ML19339C240
| ML19339C240 | |
| Person / Time | |
|---|---|
| Site: | 07105939 |
| Issue date: | 10/31/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19339C237 | List: |
| References | |
| NUDOCS 8011170888 | |
| Download: ML19339C240 (3) | |
Text
i e
9 form NAC618 U.S. NUCLEAR AEGULAToRY CoMMISStoN U
CERTIFICATE OF COMPLIANCE 10 CF9 71 For Radioactive Materials Pacmages 1.tal Certificate Numoer 1.(b) Revision No.
1.tc) Pachece acentification No.
1.(d) Pages No. 1.(e) Total No. Pages 5939 6
USA /5939/8( )F 1
3
- 2. PAEAMBLE 2.f a)
This certi icate is issued to satisfy Sections 173.393a.173.394.173.395. and 173.396 of the oeoartment of Transoortaten Hazardous f
Materials Aegulations 149 CFA 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the oeoartment of Transoortation oangerous Cargoes Regulations (46 CFR 146-149). as amended.
2abi The packagirig and contents described in item s below, meets the safety standards set forth in Suecart C of Titie 10. Code of Federal Regulations, Part 71. " Packaging of Radioactive Materials for Transport and Transportation of Racioactive Material Under Certain Conditcas."
3.tc)
This certificate does not relieve tne consegnor from comoeiance with any reouirement of the regulations of the U.S. oeoartment of -
Transportation or otner acolicaole regulatory agencies. encluding the government of any country througn or into whsch the package wdl be transoorted.
- 3. This certificate is issued on the basis of a safety analysis reoort of the package design or aposication-3.(a)
Prepared by (Name and address):
3.!b)
Titte and identification of report or aoolication:
General Electric Company General Electric Company application dated l
P.O. Box 460.
February 21, 1980, as supplemented.
Pleasanton, CA 94566 3.te) oocket No.71-5939 4 CoNoiTioNS This certificate is concitonal upon the fulfilling of the recuirements of Subpart O of to CFR 71. as apodicacio, and the conditens specified in item s below.
- 5. oescription of Pacnaging and Autnorized Contents. Model Numoor. Fissde Class. Ctner Conditions, and
References:
(a) Packaging (1) Model No.:
GE-1500 (2) Description A steel encased lead shielded shipping 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 is reduced from-31 inches to 17-1/2 inches by cone construction at the top 7-1/2 inches cf 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.
i
\\
801377o
%BR i
Pag'. 2 - Certificate No. 5939 - Revision No. 6 - 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 163B8389, Rev. 2 106D3858, Rev. 6 12904690, Rev. 0 106D3870, Ree. 11 (b) Contents (1) Type and form of material (i) Byproduct material and special nuclear material meeting special form requirements of 10 CFR 671.4(o) and antimony pins encased in stain-less steel; or (ii) Byproduct material in the form of 90SrF 2 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 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) above:
00SrF shall be encapsulated in accordance with Vitro _Orawing Nos. H-2-66759, 2
Rev. 0; and H-2-66758, Rev. 0; or 137CsC1 shall be encapsulated in accordance with Vitro Drawing Nos. H-2-66760, Rev. 0; and H-2-66761, Rev. O.
1 The 90SrF2 and 137CsCl capsules after fabrication shall be leak tested usirg a method having sufficient sensitivity to detect a leak rate (air at standard f
3
)
i
Page 3 - Certificate No. 5939 - Revision No. 6 - Docket No. 71-5939
~
temperature and pressure leaking to 10 2 atm) of 10 8 atm cc/sec.
Any capsule with a detectable leak shall not be delivered to a carrier for transport.
7.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12(b).
8.
Expiration date:
April 31, 1981.
4 REFERENCES General Electric Company application dated February 21, 1980.
Additional References Required for Contents 5(b)(1)(ii):
Oak Ridge Nrtional Laboratory letter dated Apri,1 3, 1980.
'upplement dated: May 7, 1980.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Chief l
Transportation Certification Branch Division of Fuel Cycle and Material Safety OCT 311980 Date:
4 4
f
.