ML20138N755

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Certificate of Compliance 9019,Rev 13,for Model BU-7. Approval Record Encl
ML20138N755
Person / Time
Site: 07109019
Issue date: 12/16/1985
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20138N738 List:
References
NUDOCS 8512240146
Download: ML20138N755 (5)
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y- ------------------------------------------------m-- g I NRC FORM eis U.S. NUCLEAR RE*ULATORY C*MMISSION N I *.u CERTIFICATE CF COMPLIANCE >

I C" " FOR RADIOACTIVE MATERIALS PACKA!ES N

1. CERTIFICATE NUMBER b REVISION NUMBER c. PACKAGE IDENTW8 CATION NUMBER . PAGE NUMBER e TOTAL NUMBER PAGES g 9019 13 USA /9019/AF 1 4 p I  : eREAusLE F g .. Tnis c.nivic.t. is .. u.o io c.ri.Ty in.i in. ptcu.ams .no coni nis o.scrio.o in siem s d.io.. m <> in..ppisc oi. < y siano ros sei tortn in Tiii. io. coo. >

g of Feoeral Reguiations. P rt Ti. "P.ck.geng .nd Tr nsport. tion of Radio.ctiv. Materi.i" ll l 4 e inns coniercai. oo.. noi r.in. in. consignor erom compie.nc. ..in any r quir m.no or in. r.gui.i ons or in. u s o.o.nm.n oe Tr nspori.iion or ein., bj i .ppisc.oi. regui. tory .g.nce . incivoing in. go rnm n oi .nv country intouan or into on cn in. pacm s. . ii o. iranspori.o h

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I g 3 THiS CERTIFICATE IS ISSUED ON THE basts OF A SAFETY ANALYSs3 REPORT OF THE PACKAGE DESIGN OR APPLICATION E

R a 55UED r TO th se Amesr8 b TITLE ANO IDENTIFICATION OF REPORT OR APPLICATION 4 >)

N $l q General Electric Company General Electric Company application dated i P.O. Box 780 June 3,1981, as supplemented. [))

I Uilmington, NC 28401 N d 71-9019 N 4 c_oOcxETNUMoui V 4 . CONOiTiO~S I N Tnis certificate is conoitson.s upon fulfisiing ine r.quifements of 10 CFR Part 7i. .s appiscabi.. nd tne conditions specified belo. k l N 4 5 h it (a) Packaging K 4l q

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(1) flodel No.: BU-7.

0 l (2) Description f0 i

q The packaging consists of either two, 5-gallon or three, 2.5 or 3-gallon, k i ll.25-inch ID, mininun 24-gauge steel pails contained in a 13.75 to 1 i 14.05-inch diameter by nominal 27-inch long inner container constructed 4 of 18-gauge steel, with bolted and gasketed (1/8-inch thick silicone '

l rubber with a durometer hardness between 45 to 75) top flange closure.

g. The inner container is centered and supported in a 22.5-inch ID,18 4 g gauge steel 55-gallon capacity DOT Specification 17H steel drum by y i solid insulating material composed of fire-retardant phenolic foam  :

i (7-9 pounds per cubic foot). Drun closure is provided by a DOT .

Specification 17H,16-gauge drum cover and a 00T Specification 17H, l 12-gauge closure ring with drop forged lugs, drilled and threaded for y .

g 5/8-inch dianeter bolt and n:t . The maximum weight of the packa.ge is g 370 pounds. k(

( 4 4 (3) Drawina h I h The container is constructed in accordance with General Electric ll g Company Drawing No. Il2D1592, Revision 4. h(

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l 8512240146 851216 l l PDR ADOCK 07109019 I l C ppg l l .

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l CONolTioNS (continueQ

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l! Page 3 - Certificate No. 9019 - Revision No.13 - Docket No. 71-9019 1 I!

It i Il (iii) For the contents described in 5(b)(1)(iii):

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! g The maximun contents per package and pail for the naxinun l.

X U-235 enrichment shall be limited in accordance with the following  %

I He table: h

! 4' h l j tiaxinun U-235 fiaximum U0 f1'*i*"" U0

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enrichment, per pail,2 per packagh, i

s w/o kgs kqs %j i Yi 2.7 45.0 90.0 h l 2.8 42.9 85.8 h 2.9 40.1 80.2 h i  ! 3.0 38.1 76.2 g l 3.2 34.1 68.2 'Q PI 3.4 31 .0 62.0 F i! 3.6 23.5 57.0 N l 3.8 26.4 52.8 4.0 24.7 49.4 g in (c) Fissile Class I Q E

6. For mixtures of contents (powders and pellets) described in 5(b)(1), the maximun N

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j ouantity of material per package shall be limited to the quantity given in 5(b)(2)(iii). fp 1 '

i 7. For mixtures of contents as described in 5(b)(1)(ii), ammonium oxalate and/or b(

annoniun bicarbonate additives are pemitted in the U07 powder to the extent Fj i

i that the C/U ratio does not exceed 1.27. F

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] 8. In addition to the requirenents of Subpart G of 10 CFR Part 71:

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!  ; Prior to each shipment, the inner drun (container) silicone rubber gasket rust M l l he inspected. The gasket rust be replaced with a new gasket if inspection ~ shows Fj I any defects or every 12 nonths, whichever occurs first. Based on gasket age Il I

1. considerations alone: no gasket need be replaced until af ter June 30, 1986. l HR '

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9. The packaging rust be narked in accordance with 10 CFR 471.85(c). hi a 6 l j l 10. The four,1/4-inch diameter boles located near the top of the outer DOT Specifi- fj l l cation 17H steel drun shall be covered with weatherproof tape to preclude the il l entry of water.

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I i g 11. The package authorized by this certificate is hereby apprnved for use under the l g general license provisions of 10 CFR 971.12.  ; j

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12. Expiration date: April 30, 1989.

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CONolTlONS (continued) l l

l Page 2 - Certificate No. 9019 - Revision No.13 - Docket No. 71-9019  !

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! 5. (b) Contents  !

E i (1) Type and fom of material j l

i (i) Uraniun oxide powder with a maxinun bulk density not greater than  !

hl g 4.2 grams /cc. Uraniun may be enriched to not more than 4.0 w/o in the U-235 isotope. The naximun H/U atonic ratio considering l

Ei l 1 Hi all sources of the hydrogenous material within the inner container i

, Ri shall not exceed 0.45.

i i (ii) Uraniun oxide powder with a naximum bulk density not greater than 1;1

%g! 4.2 grans/cc. Uraniun may be enriched to not more than 4.0 w/o i

in the U-235 isotope. The naxinun H/0 atonic ratio considering glp3 E!

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

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l (iii) Uraniun oxide as pellets with a maximun bulk density of 4.2 grams /cc. Uraniun nay be enriched to a naximum 4.0 w/o in the U-f gj l 235 isotope. The maximum H/U atomic ratio considering all sources y i of the hydrogenous material within the inner container shall not Ly i

i exceed 0.45. Ipi d, '91 (2) Itaxinun quantity of material per package 1 i kl h

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R, (i) For the contents described in 5(b)(1)(i):  !

8 The maximum contents per package and pail for the maximun U-235 f

, enrichnent shall be limited in accordance with the following 1 j

table: lpj l

Itaximun U-235 h

' , Maxinun.U0 Maximun U0 N enrichnent, per pail,2 per package 2 N w/o kgs kgs - j 3.0 44.5 89.0 l1

, 3.2 38.9 77.8 l' 3.4 34.6 69.2 l 3.6 31 .1 62.2 i

3.8 28.3 56.6 j.

j j 4.0 25.7 51.4 {Fj l l i-

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j (ii) For the contents described in 5(b)(1)(ii)- i i g! {

! gl g The naximum contents of urmium oxide powder per package and pail i i l' shall be limited to 70 kqs and 35 kgs, respectively.

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l l l CONDITIONS (continued) '>

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j Page 4 - Certificate No. 9019 - Revision No.13 - Docket No. 71-9019 i i i

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[ REFERENCES l i-General Electric Company application dated June 3,1981.  !

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

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! i! FOR THE U.S. NUCLEAR REGULATORY C0ft11SSION  ;

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, N fj i Charles E. MacDonald, Chief k Transportation Certification Branch &

Division of Fuel Cycle and E' j i

flaterial Safety, fitSS f)u

! j Date: DEC 161985 g h.

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% f,, UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION 5 :p WASHINGTON, D. C. 20555

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Transportation Certification Branch Approval Record flodel No. BU-7 Package Docket No. 71-9019 By application dated November 18, 1985, General Electric Company (GE) has requested a time extension for gasket replacement on the Model No.

BU-7 package.

On September 19, 1985, the certificate of the fiodel No. BU-7 package was amended to require gasket replacement at least every 12 months after December 31, 1985. GE has requested an extension of time until af ter June 30, 1986, for about 350 packages that had been loaded prior to October 2,1985. This extension of time should have no significant effect on the ability of the package to meet the requirements of 10 CFR Part 71.

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8 Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and flaterial Safety, fitiSS Date: DEC 161985 l

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