ML19257D150
| ML19257D150 | |
| Person / Time | |
|---|---|
| Site: | 07105796 |
| Issue date: | 01/17/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19257D149 | List: |
| References | |
| NUDOCS 8002010388 | |
| Download: ML19257D150 (3) | |
Text
Form NRC418 U.S. NUCLEAR 7EGULATORY COMMISSION CERTIFICATE OF COMPLIANCE to CFR 71 Fos Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package identification No.
1 (d) Pages No.
5796 2
USA /5796/B( )
1 1.(e) Tot 5
- o. Pages iN
. 2. PRE AMBLE 2.la)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Departmet t of Trarsportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146--19-100 ef tN Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.lb)
The packaging and cxantents described in 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 consignor 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 transported.
- 3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.f a) Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Picker Corporation Picker Corporation application dated 1020 London Road December 19, 1974, as supplemented Cleveland, OH 44110 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in item 5 oeiow.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, Other Conditions, and
References:
(a) Packaging (1) Model Nos.:
181375 and 181361 (2) Description Overpacks that provide impact and thermal protection for teletharapy head assemblies or source exchange assemblies. The cubical overpacks 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 incnes.
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 3,325 pounds.
Dimensions of the itdel No.181361 are 39"x39.5"x 48" with a maximum gross weight of 4,000 pounds.
(3) Drawings The packagings are constructed in accordance with the following Picker Corporation Drawing Nos.:
(1) Model No. 181375: 0-18375, Rev. G; C-181368, Rev. B; D-181369, Rev. B; and C-55156, Rev. B, with teletherapy heaos Drawings Nos.;
D-63790; C-46879, Rev. C; D-184713; B-184704; D-16424-E, Rev. D; D-16423B, Rev. F; and B-T60A-547.
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Page 2 - Certificate No. 5796 - Revision No. 2 - Docket No. 71-5796 5.
(a) Packaging (continued)
(3) Drawings (continued)
(ii) Model No. 181361: D-181361, Rev. D; C-181357, Rev. D; C-181355, Rev. 0; B-181390, Rev. A, wi th source exchange assembly Drawing 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-13709B.
(b) Contents (1) Type and fonn 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 in the form of cesium chloride c.._apsulated in sealed sources that meet the requirements of special form as defined in 571.4(o) of 10 CFR Part 71 or in sealed sources constructed and inspected in accordance with Picker Corporation letter dated January 4,1980.
The sources are to be packaged in secondary inner con-tainers 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).
2,200 curies, with a radioactive decay heat load not to exceed 17 watts.
6.
The packages autnorized by this certificate are hereby approved for use under the general license provisions of 10 CFR 571.12(b).
7.
Expiration date: December 31, 1980.
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Page 3 - Certificate No. 5796 - Revision No. 2 - Docket No. 71-5796 REFERENCES Picker Corporation application dated December 19, 1974.
Supplement dated: October 17,1975; May 29 and August 15, 1979; and January 4, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
1855 3S4
.