ML19336A383
| ML19336A383 | |
| Person / Time | |
|---|---|
| Site: | 07109044 |
| Issue date: | 10/08/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19336A382 | List: |
| References | |
| NUDOCS 8010220684 | |
| Download: ML19336A383 (4) | |
Text
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L.:3 Form NRC 61S '
U.S. NUCLEAR REGULATORY COMMISSION 0CFR y CERTIFICATE OF COMPLIANCE For Radioactive Materials Pa'ckages 4 Jai Certificate Numoer 1.(b) Revision No.
1.(c) Package identifi io No.
1.(d) P 9044.
6 USA /9044/
F 3es No.1.(e) Totad No. Pages
' 2. PRE Ah.tSLE 2.f al This certificate is issued to satisfy Sections 173.393a.173.394.173.395 and'173.396 of the Department of Transportation Hazarcous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transoortation Cancerous Cargoes Regulations (46 CFR 146-149), as amended.
2Jb) The pacnaging and contents described in item 5 below, meets the safety standaros set forth in Subpart C of Title 10. Code of Federal Regutations. Part 71, "Pacnaging of Racioactive Materials for Transport and Transportation of Raas actise Material Under Certain Conditions."
2.fc)
This certificate does not relieve the consignor from compliance with any recuirement of the regulations of the U.S. Department of
- Transportation or other applicable regulatory agencies. including the government of any country threwh or into which the package
. will be transoorted.
- 3. *his certificate is issued on tne bases of a safety analysis report of tne package desian or application-3Ja! Prepared by plame and adiess):
3.lb)
Title and identification of report or application:
General Electric Company General Electric Company application dated P. O. Box 460'
. January 8, 1969, as supplemented.
Pleasanton, CA '94566' 71-9044 3.(c)
Docket No.
4 CONOtTIONS
'his certificate is conditional upon the fulfitting of the reovirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified M item 5 below.-
- 5. Cescriction of Packaging and Authorized Contents. Mocel Number. Fissile Class. Otner 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 to a steel pallet. ~ The cask is closed 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 :oiamete", in 38.5 Cavit)_ 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 8010220- NY
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'Page 2.- Certificate No. 9044 Revision-No. 6 - Docket No. 71-9044 15.
(a) Pack' aging (continued)-
(3)' Drawings The: packaging is constructed in accordance with the following General Electric ~ Company Drawing Nos.:
212E255, Rev. 3
'135C5598, Rev. 1 106D3986, Rev. 1 106D3973, Rev. 1 174F237, Rev. 1 (b) Cont'ents (1) Type, form and maximum quantity of material per package i
Plutonium in excess of twenty (20) curies per package must be in the for'a 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 the form of. fuel rods, or plates, fuel assemblies, or meeting special form requirements of 10 CFR G71.4(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 Pu0 and U0 fuel rods clad.in zircaloy or stainless 2
2 steel.
Decay heat not to exceed 600 watts.
All fuel rods snall be l
contained within a closed 5-inch Schedule 40 pipe.with a maximum-l tiseable length of 39-5/8 inches.
1,200-gm fissile: material with no more than 300 gm fissile material
.per 5-inch Schedule 40 pi.pe.
l (iv) Irradiated UC and-ThC fuel particles clad in graphite.and contained L
within a standard HTGR hexagonal cross-section graphite block.
l Decay heat not to exceed 600 watts.
Each graphite block shall be-i.
contained within a sealed cylindrical inner container constructed in accordance with General'Atcaic Company Drawing No.- 021583,- Issue A, with~three, 1/2-inch by 4-1/2-inch radial fins to provide centering-
-within'the cavity.-
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1,400 grams U-235 equivalent mass in each inner container wit' no more than one inner container per package.
(v) Process solids, either dewatered, solid, or solidified in ~ a secondary sealed container meeting the requirements'for low specific activity radioactive' material.
o
!? age 3 - Certificate-No.'9044' Revision No. 6 - Docket No'. 71-9044
-5. _(b)~ (1)! Contents-(continued)
(vi) -Solid nonfissile irradiated metal hardware, reactor control rods.
(blades), and _ reactor start-up ources.
(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 I
(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 firts. Cavity drain line shall be sealed with appropriate sealant applied to. threads of pipe plug.
11.
For packaging =of neutro~ sources, measurements shall be made to determine that the dose rate does not e) i 1,000 mrem /hr at 3 feet from the surface of a dry cask with no. additional shu ng within the cask.
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12.
The contents described in 5.(b)(1)(v) shall be transported on a motor vehicle, railroad car,Eaircraft, inland water crafts, or hold or deck,f a seagoing vessel assigned for sole useJof the licensee.
The package authorized by this certificate is hereby. approved ~for use under the J
13.
general' license provisions of'10~CFR 671.12(b).
114. l Expiration _date: : December 131, 1980.
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Page 4. : Certificate.No? 9044~- Revision No. 6 --Docke't-No.- 71-9044 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;'and August' 26,-1980.
p Nuclear Plant Services supplement dated:
July 7, 1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION :
Charles E. MacDonald, Cnief Transportation Certification Branch Division of Fuel Cycle and Materials Safety OCT 0 81980 Date:.
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