ML19281B113
| ML19281B113 | |
| Person / Time | |
|---|---|
| Site: | 07109044 |
| Issue date: | 03/30/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19281B112 | List: |
| References | |
| NUDOCS 7904210096 | |
| Download: ML19281B113 (4) | |
Text
.
Form NRC-618 U.S. NUCLE AR REGULATORY COMM!SSION CERTIFICATE OF COMPLI ANCE to C R For Radioactive Materials Packages 1.(a) Certificate Nun er 1.(b) Revision o.
1.(d Pac c.
ttc 1.(d ) Page No. 1.(e) Total
- a. Pages
- 2. PRE AMBLE 2.(a)
This certificate is is;ued to satisf y Sections 173.393a,173.394.173.395, and 173.396 of the Department of Transportation Hazardous Materials Requ!ations (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 (40 CF R 14G-149), as amenced.
2.(b)
The packagina and contents described in ' tem 5 below, meets the safety stIndards set fcrth in Subpart C of Title 10, Code of Federal Regulations, Part 71, " Packaging of Radioactive Yaterials for Transport and Transpo.unimi of Radicactive 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. Department 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 package design or application-3.(a)
Prepared by (tlame and address):
3.lb)
Title and identificat;on of report or application General Electric Company General Electric Company application dated P. O. Box 460 January 8, 1969, as supplemented.
Pleasanton, California 94566 j
3.(c)
Docket No.
71 CDdd 4.
CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpsrt D of 10 CFR 71, as applicable, and the cond;tions specified in item 5 below.
g 5.
Description of Packaging aryl Authorized Contents, Model Number, Fissde Class, Other Conditions, armi 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 to a steel pallet.
The cask is closed by a lead-fi' led 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 7904216c> 96
Page 2 - Certificate No. 9044 - Revision No. 4 - Docket tio. 71-9044 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawings flos.:
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 the form of metal, metal alloy or reactor fuel elements; and 7'
(i)
Byproduct material and special nuclear material as solid metal or oxides.
Decay heat not to exceed 600 watts. 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) Neutron sources in special form.
500 gm U-235 equivalent mass.
Decay heat not to exceed 50 watts; or (iii)
Irradiated Pu0 and U0 fuel rods clad in 2
2 zircaloy or stainless steel.
Decay heat not to exceed 600 watts. All fuel rods shall be con-tained within a closed 5-inch Schedule 40 pipe with a maximum 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.
Page 3 - Certificate No. 9044 - Revision No. 4 - 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 shal, be contained within a sealed cylindrical inner container constructed in accordance with General Atomic Company Drawing No. 021583, Issue A with three 1/2-inch by 4-1/2-inch radial fins to provide centering within the cavity.
1,40(Lgrams U-235 equivalent mass in each inner container with no more than one inner container per package.
/
i (v) Byproduct material and uranium enriched in the U-235 isotdpe i
as solids, non-powder, and dry, which will re decompose at temperatures up to 500 F and packaged in accordance with Union Carbide specifications UCC-9044, Revision 0, dated March 28, 1979. The thermal decay shall not exceed 400 watts.
The U-235 per package shall not exceed 350 grams. The H/X i
shall not exceed 500.
(vi)
Process solids, either dewatered, solid, or solidified in a secondary sealed container meeting the requirements for low specific activity radioactive material, or Solid reactor components in secondary containers, as required, that meet the requirements for low specific activity radio-active material.
(c)
Fissile Class III Naximum number of packages (i) Contents 5.(b)(1)(i),
per shipment 5.(b)(1)(ii),
5.(b)(1)(iii), or 5.(b)(1)(v):
l 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 1.66 times Pu mass.
Page 4 - Certificate No. 9044 - Revision No. 4 - Docket No. 71-9044 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 in the cask shall be used to prevent damage to any component of the package due to freezing.
8.
For packaging of other than neutron sources, the cask shall be delivered to 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.
9.
For packaging of neutron sources, measurements shall be made to determine that the dose rate d( s not exceed 1000 mrem /hr at 3 feet from the surface of a dry cask with no additional shielding within the cask.
- 10. The contents described in 5.(b)(1)(vi) shall be transported on a motor vehicle, railroad car, aircra,ft, inland water craf ts, or hold or deck of a seagoing vessel assigned for sole use of the licensee.
t
- 11. The p< tkage authorized by this certificate is hereby approved for use und(r the general license provisions of 10 CFR 571.'.2(b).
12.
Expiration date: May 31,1980.
Approved for contents 5.(b)(1)(v) shall expire on December 31, 1979.
REFERENCES General Electric application dated January 8,1969.
Supplements dated:
February 12, 20, and 27, and March 10 and 24,1969; November 20, 1970; January 29 and March 12, 1971; and July 3 and November 15, 1973.
Nuclear Plant Services supplement dated: July 7,1975.
Additional References Required for the Contents 5.(b)(1)(v)
Union Carbide Corporation supplements dated: March 22 and 28,1979.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION d [td'y Charles E. MacDona d, Chief Transportation Branch Division of Fuel Cycle and Materials Safety MAR 3 01979 Date: