ML19289E389
| ML19289E389 | |
| Person / Time | |
|---|---|
| Site: | 07109126, 07109127 |
| Issue date: | 04/06/1979 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19289E387 | List: |
| References | |
| NUDOCS 7904170369 | |
| Download: ML19289E389 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION SAFETY EVALUATION OF THE TRANSPORTATION 8 RANCH DIVISION OF FUEL CYCLE AND MATERIAL SAFETY GAMMA INDUSTRIES Model Hos. 20, 20A, 50, 50A, 100, 100A, 200. 200A and C-8 Packaoing USA /9126/B( )
USA /9127/B( )
USA /9128/B( )
Revision 1 Enclosure to ltr dtd APR 0 g 1979 Summary By application dated May 20, 1978 Gamma Industries requested approval of the Model Nos. 20, 20A, 50, 50A, 100, 100A, 200, 200A and C-8 shipping packages to be used for shipment of radiographic sources containing cobalt-60 in special form.
Based on the statements and representations presented in the application, we have concluded the packaging and contents meet the requirements of 10 CFR Part 71, for the proposed contents, subject to the conditions contained herein.
References Gamma Industries application and supplement dated May 20 and October 25, 1978, respect:vely.
Drawings The packaging is constructed in accordance with Gamma Industries Drawings Nos. 180-01, 821-1001-128, 821-1001-129, 821-1001-033, 191, 821-1001-347, 821-1001-389, 821-1001-116, 821-1001-414, 811-1001-346, 811-1001-408, 801-1001-336, 801-1001-228, 801-1001-283, 801-1001-538, 801-1001-224 and 801-1001-159.
Descrintion The Model Nos. 20, 20A, 50, 50A, 100, 100A, 200 and 200A industrial radiographic devices used in nondestructive testing are also designed for use as Type B shipping containers for radiographic sources in special form.
The Model No. C-8 source exchanger for radiographic devices is also designed for use as a Type B shipping container for radiographic sources in special form.
The capacity of the shipping containers vary from 20 to 200 curies of cobalt-60 in special form as 7 9 0 417 0 3G9
s a function of specific model number.
The radiographic device shipping containers measure approximately 21 inches long, 23 inches wide and 42 inches high, The source exchanger shipping container measures approxi-mately 16 inches in diameter, 13 inches wide and 26 inches high.
The radioactive source assembly is housed in a Zircalloy or titanium "S" tube.
The tube is surrounded by depleted uranium metal as shielding material.
The depleted uranium shield assembly is encased in a steel housing.
The void space between the depleted uranium shield assembly and the outer container is filled with a polyurethane foam.
The gross weight of the containers vary from 325 to 500 pounds as a function of specific model number.
Contents The contents consist of cobalt-60 as sealed sources that meet the require-ments of special form as defined in 10 CFR 671.4(o).
The contents are limited as follows:
flodel No.
Content Limit 20, 20A 20 Curies 50, 50A 50 Curies 100, 100A 100 Curies 200, 200A, C-8 200 Curies Structural Our review of the structural analysis submitted by the applicant demon-strates that the Model Nos. 20, 20A, 50, 50A, 100, 100A, 200, 200A and C-8 packages satisfy the structural requirements for the normal condi-tions of transport, as well as for the hypothetical accident.
The applicant has demonstrated by analysis and by results of testing that the subject package does meet the requirements of the normal conditions of transport.
The evaluation of the ability of the package to meet the structural requirements of the hypothetical accident conditions is based upon actual test results.
The shipping container was dropped from a height of 30 feet onto a flat surface, ar.d subsequently dropped from a height of 40 inches onto a steel bar six inches in diameter and eight inches high.
As a result of these tests, there was no reduction in shielding effectiveness nor loss of radioactive material.
Detailed information regarding the free drop and puncture tests are a part of the tests report and are presented by the applicant.
Thermal The staff has reviewed the therm l 50, 50A applican,t for100, 100A, 200, 200A and C a
analysis
-8 packages provided by theof t damage conditionsnormal conditions of conclusions were r.The applicant's thermal a transport and for the a
. concluded that the package satisfies th eviewed and found to be satisfnalyses, test r 71.
ccident Based on our actory.
and Shielding review of the package, we coe thermal req ncur with that conclusion FR The shield for theapplicant has demonstrated th cobalt-60 loadings fornormal and accident damageei tion of gamma profile m each model. conditions for the respectivource Cha uranium 200 and C-8 series For normal conditions easurements e maximum for the 20 series),were36 Ci Co-63 for(the 50 susing at one meter from the surfaat the surfa
, extrapola-made showing no dose rate greater theries an and no dose rate greater th demonstrating shield andFor accident damage co ce.
an 145 mr/hr an 5 mr/hr containment integrityons, two Model 200 was used in the dose rate increases wer models for both thick and thi ns were tested 40 inch puncture test n housings.A 34 Ci Co-60 source e measured af ter the 30 foot d loading requested showed Extrapolation of these me No the significant a permissiblsurface, thus demonstrating asurements to therop followed no case to exceed li ar/hr at three feet the package. e limit of 1000 mr/hrsatisfaction of 10 CFR 7136 at 3 feet from the external, which has from Conditions surface of The Gamma Industries Mod l and C-8 packaging is limitedNos. 20, 20A,'50, 50A e
the requirements to source assemblies forof special formcobalt-60 as sealed sourc, 100, 10 use in these packagings are las defined in 10 CF es tha 671. 4(o). t meet The imited as follows:
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LnN A*
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Model No.
Content Limit 20, 20A 20 Curies 50, 50A 50 Curies 100,100A 100 Curies 200, 200A 200 Curies (Q',j?
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fys Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety APR 0 81979 Date:
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