ML20129D893
| ML20129D893 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 07/12/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20129D870 | List: |
| References | |
| NUDOCS 8507300188 | |
| Download: ML20129D893 (4) | |
Text
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- CERTIFICATE OF COMPLlANCE
- , 'o CrR 7 FOR RADICACTlvE MATERIALS PACKA!ES
' 1 a CERTsFICATE NUMBER D REvtSION NUMBER C PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES !
5942 9 USA /5942/B( )F 1 3 l
.t 2 PREAMBLE
- a. This CertifsCate is issued to Certsf y that the packaging and Contents described in item 5 below, meets the applicable safety standards set forth in Title 10. Code
- of Federal Regulations. Part 71, ~PaChaging of Radioactive Materials for Transport and Transportation of Radioactive Matenal Under Certain Conditions."
- b. Thss CertifsCate does not relieve the Consignor from Complaance with any requirement of the regulations of the U $ Department of Transportation or other
- l lj applicable regulatory agencies, including the government of any Country through or anto which the package will be transported.
I
., a PREPA E BYthame Ad ress bT LE AND IDE tF CAT ON F E A ATION a General Electric Company General Electric Application dated May 30, 1985, '
l P.O. Box 460 as supplemented.
- Pleasanton, CA 94566 71-5942 l C. DOCKET NUMBER g
- i 4 CONDITIONS
- This certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as appi
- Cable, and the conditions specified below I
j (a) Packaging 1
l (1) Model No.: 700 d
(2) Description v
$ A steel encasea lead shielded shipping cask enclosed by a double-s walled protective jacket of the same shape with a rectangular baseplate.
y The cask is a double-walled steel circular cylinder, 37-inch-diameter
- ! 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
- set at 100 psig, and lifting device. Closure is accomplished by a
- silicone rubber gasketed and bolted steel lead filled plug. The maximum gross weight of the package (contents, cask assembly, protective y jacket and base) is 35,500 pounds.
u h The cask may be modified with a 14-inch high cavity extension with an
- i additional silicone rubber gasket. The modified cask is 79 inches
[ high. The maximum gross weight of the package (contents, modified y cask assembly, protective jacket and base) is 40,200 pounds.
j (3) Drawings
- The packaging is constructed in accordance with the following General '
1 Electric Company Drawing Nos.: 129D4768, Rev. 3; 129D4769, Rev. 4;
.? and 129D4770, Rev. 5.
ul 1 Lifting and/or tie-down devices which are a structural part of the R package must be in accordance with the above drawings.
l 4
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$l Page 2 - Certificate No. 5942 - Revision No. 9 - Docket No. f'
- 5. (b) Contents l (1) Type and form of material l lj E:
1 Byproduct, source, and special nuclear material contained in solid W oxide or metal form and in special form.
) l (2) Maximum quantity of material per package l fi- r 1l Not to exceed 700 pounds (including shoring), and 5 J E i
J; (i) 740 gm U-235, provided that the maximum U-235 enrichment does not I:
}ji exceed 6 weight percent;,or_
MF I? e - (
. r E! E f (ii) 1,200 gm U-235, provided th'at the fuel naterial is in the form of p f MTR-type fuel elements with a minimum active fuel length of 23 E
J inches;sorJ . #:
1 y 'n El jl i (iii) 220 gm fissile material; or M3 [
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(iv) 1,650 gm'U-235, provided that the maximum U-235' enrichment does k I, not exceed 3.5 weight percent and'the' fuel material is in the l' 1; form of 88 rodsiloaded,with 0.376-inch-diameter. pellets with a E J, minimum active: fuel length of 371nches;3 or -
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E R c:a , 3. / [. ( ) -
ly (v) those values presented'in-Figur)e '1,Weight Limits for Model 700 U0,,
] Shipping Container, of. Exhibit:A to this application, applicable g 3
j, to fuel material. in the form.of rods with a minimum pellet diameter I Of ,0.40' inch;'or ]} } g { j[( ,-
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f (vi) 5,10'0 gm U-235,' provIdeNtIhe9u$1 ~ f[in the f$rm of ETR-type fuel
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f elements (GETR Fuel),with 'each element containing no more than l
g 3
1 510 gm U-235 and inserted ;in the' spaced stainless steel fuel I f shipping; basket described in' GE Drawing No.* 106D4150, Rev. 0.; or R E
1 /' '
1l (vii) 6,200 gm U-235,,provided the fuel :is in'the form of MURR TRTR E jl type elements containing,not.more"than 775 gm U-235 per element; loaded and spaced in' the, stainless steel fuel shipping basket as (g
g!
j described in MURR Drawing No. 1228, Sheets 1 thru 5, Revision 0. n Fuel elements shall have at least 150 days cooling time since R last reactor operation; or T{ [
(viii) 3,510 gm U-235 provided the fuel is in the form of MTR-type fuel l elements with each element containing no more than 351 gm U-235 g
}I and inserted in a spaced stainless steel fuel shipping basket I 1! described in GE Drawing No.106D4150, Rev. O. A shoring device Il j to limit vertical motion of the fuel elements nust be included. [
(3) Maximum quantity of radioactive decay heat per package !
11 I gj (1) 6,500 watts for dry shipments, or I 1 Il 1! (ii) 1,500 watts for wet shipments, provided that the cavity shall j '
l contain at least a 1,000 cu in air void (at standard temperature y j and pressure) at the time of delivery to a carrier for transport. g u
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! Page 3 - Certificate No. 5942 - Revision No. 9 - Docket No. 71-5942 l!
I ll 5. (c) Fissile Class III l i Maximum number of packages per shipment 2 f6.
i The radioactive material nust be in the form of fuel rods, or plates, fuel assemblies, or meeting the requirements of special form radioactive material.
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I ll Shoring must be provided to minimize novement of contents during accident conditions I, 7. of transport.
I:
l f8.
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Prior to each shipment (except for contents meeting the requirements of special form radioactive material), the pack I
I s' of determining that a leakage of 10~gge atm cm musg/s at standard temperature andbe leak Isl 1
gl pressure is not exceeded. c rrr p; ;sti . /
[j 9. Prior to each shipment the silicone rubber lid gasket (s) must be inspected. !
g! This gasket (s) must be , replaced if inspection shows any defects or every twelve !
gl (12) months, whichever< occurs first. Cavity drain line must be sealed with di appropriate sealant applied to threads of pipe plug. l
( ~
'.* i
- l 10. The applicant nust;co fim annually that the pressure relief valve is operable i
[ at 100 psig. r,, < .x - ,4,
!,11. When needed, sufficient antifreeze in the cask:must be used to prevent damage of I
ll any component of; the package due _ to freezing. L ,
l' .
. __o /
Fabrication of a'dditional packagings is not auttiorized.
jl 12. < _ ,
l: 13. The package authorized by this certificate is' hereby approved for use under the g' general license provisions ~of 10 CFR 971.12. ' -
l 2 l 1. 4 Nl 14. Expiration date: July 31,1990. , ,
i REFERENCES !'
( m .
gli g G:neral Electric application dated May 30, 1985.
< , t -
%q' Supplements dated: June 5 and 7, 1985. i 7 j il f University of Missouri letter dated March 20, 1980.
Appendix 6-A regarding University of Missouri's quality assurance program is not ll considered part of this application.
di i l' FOR THE U.S. NUCLEAR REGULATORY COMMISSION I Il I l k
% Charles E. MacDonald, Chief I di Transportation Certification Branch E! Division of Fuel Cycle and l Material Safety, fitSS f I JUL 12 M fll 3
Date:
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Transportation Certification Branch
, Approval Record Model No. 700 Package Docket No. 71-5942 By application dated May 30, 1985, General Electric Company requested renewal of Certificate of Compliance No. 5942 for the Model No. 700 (formerly GE-700) packaging. A consolidated application was submitted which incorporated the consolidated application of March 18,1980, and all pertinent supplement information.
A review of the consolidated application confirmed that all pertinent supplement information along with the application of March 18, 1980 has been incorporated into the consolidated application with the exception of the June 5 and 7,1985 supplements. The application has been expanded to include sections on operating procedures and maintenance program.
The applicant has also revised Drawing No. 12904770 to show the addition of a fillet weld on the cavity step to reinforce the existing weld
, joint.
The applicant has stated that they do not currently plan to obtain new packagings. The Certificate of Compliance has been conditioned to preclude the fabrication of additional packagings. The Certificate of Compliance has been further conditioned to require leak testing of the package prior to each shipment for authorized contents other than contents meeting the requirements of special form radioactive material.
Based on the staff's review of the consolidated safety analysis report and the conditions stipulated in the Certificate of Compliance, the staff concludes that the requirement for renewal of the Certificate of Compliance has been satisfied.
dg _
CfFarTes T. ac onaTd, Chie Transportation Certification Branch Division of Fuel Cycle and Material Safety, MiSS Date: M IP E