ML20129C885

Certificate of Compliance 9096,Rev 8,for Model CNS 21-300. Approval Record Encl

ML20129C885
Person / Time
Site:	07109096
Issue date:	05/22/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20129C877	List: ML20129C874 ML20129C885
References
NUDOCS 8506050702
Download: ML20129C885 (4)

Text

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NRC FORM 818 U.S. NUCLEAR RE!ULAT!RY C!MMISSl!N i I

CERTIFICATE OF COMPLIANCE l

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av FZR RADl! ACTIVE MATERIALS PACKAGES i

1.a.CE..TIFICATE NUMBER D REVISION NUMBER

c. PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER

e. TOTAL NUMBER PAGES i g

9096 8

USA /9096/A 1

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2. PREAMBLE

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a. Tnis eertificate is issued to certify inat tne pacxaging and contents descneed in item s ocio.. meeti tne appiicacie safety standardi sei fortn in ritie to. code i g of Federai seguiations. Part 71,' Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certain Conditions."

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n. Tnis certificate does not reheve ine consignor from comphance witn any requirement of ine reguiations of tne u.s. oepartment of Transportation or otner l

apphCable regulatory agencies, including tne government of any Country tnrougn or into wnicn tne package will be transported.

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lE 3 THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSf3 REPORT OF THE PACKAGE DESIGN OR APPLICATION g

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e. PREPARED BY (Name and Addresst

b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION 13 Chem-Nuclear Systems, Inc.

Chem-Nuclear Systems, Inc. application lN j

220 Stoneridge Drive dated April 14, 1980, as supplemented.

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Columbia, SC 29210

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71-9096 R

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Tnis certificate is conditional upon fulfithng tne requir'ernents of to CFA Part 71, as apphcable, and tne conditions specified below l

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(a)

Packaging C#

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5 (1) Model No.: 'CNS.21-300 N

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(2) Description

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g' A steel encased lead shielded cask for [ low specificiactivity radioactive g

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The caski st a right. circular cylinder with 86-3/4-inch OD E

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by ll7-1/4-inch height,Jand a cavity 83-inch ID by.109-1/4-inch height.

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l1 The 1-inch thick lead -shield-is supported by outer and inner steel N

!N shells -3/4-inch and 1/8-inch thick.; The inner plates of the lid and 8

ll base are laminated ~steelf plates with a total thickness of 1/2-inch.

gj Positive closure of"the silicone rubber sealed lid is provided by g

g twelve,1-1/4-inch diameter cap screws. A secondary lid with a Neoprene i

1 seal uses eighteen, 3/4-inch diameter bolts for closure. The cask is N

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j welded to a 96-inch square' base plate and has two lifting trunnions, I

three lid lift rings and one secondary lid lift ring.

Package gross j

l weight is 57,450 pounds.

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(3)

Drawings N

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The packaging is fabricated in accordance with Chem-Nuclear Systems, N

j Inc. Drawing Nos. 1-298-101, Rev. J, and C-114-D-0006, Rev. A.

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' Page 2 - Certificate No. 9096 -1 Revision No. 8 - Docket No. 71-9096

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55.

l(b)-. Contents-l r

(1) Type and fom of material L

r (i) Process solids, either dewatered, solid or solidified in secondary L

containers, meeting the requirements for low specific activity l

material; or i

r (ii) Solid reactor components in secondary containers, as required -

I that meet the requirements for low specific activity material.

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'(2) Maximum quantity of materi,alQeitpackage

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Greater than, Type A'q}uantity of radioactiyelmaterial with the weightI of the contents', secondary containers, auxi-liary shield, and shoring I

For any packa& g

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not exceedin 27,250 pounds.

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ge' containing water and/or organic,substa'nces which could f

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-(a) radiolytical.ly generate, combustible gases, determinatiorii must be made by r

tests and sieasuremehtpfrsby analysis of,a'repfesentative, package such that l

l the follow {ng criteria 7are met overga periodiof time tha'tJis twice the I

expected shf'pment tims:

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. (1) The hyjrogenfgenerat must-$Elimi ed?td a molar qGHtity that would l

be no inore than' SE6y4f,'olume (ot eqUivil'entglimits f6r other inflam-l 7

mabidgeses)fol he2secohda'ry(costaipr gasso~id iCp: asent at STP l

n;0.063{' ore 5/ft at 14;7< psia ana 70*F); or I

(i.e.,0 no more; (ii) The secondary?W }%Q l1h h fcont$ner-an : cask. cavity must be ine I

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to assu'rii that "oxygenimust'belliinited ts 5% by v61ume in those portions l

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i of the pa,ckage which could' hava hy'drogen greaterJthan 5%.

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f For any package del 19ered to a carrier for transport, the secondary container I

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must be prepared foFshipment in the same manner in which detemination for L

j gas generation is made. > Shipment _ period begins when the package is prepared l

L (sealed) and must be completedtwithin twice the expected shipment time.

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(b) For any package shipped within 10 days of preparation, or within 10 days I

after venting of drums or other secondary containers, the detemination in I

(a) above need not be made, and the time restriction in (a) above does not I

a pply.

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Shoring must be placed between secondary containers (or activated components),

i auxiliary shield, and the cask cavity to prevent movement during nomal conditions I

of transport.

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The auxiliary shield shown in Drawing No. C-114-E-0004, Rev. No. 8, may be used l-l n

for the shipment of solidified wastes and solid reactor components.

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CONDITl:Ns (continuid) l Page 3 - Certificate No. 9096 - Revision No. 8 - Docket No. 71-9096 W

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The lid lifting lugs must not be used for lifting the cask and shall be covered I

f in transit.

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Prior to each shipment the lid gaskets must be inspected.

The gaskets shall be

!t replaced if inspection shows any defects or every twelve (12) months, whichever t

occurs first.

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11.

Packagings fabricated af ter April 14, 1980, must be constructed of A-516, Grade 70 carbon steel instead of A-36 carbon steel.

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12.

The package authorized by this certificate-must be transported on a motor

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vehicle, railroad car, aircrafthihlandMtericfaft, or hold or deck of a seagoing I

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vessel assigned for sole use'of' the licensee. V/

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The package authorizech this certificate is hereby approved for use under the g!

general license provist'ons of 10 CFR 971.12.

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Expiration date: rMay 31N985.

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,N NO REFERENCES

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i Chem-Nuclear Systems,rInc. application' dated. Apri1\\143:1980.

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dune 28,il983.E@y'N)ihAg');L;ys f2 J"',

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i Supplement dated:

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%a "d ! Char' es E. MacDonald, Chief I

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" Transportation : Certification Branch f

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Division of Fuel Cycle and y

Material. Safety, NMSS E

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WASHINoTON, D. C. 20555

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Transportation Certification Branch Approval Record Combustible Gas Mixtures Conditions were imposed on packages containing water and/or organic substances to limit the accumulation of radiolytically generated gases u

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 detennined by tests and measurements of a representative package whether or not...."

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 determined by tests and measurements or by analysis of a representative package whether or not...."

The analytic approach involves detennining 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 mixture, the period since closure-and twice the shipping time must be considered. The calculation requires that the properties of the waste are known. These properties may be detennined from test and measurement of representative waste fonns or from data that is applicable to the waste fonn.

The determination should be documented and retained as part of the records for the shipment.

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-Y Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: IIAY 2 21985

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