ML19291B116

Requests Renewal of Certificate of Compliance 9021 Issued for Technical Operations Manual B Package.Forwards Package Description & Renewal Fee

ML19291B116
Person / Time
Site:	07109021
Issue date:	07/25/1979
From:	Munra J TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 7908290422
Download: ML19291B116 (59)

Text

• TechrOps

]-}Q) g Aaoat>on Products Omsson do North Avenue Burnngton, Massachusetts 01803 Teies:none (617) 272 2000 25 July 197o O'

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Mr. Charles 3. MacDocald, Chief g

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Transportation Branch c

Division of Fuel Cycle and Material Safety 3g,..o',

[Q-United States Nuclear Regulatory C H ssicn 7.

Washington, DC 2 3 55

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7 Eear Mr. MacDonald:

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We request renewal of USNRC Certificate of Ccmpliance No. 9021 issued for Technical Operations Model 750 Type B Package. In accordance with your letter of 6 June 1979, eight copies of a censolidated application fer this package are enclosed. In accordance with 1CCFRlTO.31, Item 11.3, ve are also enclosing a check for $150 for the renewal fee.

We are si=ultaneously applying to the U.S. Department of Transportation for an International Atcmic Energy Agency Certificate of Ccmpetent Authority issued under the 1973 Revised Edition of IAEA Safety Series No. 6 for Type 3(U) packaging.

We trust that this application satisfies your requirenents for renewal of this certificate. As this certificate expires on 30 September 1979, we ask that you act upcn our application as scon as is practicable.

We thank you for your cooperation.

Since;ely,

/

• hn J. Munro III dehnical Director JJM/fb Encls.

xc:

R. R. Rawl, USDOT 7908290 N 18622 2012

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Tech / Ops Ascation Products Division 40 Noct Avenue Bursngton, Massachusetts 01803 Teiephone (617) 272-2000 PACKAGE DESCRI?rION TECICTICAL OPERATIONS MODEL 750 USA /9021/3 201 G2

1.

General Infor=ation 1.1 Intrc*uction The Tech / Ops Mcdel 750 is designed for use as a scurce changer and shipping container for Type 3 quantities of radicactive =aterial in special for=.

The Model 750 confer =s to the criteria for Type 3 packaging in acccrdance with 10CFR71 and satisfies the criteria for Type 3(U) packaging in accor-dance with IAEA Safety Series No. 6 1973 The scurces to be used in conjunction with Model 750 are Techf0ps sealed scurce Models No. 63309 and No. Ak24-20. The Model 750 vill contain a maxi =u= of 2h0 curies of

' ridiu=-192 as special for=.

i 1.2 psekage rescription 1.2.1 packaging The Model 750 is 17.16 inches (h3,6==) high,10 inches (25h==) icng, and 8.25 inches (210==) wide in overall di=ension. The grcss weight cf the package is 70 pounds (3Ek' ).

The radicactive scurce asse=bly is hcused g

in a titaniu= "U" tube. The tube is cri= ped in the =iddle of the "U" to prcvide a positive stop for the scurce asse=bly. The "U" tube is cast inside a depleted uraniu= shield asse=bly. The weight of the uraniu:

shield is 35 pcunds (16kg).

The shield asse=bly is enclosed in a steel bcttc= housing consisting cf a rectangular shell and top and bettc= ccver plates of 0.135 inch (3 4==)

thick cold rolled steel. The rectangular steel shell is further enciesed in a rcund steel tube with a vall thickness of 0.Ch7 inch (1.2==).

The void s;nce batvecn the shield and the shells is filled with a castable rigid polyurethane fea=.

The steel-uranium interface is separated with a 0.010 inch (0.25k==) thick copper shi=.

Mounted on the top cover plate is a Iceking asse=bly. This asse=bly is used to secure the radicactive scurce in a shielded position during transport.

An cuter package lid, fabricated frc= 0.135 inch (3.h==) thick cold rolled steel,is bolted to the package to provide protecticn to the locking assenbly.

Ta=per-prccf seals are provided during ship =ent of these scurces. Tvc vent holes and assembly joints which are not leak tight previde passageways fer the escape of any gas generated frc= decc=pesiticn of the pctting fca: in the event the source changer is involved in a fire accident. The cuter packaging is designed to avoid the collection and retention of water.

-The package is painted and finished to prcvide for easy decen' a=inatien.

The radicactive =aterial is sealed inside a stainless steel scurce capsule.

The capsule acts as the centain=ent vessel fcr the radicactive =aterial.

2012 2

n r.Y.o.v11m0 2,

JUL. 2 7 :373

The Model 750 has been previously approved for use as a Type B package under USIBC Certificate of Cc=pliance No. 9021, Rev. 4 (Secticn 13).

It differs fret Tech / Ops Model 650 only by a change in the lock asse=bly and a different package lid. The Mcdel 650 was approved for use as a Type 3 package under US!GC Certificate of Cc=pliance No. 9032, Rev. 1.

Drawings of the Models 650 and 750 are enclosed in Section 13

• 1.2.2 Oceraticnal Features The source asse=bly is secured in the proper stcrage pcsition by means of the lock assembly. With the source in the stcrage position, the "Teleflex" cable portien of the scurce asse=bly is located inside the scurce changer fitting. The lock plate is engaged to secure the cable in place. Operation of the lock requires the use of a special key.

Ts=per-proof seals are provided 'during shiptent.

1.2 3 Contents of Package The Mcdel 750 is designed for the transport of Iridiu=-192 in quantities of up to 240 curies as Tech / Ops source assemblies Models No. 68309 and Ah2h-20. The Iridiu=-192 is in special for= ss prescribed in 1CCFR71 and IAEA Safety Series Nc. 6, 1973 (Section 2.8) 1-2 BE'R510N O JUL 2 71979 20.nz

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13 AFFENDIX USNRC Certificate of Compliance 9021 Rev. 4 Descriptive Asse=bly Drawing, Model 750 Descriptive Assembly Drawing, Model 650 3fn n

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roim *.aC418 U S. NUCt E AR A E Gul AT CR Y Co P.",*iSSirse o2 31 CERTIFICATE OF COMPLI ANCE

,g c p 73 For Aadioactive Maierials Pachapes 0

1.f al Certif.cate Number,

1.(b) Revision No.

1.(c) Pack age toentircs e. No.'

1.(d ) Pages No. 1.le) Total No. P 4

USA /9021/B( )

1 3

9021

2. PRE AMBLE 2.(a)

This certificate is inued to satisf y Sections 173.393a.173.394,173.395, are 172 rs of tw Ceoanment of T<ansportation haza.

Materials Regulations f 49 CFR 170-189 and 14 CFR 103) and Sections 146-11-1t are 146--19-100 of the Cep.anment of Transportation Dangerous Cargoes Regulations (46 CF R 146-149). as amended.

2.fb)

The packag;ng and contents described in itens 5 below, meets the safety staadaros set forth in Sueoart C of Title 10. Code of Federal Aegulations, Part 71, "Packageng of Padioactive Materials for Transpon ard Tsansportat on of Radioactivt Vaterial urde Certain Conditions."

2.fc)

This certificate does not relieve tne consignor from cornpliance with any recuisern of the regulations of the U.S. Oeoanment o-Transportatson or other applicable regulatory agencies, including the government as si, country t.nrough or into wh.ch the packs:

will be transported.

3. This cartificane is issued on the basis of a saf ety analysis report of tne pecuage desegn or a# ras ca-3.(a)

Prepared by (Name and adoren#

3.(b)

Title and identircation of scrort or apolicaten:

Technical Operations, Inc.

Technical Operations, Inc. application date Northwest Industrial Park 3 June 1974, as supplemented.

Burlington, Massachusetts 01803 3.tc)

Dock et No.

71-9021 4.

CCNDITioNS This certif.cate is conditional upon the fulfilling of the recuisemeaits of Sube art o of 10 CF A 71, as acclicable, and the conditions s:ecti.

in item 5 below.

5.

Oescript.on of Packaging and Authoraed Contents. Model Number, Fissde Class. Other Corsfi:=,es. are Rete,ences:

(a) Packaging e

(1 ) Model fiumber:

750 (2)

Description A portable container which utilin s depleted uranium for shielding.

The depleted uranium srhiel. ding sur rounds a titanium "U" tube which is crimped at the middle of the "U'.

The tianium source tube is reinforced with a titanium slee 'e (2 inches long) located on the upper ends of the "U" tW wM.re the source tube leaves the uranium.

The shielding and the "U" tube are encased in a steel bottom housing.

The space between the' shielding and the bottom steel housing is potted with a polyurethane foam.

During transport, the contents are securely positioned in the source _ tube by the source drive cable locking device. ~ An outer steel top cover is bol ted to the bottm steel housing to provide protection to the locking device ar.d containment of the coiled drive cable.

Tamper-proof seals are provided on the package.

Shipping weight is 70 pounds.

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1h MVISICN O JUL.2 7 E

.Page 2 - Certificate No. 9021 - Revision No. 4 - Docket No. 71-9021 h

5.

(a) Packaging (continued)

(3)

Drawings The packaging is constructed in accordance with the following Technical Operations, Inc. Drawings Nos.:

0 65000-1, Rev. A D 75000-1, Rev. B C 65000-2, Rev. A B 75001-2 C 65000-4 B 75001-3 C 65000-5 B 75001-4 C 65000-6 B 75001-5 C 65000-7 B 75003 0 75000, Rev. A (b) Contents

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(1 ) Type and form of material Iridiumi92assealedsourceswhichmeetthe requirements of special form as defined in 5 71.4(o) of 10 CFR Part 71.

(2) Maximum quantity of material per package 240 Cur'ies 6.

The source shall be secured in the shielded position of the packaging by the source assembly.

The source assembly must be fabricated of materials capable of resisting a 1475"F fire environ-ment for one-half hour and maintaining their~ pos-itioning function.

The cable of the source assembly must engage the lock retainer clip.

The flexible cable of the source assembly must be of sufficient length and diameter to provide positive positioning of the source at the crimp of the "U" tube.

7.

The name plate shall be fabricated of materials capable of resisting thc fire test of 10 CFR Part 71 and maintaining their legibility.

8.

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:

September 30, 1979.

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2012 ?'1 1-5 EVI5:CN O JUL 2 7 b a

Page 3 - Certificate No. 9021 - Revision No. 4 - Docket No. 71-9021 b

t, REFERENCES Technical Operations, Inc. application dated June 3,1974.

Supplements dated: August 14, 1974; and April 2 and September 8,1976.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION Y

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Charles E. MacDonald, Chief '

Transportation Branch Division of Fuel Cycle and Ma cerial Safety U8 2 3 577 Date:

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Stractural Evaluation 7

2.1 StruMural Iesi.:n t

2.1.1 Discussie Structurally the Model 750 censists of four cc=ponents: A source capsule, shield asse=bly, cuter casing, and lock assembly. The source capsule is i

the primary containment vessel.

It =eets the require =ents of special for= ::entain=ent as outlined in 10CFRTl (see Section 2.8).

The shield asse=bly fulfills two f2nctions: It provides shielding for the radicac-

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tive =aterial and, together with the lock asse=bly, insures proper positioning cf the source. The outer casing is a double thickness of steel, 0.047 inch (1.19==) outer, 0.1345 inch (3.k2==) inner, in the side directions and single thickness (0.1345 inch, 3 42==) in the top and bettc= directions. Attached to the top cover is a lid cf 0.13h5 r

inch steel. The es, sing provides the structural strength of the package.

The ca. sing joints are butt joints. The top lid protects the lock asse=bly.

The lock asse=hly secure the scurce asse=bly in the shielded positien at the cri=p in the "U" tube, and assures positive closure.

2.1.2 Design CriterLn The Model 750 is designed to ec= ply with the require =ents of ICCFRTl and IAEA Safety Series No. 6,1973 The device is si=ple in design, such that there are no design criteria which cannot be evaluated by straight-forward application of the appropriate section of ICCFR71 or IAZA Regula-tiens.

2.2

'4 eights and Centers of Gravity The Model 750 Source Changer weighs 70 pounds (31.8kg). The shield asse=bly contains 35 pounds (15 9kg) of depleted uranium. The center of gravity was located experimentally 5 inches (127:=) frc= the bottc= of the package along the cylindrical axis.

23 Mechanical procerties cf Materials The Model 750 Scurce Changer casing is cold rolled steel. This =aterial 2

has a yield strength of h0,000 pounds per square inch (270 ;ct/m )

(

Reference:

Machinery's Handbeck, 20th edition,1976, page h52. )

The radicactive sources to be used with the Model 750 are Tech / Ops 6330o Scurce Asse=bly and Tech / Ops Ak2h-20 Scu-ce Asse=bly.

Drawings of these source asse=blies are enclosed in Section 2.10.

Both assemblies censist of a Type 30h or a Type 3thL stainless steel espsule to which is svaged a "Teleflex" steel drive cable. The capsules are sealed by tungsten

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inert gas velding and the svage joints are tensile tested en a ; reduction basis to 75 pcunds. -

2.h General Standards for All packsces E/ISION O 2-1 JUL 2 71979 2012 27'

2.k.1 Chemical and Galvanic Reactions The =aterials used in the ccnstruction of the Model 750 Scurce Changer are uranium =etal, steel, titanium, bronze, and copper. The copper is used as a shim to separate the steel-uranium interfaces. Thus, the re vill be no significant chemical er galvanic action between any of these components.

Nonetheless, the possibility of the phenc=ena of the femation of the eutectic alloy of iron uranium at temperatures belev the melting tempera-tures of the individual =etals was censidered. The iron uranium eutectic 0

alley temperature is approxi=ately 1337 F (725 C).

Ecvever, vacuum conditions and extre=e cleanliness of the surfaces are necessary to produce the alley at this icv temperature. Due to the conditions under which the shields are mounted, sufficient contact for this effect dces not exist.

In support of this cenclusion, the follevir4 test results are presented.

A ther=al test of a sample of bare depleted uraniu= =etal was perfer=ed by Nuclear Metals, Inc., The test indicated that the uranium sample cxidized such that the radial dimension was reduced by 1/32 inch. A subsequent test was perfer=ed in which a sample of bare, depleted u-anium

=etal was placed on a steel plate and subjected to the ther=al test ecnditions.

"he test shewed no alleying or =elting characteristics in the sample, and the degree of oxidation was the same as evidenced in the first test. A copy of the test report appears in Sectinn 2.10.

2.h.2 Nsitive C1csure The Medel 750 source cannot be expcsed withcut opening a key-operated icek.

Access to the lock r7 quires the re= oval of the top lid. The lid is seal vired and provided with a tamperproof seal. The top and bottem covers are lock vired to insure that the retaining bolts are not accidentally locsened.

2.h.3 Lifting Devices The Model 750 is designed to be lifted by the bettem or top ccvers er top lid. Each is secured by fcur 5/16 hex bolts (the bettc= and top cover bolts are safety wired). Each bolt has a cross-secticnal ares of 0.0500 in2 ( 32 3==2).

The yield strength of the =aterial is 40,000 pcunds per square inch. Thus, each bolt can support apprcxi=ately 2,000 pounds (909kg),

or apprcximately 30 times the package weight.

~41th the lid off, the Medel 750 cculd possibly be lifted by the extended Jeleflex drive cable. To insure the integrity of,the package under this circumstance, a tensile test of the drive cable / lock assembly was perfcmed.

A veight of 275 pcunds (125kg) vas suspended frcm the Teleflex drive cable.

There was no adverse affect on the package. A copy of the test re;crt is enclosed in Secticn 2.10.

REV.SION O JUL 2 7 m,

2-2 2012 777

2.4.4 Tiedevn Devices The tiedevn devices on the Model 750 are the top and bottcm ecvers. As indicated in (2.4 3) above, the bolts attacting these devices can each suppcrt approxi=ately 30 ti=es the package weight.

25 standards for Type B and Large cuantity Packages 251 Lead Resistance Considering the package as a si=ple beam supported on both ends with a uniform load of 5 ti=es the package weight evanly distributed along its length, the maximum stress can be ecmputed frcm:

F1 S

=

5 where :

S: =axi=um stress F: tota;1, lead (350 pcunds) 1: Length of beam (17 2 inches).

3 Z:

section =odulus of beam (2.05 in )

(

Reference:

Machinery's Handbcok, 20th ed.,1976, phh2)

The load is taken to be 350 pcunds (159kg). The container is assu=ed to be a cylindrical tube 17 2 inches (436=m) long vith a vall thickness cf 0.047 in. (1.19=m) and inside di reter of 7.hh inches oms). The section

=cdulus is ccmputed to be 2.05 cubic inches (3 36 x 10{- ).

Thus, the =ax*=um stress generated in the Seam is 367 pcunds per square S

in.(25.8kg/cm ), which is far belev the yield strength of the =aterial.

252 acternal Pressure The Model 750 is open to the at=csphere; thus, t:here vill be no differen-tial pressure acting en it.

The collapsing pressure of the scurce capsules can be found:

86,670 t - 1386

?

D where:

P:

collapsing pressure M pcunds per square inch t: vall thickness in inches (0.020 inch)

D: Outside diaEetar in inches (0.25 inch) 07G I

(

Reference:

Machinerf's Hanrecck, 2Cth ed., p.Lh8)

EEVISion o 2-3 JUL '2 7 1 s. 2

_m

The collapsi g pressure of the capsules is calculated to be 5,550 pcunds per square inch (39Ckg/c=2). Therefore, the capsule can withstand an eaternal pressure of 25 psig.

2.6 Normal Conditions of Transport 2.6.1 Heat i

The ther=al evaluation is perfor:ed in Chapter 3 of this application.

• Frcm this evaluation, it can be concluded that the Medel 750 can with-stand the nor=al heat transport conditiens.

2.6.2 Cold The =etals used in the manufacture of the Nbdel 750 can all withstand c

0 temperatures of -ho ? ( h0 C). The lever operating limit of the polyurethane fea= is -100 F ( -73 C). Thus, it is concluded that the C

Model 750 vill withstand the normal transport cold conditions.

2.6 3 Pressure

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The Model 750 is open to the at=osphere; thus, there vill be no differen-tial pressure acting en it.

In Section 3 5 4, the scurce capsules are demonstrated to be able to withstand an external pressure reduction cf 0 5 at=cspheres (0 5kg/c=2),

2.6.h Vibration The Model 750 has been in use fcur years.

During that time there have been no vibrational failures repcrted. In addition, the Tech / Ops Model 650 has been in use ten years. The Model 750 differs frc= the Medel 650 cnly in the source iccking device and cover asse=bly. There has never been a vibrational failure of the Model 650 repcrted.

Thus, we contend the Mcdel 750 vill not undergo a vibrational failure in transport.

2.6 5

'Jater Sersy Test The water spray test was not actually perfor=ed en the Model 750.

'4e contend that the =aterials used in construction of the.stdel 750 are all highly water resistant and that exposure to vater vill nct reduce the shielding or affect the structural integrity of the package.

no n 201n4 2-h EU:175! CUM C)

JUL 2 7 m;g e ea m.e s w. m m-mm-o k

2.6.6 Free Droo The drop analysis perfomed in Hypothetical Accident Cenditions (See Section 2 71) is sufficient to satis 3 the requirements cutlined for the nomal transpcrt free drop condition in 10CFR71 and IAEA Safety Series No. 6, 1973 On this baais, we conclude that the Model 750 can withstand the free drop without i=paiment of the shielding or packa6e integrity.

2.6.7 Corner Drop

- '.Not Applicable 2.6.8 Penetraticn.

A penetration test of the Model 750 was perfer=ed. There was no less of shielding er structural integrity folleving the penetration test. A ccpy of the test report appears in Section 2.10.

2.6.9 Cc=cression The gross weight of the Model 750 is 70 pounds (31.8ks). The maxi =u=

cross-secticnal area is 172 square 1.nches (0.111=2). Thus, five ti=es the weight (350 lbs.,159kg) is greater than 2 pounds per square inch ti=es the cross-sectional area (344 lbs.,15Ckg). For this analysis, the Ic2d vill be taken to be 350 pcunds.

The maxi =u= stress generated in a flat rectangular steel plate with all edges fixed and a unifemly distributed load over the surface of the plate can be ec=puted frc=:

0 5F S

=

E~

t2 ~l 0.623 /1

+

,5

\\ v).

where: S:

=axi=u= stress F:

total load = 350 pounds t:

thickness of plate = 0.1345 inches v: viith of plate = 8.3 inches 1: 1ergth of plate = 10 inches

- (

Reference:

Machinery's Handbeck, 20th Edition,. p. 4h4, Eq.13)

Frc= this relationship,, the =axi=:.nn stress generated in the plate ic 34h6 pcunds,'er square inct (2hlkg/c=2). This figure is greatly belev the 2-5 m3 cy o 2012

a. 2

n

yield strength of the =aterial, h0,000 pounds per square inch. Thus, it can be concluded that co=pression vill not adversely affect the package.

27 Hypothetical Accident Conditions 271 Free Drop The Model 750 was not actually subjected to the drop test. Ecvever, the Model 750 differe from the Model 650 only -in the source locking device and the gec=etrical configuration of the steel cover (Section 1.2.1).

Drawings are enclosed in Section 13 The Model 650 was drop tested through a distance of 30 feet onto a steel plate. The container was fcund to experience no loss of shieldin6 or integrity as a result of this test. The test report is enelescd in Section 2.10.

Based on the similarity of the Model 750 to the Model 650, ve conclude that the Model 750 can withstand-the Free Drop Condition.

272 Functure ~

~ ~'

The Model 750 Scurce Changer was not actually submitted to the puncture test. Ecwever, as noted in Section 1.2.1, the Model 750 differs from the Model 650 only in the source locking device and the gec=etrical configuratica of the steel cover. The Model 650 was subjected to the puncture test of 1CCFR71. A copy of the test report is enclosed in 2.10.

The ability of the Model 650 to successfully withstand this test enables cne to conclude that the Model 750 can withstand the puncture conditions of the hypothetical accident.

2.T.3 Ther=al The themal analysis is presented in Section 3 5 There it is shown that the =elting point of the materials, except the potting ec= pound,0 used in the construction of the Model 750 are all greater than ikT5 F (8cc C). Also indicated is the previcus acceptability of this design o

(NRC Certificate of Cc=pliance No.

9021 Rev. 4) using this evaluation.

To de=cnstrate that the rsdicactive source asse=bly vill re=ain in a shielded position follevin6 the hypothetical the=al accident, the folleving analysis is presented. At the conclusien of the the =al test, it is assumed that the polyurethane fes= has ec=pletely esesped frc= the container. The shield asse=bly is restricted fren rotational =cve=ent

, by the titanium U" tube which protrudes through the top of the tottc=

section of the container. Hence, the only freedc= of =ove=ent available to the shield is vertically tcvard the lock holddewn asse=bly.

2-6 REVISION O Jut,a,..,

2012

.,nq-

Thus, it is concluded that the Model 750 satisfactorily meets the require =ents for the hypothetical accident-the=al evaluation as set forth in 10CFRT1.

2.7.4

'Jater I==ersion Not applicable.

2.75 S m ary of Da= age The tests designed to induce mechanical stress (drop, puncture) caused

.. =inor defor ation, but no reduction in the safety features of the package.

The ther=al test resulted in no reduction of the safety of the ptekage.

A special tensile test, designed to determine the ability of the lock

=echanis=/Teleflex cable to support the weight of the package, also resulted in no reduction of the safety features of the pcekage.

(Test report is enclosed in Section 2.10).

It can be concluded that the hypothetical accident cendit'cus have no adverse effect on the shieldin6 effectiveness and structural integrity of the package.

2.8 Special For:

The Mcdel 750 Scurce Changer is designed for use with e'ther Tech / Ops scurce asse=bly 68309 or Tech / Ops scurce assembly Ak24-20. Both of these source assemblies have been previcusly certified as special fem radicactive =aterials (IAEA Certificate of Cc=petent Authcrity No.

USA /0154/S, see Section 2.10) under IAEA Safety Series No. 6,1973

'Je contend that these certificates are sufficient evidence that the require-

=ents for special form radicactive =aterials, as established in IAEA Safety Series No. 6, Rev. 1973, are satisfied.

29 Fuel Reds Not Applicable EEVI5 ION O JUL 2 ~ $9 2012 ? "

2.10 AFFENDIX

- Nuclear Metals, Inc., Test Report: Iron Uranium A11cying

- Test Report: Teleflex Cable Tensile Test

- Test Report: Penetration Test, Model T50

- Test Report: Puncture and Drop Tests, Model 650

- Descriptive Assembly Drawings, Source Assemblies Models 68309 and No. A424-20

- IAEA Certificate of Ccmpetent Authority No. U3A/0154/S O

a 2012 ??'

REVISICN O 2-S

.27133

d.

1 ;

N U C L E A lt M E T A L S, I N C.

O TO

- tFP unita $1 f4C f f CONCono unssace'USETTS 04742

.....,...~,.......-

..o 253 January 1974

~

h q

Technical Operations, Inc.

Radiation Products Division Snuth Avenue

~

Burlington, Massachusetts 01803 Attention:

Mr. J. Lima Gentlemen:

In respunse to a request by Joe Lima of Tech Ops, a simulated fire test was performed on samples of bare denleted uranium in contact with mild steel, the object being to detennine what, if any, alloying or melting

~ would occur under thes~e conditinns.

TEST DATA:

O A 3/4-inch diameter x 5/8-inch lonq bare denleted uranium specimen was set on a 1-inch diameter x l/8-inch thich miid steel plate, placed in a 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 cool under a ventilated hood.

RESULTS:

l'o reaction was evidenced between the two metals.

Both separated readily and showed no alloying or melting characteristics.

Oxidation of the uranium was about the same degree as that reported to Joe Lima on an earlier experiment.

The-test was perfonned by NMI on 25 January 1974.

Very truly your.s,

m k'Au' 3

.~

u John G. Pcwers Project Engineer Og EVISION O 2 -

y,

• 2 012 7

~aut. 2 71922

-u

- " -7.w _.'%:-wg?::s G: ?.;:. ~

9#7iE

. 1 w g, w -c m.g.y:

== r- -3 1-m e.,,.p.m.m. gng m.:.;

.

s --.

5e..-

.2 w

.:... a..- x -m.

TEST REPORT TENSILE TEST: MODE L 750 LOCK ASSEMBLY -

OESCRIPTlON:

DATE 2 August 1974 A Tensile Test was performe:.1 on th~e Model 750 Lock Mechaniam/

Telenex Wire Assembly.

The Telencx wire was locked into the Model 750 Lock Mechanism, Drawing D' 6001.

The TeleGex Wire was suspended over-

- head, and a load of 275 pounds was suspended from the lock mechanism.

CONCLUSION:

M No damage occurred to either the TeleGex wire or the Model 750 lock aa sembly.

~

fN <<,,/

l M4 W I T N E S S ED B Y ' d'% /

~

W*

J

, hn J. Munro llI

~ BY Arthur'I Proulx o

U

':s

. 3

• wn510N O 2 - 10 JUL 2 71979 2012

.,g, w

a m v e.w e =. a..

W.,

m... -.:s v a m e m w m,._a.;. n s - ~.,'?.' m m*;c.c m

=.

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L:wre. -b e1.. 1.: * :.P-

TEST REPORT RADIATION FF0DUC"'S DIVISION 3Y:

David Marcilli DATE:

7 June 1979

SUBJECT:

750 Penetration Test On 7 June 1979, a penetration test in accordance with 10CFRT1, Appendix A, Paragraph 8 and IAEA Safety Series No. 6,1973, Paragraphs 71h(a) and 71h(b), was performed on a Tech / Ops Model 750 Source Changer, Serial Nu=ber 273 The most vulnerable location was dee=ed to be the vide side of the top cover, at a position shefe the lock =echanis= vould experience maximum shear if penetration occurred. The drop was done twice.

1.

The hemispherical end of a vertical steel cylinder 1[

inches in dia:eter, veighing la pounds, was dropped from a height of hl inches onto the location specified.

The resultant damage was an indentation apprcximately 1 inch in diaceter and less than } inch deep. There was no dacage which would affect the shielding or structural integrity of the projector.

2.

"he test in step (1) was repeated at approximately the same 1ccation. Ancther small, indentation (approximately 1 inch diameter by less than t inch deep) was made within 2 inches of the first.

The resultant da= age in no way affected the shielding er structural integrity of the package.

Perforred by:

k'itnessed by:

icm EcoltW,a\\ k.

cw E / & '

David Jar:Illi 2-11 EVISICN O JUL 2 7 :379 an7 201,2

u d

_2 TEST REPORT DESCRIPTION:

DATE 9-4-G9 Shipping Container Model No. G50 Drop Test 1.

The shipping container was dropped from a height of 30 ft. with the cover a) and a dummy source instalW hose plate, and bent it over.

The first drop landed in the corner of ihe' b)

The second drop landed on the cover and distorted it.

There was no dam-age in either dre; to the body of the c on> air.e:. The dummy source and cover were both removeable.

2.

a)

The container was drooped frem'a height of 40 inches onto a steel bar of G inch radius and 10 i_nches in length. It was dropped so as to land on the body of the container.

The only apparent damage was a slight dent in the body. The dummy source and cover were both removeable and there was no apparent damage to the uranium shield.

CONCLUSION:

b

~

ELY _

s.

s.

.- w. -

V'! TNESS ED BY b

.C

~

EVISION O JUL.2 7 1973 2012

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RESEARCH AND SPE CI AL PROGRAMS A D MINISTR ATION

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IAEA CERTIFICATE OF COMPETENT AUTHORITY

.....e Soecial Foru Radioactive Material Encaosulation

,y u yo.

Certificate Number USA /0154/S This certifies that the encapsulated sources, as described, when 1caded with the authorized radioactive contents, have been demon-strated to meet the regul'atory requirements for spegial form radicactive material as prescribed in IAEAl and USA regulations for the transport of radicactive materials.

I.

Source Description - The sources described by this certificate I

are identified as the Technical Operations, Inc., Models which are described and constructed as follows:

Model No.

Caosule Style Approximate Size (in inches, diameter x length)

A424-1 B60001 or B60004

.25 x.97 A424-6 B60001 or B60004

.25 x.97 A424-9 B60001 or B60004

.25 x.97

(

4424-20 B60001 or B60004

.25 x.97 58101 360006 Pellet, Wafer or Large Wafer

.25 x.90 s 8309 C68310 Pellet or Wafer

.25 x.78 A31401 B60001 or B60004

.25 x.97 B69701 B60001 or B60004

.25 x.97 All capsules are constructed.of either 304 or 3041 stainless steel and co form with the following design drawings:

Caosule Stvle Drawing Namber B60001 B60001 - 1 Rev. E and - 2 Rev. F B60004 B60001 - 1 Rev. E and B60004 - 1 Rev. D B60006 Fellet 360006

.1 Rev. E and B60001 - 2 Rev. F B60006 Wafer B60006 - 1 Rev. E and B60004 - 1 Rev. D 360006 Large Wa fer B60006 - 2 and 360001 - 2 Rev. F C68310 Fell et C66310 Rev. B and B68310-3

..C68310 Wafer C68310 Rev. B II.

Radicactive Contents - The authorized radicactive contents of thwse sources consist of not more than he following amounts of Iridium-192 as solid metal:

U EVISION O

~~

2-18 JUL 2 7 A 2 ? "

E e ;q:= w.r. m < m w a m mr v m ?+ v e m m w "

r Certificate Number USA /0154/S Tage 2 o

Model No.

Contents (Curies) h A424-1 120 A424-6 120 A424-9 120 A424-20 240 A58101 240 A68309 120 A81401 120 B69701 120 III.

This certificate, unless renewed, expires December 31, 1981.

This certificate is issued in acecrdance with paragraph 803 of the IAF.A RegulationsI, and in respcnse to the November 3, 1978, petition by Technical Operations, Inc., Burlington, Massachusetts, and in consideration of the associated information therein.

Certified by:

J0L x som 151978 R. R. Rawl, Heaith ' Physicist (Date)

U.

S. Department of Transportation Office of Hazardous Materials Regulation

'a'a s h i n g t o n, D. C.

20590.

~

I" Safety Series No. 6, Regulations for the Safe Transport of Radioactive. Materials, 1973 Revised Edition", published by the International Atomic Energy Agency (IA.EA), Vienna, Austria.

9

~

' Title 49, Code of Federal Regulations, Part 170-178, USA.

(,

t.

EVISION O 2-19 JUL. 2 7 1973 2012.7

~

r.= w -. m e.c.a. w w w.m m e m s m e g g e ; m m

3 The=al ?<eluation 31 Discussion The Model 750 Source Changer is a ecmpletely passive the=al devica and has no mechanical ecoling systems or relief valves. All cooling of the package is through free convection and radiation. The only heat scurce is the (=aximu=) 2hCCi II-192 Source. A conservative figure for the corresponding decay heat is 2 5 vatts (see Section 3.h.1).

32 S--y of Themal Properties of Materials k'he =elting points of the metals used in the construction of the Model 750are:

Depleted Uranium Metal 2070 F (1133 C)

Carbon Steel 2453 F (1345 C) 33C8 F (1820 C)

Titaniu=

Copper 19h0 F (1080 C)

Bronze 1840 F (1005 C)

(

Reference:

Machinery's Handbeck, 20th ed. )

The rigid colyurethane fcam has a mini =um operating range of -100 F to D

200 F (-73 to 93 C).

It vill deccmpose at the fire test temperature of C

lkTS F (800 C).

Deccmposition vill result in gasecus 5yproducts which vill burn in air.

33 Technical Scecifications of Cceronents Not Applicable 3.h Nc=al Conditions of Transport 3.h.1 The=al Mcdel The heat scurce in the Model 750 is a =axi=um of 2hCCi of iridiu=192 The decay heat generated by the scurce can be calculated kncving that 19277 decays by electron capture and beta emission.

• he decay energy for both processes is approxi=ately 1.h5 MeV (

Reference:

Radiolegical Health HanS cek, p.h03):

-13 ) x as ci = 2.C6 'Jatts 10 1.h5 MeV x (3 7 x 10 disint) x (1.6 x 10 J

S-Ci MeV The decay heat scurce is cense ratively taken as 2 5 vatts.

E_~. /:3:C I O

,.~

.UL 2 7 19ed

'^

2 0,i 2

. ' o,

m y =.-==v m g e w c; a m m s m e w w m :s w

To qualify as a Type 3(U) package the additional require =ents of IAEA Safety Series No. 6, 1973, paragraphs 231 and 232 =ust be satisfied. The calculational =odel used to de=enstrate ec=pliance with these regulations is described in detail in Section 3.6, alorg with the results of the analysis.

Essentially, it is assu=ed that one-fourth of the entire decay heat load is deposited unifo=1y in each of six sides. The s=allest of the sides is assumed to reach the maxi =u=

surface te=perature. Heat transfer frc=

the side is restricted only to convective heat transfer frcm the upper face of the plate.

'To =eet the additional requirements of paragraph 2h0 of the IAEA regula-tiens, a separate analysis was perfc=ed. To do this, a heat balance was set up over the surface of the package, using the insolation data in Table III of the IAEA Regulations. The decay heat scurce was considered negligible. The cuter shell was assu=ed to be insulated frc= the interior of the package.

Heat transfer frc= the package was taken to occur by radiation, and over specific surface areas by free convection. A detailed description of the =cdel is given' in the analysis, in Section 3.6.

i 3.h 2 Maxi =n Te=peratu' es An exa=ination of the =elting points of the materials used in ecnstruction of the Model 750 show that the =aximum temperatures encountered under nor=al conditions of transport engender no less of structural integrPy or loss of shielding of the package. The specific Type 3(U) analys;s (Section 3.6) shew the package te=perature to be belcw 40 C (10kOF) in 0

the shade and belev 79 C (17h0F) when insolated.

0 3.4.3 Minimu= Temperatures The =ini=um nor=al operating te=perature of the Model 150 is -kC C ( kO F).

C O

This temperature vill have no ad"erse effect en the package.

3.h.h Mm =u= Internal P essures Nor=al operating ccnditiens generate negligible internal pressures. Any pressure generated is significantly belev that of the hypcthetical accident pressure, which is shcvn to result in no less of shielding or contain=ent.

3.h.5 Maxi =um The =al Stresses The =axi=um te=peratures that occur during nc=al transport are icv enough _

to insure that ther=al gradients will cause no significant ther=al stresses.

.3.k.6 Evaluation of package terfe=ance for Nc=al Conditiens of Trsnsport The the=al ccnditions of ner=al transpcrt are cbvicusly insignificant frc= a functional point cf view for the Model 750. Also, the applicable conditiens of IAEA Regulations for Type 3(U) packages have been shcwn to be satisfied by the Model 750.

HI; VISION O 3-2 JUL 2 7 S73 P

. g. m

,_,_,.,, n.,' _ g n.

i n.

t r

i.

F 35 Hyocthetical Accident The=al Evaluation u

f 351 The =al Model

{

?

The Model 750, includir4 the scurce asse=bly, is assu=ed to reach the fire i

test temperature of 8CCCC (1475 ?). At this te=pereture the polyurethane

[

0 potting cc= pound vill have decc=pesed and the resulting gases vill have escaped the package thrcugh the vent holes and the asse=bly joints which i

are not leak-tight.

r

~

.~--

_3 5 2 rackage cenditions and Environ =ent

(

L The Model 750 underwent no significant Mn-nge during the free drop and h

meture tests. The package used in this analysis is considered unda= aged.

(

I 353 Packaee T moeratures

~

As indicated in 3 51, the package reaches a naximum of 8ccoc (1475 F) thrcughout. An exa=ination of the =bitir4 points of the =sterials used in the construction of the Model 750 (except the potting cc= pound, as r

noted) indicates that there ' vill be no an-nge to the package as a result l

of this te=perature. The possibility of the fc=atien of the iren-uranit=

?

eutectic alloy was addressed in Section 2.4.1, where it was concluded that

[

the for=ation of the alley was not a likely eventuality.

I-3 5.h Maximu= Internal Pressures

+-

The Mcdel 750 packaging is open to the atmosphere, insur ing that there vill be no pressure buildup within the package. In sectica 3.6 there is an analysis of the scurce capsules under the fire test conditions.

It is shcun that the =axi=u= internal gas pressure at this temperature is L

3.8hkg/c=2 (54.6 psi).

Thecritigallocationforfailureistheveld.(54.6 psi) vill generate n =aximum stress of 201 nevtens/

An internal pressure e

9.8hkg/c=

C 0

{291 psi) in the veld. At a temperature of 87C C (1600 ?) the yield strength of Type 304 stainless steel is 69c0 N/c=2 (10,coopsi).

Thus, at 8CO C, the maxi =u= stress in the package vculd be only 3% cf the yield strength at that point.

355 Maximu= The =al stresses There are no significant themal stresses generated durir4 the the mal test.

3.ji.6 Evaluation of Pschage M rfc=ance The Mcdel 750 vill undergo no less of structural integrity cr shielding when subjected to the ecnditiens of the hypothetical the=al accident.

The pressures and te=peratures generated have been de=cnstrated to be within acceptable li=its.

EVISION u 2-3 JJL27 Ms

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3.6 AFFENDIX

- Model 750 The:=al Analysis: IAEA Safety Series No. 6, 1973, paragraphs 231, 232 Model 750 Ther=al Analysis: IAEA Safety Series No. 6, 1973, parsgraphs 2ko

- Iridium Capsules - Thermal Analysis 2012 REVISION O 3h JUL. 2 71973 2.'+,2,-- :u. c.h.;T 5 P. n.. n.,mev..-Fe % T W r;e.%r.1.;7.1__:r'\\'..,;,%v.%.

.s..rui,- 1,7=qg.,7 r i

,. g; a.m.

7.-_,,

Model 750 - Ther=al Analysis Type B(U), Paragraphs 231, 232, IAEA Safety Series No. - 6,1973 This analysis is perfoaad to de=onstrate that the Model 750 source changer

=eets the specific Type E(U) the: ::al require =ents of paragraphs 231 and 232 of IAEA safety series No. 6, 1973, i.e., that the =axi=um surface-temperature does not exceed 50 c in the shade, assuming 38 c a=bient temperature.

To assure conservatis=, it is assumed that:

(1) The entire heat decay

- heat (2 5 vatts) is deposited in the exterior faces of the Model 750, (2)

'the interior of the Model 750 is perfectly insulated, providing heat transfer frc= the vall only to the atmosphere. This rectangular shape of the con-tainer =eans that each face eclipses a different amount of the solid angle thrcugh which the radiation (and thus decay heat) is distributed. To (censervatively) simplify, it is assumed that each of the six exterior faces receives 1/4 of the total source (0.63 vatts) unifer=ly distributed over the face.

2 Considering.the s=allest.' face as undergoing one-di=ensional convective heat transfer:

/

x o

q Interier (Insulated)

T T

a Air y

/

/

\\

vall

/

\\

>t Ty = q/hA + T where a

T = te=perature at the vall outer surface y

q = (decay) heat scurce (0.63 vatts)

A = surface area of the smallest face (0.c53 square =eters) h = free convective heat transfer ccefficient fer air (5 vatts/=eter2 -

C,

Reference:

Heat Transfer, J.p.

c Hol=an, k th Edition, p.13)

Thus, the =axi=u= te=perature at the vall T,is h3 C under ner=al condi-tiens of transpcrt. This satisfies the require =ents of the afore=enticced regulations.

1 hTJ7 IC'* O 3 -

)_

inn 201~z aut 2 7 :n

... - w:,

-n_. _. n..n _ =,,.. nm

f.O

[

=

Model 750 - Thermal Analysis

]'

lI Type BlU), Paragraph 240, IAEA Safety Series No. 6,1973 9y This analysis is performed to de=onstrate that the Model 750 Scurce Changer

[

=eets the specific Type 3(U) thermal require =ents of paragraph 2kO, IAEA q[-

Safety Series No. 6, 1973 This paragraph requires that the raximu=

aurface te=perature of a Type 3(U) package not exceed 82 C urder nor=al

{

conditions of transport, given insolation as cutlined in Table III of the regulations and an a=bient te=perature of 38 C (100 F).

E The calculational =cdel consists of taking a steady state heat balance

{

~

over the surface of the package. To facilitate calculations, certain simplifying assu=ptions are =ade.

These are cutlined belev:

s r

i Insolatica i

800 cal /c=2-19hr (775 W/=2) for the top surface, 400 cal /c=2-12hr (388 W/=2) for the sides, none for the base, as cutlined in Table III of IAEA Regula-tiens. It is assu=ed that the total surface insolated is the top face and the surface area of a right cylinder 1716 inches (h3Cc:=) high and 7 53 inches (191==) in dia=eter. This is a conservative area, as the over-hanging tips of the top cover and top lid provide shade over sc=e of the side area.

The package is finished with either russett or green enamel. The solar absorptivities of these enamels are 0.81 and 0 76, respectively (

Reference:

The=al Radiation Procerties Survey, G.G. Gubareff et.al., 2nd ed.1960, p.260).

A conservative figure of 0 90 vas chosen as the package absorptivity.

Decay Heat I. cad The decay heat lead (2 5 watts) is assu=ed negligible.

package Crientation The package rests on the bottc= cover, i.e.,

in the ner=al transport crientation.

Heat Transfer Mechanis=s The Model 750 is assu=ed to underge free convection and to radiate tc the enviren=ent. The inside faces are considered to be insulated, so there is no conduction into the package. Further, the sides are taken to be thin encugh so there are no tenperature gradients present.

Radiation:

The package is assu=ed to radiate frc= the top surface of the top lid, bettc= surface of the

- bottc= lid, and frc= the surface area of a cylinder 17.16 inches (h36==) high and 7 53 inches (191==) in diameter. This surface area EVISION O

, 1. -

20,1z

'n' JUL 2 7 379 r_g--;p.. 7.gqqg,gg*ggy..pg.ggvglp';,Q-7 g

-r

=

. _~ w y

i y

LL 6

is smi ller than the actu:.1 surface are of the p ekage, providing for a conservative radiative heat loss esti.= ate.

The solar emissivity is conservatively chosen

~

.to be 0.8 (Beference:

Thermal Radiation Properties Survey, G. G. Gubareff, et.al.,

2nd ed. 1960,.p.p.

217, 220).

Convection, Top:

The top surface of the _cackage is assumed to undergo free convection as a horizontal flat

~ ~

plate. The beat transfer coefficient is given <

by:

'b

= 1 32 AT L

(Beference:

Beat Transfer, J.

. Hol=an, 4th ed.

1976, 9253)

_ !l,.;.where i is the average of the legtb of the

_ -?

sides, 0.232m Thus:

0.25 A., = 1 9 (n T)

Convection. Sides:

Tne Podel 750 is constructed in sucb a vay that there are overhanging edges whic'n could int,arfare with convection in the vertical direction.

To provide a conservative estimate of the vertical convective heat transfer, it is assu:::ed that free convection occurs onbr a'nere t'nis ovefnaq is le ss than _r.m.

Tais is true for 1/3 of the total side surface area:

(

3 2'OP V1 5 s

/

s I

\\

l s

Y

'I

3 " '"

L JA A

9 : 50 s

P Tnus, for convecti og along the sides, the 750 is considered to be a right cy1' nder of O.C973t surface a rea.

REVISION O 2_

JUL. 2 71579 e_~

s n

-. - _ ~ - nn a

. - w=mm;-

_-,.,r, n

The convection coefficient is taken to be:

h = 1.h2 A 3

(

Reference:

Heat Transfer,.J, P. Hol=an, hth ed., 1976, p253) where:.L is the height of the cylinder, 0.436m.

Thus:

hs = 1. 75 ( A T

.- 'Taking a heat balance over the package surface:

heat in = heat out (radiation + convection top + convection side) q in = q rad + qct + qcs k

k grad = c-EA (T

-T

).

R y a

= (5 669 x 10.8):(0.8) (o.315) [T (311K)]

y

=hAAT where A T. = Tv Ta qct tt

= (1 9 aT 5 ) (o.c532)a T O

qcs = hsAsaT O

= (1.75 4 T '

) (o.0873)aT Iteration yields a vall temperature T of 79 C (17h0F). Thus, it is 0

y concluded that the Mode: 750 is in ecmpliance with paragraph 2ko of IAEA Safety Series No. 6, 1973

/ n7 c

,L. o,t l

. E 38

n. 2 7 373 m -.

-,, - n.-.--, - w..mw= w

Iridiu= Scurce Capsules - Ther=al Analysis Hyecthetical Fire Conditions This analysis is intended to demonstrate that Tech / Ops scurce capsules which are of 0.25 inel (6.35=m) dia=eter, seal velded to a mini =um penetration of 0.020 inch (0 51==), =ade of Type 30h er 304L stainless steel, and licensed as special form containers under IAEA Safety Series No. 6,1973, also =eet the requirements of 2:aragraph 238, IAEA Safety Series No. 6,1973, i.e., contain=ent under specified thermal test conditions.

'I'he actual containment vessel fer the radioactive =aterial is the velded source capsule. These capsules are all 0.25 inches (6.35==) in dia=eter and less than 1 inch (25.h=m) in length.

The internal volume of the scurce capsules centains only iridium =etal (as a solid) and air. It is assumed at the time of Icading that the entrapped air in the capsule is at standard temperature and pressure (200C,1.03 kilogra=s per square centi =eter). We centend that this is a conservative assu=pticr. because, during the velding process, the in-ternal air is heated, causing sc=e cf the air = ass to escape befcre the capsule is sealed. When the velded capsule returns to ambient te=perature, the internal pressure vould be sc=ewhat reduced.

As described in Tech / Ops standard source encapsulation procedure, the mini =um veld penetration is 0.020 inch (0 51==).

Under ccnditions of internal pressure, the critical location for failure is this veld.

Since the capsule has an outside dia=eter of 0.25 inc% (6.35==)

veld has a cross-sectional area of 0.014 square inchu, (0.093cm$)this Under conditions of paragraph 238 of IAEA Safety Series, No. 6, it is

. assu=ed that the capsule could reach a temperature of 14750F (800 C).

0 Using the ideal gas law and requiring the air to cecupy a constant volu=e:

P T2 P

=

1 2

T1 1

initial pressure (1.03&g/cm )

P

=

initial temperature (293ok)

T1

=

T2 final te=perature (1093 %)

=

The internal gas pressure could reach 3 84 kg/cm. ItisassE=edthat 2

the capsule can be treated as a thin-valled, cylif.drical pressure vessel.

'}

}' '

REVI3 ION O 3-9 J k,,.,<_,,. ~

_ m ym __

-qp

--s

__m,y,,,,

W,gW6'"'-

,'n'T

The naximum longitudinal tensile stress can be calculated by writing a longitudinal feree balance thrcugh the veld:

stress x area - pn ssum x am a

=0 s

p 2

S TT (Do - Di ) - P Tr

,o 1

where S1=

longitudinal stress Do= outer diameter (0.635c=)

Di=

inner diameter (0 535cm) pressure (3 8hkg/c=2)

P

=

2 Thus, the longitudinal stress is 228 newtons /cm.

The hoop stress can be found in a similar fashicn.

Taking a longitudinal cross-section and su= ming forces:

hecp stress x areas - pressure x areap = 0 2S Lt - PD L = 0 h

i where Sh = hoop stress L = length of cylinder t = thickness of 931d (0 51m m) 2 Thus, the hoop stress is 201 newtons /cm,

c At a te=;erature of 1600 p (g79cC) the yield strength is of type 304 stainless steel is 10,000 psi (o900 N/c=2). Thus, the pressure induced stresses are less than 3% of the yield strength at 800cC.

2012 ""

. REVISION O 3-10

,.lUL 2 7 ;979

b..

g,.

P1 4.

Contai=ent k.1 Contai =ent Ecundary

?

4.1.1 Contai=ent Vessel y

sI T-The contai=ent system for the Model 750 Scurce Changer is either the Model Ak24-20 or the Model 68309 Source Assembly. The actual centain=ent

[

either style for the radioactive =aterial is the velded source capsule,8310 in the 360001 or 360004 in the case of the Ah24-20 Assembly, or 6 63809 Assembly. Both scurce asse=blies are currently certified (IAZA p-Certificate of Cc=petent Authority No. USA /0154/S) as special form E'

).

containment for radicactive =ateriale.

J.

The capsules are =ade of Type 304, or 304L stainless steel.

tey are p

seal velded with a mini =um veld penetration of 0.020 inch (0 51=m). The f

capsule styles 360001 or 360004 are rounded cylinders 0.25 inches (6.35=m)

[E in diameter x 0 97 inches in length (24.6==).

The style 68310 is cylindrical, 0.25 inches (6.35=m) diameter x 0.78 inches (19.8cm) length. Appropriate f.

drawings are enclosed in _Section 2.10.

EL.

E h.l.2 Contain=ent Penetrations

F There are no penetrations of contain=ent. The entire scurce assembly is seal velded to provide conformity to special form requirements.

g h.l.3 Seals and Welds y

The contain=ent vessel is tungsten inert gas velded as described in Tech / Ops p

standard scurce encapsulatica procedu-es (See Secticn T.4).

The mini =um f

veld penetration is 0.020 inch (0 51=m). This has proved acceptable for f

certifying this vessel as special form.

i h.l.h Closure a

Not Applicable h.2 Recui e=ents for Nor=al Conditiens of Transcort i.

4.2.1 Release of Radicactive Material The scurce asse=blies used all =eet the requirements of special form

~

radicactive =aterial as delineated in IAEA Safety Series D. 6,1973 and 10CFR71. Thus, there vill be nc release of radicactive matericls under conditions of nor=al transpcrt.

k 2.2 Pressurization of Contai=ent Vessel The scurce sssa=blies used all meet tne require =ents of special fcrm radicactive =aterial. Sressure buildup due to the conditicns of the hypothetical thermal accident has been shown to create stresses well REVISION O h-1 JUL 2 71973

20l,

,g, z

.n.m n=g

a belcni the structural limits of the capsule (See Section 3 5). Thus, the containnent vessel vill withstand the pressure variacions of nomal transport.

4.2 3 Coolant Contamination Not Applicable u'

4.2.4 Coolant Loss Not Applicable 4.3 Contairment Recuirements for the Hypothetical Accident Condition 4.3 1 Fission Gas Products Not Applicable k.3 2 Releases of Contents The hypothetical accidenhconditions as outlined in 1CCFRT1, Appendix B, l.,

2., and 3. have been shown (Sections 2 71, 2.7 2 and 3 5 respectively) to result in no loss of package containnent.

e 2012 P h-2 7,EVISIO11 Q JUL 2 71373 b_

i 1

5 Shielding Evaluation

~

51 Discussion and Results The Model 750 is shielded with 35 pounds of depleted uranium. The uranium metal is cast around the titanium "U" tube which holds the souyce. A radiation profile of Model 750 S.N. 201 containing 200.8Ci of.92 Iridium (See Section 5 5) was made. An erdrapolation for a 2h0C1 source yielded the results which are presented in Table 5 1.

A-om this data and from i

previous acceptability (NRC Certificate of Compliance No.

9021

. Rev. 4 enclosed in Section 13), it is concluded that the Model 750 ccuplies

.vith the regulatory standarda in 10CFR71 at.1 IASA Safety Series No. 6,.1973 TABLE 5 1 SLM4ARY OF MAXIMUM IESE RATES

(=R/ h$

Contact At 1 Meter Side

. Top Ecttcm Side Top Ecttom ca=a 1(3 108 66 1.0 25 05 Neutron Not Applicable Not Applicable Total 173 108 66 1.0 25 05 Rypothetical accident conditions vill result in essentially no change in the above readings.

52 Source Scecification 5 2.1 Ga =a Source The gn -n source used is encapsulated Iridiu=-192 in the quantity of up to 240 curies. It is contained in either Tech / Ops Source Assembly o8309 or Tech / Ops Source Asse=bly Ah2k-20.

5 2.2 Neutron Source Not Applicable 53 Model Specification Not Applicable

, 5-1 REVISION O I

JUL 2 71979

/

2012 F

5.h Shielding Evaluation The Model 750 shieldire evaluation was perfcmed on Mcdel 750, Serial N=ber 201, centaining 200.8 curies of Iridium-192. The radiation profile is included in Section 5 5 Extrapolation of this data to the capacity of 240 curies, (Section 51) clearly indicates that the Model 750 conforms to the regulatcry radiation limits. As the hypothetical accident te::ts (Section 2 7) revealed no change in the shieldir4 arrangement, it is concluded that shielding after the hypothe:ical accident is essentially unchanged. Ther dere, th( radiation profile indicates the package vill be vithin acceptable limits.

2012 F 5-2 REVISION Q

~

JUL 2 7 N79

.a 55 AFFEGIX Radiatien Profile Model 750 Serial Th=ber 201 2012 EVISION O 5.,.

E. 2 71979

.t

=d 9

U Top Front

{

~~~ - - -

s-

. -J y

Left Right t

w

\\

j Rear Bottom RADIATION FROFIII Model 750 Serial Number 201 e

9 Containing 200.8 Ci.

Iridium O

Location At Contact At 1 Neter Top 90 2.0 Bottom 55 05 Front 1h5 1.0 Bear 130 1.0 left 125 10 Right 140

1.0 Notes

1.

All intensities are expressed in uniths of Millircentgens per hour.

2.

Intensities expressed are the maximum intensities on the measured side.

3 Seasurements were made with an AN/PER-27 (J) survey :teter.

P,

.s-711 20\\n&

P2VI51CN O q

JUL. 2 7 ;373

_. - _- - - = w - ----yg-

___. _. _ _-_ g -- =

w --. w w. s @ y,._,j p g;

~ c M ~ M &

6.

Cnticality Evaluation Not Applicable 719 2012 6-1 REVISION Q JUL. 2 7137; Mf--^~--

um

.m

--w-m

-w--

M

7 Ooersting Procedures -

71 Procedures for Leading the Package Section 7.4 describes the precedure for fabricating the special fem source encapsulation.

Section 7.k contains the procedure for leading this scurce assembly into the package and, preparing the package for tra nsport.

72 Procedures for Unicading the Package Section 7.k contains the procedure fer unicading the source assembly frem the package.

73 Preceration of an Empty Package fer Transpert Section 7.4 has the procedure for preparing an e=pty package for transport.

2012 y<'7

~

REVISION O 7-1 JUL.2 7 13Is

.2 7.h A*EIDIX Source Encapsulation Precedure Source Char 41r4 Procedure-(E:spty) Package Transport Procedure

?

2 0 1 2,,'-

REVISION O 2

u-

.vt. 2 71979 w.

- -- ^ ~ ~

~

~

A_

w--

n.. _

-c_

--fM

~

RADIATION SAFEI'Y MANUAL Part II In Plant Operations Section 2 m

ENCAPSULATION OF. SEALED SOURCES o

A.

Persennel Requirements.

Only an individual qualified as a Senior Radiological Technician shall perform the operations associated with the encapsulation of 192 Iridium. There =ust be a seccad qualified Radiological Technician available in the building when these operaticus are being perfor=ed.

B.

General Require =ents s.

. The 192 Iridium loadi cell shall be used for the encapsulation o; solid metallic 192 Iridium and the packaging of sealed scurces such DO as 17CThuliu=, 137 esium and 169 C

Ytterbium.

Solid metallic Cobalt

, ' not exceeding one curie may be handled in this cell also.

The maximum a= cunt of 192 Iridium to be handled in this cell at any one time shall not exceed 1000 curies. The maxi =um a=ount of 133Cs to be handled in this cell at any cne time shall not exceed 100 curies.

This cell is designed to be operat,ed at lens than etmospheric pressure. The exhaust bicwer provided she.1 not be turned off except when the cell is in a decenta=inated condition.

Sources shall not be stordd in this cell over-ight or when cell is unattended. Unencapsulated =aterial shall be returnad to the transfer containers and encapsulated sources transferred to approved source centainers.

When any of the "through-the-vall" tcols such as the velding fixture or transfer pigs are re=oved, the openings are to be closed with the plugs provided. These tcols shall be decontaminated whenever they are re=oved frem the hot cell.

C.

Preparatory Procedure 1.

Check velding fixture, capsule drawer and =anipulator fingers frco cell and survey for centamination.' If centamination in excess of 0._001 A C1 of rencvable contamination is found, these itens must be deconta=inated.

2.

If the velding fixture or the electrodes have been changed, perform the encapsulation precedure emitting the insertico of any activity. Examine this du==y capsule by sectioning thru veld.'

Weld ;enetratien =ust be not less than 0.C20 inch.

.2017 7}~

REVISION O Il.a.1 JUL d I 0 88 7-3

If veld is scund and penetration is at least 0.020 inch, the preparation of active capsules =sy proceed.

If not, the ecndition responsible for an unacceptable veld must be corrected and the preparatory procedure repeated.

3 check pressure differential across first absolute filter, as measured by the =anometer en the left side of the hot cell.

This is about i 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 Precedure 1.

Prior to use, asse=ble and visually inspect the two capsule components to determine if veld zone exhibits any misalign=ent and/or separation. refective capsules shall be rejected.

2.

Degrease capsM s ecmponents in the Ultrasonic Bath, using isopropyl alcohol as degreasing agent, for a period of 10 0

minutes.

Dry the capsulb compenents at 100 C for a mini =um of twenty minutes.-

3 Insert capsule ecmponents into hot cell with the posting bar.

4.

Place capsule in veld positienin6 device.

5 Move drawer of scuree transfer container into hot cell.

6.

Place proper a=ount of activity in capsule.

Disposable funnel =ust be used with pellets and a brass rivet with vafers to prevent contaminstien of weld zone.

7 Re=ove unused radicactive =aterial frcm the hot cell by with-drawin6 the drawer of the source transfer container frem the cell.

8.

Re=cve funnel or rivet.

9 Assemble capsule components.

10. Weld adhering to the follevin6 conditicas:

a.

Klectrode spacing.C21" to.C2h" centered on joint 1 002"; use jig for this purpose.

b.

Preflow argen, flush 10 seconds; c.

Start 15 amps.

d.

Weld 15 a=ps.

e.

Slope 15 a=ps.

f.

Post flev 15 seccnds II.2.2 REVISION O 7u 2012 '

9.a-W L. - t e

1

__m

11.

Visually inspect the veld. An acceptable veld =ust be continucus without cratering, cracks or evidence of blev out.

If the veld is defective, the capsule =ust be cleaned and revelded to acespt-hLe conditions or disposed of as radicactive vaste.

12.

Check the capsule in height gauge to be sure that the veld is at the center of the capsule.

13 Wipe exterior of capsule with flannel patch vetted with EurA solution or equivalent.

14. Count the patch with the scaler counting system. Patch must shev no more than.005p Ci of contamination.

If the patch shows more than.OO5 pCi the capsule must be cleaned and reviped.

If the revipe pateb still shows more than 0.005 pCi of contamina-tion, steps 8 through 11 =ust be repeated.

15 Vacuum bubble test the capsule.

Place t he velded capsule in a glass vial containing isopropyl alechol. Apply a vacuum of 15 in Hg(Gauge). 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 alechol. Reveld the ca'psule.

~

16. Transfei the ca sule to the 7:. aging fixture. Insert tM

~

wire and cennector assembly and swage.

Hydraulic pressure should not be less t'aan 1250 nor = ore than 1500 pounds.

17.. Apply the tensile test to asse=bly between the capsule and

. connector by applying proof Icad of 75 lbs.

Extension under the load shall not exceed 0.1 inch. If the extension exceeds 0.1 inch, the scurce must be disposed of as radioactive vaste.

18. Fcsition the source in the exit port of hot cell. Withdraw all personnel to the control area. Use remote centrol to insert source in the ion cha=ber and position the source for

=axi=um response. Record the meter reading. Ccepute the activity in curies and fill cut a te=perary source tag.

19 Using remote centrol, eject the scurce frem cell into source changer through the tube gauze vipe test fixture. Mcnitor before reentering the hot cell areato be sure that the source is in the scurce changer.

Remove the tube gauze and count with scaler ccunting system. This assay =ust show no more than 0.005 pC1.

If centamination is in excess of this level, the source is leaking and shall be rejected.

20.

Cceplete a Scurce Leading Lcg (Figure II.2.1) for the operation.

71 7 II.2 3 20 2 t

EVISION O T-5 JUL 2 71973

Technical Oterations Standard Source Changira Procedure Wear personnel monitoring devices during all scurce changing operaticas.

Monitor all operations with a calibrated, operable survey meter.

hote: All the precautions used when making radiographic exposures =ust be followed.

1.

Upon receipt of the scurce changer, survey the source charger to ensure that the scurce is in the proper storage position.

2.

Locate the source changer and projector in a restricted area.

Incate the devices so as to avoid sharp bends in the guide tube or control hcusing.

3 Set the projector as for an exposure.

4 Re=ove the cover from th'e scurce changer by breaking the seal vire and removin3;the bolts.

5 Connect the extension scurce guide tube frem projecter to the fitting above e=;ty chamber.

(Avoid sharp bends). Insure that the locking mechanism for the empty chamber is unlocked.

6.

Crank scurce into the source charger.

a.

Survey this operation with a gnmn survey meter to be sure scurce has been transferred frem projector to chargr r.

b.

With a survey =eter verify radiation level does not exceed 200 =r/hr at the surface of changer.

7 Icck the source in the scurce changer by depressir4 the lock attached. Re=ove the key.

8.

Disecnnect the extender guide tube frem the source changer and re=ove the drive cable frcm this projector by =anually pulli g the entire length of drive cable frcm the projector asse=bly.

Coil the drive cable, tie it and place it in the plastic bag provided.

9 Feed the new drive cable thrcugh the extender guide tube, projector and control assembly. Reattach the extender guide tube to the scurce changer-10.

Unlock the source drive cable frc= the s'curce changer.

REVI3 ION O 7-6 JUL. 2 71979 2012

/

-wMM m--me.

11.

Crank source to full retraction within projector.

Survey this operation with a gn==a survey meter to be a.

sure scurce has been transferred into the projector.

b.

With a survey =eter verify radiation level does not exceed 200 =r/hr at the surface of the projector.

12.

Disconnect the source guide tube from chan6er and projector and lock the projector.

- 13 Affix ID plate of new source to projector.

14. Prepare 50urce changer for shippirg:

Attach ID plate of old source to source changer.

s.

b.

Bolt changer cover in place and seal.

Again survey the source changer to insure that the radiation c.

level does not' exceed 200 =r/hr at the surface of the changer.

d.

Survey the radiation level at a distance of 3 feet from the surface of the source changer. This radiatien level shculd not exceed 10 mr/hr. The highest radiation level measured at three feet frem the container is used to determine the Transport Index in accordance with 49CF3173 389(h).

Affix the proper shipping labels and return to Techniccl e.

Operations, Inc.

2012 2 -

7-7 REV!SION O JUL 2 71379

~~~r=m w w g;mmmy

;rgyp.

p3 3.-

Technical 0::erations ProcedureF for Shi ment of Scurce Charger (Enpty)

Wear personnel monitoring devices during all source charging operations.

Monitor all operations with a calibrated, operable survey meter.

Note: All the precautions used when makir4 radiographic exposures must be followed.

1.

Upon receipt of the source charger, survey the source charger to ensure that the source is in proper position.

2.

Locate the source changer and projector in a restricted area.

Locate the devices so as to avoid sharp bends in the guide tube or control housing.

3 Feed t'.ie new drive cable through the extender guide tube, projcetor and control assembly. Attach the extender guide tube to the source changdr.

4.

Unlock the souic ' drive cable from the source changer.

,5 crank source to full retraction within projector.

Survey this operation with a ga==a survey a.

meter to be sure source has been transferred into the projector.

b.

With a survey meter verify radiation level does not exceed 200 ex/hr at the surface of the projector.

6.

Disconnect the source guide tube frcm changer and projector, lock the projector and lock the source changer.

7 Affix ID plate of new source to projector.

8.

Affix a green "e=pty" tag to scuree charger.

9 Perfom a vipe test of the source changer to assure that the radiation observed is less than 0.001 microcuries per 100 square centimeters.

10. Mark the source charger: Radioactive "LSA" 11.

Survey the source changer radiation level at 3 feet. This level should be less than 10 =r/hr.

REVISION O 7-8 JUL 2 71979 yaa 7 n 1 -)

eUic e!dsA

$3 h

• = L$ "Wj 'W' 2_'-

s

a.

If there is no measurable radiation at 3 feet, perform a surface survey. If the surface levels are less than 0 5 mr/hr, no label is required. Mark the outside of the source changer:

"hempt from specification packag-of $ marking, and labeling, and exempt frcm the provisions ing 9CFR173 393 per 49CFR173 391(c). hempt frcm the requirements of 49CFR Part 175 per 49CFalT5,10(a)(b)."

b.

If there is radiation measurable at 3 feet, use this level to determine the transport index in accordance with 49CFR173 389(h).

Affix the proper shipping labels.

12.

Ccmplete the proper shipping papers as spelfied in Tech / Ops Radiation Safety Manual II.6 3.E(4),(5),t I).

2012 'T 7-9 REVISICN O JUL 2 71373

---w

- - ' - e.,,. _

8.

Acceptance Tests and Maintenance Freeram 8.1 Af.:eptance Tests 8.1.1 Visual Inspection The package is visually examined tu assure that the appropriate fasteners are seal wired properly and that the package is properly marked.

The seal veld of the radioactive source capsule is visually inspected for proper closure.

8.1.2 Structural and M essure Tests The swage coupling between the scurce capsule and cable is subjected to a static tensile test with a load of seventy five pcunds. Failure of this test vill prevent the source asse=bly frcm beira used.

8.1 3 Ieak Tests The radicactive scurce'ca'p'sule (the pri nry containment) is vipe tested for leakage of radicactive contamination. The source capsule is subjected to.a vacuu= bubble leak test. The capsule is then subjected to a second vip's test for leakage of radioactive contamination. These tests are de' cribed in Section 7.4.

Failure of any of these tests will prevent use of this source asse=bly.

8.1.4 Ccmronent Tests The lock assembly of the package is tested to assure t':st security of the source vill be =aintained. A length of Teleflex cable is locked in position in the package. The package is lifted by this cable to assure that the lock asse=bly will secure the cable in position under a lead eqtial to the package weight. Failure of this test vill prevent use of the package until the lock assembly is corrected and retested.

8.15 Tests for Shieldies Inteerity The radiatica levels at the surface of the package and at three feet frcm the surface are =easured using a s=all detector survey instr' ment (i.e.

A:# FIR-27).

'"hese radiatica levels, when extrapolated to the rated capacity of the package, =ust not exceed 200 milliroentgens per hour at the surface nor ten milliroentgens per hour at three feet frem the surface of the package. Failure of this test will prevent use of the package.

8.1.6 The: ::al Acceptance Tests Not Applicable REVISION O 8-1 JUL 2 71979

~

20i2 7 "

e..

8.2 Maintenance program 8.2.1 Structural and pressure Tests Not Applicable 8.2.2 Leak Tests As described in Section 8.13, the raddcactive source asse=bly is leak

' '. tested at manufacture. Additionally, the source assembly is vipe tested for leakage of radioactive contamination every six months.

8.2 3 Subsystem Maintenance The lock assembly is tested as described in Section 8.1.4., prior to each use of the package. Additionally, the package is inspected for tightness of fasteners, propr seal vires and general condition prior to each use.

8.2.4 valves, Ructure'Di es and Gaskets Nct Applicable 8.2 5 Shielding Prior to each use, a radiation survey of the package is =ade 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.

8.2.6 The=al Not Applicable 8.2 7 Miscellaneous Inspections and tests designed for secondary users of this package under the general license previsions of 1CCFRT1.12(b) are included in Section 7.4.

3-2 REVISION O JUL 2 71979

.3n 2

79' M822 cui

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