ML19310A700
| ML19310A700 | |
| Person / Time | |
|---|---|
| Site: | 07105939 |
| Issue date: | 06/06/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19310A694 | List: |
| References | |
| NUDOCS 8006230037 | |
| Download: ML19310A700 (3) | |
Text
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p Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION -
CERTIFICATE OF COMPLIANCE 10 C R 71 For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 5939 5
USA /5939/B( )F 1
3
- 2. PRE AM8LE 2.fa)
This certificate is issued to satisfy Sections 173.393a,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sectioes 146-19-10a and 146-19-100 of the Department of Tramportation Dangerous Cargoes Regulations (46 CFR 146-149), at amended.
2.lb)
The packaging and contents described in item 5 below, sneets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations, Part 71," Packaging of Radioactive Materials for Tran. port and Transportation of Radioactive Material Under Certain Conditions."
2 (c) This certificate does not relieve the consignor from compliana 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 irto Lhich the package will be transported,
- 3. This certificate is issued on the basis of a safety analyses report of the package design or application-3.la)
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, CA 94566 3.(c)
Docket No. 71-5939
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CPR 71, as applicable, and the conditions specified in item 5 below.
- 5. Description of Packaging and 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 40 inches high with a central cavity 7-inch-diameter by 25 inches high. The diametar is reduced from 31 inches to 17-1/2 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 packagin'g is approximately 15,000 pounds.
8006280O p
Page 2 - Certificate No. 5939 - Revision No. 5 - Docket No.
e 71-5939 s
5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing :los.:
i t
706E441 Rev. 6 706E792, Rev. 2 10603858, Aev. 2.
-106D3870, Rev. 3 135C5598, Rev. 0
'(b) Contents (1) Type and form of material 4
(1) Byproduct' material and special nuclear material as solid metal or in 4
solid oxide form.
(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 reac) tor fuel elements, and 50 i
U-235 equivalent mass.
1.66 times Pu mass.)
(U-235 equivalent mass equals U-235 mass plus.
(ii) : Item 5(b)(1)(ii) above:
458,000 Ci.
i
.(c) Fissile Class III l'
Maximum number of packages per shipment 22 e
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- = + " * ' - " '
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Page 3 - Certificate No. 5939 - Revision No. 5 - Docket Nc. 71-5939 6.
(i)
For the contents described in Item 5(b)(1)(1) above:
The radioactive material shall be clad, eacapsulated 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 137CsC1 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 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 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 Required 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. M,acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety JUN 0 61980 Date:
i