ML20059N691

Certificate of Compliance 9094,Rev 10,for Model CNS 14-195-H Package

ML20059N691
Person / Time
Site:	07109094
Issue date:	10/10/1990
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20059N689	List: ML20059N686 ML20059N691
References
NUDOCS 9010170146
Download: ML20059N691 (5)

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u.6, NUCLEAR Re!ULATORY COMMISSCN l E "".

CERTIFICATE CF CHIPLIANCE I

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I o cen ri pon nAotoacTivE aAATERIALS PACKAGES l

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-9094 10 USA /40cala i

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• Mc'eni,icai. i u.o io c.nir inat ine packaging ana conionis oe.cnoeo in item o deio*. rneeti ta* *pphcan'e **'e'v.tanaero..eiiorin m Tiii. io.coogI v

i os peoeral Reguistions Part 71. " Packaging and Transportater n of Radioactive Mater 31."

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I d Tna certificeve does not reheve ene consignor from comphance with any requirement of the reguistions of the U.S. Department of Transportation or other I

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.,pi.e. bio reguiatory agencies,inciuoing ine government of any country through or into which the pack *o'"'H be t'anipoeo-I I

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> rsisjtagspys;ssguon Tse easis or a sattTv Anatysis,ncy,tgiggego,rgs,i,ogo,a *ge,A,gy, I

!g Chem-Nuclear Systems, Inc.

Chem-Nuclear Systems Inc. application i

220 Stoneridge Drive dated May 1, 1985, as supplemented

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Columbia, SC 29210 y

c DOCKET NUMBER

• / j,QQQ g ste 6s conditional upon fulfiinng the requirements of 10 CFR Part 71, as apphcable, and the conditions specified below.

(a) Packaging l

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(1)

Model.No.: CNS 14-195-H I

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Description l

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I A steel encased lead shielded cask for low specific activity l

l material. The c6sk is a right circular cylinder 83-1/8-inch I

diameter by 89-7/8-inch with a 77-inch diameter by 80-1/8-inch I

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cavity.

Lead shielding-is 2-3/16-inch thick, and is encased in I

l an outer steel shell 3/4-inch thick and an inner steel shell l

l 1/8-inch thick. Positive closure of the silicone rubber-sealed g

I lid is provided by' twelve, 1-1/4-inch diameter cap screws. A I

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secondary lid with'a Neoprene seal uses eighteen, 3/4"-10VNC 1

bolts for closure. The cask is~ welded to a 96-inch square based I

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plate,.has two lifting trunnions, three lid lift rings and one I

i secondary: lid lif ting ring.

Package gross weight is 56,500 pounds.

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(3)

Drawings I

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The packaging is fabricated in accordance with Chem-Nuclear II l

Systems, Inc. Drawing No. 1-189-101, Sheet 1 of 1, Rev. A-G.

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The optional shield inserts are fabricated in accordance with l

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Chem-Nuclear Systems, Inc. Drawing No. C-119-B-0017, Rev.

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,I (b) Contents ll l

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(1)

Type and form of material l.

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(1)

Process solids, either dewatered, solid or solidified in gl l

l secondary containers, meeting the requirements for low I

specific activity material; or i

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(ii)

Solid reactor components in secondary containers, as I

required that meet the requirements for low specific p

l activity material.

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9010170146 901010 N

PDR ADOCK 07109094 l

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ctwom:ws (cononv.s.

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.Pe9e 2 - Certificate No. 9094 - Revision No. 10 - Docket No. 71-9094~

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(2)

Maximum quantity of material per package i

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I Greater than Type A quantity of radioactive material with the I

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weight of the contents, secondary containers, shield inserts i

and shoring not exceeding 17,700 pounds.

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(a) For any package containing water and/or organic substances whichl 1

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could radiolytically generate combustible gases, determination must I

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be made by tests and measurements or by analysis of a l

l representative package such that the following criteria are met i

i over a period of time that is twice the expected shipment time:

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(i)

The hydrogen generated must'be limited to a molar quantity i

I that would be no more than 5% by volume (or equivalent limits.

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for other inflamable gases) of the. secondary container gas l

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void if present at STP (i.e., no more than 0.063 g-moles /ft i

i at 14.7 psia and 70*F); or

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I (ii)

The secondary container and cask cavity must be inerted with a 1

I diluent to assure that oxygen must be limited to 5% by volume l

l in those portions of the package which could have hydrogen l

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. greater than 5%.

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l For any package delivered to a. carrier for transport,3the secondary 1

l container must be prepared for shipment.in the same manner in which l

I determination for gas generation.is made.. Shipment period begins l

when the package is prepared (sealed) and must be completed within l

i twice'the expected shipment: time.

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(b) For any packageishipped within'10 days of. preparation, or within 10 l

I days after venting of drums or other< secondary containers, the I

I determination in (a) above need not be made, and'the time I

i restriction in (a) above does not apply l :

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1 7.

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

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and the cask cavity to prevent' movement during normal conditions I

l of transport.

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8.

The lid lifting -lugs must not be used for lifting the cask and shall be l

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covered in transit.

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9.

In addition to the requirements of Subpart G of 10 CFR-Part 71:

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. a.-

Prior to each shipment the lid gaskets if opened (or if security seal is l

o broken), must be inspected. These shows any defects or every twelve (gaskets shall be replaced if inspection i

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12) months', whichever occurs first.

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b.

The package shall be prepared for shipment and operated in I

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accordance with Section 7.0, Operating Procedures, in the I

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application dated May 1, 1985, and supplements dated August i

26, 1985 and August 23, 1990, i

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The package must be maintained in accordance with Section 8.0, I

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Tests and Maintenance, in the application dated May 1, 1985.

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I CONDITl:NS (connnusd)

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'Page 3 - Certificate'No. 9094 - Revision No. 10 Docket No. 71-9094 l

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-10.

Fabrication of additional packagings is not authorized.

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11. The package authorized by this certificate must be transported on a I

l motor vehicle, railroad car, aircraft, inland water craft, or hold or l

i deck of a seagoing vessel assigned for sole use'of the licensee.

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12. The package authorized by this certificate is hereby approved for use I

l under the general license provisions of 10 CFR 971.12.

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13. Expiration date: October 31, 1995.

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1 REFERENCE I

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l Chem-Nuclear Systems, Inc. application dated May-1,1985.

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i Supplements dated: ' August 26, 1985 and August 23, 1990.

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I FOR THE U.S. NUCLEAR REGULATORY COMMISSION I

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&&A Mad.

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Charles E.

acDonald, Chief I

I Transportation Branch:

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Division of Safeguards,

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and Transportation, NMSS I

Date: OCT 10 1993 l l

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8 UNITED 8TATES NUCLEAR REGULATORY COMMISSION s

nAsHmoTow, o. c. zosos -

APPROVAL RECORD Model No. CNS 14-195-H Certificate of Compliance No. 9094 Revision'10 By application dated August 23, 1990, Chem-Nuclear Systems Inc., requested that Cert'ificate of Compliance-No. 9094 be amended to allow the use of optional steel shield inserts in the Model No_. CNS 14-195-H package..The Model No. CNS 14-195-H-is used-for shipment of low specific activity (LSA) material. The applicant also requested that the certificate be renewed for a five' year period.

The optional shield inserts would be used to increase the total activity (number of curies) of LSA material that could be shipped in the Model No. CNS 14-195-H package. The shield inserts are needed for some LSA contents to reduce the external radiation levels at-two meters to 10 mrem /hr or less (as specified in 10 CFR 971.47 for~ exclusive use shipments). The limit at two meters is more restrictive for most LSA wastes than the limit (200 mrem /hr) at the-package s

surface.

No additional shielding is required on the top or bottom of the package where the limits for exclusive use shipments (in open vehicles) require only that the radiation level at the package surface.does not exceed 200 mrem /hr.

The-Model No. CNS 14-195-H package is required to be shipped in an upright position as'an exclusive use shipment.

The certificate is being amended to allow the use of optional steel shield inserts fabricated in accordance with Chem-Nuclear Systems, Inc. Drawing No. C-119-B-0017, Rev.

. The drawing specifies the minimum and maximum height, outer diameter and wall thickness of the shield inserts.

The drawing also specifies that the inserts be fabricated from ASTM A36 carbon steel.

The certificate has also been conditioned to require that the weight of the shield inserts be included in the overall content weight limit of 17,700 pounds.

The weight.of the shield inserts is significant and depending on wall thickness can-vary between 1,940 and 7,900 pounds.

The applicant submitted revised operating procedures outlining the methods used

--to determine whether a shield insert is required'for a shipment of LSA material.

Based on the activity and isotopic composition of the LSA waste, the shipper determines whether a shield insert is needed by comparing the contents with

g previous shipments or by performing a specific shielding analysis. As specified in the operating procedures, each_ package, whether it contains_an optional shield insert or not, must be surveyed prior to shipment to assure that it meets-the requirements of 10 CFR 671'.47.

The certificate has been conditioned to requirei that-the package be prepared for shipment,' operated and maintained -in accordance with the May 1,1985' application, as supplemented on August 26, 1985 and August 23, 1990.

Fabrication 'of additional packagings is'.not authorized.

The' inserts were reviewed by staff.and determined not to be significantly affected by normal conditions of transport.

The amendment will'not affect the ability of the Model No. CNS 14-195-H packaging to meet _ the requirements of 10 CFR Part 71. Accordingly, the certificate has been renewed for a five year term which expires October 31, 1995.

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Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS 00T 101990 Date:

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