ML19320B438

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Application for Renewal of Certificate of Compliance 9053 for Model 683 Type B
ML19320B438
Person / Time
Site: 07109053
Issue date: 06/13/1980
From:
TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:
Shared Package
ML19320B436 List:
References
NUDOCS 8007100376
Download: ML19320B438 (52)
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Ra$aton Products Divison 40 North Avenue Burkngtori Massachusetts 01803 Te' phone (617) 272 2000 e

i PACKAGE DESCRIPTION TECHNICAL OPERATIONS MODEL 683

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General Information 1.1 Introduction The Tech / Ops Model 683 shipping container is designed for use as Type B packaging for the transport of the Tc h/ Ops Model 683 gamma ray projector containing Iridium-192 as a sealed radioactive source in special form. The Model 683 shipping container conforms to the 71 and criteria for Type B packaging in accordance with 10CFR Part satisfies the criteria for Type B(U) packaging in accordance with IAEA Safety Series No. 6, 1973 Edition.

1.2 Package Description i

1.2.1 Packaging The Model 683 shipping container consists of an outer steel drum with inside dimensions of 18.5 inches (470mm) diameter and 14.25 inches (362mm) high. The steel drum is fabricated from 18 gauge (.048 inch,

,(1.2mm thick) steel, MS27683-7.

The gross weight of the package containing the Model 683 gamma ray projector is 85 lbs. (39kg).

The steel drum is closed by means of a cover secured by a clamp ring

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The head closure is fastened by means of a bolt drilled head closure.

for a seal wire to provide a tamper proof seal.

Inside the drum is a molded rubberized hair filler. This filler is

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molded to conform to the configuration of the Model 683 gamma ray projector.

The radioactive source assembly is contained inside the Model 683 gamma ray projector. The radioactive material is sealed inside a stainless steel source capsule. The capsule acts as the containment vessel for the radioactive material. The gamma ray projector provides shielding for the radioactive source and also provides a means of securing the radioactive source in its proper storage position.

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Des-criptive drawings of the Model 683 shipping container and gamma ray projector are provided in Section 1.3.

1.2.2 Operational Features The Model 683 gamma ray projector with the proper guide tubes and controls is installed in the shipping container and positioned so that it' fits securely in the molded rubberized hair filler. Ihe top The plate of.the molded filler is set in place over the projector.

containet-top is covered with the lid. The clamp ring is then placed' around the lid and the bolt is tightened. A seal wire is inserted through the bolt and nut to provide a tamper proof seal.

Revision 0 1-1 13 June 1980

A 1.2.3 Contents of the Package The Model 683 package is designed to be a shipping container for the Tech / Ops Model 683 gamma ray projector.

The maximum-radioactive contents would be 120 curies of Iridium-192 as Special Form radioactive material (Source Model No. A68309). This source assembly satisfies the criteria for Special Form radioactive material in accordance with 10CFR Part 71 and IAEA Safety Series No.6, 1973 Edition (Section 2.8).

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4 1.3 Appendix 1.3.1 Descriptive Assembly Drawing, Model 683 Type B Shipping Container 1.3.2 Descriptive Assembly Drawing, Model 683 Gamma Ray Projector 1.3.3 USNRC Certificate of Compliance USA /9053/B 1

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HAND CRANtf SHIPPING PLUG KEY LOCKED 4' SEAL WIRED MOULDED FILLER STEEL bl?UM 19 !Ie. DIA.X 15'lll6ll RUBBE2/2ED HAIR MS 29683 IB 6 A.

TOTAL WEIGHT - 89 L BS.

AoVG TE CHNICAL OPER ATIONS INC TYPE B SHIP. PING CONTAINE2 ASf ggy, k

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(sr srt) 3 YELL (!/8 NX CR STEEL WELD'T)

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  • I U I3' U s. NUCL[ AR nE GUL ATon Y COr.1 MISSION l

10 Cf n 71 CEnTIFICATE OF COMPLI ANCE

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1.lal Certificate Number 1.(b) Revision No.

1.lcl P.*cLane hfennlication No.

90 9 1

USA /9053/B( )

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1.ld) Pages No 1.le] Jotal No. P a.

2. PRE ARABLE
  • *f'i 2.lal This certificate is issued to satisfy sections

,. N 'e Maierials Regulations (49 CFR 170189 anct 14 CFR 103l and Sections 14G-19-10a and 14G ransportaiton Paran Transponation Dangerous Caepoes Regulations (40 CFR 14G-1491, as amentfas. 100 of the Orpartment of 2.lbl The packno;no and contents desceilic<t in item s below, meris the satety standaerts ses forth in Subpa Fssferal Regulat.ons, T' art 71. Packaging of Raticactive e 10. Corse of Ceenain Conrhtions/*

Materials for Transpoet and Tsansportation of Radioactive Maireial Unde

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Transportai.on or other applicable regulatory agencies, including th 9

will be transponed.

epa <iment of which the packar, S'T t*

3. This certificant is issued on the basis of a safety analysis scoort of the package clesign or application-
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Prepared by (Name and address):

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Title anel idensification of seport or application:

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Technical Opera tions, Inc.

Technical Operations, Inc. application dated l

Northwest Industrial Park April 11,1975, as supplemented

-.1 Burlington, Massachusetts 01803 a

3.ici ooche No.

71-9053 4.

CONDITIONS

,This testificate is conditional upon the futhiting of the sequisements of Suboart O of 10 CFR 71 g

an seem s below.

, as apot; cable, anc the conditions specific

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s. oesteiption of Packaging and Authorised Contents Modet Nurnber, Fiss.te Ctass. other Conditions, a

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V (a) Packaging

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(1) Model No.:

683 (2)

Description A radiographic exposure device contained within a protective overpack, i

The overpack is an 18-gage, MS27683 steel drum with a bolted and seal

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wire clamp closure ring.

The drum is filled with molded rubberized hair to maintain a snug fit.

Overall dimensions are 19.5" diameter x 15" high.

The radiographic exposure device consists of an ll-gage carbon steel shell, depleted uranium shielding, zircalloy "S" tube, polyurethane filler material,' source shipping plug and lock assembly.

__,,,I Gross weight of the package is approximately 89 lbs.

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(3) Drawings

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

C68302;C68302-1, 3, 4: C68303: B68303-1, Sh. 2; B68302-9, 068307-1; A68307; A68308-lC; A86302-8; A68311; A68309-9.

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Page 2 -' Certificate tio. 9053 - Revision No.1 - Docket No. 71-9053 iV 1

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Contents

.1 (1) Type and form of material

.a Iridium-192 as sealed sources that meet the requirements of special

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form as defined in 571.4(o) of 10 CFR Part 71.

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(2) Maximum quantity of material per package

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{ig Source assemblies for use in this packaging are limited to those assemblies 4;

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as identified in Technical Operations, Inc. Drawings t;os. A68309, and C68310.

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?!ameplate shall be fabricated of materials capable of resisting the fire

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test of 10 CFR Part 71 and maintaining their legibility.

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  • The packaging authorized by this certificate is hereby approved for use under the general provisions of Paragraph 71.12(b) of 10 CFR Part 71.

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Expiration date:

July 31, 1980.

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...!u REFERENCES f,

'( j Technical Operations, Inc. application dated April 11, 1975.

pp 8d Supplement dated:

June 6, 1975.

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FOR THE U.S. NUCLEAR REGULATORY COMMISSIO:

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Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and f?]...

Material Safety

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Structural Evaluation 2.1 Structural Design 2.1.1 Discussion Structurally the Model 683 consists of three components: a source capsule, gamma ray projector and outer packaging. The outer packag-ing consists of a molded rubberized hair filler contained in a steel drum. The source capsule is the primary containment vessel. It satisfies the criteria for special form radioactive material. The gamma ray projector fulfills two functions. It provides shielding for the radioactive material and with its lock assembly secures the source assembly in the proper shielded position.

The outer steel drum is fabricated from 18 gauge (.048 inch, 1.2mm thick) steel, MS 27683-7, with inside dimensions of 18.5 inches (469.9mm) diameter and 14.25 inches (362mm) high. The steel drum is closed by means of a cover with gasket (MIL-5-6855) and secured by a clamp ring head closure. The head closure is fastened by means of a bolt drilled for a seal wire to provide a tamperproof seal. The steel drum is lined with a molded rubberized hair filler. This filler is molded to conform to the shape of the Model 683 gamma ray projector, guide tubes and controls to be transported.

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The outer housing provides the structural strength of the package and also ensures that the gamma ray projector cannot be accidentally removed from the package and damaged. The filler prevents against shif ting lof the contents during transport and also prevents damage to the contents. The gam =a ray projector secures the source assembly in the shielded position and assures positive closure.

2.1.2 Design Criteria The Model 683 shipping container is designed to comply with the requirements of 10CFR Part 71 and IAEA Safety Series No. 6,1973 Edition. The package is simple in design..There are no design criteria which cannot be evaluated by straight forward application of the appropriate section of 10CFR Part 71 of IAEA Safety Series No. 6.

2.2 Weights and Centers of Gravity The Model 683 shipping container weighs 85 lbs. (38.6kgs) with a Model 683 gamma ray projector secured for shipment. The center of gravity was determined empirically. It is located along the cylindrical axis at a distance of 7 inches (0.18m) above the bottom surface at the geometrical center of the package.

Revision 0

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13 June 1980 2-1

2.3 Mechanical Properties of Materials The Model 683 housing is fabricated from cold rolled low-carbon sheet steel. This material has a yield strength of 65,000 pounds per square 2

inch (448MN/m ),

(Re ference : Machinery's Handbook, 21st Edition, P. 2118 Edgecomb's Buyers Guide p. 264 Ryerson Data Book 1967, p. 17 A drawing of the source capsule shipped in the Model 683 package is enclosed in Section 2.10.

For a description of the Model 683 gamma ray projector see Section 1.3.

The source assembly consists of a source capsule fabricated from Type 304 or Type 304L stainless steel with a yield strength of 35,000 pounds per square inch (241MN/m ),

2 The source capsule is swaged to a "Teleflex" steel cable. The capsules are sealed by tungsten - inert gas welding. The swaged coupling is tensile tested on a production basis to 75 pounds (334 newtons)

(See Section 7.4).

2.4 General Standards f'or All Packages 2.4.1 Chemical and Galvanic Reactions The materials used in the construction of the Model 683 shipping

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container are a molded rubberized hair filler and low carbon steel for the outer housing. There will be no significant chemical or galvanic action between these components.

2.4.2 Positive Closure The source assembly of the gamma ray projector in the Model 683 shipping container cannot be exposed without opening a key operated lock on the projector. Access to the lock on the projector requires removal of the Model 683 cover. Ine cover is sealwired which provides a tamperproof seal.

2.4. 3 Lifting Devices The Model 683 shipping container is designed without any lif ting devices.

The entire container must be lif ted from either end during transport.

2.4.4 Tiedown Devices The Model 683 shipping container has no tie down devices. To secure container during transport requires the use of restraining devices t

that wrap around container.

Revision 0 l

13 June 1980 2-2

4 2.5 Standards foe Type B and Large Quantity Packages 2.5.1 Load Resistance Considering the package as a simple beam supported on both ends with a uniform load of five times the package weight evenly distributed along its length, the maximum stress can be computed from:

S = F1 8Z where S = Maximum Stress F = Total Load (425'lbs; 1.88kn).

1 = Length of Beam (15.6 in; 396.2mm) 8 3

Z = Section Modulus (13.45 in ; 207,500em )

(

Reference:

Machinery'? Handbook, 21st Edition, p. 404)

The load is assumed to be 425 lbs (1.88kh). The container is assumed to be a hollow cylinder with an outside diameter of 18.6 inches (472.3mm), a wall thickness of 0.048 inch (1.2mm) and a length of 15.6 inches (396.2mm). Consequently, the section 8

8 modulus of the beam is 13.45 in (207,500mm ).

Therefore, the maximum stress generated in the beam is 61.6 pounds 2

per square inch (0.42MN/m ) which is far below the yield strength 2

of the material at 65,000 pounds per square inch (448Ud/m ),

2.5.2 External Pressure The Model 683 shipping container and the Model 683 gamma ray projector are open to the atmosphere. Therefore, there will be no differential pressure acting on them. The collapsing pressure of the source capsuler is calculated assuming that the capsules are thin wall tubing with a wall thickness equal to the minimum depth of weld penetration (0.20 inch; 0.5mm). The collapsing pressure is calculated from:

P = 86,670 t:,- 1386 d

where P: Collapsing pressure in pounds per square inch t: Wall thickness (0.02 inch) d: Outside diameter (0.25 inch)

(

Reference:

Machinery's Handbook, 21st Edition, p. 440)

The collapsing pressure of the source capsules is calculated to be 2

5547 pounds per square inch (58EN/m ).

Therefore, the source capsules can withstand an external pressure of 25 pounds per square inch gauge.

t Revision 0 13 June 1980 2-3

2.6 Normal Conditions of Transport 2.6.1 Heat The thermal evaluation of the Model 683 shipping container is performed in Section 3.

From this evaluation, it can be concluded that the Model 683 can withstand the normal heat transport condition.

2.6.2 Cold The metal used in the manufacture of the Model 683 barrel can with-stand a temperature of -40 F (-40 C).

The molded rubberized hair filler can also withstand temperatures

~ of less than -40 F (-40 C).

Therefore, it is concluded that the Model 683 shipping container will withstand th> normal transport cold conditions.

2.6.3 Pressure The Model 683 transport package containing the Model 683 gamma ray projector is open to the atmosphere; thus, there will be no differen-tial pressure acting on the package. In Section 3.5.4, it is demon-strated that the source capsules are able to withstand an external 2

pressure reduction of 0.5 atmospheres (50.7kn/m ),

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2.6.4 Vibration The Model 683 shipping container (Certificate of Compliance USA /9053/B) has been in use for five years. During that time, there have been no vibrational failures reported.

On that basis, we contend that the Model 783 package will not undergo a vibrational failure during transport.

4 2.6.5 Water Spray Test The water spray test was not actually performed on the Model 683 shipping container. We contend that the materials used in construc-tion of the Model 683 are all highly water resistant and that exposure to the water will not reduce the sh' iding or affect the structural integrity of the package. During t'. e five year period the Model 683 shipping container has been in use, no failures due to exposure to water have been reported.

2.6.6 Free Drop The drop analysis performed in Section 2.7.1 is sufficient to satisfy the requirements of the normal free drop condition. On this basis, we conclude Revision 0 13 June 1980 2-4

that the Model 683 transport package will withstand the free drop without loss of shielding effectiveness or loss of package integrity.

2.6.7 Corner Drop Not Applicable 2.6.8 Fenetration A penetration test of the Model 683 shipping container was not actually performed. We contend that the materials used in the construction of the Model 683 barrel are highly resistant to penetration. Furthermore, the nature of the shipping package is such that the. source assembly is secured inside the gamma ray projector which is centered inside the container surrounded by the rubberized hair filler.

It is impossible to penetrate the siipping cc.,tainer and affect the integrity of the source assembly irside the gamma ray projector.

1 2.6.9 Compression The gross weight of the Model 683 shipping container with the Model 683 gamma ray projector is 85 lbs (38.9kg). The maximum cross sectional area is 271.7 in2 2

(.18m ).

Thus, 2 pounds per square inch times the maximum

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horizontal cross section (543.4 lbs; 2420 newtons) is greater than five times the weight of the package (425 lbs; 1893 newtons).

The maximum stress generated on a cylinder of equal cross sections and a uniformly distributed load over the end surfaces can be computed from:

a = _0.24F

_ t' where a: maximum stress generated in the cylinder F: Load applied to the cylinder (543.4 lbs; 2420 newtons) t: Thickness of plate (.048 inch; 1.2mm)

(

Reference:

Machinery's Handbook, 21st Edition, p. 436)

From this relationship, the maximum stress generated in the cylinder 2

is found to be 56604 pounds per square inch (390MN/m ) which is less 2

than the yield strength of the raterial (65,000 psi; 448MN/m ).

There-fore, it can be concluded that the compression condition will not affect the package.

2.7 Hypothetical Accident Conditions ck-Revision 0 13 June 1980 2-5

e 2.7.1 Free Drop Prior to the submittal of the Model 683 shipping container application in April 1975, the Model 683 gamma ray projector was subjected to a drop test through a distance of 30 feet onto an asphalt driveway.

As a result of this test, there was no reduction of shielding effective-ness nor loss of radioactive material.

It.is concluded that the Model 683 gn=ma ray projector installed in the Model 683 steel drum will also satisfactorily meet the requirements of the Free Drop Test. In support of this evaluation, the Model 715 shipping container, a steel drum of similar construction, was subjected to a drop test through a distance of 30 feet onto a steel plate.

The Model 715 shipping container contained a Model 616 ga=ma ray projector during the test. Damage was limited to minor deformation and some crushing of tne insulating liner. There was no increase in radiation intensity nor loss of radioactive material.

(See Package Description, Technical Operations, Model 715, submitted 11 April 1980, Docket No. 71-9039).

2.7.2 Puncture Prior to the submittal of the Model 683 shipping container application in April 1975, the Model 683 gamma ray projector was dropped from a height of 40 inches onto a six inch diameter steel bar 8 inches high.

f-As a result of this test, there was no reduction of shielding effective-ness nor loss of radioactive material.

It is concluded that the Model 683 gamma ray projector installed in the Model 683 steel drum will also satisfactorily meet the requirements of the Free Drop Test. In addition, the steel drum affords protection to the lock assembly during these accident conditions, insuring that the locking mechanism will not fail and the source assembly remains secured in the shielded position.

2.7.3 Thermal The thermal analysis is presented in Section 3.5.

It is shown that the melting temperatures of the materials used in the construction of the Model 683 transport package, exegpt the molded rubberized hair filler, are all in excess of 1475 F (800 C).

The thermal test was not actually performed on the Model 683 transport package. However, the melting temperatures of the materials used in the Model 683 transport package are well above the thermal test temperatures.

It can be concluded that the Model 683 transport package will perform sat-isfactorily under the thermal test conditions.

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Revision 0 13 June 1980 2-6 t-

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A further evaluation demonstrates that the Metrefoam will undergo de-composition at the thermal test temperature. The gaseous byproducts will ignite in air. The Model 683 shipping container and gamma ray projector is not a sealed container, and thus will allow the gaseous byproducts of the Metrefoam to vent from the projector enclosure with-out pressure buildup sufficient to cause loss of the structural in-tegrity.

In conclusion, the Model 683 shipping container with the Model 683 gamma ray projector satisfactorily meets the requirements for the hypothetical accident thermal condition of 10CFR Part 71.

2.7.4 Water Immersion Not Applicable 2.7.5 Summary of Damage The tests designed to induce mechanical stress (e.g., free drop test) caused minor deformation, but no reduction in the safety features of this package. The thermal condition will result in no reduction of the safety of the package.

It can be concluded that the hypothetical accident conditions have no adverse effect on the shielding effectiveness or structural integrity

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of the package.

2,S Special Form The Nodel 683 shipping container is designed for use in transporting the Model 683 gamma ray projector containing the source assembly Model A68309. This source assembly has been certified as Special Form Radioactive Material under IAEA Certificate of Competent Authority No. USA /0154/S. A copy of this certificate is included in Section 2.10.

2.9 Fuel Rods Not Applicable Revision 0 13 June 1980 g:

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O 2.10 Appendix Descriptive Assembly Drawings of Sources IAEA Certificate of Competent Authority USA /0154/S.

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DATE DESCRIPTION A.

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DWG TITLE flNISH 192 TIRIDIUM SOURCE.. REFERENCE

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RESEARCH AND SPECI AL PROGR AMS ADMIN!STR/. TION

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IAEA CERTIFICATE OF COMPETENT AUTHORITY

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Special Form Radioactive Material Encapsulation y, u,,,

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Certificate Number USA /0154/5 This certifies that the encapsulated sources, as described, when Ioaded with the authorized radioactive contents, have been demon-strated to meet the regulatory requirements for spegial form I

radioactive material as prescribed in IAEA and USA' regulations for the transport of radioactive materials.

1.

Source Description - The sources described by t~ds certificate are identified'as the Technical Operations, Inc., Models which are e

described and constructed as follows:

Model No.

Capsule Style Approximate Size (in inches, diameter x lencth A424-1 B60001 or B60004

.25 x.97 A424-6 B60001 or B60004

.25 x.97 A424-9 B60001 or B60004

.25 x.97 A424-20 B60001 or B60004

.25 x.97 s[

A58101 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 B60004

.25 x.97 4

i All capsules are constructed of either 304 or 304L stainless steel and conform with the following design drawings:

Caosule Style Drawing Number i

B60001 B60001 - 1 Rev. H and - 2 Rev. F B60004 B60001 - 1 Rev.- H and B60004 - 1 Rev. D B60006 Pellet B60006 - 1 Rev. H and B60001 - 2 Rev. F B60006 Wafer B60006 - 1 Rev. H and B60004 - 1 Rev. D B60006 Large Wafer B60006 - 2 and B60001 - 2 Rev. F C68310 Pellet C68310 Rev. B and B68310-3 C68310 Wafer C68310 Rev. B II.

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

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".J Certificete Number USA /0154/S Page 2

-4 Model No.

Contents (Curies)

(~N A424-1 120 A424-6 120 A424-9 120 A424-20 240

-I 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 f

consideration of the associated information therein.

t Certified by:

.1, anAs /5/978 2

/

l R. R. Rawl, Health Physicist (Date)

U. S. Department of Transportation Office of Hazardous Materials Regulation

'a'a shingt on, D. C.

20590.

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-1 1" Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition", published by the l

International Atomic Energy Agency (IAEA), Vienna, Austria.

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

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Thermal Evaluation 3.1 Discussion The Model 683 transport package is a completely passive thermal device and has no mechanical cooling system nor relief valves. All cooling of the package is through free convection and radiation. The heat source is 120 curies of Iridium-192. The corresponding decay heat is 1.03 watts.

3.2 Su= mary of Thermal Properties of Materials The melting points of the metals used in the construction of the Model 683 transport package are:

Zircalloy 3350 F (1845 C)

Steel 2453 (1345 C)

Uranium 2070 F (1133 C)

Bronze 1840 F (1005 C) 3.3 Technical Specifications of Components Not Applicable 3.4 Normal Conditions of Transport 3.4.1 Thermal Model The heat source in the Model 683 transport package is a maximum of 120 curies of Iridium-192. Iridium-192 decays with a total energy liberation of 1.45 MeV per disintegration or 8.59 milliwatts per curie. Assuming that all of the decay energy is transformed into heat, the heat genera-tion rate for the 120 curies of Iridium-192 would be 1.03 watts.

To demonstrate compliance with the requirements of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 for Type B(U) packaging, an analysis is presented in Section 3.6.

The thermal model employed is described in that analysis.

To demonstrate compliance with the requirements of paragr'aph 240 of IAEA Safety Series No. 6, 1973 for Type B(n) packaging, a separate analysis is presented in Section 3.6.

The thermal model employed is described in that analysis.

Revision O 13 June 1980 3_1

o 3.4.2 Maximum Temperatures The maximum temperatures encountered under normal conditions of transport will have no adverse effect on structural integrity or shielding.

To demonstrate compliance with the requirements of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 for Type B(U) packaging, an analysis is presented in Section 3.6.

The thermal model employed is described in that analysis.

To demonstrate compliance with the requirements of paragraph 240 c' IAEA Safety Series No. 6, 1973 for Type B(U) packaging, a separate analysis is presented in Section 3.6.

The thermal model employed is described in that analysis.

'As shown in Section 3.6, the maximum temperature in the shade would be less than 40 C and the maximum temperature when insolated would be less than 74 C.

3.4.3 Minimum Temperatures The mimimum normal operating temperature of the Model 683 transport package is -40 F (-40 C).

This temperature will have no adverse effect on the package.

('

3.4.4 Maximum Internal Pressures Normal operating conditions generate negligible internal pressures.

Any pressure generated is significantly below that of the hypothetical accident pressure, which is shown to result in no loss of shielding or containment.

3.4.5 Maximum Thermal Stresses The maximum temp,eratures that occur during normal transport are low enough to insure that thermal gradients will cause no significant thermal stresses.

J.4.6 Evaluation of Package Performance for Normal Conditions of Transport The thermal conditions of normal transport are insignificant from a functional viewpoint for the Model 683 shipping container. The applicable conditions of IAEA Safety Series No. 6, 1973 for Type B(U) packages have been shown to be satisfied by the Model 683 package.

3-2 Revision 0 13 June 1980 4

r

3.5 Hypothetical Accident Thermal Evaluation 3.5.1 Thermal Model The Model 683 shipping container with the Model 683 gamm, ray projector and sogree assembly, is assumed to reach the thermal tes; temperature of 800 C.* At this temperature the polyurethane foam in the projector will have decomposed and the resulting gases will have escaped the package through vent holes and non-leak tight assembly joints. In addition the rubberized hair filler in the shipping container undergoes a small amount of melting.

3.5.2 Package Conditions and Environment The Model 683 underwent no significant damage during the free drop and puncture tests. The package used in this analysis is considered undamaged.

3.5.3 Package Temperatures As indicated in Section 3.5.1 the entire Model 683 package is assumed 3

to reach a temperature of 800 C.

Examination of the melting tempe ratures of the materials used in the construction of the Model 683 transport package (except the potting compound, as noted) indicates that there will be no damage to the package as a result of this temperature.

3.5.4 Maximum Internal Pressures The Model 683 package is open to the atmosphere. Therefore, there will be no pressure buildup within the package. In Section 3.6, an analysis of the source capsules under the thermal test condition demonstrates 2

that the maximum internal gas pressure at 800 C is 55 psi (380kN/m ),

The critical location for failure is the veld. An internal pressure 2

2 of 55 psi (308kN/m ) wil generate a maximum stress of 291 psi (2.0MN/m ),

At a temperature of 870 C (1600 F), the yield strength of Type 304 2

stainless steel is 10,000 psi (69MN/m ),

Thus at 800 C, the maximum stress in the source capsule would be only 3%

of the yield strength of the material.

3.5.5 Maximum Thermal Stresses There are no significant thermal stresses generated during the thermal test.

3.5.6 Evaluation of Package Performance The Model 683 transport package will undergo no loss of structural Revision 0 13 June if80 3-3

integrity or shielding when subjected to the thermal accident condition.

The pressures and temperatures have been demonstrated to be within l

acceptable limits.

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3.6 Appendix 3.6.1 Model 683 Type B(U) Thermal Analysis: Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1971.

3.6.2 Model 683 Type B(U) Thermal Analysis: Paragraph 240 of IAEA St.fety Series No. 6, 1973 3.6.3 Iridium Source Capsules Thermal Analysis

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3.6.1 Model 683 Type B(U) Thermal Analysis Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 This analysis demonstrates that the maximum surface temperature of the Model 683 will not exceed 50 C with the package in the shade and an amb!ent temperature of 38 C.

To assure conservatism, the following are used:

1) The entire decay heat (1.03 watts) is deposited in the exterior faces of the Model 683 barrel.
2) The interior of the Model 683 is insulated and heat transfer occurs only from the exterior wall to the atmosphere.
3) Because each face of the package eclipses a different solid angle, it is assumed that fifty percent of the total heat is deposited in the smallest face (top).
4) The only heat transfe.. mechanism is free convection.

Using these assumptions, C

  • maximum wall temperature is found from:

b q = hA (t,- T, where q: Heat deposited per unit tiw in the face of interest (0.515 watts) h: Free convective heat transfer coefficient for air (1.84 (AT)I w/m oC)

A: Area of the face of interest (0.18m)

T,: Maximum temperature of the wall of the package Ta: Ambient temperature (38 C)

From this relationship, the maximum temperature of the wall is 39.5 C.

This satisfies the requirement of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973.

Revision 0 13 June 1980 3-6

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3.6.2 Model 683 Type B(U) Thermal Analysis Paragraph 240 of IAEA Safety Series No. 6, 1973 This analysis demonstrates that the maximum surface temperatures of the Model 683 will not exceed 82 C when the package is in an ambient temperature of 38 C and insolated in accordance with paragraph 240 of IAEA Safety Series No.

6, 1973.

The calculational model t sists of taking a steady state heat balance over the surface of the package. The following assump-tions are used.

2

1) The package is insolated at the rate of 775w/m 2

(800 cal /cm2 - 17h) on the top surface, 388w/m 2

(400 cal /cm - 12h) on the sides, and no insola-tion on the bottom.

2) The decay heat load is considered negligible.
3) The package has a painted steel surface.

The.=olar absorptivity is assumed to be 0.9.

The solar emissivity is assumed to be 0.8.

4) The package is assumed to undergo free convection

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from the sides and top, and undergo radiation from the sides, top and bottom. The inside faces i

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

5) The package is approximated as a right circular cylinder resting on an end. The surface areas of 2

the top and bottom are each 0.18m. The surface area of 2

the side is 0.54m,

The maximun surface temperature is established from a steady state heat balance relationship.

q in = q out "9

+9 r where q: Convective Heat Transfer c

q: Radiative Heat Transfer L

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Revision 0 13 June 1980 3-7

5 The heat load applied to the package is:

q in = = q, where a : Absorptivity (0.9) q,: Solar heat load (149 watts)

The convective heat transfer is:

9 =(Wgop + (M) sides ( w

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e a

where h Convective heat transfer coefficient t

A : Area of surface of interest T, : L sperature of wall T, : Ambient temperature i

The heat transfer due to radiation is:

= cc A(T," - T,4) gr a

where o Stefan Boltzmann Constant (5.669 x 10 w/mmog) c Emissivity (0.8)

Iteration of this relationship demonstrates that the wall temperature of the Model 683 is 73.2 C which satisfies requirement of paragraph 240 of IAEA Safety Series No. 6, 1973.

i Revision 0 13 June 1980 3-8

3.6.3 Model 683 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 i.n conjunction with the Model 683, when subjected to the thermal test, does not exceed the pressure which corresponds to the minimum yield strength at the thermal test temperature.

The source capsules are fabricated from stainless steel, Type 304 or 304L. The outside diameter of the capsules is 0.250 inch (6.35mm).

The source capsules are seal welded. The minimum weld penetration is 0.020 inch (0.5mm). Under conditions of internal pressure, the critical location for f ailure is this weld.

The internal volume of the source capsules contains only iridium me.a1 (as a solid) and air. It is assumed at the time of loading, r

the entrapped air is at standard temperature and pressure (20 C; 2

100kN/m ).

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

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Under the conditions of paragraph 238 of IAEA Safety Series Ng. 6, ig ).

is assumed that the capsule could reach a temperature of 1475 F (800 C Using the ideal gas law and requiring the air to occupy a constant volume, the internal gas pressure could reach 373kN/m (55 psi).

The capsule is assumed to be a thin-walled cylindrical pressure vessel.

The maximum longitudinal stress is calculated from:

cay y - PA where a1: L ngitudina'. Stress 2

2 A;

Stress Area = u(r

-r y

g)

P:

Pressure 2

A:

Pressure Area = nr p

g From this relationship, the maximum longitudinal stress is calculated j

2 to be 894kN/m (129 psi).

Revision 0 13 June 1980 3-9

f f

The hoop stress can be found by:

2c lt " Pld h

g where'c : hoop stress h

1: Length of the cylinder t : thickness of cylinder From this relationship, the hoop stress is calculated to be 2

1.96MN/m (284 psi).

At a temperature of 1600 F (870 C), the {ield strength of type 304 stainless steel is 10,000 psi (69MN/m ).

Thus, under the

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conditions of paragraph 238 of IAEA Safety Series No. 6, 1973, the stress generated is less than 3% of the yield strength of

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the material.

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Revision 0 13 June 1980 3 - 10 6

o 4.

Containment 4.1 Containment Boundary 4.1.1 Containment Vessel The containment system for the Model 683 is the radioactive source as stated in Section 1.2.3 of this application. The actual containment for the radioactive material is the welded source capsule as shown in Section 2.10.

The source asse=bly is certified as Special Form radio-active material (IAEA Certificate of Competent Authority No. USA /0154/S).

The capsule is constructed of either Type 304 or Type 304L stainless steel. The capsules are rounded cylinders with a diameter of 0.25 inch (6.35mm) and a length of 0.78 inch (19.8mm).

4.1.2 Containment Penetrations There are no penetrations of the containment.

4.1.3 Seals and Welds The containment is seal welded by a tungsten inert gas welding process which is described in Tech / Ops Standard Source Encapsulation Procedure (Section 7.4).

The minimum weld penetration is 0.020 inches (0.51mm).

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4.1.4 Closure Not Applicable 4.2 Requirements for Normal Conditions of Transport 4.2.1 Release of Radioactive Material The source assemblies have satisfied the requirements for Special Form radioactive material as delineated in IAEA Safety Series No. 6, 1973 Edition and USNRC 10CFR Part 71. Therefore,,there will be no release of radioactive material under the normal conditions of transport.

4.2.2 Pressurization of the Containment Vessel Pressurization of the source capsules under the conditions of the hypothetical thermal accident was demonstrated to generate stresses well below the structural limits of the capsule (See Section 3.5).

Thus, the containment will withstand the pressure variations of normal transport.

4.2.3 Coolant contamination Not Applicable

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Revision 0 13 June 1980 4-1

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4.2.4 Coolant Loss Not Applicabis 4.3 Containment Requirements for the Hypothetical Accident Conditions

'4.1 Fission Cas Products Not Applicable 4.3.2 Releases of Contents The hypothetical accident conditions of 10CFR71, Appendix B will result in no loss of package containment as shown in Sections 2.7.1, 2.7.2 and 3.5.

k Revision 0 e

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5.

Shielding Evaluation 5.1 Discussion and Results I

The Model 683 barrel is designed for use as a Type B shipping container for the transport of the Tech / Ops Model 683 gamma ray projector con-taining Iridium-192 as a Special Form sealed radioactive source. The radioactive source assembly is contained inside the gamma ray projector.

The gamma ray projector provides shielding for the radioactive source and also provides a means of securing the radioactive source in its proper storage position. Descriptive drawings of the Model 683 gamma ray projector and shipping container are provided in Section 1.3.

Radiation profiles of a Model 683 gamma ray projector containing 107 curies of Iridium-192 and a Model 683 shipping container with the projector were done. The results of this survey are presented in Section 5.5.1.

Extrapolation to the maximum capacity of 120 curies is presented in Tables 5.1A and B.

The results demonstrate that with the Model 683 gamma ray projector positioned in the Model 683 barrel ready for transport, the radiation levels are well below the regulatory limits for a shipping container.

As the Model 683 contains no neutron source,,the gamma dose rates are the total dose rates which are presented.

k Revision 0 13 June 1980 i ~

5-1

Table 5.1-A Model 683 Gama Ray Projector Sumary of Maximum Dose Rates (mR/hr)

Surface 6 Inch 1 Meter Top 78 11 0.8 Bottom 101 15 1.5 Front 230 28 2.5 Back 258 25 1.6 Right 247 22 1.3 Left 269 27 2.0 Table 5.1-B Model 683 Shipping Container (with a Model 683 Gama Ray Projector)

Sumary of Maximum Dose Rates (mR/hr)

At Surface At One Meter Top Sides Bottom Top Sides Bottom 11 38 39 0.7 1.2 0.9 5.2 r;9yge Specification 5.2.1 Gama Source The gama source is Iridium-192 in a sealed capsule as Special Form in quantities up to 120 curies.

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5-2

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O 5.2.2 Neutron Source Not Applicable 5.3 Model Specification Not Applicable 5.4 Shielding Evaluation The shielding evaluation was performed on a Eodel 683 gamma ray pro-jector containing 107 curies of Iridium-192 and on a Model 683 shipping container with the projector secured inside for transport. The source used for measurements was a Model A68309. The results of the measure-ments demonstrate that when the projector is transported in the Model 683 shipping container the dose rates surrounding the package are well within the regulatory requirements.

To demonstrate the effects of hypothetical accident conditions on the shielding evaluation of the Model 683 shipping container, it is necessary to refer to a previous submittal for Type B packaging certification on the Tech / Ops Model 715 shipping container. The Model 715 shipping container, a steel drum of similar construction to the Model 683, was subjected to a free drop of 30 feet onto a steel plate. During the test the Model 715 barrel contained a Model 616 gamma ray projector. Damage was limited to minor de-formation and some crushing of the insulating liner. There was no increase in radiation intensity and no loss of radioactive material. (Package Description, Technical Operations, Model 715, Section 5.4, 11 April 1980).

Revision 0 13 June 1980 5-3

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5.5 Appendix 5.5.1 Radiation Profile - Model 683 Gansna Ray Projector Serial No. 220 5.5.2 Radiation Profile - Model 683 Shipping Container Serial No. 7 l

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4 5.5.1 RADIATION PROFILE Mod'.1683 Camma Ray Projector Serial No. 220 TOP TOP g

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RIGHT LEFT FRONT BACK kla

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BOTTOM BOTTOM i

Source Model A68309 Serial No. S-2831 f

Activity:

107 Curies on '30 May 1980 Survey Instrument: AN PDR-27J Serial No: 7930 Calib. Date: 15 May80 Maximum Dose Rates (mR/hr)

Surface 6 Inch 1 Meter Top 70 10 07 Bottom 90 13

.1. 3 j

l Front 205 25 L'2 Back 230 22 T.'4 Right 220 20 T.2 Left 240 24 TN Revision O 5-5 13 June 1980 k

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a 5.5.2 RADIATION PROFILE Model 683 Shipping Container Serial No. 7 TOP

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Source Model: A68309 Serial No: S2831 Activity: 107 Curies on 30 May 1980 Survey Instrument: AN PDR-27J Serial No: 7930 -Calib. Date:

15 May 1980 Maximum Dose Rates (mR/hr)

Surface At One Meter Top Side Bottom Top Side Bottom i

10 34 35 0.6 1.1 0.8

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Revision 0 5-6 13 June 1980

6.

Criticality Evaluation Not Applicable

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Revision 0 13 June 1980

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6-1

7.

Operating Procedures 7.1 Procedures for Loading the Package The procedure for fabricating the special form source capsule is presented in Section 7.4.1.

The procedure used in preparing the Model 683 shipping container for transport is presented in Section 7.4.2.

I 7.2 Procedures for Unioading the Package The procedure. for unloading the Model 683 shipping container is presented in Section 7.4.2.

7.3 Preparation of an Empty Package for Transport The procedure for preparing an empty package for transport is presented in Section 7.4.2.

Revision O

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7.4 Appendix 7.4.1 Procedure for Encapsulation of Sealed Sources 7.4.2

. Model 683 shipping container Operating Instructions i

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RADIATION SAFETY MANUAL Part II In Plant Operations Section 2 ENCAPSULATION OF SEALED SOURCES A.

Personnel Requirccents Only an individual qualified as a Senior Radiological Technician shall perform 192 the operations associated with the encapsulation of Iridium. There must be a second qualified Radiological Technician available in the building when these operations are being performed.

B.

General Requirements 182 The Iridium loading cell shall be used for the encapsulation of solid 170 mer. 11ic is2Iridium and the packaging of sealed sources such as

Thulium, 188 80 187Cesium and Ytterbium. Solid metallic Cobalt not exceeding one curie may be'.1andled in this cell also.

192 Iridium to be handled in this cell at any one time The maximum amount of 137Cs to be handled in shall n;t exceed 1000 curies. The maximu= amount of this ". ell at ony one time shall not exceed 100 curies.

T'is cell is designed to be operated at less than atmospheric pressure. The exhaust blower provided shall not be turned off except when the cell is in a de-contaminated condition.

Sources shall not be stored in this cell overnight or when cell is unattended.

Unencapsulated material shall be returned to the transfer containers and encapsulated sources transferred to approved source containers.

When any of the "through-the-wall" tools such~as-the welding fixture or transfer pigs are removed, the openings are to be closed with the plugs provided. These tools shall be decontaminated whenever they are removed from the hot cell.

C.

Preparatory Procedure 1.

Check welding fixture, capsule drawer and manipulator fingers from cell and survey for contamination. If contamination in excess of 0.001pci of removable contamination is found, these items must be decontaminated.

2.

If the velding fixture or the electrodes have been changed, perform the encapsulation procedure omitting the insertion of any activity. Examine this dummy capsule by sectioning thru weld. Weld penetration must be not less than 0.020 inch.

Revision 0 13 June 1980 7-3

i If weld 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 weld 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. This is about % inch of water for a new filter. When this pressure differential rises to about 2 inches of water, the filter must be changed.

5 D.

Encapsulation Procedure 1.

Prior to use, assemble and visually inspect the two capsule components to f

determine if weld zone exhibits any misalignment and/or separation.

De-fective capsules shall be rejected.

2.

Degrear* capsule components in the. Ultrasonic Bath, using isopropyl alcciol I

as degreasing agent, for a period of 10 minutes. Dry the capsule components at 100 C for a minimum of twenty minutes.

3.

Insert capsule components into hot cell with the posting bar.

4.

Place capsule in weld positioning device.

5.

Move drawer of source transfer container into hot cell.

6.

Place proper amount of activity in capsule. Disposable funnel cust be used with pellets and a brass rivet with wafers to prevent contamination of weld zone.

7.

Remove unused radioactive material from the hot cell by withdrawing the drawer of the source transfer container from the cell.

8.

Remove funnel or rivet.

9.

Assemble capsule components.

10. Weld adhering to the following conditions:

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.

Weld 15 amps.

e.

Slope 15 amps f.

Post flow 15 seconds.

Revision 0 13 June 1980 7-4

11. Visually inspect the weld. An acceptable weld must be continuous without cratering, cracks or evidence of blow out.

If the weld is defective, the capsule cust be cleaned and rewelded to acceptable conditions or disposed of as radioactive vaste.

12.

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

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

14. Count the patch with the scaler counting system. Patch cust show no more than.005 Ci of contamination. If the patch shows more than.005pci of contamination, steps 8 through 11 must be repeated.

15. Vacuum bubb1'e test the capsule. Place the welded 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. Reweld the capsule.

16. Transfer the capsule to the swaging fixture. Insert the wire and connector assembly and swage. Hydraulic pressure should not be less than 1250 nor more than 1500 pounds.
17. Apply the tensile test to assembly 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 maximum respcase. Record the meter reading. Compute the activity in curies and fill out a temporary source tag.

19. Using remote control, eject the source from cell into source changer through the tube gauze wipe test fixture. Monitor before reentering the hot cell area to be sure that the source is in the source changer.

Remove the tube gauze and count with scaler counting system. This assay must show no more than 0.005pCi. If contamination is in excess of this level, the source is leaking and shall be rejected.

20.

Complete a Source loading Log (Figure II.2.1) for the operation.

Revision 0 13 June 1980 7-5 s

i TECH /0PS MODEL 683 SliIPPING CONTAINER OPERATING INSTRUCTIONS Technical Data Size:

18.5 in diameter,14.25 in high (469.9mm diameter, 362=m high)

Capacity:

120 curies of Iridium-192 as special form sealed radioactive source in the Model 683 gamma ray projector.

Transport Status:

Type B USNRC USA /9053/B IAEA USA /0012/B Ceneral The Model 683 shipping container is designed as Type B packaging for the transport of the Tech / Ops Model 683 gamma ray projector.

Receipt k

1.

Upon receipt of the Model 683 shipping container, survey the package on all sides to ensure radiation levels to not exceed the following:

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

Check surface of container for obvious damage.

3.

Check Invoice and Bill of Lading to ensure all are intact and are representative of the shipment.

4.

If there are any discrepancies in Items 1-3, secure the shipping container and contact Technical Operations, Inc.

immediately to resolve the discrepancy.

(Tel: 800-225-7383, Telex 949313).

5.

If Items 1-3 are determined to be in order, place the transport package in a restricted area until the gamma ray projector is to be unpacked.

Revision 0 13 June 1980 7-6

Opening the Package NOTE: During all unloading and loading operations of the Model 683 shipping container, personnel must have a calibrated and operational survey meter with a range of at least 0-1000 mR/hr.

In addition, personnel monitoring devices must be worn during the operation. They are, a film badge (or thermolu=inescent dosimeter, TLD) and a direct reading pocket dosimeter.

1.

Prior to opening the package, survey the container on all sides and ensure radiation levels are not in excess of 200 mR/hr on the surface nor 10 mR/hr at one meter from any surface.

2.

Place the package in a Restricted Area which is properly identified.

3.

Break the real wire, unfasten the bolts and remove the top.

4.

Examine the contents of the package to determine if any shif ting or damage had occured during transport.

5.

If items 1 to 4 are in order, remove the Model 683 pr( jector as needed.

When stored, secure the Model 683 projector in a Restricted Area.

Preparation for Shipment f

1.

Wearing a film badge and dosimeter, approach the gam =a ray projector

  • a ha shipped with a calibrated and operable survey instrument.

2.

Sur rey the exterior surfaces of the gamma ray projector to insure that the radiation intensities are normal.

(Less than 50mR/hr at six inches from the surface). Check to insure that the gamma ray projector is locked.

3.

Place the Model 683 gamma ray projector in the Model 683 shipping container positioned to sit firmly in the molded rubberized hair filler. Place the top section of the molded filler over the projector.

Cover the container top with the gasket and lid.

4.

Place the clamp ring on the container and tighten the bolt. Sealwire the bolt and nut using a tanp proof seal.

5.

Survey the exterior surfaces of the container and insure that the maximum radiation level is less than 200 milliroentgens per hour.

'6.

Measure the radiation level three feet from all exterior surfaces of the ec-*ainer and insure that the radiation level is less than 10 milliroentgens per hour.

Revision 0 13 June 1990 7-7

7.

Determine the proper shipping label to be applied to the package using Table I.

The maximum radiation level measured three feet from any exterior surface of the shipping container is the Transport Index.

8.

Fill out the information requested on the label indicating:

a) Contents (Isotope) b)

No. of curies

'c ) Transport Index (Maximum Radiation Level measured at f

three feet from the surface).

9.

Remove all old shipping labels. However, do not remove the metal container identification tag.

10. Affix new shipping labels to two opposite sides.
11. Perform a radioactive contamination wipe test of the shipping package

(

and insure that the wipe test does not exceed 0.001 microcuries per 100 square centimeters.

12. Properly complete the shipping papers indicating:

a) Proper shipping name (i.e. radioactive material, special form, n.o.s.)

b) Name of radionuclide (i.e. Iridium-192) c) Physical or chemical form (or special form)

Revision 0 13 Jude 1980 i

7-8 1

t TABLE I Maximum Radiation Levels Surface 3 "cer

_RADIQACTIVe-WHITE,I.

/N

/

's

' d,k N s s

g f

0.SmR/hr None

(

's RADIDACTIVE N in-[ /,'

N 7N, '

RADIOACTQE-YELLOW.11

'N s

s N

50mR/hr 1.0mR/hr s

RADl0ACTIVEa5 >

s s =_

/

x '::=_-

/

s --

/

/

N 7N' RADIOACTIVE-YELLOW J II

/s N

N

/

s

/

s

/ -

g 200mR/hr 10mR/hr

'(

'2 s AD10ACTIVEm5 /

N T.5-

/

s -;

/

7 g

f V

L_

Revision 0 7-9 11 April 1980

0 t

l d) Activity of source (expressed in curies or millicuries) e) Category of label applied (i.e. Radioactive Yellow II) f) Transport Index g) USNRC Identification Number (USA /9053/B) h) For export shipments, IAEA Identification Number (USA /0011/B)

Shipper's Certification required:

"Iids is to certify that the above named materials 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 cercification may be used:

"I hereby certify that the contents of this consignment are fully and accurately described above by proper shipping name and are classified, packed, marked and labeled and are in prsper condition for carriage by air according to applica*>1e National Governmental Regulations."

2.

For air shipments, the package must be labeled with a

" Cargo Aircraf t Only" label and the shipping papers must state:

"THIS SHIPMENT IS L'ITHIN THE LIMITATIONS PRESCRIBED FOR C; (GO-ONLY AIRCRAFI."

13.

Return the Model 683 shipping container to:

Technical Operations, Inc.

40 North Avenue Burlington, MA 01803 USA Shipning Empty Package NOTE: Wear personnel monitoring devices during all source changing operations.

Monitor all operations with a calibrated, operable survey meter.

Revision 0 13 June 1980 7 - 10

1.

The Iridium 152 source is to be secured in a Tech /i.ps Model 750 source changer when it is necessary to ship an empty Model 683 package. The procedures for source changing with the Model 750 are to be followed. The precautions used when making a radiographic exposure must also be followed, 2.

When shipping an empty Model 683 projector containing depleted uranium ts shielding, all the steps 1 through 6 under the procedures for shipmeat must be followed.

3.

If the surface rediation level is less than 0.5 milliroentgens per hour and there is no measurable radiation level at 3 feet from the surface, no label is required. Mark the outside of the package with the statement:

" Exempt from specification packaging, marking and labeling, and exempt from the provisions of 49CFR173.393 per 49CFR173.391(c).

Exempt from the requirements of 49CFR Part 175 per 49CFR175.10(a)(6)."

Properly complete the shipping papers indicating:

a) Proper shipping name (Radioactive Marked LSA, n.o.s.)

b) Name of Radionuclide (Depleted Uranium) c) Physical or chemical form (Solid metal) d) Activity (in curies or millicuries e) The statement as stated abmre for exemption from specification packaging f) Shipper's certification NOTE: The shipper's certification and the additional certification for air shipments are as stated in the procedures for Preparation for Shipment.

4.

If the surf ace radiation level exceeds 0.5 milliroentgens per hour, or if there is a measurable radiation level at three feet from the surface, use the criteria of Table I to determine the proper radioactive shipping labels to be applied to the package.

The steps to be followed in shipping the package for this situation are specified in the section on Preparation for Shipment steps 1-13.

Revision 0 13 June 1980 7 - 11

s 8.

Acceptance Tests and Maintenance Program 8.1 Acceptance Tests 8.1.1 Visual Inspection The package is visually examined to assure that the appropriate fasteners are properly sealwired and that the package is properly marked.

The Model 683 gamma ray projector which is transported in the Model 683 shipping container is also visually examined to assure that the appropriate fasteners are properly sealwired and that the package is properly labeled.

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

8.1.1 Structural and Pressure Tests The swage 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 1

The radioactive source capsule (the primary containment) is wipe tested for leakage of radioactive contamination. The source capsule is subjected to a second wipe test for radioactive contamination.

These tests are described in Section 7.4.

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

8.1.4 component Tests The locking. assembly of the Model 681 gamma ray projector is tested -

to assure that the security of the ri.dioactive source will be main-ta'ned.

Failure of this test prever.t s use of the gamma ray projector

,acil the lock assembly is corrected and retested. Only when the source assembly is correctly secured in the gamma ray projector is the Model 683 used as a shipping container.

" sts for Shielding Integrity 8.1.5 j

The radiation levels at the surface of the package and at three feet from the surface are measured using a small detector survey instrument (i.e., AN PDR-27). These radiation levels, when extrapolated to the

-rated capacity of the package, must not exceed 200 milliroentgens per hour at the surface nor ten milliroentgens per hour at three feet from the surface of the package. Failure of this test will prevent use of

'the package.

Revision 0 13 June 1980 8-1

fr-j i

~

\\

l 8.1.6 Thermal Acceptance Tests Not Applicable j

8.2 Maintenance Program 8.2.1 Structural and Pressure Tests Not Applicable 8.2.2 Leak Tests As described in Section 8.1.3, the radioactive source assembly is leak tested at manuf acture. Additionally, the source assembly is wipe tested for leakage of radioactive contamination every six months.

8.2.3 Subsystem Maintenance The lock assembly of the gamma ray projector is tested as described in Section 8.1.4, prior to each use of the Model 683 shipping container, Additionally, the Model 683 shipping container' is inspected for tightness of' fasteners, proper seal wires, and general condition prior to each use.

8.2.4 Valves, Rttpture Discs and Gaskets Not Applicable 8.1.5 Shielding Prior to each use, a radiation survey of the transport package is made to assure that the radiation levels do not exceed 200 milliroentgens per hour at the surface nor ten milliroentgens per hour at three feet from the surface.

8.2.6 Thermal Not Applicable 8.2.7 Miscellaneous Inspections and tests designed for secondary users of this package under the general license provisions of 10CFR Part 71.21(b) are included in Ser. tion 7.4.2.

Revision 0 13 June 1980 8-2 Ps

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