ML19308A254
| ML19308A254 | |
| Person / Time | |
|---|---|
| Site: | 07109127 |
| Issue date: | 01/17/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19308A253 | List: |
| References | |
| NUDOCS 7901250128 | |
| Download: ML19308A254 (6) | |
Text
.
e Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION U
CERTIFICATE OF COMPLIANCE 10 CFR 71 For Radioactive Materiels Packages i
1.(a) Certificate Number 1.(b) Revision No..
1.(c) Package Identification No.
1.(d) Pages No. 1.fe) Seal No. Pages 9127 0
USA /9127/B( )
1 2
- 2. PREAMBLE 2.(a)
This certificate is issued to satssN Sections 173.393a,173.394.173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described en item 5 below, meets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations, Part 71," Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c)
This certificate does not relieve the cnnsignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be tesnsported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Gamma Industries Gamma Industries application dated 2255 Ted Dunham Avenue May 20,1978.
P.O. Box 2543
. Baton Rouge, Louisiana 70821 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of :he requirements of Subpart D of 10 CFR 71, as applicable, and the conditions sp>cified in item 5 below.
- 5. Cescription of Packaging and Authorized Contents Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model Nos.: 100,100A, 200 and 200A (2) Description A steel encased, uranium shielded radiographic device. The shipping containers is approximately 21 inches long, 20 inches wide and 42 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 inner container is filled with a polyurethane foam. The gross weight of the container is 500 pounds.
(3) Drawings The packaging is constructed in accordance with Gamma Indus-tries Drawings Nos. 821-1001-128, 821-1001-129 and 180-01.
(b) Contents (1) Type and form of material Cobalt-60 as sealed sources that meet the requirements of special form as defined in 10 CFR 571.4(o).
7 9 012 5 01 Z3
Page 2 - Certificate No. 9127 - Revision No. 0 - Docket No. 71-9127 (2) Maximum quantity of material per package Model No.
Quantity 100 and 100A 100 curies 200 and 200A 200 curies 6.
The source shall be secured in the shielded position of the packaging by the safety plug assembly, source assembly and lockbox assembly. The components used to secure the source must be fabricated of materials capable of resisting a 1475 F fire environment for one-half hour and maintaining their positioning function. The ball stop of the source assembly must engage the locking device. The flexible cable of the source assembly and safety plug assembly must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.
7.
The can and side plates must be a minimum of 1/4-inch thick carbon steel.
The can and side plates shall be joined by full penetration welds. All other welds shall be fillet welds having sufficient throat thickness to develop strength equal to or greater than the metals beirg joined.
8.
The nameplates shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their legibility.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
10.
Expiration date: October 31, 1983.
REFERENCES Gamma Industries application dated May 20, 1978.
Supplement dated: October 25, 1978.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
[k Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety M'I Date:
UNITED STATES NUCLEAR REGULATORY COMMISSION SAFETY EVALUATION OF THE TRANSPORTATION BRANCH DIVISION OF FUEL CYCLE AND MATERIAL SAFETY GAMMA INDUSTRIES Model Nos. 20, 20A, 50, 50A,100, 100A, 200, 200A and C-8 Packaging USA /9126/B(
USA /9127/B )
USA /9128/B Enclosure to ltr dtd JAN 171979 Summary By application dat?d 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, respectively.
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, 801-1001-328, 801-1001-283, 801-1001-338, 801-1001-224 and 801-1001-159.
Description 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
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.
.r.
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 inner 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:
Model 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, and 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 thermal analysis of the Model Nos. 20, 20A, 50, 50A, 100, 100A, 200, 200A and C-8 packages provided by the applicant for normal conditions of transport and for the accident r.
-damage conditions. The applicant's thermal analyses, test results and conclusions were reviewed and found to be satisfactory.
The applicant concluded that the package satisfies the thermal requirements of 10 CFR
- 71. Based on our review of the package, we concur with that conclusion.
Shielding The applicant has demonstrated the adequacy of the depleted uranium shield for the eight Gammatron Models and Source Changer C-8 under normal and accident damage conditions for the respective maximum cobalt-60 loadings for each model.
For normal conditions, extrapola-tion of gamma profile measurements (using 110 Ci Co-60 for the 100, 200 and C-8. series, 36 Ci Co-60 for the 50 series and 22.8 Ci Co-60 for the 20 series) were made showing no dose rate greater than 145 mr/hr at the surface of each model and no dose rate greater than 5 mr/hr at one meter from the surface.
For accident damage conditions, two Model 200 Gammatrons were tested demonstrating shield and containment integrity.
A 34 Ci Co-60 source was used in the models for both thick and thin housings.
No significant dose rate increases were measured after the 30 foot drop followed by the-40 inch puncture test.
Extrapolation of these meascrements to the loading requested showed no case to exceed 11 mr/hr at three feet from the surface, thus demonstrating satisfaction of 10 CFR 71.36, which has a permissible limit of 1000 mr/hr at 3 feet from the external surface of the package.
Conditions The Gamma Industries Model Nos. 20, 20A, 50, 50A, 100, 100A, 200, 200A and C-8 packaging is limited to cobalt-60 as sealed sources that meet the requirements of special form as defined in 10 CFR 571.4(o). The source assemblies for use in these packagings are limited as follows:
Model No.
Content Limit 20, 20A 20 Curies E,,
10A 50 Curies 1(J, 100A 100 Curies
.200, 200A, C-8 200 Curies ti,e =; h ! f e-
-av,e sc.
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety JAN 171979 Date:
6