ML20002C266
| ML20002C266 | |
| Person / Time | |
|---|---|
| Site: | 07109044 |
| Issue date: | 12/23/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20002C262 | List: |
| References | |
| NUDOCS 8101090838 | |
| Download: ML20002C266 (4) | |
Text
.
O-r,m*4RC413 U.s. NUCLEAR REGULATORY Commission
" 7 03 33 cj,73 CERTIFICATE OF COMPLI ANCE Fo, Ra i. acts.e Mate,,ais, song.s 1.14 ) Cartif^ ante Nunter 1.lb) Revision No.
1.tc) Package toentification No.
1.(d) Pages Noi..tel Total No. Pages 9044 7
USA /9044/B( )F 1
4
- 2. PREAMBLE 3.'J )
This certeficate is issued to satisf y sections 173.393a.173.394,173.395, and 173.396 of the Department of Transoortation Matarcous Materiais Regulations t49 CFR 170189 and 14 CPR 103i and sections 146-19-10a ano 146-19-100 of the Ceoertmeat of Transoortation Cangerous Cargoes Regulatens (46 CF R 146-149), as amences.
3.'ol We sectagerus and contents descriose in + tem 5 beiow, meets vne safety stancarcs set forth in sucoart C of Titte 10. Code of Federal Regulatens. Part 71. **Pacmageng of Radioactswe Materials for Transoort and Transoortation of Racioactive Material Under Certa.n Canditions.
3.!c)
Thes artifecate does not relieve the consignor from composance with any requirement of the regulatens of the U.S. Desertment of Transcortation or otner acclicaole reguaatory. agencies, inciuorng rne government of any country througn or into whicn the neckage nell be transported.
- 3. Ses ceftsficate is iuved on the basis of a safety analysis report of the oack. ige cesegn er apotecation-3.:al Preperso by (Name artsf address):
3.!b)
Title and centification of report or acceicaten.
General Electric Company General Electric Company application dated P. O. Box 460 January 8,1969, as supplernented.
Pleasanton, CA 94566 71-9044 3.(c)
Docket No.
4 CONDITIONS This certificate is conditenal upon the futfitting of the recuerements of subcort D of 10 CFR 71. as aposicabee. and the concetens soecifica in item 5 be+ow.
- 5. Gese notion of Packaging and Aufnorized Contents. Mocol Numoer. Fissiee Class, other Concatens, anc 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-filled flanged plug fitted with a silicone rubber gasket and bolteu 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 81 01090 US
Page 2 - Certificate No. S,14 - Revision No. 7 - Docket No. 71-9044 5.
(a) Packaging (continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:
212E255, Rev. 7 10603973, Rev. 5 106D3986, Rev. 4 12904687, Rev. 0 174F237, Rev. 4 12904688, Rev. 1 135C5598, Rev. 2 10603989, Rev. 1 913E307, Rev. 1 (b) Contents (1) Type, form and maximum quantity of material per package Plutonium in exces of twenty (20) curies per package must be in the form of metal, metal alloy or reactor fuel elements; and (i) Byproduct material and special nuclear material as solid metal or oxides.
Decay heat not to exceed 600 watts.
The radioactive material shall be in tht: form of fuel rods, or plates, fuel assemblies, or meeting special form requirements of 10 CFR 571.4(o).
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 Pu02 and UO2 fuel rods clad in zircaloy or stainless steel.
Decay heat not to exceed 600 watts.
All fuel rods shall be contained 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.
(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 shat 1 be contained within a sealed cylindrical inner container constructed in accordance with General Atomid Company Drawing No. 021583, Issue A, with three,1/2-inch by 4-1/2-inch radial fins to provide centering within the cavity.
1,400 grams U-235 equivalent mass in sach inner container with no Tore than one inner container per package.
w
Pege 3 - Certificate No. 9044 - Revision No. 7 - Docket No. 71-9044 5.
(b)
(1) Contents (continued)
(v) Process solids, either dewatered, solid, or solidified in a secondary sealed container meeting the requirements for low specific activity radioactive material.
(vi) Solid nonfissile irradiated metal hardware, reactor control rods (blades), and reactor start-up sources.
(c) Fissile Class III Maximum number of packages (i) Contents 5.(b)(1)(i), 5.(b)(1)(ii),
per shipment 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 1,66 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 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 main-tain its seal at temperatures up to at least 620*F.
9.
Shoring shall be provided to minimize movement of contents during accident condi-tions of transport.
10.
Prior to each shipment the silicone rubber lid gasket (s) shall be inspected.
This gasket (s) shall be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first.
Cavity drain line shall be sealed with appropriate sealant applied to threads of pipe plug.
11.
For packaging of neutron sources, measurements shall be niade to determine that the dose rate does not exceed 1,000 mrem /hr at 3 feet from the surface of a dry cask with no additional shielding within the cask.
- 12. The contents described in 5.(b)(1)(v) shall be transported on a motor vehicle, railroad car, aircraft,' inland water crafts, or hold or deck of a seagoing vessel assigned for sole use of the licensee.
Page 4 - Certificate No. 9044 Revision No. 7 - Docket No. 71-9044 13.
The packace authori:ed by this certificate is hereby approved for use under the general 1 cense provisions of 10 CFR 571.12(b).
14.
Expiration date:
December 31, 1981.
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; July 3 and November 15, 1973; December 4, 1979; l
and August 26, 1980.
Nuclear Plant Services supplement dated:
July. 7, 1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION O4[
_ =h Ch'a'rles E. MacDona d, Chief Transportation Certification Branch Division of Fuel Cycle and Materials Safety DEC 2 31923 Date:
O e
O e
e