ML20204C022

Certificate of Compliance 9179,rev 9,for Model Nupac 6-100L, Nupac 6/100H,LN 6-80L & Ln 6-80H Packages

ML20204C022
Person / Time
Site:	07109179
Issue date:	03/17/1999
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20204C019	List: ML20204C016 ML20204C022
References
NUDOCS 9903220357
Download: ML20204C022 (6)

Text

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CERTIFICATE OF COMPLIANCE ji FOR RADIOACTIVE MATERIALS PACKAGES k hl I a CERTIMCATE NUMB (R b REVISION NUMBER c. PACKAGE IDENTIMCATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES El C_

9179 9 USA /9179/A 1 5 kl k

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[j a This cenificate is issued to cenify that the packaging and contents desenbed in item 5 below, meets the apphcable safety standards set forth in Title 10. k T; Code of Federal Regulations. Part 71.*Packagmg and Transportation of Radioactive Malenal." W C

ji b. This cenificate does not rehese the consignor from compliance with any requirement of the regulations of the U.S. Department of Transponation or other N l g apphcable regulatory agencies,includmg the government of any country through or into w hich the package will be transponed. k l I 3 THIS CERTIRCATE 15 ISSUED ON THE B ASIS OF A SAFETY ANALYSIS REPORT OF THE PACKACE DESIGN OR APPLICATION g a ISSUEDTOI%,wandAddressi b TITLE AND IDENTIRCATION OF REPORT OR APPLICATION k l S

i ATG Nuclear Ssrvices L.L.C. NUPAC application dated February 29,1988, E Ei 669 Emory Valley Road as supplemented. E I El Oak Ridge, TN 37830 E l El k l

c. DOCKET NUMBER 9 4 CONDITIONS g l This ceni'icate is conditional upon fulfilhng the requirernents of 10 CFR Part 71, as applicable. and the conditions specified below. g l El 5 g

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j, (a) Packaging g

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@1 i (1) Model Nos.: NUPAC 6/100L, NUPAC 6/100H, LN 6-80L, and LN 6-80H E Yi E

?l (2) Description E  ;

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?! Steel encased lead shielded casks for radioactive material. The casks are right circular E h cylinders with a 61.0-inch ID by 62.0-inch lH cavity. The walls of the casks contain a lead E thickness ranging from 2.43 to 3.56 inches encased in 0.50-inch thick inner steel shell and E si l N

El 1.13 inch thick outer steel shell. The top cover and cask bottom are made up of two steel plates ranging in thickness from 2.0 to 3.0 inchez. The primary cask lid is secured to the i jlI

} cylindrical cask body by eight,1-1/4-inch rachet binders. An optional secondary lid is g I s, centered in the primary lid and is secured to the primary ;id with eight,3/4-inch studs and g s nuts. Each lid is provided with a Neoprene gasket seal. The casks may be provided with an g j;j optional 12-gauge stainless steel liner (seal welded along all edges), an optional lid vent line E l

' ?, with pipe plug, and an optional 3/4-inch drain line and pipe plug. The casks are provided with E i

S i four equally spaced lifting / tie-down devices. The primary lid is provided with three lifting lugs E i

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0 and the optional secondary lid is provided with one lifting lug. The casks gross weights range from 42,900 to 53,900 pounds.

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• l Model OD, Lead Tk, Top Tk, Bottom Tk, Gross Wt, E ji oounds I

Number NUPAC 6/100L, LN 6 80L inshedi inches 69.11 2.43 inches inches _

4.5 4.5 42,900 lg l 3

) NUPAC 6/100H, LN 6-80H 71.37 3.56 6.0 6.0 53,900 g l s E I i

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p Page 2 - Certificate No. 9179 - Revision No. 9 - Docket No. 71-9179 p' t l , .

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i pl D 5. (a) (3) Drawings I b; E E

l Model Nos. NUPAC 6/100L and NUPAC 6/100H I Dj t f

gl The packages are fabricated in accordance with Nuclear Packaging, Inc., Drawing No. X-20 310-SNP, Sheets 1 and 2, Revision No. A. l g

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g Model Nos. LN 6-801. and LN 6-80H g

) e p The packages are fabricated in accordance with LN Technologies Corporation Drawing No. E p 5025 M-2005, Sheets 1 and 2, Revision No. O. t l;'

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D (b) Contents E D I I (1) Type and form of mate,ial I bg I l Dewatered, solid, or solidified wastes, or activated solid components, in secondary ll containers, and limited to the following: l g g I

D I gl (i) Materials in which the radioactivity is essentially uniformly distributed and in which g pl the estimated average concentration per gram of contents does not exceed: l I

D I p! O.0001 millicurie of radionuclides for which the A, quantity in. Appendix A of I h 10 CFR Part 71 is not more than 0.05 curie; I

1. lg t-b, 0.005 millicurie of radionuclides for which the A, quantity in Appendix A of I E 10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; er I

>{j l O.3 millicurie of radionuclides for which the A2 quantity in Appendix A of I g 10 CFR Part 71 is more than 1 curie. g 9 I g (ii) Objects of nonradioactive material externally contaminated with rad:oactive material, g p provided that the radioactive materialis not readily dispersible and the surface i ,

y contamination, whan averaged over an area of 1 square meter, does not exceed a p O.0001 millicurie (220,000 disintegrations per minute) per square centimeter of I D radionuclides for which the A2quantity in Appendix A of 10 CFR Part 71 is not more I b than 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per minute) per square I i B- centimeter for other radionuclides. E D I (2) Maximum quantity of material per package l

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

g provided the fissile material does not exceed the limits of 10 CFR 571.53. The decay g p heat load is limited to 9 watts for the Model Nos. NUPAC 6/100L and LN 6-80L casks and q p 61 watts for the Model Nos. NUPAC 6/100H and LN 6 80H casks. I D E D, I t

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p Page 3 - Certificate No. 9179 - Revision No. 9 - Docket No. 71 9179 e p, '

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D L D 6. (a) For any package containing water and/or organic substances which could radiolytically t N{ generate combustible gases, determination must be made by tests and measurements or by E Ij analysis of a representative package such that the following criteria are met over a period of E time that is twice the expected shipment time: E D E gl (1) The hydrogen generated must be limited to a molar quantity that would be no more g g

l than 5% by volume (or equivalent limits for other inflammable gases) of the g l

secondary container gas void if present at STP (i.e., no more.than 0.063 g-moles /ft* g a!

p at 14.7 psia and 70'F); er g b I p

g (2) The secondary container and cask cavity must be inerted with a diluent to assure t lj that oxygen is limited to 5% by volume in those portions of the package which could 0 lj have hydrogen greater than 5%. I B L 5

For any package delivered to a carrier for transport, the seconoary container must be I f prepared for shipment in the same manner in which determination for gas generation is made. Shipment period begins when the package is prepared (sealed) and must be [

pl completed within twice the expected shipment time.

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)l p (b) For any package shipped within 10 days of preparation, or within 10 days after venting of l

r b drums or other secondary containers, the determination in (a) above need not be made, and I p! the time restriction in (a) above does not opply. I B l~

5, 7. Maximum gross weight of the contents, secondary containers, and shoring is limited to 15,000 0 B; pounds. L bj C Ej 8. Except for close fitting contents, shoring must be placed between secondary containers and the t I cask cavity to minimize movement during normal conditions of transport.

mI L El 9. The lid and the shield plug lifting lugs must not be used for lifting the cask, and must be covered  ;

in transit. g

,l p 10. The cask must be provided with either (or both) a drain line or a lid vent line as shown in the g b drawing in order to provide a method to leak test the package. r I

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, >l Page 4 - Certificate No. 9179 - Revision No.

p 9 - Docket No.

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

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1. (a) Prior to each shipment, the packaging Neoprene lid seats if opened (or if security seal is I j broken), must be inspected. The seats must be replaced with new seals if inspection shows I I

l any defects or every twelve (12) months, which ever occurs first. Cavity drain and vent lines I I

must be sealed with appropriate sealant applied to the pipe plug threads.

B E l (b) Each packaging must meet the Acceptance Tests and Maintenance Program of:

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D Model Nos. NUPAC 6/100L and NUPAC 6/100H g ,

9 I s Section 8.0 of the application. L D L E Model Nos. LN 6-80L and 6-80H L 1 D. E f Il LN Technologies Corporation Frocedures WM-036, Rev. A; WM-026, Rev. B; and WM- I 013,Rev.F. I f

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(c) The package shall be prepared for shipment and operated in accordance with the Operating Procedures of:

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)I I i p Model Nos. NUPAC 6/100 and NUPAC 6/100H l l D L  !

9 Section 7.0 of the application. L B l Bj Model Nos. LN 6-80L and LN 6-80H I 9; L U

LN Technologies Corporation Procedures WM-025, Rev. C. I Bl l ljl 12. The ratchet binders on the cask lid must be torqued to 100* 10 ft-lbs.

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.! i g! 13. The cask body and each cask lid must be marked in accordance with 10 CFR 571.85(c). p D L p 14. The packages authorized by this certificate must be transported on a motor vehicle, railroad car, t

) aircraft, inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the r b licensee. I B L D 15. The packages authorized by this certificate are hereby approved for use under the general license I b provisions of 10 CFR 571.12. L b I

16. Expiration date: April 1,1999. This certificate is not renewable.

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Bl; D r D REFERENCES C i

D E D,

, t i Nuclear Packaging, Inc., application dated February 29,1988, f

l Supplements dated: April 19 and 26,1988; February 16,1993; and August 5,1997, f

NUS supplement dated: November 22,1985.

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p Scientific Ecology Group, Inc., supplement dated: April 30,1993. r B L Bf LN Technologies Corporation supplement dated: February 16,1988. t W L I ATG Nuclear Services L.L.C. supplement dated: December 1,1998. L B, l L FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

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Cass R. Chappell, Chief r

); Package Certification Section i

); Spent Fuel Project Office L Office of Nuclear Material Safety L and Safeguards I L

I Date: March 17, 1999 L

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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2006Ho01

• s...../ APPROVAL RECORD Model No. NUPAC 6/100L, NUPAC 6/100H, LN 6-80L, and LN 6-80H Packages Certificate of Compliance No. 9179 Revision No. 9

, By letter dated December 1,1998, ATG Nuclear Services L.L.C., and Molten Metai Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9179 for the Model Nos. NUPAC 6/100L, NUPAC 6/100H, LN 6-80L, and LN S-80H Packages 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 completeness and ,

accuracy of the statements and representations of the previous certificate holder. ATG j Nuclear Services L.L.C., will be responsible for maintenance of the certificate, the safety j analysis report for the package designs, and the quality assurance records in accordance l with 10 CFR 571.91(c). ATG Nuclear Services L.L.C., has been issued Quality Assurance i 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 packages to mset the requirements of 10 CFR Part 71.

-t Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards 1

Date: March 17, 1999 6