ML20129C213

Certificate of Compliance 9111,Rev 11,for Models CNS 6-80-2 & CNS 6-80-2A.Approval Record Encl

ML20129C213
Person / Time
Site:	07109111
Issue date:	05/22/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20129C196	List: ML20129C193 ML20129C213
References
NUDOCS 8506050439
Download: ML20129C213 (4)

Text

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• I E " CERTIFICATE OF COMPLIANCE "lN N l io Crm

• FCR RADIOACTIVE MATERIALS PACKAGES jE 1 a CEAT!FICATE NUMBER b REvi$loN NUMBER c. PACKAGE loENT.'ICATION NUMBEST' d.PAGE NUMBER e. TOTAL NUMBER FAGES i 9111 -11 USA /9111/A 1 3 g l 2 PREAMBLE N 1 I a. This certificate is issued to certify tnat tne packaging and contenis deseneed in item s beiow. meets tne appocaeie safety standaros set fortn in Titie io, code N l of Federal Regulations, Part 71. " Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certain Conditions." Il

b. This certificate does not reheve the con,ignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other k l apphcable regulatory agencies, including the government of any country through or into which the package will be transported.

1 il l * *'*4,"Ns^8v'fN.' '* .'".'JE"4"^5'S Chem-Nuclear Systems, Inc.

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Chem-Nuclear Systems, Inc., application fj lj 220,Stoneridge Drive dated June 29, 1583, as supplemented. y

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This certificate is conditional upon fulfilhng the requirerrients of 10 CFR Part 71. as apphcaele, and the conditions specified below

% 5- (a) Packaging N N

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lg (1) Model Nos.': (CNS6-80-2andCNS6-80-2A f

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1 (2) Description - lE E 1 1 lN <

E A steel l encased. lead-shielded cask' for solid radioactive material ill meeting the requirements for-low specific activity material. The f

.g overal1 dimensions of'the cask are 70-1/2-inch diameter by 78-5/8-inch

- p 1 height._ The. cask consists. of._two concentric carbon- steel cylindrical u 1 shells' surrounding aJ4-1/4-inch: thick ' lead shield. :The 3/8-inch thick N

,1 inner shell has2 59-inch -ID, and the 1-inch thick outer shell has a E il 70-1/2-inch OD; the base consists of 4-inch thick welded steel plates E

) 6f 60-inch diameter and 70-1/2-inch diameter, and a stepped welded lid l j comprised of two, 4-inch thick steel plates containing a centered y

) 29-inch diameter secondary lid of1similar construction with an additional n

1 1-inch thick upper plate. The containment' cavity is 59-inch diameter ;E il by 58-inches high. Closure of the primary lid is accomplished by ;H eight,1-1/4-inch bolts or studs and nuts. Both lids on Model No. lE j

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!yl CNS-6-80-2 are sealed using silicone gaskets. The secondary lid has a redundant Neoprene seal ., Both lids on Model No. CNS 6-80-2A are jly

!1 sealed using a double 0-ring configuration as shown on Drawing No. C- p ,

1 110-D-0020, Rev. . A plugged drain port is located at the cask N

1 bottom. The cask is lined with 12 gauge stainless steel. Three lift N 1 lugs, located on the secondary lid are used for lifting both the cask lg and the primary lid. Four lugs, welded to the outer shell are used j!) for tie-down. The package gross weight is approximately 51,500 pounds. y 1 N 1 (3) Draking N 1 it il The packaging is fabricated in accordance with Chem-Nuclear Systems, j

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_ Incorporated Drawing No. C-110-D-0028, Sheets 1 and 2 of 2, Revision A. l  :

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l PagiP.'-CertificateNo'.9111-RevisionNo.11-DocketNo. 71-9111 [

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I ~5. .(b)~_ Contents t I E l .(1) Type and form of material [

! (i) -Greater than Type A_ quantity of byproduct material contained in f I solids and solidified waste, meeting the requirements for low t I specific activity material, in secondary containers. L I L l (ii) Greater than Type A quantity of byproduct material contained in [

g activated solid components meeting the requirements for low t..

I special activity material. t-I n QC E (2) Maximum quantity o . terial per. n .pacgge, g l

l Greater than q[y e' A quantity of- radioackiv(material with the weight [

q of the cont'ent , secondary containers and sho"r'ing not exceeding 7,500 t I pounds. Th'e' decay heat load must not exceed 60fwatts. The contents t I may incibd6 fissile materials provided the mass-limits of 10 CFR 571.53 t I X/ "" / E t

'] are n[ot f exce'eded.Mh .k/

(a) For any package containingswater_.and/or ,organi.c' substances which could

6.

radiolytically genera'teTcombustiblPgasest determination,must be made by (Ig" l

I tests and.measurementsJdrfby analysis of a9epresentativefpackage such that l t t I the following criteria are metJverzitperiodtof time that>is twice the E l

expected [shipmentCtimei3 M g ,,/ f $

g (1) fB Dil %j 9 s i a j a l E w ,WZ The hydrogen;generatedanust g

g be no1more than\S%.by(or, volume;bejl,iniitEd tocalmolar giantity[t th equivalent > limits,forotherinflam-I mable'ga'ses.)'of$thdt se?condaritc6ntaifer)ga's voiditf[present at STP t I (i.e.,'no moreithan10.063 g-m' oles /ftfat 14.7 psis'and 70*F); or t I

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'6 container (ii) The secondary U M/liand,ca@sk WU W cavity must;be'inerted with a dilue l g g to assure that oxygen must be limited to 5%;by' volume in those portions g g of the package which could have hydrogen greater than 5%. t

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> For any package deliver i tol$l'ca/rie[. Tor ransport, the secondary container 1 -must be prepared for shipment in 'the same manner in which determination for E l gas generation is made. Shipment period begins when the package is prepared (-

g (sealed) and must be completed within twice the expected shipment time. t I t 1 (b) For any package shipped within 10 days of preparation, or within 10 days t I after venting of drums or other secondary containers, the determination in L (a) above need not be made, and the time restriction in (a) above does not [

' l apply.

, g l t l l 7. Except for close fitting contents, shoring must be placed between secondary t I . containers and the cask cavity to prevent movement during nonnal conditions of t.

I ~ transport. . t-I L

) 8. The cavity drain line must be sealed with appropriate sealant applied to the (

i i pipe plug threads prior to transport, r M .

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conoirsons (continued) 1

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)j Page 3 - Certificate No. 9111 - Revision No.11 - Docket No. 71-9111 l 3 W 1 - - -

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9. Packages must be leak tested initially and at least once every 12 months. A l

-l pressure drop test shall be used. The cavity or volume between the double 3

0-ring seals (Model No. CNS 6-80-2A) shall be pressurized to 14.0 psig. Seal 5

-) acceptance must be based on no observable leakage over a ten minute period using ,

1 a pressure gauge with a maximum graduation of two pounds and the pressure l 3 supply line disconnected from the cask and test fixture.  ;

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-j 10. The package authorized by this certificate must be transported on a motor j vehicle, railroad car, aircraft, inland water craf t, or hold or deck of a seagoing lg .

j vessel assigned for sole use of the licensee. d

1 m n r- m W 3 11. The package authorized by this dertificatd!is;hereby approved for use unde'r the E 3 general license provisions;of010 CFR 571.12. U) - E 1 s.q , li

! 12. Expiration dated: Oct'ob{d[v 31, 1988. 'd lp 2 %Y U i T '

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4 REFERENCES ti!

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! Chem-Nuclear Systems,'Ilicorporatsd'a'pplication dated' June 229,1983.', j 2

Supplement dated:

~ ru September 19fl983.)/ ,/._

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O LChar es t. MacDonald, ChidT in

l  % Transportation'. Certification Branch jI

-l ' d'n Div'ision of Fuel Cycle and Material Safety, NMSS  !

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-~,, UNITED STATES

' * 'y[." g NUCLEAR REGULATORY COMMISSION p WASHINGTON, D. C. 20555

\ ..... p .. 2 Transportation Certification Branch Approval Record l

Combustible Gas Mixtures  !

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Conditions were imposed on packages containing water and/or organic i substances to limit the accumulation of radiolytically generated gases d over the shipping period to preclude the possibility of significantly reducing the packaging effectiveness due to explosion.

Part of the conditions included "...it must be detemined by tests and measurements of a representative package whether or not...."

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!. There is no reason to believe that calculational methods could not be used as means of determining gas generation. So as not to preclude a valid analysis, part of the condition to limit the accumulation of radiolytically generated gases is revised to read "...it must be detemined by tests and measurements or by analysis of a representative package <

whether or not. . . ."

The analytic approach involves detemining the hydrogen generated in the waste by radiolysis based on the absorbed dose of the waste over a given period of time. To satisfy the condition to preclude a combustible t mixture, the period since closure;and twice the shipping time must be I considered. The calculation requires that the properties of the waste are known. These properties may be detemined from test and measurement of representative waste forms or from data that is applicable to the waste form. The determination should be documented and retained as part of the records for the shipment.

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Charles E. MacDonald, Chie Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:

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