As a l result of this test, there was no loss of shielding efficiency nor loss of structurial integrity. A copy of the test report is included l in Section 2.10. i 2-5 i Revision 0 30 October 1980 { h e P r b

+ - T '2.7.3 Therral fThe fhermalfanalysis'is presented in Section 3.5. It is shown that i the melting temperatur(> of the' materials used in the construction of i the Model 850, except.the polyurethane foam, are all in excess of 1475 F'(800 C). 0 To demonstrate that the radioactive source assemblies will remain in. a shielded position following the hypothetical thermal accident, the following analysis is presented. At; the conclusion of the thermal- . test, it is assumed that the polyurethane foam has completely escaped. from the pack &ge. ' The shield assembly is prohibited.from ' rotational movement by the ti'anium "U" tubes which.protuCe from the package t housing. The shield is restricted from vertical movement by the. shield support ' plate, connecting rods and lock assemblies. 'Thus, it is concluded that the'Model 850' satisfactorily meets the i requirements.for the hypothetical accident.- thermal condition of 10CFR71. -2.7.4 Water Itsersion Not Applicable r 2.7.5 Summary of Damage The tests designed to induce meche,ical stress (drop, puncture) caused minor deformation but no reduction in the safety features of this package. The thermal condition will result in no reduction of the safety of the package. It can be concluded that the hypothetical accident conditions have no adverse effect on the shielding effectiveness or structural integ-rity of the package. 2.8 Special Form The Model 850 is designed for use with Tcch/ Ops Model 90003 Source Assembly. This source assembly contains either Tech / Ops Model 90004 or Model 90005 source capsule. These source capsules satisfy the criteria for special. form radioactive material. A copy of IAEA Certificate of Competent Authority No. USA /0179/S is included in Section 2.10. 2.9 Fuci Rods Not Applicable 2-6 i Revision 0 30 October 1980 ,.,,.,.n. ,,,-,,n._,.,,,,-. ,_,,,,,,w,,,,p,-..

4 2.10 Appendix Descriptive Assembly Drawings - Model 90004 Source Capsule Descriptive Assembly Drawing - Model 90005 Scarce Capsule Test Report: Uranium Thermal Test Test Report: Penetration Test Test Repor*.: Compression Test Test Report: Free Fall and Puncture Tests IAEA Certificate of Competent Authority No USA /0179/S L 2-7 Revision 0 30 October 1980 l

REV. CATE DESCRIPTION A \\; cr.n'so REcm.yri Ft:v'd stzG - rw crawr.w,~ a L .@.0 REF E.I NT' P4 A 3 % i\\ \\' . 3' ' fI l. J --. - TO FROMT + .C $ ' ill 11i1 ',,1-

2EF.

1 . ' /eP' * \\ \\ 'k\\\\,h CF PROJECTOR J 2 4 i 3 HEUARC 7,ED PER TEGW:P5:JiCAPS, PRCGDUE l MAX CA AT P,'aD u.?l5 TECHNIC AL OPER ATIONS IN C. ' t1ATERIALS y-4h RADIATION PRODUCTS DIVISION [L 3 E $ l.J 9 0 0 M 1 B U R LIN GTON. MA O!BO3 DWG TITLE T MSH GENESS 8B ('l ,^ " Uk5Nt$$$[c"n' ccs anc f ) Wi.W 79 .X 1 CHECKE0 SY .XX = CLASSiflCATION SIZE DWG.NO. REV 2.C. 1..< i 7.#, I XXX APFROVED BY ANGLES A E ETicN3 A SCALE 4 ;l l SHEET l OF l -- m m.

R EY. DATE DESCRIPTION A w n'S3 mWN n:M*B"Sr:E-no:W CWhT5 m g d Q ' i 00005 _ o ~ [3 .09575 DIA y c< ST STL EALL r

n v

PIC~a AK-7 .., s CR EQUIV, ' li?Q 2,00007 + i l2 v q n O ,lM00 DIA uoQ STSTL BALL o

  • g=

0 Plc d AK-3 4 OR EQ'JIV. r // V///// ' sL 17 r N. h t a.ltN 4 I i " P< q [h- 'i (../ /$ l'5 y l v //r/// s e ,I \\. s Si i.cca oc -,.ll 7 - - P t,002 .373 5 y ,y

  • 5

.D3E5 $NARP

l. ALL JriCLUDED DelLL o

SUT FREEOF BURR 7 An3LW5 II8 i l* q t.iATERIALS 2 J4 OR 304L ST STL TECHNICAL OPERATIONS IN C. p~ 0 Gig-N.. '^Ene"Jo"oNff/liojf5 "^ !.M32.'AL GRT FICCTICN REWiEED l ' FINISH DWG TITI.E l I F * %\\'< N SY enttss oTHtawist SPECif tf D TOLER ANCES ARE jW,.,/w, .x 7 50JRCE CAP 5ULE B01 TOM CHECKED BY .XX = 8 C.34w > 4,7).;u ff .XXX i./M~ CLASSIFICATIONj SIZE DWG,NO. REV. APPROVED BY ANGLES l/2 l ~ TRACTICNS A SCALE dl l SHEET I OF l \\ - w n

4 REV. DATE DESCRIPTION FED @WM FEM B Sl?E ; m A G 53 no oTsaR cHAnsas dg O g a V E2 o 0-d.003 E o ,.3CO - tn S' d,005 a { mlTb +o S 0 .030 WlDE x.OIO DEEP + -e x9 UrlCERCUT 8 +i o* I f d y g4 gw] tn. -'l h' +; gn +, g5 so g ?p p - "'N\\,, s' \\ .070 x49 CMl/F ( BOTH EnD5 Lr m's 094,- H c P qw 4 8 -- oc I E8,O

l% +

Si f 4 EDGESl&RP g ap BUT FRE5 CF EUR:l$ ~,218 q MCF:~: I, ALL INCLUCED CRILL ArG.L5 ll8 t l'. TECHNIC AL OPER ATIONS INC. 3 C4 *iE 304b N. 3b T5 MATE.'AL C;ElFiCATG1 RJ RED bMM RADIATION PRODUCTS DIVISION B U R LI N G TO *J. MA 01803 f tNISH DWG TITLE GEriESS 6B m er =,t = =,,...

$,;"i' ;

SOUR CAP 9JLE SHANK r7 O

  • i..-r. *,,/felg. '.XXX

. IM CLASSiflCATION SIZE DWG.NO. REY. vr A 90004-2 A meom eT A,auS e 7RAcTIONS A SCALE dl l SHEET I 0F l

{ REV. DATE DESCRIPTION O.650 REF ~ = /tq;p' lp y x p g,,! % o

;/

f / - Q 0,'205 =y x 4 3 . lR METAL MATERIALS ,,,.s, TECHNIC AL CPER ATIONS INC. SEE BtA 90 COB Wi!03>; RAO!ATION PRODUCTS DIVISION B U R LIN GTON. MA 01803 "~ h " !?iNISH DWG TITLE a SOURCE CAP 5ULE ASSY ~ =n=:- ~:.8v,"i3 ~ .x 2 / [ NECKED BY ,XX = .xxx / ~~~ class;ricATioN s:zE DwG. No. a cy. / A 90005 o ~= = 8v ANm: s F R AcTICNS, SCALE / :4I l SHEET l OF l /

R EV. DATE E ESCRIPTION ~ $ O O EDGE 7 SHARP _ BUT FREE OF PJJRR$ g -~ 0.l250 DIA Bali Nf N E. 8 c< c3 f i j]. :'\\ a f h O.C6 (/ f p _ c 31 Itr + p ~i 0.541--~ no 9 o. i

.0522

~ = ino _R 4 o NOTE : 1riCLUDED C2iLL APGLE - US q s i.'.t AT E RIALS -'[P3 3 d C$ 3C4 L TECHNICAL OPERATIONS IN C. Eb RA lATI N PRODUCTS DIVISION STANL5"f5 SEEL B U R LIN G TVN, M A 01803

  • nNISH OWG TITLE rics-v

-N er =,u = 12m..- OURCE CAPSULE ECTTGM r. I. r i 3

  1. ~ 3

,y 3 lCuECKED BY .Xx - 0.01 CLASS!F IC ATION SIZE DWG.NO. REE O. i, g .XXX l#

  • APPROVT.D SY ANGLFe A

s FRACTIONS A SCALE /.A ' l SHEET I CT I l

- y 4 F TECHid! CAL OPERATIOrdS, mcouonma j R A DI ATION PRODUCTS OlVISION NORTHWEST INDUSTRI AL PARK BURLINGToN.- M A SS Ac HUSEf t S 01803 [DN O[3 .,f L i61.7)272 2000. 5 i Telephone Converration-Recoret 28 November 1973 ? Mr.-John G. Fovers and Joseph Lise .Froject Engineer -Engineering Manager Nuclear. Metals, Inc. Technical Operations, Inc. .2229 Main Street Radiation ?roducts Division Concord, Fassachusetts .i -I I Mr. Fevers performed a Thermal Test on a sample of bare depleted uranium. l The semple, prier to the test, was a right circular cylinder measuring 1 0.h32 inch diameter and 0,495 inch long. The mess of the sample was 22.2 grams. i The sample was placed in a thin vall ceramic crucible and inserted in e resistance hested furnace prehested to 1475 F. The sample was heated l 0 for 30 minutes. The semple was then remcved and allowed to air cool under [ a ventilated hood. i Mr. Fevers reported that at the conclusion of the test,rthe sample measured L 0.hl8inchdiameterand0.hblinchlong. The mass of the sample was 20.8 grams. / r\\

/,

.e a ei V / ) _ / r 'M j e i i I r s 4 4 r i 2' O .. -. ~.. -. -.,,...... -.. - -...... -. _ _.

.._-..n. t 4 4 r N U C LE A R M E T A L S, I N C.. f,1 ' \\ [ 2229 MAIN STREET CONcomo, M AS S ACHUSETTS 0042 t c L e pw o N E 617 2 6 9 - 6 41Q

28 January 1974 Technical Operations, Inc.-

. Radiation Products Division South Avenue Burlington, Massachusetts 01803 Attention: Mr. J. Lima-Gentlemen: In response to a request by Joe Lima of Tech Ops, a simulated. fire test was performed on samples of bare depleted uranium in contact with mild' steel, the object being to determine what, if any,' alloying or melting would occur under these conditions. TEST DATA: // A 3/4-inch diameter x 5/8-inch long bare depleiad uranium specimen was set on a 1-inch diameter x 1/8-inch thick mild steel pl. ate,.placed in a j thin wall ceramic crucible. A mild steel cover plate was used on top of the crucible to act as a partial air seal. The crucible was loaded in a preheated 1450*F resistance heated furnace, held for 35 minutes, then removed and allowed to air cotl under a ventilated hood, RESULTS: l!o reaction was evidenced between the two metals. Both separated readily and showed no alloying or melting characteri,stics. Oxidation of the uranium was about the same degree as that reported to Joe. Lima on an earlier experiment. The test was performed by NMI on 25 January 1974. 'Very truly yo O 6.wx - John G. Powers Project Engineer f w 2-fY .c...z J

rLbr 4L TEST REPORT

'ADIATION PRODUCTS DIVISION BY

Keith Spinney - DATE: 20 October 1980

SUBJECT:

Model 850 Compression Test On 17 October 1980 a Model 850 source changer was subjected to a compressive load of 459 pounds. A steel block weighing 24 pounds was placed over the lock plate weldment to provide clearance above the two lifting handles, and a shipping package weighing 435 pounds was placed on the block. The load was left in place from 1:00 P.M. 17 October 1980 to 9:00 A.M. 20 October 1980. The package was not adversely affected as a result of the test. The package did not suffer any loss of structural or shielding integrity. Thus, it is concluded that the Model 850 meets the requirements of the compression test as described in Appendix A of 10CFR71 and Paragraph 713 of IAEA Safety Series No. 6, 1973 Edition. h / .e ~ Witn'essed y #.sf.9 _.s) rf /9 i Ang/elo Kiklis / KS/js l 2'T

6 l 4 w.m..-.e#=...m a.m., 4w es .. s* .we m. ee. -co N =e..h e.ee. **+ t.. J, 9,.. L (. k

y

,{ U n. pT s 1 ~~ ~ Y g,. . h 3 5 'W > y,y..j ,.w '7' }.r.L - K,e..tt y,, s,..@. >. ;. v p N. Q -t e s

  • 5 '-..'" *
  • D. I' Asar '

ep. = [,,'g* y - - ' ^7["i ***

t. /,:. l n g-s:- w 1 k(t j

. p ',,b, . 4 .g . 4 , 3,.. i - -..,e s.J L -e - , - e... "u.f,, g -. *

  • o'***$..

f q e Y ) +, 4.. s... [ *l $MM . NN.,... N[9 Y ,+q[m,-' ;~ 4,,,Le_.6 m ( ..w. ~. m . y :*.? V,_* e..r A u J 3 .r.

  • .j.*

M. .w1 ,,1 ..- em-1 %g gj s .".--e

  • 8 'y, s.
4., s. p

.e.,

=

  • s..:.:

A.w.a*c cA'e W uh... -. f, 7e

g. m w m y[4 t. e....

y . yl a g ~- . of g s f .h r.l.,I y';;. h}..;.,. p:.gn$ a

,. u.

r.. ~ ."_%. {. !lC.9 *? -.-3 m.. M M_ ~.q - ezuzu m -f %.., Q-..,, 4 --e W. 2 gi.' M-(. t ij , ~.. . c.,.. m, -j p: ' a -jy :. w pn. t-1 -. i.. (.. y ,g t.. y 5 /. V.: h.]- & _ :0! 'so ~~ ' a A.v,; M"n.S Ff. y$6=w? w m e ' w :ra u.m w u ~ =.,,.. & u w.w w l [ -- --.. ) COMPRESSION TEST ] ~~f M Q l g ,f N'i","'. -7." Q PW. 49tW" g 4,,.., 9 y~..( ' .,j % ; (*/ '

  • P r

i1.:. w ma.eg.4..#.f,3, ' " g -e p..t.i e .y 4 :, 2 v ( g,e -4 e !, A"

  1. 7, M

@+- m. y .l ' f*' '. .r n.s., ,..m. ,g, - y , i J 2 g: c n g ;... Q. s..' g, -f e,' .l u.

a wg e i

s-se s' F .~ w ,~,.. :e .c..., y - .r.. ; rh ; y . a=. y 1 y '_ t, es.. e., g s ,~ g .4 .= y, .'.-s* \\ ~~ 6a '. 4, * %...4 s mg s. :e~ *- We r-r 'vupapy ' l -y kJ Y

i..

L . {, b a A.,, e. j' . _ y. ~ s s,

      • ,,,,,e o

P.-

  • ,,......I%.f.

a : ~ ~.'~~s. ,._,,<r,

  • /.~%.', f *., ? ;.
==

.l' r---- - ? .^,.;--

  • s$ e,.y.....

m,,, A,,, %.'.. .g,- L.. .a I '. I* ' b'd8 ( $.' - w .) t

e. ~ <. A

,' - - N$4?j C.w p c m.ori h* J,, ; * ,,, ', * *]. & ' d M.A.. f,,.,h- *' . - ) 6h..

  • 7 'o f

t",,.,, %s + .a g ~ k' hriJ A u e% M I ,.;L*N Caille M L s. 2-tG 1y-e.g

1 VW'M m. i i TEST REPORT RADIATION PRODUCTS DIVISION KeithSpinney9k BY: i DATE: 20 October 198'O {

SUBJECT:

Model 850 Penetration Test l i I On 20 October 1980 a Model 850 source changer was subjected to-an impact of the hemispherical end of a vertical steel-cylinder 1% inches' in diameter and weight of 13. pounds. The cylinder was dropped three times from a height of 40 inches onto the front, side, and cover plate of the-container. The l long axis of the cylinder was perpendicular to the container surface for each . trial. l I The Model 850 suffered only minor superficial dents to the exterior of the I package as a result of this test: There was no loss of structural or shield-ing effectiveness. l t Therefore, it is concluded that the Model 850 meets the requirements of the penetration test outlined in "10CFR71 Appendix A and paragraph 714 of IAEA Safety Series No. 6, 1973. 1 b Mitnes. sed ,y;)

  1. }.

r Angelo Kiklis J i KS/js' i i i 2-11

6 .e .---+.,m4..#_.....,,,, W** 4m.s 4eHWa dum.eese Game opm es.we .g,.m.,,g W h_W M ' __- C gN"- mE"'"'~, r.Y {, --- y m==wur=;* ,., -. _. pp .. c.. ~, - Q'g l 4Wty".;. 4.n :s .~ 4. ~ m ? } g.:.. V :; +.-: w. c - m %c yW -d g,, g.i * =~'! .. y-,

. r. :

6 na*'" t "4- , N. y - Q;**'***.",i.<-..'.

1. -

+ ,,.vc2, ,.w, (~}.*@i -%c*"'~~ y %. 3.a ;. q \\ ,f;& - ~ r c'  :.I ( ji ,,,.a 1-i

    • f.,

.~,1' i- .y , :. h.. y( J.a. '. f. ^[, .2 s._. .. f, q' p -- y,-* a... e. ;%' l,. '4.

y. q '

s J e .m t y j f'. y.'g -/ - ~- .,-.~.7. ,a. \\ ,. J. -a-g- . t,y 7..ee t ,,i ,4 g 1, - t a 2- - i [- u..,. ..u - s e') U, ~ * - $.l,+. .4,,;a'h, *.* + 1 .n. -h, k a A fs.k T a, ;- -. *.,..,.

  • *
  • f[.

h- ', ;.+' ,\\.,,* .,[ f .q... .g,- f s-m c ,W

    • s

. Ya f <] 4 '. ~ p o I 9. a

,'.,.g. p..,;.JA}
  • ,,/

k' l ,$,.s- ~~ .e 7a., ..t j t w44.;4-Masb .m' db &. e , ~ ', .6 he.e-et. ease.n.. t. ss.a.sean,'. h e...,

v....

.. ra. e 4.,4 -= w I + ..e-4.-. 4 H PENETRATION TEST t 0 n, ,s ,~~ s n,p - ;...... ' f A .n, F '/* y ;.:: ,~n, .~ *:t s i l f;.5 ! w] v, <..!e ~ wlw + w f i n. 1 ~ - - 4i* ,5 g {* g ,,me-', r *"j e wa. r I 9 b f i I e S '. '(.'..? "[ j i.. *~/ a }..,.. ,a i l v e G., A 3 l t.- t. ~< s * ' g.. y..F p. s < 0 1.# j i l i t e r r i f:,,. 1~ f t l ( I r*. r * .... ~. I l 4:f l t..- l > ~ * ..u i ' A. $* l { g '.w-o'J. 1 m... r -. -._.. _ - -.... w I

s p. us.mm i r TEST REPORT RADIATION PRODUCTS DIVISION r Keith. Spinney E5 $ BY: DATE: 20 October 1980

SUBJECT:

Model 850 Drop Test and. Puncture Test [ On 20 October 1980 a Model 850 source thanger was.twice submitted to free ~ f all of.30. feet onto a flat horizontal. steel' plate measuring 4 feet by 4 feet by 3/8 inch which was lying on top of a paved curf ace. The. odel 850 struck a dif ferent corner each time, causing minor deformation M ot the outer shell. There was no loss of structural integrity. t The Model 850 was then twice submitted to a free fall of 40 inches onto a steel bar.6 inches in diameter and eight inches high. The top surface of the~ bar was horizontal,-with its edges rounded to a radius of not mors than one quarter inch. The first time the >cttom of the container struck the bar with no effect en the container. the second time, the top of the container struck the bar. As a result one handle was bent. One side of that handle was broken off where it was welded to the container. However, there was no loss of structural integrity. Upon' removal of the lock mechanism at the conclusion of the test, it was observed that the depleted' uranium shield had moved approximately one quarter inch. A radiation profile was performed (See Section 5.) and trom that it wgs concluded'that there was no loss of' shielding integrity. Therefore, it. is concluded that the Model 850 meets the requirements of the free f all and puncture tests outlined in 10CFR71 Appendix A and IAEA Safety Series No. 6, 1973. 6 Witnessed A,p IngeloRiklis KS/j s 2-19 , _. ~.

= t J l. I i e - ~ ,, mas

  • e.*-

e. s A .s.ur a sp

  • s

-e 'a. ~ y.. I e w e.- _-_ _a 4*. f q . - * = = * * - * *. 3 t sd t-e., 6- . a, -?I L... 3 4 .j s .;g ~ ..d. ra I .*'.J. l ?".- J.T i l .. >= e e -- m..;j s w g e .4.=> { M..T:.7 .-%-y+e====.,r,=e-r- - 2 t i..,: __ m a. 3 , *s /

4. e.

j<. v ,a ~. s.

  • f-s %., ;

<.m.J.xM% w t i ( r ~ v =-- .vs..=*= .4 i ,. ].,. .,t -.. >.. s i 3 -... s, 6 .. o...p t . c.,. ,.m. t 5.

~

2 * ; y;,,, - ,.,g.,.. -a .. e,.- r +

\\, s sL,..-

.g. i.~. ,,..'. b. :.1 / i r -- W - - -: ;;, ; FREE DROP TEST p.' ~','".f~- ~3 .'el.- * '. ,. g ',4 Y h- ,.y, -,, ~..... s w. f.a. s.Ada Musa E. add a.as4.07,h %s' O.' s M 8 I annus t I, e-e A e.d. 'g 4 35 e hw q e M

  • WYP*T'.W***"

M' - 940 p 4..,.m" 'sa'."wi, Y"* g y' I *.. $M 1 g m.,i vom. ' 4 a 9 0 4 {,,,,, g Y eV

  • g t*

g s\\ Q' = ,,,. g ?) - v

h. -

.. h., .4,%- o q. A 4 Y s \\

9..

se .. y ,,4 e g (* '4d

  • 4',,

5. ,y e".s.J r ~i t t t s s l I e k. l .w ) .ew .-eOe. M* 2* LO -u w h.

  • .m=*..d4t

.. e... l -..,........ ~.,

e a .--s9 .4 sf' $, I f p., n. 6 4 W j 4 7*?.*.Ne**?eVF 'N ?f.* *..T. ** *'*9' E d ' 'T i.P,. '** N *

  • I f

l-y h I E' e 4 -, 't. e.]. .,,. i y 6 4,

  • x r,

., j go., ',. s -s .( r, , ps. _ g.e . ;'*en ,,' + 7*. 1 ,,g . 2. p i f d - 3 h 9 St ; ,e 1 -'.1 i p-s l' g-I f, j. . 3, w. 4'..%.. g ,j ,4 p7 l -2 ,) { e- =. 4 9 9 i t. -e e { N.- [ t 4 I -. 1 + 6 g f V. ~ w ( y f -' no.4 # r .3 c .y .a, .o s ...p /' e /- s I.$ e E.2d7.* r .*'# A.* b [( ' ) s . 4eme e.de*7

  • ...m a ee e

.me 4 s.r o m e am. .Og l PUNCTURE TEST i s j l v./ m L. -. u.. _ r.. i. ~ I t r - IL ,, n,. 4..., l L' e -= e. e 'g.... a. , =q..., _gc - ~,...l 3 ". l ..m. +,. y ~. T 0

  • e _

i l e = '6 ~~.4 I f i 1 O p I s .3-c-Og 9 .p' i / F*, 3. W ] 'd I s j 2 e. i b. 1

  • i' s

s 4 5 ej g i g r e i f. e w e i. ( e s w j 1 1 ._.9.... _ .....-2 , l,_ 1 f.e. L ~ -, - 'M I I O 21 i M

1 .a i. l e -. ~.. -w.--,.,.=r**m j l .,,.n'.-w' f 1 o. M 4. ..1.. q < + w ;. ' t. '/ v.] n 1.4'.t.N.*.3....'t.5). ~,. ~ ^~ ..a. S. .4. y ~ .-..e g. ....-5 4 c ..t -i 4 a j ,**.-%.1 r_ _.....--.~...+.~m y w., _. n.. . u. '

.r u.:

o_...,J. c i 6 =- {,2s. '. .J .,w ._e-g.. tY3 } - - t P.0 DEL 850 AFTER COMPRESSION, i- ~~ ~~/ PENETRATION, FREE DROP, AND ~, ./ PUNCTURE TESTS n ... - e t e e re.4 g'S-w V se e t

  • s r

f 3 s f M.WM4 h ** dDS A Sea.e ..GO i E O*'* b all> d I* h 4 '*. ges*bd.ep" .._.......-. ~ _.... _. -. <... ~. - } i ~ ) ngn e., e n e. ** 9.ee* y.* .-swre e. w=*.. 4r -a.* r.*w =*w,4*a*

  • wee + 6 -
  • fee =* W a L'

l e s O ,6 O -.l.i> s W ^ ', F l ..d* p-4 l i e s= W.. a m ai... 4

w....

.. +,.. !=sk --.a.-s**a==..*d

  • s. -

l ? _.,._ _.. ~ _. _ _ _., _ __ _ _... _..

DEPARTMENT OF TRANSPORTATION k RESE ARCH AND SPECI AL PROGRAMS AC'.i!NISTR ATioN WASHINGTCN, O C. J0!90 y ( IAEA CERTIFICATE OF CCW, ENT AU'IT.3ORITY Special Form Padicactive Material Encapsulatf0ff"

  • Certificate Nxter USA /0179/S (Pavision 1)

Tais certifies that the encapsulated sources, as described, when Icaded with the authorized radioactive contents, have been dcronstrated to neet the rcpatory re-and USA 2 cuircrents for special form radicactive raterial as prescrilx'd in IAEA Fofalations for the transport of radicactive raterials. I. Sc. tree D'scriotion - The sources described by this certificate are identified as I-~ Tech 70]is ibiel 90O047nd 90005 which are 304 or 304L stainless steel welded encapsu-1ations.maasuring 0.205 inch in diareter by 0.65 inch in length. II. Fadicactive Contents - The authorized radicactive contents of this source con - sist of Iridium-192 in solid retallic form with not r: ore than 120 curies in the Mcdel 90004 or 240 curies in the rodel 90005. III. This certificate, unless reneaed, expires on Cbtober 31, 1980. 21is cartificate is issued in accordance with paragraph 803 of the IAEA Pg21ations and in response to the August 1,1980 ptition by Tech / Ops, Surlington, 'assachusetts, and in consideration of the asscciated inforration therein. Gutificd by: r ' /~. l / j // c.t. l F~ ~R. Yal ~ifa^t'e) ~ ( D2signated U.S. Competent Authority for the Interr.ational Transprtation of ?adicactive Materials Office of Hazardous Paterials Pagulation 'hterials Transprtation Bureau U. S. D?parkent of Transportation cashington, D.C. 20590 1"'Safuty Series !b. 6, 3cs.lations for the Safe Transprt of Radioactive Pate: rials, IM7 53ition"., published by the International Atcmic Energy Agancy (LW.), Vien a, Aust ria. 2Title 49, Ccde of Federal Pagulations, Part 170-178, USA. Pavision 1, issued to add Ltdel 90005 and to extend expiration date. 2 - 2. 3

3. Thermal Evaluation 3.1 Discussion The Model 850 is a completely passive thermal device aad has no mechanical cooling system nor relief valves. All cooling of the pack-age is through free convection and radiation. The heat source is 240 curies of iridium-192. The corresponding decay heat is 2.06 watts. 3.2 Summary of Thermal Froperties of Materials The melting pointa. of the metals used in the construction of the Model 850 are: 0 Titanium 3308 F (1820 C) 0 Steel 2453 F (1345 C) Uranium 2070 F (1133 C) 0 0 Copper 1940 F (1060 C) Bronze 1840 F (1005 C) The polyurethane foam has a minimum operating range of -100 F (-730C) to 200F (9300). It will decompose at the fire test tem-perature (8000C). Decomposition will result in gaseous byprodu' cts which will burn in air. 3.3 Technical Specifications of Components Not Applicable 3.4 Normal Conditions of Transport 3. 4.1 Thermal Model The heat source in the Model 850 is a maximum of 240 curies of iridium-192. Iridium-192 decays aith a total energy liberation of 1.45 MeV per disintegration or 8.58 milliwatts per curie. Assuming i that all of the decay energy is transformed into heat, the heat gen-eration rate for the 240 curies of iridium-192 would be 2.06 watts. For this analysis, the heat source will be assumed to be 2.5 watts. To demonstrate compliance with the requirements of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 for Type B(U) packaging, an analysis is presented in Section 3.6. The thermal model employed is described in that analysis. To demonstrate compliance with the requirements of paragraph 240 of IAEA Safety Series No. 6, 1973 for Type B(U) packaging, a separate analysis is pr:2sented in Section 3.6. The thermal model employed is described in that analysis. 3-1 l Revision 0 l 30 October 1980 l

} ~ v. 3.4.2 Maximum Temperatures The maximum temperetures encounted under normal conditions of trans-port will have no adverse effect on structural integerity of shield-ing..As shown in Section 3.6, the maximum temperature in the' shade' would be less.than 430C and the maximum temperature when insolated would be less than 570C. 3.4.3 Mini =um Temperatures The minimum normal operating temperature of the Model 850 is -40 F. 0 (-4 0 C ). This temperature will have no-adverse affect on the package. 3.4.4 Maximum Internal P;essures i Normal operating conditions generate negligible internal pressures. ( Any pressure generated is significantly-below that'of the.hypotheti-cal sceident pressure, which is shown to result in no loss of shield-ing or containment. 3.4.5 Maximum Thermal Stresses, r The maxi =um temperatures that occur during normal transport are low -enough to insure that thermal gradients will cause no significant-thermal stresses. 3.4.6 Evaluation of Package Performance for Normal Conditions of Transport The thermal conditions of ':ormal transport are insignificant from a fenctional viewpoint for the Model 850. The applicable conAitions of iAEA Safety Series No. 6,1973 for Type B(U) packages have been shown to be satisfied by the Model 850. 3.5 Hypothetical Accident Thermal Evaluation 3.5.1 Thermal Model t i The Model 350, including the. source assemblies, is assumed to reach the thermal test temperature of 800 C. At this temperature the polyurethane foam will have decomposed and the resulting gases will have escaped the package through vent holes and non-leak tight assembly joint. 3.5.2 Package Conditions and Environment The Model 850 underwent no significant damage during the free drop and puncture tests, The pachtge used in thi: analysis is considered undamaged. 3-2 Revision 0 30 Octater 1980

3.5.3 Package Temperatures As indicated in Section 3.5.1, t?:e entire package is assumed to reach a temperature of 800 C. Examination oi the melting temperatures of 0 the materials used in the construction cd the Model 850 indicates that there will be no damage to the package as a result of this temperature. The possibility of the formation of an iron-uranium eutectic alloy was addressed in Section 2.4.1 where it was concluded that the formation of the alloy was not a likely eventuality. 3.5.4 MaximumInternsLPressures The Model 850 packaging is open to the atmosphere. Therefore, there will be no pressure buildup within the package. In Section 3.6, an analysis of the source capsules under the thermal test condition demonstrates that the maximum internal gas pressure at 800oC is 55 psi 2 (380 kN/m ). The critical locatien for failure is the weld. An internal pressure of 2 2 55 psi (380 kN/m ) will generate a maximum stress of 223 psi (1.5MN/m ), At a temperature of 8700C (1600 F), ghe yield strength cf Type 304 stainless steel is 10,000 psi (69MN/m ). Thus, at 800 C, the maximum stress in the source capsule would be only

37. of the yield strength of the material.

3.5.5 Maximum Thermal Stresses There are no significant thermal stresses generated during the thermel test. 3.5.6 Evaluation of Package Performance The Model 850 will undergo no loss of structural integrity or shield-ing when subjected to the thermal accident condition. The pressures and temperatures have been demonst, rated to be within acceptable limits. j t 5 3-3 Revis~on 0 30 October 1980

3.6 APPENDIX 3.6.1 Model 850 Type B(U) Thermal Analysis: Paragraphs ?31 and 232 of IAEA Safety Series No. 6, 1971 3.6.2 Model 850 Type B(U) Thermal Analysis: Paragraph 240 of IAEA Safety Series No; 6,1973 3.6.3 Iridium Source Capsules Thermal Analycis 4 t 5 i 3-4 Revision 0 30 October 1980 j

1 f i i i \\ l 4 3.6.1 Model 850 Type B(U) Thermal Analysis Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 I This analysis demonstrates that the maximum surf ace temperature of the Model l 0 850 will not exceed 50 C Vith the package in the shade and an ambient tempera-0 ture of 38 0. ( To assure conservatism, the following are used:

1) The entire decay heat (2.5 watts) is deposited in the exterior f aces of the Model 850.
2) The interiur of the 'Model 850 is perfectly insulated and heat transfer occurs only from the exterior wall to the atmosphere.
3) Because each face of the package eclipses a different sol!d ar.gle, it is assumed that twenty five percent of the total heat is deposited in the smallest face (top).
4) The only heat transfer mechanism is free convection.

{ Using these assumptions, the maximum wall temperaturn is found from: q = hA ( Tw - T )a i where q: Heat deposited per unit time in the face of ) interest (0.63 wat<:s) I h: Free convective heat transfer coefficient for air t ( 1. 34 ( AT)* W/m - C) S 2 2 A: Area of the face of interest ( 0.04 8m ) T: Maximum temperature of the wall of the package y T: Ambient temperature (38 C) a From this relationship, the maximum temperature of the wall is 42.8 C. This satisfies the reauirement of paragraphs 231 and 232 of 1AEA Safety Series No. 6, 1973. 3-5 Revision 0 I 30 October 1980 l 1

s. 3.6.2 Model 850 Type B(U) Thergal Analysis Paragraph 240 of IAEA Safety Series No. 6,1973 This analysis 'emonstrates that the maximum surface temperatures of the Model d 850 will not exceed 820C when the package is in an ambient temperature of 3800 and insolated in accordance with paragraph 240 of IAEA Safety Series No. 6, 1973.. The calculational model consists of taking a steady state heat balance over -the surface of-the package. The following assumptions are used.

1) The package is insolated at the rate-of 775W/m2 (800 cal /cm2 - 12h) on the top surface, 194W/m2 (200 cal /cm2 - 12h) on the sides, and no insolation on the bottom.
2).The decay heat load is added to the solar heat load.
3) The package has an unfinished stainless steel surface.

The solar absorptivity is assumed to be 0.9 The solar emissivity is assumed to be 0.8

4) The package is assumed to undergo free convection from the sides and top, and undergo radiation from the sides, top and bottom. The inside faces are considered insulated so there is no conduction into the package. The faces are considered to be sufficiently thin that no temperature gradients exist in the faces.

1 l

5) The package. is approximated as a rectangular parallelepiped rest-ing on an end.

The surface areas of the top and bottom are each 2 0.048m. The surf ace area of one side is 0.045m2 and the area of 2 the adjacent side is 0.04 7m, The maximum surface temperature is established from a steady state heat balance relationship. 5 q in = q out = 9e + 9r whero qc: Convective Heat Transfer gr: Radiative Heat Transfer The heat load applied to the package is q in = aqs + 9d. where a: Absorptivity (0.9) qs: Solar Heat Load (72.9 Watts) qd: Decay Heat Load (0.63 Watts) l t 3-6 Revision 0 30 October 1980 . _. _,. _.. _.,. _. _... _. ~. ~ _. - _. _ _

] The. convective heat transfer is: l (M) 4(M) (T - T a).

=

.qc w top sides _ where h: Convective heat transfer coefficient ~ A: Area of surface of interest [

Tw:- Temperature of wall T: Ambient Temperature i

a i The heat transfer due to-radiation is: ~ 'gr = cc A(T 4-Ta) 4 4_ -w where.o: Stefan Boltzmann Constant-(5.669 x 10-8 97,2 _ Lo ) g c: E=missivity (0.8)~ Iteration of this relationship' demonstrate, that the vall temperature of. the Model 850 is' 56.9 C which satisfies the requirement of paragraph 240__ of IAEA Safety Series No. 6, 1973. f a L 's 3-7 Revision 0 30 October 1980

S l l l i 3.6.3 Model-850 Type B(U) Source Capsule Thermal Analysis,, i Paragraph 238 of IAEA Safety { cries No. 6, 1973 Edition Thisl analysis demonstrates that the pressure inside the_ Model 90004 or Model 90005 source capsule, when subjected to'the thermal test, .does not exceed the' pressure which corresponds to the minimum yield strength of'the material at the-thermal test temperature.. The source capsules are f abricated from stainless' stbel, Type 304. or 304L. The outside diameter of each capsule is 0.205 inch (5.2mm). The source capsule is seal welded. The minimum. weld penetration is 0.020 inch (0.5mm). Under the conditions of internal pressure, the critical location;for failure is this weld. The internal volume of the source capsule contains only iridium metal as a solid and air. It is assumed that the air is at standard tem-0 2 perature and pressure (20 C; 100kN/m ) at the time.of loading. This is a conservative assumption because, during the welding process, the internal air is heated, causing some of the air mass to escape before the capsule is sealed. When the welded capsule returns to ambient temperature, the internal pressure would be somewhat reduced. Under the conditions of paragraph 238 of IAEA Safety Series No. 6, 0 it is assumed that the capsule could reach a temperature of 800 C 0 (1475 F). Using the ideal gas law and requiring the air to occupy a constant volume, the internal gas pressure could, reach 373kN/m2 (54 psi). 1 The capsule is assumed to be a thin walled cylindrical pressure vessel. The maximum longitudinal stress is calculated from: A 01 1

  • pap t

where ci: Longitudinal Stress Stress Area = n(r 2 - rg ) 2 A: o 2 P: Pressure (373kN/m ) pressure Area = Wr;2 A: From this relgtionship, the maximum longitudinal stress is calculated to be 686kN/m (o9 psi). 3-8 Revision 0 30 October 1980 - -. _ _. _ _ _ _... _ _. _, ~, _,. -..,,

N + A / 4 J +.<.4 4 .,3 m q .g.

.l,y 1

'The hoop stress'can be.found by:. . 20h it = pid; ch = Pr; or t-where ch: hoop. stress .j 1: iccgth-of the cylinder t : thickness of: the cylinder - t 2~ + From this relationship, the hoop stress is calculated to be 1.541M/m (223 psi). i e 0 At a temperature of '870 C (1600 F), the yield strength of Type 304 stainless steel is 6913/m2 (10,000 psi).- Thus, under the conditions of paragraph 238 of IAEA Safety Series No..6, 1973, the stress generated is less than 3% of'the yield strength of the material. P L i i i t t 'i l i 3-9 Revision 0 30 October 1980 -,_............_,..,_._...___...___-,_,....._,...,__...__.m.,.._,,__.,

s t 4.' Containment '4.1 Containmdnt Boundary 4.1.1 Containment Vessel The containment system for the Model 850 is the radioactive source assembly Mode 190003'.- The actual containment for the radioactive mat-erial is the welded source capsule as shown in Section 2.10. These source capsules _are certified as special form radioactive materials (IAEA Certificate of Competent Authority No. USA /0179/S). The capsules are fabricated from either Type 304 or Type 304L stain-less steel. The capsules are cylinders with a diameter of 0.205: inch (5.2mm) and length of 0.650 inch (16.5mm). 4.1.2 Containment Penetrations There are no penetrations of the containment. 4.1.3 Seals and Welds 'The containment is seal welded by a tungsten inert gas welding process l Which is described in Tech / Ops Standard Source Encapsulation Proceadre (Section 7.4). The minimum weld penetration is 0.020 inch (0-51mm). 4.1.4 Closure Not Applicable 4.2 Requ(1ments for Normal Ccnditions of Transport 4.2.1 Release of Radioactive Material t The seurce capsules have satisfied the requirements for Epecial Form Radio #ctive Material as delineated in IAEA Safety Series No. 6,1973 Therefore, t'ere will be no release of radio-l h. t edition and 10CFR71. active material under the normal conditions of transport. l l 4.2.2 Pressurization of the Containment Vessel Pressurization of the source capsules under the conditions of the hypothetical thermal accident was deconstrated to generate stresses I well below the structural limits of the capsule (See Section 3.5). Thus, the containment will withstand the pressure variations of normal transport. 4-1 Revision 0 30 October 1980

1; 4

ii t

'.2.3 Coolant Contamination 4 Not Applicable. 4.2.4-Coolant Loss 1 -Not Applicable 4.3 - Containment Requirements for the Hypothe'tical Accident Condition 4.3.1 . Fission Gas Products Not Applicabla 4.3.2-Release of Contents t The. hypothetical accident conditions of 10CFR71, Appendix B will result in no loss of package containment as shown in Sections.2.7.1, 2.7.2 and 3.5. t V t r t l i I 1: 1 ) l 4-2 Revision 0 30 October 1980 - - - ~ .. ~, _. -... _... -. _ _ _ _ _.. _..,

i 5. Shielding Evaluation 5.1 . Discussion and:Results. The. Model 850 is shielded with 49 pounds of depicted uranium. The uranium metal 'is cast around the titanium "U" tubes. A radiation profile of.Model'850 Serial No.1 containing 215; curies of iridium-192 was made. The results of this survey ar~e presented in Section 5.5.1. Extrapolation of this data'to a capacity of 240 curies of iridium-192 is presented.in Table 5.1. As the Model 850 has no neutron. source,- the gamma dose rates are the total dose ' rates which are ptasented. As shown'in Table 5.1, the maximum dose rates are below the reguistory

requirements..

Table 5.1 Summary of Maximum Dose Rates (mR/hr) At Surface: At One Meter ~ Side Top Bottom Side Top Bottom 100 123 112 1.8 2.0 1.C 5.2 Source Specification 5.2.1 Camma Source The gamma source is iridium-192 in a sealed capsule as special form in quantities up to 240 curies. 5.2.2 Neutron Source Not Applicable 5.3 Model Specificatioc g Not Applicable e 5.4 Shielding Evaluation The Model 850 shielding evaluation was performed on Model 850, Serial No. 1 containing 215 curies of iridium-192. The results of this survey (Section 5.5.1) demonstrate that the dose rates surrounding this pack-age are within the regulatory requirements. A radiation profile made on this package af ter being subjected to the hypcthetical accident condi-tions, (Section 5.5.2) show that there was no significant change in the shielding effectiveness. 5-1 Revision 0 30 Oct Ser 1980 1 i ..,.. -...-..,,,_._.--...._,.I

5.5 Appendix 5.5.1 Radiation Profile - Model 850, Serial Number 1 5.5.2 Radiation Profile - Model 850, Serial Number 1 .after hypothetical accident conditions t 5-2 Revision 0 30 October 1980

.5.5.1 ' Radiation' Profile, Model 850 S.N.1. ' TOP TCP \\ r +. ~ r ' *= 9 (" i ,f 9, i L F R 'R ') E- - R E A. F-T R 3 ' BOTTOM BOTTOM Contai. ting Sources: S.N. 8'421: 107Ci iridium-192 S.N. 8422: 108Ci Iridium-192 Total Activity: 215 Curies of iridium-192 Maximum Dose Rates (e.R/hr) at surface at one meter Top 110 1.8 Front 80 1.4 Right 70 1.2 Rear 90 1J Left 60 1.2 Bottom 100 1.4 e Measurements made with AN/PDR-27(J) Survey Instrument r 5-3 Revision 0 i 30 October 1980 P-mv' g -vr w r wrwi- =-9-tg e- <y,-w-wa e,-w+tig g-wWW,-g +-g-gy -9p yy ag--9 rs g 9,yq-g4--g<acew>-9-- 99ty=~ge--g g g aw-e ++ g g w --v'mygu-

5.5.2 Radiation Profile, Model 850 S. N.,1 After free fall and puncture tests TOP TOP e I" f-I l R L F' R 1 E R E 0 F A H N 8 T T T 50TTOM BOTTOM Containing Sources: S.N. 8421: 106Ci Iridium-192 S.N. 9422: 107Ci Iridium-192 Total Activity: 213 Curies of Iridium-192 Maxiraum Dose Rates (mR/hr) at surface at one meter Top 90 1.8 Front 110 1.9 Right 70 1.2 Rear 90 1.6 Left 60 1.4 Bottom 14 0 1.8 k Measurements made with AN/PDR-27(J) Sur'vey Instrument 5-4 Revision 0 30 October 1980

6. Criticality Evaluation Not Applicable t t 6-1 Revision 0 30 October 1980 i v v r-wrt ? v---*w wm m-* rm -av"w

ic 7... 10perating' Procedures 7.1 Procedures for Loading the Package l_ The procedure for fabricating the special' form source capsule is pre-gented_in Section 7.4, Encapsulation of Sealed Sources. The procedure t for loading the. source assembly into the package is presented in Section 7.4, Operation Manual. 7.2 Procedures for Unioading the Package l. .The procedure for unloading the package is presented in Section 7.4, Operation Manual. 7.3 Preparation of an Empty Package for Transport The procedure for preparation of an empty package for transport is presented in Section 7.4, Operation Manual. l l i i 1 i I l l 1 \\ \\ j t ) 1 -1 l l 7-1 Revision 0 30 October 1980

7.4 Appendix Encapsulation of Sealed Sources Model 850 Operation Manual 9 L l 7-2 Revision 0 30 October 1980

v L ENCAPSULATION OF SEALED SOURCES A. Personnel Requirements. Only~ an individual qualified as a Senior Radiological Technician shall perform the operations associated with the encapsulation of 192 Iridium. -There must be a second qualified Radiological Technician available.in the. building'when these operations are being performed. B. General Requirements The 192 Iridium icading cell shall be used'for the encapsulation of solid metallic 192 Iridium. The' maximum amount ofl92Iridium to be handled ia this cell at any one time shall not exceed 1000 curies. This cell is designed to be operated at less than atmospheric pressure. The exhaust blower provided shall not be turned off except when the cell l is in a decontaminated condition. Sources shall not be stored in this cell overnight or when cell'is un-attended. Unencapsulated material shall be returned to the transfer containers and encapsulated sources transferred to approved source containers. When any of the "through-the-wall" tools such as the welding fixture or i transfer pigs are removed, the openings are to be closed with the plugs-provided. The tools shall be decontaminated whenever they are removed from the hot cell. C. Preparatory Procedure 1. Check welding fixture, capsule drawer and manipulator fingers from t cell and survey for contaminatios, If contamination in excess of 0.001 pCi of removable contamination is found, these items must be decontaminated. j 2. If the welding fixture or the electrodes have been changed, perform the encapsulation procedure omitting the insertion of any activity. Examine this dummy capsule by sectioning thru weld. Weld penetra-tion must be not less than 0.020 inch. If weld is sound and penetration is at least 0.020 inch, the pre-paration of active capsules may proceed. If not, the condition responsible for an unacceptable weld must be corrected and the preparatory procedure repeated. 7-3 Revision 0 30 October 1980 _...-..--_-..-,-_,._.-,-..._.,_.-._-,.,n,-,-

~. L s 3. Check pressure differential across first absolute filter, as measured by the_ manometer on the left side of the hot cell. -This is about % ~ inch of water for a new filter. When this pressure. differential rises to about -2 inches of water, the filter must be changed. D. Encapsulation Procedure 1. Prior to use, assemble and visually in'spect the two capsule comp- 'onents to determine if weld zone exhibits any misalignment and/or separation. Defective capstles shall be rejected. 2. . Degrease capsule components in the Ultrasonic Bath, using isopropyl alcohol as degreasing agent, for a period of 10 minutes. Dry the 0 capsule. components at 100 C for a minimum of twenty minutes. 3. Insert capsule components into hot cell with the posting bar. 4.- Place capsule in weld positioning device. 5. Move drawer of source transfer container into hot cell. 6. Place proper amount of activity in capsule. Disposable funnel must be used with pellets and a br ass rivet with wafers to prevent contamination of weld zone. 7. Remove unused radioactive material from the hot cell by withdrawing the drawer of the source transfer container from the cell. C. Remove funnel or rivet. 9. Assemble capsule components. 10. Weld adhering to the following conditions: a. Electrode spacing 021" to.024" centered on joint +.002"; use t jig for this purpose. b. Preflow argon, flush 10 seconds. c. Start 15 amps. d. Weld 15 asps. e. Slope 15 amps. f. Post flow 15 seconds ) 7-4 Revision 0 l 30 October 1980

11. Visually inspect the weld. An acceptable weld must be continuous without cratering, cracks or evidence of blow out. If the weld is defective, the capsule must be cleaned and rewelded to acceptable conditions or disposed of as radioactive saste. '1 12. Check the capsule in height gauge to be sure that the weld is at the center.of the capsule.

13. Wipe exterior of capsule with flannel patch wetted with EDTA solution or equivalent.

14. Count the patch with the scaler counting system. Patch must show no j more than.005pCi of contamination. If the patch shows more than .005pci, the capsule must be cleaned and rewiped. If the rewipe patch still shows more than 0.005pCi of contamination, steps 8 through 11 must be repeated. 15. Vacuum bubble test the capsule. Place the welded capsule in a glass i vial containing isopropyl alcohol. Apply a vacuum of 15 in Hg(Cauge). Any visual detection of bubbles will indicate a leaking source. If the source is determined to be leaking, place the source in a dry vacuum vial and boil off the residual alcohol. Reweld the capsule. 16. Transfer the capsule to the source loading fixture. Insert the source capsule into the source holder. Screw the' source holder together and install the roll pin. Check to assure that the pin does not. protrude on either side. 17. Apply the tensile test to assembly by spplying proof load of 751bs. Extension under the load shall not exceed 0.05in. If the exten-sion exceeds 0.05 in., the source must be disposed of as radio-active waste. 18. 1.sition the source in the exit port of hot cell. Withdraw all personnel to the control area. Use remote control to insert source in the ion chamber and position the source for maximum response. t Record the zeter reading. Comput'e tha activity in curies and fill out a temporary source tag. 19. Using remote control, eject the source from cell into source changer through the tube gauze wipe test fixture. Monitor before reentering the hot cell area to be sure that the source is in the source changer. Remove the tube gauze and count with scaler counting system. This assay must show no more than 0.005 pCi. If contamination is in excess of this level, the source is leaking and shall be rejected. 20. Complete a Source Loading Log for the operation. 7-5 Revision 0 30 October 1980

e TECH /0PS MODEL 850 SOURCE CHANGER - SHIPPING CONTAINER OPERATICN MANUAL Technical Oata i Size: 10.4in high, 8. Sin wide, 8.8 n deep (264mm high, 216mm wide, 224mm deep) Capacity: 240 Curies of 192 Iridium Special Form Transport Status: Typ2 B USA / /B( ) Shielding : Depleted Uranium Metal 49 Lbs (22kg) Weight: 77 Pounds (35kg) General The Model S10 Source Changer - Shipping Container is designed for trans-ferri.g encapsulated radioisotope sources into radiographic devices and for transporting these sources. The U.S. Nucicar Regulatory Commission allows the use of this source changer or.ly if the user is specifically authorized by the terms of his license. If the user 's not authorized to make source exchanges, contact Technical Op,erations, Inc. It has personnel who are authorized to perform this operation. If the user wishes to be licensed to make source exchanges, application should be made to: ~ Radioisotope Licensing 3 ranch Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Commission Washington, DC 205:5 7-6 Revision 0 30 October 19'80

Prior to the first shipment of this source? changer, the user, in addition should register with: Transportation Certification Branch Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Commission Washington, DC 20555 Shipping Information When the 850 Source Changer is shipped to the uaer the following items are iacluded in addition to the radioisotope sources. 1. For Each Source a. Source decay chart b. Source leak test certification c. Verification of source physical dimensions d. Source identification tag 2. Tamperproof Seal 3. Return Shipping Labels 4. Instruction Manual - NOTE - The user is urged to perform the source changing operation as soon as possible after receipt and to return the source changer insediat ely upon completion of the changing operation. Only in this way can we keep these source changers in continued use. Receipt 1. Upon receipt of the source changer, survey the container on all l sides to ensure radiation levels do not exceed the following: Surface 200 mR/hr At One Meter 10 mR/hr 2, Check surface of container for obvious damage. 3. Check Invoice and Bill of Lading to ensure all are intact and are representative of the shipment. 2 7-7 Revision 0 30 October 1980

Receipt (Continued) 4. If there are any discrepancies in Items 1-3 above, do not j use the source changer and contact Technical Operatioas, Inc. immediately to resolve discrepancy. (Tel: 8C0-225-7383 Telei 949313) 5. If items 1-3 are determirad to be in order, place the source changer in a restricted area until ready to use. Operati;n - NOTE - Personnel performing source changing operation must have a calibrated and operational survey meter with a range of at le ast 0-1000.aR/hr. In addition, personnel monitoring devices must be worn during these operations. They are a film badge (or Thermoluinescent Dosimeter, TLD) and a direct reading pocket dosimeter. (I CCFR34.33 ) 1. Survey the container on all sides and ensure radiation levels are not in excess of 200 mR/hr on the surface nor 10mR/hr at one meter from any surface. 2. Place the ;ource chcager and the projector (s) to be loaded in a restricted area which is properly identified. i 3. Break the seal wire, unf astenr the bolts and remove the cover platec. 4. To transfer the source from the projector to the source changer: a. Connect the control unit to

  • he project ar as for an exposure.

b. Connect one length of source guide tube to the projector and to the empty hole on the source changer, c. Ensure the lock is open. 3 7-8 Revision 0, 30 Oc tobe r '.980

J es ( d. Ensure'that there are no unauthorized" personnel in.the restrictdd area and place =the projector in the operate condition. i e. Letve the area of the. projector and source changer -1 and, using the control unit, crank the source.from 1 i . projector. to the source changer. 4

f. ' Approach' the projector observing the survey meter.

' Survey 1the projector on'a11' sides-to ensure the source.has been properly transferred. The radia-tien level-at the surface of.the projector should .be.less ' tban the origina1 ' survey readings observed. g. Approach the source changer observing the survey meter and verify that the source.is'in the proper storage position. h. "ove the lock slide to the LOCK position'and depress the plunger lock to lock the source in the storage position.

i. Disengage the source guide tube from the source changer and disconnect the source assembly from-the drive cable.
j. Remove source ID tag from projector and attach to guide tube opening on source changer. Be sure the proper ID tag is attached to the proper source.

5. To transfer a source Ivom the source changer: a. Survey the source changer on all sides to ensurs the sources are pro'perly stored. b. Survey the projector to ensure it does not have a source in it. - t c. Crank the control unit drive cable through the , ojector until the male connector end protudes beyond the guide. tube.enough to make connection to the source. d. Connect the source to the control unit drive cable. Connect the guide tube to the fitting on the source j connector. e. Ensure all unauthorized personnel are out of the restricted area. 4 1 7-9 Revision 0 30 October,1980

,I : i f.- Unlock the plunger lock on the source. changer and nove the lock slide to the OPEN position. g. Return to the control unit and crank the source H

drive in the retract-direction until the source I

is stored.in the projector. h. Approach the projector observing the; survey meter Jacd survey on all sides'to ensure the source isiin the. proper stored position.. "c Li., Lock projector and disconnect. guide ~ tubes and 'ontrol un.it. c

j. Remove source ID tag from source changer and, attach to pro'jector.

6. When source-transfers are completed, in:Jre all sources are properly stored and locked in the source changer. 7. Place the cover plates on the source changer and install all-bolts.

8..To return source changer:

Safety lock wire the changer and ' crimp icad seal, a. b. Survey container at the surface:and.at one meter, and determine proper shipping label in accordance with Table I. t 1 1 5 7 - 10 "evision 0 30 October 1980 ,...,..... - +.,. ~.... - ...-....,---~~,...-,.,-yv,---,-#,-,-,m...-.,~,,_w_m,~,, ,,-wm,,_ ,y,r%m,y.,.-- or,, r,g

TABLE I Su r fa ce 3 Feet RA D I O. ACT I V E - Wil.I.T E 1.. / s ' bo i \\ ,f s,. a v ( 's 0.SmR/hr None 's RA0!0 ACTIVE .l / s =: g s 3 / \\ F / 'N j RADIOACTIVE-YELLOW II ^s' . \\. s ho \\ s o s 5OmR/hr 1.OmR/hr \\ [(0lfglg[~fg s s =:... / 0I \\ "-70"$j]/ / / N si\\/ RA DIOA CTIVE-Y E L LOW III ~~ es 'N N ,/I),q)'s ' G 200mR/hr 10mR/hr ( D 2 s A010...AtilyprFJ -- / \\.. / s C ]. fI/ D N ".: 7 N / v t c. Fill out information requested on label indicating: a. Contents (isotope) b. No. of Curies c. Transport Index The Transport Index is determined by observing the maximum reading at 1 meter from the source container. This reading becoces the Transport Index. 6 7 - 11 Revision 0 30 Oct.ober 1980

i i d. Remove all old shipping labels. - NOTE - i Do not remove metal container-identification label, e.. Affix new shipping labels to two opposite. sides. f..l Properly complete the. shipping papers indicating: t Proper. shipping name (i.e. Radioactive Material, Special: Form, n.o.s.) Physical or chemical form.(or.Special' Form) i Activity' of Source (expressed in curies or millicuries) i Category of Label applied (i.e. Radioactive l Yellow III) Transport Inder USNRC Identification Number (USA /, /B) For export shipments, IAEA Identification Number { Shipper's Certification: "This is. co cer tify that the above named materials are properly classified, described, packaged, marked and labeled and are in proper condition for transport according to the applicable j regulations of the Department of Transportation." Notes: 1. For air ~ shipments, the following shipper's certification'may be used. t "I hereby certify that the contents of this cor.s ignment are fully and accurately described ' above by proper shipping name and are classified, packed, marked and labeled and are in proper i condition for carriage by air according to applicable i a national. governmental regulations. l, t 2. For air shipments, the package must be label::d i with a " CARGO AIRCRAFT ONLY" label and the shipping papers must state: } l I 7 i 7 - 12 Revision 0, 30 October'1980 i 4 t I ._m.-...m., ..,........~.-.s..

? o l "THIS SHIPMENT IS WITHIN THE LIMITATIONS PRESCRIBED FOR CARGO-ONL'l AIRCRAFT." G. Return the container to: Technical Operations, Inc. 40 North Avenue Burlington, Ma. 01803 USA Preparation of an Empty Package for Transport 1. To prepare an enpty package for transport, follow the instructions of the operating prccedure above beginning with Step 8 with the following exceptions: The package must be marked (Radioactive Material - a. LSA-NOS:. b. The proper shipping name is Radioactive Material - LSA-n.o.s. c. Radionuclide is Depleted Uranium. t J 3 7 - 13 Revision O' l 30 October 1980 l i i i

9 .a 1 '8. Acceptance Tests and Maintenance Program '8.1-Acceptance Tests l8.1.1 ' Visual InspectionL The' package is visually examined to assure that the appropriate f ast-eners are properaly seal wired and that the package is properly marked. The ' seal weld of the radioactive source capsule is' visually inspected for proper closure. '8.1.2 Structural and Pressure Tests The source assembly is subjected to a static' tensile test with a load of seventy five pounds. Failure of this test will prevent the source assembly from being used. 8.1.3 -Leak Tests The radioactive source capsule (the primary containment) is wipe tested for leakage of radioactive contamination. The source capsule is sub-jected to a vacuum bubble leak test. Thr capsule is then subjected to . a second wipe test for radioactive contamination. These tests are described in Section 7.4. Failure of any of thest tests will prevent use of this source aJsembly. 8.1. 4 Co=ponent Tests The lock assembly of the package is tested to assure that the security of the source will be maintained. Failure of this test will prevent use of the package until the lock assembly is corrected and retested. 8.1.5 Tests for Shielding In_tegrity The radiation levels at the surf ace of the package and at three feet L from the surf ace are measured using A small detector survey instrument (i.e. AN/PDR-27). These radiation levels, when extrapolated to the rated capacity of the package, must not exceed 200 milliroentgens per hour at the surface not ten milliroentgens per hour at three feet from the surface of the package. Failure of this test will prevent use of the package. 8.1.6 Thermal Acceptance Tests Not Applicable 8-1 1 Revision 0 30 October 1980

- io J' i i 8.2 Maintenance Progrrm 8.2.1 Structural and Pressure Tests Not Applicable 8.2.2 Leak Tests As ' described in Section 8.1.3, the radioactive source assembly is leak tested at manufacture. Additionally, the source assembly is wipe tested for leakage of radioactive contamination every six months. 8.2.3 Subsystem Maintenanc'e The lock assembly is. tested as described in Section 8.1.4, prio to each use of the package. Additionally, the package is inspected for tightness of f asteners, proper seal wires and general condition prior to each use. 8.2.4 Valves, Rupture Discs and Gaskets ( Not Applicable 8.2.5 Shielding ?rior to each use, a radiation survey of the package is made to assure that the radiation levels do not exceed 200 milliroentgens per hour at the surface not ten milliroentgens per hour at three feet. from the surface. 8.2.6 The rmal Not Applicable 8.2.7 Miscellaneous Inspections and tests' designed for secondary users of this package under ^ the general license provisions of 10CFR71.12(b) are included in Section 7.4. 8-2 Revision 0 30 October 1980 1'~813 . -. -..}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20148L641&oldid=4172058"