ML19341D750
| ML19341D750 | |
| Person / Time | |
|---|---|
| Site: | 07105939 |
| Issue date: | 03/27/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19341D749 | List: |
| References | |
| NUDOCS 8104080714 | |
| Download: ML19341D750 (3) | |
Text
.
O Form NAC 618 U.S. NUCLE AR AEGULAToRY COMVISSloN
[c[q h, CERTIFICATE OF COMPLI ANCE 2 3 For Aadioactsve Materiais Packages IJsl Certificate Numoer 1.!b) Revision W.
1.tc) Pacmage Icentefication No.
1Jd) Pages No. 1.!el Tatal No. Pages 5939 7
USA /5939/B( )F 1
3
- 2. P n E A?.'B L E 2.f a t This certificate is issued to satisfy Sections 173293a.173294.173295. and 173036 of the Oeoart'nent of Transocetacean Mazarcous
- laterials Pequiations 149 CFA 170139 and 14 CFR 100) ano Sections 146-t9-10a ano 146-19-t00 of :ne oeoarn eat of Transoortation congerous Cargoes Aequeations (46 CF R 146-1a91. is arnenced.
2Jbt ne saceaging and centents cescritec in item 5 estow. meets the saferv stancaras :et forth in Sueoart C of Titte to. Coce of 3Eaderat Requtations. Part 71, "Pscuaging of Racicactive Vateriass for Transoort and Transoortation of Radioactive ?.'ater'ai Under Certain Conoitions/'
2.fc)
This certif cate aces not relieve the consignor from comohance wetn anv recuirement of the requiations of tne U.S. Oeoar' ment of Transoortation or ott'er aco+icasse regulatory agencies. inctucirig rne }overnment of any country througn or into.vnic-t **e sacuage will be transoor se.
- 3. This certificars is issuea on tne casrs of a safety anaavses recort of the racmage cesegn or aconcaten-3JJ6 Precaraa av tMme ano addressi:
3.!b)
Title aru iaentification of recort or aconicaten.
General Electric Company General Electric Company application dated P.O. Box 460 February 21, 1980, as supplemented.
Pleasanton, CA 94566 3.tci coc=et No.71-5939 4 CONotTioNS This artificate is conditenal upon the fulfEeng of the requirements of Svocart o of 10 CF t 71, as apodicacio, and the concet.ons specified in item 5 eetow.
- 5. oescription or 7xhaging ano Avenonreo Cont +nts, voces Numcer,
- issue Class. Ctner Conditent. and Peterences.
(a) Packaging
'(1) Model No.: GE-1500 (2) Description A steel encased lead shielded shioping cask. The cask is a double-walled steel circular cylinder, 31-inch-diameter by 48 inches high with a central cavity 7-inch-diameter by 25 inches high.
The diameter it reduced fro;n 31 inches to 17-l/2 inches by cone construction at the top 7-1/2 inches of the cask.
Approximately 11 inches of lead surround the central cavity.
The cask is equipped with a cavity drain line and lifting device.
Closure is accomplished by a gasketed and-bolted steel-lead-filled plug.
A pro-tective jacket ' consisting of an upright circular cylinder with open bottom and a protruding box section diametrically across the top and vertically down the' sides attaches to a square pallet.
Dimensions of the protective jacket'are 60-7/8 inches high by 49-3/4 inches wide across the box section.
The outer cylindrical diameter is 36-1/2 inches and the pallet is 59-1/2 inches square. The maximum weight of the packaging is approximately 15,000 pounds.
8104080m W
Page 2 - Certificate No. 5939 - Revision No. 7 - Docket No. 71-5939 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
706E441, Rev. 12 135C5598, Rev. 2 706E792, Rev.
5 163883S9, Rev. 2 10603858, Rev. 6 12904690, Rev. 0 10603870, Rev. 11 (b) Contents (1) Type and form of material (i) Byproduct material and special nuclear material meeting special form requirements of 10 CFR 571.4(o) and antimony pins encased in stain-less steel; or (ii) Byproduct material in the form of 90SrF2 or 137CsC1.
(2) Maximum quantity of material per package Not to exceed a decay heat generation of 3,120 watts and (i) ' Item 5(b)(1)(i) above:
' Plutonium in excess of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements, and 500 grams U-235 equivalent mass.
(U-235 equivalent mass equals U-235 mass
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plus 1.66 times Pu mass.)
(ii) Item 5(b)(1)(ii) above:
458,000 Ci.
(c) Fissile _ Class III.
Maximum number of packages =per shipment 22 6.
For the contents described in Item 5(b)(1)(ii) ab'ove:
90SrF2 must be encapsulated in accordance with Vitro Drawing Nos. H-2-66759, Rev. 0; and H-2-66758, Rev.--0; or 137CsCl must be encapsulated in aCCordance with Vitro Drawing Nos. H-2-66760, Rev. 0; and H-2-66761, Rev. O.
The 90SrF and 137CsC1 capsules after' fabrication must be leak t'ested using a 2
method having sufficient sensitivity to detect a leak rate (air at standard
Page 3 - Certificate No. 5939 - Revision No. 7 - Docket No. 71-5939
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temperature and pressure leaking to 10 2 atm) of 10 8 atm cc/sec.
Any capsule with a detectable leak may not be delivered to a carrier for transport.
2 7.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
. 8.
Expiration date: April 30, 1982.
l REFERENCES General Electric Company application dated February 21, 1980.
.idditional References Recuired for Contents 5(b)(1)(ii):
Oak Ridge National Laboratory letter dated April 3, 1980.
Supplement dated:
May 7, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
[
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety
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Date:
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