ML20207J278

Certificate of Compliance 9145,rev 13,for Models Nupac 50-1.5L,NUPAC 50-2.5L,NUPAC 50-3.0L & Nupac 50-4.0L Packages

ML20207J278
Person / Time
Site:	07109145
Issue date:	03/04/1999
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20207J269	List: ML20207J266 ML20207J278
References
NUDOCS 9903160233
Download: ML20207J278 (4)

Text

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CERTIFICATE OF COMPLIANCE i i'"' FOR RADIOACTIVE MATERIALS PACKAGES N e

l.a CERT 7 ATE NUMBER b REVISION NUMBER c. PACK AGE IDENTinCATION NUMBER d PAGE NUMBER c. TOTAL NUMBER PAGES s'l p 9145 13 USA /9145/A 1 3 gl h 2. PREAMBLE k

blj a. This cenincate is issued to certifs that the pacLagmg and contents descnbed in item 5 below. rnrets the apphcable safety standards set forth in Title 10 Code of rederal Regulations, Part 71. " Packaging and Transportation of Radioactise Material."

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b. This cenificate does not rehese the consignor frorn compliance with any requirement o.'the regulations of the U.S. Department of Transportation or other k hl apphcable regulatory agencies, including the government of any country through or into which the package will be traraponed.

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a. ISSUED TO thms and Addrcus issued ON TnE Basis OF A SAFETY ANALYSIS b TITLE AND IDENTinCATION OF REPORT OR APPLICATION.

REPORT OF THE PACK A

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El gt NUPAC Services Division, Inc. application

@ 669 ATG EmoryNuclear Valley RoadServices L.L.C. dated February 21,1991. 4 i Oak Ridge, TN 37830 g, p

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c. DOCKET NUMBER pf a CONDmONs gj p

Bl 1 This cenincate is conditional upon fulGlhng the requirements of 10 CFR Pad 71. as appbcable gl ml El Packaging g-si

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(1) Model Nos.: NUPAC 50-1.5L, NUPAC 50-2.5L, NUPAC 50 3.0L, and NUPAC 50-4.0L. E g,

l Description 5

i (2)

A steel encased lead shielded cask for radioactive material. The casks are right circular f

E I cylinders with a 48.5-inch inside diameter by 52.5-inch inside high cavity. The walls of the casks li al contain a lead thickness ranging from 1.25 to 3.75 inches encased in 3/8-inch thick steel shells. E The bottom and top covers of the cask are made up of two steel plates ranging in thickness from El

@El 1.00 to 3.00 inches. The primary cask lid is secured to the cylindrical cask body by eight,1-inch E'

'1I rachet binders. A secondary cask lid is centered in the primary lid and is secured to the primary E lid with eight,3/4-inch studs and nuts. Each lid is provided with a Neoprene gasket seal. The E,

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gi cask is provided with four equally spaced lifting / tie down devices. Cask gross weights range from 13,200 to 28,900 pounds.

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5 The Model No. NUPAC 50 Series packagings are fabricated in accordance with Nuclear E 9 Packaging, Inc. Drawing No. X-20-201D, Sheets 1 and 2, Revision C. E B'

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5. (b) Contents h (1) ' Type and form of material l a

$ Dewatered, solid or solidified waste, in secondary containers, or activated solid components, and limited to the following: l

! (i) Materials in which the radioactivity is essentially uniformly distributed and in which j the estimated average concentration per gram of contents does not exceed:

! 0.0001 millicurie of radionuclides for which the A2 quantity in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; l

0.005 millicurie of radionuclides for which the A2 quantity in Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; or 5

0.3 millicurie of radionuclides for which the A, quantity in Appendix A of B

10 CFR Part 71 is more than 1 curie.

B B Objects of nonradioactive material externally contaminated with radioactive (ii) 5 material, provided that the radioactive material is not readily dispersible and the N surface contamination, when averaged over an area of 1 square meter, does not

!2 exceed 0.0001 millicurie (220,000 disintegrations per minute) per square centimeter of radionuclides for which the A2 quantity in Appendix A of 10 CFR Part 71 is not 9 more than 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per minute) per e square centimeter for other radionuclides.

B B (2) Maximum quantity of material per package 5

5 Greater than Type A quantity of radioactive material.

B B 6. (a) For any package containing water and/or organic substances which could 5 radiolytically generate combustible gases, determination must be made by b tests and measurements or by analysis of a representative package such that the following B criteria are met over a period of time that is twice the expected shipment time:

B B (1) The hydrogen generated must be limited to a molar quantity that would be no more than i 5% by volume (or equivalent limits for other inflammable p gases) of the secondary container gas void if present at STP (i.e., no more than 0.063 g-p moles /ft3 at 14.7 psia and 70*F); or 9

5 (2) The secondary container and cask cavity must be inerted with a diluent p to assure that oxygen must be limited to 5% by volume in those portions of the package p which could have a hydrogen concentration greater than 5%.

B p For any package delivered to a carrier for transport, the secondary container must be prepared p for shipment in the same manner in which determination for gas generation is made. Shipment p period begins when the package is prepared (sealed) and must be completed within twice the B expected shipment time. .

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! Page 3 - Certificate No. 9145 - Revisinn No.13 - Docket No. 71-9145 nl g

,i a .- p 1 9; N: i Ni 6. (b) For any package shipped within 10 days of preparation, or within 10 days N N{ after venting of drums or other secondary containers, the determination in q;

!l (a) above need not be made, and the time restriction in (a) above does not apply, k 5l E' N

I 7. Shoring must be placed between secondary containers (or adivated components) and the cask cavity q!

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to prevent movement during normal conditions of transport. ll d

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N 8. In addition to the requirements of Subpart G of 10 CFR Part 71: Ei

!I k fj (a) Prior to each shipment, the packaging tid seals must be inspected. The seals must be replaced  %

with new seals if inspection shows any defects or every 12 months, whichever occurs first. gl Bl B g i W Each package must meet the Acceptance Tests and Maintenance Program of (b) ll Section 8.0 of the application. ll B q;

!N (c) The package shall be prepsred for shipment and operated in accordance with the operating procedures in Section 7.0 of the appliention.

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B q; b 9. The package authorized by this certificate must be transported on a vehicle, railroad car, aircraft, d )

b inland water craft, or hold or deck of a seagoing vessel assigned for sole use of the licensee. 1 i g l- l Rl b

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10. Lid lifting devices must be covered prior to transport to prevent their use as tie-down devices, ll g

q Bl 11.The cask body and each cask lid must be marked in accordance with 10 CFR $71.85(c).

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'I !lI q;i 9 12. The package authorized for use by this certificate is hereby approved for use under the general ll license provisions of 10 CFR $71.12.

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B 13. Expiration date: April 1,1999. This certificate is not renewable. g l N l l 5 ll 3 REFERENCES gl W el, R NUPAC Services Division, Inc. application dated February 21,1991. gll B g!l p Supplements dated: February 16,1996; August 5,1997 and December 1,1998. g B q l B. FOR THE U.S. NUCLEAR REGUI.ATORY COMMISSION g l B gll W -

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l Cass R. Chappell, Chief g g Package Certification Section ,,

g Spent Fuel Project Office g Office of Nuclear Material Safety g gl l g and Safeguards y j B' q  !

B p Date: March 4, 1999 q,'

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e-NUCLEAR REGULATCRY COMMISSION WASHINGTON, D.C. 3088MW01

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l APPROVAL RECORD Model No. NUPAC 50-1.5L, NUPAC 50-2.5L, -

NUPAC 50-3.0L, and NUPAC 50 4.0L Packages 3

Certificate of Compliance No. 9145 Revision No.13  ;

l By letter dated December 1,1998, ATG Nuclear Services L.L.C., and Molten Metal _

i Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9145 for i the Model No. NUPAC 50-1.5L, NUPAC 50-2.5L, NUPAC 50-3.0L, and NUPAC 50-4.0L '

packages be changed from Molten Metal Tecnnology, 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 Nuclear Services L.L.C., will be responsible for maintenance of the certificate, the safety analysis report for the package designs, and the quality assurance records in accordance with 10 CFR

$71.91(c). ATG Nuclear Services L.L.C., has been issued Quality Assurance Program )

Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71. I i

The Certificate has been revised to show ATG Nuclear Services L.L.C., as certificate holder. l These changes do not affect the ability of the packages to meet the requirements of 10 CFR i Part 71, smH'

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'k Cass R. Chappell, Chief

Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date

March 4, 1999

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