ML19290E640

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SAR Model 900 Type B(U) Package
ML19290E640
Person / Time
Site: 07109141
Issue date: 02/01/1980
From:
TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:
Shared Package
ML19290E638 List:
References
NUDOCS 8003140322
Download: ML19290E640 (61)
v • d • e


Text

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nun, Rad.ation Products Dmsion 40 North Avenue Burhngton, Massachusetts 01803 Telephone (617) 272-2000 SAFETY ANALYSIS REPORT TECHNICAL OPERATIONS MODEL 900 TYPE B(U) FACKAGE

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1.

General Information I

1.1 Introduction Technical Operations Model 900 is designed for use as a radiographic exposure device and shipping container for Type B quantities of radioactive material in special form. The Model 900 conforms to the criteria for Type B(U) packaging in accordance with IAEA Safety Series No. 6, 1973 Edition.

1.2 Package Description 1.2.1 Packaging The Model 900 is 13 inches (330 mm) long, 7 7 inches (195 mn) high and 5 3 inches (135 nm) wide. The gross weight of the package is h4 pounds (20 kg).

The radioactive source capsule is housed in a source assembly which is fabricated from tungsten and stainless steel. The source asseibly is housed inside a tungsten source tube with an outside diameter of 0.63 inch (16c=) and inside diameters machined to conform to the configuration 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 28 pounds (13 kg).

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

The shield assebbly 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 enclosed with end plates fabricated from 0.09 inch (2 3 mm) thick stainless steel. The sides of the package are enclosed by a shell fabricated from 0.06 inch (15 mm) thick stainless steel.

The void space between the uranium shield assedbly 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 foam in the event that the package is involved in a fire accident.

Revision 0 1 Feb 1930 1-1

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The outer packagin6 is designed to avoid the collection and re-tension 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 radioactive material.

1.2.P Operational Features The source assedly is secured in the proper storage position by means of the locking ansembly. A lock slide 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 "LOCF" position by means of a key operate, k mounted on the rear plate of the projector.

In the event that She lock failed, the source assedbly would be contained within the package. The source position indicator slide would prevent movement in the forward direction.

In-terference between the source assembly and source tube vould prevent movement in the rearward direction.

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l.2 3 contents of Package The Model 900 is designed for the transport of iridium-192 in quantities of up to 120 curies as Tech / Ops source assedbly 90003 This source assembly contains Tech / Ops Model 9000h source capsule which satisfies the criteria for special form radioactive material in accordance with 10CFRT1 and IAEA Safety Series No. 6,1973 Edition.

Revision O 1 Feb 1980 1-2

t 13 APPENDIX Lescriptive Assembly Drawings, Model 900

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Structural Evaluation 2.1 Structural Design 2.1.1 Discussion Structurally, the Model 900 consists of fcur components:

source capsule, shield asse=bly, 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 functionc. 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 900 is designed to comply with the requirements of 10CFRTl and IAEA Safety Series No. 6,1973 Revised Edition.

2.2 Weights and Centers of Gravity The Model 900 veighs kh pounds (20 kg). The shield assembly contains 28 pounds (13 kg) of depleted uranium. The center of gravity was located experimentally. It is located approximately 4.5 inches

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(llhmm ) from the front surface, 30 inches (

To mm) from the bottom surface and 2 7 inches (68mm) from the right surface.

23 Mechanical Properties of Materials The housing of the Model 900 is fabricated from Type 304 stainless steel. This material Was a yield strength of 35,000 pounds per 2

square inch (241 MN/m ).

Drawings of the Model 90004 source capsule are enclosed in Section 2.10.

This source capsule is fabricated from Type 30h or Type 304L stain-less steel. The capsule is sealed by tungsten inert gas velding.

2.4 General Standards for All Packages 2.4.1 Chemicei and Galvanic Reactions The materials used in the construction of the Model 900 are uranium metal, stainless steel, tungsten, bronze, carbon steel, and aluminum. There vill be no chemical or galvanic action be-tween any of these components.

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

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Revision O 1 Feb 1980 2-1

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2.4.2 Positive Closure The source assembly in the Model 900 cannot be exposed without opening a key operated lock. Thus, positive closure is provided.

2.4.3 Liftina Devices The Model 900 is designed to be lifted by its handle. The handle is fabricated from aluminum and attached to the endplates by means of four No. 10-32 UNC flat head machine cerews. The weakest area of the handle is the screv gttachment. The stress area of each screw is 0.0175 in2 (11 3m= ).

The yield strength of these screws 2

is greater than h0,000 pounds per square inch (276 M'i/m ).

There-fore each screw can support 700 pounds (3.lkN) or more than fifteen times the weight of the package without exceeding the yield strength of the material.

2.h.2 Tiedown Devices The handle is also used as a tiedown device. As demonstrated in Section 2.4.3, each of the four screws attaching the handle can support more than fifteen times the weight of the package with-out exceeding the yield strength of the material.

25 Standards for Type B and Large Quantity Packages 251 Load Resistance

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Considering the package as a simple beam supported on both ends with a uniform load of five times the package weight evenly distributed along i 1 length, the maximu= stress generated can be computed from:

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I'aximum Stress Generated F: Total Load (220 pounds; 980 Newtons)

Length of Beam (13 inches 1:

Section Modulus (2 32 in3;; 330m=)38,018mm3)

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Machine ry's Handbook, 21st Edition, p.404)

The package is assumed to be a rectangular shell 5 0h inches (12Bmm) vide and 5 75 inches (lh6mm) high with a vall 'hickness of 0.06 inch (1 5mm). Consequently, the section modulus is 2 32 in.

From this relationship, the maximum stress generated in the beam is 154 pounds per square inch (1.06 MN/m2) which is far below the yield strength of the material.

Revision 0 1 Feb 1930 2-2

252 Bcternal Pressure The Model 900 is open to the atmosphere. Therefore, there vill be no differential pressure to act upon the package.

The collapsing pressure of the source capsule is calculated assuming that the capsules are thin vall tubing with the vall thickness equal to the minir:um depth of veld 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 t: Wall thickness (0.020 inch) d: Outside diameter (0.205 inch)

(

Reference:

Machine ry's Handbook, 21st Edition, p 440)

From this relationship, the collapsing cressure is co=puted to 2

be7070poundspersquareinch(491s/m). Therefore, the source capsule can withstand an external pressure of 25 psig without adverse affect.

2.6 Normal Conditions of Transport

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2.6.1 Heat The thermal evaluation of the Model 900 is presented in Chapter 3 From this evaluation, it can be concluded that the Model 820 can withstand the nor=al heat transport condition.

2.6.2 Cold The metals used in the manufacture of the Model 900 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 900 vill withstand the normal transport cold condition.

2.6.3 Pressure The Model 900 is open to the atmosphere. Therefore, there vill be no differential pressure to act upon it.

In Section 3 5.4, it is demonstrated that the source capsule is able tc withstand an external pressure reduction of 0 5 atmosphere (507kN/m2).

2.6.h Vibration A vibration test of the Model 900 was conducted. The package was Revision O 1 Feb 1980 2-3

vibrated for seventy minutes with a maximum acceleration of 9.8m/s2 at each cf 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.

Additionally, the Model 900 is similar in construction to the Model 660 (USA /9033/B(U)). The Model 660 has been in use for more than ten years. During that time, there have been no vibrational failures reported.

On these bases, it is concluded that the Model 900 vill withstand the normal transport vibration condition.

2.6.5 water spray Test The water spray test was not actually performed on the Model 9 00.

The materials 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 71 demonstrates that the Model 900 vill withstand the norral transport free drop

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condition without loss of shielding effectiveness nor loss of structural integrity.

2.6.7 Corner Drop Not Applicable 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 incluaed in Section 2.10.

2.6.9 Compression 2

The maximum cross sectional area of the Model 900 is 100 in. The weight of the package is 44 pounds. Therefore, five times the weight of the package is greater than two pounds per square inch times the maximum cross sectional area. The load used is 220 pounds.

Revision 0 1 Feb 1980 2-h

The Model 900 was subjected to the conditions of the co=pression test. There was no reduction of shieldin6 effectiveness nor loss of structural integrity as a result of this test. A copy of this test report is included in Section 2.10.

27 Rypothetical Accident Conditions 2 7.1 Pree Drop The Model 900 was subjected to a drop test through a distance of 30 feet (91m) onto a steel plate. There was no loss of shielding effectiveness nor loss of structural integrity as a result of this test. A copy of the test report is included in Section 2.10.

2.7.2 Puncture The Model 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 lon6 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.

273 Thermal The thermal analysis is presented in Section 3 5 It is shown that the melting temperatures of the materials used in the con-(

struction of the Model 903 except the polyurethane foam, and the aluminun handle, are all in excess of lh75 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.

Thus, it is concluded that the Model 900 satisfactorily meets the requirements for the hypothetical accident - thermal condition of 10CFR71.

2 7.4 Water Im=ersion Not Applicable 275 Sut=ary of Damage The tests designed to represent the hypothetical accident conditiens caused minor deformation but no reduction of shielding effectiveness Revision O 1 Feb 1980

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nor loss of structural integrity. A radiation profile of the package at the conclusion of these tests is presented in Chapter 5 2.8 Special Form The Model 900 is designed for use with Tech / Ops Model 90003 Source Assembly which includes Tech / Ops Model 90004 Source Capsule. This capsule has been tested to the criteria for special form radioactive material in accordance with the requirements of 10CFR71 and IAEA Safety Series No. 6, 1973 with satisfactory results. Application has been sent to the US Depaetment of Transportation for an IAEA Certificate of Competent Authority for this source capsule.

29 Fuel Rods Not Applicable

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Revision 0 1 Feb 1980 2-6

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i 2.10 Appendix Descriptive Assembly Drawings - Source Capsule Test Report: Vibration Resistance Test Test Report: Penetration Test Test Report: Compression Test Test Report: Free Fall Test Test Report: Puncture Test

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RADIATION PRODUCTS DIVISION TEST REPORT BY:

George Parsons DATE:

30 January 1980

SUBJECT:

Model 900 Vibration Resistance Test A vibration resistance test of the Model 900 radiographic exposure device-Type B package was conducted by Associated Testing Laboratory, Burlington, MA, on 9 January 1980 in accordance with International Standard ISO 3999.

The device was f astened to the platform of a vibrating machine and was continuously scanned through a frequency range of SHz to 80Hz with a maximum acceleration of 9.8m/see to search for a resonant frequency.

Over this This scan was performed on each of three rectilinear axis.

range, there was no resonant frequency found.

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

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

As a result of this test, there was no loss of structural integrity nor loss of shielding efficiency. There was no loosening of fasteners. The device functioned normally at the conclusion of the test.

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REVIS:c:: o ric 2-il

TEST REPORT RADIATION PRODUCTS DIVISION BY:

David Marzilli DATE:

14 January 1980

SUBJECT:

Model 900 Penetration Test On 14 January 1980 a penetration test was performed 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 Standard 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

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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 ncted.

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

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RADIATION PRODUCTS DIVISION BY:

David Marsilli DATE:

7 January 1980

SUBJECT:

Model 900 Co=pression Test On 3 January 1980 a Model 900 Ga==s Ray Projector was subjected to a compression test exceeding the requirements in 10CFRT1, Appendix A, Section 9 and IAEA Safety Series No. t3, paragraph 713 The Nodel 900, veight 20P4 (k5 pounds), was loaded with 105kg (232 pounds) of lead and steel evenly

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distributed alorg the upper surface of the package. 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.eas no evident damage of the package.

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TEST REPORT RADIATION PRODUCTS DIVISION BY:

David Marzilli DATE:

14 January 1980

SUBJECT:

Model 900, 30 Ft. Free Fall Test Ch 11 January 1980, a Model 900 Gamma Ray Projector was submitted to a free fall of 30 feet, as outlined in 10CFR71 and IAEA Safety Series No. 6, 1973. The drop was done twice, onto a concrete driveway covered with a 7/16 inch steel plate. On the first drop the machine impacted on its front face, bounced and impacted the rear. The second drop caused the machine to impact on its rear lower left corner (as the machine is faced from the rear).

The first drop caused the indicator cover plate screws (4) and the lower four front end plate screws to shear. The front housing 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

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loss of security of the source assembly. Thus, it is concluded that the Model 900 satisfies the requirements of the free fall test as described in 10CFR71, IAEA Safety Series No. 6, 1973 and ISO 3999.

Witnessed:

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a s. TEST REPORT RADIATION PRODUCTS DIVISION BY: David Marzilli DATE: 14 January 1980

SUBJECT:

Model 900 Puncture Test On 11 January 1980 a Model 900 Gamma Ray Projector was twice submitted to a free fall of 40 inches onto a six inch liameter steel billet. The projector had already been twice submitted to a 30 foot free fall (See Test Report dated 14 January 1980). The most vulnerable portion of the Model 900 was deemed to be the lock mechanism. The package was dropped 40 inches onto its lock, once in shear and once in compression. There was no structural or functional damage. I Thus, we conclude that the Model 900 meets the requirements of the puncture test as described in 10CFR71 and IAEA Safety Series No. 6, 1973. O

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30 Therral Evaluation 31 Discussion The Model 900 is a completely passive ther=al 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 vatts. 32 Su=.ary of Thermal Progrties of Materials The melting points of the maw.Jals used in the construction of Lhe Model 900 are: Steel 2453 F (1345 C) Uranium 2070 F (1133C) 0 Tungsten 60980F (3370 C) 0 Bronze 1840 F (1005 0) O Aluminum 1220 F (660 C) The polyurethane foam has a minimum operating range of -100 F temperature (8000C)3c). (-73 C) to 200oF (o It vill decompose at the fire test Decomposition vill result in gaseous typroducts which will burn in air. 33 Technical Specification of Components (' Not Applicable 3.k I;ormal Conditions of Transport 3.4.1 Thermal Model The heat source in the Model 900 is a maximum of 120 curies of iridium-192. Iridiu=-192 decays with a total energy liberation of 1.h5 MeV per disintegration or 8 58 millivatts per curie. Assuming that all of the decay energy is transformed into heat, the heat generation rate for the 120 curies of iridium-192 would be 1.03 vatts. To demonstrate co=pliance with the requirements of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 Edition for Type B(U) packaging, an analysis is presented in Section 3.6.1. The therral model employed 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 O 1 Feb 1980 3-1

3 4.2 Maximum Temperatures The caximum temperatures encountered under norcal 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 vould be less than 42 C and the maximum tenperature 0 when insolated would be less than 62 C. 3.4.3 Minimum Te=peratures The minimum normal operating temperature of the Model 900 is -40 C (-40 F). This temperature vill have no adverse affect on the package. 3.4.4 Maximum Internal 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 loss of shielding nor containment. 3.4.5 Maximum Thermal Stresses The maximum temperatures that occur during normal transport are low enough to insure that thermal gradients vill cause no significant thermal stresses. 3 4.6 Evaluation of Package Performance for Normal Conditions of Transport i The thermal conditions of normal transport are insignificant fro: a functional riavpoint for the Model 900. The applicable conditions of IAEA Safety Serc I;o. 6,1973 Edition for Type B(U) packagec have been shown to be satisff ed by the Model 900. 35 Hypothetical Accident Thermal Evaluation 351 Thermal Model The Model 900, ine) ling the source assembly, is assumed to reach the thermal test temperature of 800 C. At this temperature the polyurethane foam vill have decomposed and the resulting gases vill have escaped the package through vent holes and non-leak tight assembly joints. 352 Packace Conditions and Environment The Model 900 underwent no significant damage during the free drop and puncture tests. The package used in this analysis is considered undamaged. Re'.sion O 1 Feb 1980 3-2 x n.. . - -,..,~ --- -.,,.

n 353 Package Temperatures As indicated in Section 3 5.1, the entire package is ascu=ed to reach a temperature of 800 C. Examination of the melting tempera-tures of the materials used in the construction of the Model 900 indicates that there vill be no damage to the package as a result of this te=perature. The possibility of the romation of an iron-uranium eutectic alloy was addressed in Section 2.4.1 where it was concluded that the fomation of the alloy was not a likely eventuality. 354 yaximum Internal pressures The Model 900 packaging is open to the atmosphere. Therefore, there vill be no pressure buildup within the package. In Section 3.6, an analysis of the source capsules under the thermal test coidition demonstrates that the maximum internal gas pressure 0 2 at 800 C is 54 psi (373kN/m ), In Section 3.6.3, an analysis is presented which demonstrates that the 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. 355 Maximum Themal Stiesces There are no significant themal stresses generated during the thermal test. 356 Evaluation of Packare Ferformance The Model 900 vill 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. Revision o 1 Feb 1980 3-3 t ~ -- ~~

36 Apnendix 3.6.1 Model 900 Type B(U) Thermal Analysis: Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 Edition 3.6.2 Model 900 Type B(U) Thermal Analysis: Paragraph 240 of IAEA Safety Series No. 6,1973 Edition 3.6.3 Model 900 Type B(U) Source Capsule Thermal Analysis: Paragraph 238 of IAEA Safety Series No. 6, 1973 Edition Revision 0 1 Feb 1980 3-4 (

3.6.1 Model 900 Type B(U) Thermal Analysis Parnernehs 231 and 232 of IAEA Safety _ Series No. 6, 1973 Edition This analysis demonstrates that the maximum surfac s temperature of the Model 900 win not exceed 500c (122 F) with the package 0 in the shade and at an ambient temperature of 38or (100 F). To assure conservatiam, the following assumptions are used: The entire decay heat (1.03 vatts) is deposited a. in the exterior faces of the Model 900. b. The interior of the Model 900 is perfectly insulated and heat transfer occurs only from the exterior vall to the atmosphere. c. Because each face of the package eclipses a different solid angle, it is assumed that twenty five percent of the total heat is deposited in the smallest face (front). d. The only heat transfer mechanism is free convection. Using these assu=ptions, the maximum wall temperature is found from: q = hA(Tv - Ta) 1 (' and h = 1.42 ~Tv - TaY L where q: Heat deposited per unit time in the face of interest (0.26 vatts) h: Free convective heat transfer coefficient for air in vatts/m2 c 2 A: Area of the face of interest (0.026m ) Tv: Maximum temperature of ti.e vall of the package. Ta: Ambient temperat.re (38o ) c L: Heige '. <? the face of interest (0.20 m) From this relations ip, the maximum temperature of the vall is 415 0 (107 F). This satisfies the requirement of paragraphs 0 231 and 232 of IAEA Safety Series No. 6, 1973 Edition. Revision 0 1 February 1980 3-5 (.

es. 3.6.2 Model 900 Type B(u) Thermal Analysis Paragraph 240 of IAEA Safety Series No. 6, 1973 Edition This analysis demonstrates that the maximu= surface temperatures of the Model 900 vill not ex:eed 820c (1800F) when the package is in an ambient temperature of 380C (100 F) and insolated in accordance 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. a. The package is insolated at the rate of 73 v/m2 (800 cal /cm2 - 12h) on the top surface, 194 v'/m2 (200 cal /cm2 - 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 absorptivity is assumed to be 0 9 The solar emissivity is assumed to be 0.8. d. The package is assumed to undergo free convection from the top and sides and undergo radiation from the top, ( sides and bottom. The inside faces are considered insulated so there is no conduction into the package. The faces are considered to be sufficiently thin that no temperature gradients exist. e. The package is approximated as a rectan,'ular solid of 0 33m length, 0.20m high and 0.14m vide. The maximum surface temperature is established from a steady state heat balance relationship. o(Qi + 9d = Qe + gr where o( : Absorptivity (0 9) q.: Solar Heat Load (72.28 watts) 9: Decay Heat Loed (1.03 vetts) d 9c: Convective Heat Transfer S: Radiative Heat Transfer r Revision 0 1 Feb 1980 s 3-6

The convective heat transfer is: 9e" ( M ) top + (hA) sides v a where b : Convective Heat Transfer Coefficient A : Area of the surface of interest Tv: Temperature of the vall Ta : Ambient Temperature The heat transfer due to radiation is: b g = Cr E A (T - T,h) r y Stephan Boltzcan C(: stant (5.67 x 10~0 v/c2 O,4) where o: p E: E=issivity (0.8) Iteration of this relationship de=onstrates that the vall temperature is 61.8 C which satisfies the requirement of paragraph 240 of IAEA Safety Series No. 6, 1973 Edition. ( Revision 0 1 Feb 1980 3-7 p 9 swe pp 4e w e.-p, ase p gow w e D ',h ""*M'* "n mM e 9 M

. ~ ' = 'r M del 900 Type B(U) S ur e Capsule Thermal Analysis 3.6.3 Paragraph 238 of IAEA Safety Series No. 6,1973 Edition This analysis demonstrates that tbt pressure inside the Model 90004 source capsule, when subjected to the thermal test, does not exceed the pressure which corresponds to the minimum yie.ld strength of the material at the thermal test temperature. The source capsule is fabricated from stain 3ess utee2, Type 304 or 304L. The outside diameter of the capsule is 0.205 reh (5 2=m). The source capsule in seal velded. The minimum veld penetration is 0.020 inch (0 5mm). Under the conditions of internal pressure, the critical location for failure is this veld. The internal volume of the source capsule contains only iridium metal as a solid and air. It is escumed that the air is at 2 standard tecperature and pressure (20 C; 100kU/m ) at the time of loading. This is a conservative assu=ption because, during the velding process, the internal air is heated, causing so=e of the air mass to escape before the capsule is sealed. When the velded capsule returns to ambient temperature, the internal pressure vould be somewhat reduced. Under the conditions of paragraph 238 of IAEA Safety Series no. 6, it is assumed that the capsule could reach a temperature of 800 C (1475 F). Using the ideal gas law and requiring the air to occu ( a constant volume, the internal gas pressure could reach 373kN/m'py (Skysi). The capsule is assumed to be a thin valled cylindrical pressure vessel. The maximum longitudinal stress is calculated from: o-A, = pap where a;: Longitudinal stress 2 2 19: Stress Area = 7T(r - ri ) o P: Pressure A: Pressure Area = 7f ri p From this relationship, the maximum longitudinal stress is calculated to be 686kN/m2 (99p31), Revision 0 1 Feb 1980 3-8

~ = From this relationship the maxir:um longitudinal stress is calculated to be 686kN (99 psi). The hoop stress can be found by: 2oh it = Pldi where crh : hoop stress 1: Length of the cylinder t: Thickness of the cylinder From this relationship, the hoop stress is calculated to be 1 54 MN/m2 (223 psi).

  • ),000 psi).

At a temperature of 870*C ( 6 F the yield strength of Type (10, Thus, under the s 304 stainless steel is 69 conditions of paragraph 23 of IAEA Safety Series No. 6, 1973, the stress generated is less than 3% of the yield strength of the material. ( Revision 0 1 Feb 1980 3-9

,u. i h. Containment h.1 Containment Boundary ( 4.1.1 Containment Vessel The containment system for the Model 900 is the radioactive source capsule as described in Section 2.10. The source capsule is fabricated from either Type 304 or Type 30hL 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 5 mm). 4.1.2 Containment penetrations There are no penetrations of the containment. h.1 3 Seals and Welds The containment is seal velded by a tungsten inert gas velding process which is described in Tech / Ops Standard Source Encapsula-tion Procedure (Section T.4). The minir:um veld penetration is 0.020 inch (0 51cm). 4.1.4 Closure Not Applicable ( h.2 Recuirements for Normal Conditions cf Transport h.2.1 Release of Radioactive Material This source capsule has satisfied the requirements for special for= radioactive material as delineated in IAEA Safety Series No. 6,1973 Edition and 10CFRT1. Therefore, there vill be no release of radioactive material under the normal conditions of transport. 4.2.2 Pressurization of the Containment Vessel Pressurization of the source capsule under the conditions of the hypothetical thermal accident was demonstrated to generate stresses well below the structural limits of the capsule (Sections 3 5.4, 3.6.2). Thus, the containment vill withstand the pressure varia-tions of nor=al transport. h.2.3 Coolant Contamination Not Applicable Revision 0 1 Feb 1980 h-1

p. 4-4.2.h Coolant Loss Not Applicable 4.3 Contain:nent Requirements for the Hypothetical Accident Conditions 4.3 1 Fission Gas Products Not Applicable h.3 2 Release of Contents The hypothetic accident conditions of 10CFRT1, Appendix B vill result in no loos of package containment as described in Sections 2 71, 2 7 2 and 3 5 Revision 0 1 Feb 1980 h-2

T a 5 Shielding Evaluation 51 Discussion and Results The Model 900 is shielded with 28 pounds of depleted uranium. The uranium shielding is cast around the tungsten source tube. A radiation profile on Model 900, serial number 1 containing 110 curies of iridium-192 was made. The results of this survey are presented in Section 5 5 1. Extrapolation of this data to a capacity of 120 curies of iridium-192 is presented in Table 51. As the Model 900 has no neutron source, the gam:::a 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 Su=cary of Maximum Dose Rates (cR/hr) At Surface At One Meter Side Top Botto= Side Top Bottom 175 153 109 1.1 1.1 05 52 Source Specification 5 2.1 Gama Source s The ga:::a source is iridiu a-192 in a sealed capsule as special form in quantities up to 120 curies. 5 2.2 Neutron Source Not Applicable 53 Model Specification Not Applicable 5.h Shielding Evrluation The shielding evaluation was performed on Model 900, Serial No.1 containing 110 curies of iridium-192. The results of this survey (Section 5 5 1) demonstrate that the dose rates surrounding this package are within the regulatory requirements. A radiation profile made on this package after being subjected to the hypothetical accident conditions (Section 5 5 2) show that there was no significant change in the shielding effectiveness. Revision o 1 Feb 1980 5-1

T ~ 55 Apoendix 551 Radiation Profile - Model 900 Serial No. 1 552 Radiation Profile - Nodel 900 Serial No.1 After hypothetical accident conditions ( Revision 0 1 Feb 1980 5-2 s

,. 7 'l ~ Tech / Ops Radiation Products Divison 40 North Avenue Burhngton, Massachusetts 01803 Telephone (617) 272-2000 551 Radiation Profile Model 900 Serial Number 1 Top / F R R 2e (( r i o g a g f n r h t i J t Bottom Containing 110 curies of iridium-192 Maxiram Dose Rates (mR/hr) @ Surface @ 50mm @ 150mm @ l meter Top 140 32 11 1.0 Front 120 38 16 1.0 Right 160 41 12 0.8 Rear 150 33 12 1.0 Left 145 38 14 1.0 Bottom 100 21 9 05 Measurements were made with an AN/PDR-27(J) Survey Instrument. Revision 0 1 Feb 1980 5-3

_.n 1* k. ' Tech / Ops ,.,, ~ - Radaten Products Dmson 40 North Avenue Burkngton, Massachusetts 01803 Telephone (617) 272 2000 5.5.2 Radiation Profile Model 900 Serial Number 1 (After Hypothetical Accident Tests) Top F 3* L 1 E e g n _a f t r h g I t Bottom s Containing 113 curies of iridium-192 Maximum Dose Rates (mR/hr) @ Surface @ 50=m @ 150=m @ 1 Meter Top 130 28 11 < 1. 0 Front 90 26 11 ( 1.0 Right 150 31 12 ( 1.0 Rear 130 35 12 ( 1.0 Left 120 32 10 < 1. 0 Bottom 110 26 11 ( 1.0 Measurements were made with an AN/PDR-27(J) Survey Instrument. Revision 0 1 Feb 1980 5-4 (

.1 6. Criticality Evaluation Not Applicable Revision 0 1 Feb 1980 6-1 N ~ ~ * * ~

g' 3 7 Operating Procedures 71 Procedures for Loading the Package The procedure for fabricating the special form cource capsule is presented in Section 7.4. The procedure for loading the source assembly into the package is presented in Section 7.4. 72 Procedures for Unloading the Package The procedure for unloading the package is presented in Section 7.h. 73 Preparation of an Empty Package for Transport The procedure for preparation of an empty package for transport is presented in Section 7.4. ( Revision O 1 Feb 1980 7-1 (

.T... -n ~ RADIATION SAFEIY MANUAL \\ Part II In Plant Opera l; ions Section 2 ENCAPSULATION OF. SEALED SOURCES A. Personnel Requirements Only an individual qualified as a Senior Radiological Technician shall perform the operations associated with the encapsulation of 192 Iridium. There must be a second qualified Radiological Technician available in the building when these operations cre being perfor=ed. B. General Requirements The 192 Iridium loading cell shall be used for the encapsulation of solid metallic 192IridiumandthepackagingofsealedsouregOs such 169 as 170 Thulium,137 cesium and Ytterbium. Solid metallic cobalt not exceeding one curie may be handled in T,his cell also. The maximum amount of 192 Iridium to be handled in this cell at any ( one ti:ae shall not exceed 1000 curies. The =axirun arount of 13'cs to 'a "" -' i n this cell at an; cne tire shall not exceed in0 cu-ies. This cell is designed to be operated at less than etrospheric pressure. The exhaust blower provided shall not be turned off except when the cell is in a decontaminated 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-vall" tools such as the velding fixture or transfer pigs are recoved, the openin6s are to be closed with the plugs provided. These tools shall be decontaminated whenever they are recoved from the hot cell. C. Preparatory Procedure 1. Check welding fixture, capsule drawer and =anipulator fingers from cell and survey for contatination. If contamine'. ion in excess of 0.001 p.Ci of removable contamination is found, these ite=s must be decontaminated. 2. If the velding fixture or the electrodes have been chance:1, perfort the encapsulation procedure omitting the insertion of any activity. Examine this du= y capsule by secticning thru veld. Weld penetraticn rust be not less than 0.029 inch. REVISION O FEB. 1 st II.2.1

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ns ]p If weld is sound and penetration is at least 0.020 inch, the preparation of active capsules may proceed. If not, the I condition responsible for an unacceptable veld must be corrected and the preparatory procedure repeated. 3 Check pressure differential across first absolute filter, as measured by the manometer on the left side of the hot cell. 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. D. Encapsulation Fracedure 1. Prior to use, assemble and visually inspect the two capsule components to determine if weld zone exhibits any misalignment and/orseparation. Defective capsules shall be rejected. 2. Degrease capsule components in the Ultrasonic Bath, using isopropyl alcohol as degreasing agent, for a period of 10 0 minutes. Dry the capsule components at 100 C for a minimum of twenty minutes. 3 Insert espsule components into hot cell with the posting bar. h. Place capsule in veld positioning device. 5 Nove draver of source transfer container into hot cell. d. Flece prc;er nic c" cf seti.i ;. i" ca; sule Disr c n le funnel cust be used with pelle:s and a trass rive: vith vafers to prevent contarination of veld zone. 7 Remove unused radioactive material from th-hot cell by with-drawing 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:

a. Electrode spacinE.021" to.02h" centered on joint +.002"; use jig for this purpose. b. Preflow ar6cn, flush 10 seconds. c. Start 15 amps. d. Weld 15 arps. (. e. Slope 15 anps. f. Post flov 15 seconds IUEVISICIN O FEB. 1 ggg( ,.3 II.2.2

7cy 11. Visually inspect the veld. An acceptable veld must be continuous without cratering, cracks or evidence of blow out. If the veld is defective, the capsule must be cleaned and revelded to acceptable conditions or disposed of as radioactive vaste. 12. Check the capsule in height gauge to be sure that the veld is at the center of the capsule. 13 Wipe exterior of capsule with flannel patch wetted with EDTA solution or equivalent. Ih. Count the patch with the scaler counting system. Patch must show no more than.005/4C1 of contamination. If the patch shows more than.005/4C1, the capsule =ust be cleaned and reviped. If the revipe paten still shows more than 0.005 ACi of contarina-f tion, steps 8 through 11 sust be repeated. 15 Vacuum bubble test the capsule. Place t he velded capsule in a glass vial containing isopropyl alcohol. Apply a vacuum of 15 in Hg(Gauge). Any visual detection of bubbles vill indicate a leaking source. If the source is determined to be leakin6, place the source in a dry vacuum vial and boil off the residual alcohol. Reveld the capsule. ~ ~

16. Transfer the capsule to the svaging fixture. Insert the vire and connector assembly and svage.

Hydraulic pressure should not be less than 1250 nor more than 1500 pounds.

17.. Apply the tensile test to assedbly between the capsule and i

connector by applying proof load of 75 lbs. Extension under the load shall not exceed C.1 inch. If the extension exceeds 2.1 inch, the scurce mn -- be dis;csc. Of es reiic::ti ce 1:1;;e. 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 chaiber 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 frcm cell into source changer thrcugh the tube geuze wipe test fixture. Mcnitor before reentering the hot cell are;to be sure that the source is in the source changer. Remove the tuhe gauze and count with scaler counting system. This assay must show no more than 0.005 Ci. If contamination is in excess of this level, the source is leaking and shall be rejected. 20. Complete e Source Loading Log (Figure II.2.1) for the oceration. s 23 REVISION O 3_4 FEB. 1 192:

w. Tech / Ops ra-Radiation Products Division 'g 40 North Avenue Buriangton, Massachusetts 01803 Telephone (617) 272-2000 Tech / Ops Model 900 Gamma Ray Projector Operation Manual Technical Data Size: 13 in. long, 7.7 in. high 5.3 in, wide (330mm long, 195mm high, 135mm wide) Weight: 44 pounds (20kg) Shielding: Depleted Uranium. 28 pounds (13kg) Capacity: 100 curies of Iridium-192 as source assembly model 90003 Transport Status: Type B USNRC USA / /B IAEA USA / /B(U) General The Model 900 is designed for use as a radiographic exposure device, storage container and transport package for Tech / Ops Model 90003 source assembly. The US Nuclear Regulatory Commission allows the use of this device 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 this device, the user, in addition, should register with: Transportation Branch Division of Fuel Cycle and Material Safety US Nuclear Regulatory Commission Washington, DC 20555 1 REVISION O 7-5 FEB. I 1950

.=, 7 Tech / Ops Radiation Products Dvison 40 North Avenue Burhngton, Massachusetts 01803 Telephone (617) 272 2000 Receipt 1. Upon receipt of the projector system, survey the projector on all sides to ensure that radiation levels do not exceed the following: At Surface 200mR/hr At 6 Inches from Surface 50mR/hr At 3 Feet from Surface 10mR/hr 2. Check the projector, control unit and guide tubes for obvious damage. 3. Check packing list and Bill of Lading to ensure that all are intact and are representative of the shipment. 4. Place the projector in a restricted area until ready to use. Operation - NOTE - Personnel using this projector must have a calibrated and operable survey meter with a range of at least 0 to 1000mR/hr. In addition, personnel monitoring devices must be worn during these operations. They are direct reading pocket dosimeter and either a film badge or a thermoluminescent dosimeter. Radiographic operations must be conducted in a restricted area and the area must be posted as required in 10CFR20. 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 much shielding as possible. ' EEVISION 6 FEb. 1*.

s 3,_ Tech / Ops r. 7 m Radiation Products Divisen 40 North Avenue Burhngton, Massachusetts 01803 TeWpene (61D 272 20% 3. At the radiographic focal point, position and secure the source stop of the guide tube assembly. 4. 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 prcjector, lay out the control cables as straight as possible (bend radius must be greater than three 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 assembly, t 9. Slide the control cable connector forward into the locking 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 THE BOUNDARY OF THE RESTRICTED AREA. 13. With a survey meter, approach the projector. Unlock the projector with the key and turn the selector ring from the LOCK position to-the OPERATE position. 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 immediately to the stored position. REVISICN O 7-7 FEB. 1"

di i e_ =?:' Tech / Ops Radiation Products Divison 40 North Avenue Burkngton, Massachusetts 01803 Telephone (617) 272-2000

15. At the control unit, rapidly 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. 18. Rotate the selector ring to the LOCK position. Lock the projector. 19. Disconnect the guide tube assembly from the projector. x 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 recommended 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. _4-REVISIC" ^ y_7 FEB. I 1930

7 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 attsched to the cont.o1 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. 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 source changer t 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. 4. Reassemble the locking assembly and test for proper operation. 5. Remove the source position indicator rod. Remove the front nd plate and the indicator cover plate. Remove the indicator slide, locking pin, and slide tube. 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,IGL-G-23827 or equivalent. 7. Clean the source tube. , REVISIC" O FEB. 1 f fE

g;__. r ISE. 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 male 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 syringing a few ounces of solvent into bore, and blow out with low pressure 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. 4. Disassemble the crank unit. Wash parts in solvent. Check inside of housing for evidence of galling and wear. A deeply scored (more than 020 deep) line where the cable contacts the inner wall of the Fousing indicates the need for replacement. Check clearance betwera the hubs of the wheel and the bushings. More than.005 clearaace 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. 7_fo FEB. 1 198

-r 3;. EL y, Clean bore of tube with water or solvent and drain out promptly. Do not soak in solvent. Check for free passage of source by holding tube vertical and dropping dummy source assembly through tube. The dummy source assembly should fall through freely. Final Inspection 1. Check the system for proper reassembly. Check fittings for tightness. 2. Reinstall the source into the projector following the projector and source changer operating instr-ctions. Check for proper operation of the control unit, source position indicator and locking assembly. 3. Survey the projector on all sides to assure that the radiation levels do not exceed the following: At Surface: 200 mR/hr At 6 inches: 50 mR/hr At 3 feet: 10mR/hr 4. Assure that the projector is properly labeled. Leak Testing k The source assembly in the Model 900 must be leak tested at intervals not to exceed six months. This can be accomplished using Tech / Ops Model 518 Leak Test Kit. 1. Place the Model 900 in a restricted area. 2, Moisten the wipe test patch with EDTA solution. 3. Wipe the exit port of the projector and the female connector assembly. 4. Place the wipe test patch in the plastic envelope. 5. Set the survey meter on its most sensitive range and place the meter in a low background area. Move the patch to the meter, not the meter to the patch. 6. If the meter indication is le_; than 0.2mR/hr above background, place the plastic envelope into the mailing box and mail to Technical Operations. BE SURE TO COMPLETE AND RETURN THE IDENTIFICATION SHEET. 7. If the meter indication is more than 0.2mR/hr, DO NOT MAIL. Contact Technical Operations for special instructions. REVISION O 7- FEB. i 1980

c' The wipe test swab will be subjected to a precise radioassay when received by Tech / Ops and a leak test certificate will be mailed promptly. 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 wire the source position indicator knob and crimp the lead seal. 3. Survey 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 fa ce 3 Fee t RADIOACTIVE-WHITE.1, A / s ' b, \\ s f / g N ( ( N 0.5mR/hr None RADIDACTIVE s x = =. r x I / N rN. ' RADIOACTIVE-YELLOW II ' \\ \\

6. 'N n

s 50mR/hr 1.OmR/hr RADIDACHVD =-~,') ' s - / \\ N M_f -1 / s / / N 7 \\/ RADIOACTIVE-YELLOW III /\\ N N f O N N A 200mR/hr 10mR/hr ( A010 ACTIVE @,2 Ns... NM }/ 7 g f v M-ia2.. s/ 3,7

se 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 USNRC Identification Number For export shipments, IAEA Identification Number Shipper's Certification: "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." 7-G REVI5Ic.. e FEB. 122

r:c EE Notes: 1. For air shipments, the following shipper's certification may be used: "I hereby certify that the contents cf 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 shipments, the package must be labeled with a " CARGO AIRCRAFT ONLY" label and the shipping papers must state: "THIS SHIPMENT IS WITHIN THE LIMITATIONS PRESCRIBED FOR CARGO-ONLY AIRCRAFT." Preparation of an Empty Package for Transport 1. To prepare an empty package for transport, follow the in-structions of the procedure above beginning with Step 2 with the following exceptions: a. The package must be marked " Radioactive Material - LSA-n o.s. b. The proper shipping name is Radioactive Material - LSA-n.o.s. Radionuclide is depleted uranium. c. 7 -14 p,g-- -- - FEE. 1

u g; a R., 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 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. ( 8.1.4 Component 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 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 pack'ge, must not exceed 200 milliroentgens per a hour at the surface nor 10 milliroentgens per hour at three feet from the surface of the package. Failure of this test will prevent use of the package. 8.1.6 Thermal Acceptance Test Not Applicable Revision 0 1 Feb 1980 8-1

w z-

,3 =

ey W-8.2 Maintenance Program 8.2.1 Structural and Pressure Tests Not Applicable 8.2.2 Leak Tests ~ As described in Section 3.1.3, the radioactive source assembly is leak tested at manufacture. Additionally, the source assembly is wipe tested for Icakage of radioactive contamination every six months. 8.2.3 Subsystem Maintenance The lock assembly is tested as described in Section 8.1.4 prior to each use of the package. Additionally, the package is inspected for tightness of fasteners and general condition prior to each use. 8.2.4 Valves, RupturnD'ses and Gaskets Not Applic 8.2.5 Shielding Prior to each use, a to ation survey of the package is made to assure that the radiation levels do not ex ceed 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 10CFR71.12(b) are included in Section 7.4. Revision 0 1 Feb 1980 iA-8-2 u u %?,^> r* "? m}}

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