ML19211A904

Requests Certificate of Compliance for Model 820 Type B. Package Description & Fee Encl

ML19211A904
Person / Time
Site:	07109137
Issue date:	11/09/1979
From:	Munro J TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
14752, NUDOCS 7912210289
Download: ML19211A904 (60)

Text

PDR 7/-1/37 Aad;ation Products Divsen 40 North Avenue Buregton. Massachusetts 01803 Telepnone (6? 7) 272 2000 9 November 1979

>T. Charles E. MacDcnald, Chief Trsnsportation 3 ranch Divisien of Fuel Cycle and Material Safety U.S. 'uclear Regulatcry Ccemission

'Jashingten, CD 20555 rear Mr. Macronald:

'ie request issuance of a US ;EC Certificate of Cc=pliance for Radioactive Materials Package for Technical Operations Model 820 Type 3 Package - Source Changer. We are enclecing eight cepies of the package descripticn of the Model 820 for your review. In acecrdance with 10CFR170 31 Item 11.3, we are also enclosing a check for $700 for the applicaticn fee.

We plan to apply to the U.S. repartment of Transportation for an International Atomic Energy Agency Certificate of Cc=petent Authority fer Type B(U) packaging under the 1973 Revised Edition of IAEA Safety Series No. 6.

We ask that this package he reviewed for ccnformance to these requirenents also.

'ie trust that this application satisfies your requirements for issuance of this certificate.

If we can provide any additional infor=ation, please contact us.

h 51nce e ',

\\ s r

or John J. >'unro III Technical Cirector v

uu/fu Encls.

1636 204 14752 7 91221 o 2 F7

Tdch/ Ops 98 Rad:ata Products Divison 40 North Avenue Burlingtor., Massachusetts 01803 Telephone (617) 272 2000 PACKAGE DESCRIPTION TECHNICAL OPERATIONS y.c3EL 820 O

e 8

1636 205

a 1.

General Infer =ation 1.1 Introduction The Tech / Ops 820 is designed for use as a scurce changer and shipping container for Type 3 quantities of radicactive

=sterial in special form. The Model 820 conforms to the criteria for Type 3 packaging in accordance with lOCfR71 and satisfies the criteria for Type 3(U) packaging in accordance with LAEA Safety Series No. 6,1973 Edition.

1.2 Package Description 1.2.1 Packaging The Model 820 is 19 5 inches (h95==) in dia=eter and 215 inches (5h6 =m) high. The gross weight of the package is 222 pounds (101 kg).

The radicactive scurce asse=blies are housed in titanium "J" tubes. The "J" tube has an cutside diameter of 0.hh inch (11.1==) and a vall thickness of 0.035 inch (0.89==).

The eight "J" tubes are velded to an octagonal scurce stop fabricated from titanium to form the source tube assembly.

This scurce stop allows positive positioning of the source asse=bly at the bettem of the "J" tube.

The source tube asse :bly is surrounded by depleted uranium metal for shielding. The uranium metal is cast around the titanium scurce tube asse=bly.

The uranium shield asse=bly is encased in a stainless steel hcusing. The shield is suppcrted on the bottom by a stainless steel shield support ring which is velded to a shield suppcrt plate. The shield support plate is velded to the hcusing shell.

The shield is supported on top by a shield spacer ring. This spacer ring is positiened by the housing top plate which is velded to the hcusing shell.

The shield spacer ring and shield support ring provide support for the shield in both vertical and horizontal directions.

Copper shi=s are pcsitioned between the shield and these rings to prevent any iron-uranium interfaces.

The housing top plate and the shield support plate, in addition to being velded to the housing shell, are mechanically connected by means of shield suppcrt posts. These support pcsts are velded to the shield support plate and bolted to the top plate.

163~6~ 2)d REVISION O l-1 NOV. O 9 G79

The void space between the uraniu= shield asse=bly and the stainless steel housing is filled with a castable rigid polyurethane foa=.

Mounted on the housing top plate ae eight locking asse=blies.

These locking asse=blies are used to secure the radioactive source asse=blies in a shielded position during transport.

An outer package lid, fabricated fro = stainless steel, is bolted to the package to provide protection to the locking assemblies.

Ta=perproof seals are provided during ship =ent of these sources.

Two vent holes in the package provide passagevays for the esespe of any gas generated frc= decomposition of the polyurethane foa= in the event the source changer is involved in a fire accident. The outer packaging is designed to avoid the collec-tion and retention of water. The package has a smooth stainless steel finish to provide for easy decontamination.

The radioactive =aterial is sealed inside a stainless steel source capsule. The capsule acts as the contain=ent vessel for the radioactive material.

1.2.2 Operational 'eatures The source asse=blies are secured in the proper storage position by means of the locking asse=blies. With a source in the storage position, the "Teleflex" cable portion of the source assembly is located inside the locking asse=bly. The lock plate is engaged to secure the cable in place. Operation of the lock requires use of a special key.

This lock assembly is similar to that used on Tech / Ops Model 750 Type 3 packege (USURC Certificate No. 9021).

1.2 3 Contents of package The Model 320 is designed for the transport of iridiu=-192 in quantities up to 1000 curies as Tech / Ops scurce asse=blies Ak2h-1, A424-9, A424-20, 68309, 69701, and 81401. These source asse=blies satisfy the criteria for special for= radicactive

=aterial in acecrdance with 10CFR71 and IAEA Safety Series No. 6, 1973 saition (Section 2.8).

1636 207 1-2 REVISION O NOV. O 91979

13 AFFENDIX Descriptive Asse=bly Drawing, Model 820 9

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2.

Structural Evaluation 2.1 Structural Design 2.1.1 Discussion Structurally, the Model 820 consists of four components:

a source capsule, shield asse=bly, cuter housing and locking asse=bly. The source capsule is the pri=ary containment vessel.

It satisfies the criteria for special for= radioactive

=aterial. The shield asse=bly fulfills two functions.

It provides shielding for the radioactive material and, together with the lock assembly, assures proper positioning of the source.

The outer housing is fabricated frc= 13 gauge (0.0938 inch or 2 38== thick) stainless steel. The housing provides the structural strength of the package. The top lid protects the lock asse=blies. The lock assemblies secure the sotr ce assemblics in the shielded position at the botto= of the "J" tube, and assures positive closure.

2.1.2 Design Criteria The Model 820 is designed to ec= ply with the requirements of 1CCTRTl and IAEA Safety Series No. 6, 1973 Edition. The device is si=ple in design. There are no design criteria which cannot be evaluated by straight forward application of the appropriate section of 10CTR71 or IAEA Safety Series No. 6.

2.2 Weights and Centers of Gravity

'The Model 820 veighs 222 pounds (101 kg). The shield asse=bly contains 125 pounds (57 kg) of depleted uranium. The center of gravity was located experi=entally. It is located along the cylindrical axis at a distance of 95 inches ( 0.2 = ) above L

the botto= surface.

23 Mechanical Procen tes of Materials The Model 820 housing is fabricated fro = ?/pe 30h stainless steel.

This material has a yield strength of 35,000 pcunds per square inch (

2h1 2C/=2).

(

Reference:

Metals Handbook, Vol 1, Eight Edition) tavings of the source capsules used in conjuncticn with the yodel 820 are enclosed in Section 2.10.

These source asse=blies all consist of a source capsule fabricated frc: mype 3Ch or ?/pe 30hL stainless steel. The source capsule is svaged to a "Teleflex" steel cable. The capsules are sealed by tungsten inert gas

' 6M 2 3

H W ISIO V O 2-1 NCV 0 91979'

welding. The svaged coupling is tensile tested on a production basis to 75 pounds (334 newtons).

2.4 General Standards for All Packages 2.h.1 Chemical and Galvanic Reactions _

The =aterials used in the construction of the Model 820 are uranium metal, steel, titaniu=, bronze and copper. There vill be no significant chemical or galvanic action between any of these components.

The possibility of the formation of the eutectic alloy iron-uranium at tenperatures below the melting te=peratures of the individual =etals has been considered. The iron-uranium eutectic alloy te=perature is approximately 1337 F (725 C).

However, vacuum conditions and extre=e cleanliness of the surfaces are necessary to produce the alloy at this lov temperature. Due to the conditions under which the shields are =cunted, sufficient contact for this effect does not exist.

In support of this conclusion, the following test results are presented. A ther=al test of a sa=ple of bare depleted uranium

=etal was performed by Nuclear Metals, Inc. The test indicated that the uranium sample oxidized such that the radial di=ension was reduced by 1/32 inch (0.8 =).

A subsequent test was per-formed in which a sample of bare depleted u anium metal was placed on a steel plate and subjected to the ther=al test conditions. The test shoved no =elting or alloying character-istics in the sample, and the degree of oxidation was the same as evidenced in the first test. Copies of the test reports are included in Section 2.10.

Notwithstanding these test results, copper shi=s are used as separators at all iron-uraniu= interfaces to prevent contact and to preclude the possibility of the for=ation of this eutectic alloy.

2.h.2 Fositive Cicsure The source assemblies in the Model 320 cannot be exposed without opening a key operated lock. Access to the lock requires re= oval of the lid. The lid is seal vired and provided with a tamperproof seal.

2.4 3 Lining revices The Model $20 is designed to be lifted by two eyenuts attached 16 UNC bolts. The cross sectional to the cover by =eans of 3/8 e (g3,7=2).

area of each bolt is 0.0693 in The yield strerg h REVISION,0 NOV. O O 1979 2-2 1636 214

of these bolts is greater than h0,000 pounds per square inch (276MN/=2). Therefore, each eyenut can support 2770 pounds (12 3 kN) or = ore than tvelve times the weight of the package without exceeding the yield strength of the caterial.

2.4.4 Tiedown Devices The tiedown devices on the Model 820 are the two eyenuts. As demonstrated in Section 2.k.3, each can support twelve times the weight of the package without generating stress in excess of the yield strength of the =sterial.

25 Standards for Type B and Large Quantity Packages 251 Load Resistance Considering the package as a si=ple beam supported on both ends with a unifor= lead of five times the package weight evenly dis-tributed along its length, the maxi =u=

stress can be ec=puted frc=:

F.1 S

=

cZ vhere S: Maxi =u= Stress F: Total Lead (1110 pcunds; 4.9 kn) 1: Length of 3ea= (215 in; gh6==)

Z: Section Modulus (19.k1 in-;

318,073==3)

(

Reference:

Machine:y's Handbeck, 2Cth Edition, P hl2)

The lead is assu=ed to be 1110 pcunds (4.9 kn). The container is assu=ed to.be a cylinder with an outside diameter of 16.375 in (h15 9==),

a vall thickness of 0.c9h inch (2.4==) and a length of 215 inches (5h6==).

consequently, the section modulus of the bea= is 19.kl in3 Therefore, the =a.ximum stress generated in the bea= is 15h pcunds per square inch (l.C6 MN/=* ) which is far below the yield strendth of the raterial.

252 External M essure The Model 820 is open to the at=osphere. Therefore, there vill be no differential pressure acting on it.

The collapsire pressure of the scurce capsules is calculated assu=ing that the capsules are thin vall tubing with a vall thickness equal to the mini =um depth of weld penetration (0.020 inch; 0 5==).

The collapsing pressure is calculated frc=:

2-3 REESICN O NCV. C 91979 1636 215

1386 86,670 t,

P

=

d where P: collapsing pressure ir. pounds per square inch t: vall thickness (0.020 inch) d: outside diameter (0.250 in)

(

Reference:

Machinery's Handbook, 205h Edition, p 448) be 5547 pounds per square inch (38 Ic/='psules is calculated to The collapsin6 pressure of the source ca

).

Therefore, the source capsules can withstand an external pressure of 25psig.

2.6

Torral Conditions of Transport 2.6.1 Heat The themal evaluation of the Model 820 is perfor=ed in Chapter 3 From this evaluation, it can be concluded that the Model 820 can withstand the nomal heat transport condition.

2.6.2 Cold The =etals used in the =anufacture of the Model 820 can a n C

withstand a temperature of -40 C.

The lover operatin6 limit C

0 of the polyurethane foa= is -10C F (-73 C). Thus, it is concluded that the Model 320 vill withstand the nor=al transport cold con-ditions.

2.6.3 Pressure The Model 820 is open to the atmosphere; thus, there vill be no differential pressure acting on the package.

In Section 3 5.k, it is demonstrated that the source capsules are able to withstand an external pressure reducticn of 0 5 at=ospheres (50 7 k'T/=2),

2.6.4 Vibration The Model 820 is similar in construction to our Model 750 Type B package (Certificate No. 9021). Additionally, the locking assembly of the Model 820 is similar to that used in the Model 750. The Model 750 has been in use for five years. During that ti=e, there have been no vibrational failures reported.

Cn that basis, we contend that the Model 320 vill not undergo a vibrational failure in transport.

2-h REVISION O NCV.'O 91979 1636 216

2.6.5

'Jater spray Test The water spray test was not actually perfor=ed on the Model 820.

'Je contend that the materials used in construction of the Model 323 are all highly water resistant and that exposure to vater vill not reduce the shielding or affect the structural integrity of the package.

2.6.6 h ee Drop The drop analysis perfor::ed in Section 2 71 is sufficient to satisfy the require =ents of the nor=al transport free drop condition. On this basis, we conclude that the Model 820 vill withstand the free drop without loss of shielding effectiveness or loss of package integrity.

2.6.7 Corner Drop

Tot Applicable 2.6.8 7enetration A penetration test of the Model 820 was performed. There was no loss of shielding or loss of structural integrity as a result of this test. A copy of the test report appears in Section 2.10.

2.6.9 ccmpression The gross weight of the Model 820 is 222 pounds (101 kg). The 2

2 maxi =um cross sectional area is h20 in.

(0.27m ).

Thus, five times the weight of the package (ll10 pounds; E945 newtons) is greater than two pounds per square inch times the maximum cross sectional area (8h0 pounds, 37h2 newtons). For this analysis, the load is assumed to be 1110 pounds (4945 newtons).

The maxi. um stress generated in a flat circubr plate with the edge fixed around the circumference and a uniformly distributed 1 cad over the surface of the plate can be computed frc=:

o=

0.2hF 2

t where 7: maximum stress generated in the plate F: load applied to the plate (1110 pounds) t: thickness of the plate (0.09h inch)

Machiner 's Handbcob, _0th Edition, p h44)

(

Reference:

/

2-5 BEVi5 ION O NOV. C G r;79 1636 217

From this relationship, the =aximum stress generated in the 2

plate is found to be 30,150 pounds per square inch (208 !C/m )

which is less than the yield strength of the material (35,000 psi; 241 IG/c2). Therefore, it can be concluded that the co=pression condition vill not adversely affect the package.

27 Hypothetical Accident conditions 271 Tree Drop The Model 820 was subjected to a drop test through a distance of 30 feet onto a steel plate. There was no loss of shielding nor loss of package integrity as a result of this test.

A copy of the test report is included in Section 2.10.

2.7.2 Puncture The Model 820 was subjected to the puncture test of 10CTR71.

As a result of this test, there was no loss of shielding nor less of package integrity.

A copy of the test report is included in Section 2.30.

273 Ther=al The ther-al analysis is presented in Section 3 5 It is shown that the =elting ta=peratures of the caterials used in the construction of the Model 820, except the polyurethane foa=,

are all in excess of 1475 7 (800 c)

To de=enstrate that the radioactive source asse=blies vill re=ain in a shielded position following the hypothetical thermal accident, the following analysis is presented. At the conclusion of the themel test, it is assumed that the polyurethane foam has completely escaped fro = the package. The shield asse=bly is prohibited from rotational nove=ent by the titanium "J" tubes which protrude from the package housing. The shield is restricted from vertical =ove-

=ent by the shield support ring and the shield spacer ring.

Thus, it is concluded that the Model 820 satisfactorily meets the requirenents for the hypothetical accident - ther=al ccndition of ICCTRT1.

2 7.h

'4ater I:=ersion Hot Applicable 275 Su==ary of TA= age The tests designed to induce rechanical stress (drop, puncture) caused minor deformation but no reduction in the safety features of this package. The the =al ecndition vill result in no reduc-tion of the safety of the package.

JiEVISION O 2-o-NOV. O 91973 1M 2lb

It can be concluded that the Fypothetical accident conditions have no adverse effect on the shieldir4 effectiveness or structural integrity of the package.

2.8 Special For=

The Model 820 is designed for use with Tech / Ops Source Assemblies Models A424-1, A424-9, A424-20, 69701, 81401 and 68309 These source asse=blies have all been certified as special form radio-active material under IAEA Certificate of Competent Authority Ilo. USA /0154/S. A copy of this certificate is included in Section 2.10.

29 Fuel F.ods

Tot Applicable 2-7 REVISION O NOV. O 91979 163'621f.:-

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2.10 Appendix Descriptive Assembly Drawings - murce Assemblies Test Report: Uranium Ther=al Test Test Report: Model 820 Penetration Test Test Report: Model 820 Free Fall and Puncture Tests IAEA Certificate of Ccapetent Authority USA /015k/S

?.EVISIC'N O 2-8 NCV. o 9 :379 1636 220

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R A DI ATIO N PRO DUCTS OlVISIO N NORTHWEST INDUSTRIAL P ARK suRusaton, u Assacwusetts Cisos (CCh OPS 46171272 2000 Telephone Conversation Fecord 28 November 1973 Mr. John G. Fovers and Joseph Lica Froject Engineer Engineering Manager nuclear Metals, Inc.

Technical Operations, Inc.

2229 Main Street Fadiation Froducts Division Concord, Massechusetts

!.'r. Fevers perfor ed a Ther=al Test en a sample of bare depleted uranium.

.The cample, prior to the test, was a right circular cylinder ressuring 0.h32 inch disteter and 0.h95 inch icng. The asss of the sample was 22.2 gra=s.

The eseple was placed in a thin vall ceracie crucible and inserted in 0

a resistance heated furnace prehested to 1475 F.

The sacple was hested for 30 =inutes. The eseple was then re=oved and alleved to air cool under a ventilated hcod.

Mr. Fevers reported that at the conclusion of the test,.the sa:ple ressured 0.h18 inch 'dia eter and 0.kbl inch long. 'The s ss of the ss=ple was 20.8 grams.

d

(

I 1636 223 REVISION O 2-11 NCV. C 91979

p i@*$

N UC LE A R M E T A L S, I N C.

us:

\\l 2229 M AIN STRECT CONConD. M ASS ACHUSETTS 0i742 trigo=o=[ si? 3se Seio 28 January 1974 Technical Operations, Inc.

Radiation Products Division South Avenue Burlington, Massachusetts 01803 Attention:

Mr. J. Lima Gentlemen:

In respcnse to a request by Joe Lima of Tech Ops, a simulated fire test was perfomed on samples of bare depleted uranium in contact with mild steel, the object being to detemine what, if any, alloying or melting would occur under these conditions.

TEST DATA:

I.

A 3/4-inch diameter x 5/8-inch long bare depleted uranium speciten was set on a 1-inch diameter x 1/8-inch thick mild 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:

I'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 performed by NMI on 25 January 1974.

Very truly yo k'

,u Jchn G. Powers Project Engineer 1636 224 HEVISICN O NCV C 9 mg

TEST REPORT RADIATION FR0 DUCTS DIVISION BY:

David Mar:1111 DATE:

8 October 1o79 SUBJECI: Model 820 Penetration Test On 8 October 1979, a penetration test was perfor=ed on a Technical Operations' Model 820 Shipping Container in accordance with 10CFRT1, Appendbc A.8 and IAEA Safety Series No. 6, 1973, paragraphs 71ha and 71hb.

The hemispherical end of a vertical steel cylinder 1.25 inches in dia=eter weighing 14 pounds was dropped from the height of El inches onto the gec=etric center of the top surface of the Model 820. There was no defor=ation and no damage which would affect the shielding or structural integrity of the package.

A second test was conducted using the sa=e cylinder.

It was dropped from a height of 41 inches onto the cylindrical surface of the package to attempt to produce penetration to the shield. There was no deformation and no da= age which would affect the shielding or structural integrity of the package.

Docu=entary photographs are enclosed.

Performed by

~41tnessed by

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' David Marzilli Willia = Urban REVISION ^

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1636 228

TEST REPORT RADIATION FRCDUCTS DIVISION BY:

John J. Munro III DATE:

25 October 1979 SUEJF.Cf: Drop and ? uncture Tests of Model 820 Shipping Container On 25 October 1979, yodel 820, Serial no.1 vas subjected to the free fall and puncture conditions of 10CFR71 Appendix B and IAEA Safety Series No. 6, 1973 The tests were conducted at the facilities of Baldwin Crane & Eculp-cent Corporation, 232 Andover St., No. Wilmington, MA.

Prior to conducting these tests, a radiation profile of the Model 820 was made. Eight du m source assemblies were installed in the source changer to allow deter ::ination of any displacement of a source assembly during the tests.

Test 1 (Free Fall)

The target for this test was a steel plate 48 inches long, h8 inches vide and 0 5 inch thick. The plate was supported on an asphalt drivevay which was supported by crushed rock to a depth of two feet.

The Model 820 was dropped frcm a height of 30 feet ento this target.

Tne container i=pacted the target at an angle of approximately 45 degrees from vertical on the bottcm rim of the centainer.

The Model 820 was again dropped from a height of 30 feet onto the target.

The container impacted the target at an angle of approxi ately 75 degrees from the vertical on the top rim of the contair.er.

Test 2 fruncture)

The target for this test was a steel billet six inches in diaceter and eight inches long scunted onto the target of Test 1.

Tne Model 820 was dropped frem a height of forty inches onto the target.

The

cntainer impacted the target vertically on the top surface.

The Model 820 was again dropped from a height of forty inches ento the target.

The container impacted the target horizontally on the cylindrical pcrtion of the lid.

Test Results The two free fall tests caused deferration of the container housing.

The two puncture tests caused minor indentation of the container hcusing.

yog g

The container remained structurally intact throughout the testing. The du=my source assemblies remained in the proper storage position durire the testirg.

A result of a radiation profile of the container after being subjected to the test conditions was not significantly different than the earlier radiation profile results. Photographs are attached.

JJM/fb Attachment EEVISIC:i Q Cv~ c " '*

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?001 DRBINAL 1656

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DEPARTMENT OF TRANSPORTATION

[N.

.k. RESEARCH AND SPECIAL PROGRAMS ADMINISTRATION W A s H IN GTO N.

O.C.

2o590 e

IAEA CERTIFICATE OF COMPETENT AUTHORITY Soecial Form Radicactive Material Encapsulation

,g,,,

yo; Certificate Number USA /0154/S This certifies that the encapsulated sources, as described, when loaded with the authorized radioactive contents, have been demon-strated to meet the regulatory requirements for spegial form radioactive material as prescribed in IAEA and USA regulations for the transport of radioactive naterials.

I.

Source Description - The sources Jescribed by this certificate 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 lencth A424-1 B60001 or B60004

.25 x.97 A424-6 360001 or 360004

.25 x.97 A424-9 B60001 or B60004

.25 x.97 A424-20 B60001 or 360004

.25 x.97 A38101 B60006 Pellet, Wafer or large Wafer

.25 x.90 A68309 C68310 Pellet or Wafer

.25 x.78 A81401 B60001 or B60004

.25 x.97 B69701 B60001 or 360004

.25 x.97 All capsules are construgted of either 304 or 304L stainless steel and conform with the following design drawings:

Caosule Style Drawing Number B60001 B60001 - 1 Rev. H and - 2 Rev. F B60004 B60C01 - 1 Rev. H and 360004 - 1 Rev. D B60006 Pellet B60006 - 1 Rev. H and 360001 - 2 Rev. F B60006 Wafer 360006 - 1 Rev..H and 360004 - 1 Rev. D B60006 Large Wafer 360006 - 2 and B60001 - 2 Rev. F C68310 Pellet C68310 Rev. B and B68310-3 C68310 */afer C68310 Rev. B II.

Radioactive Contents - The authorized radioactive contents of these sources cons',: of not more than the following amounts of Iridium-192 as solid metal:

1656 235 REVISION O NOV. C 91979 2-23

Certificate Number USA /0154/S Page 2 Model No.

Contents (Curies)

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 accordance with paragraph 803 of the l

IAEA Regulations, and in response to the November 3, 1978, petition by Technical Operations. Inc., Burlington, Massachusetts, and in consideration of the associated information therein.

Certified by:

seet /4/978 u

o, R. R. Rawl, Health Thysicist (Date)

U. S. Department of Transportation Office of Hazardous Materials Regulation Washington, D. C.

20590.

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

2Title 49, Code of Federal Regulations, Part. 170-178, USA.

~

1636 236 REVISION O taCV. C 9 1979 g_gg

3 Therral Evaluation 31 Discussion The Model 820 is a ec=pletely passive ther=al device and has no techanical ecolin6 system nor relief valves. All cooling of the package is througn free convection and radiation. The heat source is 1000 curies of iridium-192. The corresponding decay heat is 8.58 vatts.

32 Summary of Thermal Froperties of Materials The celting points of the retals used in the construction of the Model 820 are:

Titanium 3308c?

(182C C)

Steel 2453 F (1345 C) 0 Cranium 2070 F (1133 C) 0 0

Copper 1940 F (10o0 C) 3ronze 18h0 F (1005 C) 0 0

The polyurethane "ca has a =inimum operating rnnge of -100 F

(-73cC) to 200 F 03cC).

It will decc= pose at *he fire test

).

Decomposition will result in gasecus 0

temperature (800 byproducts which will burn in air.

33 Technical Specifications of Components Not Applicable 3.4 Ucr=al Conditions of Transport 3.k.1 Therral Model The heat scurce in the Model 820 is a maximum of 1000 curies of iridiuu-192. Iridium-192 decays with a total energy liberation of 1.h5 MeV per disintegration or 8 58 millivatts per curie.

Assurin6 that all of the decay energy 'is transformed into heat, the heat generation rate for the 1000 curies of irid;u=-192 vculd be 8 58 vatts. For this analysis, the beat source vill be assured to be 10 watts.

To de custrate ecmpliance *:ith the requirements of paragraphs 231 and 232 of IAEA Safesv series 30. 6, 1973 for Type 3(U)-packaging, an analysis is presented in Section 3.6.

The thermal codel empicyed is described in that analysis.

To de=cnstrate ccmpliance with the recuirements of paragraph 240 cf IAEA Safety Series No. 6, 1973 for Type 3(U) packaging, a separate analysis is presented in Secticn 3 6.

The the mal codel emp]cyed is described in that analysis.

REVISION O 40'V. C 91979 3-1 1636 237

3.h.2 Maximum Temperatures The maximum temperatures encountered under normal conditions of transport vill have no adverse effect on structural integrity or shielding. As shown in Section 3.6, the maximum temperature in the shade vould be less than hh0C and the maximum temperature when insolated would be less than Th0C.

3.k.3 Minimum Temperatures The mini =um nor=al operating temperature of the Model 820 is ho F 0

(-h0 C). This temperature vill have no adverse affact on the package.

3.h.h vaximum Internal Pressures Nomal operati.g conditions generate negligible internal pressures.

Any pressure generated is significantly below that of the hypo-thetical accident pressure, which is shown to result in no loss of shielding or contain=ent.

3.h.5 Maximum Ther=al Stresses The =aximum temperatures that occur during no =al transport are lov enough to insure that ther=al gradients will cause no significant themal stresses.

3.k.6 Evaluation of Package Perfor=ance for Normal Conditions of Transport The thermal conditions of nc=al transport are insignificant frcm a functional viewpoint for the Model 820. The applicable ecnditions of IAEA Safety Series No. 6,1973 for Type 3(U) packages have been shcwn to be satisfied by the Model 820.

35 Hypothetical Accident Themal Evaluation 351 Themal Model The Model 820, including the source assemblies, is assured to reach the the m al test temperature of 800 C.

At this temperature the pchurethane fcam vill have deccepcsed and the resulting gases will have escaped the package thrcugh vent holes and non-leak tight asse=bly joints.

352 Package Conditions and Envirennent The Model 820 underwent no significant damage during the free drop and puncture tests. The package used in this analysis is censidered undamaged.

1636 238 3-2 REVISICN O

'C. O 9 :;7;

353 Package Te=peratures As indicated in Section 3 51, the entire package is assumed to 0

reach a temperature of 800 C.

Examination of the =elting te=pera-tures of the raterials used in the construction of the Model 820 indicates that there vill be no da= age to the package as a result of this temperature. The possibility of the formation of an iron-uranium eutectic alloy was addressed in Section 2.4.1 where it was concluded that the fomation of the alloy was not a likely eventuality.

3 5.4 Maximum Internal Pressures The Model 820 packaging is open to the atmosphere. Therefore, there vill be no pressure buildup within i.he package.

In Section 3.6, an analysis of the scurce capsules under the thermal test condition de=onstrates that the =aximum internal gas pressure at 800 C is 55 psi (380 kN/=2),

0 The critical location for failure is the veld. An internal of 291 psi (2.0 ?G/=2)0 kN/=2) vill generate a maximum stress pressure of 55 psi (18 o

At a te=perature of 870 C (1600 7),

the yield strength of Type 304 stainless steel is 10,000 psi (69ra/=2),

Thus, at 800 C, the maximu= stress in the source capsule vould be only 3% of the yield strereth of the =aterial.

355 yaxi=u= Thermal Stresses There are no significant themal stresses generated during the ther al test.

3 5.6 Evaluation of Package performance The Model 820 vill undergo no loss of structural integrity or shielding when subjected to the ther=al accident condition. The pressures and te= pert.tures have been demonstrated to be within acceptable limits.

EEVISION O 3

NOV. C 9 :,5,a 1636-239

36 AP M DIX 3 6.1 Model 82o Type B(U) Thermal Analysis: Paragraphs 231 and 232 of IAEA Safety Series No. 6,1971 3 6.2 Model 820 Type B(U) Ther=al Analysis: Paragraph 240 of IAEA Safety Series No. 6, 1973 3.6.3 Iridium Source capsules Ther=al Analysis

,_h REVISION O

cy. C 0 *;79 1636~240

3.6.1 Model 820 Type 3(U) Therral Analysis Paragraphs 231 and 232 of IAEA Safety Series No. 6,1973 This analysis de=enstrates that the maximu= surface te=perature of the Model 820 vill not exceed 50 C vith the packaSe in the shade and an a=bient tempera-ture of 38 C.

To assure conservatis=, the following are used:

1) The entire decay heat (10 watts) is deposited in the exterior faces of the Model 820.

2) The interior of the Model 820 is perfectly insulated and heat transfer occurs only frc= the exterior vall to the atmosphere.

3) Eecause each face of the package eclipses a different solid angle, it is assu=ed that twenty five percent of the total heat is deposited in the s=allest face (top).

k) The only heat transfer =echanis: is free convection.

Using these assu=ptions, the maxi =u= vall temperature is found frc=:

hA (T -T) q

=

y a

where q: Heat deposited per unit ti=e in the face of interest (2 5 vatts) h: Free convective heat transfer coefficient for air (1 57(AT)*

v/=2_oC)

A: Area of the face of interest (0.193=2)

T: Maxi =u= te=perature of the vall of the package y

T: A:foient te=perature (3800) a Frc= this relationship, the maxi =u= te=perature of the vall is 43.h C.

This saticfies the require =ent of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 1636 241 3-5 REVISION O Not/ O o 197g

3 6.2 Model 820 Type B(U) The: ::a1 enalysis Paragraph 240 of IAEA Safety deries No. 6,1973 This analysis demonstrates that the maxbum surface temperatures of the Model 820 vill not exceed 820C when the package is in an ambient temperature of 380C and insolated in accordance with paragraph 240 of IAEA Safety Series No. 6, 1973 The calculational model consists of taking a steady state heat balance over the surface of the package. The following assumptions are used.

2

1) The package is insolated at the rate of 775v/m2 (800 cal /cm - 12h) onthetopsurface,388v/m2 (400 cal /cm2 - 12h) on the sides, and no insolation on the bottom.

2) The decay heat load is considered negligible.

3) The package has an unfinished stainless steel surface.

The solar absorptivity is assumed to be 0 9 The solar emissivity is assumed to be 0.8

4) The package is assured to undergo free convection frcm the sides and top, and undergo radiation frcm the sides, top and bottc=.

The inside faces are censidered insulated so there is no conduction into the package. The faces are considered to be sufficiently thin that no temperature gradients exist in the faces.

5) The package is approx hated as a right circular cylinder resting cn 2

an end. The surface areas of the top and bottom are each 0.193m,

2 The surface area of the side is 0 719m,

The =axi=um surface temperature is established frcm a steady state heat balance relationship.

q in q out

==

q

+ g

=

r where q: Convective Heat Transfer q,:

Radiative Heat Transfer The heat lead applied to the package is q in = c( q, absorptivity (0 9) where c( :

Solar heat lead (h29 vatts) q,:

1636 242 3-6 EE7:3:Cq O NOV. O G 1973

The convective heat transfer is:

9. c. =

-(hA) top (hA) ides. (T -T)

+

s v

a where h: Convective heat transfer coefficient A: Area of surface of interest T: Temperature of vall y

T: Ambient Te=perature a

The heat transfer due to radiation is:

o6 A(T

- T,b) q,

=

y where c: Stefan Bolt::: ann Constant c: E::lissivity (

0.8)

Iteration of this relationship demonstrates that the vall temperature of the Model 820 is 73.8 C which satisfies the requirement of paragraph 240 of IAEA Safety Series No. o, 1973 1636 243 3-7 REVISION O NOV. O 91979

3 6.3 Model 820 Type B(U)

Source Capsules - Thermal Analysis Paragraph 238 of IAEA Safety Series No. 6, 1973 This analysis demonstrates that the pressure inside the source capsules used in conjunction with the Model 820, when subjected to the themal test, does not exceed the pressure which corresponds to the minimum yield strength at the themal test te=perature.

The source capsules are fabricated from stainless steel, Type 304 or 30hL.

The outside diameter of the capsules is 0.250 inch (6.35mm). The source capsules are seal velded. The minicum veld penetration is 0.020 inch

( 0 5=m). Under conditions of internal pressure, the critical location for failure is this veld.

The internal volute of the source capsules contains only iridium metal (as a solid) and air. It is assu=ed at the time of loading the entrapped 5

air is at standard temperature and pressure (20 C; 100kN/c ).

We contend that this is a conservative assumption because, during the velding process, the internal air is heated, causing some of the air mass to escape before the capsule is sealed. When the velded capsule returns to ambient temperatures, the internal pressure would be somewhat reduced.

Under conditions of paragraph 238 of IAEA Safety Series No. 6, it is assured that the capsule could reach a temperature of lhT5 F (COO C). Using the 0

ideal gas law and requiring the air to occupy a constant volu=e, the internal gas pressure could reach 373kN/=2 (Shpsi).

The capsule is c

.ed to be a thin-valled cylindrical pressure vessel.

The =aximu= longitudinal stress is calculated from:

PA gA1

=

p where 7: Longitudinal stress 1

A: Stress Area = 7 (r

_ ri 1

g

?: Pressure A: Pressure Area = 5 r p

1 Frca this relationship, the maximum longitudinal stress is calculated to be 89hkN/m2 (129 psi).

1636 244 3-8 REVI3 ION O NOV. O 91979

The hoop stress can be found by:

Pld 2, c hlt

=

t where rh: hoop stress 1 : length of the cylinder t

thickness of cylinder 2

Frcm this relationship, the hoop stress is calculated to be 196MN/m (28hpsi).

At a temperature of 1600 F (870 C), the yield strength of type 3Ch stainless C

steel is 10,000 psi (691G/m ).

Thus, under the conditions of paragraph 238 2

of IAEA Safety Series No. 6, 1973, the stress generated is less than 3% of the yield strength of the uterial.

1636 245

,_q I.ri' ION O

~'

NOV. C S 197s

h.

Containment h.1 Contain=ent Boundary h.l.1 Contain=ent Vessel The contairrent systems for the Model 820 are the radioactive source asse=blies as listed in Section 1.2 3 of this application. The actual contain=ent for the radioactive material is the velded source capsules as shown in Section 2.10.

These source assemblies are certified as special form radioactive materials (IAEA Certificate of Competent Authority No. USA /015h/S).

The capsules are fabricated frc= either Type 3Ch or Type 3OhL stainless steel. The capsules are rounded cylinders with a diameter of 0.25 inch (6.35==) and lengths of either 0 78 inch (19.8==)

or 0 97 inch (2h.6==).

h.l.2 Contairrent Fenetrations There are no penetrations of the contain=ent.

h.l.3 Seals and Welds The contairrent is seal velded by a tungsten inert gas velding process which is described in Tech / Ops Standard Source Encapsulation Procedure (Section T.4). The mini =um veld penetration is 0.020 inch (0 51==).

h.l.k Closure Hot Applicable k.2 Reauire=ents for Nomal Conditions of Transport k.2.1 Release of Radicactive yaterial The source assemblies have satisfied the requirements for Special For= Radicactive Material as delineated in IAEA Safety Series No. 6, 1973 edition and 10CFRT1. Therefore, there vill be no release of radicactive caterial under the nc=al conditions of transport.

h.2.2 Pressurization of the Containment vessel Pressurization of the source capsules under the conditions of the hypothetical thermal accident was de=cnstrated to generate stresses well below the structural limits of the capsule (See

}{ }f{

Section 3 5). Thus, trie contain=ent vill vithstand th e press e variations of ner=al transpcrt.

h-1 REVISION O NOV. 0 91979

4.2 3 coolant contamination Not Applicable 4.2.4 Coolant Loss Not Applicable 4.3 Containment Require =ents for the Hyrothetical Accident Condition 4.3 1 Fission Gas Products Not Applicable 4.3 2 Release of contents The hypothetical accident conditions of 10CFR71, Appendix 3 vill result in no loss of package contain=ent as shown in Sections 2 7 1, 2.7 2 and 3 5 l~636 247 4-2 REVISION O NOV. O 91979

5 Shieldir4 Draluation 51 Discussion and Results The Model 820 is shielded with 120 pounds of depleted uranium.

The uranium metal is cast around the titanium "J" tube. A radiation profile of Model 820 Serial No.1 containing 860 curies of iridium-192 was =ade.

The results of this survey are presented in Section 5 5 1.

Lctrapolation of this data to a capacity of 1000 curies of iridium-192 is presented in Table 5 1.

As the Model 820 has no neutron source, the gam a dose rates are the total dose rates which are presented. As shown in Table 51, the maxi =um dose rates are below the regu-latory requirements.

Table 5.1 Senry of Maximum Dose Rates (mR/hr)

At Surface At One Meter Side Top Ecttom Side T_o2 Ecttom 26 33 56 0.T 2.0 1.T 52 Source Specification 5 2.1 ca=a Source The ga mn source is iridium-192 in a sealed capsule as special form in quantities up to 1000 curies.

5 2.2 Neutron Source Not Applicable 53 Model Specification Not Applicable 5k Shielding Evaluation The Model 820 shielding evaluation was perfomed on Model 820, Serial No. 1 containing S60 curies of iridium-192. The results of this survey (Section 5 51) demonstrate that the dose rates surrounding this package are within the regulatory require =ents.

A radiation profile made on this package after being subjected to the PJpothetical accident conditicns, (Section 5 5 2) show that there was no significant change in the shielding effectiveness.

b f k0-5 -1 REVISION O NCV. 0 91979

55 Appendix 551 Radiation Profile - Model 820, serial :heber 1 552 Radiation Profile - Model 820, serial IAnoer 1 after hypothetical accident conditions 5-2 REVISION 6 NCV. 0 3 !;73

,636 249

551 RADIATION PROFILE Model 820 Serial No. 1 K

1 W

Containirg Source Assemblies Model A424-9 S.N.

6431 105Ci S.N.

6h28 10TCi S.N.

6425 108Ci S.N.

6h29 110Ci S.N.

6h26 109C1 S.N.

6h30 105Ci S.N.

6427 109Ci S.N.

6432 10TCi Total Activity:

860 curies of iridium-192 Maximum Dose Pates (=R/hr)

@ Surface

@ One Meter Top 28 17 Sides 22 0.6 Ecttc=

48 15 Measure =ents were =ade with an AN/FDR-27(J) Survey Instrument.

16 6 250 5-3 REVISION O NOV. 0 919??

552 RADIATION FROFILE Model 820 Serial No. 1 After Hypothetical Accident Conditions W

c x

Containing Source Asse=blies A424-9 and A42h-1 S.N.

6953 106Ci S.N.

6957 1c6Ci S.N.

6952 107Ci S.N.

6956 109Ci S. N.

6951 lo9Ci S.N.

6955 107Ci S.N.

9991+

107Ci S.N.

6954 99Ci Total Activity:

35 0 curies of iridiu=-192 Maximum Dose Rates (=R/hr)

@ Surface

@ Or.e Meter Top k0 15 Sides 20 0.7 3cttc=

30 1.0 Measurements eere =ade sith an AN/PDR-27(J) Survey Instrument.

1636 251 5-h REVISICN O NCV. C 9 :;;;

6.

criticality Evaluation Not Applicable REVISION O

'S' 6-1 1636~252

7 Ocerating Procedures 71 Procedures for Icading the Package _

The procedure for fabricating the special form source capsule is presented in Section 7.4.

The procedure for loading the source assemblies into the package is presented in Section 7.4.

72 Procedures for Unloadira the Package The procedure for unloading the package is presented in Section T.4.

73 Precaration of an moty Package for Transoort The procedure for preparation of an empty package for transport is presented in Section 7.4.

9 1636 2'53 REVISION O 7-1 NOV. O 91979

7.h Appendix Procedure for Encapsulation of Sealed Sources Model 820 Opeesting Fanual 1

254 7_2 REVISION O NOV. O 9 1979

RADIATION SAFETY MA? MAL Part II In Plant Operations Section 2 ENCAPSULATION OF. SEALED SOURCES A.

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

B.

General Require =ents The 192 Iridium loading cell shall be used for the encapsulation of solid metallic 192 Iridium and the packaging of sealed sources such 60 as 17%huliu=, 137 esium and 169Ytterbitm. Solid =etallic Cobalt C

not exceeding one curie =ay be handled in this cell also.

The =axi=um a=ount of 192Iridiumtobehandledinthiscellataks The =axi=um amount of 13 one time ehall not exceed 1000 curies.

to be handled in this cell at any one time shall not exceed 100 curies.

This cell is designed to be operated at less than et=ospheric pressure. The exhaust blower provided shall not be turned off except when the cell is in a decontaminated condition.

Sources shall not be storsd in this cell overnight or when cell is unattended. Unencapsulated =aterial shall be returned to the transfer containers and encapsulated sources transferred to approved source containers.

'4 hen any of the "through-the-vall" tools such as the velding fixture or transfer pigs are re=oved, the openings are to be closed with the plugs provided. These tools shall be deconta=inated whenever they are re=oved from the hot cen.

C.

Precaratory Procedure 1.

Check welding fixture, capsule drawer and =anipulator fingers from cell and survey for contamination. If contamination in excess of 0.001 A Ci of re=ovable contamination is found, these ite=s =ust be deconta=inated.

2.

If the welding fixture or the electrodes have been changed, perform the encapsulation procedure omitting the insertion of any activity. Examine this dm capsule by sectioning thru veld.'

'4 eld penetration =ust be not less than 0.020 inch.

REVISION O 7-3 NOV. O G 197; II.2.1 1636-255

If veld is sound and penetration is at least 0.020 inch, the preparation of active capsules may proceed. If not, the condition 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 manometer on the left side of the hot cell.

Thisisabout}inchofwaterforanewfilter. When this pressure differential rises to about 2 inches of water, the filter must be changed.

D.

Encapsulation Procedure 1.

Prior to use, assemble and visually inspect the two capsule components to determine if veld zone exhibits any misalign=ent and/or separation.

Defective capsules shall be rejected.

2.

Degrease tapsule ecmponents in the Ultrasonic Bath, using isopropyl alcohol as degressing agent, for a period of 10 0

minutes.

Dry the capsule components at 100 C for a minimum of twenty minutes.

3 Indert capsule components into hot cell with the posting bar.

4.

Place capsule in veld positioning device.

5 Move drawer of source transfer container into hot cell.

6.

Place proper amount of activity in capsule. Disposable funnel =ust be used with pellets and a brass rivet with vafers to prevent contamination of veld zone.

7 Remove unused radioactive =aterial frcm the hot cell by with-dz ring the draver of the source transfer container frcm the cell.

8.

Re=ove funnel or rivet.

9 Asse=ble capsule ec=ponents.

10. '4 eld adhering to the folleving conditicns:

Electrode spacing.021" to.024" a.

centered on joint +.002"; use jig for this purpose.

b.

Preflow argon, flush 10 seconds.

c.

Start 15 amps.

d.

'Jeld 15 amps.

e.

S1t-15 a ps.

f.

Ecst flov 15 seconds EVISION O 1636 256 73 m mg II.2.2

11. Visually inspect the veld. An acceptable veld =ust be continuous without cratering, cracks or evidence of blev cut. If the veld is defective, the capsule must be cleaned and revelded to acceptable conditions or disposed of as radioactive 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 wetted with EDIA solution or equivalent.

14. Count the patch with the scaler counting system. Patch must show no more than.00$p Ci of contamination. If the patch shows more than.005 pC1, the capsule =ust be cleaned and reviped.

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

15 Vacuum bubble test the capsule. Place t he velded capsule in a glass vial containing isopropyl alcohol. Apply a vacuum of 15 in Hg(Gauge). Any visual detection of bubbles will indicate a leaking source.

If the source is determined to be leaking, place the source in a dry vacuum vial and boil off the residual alcohol. Reveld the capsule.

16. Transfer i,he capsule to the svaging fixture.

Insert the vire and connector assembly and svage. Hydraulic pressure should not be less than 1250 nor = ore than 1500 pounds.

17.., Apply the tensile test to asse=bly between the capsule and connector by applying proof load of 75 lbs. Extension under the load shall not exceed 0.1 inch.

If the extension exceeds 0.1 inch, the source must be disposed of as radioactive vaste.

18. position the source in the exit port of hot cell. Withdraw all personnel to the control area. Use remote control to insert source in the ion chamber and position the source for maxi =um response. Record the meter reading. Compute the activity in curies and fill out a temporary source tag.

19 Using re=ote control, eject the source from cell into source changer through the tube gauze vipe test fixture. Monitor before reentering the hot cell areato be sure that the source is in the source changer. Re=ove the tute gauze and count with scaler counting system. This assay =ust show no more than 0.005 pC1.

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

20.

Cceplete a Source Loading Log (Figure II.2.1) for the operatien.

1636~257 T-5 REVISION O II.2 3 NOV. O G mo

TECH /0PS MODEL 820 SOURCE CHANGER - SHIPPING CO:TfAINER OPERATION MANUAL Technical Data Size:

19 5 in. dia=eter, 21 5 in. high (495 =m dia=eter, 546 m high)

Capacity:

1000 Curies of 192 Iridium Special Fom Transport Status:

Type B USNRC USA /

/3 IAEA USA /

/B(

)

Shielding:

Depleted Uranium Metal 120 Lbs. (55kg)

General The Model 820 Source Changer - Shipping Container is designed for transferring encapsulated radioisotope sources into radicEraphic devices and for transporting these sources.

The U.S. Nuclear Regulatory Co=ission allevs the use of this source changer only if the user is specifically nuthorized by the te=s of his license.

If the user is not authoriced to =ake source excr.cges, contact Technical Operations, Inc.

It has personnel who are authorized to perfer= this operation.

If the user wishes to be licensed to nake source exchanges, application should be =ade to:

Radioisotope Licensing Eranch Division of Fuel Cycle and :'aterial Safety U.S. :hiclear Regulatory Cc=ission Washington, DC 2C555

'636 258

-5 REVISION O NOV. 0 91979

milil Prior to the first shipnent of this source changer, the user, in addition should register with:.

Transportation Branch Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Co= mission Washington, DC 20555 Shippir4 Information When the 820 Source Changer is shipped to the user the following items are included in addition to the radioisotope sources.

1.

For Sach Source a.

Source decay chart b.

Source leak test certification c.

Verification of source physical di=ensions d.

Source identification tag 2.

Tamperproof Seal 3

Return Shipping Labels h.

Instruction Manual

- NOT3 -

The user is urged to perfom.the source changing operation as soon as possible after receipt and to return the source changer immediately upon completion of the changing operation. Only in this vay can ve keep these source changers in continued use.

Feceipt 1.

Upon receipt of the source changer, survey the container on all sides to ensure radiation levels do not exceed the following:

Surface 200mR/hr At One Meter 10nR/hr 2.

Check surface of container for obvious damage.

3 Check Invoice and Bill of Lading to ensure all are intact 1636 259 and are representative of the ship =ent.

REVISION O T-7 NOV. O 91979

Receipt (Continued) 4 If there are any discrepancies in Ite=s 1-3 above, do not use the source changer and contact Technical Operations, Inc.

Ir=ediately to resolve discrepancy.

(Tel: 800-225-7383 Telex 9h9313) 5 If ite=s 1-3 are determined to be in order, place the source changer in a restricted area until ready to use.

Operation

- NOTE -

Tersonnel perfer=ing source changing operation must have a calibrated and operational survey =eter with a range of at least 0-1000 =R/hr.

In addition, personnel =onitoring devices must be worn during these operations. They are, a fil= badge (or Ther=olu=inescent Dosi=eter, TLD) and a direct reading pocket dosi=eter.

(10CFR34.33) 1.

Survey the centainer on all sides and ensure radiaticn levels are not in excess of 200 =R/hr on the surface nor 10 =R/hr at one =eter frc= any surface.

2.

Place the source changer and the projector (s) to be leaded in a restricted area which is properly identified.

3 3reak the seal vire, unfasten the bolts and re=ove the top.

4.

To transfer the source from the projector to the source changer:

a.

Connect the control unit to the projector as for an expcsure.

b.

Connect one length of scurce guide tube to the projector and to the e=pty hole on the scurce changer.

c.

Ensure the lock is open and the scurce guides are closea-1 96 ?40 REVISION O T-8 NOV. 0 91979

die d.

Ensure that there are no unauthorized personnel in the restricted area and place the projector in the operate condition.

Leave the area of the projector and source changer e.

and, using the control unit, crank the source frcm projector to the source changer.

f.

Approach the projector observing the survey neter.

Survey the projector on all sides to ensure the source has been properly transferred. The radia-tion level at the surface of the projector should be less than the original survey readings observed.

g.

Approach the source changer observing the survey

=eter and verify that the source is in the proper stcrage position.

h.

Depress the plunger lock to lock the source in the storage position.

1.

Open the source guides and disconnect the scurce assembly.

J.

Disengage source guide tube from source changer.

k.

Re=ove source ID tag frcm projecter and attach to guide tube opening on source changer. Se sure the proper ID tag is attached to the proper source.

5 To transfer a source frcm the source changer:

, Survey the source changer on all sides to ensure a.

the sources are properly stored.

b.

Survey the projector to ensure it does not have a source in it.

Ccnnect the source changer to the projecte-using c.

one length of source guide tube.

d.

Crank the centrol unit drive cable thrcugh the projecter until the male connector end protrudes beyond the guide tube enough to take connection to the source.

Ccnnect the scurce to the centrol unit drive cable, e.

f.

Close the source guides.

g.

Ensure all unauthorized personnel are cut of the restricted area.

1636 261 REVISION O 7-9 NCV. O 91979

t h.

Unlock the plunger lock on the source changer.

1.

Return to the centrol unit and crank the source drive in the retract d!.rection until the scurce' is stored in the projector.

J.

Approach the projector observire the survey meter and survey on all sides to ensure the source is in the proper stored position.

k.

Icek projector and disconnect guide tubes and control unit.

1.

Remove source ID tag from source changer and attach to projecter.

6.

When source transfers are ecmpleted, insure all sources are properly stored and locked in the exnarce changer.

Source guides =ay be left open.

7 Place the cover on the source changer and instcll all bolts.

8.

To return source changer:

a.

Safety lock vire the changer and crimp lead seal.

b.

Survey container at the surface and at one =eter, and determine prcper shipping label in accordance with Table I.

1636 262 REVISION O m. 0 9 1979 7-10

TABLE I Su rfa ce 3 Feet EDI0 ACTIVE-WHITE..I.

/

O,W\\

s s

a 0.5mR/hr None

/(

',3 N RADIDACTIVE s=

N r'/

N Nj RADIOACTIVE.-YELLOW II 6.

's

/

a

's 50mR/hr 1.0mR/hr

's RADl0ACIIVE~i-;F ',')

2

],'

N r,'

\\

s/

RADIOACTQ'E-YELLOW III

'N N

N

/

N

/

s 200mR/hr 10mR/hr

( s A0:0ACIWE@,2

\\Y e'

a

\\:

i 7

g 7

v c.

Fill out infc=ation requested on label indicating:

Contents (Isotope) a.

b.

No. of Curies c.

Transport Index The Transport Index is determined by observing the maximus reading. at 1 nster frcm the source container. This reading becomes the Transport.

Index.

1636 263 P0~0R0IlGN'lIL fl REVISION O T-11 NOV. o 9 :s73

i d.

Remove all old shipping labels.

- NOTE -

Do not remove retal container identification label.

e.

Affix new shippir4 labels to two opposite sides.

f.

Properly co=plete the shipping papers indicating:

Proper shipping name (i.e. Radioactive Material, Special Form, n.o.s.)

Name of Radionuclide (i.e.192Iridiu=)

Physical or chemical for= (or Special Form)

Activity of Source (expressed in curies or

=illicuries)

Category of Label applied (i.e. Radioactive Yellow III)

Transport Index USURC Identiff. cation Number For export shipments, IAEA Identification Nu=ber Shipper's Certification:

"This is to certiff that the above named raterials are properly classified, described, packaged, marked and labeled and are in proper condition for transport according to the applicable regulations of the Department of Transportation."

Notes:

1.

For air shipments, the following shipper's certification =ay be used:

"I hereby certiff-that the contents of this consign =ent are fully and ' accurately described above by proper shipping name and are classified, packed, marked and labeled and are in proper condition fer carriage by air according to applicable national governmental regulations".

2.

For air shipcents, the package =ust be labeled with a " CARGO AIRCRAFT ONLY" label and the shippirq papers must state:

1636~264 REVISION O N ov. 0 9 5 2 T-M

"THIS SHIBM IS WITHIN THE LIMITATIONS F.iESCREED FOR CARGO-ONLY AIRCRA7r.

G.

Return the container to:

Technical Operations, Inc.

h0 North Avenue Burlington, MA 01803 USA Dreparation of an Emoty Package for Transport 1.

To prepare an e=pty package for transport, follow the instructions of the operating procedure above beginning with Step 8 with the following exceptions:

The package =ust be marked " Radioactive yaterial -

a.

LSA-?;O S".

b.

The proper shipping name is Radioactive Material -

LSA-n.o.s.

c.

Radionuclide is Depleted Uraniu=.

i636 265 REVISION O NOV. O 5 :s7g 7-13

8.

Acceptance Tests and Mai:.tenance Proeram 8.1 Acceptance Tests 8.1.1 Visual Inspection The package is visually examined to assure that the appropriate fasteners are properly seal wired and that the package is properly

=arked.

The seal veld of the radioactive source capsule is visually inspected for proper 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 load of seventy five pounds. Failure of this test will prevent the source assembly from being used.

8.1 3 Leak Tests The radioactive source capsule (the primary contain=ent) is wipe 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 wipe test for radioactive contamina-tion. These tests are described in Section T.h.

Failure of any of these tests vill prevent use of this source assembly.

8.1.4 Ccmponent Tests The lock' asse=bly of the package is tested to assure that the security' of the source vill be maintain ~ed.

Failure of this test will prevent use of the package until the lock assembly is corrected and retested.

8.1 5 Tests for Shielding Integrity l'he radiation levels at the surface of the package and at three feet frcm the surface are measured using a small detector survey instrument (i.e. AN/PI:R-27). These radiation levels, when extrapolated to the rated capacity of the package, =ust not exceed 200 =illiroentgens per hour at the surface nor ten millircentgens per hour at three feet from the surface of the package. Failure of this test vill prevent use of the package.

8.1.6 Ther=al Acceptance Tests Not Applicable 1636 26~6 8-1 REVISION O NOV. O 91573

8.2 Maintenance Program 8.2.1 Structural and Pressure T* ^,s Not Applicable 8.2.2 Leak Tests As described in Section 8.13, the radioactive source asse=bly is leak tested at =anufacture. 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.h, prior to each use of the package. Additionally, the package is inspected for tightness of fasteners, proper seal wires and general condition prior to each use.

8.2.4 Valves, Rupture Discs and Gaskets Not Applicable 8.2 5 Shielding

?c.or to each use, a radiation survey of the package is =ade to a :ure that the radiation levels do not exceed 200 milliroentgens psr hour at the surface nor ten milliroentgens per hour at three feet frcm the surface.

8.2.6 Ther=al Not Applicable 8.2 7 Miscellaneous Inspections and tests designed for secondarf users of this package under the general license provisions of 10CFRT1.12(b) are included in Section T.k.

1636.267 REVISION Q 8-2 NOV. O e ;sn,.,

l'1 i u x.