ML19212A423
| ML19212A423 | |
| Person / Time | |
|---|---|
| Site: | 07105796, 07109011 |
| Issue date: | 09/10/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19209A417 | List: |
| References | |
| NUDOCS 7910030818 | |
| Download: ML19212A423 (3) | |
Text
.
Form NRC 618 U.S. NUCLE AR REGULATORY COMMISSION U
CERTIFICATE OF COMPUANCE 10 CFR 71 For Radioactive Materials Packages 1.fa) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) P 1.(e) Total No. Pages 5796 1
USA /5796/B( )
1es No.
2
- 2. PREAMELE 2.ta)
This certificate is issued to satisfy 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 Sectens 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.tb)
The packaging and contents described in item S below, meets the safety standards set forth in Subpart C of Title 10. Cada.
Federal Regulations. Part 71. " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditens."
2.(c)
This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicaole regulatory agencies, including the r,overnment of any country through or into which the package wdl be transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or applicatiorr 3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Picker Corporation Picker Corporstion application dated 1020 London Road December 19, 1974, as supplemented Cleveland, OH 44110 3.fc)
Docket No. 71-5796
- 4. CCNDITIONS This certificate is conditional upon the fulfilling of the reouirements of Subpart D of 10 CFR 71, as applicable. and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized G)ntents, Model Nurncer, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Models Nos.: 181375 and 181361 (2) Description Overpacks that provide impact and thernal protection for teletherapy head assemblies or source exchange assemblies. The cubical overpacks s
consist of laminated 2x4 hardwood maple panels bolted together and covered with 16 gage steel panels.
Reinforcing steel straps and angles are welded together and spaced to limit the openings between them to less than 6 inches.
Skid runners are provided to facilitate fork lift usage.
Dimensions of the Model No. 181375 are 37"x40"x41" with a maximum gross weight of 3325 pounds. Dimensions of the Model No.181361 are 39"x39.5"x 48" with a maximum gross weight of 4000 pounds.
(3) Drawings 1086
'l5 The packagings are constructed in accordance with the Lllowing Picker Corpor& tion Drawings Nos.:
(1) Model No. 181375: 0-18375, Rev. G; C-181368, Rev. B; D-181369, Rev. B; and C-55156, Rev. B, with teletherapy heads Drawings Nos.;
D-63790; C-46879, Rev. C; D-184713; B-184704; D-16424-E, Rev. D; D-16423B, Rev. F; and B-Te0A-547.
Page 2 - Certificate No. 5796 - Revision No. 1 - Docket No. 71-5796 5.
(a)
Packaging (continued)
(3) Drawings (continued)
(ii) Model No. 181361: D-181361 Rev. 0; C-181357 Rev. D; C-181356 Rev. 0; B-181390 Rev. A, with source exchange assembly Drawings Nos.; D-T60-478; B-13708-A; B-37092-A Rev. C; C-13707-A Rev. C: B-14241A; D-T60-558; and C-13709A or C-137098.
l (b'
Contents (1) Type and form of material (i) Cobalt-60 sealed sources that meet the requirements of special form as defined in 571.4(o) of 10 CFR Part 71.
The sources are to be packaged in secondary inner con-tainers as described in 5(a)(3)(i) or 5(a)(3)(ii)
Drawing Nos.
(ii) Cesium-137 sealed sources that meet the requirements of special fann as defined in 571.4(o) of 10 CFR Part 71. The sources are to be packaged in secondary inner containers as described in 5(a)(3)(ii) Drawing Nos.
(2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i).
13,680 curies, with a radioactive decay heat load not to exceed 200 watts.
(ii) For the contents described in 5(b)(1)(ii).
2200 curies, with a radioactive decay heat load not to exceed 17 watts.
6.
The packages authorized by this Certificate of Compliance are hereby approved for use under the general license provisions of 10 CFR 571.12(b).
7.
Expiration date:
December 31, 1980.
1086 '.C6
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Page 3 - Certificate No. 5796 - Revision No. 1 - Docket No. 71-5796 REFERENCES t
Picker Corporation application dated December 19, 1974.
Supplement dated: October ll,1975; and May 29 and August 15, 1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Dated:
s 1086
^:37
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