ML20203G630

Certificate of Compliance 9089,rev 13,for Model HN-194S Package

ML20203G630
Person / Time
Site:	07109089
Issue date:	12/08/1997
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203G619	List: ML20203G618 ML20203G630
References
NUDOCS 9712180176
Download: ML20203G630 (5)

Text

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1. l #" N I OR RADIO 4CTIVE MATERIALS l'ACKAGES

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9089 13 USA /9089/A 1 4 l

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$ a thinerurante is issued to ceruf that 3 the packagarrs and contents ociented in item 5 telo , nects the appbcable safet) standardi sei forth in Title 10. k

% Code of f ederal Regulations. Part 71,

• Pat Leging and Transynaten of Radniective Maienal

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It b This certifnate d:e run reheve the consignor hom comphance mith any requirement of the regulanons of the U.s Department of Tranignauon cv other I T, appinable regulator) agencies,includarig the gmernrnent of ariy countr) through oc anno which the package mill be transyned I' s

.I ( i h ) TMit CI RTIF1CATE a l$$tU)TO f Aww.md A.tdress) 15155tu)ON T1(I bli41110F A S AFTTY TiltL ANDIDLN71nCA110N ANORALY115 OT R.EPORT APPL.lCAT10NRifoRT OF T}tt FACA 4GL k ki Molten Metal Technology, Inc. Westinghouse Hittman Nuclear, Inc. 4

'i 1009 Commerce Park Drive App 1tcation dated October 28, 1988, E

? Oak Ridqe, TN 37830 as suppleunted. E;

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+ Tius cemfnete 6s condiuonal upon fulfilhng the requirernents of 10 CfR Part 71, as apphcable, and the conJiuons specified telom g:

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%, s(a) Packaging El S E

$, (1) Model No.: HN-1945 E 3 E 4, (2) Description E

$ E The cask is a steel annulus 84-1/4 inches high by 81-5/8 inches in diameter. g

%; The cavity is 75-1/2 inches high by 7S-5/8 inches in a

+. diameter. The side walls consist of two plys of 1-1/2-inch steel. g  !

+l The 3-inch steel base is integrally welded to the cylinder. The lid g

+, is a 3-inch steel plate, stepped to mate with the upper flange of the g

% cylinder. A centrally located shield plug is similarly constructed. g

+, The lid and plug are attached with stud-bolts and nuts and sealed y j with duna N 0-ring gaskets. A plugged drain line and/or optional vent / test in y, 4 the secondary lid connecticn is provided. Four skewed g i lugs welded to the outer shell are used for tie down. There are g

+ three cask lifting lugs, three lid lifting lugs, and one shield plug lifting g gl lug. The package gross weight is approximately 43,000 pounds. gl

'l (3) Drawings E

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+ The packaging is fabricated in accordance with Westinghouse Hittman Nuclear, y y' Inc. Drawing Nos.: STD-02-078, Rev. I and STD-02-079, Rev. O. g

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'  %- N Page 2 - Certificate No. 9089 - Revision No.13 - Docket No. 71-9089 f

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5. (b) Contents l

(1) Type and form of material. I

% Process solids', either dewatered, solid or solidified, and limited to the d

% following: I I 4

>% (1) Materials in which the radioactivity is essentially uniformly I l

%; distributed and in which the estimated average concentration per I

% gram of contents does not exceed: N ,

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% 0.0001 millicurie of radionuclides f ar which the A quantity in d

% Appendix A of 10 CFR Part 71 is not more than 0.05, curie; I .

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0.005 millicurie of radionuclides for which the A quantity in a A)pendix A of 10 CFR Part 71 is more than 0.05 c.u,rie, but not more u

% tian 1 curie; or I

% I 0.3 millicurie of radionuclides for which the A q g 9 Appendix A of 10 CFR Part 71 is more than 1 curie.uantity in g s, p ,

pl (ii) Objects of nonradioactive material externally contaminated with a t

radioactive material, provided that,the radioactive material is not g readily dispersible and the surface contamination, when averaged q

%p over an area of I square meter, does not exceed 0.0001 millicurie y D'

I (220,000 disintegrations )er minute) per square centimeter of g p radionuclides for which tie A, quantity in Appendix A of g 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie g tl' p

e (2,200,000 disintegrations per minute) per square centimeter for other radionuclides, g

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1. E p (2)- Maximum quantity of material per package, g

1. l gl Greater than Type A quantity of radioactive material which may contain E

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i fissile material provided the fissile mateiial does not exceed the g p' ,

limits in 10 CFR 671.53. The weight of the contents, secondary g containers and shoring must not exceed 17,000 pounds and the internal pl decay heat load must not exceed 2 thermal watts.

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Page 3 - Certificate No. 9089 - Revision No. 13 - Docket No. 71-9089 l

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6. (a) For any package containing water and/or organic substances which could I l4 radiolytically generate combustible gases, determination must be made by I

,t I tests and measurements or by analysis of a representative package such that

'i s the following criteria are met over a period of time that is twice the I expected shipment time:

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

1. e gases) of the secondary coptainer gas void if present at STP (i.e., no I 6 mcre tht ' ^'3 g-moles /ft at 14.7 psia and 70*F); or I i

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I (2) The se ondary container and cask cavity must be inerted with a diluent I 1

to as ure that oxygen must be limited to 5% by volume in those portions E 4

of the package which could have hydrogen greater than 5%. E i

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% For any package delivered to a carrier for transport, the secondary I

1. 4 container must be prepared for shipment in the same manner in which I

1. determination for gas generation is made. Shipment period begins when the u D, package is prepared (sealed) and must be completed within twice the expected u

1. , shipment time. I

1. I 6,i (b) For any package shipped within 10 days of preparation, or within 10 days a after venting of drums or other secondary containers, the determination in u (a) above need not be made, and the time restriction in (a) above does not a apply. E i

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7. Except for close fitting contents, shoring must be placed between the secondary q containers and cask cavity to minimize movement during normal conditions of g transport. g l 8. The lid and shield plug lifting lugs must not be used for lifting the cask, and l shall be covered in transit. y Packagings without a drain line must be provided with the optional vent / test g connection in the cask secondary lid, l9. g

10. The drain line and optional vent / test connection must be appropriately plugged and l-sealed prior to transport. g l

n'i 11. Prior to each shipment, the packaging lid seals, if opened (or if the security l g seal is broken), must be inspected. The seals must be replaced with new seals if g g inspection shows any defects or every twelve months, whichever occurs first, y hl'12.

p The packaging must be leak tested at least once every twelve months in accordance with Leak Test Procedure STD-P-02-002, Rev. 3, dated August 18, 1989. Each cask f

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which has been damaged or repaired in the area of a seal must also be tested prior g g to subsequent use; normal gasket maintenance does not require a subsequent test. y f

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Packagings fabricated after November 30, 1983, must be constructed of A-516, Grade 70 carbon steel. y El E

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. e h Page 4 - Certificate No. 9089 - Revision No. 13 - Docket No. 71-9089 I '

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% N 8, 14. The package authorized by this certificate must be transported on a motor vehicle, N ,

t railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel N;

% assigned for the sole use of the license, d'

% I e, 15. The packaging shall be prepared for shipment and operated in accordance with the d

% Operating Procedures of Section 7.0 of the application. I

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% 16. Each package must meet the Acceptance Tests and Maintenance Program of Section 8.0 g 6 of the application, q

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1. Packaging fabricated in accordance with Hittman Nuclear & Development Corporation u

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Drawing Nos. C001-5-9128 Rev. 5 and C001-5-9129, Rev. 3 are not authorized after a 9

4; April 1989. q

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>l18. The package authorized by this certificate is hereby approved for use under the g general license provisions of 10 CFR 671.12. g

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4l19. Expiration date: April 1, 1999. This certificate is not renewable. g N

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REFERENCES g I

28, 1988. I

• lWestinghouseHittmanNuclear,IncorporatedapplicationdatedOctober

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fSupplementsdated: January 26, 1989; December 22, 1993; and October 10, 1997. l '

s d f$ FOR THE U.S. NUCLEAR REGULATORY COMMISSION f

N h$ f'? 8 Cass R. Chappell, Chief h' Package Certification Section I t

,i Spent Fuel Project Office I

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, Office of Nuclear Material Safety N and Safeguards

,l Date; December 8,1997 E

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APPROVAL RECORD Model No. HN-194S Certificate of Compliance No. 9089 Revision No. 13 By letter dated October 10, 1997, Scientific Ecology Group, Inc., 'and Holten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9089 for the Model No. HN-1945 package be changed from Scientific Ecology Group, Inc., to Molten Metal Technology, Inc. Molten Metal Tec5nology, Inc., has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holder. Molten Metal Technology, Inc., will be responsible for maintenance of r the certificate, the safety analysis report for the package design, and the quality assurance records in accordance with 10 CFR 67).91(c). Molten Metal Technology, Inc., stated that tht records required by 10 CFR $71.91(c) for the pt.ckage design will be maintained at their document control center in Oak Ridge, Tennessee. Molten Metal Technology, Inc., has been issued Quality Assurance Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71.

The Certificate has been revised to show Molten Metal Technology, Inc., as certificate holder. These changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.

Cass R. Chappell, Chief Package Certification Section Spent fuel Project Office Office of Nuclear Material Safety and Safeguards Date: December 8, 1997 l

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