ML20008F046
| ML20008F046 | |
| Person / Time | |
|---|---|
| Site: | 07109143 |
| Issue date: | 02/26/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20008F045 | List: |
| References | |
| NUDOCS 8103120118 | |
| Download: ML20008F046 (5) | |
Text
mu.
Form NRC 618 U.s. NUCLE AR REGULATORY COMMISSION U
7' CERTIFICATE OF COMPLIANCE M CFR M For Radscactive Materis s Packages e
1.(ca Certificate Numoer 1.ib) Revision No.
1.(c) P,ck 1.{di Pages No. 1.(e) Total No. Pages USA /913e identification No.
1 2
3/B( )
9143 0
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisfy Sections 173.3934.173.394,173.395. and 173.396 of the Deoartment of Transportation Hazardous Materia 6s Aegulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10s and 146-19-100 of tne Department of Transportation Qangerous Cargoes Regulations (46 CFR 146-149). as amended.
2.(b)
The packaging and contents described in item $ below. meets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulatsons. Part 71. "Pacnaging of Radioactive Materiais for Transoort and Transoortation of Radioactive Matenal Under Certain Conditions.
2.(c)
This certificate does not relieve the cons gnor from comoliance with any reouirement of the regulations of the U.s. oepartment of Transportation or other applicable regulatory. agencies induding the novernment of any country through or,into wnicn the package will be transoorted.
- 3. This certificate is issued on the basis of a safety analysis report of the package desagn or application-3.(a)
Prepared by (Name and address):
3.tbl Title and identification of report or aootication:
Technical Operations, Inc.
Technical Operations, Inc. application dated Northwest Industrial Park August 1, 1980.
Burlington, MA 01803 3.(c) oocket No.
- 4. CONDITIONS This certificate is condational upon tne fulfilling of the rooverements of Suoport O of 10 CFR 71. as applicaole. and the conditions specified in item 5 below.
- 5. Descriotion of Packaging and Autnorized Contents. Mooel Numoer, Fissile Wass. other Conditions, and
References:
(a)
Paciraging (1) Model No.:.920 (2) Description A stainless steel encased, uranium shielded radiographic device.
The shipping container is 13.0 inches long, 7.7 inches high and 5.3 inches wide.
The radioactive source assembly is housed inside a tungsten source tube.
The source tube is surrounded by depleted uranium metal for shielding.
The depleted uranium shield assembly is encased in a stainless steel housing.
The void space between the uranium shield assembly and stainless steel housing is filled with a castable rigid polyurethane foam.
The gross weight of the container is 47.0 pounds.
(3) Drawings The packaging is constructed in accordance with the following Technical Operations, Inc. Drawing Nos. 92090, Sheets 1, 2, and 3 of'3, Rev. 0; 90090, Sheets 3, and 4 of 4, Rev. 0; and 90091, sheet 1 of 1, Rev. A.
8103120/&
Page 2 - Certificate No. 9143 - Revision No. 0 - Docket No. 74-9143 5.
(b) Contents (1) Type and form of material Iridium-192 as sealed sources which meet the requirements of special form as defined in $71.4(0) of 10 CFR Part 71.
(2) Maximum quantity of material per package 240 curies 6.
The source shall be secured in the shielded position of the packaging by the source assembly.
The source assembly must be fabricated of materials capable of resisting a 1475*F fire environment for one-half hour and maintaining their positioning function.
The source assembly must engage the locking device.
The source assembly must be of sufficient length and diameter to provide positive positioning of the source within the depleted uranium shield assembly.
7.
The name plate shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their legibility.
8.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
9.
Expiration date:
February 28, 1986.
REFERENCE Technical Operations, Inc. application dated August 1, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION 1
&h
_-h Charles t.
acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Dnte:
8261987 l
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U.S. Nuclear Regulatory Commission Safety Evaluation By tne Transportation certification Branch of tne Model No. 920 Packaging USA /9143/8( )
Enc 1 to ltr dtd:
Summary By application dated August 1, 1980, Technical Operations, Inc. requested approval of the Model No. 920 shipping container to be used for shipment of radiographic sources containing iridium-192 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, subject to the conditions contained herein.
Reference Technical Operations, Inc. application dated August 1, 1980.
Drawings _
The packaging is constructed in accordance with Technical Operations, Inc.
j Drawing Nos. 92090, Sheets 1, 2, and 3 of 3, Rev. 0; 90090, Sheets 3 and 4 of 4, Rev. 0; and 90091, Sheet 1 of 1, Rev. A.
i Descriotion The shipping container is a stainless steel encased, uranium shielded radiographic i
device which is also designed for use as a Type B shipping container for radioactive sources in special form.
The shipping container is 13.0 inches long, 7.7 inches high and 5.3 inches wide.
The radioactive source assembly is housed inside a tungsten source tube.
The source tube is surrounded by depleted uranium metal for shielding.
The depleted uranium shield assembly is encased in a stainless steel housing.
The void space between the uranium shield assembly and stainless steel housing is filled with a castable rigid polyurethane foam.
The gross weight of the container is 47.0 pounds.
l Contents 1
The contents consist of iridium-192 as sealed sources that meet the requirements l
of special form as defined in 10 CFR 671.4(o).
The contents are limited to 240 curies of iridium-192 in special form.
l Structural Our review of the applicant's structural analysis indicates that the Model No. 920 package satisfies the structural requirements of 10 CFR 71 for both the normal conditions of transport and the hypothetical accident conditions.
The applicant has demonstrated by analysis, comparison with sim'lar package I
l
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2 and by results of testing of the similar package 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 of a similar package and comparison with the subject package.
The similar 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 of the similar package is a part of the test report and is presented by the applicant.
Thermal The staff has reviewed the thermal analysis of the Model No. 920 package provided by the applicant for normal conditions of transport and for the accident 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 demonstrate 1 by comparison with a similar package on which measurements and analysis were made the adequacy of the depleted uranium shield for the Model No. 920 shipping container under normal and accident damage conditons for the maximum iridium-192 loading of 240 curies.
The DOT normal condition of transport was shown to be'well below the 200 mr/hr surface dose rate limit.
The applicant made a radiation profile measurement of a similar package after it was rubjected to the hypothetical accident conditions.
These measurements show the radiation level to be well below the limit of 1,000 mr/hr at three feet from the surface of the container.
By comparison the applicant concluded that the Model No. 920 would also be below the 1,000 mr/hr limit.
The above results demonstrate satisfaction of 10 CFR 671.36 which has a permissible limit of 1,000 mr/hr at three feet from the external surface of the package under accident conditions.
Conditions ThelechnicalOperations,Inc.ModelNo.920packagingislimitedto240 curies of iridium-192 as sealed sources that meet the requirements of special form as defined in 10 CFR 571.4(o).
The source shall be secured in the shielded position of the packaging by the source 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 source assembly must engage the locking device.
The source assembly must be of sufficient length and diameter to provide positive positioning of the source within the depleted uranium sheld assembly.
The nameplates
3 shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their legibility.
h Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety IE Date:
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