ML20003G483

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RSAR for Tech Ops Model 910,Type B(U) Package
ML20003G483
Person / Time
Site: 07109149
Issue date: 04/10/1981
From:
TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:
Shared Package
ML20003G482 List:
References
NUDOCS 8104290638
Download: ML20003G483 (64)
v • d • e


Text

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SAFETY ANALYSIS REPORT TECHNICAL OPERATIONS MODEL 910 TYPE B(U) PACKAGE 810.4 2 9 o (a37

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General Information 1.1 Introduction Tech / Ops Model 910 is designed for use as a radiographic exposure device and shipping container for Type B quantities of radioactive material in special form. The Model 910 conforms to the criteria for Type B (U) packaging in accordance with IAEA Safety Series No. 6, 1973 Edition. The Model 910 is identical to Tech / Ops Model 900 Type B package (Certificate of Compliance No. 9141) with the exception of the uranium shield.

1.2 Package Description 1.2.1 Packaging The Model 910 is 13 inches (330mm) long, 7.7 inches (195mm) high and 5.3 inches (135mm) wide. The gross weight of the package is 34 pounds (15kg).

The radioactive source capsule is housed in a source assembly which is fabricated from tungsten and stainless steel. The source assembly is housed inside a tungsten source tube with an outside diameter of 0.63 inch (17mm) and inside diameters machined to conform to the con-figuration of the source assembly.

The source tube is surrounded by depleted uranium metal for shielding.

The uranium metal is cast around the tungsten source tube. The mass of the uranium shield is 18 pounds (8.2kg).

The uranium shield assembly is encased in a stainless steel housing.

The shield assembly is supported on the front end by the front housing.

It is supported on the rear end by the lock assembly which is attached to the rear plate. The front plate and rear plate are attached by means of four spacer rods and screws.

The ends of the package are enc 1'osed with end plates fabricated from 0.09 inch (2.3mm) thick stainless steel. The sides of the package are enclosed by a shell fabricated from 0.06 inch (1.5mm) thick stain-less steel.

The void space between the uranium shield assembly and the stainless steel housing is filled with a castable rigid polyurethane foam.

Mounted in the front plate is a source position indicator slide.

This slide, in the closed position, closes the exit end of the source tube.

Tamperproof seals are provided during shipment of this package. Four vent holes in the bottom of the package provide passageways for the escape of any gas generated from the decomposition of the polyurethane form in the event that the package is involved in a fire accident.

Revision 0 10 April 1981 1-1

A The outer packaging is decigned to avoid the collection and re-tention of water. The package has a smooth finish to facilitate decontamination.

The radioactive material is sealed inside a stainless steel source capsule. The capsule acts as the containment vessel for the radio-active material.

1.2.2 Operational Features The source assembly is secured in the proper storage position by means of the locking assembly. A lock side engages an undercut in the source assembly preventing movement in either the forward or rearward direction. The lock slide is held in position by the selector ring. The selector ring is secured in the " LOCK" position by means of a key operated lock mounted on the rear plate of the projector.

In the event that the lock failed, the source assembly would be con-tained within the package. The source position indicator slide would prevent movement in the forward direction. Interference between the source assembly and source tube would prevent movement in the rear-ward direction.

1.2.3 Contents of Package

('#

The Model 910 is designed for the transport of iridium-192 in quantities of up to 30 curies as Tech / Ops source assembly 91003. This source assembly contains either Tech / Ops Model 90004 or 90005 source capsule which satisfies the criteria for special form radioactive material in accordance with 10CFR71 and IAEA Safety Series No. 6, (IAEA Certificate of Competent Authority Number USA /0179/S).

Revision 0 10 April 1981 1-2

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Structural Evaluation 2.1 Structural Design 2.1.1 Discussion Structurally, the Model 910 consists of four components: source capsule, ahield assembly, outer housing and locking assembly. The source capsule is the primary containment vessel. It satisfies the criteria for special form radioactive material. The shield assembly fulfills two functions. It provides shielding for the radioactive material and, together with the locking assembly, assures proper positioning of the source. The outer housing provides the structural strength of the package. The locking assembly secures the source assembly in the shielded position in the package and assures positive closure.

2.1.2 Design Criteria The Model 910 is designed to comply with the requirements of 10CFR71 and LAEA Safety Series Noi. 6, 1973 Revised Edition.

2.2 Weights and Centers of Gravity The Model 910 weighs 34 pounds (15kg). The shield assembly contains 18 pounds (8.2kg) of depleted uranium. The center of gravity was

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located experimentally. It is located approximately 4.5 inches

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(114mm) from the front surface, 3.0 inches (76mm) from the bottom surface and 2.7 inches (68mm) from the right surface.

2.3 Mechanical Properties of Materials The housing of the Model 910 is f abricated from Type 304 stainless steel.

1 This material has a yield strength of 35,000 pounds per square inch I

(241MN/m ),

2 Drawings of the M6dels 90004 and 90005 source capsules are enclosed in Section 2.10.

These ' source capsules are f airicated from Type,304 -

or Type 304L stainless steel. Each capsule is sealed by tungsten inert gas weldias.

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2.4 General Standards for All Packages 2.4.1 Chemical and Galvanic Reactions The materials used in the construction of the Model 910 are uranium metal, stainless steel, tungsten, bronze, carbon steel, and aluminum.

There will be no chemical or galvanic action between any of these components.

There is no iron-uranium interface in this package. Therefore, there is no possibility of the forma' tion of an iron-uranium eutectic alloy at elevated temperatures.

i i

Revision 0 10 April 1981 2-1

2.4.2 Positive Closure The source assembly in the Model 910 cannot be exp'osed without opening a key operated lock. Thus, positive closure is provided.

2.4.3 Lifting. Devices.

The Model 910 is designed to be lifted by its handle. The handle is f abricated from alumhum and attached to the end plates by means of four No. 10-32 UNC flat head machine screws. The weakest area of the handle is the screw attachment. The stress area of each 2

2 screw is 0.175 in (11.3mm ).

The yield strength of these screws 2

is greater than 40,000 pounds per square inch (276HN/m ).

Therefore, each screw cannot suppoct 700 pounds (3.1kN) or more than twenty times the weight of the package without exceeding the yield strength of the material.

2.4.4 Tiedown Devices The handle is also used as a tiedown device. As demonstrated in Section 2.4.3, each of the four screws setaching the handle can support more than twenty times the weight of the package without exceeding the yield strength of the material.

2.5 Standards for Type B and Large Quantity Packages f

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 generated can be computed from:

a - !1.

8Z Where c: Maximum St'ress Generated F: Total Load (170 pounds; 757 newtons) 1: Length of Beam (13 inches; 330mm) 3 8

Z: Section Modulus (2.32 in ; 38,018mm )

l Machinery's ' andbook, 21st Edition, p.404) d

Reference:

The package is assumed to be a rectangular shell 5.04 inches (128mm) wide and 5.75 inches (146mm) high with a wall thickness of 0.06 inch 3

(1.5mm). Consequently, the section modulus is 2.32in.

From this relationship, the maximum stress generated in the beam is 2

119 pounds per square inch (822kN/m ) which is far below the yield strength of the material.

Revision 0 10 April 1981 2-2

2.5.2 External Pressure The Model 910 is open ~ to the atmosphere. Therefore, there will be i

no differential pressure to act upon the package.

4 The collapsingipressure of the source capsule is calculated as using that the capsules are thin wall tubing with the wall thickness' equal to the minimum depth of weld penetration (0.020 inch; 0.5mm). The collapsing pressure is calculated from:

P - 86,670 t - 1386 d

Where P: Collapsing pressure in pounds per square inch c: Wall Thickness (0.020 inch) d: Outside diameter (0.205 inch)

(

Reference:

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

From this relationship the collapsing pressure is computed to be 2

7070 pounds per square inch (49MN/m ).

Therefore, the source capsule can withstand an external pressure of 25psig withect adverse affect.

2.6 Normal Conditions of Transport 2.6.1 Heat The thermal evaluation of the Model 910 is presented in Chapter 3.

From this evaluation, it can be concluded that the Model 910 can with-stand the normal heat transport condition.

2.6.2 Cold The metals used in the manufacture of the Model 910 can all withstand a temperature of -40 C.

The lower operating limit of the polyurethane foam is -100 F (73 C).

Thus, it is concluded that the Model 910 will withstand the normal transport cold condition.

i 2.6.3 Pressure The Model 910 is open to the atmosphere. Therefore, there will be no differential pressure to act upon it.

In Section 3.6.4, it is demonstrated that the source capsule is able to withstand an external pressure reduction of 0.5 atmosphere 2

(50.7kN/m ),

2.6.4 Vibration A vibration test of the Model 900 was conducted. The package was Revision 0 10 April 1981 2-3

vibrated for seventy =inutes with a =aximum acceleration of 9.Sm/s2 at each of the following frequencies:

5, 8,12, 20, 32 and 80Hz. At the conclusion of this test, the source asse=bly remained secured in the proper storage position. A copy of this test report is included in Section 2.10.

f The Model 910 is identical to the Model 900 with the exception of the shield asse=bly. Because of the satisfactory perfor=ance of the Model 900 during the vibration test and the si=ilarity of the Model 910 to the Model 900, it is concluded that the Model 910 vill withstand the normal transport vibration condition.

2.6.5 Water Spray Test The water spray test was not actually performed on the Model 910.

The =aterials used in the construction of the package are all highly water resistant. Exposure to water vill not affect the structural integrity nor reduce the shielding effectiveness of the package.

2.6.6 Free Drop The drop analysis presented in Section 2.7.1 demonstrates that the Model 910 vill withstand the normal transport free drop conditica without loss of shielding effectiveness nor loss of. Structural integrity.

2.6.7 Corner Drop 2.6.8 Penetration A penetration test of the Model 900 was performed. There was no reduction of shielding effectiveness nor loss of structural integrity as a result of this test. A copy of this test report is included in Section 2.10.

Because of the satisfactory perfor=ance of the Model 900 during the penetration test and the similarity of the Model 910 to the Model 900, it is concluded that the Model 910 vill withstand the pene-tration test condition.'

2.6.9 Co=pression 2

The =axi-am cross sectional area of the Model 910 is 100in. Ihe weight of the package is 34 pounds. Therefore, two pounds per square inch times the maxi:sim cross sectional area is greater than five times the weight of the package. The load used is 200 pounds.

Revision 0.

10 April 1981 2-4

~

The Model 900 was subjected to the conditions of the compression test.

There was no reduction of shielding effectiveness nor loss of structural integrity as a result of this test. A copy of this test report is inclu-ded in Section 2.10.

Because of the satisfactory perforsance of the Model 900 during the compression test and the similarity of the Model 910 to the Model 900, it is conclud'ed that the Model 910 vill withstand the compression test condition; 2.7 Hypothetical Accident Oonditions 2.7.1 Free Drop The Model 900 was subjected to a drop test through a distance of 30 feet (9.im) onto a steel plate. There was no loss of shielding effect-iveness nor loss of structural integrity as a result of this test. A copy of the test report is included in Section 2.10.

Because of the similarity of the Model 910 to the Model 900, it is concluded that the Model 910 will withstand the free drop test condition.

2.7.2 Puncture The Model 900 was subjected to a free drop from the height of one meter onto a steel billet which was six inches in diameter and eight inches long. As a result of this test, there was no loss of shielding effectiveness nor loss of package integrity. A copy of this test report is included in Section 2.10.

Because ci the similarity of the Model 910 to the Model 900, it is concluded that the Model 910 will withstand the puncture test condition.

~

l 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 l

the Model 910 except the golyureghane foam, and the aluminum handle, are all in excess of 1475 F,(800 C).

To demonstrate that the radioactive source assemblies will remain in.

a shielded position following the hypothetical thermal accident, the following analysis is presented. At the conclusion of the thermal test, it is assumed that the polyurethane foam has completely escaped from the package. The shield assembly is prohibited from movement by the front housing, rear plate and lock assembly which are attached by the spacer rods.

l Thus, it is concluded that the Model 910 satisfactorily meets the l

requirements for the hypothetical thermal accident condition of l

10CFR71.

i t

Revision 0 j

10 April 1981 l

2-5

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2.7.4 Water Immersion Not Applicable 2.7.5 Su-ary of Demage i

Thetesdsdesignedtorepresentthehypotheticalaccident' conditions caused minor deformation, but no reduction of shielding effectiveness, nor loss of structural integrity.

2.8 Special Form The Model 910 is designed for use with Tech / Ops Model 91003 Source Assembly which includes either Tech / Ops Model 90004 or 90005 Source Capsule. These capsules have been tested to the criteria for special form radioactive material in accordance with the requirments of 10CFR71 and IAEA Safety Series No. 6,1973 with satisfactory results.

The US Department of Transportation has issued an IAEA Certificate of Competent Authority for this source capsula (USA /0179/S).

2.9 Fuel Rods Not Applicable i

Revision 0 10 April 1981 2-6

7 2.10 Appendix Deucriptive Assembly Drawings - Source Capsule Test Report: Vibration Resistance Test Test Report: Penetration Test Test Report: Compression Test Test Report: Free Fall Test Test Report: Panc.ture Test IAEA Certificate of Competent Authority USA /0179/S 4

4 Revision 0 10 April 1991 2-7

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TEST REPORT RADIATION PRODUCTS DIVISION 3Y:

George Parsons DATE:

30 January 1980

SUBJECT:

Model 900 Vibration Resistance Test

'#1 vibration $5sistancetestoftheModel900radiographicexposuredevice-

~

Type 3 package was conducted by Associated Testing Laboratory, Burlington, MA, on 9 January 1980 in accordance with International Standard ISO 3999.

The device was fastened to the platfors of a vibrating machine and was continuously scanned thrcugh a frequency range of 5Ha to 80Ha with a m?i-", acceleration of 9.S=/see to search for a resonant frequency.

This scan was performed on each of three rectilinear axis. Over this range, there was no resonant frequency found.

-lhe device was then vibrated along its longitudinal axis (the axis of the source tube) for 70 minutes at each of the following frequencies:

5, 8, 12, 20, 32, 80Hz.

As a result of this test, there was no loss of structural int?grity nor loss of shielding efficiency. There was no loosening of fasteners. The device functioned nor= ally at the conclusion of the test.

l GP/fb i,

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Revisics 0 10 April 1981 2 - 13

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TEST REPORT RADIATION PRODUCTS DIVISION BY:

David Marzilli DATE:

14 January 1980 x

I

SUBJECT:

Model 900 Penistration Test On 14 January 1980 a penetration test was perforned on a Model 900 Gamma Ray Projector. This projector already had been submitted to the shielding efficiency; vibration resistance and shock resistance tests outlined in International Standara ISO 3999.

A 13 pound steel bar, with a hemispherical end 1% inches in diameter, was dropped more than 40 inches onto the lock mechanism of the Model 900. A guide tube, 1 5/16 inches square along its inside dimensions, was used to

--insure positioning over the lock. The test was done twice. The lock mechanism functioned before and after the tests, and no other damage was noted.

Thus, the Model 900 will satisfy the penetration test requirements of 10CFR71.

Witnessed:,

44#

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Model 900 ce=pressica Test on 3 Jammry 1980 a Model 900 Ga=a P4y Projector was subjected to a cenpression test exceeding the require ents in 10CFRT1, Appendix A, Section

'9 and LEA Safety Series No. 6, paragraph 713 The Model 900, veight 2cks 7(45 pcunds), was leaded with 105kg (232 pcunds) of lead and steel evenly

.=-distributed alces the upper surface of the packcse. The-load was applied for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. There was no evident da nge of the package-i t

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David Marzilli DATE:

14 January 1980 SUBJEC*r:

Podel 900, 3G Ft. Free Fall Test on 11 January 1980, a Model 900 Ga=ma Ray Projector was submitted to a free The as outlined in 10CFR71 and IAEA Safety Series No. 6, 1973.

fall of 30 feet, Q rop was done_tvice, ento-a concrete drivevay covered with a 7/16 inch steel On the first drop the machine impacted on its front face, bounced and

- plate.

The second drop caused the machine to impact on its rear i=pacted the rear.

--lower lef t corner (as the machine is faced from the rear).

The first drop caused the indicator cover plate screws (4) and the lover four front end plate screws to shear. The front huusing remained secured by the screws mounting it to the spacer rod and the rear plate.

The second drop caused deformation of the rear end plate and shell.

As a result of these tests, there was no loss of shielding effectiveness nor loss of security of the source assembly. Thus, it is concluded that the Model 900 satisfiee che requirements of the free fall test as described in 10CFR71, IAEA Safety Series No. 6, 1973 and ISO 3999.

Witnessed *

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DEPARTMENT OF TRANSPORTATION RESEARCH AND SPECIAL PROGRAMS ADMINISTRATION

)

Q W ASHINGTON, D.C.

20590 IAEA CERTIFICATE OF CDMPElWf AIHHORITY a

Soecial Form Fadioactive mterial Encapsulation Certificate Number USA /0179/S"*'*" *

(Revision 2)

This certifies that the encapsulated sources, as described, when loaded with the authorized radioactive contents, have been desenstrated to rxet the regulatory requirenents for special form radioactive material as prescribed Regulations for the transport of radioactive materials.

in IAEAl and USA 2 Source Description

'Ihe scurces described by this certificate are I.identifiec as hen / Ops htdel 90004 and 90005 which are 304 or 304L stainless steel welded encapsulations measuring 0.205 in h in diameter by 0.65 inch in length.

Fadioactive Contents

'Ihe authorized radioactive contents of this source II.

consist of Ridium-192 in solid metallic form with not mare than 120 curies in the maiel 90004 or 240 curies in the Ftdel 90005.

This certificate, unless renewed, expires on October 31, 1983.

III.

This certificate is issued in accordance with Paragraph 803 of the IAEA Regulations and in respons to the Novenber 12, 1980 petiticn by Tech / Ops, I

Burlington, Massachusetts, and in consideration of the associated information therein.

Certified by:

lanumaa /3 l9 8'l R. R. Fawl G

()(date1.,

l Chief, Radioactive Materials Branch Office of Hazardous Materials Pegulations Sterials Transportation Bureau 1/ " Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1975 Revised Edition", published by the International Atomic Energy Agency (IAEA),

Vienna, Austria.

170-178, USA.

2f Title 49, Code of Federal Regulations, Part lh Revision 1 issued to add otdel 90005 and to extend expiration date.

f Revision 2 issued to reflect confortrarce with the 1973 IAEA Fegulations. ~

l Revision 0 10 April 1981 2 - 23

a 3.0 Thermal Evaluation 3.1 Discussion The Model 910 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 30 curier of iridium-192. The corresponding decay heat is 257

~

milliwatts.

3.2 Summary of Thermal Propgrties of Materials The melting points of the materials used in the construction of the Model 910 are:

Steel 2453 F (1345 C)

Uranium 2070 F (1133 C)

Tungsten 6098 F (3370 C)

Bronze 1840 F (1005 C)

Aluminum 1220 F

( 600 C)

The golyurethane form has a mini:mim operating range bf -100 F

(-73 C) and 200 F (93 C).

It will decompose at the fire test tempera-tures (800 C).

Decomposition will result in geaseous byproducts which will burn in air.

,~

3.3 Technical Specification of Components Not Applicable 3.4 Normal Conditions of Transport 3.4.1 Thermal Model The Heat source in the Model 910 is a maximum of 30 curies of iridium-192.

Iridium-192 decays with a t'otal energy liberation of 1.45 MeV per dis-intergration or 8.58 milliwatts p'er curie. Assuming that all of the.

decay ener3y is transformed into heat, the heat generation rate for the

~

30 curies of iridium-192 would be 257 milliwatts.

- To demonstrate compliance with the requirements of paragraphs 231 and 232 of IAEA Safety Series No. 6,1973 Edition for Type B(U) packaging, analysis is presented in Section 3.6.1.

The thermal model employed a.

is described in that section.

To demonstrate compliance with the requirements of paragraph 240 of IAEA Safety Series No. 6, 1973 Edition for Type B(U) packaging, an analysis is presented in Section 3.6.2.

The thermal model employed is described in that section.

Revision 0 10 April 1981 3-1

3.4.2 Maximum Te_mperatures The maximum temperatures encountered under normal conditions of transport will have no adverse effect on the structural integrity or shielding. As presented in Section 3.6. the maximum temperature in the shade would be less than 40 C and the maximum tenusrature when insolated would be less than 63 C.

3.4.3 Mini =um Temperatures The minimum normal operating temperature of the Model 910 is -40*C

(-40 F). This temperature will have no adverse affect on the package.

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

Any pressure generated is significantly below that generated during the hypothetical ther=al accident, which is shown to result in no i

loss of shielding nor contain2ent.

3.4.5 Maximum Thermal Stresses The maximum temperatures that occur during normal transport are low anough to insure that thermal gradients will cause no significant ther=al s. cresses..

3.4.6 Evaluation of Package Performance Or Normal Conditions of Transport The thermal conditions of normal transport are insignificant from a functional viewpoint for the Model 910. The applicable conditions of IAEA Safety Series No. 6,1973 Edition for Type B(U) packages have been shown to be satisfied by the Model 910.

3.5 Hypothetical Accident Thermal Evaluation 3.5.1 Thermal Model assembly, is assumed to reach The Model 910, including the source,C. At this temperature the poly-,

i the thermal test temperature of 800 l

urethane foam will have decomposed and the resulting gases will have l

- eacaped the package through vent holes and non-leak tight assembly joints.

3.5.2 Package Conditions and Environment I

The Model 910 underwent no significant damage during the free drop and puncture tests. The package used in this analysis is considered undamaged.

Revision 0 10 April 1981 l

l 3-2 l

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3.5.3 Package Te=peratures As indicated in Section 3.5.1, the entire package is assumed to reach a temperature of 800 C.

Examination of the melting tempera-tures of the materials used in the construction of the Model 910 indicates that there will be no damage to the package as a result of this temperature. The possibility of the formation of an iron-uranium eutectic alloy was addressed in Section 2.4.1 where it was concluded that the formation of the alloy was not a likely eventuality.

3.5.4 Maxi =um Internal Pressures The Model 910 packaging is open to the atmpsphere. Therefore, there will be no pressure buildup within the package. In Se.: tion 3.6, an analysis of the source capsules under the thermal test congition demonstrates that the maximm internal gas pressure at 800 C is 54 psi.

2 (373kN/m ),

In Section 3.6.3, an analysis is presented which demonstrates that tne maximum stress generated in the source capsule (containment) under the thermal test conditions could only be 3% of the yield strength of the material at the test temperature.

3.5.5 Maxi =um Thermal Stresses There are no significant thermal stresses generated during the thermal test.

3.5.6 Evaluation of Package Performance The Model 910 will undergo no loss of structural integrity or shielding when subjected to the thermal accident condition. The pressures and temperatures have been demonstrated to be within acceptable limits.

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Revision 0 10 April 1981 3-3 I

[

3.6 Appendix 3.6.1 Model 910 Type 3(U) Thermal Analysis: Paragraphs-231 and 232 of IAEA Safety Series No. 6, 1973 Edition 3.6.2 Model 910 Type B(U) Thermal Analysis: Paragraphs 240 of IAEA Safety Series No. 6,1973 Edition 3.6.3 Model 910 Type 3(U) Source Capsule Thermal Analysis:

Paragraph 238 of IAEA Safety Series No. 6,1973 Edition

{

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l Revision 0 10 April 1981 3-4

3.6.1 Model 910 Tvpe B(U) Thermal Analysis Paragraphs 231 and 232 of IAEA Safety Series No. 6,1973 Edition This analysis demonstrates that the maximug surf act temperature of the Model 910 will not exceed 50 C (122 F),with the package in the shade and at an ambient temperature of 38 0 (100 F).

To assure conservatism, the following assumptions are used:

The entire decay heat (257milliwatts) is deposited a.

in the exterior faces of the Model 910.

b.

The interior of the Model 910 is perfectly insulated and heat transfer occurs only from the exterior wall to the atmosphere.

c.

Because each face of the package eclipses a different solid angle, it is assumed that tvanty five percent of the total heat is deposited in the smallest face (front).

d.

The only heat transfer mechanism is free convection.

Using these assumptions, the maxi:mim wall temperature is found from:

q = hA(T - T,)

s y

and h = 1.42 T,- T[ %

~

1 a Where: q: Heat deposited per unit time in the face of interest (64 tilliwatts) h: Free convective heat transfer coefficient for air in watts /m.oC 2

2 A: Area of the face of interest (0.026m )

~

T,:

Maximum temperature of the wall of the package T,:

Ambient temperature (38'C)

Hei ht of the face of interest (0.20m) i 1:

3 Fromgthis relationship, the maximum te=perature of the wall is 39 C (102 F).

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

~

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[

Revision 0 10 April 1981 3-5 l

4

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3.6.2 Model 910 Type B(U) Thermal Analysis Paragraph 240 of IAEA Safety Series No. 6,1973 Edition This analysis demonstrates that the,maximug surface temperatures 180 F) when the package is of the Model 910 will not exceeg 82 C {F) and insolated in accordance in an ambient temperature of 38 C (100 with paragraph 240 of IAEA Safety Series No. 6,1973 Edition.

The calculational model consists of taking a steady state heat balance over the surface of the package. The following assumptions are used.

2 The package is insolated at the rate of 775 w/m a.

2 (800 cal /cm*-12h) on the top surface, 194 w/m (200 cal /cm*-12h) on the sides and no insolation on the bottom.

b.

The decay heat load is added to the insolation heat load.

c.

The solar absotptivity is assume 9 to be 0.9.

The solar emissivity is assuted to be 0.8.

d.

The package is assumed to undergo free convection from the top and sides and undergo radiation from the top, q

sides and bottom. The inside faces are considered insulated so there is no conduction into the package.

/

The f aces are considered to be sufficiently thin that no l

temperature gradients exist.

[

The package is approximated as a rectangular solid of l

e.

(

0.33m length, 0.20m high and 0.14m wide.

t The maximum surface temperature is established from a steady state heat balance relationship.,

09i+9d"S S

c r

where a : Absorptivity (0.9)

~

qt: Solar Heat Load (72.28 watts) l l

qd: Decay Heat Load (0.257 watts) q: Convective Heat Transfer Radiative Heat Transfer g:

l' l

l Revision 0 10 April 1981 l

3-6 l

The convective heat transfer is:

(hA) top + (hA) sides (T - T )

q

=

w a

e where h: Convective Heat Transfgr Coefficient A: Area of the Surf ace of Interest T,:

Temperature of the Wall T,:

Ambient Temperature The heat transfer due to radiation is:

q= scA (T " - T ")

r w

a Where c : Stephan Boltzman Constant (5.67 x 10 s yj,2_ o *)

g c: Emissivity (0.8)

Iteration of this relationship demonstrates that.the wall temperature is 61.6 C which satisfies the requirement of paragraph 240 of IAEA Safety Series No. 6, 1973 Edition.

t l

Revision 0 10 April 1981 3-7

3.6.3 Model 910 Type B(U) Source Capsula Thermal Analysis Paragraph 238 of IAEA Safety Series No. 6, 1973 Edition This analysis demonstrates that the prem!ve inside :he Model 90004 or Model 90005 source capsule, when subjected to the thermal test, does nor exceed thel pressure which corresponds to the mini =n= yield i

strength of the material at the thermal test temperature.

The source capsules are f abricated from stainless steel, Type 304 or 304L. The outside diameter of each capsule is 0.205 inch (5.2mm).

The source capsule is seal welded. The minimum weld penetration is 0.020 inch (0.5mm). Under the conditions of internal pressure, the critical loca. tion for failure is this weld.

The internal volume of the _ source capsule contains only iridium metal as a solid and air. ft is assumed that the air is at standard tempera-2 ture and pressure (20 C; 100kN/m ) at the time of loading. This is'a conservative assumption because, during the welding process, the internal air is heated, causing some of the air mass to escape before the capsule is sealed. When the welded capsule returns to a=bient temperature, the internal pressure would be somewhat reduced.

Under the conditions of paragraph 238 of IAEA Safety Series No.,C 6,

it is assumed that the capsule could reach a temperature of 800 (1475,F). Using the ideal gas law and requiring the air to occupy a (sj constant volume, the internal gas pressure could reach 373kN/m (54 psi).

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

The maximum longitudinal stress is calculated from:

aA - PA g7 Where c: Longitudinal Stress y

2 A: Stress Area = 2(r r *)

g 2

P: Pressure (373kN/m )

A: Pressure Area = 2r.2 p

i From this relationship, the maximum longitudinal stress is calculated to be 686kN/m* (99 psi).

Revision 0 10 April 1981 3-8 e-f yg

-p--

e

.,r---

-ew

.m-u-m---,

f j

The hoop stress can be found by:

e 2c it - Pid h

g or ab = Prg t

where a: hoop stress h

1:

length of the cylinder e

t : thickness of the cylinder From this relationship, the hoop stress is calculated to be 1.54NN/m3 (223 psi).

At a temperature of 870 C (1600 F), the yield strength of Type 304 stainless steel is 69HN/m3 (10,000 psi). Thus, under the conditions of paragraph 238 of IAEA Safety Series No. 6,1973, the stress generated is less than 3% of the yield strength of the material.

I

.~

Revision 0 4 April 1981 3-9

4.

Centainment 4.1 Containment Soundary 4.1.1 Containment vessel The containment system for the Model 910 is the radioactive source

~

capsule as described in Section 2.10.

The source capsule is fabricated from either Type 304 or Type 304L stainless steel. The capsule is cylindrical in shape with a diameter of 0.205 inch (5.2mm) and a length of 0.650 inch (16.5mm).

4.1.2 Centainment Penetrations There are no penetrations of the containment.

4.1.3 Seals and k' elds The containment is seal velded by a tungsten inert gas velding process which is described in Tech / Ops Standard Source Encapsulation Procedure (Section 7.4).

The minimum veld penetration is 0.020 inch (0.51mm).

4.1.4 Closure Not applicable 4.2 Recuirements for Normal Conditions of Transport 4.2.1 Release of Radioactive Material This source capsule has satisfied the requirements for special~ form radioactive =aterial as delineated. in IAEA Safety Series No. 6,1973 Edition and 10CFR71. Therefore, there will be no release of radioactive material under the normal cpnditions of transport, l

l 4.2.2 Pressurization of the Containment Vessel Pressurization of the source capsule under the conditions of the hypothetical thermal accident was demenstrated to generate stresses

- vell below the structural limits of the capsule (Sections 3.5.4, 3.6.2).

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

i 4.2.3 Coolant Contamination Not Applicable Revision 0 10 April 1981 i

4-1

O 4.2.4 Coolant Less Not Applicable 4.3 Cc= tai =:nent Requiremets for the Hypcthetical Accident Conditions 4.3.1 Fissien Cas Products 4.3.2 Release of Centents ne hypothetical accident conditic=s of 10CFR71, Appe= dix 3 will result is no loss of package ecstainment as described is. Sections 2.7.1, 2.7.2, and 3.5.

Revisica 0 10 April 1961 -

4-2 l

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5.

Shialding Evnlurtion 5.1 Discussion and Results Tha Model 910 is shielded with 18 pounds of depleted uranium. The uranium shielding is cast around the tungsten source tube. A radia-tion profile on Model 910, Serial Number 2 containing 29.5 curies of iridium-192 was made. The results of this survey are presente d in Section 5.5.1.

Extrapolation of this data to a capacity of 30 curies of iridium-192 is presented in Table 5.1.

As the M6 del 910 has no neutron source, the gamma dose rates are the total dose rates which are presented, As shown in Table 5.1, the maximum dose rates are below the regulatory requirements.

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

At Surface At One Meter Side Top Bottom Side Top Bottom 15 3 142 92 2.0 1.6 1.1 5.2 Source Specification 5.2.1 Gamma Source The gamma source is iridium-192 in a sealed capsule as special form in quantities up to 30 curies.

5.2.2 Neutron Source l

Not Applicable 1

5.3 Model Specification Not Applicable -

5.4 Shielding Evaluation The shielding evaluation was performed on Model 910, Serial No. 2 c'on a taining 29.5 euries of iridium-192. The results of this survey (Section -

5.5.1) demonstrate that the dose rates surrounding this package are with-l in the regulatory requirements. A radiation profile was made on a Model 900 package after being subjected to the hypothetical accident conditions.

l That radiation profile showed that there was no significant change in the shielding effectiveness of that package as a result of these tests.

Be-cause of the similarity of the Model 910 to the Model 900, it is concluded that there would be no adverse affect on the shielding efficiency of the Model 910 as a result of the hypothetical accident conditions.

1 l

Revision 0 l

10 April 1981 I

5-1 i

J 5.5 Appendix

$.5.1.

Radiation Profile - Model 910 Serial No. 2

~

Revisica 0 10 April 1981 5-2

a TechiOps

.. ~ -

Aaoa*e P* cots Onesen i

a0 Nor n Aveu Buring::rt MassacNseas 01803 Teeoncn t07) 272 2000 Radiatics Profile Model 910 Serial Nu=ber 2

~

EP l

I L

G

~=

P!/R eM.

= ;.

CC

(

5 B~Tickt LEFT Containi.sg 29.5 Curies of Irid"um Maxi::ns Exposure Rates (=R/hr)

At Surface At 50=xn At 150=n At 1 Meter Top 140 45 19 1.6 Front 120 46 9

1.4 l

Right 15 0 42 16 1.4 I

Re ar -

110 40 20 1.7 Left 120 40 14 2.0 l !

Bottom 90 20 7

1.1 Measure:aents were =ade with an AN/PDR-27(j) Survey Instru:aent 1

l Revision 0 10 April 1981 l

l l

l 5-3 l

t 8.2 Maintenance Program 3.2.1 Structural and Pressure Tests Not Applicable 8.2.2 Leak Tests As described in Section d.1.3, the radioactive source assembly is leak tested at manufacture. Additionally, the source assembly is wipe tested for leakage of radioactive contamination every six months.

8.2.3 Subsystem Mnintenance I

The lock assembly is tested as described in Section 8.1.4 prior to each use of the package. Additionally, the package is inspected for : -

tightness of fasteners and general condition prior to each use.

i 8.2.4 Valves, Rupture Discs and Gaskets Not Applicable 8.2.5 Shielding i

l Prior to each use, a radiation survey of the package.'s made to assure that the radiation levels do not exceed 200 =illiroentgens per hour at the surface nor ten milliroentgens per hour at three feet form the surface.

8.2.6 The m i Not Applicable 8.2.7 Miscellaneous Inspections and tests designed for' secondary users of this package under the general license provisions of 10CFR71.12(b) are included

  • l in Section 7.4.

l 1

l Revision 0 10 April 1981 18981 8-2

,,_,,c.

O 6.

Criticality Evaluation Not Applicable l

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Revision 0 10 April 1981 l

i 6-1 l

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7.

Operating Procedures 7.1 Procedures for Loading the Package The procedure for f abricating the special form source capsule is presented in Section 7.4.

The procedure fur loading the source assembly into the package is presented in Section 7.4.

7.2 Procedures for Unioading the Package 5

The procedure for unloading the package is presented in Section 7.4.

~

7.3 Preparation of an Empty Package for Transport l

The procedure for preparation of an empty package for transport is

/

presented in Section 7.4.

I Revision 0 10 April 1981 7-1

7.4 Appendix Tech / Ops Stands-d Source Encapsulation Procedure Model c' ' Operating Instructions 1

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Revision 0 l

10 April 1981 l

l 7-2

ENCAPSULATION OF ST.ALED SOURCES - MODE.LS 90003 AND 91003 A.

Personnel Requirements Only an individual qualified as a Senior Radiological Technician shall 1s2 perform 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.

3.

General Requirements Iridium loading cell shall be used for the encapsulation of solid The 1s2 metallic 192 Iridium.

The maximum amount of is2 Iridium to be handled in this cell at any one time shall not exceed 1000 curies.

This cell is designed to be operated at' less than atmospheric pressure.

The exhaust blower provided shall not be turned off except when the cell is in a decontaminated condition.

Sources shall not be stored n this cell overnighc or when cell is un-attended. Unene.p-ulated material shall be returned to the transfer con-tainers and encapsulated sources transferred to approved source containers.

When any of the "through-the-wall" tools such as he velding fixture or transfer pigs are removed, the openings are to be closed with the plugs provided. The tools shall be decontaminated whenevar 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 contaminatics in excess of 0.001 aci of removable contamination is found, then items enst be t

decontaminated.

2.

If the welding fixture or the electrodes have been changed, per' form-the encapsulation procedure omitting the insertion of any activity.

Examine this dummy capsule by sectioning thru weld. Veld penetra '.

tion =ust be not less than 0.020 inch.

If weld is sound and penetration is at least 0.020 inch,. the pre-paration of active capsules may proceed. If not, the ccudition l

responsible for an unacceptable veld must be corrected and the 7re-paratory procedure repeated.

3, Check pressure differential across first absolute filter, as me.usured by the manometer on the left side of the hot cell. This in abc 2 %

inch of water for a new filter. When this pressure differru' tal rises to about 2 inches of water, the filter =ust be change.

Revision 0 10 April 1981 i

7-3

a

+

D.

Encapsulation Procedure 1.

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

Defective capsules shall be rejected.

2.

Degrease capsule components in the Ultrasonic Bath, using isopropyl alechol as degreasing agent, for a period of 10 minutes. Dry the capsule components at 100 C for a mini =um 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 ascunt of activit'y in capsule. Disposable funnel must be used with pellets and a brass rivet with wafers to prevent contamina-tien of weld zone.

7.

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

S.

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 jib for this purpose.

b.

Preflow argon, flush 10 seconds.

c.

Start 15 a=ps.

~

  • d.

Weld 15 amps.

i e.

Slope 15 amps.

f.

Post flow 15 seconds.

11. Visually inspect the veld. An acceptable weld must be continuous with-out cratering, cracks or evidence of blev eut.

If the veld is defect-ive, the capsule must be cleaned and revelded to acceptable conditions or disposed of as radioactive waste.

12.

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

Revision 0 10 April 1981 7-4

1 i

13. Wipe exterior of capsule with flannel patch wetted with EDTA solution or equivalent.
14. Count the patch with the scaler counting system. Patch must show no more than.005pci of contamination. If the patch shows more than

.005uci, the capsule must be cleaned and rewiped. If the rewipe patch still shows more than 0.005pCi of contamination, steps 8 through 11

~

must be repeated.

15. Vacuum bubble test the capsule. Place the welded capsule in a glass 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 aad boil off the residual alcohol. Reveld the capsule.

16. Transfer the capsule to the source loading fixture. Insert the source capsule into the source holder'. Screw the source holder together and install the roll pin. Check to assure that the pin does not protrude on either side.
17. Apply the tensile test to assembly by applying proof load of 100 lbs.

Extension under the load shall not exceed 0.05ic. If the extension exceeds 0.05 in., the source must be disposed of as radioactive waste.

18. Position the source in the exit port of hot cell. Withdraw all personnel f

to the control area. Use remote control to insert source in the ion chamber and position the source for maximum response.. 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 for the operation.

Revision 0 10 April 1981 7-5

o-y Tech / Ops Model 900, Model 910 and Model 920 Gamma Ray Projector Operation Manual Technical Data Size:

13 in long, 7.7 in high 5.3 in. wide (330=m long,195mm high,135mm wide)

Model 900 Model 910 Model 920 Weight:

441bs (20kg) 341bs (15kg) 471bs (21kg)

Shielding (Uranium) 2 Sibs (13kg) 181bs (8.2kg) 311bs (14kg)

Capacity (ir-192) 100Ci 25Ci 200Ci Transport Status Type B USA /9141/B USA /

/B USA /9143/B Source Assembly 90003 91003 90003 General The Models 900, 910 and 920 are designed for use as rrdiographic exposure devices, storage containers and transpcrt packages for the ir.dicated source assemblies.

b' The US Nuclear Regulatory-Commission allows the use of these devices only by persons who are specifically authorized under the terms of their license.

Application for a license to use this device should be made to:

Radioisotope Licensing Branch Division of Fuel Cycle and Material Safety US Nuclear Regulatory Commission Washington, DC 20555 Prior to the first shipment of these devices, the user, in addition, should register with:

Transportation Certification Branch Division of Fuel Cycle and Material Safety US Nuclear Regulatory Commission Washington, DC 20555 Revision 0 10 April 1981 7-6

TcchlOp2 Radaten P oc.cs Cwson 40 Nerft Averse Ik.rtrgon. Vassac*tse"s 018C3 Teeptere (617) 272 2000 Receipt 1.

Upon receipt of the pr'ojector system, survey the projector on all sides to ensure that radiation levels do not exceed the following:

At Surface 20 M /hr At 6 Inches from Surface S M /hr At 3 Feet from Surface 10mR/hr 2.

Check the projec.or, centrol unit and guide tubes for obvious da= age.

3.

Check packing list and Bill of Lading to ensure that all are intact and are representative of the ship =ent.

4.

Place the projector in a restricted area until ready to use.

Operation

- NOTE -

?2rsonnel using this projector =ust have a calibrated and operable survey seter with a range of at least 0 to 1000=R/hr. In adelition, personnel =onitoring devices =ust be vorn during these operations. They are dir:ect reading pocket dosimeter and either a film badge or a thermoluminescent dosi=eter.

Radiographic operat, ions =ust be conducted in a restricted area and the area must be

~

1.

Survey the projector on all sides and ensure that the radiation levels do not exceed 50 milliroentgens per hour at six inches

~

from the surface.

2.

Locate the projector and controls to afford the operator as =uch shielding as possible.

Revision 0 10 April 1981 7-7

Tcch / Ops Radiabon Products Chvisen 40 Nortti Avenue Buringon, Massachusetts 01803 Telephone (617) 272-2000 3.

At the rdiographic focal point, position and secure the source stop of the guide tube assembly.i 2

Connect together as many guide tube assemblies as necessary (maximum of three). Lay out the guide tube assembly as straight as possible (bend radius must be greater than 20 inches).

5.

Position the projector at the end of the guide tube assembly.

6.

From the projector, lay out the control cam es as straight as possible (bend radius must be greater than chree feet).

7.

Unlock the projector with the key and rotate the selector ring from the LOCK position to the CONNECT position. The storage cover will disengage from the projector.

8.

Engage the male connector of the driving cable to the female connector of the source u sembly.

9.

Slide the control cable connector forward into the locking L

assembly of the projector. Rotate the selector ring from the CONNECT position to the LOCK position. Depress the lock and remove the key.

10. Attach the guide tube assembly to the exit port of the projector.
11. Thoroughly check all cable connections, bend radii and the position of the source stop.
12. INSURE THAT NO ONE IS WITHIN 1"dE BOUNDARY OF THE RESTRICTED AREA.
13. With a survey meter, approach the proj'ector. Unlock the pro'jector with the key and turn the selector ring from the LOCK position to.,

the OPERATE position.

i 1

14.

Fully raise the source position indicator knob. The knob will stay in the raised position.

- NOTE -

If cranking becomes difficult at any time, return the source i= mediately to the stored position.

1 1

Revision 0 10 April 1981 l

l 7-8

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-A Radaten Producs Dwson 40 North Avenue Burtngton. Massachusetts 018o3 Teiephone (617) 272 2000

15. At the control unit, rapid 2y rotate the hand crank in the EXPOSE direction. Continue to rotate the hand crank until the source assembly reaches the source stop. The odometer should read the approximate distance of source travel.
16. At the end of the exposure time, rapidly rotate the hand crank in the RETRACT direction. Continue to rotate the hand crank until the source assembly reaches the storage position in the projector, which serves as a mechanical stop for the source assembly. The source position indicator knob should drop to the closed position and the odometer should read approximately 000.
17. Approach the projector with a survey meter. Survey the projector on all sides, survey the guide tube and survey the source stop to assure that the source assembly is in its proper stored position.

The radiation level should not exceed 50 milliroentgens per hour at six inches from the projector.

13.

Rotate the selector ring to the LOCK position. Lock the projector.

t

19. Disconnect the guide tube assembly frem the projector.

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20. Unlock the projector. Rotate the selector ring from the LOCK position to the CONNECT position. Slide the control cable connector back and disconnect the drive cable from the source assembly.

21.

Install the storage cover into the locking assembly and rotate the selector ring to the LOCK position. Depress the lock and remove the key.

Daily Inspection Daily inspection of radiography equipment is recomended to assure that the equipment is in proper working condition. Daily inspection should be performed prior to the start of each shift.

1.

Inspect the entire length of each guide tube section and insure that each section is free from dents. Inspect the end fittings to insure that they are tightly attached to the guide tube section.

Inspect the threads to insure that they are not galled or damaged.

Do not use damaged guide tubes.

Revision 0 10 April 1981 7-9

i u.

2.

Inspect the entire length of control cable housings and insure that each section is free from dents. Inspect the end fittings to insure that they are tightly attached to the control cable housings. Check the control cable connector for damage. Check the male source connector for damage. Do not use a damaged control unit.

3.

During the first radiographic operation, note the operation of the selector ring and lock assembly. If operation is difficult, do not operate the equipment.

I

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4.

During the first radiographic operation, note the operation of the control crank. If operation is difficult, retract the source to the stored position, and survey the equipment in accordance with the operating instructions.

Periodic Inspection and Maintenance Periodic inspection and maintenance of radiography equipment is recommended to assure that the equipment remains in proper working condition. Periodic inspection and maintenance should be performed at intervals not to exceed three months.

Projector 1.

Remove the source from the projector and install it in a source changer following the projector and scurce changer

.k operating instructions.

2.

Remove the rear plate from the projector. Disassemble the lock assembly.

3.

Clean the components of the lock assembly. Examine the com-ponents for damage, excessive wear, galling and burrs. Lightly lubricate the lock slide and locking pin with grease MIL-G-23827 or equivalent.

l Reassemble the locking assemb'17 and test for proper operation.

4.

5.

Remove the source position indicator rod. Remove the front end,.

plate and the indicator cover plate. Remove the indicator slide, locking pin, and slide tube.

i 6.

Clean these components. Examine the components for damage, excessive wear, galling and burrs. Lightly lubricate the in-dicator slide and locking pin with grease, MIL-G-23827 or equivalent.

7.

Clean the source tube.

1 Revision 0

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10 April 1981 l

7 - 10

u 8.

Reassemble the slide tube, locking pin, indicator slide, indicator cover plate and front end plate. Reinstall the source position indicator rod. Reinstall the rear end plate. Test the projector for proper operation.

Control Unit 1.

Crank the drive cable in the expose direction until the stop spring reaches the crank gear. Disassemble the control housing from the crank assembly. Remove the stop spring.

Remove the drive cable from the control unit.

2.

Clean the drive cable. Examine the drive cable for damage or excessive wear. Test the sale connector with Tech / Ops no-go gage. Check the male connector for proper connection to the driving cable.

3.

Remove the control housings from the control unit. Examine carefully for internal damage by flexing the housings by hand.

Internal damage to the reinforcing braid or flexible metallic tube will be evidenced by a crunch feeling when the cable housing is flexed.

Cut, flattened or burnt cable housings should be replaced. Superficial cuts or burns may be sealed and reinforced with tape. Clean housings by eyringing a few ounces of solvent into bore, and blow out with icw pressure

.s air (not more than 20 psi). Do not allow solvent to remain in housings. Do not soak in solvent. Check end fittings for -

secure attachment.

1 l

l 4.

Disassemble the crank unit. Wash parts in solvent. Check inside of housing for evidence of galling and wear. A deeply scored (more thac 020 deep) line where the cable contacts the inner vall of the housing indicates'the need for replacement.

Check clearance between the hubs of the wheel and the bushings.

More than.005 clearance indicates need for replacement.

Examine teeth of wheel for damage. A bent tooth may be filed'

~

off. Two or more adjacent bent teeth will require replacement of the wheel. Lubricate the gear with grease and MIL-G-23837 or equivalent.

5.

Reinstall the control housings to the crank unit. Lubricate the driving cable with grease MIL-G-23827 or equivalent. Reinstall the driving cable, installing the stop spring.

Source Guide Tubes 1.

Check for cuts, burns or crushed tubes. Check fittings for secure attachment. Examine and test screw threads for function.

Revision 0 10 April 1981 1

7 - 11

-gg Clean bore of tube with water or solvent and drain out pro =pely.

Do not soak in solvent. Check for free passage of source by holding tube vertical and dropping du:ny source asse=bly through tube. The du==y source asse=bly should f all through freely.

Final Inspection 1.

Check the syste= for proper reasse=bly. Check fittings for tightness.

2.

Reinstall the scurce into the projector following the projector and source changer operating instructions. Check for proper operation of the control unit, source position indicator and locking asse=bly.

3.

Survey the projector on all sides to assure that the radiation levels do not exceed the following:

At surface:

200=R/hr At 6 inches:

50=R/hr At 3 feet 10=R/hr 4.

Assure that the projector is properly labeled.

Leak Testing The source asse=bly in the Models 900, 910 and 920 =ust be leak tested at intervals not to exceed six :onths. This can be acco=plished using Tech / Ops Model 518 Leak Test Kit.

1.

Place the projector in a Restricted Area.

2.

Moisten the vipe test patch with EDTA solution.

3.

Wipe the exit port of the projector and the fe= ale connector assembly.

Place the vipe test patch in the pkastic envelope.

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4.

5.

Set the survey meter on its =est sensitive range and place the meter,

. b2 a low background area. Move the patch to the meter, not the meter to the vecch.

6.

If the meter indication is less than 0.2=R/hr above background, place the plastic envelope into the = ailing box and = ail to Technical Opera-tions. 3E SURE TO COMPLETE AND RETURN THE IDENTIFICATION SHEET.

7.

If the meter indication is = ore than 0.2=R/br, DO NOT MAIL. Contact Technical 0;erations for special instructions.

Revision 0 10 April 1981 7 - 12 m

The wipe test swab will be subjected to a precise radioassay when received by Tech / Ops and a leak test certificate will be mailed pro =ptly.

This certificate must be kept with your records. It is subject to NRC inspection.

Transportation 1.

Assure that the source assembly is in the proper storage position in the~ projector following the operating instruc-tions. Be sure that the storage cover is installed.

2.

Safety lock vire the source position indicator knob and cri=p the lead seal.

3.

Sarvey the projector on all sides at the surface and at one meter and determine the proper shipping label to be applied in accordance with Table I.

TABLE I Su r face 3 Feet RAD IOACTIVE-WHITE..I.

/

,' 8 N g s

g 0.5mR/hr None

/

DI0iTTIiE 6}

(

' s s=[

s 3

\\ FN,'

RADIOACTIVE.-YELLOW II

- s s

6. 'N a

s s '>

50mR/hr 1.0mR/hr s

D010ACilVEa5 /

s s :r.

/

N*lP

/

% r

~

\\/

l RADI0 ACTIVE-YELLON III

,/ss N

/

N

/

s

/

s 200mR/hr 10mR/hr (s '010ACTIVEzj,2 N %-Q } f N.

N

/

7 N

/

v P0a U

U ri.

10 April 1981 7 - 13

4.

Fill out information requested on label indicating:

a.

Contents (Isotope) b.

No. of Curies c.

Transport Index The Transport Index is determined by observing the maximum reading at 1 meter from the source container. This reading becomes the Transport Index.

5.

Remove all old shipping labels.

- NOTE -

Do not remove metal container identification label.

6.

Affix new shipping labels to two opposite sides.

7.

Properly complete the shipping papers indicating:

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

Name of Radionuclide (i.e.

' Iridium)

Physical or chemical form (or Special Form)

Activity of source (expressed in curies or millicuries)

Category of label applied (i.e., Radioactive Yellow III)

Transport Index i

USNRC Identification Number For export shipments, IAEA Identification Nu=ber

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Shipper's Certification:

l "This 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."

Revision 0 10 April 1981 7 - 14

>.. e e-A Notes:

1.

For air shipments, the following shipper's certification 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 proper condition for carriage by air accord-ing to applicable national governmental regulations."

2.

For air ship =ents, the package must be labeled with a

" CARGO AIRCRAFT ONLY" label and i.he shipping papers must state:

"THIS SHIPMENT IS WITHIN IHE LIMITATIONS PRESCRIBED FOR CARGO-ONLY AIRCRAFT."

Preparation of an Emptv Package for Tr'ansport 1.

To prepare an e=pty package for transport, follow the in-structions of the procedure above beginning with Step 2 with the following exceptions:

a.

The package =ust be marked " Radioactive Material - LSA-n o.s.

b.

The proper shipping name is Radioactive Material - LSA-n.o.s.

c.

Radionuclide is depleted uranium.

Revision 0 10 April 1981 7 - 15

7-m er 8.

Acceptance Test and Maintenance Program 8.1 Acceptance Tests _

8.1.1 visual Itapection The package is visually examined to assure that the appropriate fasteners are properly secured and the package is properly marked.

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

8.1.2 Structural and Pressure Tests The source assembly is subjected to a static tensile test with a load of seventy five pounds. Failure of this test will prevent the source assembly from being used.

8.1.3 Leak Tests The radioactive source capsule (the primary containment) is wipe tested for leakage of radioactive contamination. The source capsule is also subjected to a vacuum bubble leak test. These tests are described in Section 7.4.

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

S.1.4 Co=ponent Tests The lock assembly of the package is tested to assure that the security of the source assembly will be maintained. Failure of this test will prevent use of the package until the lock assembly is corrected and retested.

8.1.5 Tests for Shielding Integrity The radiation levels at the surf ace 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 tha rated capacity of the package, must not exceed 200 milliroentgens per,

hour at the surf ace nor 10 tilliroentgens per hour at three feet freni

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the surf ace of the pack 1ge.

Failure of this test will prevent use of the package.

8.1.6 Thermal Acceptance Test Not Applicable Revision 0 i

10 April 1981

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