ML20127P259
| ML20127P259 | |
| Person / Time | |
|---|---|
| Site: | 07109006 |
| Issue date: | 04/19/1985 |
| From: | TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.) |
| To: | |
| Shared Package | |
| ML20127P237 | List: |
| References | |
| NUDOCS 8505230734 | |
| Download: ML20127P259 (11) | |
Text
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SAFETY ANALYSIS REPORT TECH / OPS, INC.
MODEL AI 589 SU i
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TYPE B(U) PACKAGE USA /9006/B (0)
Revision 1 19 April 1985 O
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Surrounding the lockbox assembly is the protective cover.
This cover is fabricated f rom Type 384 stainless steel and is attached to the package shell by means of a hinge and a seal - bolt.
.The head of the seal bolt is drilled to provide a means for attaching tamperproof seal wire during transport.
4 On certain packages, additional shielding plates are installed to reduce the surface radiation level.
These plates are 6.4 mm (0.25 inch) thick and welded to the out-side of the package as described on drawing AI 500 SU 93.
The outer packaging is designed to avoid the collection and retention of water.
The package has a smooth, unpainted stainless steel finish to provide for easy decontamination.
The radioactive material is sealed inside a stainless steel source capsule.
This capsule acts as the containment vessel for the radioactive material.
- 1. 2 2 : Denxakinnal Esakvxas The source holder assembly is secured in the proper shielded storage position by means of the locking assembly.
With the source holder assembly in the proper shielded storage posi-tion, a cap is installed over the source holder assembly and attached to the lockbox.
This cap is sealwired to prevent inadvertent loosening.
An outer protective cover is u
installed over the lockbox and is locked in the closed position to prevent unauthorized access.
1.2.3 C9D%sDks 92 kb2 EDGkA99 i
The Model AI 500 SU is designed for t.he transport of i
iridium-192 in quantities up to 120 curies in Tech / Ops source assemblies listed in the appendix.
The source cap-sule used with each of these source assemblies satisfies the criteria for special form radioactive material in accor-dance with 10 CFR 71 and IAEA Safety Series No.
6, 1973 Revised Edition (as amended).
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1-2 Revision 1 19 April 1985 O
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Drawing AI500SU90 Sheets 1 through 3 Drawing AI500SU91 Drawing 42402-1 Drawing 42402-4 Drawing AI 500SU92 Drawing AI 500SU93 s-e 1-3 Revision 1 19 April 1985
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k 7.4 App 2Dd13 7.4.1 Procedure for Encapsulation of Sealed Sources 7.4.2 Model AI See SD Source Changer Operation Manual
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v 7-2 Revision 1 19 April 1985 O
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7.4.1 - PrecGdura for Encip::ulaticn cf S2alad Scurc33 RADIATION SAFETY MANUAL Port'B - In Plcnt Operotions Section 2-
'l ENCAPSULATION OF SEALED SOURCES A.. Personnel Requirements f
Only an' individual qualified,as a Radiological Technician ~shall perform the operations associated with the encapsulation of sealed i
sources.
A second Radiological Technician must be available in the i
building when these operations are being performed.
B.
General Recuirements
- 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 EnIm Maximum Activity Iridium-192 Solid Metallic 2099 curies Cobalt-69 Solid Metallic or sealed sources 1 curie Cesium-137 Sealed Sources only 180 curies Ytterbium-169 Sealed Sources only 100 curies
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Tantalum-182 Sealed Metallic or 190' curies Solid Carbide Limits for any other radioisotopes or forms shall be specified by the Radiation Safety Committee.
- 2. In the Pho'enixville, PA facility, the general purpose hot 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 cell is specified below:
Radioisotope Form Maximum Activity Iridium-192 Solid Metallic 29,999 curies Cobalt-60 Solid Metallic 1 curie Cobalt-69 Sealed Sources 390 curies Cesium-137 Sealed Sources 299 curies Ytterbium-169 Sealed Sources 190 curies Tantalum-182 Solid Metallic or 100 c.uries Solid Carbide
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Limits for other radioisotopes or forms shall be specified by the Radiation Safety Committee.
7-3 Revision 3 19 April 1985 m
4 Tech / Ops, Inc.
TecSOps
- Mediaton Products DMelon J
so mem A nnue 7.4.2 moDEL AI 500 SU nuruneton. wesemusette cteos eisphone tsuj m-acco SOURCE CHANGER OPERATION MANUAL NOTICE This device is used as k radiographic source changer and Type B(U) transport package for Tech / Ops, Inc. radioactive sources listed in this manual.
Tha.unar abould becomm. thoroughly familiar-with.the instruction manual before attempting operation nf the eauipment.
In order to use this equipment to perform source changes within the United States, the user must be specifically licensed to do so.
Application for a license should be filed on Form NRC-313R with the appropriate U.S.
Nuclear Regulatory Commission Regional Office -listed-in Appendix D of 10 CFR 20 or with the appropriate agreement state office.
Prior to initial use of the source changer as a transport package, the user in the United States must register his name, license number and package identification number with:
Director Office-of Nuclear Material Safety and Safeguards ik U.S. Nuclear Regulatory Commission Washington, DC 20555 TheusermusthkveinhispossessionacopyofUSNRCcertificate of Compliance Number 9006 issued for this package.
Prior to the first export shipment of this source changer from the United States, the user must also regi' ster his identity with:
Office of Hazardous Materials Regulation Materials Transportation Bureau U. S. Department of Transportation Washington, DC 20590 The user-must have in.his possession a copy of International Atomic Energy Agency Certificate of Competent Authority Number USA /9006/B(U)T issued for this source changer.
Users of this equipment outside the United States must comply with the regulatory, licensing and transportation rules and regulations as they apply in their respective countries.
O 7-9 Revision 1 19 April 1985
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8.8 bCGR9kADGB ZRnks ADO BaiDktDDDGB R1991Rm 8.1 bCGR9tBDGR Staks 8.1.1 yianBI InspsChisD The package is visually examined to assure that the apprc-priate f asteners are properly seal wired.
The package is inspected to assure that the proper marking and labeling is present.
The seal weld of the radioactive source capsule is visually inspected for proper closure.
8.1.2 Skxncknxal BDD Exssanzt Zsska 1
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 Laak Taska The radioactive source capsule, which serves as the primary containment, is wipe tested for leakage of radioactive contamination.
The source capsule is subjected to a vacuum bubble leak test.
These tests are described in Section 7.4.1.
Failure of either of these tests will prevent use of this source assembly.
8.1.4
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The lock assembly (source holddown 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 source changer and the appropriate source holddown cap is ins.talled.
Verification is made that the source holddown cap contacts the source assembly prior to the threads being fully bottomed.
A check is made that the holddown cap is securely attached to the device.
Failure of this test will prevent use of the package until the cause of the failure is corrected and retested.
8.1.5 Zests 191 ShisidiDS 1Dksgxikx With the package containing a source assembly, the radia-tion levels at the surface of the package and at one meter from the surfcce of the package are measured using a small detector survey instrument.
These radiation levels, when 8-1 Revision 1 19 April 1985
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extrapolated to the rated capacity of the package, must not exceed 288 milliroentgens per hour at the surface of the f].
-package.
8.1.6 Tb2Ianl Ass 2&knDs2 Tasks Not applicable.
8.2 BaiDksDnDGs R19ssam l
8.2.1 Skxnsknxal ADD Exssanxs Zenks i
Not applicable.
4 8.2.2 Lenk Tasks As described in Section 8.1. 3, - the radioactive source assembly is leak tested at manufacture.
Additionally, the source aasembly is wipe tested for leakage of radioactive contamination every six months.
8.2.3 BDksXskRE EniDkRDDDGR The source holddown 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 prior to each use.
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8.2.4 Mals w ED&kDER DiSGsz DDD Gasksha Not applicable.
8.2.5 BhisldiD9 Prior to 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 ten milliroent-gens per hour at three feet from the surface.
8.2.6 Tb2Ianl Not applicable.'
i 8.2.7 BissallDDDDus l
l-Inspections and tests designed for secondary users of this package under the general license provisions of 10CFR71.12 (b) are included in Section 7.4 8-2 Revision 1 19 April 1985 0
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