ML20207G116

Certificate of Compliance 9089,rev 14,for Model HN-194S Package

ML20207G116
Person / Time
Site:	07109089
Issue date:	03/04/1999
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20207G113	List: ML20207G109 ML20207G116
References
NUDOCS 9903110417
Download: ML20207G116 (5)

Text

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1. j """ w"E """ CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES NlI 1.a CERTIMCATE NUMBER g i-g b. REVISION NUMBER c. PACKAGE IDLNTIMCATION NUMBER d. PAGE NUMBER c. TOTAL NUMBER PAGLS g

D j ' 9089 ' 14 USA /9089/A 1 4 g lj ,

Nl 2. PREAMBLE gl h

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a. This cenincate is issued to certify that the packaging and contents described in hem 5 below. meets the apphcable safety standards 6et forth in Title 10.

j Code of Federal ReFulatic ns. F.n 71. " Packaging and Transportation of Radioactive Material."

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b. This ceruncate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Depanment of Transponation or other h applicable regulatory agencies,includits the government of any country through or into which the package will be transponed. N kl 3 THIS CERTIRCATE IS ISSUED ON THE BASIS OF A SAFETY AN ALYSIS REPORT Ol

el a ISSUED TO(Name and Addersu b. TITLE AND lbEN11HCATION OF RE PORT OR APPLICATION. k N

Westinghouse Hittman Nuclear, Inc. 4 p- ATO Nuclear Services LL.C.

pf 669 Emory Valley Road Application dated October 28,1988, 4 gjj) b Oak Ridge, TN 37830 as supplemented. g; E q i p

c.DoCKETwuwBER71 9089 g )

$ 4 CONDITIONS g

p This cenincate is condiuonal upon fulfilling the requirements of 10 CFR Pan 71. en applicable, and the conditions specined below. g bij g i 5

R 1 (a) Packaging (1) ModelNo.: HN-194S l

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j (2) Description g ,

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j The cask is a steel annulus 84-1/4 inches high by 81-5/8 inches in diameter. The cavity is 75- g Bj 1/2 inches high by 75-5/8 inches in diameter. The side walls consist of two plys of 1-1/2-inch q B

steel. The 3-inch steel base is integrally welded to the cylinder. The lid is a 3-inch steel plate, y

%j stepped to mate with the upper flange of the cylinder. A centrally located shield plug is similarly q

1. j constructed. The lid and plug are attached with stud-bolts and nuts and sealed with Buna N N N

0-ring gaskets. A plugged drain line and/or optional vent / test in the secondary lid connection is N j provided. Four skned lugs welded to the outer shell are used for tie down. There are three N g cask lifting lugs, three lid lifting lugs, and one shield plup D' ting lug. The package gross weight is N g approximately 43,000 pounds.

E Drawings h n (3) y

% N B The packaging is fabricated in accordance with Westinghouse Hittman Nuclear, Inc. Drawing g B Nos.: STD-02-078, Rev.1 and STD-02-079, Rev. O. g E

N E Contents

5. (b) q E

N (1) Type and form of material.

D Process solids, either dewatered, solid or solidified, and limited to the following:

f pl p (i) Materials in which the radioactivity is essentially uniformly distributed and in which b the estimated average concentration per gram of contents does not exceed: 4 gj b

gl D 0.0001 millicurie of radionuclides for which the Ag quantity in Appendix A of B

gj 10 CFR Part 71 is not more than 0.05 curie; qi bj D<'

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l NRC FORM 618A CONDm0NS(natanwd; ' u.s. NUCLEAR CE2uLATORY CotRNasioN veo i-I Page 2 - Certificate No. g08g - Rey!sion No.14 - Docket No. 71-g08g I I I I - ,

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0.005 millicurie of radionuclides for which the A, quantity in Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; or l

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, 0.3 millicurie of radionuclides for which the A, quantity in Appendix A of i i 10 CFR Part 71 is more than 1 curie. i I L I (ii) ' Objects of nonradioactive material extemally contaminated with radioactive l I material, provided that the radioactive material is not readily dispersible and the i I surface contamination, when averaged over an area of 1 square meter, does not I 1 exceed 0.0001 millicurie (220,000 c',sintegrations per minute) per square centimeter I I of radionuclides for which the A, quantity in Appendix A of 10 CFR Part 71 is not I j more than 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per minute) per I squore centimeter for other radionuclides.  ;

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, , (2) Maximum quantity of material per package. ,

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Greater than Type A quantity of radioactive material which may contain fissile material i

I provided the fissile material does not exed the limits in 10 CFR $71.53. The weight of l i

i the conteras, secondary containers, and sho:ing must r,ot exceed 17,000 pounds and the l 4

) intemal decay heat load must not exceed 2 thermal watts. . I I h l I 6. (a) ' For any package containing water and/or organic substances which could radiolytically generate I I combustible gases, determination must be made by tests and measdroments or by analysis of a I I l representative packaca euch that the following criteria are met over a period of time that is twice I

the expected shipmerame: y l

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, (1) The hydrogen generated must be limited to a molar quantity that would be no more than , i'

, 5% by volume (or equivalent 1;mits for other inflammable gases) of the secondary i s container gas void if present at STP. (i.e., no more than 0.063 g-moles /ft* at 14.7 psia and i I 70*F); or >

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>. l I (2) The secondary container and cask cavity must be inerted with a diluent l l

1 to assure that oxygen must be limited to 5% by volume in those portions of the package I  ;

which could have hydrogen greater than 5%. I l l 8

For any package delivered to a carrier for transport, the secondary I j container must be prepared for shipment in the same manner in which determination for gas I

, generation is made. Shipment period begins when the package is prepared (sealed) and must ,

, be completed within twice the expected shipment time. ,

4 I l s (b) For any package shipped within 10 days of preparation, or within 10 days after venting of drums i j i or other secondary containers, the determination in (a) above need not be made, and the time l

I restriction in (a) above does not apply. I !

i i I j i 7. Except for close fitting contents, shoring must be placed between the secondarv containers and cask I j l cavity to minimize movement during normal conditions of transport. I l

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8. . The lid and shield plug lifting lugs must not be used for liftir:g the cask, and shall be covered in transit.

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D r D Page 3 - Certificate No. 9089 - Revision No.14 - Docket No. 71-9089 I B

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g Packagings without a drain line must be provided with the optional vent / test connection in the cask secondary lid. f g

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r g The drain line and optional vent / test connection must be appropriately plugged and sealed prior to g g transport. i b L b 11. Prior to each shipment, the packaging lid seals, if opened (or if the security seal is broken), must be L b inspected. The seals must be replaced with new seals if inspection shows any defects or every twelve r B mon &s, whichever occurs first. L b I E 12. The packaging must be leak tested at least once every twelve months in accordance with Leak Test I N

Procedure STD-P-02-002, Rev. 3, dated August 18,1989. Each cask which has been damaged or I E I repaired in the area of a seal must also be tested prior to subsequent use; normal gasket maintenance does not require a subsequent test.

f B l p 13. Packagings fabricated after November 30,1983, must be constructed of A-516, Grade 70 carbon i

y steel.

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l-b 14. The package authorized by this certificate must be transported on a motor vehicle, railroad car, i B, aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for the sed use of the license. I B l B 15. The pachaging shall be prepared for shipment and operated in accordance with the Operating i i b Procedures of Section 7.0 of the application. I B I N

16. Each package must meet the Acceptance Tests and Maintenance Program of Section 8.0 of the I application.

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lg 17. Packaging fabricated in accordance with Hittman Nuclear & Development Corporation Drawing Nos.

C001-5-9128, Rev. 5 and C001-5-9129, Rev. 3 are not authorized after April 1989.

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I B 16. The package authorized by this certificate is hereby approved for use under the general license i B provisions of 10 CFR $71.12. I b i B 19. Expiration date: April 1,1999. This certificate is not renewable. I b I b I b I b I b I b I B e 1  :

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b i 8 Page 4 - Certificate No. 9089 - Revision No.14 - Docket No. 71-9089 t 1 b L b -

r REFERENCES [l, bg L. i b L i b Westinghouse Hittman Nuclear, incorporated application dated October 28,1988. g

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b L I B Supplements dated: January 26,1989; December 22,1993; October 10,1997; and December 1,1998. L b I B L b FOR THE U.S. NUCLEAR REGULATORY COMMISSION I B i b I b L 5

B I g Cass R. Chappell, Chief ~

i p Package Certification Section i b Spent Fuel Project Office i p Office of Nuclear Material Safety i 1 b and Safeguards i D I b Date: March 4, 1999 I b I B l 1

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APPROVAL RECORD Model No. HN-194S l Certificate of Compliance No. 9089 k Revision No.14 By letter dated December 1,1998, Molten Metal Technology, Inc. and, ATG Nuclear Services i LL.C. requested that the certificate holder for Certificate of Compliance No. 9089 for the Model No. HN-194S package be changed from Molten Metal Technology, Inc. to ATG Nuclear Services L.L.C. ATG Nuclear Services L.L.C., has accepted responsibility for the completer 3ss -

and accuracy of the statements and representations of the previous certificate holder. ATG Nuclear Services L.L.C., will be responsible for maintenance of the certificate, the safety analysis report for the package design, and the quality assurance records in accordance with 10 CFR 971.91(c). ATG Nuclear Services LL.C., 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 ATG Nuclear Services L.L.C., as certificate holder.

These changes do not affect the ability of the package to ' meet the requirements of 10 CFR Part 71.

• H Cass R. Chappell, Chief l Package Certification Section l Spent Fuel Project Office l Office of Nuclear Material Safety and Safeguards Date: March 4, 1999