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Rev 1 to SAR on Model 660,Type B (U) Package USA/9033/B(U)
	ML20005E932
Person / Time
Site:	07109033
Issue date:	12/31/1989
From:	; AMERSHAM CORP.
To:	;
Shared Package
ML20005E924	List: ML20005E923; ML20005E925; ML20005E931; ML20005E932;
References
	NUDOCS 9001120073
	Download: ML20005E932 (66)
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TABLE OF CONTENTS

SECTION PAGE 1

GENERAL INFORMATION. I 1.1 Introduction. I 'l 1.2 Package Description l.2.1 Packaging. I 1.2.2 Operational Features 2 4.2.3 Contents of the Package. 3 2 STRUCTURAL EVALUATION. 4 2.1. Structural Design 4 2.1.1 Discussion 4 2.1.2 Design Criteria. 4 2.2 Weights and Centers of Gravity. 4 2.3 Mechanical. Properties of Materials. 4 2.4 General Standards for all Packages, 5 2.4.1 Chemical and Galvanic Reactions. 5 2.6.2 Posittve Closure 5 2 4.3 Lifting Devices. 6 0.4.4 Tiedown Devices. 6 2.5 Standards for Type B Packages 7 2.5.1 Load Resistance. 7 2.5.2 External Pressure. 7 2.6 Normal Conditions of Transport. 7 2.6.1 Heat 8 2.6.2 Cold 8 2.6.3 Reduced Pressure 8 2.6.4 Vibration. 8 2.6.5 Water Spray. 8 2.6.6 Free Drop. B 2.6.7 . Corner Drop. 9 2.6.8 Penetration. 9 2.6.9 Compression. 9 O-2.7 Hypothetical Accident Conditions. 9 2.7.1 Free Drop. 9 2.7.2 Puncture 9 2.7.3 Thermal. 10 2.7.4 Wate.- Immersion. 10 2.7.5 Summary o f Damage. 10 2.8 Special Form. 11 2.9 Fuel Rods 11 2.10 Appendix 12 REVISION 1 DECEMBER 1989

TABLE OF CONTENTS -(Continued) SECTION PAGE 3 THERMAL EVALUATION 13 3.1 Thermal Properties of Package'. 13 3.2 Summary of Thermal Properties of Materials. '13 3.3 Technical Specifications of Components. 13

3. 4 Normal Conditions of Transport.

13 3.4.1 Thermal Model. 13 3.4.2 Maximum Temperatures 14 3.4.3 Minimum Temperatures 14-3.4.4 Maximum Internal Pressures 14 3.4.5 Maximum Thermal Stresses 14 3.4.6 Evaluation of Package Performance Under-Normal Conditions of Transport 14 3.5 Hypothetical Thermal Accident Evaluation. 14 3.5.1 Thermal Model. 14 3.5.2 Package Conditions and Environment 14 3.5.3 Packaqw 'emperatures 15 3.5.4 Maximum internal Pressures 15 3.5.5 Maximum Thermal Stresses 15 3.5.6 Evaluation of Package Performance. 15 3.6-Appendix. 16 3.6.1 Model 660 Type B(U) Thermal _ Analysis 17 3.6.2 Model 660 Type B(U) Thermal Analysis 18 3.6.3 Iridium-192 Source Capsule Thermal Analysis 19 4 CONTAINMENT. 21 4.1 ' Containment Boundary. 21 4.1.1 Containment Vessel 21 4.1.2 Containment Penetrations 21 4.1.3 Seals and Welds. 21 4.1.4 Closure. 21 4.2 Pequirements for Normal Conditions of Transport 21 4.2.1 Release o f Radioac t ive Mater ial. 21 4.2.2 Pressurization of the Containment Vessel 21 4.2.3 Coolant Contamination. 21 4.2.4 Coolant Loss 22 4.3 Containment Requirements for the Hypothetical 22 Accident Condition. 22 4.3.1 Fission Gas Products 22 4.3.2 Release of Contents. 22 REVISION 1 DECEMBER 1989

TABLE OF CONTENTS (Continued) SECTION PAGE 5 SHIELDING EVALUATION 23 5.1 Discussion and Results. 23 5.2 Source Specification. 23 5.2.1 Gamma Source P3 5.2.2 Neutron Source 23 5.3 Model Specification 23 5.4 Shielding Evaluation. 24 6 CRITICAulTV EVALUATION 25 7 OPERATINO PROCEDURES 26 7.1 Procedure for Loadang the Package 26 7.2 procedure for Using the E posure Device 2e 7.3 Procedure for Unloading the Package 26 7.4 Preparation of a Package for Transport. 26 7.5 Append 1x. 27 7.5.1 Procedure for Encapsulation of Sealed Sources. 27A ' 5.2 Model 660 Exposure Device Operation Manual 28 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM ', 2 8.1 Acceptance Tests. 42 8.1.1 Visual Inspectlon. w2 8.1.2 Structural and Pressure Tests. 92 B.1.3 Leak Tests 42 8.1 4 Component Tests. 4P 8.1.5 Tests for Shieldtog 'ntegr itv 42 B.l.c Thermal Acceptance Tests 42 B.2 Maintenence Program 43 8.2.1 Structural and pressure Tests. ~ '3 8.2.2 Leak Tests -3 8.2.3 Subsystem Maintenence. 43 8.2.4 Valves, Rupture Discs and Daskets. ~3 8.2.5 Snielding. "3 8.2.6 Thermal 43 A.E. M iscellaneous. '+3 REVISION 1 DECEMBEF 1989

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SECTION 1 13 GENERAL INFORMATION 1.1 Introduction g The Amersham-Model 660 is designed for use as a radiographic exposure device and transport package for Type B quantitles of radioactive material in special form. The Model 660 conforms to the criteria for Type B(U) packaging in accordance with 10 CFR 71 and IAEA Safety Series No. 6. 1973 Revised Edition (as amended). 3. 1.2 Packaoe Description 1.2.1 PacLeoino The Model 660 is'324 mm (12.75 in) long. 133 mm (5.25 in) wice and 245 mm (9.65 in) high. The package incorporates an aluminum handle for movement of the exposure device. The total mass of the package is 24 kg (53 lbs). The radioactive material is sealed in a source capsule which conforms to the requirements for special form radioactive material. This source capsule is installed into a source holder assembly. The-source. holder assembly is housed in an "S" shaped titanium or zircalloy source tube. The source tube has an outside diameter of 11.86 mm (0.467 in) and en-inside diameter of 9.78 mm (0.385 in). The source tube is surrounded by uranium metal as shielding material. The uranium shielding is cast in place around the source tube. The mass of the uranium shield is (16.8 kg) 37 lbs. The urantum shield is encased in a steel housing. The housing is made up of a shell and two end plates. .The shell is fabr'scated from 16 gauge (0.060 in thick) stainless steel. The end plates are bolted tngether 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 polvurethane foam. The outer packaging is designed to avoid the collection and retention of water. The package has a smooth finish in provide for easy decontamination. Attached to the rear plate is the control connector and lock assembly. This assembly incorporates an automatic locking feature that locks the source assembly in the exposure device when the source is returned to the Gtored position.

REVISION 1 DECEMBER 1989 PAGE 1

4 L in addition the source cannot be exposed unless a secure 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. i Attached'to the front plate'of the exposure device is the storage plug connector. This connector provides a means of 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 . i ne, t a l l-i ng 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. li The radioactive material is sealed inside a stainless steel capsule. This capsu.le acts as a containment vessel-for the radioactive material. .2.2 Operational Features The source' assembly is secured.in the proper shielded storage position by the locking assembly. 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. A protective cap is 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 means of securing the source assembly in the proper storage position. 1.2.3 Contents of the Packaoe The Model 660 is designed for the transport of Iridium-192 in quantities up to 140 curies in the Amersham source assembly A424-9. REVISION 1 DECEMBER 1989 PAGE 2

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SECTION 2 STRUCTURAL EVALUATION '2.1 Structural Desion D'scussion 12.1-.1 i The Model 660 is comprised of five stru tural 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 is fabricated from 1.5 mm (0.060 in) thick stainless ~ steel. The housing provides the structural integrity of the package. The lockbox assembly secures the source holder assembly in the shielded position at the center of the source tube and assures positive closure. 2.1.2 Desian Criteria The Model 660 is designed to comply with the requirements for Type B(U) packaging as prescribed by 10 CFR 71 and IAEA Safety Series No. 6 1973 Revised Edition (as amended). All design criteria are evaluated by a straightforward application of the appropriate section of 10 CFR 71 or IAEA Safety Series No. 6. 2.2 Weiahts and Centers of Gravity The total mass of the Model 660 is 24 kg (53 lbs). The shield assembly consists of 15 kgt34 lbs) of depleted uranium. The center of gravity is located approximately in the center of the device. 2.3 Mechanical oroperties of Materials The. outer housing of the Model 660 is fabricated from stainless steel. This material has a yield strength of 207 MPa (30,000 psi). Drawings for the source capsules used in conjunction with the Model 660 are enclosed in Section 2.10. Thrse source capsules are fabricated from titanium or stainless steel. t REVISION 1 DECEMBER 1989 PAGE 4

2.4 General Standards for All Packaoes 2.4.1 Chemical and Galvanic Reactions The materials used in the construction of the'Model 660 are uranium metal, stainless steel, titanium, and vultafoam. There will be no significant chemical or galvanic action between any of these components. The possibility of the formation of an eutectic alloy of iron and uranium at temperatures below the melting temperatures of the individual metals has been considered. The iron uranium eutectic 0 0 alloy temperature is approximately 725 C (1337 F). However, vacuum conditions and extreme cleanliness of the surfaces are necessary to produce this 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, 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 Jample was placed in a ceramic crucible and inserted in a furnace preheated to 800'C (1475'F) and remained there for thirty minutes. The sample was then removed and allowed.to cool. The test indicated that the uranium sample oxidized such that the radial dimension was reduced by 0.18 mm (0.007 in). On 25 January 1974, a subsequent test was performed by Nuclear. Metals, Inc. In-this test, a sample of bare depleted uranium metal was placed on a steel plate and subjected to the thermal test conditions. The test revealed no melting or alloying characteristics in the sample and the degree of oxidation was the same as experienced in the earlier test.

2. 4. 2-Positive Closure The control connector and lock assembly consists of a hardened steel locking slide, 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. 4 REVISION 1 DECEMBER 1989 PAGE 5

...... ~, - ~ ~ - - - 3 V 2. The locking slide cannot unlock the source until all of the following conditions are 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, d) the selector ring has'been rotated to the operate position, e) the locking slide is manually moved to the unlocked position. 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 seen. 3. 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 t h.e storage plug is seal wired to prevent unauthorized removal of the source assembly. Positive closure of the package during transport is maintained with these features. 2.4.3 Liftino Devices The Model 660 is. designed to be lifted by its handle. Failure of this lifting system could be accomplished by shearing two Number 10 by 32 flat head. screws securing one side of the handle. The yield strength of the material is assumed to be 40,000 pounds per square inch. The cross sectional area of each screw is 0.018 in. Therefore, a load of 1440 lbs must be applied to generate stress equal to the yield strength of the material. This is equal to thirty times the weight of the package. Therefore the handle is capable of suporting three times the weight of the package without generating any stress in excess of the yield strength of the material. .2.4.4 Tiedown Devices The handle of the Model 660 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. REVISION 1 DECEMBER 1989 PAGE 6

If ithe'tiedown technique were to fail under excessive load, 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 -2.5 . Standards for Tvoe B Packaoes 2.5.1. Load, Resistance 'A'Model 660.was subjected to a compressise load of 300 pounds which is .five times the weight of the package. This is greater than 1.85 '2 lb/in times the vertically projected area of the package. This load was' distributed uniformally over the top surface of the Model 660 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 result of this test. Therefore the Model 660 will withstand the normal conditions of transport compression condition. 2.5.2 Esternal Pressure The Model 660 is open to the atmosphere, thus there will be no differential pressure acting on it. The collapsing pressure of the source capsule is calculated assuming that the capsule is a thin wall tube,with a wall thickness equal to the minimum depth of weld penetration which is 0.5mm (0.020 inch). The collapsing pressure is calculated from: P = 597.6 t/d - 9.556 where P: Collapsing pressure in MPa -t: Wall Thickness (0.5mm or 0.02 inch) d: Outside Diameter (6.4mm or 0.250 inch) (Ref ' Machinery's Handbook, 22nd Edition, p. 330) From this relationship, the collapsing pressure of the source capsule is calculated to be 37.1 MPa (5548 psi). Therefore, the source capsule could withstand an external pressure of 0.17 MFa (25 psi). 2.6.0 Normal Conditions of Transoort

2. 6.1 ' Heat

~' The thermal evaluation of the Model 660 is presented in Section 3. From this evaluation. it is concluded that the Model 660 will maintain Lits structural integrity and shielding effectiveness under the normal transport heat condition. REVISION 1 . DECEMBER 1989 PAGE 7

.R.6.2 Cold The metals used in the manufacture of the Model 660 can all withstand' a temperature of -40*C (-40*F). The outer package housing and the primary containment are all fabricated from stainless steel. Vultafoam used-in _the Model.660 has an operating temperature range down to ~43'C. From this data,-it is concluded that the Model 660 will' maintain its structural integrity and shielding effectiveness under-the normal transport cold condition, a 2.6.3: Reduced Pressure-The Model 660 is open to the atmosphere. Thus there will be no differential pressure acting on it. A demonstration-of the ability of the source capsules to withstand an external or e%ure of 0.5 atmosphere is oresented in Section 3.5.4. On the basis of this data, it is concluded that the Model 660 will maintain its structural integrity and shielding effectiveness-under the normal transport pressure condition. 2.6.4 Vibration The Model_660 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 h2 story, it is concluded that the Model 660 will . maintain its structural integrity and shielding effectiveness under the normal transport vibration condition. 2'.6.5 Water Sprav The water spray test was not actually perfo~med on the Model 660. The -materials used in the construction of the Model 660 are highly water resistant. Therefore. it is concluded that the Model 660 will maintain-its structural integrity and shielding effectiveness under the normal transport water spray condition. 2.6.6 Free Drop A. prototype Model 660 weighing 26 kg (58 lbs), was subjected to the hypothetical accident free fall condition. This is described in Section 2.7.1. On the basis of this testi it is concluded that the Model 660 will maintain its structural integrity and shielding effectiveness under the normal transport free drop condition. REVISION 1 l = DECEMBER 1989 1 PAGE 8 l

Y - 2.6.7 Corner Droo ' Not applicable. 2.6.8 Penetration A' prototype Model 660 was subjected to a penetration test. The package.was impacted by the penetration bar on the locking assembly. As a result of this impact, there was no loss of structural integrity nor reduction of shielding efficiency. A report of this test is presented-in Section.2.10. On the basis of this test' it is concluded that the Model 660 will maintain its structural integrity and shielding effectiveness under the normal transport penetration condition. 2.6.9 Comoression A compression test was performed on the Model 660; results are listed in Section 2.5.1. 2.7-Hvoothetical Accident Conditions 2.7.1 Free Drop The Model 660 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 10 m (30 ft) 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 this test.is presented in Section 2.10. On the basis of these tests, it is concluded that-the Model 660 will maintain its structural integrity and shielding effectiveness under the hypothetical free drop accident condition. 2.7.2 Puncture At-the conclusion of the free drop test, a Model 660 was subjected to the puncture condition. The target for the puncture test was a steel billet 152 mm 16 in) in diameter and 203 me. (8 in) high mounted on the target used in the free drop test. REVISION l' DECEMBER 1989 PAGE 9

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During_this test, the packages dropped from the height of one meter (40 in) 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 efficeincy. A report of this test is presented in Section 2.10. On the basis of these tests, it is concluded ~that the Model 660 will maintain its structural integrity and shrelding, effectiveness under the hypothetical puncture accident condition. 2.7.3. Thermal-The thermal analysis is presented in Section 3.5. It is shown that the melting temperatures of the materials used in the construction of . the Model 660 except for the Vultafoam are all in excess of (1475'F) - 800'C. To-demonstrate that the radioactive source' assemblies will remain in a shielded position following the hypothetical accident condition, the following analysis is presented. At the conclusion of the thermal test it is-assumed that the Vultafoam has completely escaped from the 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. A Model 660 was insolved in a fire in 1974 and did not 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 satisfactorily meet the requirements of the hypothetical thermal accident conditions of-10 CFR~71. 2.7.4 Water immersion Not applicable. 2.7.5 Summarv of Damace 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. As a result of these tests, there was no loss of structural integrity nor release of any contents. Prior to the performance of these tests and subsequent to the conduct 'of these tests, measurements of the radiation 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. 1 REVISION 1 l DECEMBER 1989 l PAGE 10 l

{; - 2.0 Special Form-The Model 660 is ' designed to transport Amersham source capsules. These source capsules have_been certified as special form radioactive material. These-certificates are presented in Section E.10. 2.9. Fuel Rods ..Not applicable. ? REVISION 1 DECEMBER 1989 PAGE 11

,g: -: 4. (i s t ' 2.10..Ajoendik IAEA Certificate of: Competent Authority USA /0335/5 -Test Reportst' . 1.) - Free Drop Test - 2) Puncture' Test . 3 )- 660 Involved in Fire f I ~ REVISION 1 DECEMBER 1989 PAGE 12

US Departm CORRECTED COPY "O 5"""'. D c"' 20590 5" 5 *' weengton Of MW BIsteerch and - SpecialPrograms IAEA CERTIFICATE OF C0KPETERT AUT110RITY Admin 6stretton SPECIAL PORM RADI0 ACTIVE MATmttALS CERTIFICATE BUMBER USA /0335/S. REVISION 1 This certifles that the source described has been demonstrated to meet the regulatory requi{ements for special fyra radioactive asterial as prescribed in 1AEA Regulations and USA regulations for the transport of radioactive- -materials.- 1. Source Description - The source described by this certificate is identified as Amersham Model 875 source capsule assembly which is a single welded encapsulation constructed of Type 304 or 304L stainless steel, and acasures approximately 24 mm (0.95") in length by 6.4 mm (0.25") in diameter. Content s 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 TBq (240 Ci) Iridium 192 as solid metal, 8.14 TBq (220 Ci) Cobalt 60 as solid netal, 7.4 TBq (200 Ci) Ytterbium 169 as Yb 0,1.11 23 TBq (30 Ci) Cesium 137 as CsC12 in a secondary stainless steel encapsulation, or 1.85 TBq (50 Ci) Thulium 170 as T"2 3 0 3. Expiration Date _ This certificate expires July 15, 1994. This certificate is issued in accordance with paragraph 803 of the IAEA 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 Corporttion, Burlington, MA, and in consideration of the associated inf ormation therein, and other inf ormation filed with this of fice. Certified by: 6,, Nich'hel E. Wangle'r' (DATE) Chief, Radioactive Material ranc h Of fice of Hazardous }bterials Transportatica Revision 1 - Issued to change the source identification from Tech Ops to Amersham and to extend the expiration date. 1 " Safety Series No. 6. Regulations for the Safe Transport of Radioactive Haterials, 1973 Revised Edition" published by the International Atomic Energy Agency (IAEA), Vienna, Austria. 2 Title 49, Code of Federal Regulations, Parts 100 - 199, USA. l l 0-O

l 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 modified with the automatic securing was subjected to a free drop test in 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 locking assembly. 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. l

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I~ .i; l TEST REPORT BY: CATHLEEN M. ROUGHAN h DAVE DUNCANSON-DATE: '13-OCTOBER 1989

SUBJECT:

Model 660 Puncture Test on 29 September 1989, a prototype Model 660 modified with the .cutomatic securing mechanism was subjected to a puncture test in-occcordance 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, Groveland, MA. Immediately following the free drop test, the prototype Model 660 -package was dropped from a height of one meter onto a target. The target consisted of a right circular cylindrical steel billet 152mm -(6 incher) 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 test did not reduce the shielding efficiency of the package.

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i t. I Wi~P d e.' rat- ~ ' ' "' reasured-Was 5 rre:/h. Sever.11 ei.2 - redhanic11 and incide the r, u1,,. t t. n [,. ' a.,i r i n c',,n nT ', u[ " " '" t ' " 1 C 3 M O .c.n ^ C ':' r ".c e t.1 : g i g e., n. ) i m., p r : e t., u r e. Tor a;tivity van less.than 0.1 nanocuricf. enenehoftnc,ly(,ilnn, i-P'rerintlen f re Gilli(*ttn o f T,,chp j en s qg p,, t ra I' 9 ' ' b-. ". l a.".1,,, curie i.ridiun-192 rourca t3 n '# "' ' I' ; tk' 10.6 r r ion (,ble f ar reWi; t, u.o Th ]i f fi,~..a,l e.,, g.a,. e xpo t i rm e n d 3 t' s. ranaaa'..

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i t i' 4 BF SECTION 3 THERMAL EVALUATION s

3. l _ -Thermal Properties of Package The Model 660 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 decaycheat generation. rate is approximately 1.2 watts. 3.2 Summary of Thermal Properties of Materials o ", The~ materials used in the construction of the Model 660 includes: Depleted Uranium Melting Point ll33'C Steel Melting Point 1 3 4 5,' C Titanium Melting Point 1800 C \\ 'The VultaToam in this device has an-operating t empera tur e range of ~ -43'C to 104'C (-45'F to 220*F). 3.3 Technical Specifications of Components Not applicable. 3.4 Normal Conditions of Transport 3. 4 1-Thermal Model The heat source in the Amersham Model 660 is a maximum of 140 curies of Iridium-192. Iridium-192 decays with a total energy liberation of 1.45 MeV per disintegration or 8.6 milliwatto 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. To demonstrate compliance with the requirements of 10 CFR 71.43(g) and . paragraph 130 of IAEA Safety Series No. 6. a separate analysis is presented in Section 3.6. The thermal model employed is described in that. analysis. To demonstrate compliance with the requirements of paragraph 240 of IAEA Safety Series No. 6 for Type B(U) packaging, a separate analysis is presented in Section 3.6. The thermal model employed is described in that analysis. REVISION 1 DECEMBER 1989 PAGE 13 4

a-n N '3;4.2 -Maximum Temperatures The maximum temperatures encountered under normal conditions of. H j'; transport'will have no adverse effect on'the structural integrity or l '4P shielding efficiency of the package. As presented in Section 3.6, the maximum' temperature in ths shade would not exceed 42'C (108'F) and the q maximum temperature when insulated would not exceed 6B'C (154'F). i 13.4.3 Minimum Temoeratures TNe minimum normal operating temperature of the Model 660 is.-40'C i (-40'F). This temperature will have no adver sie ef fec t on the structural integrity of shielding efficiency of the package. 3.4.4 Maximum Internal Pressures j Normal operating conditions will generate negligible internal pressures. Any pressure generated is significantly below that-which would be generated during the hypothetical thermal accident condition,- Y which is shown'to result in'no reduction in structural integrity or shielding efficiency. l 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 under Normal Conditions of l Transport, l The normal transport thermal condition will have no adverse effect on the structural integrity or shielding efficiency of the package. The applicable'condit' ions of 1AEA Safety Series No. 6 for ~ Type B(U) I packages are shown to be satisfied by the Model 660. i 3.5.0 -Hvoothetical Thermal Accident Evaluation-3.5.1 Thermal Model i 3.5.2 Packaae Conditions and Environment i The prototype Model 660 package which was subjected to the free drop f ~ test and puncture test, suffered minor structural deformation during ? these mechanical tests, but suffered no reduction in structural integrity or shielding efficiency. REVISION 1 DECEMBER 1999 PAGE 14 l

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{^h 5l _ 0 _. 1 &n e, y~ wr,9 t @*i -13.5 3 ); Packace Tempera tures -j J n,%' ~ ':As-indictediin'Section 3.2 the entire package is' assumed to,. reach'a-j ~ '. tempera ture of _800.*C e ~ Examination ofuthe melting temperatures of.t'he b, .ina ter ials? used : i n construc t ion of the Amersham Model'660'. indicates =there wil_libe no damage to the-package as a result lof.this: ^ Q temperature.. l Vg> f'^ }The possi~oilitygof the formation'of a. iron-uranium.eutectic alloy wat,' t.M ,faddressed in.Section 2.4.1-where..it.was concluded.that thelformation-R 14 M theial'loy was not a likely poss'bility. There'was no indication *of- ~ i -anyjmetting;orDalloyl formation as'a' result of this thermal-test.. r} 3.5.4 1 Maximum' Internal'-Pressures rf ~1n Section 3.6.3' ? anfanalysis of theisource capsule, whichcserves as> '"j lthe primary. containment'"under the thermal' test conditions is-fpresented.-.This~ analysis. demonstrates - that t.the maximum : internal. gas p , pressure'at 800?C:would:be-373 kPa_(54 psi'). p !The(critical location for. failure is the source capsule--weld.- r The. analysis'. shoes that an internal' pressure of 373 kPaL(541 psi) w o u l 'd.- g 4 [ l generate a maximum stresscof 1.96 MPa--(284' psi.). At 870*C (1600'F),o {

the' yield'.strengthJofcstainless. steel-in 69.MPa (10.000 py,1).

'I

g

,ATherefore,-if the source capsule-were to reach'a temperaturefof-800'C,- ((.

theimaximum stress'incthe capsule would be;.only 3 percent of4the yield--

strength _of:the.materi'al.. g pn ' 3.5'.5 Maximum Therma 1 Stress M .There?are no significant thermal stress generated during the thermall otest.

3.5.6;. Evaluation of Dackaoe Performance I

The'Model'660 wi d undergo.no, loss of: structural integrity or .j f [.

shielding.when subjectedLto the thermal accident condition. -The d

pressures and temperatures have been demonstrated t o b e - w i t h i n.--

. acc ep t ab l e': 1 i m i-t s. n 1 o a 4 i I b (-M. t i .. REVISION 1~ 1 DECEMBER 1989 PAGE 15

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Daranranh~230=of-TAEA Safety Series No.

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j. @k ' 13;6;3:- tr'idiUm-192 Seuree'caosule Thermal Analysis" L'

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3.6.1 Model 660 Tvoe B(U) Thermal Analysis 10 CF9 71.43 to) and Paraorach 231 of IAEA Safety Series No. 6 This analysis demonstrates that the maximum surface temperature of the Model 660 will not exceed 50*C with the package 2n the shade and an ambient temperature of 39'C, To assure conservatism, the following assumptions are usedt (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 q = hA(T y. T,) where q = heat dt Hsited per unit time in the face of interest (0.30 wa.ts) Free convection heat transfer coefficient for air h *- 2 1.42 (AT )l/4 watt / oC = d Area of the face of interest (0.032 m2) A = TW Maximum temperature of the surface of the package = Ta = Ambient Temperature '38'C) d a Height of face of interest (m) = 0.244 m From this relationship, the maximum temperature of the surface is 42'C. This satisfies the requirement of 10 CFR 71.43 (g) and paragraph 230 of lAEA Safety Serial No. 6 REVISION 1 DECEMBER 1989 PAGE 17

4; ? f 4 3 s i < , g/ '3.6.2 'Model 660 Tvoe B(U) Therma l-Ana l ys i s ~, caraoreoh 240 of IAEA Qy -Safety Series No. 6 This analysis demonstrates that'the maximum s'urface temperature of the .Model 660 will not exceed.52*C when'the'pacxage is.in an. ambient ' temperature.of 30*C and-is insulated in act ardance wi th 10 CFR.71.71. I c(c)=(IL and Table Ill of IAEA Safety Series. No. 6. 'O -'The calculational =model consists of taking a steady' state heat balance' i over the surface of the package. In order to' assure 1conservatisme the. following assumptions are used.' . ( a )' The' package 15: insulated at the rate of'775 W/mE (800 cal /cm -12 E hr),on the top. surface. 194 W/mE (200 cal /cm -12 hr) on the side I E surfaces and on. insolation on the bottom surface. I (b) The decay heat load is odded to the solar heat load. (' c i ' The package'has an unpainted stainless steel-surface. The Solar ~ n absorptivity is assumed to be 0.9 The solar emissivity'is I assumed to 0.9. i -(d) .The-package ist assumed to undergo the convection from the sides [ 1and top, and undergo radiatior.-from'the sides, top and bottom. l The inside faces are-considered perfectly insulated so there is i no conduction into the package. The faces are considered to.be sufficiently than so that no temperature gradients exist in the ' f ac es.. lei The package-is approximated as a rectangular so' lid of 13.3 cm' (5.25 in). wide, 24.4 cm (9.62 in) high and 25.1 cm (9.87 in) long-transported on Igsside. The. total surface area of-the top and-botgom is 0.062 m The total surface area of the sides is -[ 0.189 m I - The maximum surface temperature is computed from a steady state heat balance relationship. f Q in " Aout i i Th.e heat load applied to the package is y A i n " A s' *Ad HC i 1 -i t A REVISION 1 DECEMBER 1989-PAGE la i t i ' '- ' " ' - '" ~

70 q] ll44-Q 1,3', a* k

V 5_ $

b LWh're o.= solar absorptivity (0.9) e M / q,(=i solar hea t -: l o ad : (91.4 Watts) qd = decay. heat. load:(1.20 watta): .The hdat dissipation is expressed as 4 .y p ${ Qout A + A r c ' Where'qc.= convective; heat transfer k[' ((hA) top-+'(hA) sides) '(Tw Ta)- = where h_m. convective heat transfer coefficient-e A =' area of the surface of. interest Ty s = Temperatures of the surface .M- .T J= Ambient Temperature (38'C) s gr.= Radiative heat transfer a C A -(T 4 y T,4) =- Where a =LStefan Boltzmann Constant (5.669 x 10-8 W/m2.g4 3 C: V Emissivity-(0.8) m . Iteration of.this" relationship yields a maximum wall temperature of , 60'C-.which. satisfies the requirements of. paragraph 240'of the IAEA; . Safety Series'No. 6. '3.6.3

Amersham Model 660 Tvoe B(U) Sourte Capsule ~ Thermal Analysis Paraorech 238 of IAEA Safety Series No. 6 1973.

.This analysis demonstrates that the pressure.inside the source ~capsdle. used in' conjunction with the Model 660, when subjected to..the hypotheticaltthermal accident condition, does'not exceed the pressure with corresponds to the minimum yield strength at the thermal test . temperature. 7, .The source capsule is fabricated from stainless steel, either Type 304 ~ 'or:304L. The outside diameter of the capsule is 6.35 mm (0.250 in). The source capsule is seal welded. The minimum weld penetration is 0.5<mm'(0.02 in). Under conditions of internal pressure, the critical ' location for failure is this weld, p r. Y> REVislON 1- . DECEMBER 1989 PAGE 19 .h C.c a

e-v <3, y.y, _ ~ + l x[f;.e-9 ml ,4' r-n. . x[.~ 'q 3 r b. _. volumefof.the source capsule'contains only iridium metal; '4The. internal p ' -(as'a solid)::and air. lt is. assumed:at the time;of leading the . entrapped' air'is at standard temperature and press're-(20'C,and 'i u s ^ -r 100 kPa).'. Thi s : is a conserva t i ve: assump t i on because, during-the welding process, the internal air 15 heated, causingssome'of the ale G mass-to escape before-.the capsule is sealed. When the welded capsule t ( returnsito ambient temperature, the internalopressure'would be [ somewhat. reduced. 46: I UnderL the. condi tions of paragraph ' 239 of IAEA Safety Series No. 6,- { uitDis. assumed that the_ capsule could-reach a temperature of.800'C-(1475'F). Usi'ng the ideal gas law'and requiring the air to'occupyfa-constant' volume, the internal gas pressure could reach 373 kPa Afi "4 t .(54 psi). 1The capsule is assumed'to be a thin walled cylindrical pressure vessel-with the = Lvall ~ thickness equal. to the depth'of weld penetration. The. maximum' longitudinal stress is calculated from: 1 c a A = PA } p-I -where a = Longitudinal Stress s i A= -Stress Area, 1 ! P = ' Pressure p.= ' Pressure Aree-A ~, [ Frcm this-relationship,.the maximum longitudinal stress is' calculated. ? U Lto be 900 kPa: (IB9 psi). 4 e .f

The' hoop. stress is calculated from:

y 2ahlt P} t I = I wherefah Hoop Stress' = ( 1 = -Length of1the Cylinder. [ t = : Thickness of the Cylinder (0.5 mm or 0.02 in) y [ .From[this; relationship,.the hoop stress-is calculated tch be 1.96 MPa e [ (284 psi).' o 4F

v At a temperature of 870'C (1600*F), the yield strength.of type 304

-stainless steel is 69 MPa (10,000 psi). Therefore, under~the la "conditionn.of paragraphs:238 of IAEA Safety Series No. 6, the stress qgeneratednis less than 3 percent of the yield strength of the. tj ~ material. i t a 4 s [* N i I REVISION l' I ( DECEMBER 19891 I s I <L PAGE 20 I is ~' }'2? -d

m~ lgmg; l;%;, y~ y, '~ A pjy ~ 9 C SECTION 4 + 1

{

' CONTAINMENT

7., +.-

1 t I4 ; 1. 0, L. Con t a i nment Bounderv 4 W E 4.1.1 'i Con t a i nment Vessel i p p --The.containmentisystem forothe Model'660 is the radioactive source g, capsule as. described in'Section l.2.3 of this application. This source capsuleLis certified as special form radioactive material in- .{ 6, ..IAEA Certificate of, Competent Authority Number USA /0335/S. .. t L A '. l. 2 ' Containment ~ Penetrations q -There:are'no penetrations.of the containment., j s4.1.3 Seals and Welds ,5 1Th'efcontainmentiin seal welded by-tungsten insert gas welding process (( E which'is described in Amersham Standard Source' Encapsulation Procedure- . presented-in Section 7.5.1. The minimum weld penetration is 0.5emm' (0;02 in). I 4.1.4 Closure-y.

Not applicables 4.2.0 LReoutrements for Normal Conditions of Transoort 9

14.2.1 Release of R&dioactive Material LThe(source capsules used'in conjunction with.the Model 660.have ,[

satisfied the c'equirements for -the special form radioactive material

') an' prescribed in 10 CFR 71.77 and IAEA Safety SeriesiNo.

6.. There tt will;beino1 release of radioactive material under the. normal conditions

'of transport. t 64.2.2 -Pressuritation of the Containment Vessel-Pressurization of the source capsules under the condi tions 'of the h hypothetical thermal accident was' demonstrated to generate stresses { well.below the: yield strength of the capsule material-as described in. ? Sec t ion 3. 6. 3. - Therefore, the containment will withstand the pressure variations of normal transport. H4.2.3-Coolant Contamination i .t 'Not applicable. i c 'l i REVISION 1 DECEMBER.1989 PAGE.21 hm2

$ {> ' ;g ,r J pS - " ;t --_,s 'ibj k, s 3 JC> 2p , j .e . ( r - 4. 2. A l ' Coo l a'nt Loss P'- f 'Not; appl-icabie. . t ) Dl, ' 4. 3,- Containment Recuirementa for'the'HvDothetIcal Accident Condition

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t l', 5 t j= -4.3.1 Fission-Gas Products i 1 i l '- -Not. applicable. t'l.L 4.3.2-Release of Contents 'I -a c .The hypothetical accident conditions of 10 CFR 71.73 will result in"noi l f I . loss;of package containment..This conclusion.is' based on'information information' presented in Sections' 2.71.'2.7.2.,2.7.3. 2. 7. 4 ', and 3.5. m, t

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g s ; - o 01 a 1 i .g I cv v + SECTION-5 SHIELDING EVALUATION' i y s b([i , 5.1 : Discussion and Results ? 3

The pr.inciple, shielding of the Model 660 is the uranium shield l

assembly. The mass of,the uraniurn shield is 16.8 kg p' ,(37m lbs). .i A radiation profile of-Model-660, Serial Number 4537, was made.using q" - en AN/PDR-27(R) survey' meter, Serial Number.1-130. 'The-Model 660' ~ > _ J-co'ntained 107 Curles'of Iridium-192 as Amersham Source Assembly A424-9.SerialfNumber'8534.' The results of these. measurements are q presented below. ;The, maximum radiation' intensity measured at'the . surface of the container was 127;milliroentgens per hour, and the-imaximum intensity measured at l' meter was 1.0 milliroentgens per-hour.-_ Extrapolating these measurements to the maximum container .j 2! t capacityfof 140 curies demonstrates that-the rediation levels are il below the. regulatory. limits.- 5.2, Source Soecificat'lon. 5.'E. l ' Gamma SourceL 'The' gamma source'isLiridium-192 in a sealed. capsule as special form. Jradioactive material in quant.ities up to 140 curies. 5.2.21 : Neutron-Source ii. < Not applicable. c 5.3-Model-Soecification LNot' applicable.; 5.4.Shieldino Evaluatlon-2A shielding efficiency testaof a Model 660'containing 107 curies.of- -Iridium-1921was-performed. The results of'this test, which'are-presented;in Section 2.10. demonstrated that the. dose rates surrounding.this-package are within the regulatory limits. t 0 REVISION'l F' .: DECEMBER'1989. PAGE-23 L.a

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,-y n, 1 SECTION 6 CRITICALITY EVALUATION Not applicable. V t t. ), b.e L ? F- [ hI [. . - REVISION 1 DECEMBER 1989 PAGE 25 r hiG% Ajn L w-4

SECTION ' OPERATING PAOCEDLAES 7.1 Pr ocedure for Loadina the Packace The procedure for fabricating the special form source capsule is preser ted in Section 7.5.1. The procedure for loading the source assemt' 11 es into the package is also included in Sectior 7.5.1. 7.2 Procedure for Usina the E oosure Device The pr oc edure for performing industrial redlegraphy with the Model 660 exposure device is included in Section 7.5.2. 7.3 Procedure 4or Unloadina the Packaae The procedure for unloading the package is presented in Sec t i o n 7.5.2. 7.4 Preparatton of a Packace for Transport The procedure for preparation o t' a paCLage for t r e. n s p o r t 1g anCluded in the Model 660 Instruction Manual presented in Eection 7.5.2. REVISION 1 DECEMBER 198Q PAGE 26

h 7.5 Appendi-7.5.1 Procedure for Encaosulation of Sealed Sources 7.5.2 Model 660 E=oosure Device Operation Manual REVISION 1 DECEMBER 1987 PAGE 27

BADIATIGE S&FETY BWR&L Part B 1a Plant Operottons Section 2. ENCAPSULATION OF SEALED SOURCES A. Personnel Reautrements Only an individual qualified as a Radiological Technician shall perform the operations associated with the encapsulation of sealed sources. A second Radiological Technician must be available in the building when these operations are being perf ormed. B. General Requirements 1. In the Burlington, Ma, facility, a loading cell shall be used for the encapsulation of sealed sources and repackaging of sealed sources. The maximum amount and form of radioactive material which may be handled in the loading cell is specified below: Radioisotope Form Maximum Activity Iridium-192 Solid Metallic 2000 curies Cobalt-60 Solid Metallic or sealed sources I curie Cesium-137 Sealed Sources only 100 curies Ytterbium-169 Sealed Source _s only 100 curies Tantalum-182 Sealed Metallic or Solid Carbide 100 curies Gadolinium-153 Solid Oxide 300 curies Limits for any other radioisotopes or forms shall be specified by the Radiation Protection and Gencral Safety Committee. 2. The loading and general purpose hot cells are designed to be operated at less than atmospheric pressure. The exhaust blower should not be turned off during the operation or at any time that radioactive material is in the cell. 3. Unencapsulated radioactive material shall not be stored in these cells when the cell is unattended. Material may only be stored inside these cells in welded capsules or screw top capsules. When radioactive material is stored in these cells, a radioactive material tag identifying the types, quantities, locations and storage dates of all such material shall be attached to the manipulator or to the cell body adjacent to the window. 4. When any "through the wall" tool is removed, the opening shall be closed with the plug provided. All tools shall be decontaminated whenever they are removed from the cell. B.2.2 REVISIOR 12 12 APRIL 89

5. Each individual performing this operatien must wear a film badg3 and prckst desinator at vaist lovol and a sacend film badge and pockot dosimetor in the vicinity of the head. All speratiens must be monitorod with a calibrated and operational radiation survey meter. C. Preparatory Procedure 1. Record the names and initial pocket dosimeter readings for the personnel performing the loading operation on the Loading Log Sheet. 2. Check the cell lights for proper operation. Check the cell manipulators both visually and operationally. Assure that all cell ports are plugged. 3. Assure that the exhaust system is operational. Record the manometer reading on the Loading Log Sheet. If the manometer reading is less than 0.5 inch or greater than 2.0 inches of water, the filter must be changed. 4. Assure that the air sampling system is operational and that sample filters are in place. S. Perform the pre-operational contamination survey as indicated on the Loading Log Sheet. Record the results on the Loading Log Sheet. 6. Perform the encapsulation procedure omitting the insertion of any activity. Examine this phantom capsule weld. If this weld is acceptable, preparation of active capsules may proceed. If the weld is not acceptable, the condition responsible for this unacceptable weld must be corrected and an acceptable t hantom capsule weld produced prior to proceeding. This step must also be p rlarmed each time the welding electrode is changed. D. Encapsulation Procedure 1. Prior to use, assemble and visually inspect the two capsule components to assure the weld zone does not exhibit any misalignment and/or separation. Defective capsules shall be rejected. 2. Degrease capsule components in the Ultrasonic Bath, using isopropyl alcohol as degressing agent, for a period of 30 minutes. Dry the capsule components at 100 C for a minimum of 20 minutes. 3. Insert capsule components into hot cell with the posting bar. 4. Place capsule bottom in weld positioning device. Withdraw the posting bar. 5. Move the drawer bar of the source transfer container into the loading cell. Open the screw top capsule. 6. Withdraw the proper amount of activity from the screw top capsule and place it in the capsule bottom. A brass rivet must be used with wafers to prevent contamination of weld zone. B.2.3 REVI SI ON 12 12 APRIL 89

7. Ass:re that all unused redicoctive motorial is removed from the leoding cell by 12 stalling it in the scrou tsp capsulo Ond eithdroving the drower bar cf the source transfer container from the cell. 1 8. Remove the rivet (if applicable). 9. Assemble the capsule components.

10. Weld in accordance with the written welding procedure for the capsule being welded.

11. Visually inspect the weld.

An acceptable weld must be continuous without cratering, cracks or evidence of blow out. If the weld is defective, the capsule must be cleaned and re-welded to acceptable conditions or disposed of as radioactive waste. 12. Check the capsule in the height gauge to be sure that the weld is at the center of the capsule.

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

14 Count the patch with the scaler counting system. The patch must show no more than 0.005 microcurie of contamination. If the patch shows more than 0.005 microcurie, the capsule must be cleaned and re-wiped. If the re s.pe patch still shows more than 0.005 of contamination, steps 10 through 14 must be repeated. 15. Vacuum bubble test the capsule. Place the welded capsule in a glass vial containing isopropyl alcohol. Apply a vacuum of 15 inch Hg(Gauge) while alertly watching the capsule for the emergence of bubbles. Any visual detection of bubbles will indicate a leaking source. If the source is determined to be leaking, place the source in a dry vacuum ' vial and boil off the residual alcohol. Re-weld the capsule; repeat steps 10 through 15. 16. Transfer the welded source capsule to the sealed source section of the loading cell. 17. For wire mounted source capsules, transfer the capsule to the swaging fixture. Insert the wire and connector assembly and swage. Hydraulic pressure should not be less than 1250 nor more than 1500 pounds. For source holder mounted source capsules, transfer the capsule to the appropriate source holder loading fixture. Insert the source capsule into the source holder. Screw the source holder together and install the roll pin (if applicable). Check to assure that the pin does not protrude on either side. 18. Apply the tensile test to assembly between the capsule and connector (where applicable) by applying proof load of 100 lbs. Extension under the load shall not exceed 0.05 inch. If the extension ex eeds 0.05 inch, the source must be disposed of as radioactive waste. B.2.4 l REVISIOB 12 1 bC 12 APRIL 89 l

19. Assuro that the coll tunnel door is clocod.

P:sitten the ocurce in the omit port af the looding cell. Uoo the remoto etntrol to insert the searce into the isn chamber and p;siticn the sturco for maximum response. Record t the meter reading. Compute the activity in curies and fill out a temporary source tag.

20. Again using remote control, eject the source from cell into source changer or transport container through the tube gauze wipe test fixture. Monitor the radiation level as the cell tunnel shielded door is opened. Ramove the tube gauze and count with scaler counting system. This assay must show no more than 0.005 microcurie.

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

21. Secure the source in the source changer or transport container and remove the container from the source loading area.

22. At the end of the day's operations, perform the post-operational contamination survey as indicated on the Loading Log Sheet. Record the results on the Loading Log Sheet.

23. Record the final pocket dosimeter readings for the personnel performing the loading operation on the Loading Log Sheet.

24. Record the daily air sample results on the Loading Log Sheet. B.2.5 RevISIos 12 12 APRIL 39 73

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MODEu e20 EaF05UAE DEc!CE I OpEAATICN MA% A u ? NOT1CE 1 Thlb dev1Ce is used as a endlegraph ic e - p o st ure devlte and ',pe $( si transpor t pac & age fcr Amersham Corporation r edioactase sour tes 1isted in this ma nua l. The user should become thorcuahls familiar with the Instcuttlon manua] Def er e attemot3no aperatitn of the eaulcment. In order to use th is e a u t p er e n t tc perform industrial radlograpt y within the United States. the aser must be specif ically 12 censed to c3 so. Appl 1tation +ce a license thould be f iled on Form NRC 313 n1*- the appropr2 ate U.S. Nucleer Rec;u 1 a t o r Comma 55lon Peglona1 1+( 1e listed in Appendi n of 10 CFR 20 or with the appropriate 4;"eement state office. l i Prnor t0 init1al use of a rad 1ograph ic e posure desice as a tr erspor e package. the user le the nited States s must register h is eamei lic ense numbe* and pac 6 age t de' t 1 4 itatIcn '.u mb e r with D1rettor Off ice of Nuc ; ear M aterial Sa'et, and Safeguards U.S. Nuclear Rego;ator3 ccmm2seaon Washington, nC 205S5 The user mu s t has e in i s possession a cop. of U$NPC Certi f Comp) lance No, G033 i s s u e cs for th is patLage. icate 0+ Prior to the f i rst e port shipment of th is errosure device f r om the .a United States, the., s e r must also register his identit3 wtth 1 Off ice of u acardous Ma t er i a l s Regulatio' Matertals Transportation Bureau U.S. Department 0+ 7ranspor t a t 10,- Washington, DC 20S;0 The user %5 t "a e in h is possesston a cop, cf : nter 'at1: cal A t o r* 1 ; Energy Agencs Cert 1f 1 tate of C:*petent Autborit Number USA 0033 E 155ued for this radlograph ic e posure des 1te. e y Users of this equipme-t outsace the united Stoltes r egu l a t or s, licens ng are tra spo.,atir most c:~g., est-tr e u;es 3 r.a re p at r app!v in tmeir es c er t i s e : our t r s.s o ,r e, 5. General the Model ee0 ser'es rsrtatle gavma 'adlogeaph' ss+te+ m"e Ee0 primaril, f or Industrial radiagraph, e s,stens :pe a'e manner and di*fer on1s in tre spe.';; c : n t r- - 'lt s4o1te5-s;' u-PEVISION 1 DECEMBEP 1989 RA3E Ee o (_________ _ __ _ _ _ - _ - _ - _ _ - - _ - - - - -- - - - - ~ '

The basic radacgraphy system corsists of t*e Model t60 adlographic r evposure device, the source dri,e assemtl, and the scu' ce qu;oe tube. The exposure device serves as tFe storage erd t a r'so o r t pac age for the radioactive source. Safety-S y 5 t e rr s The systems ar e designed to pros 13e ma=1 mum oper a t oi safety Thece is a positive mechanical contrel of the source, and the odometer provides a visual indication of the sourte's position. In addition, the source connector is designed to be +all-safe so that: 1. The system cannnt be operated Isource exposed' unless a seture connection of the source assembly to the drive cable is madet and 2. The control unit cannot be d15 connected unless the radioact1.e source assemb13 15 properlv stored in the shield. Radletion Safetv Consider etions Pursuant to USNRC and agreement state regulations, all personnel present durIng radiographic and source changing operations are required to wear a d i r ec t reading pocLet dosameter and either a f11m badge or a thermoluninescent dos 1 meter rTLD) The pocket dos 1 meter must be recharged at the st ar t of each sh i ft. The operator should f r equent l y check the pocket dosameter reading throughout the shift. Dos 1 meter readings must be recorded at the end of each shift. Records of the initial and final readings of the pc;ket dostmeter must be kept for inspection by the USNAC. In the esent that a person's pocLet dostmeter 15 found to be off scale, that person must stop all work with radiation immediately. His f11m badge to, TLD must be bent in immediatelv for pr ocessing, and he must not reenter a restr icted area urt11 at has b ee r, cetermined that he received less than the ma Imam ellowed occupatlonal e posure as def ined in 10 CFA 20.101 Personnel be fc" ming source c h a ng i r1g and radic;rsphic ;ce'st2crs must also hase a calibrated and oper able radiation sur sev reter 'apeble of measering f,om 2 mA'hr to at least 1000 mA hr to .? e t e r m i n e rediation levels when performing these operations. adiog,aphy is perfarmed must be Areas in which source changing or r Identified. If a perTaneet radlographic installation is used, it must have the approorlate personne'. access control c e s.1 c e s as ee<: ned 1 10 CFR 20,2D3. Other wise, certale, areas Tru s t be estab11sked as follows: Access to the Restr1cted Area m ust be tr c. led. A Restricted Area is defined in 10 :rR 105 as tne area wtere an Individual could receiv e ar e pcsure i e cess r-of two ml111rcentgens In an v one rour. c-100 REvlSION 1 DECEMBER 1099 PAGE 20

i milliroentgens in seven consecutive days or 500 milliroentgens in one year. The Restr ic ted Area should also be posted with signs reading " Caution (or Danger) - Radiation Area." Signs reading " Caution (or Danger) - high Radiation Area" should be posted around the perimeter where an individual could receive an exposure in excess of 100 milliroentgens in any one hour. The radiographer or radiographer's assistant must guard against unauthorized entrance into these areas at all times. No personnel should be allowed into the restricted area without a direct reading pocket dosimeter and either a film badge or TLD. Receipt of Radioactive Maternal 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. 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 hours after it was received during normal working hours. Radiation levels should not exceed 200 milliroentgens per hour at the surface of the exposure device, nor 10 miliroentgens per hour at a distance of three feet from the surface. Actual radiation levels should be recorded on the receiving report. If the radiation levels exceed these limits, the container should be secured in a Restricted Area, and th'e appropriate personnel notified. 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. peeration 1. Survey the entire circumference of the exposure device to assure the source is properly stored and to obtain a reference reeding of the radiographic exposure device. Assure that the device is locked. 2. Position and secure the source stop of the master source guide tube at the radiographic focal position using the tripod stand and swivel clamps. REVISION 1 DECEMBER 1989 l PAGE 30

3. Determine wher e the e=posur e desice wall be positior.ed and connect the extended source guide tubes as reQuared, la, log them as straight as possible and with no bend radius less than twenty inches. ($maller bend rad 11 will reftract the moseTent of the Control Jable' NOTE: Ne.er operate the system with more than three gulde tube sections ( including the master) 4 Pemove the storage plug from the exposure device and connect the source guide tube (s) to the e*posure device. 5. Determane where the control un1t will be positioned i ds far away from the radiographic focal position as possible end preferably behind a radiation shleld) and lay out the control housing with no bend red 11 less than 36 Inches. 6. Jorme:t

he control unit to the e posure device according to the illustrated s e O _ e n r. e : n r;g.,es ! tkrough 5.

Fef-e ce'at :- : re: L all cc' wctions and tend adz ard c',et* the pos 'i-r 't.e a.c re +.;. e.:F cprese"ts t"e radlographlt focal position of the source. 8. Check the operation of the survey meter by reading the radiation level at the s u r f' a c e of the e po'sure device. It should read no more than 200 mP/hr for a 140 curie Iridium-192 source. 9 Unlock the exposure device lock and rctate the selector ring to the OPERATE position. Move the lock slide to the right, so that the red Indicator shows. The source is now free to move. 10. Aeturn to the control unit. Adjust the odometer reset knob to obtain a 000 reeding on the odometer. 11. Recheck to be sure that no unauthorized personnel are inside the Restr itted Area. 12. Rapidls otate the crank 1^ the EiPDEE i ounterclocLwise) e 01 r et t l o n to move the source to the radiographic focal positlon. The survey meter should read about full scale <1000 mP/hr for a 100 curie Iridium 102 source when the source f irst leaves the exposure device, drop gradually as the source is driven to the radiographic focal position, and remain steady durIng the e<posure. TFe survey meter readings wil te substartially reduced i f the meter 15 oCerated behind a radiatlor sh leld or f a collitatct 15 ased. REVISION 1 DECEMBER 1789 PAGE 31

13. When the source reaches the scarce stop, the hand crank will stop turning. Never exert more than 5 ft.-Its. of torcue cn the hand crank, as this nay cause damage to the ccetr ol unat or dri /e cable. The odometer eading will indicate the total distance the source has traveled ( appro=1mately 7 ft. for one Ecurce guide tube sectioni 14 ft. for two source guide tube sections, and El i t, for three sections) Set t he Dr ak e to ON to prevent move ~emt of the source during the ewposure. 14 F i gur e the specimen erposure time from the moment the source reaches the source stop. 15. During the e=posure, spent as little time as poss1ble in the Restricted Area to minim 1ce personnel e=posure. 16. To return the source to the e=oosure device after the desired exposure time has elapsed, tur n the brake to DFP and rapidly turn the Crank in the RETRACT (clockwise) directnon until the trank will no longer move. The odometer should read 000. OurIng this process. the sur vey meter should indicate a continually i nc r eas i ng radtation level up to appro imatelv 1000 mR/hr for a 100 cuile iridium-192 source. then drop to background level when the source is shielded In the e*Cosure dev1Ce. 17 Approach the eaposure device with the survey meter and survey the e posure device on all sides. The meter should Indicate the same radiation level as obser sed A rt step 8 of Operation. 18. The 'ock slide will automaticallv secu re the source in the shielded position. The 511de w111 show the green Indicator when the source is proper]3 stored. 19. Survey the entire source guide tube with the sur vey meter. If the meter shows a sharp increase, the source could still be e posed or incompletely shielded. 20. If the source is still e pcsed, attempt to store it properlv O, tran*1^g the source a short dlstacce t o.v a r d the source stop ana retracting it, repeating If necessar 21 If the source becomes jammed in an e posed positicn, do not tr to retrleve the source. Treat the situation as a rs emergency; notify the super visor and Amersham for helt l' necessary REVISION 1 DECEMBE9 1999 PAGE 32

22. when the source is proper 1y stored in the e posure device rctete the selector ring from the OPERATE position to the LOCK cosition and secure it with the e Cosure deel;e loce, NOTE: If the selector ring cannot be rotated to the L DC* Position. the source has not been fully retracted. Imec6 the ctr't ol unit ndometer reading. It should De 000. Turn the hand cranL to the full clockwise 'AETPAC direction. 23. Unlock the exposure device, and rotate the selector Ing from r LOCH to connect. The control unit connetter will partiall, disengage. 24 Refer to F igur es 1 through 5 to disengage the control unit from the exposure dev i c e. 25. Replace the storage tover in the control unit connector and rotate the selector ring to the LOCF position. Aemose the >e and engage the lock to sec.ure the enposure devace. Survey the entire circumference of the evposure devic e with the sursey meter to ensure the source is properly secured. 26. Unscrew the source guide tube sections and remove the master guide tube from the tripod stand. Place the plastic caps on the tubes and on the Model 661 connector to ellmlnate dust and dirt from entering the tubes. 27. Insert the storage plug into the guace tube connector and taghten. 28. Disassemble the tripod stand and store the system where it will not be subjected to any undue stress or abuse. Source Changes Source changes may be performed using Amersham Model e50 uource changer. .v h i c h also serves as a shipping Container, The Spec f a c instructiors for the appropriate source changer should be followed to perform e sour c e exchange. The source e-change mast be done ir a Resteacted Area as prevlously descr1 bed. The same personnel monitoring requirements and safety precautloos prevlously descr1 Dea for performing radiography must also be followed in performing scurce e channes. 1. Su r ves the souece changer to ensure the source is o t"e p oper b+; rage pag 1tice, 2. Positton the source changer and e posure desice clcse together so that one settion of source guide tube wl l conrect them with oc sharp t ur ns or bends. The berd adias of the gu.de t.be showid r neser be less than twenty nches. 5"orter bend rad 11 can restract source tovement in the sou"ce guide tute. REVISION 1 DECEMBER 1989 PA3E 33

3 Remose the stor age plug from t e e posur e des I c e, and attach the source guide tube. Remose the source changer coser and attach the other end of the tube to the empty chamber 0 the source 4 Changer. 4 Attach the Contr01 unit to the e=posure d e s' a c e as in Step 6 of the operating procedure. 5. Crank the source rapidly from the exposure device to the source changer. During this process. the survey meter reading should increase ( to approwimately 1000 mP/hr for a 100 curie Iridium-192 source) as the source is first evposedi fall slightly as the source 15 being cranked out. then drop to background when the source is in the source changer. 6. Approach the source changer and source guide tube with the sursey meter to ensLre that the source is fully within the source changer. 7 Open the source guides and disconnect the drive cable from the source assembly bv moving the lock pin down and sliding the drive cable connector out through the keyway. 8. Disconnect the source guide tube from the source changer, ]f a replacement source 15 to be Installed in the e=posure device, connect the source guide tube to the fitting above the chamber containing the new source and couple the crlve cable to the

source, if the source is being removed to service the e=pos desIce. connect the drive cable to the jumper that is Cllppeo inside the storage coser of the e v oost.r e device.

9 Return to the controls and cr ank the new source (or jumperi into the exposure device. If e new source 15 being transferred. the sursev meter reading should increase as the source leaves the source changer and approaches the esposure device, then drop to backg ound lesel when the source is shieldec .o the e posure dev ic e. 14 a jumper 15 being transferred, the su ses meter r should I 'dtcate only backgroa'd radlatic, lesels. 10. Sursey tte exposure device tc ensu' e that the pr ocess h6s been properlv completed. Radlatlon levels should read no more th.n 200 mR/hr at the surface of the e posurE device 1+ a new 1*O curie source has been transferred. If the jumper is in the e=posure desIce, on1v bac$groand 'adiation should be detected vey meter. Rotate the selector ang to the LOCF bv the sur r position. 11. Surse, the source guide +ube and sour-- changer tc c*eck t at +re source has been cc-rectlv trans+errea. REVISION 1 DECEMBER 1789 PAGE 3-

12. Secure the source's) In the sour ce thanger in accorcance with tr e appropriate source changer 1"str uction manue;. 13. Disconnect the c or+ t o l unit and source guide tube fr om the e ptsure device ab in Step 23 of the Operating Procedure end disconnect the source guide tube from the source thenger 14 Remove the scur ce Identificatton plate from t 'ie e*PCsure dev1ce and attach it with seal w1re to the source holddown cap. 15. If the e posure desite contains a source, aff i-the Identif ication plate of the new source to the e posure dev ic e. If net. attach an EMPTi' tag to the handle of the e posure device. 16. If the source changer is to be transported, surs ey it to determine the correct sh ipping label reQuared as in Shipping Radioactave Matertal (Radiation levels must not e ceed 200 mR-hr at the surface nor 10 mR/hr at one meter from the surface.' Bolt the source changer cover in place and secure it with seal wire. 17 Return the.ource changer promptlv to Amersham. Demurrage rental charges will be assessed for containers held beyond normal operating time. Shipment of Radloactive Source 1. Ensur e that the source is loc L ed into place in its storage position. To check th;s, the lock should be In the down position, the Ley removed, and tt e selecttr ring should be Immobile. Attach a tamper prcof securitv seal with an Identification mark to the storage plug. 2. If the shipping c o n t a i ner 1s to be pac 6 aged In a crate or other outer pec6 aging. the outer pac k ag i ng must be strong enough 'o wit" stand the normal conditions of t r a.,s p c r t. 7hese re-qul ements are outlined in 10 CPR '1. The sh apping container shculd be out in the outer p a c: > a g e with s ff iclent blocking to prevent shi fting during tranEccrtation. PEVISION 1 DECEMBER 1989 PAGE 35

a l l 3. Perform a radioattive contaminatton wipe test of the outer shipping package. Th is consists of rubbing 1.ter paper or other absorb 5"'(16 ""S "S"' ""'*' ='"' "" ' ' "

b' of the package surface The ectivat, on the 100 cm In f ilter paper se_

'~ ot e ceed 2.20'. ~# 'E*C able

^tenir4+:

5 e,

"e

e.sye n.to o

e ae'er a* 're sa- *sce s..) et d i s t anc e of rw <r e ' e - >m t ', e sa <a e t r o t e re ; e the pr,. radioactive shipping labels to be applied to the pac k age as required bv 49 CF4 172.403. The radiation exposure limits for each shipping label are given in Figu re 4.1. ]f radiatlon levels abose E00 mP hr at the surface or 10 mR/hr one meter from the surface are measured, the container must not be shipped. 5. Proper)v comolete *wo shipping labels indicating the radioactive isotope, attivity ard the Trarsport Inde. The Transport Inde= 15 used only on vellow 11 and Yellow III labels and is defined as the maximum radiation level in mi l l a r oent gens per hour measur ed et a distance of one meter from the surface of the package. Put these two labels on opposite sides of the container after making sure any prevlous labeln hase been removed. The package should be marked with the proper shipping name (Radioactive Material. Spectal rorm, n.c.s., JN 2974) If the exposure device le packaged insice an outer container, mark the outside packege 'INSIDE PAC > AGE COMPLIES WITH PRESCRIBED SPECIFICATIONS - TYPE B USA /CO33,Biui. 6. Complete the appropriate sh ipping papers - These shipping papers must Irclude: a. Proper shipoing Name ( Radioattive Material. Special Form, n.o.s. and Identif ication Number (UN 2974). b. Name of Radionuclide ( IrIdtam-192'. c. Actis Ity cf the Source in [r :es d. Categor of Label Applied '1.e. Aa~;rattive vellow 11) y e. Tcarsport Inde. f. Package Identification Number 1.e. JSA'OO33 BiU> Tvpe B U) g. Shipper 's Certi f icatler. 'This is to ter ti f that the abo,e nated Tatertale are p Operl', v classi f leo. descr1 bed. packaged. mar ed and laceled and are proper cCnditlor for transport accte ding to the applicable regulations of the Department of Transpor tatIcn. REVISION 1 DECEMBER 1989 PAGE 35

1 l l l l Notes: 1. For air shipments, the following shipper's certification may be used: "I hereby certify that the contents of this consignment are fully and accurately described above by proper shipping name and are classified, packed, marked and labeled, and are in proper condition for carriage by air according to applicable national govermental regulations." 2. For air shipments to, from or through the United States, a " CARGO AIRCRAFT ONLY" label and the shipping papers must states "THIS SHIPMENT IS WITHIN THE LIMITATIONS PRESCRIBED FOR CARGO ONLY AIRCRAFT." 6. Due to the dupleted uranium used as shielding in the exposure device, a notice must also be enclosed in or on the package included with the packing list, or otherwise forwarded with the package. This notice must include the name of the consignor or consignee and the following statement: "This package conforms to the conditions and limitations specified in 49 CFR 173.424 for expected radioactive material, articles manufactured f: om depleted uranium, UN 2909 7. For shipment of an empty exposure devtee. assure that there is no source in the container. If the radiation level is below 0.5 mR/hr at the surface, and there is no measurable radiation level at one meter from the container, no label is required. Mark the-outside of the package with the proper shipping name (Radioactive material. articles manufactured from depleted uranium. UN 2909). Mark the outside of the package: " Exempt from specification packaging, shipping paper and certification, marking and labeling and exempt from the requirements of Part 175 per 49 CFR 173.421-1 and 49 CFR 173.424." Additionally, a notice must be enclosed in our on the package included with the packing list or otherwise forwarded with the package. This notice must include the name of the consignor or consignee and the statement: "This packnge conforms to the conditions and limitations specified in 49 CFR 173.424 for excepted radioactive materials, articles manufactured from depleted uranium, UN 2909." REVISION 1 DECEMBER 1989 PAGE 37

l $?% %~I y! 6: plhWC N' Mn k PWL4 "1 !!f, x N I .s 9: ao ~ a f8., . Ret'urnsthe=containersto' Amersham' Corporation accordingsto proper; I g,

procedures 7For transporting. radioactive material-as established'
i

'W ',St E Jin 49 CFR 171-178n i ^

NOTEF The U.S.EDepartment of Transportation. 1n 49 CFR 173.22;

{ l

(c) reouires,each shipper of Ty'pe B-quantitiescof radioacti-ve-l

. ma t e'r i a l t -to provide" prior notification to the consignee'of the 3 [%* ~ dates:of shipment and expected, arrival. s i '4 4 . Maintenance ~ N :'. .~ Inspection'and' maintenance'of;the1Model l9 660 exposure 'evice andither d -contro1Lunit~must'be' performed at intervals not to exceed three -) ?mo n th's'in 'i n - acc or da nce wi t h 10-CFR 34.28. l u n

i cDrive. Cable,' Control-Housings and Source Guide Tubes t

s y.

11

-Disconnect the' control unit from the exposure device.1 I o 2. Turn the hand. crank of the control unit in.the EXPOSE,(counter. M . clockwise)Ldirection until the trank will no longer turn; Do.not. juse' force,Das this may damage 1the drive wheel inside'thefcontrol cox. The-' emergent cable _should be cranked'into a. bucket ~or other' container to keep it clean. 3... Disconnect the1 control housing from the' RETRACT' side of. the . crank:and remove the stop-spr.ing from the-drive. cable.._ The. d r.i ve; 7 . c ab l'e. w i l'ltnow pass through the crank. 'l

4.,

-Turn:-theicrank until the drive cable is. totally disconnected. 5. Pull-the drive cable out through: the Model 661 control; cable ~ connector-and coil'it with a radius of'no less than 4Dinches. i 6.- ' Remove'the Model 661 control cable connector and connector plug! from'the control housings, and' disconnect the other1 control -2 housingffrom the crank. Label the housings-for proper i -reassemble. 1 2 7.- Clean the drive' cable with chlorothene and flush the control 4 housings and source guide tubes. i 8. Using compressed dry air (15 psi max.), thoroughly dry the drivef d ' cable, control housings and guide tubes. Any remainir.g sol ~ vent -can cause permanent damage. 9 tCheck the source guide tubes for binding by holding them vertical- ~ and dropping a dummy source (or jumper) through them. s 1 l s s . REVISION 1 TDECEMBER'1989 T PAGE 38 .w k t 4

M rc h 10 Wipe the guide tubes and control housings with a cloth soaked in chlorothene and flex them to check for internal damage. Damage is evidenced by.a crunching feeling when t' ? houoing or tube is bent. While doing this, feel for dents. Cut, flattened or burnt control housings or guide tubes should be repaired or replaced, 11. The guide tubes or control housings may be covered with tape where only the outer plastic is cut through. 12. Using a Model 550 no-go guage, check the male connector of the drive cable. If the ball of the connector fits through the hole of the guage or the ball shank fits into the slot in the guage, the connector is worn and the cable must be replaced. Refer to Figure 7.1. 13. Lightly grease the cable using Mil-G-23827 B grease or equivalent. Other greases may form tars or corrosive compounds when exposed to r a d i a t -i o n. ' ' Exposure Device To service the exposure device, remove the source following the source . changing procedures. (Before removing the source, check the female' drive cable connector of the source with a Model 550 no-go guage, as in Figure 7.11 if the gauge width can fit into the female slot, the connector is worn and the source must be replaced.) After the source has been removed, service the exposure device by performing the following steps: 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. 3. Unlock the connector lock, and then remove the lock assembly and control unit connector assembly by unscrewing the six socket head screws securing them to the rear plate. 4 Disassemble the control unit connector assembly, referring to Figure 7.2 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 7.2 for component identification and for order of removal. Remove the lock (BT from the lock retainer (3) by unscrewing the screw (4) and turning the key about 900 1 . REVISION 1 DECEMBER 1989 PAGE 39

7 m c +tr 3 1: ~ y; 1 W ,m' c 6".1 2 Remove-the) front end plategfrom the exposure device, and remove. theJguideltube connector and retaining ring with Tru Arefpliers, [ ~ 'referringLto. Figure'7.2. _-The. handle may.be.leftfon the front jg = plate.' E7 > Clean a~11c. parts-;in chlorothene and flush the source tube with q so l v e n t '.. Dry. the. parts.and the. source-tube-thoroughly using dry-l compressed-air;.(20. psi. maximum). Clean the<S-Tube in the

i w;

, exposure device by runningia cloth soaked with'chlorothene, gr ,through it:severalLtimes. Dry the S-Tube by running a dry' cloth n~ -through;the tube. I e o ,l8.

]nspect,all. parts.forfdamage or excessive 4' ear.and replace if r

necessary. .Use Figure 7.21for component identification-4 numbers. 4 9. -- Light'ly, grease.all moving parts at'their contact; Surfaces ~with .t M1-G-23827 8-grease.or equivalent. -10. -Reassemble the. front'end plate.-and secure it to the exposure

device withithe proper. screws.

'VU ..11. Reassemble.theflock'by placing the return springs'and spring guides into the lock (2),L depressing' the. internal plunger,- l inserting the lock -(2) into-the lock 1 retainer (3),Lan securing Q .the lockLwith the set sc r ew.( 4'). I ~$ ' 12. Attach 1theTlock assembly to the rear plate with two socket hess screws. 13. JTo. reassemble the-control' uni.t connector assembly,. refer-to tFigure 7,2. 11 4.; Refer nto FigureE7.2 and place ~the' compression spring (11) on the hub-of the-selector _ ring retainer._ The spring'should be firmly - sea ted ~- over the hub. Then place-the sleeve (12) on-top.of the compression spring _(11)' -15. Place the selector body (6)-on a flat surface so that it-is d resting on its 5/8" hub' i U 16. Insert the two short compression springs (8).and locking pins (7). into the holes ' ort the edge of_ the selector ~ body. 17.1 Place;the selector ring (10) over the selector body (6) while restraining the locking pins (7). Ensure that the lettering: !(OPERATE-LOCK-CONNECT) on the selector 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 7.2. i REVISION 1

DECEMBER 1989 PAGE 40

ff?? Rbc; ~ Il Ri; ' V ' :n V: i ' i 3< '

18.

Hold;theDselector r i ng.(.10 ).and-selector body'(6') together.and p' place <them over the assembl y - shown in Figure :7.2.' The resulting = assembly.is shown in Figure-7.2.. Align the-resulting' assembly (, such'that' the two large holes in the sel ec t or r i ng - r e t a i ner1 l( 9 )- j 111ne up with the two11arge holes in the selector body-E(6). The p(, -internal. locking-cam wi'll' partially-block these holes. b ,I ns e r.t the. anti-rotation lugs (13). and.long. compression: springs-1 j .- 19. i t (14)finto the-two large holes in the selector _ body. Secure the-resulting; assembly.onto the rear plate ~with'four socket 1 head l D {' iscrews. The word OPERATE should be facing outward,'and should be in the.12 o' clock pcsition. [ '20.- Connect'the jumper-to the'short length drive cable and. insert the; c; ,Ly lc'able through the-rear end plate and control unit' connector; a assembly.' l P-21. Insert a U-tool.into the control unit connector assembly a n'd ] ' check;the operation by turning the selector ring'from OPERATE to CONNECT:several-times. If the-connector assembly.does not j operate-proper.ly,idisassemble and inspect the parts for1 damage. and prop'er ~lignment. Relubricate'the parts and reassemble.: a s i 22. Secure the rear end plate to the exposure device and handle-using j 2 the'six attaching phi.llips head screws and replace the protective;

g plate over_the bottom two rear plate screws using pop rivets.

(0.125 in. diameter x 0.295 in long). s 23. ' Chec k' 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.Section VI, Source-Changes. + 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.g Check the exposure device for the proper labels. i -? f 1 L .1 REVISION 1 2 DECEMBER 1989 PAGE 41 i -At

Cable connection: Connect the drive cable to the source projector as shown.in fig. 5.2. (c) Press back the spring loaded locking pin with a thumb nail and engage the (a) Unlock with the key and turn the male and female portions of the swivel selector ring from LOCK to CONNECT. coupling. The storage cover will disengage from the projector. Raum s.2nn ,(. (b) Slide the control cable collar back ' - ).- .w l and open the jaws to expose the male y ball-end on the drive cable). / portion of the swivel coupling (ie. the Raure s.2m i ~ c ?' w z {. 4.pgf "", f {< 'f g 71 4 gt y hjf&: '-l l .l' j pi T l s ly: i t t .K l Y ~ /_ y ;....,,_, d __ ^ ;; ? ' h'. l "^ w. - Ap.. M -c =, }3 A % #>y' ' gs ' 1 l. . #9 j, g, > ;t,, .q; 4L' MM i y + N. '.h ,_ L; i ., ' ' ' ~ gg FAN ~ gw T l, [ "' : f 9; hkl 4;.cz,.- ?'l '/ f Q ,'_y; hs.- hk e M s :g. 1 . :q qy;.:.. 4 (.y, [/. ff.A. . *, ye (d) Release the locking pin and check that the connection is secure. kgy $tk%k$hiff['b2 S. 5.: l p ( ls:ii..\\$ [ ($l 8 d f c ; i f f 5 - h[ Close the jaws of the control cable i Of# connector over the swivel coupling. f f h-);'lfk,k/y Ja g l Figure 1 Figure 2 l f \\.\\ l

l l (e) Slide the control cable collar over the (f) Push and hold the control cable collar connector jaws. flush against the projector connector and rotate the selector ring from CON-Figure s.2nin NECT to LOCK. r"n .J;~ Do not rotate past LOCK. The drive cable connector is now locked into the projector. Floure 5.2nvi

. ;'~'.~

xr 73 -. t. e ,1; ,y -tg 4 i ' [r,

f,

' yps sh .- '3 f khh ~ i ^?I f- + g; .g; t. $l 4 t' ~ l'

gy'

[ v. g' { dp ^ y@ds INote that the drive cable connector, when' properly installed with the selector ring in (g) Keep the projector in the LOCK posi-the CONNECT position, displaces anti-tion until ready to start the exposure. rotation lugs which allows the selector ring to be rotated to the LOCK position and when required, through to the OPERATE position. Figure 6 A"

7_, _. .. - -.-.. ~ - -. - 5.,.

L 4;

l 61. 1 -j ; 1 l (II) ball shank 'k A. T?. 'g,. (1) ball diampr ',,..{,.,, l +k se (iv) connector gap width (111) female slot width B i- [.l-l '. y l' t Figure 7.1 i f$ b i !g

. +. ~. J 21 $>2 ' k*n *' 5 i \\ E neenal gg hun ger g ~k 11 A) * \\\\ ', s l 3 / / y N NV 'd / 4 13 'N ky d 18 'gpf 14. g - \\ @ /,

N 8

i8 j g/ D s I sY Y' 16 \\ \\ h"'I D 6- \\ / 1 12 AMERTEST* 660 GAMMA RAY PROJECTOR U 000 Repolt Kit g Port # Code Kit 402 Ret # Cet Code U.S.A. Oty Deectlption Oty in Kit [ 1 TMN1 2 Socket Head screw 10 32x5/8 in. A 'g 3 2 TSN66011 66001 11 1 Lock [ dmd d. l J 3 TSN66012 66001 12 1 Lock Retainer 4 1 Saew(supplied w/ Item 2) 1 5 1 Internal Plunger 10 6 . TSN66001 66001 1 1 Selector Body 7. TSN66005 660015 2 Locking Pin 'a TSNO321 2 Compression spring (LC-032E 1) 2, 6 of E R A yg -9 TSN66003 660013 1 Selector Ring Retainer 10 TSN66000 660018 1 Seiector Ring 7 g O 11 TSN0541 1'- Compression Spring 1 8 p* - 12 TSN66004 66001 4 1 - Sleeve 13. TSN66006 - 660016 2 Ann-Rotauon Lugs 7 % o 14 TSN0267 2 ' Compression Spnng 2 2 15 TMN1 ~4 Socket Head Screws 8 4 10-32x1 1/4 in. (st. steel) )G - 16. TMN1 4 Lock Washer, #10 4 17 TSN53311 53301 11 1 Guide Tube Connector Nut '18 TMN1 1 Retalning Ring 19 TSN002 LBL-010 1 Sourceiconefication Plate 20 1/4 20x3/4* PH Screws 8 21 66001 811 Key 2 22 - 4 4-40 3/16 BHMS (for lock) 4 10 '\\ 6 23 -1 6-32 x 5/8* (for 2 \\ 24 10-32x3/8* S.S. Allen Screw 4 h @4 66001 20 1 Jumper Connector 1

30 Drill Bit 1

/ 12 1/8' S.S. Pop Rivets 12 k'l 1 6 Links of Cover Chain 1 1 84 Scott Drive Saews 5/6* 2 \\ . GRE TUB Grease 1 0 660 CL Check List 1 MAN-006 1 660 Operatontw%nt. Manual L J ~ Figure 7.2 k t

-SECTION 8 ' ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.1 Acceptance Tests 8.1.1 Visual inspection The package is visually examined to assure that the. appropriate fasteners are properly seal wired. The package is inspected to assure Ethat the' proper marking and labeling is present. The; seal weld of the radioactive source capsule is' visually inspected for-proper-closure. 8.1.2 Structural and Pressure Tests The swage coupling between the source capsule and cable is subjected to'a-static tensile-test with a.-load of one hundred pounds. .8.1.3 Leak Tests The radioactive source capsules which serves as the primary containment.,is wipe, tented for leakage of radioactive contamination. 3 EThe source capsule is subjected to a vacuum bubble leak test. These ' tests are described in Section 7.5.1. Failure of either--of these tests'will prevent use of this source assembly. '8.1. 4 ' C'omeonent tests The lock assembly of the package is tested to. assure that the security of the source will be maintained. A simulated (dummy) source assemoly is installed in the radiographic exposure device and the lockbox locked. An attempt is made 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. l ~. 5 Tests for Shieldina Inteority

+J i t h the package containing a source assembly, the radiation levels at the surface of the package-and at one meter 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 EmR/hr at one meter from the surface. 8.1.6 Thermal Acceptance Tests Not applicable. REVISION 1 DECEMBER 1989 PAGE 42

s (;. 4 -8.2' Maintenance Proaram 8.2.1 Structural and Pressure Tests Not-applicable. H8.2.2. Leak Tests As described in section-8.1.3, the radioactive source assembly is leak tested at manufacture. Additionally, the source assembly is wipe -tested for leakage of radioactive contamination every six months. -8.2.3 . Subsystem Maintenance The lockbox assembly is tested as described in section 8.1.4 prior to each use of the package. Additionally, the package is inspected for tightness of fasteners, proper seal. wires, and general condition before~each use. 18. 2. 4 Valves, Ruoture Discs, and Gaskets Not applicable. 8.2.5 Shieldino Priorfto each use, a radiation survey of the package is made to. assure. .that the radiation levels do not exceed 200 milliroentgens per hour.at-the surface nor 2 milliroentgens per hour at one meter from the surface. 8.2.6 Thermal Not' applicable. 8.2.7 Miscellaneous Inspections and tests designed for secondary users of this package under the general license provisions of 10 CFR 71.12(b) are included in Section 7.4 REVISION 1 DECEMBER 1989 PAGE 43}}

ML20005E932

Text

SUBJECT:

SUBJECT:

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