ML20207J345

Certificate of Compliance 9079,rev 18,for Model Nupac 14D-2.0 Package

ML20207J345
Person / Time
Site:	07109079
Issue date:	03/04/1999
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20207J326	List: ML20207J322 ML20207J345
References
NUDOCS 9903160248
Download: ML20207J345 (4)

Text

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CERTIFICATE OF COMPLIANCE i

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FOR RADIOACTIVE MATERIALS PACKAGES Nl 9

q l L a CERTlHCATE NUMBER b REVISION NUMBER

c. PACKAGE IDENTIF ICATION NUMBLR d PAGE NUMBER

e. TOTAL NUMBER PAGES g

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1 9079 18 USA /9079/A 1

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2. PRLAMBLE k

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a. This cert ficate is issued to certify that the packaging and contents described in hem 5 below, meets the apphcable safety standards set fonh in Title 10.

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Code of Federal Regulations. Part 71. Packagmg and Transponation of Radioactise Material

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b. This certi6cate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other g

applicable resrulatory agencies. including the government of any country through or into which the package uill be transported.

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3. THIS CE RTIF1CATE IS ISSUED ON THE BASIS OF A 5 AFETY AN ALYSIS RLPORT OF THE PACK ACE DESIGN OR APPLICATION

a. $ SUED TO thnw and Addrrus

b. Tin E AND IDENTIFICATlw OF REPORT OR APPLICATION-k E{

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h ATG Nuclear Services L.L.C.

Nuclear Packaging Inc. application 4

B; 669 Emory Valley Road dated March 30,1988, as supplemented.

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1. l Oak Ridge, TN 37830 N

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c. DOCKET NUMBER 71-9079 i

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This cenincate is conditional upon fu!G! ling the requirements of 10 CFR Pan 71. as apphcable, and the conditions specined below, g

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Packaging N-Bj d

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Model No.: NUPAC 14D-2.0 E

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Description g

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Steel encased, lead shielded cask for radioactive material. The cask is a right circular cylinder q

B; 81-1/2 inches high by 81-3/4 inches in diameter the cask cavity is 73-3/8 inches high by 75-1/2 g

B inc,hes in diameter. The cask side wall consists of a 3/8-inch thick inner steel shell, a 1-3/4-inch q

Bj; lead shell, and a 7/8-inch thick outer steel shell. Each base is comprised of two,2-inch thick steel g I

9; plates welded together to form a 4-inch thick base which is intergerally welded to the inner and g

i outer steel shells of the side wall. A steel flange is welded to the inner and outer steel shells of g

5 the side wall at the top. The lid is comprised of two,2-inch thick steel plates, which are stepped g

b and welded together to mate with the steel flange. The cask closures are sealed by a Neoprene g

B gasket located between the lid and steel flange, positive closure of the lid is accomplished by g

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eight rachet binders. The lid contains a centrally located shield plug comprised of two,2-inch g

I thick steel plates and one,1-inch thick steel plate stepped and welded. The shield plug is sealed g

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by a Neoprene gasket, and eight,3/4-inch studs and nuts are used to provide positive closure.

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sI Tie down is accomplished by four tie-down lugs welded to the cask body. There are four cask g

p lifting lugs, three lid lifting lugs, and one shield plug lifting lug. The package gross weight is I

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approximately 48,000 pounds.

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Drawings g

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The Model No. NUPAC 14D-2.0 packaging is fabricated in accordance with Nuclear Packaging, y

p incorporated Drawing No. X-20-215D, Revision C.

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g Page 2 - Certificate No. 9079 - Revision No.18 - Docket No. 71-9079 E

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(b)

Contents g

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Type and form of material g

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j Process solids, either dewatered, solid or solidified, in secondary containers, and limited to g

g the following:

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(i)

Materials in which the radioactivity is essentially uniformly distributed and in which

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g the estimated average concentration per gram of contents does not exceed:

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0.0001 millicurie of radionuclides for which the A quantity in Appendix A of 2

10 CFR Part 71 is not more than 0.05 curie; g

l 0.005 millicurie of radionuclides for which the A, quantity in Appendix A of r

9 10 CFR Part 71 is more than 0.05 curie, but not more than 1 curie; or N

0.3 millicurie of radionuclides for which the A, quantity in Appendix A of 10 CFR Part 71 is more than 1 curie.

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(ii)

Objects of nonradicadive material externally contaminated with radioactive material, k

provided that the radioactive materialis not readily dispersible and the surface L

contamination, when averaged over an area of 1 square meter, does not exceed I

5 0.0001 millicurie (220,000 disintegrations per minute) per square centimeter of I

E radionuclides for which the A quantity in Appendix A of 10 CFR Part 71 is not more I

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than 0.05 curie, or 0.001 millicurie (2,200,000 disintegrations per minute) per square L

E centimeter for other radionuclides.

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(2)

Maximum quantity of material per package I

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

b provided the fissile material does not exceed the limits in 10 CFR 971.53. The weight of L

b the contents and secondary containers shall not exceed 14,000 pounds and the intemal i

B decay heat load shall not exceed 7 watts.

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6.

(a) For any package containing water and/or organic substances which could radiolytically generate I

B combustible gases, determinstion must be made by test and measurements or by analysis of a L

D representative package such that the following criteria are met over a period of time that is twice the F

D expected shipment time:

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(1)

The hydrogen generated must be limited to a molar quantity that would be no more than I

h 5% by volume (or equivalent limits for other inflammable gases) of the secondary container i

B gas void if present at STP (i.e., no more than 0.063 g-moles /ft' at 14.7 psia and 70'); or i

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9 (2)

The secondary container and cask cavity must be inerted with a diluent to assure that t

B oxygen must be limited to 5% by volume in those portions of the package which could have i 9

hydrogen greater than 5%.

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For any package delivered to a carrier for transport, the secondary container must be prepared t

p for shipment in the same manner in which determination for gas generation is made. Shipment t

b period begins when the package is prepared (sealed) and must be completed within twice the r

5 expected shipment time.

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

D other secondary containers, the determination in (a) above need not be made, and the time t

b; restriction in (a) above does not apply.

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r Page 3 - Certificate No. 9079 - Revision No.18 - Docket No. 71-9079 l7.

Elxcept for close fitting contents shoring must be placed between secondary containers and the cask I

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cavity to prevent movement during normal conditions of transport.

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

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9.

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

f (a) Prior to each shipment, the packaging lid seals, if opened (or if security seal is broken), must be I

inspected. The seals must be replaced with new seals if inspection shows any defects or every I

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twelve (12) months, whichever occurs first. Cavity drain line and optional vent / test connection must I

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

I (b) Each cask must meet the Acceptance Tests and Maintenance Program of Section 8.0 of the 1 l I

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application. In addition, the cask must be leak tested at least once every twelve (12) months in I

E accordance with Appendix 8.4 of the application.

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N (c) The package shall be prepared for shipment and operated in accordance with the operating i

E procedures of Section 7.0 of the application.

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B 10.

The cask body and each cask lid mLst be marked in accordance with 10 CFR 971.85(c).

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I 11.

The package authorized by this certificate must be transported on a motor vehicle, railroad car, aircraft, L

inland watercraft, or hold or deck of a seagoing vessel assigned for the sole use of the licensee.

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12.

The package authorized by this certificate is hereby approved for use under the general license I

provisions of 10 CFR 971.12.

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I 13.

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

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L REFERENCES r

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Nuclear Packaging, incorporated application dated March 30,1988.

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Supplement dated: April 26,1988; February 23,1993; August 5,1997; and December 1,1998.

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BI FOR THE U.S. NUCLEAR REGULATORY COMMISSION i

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p' Cass R. Chappell, Chief g

g Package Certification Section i

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Spent Fuel Project Office e

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Office of Nuclear Material Safety i

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and Safeguards i

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p Date: March 4, 1999 3

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APPROVAL RECORD Model No. NUPAC 14D-2.0 Certificate of Compliance No. 9079 Revision No.18 By letter dated December 1,1998, MoNen Metal Technology, Inc. and, ATG Nuclear Services L.L.C. requested that the certificat: holder for Certificate of Compliance No. 9079 for the Model i

No. NUPAC 14D-2.0 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 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 design, and the quality assurance records in accordance with 10 CFR 971.91(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.

Certificate of Compliance No. 9079, Revision No.17, contained a typographical error in paragraph 5(a)(2). This error has been corrected in Revision No.18.

The Certificate has been revised to show ATG Nuclear Services L.L.C., as certificate holder.

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

tm44' Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date;j! arch 4,1999