ML20132A904

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Certificate of Compliance 9019,Rev 12,for Model BU-7. Approval Record Encl
ML20132A904
Person / Time
Site: 07109019
Issue date: 09/19/1985
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20132A900 List:
References
NUDOCS 8509260050
Download: ML20132A904 (6)
v • d • e


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.MA C FOnes s1s U.S. NUCLEAR REGULATORY COMZISSloN

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CERTIFICATE OF. COMPLIANCE l'

{ io Cra n FCR RAD 12 ACTIVE MATERIALS PACKAOES I E

1 a CEWTIFICATE NUMBER D REVISJON NUMBER c PACKAGE iOENTIFiCATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 9019 12 USA /9019/AF 1 4 't 2 PREJ.MBLE I a Thi.s certificate is issued to certify tnat the pactaging and contents described in item 5 below. meets the applicabie sa'ety standards set forth in Titie 10. Code i of Federal Regulations. Part 71. ~Pacnaging and Transportation of Radioactrve Material" }

b This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U S. Department of Transportation or oteer i applicatse regulatory agencies. including the government of any country through or into enich the package will be transported f E

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> 3 THtS CERTIFICATE iS ISSUEo oN THE BASIS oF A SAFETV ANALYSIS REPORT of THE PACKAGE DESIGN oR APPLICATION a iSSvEo To % -- t, TiTtE ANo ioENTwiCATioN of aEPoaT oa APPuCATioN y

lg! General Electric Company General Electric Company application dated 1 P.O. Box 780 June 3,1981, as supplemented. )

Wilmington, NC 28401 E!

l- c. ooCKET NuweER ,

71-9019 $

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1. This certificate is conditional upon fulfithng the requirernents of 10 CFR Part 7t. as apphcable. and the conditions specified below il

' il I s E g, (a) Packaging fr gi I 5! (1) fiodel No.: BU-7. i t

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)ll (2) Description _

fif i The packaging consists of either two, 5-gallon or three, 2.5 or 3-gallon,1 I ll.25-inch ID,~ minimum 24-gauge steel pails contained in a 13.75 to i I .14.05-inch diameter by nominal ~27-inch ~1ong inner container constructed jI I of.18-gauge steel', 'wi th bolted ~and gasketed. (1/8-inch thick silicone rubber with a durometer. hardness between 45 to 75) top flange closure. ll l g 4

The inner; container is centered and supported in a 22.5-inch ID,18- lg gi gauge steel 55-gallon ~ capacity DOT Specification 17H steel drum by 'I ll solid insulating material . composed of fire-retardant- phenolic foam I (7-9 pounds per cubic. foot). Drum closure is provided by a DOT @

j,1l i Specification 17H,16-gauge drum cover and a D0T Specification 17H, l, 12-gauge closure ring with drop forged lugs, drilled and threaded for i{p g 5/8-inch diameter bolt and nut. The maximum weight of the package is !g g 370 pounds. .

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l The container is constructed in accordance with General Electric y Company Drawing No.112D1592, Revision 4. [)g I iI I il l 'N I N l 1 ,

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_ . . . - An/E N E E W EER N *i CoNDITlcNS (contenusd) pn Page 2 - Certificate No. 9019 - Revision No.12 - Docket No. 71-9019

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g 5. (b) Contents f (1) Type and form of material f k (1) Uranium oxide powder with a maxinun bulk density not greater than h

& 4.2 grams /cc. Uranium may be enriched to not nore than 4.0 w/o '

@ in the U-235 isotope. The maximun H/U atonic ratio considering all sources of the hydrogenous material within the inner container shall not exceed 0.45.

91 (ii) Uranium oxide powder with a maximun bulk density not greater than y 1 4.2 grams /cc., Uranium may .be enriched to not more than 4.0 w/o I

in the U-235 'isot'op'e . The maMimum H/U atomic ratio considering .

all sources of the hydrogenous material within the inner container shall.not exceed 1.6.

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[j' (iii) Uranium oxide as pellets with a maximun bulk density of 4.2 g rams /cc. Uranium nay be enriched to a maximun 4.0 w/o in the U-235 isotope. The naximun H/V atomic ratio considering all sources i of the hydrogenous material within the inner container shall not exceed 0.45. -

(2) Maximum quantity of material per package

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i l (i) ~ For the contents described in 5(b)(1)(1)
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A The maximum contents per package and pail for the maximum U-235 4 enrichment shall be limited in t.ccordance with the following h table: lpi

$@l Maximun,U-235 enrichment, tiaxinun UO per pail,2 flaximun U0, per package' .

i w/o kas kgs ,

l 3.0 N ~

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44.5'. 89.0 I 3.2 ' ~ 38.9

77.8 i j 3.4 34.6 69.2 i

! 3.6 31.1 62.2 3.8 28.3- 56.6

4.0 25.7 51.4 ,

(ii) For the contents described in 5(b)(1)(ii):

The maximum contents of uranium oxide powder per package and pail shall be limited to 70 kgs and 35 kgs, respectively, fg

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>1 Page 3 - Certificate No. 9019 - Revision No. 12 - Docket No. 71-9019 Ef p

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(iii) For the contents described in 5(b)(1)(iii): Ie The naxinun contents per package and pail for the maximun h-U-235 enrichment shall t'e limited in accordance with the following f; k table: g e'

, Maximum U-235 Maximun U0 Maxinum U0,3 tj enrichment, per pail,2 per package, R:

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1 f 2.7 , . . x e45.0 90.0 I

2.8 CA*' "'"\4219' - 85.8 'gi 2.9 40.1 80.2 g:

& 3.0 38.1 76.2 R:

3.2 34.1 68.2 F

{U 3.4 31 .0 62.0 E!

Y 3.6 28.5 57.0 h 3.8 26.4 52.8 g-4.0 24.7 49.4 R:

_. _ g-(c) Fissile Class I E F

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6. For mixtures of contents.(powders and pellets) described in 5(b)(1), the maximum quantity of material per package shall be_ limited to the quantity given in gi 5(b)(2)(iii). I:

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7. For mixtures of fo'ntents' as described in 5(b)(1)(ii), ammonium oxalate and/or I ammonium bicarbonate additives are permitted in the U02 p wder to the extent that the C/U ratio does not exceed 1.27.

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8. In addition to the requi ements of Subpart G of 10 CFR Part 71: E-t Prior to each shipment, the inner drum (container) silicone rubber gasket must E j

be inspected. The gasket nust be.. replaced with,a new gasket if inspection shows any defects or every 12 months, whichever occurs first. Based (.n gasket age j

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!g considerations alone, no gasket need be replaced until after December 31, 1985. !g; t

9. The packaging cust be marked in accordance with 10 CFR 971.85(c). E!

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10. The four,1/4-inch diameter holes located near the top of the outer D0T Specifi-cation 17H steel drum shall be covered with weatherproof tape to preclude the f

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entry of water. E:

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11. The package authorized by this certificate is hereby approved for use under the A general license provisions of 10 CFR 971.12. f,

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12. Expiration date: April 30, 1989. ll )

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Page 4 - Certificate No. 9019 - Revision No.12 - Docket No. 71-9019 l g

1 f REFERENCES f, General Electric Company application dated June 3,1981. !l e

Supplements dated: June 25,1981; November 13 -1984; and April 29, 1985. g

@ FOR THE U.S. NUCLEAR REGULATORY COMf1ISSION k Di B e i ,- . , .

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  • i Char.les E. MacDonald, Chie

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Transportation Certification Branch Division of Fuel Cycle and q Material Safety, ft1SS p.,

SEP 191985 'El Date: 58 B

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1 Transportation Certification Branch Approval Record Model No. BU-7 Packaae Docket No. 71-9019 By application dated November 13, 1984, as supplemented April 29, 1985, General Electric Company (GE) has requested several small changes to the Model No. BU-7 ~ package. Among other things, these changes include dimensional changes to the outer and inner drums (adding tolerances) and inner drum gasket testing changes.

GE reauests dimensional changes be approved for the !!odel No. BU-7 shipping container. Those changes that can affect criticality are the inner container increasing its inner diameter from 13.75 to 14.05 inches and the inner height from 26.75 to 27.25 inches. Thus, the inner container volume increases about 6.5 percent. . All contents are to remain identical as per previous approvals. Thus, these contents fill the extra volume and the expected increase in keff is about 2.5 percent in units of keff.

GE used the same criticality methods (KEN 0 IV with the Hansen-Roach 16-group cross section set, successfully benchnarked against appropriate criticals) that were used.in establishing subcriticality of the Model No. BU-7 with old inner container dimensions with identical fissile i contents.

The maximum koo (202 kg U(4)0 9 ) per tiodel No. BU-7 container 60% resin density, H/U = 1.58, C/U = 1.260 was calculated to be 0.913 +-0.005 for normal conditions, maximum reactivity. The corresponding naximum keff for 256 damaged (9x9x4) H7 0 reflected with maximum interspersed moderator was calculated to be 0.955 + 0.005. The maximum keff for a single (70 kg U(4)0 plus 40 w/o water flooding) package-was calculated to be.

0.904_+8).004. .

The staff has reviewed the KEN 0 IV input and output for selected cases and found them to be accurate and representing the cases intended.

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e The GE Orawing No. 11201592, Revision 4, shows the use of a 1/8-inch thick silicone rubber gasket with a har.dness range of 45 to 75 durameter.

Test results have been included to demonstrate the acceptability of the proposed gasket material. . However, the reuse of the gasket material has not been satisfactorily addressed because only the change in hardness was considered (inspection frequency was not specified). Because of uncertainties in specifying performance criteria for reused gaskets, we have previously required elastomer gaskets to be replaced at least annually. In a new application, we would be wil. ling to consider additional j

infonnation which includes tests for (1) tensile strength, (2) elongation, and (3) durometer hardness. Except for defective gaskets, replacement of gaskets need not be made until after December 31, 1985, in order to allow for a transition time, a n s_-I Charles E. MacDonald, Chief '

Transportation Certification Branch Division of Fuel _ Cycle and Material Safety, NMSS Date:

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