ML19341B979
| ML19341B979 | |
| Person / Time | |
|---|---|
| Site: | 07105796 |
| Issue date: | 02/03/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19341B977 | List: |
| References | |
| NUDOCS 8102280328 | |
| Download: ML19341B979 (3) | |
Text
Forri NRC 613 U.S. NUCLEAR AEGLLATORY COMMtSSICN 7='
CERTIFICATE OF COMPL1ANCE
,,"CFA M For Aaoeoactive Materials #acmages 1.tal Certaricate Nurneer 1.lb) Revision No.
1.(c) Pacuage toontificaticn No.
1.fdl hges No. 1.tes Total No hges 57CA 3
USA /5706/B( )
1 3
- 2. PREAMBLE 2.tal This certificate is issweJ to satisfy Sections 173. l93a.173.094.173.035 arts 173.036 of tne Decartment of Transoortatica dazarcous Vateriais Aegulations (49 CFA 170-189 and 14 CFR 103) and Sections 146-19-10a ano 146-19-1C0 of tne cecartment of Transportation Cangerous Cargoes Aegulations 146 CF A 146-1496, as amenceo.
2.'.b)
The oscnagmg and contents cesenbec in itern 5 besow, meets the safety stanoarcs set fortn n Suemart C of Titte 10. Coce of Feoeran Regulations. Part 71. "8acuaging of Racioactive Materiass for Transport and fransportation of Racioactive Matenat Unoer Certain Conostans.*
2.fc)
Thes c&itificate does not reheve the consignor from comphance witn any recuerement of rne regulations of !ne U.S. cecartment of Transportation or sener aochcaole regulatory.agenc:es. inctuoing tne government at any country througn or into v.nicn the cacuage will be transoorted.
- 3. ihis certificate is issued on tne basss of a safety analysis report of the package oesign or acchcation-3.la n Prepared by (Narne and address):
3.(b)
Title and identification of reoort or sootication:
Advanc5dMedicalSystems,Inc.
Picker Corporation application dated 1020 London Road December 19, 1974, as supplemented Cleveland, OH 44110 3.let Cocuet No. v.c;yog 4 CONORTIONS
% s certificate is conditional uoon the fulfilling of the recuarements of Suboart o of to CF A 71. as acosicsoie and ene conoitions soeofied in item $ below.
- 5. Cescription at Packaasne ano Autnonzea Centents. Mc:ces Nurnoer, F;ssde C: ass. other Conditions. and Peterences:
(a) Packaging (1) Model Nos.:
181375 and 181561 (2)' Description Overpacks that provide impact and thermal protection for teletherapy 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 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 3,325 pounds. Dimensions of the Model No. 181361 are 39"x39.5"x 48" with a maximum gross weight of 4,000 pounds.
(3) Orawings The packagings are constructed in accordance with the following Picker Corporation Drawing Nos.:
(1) Model No. 181375:
0-18375, Rev. G; C-181363, Rev. B D-181369, Rev. 8; and C-55156, Rev. B, with teletherapy heads Drawings Nos.; 0-63790; C-46879, Rev. C; D-184713; B-184704; D-16424-E, Dev. 0; 0-164238, Rev. F; and B-T60A-547.
O O OO 3 AE
'Page 2 - Certificate No. 5796 - Revision No. 3 - Docket No. 71-5796 5.
(a) Packaging (continued)
(3) Drawings (continued)
(ii) Model No. 181361:
0-181361, Rev. 0; C-181357, Rev. 0; C-181356, Rev. 0; B-181390, Rev. A, with 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-137098.
(b) Contents (1) Type and form of material (i) Cobalt-60 sealed sources that meet the requirements of special form
' as defined in 971.4(o) of 10 CFR Part 71.
The sources are to be packaged in secondary inner containers as described in 5(a)(3)(i) or 5(a)(3)(ii) Drawing Nos.
(ii) Cesium-137 ir, the form of cesium chloride encapsulated in sealed sources that meet the requirements of special form as defined in s71.4(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 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).
8 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' authorized by this certificate are hereby approved for use under the general license provisions of 10 CFR 571.12(b).
7.
Expiration date:
June 30, 1981.
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i Page 3 - Certificate No. 5796 - Revision No. 3 - Docket No. 71-5796 REFERENCES Picker Corporation application dated December 19, 1974.
Supplements dated: Octooer 17, 1975; May 29 and August 15, 1979; and January 4, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
- = df i
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and i
Material Safety FES 0 31931 Date:
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Advanced Medical Systems. Inc.
Model Nos. 181375 and 181361 Docket No. 71-5796 1.
Drawings provided in the Appendix 1.3 are not appropriate for incorporation in the Certificate of Compliance.
Provide consolidated drawings showing the general arrangement of the package, the materials of construction, size of welds, internal supports / connections of the irradiator machine head and the source shipping / exchange containers to the overpack, lifting and tie-down systems, and the design features and dimensions that are import nt to the safe performance of the package.
' 2.
Many typographical and computational errors were found in Sections 2.4.4 and 2.5.
Please revise these sections.
.3.
The assumption of a 3-inch deformation in Section 2.7.1.0.1 to obtain the equivalent g load developed by 30 ft free fall is arbitrary and is contradictory to your conclusion in Section 2.7.5.1 that a deformation approximately 1/4 inch for a top drop and only 0.006 inch for a bottom drop will be resulted by the 30 ft drop.
Provide analysis to show:
(a) The packaging can withstand a much larger g load and thus, a smaller deformation may be assumed to calculate the equivalent g load.
Iterations may be necessary until the assumed deformation are approximately the same as the calculated deformation.
(b) There.will be no appreciable damage to the irradiator machine head or the source shipping / exchange container if the deformation calculated by. (a) is larger than those indicated in Section 2.7.5.1 4.
'In Sections 2.7.1.0.4 and 2.7.1.0.5, it has shown that the energy produced by 30 ft (upside down) top drop is equal to 3,360,000 in-lb and the total energy absorbed by the overpack on impact is only 68,200 in-lb.
Provide an analysis to show how the remaining energy is dissipated and the extent of damage the irradiator machine head will suffer.
5.
As an alternative to the above Items 3 and 4, tests may be conducted to demonstrate that the packages meet the performance standards of 10 CFR 571.36.
.