ML19261B671
| ML19261B671 | |
| Person / Time | |
|---|---|
| Site: | 07109044 |
| Issue date: | 01/25/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19261B659 | List: |
| References | |
| NUDOCS 7902280379 | |
| Download: ML19261B671 (4) | |
Text
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Form NRC418 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE 10 C R For Radioactive Materials Packages 1.(a) Certificate Number 1.(b) Revision No.
1.lc) Pacuage Identification No.
1.(d ) Pages No. 1.(e) Total No. Pages 0044 3
USA /gnaa/n( ir 1
a
- 2. PR E AMBLE 2.la)
This certibcate is issued to satisfy Sections 173.393a.173294,173.335, and 173.396 of the Cepartment of Transocrtation Hazarcous Materials Regulations (49 CFR 170-189 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 amenced.
2.to)
The packaging and contents described in item 5 below rr eets the safety standards set fortn 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 elieve the consignor from compliance with any recuirement of the regulations of the U.S. Cepartment of Transportation or otnc acphcaole regulatory agencies, including the government of a 1y country through or into ansch the package will be transported.
- 3. Tnis certificate is issued on the basis of a safety analysis recort of tne package oesign or application-3.la)
Prepared by (Name and addren):
3.(b)
Title aru eentification of report or application:
General Electric Company General Electric Company application dated P. O. Box 460 January 8, 1969, as supplemented.
Pleasanton, California 94566 3.(c)
Oocket No.
73_oq3
- 4. CONDITIONS This certificate is conoitional upon the fulfil'ing of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specifieu in item 5 below.
- 5. Description of Packaging and Authorized Contents, Mode { Numter, Fissale Class Other Conditions, and
References:
(a) Packaging (1) Model No. : GE-1600 (2) Description Steel encased lead shielded shipping cask.
A double-walled steel cylinder protective jacket encloses the cask during transport.
it is bolted tu a steel pallet. The cask is cicsed by a lead-filled flanged plug fitted with a silicone rubber gasket and bolted closure. The cavity is equipped with a drain line and the physical description is as follows:
Cask height, in 67.5 Cask diameter, in 38.5 Cavity height, in 54.0 Cavity diameter, in 26.5 Lead shielding, in 5.0 Protective jacket height, in 81.4 Protective jacket width, in 68.0 Packaging weight, lbs 23,050 790228031C' y
Page 2 - Certificate No. 9044 - Revision No. 3 - Docket No. 71-9044 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawings Nos.:
212E255, Rev. 3 106D3986, Rev. 1 174F237, Rev. 1 135C5598, Rev. 1 106D3973, Rev.1 (b) Contents (1) Type, form and maximum quantity of material per package Plutonium in excess of twenty (20) curies per package must be in j
the form of metal, metal alloy or reactor fuel elements; and j
(i) Byproduct material and special nuclear material as solid metal or oxides.
Decay heat not to exceed 600 wat.ts.
All material shall be clad, encapsulated or contained in a metal encasement and tested for leak tightness prior to loading in the package in accordance with the statements and representations contained in the licensee's submittal dated February 12, 1969.
500 gm U-235 equivalent mass; or (ii) Neu+.ron sources in special form.
500 gm U-235 equivalent mass.
Decay heat not to exceed 50 watts; or fuel rods clad in (iii)
Irradiated Pu02 and UO2 zircaloy or stainless steel.
Decay heat not to exceed 600 watts. All fuel rods shall be con-tained within a closed 5-inch Scheoule 40 pipe with a maxirc.um useable length of 39-5/8 inches.
1,200 gm fissile material with no more than 300 gm fissile material per 5-inch Schedule 40 pipe.
6 Page 3 - Certificate No. 9044 - Revision No. 3 - Docket No. 71-9044 5.
(b) Contents (continued)
(1) Type, form, and maximum quantity of material per package (continued)
(iv) Irradiated UC and ThC fuel particles clad in graphite and contained within a standard HTGR hexagonal cross-section graphite block.
Decay heat not to exceed 600 watts.
Each graphite block shall be contained within a sealed cylindri-cal inner container constructed in accordance with General Atomic Company Drawing No. 021583, Issue A with three 1/2-inch by a-1/2-inch radial fins to provide centering within the cavity.
1,400 grams U-235 equivalent mass in each inner container with no more than one inner container per package.
(c) Fissile Class III Maximum nember of packages (i) Contents 5.(b)(1)(i),
per shim..ent 5.(b)(1)(ii), or 5.(b)(1)(iii):
Two (2); or (ii) Contents 5.(b)(1)(iv):
One (1) 6.
The U-235 equivalent mass is determined by U-235 mass plus 1.66 times U-233 mass plus '.66 times Pu mass.
7.
For packaging of neutron sources, the cavity drain line shall be closed with a plug with a melting temperature of 200 F and the cask cavity shall be filled with water with a 5-inch air space within the cask cavity. When needed, sufficient antifreeze ia the cask shall be used to prevent damage to any component of the packnge due to freezing.
8.
For packaging of otner than neutron sources, the cask shall be delivered t: a carrier dry and the cavity drain line shall be closed with a plug which will maintain its seal at temperatures up to at least 620 F.
Page 4 - Certificate No. 9044 - Revision No. 3 - Docket No. 71-9044 9.
For packaging of neutron sources, measurements shall be made to determine that the dose rate does not exceed 1000 mrem /hr at 3 feet from t6e surface of a dry cask with no additional shielding within the cask.
- 10. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
- 11. Expiration date: May 31,1980.
REFERENCES General Electric application dated January 8,1969.
Supplements dated: February 12, 'Z0, and 27, and March 10 and 24,1969; November 20, 1970; Jar.uary 29 and March 12, 1971; and July 3 and November 15, 1973.
Nuclear Plant Services supplement dated: July 7, 1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION f
$l4u Charles E. MacDonald, Chief Transportation Branch Diiision of Fuel Cycle and Materials Safety JAN P = G79 Date: