ML20004F988
| ML20004F988 | |
| Person / Time | |
|---|---|
| Site: | 07109149 |
| Issue date: | 06/23/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20004F982 | List: |
| References | |
| NUDOCS 8106260409 | |
| Download: ML20004F988 (3) | |
Text
.
mC.
-11.S. Nuclear Rpquiatory Commission Safety Evaluation by the Transportation Certification Branch of the Model No. 910 Packaging USA /9149/B( )
Encl to ltr dtd: JUN 2 3121 j.
Sumary By application dated April 10, 1981, Technical Operations, Inc. requested approvai of the Model No. 910 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 April 10, 1981.
Drawings The packaging is constructed in accordance with Technical Operations, Inc.
i
- Orawing Nos. 91090, Sheets 1, 2, and 3 of 3, Rev. O and 90090, Sheets 3 and 4 of 4, Rev. O.
Descrbtion The shipping container is a stainless steel encased, uranium shielded radiographic device wh'ch is also designed for use as-a Type B shipping l
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 L
tube is surrounded by depleted uranium metal for shielding. The depleted uranium shield assbmely 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 I
weight of the container is 34.0 pounds.
Contents The coitents consist of iridium-192 as sealed sources that meet the requirements of special fom as defined in 10 CFR 571.4(o). Thc contents are limited to 30 curies of iridium-192 in special form.
[.
g to&?
r
=-tw.y g
y
=-ww--o
--e --ygn,e-,
,.-e, ww w-y
+
w w.--%,e,,ww.,4w w,
,ww.----,
~,-w-v,-w.,
-g,-,-,--iw m-
--w-r--e
P Structural Our review of the applicant's structural analysis indicates that the
-Model _ No. 910 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 and by results of.
- testing of a similar package that the subject package-does meet the requirements of the ' normal conditions of transport. Tne 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 su'usequently 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.
Thema1 The' staff has reviewed the thema1. analysis of the Model No. 910 package provided by. the applicant for. normal conditions of transport and for the accident damage conditions. The applicant's themal analyses, test
~
results, and conclusions were reviewed and 'sund to be satisfactory.
The applicant concluded that the package sa,asfies the themal requirements of 10 CFR 71. Based on our review of the package, we concur with tnat
' conclusion.-
g Shielding,
~ The applicant has demonstrated by measurements 'and analysis the adequacyL l~
of the depleted uranium shield for the Model No. 910 shipping container under normal and accident damage conditions for the maximum iridium-192 1cading of 30 curies. The DOT nomal condition of transport was shown to be satisfied by actual gama profile measurements which gave dose rates well below the 200 mr/hr surface dose rate limit. The applicant j~
made a radiation profile measurement of a similar package after it was subjected to the hypothetical accident conditions. These measurements l
-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 L
concluded that the Model No. 910 would also be below the 1,000 mr/hr l
-limit.
The above results demonstrate satisfaction of 10 CFR 71.36 which has a L
pemissible limit of 1,000 mr/hr at three feet from the external surface of the oackage under accident conditions.
1
[
f I.:u.
a.e+
...m.--
'... -... _ _..../., _ -.. '.....~,-..__,A4._.......~,'-.,,_-----m-.----.,-..,--,,_r...-.
,,,, -., ~, _, _ - ~
Conditions The Technical Operations, Inc. Model No. 910 packaging is limited to 30 -
curies of iridium-192 as sealed sources that meet the requirements of special fann as defined in 10 CFR 571.4(o). The source must be secured-'
-e in tne shielded position of the packaging by the source assembly. The components used to secure the source must be fabricated'of materials i
capable of resisting a 1475'F fire en'/fronment for one-half hour and maintaining their positioning functien.
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. The name plates must be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their legibility.
Y C.1ar es t. MacDonald, Chief Trvisportation Certification Branch Division of Fuel Cycle and Material Safety JUN 2 31981 Date:
g l
s
-n e-.
e m-. - - -,re,...,-,-
.n.,
, -,-+, --,, - - - --,..,,,
+,,,v r