ML20126F156
| ML20126F156 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 06/10/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20126F155 | List: |
| References | |
| NUDOCS 8506170375 | |
| Download: ML20126F156 (4) | |
Text
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. CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES '
E 1 a CERTIFCATE NUMBER D REVISION NUMBER C PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES y 5942 8 USA /5942/B( )F 1 3 j i 2 PaEAMBLE $
a This certificate is issued to certif y that the packaging and contents desenbed in item 5 below, meets the apphcable safety standards set fortn in Title 10. Code E of Federal Regulations. Part 71, "Pacnaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certain Conditions?' %
b This certihcate does not reheve the consignor from compliance with any requirement of the regulations of the U S. Department of Transportation or other k apphcacie regulatory agencies, including the government of any country through or into which the package will be transported E 1
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A CATION -
i General Electric Company General Electric Application dated March 18, 1980, E' g' j P.O. Box 460 as supplemented. E
, Pleasanton, CA 94566 IK 71-5942 E:
y c OOCKET NUMBER b a CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as apphcacle. and the conditions specified betow s'
(a) Packaging ;Eg!
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i (1) Model No.: GE-700 'Dj gs (2) Description g!
It A steel encased lead shielded shipping cask enclosed by a double- 4 i walled protective jacket of the same shape with a rectangular baseplate. ,Ei i The cask is a double-walled steel circular cylinder, 37-inch-diameter Ii E i by 65-inch high with a central cavity 15-inch-diameter by 40-inch high. Approximately 10.25' inches of lead surround the central cavity.
The cask is equipped with a cavity drain line, pressure relief valve f)
- gp set at 100 psig, and lifting device. Closure is accomplished by a in silicone rubber gasketed and bolted steel lead filled plug. The 'E i maximum gross weight of the package (contents, cask assembly, protective E l Jacket and base) is 35,500 pounds. l i The cask may be modified with a 14-inch high cavity extension with an ,E additional silicone rubber gasket. The modified cask is 79 inches high. The maximum gross weight of the package (contents, modified lljg l cask assembly, protective jacket and base) is 40,200 pounds, g E
(3) Drawings lE
- E The packaging is constructed in accordance with the following General j' l Electric Company -awing Nos.
- 12904768, Rev. 3; 12904769, Rev. 4; 'g and 12904770, Rev. '. g;
,E Lifting and/or tie-down devices which are a structural part of the i E
package must be in accordance with the above drawings, i
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E . CONDITIONS (continu1d) g f
- 1l P. age 2 - Certificate No. 5942 - Revision No. 8 - Docket No. 71-5942 fl Il
- 11 5. (b) Contents lg! g T 1 El
) 1 (1) Type and form of material ,E:
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!yj Byproduct, source, and special nuclear material contained in solid oxide or metal form and in special form. f,;
'1l 1! (2) flaximum quantity of material per package
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j Not to exceed 700 pounds (including shoring), and
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- 1, (1) 740 gm U-235, provided that the maximum U-235 enrichment does not exceed 6 weight percent; or f
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'3I (ii) 1,200 gm U-235, pro'vided thati ths fuel material is in the fom of ,
j MTR-type fuel ' elements with a minimum active fuel length of 23 .
inches; or j '
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- li s s
- 1l (iii) 220 g{ fissile material; or ;
@! not exceed 3.5 weight percent and the fuel material is in the E fonh of 88 rods loaded.with 0.376-inch-diameter pellets with a E
' j;sj minimum active fuel length of 37 inches; or f l i x - - ! . .
i l1'1 (v) those values presented infigure.1, U0J Ueight Limits for Model 700 lp' fl l Shipping Container,;of Exhibit A to this application, applicable in
,to fuel._ material in thc7fom of rads with a minimum pellet diameter E di g of 0.40- inch;; or- ,
j i
el 'E (vi) 5,1b0 gm' U-235, providad the fuel is in the fom of ETR-type fuel !g hl (1 elements (GETR Fuel) with each element containing no more than ;E h 510 gm U-235 and inserted in the spaced stainless steel fuel h shipping basket described in GE Drawing No. 10604150, Rev. 0.; or j lN p
d (vii) 6,200 gm U-235, provided the fuel is in the fom of MURR TRTR ig ,
type elements containing not more than 775 gm U-235 per element; h't loaded and spaced in the stainless steel fuel shipping basket as described in MURR Drawing No.1228, Sheets 1 thru 5, Revision 0.
lif N' H
h Fuel elements shall have at least 150 days cooling time since last reactor operation; or j!,
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a 4 (viii) 3,510 gm U-235 provided the fuel is in the fom of MTR-type fuel elements with each element containing no more than 351 gm U-235
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b and inserted in a spaced stainless steel fuel shipping basket l E
described in GE Orawing No. 10604150, Rev. O. A shoring device b
to limit vertical motion of the fuel elements must be included, j jE l
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- (3) Maximum quantity of radioactive decay heat per package E :D U (1) 6,500 watts for dry shipments, or t E
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H (ii) 1,500 watts for wet shipments, provided that the cavity shall !
O contain at least a 1,000 cu in air void (at standard temperature !n.
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and pressure) at the time of delivery to a carrier for transport. lp j 1
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Page 3 - Certificate No. 5942 - Revision No. 8 - Docket No. 71-5942 h 1
3
- 5. (c) Fissile Class III f
Maximum number of packages per shipment 2 E
- 6. The radioactive material must be in the form of fuel rods, or plates, fuel assemblies, or meeting the requirements of special form radioactive material.
d-N Shoring must be provided to minimize movement of contents during accident conditions I7. 8.
of transport.
prior to each shipment the silicone. rubber-lid gasket (s) must be inspected.
r,t E
N This gasket (s) cust be replaced :iffinspection:shows any defects or every twelve d (12) months, whichever occurs -first. Cavity drain line must be sealed with appropriate sealant applied'to threads of pipe plug. lq
- 9. The applicant must ebhfirm annually that the pressure relief valve is operable at 100 psig.
q.
- 10. When needed, sufficient antifreeze in the cask cust be used to prevent damage of any component of-the package due to freezing, l
- 11. The package authorized by this certificate is hereo,w approved for use under the .
general license provisions of.10 CFR.97.1_12.
~
- 12. Expiration date: Juns 30, 1985. ~' ^
REFERENCES-General Electric application dated March 18, 1980. I!
Supplements dated: August 10, 1982; December 5,1904; and June 5 and 7,1985.
University of Missouri letter dated March 20, 1980. t.1 i Appendix 6-A regarding University of Missouri's quality assurance program is not considered part of this application.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION #
10'
$$ A Jhm CharTeiE.~ MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, FESS Date: Jull10 W f
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Transportation Certification Branch Approval Record Model No. GE-700 Package Docket No. 71-5942 By application dated June 5,1985, as supplemented June 7,1985, General Electric Requested approval of 10 Brookhaven High Flux Beam Research reactor fuel elements as contents in the GE-700 package for Fissile Class III shipments. These elements (MTR-type elements each containing no more than 351 grams U-235) are to be inserted into a spaced stainless steel fuel shipping basket (described in GE Drawing No.106D4150, Rev. 0) with vertical shoring as necessary to prevent fuel element motion.
The applicant established the subcriticality of the above requested contents under accident flooded conditions by calculation using the i KENO-IV computer program together with the 27-group neutron cross-section set in the SCAL.E (NUREG/CR-0200) system. Explicitly, geometric modeling was used to represent each of the 20 aluminum clad plates per assembly (18 contain fuel, 2 are aluminum). The steel basket was also modeled explicitly as was the water regions external to the basket. The
, basket was then reflected by an appropriate water region followed by an 11-inch thick lead cylindrical annulus shield. A 12-inch all-around water reflector surrounded the cask. The k for this single flooded water reflected cask was calculated to a maINum k I of 0.94. The maximum k,ff value calculated for a water reflecte8 fuel basket was 0.87.
The NRC staff reviewed the computer input-output sheets for the above KEN 0 calculations and found them to represent the cases intended.
Geometric volumes of regions, material dispositions and fuel loadings were verified using the input-geometry and atomic number densities for the KEN 0 cases. No discrepancies or errors were found.
The applicant also analyzed two dry casks fully loaded, in contact under nonnal conditions with a variety of interspersed moderation between casks. The k eff was less than 0.35.
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: uma1 8 M i
I
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