ML20197G767

Certificate of Compliance 9073,rev 20,for Model 10-142A Package

ML20197G767
Person / Time
Site:	07109073
Issue date:	12/08/1997
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20197G764	List: ML20197G760 ML20197G767
References
NUDOCS 9712310119
Download: ML20197G767 (5)

Text

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> 9073 . 20 USA /9073/A 1 4 l r I; _3 PREAMBLE I

% a. His cerufacate is issued to ceruf) that the packaging and contents desenhed in hem 5 below, meets the apphenble safety standards set forth in Tide 10. b I; Code of Federal Rervlations, Part 71 *Pachsing and Transportation of Radioactive Matenal? E

( b. This certifcate does sai reheve the consignor from comphance with any requirement of the regulations of the U.s Department of Transportation or other I g spphcable regulatory agencies, including the government of any country through or into wheb the pacLage will be transported. I

~l k ) THIS CERTinCATE a 155UED 70 f Aeme and Adbrul 13 IS$UED ON THE bBTTTLE A515 OF A 5 AM'TY ANDIDENT1ntATION OF REPORTOP AN ALYSIS REPORT OF THE PACKAGE APPUCATION. I DESIGN p Molten Metal Technology, Inc. Scientific Ecology Grot i, Inc., application L

g pl 1009 Commerce Park Drive dated January 26, 1994. i 3 Oak Ridge, TN 37830 i

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( This ceruficate is conditional upon fulfilhng the requiremene of 10 CFR Part 71, as applicable, and the conditions specified below.

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l (a) Packaging i

I (1) Model No.: 10-142A (2) Description f

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I A steel acased, lead shielded cask for solid radioactive material. I-

'l The overail dimensions of the cask are 101-inch diameter by 120-inch I

'Il hei ht. The cask consists of two concentric carbon steel cylindrical I she is surrounding a 3-1/2-in& thick lead shield. The 1/2-inch L I

$ thick inner shell has a 66-inch ID, and the 1-inch thick outer shell I t has a 76-1/4-inch OD; the base consists of two, 3-inch thick welded L

$ steel plates. The base is welded to the steel cylindrical shells. A I

$ stepped welded lid, secured by eight ratchet binders, is comprised of I I

s two, 3-inch thick steel plates containing openings for a secondary E lid of similar construction with an additional 1-inch thick upper L plate. The secondary lid is secured to the primary lid through L eight, 1-inch diameter bolts. The containment cavity is 66 inches in I i diarseter by 72 inches high. The package design is provided with a L E

t lid test port. Toroidal impact limiters are located at the top and r

% bottom of the cask. The impact limiters are 10-gauge stainless steel r

% filled with rigid polyurethane foam. Interior and exterior surfaces r

1. 1 of the cask body and interior surfaces of the upper lid are covered I 8 with 12-gauge, 304 stainless steel cladding and seal welded, t t l

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% The primary lid is closed by means of eight ratchet binders. The L

% 29-inch diameter secondary lid is closed by eight, 1-inch diameter r

% stud bolts. Both-116 are sealed using silicone gaskets bonded to r

% the lid plates. Lifting is facilitated with three lugs welded to the L D

i primary lid. The secondary lid has a redundant Neoprene seal, and a L

% centrally located lift lug. r

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% All exposed side walls are covered with a stainier.s steel thermal L

%. barrier. Four skewed lugs, welded to the outer shell, are used ')r L

% tie-down. The package gross weight is approximately 64,000 por ,os. L C

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p NRC FORM 518A coNDmoNs temmeh U.S. HucLEAR CE!ULATORY COMMISSION g p Page 2 - Certificate No. 9073 - Revision No. 20 - Decket No. 71-9073 g

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1. t p' 5.(a) (3) Drawings r D'i r g -The packaging is fabricated in accordance with Scientific Ecology r p'

l Group, Inc., Drawing No. STD-02-107, Sheets I and 2, Rev. O. g D t p'

l (b) Contents g 4 I p

l (1) Type and form of material g ll q

Dewatered ion exchange resins, solid waste, or activated solid components; in secondary containers; and limited to the following: [

,f (1) Materials in which the radioactivity is essenticily uniformly I i distributed and in which the estimated average concentration r g

per gra of contents dces not exceed: ,

1 0.0001 millicurie of radionuclides for which the A quantity in I Appendix A of 10 CFR Part 71 is not more than 0.05, curie; E

1. 0.005 millicurie of radionuclides for which the A quantity in E 1

1. Appendix A of 10 CFR Part 71 's more than 0.05 cu,rie, but not E 1

more than 1 curie; or I 1 0.3 millicurie of radionuclides for which the quantity in E 1 Appendix A of 10 CFR Part 71 is more than 1 cu'ie. E

1. E i (ii) Objects of nonradioactive material externally contaminated with E fi radioactive material, provided that the radioactive material is I 9 not readily dispersible and the surface contamination, when t s averaged over an area of I square meter, does not exceed E i-

1. j 0.0001 millicurie (220,000 disintegrations per minute) per E

1. l square centimeter of radionuclides for which the A quantity in F i

Appendix A of 10 CFR Part 71 is not more than 0.05, curie, or E i

0.001 millicurie (2,200,000 disintegrations per minute) per E

1. square centimeter for other radionuclides. E

1. j E i (2) Maximum quantity of material per package E

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% Greater than Type A quantities of radioactive materials which may 3

1. contain fissile contents not to exceed the generally licensed mass q

.%, limits as specified in 10 CFR 55671.18, 71.20, and 71.22. Internal E

% decay heat not to exceed 400 watts and the maximum weight of- g 5, contents, including secondary containers, not to exceed 10,C00 g pounds. g 4, y

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f. p '* Page 3 - Certificate No. 9073 - Revision No. 20 - Docket No. 71-9073 g

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E D' for any package containing water and/or organic substances which could p 6. (a) g p'

l radiolytically generate combustible gases, determination must- be made by g p' tests and measurements or by an& lysis of a representative package such that g p' the following criteria are met over a period of time that is twice the a p expected shipment time: i

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l (1) The hydrogen gencated must be limited to a molar quantity that would g p be no more than 5% by volume (or equivalent limits for other y p

i inflammable gases) of the secondary container gas void if present at g

, STP (i.e., no more than 0.063 g-moles /ft 8 at 14.7 psia and 70*F); or g fi (2) The secondary container and cask cavity must be inerted with a l diluent to assure that oxygen must be limited to 5% by volume in l p g l those portions of the package which could have hydrogen greater than ,

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8 ll For any pack y e delivered to a carrier for transport, the secondary container must be prepared for shi;, ment in the same manner in which I determination for gas generation is made. Shipment period begins when the E

'i package is prepared (sealed) and must be completed within twice the U expected shipment time.

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k# (b) For any package shipped within 10 days of preparation, or within 10 days E i after venting of drums or other secondary containers, the determina+W in f fi (a) above need not be made, and the time restriction in (a) above does not I i apply. t

1. 7. Except 'for close fitting contents, dunnage must be provided in the shipping cask r

• 1 cavity' sufficient to prevent significant movement of the contents or secondary I

1. ,6 containers relative to the outer packaging undsr normal conditions. I i

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1. 8. In addition to the requir eents of Subpart G of 10 CFR Part 71; I D, I i (a) Prior to each shipment, the packaging lid seals must be inspected. The i l

i seals must be raplaced with new seals if inspection shows any defects or i bl every 12 months, whichever occurs first. -The cavity test port must be l i

sealed with appropriate sealant applied to the pipe plug threads. L D r

1. j The package shall be ' prepared for shipment and operated in accordance with (b) i B;; the Operating Procedures in chapter 7 of the application. L 9, I l

i (c) The package must meet the Acceptance Tes+.s and Maintenance Program in r

1. chapter 8 of the application. i I

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Dj 9. The package authorized by this certificate must be transported on a motor i D, vehicle, railroad car, aircraft, inland watercratt, or hold or deck of a seagoing i t

i vessel assigned for the sole use of the licensee, i b l

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' Page 4 - Certificate No. 9073 - Revision No. 20 - Docket No. 71-9073 I

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1. l r i 10. Packagings fabricated after Marr.h 28, 1980 must be constructed of A-516 Grcle D

1. j 70 carbon steel. t i

1. ,; 11. The packaging authorized by this certificate is hereby approved for use under E 4

the general license provisions of 10 CFR 671.12. t 6, t

1. 12. Expiration da.te: April 1, 1999. Tiiis certificate is not renewable. t

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PEFERENCES E L

9,, t 9, Scientific Ecology Group, Inc., applicatbn dated January 26, 1994. t

1. I si Supplement dated October 10, 1997, e

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1. j FOR THE U.S. NUCLEAR REGULATORY COMMISSION g s

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p Cass R. Chappell, Chief g l

Package Certification Section g p!

p Spent Fuel Project Offica g p' Office of Nuclear Material Safety q i

p and Safeguards g Date: December 8, 1997 (

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'4 9**...jo APPROVAL RECORD Model No.10-142A Certificate of Compliance No. 9073 Revision No. 20 By letter dated October 10, 1997, Scientific Ecology Group, Inc., and Molten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9073 for the Model No.10-142A package be changed from Scientific Ecology Group, Inc., to Molten Metal Technology, Inc. Molten Metal Technology, Inc., has accepted responsibility for the completeness and accuracy of'the statements ar:d representations of the previous certificate holder. Molten Metal Technologi, Inc., 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 571.91(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR !71.91(c) for the package desigr. will be maintained at their document control center in Oak Ridge, Tennessee. Molten Metal Technology, Inc., has been issued Quality Assurance P.ogram 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.

sM 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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