ML20245J641

Certificate of Compliance 9168,Rev 5,for Model CNS 8-120B

ML20245J641
Person / Time
Site:	07109168
Issue date:	06/27/1989
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20245J635	List: ML20245J631 ML20245J641
References
NUDOCS 8907030115
Download: ML20245J641 (9)

Text

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1 I eron n u u.s. NUCLEAR CEIULATORY COMMIS88 N l l m.au 1 CERTIFICATE OF COMPLIANCE 10 CFR 7 I FOR RADIOACTIVE MATERIALS PACKAGES NUMBER d PAGE UMBER e. TOTAL NUMBER PAGES T/dgg NUMBER b RgiS3ON NUMBER c PAgA E IgT T

I I r.eREAMatE i a. This certificate is ertued to certify that the packaging and contents described in item 5 below, meets the applicable sa fety standards set forth in Title 10. Code i of Federal Regulations. Part 71. " Packaging and Transportation of Radioactive Material."

I b. This carbrier's does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportal 6on or other I appiicabie reguistory agencies, including the governtnent of any country through or into which the package will be transported.

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T CA DN l s Tgiggs;ssugo oN uE sAsis of A SAFETY ANALYSIS REgRT g GgS I

l Chem-Nuclear 220 Stoneridge Systems, Inc.

Drive Chem-Nuclear Systems, Inc. application i dated June 19, 1984, as supplemented.

i Columbia, SC 29210 l . ooAET Nuuoc,! ;71-9168 cert icate is conf- . < wi fulfilling the requir

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nts of 10 CFR Part 71. as applicab and the conditions specified below.

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, 'p l (1) Modello.: CNS 8-1208 ,/ fr[/.

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I The packaging is a carbon steel-encased',1; lead shielded J4-inch OD by I

88-inch high cask for radioactive waste mater als. The cask is a right l circular cyl'inder.with al62-Tnch IDiby 75-inch high cavity. The walls l i of1the cask contain a' lead thickness of43:35 inches encased in 0.75-inch  !

i thick

• inneri steel, shell 'and!1-1/2-inch; thick outer stfel shell. The l exposed sides 'of:the package:are provided with, a thermal barrier l I consisting of a-5/32-inch diameterjwire wrap o'n 12-inch centers and I cove red ' wi th ' a ' 3/16-i nch - thi cki. steekja c ke t. The bottom weldment is made l of two; 3_-1/4-inch ~ thick. carbon' steel. plates. The7 primary lid is sealed i with a" double silicone 0-ring and'20 eq6 ally spaced-2-inch diameter bolts, i The 29-inchidiameter cente' red secondary lid is s'ealed with a double I silicone 04ingandtwelveeq0allyspaced2-inchdiameterbolts. The I optional drainjline is sealed with a 3/4-inch' diameter cap screw and a l I silicone 0-ring. The lid sealing surfaces are stainless steel and the j space between the double 0-ring. seals is"provided with a test port for leak testing. "1  %

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l The top and bottom of the cask is provided with steel encased, rigid I polyurethane foam impact limiters. The impact limiters are secured to I

each other about the cask with eight 1-inch diameter ratchet binders.

l The impact limiters are 102 inches in diameter and the overall height i of the package with the impact limiters attached is 132 inches.

I I The package is provided with four tie-down and two removable lifting i devices. Each lid is provided with three lifting lugs. The gross I

I weight of the packaging and contents is approximately 74,000 pounds.

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I 8907030115 890627 S I PDR ADOCK 0710 n c .-

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I Page 2 - Certificate No. 9168 - Revision No. 5 - Docket No. 71-9168 l -

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I (a) (3) Drawings 3

I I The packaging is constructed in accordance with Chem-Nuclear I Systems, Inc. Drawing No. C-110-E-0007, Sheets 1, 2 and 3 Revision I H.

l (b) Centents l

l l

l (1) Type and form of material '

(1) Byproduct $aEer 1i t 'fhrn/of l soli 4%i Aw'aste contained withh(.dewatered secondary containerresins, (s); or solids, o

( 6 g/ ,

l (ii) Ra'di# t ave of material in the form of/Ictivated reactor

'c6m^ponents.

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l (2) Maximu uantity of material per package gr7 i

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". ,to exceed 2,000 times a i

l Type Type!.A,kquantityTofs quantity,1100lth'ermalf radioactive watts, ana .1 materialg 4;680 pounds includ I of the, contents,Jehohda'ry cintainer('s)/hndLshoring. Thi contents may I incluide fissile mat'srials provided the mask, limits of 10 CFR 671.53 are I

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i Except secondary forcontainer clossj fitting'conter,tspwood (s):(or^activatedicomp^onents shoring)must 'and thebe caskp, laced between cavity to prevent the I movement during; accident ccaditionsjofitransport. T ";

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7. The cask primaryslid must be2 secured.by twenty and the secondaryjlid by twelve, l 2"-8UNC-2A x 4" long hex cap screwsfwith a fla.t washer torqued.to 500 ft-lbs 50 ft-lbs(lubricated).A 1 i .

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,9 I 8. Prior to each shipment (except for the contents meeting th'e requirements for low I specific activity material which is transported by exclusive use vehicle), the I

packaging must be leak tested"in. accordance with Section 8.2.2.2 of the l application. "

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I 9. In addition to the requirements of Subpart G of 10 CFR Part 71:

I I (1) Each package must meet the acceptance tests and be maintained in accordance I

with the Acceptance Tests and Maintenance program of Section 8.0 of the I, application, and I

I (ii) The seals must be replaced with n:w seals if inspection shows any defects or i every 12 months, whichever occurs first. The test ports and optional drain I

line must be appropriately plugged and sealed prior to transport.

l l 10. (a) For any package containing water and/or organic substances which could i radiolytically generate combustible gases, determination must be made by I tests and measurements or by analysis of a representative package such that I the following criteria are met over a period of time that is twice the I

expected shipment time:

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Y I nerum . . .

l . nNu ea' conomous (continued) * * " " " " " " *

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I Page 3 - Certificate No. 9168 - Revision No. 5 - Docket No. 71-9168 I

I l (1) The hydrogen generated must be limited to a molar quantity that i would be no more than 5% by volume (or equivalent limits for other i

inflammable gases) of the secondary containgr gas void if present I

at STP (i.e., no more than 0.063 g-moles /ft at 14.7 psia and I 70*F);or I

l (ii) The secondary container and cask cavity must be inerted with a i diluent to assure that oxygen must be limited to 5% by volume in I those portions of the package which could have hydrogen greater I than 5%. r7 CF g I

(, Ih O I { E by [f l For any package.delive' red to a carrier fordragsport, the secondary i containermustbelreparedforshipmentinths/samemannerinwhich i determination f~or gas generation is made. Shipment period begins when I

I thepackage'isprepared(sealed)andmustbecomp@edwithintwicethe expected 4hipmenttime. .

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% .m l (b) For ap packa'ge c'ontaining materials with.agadidactivlty concentration i not ek eeding that'f6rslow specific actiftly' material, and shipped i with,14,10 days off hepa'rationr~or-withirp17 days afterffenting of drums I orothprsecondarfcontainers,>th'e'determinationin(a)laboveneednot I

bem4de,andthetimeire'striction(in(a}abovedoesnotsapply.

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l 11. The package au,thbrized by th'is~ certificate is Ihefebyiapproved for'Q's e under the i

i general license" provisions of 10lCFR 971y12;gf y 43 4

Q l 12. Expiration date(mMarchl31,i1990.  !>

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i Chem-Nuclear Systems, I$. , application dated June ~19','1984.

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l l Supplements dated: Decembei 7; 1984; March 15 and December 9,11985; April 30, 1986; i I March 16 and April 13, 1987; and March 28, 1989.

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'FORTHEU.S;NbCEARREGULATORYCOMMISSION I I I

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Charles E. MacDonald, Chief l Transportation Branch i Division of Safeguards  ;

I and Transportation, HMSS i JUN 2 7 1989 Date: j l _

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. 'o UN8TED STATES 8 k NUCLEAR REGULATORY COMMISSION

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~ Transportation Branch ^

Approval Record liodel No. CNS 8-1208 Docket No. 71-9168 Gy application dated March 28, 1989, Chem-fluclear Systems, Inc, requested an amendment to Certificate of Compliance No. 9168 to authorize an optional lid lifting lug design and to make editorial changes in the content description.

The requested optional design in the lid lifting lug was reviewed and the analy-ses have verified that no safety features will be adversely affected on the package. The content description in the Safety Analysis Report was changed to use the wording in Revision 4 of the Certificate of Compliance and incorporate the wording of 10 CFR 671.53.

The NRC staff finds that the proposed amendments to Certificate of Compliance No.

9168, do not adversely affect the ability of the package to meet the requirements of 10 CFR Part 71.

b A':.b c uY Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS 27 N Date:

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