ML19259D632
| ML19259D632 | |
| Person / Time | |
|---|---|
| Site: | 07109028 |
| Issue date: | 09/27/1979 |
| From: | Munro J TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.) |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 14263, NUDOCS 7910250195 | |
| Download: ML19259D632 (6) | |
Text
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Tech! Ops pmv Y'h LDa a
Pad. abor. D oduC*S Civison f
40 North. Avenue I
BMrg*on Massachusers 01803 Te'e;; hone (617) 272 2000 27 Feptenter 1979
- 55. Charles E. I/acDonald, Chief
. Transportation 3 ranch Division of Pael Cycle and Material Safety U.S. Itacle ar Regulatory Cc= mission Washington, DC 20555 Daar Fr. IzacDonald:
We request renewal of USNRC Certificate of Cc pliance !!o. 9028 issued fer Technical Operations Models 684 and 68h2 Type 3 Facka6es.
In acecrdance with your letter of 23 July 1979, eight copies of a censolidated application
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for this package are enclosed. In accordance with lOCTR170 31 Item 11.E, we are also enclosing a check for $150 for the renewal fee.
We are simultanecusly applying to the U.S. Lapartcent of Transportation f6r an. International Atenic Energy Agency Certificate of Ccapetent Authcrity issued under the 1973 Revised Edition of IAEA Safety Series IIo. 6 for Type 3(U) Fackaging.
We trust that this applicaticn satisfies your requirerents for renewal of this certificate.
& *ncerly,
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.s Jchn J. !?anro III Technical D' rector JJM/fb xc:
- 35. R. R. Rawl, USDOT j } } } ]I)3 Encl.
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Tech! Ops i
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e 'e Pad:apon Produc's Divison
.m 40 North Avenue Burlingon, Massachusetts 01803 Te' phone (617) 272 2000 e
27 September 1979
- 55. Richard R. Ravl Health Physicist Office of Ra:ardous ?&terials Regulation Materials Transportation Eureau
- United States Department of Transportation Research and Special Fregrams Administration
'4ashington, DC 20590 rear Mr. Esvl:
'4e request issuance of an International Atomic Energy Agency Certificate of Competent Authority for Type B(U) packaging under the 1973 Revised Edition of IAEA Safety Series No. 6 for Technical Operations Models 684 and 63hz Type B Packages, USA /9028/B. We are requesting this certificate due to
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the serious difficulties we have encountered in transporting this package internationally with its approval based on the 1967 Edition of IAEA Safety
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Series No. 6.
~Je are enclosing two complete copies of the package description for the Models 634 and 63hE. We are sinultaneously applying to the U.S. Nuclear Regulatory'Co==ission for renewal of USNRC Certificate of Co=pliance No.
9028 issued for this package. Eight copies of this package description have been forwarded to USNRC.
We trust that this request contains the information you require for your review. Your prompt action vould be greatly appreciated.
U ncerely,
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s (chn[J. Punro III Technical Director JJN/?b xc:
Mr. C. E. Maercnald, USNRC r
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Te:e;;hene (617) 272-2000 FACKAGE DESCRIFTIOi IECHNICAL CFEP.ATIO:JS 5:CDIL 68k CSA/9c28/3 Srecared by DAVID MAP.ZILLI 21,A
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General Inferration n
1.1 Introduction The Tech / Ops Models 634 and 6Sh3 are designed for use as ga=a ray projectors and shipping containers for Type 3 quantities of radicactive raterial in spe-cial form. The Fodel 63h3 differs from the Model 684 only by the addition of an electric circuit, which provides cccpatibility with Tech / Ops Fodel 657 Autcratic Exposure revice. Throughout this evaluation the Models 68h and 68h3 are considered intercha.geable, except where specifically designated.
The Model 634 conferns to the criteria for Type 3 packaging in acecrdance with 10CFR71 and satisfies the criteria for Type 3(U) packagin6 in accordance with IAEA Safety Series no. 6,1973 The sources to be used in conjunction with v del 68h are Tech / Ops scaled Source Asse blies Model Ncs. A42h-15 and the o
Ah2h-20. The scurce assemblies vill contain a maximum of 11 curies of cobalt-
. 60 cr 2h0 curi's of iridium-192, respectively, as special fcm.
1.2 Package description 1.2.1 Packagirg The Medel 68h is 12 9 inches (327=) high,171 inches (k35=) Icng, and 10.1 inches (257=) wide in overall dirension. The gross weight of the package is 225 Pounds (lO2%g). The radicactive scurce assembly is stored in a circalloy or titanium "S" tube in the gecretric center of the package.
The "S" tube is cast inside a depleted uranium shield assembly. The weight of the uraniu= shield is 150 pounds (6ckg). The shield is provided with a paint finish.
The shield is enclosed in a shell fabricated of 0.1375 inch (h.76t=) thick hot rolled steel. The shield _ is fixed in pcsition within the shell by the retaining bar asserblies. The void space between the shield, and the shell is filled with a castable rigid polyurethane feam. Steel-uranium interfaces are separated with 0.010 inch (0.25hrm) thick cepper separators.
Attached to the sides of the container are 0.625 inch (15 9
) thick hot rolled steel side frames used fcr liftird the package.
Mcunted at each end of the "S" tube are pcsitienirs devices.
'"he scu ce a s s e -
bly is locked in positica by means of the control cable ecnnector and addition-ally secured by means of a 1 hipping plug. A prctective shipping plate (I inch thick steel) is rou.ted cver the control cable connector assembly.
Tarperprcof seals are provide 1 du-ing shiptent of these scurces. Assembly joints which are not leak-tight provide passageways for the escape of any gas generated frc= de:cepcsition of the ;otting fcan in the event the crejector is involved in a fire accident.
'"he cuter packagins is designed to avoid the ecliection and retention of water. The package is painted and finished to previde for easy decca d ation.
"ne ridicactive raterial is sealed inside a scu ce capsule, which is the contairent vessel of the ;.ackage.
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.- l00 REVISION O 1-1 SEP.2~7 G79
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o "he Fodel 68k has been previously approved for use as a Type 3 package under US'.'BC Certificate of Ccmpliance No. 0028, Rev. 2 (enciesed in Section 13).
m 1.2.2 Operational F3atures The source assembly is secured in the proper pcsition by the -ontrol cable con-nector and Icek assembly. This assemb(v requires a key for operation, and thus provides po itive cicsure. A inch (6 35mm) thick steel shipping plate is used to protect the assembly during shipment. Additionally, the source assembly is secured by teans of a shipping plug inserted in the opposite end of the "S" tube.
This plug is seal wired and provided with a tamperproof seal.
1.2 3 Contents of Fackagir4
-The vedel 63h is designed for a capacity of up to 11 curies of ecbalt-60 as Tech / Ops Scuree Asse.ebly Ak2h-15 or up to 2h3 curies of iridium-192 as Tech / Ops Scuree Assembly Ak2h-20. The assemblies are in special form as prescribed in 10CFRT1 and I.EA Safety Series 'To. 6,1973 l'i1 1A7 i 't um ;
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1-2 REVISION O SEP. 2 7 m3
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- US:.'BC Certificate of Ccmpliance '!o. 9028, Rev. 2
- Descriptive Assembly Drawing, Mo'.el 684 1 ?21..
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rerm t.a C4 8 U S. N UCL ' A R A E G U L AT O R Y C O P.'.U S $Ked U 24 33 CE RTIFICAT E OF COT.'PLI ANCE 10 CF R 71 For Rad;c.ciive Materials PacLa;es 1.f a) Certif; ate Nu -ter 1.(b) Revision No.
- 1. (c) f*acm age identiGc.a b No.
1.f d ) Pi;es No 1.fel Total No. P4;f r
9028 2
USA /902AiB( )
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- 2. FF E :NSLE 2.(a)
This certificate is issued to satisf y Se:t;ons 173 393a.173.394.173 335, and 173?5& of the Ce:anment cf Transxr:.:icn Ha:arcot
'.*a:c':ats Ae;uistions f 49 CFR 170-:29 and 14 CF R 103) and Sections 146-19-L exs 1G-19-1CO cf the Oe:a : ment of Transpor ation Cangercus Cargoes Fegulatiers (46 CFR 146-149), as amended.
2.!b)
The racia;ing and centents described in item S'tetow. meets :Se safety mnda ds e fonk in Sce:ar* C of 96e 10. C:.de of Te-dera: Fe;u!ations. Part 71. '"PaciaW of Reficactive * *a:eWais for Traanen a,d Tanner 214n of Fad:ca: ev e *.'ai r' a' und er Certain Ccndit.ons."
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TNs certificate does not re!;ese the cens';nor frc,rn com !:ance with any t r::uss e.e.t of :.Se re;ufatiens of the U S. Ce:ar.ent of Transpor:at.on or cther ap;)hc.able regu:a? cry agencies. in:!ucing the ;cverntm=nt of a.~y =vnity tusev;h or into w51cn the pria;e wd! be trarsyrted.
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- e trsis of a az'en a a'vs:s rex-t o8 ?'e 3-i7;e das;;n or a6-:::co--
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F e p.r e-by p.ame at:i address):
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Tiik and : ect.ficar:on of ar:cn or a::::iica' ion:
iecnnlcal' Operations,Inc.
Techr.ical Opera tions, Inc. applica tion
- iortNest Industrial Park-dated August 26, 1974, as supplemented.
Burlington, *'assachusetts 01803 3aci cocaet No.
71-9028 4 CCN OiTiC NS This :ertif..iie is cor ditions: upon the fc!h!!:ng of the recuirements of Sut: art C of to G A 71 as a: nca::e. and the ec-di:.ns t;e:J;ed in ::em 5 be:ow.
- 5. C escricGon c' P.:ka; n; and Av:ScriN Cor ents. *.4c'el %.r ter. Fis. e C: ass. C:5er Case u s. at Fef e.ences:
(a) Packaging
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(1) Model Nos.:
684 and 684E (2) Description A steel encased uranium shielded Gamma Ray Proiector.
Primary czponents consists of an cuter stee' shell, internal bracing, polyurethane potting material, depleted uranium shield, and a zircalloy "S" tube.
The contents are securely positioned in the zircalloy "S" tube by a source cable locking device and shipping plug.
Tarcer-proof seals are providedJn the packaging and a 1/4-inch thick steel shipping plate is bolted over the source locking mechanism for additional protection during transport.
The total weight of the package is approxima tely 225 pounds.
'00f1OPJGIU1 1-h REVISICH O SEP. 2 7 im C
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s Page 2 - Certificate No. 9028 - Revision No. 2 - Docket No. 71-9028 5.
(a ) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following Technical Operations, Inc. Drawings Nos.:
B66001-1 thru 8 D65403 B66001 -11,12, 20 063403-1 B65502 CSS 403-2 D65503 065404 9655E01 B68404-1 D63402. Rev. A CSK 1923 B68402-1 868402-3, 5, 6, 9 A 62402-8, 10, 11, 12 (b) Contents (1) Type and form of material Cobal t-60 or Iridium-192 as sealed sources which meet the requirements of special form as defined in 571.4(o) of 10 CFR Part 71.
(2) Maximum quantity of material per package T
l'1 Curies of Cobalt-60; or
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240 Curies of Iridium-192 6.
The source shall be secured in the shielded position of the packaging by the shipping plug, source assembly, and locking device.
The shipping plug, scurce assembly used must be fabricated of materials capabfe of resisting a 1475 F fire environment for one-half hour and maintaining their positicning function.
The ball stop of the scurce assembly must engage the locking device.
The flexible cable of the source assembly and shipping plug must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.
7.
The name plates shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their l egibil i ty.
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Pag' 3 - Certi ficate No. 9028 - Revision No. 2 - Docket No. 71-9028 e
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The package authorized by this certificate is hereby approved for use under the general license provisions of Paragraph 71.12(b) of 10 CFR Part 71.
9.
Expiration date:
January 31, 1980.
REFERENCES Technical Cperations, Inc. application dated August 26, 1974.
Supplements dated: December 15, 1974; and January 8,1975.
FOR THE U.S. NUCLEAR REGULATORY CO:OilSSION
$ hx 0
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety UR 2k Gil emate:,
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POORORl81UL 2.
Structural Evaluation 2.1 Structural Design 2.1.1 Discussion Structurally the Ycdel 63h consists of five components: a scuree capsule, shield assenbly, outer shell, s' te frames and Icek assembly. The source cap-sule is the primary containter vessel.
It meets the requirements for special form radicactive caterial as outlined in 10CFR71 (see Section 2.8).
The shield is 150 pounus (68kg) of depleted uranium. The shield assembly fulfil 3s two functi.ons:
it provides shi3?. ling for the radicactive naterial and, together with the positioning rechanists, insures proper positiening of the scurce. The shield assembly is suppcrted with retaining bars which are fcreed tcgether by r eans of hex nuts threaded on adjusting screws. The adjusting screws and re-talning bars are secured with jam nuts. The entire shield assenbly is pctted in a esstable rigid polyurethane fcam and encased in a 0.1375 inch (4.76mm) thick hot rolled steel shell. Steel-uranium interfaces are separated with ecpper. Attached to the shell are side frames rade of 0.625 inch (15 9mm) thick steel which are bolted together with T/16 - 20 7;F hex head bolts. These are designed as lifting devices and impact limiters. The key cperated lock asse -
bly and control cable connector secure the source in the shielded pcsition. A d inch (6.35mm) thick steel shipping plate is installed to protect the lock frca damage.
Positive proof of source position is evidenced by the use of a
'T seal vired shipping plug.
2.1.2 Desien Criteria The Mcdel 634 is designed to cenply with the requirements of 10CFR71 and IAEA Safety Seried !!o. 6, 19'3 The device is simple in design, such that there are no design criteria Vhich cannot be evaluated by straight-fervard application
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of the appropriate section of 10CFRTl or IAEA Safety Series :;o. 6,1973 2.2
'4 eights and Centers of Gravity The "cdel 63h prcjectcr veighs 225 pounds (lC2kg). The shield assanbly con-tains 150 pcunds (63kg) of depleted uranium. The center of gravity is loca-ted apprcximately at the gecretric center of the package.
23 "echanical Frcperties cf "aterials The Model 63h Garra Eay Frejecter shell is ade of hot rolled steel. This ca-2 terial has a yield strength cf h0,000 pcunds per square inch (276V';/c ).
(Re-ference: "achinery's Handbeck,, 20th Edition, 1976, p. h52).
2.k General Standards for All Fackages v
2-1 IiEVIS:CN O
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1300RORIGd 2.h.1 Chemical and Galvanic Reactions The raterials used in the construction of the Model 68h Gasma Ray Projector are uranium retal, steel, beryllium copper, bronze, copper, and titanium or zire-alloy. There vill be no significant chemical cr galvanic action between any of th m ccepenents.
The possibility of the foration of the eutectic alloy of iron uranium at teep-eratures belev the celting temperatures of the individual m2tals was considered.
The iron uranium eutectic alloy temperature is apprcximately 1337"? (T25 C).
Hcvever, vacuum conditions and extreme cleanliness of the surfaces are necessary to produce the alloy at this lov temperature.
Due to the cenditions under which the shields are counted, sufficient contact for this effect dces not exist.
In support of this conclusion, the folicving test results are presented. A ther-tal test of a sample of care depleted uraniue metal was perfo= 3d by "uclear
- etals, Inc. The test indicated that the uranium sample cxidized such that the radial dirension was reduced by 1/32 inch. A subsequent test vac perfered in which a sample of bare, depleted uranium metal was placed en a steel plate and subjected to the thermal test conditions. The test showed no alleying or mel-ting characteristics in the sa:ple, and the degree of cxidation was the sare as evidenced in the first test. A copy of the test report appears in section 2.10.
Althet.gh the likelihcod of the formation of'an iron-uranium eutectic alley is remote, copper separators are used at steel-uraniu= interfaces.
2.h.2 positive Closure The :/odel 634 scurce cannet te expcsed without opening a key-operated lock.
Ace'ess to the lock requires the receval of the shipping plati. Additionally, there is a shipping plug which is seal wired and provided with a tamperproof seal.
2.k.3 Lifting revices The Medel 63h is designed to be lifted by the side fraces. Each is secured by four T/16 '- 20 U'.7, SAE J h29 Grade 5 hex head bolts. These bolts are installed with 7/16 Icek washers. The yield strength of these 7/16 - 20 U:.? bolts is 10,900 pcunds (he.6kN). As there is a thread engagement of 3/h inch between the bolt and the tapped rod, the yield strength is less than the stripping strergth (apprcxicately 21,000 pcunds) and thus, is the limiting factor. A torque of 30 fcct-pounds (hlN-m) is applied to these bolts. This correspcnds to a tension cf approximately h083 pcunds (13.2kN). The tctal tensile leading en each telt is h250 pounds (18.9kN), due to the bolt terque and three times the weight of the package. The total torsional leading is 6090 pounds (27.lkN). 2cth leads are less than the yield strength cf the bolts.
The veld joining the side frare to the side frame insert on the Mclel 68h is a 3/16 inch fillet veld.
?.e American Welding Ecciety " Code for Arc and Oas Welding in Euilding Constructien" permits the stress on a fillet veld to be mj 13,600 psi (39.6?C/=2). As the shear stress on the threat of the fillet veld 2-2 EE*[ISICN Q l2l4 073 SEP. 2 71579
-v.-._-
_. =. _..
~~
is the limiting factor, the allevable stress on a 3/16 inch fillet veld (thrcat dinension, 0.133 inch, 3 38:m) is calculated to be 1,800 pounds per linear inch (320N/cm). As the perimeter of the side frame insert is 40 inches (l.Olm), the allevable lead on the side frame insert veld is greater than the yield strength of the bolt.
2.h.4 Tiedevn Devices The tielcun devices on the Model 68h are the side frames. As indicated in 2.h.3 above, these frates can safely support the package.
25 Standards for Type 3 and Large Quantity Fackages 2 5.1 icad Fesistance Considering the pack 35e as a simple beam supported on both ends with a unifcrm 1 cad of 5 times the package weight evenly distributed along its length, the sximum stress can be ec=puted frcm:
,F1-S
=
cZ vhere:
S: maxi =um stress F: total load (1125 pounds) a 1:
length of bess (171 inches) 3 Z-section modulus of beam (33 2 in )
(
Reference:
yachinery's Handbeck, 20th ed., lh76,p.hh2)
Thus, the taxt=um stress generated in the beam is 72 pounds per square inch (5C0kN/=2), which is far belev the yield strength of the raterial, h0,000 psi (275MN/=2).
252 2:cternal Fressure The Fcdel 63h is open to the attesphere; thus, there vill be no differential pressure acting on it.
The collapsing pressure of the source capsules can be fcund:
86,670 1 - 1336 P
=
D vhere:
?: collapsinE pressure in pouhds per square inch t: vall thickne:s in inches (0.C23 inch) s
~
D: cutside diameter in inches (0.25 inch) e r v' 'r c *+ w' O
^~
2-3 1214 377 sce. 2 7 s:s
=
~
?0DR ORIGIM N
(
Reference:
Machinery's Handbcok, 20th ed.,1976, p. hh8)
The collapsing pressure of the capsule is calculated to be 5550 pounds per 2
square inch (38.8?cI/m ).
Therefore, the capsule can withstand an external presure of 25 psig.
2.6
- iormal Conditions of Transcort 2.6.1 Meat The thermal evaluation is performed in Chapter 3 of this application. Frem this evaluation, it can te concluded that the Model 63h can withstand the ncrral heat transport conditions.
2.6.2 Cold 3e retals used in the manufacture of the Model 634 can all withstand tempera-tures of h00F ( h0cC).
"'hc lover cperating limit of the polyurethane fcam is
-100 F (-73 C). Thus, it is concluded that the Mcdel 63h will withstand the ncrmal transport cold conditions.
2.6.3 pressure
~
The Model 63h is open to the atmosphere; thus, there vill be no differential pressure acting on it.
In Section 3 5.k, the scurce capsules are derenstrated to ';e able to withstand an external pressure reduction of 0,.5 at:cspheres (5 0. TkN/h2).
k 2.6.4 Vibration Se Mcdel 63h has been in use seven years. During that time there has never been a vibrational failure reported. Thus, ve contend the Model 68h vill not andergo a vibrational failure in transpcrt.
2.65
'iater Spray Test The vetar spray test was not actually perfered en the Model 6Sh.
'4e centend that the esterials used in ecnstruction of the Mcdel 68h are all highly water resistant and that expcsure to vater vill not reduce the shielding er affect the structural integrity of the package.
2.6.6 Free Droo The top analysis perfcmed in Hypothetical. Accident Conditions (see Section 2 71) is sufficient to satisfy the require:ents cutlined fcr the nc=al trans-2-E REVISICN O 1214 083 sse. 2 7 372
.___m._
___,m.....
_.....__.__s.
t 8
p!crt free drop condition in 10CFRT1 and IAEA Safety Series No. 6,1973 On T
this basis, we conclude that the Model 68h can withstand the free trop without inpairnent of the shielding or package integrity.
2.6.7 Corner Drop
- Tot applicable.
2.6.3 Fenetration A penetration test, consisting of a 40 inch drop of a 13 pound billet with a hemispherical end, was performed on the Mcdel 68h.
(A copy of the test report in enciesed in Eection 2.10).
The Model 68h suffered no loss of shielding or
, structural integrity, satisfying the requirements of 10CFR?l.
2.6.9 Concression The gress weight of the Model 63h is 225 pounds (lC2kg). The maximu= cross-sectional area of the.cackage is 220 square inches (0.142:2). Thus, 2 pcunds per square inch tires the cress-sectional area (hh0 pounds, 200kg) is less than five tires the package weight (1125 pounds, 511kg).
For this analysis, the load vill be taken to be 1125 pounds.
ine raximum stress generated in a flat rectangular steel plate with all edges fixed and a lead distributed uniformly over the surface of the plate can be cceputed frcm:
e 0 5F i
S
=
2-1 0.623 1 t
- +
v v
where: S: caximum stress F: total lead (1125 pcunds) t:
thickness of plate (0.133 inches) v: vidth of plate (12 9 inches) 1:
length of plate (17.1 inches)
(Eeference: Ma ch inery 's Ha n d':eck, 20th e d., 1976, p. hhh, Eq. 13 )
the maximum stress generated in the plate is L110 pcunds Frem this relationship,/c ).
per square inch (23.3:CI 2 This figure is greatly telev the yield strength of the caterial, LO,0C0 pcunds per square inch (276M'I/=2). Thus, it can be cen-cluded that ec pression vill not adversely affect the packsge.
27 g;;cthetical Accident Cenditions n-iie" O
^"
J' 2-5 1211 D81 saa m
_. - -. =. =
=.
'2.T.1 Free Drop s
The Model 634 was not actually submitted to the 30 foot drop test. However, the Medel 670 was submitted to the drop test (the test report appears in Section 2.10). The Model 684 has approximately the sete weight and is constructed frca the same caterials as the Model 670.
Model 670
'.iodel 684 Length 15-1/2 inches (39 =m) 17-1/8 inches (435cm) h
'viidth 8-5/8 inches (219:ca) 12-7/8 inches (327mm)
Haight 7-1/2 inches (191nn) 10-1/8 inches (257=m)
Weight of Shield 134 Lbs. (61kg) 150 Lbs. (68kg)
Gross Veight of Container 175 Lbs. (76kg) 225 Lbs. (102kg)
Sih '- ~ Material 9/16inchthick(14.3=m) 5/8 inch thick (15 9 =)
ductile iron hot rolled steel 0.120 inch thick (3 05cm) 3/16 inch thick (h.76m )
Shell Material steel hot rolled steel 3aued on the satisfactcry perfomance of the Model 670, we conclude that the Model 634 vill undergo no loss of shielding cr structural integrity as a result of the 30 foot drop test 7.2 hneture The Model 63h ves not submitted to the puncture test of 10CFR71. Ecwever, the similar Model 670 (see Section 2 71) was submitted to the puncture test. ~here was no resultant damage to the container acr reduction in s'qielding.
(a copy of the t ;st re;c t appears in Section 2.10), The shippirs plate used in the Model 63h is the same as that used in the Model 676. The Mqdel 676 puncture test report (included in Section 2.10) shows that the shipping plate withstood the puncture test.
Cn this basis,. We conclude that the Model 634 can withstand the punett. w:.diticn as specified in 10CFR71.
273 The=al Se themel a.alysis is presented in Sdeticn 3 5 There it is shcvn that the talting points of the caterials, except the ;otting ccn;cund 75cp(3ccCh.usedin c
the ecnstruction of Model 63h are all greater than IL Also indicated is the previcus acceptability of this design (.NRC Certificate af Ccepliance No. 9028, Rev. 2) usire this evaluaticn.
D us, it is ccnclude'. that the vedel 63h satisfactorily teets the require-cents fcr the hy;othetical acci<1ent-themal evaluation as set fcrth in ICCFRT1.
2 7.h
ater B~ersion 3ct applicable 2 - o-IL:./ c o N O 121,1 V pJ w?
SEP. 2 71579 7
I (
-.... -....,..... - _. =.,. - _. -.
275 Su'marv of n,nage s
The tests designed to induce mechanic r.1 stress (drop, puncture) caused minor deformation, but no reduction in the safety features of the package.
The thermal test resulted 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 and structural integrity of the package.
2.8 Special Form The Model 684 Garza Ray Projector is designed for use with Tech / Ops Source Assenblies Ah24-15 and Ah24-20. These source assecblies have been certified as special fem radioactive caterial.
(IAEA Certificate of Cocpetent Authority ?ios. USA /0165/S and USA /015h/S, see Section 2.10.
'Je contend that these certificates are sufficient evidenca that the require ents for
- special fom radicactive caterials, as established in IAEA Safety Series Xo. 6, 1973, are satisfied.
29 Fuel Rods
'ict applicable.
^
1214 033 i
2-7 ggyrg;og o SEP. 2 7 G7)
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3 2.10 AFP ITDIX
- :helear Metals, Inc., Test Report: Iron Uraniu'n Alloying
- Test Report:
Penetration Test, Model 684
- Test Report: Erop and ?2ncture Tests, Model 670
- Test Re, cort: Pancture Test Model 676
- rescriptive Asse='oly Drawings, scurce Asser?olies
- IAEA Certificates of Cocpetent Aut'nority Ncs.
10,1
- ,.u 4
E
~
2-8 REVIs;Oli 0 SEP,2 71979
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N U C L E A R M E T A L S, I N C.
37 2 ;g wa os 3? a E ET CCNC Ost. M AE S ACwus LTT5 Co?42
?ttcmc=c 60 J e 9 5 *'O 28 January 1974 Technical Operations, Inc.
Radiaticn Products Division South Avenue Burlington, Massachusetts 01803 Atter, tion: Mr. J. Lima Gentlemen:
In response to a recuest by Joe Lima of Tech Ops, a simulated fire test was cerformed on samples of bare depleted uranium in contact with mild steel, the cbject being to delen.:ine what, if any, alloying or melting would occur under these conditions.
TEST DATA:
}~
A 3/4-inch diameter x 5/8-inch long bare depleted uranium specir.en was set on a 1-inch diameter x 1/8-inch thick mild steel plate, placed in a thin wall ceramic crucib;e.
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 removeg! ana allowed to air cool under a ventilated hood.
'RESULTS:
i'o reaction was evidenced between the two metals.
Both separated readily and shcwed no alloying or melting characteristics.
Oxidation of the uranium was about the same degree as that reportsd to Joe Lima en an earlier experiment.
The test was performed by tiMI en 25 January 1974.
"ery truly ow Ai^'
i 21 i J P> 3 Jchn G. Fcwers Project Engineer b._
e_9 REVISION O SEF. 2 71U9
, w.
c Wr ;p.c;:.3. & g '
--+-
L _'. LM t:
TEST REFCRT RADIATION FRODUCTS DlV'SION SY:
John J. :tanro III DATE:
5 September 1979
SUBJECT:
Model 68k Fenetration Test
_On 5 September 1979 a penetration test was perfor:ed on a Technical Operatior.s Model 63b Shipping Centainer in acecrlance with 10CFR71 Appendix A.3 and IAEA Safety Series :io. 6,1973, paragraphs 71ha and 71Lb.
The hemispherical end of a vertical steel cylinder 1.25 inch in diameter weighing ik pounds was dropped frcm the height of 40 inches onto the gecretric center of the bottem surface of the Model 63k. There was no defomation and no damage which would affect the shielding er structural integrity of the package.
A second test was conducted using the same cylinder.
It was dropped frce the height of 40 inches onto the shipping plate. There vas no deformation and no darage which vculd affect the shielding or structural integrity of the package.
-~
recumentry photcgraphs are enciesed.
Perferred by
'4ttnessed by 4
//rf / / A Y
,r1
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Cch.
J.' Punro III
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'ml TEST REPORT DESCR1PTION:
Model 670 - 30' Drop DATE March IS,19~0 Subjected to two drop tests during which no damage was sustained. The third drop test landed on the front leading edge brcaking it off Gush with the skin.
There was no other damage.
The puncture test (41" drop on to a 6" dia, steel bil:et) produced no dsible dam a ge.
CONCLUS10N:
't BY F.ichard Evans WITNESSED BY Fred Hauser l2l$
) )
2 - 14 EEVISION O SEP. 2 7 ::.79
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DATE 9 racer.ber lo7h Pr.cture Test of "odel bT6 Container Connector A Model 6T6 Garns Psy Projector with Shipping Plate installed was dropped
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as shcvn in Figure 1 s. The Centainer inpacted en the Shippir4 Plate as shewn in Figure 1 b.
CONCLUSION:
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IAZA C r.h T1/1 CATE OF CC '.F:-: T ES'i A U TH O R 11'i
%ecial Tcm a E.4 d i c a c t i v.- "a:erial Encarsolation
.,,,,, m ce rti f 5 cat e ::ar.ber USA /0154/S This certifi es that the encapre:ated sources, as descriced, unen 2 coded with the authorirgd radicoctive contents, have been d oo n -
strated to -.eet the regulatorv r ec u i r,".w n t s for special f c. m 2
adi c,,c t ive mat er i al as prescribed in I A r.A } and USA rego:ations for the transport of radicactive =aterials.
1.
F.our ce a sc -i a i on - The sour.es desc-ihrd ';y this certif3 care
-re 32-ntified an the Technical Cptrations, Inc., %dels -hich are described and cons t ::uc t ed as foliews:
Mcdel ?;c.
Ca rs ul e Stvle App r o: 1=a t e S i r.e (in inches, d :. e_t _e r _ _x _:_ n o. - M. _
A.4 2 4 -1 E60001 or r.60004
.25 x.97
.424-6 Ei0001 or E60004
.25 x.97 A424-9 360001 or E60004
.25 x.97 A424-20 360001 or 3 60'J 04
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309 C55310 re]let o r 1:a f er
.25 x.78 AE2401 3'60001 or 360004
.25 x.97 3t9/02 E60001 or B60004
.25 x. 9~7q All capsul es a r>e i onst ruc t ed of either 30' o r_ 30'.L stain]ecs st eel
.:,d '.c on f e r r wi t h the fo))cring design d ra wi ngs :
Ca rcul e Stv]e Drawint h-ber 350001 260001 - 1 Fev. E and - 2 Eev, F 50004 E60001 - 1
- r. e v. E and 250004 - 1
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N 00E F=1]et 350006 - 2 ?ev E nad ;n2001 - 2
- 2. + v. F Ir0006 Lafer 350006 - 1 L-v.
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D 3E06 Larie Ca f er 360006 - 2
.nd 26.0001 - 2 r.ev.
F C5F310 Fellet C68310 Rev. E and E65310-3 C' S 310 'ia f e r
,C68310 Fev. B 11.
Eodicoc t ije_ Cont ents -
~~h e authoriced odicactise
( ca:ents of
-se e cu r c as cc u r.i s t of i.ot ore than the f o] 2 c ing :.ats of I r i d ;. -3 9 2 a s s ol i d t...M a l :
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A424-9 120 A424-20 240
'.55101 240 A68309 120 AS1401 120 369701 120 JII.
This certificate, unl ess r e r. e x e d, e>.pires Drcember 31, 2981.
This certificate is issued in accor cance with paragraph 303 of the I'ZA Eegulations I, and in raspense to t he ':ovember 3, 1978, pet i tion by Technical Operations, Inc., Eurlington, Macsachusetts, and in censideration of the acsociated information ti,e r e i n.
CeMified by.-
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C.
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6, Regulaticns for the Safe Transport of 7.adi c.ac t i ve Ma t e ri al s, 1973 Kevised Edition", published by the Internaticr.al Atomic Energy Agncy (I*. A), Vienna, Austria.
Ti: e 49, Code of 'rehral T.ege:ations, art 170-178, USA.
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(Revision 0)
Onis c -rtifies that the <:ncy su'ated sources, as described, w.c:n Ica&d with the authorized --Wicactica ecit.nts, 2va L en dr: wt rat -d t o
- et s c i e., e t i e e macr'al :s Pte re u'ator.y rec ;icc an t s.,for s-ecial for.2 4
s prescribed in 1.23 A) ad CSA Eegel.:ic,s for the tre-m pcrt of.acic-ct.ve
- sterials.
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Sc.urce "escription and h di c.,ct i ce n n t en t s - Tae cu r c e s d e sc r ib.-d c e r t.1, c a t e c c.s _ s t
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c stain:ess steel to the lis:ed ensele da:ps ( ee A;pendix A) rd mich contain not c ore than the list ed cuantit ies of Cc' alt-60 in me t allic
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.-ot A u t :.c ri t y I or tae
{
- -[;rnat _r sl Tr -::s: ort at;:n of Lc. r ict ce ':at erials Office cf % ;ardous "a:erials 7,e g ul a t i en i
Materials Tran3portation Bureau t. S. D ;; 3 c t :.. n t of Transportation S3f3ty S e ; i e s ':o. 6, Pagulaticns for ge Safe Trc: 3p rt of 7 3.'
'aci;3e
': ate ials, 1973 r-eised Edition" publish-d by the I r. t e r.' 41 ' ' ' 31 AtcTic "c.-rgy ' p:,cy (IAEA), Vienna,
- ust ria.
N 2 Ti t l e
',9, Code of 7eferal 3e.;ui-t:cns, Part 17C-178, l'SA.
i I
t
.y e
\\
I o
I 1
1 1
P00Rgagg m,_
_4J.J 04.
I 2-23 12i1 1
1 I*
'i e amamer eme ee e
e - -
u
...u 3
Ti er.sl ?calustien a
31 Discussien S e "cdel 63h Cara Fay Frejector is a ecmpletely passive the mal device and has no nechanical ecoling systems or relief valves. All cooling of the pack-age is through free convection and radiation. The maxi. mum heat source is the 2h0 Cl iridium-192 scurce. The ccrresponding decay heat is 2 5 watts (see Section 3.k.1).
32 C = ary of The ral Froperties of "aterials
-'he neiting points of the retals coed in the constr_ction of the '!clel 63L are:
repleted "ranium "etal 207C p (1133c )
c C
C Car' con Steel 2k33c? (13L5 C)
C Copper 19hD F (1360 C) c 3ronze 13LC ? (10@ C)
/ efarence: "achinery's FerToock, 20th 2d., 1976)
F Titanium 330C F (1320 C)
Eerylliun Copper 1600 F ( 870 C)
C Circa11cy 335C F (lSh5 C)
N (Feference: '?stals Ie r.ibeck, 1961)
~
C C
32 rigid pol,,.u ethane fear has a minicum cperating range of,-1CO F to 200 F
(-f3 C to 93 C).
It vill deccepcse at the fire test tempere%re of IkT5 ?
n C
C (300 C).
regenpesition vill result in gasecus byproducts which will turn in air.
' Q.'"Q 33 Technical Srecifications cf Cc cenents
~
a v: o.
r
?ict applicable.
/,3 1
3,
__ yd 3.h
'!cr 91 f:niiticns of Tra secr:
" ~
3.k.1
?.::ral '/cdel I
y,
,1-..
2 e maxirun heat scurce in the "cdel 63L results fre the decay of 2ho Ci of J%
~
iridi=-192.
Iridiur-192 deceys by electrcn capture and beta eticcien. Se 12eej energy for teth prccesses is ap;rcximately 1.k5 '?37.
(3eference: Fa i' c-
" !s.C.
lcrical Eesith Handbeck, p. LC3). Thus:
M x 1.6 x 10-13; ELO Ci 2.^6-m ts 3.7 x 10",di sint i
- 1. k5 '/ev x x
=
s-C"
?"V The decay hat scur e is conservatirely tsken as 2 5 -istts.
,. _.,.. y q y *,
n I db1V e "l
ab Off gg 1
s w wn i
=
rc qualify as a Type 3(U) package, the requ2 cents of IAEA Safety Series No. 6, 1973, parsgraphs 231 and 232 rust be satisfied. The calculational cedel used to deconstrate compliance with these regulations is described in detail in Section 3.6, along with the results of the analysis.
Essentially, it is assured that cne-fourth of the entire d3 cay heat 1 cad is depcsited uniformly in each of the six sides. The smallest of the sides is assumed to reach the taximum surface temperature.
Heat transfer frc= the side is restricted only to convective haat transfer frcm the upper face of the plate.
To meet the additional requirements of paraErsph 2ko of the IAEA regulations, a separate analysis was perfor ed.
To do this, a heat balance was set up cver the surface of the.cackaze usin$ the insolation data in Table III of the !AEA
-1 regulaticns. The decay heat scurce was censidered negligible. The cuter stell was assured t'o Se insulated frem the interier of the package.
Heat transfer frcm the package was beken to cccur by radiation, and ever specific surface areas by free ccavection. A detailed descriptien of the rodel is given in the analysis
'in Section 3.6.
3.h 2 yaxirum T2rceratu es An examination cf the =elting points of the raterials used in ccastruction of the Vodel 63h shcw that the maximu= temperatures enccuntered under ncrral ecn-ditions of transpcrt engender no less of structural integrity er less of shield-The specific Type 3 U) analyses (Section 3.6) shcw the
/
ing cf the package.
packege terperature to be belew h0cC /104CF) in the shade and belea 63Cc (15kCF) when insciated.
^
3.h.3 Vinimum Temperatures
.s The m*-'-"- -cr:al cperating terperature of the "cdel 684 is -k0 C /-hD ?).
This temperature vill have no adverse effect on the packaEe-3.k.h
'?eximum Internal Pressun Ncrral cperating conditicns generate negligible internal pressures. Any pres-sure generaned is significantly belev that cf the hypothetical accident ;ressure,
.hich :s shcvn to result in no less of shielding cr centainrent.
3.h.5 "sxi.2: The mal Stresses The maxizu: terperatures that occur during ncr al transpcrt are Icv encugh to i-e"-a -'at therral gradients will cause no significant therral stresses.
3.h.6 Evaluation of Fackage Perferrance fcr Ucrnal Ccnditicns of Transpcrt The therral ecnditions cf ncrzal trsnspcrt are cbylcusly insignific ant frc: a functicnal.ceint of view fcr the Mcdel 63h. Also> the applicable ecnditiens cf 2 -2 EVISICII O s
l } i,1 1 Il f SEE 2 7 W 103R Rgys 1
I r io J
DEA ?.egulations for Type 3(U) packsges have been shewn to be satisfied by the v del 68h.
e
/
35 Hypothetical Accident Tnemal Evaluation 351 Rer-al '!cdel Tne cdel 63h, including the source assenbly, is assu-ed to resch the fire test tenperature of 300 C (lkT5cF). At this temperature the pol'.rethane potting C
ccrpcund vill have deccepcsed and the resulting gases vill have escaped the package through the asse bly joints which are not leak-tight.
352 Facka.e Ccnditicns and Enviren ent TSe "clel 63h is considered to have undergone no significant darage durirq the free drop and puncture tests; thus, the package in this analysis is assumed to be free frc= functional darage.
353
?sekage Tenperstures As indicated in 3 5 1, the package reaches a taxirum tamperature of 800 C (lh75 F) t'c rcughcut. An examination cf the telting points of the caterials used in the v del 63k (except the pctting ccepound, as noted) indicates
'x censtruction of the e
that there vill be no damage to the package as a result of this temperature.
~
Se ;cssibility of the femation of the iren-uraniu= eutectic allcy was add essed in Section 2.k.1, where it 'vas cencluded that the for:stien of the alloy was unMkely.
T 35.4 t'axi-um Internal h essures Tne yodel 634 packaging is open to the annesphere; insuring that there vill he no pressu e buildup within the package. In Sectica 3.6, there is an analysis of the scurce capsyles under the fire test conditions.
It is shewn that the
.uinn internal gas pressure at this terperature is 5h.7 psi (0 377'G/ 2).
Tne critMal Icestien fcr failu e of the esesule is the veld. An inte=al cres-sure of 51.7 psi (C.377?G/ 2) vill generate s maxiru stress of 267 psi (l.h :d/ 2) in the veld. At a temperatu e cf 870cc (1600 M the yield strength of Type 3Ch cr 3SL stainlecs steel is 10,000 psi (69.0 G'=2).
Tnus, at 33CoC (ikT5 F), the maxinu stress in the capsule veuld only be 3% cf C
the yield strength at that point.
355 yaxinum ~he=al Strecses Tnere are no significant thenal stresses generated during the therral test.
3-3 Evic!CN O 1214 07 sm :m
t 6
3.$.6
?taluation of Fackage Perfe mance s
""he t/odel 634 vil] undergo no less of structural integrity or shielding when subjected to the conditions of the hypothetical the mal accident. The pras-sures and temperatures generated have been detenstrated to be within the acceptable limits.
)2)'
+
~
3-h 9.E*E3 ION O er:
- r.. c,
- x.. p t
- -m
~
_w e
..m.
.m,
~
m i
I 3.6 AFFE'OIX
- Model 684 The nal Analysis:
!AEA Safety series :'o. 6, 1973, paragaph s 231, 232
- Model 63h "'hemal Analysis:
IAEA Safaty Series No. 6,1973, para gaph 2k0
- Themal Arslysis, 0.25 Inch 0.D. Capsules 121.:
107
.s W
3-5 r...r,.ncIvo O m
Q79 9eMq wCr.
I iJ*3
~.an
~
~.
[
!/cdel 68h - Thermal Ar.alysis
~S l
Type 3/17), Paragrachs 231, 232, IAEA safety series No. 6. 1973 This analysis is performed to deconstrate that the Model 68h Gaara Fay Pre-jector teets the specific Type 3(.U) thermal requiremants of paragraphs 231, a nd 232 of IAEA Safety Series Mc. 6,1973, i.e., that the eaximc= surface temperature does not exceed SocC in the shade, assumi g 38 C arbient temp-erature.
To assure cor.servatism, it is assumed that:
(1) the entire decsy heat (2 5 watts) is depcsited in the exterior faces of the Yodel 63h, (2) the intericr of the Model 68h is perfectly insulated, providing heat transfer frcm the vall only to the atr.csphere. The rectansular shape of the cen-tainer ssns that each face eclipses a different s=ount of the solid angle
-thrc :gh which the radiation f and thus decay heet) is distributed. To (conservstively) simplify, it is escured th ~c each of the six exterior faces rece ive s of the total source (0.63 vatts) uniformly distributed ever the face.
Ccesidering the srallest face as andergoing one-dicensional convective heat trsasfer:
T T
/
Interior (Insulated) q aAir
/
v
/
vall T
6 a
Ta Wher**
y hA T: temperature at the vall cuter surface y
q-
/ decay) heat scurce (0.63 vstts)
A:
surfsce area of the sr.allest face (0.C80 =2) h: free ccnvective heat transfer ccefficient for air 2O 5 watts'reter C (Feference:
"e s t Tra n s fe r, J. P. Ec1:en, k th Editien, p. 13)
Thus, the raxim m terperature at the vall T is kgcC (10h ?) under ncrral cen-y ditions cf transport. This satisfies the req;irements of the afcrene. tic:.ed regulations.
?d:VI5?C'i O 3-6
),2 }.,
,!J c.c.o. 2 i.r4.:
I
Model 684 - Therral Analysis Type 3(U), Paragraph 2h0, IAEA Safety Series :o. 6,1973 This analysis is perforced to detenstrate that the Fcdel 634 Ga:=a Bay Pro-jectcr =eets the specific Type 3(U) therral requirements of par 36raph 240, IAEA Saf aty Series 'To. 6,1973 This paragraph requires that the maximum surface temperuture of a Type 3(U) package not exceed 82cc (180cF) under ncr al conditions of transport, given insclatica as cutlined in Table III c
of the regulat ;ons and an ambient temperature cf 33c0 (100 7),
The calculaticnal odel used censists of taking a steady state he t balance a
ever the surface of the package. To facilitate calculations, certain sic-plifying assumptiens are made. These are cutlined belev:
-Ia sciatien 800 cal /c 2-12hr (h75W/=2) fcr the top surface, 200 cal /c=2-12hr (19LW/m )
fer the sides and side frates, none fcr the base as cutlined in Table III of IAEA Regulaticns.
The package is finished with russett enanel. The solar a'escrptivity cf this enstel is 0.81 (
Reference:
Thertal Radiaticn Procerties Survey, G. G. Cubareff et. al., 2nd ed., 1960, p. 200). A conservative figure of 0 90 was used as the package abscrptivity.
s
/
- 1 cay Heat Ecad The decay heat lead (=axt=um 2 5 watts) is assumed negligible.
~.
Package Crientation The package rests en the side franes, i.e.,
in the ner:al transport crientation.
Weat Transfer Mechanists Tha "cdel 63h is assured to undergo free ce nvection and to radiate to the envi----aa'
- be inside faces are considered to be insulated, so there is nc cenriucticn inte the package.
Further, the sides are taken to be thin encugh sc there are nc temperature gradients presant.
?adiaticn: The package is assured to radiate frcm the cuter shell caly 1.e., a cube 91 inches (230t=) x 11.1 inches (23Cr=) x 11 9 inches (300==).
This arsu=ptien provides for ccncervatism by not censidering any radiative heat less thrcugh the side frame.
Ccnvection, top: The u;;er surface cf the cuter sha *s taken to endergo free ccnvection. To crevide ecnservatis the upper surf aces 9
cf the side fra es are censilered nct to undergo ecnvecticn.
The heat transfer ccefficiant of a herincntal flat plate is given by:
A
,j) 3-T
) 2 }.,;
- -, ph ' g
.m.
E c.:?. ~ i..
3' d
y,
,w
ht 1 3-o_T_
=
L
(
Reference:
Heat Transfer, J. P. Holman, hth ed.,1976, p. 253) where L is the average of the lengths of the sides, 0.29c.
Thu.
1.ShT)0.25 h
=
g Ccnvection, sides: The vertical ec=ponents of the cuter shell are ccc-sidered tc exhibit free ccnvective heat tranaf ar.
Fcr conservatism, the s' de fra=es are taken to be insulated. Effectively, the vertical ecnvective heat transfer area is that of a vertical plate 0.23 high x 2(0.2E= + 0 3 m) 1 cts, convecting cn ene side cnly.
The heat transfer coefficient for a vertical flat plate is:
0.25 h = 1. c, 2 aT--
s L
(F<irence: Heat Transfer, J. P. Holman, hth ed., 1976, p. 253)
~
vhere L is the height of the plate, 0.23n.
Thus:
= 2.05(6T)'n' 2<'
h 3
~
a Taking a heat balance ever the package surface:
5 heat in = heat cut (rad. + con. top + conv. sides) 91n " 4 rad 9ct
- 9es 0 90 (775 W xAt
- 19h W XA) q
=
s in 2
22 0 90 (775 x 0.03h + 19h x 0 39) = 133 vatts
=
h r (m a) m A
9
= Ec v
rad
)(0.h3=")[h
-(311,s)b]
o h
0 Q
= (0.8) (5.6c9 x 10'"
W y
=
's' t t (a?)
q
=hA where60 = T
-T v
a ct
- 1' l 9 ) 'i
= (1.80 x (cT)0.25] (0.03L:") (CT) o 4
t "h A
'A T )
q 3 3 CS
- 2. C5 (A T )
0.97m2 (eT)
=
3-8 ESIM O c.c 0 /
,:-]
i m - %
y-e-.
--.----n
Iteraticn yields a wall te:aperature T of 68 C (154 F). Thus the Mcdel 68h i
satisfies the require:nents of paragraYh 2h0, IAEA Safety Series !ic. 6,1973 l2}i
.l,3 i
s 1
i i
3-9 RI VISIC M O SEP. 2 7 s?9
C.25 Inch 0.D. Scurce C3; sules - Thimal Analysis Hypothetical Fire Conditions This enelysis is intended to d=nenstrate that Tech / Ops source capsules which are of 0.25 inch (6.35mm) diameter, seal velded to a mininun penetration of 0.020 inch (0 51=), cade of Type 304 or 3CEL snainless steel containers under IAEA Safety Series No. 6, and licensed as special for:,1973, aisc teet the requirezents of paragraph 23 Series :ic. 6,1973, i.e., conteirrent under specified the=al test conditions.
t The actual conteircent '.essel for the radicactive esteria1 is the velded source capsule. These capsules are all G.25 inches (6.35cm) in dia.neter and less than 1 inch (25.L:=) in length.
ne internal volcre of the scree capsules contains only 5-id'un-192 cr
~ ecbalt-50 ne:al (as a solid) and air.
It is assured at the t'_
e of Icadin.g that the entrapped air in the capsule is at standard tetperatre and pressu e (2CcC, C.101 ?.:cgenevtons per scuare neter).
- ie contend that this is a ecnsertative assurption because, during the velding process the in-tarnal air is heated, causing sere of the air n'ss to escape befcre the cepsule is sealed. 7nen the velded capsule retu ns to achient terperatre, the ir.terno' r =ssure is socavhat reduced.
As. described in Tech /Cys standard source encapsulation procedre, the ninirun veld penetration is 0.020 inch (0 51:::).
'Jnder ecnditions of
~'S, internel pressure, the critical locatica fer failu e is this veld. Since the capsule has an outside diareter of 0.25 inch (6.35,r_), this veld has a cress-s:ctionel area of 0.014 square inches (9 3Mrl-).
No. 6 it is Under ponditicns of paracarh 238 of IAM Safety Series L
e.ssured that the capsule could reach a te peratu e of 1750F (cOCCC).
Using the ideal gas law and requiring the air to cecupy a constant vol= e:
oT o
-12
-2 m*1 initial prbssu e(0.10D2;/= )
p,
=
/o;;c s m
~_ <,,.. < a, %. y v
_e.*....
m.
4~
\\ s,
,1 -- )
sq s...L
.ww final temperature (lC93 k)
=
rp
^2
'~ne internal gas pressure eculd reach 0 3TSC/12 It is assu ed that the capsule can be treated as a thin-valled, cylindrical pressure vessel.
'O r.r-,I: w-- ~.A.O SEo 2 7 379 l
n '.
'f t
~~-
--~~-ee
.-m_,.m...
- m.,, w,,
~
. "ne raxirr,n Icr.gitudinal tensile stress can be calculatad by writir.g a
~
icngit dinal fcree balance thrcugh the weld:
stress x area ~ E#' S'#8 *
- O s
p
- 2) - P it D4
=0 2
2 S,TT (Lo - Di 4
7 where S, = loneitudinal stress outer disneter ( <* ?;cm)
D
=
O ir:er dianater ( 5 35c=)
D.4
=
2
- ressu
- e fC.37Z.3.r ).
?
=
'Thus, the longitt.dinal stress is 0,320X;/c2 The hoop st:ess can be fcund in a similer fashion.
Taking a icngitudinal cross-section and suncir.g forces:
=0 hccp szress x areag - pressure x areap 2c Lt - pD, L = 0
-n i
where s = bocp stress C
m L = length of cylind r t = thick ess of weld (0 512 m)
I~nus, the hcop stress is 1 93:.C;/m2 o
c At a tenterat're of 1600 ? (oTCcC) the yield strength of tyre 30h
/2 stainless steel is 10,000 psi ( 69.C.gi n )
Thus, the tresrae induced 0
stresses a:e less than 3fe of the yield strength et 800 C.
0$
fili (d$klQwL' i211 :i3 r
I Q, 11 h.1.. ). V. O
m y
- - - - ~ ~ ~
g-
,,7
.ce.
4.
,g
,,----g-.
s.
,h.
Conta inment m
h.1 Containment Foundary h l.1 Containment Vessel The ccntainment system for the Model 68h Ca==a Ray Projector is either Tech /0;s Model Ak2k-15 or Medel A424-20 Source Assembly. These source asse=blies are currently certified (IAEA Certificate of Competent Authority Nos. USA /0165/S, USA /015E/S) as special for: containment for radicact'.ve caterials.
The actual contain=ent vessel is the velded source capsule, style 6000h or style 60011. The capsules are made of Type 30h or 3OhL stainless steel.
They are seal velded with a minimum veld penetration of 0.020 in.
( 0 51== ).
The capsules are rcunded cylinders 0.25 inches (6.35=m) in disceter and 0 97 inches (25cm) or 0 96 inches (2h =) in ler.sth. Appropriate descriptive
_ drawings are enciesed in Section 2.10.
h.l.2 Coritainme'nt penetrations There are no penetrations of contain=ent. The source capsule is seal velded to provide confer =ity to special form requirements.
hol.3 Seals and 'Jelds The containrent vessel is tungsten inert gas velded. This is done in accordance vith Tech / Ops standard scurce encapsulation procedure (see Section 7.h).
The mini =un veld penetration is 0.020 inches (0 51==).
This has proved acceptable for licensing this vessel as special for=.
h,1.h Closure Nct, applicable.
k.2 Recuirerents for Nernal Ccnditions of Transport h.2.1 Release cf Radicactive yaterial The source assemblies used all rest the require ents of special form radicactive caterial as delineated in IAEA Safety Series No. 6,1973 and 10CFR71. Thus, there vill be no release of radicactive na:erials under conditions of nernal transport.
i j ',
4 h.2 3 Coclant Contarination
- g i.V Not applicable.
E-1 REVISICU O SEP. 2 7137L
...-r.
.s
~
1.2.4 Coolant Loss 4
IIot applicable.
h.3 contain-ent Recuirements for the Hypothetical Accident condition h.3.1 Fission cas M oducts
!!ct applicable.
L.3.2 Felease of Contents
' he h'rpethetical sceident conditlens as outlired in 10CFRT1, apper. dix 3, l.,
2., and 3. have been shewn (Eections 2.7.1. 2.7 2 and 3 5 respeett rely) to re-sult in no less of, pac' age contaircent.
4 g
4 ~/
}2ls'-
!l i
m i
E-2 3Ey7sio:: 7 SEP. 2 71579
.......r-y.._.
.... ~... _ -... - -.
... - ~ -
5 Shielding Evaluation 51 Discussion and Results The Model 684 is shielded with 150 pounds (68kg) of depleted uranium. The uranium =etal is cast around the zircalloy or titanium "S" tube which holds the source. The storage positicn for the source is at the inflection in the "S" tube.
Eadiaticn profiles of t'odel 6814 S.N. 229 containing 10.CCi of ecbalt-60 and Model 684 S.N.184 containing 2LCCi of iridiu=-192 were made.
Ex-trapolation to the rated capacity of the package produced the results shcvn in Table 5 1.
frc= this data, and frcm previous acceptability (IEC Certificate of Ccmpliance No. 9028, Rev. 2) it is concluded that the Model 634 complies with the regulator-y standards in ICCTRT and IAEA Safety Series
,:Ic. 6, 1973 TABLE 5 1 SUO!ARY Of MAXIMUM DOSE RATES
(=R/hr)
Contact At 1 Meter Side Top
?ottcm Side Top Ecttc=
Ga-,
165 176 187 2.2 2.8 2.8
!eutron I!ot Applicable Iiot Applicable Total 165 176 187 2.2 2.8 2.8 Hy;bthetical accident conditions vill result in essentially no change in the,above readings.
52 Scurce Specification 5 2.1 Gam a Scurce
-ne g?=a sources used are encapsulated ccbalt-60 in cuantities of. up to 11 curies, or iridiu=-192 in quantities up to EkC curies.
5 2.2
- eutrcn Scu ce IIct Applicable.
1,2 1 1
,.,i s 53 yodel Srecificationa
- ot Applicable.
5.h Shieldir4 Dialuation 5-1
- . v >.,., a
- ,)
SEP. 2 7 !979
s.
Yhe Model 6% shieldire evaluation was perfomed on Model 6% Serial
-s l
IT.=bers 229 and 1%. The radiation profile is included in section 5 5 This data clearly indicates t~ac the Model 6% confons to regulatory radiation limits.
As the hypothetical accident evaluation (Section 2.7) re-vealed no change in the shielding arrargement, it is concluded that shield-in6 after the hypothetical accident is essentially unchanged. Therefore, the radiation profile indicates the package vill be within acceptable limits.
2
- 1
]O
/
s a
s s
v 5-2 EEVISICN O cEP,2 7 979
~
f) 55 APFTGIX
- Model 68k: Radiation Profile I L I '1 iLJ 1 ') 1 1 7m
~ s i
4
/
~ ~)
5-3 3EV SICIT O SEP. 2 71379 ab-O
RADIATION FROFIL3 Model 654 Serial I:u=ber 229
'O Containing 10.0 Curies of Cobalt (AN PDR 2T-J) location At Contact At 1 I'eter Top 160 25 3ottcm 170 25
.tont lho 2.0
. Rear 140 2.0 vert 15 0 2.0 Right 50 1.0 Mcdel 684 Serial :!u=ber 134 Containing 240 Curies of 192 Iridium (AN/PER-27(J)SurveyMeter) 3
~
Top 19 0.2 Ecttem-1.2
's 0.2 Trent 1.0 C.2 o
Rear 1.0 O.2 Left 09 0.1 Right 09 0.1
- ICES: All intensities are expressed in units of tillircentgens per hcur.
Intensities given are the =aximum intensities on the ceasured side.
1211
'21 5-EVISION O SE?,2 71979
- - ' +
. rw w y... - *,
-...y....3,
,..w.
~.
6.
Criticality Evaluation N,
./
';ct applicable.
7' 1 2
- 1 t
L~
3 g
6-1 IiEVISICN O SEP. 2 71373 s*..
_?
.-- ~,,_.,,.
.,g,,
.w,
s T.
Ocerating Procedures D
/
7.1 Procedures for Icading the Fackage Section 7.4 descri.,es the procedure for fabricating the special for a source encapsulation. Section 7.4 also contains the procedure for leading this source assembly into the package and preparing the package for transpcrt.
7.2 Frecedures for Unicading the Package Section 7.h contains the procedure for unicading the source assembly from the package.
.73 R-eparation of an Emety ackage for Transport Section 7.4 describes the procedure for preparing an empty package for transport.
g, 1<
4 I
'i i c; 1
i 7-1 REVISION O SEP. 2 7 :979
.,. -.,..-.,,..;; g
,=g.-----__.7.
__, g7,,..
7.4 APPENDIX
- Encapsulation of Sealed Sources
- Technical Operations Mcdel 68h:
Procedures of Leading-Unicading the Package 3,.33
,7 iLI-ie.
N
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- e g...c. 914' O 7-2 a-SEP. 2 7 ii79
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vpu t.;-A LWWJ RADIATION SAFETY MANUAL 3
Part n In Flant Operations Section 2 ENCAPSULATION OF. SFJJE SOURCES A.
Persennel Recuirements Caly an individual qualified as a Senior Radiological Technician shall perform the operaticns associated with the encapsulation of 192 Iridium. There must be a second qualified Radiological Technician available in the building when these operations are being perferred.
3.
General R*ecuirements The 192 Iridium leading cell shall be used for the encapsulation of solid retallic 192 Iridium and the packaging of sealed sources such DO as ITCnulium,137 esium and 169?tterbium.
Solid =e.tallie Cobalt C
not exceeding cne curie may be handled in this cell also.
The maximum amount of 192 Iridium to be handled in this cell at any one time shall not exceed 1000 curies. The maxiru: amount of 13,fCs T
to be handled in this cell at any one time shall not exceed 100 curies.
i 1
d This cell is designed to be operated at less than etrospheric pressure. The exhaust b1cwer provided shall not be turned cff exeept when the cell is in a decentaminated conditicn.-
Sources'shall not be storsd in this cell cvernight cr when cell is unattended. Unencapsulated material shall be returned to the transfer containers and encapsulated sources transferred to approved scurce centainers.
When any of the "through-the-vall" tools such as the velding fixtu-e er transfer pigs are recoved, the openings are to be closed with the plugs provided.
"'hese tools shall be decentaminated whenever they are recov.
from the hot cell.
C.
Fre_raratory M ocedure l.
Check veldin6 firture, capsule drawer and manipulator fingers frcm cell and survey fcr ecntamination.' If ecntarination in excess of 0.001 ACi of renovable ecntasination is fcund, these iters rust be decentaminated.
2.
If the velding fixture or the electrodes have been changed, perform the encapsulation procedure caitting the insertion of any activity. Examine this dn y ca,cule by secticning th-u veld.'
Weld penetratica cust be not less then C.020 inch.
REVISION O T-3 1 2,i :
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If veld is sound and penetration is at least 0.020 inch, the preparation of active capsules may proceed.
If not, the a
T condition responsible for an unacceptable veld rust be corrected J
and the preparatory procedure repeated.
3 Check pressure differential across first absolute filter, as
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ceasured by the canc=eter on the lei side of the hot cell.
This is about } inch of water for a L iv filter. When this precsure differential rises to about 2 inches of water, the filter cust be changed.
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D.
Encapsulation Procedure 1.
Prior to use, asseiole and visually inspect the two capsule ecmponents to determine if veld zone exhibits any misalign=ent and/or separation.
refective capsules shall be rejected.
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2.
Eegrease capsule ec=ponents in the Ultrasonic 3ath, using isopropyl
- alechol as degreasing agent, for a period of 10 minutes. Dry the capsule components at lOCcC for a minimum of twenty minutes.
3 Insert capsule cc=pcnents into hot cell with the posting bar.
h.
Place capsule in veld positicning device.
5 Nove drawer of source transfer ccntainer into hot cell.
T
\\J 6.
Place proper arount of act.vity in capsule.
Disposable funnel rust be used with pellets and a brass rivet with vafers to prevent contamination of veld zone.
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, 7 Ferove unused radicactive raterial from the hot cell by with-drading the drawer of the source transfer container from the cell.
8.
Herove funnel or rivet.
9 Asse ble capsule ec penents.
- 10. Weld adhering to the folleving conditions:
a.
Electrode spacing.C21" to.C2k" centered on joint +.0C2"; use jig for this purpcse.
b.
Preflew argon, flush 10 seconds.
c.
Start 15 arps.
d.
Weld 15 a ps.
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Slope 15 amps.
f.
post fim 15 seccnds REVISION O 7-h SEP. 2 71N9
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11.
Visually inspect the weld. An acceptable veld cust be continuous without cratering, cracks or evidence of blow out.
If the weld is defective, the capsule cust be cleaned and revelded to acceptable conditions or disposed of as radicactive vaste.
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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 vetted with EDTA solution or equivalent.
- 14. Count the patch with the scaler counting system.
Fatch cust show no more '.han.005/ sci of centamination. If the patch shows more than.005/4Ci the capsule rust be cleaned and rewiped.
Iftherevipepatebstillshowsmorethan0.005ACiofcontamina-f tion, steps 8 through 11 must be repeated.
15 Vacuum bubble test the capsule.
Place t he velded aapsule in a glass vial containing isopropyl alechol. Apply a vacuum of 15 in Ky(Cauge). Any visual detection of bubbles vill indicate a leaking source.
If the scurce is determined to be leaking, place the scurce in a dry vacuum vial and boil off the residual elechol. Eeveld the capsule.
lo.
Transfer the capsule to the swaging fixture.
Insert the wire and connector assembly and svage.
Hydraulic pressure should not be less than 1250 nor = ore than 15 30 counds.
- 17. Apply the tensile test to assembly between tre capsule and
. connector by applying proof lead of 75 lbs.
zrtension under the lead shall not exceed 0.1 inch.
If the extension exceeds s
0.1 inch, the source cust be disposed of as radicactive waste.
- 18. position the source in the exit port of hot cell. Withdraw all personnel to the control area. Use remote centrol to
- idsert source in the ion cha ber and position the source for taximum response. Record the reter reading. Cccpute the activity in curies and fill cut a tempcrary source tag.
19 Using remote centrol, eject the source frca cell into scurce changer through the tube gauze wipe test fixture. Monitor before reentering the hot cell ares to be sure that the scurce-is in the scurce changer.
Remove the tuhe gauze ead count with scaler counting syster. This assay must she ne rcre than O.CC5j4C1.
If contamination is in excess of this level, the scurce is leaking and shall be rejected.
20.
Cceplete a Scurce Lcading Lcg (Figure II.2.1) for the cperation.
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EVISION o SCP. 2 7 IU9
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Technical Operations Model 664
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Frocedures for Loading - Unicading the Package
'4 ear personnel nonitorir.g devices during all scurce changing procedures. Mon-itor all operations with a calibrated, operable survey meter.
!Iote: All the precautions used when making radicgraphic exposures must be folleved.
1.
Survey the projector to ensure that the source is in the proper.
position.
2.
Locate the projector and source changer in a restricted area. lccate the devices so as to avoid sharp bends in the guide tube or control housing.,
The control cable housing bend radius should not be less than 36 inches (0.olkm), and the guide tube bend radius should not be less than 20 inches (0 508m).
3 Set the scuree changer fcr operation.
h.
Attach or.e end of a guide tube fitting to the fitting above the empty chanber in the source changer and the other end to the projector.
t 5
Attach the centrol cable to the projector:
a.
Unicek the projector with the key provided and. turn the c;nnector selector ring frem the LCCK position to the CCIE!ECT pcsttion. 7cen
,the ring is in the COT;ECT pcsition, the storage cover vill disen-gage frem the projector.
b.
Slide the control cable collar back and open the jaws of the svi-vel connector, expcsing the male portion of the connector.
Engage the male and female portions of the svt. vel ccnnector by depressing the spring leaded locking pin tcward the projector with the thumb-nail. Relesse the lockSig pin and tes; that the ccnnection has been made.
c.
Clcse the jaws of the control cable connector over the swivel type Connector.
d.
Slide the control cable ecllar ever the connector jaws. Hold the control cable collar flush against the projector connectcr and rotate the celector ring frc: the C07CTECT pcsition to the CFERATE pcsition.
6.
Crank the source into source changer.
a.
Survey this operation with a survey P.eter to be sure the source 3.) j j 7'
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> 'J REVISION O SEP. 2 7 :373
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has been transferred fro = projector to changer.
b.
With a survey meter verify radiation level does not exceed 200 nR/hr at the surface of the changer.
7 Disconnect the control cable frc= the source assembly. Disconnect the guide tube from the source chan6er. Secure.he source in the scurce changer.
8.
I? 753,aoJzcTOR rs To RanAI" :TarY :
a.
Fully retract the control cable.
Disengage the control cable frc=
the projector and lock the projector.
b.
Attach cne identification plate of the ccurce to the source changer.
.sffix a green "espty" tag to projector.
c.
d.
Perfort a >ipv test of the projector tc assure that the radiation observed is less than 0.001 microcuries per 100 square centineters.
Surtey f'e prcjec+.or tc assure that the radiation levels do not e.
exceed 200=R/hr at ;he surface nor IC R/hr at three feet frc= the.
surface.
f.
Mark the prcJector:
Radicactive - "LSA".
Affix the proper ship-
.ein: labels to the.ceckere.
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Cc plete the proper shipping papers as specified in Tech / Ops Radi-ation Safety Manual II.c.35(4), (5), (o).
A 9.
I? Zi3 7R0J301'OR -IS TO 33 PT_,0ADSD: connect the scurce char.ger end of the guide tube to the fitting above the new scurce in the source changer.
10.
Crank source to full retraction within the prcjector, a.
Survey this cperation with a survey reter to be sure the scurce has been transferred into the projector.
b.
With e sursey neter verify radiation '.e/el dces net exceed 200rr'tr at the surface of the projecter.
11.
Disconnect the ccatrol cable and lock the projector.
12.
Disconnect the scurce guide tube free the projector and scurce changer.
13 Affix the identification plate cf the new scurce to the projector and attach the identificat'on plate of the cid source to the scurce cha r.g e r.
lb.
Frepa re fcr shi; rant:
a.
Again survey prc.'ector to ("sure that thr. radietion la'tel ices nc 2 2
REVISIOIT O
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exceed 200rtr/hr at the surface of the projec. tor.
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b.
Survey the radiation level at a distance of three feet from the sur' ace of the projector. This radiation level should not exceed 10mr, hr.
The highest radiation level reasured at three feet frem the container is used to determine the Transport Index in accor-dance with 49CFRlT3 389(h).
c.
Affix the proper shipping la'cels.
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- 8.
Acceptance Tests and Maintenance Program s
T 8.1 Acceptance Tests 8.1.1 Visual Inspection The package is visually examined to assure that the appropriate fasteners are seal vired properly and that the packaEe is properly marked.
The seal veld of the radicactive source capsule is visually inspected for pro-per closure.
8.1.2 Structural and pressure Tests The svage coupling.between the source capsule and cable is subjected to a static tensile test with a lead of seventy-five pounds. Failure of this tcst vill pre-vent the source assembly from being used.
8.1 3 Leak Tests The radicactive source capsule (the primary containment) is vipe tested for leakage of radicactive contamination. The source capsule is subjected to a vacuum bubble leak test. The capsule is then subjected to a second vipe test for leakage of radicactive contamination. These tests are described in See-tion 7.4.
Failure of any of these tests vill prevent use of this source assembly.
s 8.1.h
'Cemponent Tests h
e The lock assembly of the package is tested to assure that the security of the source vill be maintained. Failure of this test will prevent use of the package until the lock assembly is ccrrected and retested.
8.1 5 Tests for Shielding Integrity The radiation levels at the surface cf the package and at three feet frca the surface are ressured using a srall detector survey instrurent (e.g., A:i/Fr?.-27).
These radiation levels, when extrapolated to the rated capacity of the package
-ust not exceed 200 millircentgens per hour at the surface ncr ten millircentgens per hcur at three feet from the surface of the package.
Failure of this test vill prevent use of the package.
8.1.6 Thermal Acceptance Tests q
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.';ct applicable.
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8.2 Maintenance hegma 8-1 REV!SION O SEP. 2 7 :979 r.
4 *. p 8.2.1 Structural and Pressure Tests i
Not applicable.
8.2.2 Iaak Tests As described in Section 8.1.3, the radicactive source assembly is leak tested at manufacture. Additionally, the source assembly is wipe tested for leakage of radicactive contamination every six conths.
8.2 3 Subsystem Maintenance The lock asse bly is tested as described in Section 8.1.h, prior to each cse of the package. Additionally, the package is inspected for tightness of fas-
'teners, proper seal vires and general condition prior to each use.
8.2.h
'~alves, Rupture Discs and Gaskets Not applicable.
8.2.5 Shielding Prior to each use, a radiation survey of the package is made to assure that the radiation levels do not exceed 200 millircentgens per hour at the surface nor ten millircentgens per hour at three feet from the surface.
s.,
8.2.6 Thermal I*ot applicable.
8.2.7
'iiscellaneous Inspections and tests designed far secondary users cf this package under the general license provisions of 1CCFR71.12(b) are ineluded in Section 7.h.
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