ML20057C832

Rev 0 to Sar,Amersham Corp Model 660 Type B(U) Package, USA/9033/B(U)

ML20057C832
Person / Time
Site:	07109033
Issue date:	08/12/1993
From:	AMERSHAM CORP.
To:
Shared Package
ML20057C830	List: ML20057C827 ML20057C832
References
NUDOCS 9309300069
Download: ML20057C832 (98)

Text

A s,/

Amersham Corporation recently determined, that it was necessary to bring the Model 660 Safety Analysis Report (S.A.R ) into line with the current USNRC Part 71 and IAEA Safety Series No.

6, 1985 Edition (as amended) Regulatory Standards.

It must be emphasized, that no changes have been made to the product, as part of this effort, and thus, there is no impact on the ability of the Model 660 to continue meeting the Safety Requirements.

The changes that have been made to the S.A.R.,

affect most of the pages of the report and therefore, it is required, that the revised report replace the existing report in its entirety.

]

The changes made to the report accompanying this letter fall into two categories.

A)

Those changes that are considered to have no impact on the technicalities of the product or the safety Standards.

B)

Those changes tk Z.:

the restructuring cf the format and certain techni al changes that cesulted from checking all weights 4

and measures.

l i

Items falling into Category A are not discussed herein, they are identified as follows:

1)

A uniform approach to the presentation of weights and measures within the S.A.R.

text has been adopted. American has been i

selected as primary with Metric as secondary.

()

2)

Correction of spelling, typographic and minor grammatical errors.

l 3)

American dimensions have been converted from decimals to fractions where appropriate.

Items falling into Category B, are identified location wise herein and are described as follows:

1)

Those changes that reflect the restructuring suggested by Revision 2 of the Regulatory Guide 7.9 and IAEA Safety Series No. 6 1985 Edition (as amended).

u>

2)

Those changes to weights and measures, resulting from a direct comparison, between current product detail / assembly drawings, from which the product is manufactured, S.A.R. Descriptive Drawings and the physical product. Or, the correction of calculative errors.

3)

The depth of the minimum weld penetration on the Containment Capsules has been changed for added conservatism, from.020 inches (0.51 mm) to.016 inches (0.41 mm).

This has impacted the results of certain stress calculations.

In addition to those changes that fall into categories A & B.

It is to be noted, that all drawings and certificates of Compliance listed in Sections and 2.10 have been replaced where necessary with the latest revision.

1.3 I

Also, Chapter 7 has been completely revised to remove all reference to operational Instructions and to relocate the Maintenance Instructions (revised) to Section 8.2 Appendix A.

/~~'s LJ 9309300069 930924 PDR ADOCK 07109033 C

PDR L

The ' Table of Contents' was restructured to reflect the suggested requirements of Revision 2 of the Regulatory Guide 7.9.

The following text will identify the location of the changes on a page/section number basis.

Page Section No.

No.

Reason for Changes

)

1-1 1-1 Changed IAEA 1973 to 1985 Edition (as amended).

1 l

Added second paragraph that identifies model I

variations.

1-1 1.2.1 Added tolerance to product weight.

Added reference to narrow body earlier version of the Model 660.

.f l

Added a descriptive breakdown to describe the j

distinguishing features of each model.

l Added tolerance to shield weight.

Added reference to supplemental lead, depleted uranium or tungsten shielding.

Added paragraph that identifies the source assembly securement methods.

Added paragraph identifying labeling requirements.

l

()

1-2 1.2.2 Changed to reflect model variations.

1-3 1.2.3 Changed to reflect Iridium capacity by Model No.

1-3 1.3 Added Certificate of Compliance 1

l Changed drawing content to reflect latest configurations and added page numbers to aid in the locetion of the drawings and certificate.

Added diagram showing the maximum activity for each Model 660 variation.

I 2-1 2.1.1 Added reference to end plates in description of the outer housing.

2-1 2.1.2 Changed IAEA 1973 to 1985 Edition (as amended).

2-1 2.2 Added tolerance to product and shield weight, i

2-1 2.3 Added type of stainless steel (304) and reference to

]

low carbon steel.

i 2-1 2.4.1 Added Section to comply with Rev. 2 of Regulatory a

Guide 7.9.

a l

2-1 2.4.2 Added Section to comply with Rev. 2 of Regulatory i

Guide 7.9.

2-1 2.4.3 Changed Section No. to comply with Rev 2 of Regulatory Guide 7.9.

w.

..,-c.,.----e-

.m.,,.,,

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

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

-,vn-,-g e

,v-,

am-,

Page Section No.

No.

Reason for Changes 2-2 2.4.3 Added reference to Model No. variations.

Added paragraph 2 and reference to Model No.

variations in paragraph 3.

2-3 2.4.4 Changed Section No. to comply with Rev. 2 of Regulatory 7.9.

Changed reference to Vultafoam to Rigid Polyurethane Foam to be more generic.

Added paragraph acknowledging, that in July 1992 it was shown, that the addition of supplemental lead to the depleted uranium shield, did not promote any eutectic reaction.

1 1

2-3 2.5 Added Section to comply with Rev. 2 of Regulatory Guide 7.9.

2-3 2.5.1 Renumbered ' Lifting Devices' section to comply with Rev. 2 of Regulatory Guide 7.9.

2-3 2.5.2 Renumbered 'Tiedown Devices' section to comply with Rev. 2 of Regulatory Guide 7.9.

2-4 2.6.2 Changed reference to Vultafoam to Rigid Polyurethane Foam to be more generic.

()

2-4 2.6.3 Changed section title to comply with Rev. 2 of Regulatory Guide 7.9.

Changed 0.5 atmosphere to 3.5 poi per 10 CFR

71. 71(c) (3) requirement.

2-4 2.6.4 Changed Section Title to comply with Rev. 2 of Regulatory Guide 7.9.

t l

Used Section 2.5.2 of previous report to satisfy the requirement for ' Increased External Pressure'.

Changed minimum depth of weld penetration from.020 inches (0.51 mm) to.016 inches (0.41 mm) for conservatism. This caused a change to the collapsing pressure of the source capsule from 5548 psi to 4162 psi.

Changed the requirement of 10 CFR 71. 71(c) (4) from 25 j

psi to 20 psi.

2-5 2.6.5 Renumbered ' Vibration' section to comply with Rev. 2 of Regulatory Guide 7.9.

2-5 2.6.6 Renumbered ' Water Spray' section to comply with Rev. 2 of Regulatory Guide 7.9.

2-5 2.6.7 Renumbered ' Free Drop' section to comply with Rev. 2 of Regulatory Guide 7.9.

O 2-5 2.6.8 Renumbered ' Corner Drop' section to comply with Rev. 2 U

of Regulatory Guide 7.9.

l l

l

__,_.,_,,._,,_er,

.m..

,,.,t.,_m m

I i

i 4

I i

Page Section l

No.

No.

Reason for Changes I

2-5 2.6.9 Used Section 2.5.1 of previous report to satisfy the l

requirement for ' Compression'.

j 2-5 2.6.10 Renumbered ' Penetration' section to comply with Rev. 2 i

]

of Regulatory Guide 7.9.

)

2-6 2.7.3 Changed reference to Vultafoam to Rigid Polyurethane (2 places). Added reference to ' Lead'.

2-7 2.7.4 Changed Section Title to comply with Rev. 2 of Regulatory Guide 7.9.

t l

+

t i

2-7 2.7.5 Added Section to comply with Rev. 2 of Regulatory i

Guide 7.9.

l f

2-7 2.7.6 Renumbered ' Summary of Damage' section to comply with

]

Rev. 2 of Regulatory Guide 7.9 l

4 2-7 2.10 Changed ' Free Drop Test' report to ' Drop Test of 660 i

l with lead added report'.

Removed ' Puncture Test' report.

Added ' Low Temperature Drop Test of 660A posi-lock' i

report. Both of the new reports include the results of a ' Puncture Test'.

l Added test report for the Drop Test of the narrow body i

version of the Model 660 dated Nov. 25, 1969.

Added page No's to aid in location of test reports.

i 3-1 3.1 Changed Section Title to comply with Rev. 2 of I

Regulatory Guide 7 9.

Added ' Lead' and tungsten and their melting 3-1 3.2 temperature.

Changed the reference to Vultafoam to Rigid Polyurethane Foam to be more generic.

3-1 3.4 Changed Section Title to comply with Rev. 2 of Regulatory Guide 7.9.

a 3-1 3.4.1 Changed reference to IAEA 1973 to 1985 Edition (as amended) and paragraph 130 (which was in error, should have been 230) to 548.

Also, made'the same change in the next paragraph with the exception that paragraph 240 was changed to 543.

3-2 3.5.1 Added the text for this section.

It was inadvertently 1

left out of the earlier report.

Changed reference to section 3.2 to 3.5.1.

Section 3-3 3.5.3 3.2 does not indicate that the package is assumed to-

)

reach a temperature of 1475'F.

l Changed reference to Section 2.4.1 to 2.4.4 to comply with previous section number change.

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

i i

Page Section No.

No.

Reason for Changes 3-3 3.5.4 Changed 284 psi to 368 psi which resulted from our reduction of the minimum weld penetration depth from

.020 to.016 inches. This also changed the maximum stress in the capsule from 3 to 4 percent of the yield strength of the material.

3-3 3.5.6 Changed Section Title to comply with Rev. 2 of Regulatory Guide 7.9.

t 3-4 3.6.1 Changed reference to IAEA 1973 to 1985 Edition (as amended), changed reference to paragraph 230 to 548.

3-4 3.6.2 Changed reference to IAEA 1973 to 1985 Edition (as amended), changed reference to paragraph 240 to 543.

3-5 3.6.1 Same changes as those on page 3-4.

Also changed 1.42 r

l in the formula

'h' to 1.32 to correct an error. This resulted in a change in the maximum surface temperature f rom 108'F to 106.3'F.

3-5 3.6.2 Same changes as those on page 3-4.

Changed maximum surface temperature from 82%: to 85N: and Table III to i

Table XII to comply with IAEA Safety Series No. 6.1985 Edition (as amended). Added a new paragraph stating that the maximum wall temperature will not cause melting or cracking of the shielding material.

3-7 3.6.3 Changed reference to IAEA 1973 to 1985 Edition (as O

amended), changed reference to paragraph 238 to 553.

Changed the minimum weld penetration from.020 inches to.016 inches.

Corrected metric equivalent of atmospheric pressure.

Changed 100 kPa to 101 KN/m8 Changed reference to IAEA 1973 to IAEA 1985 Edition (as amended), changed reference to paragraph 238 to 553.

3-B 3.6.3 Changed longitudinal stress from 129 psi to 171 psi.

'i This resulted from the reduction in weld penetration depth.

Corrected Hoop Stress formula.

l Noted change in wall thickness of cylinder.

(.020 inches to.016 inches),

a Changed the results of the hoop stress calculation from 284 psi to 368 psi which also resulted from the reduction in weld penetration depth'which equals the minimum wall thickness of the cylinder.

This resulted in the stress generated to be changed from 'less than 3 percent' to 'less than 4 percent' of the yield strength of the material.

4-1 4.1.3 Changed minimum weld penetration from.020 inches to

.016 inches.

. _ ~

Page Section No.

No.

Reason for Chances 4-1 4.2.1 Changed Section Title to comply with Rev. 2 of Regulatory Guide 7.9.

Changed reference to IAEA 1973 to 1985 Edition (as amended).

s i

4-1 4.2.3 Changed Section Title to comply with Rev. 2 of Regulatory Guide 7.9 and added reference to Section 2.6.

r Deleted Section 4.2.4 Coolant Loss to comply with Rev.

4 I

2 of Regulatory Guide 7.9.

g 4-1 4.3.2 Changed Section Title to comply with Rev. 2 of Regulatory Guide 7.9.

l 1

4-2 4.3.3 Added section to comply with Rev. 2 of Regulatory Guide 7.9.

i 4

4-2 4.4 Added Section Title and N/A, to comply with Rev. 2 of' Regulatory Guide 7.9.

4-2 4.5 Added Section Title and N/A, to comply with Rev. 2.of Regulatory Guide 7.9.

5-1 5.5 Added Section Title and contents, to comply with Rev.

2 of Regulatory Guide 7.9.

7-1 7

Section 7 has been rewritten to remove all reference

)

to Operational Procedures.

r 8-1 8.1.5 Changed 2 mR/hr. to 10 mR/hr which was in error.

[

8-2 8.2.7 Added reference to Appendix A which is the Maintenance Section that follows.

s

(:)

O SAFETY ANALYSIS REPORT AMERSHAM CORPORATION MODEL 660 TYPE B(U) PACKAGE USA /9033/B(U)

O REVISION 0 REVISED AUGUST 12, 1993 O

r w

i-w, w-,

ww w

->yrr g-www-y eiee-wwn

,-g yg w--gy9

4 f

TABLE OF CONTENTS PAGE 1

GENERAL INFORMATION 1-1 1.1 Introduction 1-1 i

1.2 Package Description.

1-1 1.2.1 Packaging 1-1 and 1-2 1.2.2 Operational Features 1-3 1-3 l

1.2.3 Contents of the Packaging.....

1-4 thru 1*-21 1.3 Appendix.

2-1 2

STRUCTURAL EVALUATION 2.1 Structural Dcsign 2-1 2.1.1 Discussion.

2-1 2.1.2 Design Criteria 2-1 2.2 Weights and Centers of Gravity...

2-1 2.3 Mechanical Properties of Materials 2-1 2.4 General Standards for all Packages.

2-1 2.4.1 Minimum Package Size..

2-1 i

4 2.4.2 Tamperproof Feature 2-1 2.4.3 Positive Closure 2-1 and 2-2 2.4.4 Chemical and Galvanic Reactions 2-3 2.5 Lifting and Tiedown Standards for all Packages..

2-3 2.5.1 Lifting Devices.......

2-3 2.5.2 Tiedown Devices...

2-4 2.6 Normal Conditions of Transport.....

2-4 2.6.1 Heat.

2-4 2.6.2 Cold.

2-4 2.6.3 Reduced External Pressure 2-4 2.6.4 Increased External Pressure.

2-4 2.6.5 Vibration 2-5 2.6.6 Water Spray 2-5 2.6.7 Free Drop 2-5 2.6.8 Corner Drop 2-5 2.6.9 Compression 2-5 2.6.10 Penetration.

2-6 2.7 Hypothetical Accident Conditions 2-6 2.7.1 Free Drop 2-6 2.7.2 Puncture 2-6 2.7.3 Thermal 2-6 2.7.4 Immersion-Fissile Material 2-7 2.7.5 Immersion-All Packages 2-7

~

2.7.6 Summary of Damage....

2-7

...._ _.~ _. _,.

f s

t PAGE

()

2-7 2.8 Special Form 2.9 Fuel Rods...

2-7 2.10 Appendix.

2-7 thru 2-42 4

[

3-1 3

THERMAL EVALUATION 3.1 Discussion.

3 q 3.2 Summary of Thermal Properties of Materials 3-1 l

3.3 Technical Specifications of Components 3-1 3.4 Thermal Evaluation for Normal Conditions of, 3-1 Transport.

3.4.1 Thermal Model 3-1 3-1 3.4.2 Maximum Temperatures....

4 3.4.3 Minimum Temperatures.

3-2 3.4.4 Maximum Internal Pressures 3-2 l

3.4.5 Maximum Thermal Stresses 3-2 1

3.4.6 Evaluation of Package Performance for Normal Conditions of Transport 3-2 3.5 Hypothetical Accident Thermal Evaluation 3-2 l

3-2 j

3.5.1 Thermal Model 3 5.2 Package Conditions and Environment 3-3 f

a 3.5.3 Package Temperatures 3-3 3-3 3.5.4 Maximum Internal Pressures 3-3 3.5.5 Maximum Thermal Stresses......

l 3.5.6 Evaluation of Package Performance j

For Hypothetical Accident Thermal Conditions 3-3 3.6 Appendix

.. 3-4 thru 3-8 4

CONTAINMENT...

4-1 4.1 Containment Boundary. '.....

4-1 4.1.1 Containment Vessel 4-1 4.1.2 Containment Penetrations....

4-1 4.1.3 Seals and Welds 4-1 4.1.4 Closure 4-1 4.2 Requirements for Normal Conditions of Transport..

4-1 4.2.1 Containment of Radioactive Material 4-1 1

4.2.2 Pressurization of the Containment Vessel 4-1 4

4.2.3 Containment criterion 4-1 4.3 Containment Requirements for Hypothetical Accident Conditions 4-1 4.3.1 Fission Gas Products 4-1 i

... ~ -

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

.==:A.

.-m

-.a A

.-_m

+,

.w,u.fa....

4

.1 l,

I I

PAGE 4.3.2 Containment of Radioactive Material 4-1 4.3.3 Containment Criterion 4-2 4

4-2 4.4 Special Requirements i

4-2 4.5 Appendix I

j I

5 SHIELDING EVALUATION 5-1 2

5-1 5.1 Discussion and Results 4

5-1 2

5.2 Source Specification

.f 5-1 1

5.2.1 Gamma Source.

5-1 5.2.2 Neutron Source 5-1 5.3 Model Specification.........

4 5-1 l

5.4 Shielding Evaluation.

5-1 AND 5-2 j

5.5 Appendix I

6-1 6

CRITICALITY EVALUATION...

j i

7-1 7

OPERATING PROCEDURES...

I 7.1 Procedure for Loading the Package.....

7-1 7.2 Procedure for Unloading the Package 7-1 7.3 Preparation of Empty Package for Transport 7-2 O

4 8-1 2

8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM B-1 8.1 Acceptance Tests 8.1.1 Visual Inspection.

8-1 8.1.2 Structural and Pressure Tests 8-1 j

8.1.3 Leak Tests B-1 l

8.1.4 Component Tests....

8-1 l

1 8-1 j

8.1.5 Tests for Shielding Integrity l

8.1.6 Thermal Acceptance Tests.

8-1 l

8.2 Maintenance Program.

8-1 8.2.1 Structural and Pressure Tests 8-1 2

8.2.2 Leak Tests.

B-2 i

1 8.2.3 Subsystem Maintenance 8-2 8.2.4 Valves, Rupture Discs, and Gaskets on Contaii. ment Vessel 8-2 8.2.5 Shielding 8-2 i

8.2.6 Thermal 8-2 8.2.7 Miscellaneous B-2 thru 8-8

)

2 l

4 1.

General Information i

1.1 Introduction i

i Amersham Corporation, Model 660 series is designed _for use as a radiographic exposure device and a transport packsge for Type B quantities of radioactive material in special form.

The Model 660 l

conforms to the criteria for Type B(U) packaging in accordance with 1

10 CFR 71 and IAEA Safety Series No.

6, 1985 Edition (as amended).

The 660 serica includes all of the following models; 660, 660E, 660A, 660AE, 660B and the 660BE.

These models are all structurally identical, all materials of construction and methods of fabrication 1

are essentially the same.

The models with the designation A, AE, B,

and BE all utilize an automatic securing mechanism to secure the source assembly. The models with an "E" designation have an electrical circuit to allow compatibility with an automatic exposure unit.

Throughout this evaluation, all the models are considered i

interchangeable, except where specifically designated.

l 1.2 Package Description i

a 1.2.1 Packaging The Model 660 series is 12 7/8 inches ' (327 mm) long, 5 1/4 inches (133mm) wide and 9 5/8 inches (244mm) high. The packaging incorporates an aluminum handle for movement of the exposure device. The total mass of the package is 53 i 3 lbs. (24 i 1.36 Kg). Earlier versions were only 4 5/8 inches wide and had a total weight of 48 3 lbs. (21.8 1.36 Kg).

The shield assembly weighed 34 1 3 lbs. (15.4 i 1.36 Kg).

()

The following descriptive break-down is provided to identify the i

distinguishing feature (s) of each model. Also included is a diagram j

which lists the maximum activity authorized for use with each different device model number, see page 1-20 Model #

Drawinq #

Revision Description 4

660 66030 Narrow body-Pre-automatic lock 660 66025 B

Wide body l

Prc~ automatic lock 660E Any version of the 660 1

with the addition of an l

electrical hookup as previously approved 660A 66030 A

Narrow body retrofitted-with automatic locking mechanism 660A 66030 C

Wide body retrofitted with automatic locking mechanism 4

1-1 REV. 0 August 12, 1993 l

i 660AE Any version of the 660A

(

O with the addition of an electrical hookup as previously approved 660B 66025 E

Wide body manufactured with automatic locking mechanism 4

660BE Any version of the 660B with the addition of an electrical hookup as previously approved The radioactive material is sealed in a source capsule which conforms to the requirements for special form radioactive j

material. This source capsule is installed in a source holder assembly.

The source holder assembly is housed in an "S" shaped i

titanium or zircalloy source tube.

The source tube has an inside diameter of 0.385 in. (9.78mm) and a minimum wall thickness of.041 inches (imm).

The source tube is i

surrounded by depleted uranium metal as shielding material.

]

The depleted uranium shielding is cast in place around the source tube.

The mass of the depleted uranium shield is 37 1 I

3 lbs. (16. 8 1 1. 36 Kg).

i The depleted uranium shield on some packages may have supplemental lead, depleted uranium or tungsten shielding O

shown in drawing 66025.

The addition of this shielding does not impair the package's ability to meet the Type B requirements as demonstrated in the report in Appendix 2.10.

The depleted uranium shield is encased in a steel housing.

The housing is made up of a shell and two end plates.

The shell is fabricated from.000 in. (1.5mm) thick stainless or l

carbon steel.

The end plates are fabricated from. 120 inch (3mm) thick steel and are bolted together by means of 4 tapped rods that extend through the shell and by flat head screws. The void space in the housing is filled with a rigid polyurethane foam.

The outer packaging is designed to avoid the collection and retention of water.

The package has a smooth finish to provide for easy decontamination.

Attached to the rear plate is the control connector and lock.

assembly. This assembly incorporates either:

i 1.

an automatic locking feature that locks the source assembly in the exposure device when the source is-returned to the stored position for models 660A, 660B, 660AE and 660BE, or 2.

a selector ring assembly that by manual operation secures the source assembly in the shielded position for the model 660 and 660E.

1 l

l 1-2 REV. O August 12, 1993 m

-.m_m. _.,,, - _ _, _

In addition the source cannot be exposed unless a secure O

connection of the source assembly to the drive cable has been made.

The control unit cannot be disconnected unless the source assembly is in the fully stored position in the shield.

j Attached to the front plate of the exposure device is the storage plug connector.

This connector provides a means of I

fastening the source storage plug to the exposure device.

The storage plug and the connector are drilled for the attachment of a seal wire which provides a means of installing a tamper proof seal to insure that the source has not been inadvertently or intentionally moved from its proper storage position during shipment. The storage plug prevents dirt from entering the exposure device'.whenever the device is not in use.

i 4

The radioactive material is sealed inside a stainless steel capsule. This capsule acts as a containment vessel for the radioactive material.

1 l

The outside of the 660 Series contains all of the marking / labeling required by 10 CFR Part 71, 10 CFR Part 40, i

10 CFR Part 20, 49 CFR Parts 171-175 and IAEA Safety Series No.

6, 1985 Edi mn (as amended) on the nameplate. The nameplates are t Sle of withstanding a 14759P (8 02*C) fire test per 10 CFR Fact 71 and maintain legibility.

a 1.2.2 Operational Features The source assembly is secured in the proper shielded storage position by the locking assembly.

For the models 660A, 660B, O

660AE and 660BE, the source assembly is locked in position by the automatic locking slide and a key lock that prevents rotation of a selector ring which must be in the operate position in order for the locking slide to be unlocked.

For the models 660 and 660E the source assembly is locked in position by placing the selector ring into the lock position and depressing the key lock which prevents rotation of the selector ring.

All model 660 series devices have a protective cap installed to prevent damage to the exposed end of the source assembly (the connector) when the control unit is not connected to the exposure device. The storage plug is used to provide another 1

)

means ol securing the source assembly in the proper storage i

position.

g 1.2.3 Contentu of the Package j

i The Model 660 series is designed for the transport of special form Iridium-192 sources in quantities up to 140 curies in 6

the Ametsham source assembly Model A424-9.

The Models 660, 660A and. 660AE are designed for 120 curies and the Model 660B and 660EE are designed for 140 curies.

This source has been designated as special form under IAEA-Certific, ate of Competent Authority USA /0335/S.

j 1

1-3 REV. O August 12, 1993 l

i

.~ _.

1.3 APPENDIX Drawings:

66025 sheets 1-3-Rev. E Model 660B Descriptive Drawing.

Pages 1-5, 6 & 7 60025 sheets 1-4 Rev. B Model 660 Descriptive Drawing.

Pages 1-8, 9,

10 & 11 66030 sheets 1-3 Rev. C Model 660A Descriptive Drawing. Pages 1-12, 13 & 14 66030 sheets 1-3 Rev. A Model 660A Descriptive Drawing.

Pages 1-15, 16 & 17 Diagram showing maximum activity for each Model 660 variation.

Page 1-21 USNRC Certificate of Compliance No. 9033 Rev.

8.

Pages 1-19 & 20 l

Drawing 42409 Rev. C Source Assembly.

Page 1-18 O

i 0

1-4 REV. O August 12, 1993

.m

. w vrw iewm n ~ % i v t.

v iv r uni c..e SHIELD - REF SOURC LOW" CARBON STL.

Il GA. (120) c 1-20 FLAT HD SCREWSfh RECEPTAg SEE SHTR (IN STORED ITiON) 4 STEEL-ZINC OR CAD PLATED CAST HANEX.E

• M2 FLAT FO SCRENS(6)

(ALUM. ALLOY) g STEEL-Zutc oR CAD PLTD.

/

~

-be i

/

/

i

' LOCK ASSY

(

SHELL

-7 TUBE-8EF (SEE SN'T 2)

}

f(D60 TYPE 3&? s.'S.)

SEE SMT3 I

L pg g zy(

.. /.

OR C/?PBy/ STEEL (STEEL) 5

/.N////UM//////L' 3i h

[__

N

/

/

fN a}

x le pq M

tm

,/j /

v

/

di

~

~~

/

Mj

'~

<f

, s_.= - -

]

/

j@_

y c

n CONTROL CONNOOR l

uigs

/

A95Y

\\

s

/

(SEE SHT 2) -

/

O G

ks F

7

~

,/

+

v

- -y -

H

~_'

_.j - '

CABLE MY--

a

't

/

A/

/

/

I' SOURCE IDENT- /

hO A g g o (i)

{

/r //

/

/ // _...

\\

/ -

/

. -GEL'C b s

/

//p

/\\t

/

i LhBEL 7

c

/

\\

\\

/

o

/

/

7 meg (SHT 5)

\\

, LWT MR.MO

-6 (0% srAin. ST) 1m [

__g,E RUG

,6 ff

. C%ECTOR

/

~

Norto M

ha=T= A.,.

C0ffMECTING RODS @)

12LM STEEL RlGID

s. 6.c.

STORAGE PLUG ASSY POLYURETHANE MODEL 660 G4e4A RAY PRGEC10R FOAM; D CN5rrt j],,, Ma 7 SHIFPit6 CONTAINER REJNREEMENT

[ gop gg

,, y g g 7tEDE-REF

1. 74mN.LB1/CUFT DESCRIPTIVE ASSEMBLY,

wa s

TOTAL WElGllT-H [8723b 6608-ido Cl

.\\

C 66025 SEE 9# 3

- i,,

in 3

. -~

l i

j!\\i e

'NF) 0 1

E c

p n; e

r" NL e

f T

y s

4 t

S g!

I

' i h '

Q T

r T pmu E T.

w '"~

RS yue e#

K

/

nams wcweg 0

/

f C0

)

s

-j O3 mI o

a h

L(

y m

c:_Ql o

T-6

[

I e

\\

v 6

c# s

[* u v

[

i.

n n S

oc o

o

,e _EQ5 i

sma f, a-k.

t n

e\\

%w 8c n

a I

j i.

s s t

M

.T b

9n Tx e

" g c

p C

o r

A(

, i E

& \\l

- Y N

I..

.~~ g f

)

+

Et R

Lr N

(

, yO Bs R

i t

9 ~

Ar I @.', -

E C

cp\\

- 3 P

M r,'

F g-U B

I j 7-D i

E E)

T l

n V

)

O kkg I R N

~ y,-'~

GE h

i B

E TB 08 U

~

~

PR

~

(

)

l g

x cm

)@

7

)

K0 C

)e CR co) ucw om O

n Yt L

y Et

)t n

E r

5T R r-Ws Sm ot L

g7 e n no n

r 4

(

aM fy ax p

D O 0 C1 f3 c/

h i

y N.

f0 o*L

(

t I

f g (2

/a o

(

b

\\ (7 i

/

(

l Y

L s ).

B y%y\\\\Alx Om':.n/(j P

\\a.

r i' t aA i t aT M

s E

/

dc7 S

7

/a S

Zm;i gu j!

l,

/

r4 A

k

,l-s t

0 wr tN m/</

1

[L c

K L (

w/

C k

/h_^ en / f / / / e L

k O

/ j/ /,/

m{

/

\\

- i F.

E N

R s

)

E

.a T

02 s

4('

c S

QS u) s u

G)N CWM me.

U eW F

5O c

L' E*

O n

c R

3 W

E C

n y.t 1 S" on r

o=m a

go. mT u

7 Tn a r

- P 3 TcT 0A W nc R

~

1 at mO C

2s i 3o

~

u"s vD

$a, t

C o

no

~

e A (3 &

ct

.a

(

pt a gp N

~

g #!

ljb~:

l!b1 i

qi us e

s Igs sa l N

$1:39 J m

e 8

trl-sk al l

e ao 2

=

IEI NS D

s (-

k a

u,s n N

za aj s

n

~

, 6-s as e ggr 4m

-j 4

m

=

s 4

c g

f b

b h

pa x

n ta gy

/

a n

j) on

.o

,x e,

T.

m su a$ 8c3 m m

.i lf ga p

h-a i

u e

I t

wo ~ r e i

xm n

[ dkw'il Db o

4 1

d s,

. jN.@6 l

~_

i i

g.4

+

2-n-

c np!

r ' s. pli il ' l,<

J Cl b

msssau s

eyx o

a

+>

l g

W fi g -g 5sa-og@,

f--}

i g

i a

e 9

1 1

$ s a.

b_-

o 5

w m z

{

1 o

y z

e 2

e a

-\\'s k

D mwsC5 R

s O

l t FB G

\\

N t-us

\\

sN O

8-N N'.s _

f N

L3 Ea

< _gs, <a s s.

a 5.

~k(h N

\\

ys

-m%

3 k

\\

\\

o g % Q3 s

c

~Ln

~ '3 \\,'

k b

iii S

d$$l e

3

. v. n.%

t~:

r-w il i

ys e

l t

4 i

I ' !!

T.'

'to M_3 f

e e

s i

-q u t i

O t' "

4'T 8

l.i n:

5

)

t s

o z

Q.

b s

c h.

• 6 I

_gQ 4

lI l-7 ji h,

~ STORAGE p E

' DEPLETED URANIUM TRADl0ACTp'5 END PLATES

-l B~)4-f 8w).2 !/f277N'qm","

...RECEPTACd SHIELD f REF "-'

50 URGE U

!!' GA. (.120) l-20 FLAT ND SCREWS (o)

TE E 9HT4-(IN STORED POSITION)

COLD ROLLED STEEL 4

STEEL-CADMlUM PLATED

. CAST HANDLE r*l0 32 FLAT HP SCRErtS(6)

( ALUM. ALLOY)-

STEEL-CADMILM PLATED

^a b

~

i

/

dD

^

r

/

i x

' LOCK ASSY SHELL

---J TUBE-REF

.(SEE SM'T 2)

]

060 CARBotJSTEEL),

SEESNT4 L

N AMEPLATE (2)-

/

(STEEL) 53 ;

=r

/)N(///// f///// / ///

i

/

N

/

/

f T'.

(

M du f

g

/

/

/

/

f s

s

/

9 Q,

--T

/

g p

- s==

jf U

I SEAL

~~

CONTROL CONNECTOR-I s

- IRE

-- - ASSY

/

~

(SEESMD2(3)

SASH s O

6

/

CHAIN y

s 1,-' y,-

y m- -. -J

=

s l

l\\

f.

/

t

?

e

/

. /.._..

.\\ -

-EELEh i SOURCE IDENTu /

hO O (,['- )

l c

f-

~

/

/ / //

/ \\ !

/

n LABEL r 'I /

/

/ //

~

x

/

c5

- /_.

~ g I REF.

BOLT CO/ER. RIVETED

• ' " ^ ' " ' "

/

\\

"'"~".

/'~_-.-. CONNECTOR

/

T REF.

l

.12 g 5

4

/

~~

. CONNECTING RODS (4)

NorED'

~ -

"ET

=b

~

' 12Li4 STEEL JRIGID

.s.

~~~*" "**

STORAGE PLUG ASSY

.REINR)RCEMENT

~

w o.n0; MVCAPACHY

.POLYURETHANE MODEL 660 GAMMA RAY PROJECTOR

~

FOAM il j"yW SHIPPING CONTAINER W*#"-" -

Od 7tEEVE-REF g

\\

DESCRIPTIVE ASSEMBLY

,,,v,

7EE sur 4 TOTAL WEIGWT-53 LBS 2-3)bs g

". l \\

C 6602!i "5

i,,,,,.

= ei..

.m u u-.

O O

8 - ~"D END PLATE-REF.

~:MODlFIED LOCK (CORBIN ** 0,7290) 9 C LOCK RETAINEG)

~ CAP SCREW (2) 10-32. SOC. W D (304 STAIN. STL WITN LOCTITE "H

/

\\

I L.. -

~ EIN$"

/

I

\\

H

. COVER

-CPERA W m m

[ j' '

l \\

(304 STAIN.STL) posmon er xty

/

/

i \\

w

\\

SELECTOR BODY l

i s

(BERYLLIUM COFFER)

/

!d L\\

/

t 4-4

'/

COMPRESSION SPRING s

/

[ -$

(MUSIC WlRE)

/

_L d /

/

/

w SEE SHEET 3

.j s

l2'

'/

B B

'e H--

CED-j 3 a l li-$L= - C. _ -

d f

i f

~ v E

,}

\\

1 Wps y

a ANN '

y

\\

' Y@

f l

tr/ iup i ]"

LOCK PINS SECURED

/

/

s"y NE

• 10-U SOC.H D. CAP SCR."

A-

.=

/' ' '

jfl,ng

\\

(STAIN.STL.) 4

'-7 ma mm 4-s s

WITH LOCTITE f -

/

r-

/

' SELECTOR RING RETAINER ANTI-ROTATE LUGS

~

__ (304 STAIN. ST*L) y (304 srAIN. srt) i WITH COMPREM{DBLLE

^4 "SELECER RING LOCKING PIN

$ COMPRESSION SPRING

+c (E4 STAIN. ST'L)

ON SPRING

~ (MUSIC WIRE)(2 PLACE 7)

LOCK ASSEMBLY SECTION C-C norsD

gg.59.

~"~

~

~ 0EL'660 GAMMA RAY PROJECTOR

~

M0 r-Q..,_,,., f9' \\

SHIPPING CONTAINER a

.N DESCRIPTIVE ASSEMBLY c

~

i aa i

-... ;u lC l 66027' B

s

-m

!wm 2g4

{

[

I eenensee so. es e.msee

-~

A E

to

~+-

REF

+

V 1 REF ~

~

.lg e.

' LOCKING PIN (RIF).

m..

e f.

s J *,

le h\\

i+.-

SOURCE ASSEMBLY e

p

/

.3125 C4A E%LL LOCKING PIN REF

qip,

</

l

/>

w I'

?, \\

7

.8'--

.2E5 D

-w

\\

j

- \\

'v GNj-g 2

-,1 c

__ I Ne 6

L 2 ~l m

W

/

BETWEEN PINS SLEEVE f6 -

i' j.-__

[

REE p

J.

1 u-:t s faxW

,/~{-

2 3 LOCKED F03 MON i

REF s]

8 l

. 7 x'

-0 SEPARATE VIEWS 4//'

?W/

/?_

?

/

c t-

~

' SELECTOR RING (RER)

-1 3

6.

f

' SELECTOR BODY (REF.)

UNLOCKED Po$ MON

~

I

-SECTION B-B 1

i 1

-"= ;te.

.:...qs s g-

.c MODEL 660 GAMMA RAY.P%)ECTOR

.~

, s

}"g"

• ?"=L -

' SHIPPING CONTAINER 'i y,

N De5CRIPTIVE AS$EMBLY.

my-;74 l~

_.m,16 esoM 3 ~

,, t e m

. +

i e

s s

.m m m~,-,,*r,-.

- - ~

,_.__-.--__.__________.__4

l 8 jd-m l7 e M i-a _

e f

9 TUBE FABRICATED FRm:

fj 0.) ZiRCALLOY, OR l

b). TITANIUM, OR _ _

C). TYPE 304L STAINLE$ STEEL COATED WITH 90-l00prn Ni AL y ih DIA HGT TCP ANDdoo-@jun AL 0';

yEEVE (3) orric>%L.

2 550 0.D. n.0?O WALL

. FAME MA7L AS1 TUBE (CAST IN 7HIELD)

^

9HIELD DEPLETED UF/ftfuM

/f.. *T "M

-a f

/ / .

l l

//'

s

/

If TYP y

,[ /

5[

f

,- m i.ea s

\\,

m

\\ i

= - = =

_ _u -

s f

u__.

= =-._=J V -

s o

s

\\

~2 f6,

=

i AFPROX 9

g g

2

'l6

\\

9HIELD DATA

,37 LBy 3lb5 A5 NOTED a = ; ; 3 [*,,g,= ~

~~

36dEE 660 GWMA f%Y FROJECTC'n.

~

~~~

m==..

~~

9HIPPIm CONTAINER-DESCRIPTIVE ASSEMBLY 4 u.

f

,ew er 4

m.....

m,66095 s,i

.$f,m< /, 4s

.. j a.

m.,,.,

i, m,,

0, a

STORAGE 8BE LAPLETED LHANIUM MNJUL ilVt t.INv PLN t.D RECEPTA SHIELD-nF SOURC O LOW CARSON $TL.

Il GA. (.l20) 0 1 -2. STEEL-t Zir4C QR. CAD 0 FLAT HD SCREvv5G j W SHT3 (IN STOREDWSITION) 4 CAST HANDE Ar')O 32 FLAT HD SCRENS(6)

(ALUM. alloy) edTEEL ' ZINC'OR CAD P13D.

A~e g

s i

/

/

i e

' LOCK ASSY

^

(

TUBE-8EF j

(SEE S4'T 2)

/

• )SEE SMT3 SHELL I

. S.) l

(

TP i

~

(STEEL) 5 3

/N//////. //////t U

i h

[

\\

//

fN j

dce

!. M@,p%

v;J

\\

3 x,/7<

5

(

[

- a.== - -

D

/

(!,@,W 9

\\

/

/

~~

CONTROL CONNECitR g

\\

A%Y

\\

WIRE G /

(SEE SHT 2) 0 7

v H

y

/

cpytg gg Al

/

i (hoAjjGERo63 D

SOURCE IDENI- /

l M

/_

\\

i CC b

/i LhBEL f

/ o J/

l

/ / /

/

/ / /1

/\\t

\\

/O c

/

/

/

7 MEF. /(SHT 5)

\\

LWT WR MO

/

4 1

C 12 y Rer. -

5 C0ffMECTING RC05(4) riorED E

@[

~~

~

/

12Li4 STEEL RlGID

s. -

STCRAGE PLUG ASSY POLYURETHANE MODEL 660 GAW44 RAY PRGEGOR REINRXEMENT yod no a g rn FOAM; DENsr7f f'"*y N=a SHIPRNG CMINNER 7tEDE-REF

- p i9.

FT d7 '

'N DESCRIPTIVE ASSEMBLY 660A 120 C' SEE 9/r 3 TOTAL WElGWT-M LBS 5lbs

,- \\

c 66030-

!c

• • c==

a

'w Iri IMU f aT m.

m m

(L ut< nuv

• u n d uj O'

--PtWTEGIVE BUMPER (R)

'0

- LUCH RETAmh (7045T.57L )

g 0-Il Mc. m j

W W (2)

/

~e (OVER

('" "'N

/Q 7

a JLE M COMPRry,Dn1MtitM

/G

( WILL Mh I

l

, LEE "tf-aty-9 2.)

\\,,_

, L N

l

/

\\

- l-t, -+, -j SELECTUt BCD(

D@ 5T W

/X l_,,,h yY;,,

j i

IY l

l, h'

CON ECT m l1 1 1 l fi ",.

(g) # / s. \\ c o) C h t % / uN -M N f@ hw c//) %wr k , %/ ,--f' ".)_ - ' g- @y$d 3--t--Z -G g dI ' e' ~~J H r g -J !.',W / e s,- A i _3 - sj i L i e xu " r_ -.[> 7 Ml /h / e ) kp z A / d gkk\\ / ..Obg 'O M 50C MA CAP SCR. 1ruu/c T1 \\- x wW (srAin.sn.) 4 /a = 4 / m e gyg // h / \\ / h / /' A

ANTI-ROWE LUGS (So3 sran. syt)

/ ' 3EttoGH RitM (pf57.yt) (704 7T. STL.) g l $ C O bd M C 530 N h e CABLE A%'f ' (Srsrt( neu am)/ LOCK ASSEMBLY \\ &stsquot M M _ W ". DL 660 6fWh% RN 6 1 (1/4 y 1/4 ftAT GMD FKK ^ Of L HARDEHit%) Em 'NM'~ ~ SHIPRNG COtTMER .x DESCRIPTWE AStSEMBLY R-E ~~esoyo f ~ ~ A

• • • d 211 Iepert 2FE --
  • "unn a o

I l J l-e . q:! h)* m a , sg o - lj 2-J8: Es l n ~c <!i g5m e@! ~ V I i oz aj w 5 k s'

E s

eE 3 a f

• I'52 r-

E

,,3

w l

2 g ( J 8 to } -m P "3 0 8 2' 'O 9 y" 3 37 I i 3 ,E ('_ _\\ i i g g a

q. 3, youy o

n 2 a go i g ="s i v.g x e i e' 2 ! k o3; .e w-T 8e e' o iy 0 _.. x .m_c p p E% 5@]- - j.f o -m e g i w g"g' I <3 S o i m y m i ! = k q i E %E 'I vs 1 O N T'l } $8_7 l '1 Il ') ~ c l c7q g 1 ll J 9585RE a , ' ' (i 3 g e-4 z 4 s 'J d ll j I r w 6 s ! a s:: is-rc. s a h b o. < h 5 ,,,ai~gu@ \\\\ E n l 5 \\ I. O yd3D T g s - i, o s 's s. o s s 's N e o ~ N NJ's, l !r g a 5 s 's s $ds 3 s 1 2._ q g s s q \\ I ~oEg ~ Rb d \\ \\ m@ 1 c- _iy s k wt 3 ',l i$' ek ak@ p a i-5 l ,l w V T 3 i ll ' :i O 3 'IO 5 L I 3 q i L" . 'F. . E. i O i l g s ET s-L 2 I / O 5 a.h A M g "%d s m g l _ g.

STORA6 DEPLETED LHANIUM f RADgTivE END PLATES kg g % ""g.. .o e..o. in i RE SHIELD-REF SOU W COLD FOLLED STEEL 4 Il GA. (.120) C --M RAT Hu SCRE W 7EE $NTE (IN STORED POSITION) STEEL-CADMlUM PLATED CAST HANDLE '!0-32 FLAT HD SCREnS(6) /(ALUM. ALLOY) STEEL-C/OAUJ PLATED w d g dD i / / i 7 e OCK ASSY ~ ' SHELL ' TUBE -8EF (SEE S4Y 2) y foso cmeon sTEEQ.:.) -)See surt c _ naugu,g up l (sTEa) 3 = / l I / / / / 'll l' @ N / / 7N l )I l/ V} h llY& g u / s -r-- g y g} 7 - L===- _8 1 y '/ / aQ a o ./ f ? l g TROL CONrfCtR ASSY \\ (5EE W 2) D 's O F s L/ w -.-y L ;L / CABLE MW-h A/ / I i [ M f, \\ , -+EL'C-k SOURCE IDENT / ho O(i) / /} / / //./ / / p /\\r / ib LABEL / r ) / \\ \\ /R v / / 7 meg /(SHT 5) \\ LBOLT MR.%'ETED / [ \\ AIN. ST) --STORAGE FtUG 12 3 s / CDifNECTING RODS (4) norm E

===' V A 12Ll4 STEEL RIGlD w STORAGE PLUG ASSY POLYURETHANE MODEL C40 GAMMA RAY PRGEGO FE#WCFICEM pdm agn FOAM _ h,'

==-, i SHIPPitt3 CONTAINER 660A I2O Cs W-REF MSCRIPTI'6 MMLY y SE 94 3 TCTTAL WElGHT-4S LBS

(

- = 2 66030 2 -mm

. ~.... s?' i oun ~. qsAE-nEr. ,--- uco.mgo coc< O (CORLa* Onsc) --PP0TEC1\\uE BUMPER (9) W BBER) - Luck RE74mb (M 9T.STL ) l bO-P JOC. tD l C^P )(RM (3 )

1. j

^ (9ygg (104 ST 7n:) f j 3 \\ JLEEVE i Cowwy,rrt1mir,6 f N (DHillROD) l I ' leg"tr.oss-91) \\ g i t-, +, -j -. L / \\ W CTtR80c1 \\ La T [..I (M) ST STL.) /E ~\\ w !mu! llfla k' CON NEC f,' \\ 11s x bs / 5 / / bb N\\ ) Q @f f ,-{,?",. -( *r-m T '., kN}i fy ~ ( ( L'Q'h 4 \\ 5 .,n r t I,' ' ~;' --y ?-- - [ '}-y i -y yo. 4 _t -- si i, y f \\ / 9 Ql e xu h ) / ao.u soc.a cesca. y Ns.*,, s I MM (srAnsit.) 4 // / & tr""/ h A grnE / // [ ) \\ / / $t$g I Ahi1-ROWE t.uGS LD H R) / l $ELLOGR RIt% (JOfFT.7L) l (fof 7T.STt.) ] $ COWFWGON SFWG e CAME A2W ' (srm( ruton coveet / LOCK ASSEMBLY \\ / noreo m,co 300, Mocet.eso cw,4% R/r/ PFDJECTC (1/4 < s/t n4T Geto pxx 7p b W - snumne coneR attMaoema) DescRipnVE ASSEMBLY .x c.. : i c e6cyo --.--a A GM. e i s,.gt yy3

tA l l >c3t' i O nuauAenanoea-O O.) ZlRCALLOY, CH b) TITANIUM, OR C) TYPE 304L STAlfvLE$f STEEL COATED WITH 90-IDO.ym Ni AL e f) DIA HOT TOP ATC400-Y30am AL2O9 JLEEVE ()\\) OFT'oMAL- .%O 0.0. =.0f0 WALL FAME MAIL AS1 TUBE (CMT In 9HIELD) 9HIELD l CEPLEIED LWWilLM w/ 1 l ._ _ p.= - - - 1, - + -_ - - --- /. ( I. . // / , /,' l l !/- } l if TYP j 'h' 5 I.ca -/ _=_= _= = g, i< ),.,,,.. ._L* s' i.'s ),l t l C __.___J__' ti i, 4 - j4 } =. i AFPRCM g 4 1 = ~ 2 16 THill(RET)

.CLO 1T PL IM DC f

')HIELD DATA V.; j n i i " 39 Lf3) t Sibs. yoryyup I"Amy A5 nOTED E mv.jM. 7 W W 1/8 H *

• d -

D ~ ML 66,0 (ywuA FN PMEM wetoep t #NsercTm in m FECTION A-A ggggga *L-

1. fg, Sgpg g g ggg

/ oegca,pT,vei aseseuau? 9CALE: ll1 ,L,,*f ^ __"( ~_ 6 G (g o l}(

l?. >C ' El"/ z Swery c/1.g. sym),Q*g '~A/Q ? -:f,?L.l%.:,2 ?. e ' < ? {-3 .= ? : .<J. g ~ ~.. - ,, 7 f-?.%. ? n;. . '..;2:. b,.', ,[. "253 3 <,jbhkNMiNS[i(Y:,a.. 'e l. 3 N $.C9I* Yi.jy.{ ? .If '44 ih.c' ) CAPSULE A35Y k URCE WIRE SUS A5T[ .MO D-REF V ,m y~~ ~ -. m .- _JH4K! ~.. ..)n _~. Q3 _y L t R t 970 +EF 3 pg, 7g =- .DGTES: ...m ~ 1. ~4NSERL E.. WIRE $US A95Y INTO CAPTWLE A55Y. ~ ....- M/u M Sous2 WIAE tF FULLY litf5!RTED. .. _q f '_ Et10 AF.6 AGE) ~ ~ ~ ~ -i.. .Assr.10 Sounx wute fue A!i5Y.ugses. { } c..h-fiitIlkflIGE OF fri0 (n08Q $~IF00(460r)1.E' "~ ovr. w engyswer posrar. ".~.Wmis1L' -Ey, APPLY._TWeLTDtFILF TEEN 1Mrrjyour(yxmx .. ~ WI8Ep.A5fL.. APPLY. A:PRDOF.(DAD OF 300 LS$ ~ ~.. - '~ EYTErryI0t!$hDER.7HE LOAD SM11 NOT EXCEED 0.05 INCH 3 2 FOR DETAfED PROCEDUMTs SEf RAD (ATOff TAFFTY MANUAL ~, WLRT 5, TFCTIOff 2 NOTE: THIf90URCE A55Y 69 U9ED IN CONJUNCTKit WITH THE FOLLOWING PAD)OGRAPHic EXPO 9URE DEVICES: ldODEL * ~" 660, 719 ~ ~ MAT ERIAL$ TechrOpt,Inc. E BM MM9 f, 7" 1 3 RADIATION PRODUCTS DIVISI.ON ~ DURLINGTON. MA 01 E'M3 F INISH PWG TITLE ,( MODEL 424-9 70URCE A75Y oaa ~ - =.= = -

k I

f- & g/ "'e M .x a

i. c xc6 sv

,. ; -: y [ ( ,f ctAssancAT10N SIZE DWG.NO. . ' ' - f;; yy .;% %.3 i APPRO,VED BY

• ANGLES

~ f b

1 rRActrONS 1

/ SCALE ):I l.-18 lSHEET. I OE I, . ntanma co .u~. n.n.i.e

g a m w - - n w r ~. M R T A T M M s'L f M M *A W A T M M ~ M ' ]NWAM3MMMEE"2"A"M"4 wac roR2 61s t IVUCLEAR REGULATORY COMMISSION I 4 om CERTIFICATE OF COMPLIANCE i f j So cra n FOR RADIOACTNE MATERIALS PACKAGES 1 a CERTIFICATE NUMBER b HEvtSION NUML.Lh h ^ ACKAGE (DLNTIFICAllON NUMBLH c PAGE NUMBER

e. TOTAL NUMBER PAGEl 9033 8

USA /9033/B(U) 1 2 l l ) encAuBor t . Tnis ceninc.ie is issueo io certivy in.i tne pack.oing.no conients oescribed ia item s beio. meets the pphC ble s iety st.nd.rds set fortn inTitle 10. Cooe I i g o, reoer.i neoui.uons. e.ri 75. e.ca.2 no.no Tr.nsport.iion of n.aso.cii e u.ier.i-i b This certsfsc.te ooes not reheve tne consignor from comph nce -etn.ny requirement of the regulations of the U.S. Dep.rtment of Tr.nsport. tion or otner h e. .ppuc.b e regui.iory.oencies. inciuoing the government of.ny country inrouan or into -necn ine pack.se -iis be tr*aspor'eo-I y l> 1 i P e 3 rwis conviricATe is icsvro ou Tuc exsis or a sartry ^~^tysis ateonT or rue PAcx^oE otsiow oa ^enticario~ p l' .. ISSUED to #Nem, omt Amuss

b. TITLE AND IDENTirlCATeoN oF REPORT oR APPLICATloN-j l

>I i Amersham Corporation Amersham Corporation application dated E 40 North Avenue December 1,1989, asssupplemented. Burlington, MA 01803 g ), N

c. ooextT ~Uuata 71-9033 A

N < conomous 4 ws ceTinc.ie is cono ilon., upon tuininna ine requirements of io crn e.ri ri. s.ppoc.bie..no in. conditions specified beio - ( 5. d 15 f (a) Packaging l (1) Model No.: 660, 660E, 660A, 660AE, 660B or 660BE l e i (2) Description 5 if 5 A steel encased uranium shielded Gamma Ray Projector. Primary { } components consist of an outer steel shell, polyurethane potting material, uranium shield, "S" tube, and end plugs. The contents are g securely positioned in the "S" tube by a source cable locking device and i shipping plug. Tamper-proof. seals are provided on the packaging. The j maximum total weight of the package is approximately 53 pounds. E, ( I 4 (3) Drawings E )1 E, ( The packaging is constructed in accordance with the following Technical f,. ) Operations, Inc. Drawings: j e F q (i) Model No. 6608 - Drawing No. 66025, Sheets 1, 2 and 3, Rev. D; il i I ( (ii) Model No. 660 - Drawing No. 66025, Sheets 1, 2 and 3, Rev. B, I j and Sheet 4, Rev. -; or Drawing No. 66030, Sheets 1, 2, 3 and 4, l, Rev. -; j i (iii) Model No. 660A - Drawing No. 66030, Sheets 1, 2 and 3, Rev. A; or I e Drawing No. 66030, Sheets 1, 2 and 3, Rev. B. / i I f liodel Nos. with an E suffix have an electrical circuit. l f (b) Contents l S I el (1) Type and form of material i I I 1ridium-192 sources which meet the requirements of special form l radioactive material. t-19 9 gg,,,,,,mwmm,,g.:mywmwnmwwwwms=w l l

e >s % f *M METTM MATX"hTE IMTA % ""A I?2"]W5L*MM M M M 2%?*3?rrEM ?EAIMMK l ) M s3 CONDITIONS (continued) i .) h* f Page 2 - Certificate No. 9033 - Revision No. 8 - Docket No. 71-9033 . 9 (2) Maximum quantity of material per package 9 l (i) 140 Curies for the Model No. 660B or 660BE package. ) d i (ii) 120 Curies for the Model No. 660, 660E, 660A or 660AE package. i i l4 i l 6. The source shall be secured in the shielded position of the packaging by the source assembly. The source assembly must be fabricated of materials capable of p i resisting a 1475 F fire environment for one-half hour and maintaining their p q positioning function. The source assembly must engage the locking device. If il The source assembly must be of sufficientelength and diameter to provide F N l positive positioning of the, source, withinithejdepleted uranium shield assembly. fl sX' a ThesourceassemblyferfusewiththispackagingiUlimitedtoTechnical g i 7. Operations, Inc. Model'No. 424-9 as shown in Technical Operations, Inc. Drawing g i No. 42409, Rev. B. j h 8. The name plate must.be fabricated of materials capable of resisting the fire test of f s j 10 CFR Part 71 and maintain.ing its legibility. g. 7 4 j i 9. In addition to the requirements of SubpartiG.of!10 CFR Part 71:. p M,' 6 "a ~ f i r;- ..T/ ~~ ' (\\j j b ? d i (a) Thepackage:mustmeet'the. Acceptance _Testjnd.. Maintenance,ProgramofChapter l 8.0 of the, application ~,Eas" supplemented;eand i y 7, .c wrryT The package'shall b~e prepared,forishipment'in accordance~ with the Operating J j (b) Procedures in. Chapter;7 0 of-therapplication, as supplemented. l 6 7 .a p. j e l general license provisions of 10 CFR 571.12. p/ i

10. The package authorized by this certificate is hereby approved for use under 4

p %] i i 11. Expiration date: October 31, 1995 i i REFERENCES i j Amersham Corporation Application dated December 1,1989. i Supplements dated: April 24, August 23, September 6, Septe h er 17, October 26 and i November 27, 1990. i l FOR THE U.S. NUCLEAR REGULATORY COMMISSION ]b ~ dW8 ]% dl l! Charles E. MacDonald, Chief f Transportation Branch Division of Safeguards { ) and Transportation, HMSS i 4 DEC 0 51990 i Date: e dy ,h I-20 .mmm_m.mmmmmm__.__.__

O O O / ) 0 NARROW BODY 0 WIDE BODY 660 660 120 Ci 120 Ci g4E 66cE ( ) l I l . - - t 5/8 -- 5 1/4 E [ O NARROW BODY WIDE BODY WIDE BODY 660A 660A c-6608 120 Ci 120 Cl 140 Ci uooAE G60AE VoosE i l-- 4 5/8 -- - 5 1/4 --- -- - 5 1/4 -- ARO-nVHD

4.4E-e.de-4 B-u4 -e .4 m.4,ogei w4m.c .a e a .e .a. w a .amaw pr "'"3"^^5'# "P* * '"'#8'f*"#"d'***" 2i"" ~~ ~-~ -'-~" t i 4 O i s i It [ i s 9 i e 1 i O

i -

I l M 4 I N i .ie J i I w d l . e -i A i I r 6 4 \\ .-ys,e -,.7,u ,--rw-+-.-4-, y, y.-re.- g.ym.me- -.-%y me.- n ew --.e----weiss-er

====--www .e r ere-i a'N'-e=>'wwm*=ewsm-*==-**+w*ae*-*n"

2. Structural Evaluation 2.1 Structural Desion 2.1.1 Discussion The Model 660 series is comprised of five primary components: a source capsule, source holder assembly, shield assembly, outer housing assembly and locking assembly. The source capsule is the primary containment vessel. It satisfies the criteria for special form radioactive material. The shield assembly provides shielding for the radioactive material and, together with the source holder assembly and locking assembly, assures proper positioning of the radioactive source. The outer housing consists of a shell and two end plates that s are secured together by means of four tapped rods. The housing provides the structural integrity of the package. 4 The lockbox assembly secures the source holder assembly in i the shielded position at the center of the source tube and 1 assures positive closure. 2.1.2 Desion Criteria i' The Model 660 series is designed to comply with the requirements for Type B(U) packaging as prescribed by 10 CFR l 71 and IAEA Safety Series No. 6 1985 Edition (as amended). All design criteris are evaluated by a straightforward l application of the appropriate section of 10 CFR 71 or IAEA Safety Series No. 6. 4 0 2.2 Weichts and Centers of Gravity The total mass of the Model 660 series is 93 3 lbs. (24 1.36Kg). f The shield assembly consists of 37 i 3 lbs. (16. 8 1 1. 36 Kg) of depleted uranium. The center of gravity is located approximately in the center of the device. 2.3 Mechanical properties of Materials The outer housing of the Model 660 series is fabricated from 304 stainless steel and low carbon steel. These materials have a yield strength of 30,000 PSI (207 MN/m8). l 1 The source capsules used in conjunction with the Model 660 are } fabricated from titanium or stainless steel. ) 2.4 General Standards for All Packaoes 2.4.1 Minimum Packace Size Package exceeds minimum package size requirements specified by 10 CFR Part 71. 4 3 (a). 2.4.2 Tamperproof Feature See Section 1.2.2 and 2.4.3. 2.4.3 Positive Closure 2-1 REV. O August 12, 1993

j The control connectcr and lock assembly consists of a hardened steel locking slide (Models 660A, 660B, 660AE and I 660BE only), a selector ring with three operating positions (connect, lock, and operate), and a casting which houses a key type lock. The control connector and lock assembly provide for system safety in the following ways: 1. The source cannot be moved from the exposure device until a secure connection has been made between the source assembly and the control cable. 2. For the models 660 and 660E the locking assembly cannot unlock the source until the following conditions are J met; a) key lock is unlocked, b) the drive cable has been connected to the source

assembly, c) the control unit has been connected to the exposure device and, d) the selector ring has been rotated to the operate

position, i

3. For the models 660A, 660AE, 660B and 660BE, the locking assembly cannot unlock the source until the following conditions are met; a) key lock is unlocked, b) the drive cable has been connected to the source

assembly, O

c) the control unit has been connected to the i exposure device, d) the selector ring has been rotated to the operate position and, e) the locking slide is manually moved to the unlocked position. i Note: When the locking slide is in the locked position a green colored indicator is visible. When in the unlocked position a red colored' indicator can be a seen. 4. The locking slide automatically locks the source assembly when the stop ball on the source assembly releases a spring loaded sleeve, that keeps the locking slide open during exposure of the source. The source assembly cannot be exposed again, until the locking slide is manually reset to the open position. During transport a protective cap is inserted into the control connector, the selector ring is rotated to the lock position and the key lock is depressed into a recess in the selector ring. A storage plug is also threaded into the front of the exposure device and positioned against the source capsule on the source assembly preventing movement until the storage plug is removed. During transport the storage plug is seal wired to provide a tamper indicator. 2-2 REV. 0 August 12, 1993

I t I j Positive closure of the package during transport is maintained with these features. 2.4.4 Chemical and Galvanic Reactions The materials used in the construction of the Model 660 [ series are depleted uranium metal, stainless steeli steel, titanium, rigid polyurethane foam and when required, supplemental lead or tungsten. There will be no significant chemical or galvanic action between any of these components. l The possibility of the formation of a eutectic alloy of iron and depleted uranium at temperatures below the melting temperatures of the individual metals has been considered. The iron-uranium eutectic alloy temperature is approximately 133 7*F (72 5*C). However, vacuum conditions and extreme cleanliness of the surfaces are necessary to produce this i alloy at this low temperature. Due to the conditions in which the shield is mounted in the Model 660, sufficient contact for this effect would not exist. I In support of this conclusion, the following test results are presented. On 28 November 1973, a thermal test of a sample of bare depleted uranium metal was performed by Nuclear metals, Inc., Concord, MA. The sample was placed in a j ceramic crucible and inserted in a furnace preheated to 1475"F (802*C) and remained there for thirty minutes. The sample was then removed and allowed to cool. The test j indicated that the uranium sample oxidized such that the i radial dimension was reduced by 0.007 in. (0.18mm). On 25 January 1974, a subsequent test was performed by Nuclear Metals, Inc. In this test, a sample of bare depleted O uranium metal was placed on a steel plate and subjected to the thermal test conditions. The test revealed no melting or i alloying characteristics in the sample and the degree of l oxidation was the same as experienced in the earlier test. In July 1992, two Model 660's manufactured in 1974 with supplemental lead shielding, were disassembled and visually examined. There was no evidence of any problematic degree of eutectic alloying. The products were then reassembled and drop tested, to show that the additional weight, did not have any adverse effect on the structural integrity of the product. The test eport and photo's are included in appendex 2-10. 2.5 Lifting and Tiedown Standards for all Packages 2.5.1 Lifting Devices The Model 660 series is designed to be lifted by its handle. Failure of this lifting system could be accomplished by shearing two #10-32 flat head screws securing one side of the handle. The yield strength of the screw material is assumed i to be 40,000 pounds per square inch. The cross sectional area of each screw is 0.02 in.2 (12. 9 mm' ). Therefore, a load of 1600 lbs. (7117N) must be applied to generate stress equal to the yield strength of the material. i This is equal to thirty times the weight of the package. () 2-3 REV. O August 12, 1993 ~ ~

.m. .m ,m = -.a.. 9 i 1 f Therefore the handle is capable of supporting three times the weight of the package without generating any stress in excess of the yield strength of the material. 2.5.2 Tiedown Devices i The handle of the Model 660 series can also be used as a tie down device. The above analysis also demonstrates that the handle will also withstand the loading requirements of 10 CFR 71.45 (b) (3) without generating stress in excess of the yield strength. If the tiedown technique were to fail under excessive load, i the ability of the package to maintain its structural integrity and shielding efficiency would not be impaired. Therefore, the package tiedown design satisfies the criteria of 10 CFR 71.45 (b) (3). l 2.6 Normal Conditions of Transport 2.6.1 Heat i The thermal evaluation of the Model 660 series is presented j in Chapter 3. From this evalttation, it is concluded that the l Model 660 will maintain its s;cuctural integrity and shielding effectiveness under the normal transport heat l condition. 2.6.2 Cold The metals used in the manufacture of-the Model 660 series l can all withstand a temperature of -40*F (-40*C). The outer i O package housing and the primary containment are all fabricated from steel. t Rigid polyurethane used in the Model 660 series has an operating temperature range down to -45*F (-43 *C). From this data, it is concluded that the Model 660 series will maintain T its structural integrity and shielding effectiveness under the normal transport cold condition. 2.6.3 Reduced External Pressure The Model 660 series is open to tne atmosphere. Thus there will be no differential pressure acting on it. A demonstration of the ability of the source capsules to withstand an external pressure of 3.5 psi is presented in Section 3.5.4. On the basis of this data, it is concluded that the Model 660 series will maintain its structural integrity and shielding effectiveness under the normal transport pressure condition. 2.6.4 Increased External Pressure The Model 660 series is open to the atmosphere, thus there i will be no differential pressure acting on it. The collapsing pressure of the source capsule is calculated i assuming that the capsule is a thin wall tube with a wall i thickness equal to the minimum depth of weld penetration 2-4 REV. O August 12, 1993 =. -. -.. ~

l l I which is 0.016 inch (0. 4 mm). The collapsing pressure is I (} calculated from: P= 597.6 t/d - 9.556 where P: Collapsing pressure in MN/m2 t: Wall Thickness (0.41mm or 0.016 inch) d: Outside Diameter (6.35mm or 0.250 inch) (Ref: Machinery's Handbook, 22nd Edition, p. 3 3 0.) I i From this relationship, the collapsing pressure of the source capsule is calculated to be 4162 psi (28.7 MN/m2 ). Therefore, the source capsule could withstand an external pressure of 20 psi (0.138 MN/m2). 2.6.5 Vibration r The Model 660 series has been in use for more than twenty years. In this period, there has been no evidence of vibration-induced failure. on the basis of this history, it is concluded that the Model 660 series will maintain its structural' integrity and shielding effectiveness under the normal transport vibration j condition. 2.6.6 Water Sorav l The water spray test was not actually performed on the Model l 660 series. The materials used in the construction of the 6 Model 660 series are highly water resistant. Therefore, it O is concluded that the Model 660 series will maintain its I structural integrity and shielding effectiveness under the normal transport water spray condition. i 2.6.7 Free Dron i A prototype Model 660 series weighing 53 lbs. (24kg), was i subjected to the hypothetical accident free fall condition. This is described in Section 2.7.1, On the basis of this test, it is concluded that the Model 660 series will maintain its structural integrity and shielding effectiveness under the normal transport free drop condition. 2.6.8 Corner Dron Not applicable. 2.6.9 Compression A Model 660 Series was subjected to a compressive load of 300 lbs. (136 Kg) which exceeds five times the weight of the package. This is greater than 1.85 lb/in2 (12.8 KN/m2) times the vertically projected area of the package 95 in2 (0.061m'). This load was distributed uniformally over the top surface of the Model 660 Series for 24 hours. As a result of this test there was no loss of structural integrity or shielding efficiency. There was no visible or detectable damage as a 2-5 REV. O August 12, 1993

J d result of this test. Therefore the Model 660 series will withstand the normal conditions of transport compression O loading. 2.6.10 Penetration A prototype Model 660 Series was subjected to a penetration l test. The package was impacted by the penetration bar on the-locking assembly. As a result of this impact,-there was no l loss of structural integrity nor reduction of shielding efficiency. A report of this test is presented in Section 2.10. i a i On the basis of this test it is concluded that the Model 660 Series will maintain its structural integrity and shielding effectiveness under the normal transport penetration condition. 2.7 Hypothetical Accident Conditions 2.7.1 Free Drop The Model 660 Series was subjected to the conditions of the free drop test. The target used in this free drop test is described in the test report in Section 2.10. During the test, the package fell from a height of 30 Ft. (9.1m) onto the target. The lock assembly was impacted as a result of this drop. As a result of this test, there was no loss of structural integrity nor reduction in shielding efficiency. A report of i this test is presented in Section 2.10. On the basis of these tests, it is concluded that the Model 660 Series will maintain its structural integrity and shielding effectiveness l under the hypothetical free drop accident condition. 2.7.2 Puncture At the conclusion of the free drop test, a Model 660 Series was subjected to the puncture condition. The target for the puncture test was a steel billet 6 in. (152mm) in diameter i and 8 in. (203mm) high, mounted on the target used in the free drop test. j During this test, the package was dropped from the height of 40 in. (1m) onto the billet, and impacted the lock assembly. As a result of this test, there was no loss of structural integrity nor reduction in shielding efficiency. A report of l this test is presented in Section 2.10. On the basis of these tests, it is concluded that the Model 660 Series will maintain its structural integrity and shielding effectiveness under the hypothetical puncture accident condition. 2.7.3 Thermal The thermal analysis is presented in Section 3.5. In Section 3.2 it is shown that the melting temperatures of the materials used in the construction of the Model 660 Series except for the rigid polyurethane and lead are all in excess of 1475"F (802*C). i w 2-6 REV. O August 12, 1993 4

I To demonstrate that the radioactive source assemblies will O remain in a shielded position following the hypothetical v accident condition, the following analysis is presented. At j the conclusion of the thermal test it is assumed that the rigid polyurethane foam has completely escaped from the 4 package. The shield assembly is prohibited from movement by the front housing, rear plate and the 4 tapped rods passing from front to back to secure the shield in place. 4 A Model 660 Series was involved in a fire in 1974 and did not i suffer any loss of shielding effectiveness. A copy of this report is presented in Section 2.10. Thus it is concluded that the Model 660 Series satisfactorily meets the requirements of the hypothetical thermal accident j conditions of 10 CFR 71. f j i I 2.7.4 Immersion - Fissile Material Not applicable. i 2.7.5 Immersion - All Packaces l Not applicable 2.7.6 Summary of Damage ] The tests designed to induce mechanical stress (free drop, puncture) caused minor deformation but no reduction in structural integrity nor impairment of any safety features. The thermal test would have no adverse affect on the package. l () As a result of these tests, there was no loss of. structural integrity nor release of any contents. l Prior to the performance of these tests and subsequent to the i conduct of these tests, measurements of the radiation 1 a intensity in the vicinity of the package were made. The results of these measurements demonstrate that there was no' reduction in shielding efficiency as a result of these tests. 2.8 Special Form The Model 660 Series is designed to trer. purt Amersham source capsules. These source capsules have been certified as special form radioactive material by U.S. DOT. This certificate is presented in Section 2.10. 2.9 Fuel Rods Not applicable. 2.10 Appendix IAEA Certificate of Competent Authority USA /0335/S. Page 2-9. Test Reports: Free Drop Test Report - see page 2-10 Shielding Efficiency Test Reports - see page 2-11 Puncture Test Report - see pages 2-12 thru 2-15 ( 2-7 REV. 0 August 12, 1993 I

I k 4 i Free Drop Test Report - see pages 2-16 thru 2-18 i 1 Q Puncture Test Report - see page 2-19 i V Low Temperature Drop Test Report of 660A ] with Posi-Lock - see page 2-20 [ Shielding Efficiency Test Report - see page 2-21 r l Drop Test Report of 660 with lead added - see pages 2-22 and 2-23 f Shielding Efficiency Test Report - see page 2-24 i i Photographs of Model 660 with lead added during i shock and drop tests - see pages 2-25 thru 2-30 660 Involved in Fire - see pages 2-31 and 2-32 Gamma Ray Projector Model 660 Drop Test - see pages 2-33 thru 2-37 4 Leading of type B Transport Devices - see pages 2-38.thru 2-42 l' i i = I ^ i l E l f i I i T i (:) i i [ i i F i l 1 8 r 1 2-8 REV. 0 O August 12, 1993 l 5 I i t i =r n -w- --e-a e m-

F Oh US Depyte CORRECTED COPY "" o'"c"' m"n' 5 wa moa or 6py.on Research and O IAEA CERTIFICATE OF COMPETEh7 AUTHORITY Spec 6al Progroms AdminjstratK>n SPECIAL FORM RADIDACTIVE MATERIALS CERTIFICATE NUMBER USA /0335/S, REVISIDE 1 This certif ies that the source described has been demonstrated to meet the regulatory requiyements for special fgtm radioactive material as prescribed in 1AEA Regulations and USA regulations for the transport of radioactive materials. 1. Source Descrirtion - The source described by this certificate is identified as Amersham Model 875 source capsule assembly which is singic welded encapsulat. ion constructed of\\ Type 304 or 304L astainless steel, and measures approximately 24 mm (0.95") in, length by 6.4 mm (0.25") in diameter. Contents may be further contained in stainless steel or titanium inner secondary encapsulations with springs and spacers. 2. Radioactive Contents - This source consists of not more than 8.88 TM (240 Ci) Iridium 192 as solid metal, 8.14 TBq (220 Ci) Cobalt I 60 as solid metal, 7.4 TBq (200 Ci) Ttterbium 169 as Yb 02 3* I II TBq (30 Ci) Cesium 137 as CsC1 in a sec ndary stainless steel 2 encapsulation, or 1.85 TBq (50 Ci) Thulium 170 'as Tmy 3 0 3. Expiration Date - This certificate expires July 15, 1994. This certificate is issued in accordance with paragraph 803 of the IAEA O' Regulations and Section 173.476 of Title 49 of the Code of Federal Regulations, and in response to the June 14, 1989 petition by Amersham Corporation, Burlington, MA, and in consideration of the associated information therein, and other inf ormation filed with this office. Certified by: ( ,p' p/ JUL - 5 E9 _,f th u in sichb.1 E. Wanglef (DATE) Chief, Radioactive Material _ ranch Office of Hazardous Ibterials Transportation Revision 1 - Issued to change the source identification from Tech Ops to Amersham and to extend the expiration date. 1 " Safety Series I;o. 6 Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition" published by the Internatior a1 Atocic Energy Agenc y (I AEA), Vienna, Austria. 2 Title 49, Code of Federal Regulations, Parts 100 - 199, USA. O 2-9

TEST REPORT BY: Cathleen Roughan Dave Duncanson DATE: 13 October 1989

SUBJECT:

Model 660 Free Drop Test On 29 September 1989, a prototype Model 660 package manufa,ctured in accordance with drawing number 66025, revision C, was76bject-ed to a free drop test in accordance with the requiremjtnts of 10 :- CFR 71.73 (c) (1) and IAEA Safety Series No. 6, para raph 719(a) The test package was constructed out of tainiess eel, had_an automatic securing mechanism and weighe 3 0 pounds".' This test' was performed at Valley Tree Service, G nd, a. The ambient' temperature was approximately 50 degrees Fahrenheit with normal ] humidity. j The Model 660 package was dropped from a height'of 9.1' meters (30 feet) onto a target. The target consisted of a concrete cube, each side measuring 1.2m (48 inches) upon which-had been wetJ .i floated a steel plate 0.9m (36 inches) wide, 0.9m (36 inches) j long, and 25mm (one inch) thick. This target conforms to'the 'O guidance for an essentially unyielding surface as prescribed in paragraph 701 of IAEA Safety series No. 37. i The package struck the target with the' center of gravity over the locking assembly as shown in the drawing. 'This caused the pack-age to strike at a 45 degree angle, impacting the bottom edge of l the locking assembly. 1 As a result of this test, there was no impairment of any esign' or safety features of the package. There was no structural damage to the locking assembly or package closure. There was no I release of the package contents. Photographs showing the' damage are attached to this test report. A shielding efficiency test performed subsequent to the comple-tion of the Model 660 test program demonstrated that the free drop tests did not reduce the shielding efficiency of the package. Revision 3 August 1990 CMR230 m 1 . ~

m. _. _

i Amersham Corporation RADIOGRAPHIC EXPOSURE DEVICE AND SOURCE CHANGER INSPECTION REPORT urtingto. Massachusetts 01803 N' Mb37 Ib Max. Capacity [, ( E Serial No.: Ci Radionuclide Model No.: SHIELDING EFFICIENCY TEST INCOMING SHIELD ASSEMBLY Source Model No.: Source Serial No.: . C l' Activity Ci l Ib b~\\ f 7 ^ [a ~ Y h Due Survey instrument. NMMCerialNo.: 7' Date Cal. SHIELD IDENTIFICATION NUMBER di{y.3 MASS OF SHIELD 3 7 ff-OBSERVED INTENSITY mR/hr ADJUSTED INTENSITY mR/hr AT W ^M AT l CoR,A p0 oN SURFACE SURFACE y [{ } j TOP ~7g

lL TOP h2 RIGHT

( (. l g,y[ IA$1'o$" RIGHT h[ FRONT O ~ Q, { [,() g,g FRONT gh/{ Ak[ C l.M LEFT

1. [y c g LEFT REAR

{(. { [, t 3 [ REAR BOTTOM hC { [, l g BOTTOM $Q O.n b b d ^di Date inspector's Signature SHIELDING EFFICIENCY TEST FINAL DEVICE ASSEMBLY { bb Source Model No.: Source Serial No.: Activity Ci Survey Instrument: OM -Serial No. I~ I S C" b b'b Due Date Cat. OBSERVED INTENSITY mR/hr ADJUSTED INTENSITY mR/hr SURFACE urff MET MILL ERS ME ER SURFACE, a to s Qh }} ] 70 ! l il 3() .b TOP TOP _m hy 3} { RIGHT b0 ! l. slf 20 ,5 ' r"^*c'flf" RIGHT FRONT [g l j,t 3 g* (, ,{ j p Q G-FRONT !/ I LEFT /y Gh j CjQ l l,.] y' t /. (, LEFT REAR Qg l i if 5e

i. L REAR

$G g{ / C{ jg G BOTTOM gj j-l 3 dt I BOTTOM L'I Os1 Date inspector's Signature FINAL DEVICE INSPECTION INITIALS INITIALS l Guide Tube Connection Functions Properly Proper identification W Lock Functions Property Painted Surf aces Not Damaged __4 Se ector Ring Functions Properly Fasteners instaHed Property E_ V Camrol Unit Connects Properly P:oper Continuity "E" MacNnes Only Source Traveis Properly __2 Total Mass of Device l.- I-) i Source Stores Properly M Lock Assembly Gage i O Proper Labels Attached / 50 '[ V Tag No Date ins Inspector s Segnature Ndb I." l } S' lipped To [ Date nipped Address 'J_ M T_( ) Sales Order No. I P-l'l

l I TEST REPORT l ) BY: Cathleen M. Roughan Dave Duncanson DATE: 2 March 1990

SUBJECT:

Model 660 Puncture Test On 29 September 1990, a prototype Model 660 manufactur,gd in accordance with drawing number 66025, revision C, was subjected in accordance with the regulrements,o'f 10 CFR to a puncture test 71.73(c) (2) and IAEA Safety Series No. 6, paragraph 719 (b). The test package was constructed out of stainlTs'sl teel, had anautomatic securing mechanism and weighedf533 pound This test was performed at Valley Tree Service, Grovela _1 " Immediately following the free drop test, the prototype Model 660 package was dropped from a height of one meter onto a target. l The target consisted of a right circular cylindrical steel-billet 152mm (6 inches) in diameter and 203mm (8 inches) high, mounted onto the target used in the free drop tests. 'During the drop, the package impacted the target squarely on the shipping cap of the locking assembly. There was no observable (]) additional deformation as a result of this drop. As a result of these tests, there was no impairment of any design or safety features of the package'. There was no structural ~ damage to the locking assembly or' package closure. There was no release of the package contents. A shielding efficiency test performed subsequent to completion of the Model 660 test program demonstrated that these puncture tests did not reduce the shielding efficiency of the package. A second puncture test on the same package that was subjected to the previous tests was conducted on 2 March 1990, in order to assess the impact of a 45 degree drop on the puncture bar. The steel billet described above was set on an essentially yield-ing surface (a 4-foot by 4-foot by 1/2 inch thick steel plate, on l a concrete slab 20 feet by 20 feet by 3 feet thick). l The 660 was dropped from a height of one meter onto the target. The 660 lock assembly hit the puncture bar on 45 degrees at the edge of the puncture bar. Since this was not a solid impact with the entire weight of the container over the lock assembly, we conducted another puncture test. Revision 3 August 1990 () 2-12 1

e~ l l In the second puncture test, the lock assembly impacted a 45 O degree angle in the middle of the puncture bar. In this test the ~ weight of the 660 was over the lock assembly. As a result of this test there was only minor damage to the package as indicated in the photographs. The lock assembly was still secured to the package with no movement of the lock assembly. The cumulative damage due to both the 30-foot drop test and the 3 puncture tests was minimal and did not impair the structural integrity of the package. A shielding evaluation indicated there was no increase in radiation levels. l ) l O l I i Revision 3 CMR231 August 1990 0 2-13

O L MODEL 660 . \\' e i i %W l FTEEL BILLET ~\\ 150 uu (sin.) DIA 2001.W'a in) HIGR f f TARGET OF FREE FALLW i i MODEL 660 PUNC~~URE TET O I:EVISION 2 Apri1 1990

g. d I 9 ^- 4- ..K} ? y, - l ? f'c ~ E j Q. L P .- fy] 4 t A 'T-s f _, 4 g. m 1 I .g. .e t } i i t ) ? f ? h S" R;.Q. p.r %;-Q Q..h:l: qy,.',,.7,;.~. ~ ~ R i . 3p. fE: ...:v+ r ~ n.,7 c.- r c-s \\ 9. ( w.k bye- .n.... <.. _ _. * - f

• ${ ~

'-5h-l-,:l f,' .' ~ ;, L ~, ' k h' r~hhh.?Y '-?:.':_ . _. +_ mr,,y cs:--(3..;- i;2 t;.ji:.. i gg ~ ' .hh k' - ' c.-.,, - ~ ~ j %bTrk@W 4Mh i um.as.. e W< r:f.:? (?.VL.% z -w, 7 g. q qu, . ':n 5' ,;;;&'d f-6. L:. ' -

• e:

tik;.::

ta_ -+,4, ;.: z - -

.,a y_.m a:mu? '[' ~ b .s. ~,%or$&ksff,? ' N n. '~

• J.

Jh: ' ? a ' ;i.-2% :: i :.. 56fbys. ' l ';f.2:-... l l g-as h (.QQ:. ;-;Q.. _. '.] %.G&h,#44 ' rid.hQ'f } DEJ G., i l J i 2-is enaci (a.o n..m.,on y I'unc t u r e '1, si rq., i i 1%p _... - - -. - - -,. -. _ - ~. _...

e

t j

b a

• • h

.J'..'seb $,0 "h .g 'gs

f.. _,

K%$mr%V.' '.c.V ,t* l%',. i

?f YN'?Y$ g.

k a. , vs - y-( y _ f.

S

^ Q $: W.' k*;k -~ W : ~ i c.& w w% M SS:. %f-

a. -. ~ r.,- a...+%.,'. ~ ~,.n,,.+.r...

w=.... ;w w. w%.;1+ >-r. -

e.. -,.

na u r a. -q :;.- ,,,1e; ...m. . -,,. ' -,. ~.,. ..). ...._.Q'.. n; , :, s.;.., v w s e e <p .,m -- v,

.. m. -;...

1

9. ;.,. :. ' ' L k

,L L.,

.a -

~' J 4 - ^ ~ ~. - g% 5, ^" r ~.- .., _. ^ 'j A f ' ' o-J '.-' g..,,.. -. = < w l 3,&:a[E 2" 5 % W % %- Q,. __&M m' m.. w m. . - dC.:j.-ki'.:7.*%'j-sc?f. h&..R - '., 5 & - % '.. Y & _ L 3.5-3 ::: : b ' 5-i l l i ] 1 \\ I i i

v..,.','$?fe.*ynn

%,_, $ & : L ' B. Y? - + U &y, m'.Q y .,, -. g,3. f - q {_. - { f J ^ _ - l f. _,yf : - }.' '. - - ' '. - - - : ..,.,gy ^g 3 'e- ~,, ,y.. .,s.

• • ' T -

-(i._, 8 - dy :. 7,s,'.t ".. ?., C --'- ^^ 1 . 7-j l& 2,:.j '-_lI -..v i . yj. '. s {.h. .l.~.. '.. .._')y.l:=ll5. ?f.. .;. s.:. - .c .fl-l. .j 8 &p_. m -. : ] ^ ;' '. kkhfdI};' ;.;;~-y ^}b:rI , ').M~.7? : ; ^ - <. .-* Sk, W M. g. n [,g.,.h .1 _.[ h h N. N M25 wg.[h M. 9 t f f b,k k4~g.@{

• n

.m n-k ' " ' '.~") -. i [' '.l... r y'.~' ;:7 ' q q.f_, ',. t f .a.

z. ' -

,5 f y ' l .~.c'y,4 %g;..,4. l ..pg,j,,c,c

9.,., 7.,. r,;., - j.

j,,. 7,a 1

y L.~~...

4., ;.51

~.- :: . = ~ - .-W;~'.;::: ~: n.: : -- n g>.. _:.. 1. ~,....",sg,r;

y. u

.,t.m...;,a.;.: s A- '... [';. ~ - - a( a _a,) .:..,.'s* , [1. a. .... w -..W,. w

• m

.. ' c- -

- p,.' A:w, T...w .~3.'. ~ T. .:.- ? <- .;;..~ }

3. n'

- ;,.y ;... i. _ 7 l 9@y2.,4,.- ? -- '.. r l . :. : r b GlM2:y._. --W:q :w.J ; ' o m. j - E ~ s.;.:7.i M.sj$'ygj--i, Q i&~frM2sM$$'[h@f.h.3 -

.n m M.i w

- =- f t 1 4 \\ 4 1 4 4 1 4 d a 4 O 2-is e(Il (* J. 4'Y b DIh, 2 i PtusCI ti re Te *;t p,. j } jggg ~_ ,r_ . ~.

TEST REPORT gb BY: CATHLEEN ROUGHAN DAVE DUNCANSON DATE: 28 SEPTEMBER 1990

SUBJECT:

Model 660 Free Drop Test On 29 September 1989, a prototype Model 660 package modified with the automatic securing was subjected to a free drop tr * 'n accordance with the requirements of 10 CFR 71.73(c) (1) and IAEA Safety Series No. 6, paragraph 719(a). This test was performed at Valley Tree Service, Groveland, MA. The Model 660 package was dropped from a height of 9.1 meters (30 feet) onto a target. The target consisted of a concrete cube, each side measuring 1.2m (48 inches) upon which had been wet floated a steel plate 0.9m (36 inches) wide,0.9m (36 inches) long and 25mm (one inch) thick. This target conforms to the guidance for an essentially unyielding surface as prescribed in paragraph 7.01 of IAEA Safety Series No. 37. During the drop, the package impacted the target on the shipping cap over the s locking assemoly. x As a result of this test, there was no impairment of any design or safety features of the package. There was no structural damage to the locking assembly or package closure. There was no release of the package contents. A shielding efficiency test performed subsequent to the completion of the Model 660 test program demonstrated that the free drop tests did not reduce the shielding efficiency of the package. g 2-1G

l O A \\. N MODEL 660 4 -l .i i l I i g Y 4,. FREE FALL TARGET 06 0F CorfCRETE CUBE I.Em x f,Em r f.2m WITH A N j 4 PtATE O.9m x 0.9mp MmmTHK-WET FLO4 TID Off TOP I wn (9.MIM) i O l i i 1 I I .j i .,. * ~ FREE FALLTARGET a Voli660 i FREE CAL_ TEST 0 2 -17 Revision 2 April 1990-

l .1 i i { - - m$ g IO 3 N l N s j N ^ b f f i l / I / s G N /^ /: I l ~ - =e:-r=ty;,,:p:m:: min %, 9, 7y -- u ~

a-

- w-

"~ -

l I crr 7Mi j... M'fU) y g l A. .x ) 4; y i ~ l }l T, WW' \\

-n%

.

f (. /,..: u; j e -, i w j ,[ s {- fn 7...;.~' 4 4 1 l 2 2 -'S i O MoDEL 660 i Qvigwy 7, i-FREE FAU 6 ' APRt L L990 i

~ i TEST REPORT -O BY: CATHLEEN M. ROUGHAN q DAVE DUNCANSON - 1 DATE: 28 SEPTEMBER 1990

SUBJECT:

Model 660 Puncture Test 1 ~i On 29 September 1989, a prototype Model 660 modified with the automatic' - ~ securing mechanism was subjected to a puncture test in accordance with the, requirements of 10 CFR 71.73(c) (2)'and IAEA. Safety Series No. 6,- paragraph ~ 719(b). This test was performed at Valley Tree Service,~ Grovelandl MA. 1 Immediately following the free drop test, the prototype Model 660 package was .l ~ dropped from a height of one meter onto a target. The target' consisted of a'right : 1 circular cylindrical steel billet 152mm-' (6 inches) in diameter and 203mm (8 inches) high mounted onto the target used in the free drop tests. During the drop, the package impacted the target squarely on the' shipping cap of f. O the iockino essembiv. There was no observebie edditionei deformation es e resuit of this drop. 'I As a result of these tests, there was no impairment of any design or safety - features of the package. There was no structural damage _to the locking lassemblyf or package closure. - There was no release of.the package conte'nts.

i o

A shielding efficiency test performed subsequent to completion of _the Model 660 test program demonstrMed that these puncture test'did not reduce the shielding efficiency of the package. ~ I t O 2-i9

i i l t l TEST REPORT (GBODROP) AMERSHAM i TO: DAVE DUNCANSON FROM: GEORGE PARSONS l DATE: 02-11-92 I l

SUBJECT:

LOW TEMP DROP TEST OF 660A POSI-LOCK l THE ACCIDENTAL DROP TEST DESCRIBED IN ANSI N432 SECTION 8.4, ISO 3999 SECTION 6.7 AND 10CFR 71.73 (b ) WAS PERFORMED ON A MODEL GSOA POSI-LOCK PROJECTOR. THE E60A WAS PACKED IN DRY ICE FOR 24 HOURS AND A TEMPERATURE j PROBE INSIDE THE "S" TUBE OF THE 560A RECORDED A TEMP. OF'-45.01 DEG C (-S0.82 DEG F ) APROX. 5 MIN. BEFORE THE DROP TEST OF THE 660A. THE AMBIENT TEMP. AT THE TEST SITE WAS 28 DEG F. DESCRIPTION A TARGET CONSISTING OF A STEEL PLATE ON THE UPPER. SURFACE OF A BLOCK OF CONCRETE AS DESCRIBED IN SECTION B.4.2 0F THE SPECIFICATION WAS PREPARED. THE MODEL 650A WAS DROPED FROM A HEIGHT OF 9 METERS SO THAT IT IMPACTED THE TARGET ON THE END THAT CONTAINS THE SOURCE LOCKING ASSEMBLY. THIS ASSEMBLY l IS PROTECTED BY A SHIPPING COVER DURING TRANSPORT SO THE SHIPPING COVER WAS IN k PLACE FOR THIS TEST. THE CENTER OF GRAVITY OF THE 550A'WAS APROX 1 INCH TO THE. I SIDE OF THE POINT OF IMPACT. ANOTHER TARGET CONSISTING OF THE UPPER END OF A SOLID STEEL BAR 150mm IN DIA AND 2P0mm LONG WAS PLACED ON THE STEEL PLATE OF THE PREVIOUS TARGET. THE GBOA WAS DROPPED FROM A HEIGHT OF 1 METER SO THAT IT IMPACTED THE TARGET ON THE BOTTOM OF THE LOCKINS ASSY.THE CENTER OF GRAVITY OF THE EBOA WAS 6 INCHES TO THE SIDE OF THE POINT OF IMPACT. RESULTS: THE 9 METER DROP DN THE SOURCE LOCK ASSEMBLY END OF THE 660A CAUSED SOME DEFORMATION OF THE CORNER OF THE OUTSIDE SHELL AND MINOR BENDING OF THE END PLATE. THE SCREWS HOLDING THE LOCK BODY CASTING WERE SHEARED OFF AND THE CASTING WITH THE LOCK WAS SEPARATED FROM THE PROJECTOR. THIS DOES NOT RELEASE i THE SOURCE AS IT TAKES A ROTATING OF THE SELECTOR RING AND MOVING OF THE LOCK SLIDE TO RELEASE THE SOURCE. THE 1 METER DROP DNTO THE SELECTOR RING / LOCK SLIDE ASSEMGLY CAUSE0 NO DAMAGE. l THE DUMMEY SOURCE, INSTALLED BEFORE THIS TEST, REMAINED IN THE STORED AND. 1 LOCKED POSITION. AFTER REMOVAL OF THE END PLATES IT WAS DISCOVERED THAT THE URANIUM SHIELD HAD MOVED TOWARD THE LOCK ASSEMBLY END OF THE FROJECTOR AND CRUSHED THE END OF THE-.! "S" TUBE. THE GGOA WAS REASSEMBLED AND A RADIATION PROFILE MADE. f-THE RESULTS OF'THIS FROFILE SHOWED A MAX. OF 1.7 mr AT I METER FROM ANY SURFACE OF THE PROJECTOR. IT IS CONCLUDED THAT THE MODEL 660A DEVICE MEETS THE REQUIREMENTS OF THE SPECIFICATIONS IN ANSI N432 SEC. 8.4 ISO 3999 SEC. 6.7 AND 10CFR 71.73 (b) j WITH NO LOSS OF STRUCTUAL INTEGERITY OR SHIELDING EFFICIENCY. -W2O ~

~ Amersham Corporation 40 North Avenue ~, SOURCE CHANGER INSPECTION REPORT- - Burlington, Massachusetts 01803 I I cI 2-( 0 7 Radionuclide 04 Seria! No.: Max. Capacity Ci Model No.: SHIELDING EFFICIENCY TEST INCOMING SHIELD ASSEMBLY s Source Model No.: Source Seria! No.: Activity Ci Survey Instrument: Serial No.: Date Cal. _ . Due SHIELD IDENTIFICATION NUMBER MASS OF SHIELD OBSERVED INTENSITY mR/hr ADJUSTED INTENSITY mR/hr ~ AT W*^" AT $URFACE l CORR SURFACE - A TOP TOP RIGHT -

1. Ac RIGHT.

FRONT FRONT LEFT! LEFT { REAR REAR BOTTOM BOTTOM. i 'M N b h Date inspector's Signature SHIELDING EFFICIENCY TEST'- FINAL DEVIC.E: ASSEMBLY w h S a t. Laid sait xn. :_y - Source M5jreudg" =n -Source Seria! Nor % 6 N. . Gag

• y _

C Ci - Activity ~ f' I 7' SurveyInhtrument: 5YEEINR Serial No. M Ot DateCal. '

• 91~

D'ue l OBSERVED INTENSITY mR/hr ADJUSTED INTENSITY mR/hr .eace icW#F SE 0## maneos er! -Act TOP (( [ ,(- TOP L[c l {. (( / ,i RIGHT YO j IN f .i FAc' eda" RIGHT .Q .[ ,6: gI }A [ ,7 FRONT. g. '[ lgCg FRONT ,So ! 1.W / S LEFT h [ , ~/ LEFT REAR q e, l j.Q [ l.1 REAR '( Q _ L/- [; 7: BOTTOM L[g j g33 [ ,5 BOTTOM [g / ,j: Inspector's Signature h 0 Date ~ h *I ~ FINAL DEVICE INSPECTION. INITIALS . INITIALS ' Guide Tube Connection Functions Properly Proper identification Lock Functions Property Painted Surfaces Not Damaged ~ Selector Ring Functions Properly Fasteners installed Properly. Control Unit Connects Properly Proper Continuity "E" Machines Only. Source Travels Properly Total Mass of Device Source Stores Property Lock Assembly Gage Proper Labels Attached Tag No.: Date insp. Inspector's Signature Shipped To: Date Shipped Address: Sales Order No. 2-20

O TEST REPORT ( 660LDROP ) AMERSHAM TO: DAVE DUNCANSON FROM: GEORGE PARSONS DATE: 07-03-92

SUBJECT:

DROP TEST OF 660 WITH LEAD ADDED ........................................................L.....................m THE ACCIDENTAL DROP TEST DESCRIBED IN ANSI N432 SECTION B.4,. ISO 3999 l SECTION 6.7 AND 10CFR 71.73 (b ) WAS PERFORMED ON A MODEL 660 PROJECTOR SN 608-THE 650 HAD 2.5 LBS OF LEAD ADDED TO REDUCE THE SURFACE RADITION TO BELOW 200 mR/h AND WAS REPOTTED INTO A STAINLESS STEEL SHELL (SEE ATTACHED PHOTOGRAPHS). DESCRIPTION A TARGET CONSISTING OF,A STEEL PLATE ON'THE UPPER SURFACE OF A BLOCK OF CONCRETE AS DESCRIBED IW SECTION 8.4.2 0F THE SPECIFICATION WAS PREPARED. THE MODEL 660 WAS DROPEl, FROM A HEIGHT OF 9 METERS SO THAT IT IMPACTED THE TARGET ON THE END THAT CONTAINS THE SOURCE' LOCKING ASSEMBLY. THIS ASSEMBLY IS PROTECTED BY A SHIPPING COVER DURING TRANSPORT SO THE SHIPPING COVER WAS IN PLACE FOR THIS TEST. THE CENTER OF GRAVITY OF THE 660 WAS APROX 1 INCH TO THE ] SIDE OF THE POINT OF IMPACT. \\ A SECOND 9 METER OROP IMPACTED THE 660 ON THE CORNER OF THE END PLATE BELOW THE LOCKING ASSEMBLY. ANOTHER TARGET CONSISTIN6 0F THE UPPER END OF A SOLID STEEL BAR 150mm IN DIA AND 200mm LONS WAS PLACED ON THE STEEL PLATE OF THE PREVIOUS TARGET. THE 660 WAS DROPPED FROM A HEIGHT OF 1 METER SO THAT IT IMPACTED THE TARGET ON THE BOTTOM OF THE LOCKING ASSY.THE CENTER OF 6RAVITY OF THE 660 WAS 6 INCHES TO THE SIDE OF THE POINT OF IMPACT. A SECOND 1 METER DROP IMPACTED THE ESO AT THE CENTER OF GRAVITY ON THE BASE OF THE SHELL. 1 RESULTS: THE 9 METER DROP DN THE SOURCE LOCK ASSEMBLY END OF THE 660 PUSHED THE LOCK ASSEMBLY AND THE END PLATE IN APROX. 1/4 INCH.'LATER EXAMINATION SHOWED NO MOVEMENT OF THE URANIUM SHIELO BUT A CRUSHING OF THE END OF THE *S*: TUBE. THE SECOND 9 METER DROP CAUSED THE BOTTOM CORNER OF_THE END PLATE AND THIS SAME END OF THE SHELL TO DEFORM INWARD. THE 2 FLAT HEAD SCREWS THAT HOLD THE HANDLE ON THIS END STRIPPED OUT OF THE HANDLE AND CAME LOOSE. THE HANDLE WAS STILL ' 'l HELD BY THE FLANGE OF THE END PLATE AND FULLY FUNCTIONAL. THE 1 METER DROP ONTO THE SELECTOR RINS/ LOCK SLIDE ASSEMBLY CAUSED NO DAMAGE. THE DUMMEY SOURCE INSTALLED BEFORE THIS TESTi REMAINED IN THE STORED AND-LOCKED POSITION. THE SECOND 1 METER OROP ONTO THE BASE OF THE 660 CAUSED ONLY MINOR DENTING OF THE SHELL BASE. THE 660 WAS REASSEMBLED WITH A NEW REAR PLATE ASM. AND A RADIATION PROFILE MADE. THE RESULTS OF THIS PROFILE IS INCLUDED WITH THIS REPORT. 2-22 j

O NOTE: THE FOUR PROJECTIONS THAT ACT AS FEET FOR THIS DEVICE-WERE GROUND OFF BEFORE THIS TEST TO SHOW THAT THE SHELL DOES NOT SUFFER ANY LOSS OF STRENGTH IF THE FEET ARE WORN OFF IN USE. THE SHELL REMAINED IN TACT DURING ALL THE DROP TESTING. IT IS CONCLUDED THAT THE MODEL 660 DEVICE MEETS THE REQUIREMENTS OF THE SPECIFICATIONS IN ANSI N432 SEC. B.4, 150- 3999 SEC. S.7 AND.10CFR 71.73 (b ) WITH NO LOSS OF STRUCTUAL INTEGERITY OR SHIELDING EFFICIENCY. s v l g-ffc . - -.

• 2 1

.- ~ ~ ~ ~ ~ l 'o 1 l O l l-2-23 L

e m ien wo.. vv. r. -~. RADIOGRAPHIC EXPOSURE DEVICE AND SOURCE CHANGER INSPECTION REPORT Burlingto, assachusetts 01803 GOI 1r N Ma x. ca pacity 14 0 C. 660 Seriaino.: Radionuclide Model No.: SHIELDING EFFICIENCY TEST INCOMING SHIELD ASSEMBLY V 914~9 Source Serial No.: Activity Ci Source Model No.: N*Il-9 2-Due 7-17~ 97-Survey Instrument:PIB GB7"I R SerialNo.: 1-80 Date Cal. SHIELD IDENTIFICATIDN NUMBER MASS OF SHIELD ADJUSTED INTENSITY mR/hr OBSERVED INTENSITY mR/hr AT s 2,JN AC l CT[Jc4.L my o" sunract survact 7 TOP l4 TOP l coEchMu encioa RIGHT RIGHT

gg FRONT FRONT l

g,g3 f l,3 LEFT LEFT REAR f,gg REAR s BOTTOu BOTTOu f,,9 Date inspector's Signature SHIELDING EFFICIENCY TEST FINAL DEVICE ASSEMBLY g1 U C. e300 3c,;,3,7 Source Model No.: 924 d - Source Serial No; Survey Instrument:PDR N 7R Serial No. I-lM Date Cal. 4-11-% Due 7'll-D ' f) ADJUSTED INTENSITY mR/hr V OBSERVED INTENSITY mR/hr

• ""#^ "

MI M ERs E r" i E su rAct r TOP HO I i6 \\ J TOP ia j \\ ,g c go j,;73 \\ ,5 cT.a#4' " RiGwT g ojg \\ g rig HT FRONT jgy \\ jg FRONT gQ l g,,3 \\ ,6 ./ j7) LEFT lqj \\* g LEFT 60 l 1.28 \\ REAR ,3Q { g,;3 k [ REAR qq k g f BOTTOM Ql /, gg \\ ,6 BOTTOM l rg \\ l,g M Date b inspector's Signature FINAL DEVICE INSPECTION INITIALS INITIALS Guide Tube Connection Functions Properly Proper identificateon Painted Surfaces Not Damaged Lock Functions Property fasteners installed Properly Selector Ring Functions Properly Control Unit Connects Properly Proper Continuity "E" Mactanes Only Total Mass of Device Source Travels Properly Lock Assembly Gage Source Stores Properly O Proper Labels Attached Tag No.: Date insp. 'V hyg g g [g Inspector's Signature [ F 76O OPOPIFST)) Date Shipped Shipped To: 2"N Sales Order No. Address:

.,s,

.a. nw a -- - - - ~ %JM...., l l:gCHA :, wh 'g %;n :Qv. # s - i I h$kS:gg.R',, iW q$al64}$p.. M ' l %9 y w.u ~ )Aff '$+;

2. l

~ k. 4 ,,j a n ?, %w ny' \\ ,n n. h-qn-Q 'K,j,fP:- I ~ YL kd i un 3;.$h?gw? i C l w g' l nt:y

,' k;;-

l . ~ s r 3 1 7x i gwwR. ._ l@ C :+ s, 1 p h - ?, I M a i e i i O ,4 ) 2,. e.. h ,'ff l 4 e l i n. -* 'n -J[ +._h ee a;, t. e j 3:/g&h;.t$f%75',ck ' ^.' n lq% ' .~ ?#g ti i } .j ~s s r ./

g. ivm

- uwegv'3 l L $kr, "l.ht$7TV e?% s ;;yg~%y:y.Wh, e ,,... r;,;;> y; 'h [%" . '$ f, k Y /h Mkh k J . w 1

in j

< 4QSg) ., fly f'* l c. m ta w? e d %s ii J URANIUM SHIELD FIGURE 1 & 2-2-25 l SN. - 608 !" LEAD ADDED TOP'& BOT.

{. I l O I i [ k ~ ',, i I g., q. : 7.....,- _.: g l _. CRANE USED TO LIFT DEVICE FOR 9 METER _ DROP TEST FIG. 5 i 4 l "ON l aa. l ~ l s ^ 4 ~ j 1 ) . -hY ~ l l i O l i i E N m-DEVICE AFTER TWO 9 METER DROP TESTS,_j ~ l FIG. 6

-a san-4 - --- - -~~--w-s g s ,se- .a, ---.m..,m-er .a ,a s d. + b \\

• j'-

{ %2rg: ? i \\ ~ t DEVICE BOUNCE AFT 7gg 1 ,;-.a-

ia. sy g"ge,,,.. --

ha. FM,~t% pe g \\ -tr. I \\ w% \\ a t \\ WS.' 4 i i 4 1 ~ - . s.,

• ..g.

.\\ gawm ,4 ~ n 6' :,g,..amg;"; ,=, V 1_ c lJ n i ,y .s + 2.-27 .-. a t

l L l ~~I, 1 - s l - e _. i p-l ii_ m i ~ d[. 1 -~ l -4 3 I l j _ ' ~ {k;... x +: i n s w s -na --="+ + +i ~- .n..... ~~ SECOND 1 METER DROP ik# FIG. 9 E' 1 l

• • '% w
• /

s 5..,., ,;[,, p;' (h *. y n x l ... ? lO y m. Y g,. iCh c Qt ...= ~ 7 22 e, .e-, Jn bG ?,,% :.;;.)c,' SECOND 1 METER DROP l

n / ,e l p.. O -o+ 1 j-1 / / / / N] g, YBL), r,, vet > j i, e l / l .~,; x 't %}; I ti. x i l j ' O / / l l i ' /h j / / 1 lVC %ts, Rg @ge.,,, ; [ Yg '/ YRg / ':c. / 4 s). ? St + l l / 4 o %:9r. l ' l 't j ^-' 4 4 % s,'e i e29 i i l .s 'N \\ NNx x'N '~'s 'N +, 4

• N w

ha

i at.. .;s s I l 1 1lO ~ i 1.* g p, 4 hYi !g l i l g, l P.'. i ~ l I l s a 4 .: ~ l l ~ d -t 1 ) -a .h,N 8 I SHIELD FOAM REMOVED M l &~,u.. FIG. 13

awc, e-:.x,

., 34# 4 d$g': t, .M h " ;gedip:.7 y ,.t., a L.f, j. M Ih hkk 5 l }%.j?$$$y" ~ . 4[;;%Migli 1% .~R W' X l .,ig}jy" d' y, f .g gt+- / ,./ G,, j .ge. 4. ~ l g,, ) -c. 3%%..-Q i q 37 4,, sg

w.. : v s -

...;Si$ ); y!flhf. .+. ~ M Q<. 1%YS$YY f[ l

p.sv g., '.

.t N, d *',., - . jt l t. 'w,. 9 n l;h. .wn s 2-3o SHIELD FOAM REMOVED FIG. 14

I kdli..N Ol N..k ll )l( R)lb. !M, I l( 'l'.J' lh.'l l I N E lll) If~ j fJoeticei C nee: 29 Cl.n. olo n n o..I. t. J i**TO li'Thr nr OW /.0331 - * ' ~ - - -

---

.s 4

c. s y hw b. s ' ?...h v r1.p v. <..m.L t,' c 'o - - -.. - - -.4 - - -- - --~~ ~ ~ - - - - - /V R ' /4 f.0 imPil - - - - - - - - ^ ~ ~ - - - - ~ ....w. ....... -. - ~ ~. - - - - - - - - - - ~ ~ ~ - - - - -

Subject:

Dinmantling 'of dama,ged cource container Address visited: Technical Opera tions Limited. I Princeuay. Team Valley Industrial Estate, Ga te:; head, Co. Durham. Date of visit: l'ay 13th, 1974 Date of report: 11ay 17th,1971: Previous relevant report: g. NHPD/VR 3/422 _In t roduc tion Inic visit followed the damage of a remote exposure container Type 369 in a van fire. _ General conclusions Tne shielding afforded by the container had been maintained and the cource had ~ not been damaged. Measu rer.en ts Several do' e rate near,urements were made close to the outside surface of the s container before any atterpt was made to dice.antle it, and the sna.xieum dose rate i measured was 5 mrem /h. Several wipes. were made of the centrol cable connecting mechanisp and inside the cuide tube durinr. the dismantling procedure. The activity .was less than 0.1 nanocurier, on each' of thene vipes. Dyr.c ri pti on IL. Gilligan of Tech-ical Operaticns Lir.:i ted protec< led to transfc r the 10.6 curie iridium-102 cource to a transport cont ainer cuitable for retur., to the suppliers. f; Uo dif ficulty was experier.:ci in connec tir.g the crnt rol c.,ble but bec mse of V l. congealci crease in the gu rie tube neveral atte pis acre necessary befere trans fer I was achieved. Tnic opera t icn was conduc t ed rer.otel ui t:- the ceurce container in a CocpOU..3. 2-31 Cont'd........

.N D s. v 'ihr rose l.ruc t : :i o f t h" r.<gu i p i."n t i: ;nch t h: 1 lb. <hilcted_ur: inta rhie) ding i i r. r.u rr ounded 1.y. r.har L ::b..arh< n t nr.:s t e ri al call ed s..;;-re-J oaia whi c h occuj.i cs the npace l'etue( n l' < u ran i ur and thr-ni e e 1 ou ter ra:.i nr,. ifhrn.the cont: iner was c [- dis:nanthd i t ca:: r ev<;nir d th it t h i r, f en:,i had trelied t,n one rii rh tr, within np}:rexi. j rr.a te] y } :.. c f t hr. leple t ed uranium. Further investig;:stion f ruGcated no. oiscernible da nage to the ut aniuna r.hi cJ di r.g. T.ic centrol cable conn <:cting mechani:-n uns diser.intled on ! it uor cicar that tuo sprint;; in the lo i had j eri:.:hed in the fire. lice.: eve r, the racchar ir ra had - failed safe.nd the container could not lie opened wi thout the al propriate key and ccnnection of the control cab 1c. The handle of the container had p irtially rnelled and dir.torted but war; still l c,ubstantin11y intnet. I t i t; understom1 that the handle b rnade f ro:n Ten:. alloy j ubich is nl.parently _an alun.iniurn - cof.per (or bracu) alloy uith a rr.elting point or j 1220 T. l .1. K. Overend- ? I e /"( p 4 l O e e b 9 e i 1' I i 2-32 ~

l o 1 EST lill' ORT DESCRIP1 ION: DAYE November 2.i. 1969 Gamma llay Projector Model GGO 1) top Test 1. I'ree 1) rop: A. The projector, containing a shiininy source. w s dropped from a height of 30 feet onto flat horivoutal, essentially unyichling. target surfarn. It landed on the upper portion of the front end plate, driving j the hamile backward and distorting the rear end plate. II. ()n the second drop, again f rom a height of 30 feet,' the projector landed on the selector lever and lock retainer assembly, which was tlamaged. The dummy source was retained in the stored position and could not be 3 removed without disassembling the unit. 2. Puncture Test: CUfREU5 F04: A. The projector was droppeil l' rom a height of 10 inches onto a G inch r:ulius mihl sicel bar, 10 inches in length. The projector landed on the di side of the shield housing assembly, which is the position in which the maximum damage would occur. 1 1 U. The dummy sm.rce stayed in the stored position and there was no apparent damage to the uranium shiehl. 1 1 i l N ) l BY uur A-

07) ? i._

WITHESSED BY,/ - Nws</ l Th l l 6 2-53

l + i Y, '.':. ft If ... F 1 ~,.h,.f e'h,k,,, s l ~ Q,t,T.f[?*'Q?@!QWD 'O Q'?.? W W' $ '**).Q.4;. 4,Q -

• H'

. n. 'f r..,[.

• l,,.'::#,.

j'.' %* n <.,'.,

.9i

,.. i.. s y. , jeg ll'. '. J.,, -*l* f*'.,. ' i' '%y a ~4 .l ^'j 'h l ' dk {h *. f,.1 e -.( ?

L- -

. y.. *{- e. . ? ' ', ',. y ^ %,, ,*n.. ,1 p ; ) *,' f .L A ,( ~ I ' '. ~ ' fl l. y f,, ' ) ?..s 7',,*., }. D v. ,/

. b.

_ u.,f.. r- . j.., s ' f.

'. ),,

,e -. ', r* y . j,* _ ;. ; 4y 4 hf 'I' e' 4 i ( .C M.Mt. kji ~ u, - J mun S/ a y'.,, s.W; 3 . 6~ a =,. h i c ', M, yh kt i j '- 4..,'-.'.. p 1 4 y9 Ii k7;, ,y y L d;> q i: h' ,. / W ?' .h W jj('giq' 3 MJh :.h,y.g,M ' ' . n j[.. . /8 4 l .,' i ' o . '( ' /,$ .i ' '.I, '.', .~

O % t

.,.,,.u..,, . }l r c-f . [,., l T. p,. i & s. ..L,. pl '. = [7, [ ' '.,I " *,. J kI f ). t x; if [.f.;;J.} & Q y n L l .,.,. ;,. 8. ' ( f, *, / p A' +. s 4 f *p ' '. ;,U a.$'* .. -. s.. ~ .Yd.. i 7,1 J [ ' (.,I," .e,,,, ' f .[ n - (8l p, ~i '6 s 1, -.i t;, ...s q.. y ..: 3-f~. >p: (; .3 l .'t .~ .,s 'A, ./ ',, ',.-}'.,. I ,i

• =* * *,

,. d. ... A. '. 6 4 i,... '. 's{'- l,...}. ' ..? [<. t - -.y ,....:.,a - 6 ,/ ' ~. '..,..,,, ' j - g c ;.,,, .. f.. *,,, - % i... ) g w l.x-9 e* ' *

s.

• 8.

} -[

• ,S' 4.t, ' t, f.

',,,,.,..r, e ,9 \\ I.. - / g p. ,g)4 W,.( )., l

• ,,
• n e-r

+ 4>- .m' . h.,,.., ;s... y.1 - f :i*.

s

, (p,,,4.;.,. e -es v

. p p...

7,' .s 3. Qt y, \\. -. 's.

s..

.,N',,,**h4;,.,;g.gl) s ;. ,, J.. '

* ** -

• f '

'.,' 1 l.. .'t '. j \\ '. l* [ 's '...'e. s' =....,'; N d.;f ; ;.l,::).f p ;,, j. - - ~

a. a

(.- ,+,4 4 7. = ',. h... * .t.

• ,,q,,

' >,q....,*e ., g., _+' . ' +, '3..~...>. . '...p.M < /,,. ...,,' " ( e : ';. y i. NE 76,,.'. 6 }.[,V([,

l;J.

.f 1..

• ~

2.,..'. M.y, %,n.; ly:.(;.. + pde.. j (.c. _ y

• 4 e.A;.

,...:. p.s ..; d

.. J,,

e ...., -. r, e ,,.. 7....,.3 y r s g' f.. e., d

• O

. p.., :...': ?, f ;. 9,.. w [ 3;. ;..-v :, <W :.; ;:. g 3,' }' w-- .-.,a w-, ..---..-.--,---.--,.,.-,,-+w.. n, -. --.-r-

I r .=- ,e l 3 ~ 4 jgij' ;,i.[} e.- ' ' g - '4, i,y; t: e, !r T. N'!" ~ Y. ' {hD!. :. ! in { gi;j (, lj s I ,k. ,4 . i j.., j' 'y ) ,\\. . j .4 I ,,. '... 'if L- ";' y l \\ ..' f y]

f l

.c sp-y q;:., M f. ',' - 3.) l ~ S - - Q,i " "; ~, 8 yj,y 3:,.; '[ U- { l 5%, s a ,~ E., . >; =-

1. 8 e

e' E 4* M MYiW

l l O!c.A6= U;vj[$.f 6 lf{}.5fl

• f}h; if$@N@

e {f,ll j g 1 j':.:!gt f hjNt'ff i gt.u.g> 1 l i l i j %~ \\ m n i lo [ f . :, T!,'l- :3;h'i;. \\ t -r-l 3 hl50 hk F. I i i y W~ .J mg J ll 4 M'. e l ggig-SERE Bifjt f l 33,4!L1j. !g I ---c s l WWYL. i 2-Sco ~

a. .a. e a .a .m-aea .so. w e ..a--s k 1 b. 9 ^ ' ' t."r.,t 4 T@c.;,gsi, sw.. ?.' 'g. e .n a y g >p Vj,,'&,,$ n y

.gp3g,., g.p;..,

p 6 7, h., 7- - 'n qs. }g *&.,, i.,.. r r!t e k & t+@k, y _ QR i wh a. s W.@:A l ?$j{gs hk$h;p$$: kb.Wk h k!?? ' yA.. 4 = 7 i c5 f W + ,a). ;. .;4:yff.

_9,

y.n_9_g.,:. g

.p I h .yf.; ' w ;:. g.. .y wz b g ~ m ' s., '. ar.

..,f..,

,, 3 9. y c.. r g- : +. ~~ n : + :. - t

c. ? p q u

?E&iQ 'q.%;) yllb.e,;.[f \\ ..n. k' \\ 9W.%,r}. , q. g g 7f p;.y.. .:#p$j&p 4Wgap9 i l48;f sf.f; l;:

)j -

@sa...

%%.Vl@v%;

i'! 4 . m u.;, y c ,Y< Rr fl .'4 ?.h "i .? ffY i f:*vtg %f. .?ES.%.%,.,. c$,,.. p. - s a. .,.x g

• ~

3 p' F gnq.q:- ~* n-t.;,R;0.x.:.y v _ }'r ,y 'J, ar

r..

, v,, k. 1 t '. r n

• ..gle,..

Nt O. -

w ~ ... * ; I* a.. __ - ~ni ' L A.cf *. me's 1 4 -c, ,...,,,,,_,-.e. .,..m. .-,,-...-..m..

REPORT AMERSHAM TO: Bill McDaniel FROM: Dave Duncanson DATE: July 16, 1992

SUBJECT:

Leading of Type B Transport Devices Following the inspection by the Transportation Branch of the NRC on 6--8-92 thru 6-11-92, an investigation was started to answr.r the question what.effect does the adding of Supplemental Shielding have on the. Safety Transport & Radiography Devices? (This question was triggeced by the practice of attaching Lead Sheets to the DU Shields. In cases where the initial profile results indicated that the surface dose would exceed 200 mR/hr, but would not exceed the limit of 1R/hrelm after accidental condit.'.ons such as 9m Drop, Fire Test) the first step in this investigation was to determine if there was any reaction between DU & Lead as a function of time (thne frame being the life of the project approx. 15 yrs). We disassembled two 660 projects t (1) S/N 608 Manufacture 10-16-74 (2) S/N 607 Manufacture 10-16-74 Both Projectors had additional Lead Shielding added to them (see Photo #1). The lead is held in place with fiberglass tape for assembly and further supported by the Rigid Urethane Foam. Photo 2 shows the Hot Top of the DU Shield. The. green area is the paint which is applied to the Shield during its Manufacturing. The areas void of paint are where the DU & Lead were in contact'. Photo 3 is Close up of the DU Shield which still shows the machining marks from the cut off saw when it was manufactured over 16 years ago. This clearly 1 demonstrates that there has been no loss of DU Shielding due to placement of Lead on the DU Shield. Photo 4 is a close up of the Lead which was in contact with the DU. The impression of. the "U" is snowing that we are examining the Lead in the same place as on the DU.' It also shows the impressions of the tool marks on the DU. It should be noted that there has been no corrosion or substantial oxidation of either the Lead or the DU. Photo 5 shows both the Lead & DU surfaces which were in contact. Regarding any questions of an eutectic reaction during-a' fire such ~ as an alloy of DU & Steel under laboratory conditions. There is no eutectic alloy of Lead & DU. Lead with a melting point of 327' C would have melted away from the DU well before even the first ALPHA phase change of the DU 0 688' C The second step was to determine if the Leading of the Shield. would mechanically affect the results of the 9 meter Drop Test or other ANSI N432 impact type tests. To that end we conducted the ANSI Test (see Test Report 1 ). [V) Page 1 of 2 j MEMO. REP ?_ - 3 8 - 4

AMERSHAM REPORT f)\\ L u Leading of Type B Transport Devices (Cont'd) Following these tests the Projector was disassembled which showed that the Lead had not been displaced or that the practice of Lead had any adverse effect on the results of these tests. We have also. conducted the ANSI N432 Drop Tests. f with a shield which has additional DU added (in the form of a DU Disc located on the Hot Top). This also had no adverse effect on the results of the test [see Test Report " Drop Test Report" 2-11-92 (660 Drop)). From these observations & tests we conclude that the practice of adding supplemented shielding (Lead or DU) - will not af fect.,the compliance of the Projector to the requirements of 10CFR part:71 or 10 CFR part-34. Amersham's engineering & QC Department have an ongoing Quality project to eliminate the need for adding additional Shielding to the Projector Shield. Due to process limitation of the DU supplies, this practice may need to continue in the future to meet customer needs. However, this practice in no way reduces the safety of the Projectors. f- \\ t 4 i i .I i Page 2 of 2 MEMO. REP .2-39

i O 9-I a h "?. c. 6 l e l i~ t i s i ? PHOTO We 1 ,\\o f 'y.;' _ <h af

• g.

m / s e ?*l ~ :,;. y. ~. h.m[j!h ~ i ~ i p 5 a.c,ns. - l. r:. 0 c. i;. M 1+"' l

lsh, l

5$&'4: f:; n L. l ..:.,e pe i '.':,,g*] f i e i - ~ g 84 4 5 , g' !O e scrro we 2 2-4o ~

I I l l p%

• n2FP h rA b y d..:-r.3':.v..s.:-@T;%

' +=?' ~r 9Qg.

! O

• % fe q d6 b t g y & psf l % w.; ;&

V.,,,'.. M+ Wg&-jW:.,$:. ~, ^

• ~

&rs. :' 7-f.*'. f.&s '. ' a -g; .,p yA; z'8.a ;..;. -- ' . sp". * - -<<. w /: .4 -:: a ve ~~ <-..f.. w.-. '~'%s 1 ;8' V ' ^ - ~ : : .1^ kNKQ,, g,m..nn..:: y/ ww: :.. ~. .u y y .1- ^ ' 1 Qfh ,b d .4 ~ c - e : a ','i,..,' " ,??.'. f ' $,h,y 5 A -P-#.;flM'e,.1 ~- h -Q* [ 'f% .. -J .. ;+: s: ij.; O ' - 'i M ..;.a ; ; . :.. w - ,.::t. y:2 .w-;h p s.y F1

c..

.ichYM*hfN'.?'..~ ,',^,,;~.'....*I $'Y ~ l .~ ^. '.. '. ' :;- * '; ~' ' .C... w 5 4 ?+ft ?( ? ? ^^ i ... v'. - - -, e ..... e. e : ;, v,s e.O, >.n:r..w/3ns. : he, f. *, '. t && ' "s t ' '. 'I-- s d' g**" 'e ,f.Q.,.: A,y'Q'y. G,yd. ?~e :'. '}. -l.. < '::. '.- *.,;; #*.' }r s. y: - e ~ i .'. f o^ **., * *. ' 'e.,e,..., pi., * =. ~

• Q, g.'.
• }.a. k ', ', r. * * ' -

a a o l PHcrTo Ne 3 i i !O i J - PD JS i (Le j '/^.* } 1; i.-p e - s #^?: - - +.(p. s 3 ., ;. r .s e

v. <.:. -

4 i (tr 1 4 ,t 1 l YO e F e r PHOTO N 4 Q A 2-4L d

\\O 1 u [. - 1 ~ '~ .g \\ \\ ~ i \\ . fd,hk, [45g:pj Rg,,, %* web ~ )j g ' ~.q \\r y-t 1 \\ \\ p, i photo bJe 5 O 1 4 i I i lo i l 2-41 -.p., _..,._m. ,.,,_,,-,.,,,,.,,,___.%,,,,...,_...,_._._._.,,_..._,_._....._______._._y._ .,w., e.

? 3. Thermal Evaluation 3.1 Discussion The Model 660 Series 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 maximum heat source is 140 curies of Iridium-192. The corresponding decay heat: 6 generation rate is approximately 1.2 watts. 3.2 Summary of Thermal Properties of Materials .f:; The materials used in the construction of the Model 660.Geries. l includes: g Tungsten Melting Point 6098'F b370*C), l Depleted Uranium Melting Point 2071*F (1113 *C) Steel Melting' Point 2453*F (1345'C) Titanium Melting Point 3308*F (1820*C) Lead Melting Point 621*F (327'C) Zircalloy Melting Point 3353*F. (1845T) f I The rigid polyurethane' foam in this devicelhas an operating. temperature range of -45'F to 220*F (-43*C_to 104*C). 3.3 Technical Specifications of Components Tj ~ Not applicable. t 3.4 Thermal Evaluation for Normal Conditions 'of Transnort: (} 3.4.1 Thermal Model The heat source in'the Amersham Model 660 Series <is a maximum of 140 curies of Iridium-192. Iridium-192. decays with a' l total energy liberation of 1.45 Mev-per-disintegration or 8.6 l milliwatts per curie. Assuming all the decay energy is-transformed into heat, the heat generation rate ~for the 140-curies of Iridium-192 would be approximately.1.20 watt. l To demonstrate compliance with the requirements of 10 CFRc

71. 43 (g) and paragraph 548 of IAEA Safety. Series No. 6,.1985 i'

Edition (as amended) a separate analysis is presented in-Section 3.6. The thermal model employed is described.in that analysis. j To demonstrate compliance with the requirements of paragraph 543 of IAEA Safety Series No. 6, 1985 Edition (as amended) l for Type B(U) packaging, a separate analysis is presented in j Section 3.6. The thermal model employed is described.in that analysis.

l

\\ 3.4.2 Maximum Temperatures { i The maximum temperatures encountered under normal conditions of transport will have no adverse effect on the structural i integrity or shielding efficiency of the package. As ~! presented in Section 3.6, the maximum temperature'in the. shade would not exceed 108'F (42*C) and the maximum 'l temperature when insolated would not ' exceed 154*F. (68*C). ] . ~\\ .3-1 -REV. 0 August 12., 1993' 1 .j l o -,-

6 3.4.3 Minimum Temperatures j O i The minimum normal operating temperature of the Model 660 Series is -40*F (-4 0*C). This temperature will have no adverse effect on the structural integrity or shielding efficiency of the package. 3.4.4 Maximum Internal Pressures Normal operating conditions will generate negligible internal' pressures. Any pressure generated is significantly below that which would be generated during the hypothetical accident thermal condition, which is shown to result in no reduction in structural integrity or shielding' efficiency. 3.4.5 Maximum Thermal Stress The maximum temperatures which will occur'during normal transport are sufficiently low'to. assure that thermal gradients will cause no significant thermal stresses. 3.4.6 Evaluation of Packace Performance for Normal Conditions of Transport. I The normal transport thermal condition will have no; adverse effect on the structural integrity or shielding efficiency of' the package. The applicable conditions of IAEA Safety Series No. 6 for Type B(U) packages are shown to be satisfied'by.the Model 660 Series. 1 3.5 Hypothetical Accident Thermal Evaluation 3.5.1 Thermal Model The Model 660 Series, including the source assembly, is assumed to reach the fire test temperature cf 1475'F (802*C). l At this temperature the polyurethane potting conpound will have. decomposed and the resulting gases will have' escaped the package through the assemblycjoints which are not leak-tight. During a. hypothetical fire test,'the supplemental lead shielding would' melt and affect the shielding integrity. The maximum thickness of lead that may be installed in a device is limited to 0.25 inch. Using the calculational model below. the increase in surface radiation levels and at one' meter could increase to 667 mR/hr at.the surface and'30 mR/hr at j one meter for 240 curies of IR-192. This is below the i allowable 1 R/hr at one meter after an accident condition as' i described in 10 CFR Part 71.51(2). maximum allowable at surface = 200 mR/hr = I, l ~ for final accepted package j i maximum allowable at one meter .= 10 mR/hr =I r for final accepted package l transmission factor for.0.25 lead ='O.3- = Tr - from Amersham Radiation Safety '. j Handbook I, = Intensity shielded ' ] 3-2

REV.

0-August 12, 1993' ) i i

i i i I, = Intensity unshielded () T, = transmission f actor maximum radiation reading if all lead was removed, I, = I = 200 mR/hr = 667 mR/hr at surface r Tr 0.3 and 10 mR/hr = 30 mR/hr at one meter 0.3 3.5.2 Packace Conditions and Environment The prototype Model 660 Series package which was subjected to i the free drop test and puncture test, suffered minor structural deformation during these mechanical tests, but suf fered no reduction in structural iritegrity or shielding efficiency. 3.5.3 Packace Temperatures As indicated in Section 3.5.1 the entire package is assumed i to reach a temperature of 1475'F (802*C). Examination of the melting temperatures of the materials used in construction of i the Amersham Model 660 Series, indicates 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 2.4.4 where it was concluded that the formation of the alloy was not a likely possibility. There was no indication of any melting or alloy formation as a result of this thermal test. j 3.5.4 Maximum Internal Pressures In Section 3.6.3, an analysis of the source capsule, which serves as the primary containment, under the thermal test conditions is presented. This analysis demonstrates that the } maximum internal gas pressure at 14759P (802*C) would be 54 psi (372 kN/m8). The critical location for failure is the source capsule weld. The analysis shows that an internal pressure of 54 psi j (372kN/m8 ) would generate a maximum stress of 368 psi (2. 54MN/m8 ). At 150A** (870*C) the yield strength of stainless steel is 10,000 PSI (69 MN/m8). Therefore, if the source capsule were to reach a temperature of 14759? (802*C), the maximum stress in the capsule would be l only 4 percent of the yield strength of the material. i 3.5.5 Maximum Thermal Stresses 1 There were no significant thermal stresses generated during the thermal test. 3.5.6 Evaluation of Package Performance for Hypothetical Accident Thermal Conditions The Model 660 Series 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. -O f 3-3 REV. O August 12, 1993 i r 9

---

,,-..,x,..,

.m_.,,,,..,_m- _%,r_,w..m. ,.w_.m__

. ~. - I l i t 1 3.6 Apper. dix i 3.6.1 Model 660 Series Tvoe B(U) Thermal Analysis: 10 CFR 71.43 f (q) and paragraph 548 of IAEA Safety Series No. 6, 1985' l Edition (as amended) 3.6.2 Model 660 Series Type B(U) Thermal Analysis: Paragraph 543 of IAEA Safety Series No. 6, 1985 Edition (as amended). j 3.6.3 Iridium-192 Source Capsule Thermal Analysis l 1 i i l t l I i F l i [ I 1 i f i O b l 1 i d i 1 i l O 3-4 REV. O August 12, 1993 I l

i l' 3.6.1 Model 660 Series Type B(U) Thermal Analysis 10 CFR 71.43 (q) O and Paragraph 548 of IAEA Safety Series No. 6, 1985 Edition (as amended) This analysis demonstrates that the maximum surface temperature of the Model 660 Series will not exceed '122*F (50*C) with the package in the shade and an ambient temperature of 100 F (3 8'C). To assure conservatism,' the following assumptions are used: (a) The entire decay heat 1.2 watts is deposited in the. exterior surfaces of the package. (b). The interior of the package is perfectly insulated and heat transfer occurs only from the exterior surface to. the environment. (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. (d) The only heat transfer mechanism is free convection. Using these assumptions, the maximum wall temperature is found from I q = hA(Tw - T,) ] where q = heat deposited per unit time in the face of interest (0.30 watts) ] h = Free convection heat transfer coefficient for air 1.32 (p_T) " watt /m8*C = d i 2 A = Area of the face of interest (0.033 m) I Tw = Maximum temperature of the surface of the package Ta = Ambient Temperature (38*C) d = Height of f ace of interest. (m) 0.244 m = From this relationship, the maximum temperature of the surf ace is 106.3*F (41. 3

• C). This satisfies the requirement of 10 CFR 71.43 (g) and paragraph 548 of IAEA Safety Serial No.

6, 1985 Edition (as amended). 3.6.2 Model 660 Series Type B(U) Thermal Ant.vsis, paragraph 543 of ? IAEA Safety Series No. 6, 1985 Edition (as amended) i This analysis demonstrates that the maximum surface j temperature of the Model 660 Series will not exceed 185'F l (85*C) when the package is in an ambient temperature of 100'F (38'C) and is insolated in accordance with 10 CFR 71.71 (c) (1) and Table XII of IAEA Safety Series No. 6, 1985 Edition (as amended) The calculational model consists of taking a steady state 3-5 REV. 0 August 12, 1993 -. ~.

t i t i l heat balance over the surface of the package. In order to

(}

assure conservatism, the following assumptions are used. l (a) The package is insolated at the rate of 775 W/n/ (800 2 2 cal /cm - 12hr) on the top surface, 194 W/m (200 cal /cnd-12 hr) on the side surfaces and no insolation on the bottom surface. i (b) The decay heat load is added to the solar heat load. j (c) The package has an unpainted stainless steel surface. The solar absorptivity is assumed to be 0.9. The solar emissivity is assumed to be 0.8. (d) The package is assumed to underge.the convection from the sides and top, and undergo radiation from the sides, top and bottom. The inside faces are considered l perfectly insulated so there is no conduction into the package. The faces are considered to be sufficiently l thin so that no temperature gradients exist in the i faces. 6 I (e) The package is approximated as a rectangular solid, 5 1/4 in (13.3 cm) wide, 9 5/8 in (24.4 cm) high and 9 7/8 l i l in (2 5.1 cm) long, transported on its side.- The total 'l surface area of the top and bottom is 104 in8 (0.067 i 4 j m'). The total surface area of the sides is 291 in (0.188 m8). The maximum surface temperature is computed from a steady [ state heat balance relationship. q O

9. = 9_

i The heat load applied to the package is 9m

• 9.0 + 9d i

Where a = solar absorptivity (0.9) q6 = solar heat load (91.4 watts) 4 q6 = decay heat load (1.20 watts) l The heat dissipation is expressed as ] Qu = 9e + Q, Where qi = convective heat transfer {(hA) top + (hA) sides) (Tw - Ta) = Where h = convective heat transfer coefficient A= area of the surface of interest T= Temperature of the surface T, = Ambient Temperature (38'C) 3-6 REV. O August 12, 1993

3 l ) 3 q, = Radiative heat transfer = oE A (Tw4 - T,4 ) l I 1 Where o = Stefan Boltzmann Constant (5.669 x 10-8 W/m'*Kf) Emissivity (0.8) c = i Iteration of this relationship yields a maximum wall i temperature of 154'F (68*C) which satisfies the requirements l of paragraph 543 of the IAEA Safety Series No. 6, 1985 l Edition (as amended). The maximum wall temperature will not adversely affect the package, as it will not cause cracking or melting of.the shielding material and will not alter the semetric form or physical state of the radioactive material. 4 3.6.3 Amersham Model 660 Series Type B (U) Source Capsule Thermal 9 l Analysis Paracranh 553 of IAEA Safety Series No. 6 1985 Edition (as amended) i This analysis demonstrates that the pressure inside the source capsule used in conjunction with the Model 660 Series, when subjected to the hypothetical accident thermal j condition, does not exceed the pressure which corresponds to the minimum yield strength at the thermal test temperature. m 1 The source capsule'is fabricated from stainless steel, either Type 304 or 304L. The outside diameter of the _ capsule is 0.250 in. (6.35 mm). The source capsule is seal welded. The O-minimum weld penetration is 0.016 in (0.41 mm). Under conditions of internal pressure, the critical location for failure is this weld, t j The internal volume of the source capsule contains only Iridium metal (as a solid) and air. It is assumed at the time of loading, the entrapped air is at standard temperature and pressure 68'F and 14.7 psi (20*C and 101 kN/m2 ). This is a conservative assumption because, during the welding i process, the internal air is heated, causing some of the air mass to escape before the capsule is sealed. When the welded capsule returns to ambient temperature, the internal pressure would be somewhat reduced. Under the conditions of paragraph 553 of IAEA Safety Series No. 6, 1995 Edition (as amended) it is assumed that the capsule could reach a temperature of 1475*F (802*C). Using the ideal gas law and requiring the air to occupy a constant volume, the internal gas pressure could reach 54 psi (372 4 KN/m8). The capsule is assumed to be a thin walled cylindrical pressure vessel with the wall thickness equal to the depth of weld penetration. The maximum longitudinal stress is calculated from: o A = PA, where o = Longitudinal Stress A= Stress Area 3-7 REV. O August 12, 1993 l I

.. -= 1 P= Pressure l () A Pressure Area = p From this relationship, the maximum longitudinal stress is calculated to be 171 psi (1.18 MN/m8). The hoop stress is calculated from: t 2 o, It = Pdt j s where a n Hoop Stress i = I= Length of the Cylinder t= Thickness of the cylinder (0.41 mm or 0.016in) d = Inside diameter l l From this relationship, the hoop stress is calculated to be l 368 psi (2. 54 MN/m2 ). At a temperature of 1598'F (870*C), the yield strength of type 304 stainless steel is 10,000 PSI (6 9 MN/m8 ). Therefore, under the conditions of paragraphs 553 of IAEA Safety Series No. 6, the stress generated is less than 4 percent of the yield strength of the material. l t 6 I i [ n I i 6 i I i ? t ) i 4 i 3-8 REV.. O August 12, 1993 .. ~

l i i 4. Containment t O 4.1 Containment Boundarv 4.1.1 Containment Vessel 4 The containment system for the Model 660 Series is the radioactive source capsule referred to in Section 1.2.3 of l this application. This source capsule is certified as [ special form radioactive material under IAEA Certificate of competent Authority USA /0335/S. 4.1.2 Containment Penetrations There are no penetrations of the containment. 4.1.3 Seals and Welds i The containment is seal welded in accordance with Amersham's Standard Operating Procedure. The minimum weld penetration is 0.016 in (0.41'mm). i 4.1.4 Closure l Not applicable. l 4.2 Recuirements for Normal Conditions of Transport I 4.2.1 Containment of Radioactive Material The source capsules used in conjunction with the Model 660 i Series have satisfied the requirements for the special form radioactive material as prescribed in 10 CFR 71.77 and IAEA Safety Series No. 6, 1985 Edition (as amended). There will l ] be no release of radioactive material under the normal conditions of transport. l 4 4.2.2 Pressurization of the Containment Vessel i Pressurization of the source capsules under the conditions of i the hypothetical accident thermal was demonstrated to generate stresses well below the yield strength of the capsule material as described in Section 3.6.3. Therefore, the containment will withstand the pressure variations of normal transport. 4.2.3 Containment Criterion See Section 2.6 where in, it is shown that the containment requirements of 10 CFR Part 71.51(a) (1) are met. j 4.3 Containment Reauirements for Hvoothetical Accident Conditions I 4.3.1 Fission Gas Products 4 Not applicable. 4.3.2 Containment of Radioactive Material The hypothetical accident conditions of 10 CFR 71.73 will result in no loss of package containment. This conclusion is 4-1 REV. O August 12, 1993 ) 1 i

.. ~. - _. 3 1 I l l1 1 i i based on information presented in Sections 2.7.1, 2.7.2, a 2.7.3, 2.7.4, and 3.5. 4.3.3 Containment Criterion See Section 2.7, where in, it is shown that the containment requirements of 10 CFR Part 71. 51 (a) (2) are met. 4.4 Special Reauirements i Not applicable r 4.5 Appendix o Not applicable [ a f t f i . i I I a r i i a J 6 i il l i i 't 9 7 i i 1 a a e 4-2 REV. O August 12, 1993 ...,,y#,__ .a,7.,,,7 ,_%,,-p_,,,y e7,.,,.,9-rpy~9 q

I 1 i l I --Shielding Evaluation I 5. I i 5.1 Discussion and Results l The principle shielding of the Model 660 Series is the depleted uranium shield assembly. The mass of the uranium shield is approximately 37 lbs. (16. 8 kg). t A radiation profile of Model 660 Series, Serial Number 4537, was made using an AN/PDR-27(R) survey meter, Serial Number I-130. The Model 660 Series contained 107 Curies of Iridium-192 as Amersham Source Assembly A424-9, Serial Number 8534 The results of these measurements are presented below. The maximum radiation intensity i measured at the surface of the container was 127 milliroentgens per i hour, and the maximum intensity measured at f meter was 1.0 milliroentgens per hour. Extrapolating these measurements to the maximum container capacity of 140 curies, demonstrates that the j radiation levels are below the regulatory limits, j 5.2 Source Specification { 5.2.1 Gamma Source The gamma source is Iridium-192 in a sealed capsule as special form radioactive material in quantities up to 140-j

curies, j

5.2.2 Neutron Source Not applicable. 5.3 Model Specification Not applicable. 5.4 Shieldina Evaluation A shielding efficiency test of a Model 660 containing 107 curies of Iridium-192 was performed. The results of this test, which are presented in Section 2.10, demonstrated that j the dose rates surrounding this package are within the l regulatory limits. ) 5.5 Appendix Table 5.5.1 Radiation Profile Results W/107Ci of IR-192. l Table 5.5.2 Radiation Profile Results W/140Ci of IR-192. O 5-1 REV. O August 12,-1993 i [_

i l Table 5.5.1 I J l Summary of Radiation Profile Results l of a Model 660 Series With 107 Curies of i Ir-192 (mR/hr) 6 At One Meter Location At Surface from Surface i Top 89 0.7 Right 86

0. 5 Front 74 0.9 l

Left 127 1.0 't Rear 99 1.0 Bottom 65 0.4 Table 5.5.2 i Summary of Maximum Dose Rates a j Extrapolated to 140 Curies of { Iridium-192 (mR/hr) Location Surface One Meter 1 Top 116 0.9 Right 110 0.6 Front 97 1.2 i Left 166 1.3 i O Rear 129 1.3 Bottom 85 0.5 i l i 1 i 5-2 REV. O August 12, 1993 . _.. _ _ _ _... _.. _ _ _ _, _ _ _,.. _.. ~. _,, _ _ _... - -. _. _ -__,,_

... ~.--._... . ~. _ - 6. Criticality Evaluation Not applicable l 1 t' i l 9 O l 6-1 REV. O August 12, 1993-I i i )

1 1 1 7. Operating Procedure 7.1 Procedure for Loading the Package 1. Ensure that the source is locked into place in its storage position. To check this, the dust cover should be in place, the lock should be in the down position, the key removed, the dust cover should be in place,.and the selector ring should be immobile. 2. The storage plug should be properly inserted. (attach a tamper proof security seal with an identification mark to the storage plug). i 3. Assure all the conditiora of the certificate of Compliance [ i are met and the package has all the required markings. 4. If the shipping container is to be packaged in a crate or j ? other outer packaging, the outer packaging must be strong l enough to withstand the normal conditions of transport. I These requirements are outlined in 10 CFR 71. The shipping container should be put in the outer package with sufficient blocking to prevent shifting during transportation. l l 5. Perform a radioactive contamination wipe test of the outer i shipping package. This consists of rubbing filter paper or other absorbent material, using heavy finger pressure, over an area of 16 in.8 (100 cm?) of the package surface. The activity on the filter paper should not exceed 0.001 uCi of removable contamination. () 6. Survey the package with a survey meter at the surface and at a distance of one meter from the surface to determine the proper radioactive shipping labels to be applied to the } package as required by 49 CFR 172.403. If radiation levels above 200 mR/hr at the surface or 10 mR/hr at 40 inches (1m)- from the surface are measured, the container must not'be shipped. l 7. Return the container to Amersham Corporation according to proper procedures for transporting radioactive material as established in 49 CFR 171-178. NOTE: The U.S. Department of Transportation, in 49 CFR 173.22 (c) requires each shipper of Type B quantities of radioactive material to provide prior notification to the consignee of the dates of shipment and expected arrival. l 7.2 Procedure for Unloading the Package The consignee of a package of radioactive material must make arrangements to receive the package when it is delivered. If the package is to be picked up at the carrier's terminal, 10 CFR 20.205 requires that this be done expeditiously upon notification of its arrival. 7-1 REV. O August 12, 1993

.-. ~. - - I e Upon receipt, survey the exposure device with a survey meter as soon as possible, preferably at the time of pickup and no more than three O hours af ter it was received during normal working hours. Radiation levels should not exceed 200 milliroentgen per hour at the surface of the exposure device, nor 10 miliroentgens per hour at a distance l of 40 inches (1m) - from the surf ace. Actual radiation levels should be recorded on the receiving report. If the radiation levels exceed j these limits, the container should be secured in a Restricted Area, and the appropriate personnel notified in accordance with 10 CFR 20. All components should be inspected for physical damage. The radioisotope, activity, model number, and serial number of the source and the package model number and serial number should be recorded. Opening and operation of the device will be performed in accordance with the operation manual supplied with the package in accordance l with 10 CFR 71.89. 7.3 Preparation of an Empty Package for Transport { 1 1. For shipment of an empty Model 660, you must first assure there are no unauthorized source assemblies or cropped sources within the container, by performing the following procedure. a) Remove the authorized source assembly from the Model 660 in accordance with the applicable ~ operations manual for the storage device. b) After removing the source and disconnecting the source () assembly, attach the jumper (dummy connector without a serial number) to the male connector of the drive cable. c) Return the drive cable and connector to the Model 660 and disconnect the controls. t d) Insert dust cover cap, place selector ring in lock [ position, depress lock and remove the key. Insert the shipping plug and seal wire. Place an EMPTY tag on the device. t 2. Assure that the levels of removable radioactive contamination on the outside surface of the outer package do not exceed l i 0.001 microcurie per 16 in.2 (100 cm2). 3. When you have assured the Model 660 is empty, survey the device and prepare the package for transport depending upon j the radiation levels obtained, as given in 49 CFR 173. i 1 7-2 REV. O August 12, 1993

=. - -... ~. l i 8. Acceptance Tests and Maintenance Program h 8.1 Acceptance Tests 8.1.1 Visual Inspection The package is visually examined to assure that the appropriate fasteners are properly seal wired. The package is inspected to assure that the required marking and labeling is securely attached to the package. The seal weld of the radioactive source capsule is visually inspected for proper closure. The package is inspected to assure it was manufactured in i accordance with drawing 66025, see Appendix 1.3. I i 8.1.2 Structural and Pressure Tests The swage coupling between the source capsule and cable of the source assembly is subjected to a static tensile test l with a load of 100 lbs. (445N). 8.1.3 Leak Tests The radioactive source capsule, which serves as the primary l containment, is wipe tested for leakage of radioactive contamination and must be less than 0.005 microcuries of removable contamination. The source capsule is subjected to j a vacuum bubble leak test. Failure of either of these tests will prevent use of this source assembly. 8.1.4 Component tests l The lock assembly of the package is tested to assure that the security of the source will be maintained. A simulated (dummy) source assembly is installed in the radiographic exposure device and the lockbox locked. An attempt is made i to pull the simulated source out through the lockbox. The shipping plugs are installed and checked to be sure they are attached securely to the device. Failure of either of these two tests will prevent use of the package until the'cause of the failure is corrected and retested. 8.1.5 Tests for Shieldina Integrity l l With the package containing a source assembly, the radiation levels at the surface of the package and at 40 inches (Im) l from the surface of the package are measured using a small detector survey instrument. These radiation levels, when extrapolated to the rated capacity of the package, must not exceed 200 milliroentgens per hour at the surface of the package nor 10mR/hr at 40 inches (1m) from the surface. 8.1.6 Thermal Acceptance Tests Not applicable. 8.2 Maintenance Procram l 8.2.1 Structural and Pressure Tests O 8-1 REV. O August 12, 1993 l l l -- I

4 Not applicable. l O 4 8.2.2 Leak Tests -j As described in section 8.1.3, the radioactive source 4 assembly is leak tested at manufacture and must be less then 0.005 microcuries of removable contamination. Additionally, the source assembly is wipe tested for leakage of radioactive contamination every six months with the same acceptance criteria. 8.2.3 Subsystem Maintenance The lockbox assembly is tested as described in section 8.1.4 f prior to each use of the package. Additionally, the package j is inspected for tightness of fasteners, proper seal wires, and general condition before each use. The device must be l inspected at intervals not to exceed three months as given in Section 8.2.7. e 8.2.4 Valves, Rupture Discs, and Gaskets on Containment Vessel Not applicable. B.2.5 shielding r t Prior to each use, a radiation survey of the package is made j to assure that the radiation levels do not exceed 200 milliroentgens per hour at the surface nor 10 milliroentgens per hour at 40 inches'(im) from the surface. { 8.2.6 Thermal Not applicable. f i 8.2.7 Miscellaneous Inspections and tests designed for secondary users of this' package under the general license provisions of 10 CFR 71.12 (b) are included in Appendix A. t 1 8-2 REV. O August 12, 1993

1 Appendix A 8.2 Maintenance Inspection and maintenance of the Model 660 exposure device should be performed as described below. A quarterly check should be 4 performed and at least annually, the lock mechanism should be stripped for maintenance. Ouarterly Check i a) Clean and inspect the projector.or wear or obvious damage. Report any defect which might afftet safe operation and withdraw it from service until repairs can PO effected. I b) See that the radioisotope warning labels are secure and legible. Do not cover with any other labels. I c) Check that the cource outlet shipping plug is in place and that the screw and nut turn freely, but are not loose. j d) Check that the selector ring and lock mechanism operate freely. If operation is faulty, contact Amersham to arrange for servicing. I e) If any operational problems are discovered, the lock mechanism l should be stripped for maintenance. i Exposure Device To service the exposure device, remove the source following the source changing procedures. After the source has been removed, service the exposure device by performing the following steps: O 1. Remove the Danger Tag (secured with riveta) from the bottom of the rear plate. 1 2. Remove the rear plate by unscrewing the six phillips head I screws securing it to the exposure device body. 3. Unlock the connector lock, and then remove the lock assembly I and control unit connector assembly by unscrewing the six socket head screws securing them to the rear plate. ?. Disassemble the control unit connector assembly, referring to-Figure 1 for component identification and for order of removal. There are several spring loaded parts in the connector assembly, so care should be taken that these parts are not lost. 5. To disassemble the lock assembly, refer to Figure 1 for component identification and for order of removal. Remove the lock (2) from the lock retainer (3) by unscrewing the screw (4) and turning the key about 90" 6. Remove the front end plate from the exposure device, and remove the guide tube connector and retaining ring with Tru Arc pliers, referring to Figure 1. The handle may be left on the front plate. 7. Clean all parts in mineral spirits (or equivalent). i O 8-3 REV. O August 12, 1993 I

l a i ? i i j 8. Inspect all parts for damage or excessive wear, and replace 4 ] if necessary. Use Figure 1 for component identification l numbers. t 9. Lightly grease all moving parts at their contact surfaces l with M1-G-23827 B grease or equivalent. l 10. Reassemble the front end plate, and secure it to the exposure device with the proper screws. i 11. Reassemble the lock by placing the return springs and spring guides into the lock (2), depressing the internal plunger, inserting the lock (2) into the lock retainer (3), an = securing the lock with the set screw (4). ? 12. Attach the lock assembly to the rear plate with two socket head screws. i i 13. To reassemble the control unit connector assembly, refer to Figure 1. l 14. Refer to Figure 1 and place the compression spring (11) on i the hub of the selector ring retainer. The spring should be i firmly seated over the hub. Then place the sleeve (12) on top of the compression spring (11) i 15. Place the selector body (6) on a flat surface so that it is resting on its 5/8" hub. 16. Insert the two short compression springs (8) and locking pins. l (7) into the holes on the edge of the selector body. 17. Place the selector ring (10) over the selector body (6) while l restraining the locking pins (7). Ensure that the lettering (OPERATE-LOCK-CONNECT) on the sslector ring is facing up and that the stop pin on the selector body is in the cam slot of the selector ring. This is shown in Figure 1. 18. Hold the selector ring (10) and selector body (6) together. and place them over the assembly shown in Figure 1. The resulting assembly is shown in Figure 1. Align the resulting assembly such that the two large holes in the selector ring a retainer (9) line up with the two large holes in the selector body (6). The internal locking cam will partially block these holes. 19. Insert the anti-rotation lugs (13) and long compression springs (14) into the two large holes in the selector body. Secure the resulting assembly onto the rear plate with four socket head screws and torque to 30 lbs.ft, 5 lbs.ft. The word OPERATE should be facing outward, and should be in the 12 o' clock position. 20. Connect the jumper to the short length drive cable and insert the cable through the rear end plate and control unit connector assembly. 21. Insert a U-tool into the control unit connector assembly and check the operation by turning the selector ring from OPERATE to CONNECT several times. If the connector assembly does not i operate properly, disassemble and inspect the parts for 8-4 REV. O August 12, 1993 1 i 7 x- ---w-..~, +.,. ++, ,w.., --.~,..~vey-fee. -.m

~.

3

'~ Q'=...:a i ,y. 13 e i,a y, - .o ~ 4 O ~ -x f'g ;-; j Ayja. .2 ![i y / A 13 N 4 \\ ,s \\' f \\ 14 \\ o/ y i8 e ,. 6 f 3 ll r> e y r ge o g/g le s '( y/C9f e ( ,Q i y d c/'k %y i 17 12 i I AMERTEST 660 GAMMA RAY PROJECTOR 660 Repair Kit Part # Code Kit 402 g Ref 8 Cat Code U.S.A. Oty Description Oty in Kit [ 1 TMN1 2 SocJet Head screw 1432.x S/8 in. 4 ~.. 2 TStFA011 66001-11 1

Locli, dW.'d i t..'

3 75WA012 OG001-12 1 t ock Retainer 4 1 Saew (suppled writem 2) 1 5 1 Internal Plunger O 6 TStFA001 60001 1 1 Se4octor Body 7 TSN66005 66C01-5 2 lochng Pin i 8 TSt0321 2 Compression spring (LC 032E-1) 2 6 e(ray g 9 TStFA003 6G001-3 1 Sciector Ring Retainer 4 g to TSt4G6008 6G001-8 1 Soioctor Rir>g op 11 T570541 1 Compression Spring 1 8 t 12 TSPF4004 66001-4 1 Sloove 7 13 TSf7400G 60001-6 2 Anti-Rota$on Lugs Q ,t 14 TSfM267 2 Cornpression Spring 2 2 J 15 TMN1 4 Socket Head Screws 8 10-32x1 1/4 in. (st st-et) p 16 TMN1 4 12x:k Washer, s t o 4 17 TSN53311 53301-11 1 Guae Tute Connocer Nut 18 TMN1 1 Retaining Ring ~ 19 TStOO2 LBL-010 1 Sourcoldentifcaton Plate 20 1/4 20x3/4* PH Screns e 21 66001-811 Key 2 22 4 440 3/1G BHMS (for bck) 4 10 6 23 1 6-32 x SS-(for 2 24 10-32x3/S* S.S. Allen Screw 4 e h h, \\ a 66001-20 1 Jumpor Connector 1 /

1. 30 Drit: Bit 1'

a ,j t 12 1,T* S S. Pop Rivets 12 pp 1 6 Unks of Cover Cra9 1 1 84 Sco!! Drue Scren SC' 2 / h h GRE 10B G ease 1 663 CL Cf xA int 1 NN ,e ,..n-, a., on.-w-,, / %~ \\. O Fi p,u r e 1 8-4a -.. -.. ~. -... -

l damage and proper alignment. Relubricate the parts and () reassemble. 22. Secure the rear end plate to the exposure device and handle i using the six attaching phillips head screws and replace the protective plate over the bottom two rear plate screws using pop rivets (0.125 in diameter x 0.295 in long). 23. Check the system for proper reassembly. Check all connections and fittings for tightness. Check for proper operation of the control unit and control unit connector assembly. 24. Reload the source in the exposure device by following the f appropriate operations manual for the Bevice. 25. Survey the exposure device on all sides to ensure that '~ radiation levels do not exceed 200 mR/hr at the surface nor 10 mR/hr at one meter from the surface. 26. Check the exposure device for the proper labels. 27. Check the general condition of the outside surfaces, if excessively worn refer to Appendix 8.3. Outer Container i Sliding the product on abrasive surfaces, can, over a period of time, cause wear-through of the extended feet on the bottom of the i unit. i O This wear characteristic, has no adverse affect on the structural integrity, functionality or safety standards of the product. If and when, wear through of the feet occurs, repair procedures should be considered in order to prevent any damage occurring to the end plates. The product can be returned to Amersham Corporation for repair. This repair can occur in two ways. l a) Additional foot pads (66001-51) can be welded over the existing foot pad locations, or ] b) The outer shell is removed and a new outer shell is installed. Devices with Automatic Locking Mechanisms /Model 660B. 660BE, 660A, and 660AE (a) Cover Plate Removal 1. Remove the Danger Tag (secured with rivets) from the bottom of the rear plate. 2. Remove the rear plate by unscrewing the six phillips head screws securing it to the exposure device body. (b) Refer to Figure 2 and dismantle the selector assembly taking care not to + lose the spring loaded parts. Remove the lock (2) from the lock retainer (3) by undoing screw (4) and turning the key through 90 degrees. O-B-5 REV. O August 12, 1993

1 (c) Remove 4 screws securing the front end plate. Remove the guide tube connector nut (17) and retaining ring (18). (d) Clean all parts with mineral spirits or equivalent and inspect for wear. Replace as necessary. i (e) Lightly grease the inside surfaces of the selector ring (10) and the lock ) retainer (3) using type MIL-G-23827 B grease. j Reassemble the lock by placing the return springs and spring guides into the lock, depressing the internal plunger (5), inserting the lo9ck into j the retainer (3) and securing the lock with the cap, screw (4). j ) Attach the lock assembly to the mounting plate with two socket screws (1). j 1 (f) Begin the Selector Assembly reassembly by lightly coating the components with type MIL-G-23827 B grease. See Figure 2. Hold rear end plate horizontally, f ace up and the lock in the 12 o' clock position. 1 Insert the 5/8 diameter of the selector boy (6) into the mating hole in l the center of the rear plate. The narrow end of the slot of selector i body. l t Locate the locking slide (7) and return spring (8) into mating slot of I selector body. Placing the selector ring (10, with the work " CONNECT" at the 12 o' clock O L position, over the selector body. Push the locking slide in slightly so the selector ring will clear and rest the selector ring on the top surface of the selector body. l I Insert springs (14) into holes at the top and bottom of the selector body. Place the anti-rotation lugs (13) over the sprihgs. l Place the sleeve (12), with the large diameter facing down, on the center of the locking slide. Place the spring (11) over the sleeve. Install the selector ring retainer (9) into the selector ring. Ensure that the three non-threaded holes line up under the word " CONNECT". See Figure 2. Depress the selector ring retainer into the selector ring until i its top is flush with the top of the selector ring. (g) While holding the assembly firmly against the end plate, turn it over to expose the back side. Install the four socket head screws (15) and the lock washers (16) and torque to 30 lbs.ft. 15 lbs.ft. to secure the connector assembly to the rear plate. Insert the "U-Tool" into the top and bottom holes of the selector l l assembly Rotate the selector ring toward the " OPERATE" position. Remove I the "U-Tool". Continue rotating to " OPERATE" position. I j 4 Push the locking slide until the sleeve snaps into place. (h) While still in the " OPERATE" position, wind out a short length of the drive cable and pass it through the front of the selector assembly. Couple the cable to the test jumper connector and withdraw it into the j selector assembly. 4 8-6 REV. O August 12, 1993 i ~. _.,_ _. .. ~

Pull on the cable and confirm that the locking slide snaps shut to lock O the connector in the safe position. _ Push in the locking slide and repeat i to assure smooth operation. If smooth operation is not attained, disassemble the selector assembly and thoroughly inspect components for rough edges, burrs, etc. which could cause jamming or irregular selector assembly action. Replace parts as necessary. Re-lubricate the components and reassemble the selector assembly. Run through the normal operations of the lock and selector assembly. (i) A gap of at lease 0.53 mm (0.021 in) should be visible between the drive i cable collar and the selector ring and it should be impossible to rotate the ring. Do not use excessive force. See Figure 2. 4 If the selector ring can be rotated, this indicatessunacceptable wear, distortion, or damage in the connector lock mechanism or drive cable connector which must be corrected before using the equipment again. (j) Secure the rear end plate to the exposure device and handle using the six attaching phillips head screws and replace the protective plate over the bottom two rear plate screws using pop rivets (0.125 in diameter by 0.294 in long). (k) Lightly grease the guide tube connector nut hub with MIL-G-23827 B lubricant. Reassemble to the front mounting plate, ensuring that the retaining ring-is seated in the inner slot. Secure the mounting plate to the projector. Inspect the shipping plug, making sure that the lead insert is present. (1) Run through the normal operating sequence several times, using the test connector or a dummy source assembly (nonradioactive), to ensure smocth operation. (m) Check that the fixed labels are in good condition. (n) Transfer the source from the source changer back to the projector as i described in the source transfer procedures in this manual. I I Use a survey meter to check that radiation levels do not exceed 2 mSv/h, (200 mR/h) at any point on the surface. Replace the source identity plate back on to the projector. 8-7 REV. O August 12, 1993

/ / ( J% ' 1. 8 o \\ ./- \\ \\/- y \\ I 4 8 12 p 1 13 CD g, O \\ l O S' s G

1. g' x

O i g Y 15 y \\ /- 9'.*/,. / / 0 h \\ 17 7 1 TMM1 2 10-32s5/t* socket Reso screw 4 O 2 TsN66011 66001-11 1 lock 3 TsM66012 66001-12 1 Lock meteiner 4 1 4-40m3/16* Socket Need screw 1 21 5 1 Internal Flunger g Tan 85112 45701-2 1 selector Body T 7 Tsus5116 e5701-4 1 locktag stia. 4 TERO121 1 Compression spring (1c-022C-7) 2 9 TsN85715 85701-5 1 selector Ring Retainer 10 TEM 45113 85101-3 1 Selector Ring - 11 Tsm0541 1 ccampreeston spring (14:-045B-5) 1 12 T$N85716 85701-6 1 Sleeve t 13 Tsp 66006 66001-6 2 Rnti-motetton Luge 7 14 TsuC261 2 Comprecolon Spring (LC-026D-7) 2 3 15 TMM1 4 Socket Read screws UP'Ecr U p 10-32s1 1/4* in. (ot. steel) S 26 O 16 TMN1 4. Lock Washere, #10 4 17 TSM53311 51301-11 1 Guide Tube Cortnector put O O 18 TKM1 1 P.steining Ring 5160-18 1 2* OP-19 T$N002 LSL-010 1 Source Indentification Plate 5 20 4 1/4-20s3/4* Flat Head Phillips a O O 21 66001-811 Key 2 22 66001-20 1 Juniper Connector 1 21 2 4-40st/4* BEK3 24 26 # 4 10-32E3/4* Fast Bead Phill!pe 4 25 2 Frotective Bumper SH-2082 4 26 3 6-32x1/2* sinder seed Phillips 3 27 19 1 6 Links of Cover Chain 1

1. 30 Drill sit i

1 p y' 12 1/8" 8.8. Pop p1vito 12 1

1. 4 Scott Drive Screwe 5/6' 2

CRE-TUS Grease 1 660-CL Check List 1 MAN-006 1 660 Operations /Maint. Manuel BSK 0bl i U-few $@)-3$ l COVE 2~(DE A L J FIG. 2 Pme e-6}}