ML19310A261
| ML19310A261 | |
| Person / Time | |
|---|---|
| Site: | 07105939 |
| Issue date: | 05/22/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19310A259 | List: |
| References | |
| NUDOCS 8006060616 | |
| Download: ML19310A261 (3) | |
Text
<
O Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION u2 3)
CERTIFICATE QF COMPLIANCE 3g e p 7 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1 (c) Package Identification No.
1.(d) Pages No. 1.(e) To* i No. Pages 5939 4
USA /5939/B( )F 1
3
- 2. PRE AMBLE 2.lal This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Oepartment of Transportation Hazardous Materials Augulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Titte 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. Oepartraent 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 cackage design or aposication-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
General Electric Company General Electric Company application dated P.O. Box 460 November 27, 1968, as supplemented.
Pleasanton, California 94566 3.(c)
Docket No.
- 4. CONOlTIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CFR 71 as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging ar.J Authorized Contents, Model Number, Fissile Class, Other 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-l/2 inches of the.ask. 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.
8 0 0 6 060 $ /' f J
=
Page 2 - Certificate No. 5939 - Revision No. 4 - 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. 6 706E792, Rev. 2 106D3858, Rev. 2 10603870, Rev. 3 135C5598, Rev. 0 (b) Contents (1) Type and form of material (i) Byproduct material and special nuclear material as solid metal or in solid oxide form.
(ii) Byproduct material in the form of 90SrF2 or 137CsC1.
l (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:
150,00 Cf.
(c) Fissile Class III Maximum number of packages per shipment 22 9
.e*
n n
Page 3 - Certificate No. 5939 - Revis.cn No. 4 - Docket No. 71-5939 6.
(i) For the contents described in Item 5(b)(1)(i) above:
The radioactive material shall be clad, encapsulated or contained in a metal encasement in accordance with the statements and representations contained in the General Electric Company's submittal dated November 27, 1968, as supplemented February 10, 1969.
(ii) For the contents described in Item 5(b)(1)(ii) above:
90SrF2 shall be encapsulated in accordance with Vitro Drawing Nos. H-2-66759, Rev. 0; and H-2-66758, Rev. 0; or 137CsCl shall be encapsulated in accordance with Vitro Drawing Nos. H-2-66760, Rev. 0; and H-2-66761, Rev. O.
The 90SrF2 and 137CsCl capsules after fabrication shall be leak tested using a method having sufficient sensitivity to detect a leak rate (air at standard temperature and pressure leaking to 10 2 atm) of 10 a 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 571.12(b).
8.
Expiration date:
October 31, 1980.
REFERENCES General Electric Company application dated November 27, 1968.
Supplements dated: February 10 and 20 (two submittals) and March 6,1969; and May 3, 1976.
Additional References Reouired 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
[b Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety n!AY 2 21980 Date:
9
._