ML20203F890

Certificate of Compliance 9224,rev 4,for Model HN-190-2 Package

ML20203F890
Person / Time
Site:	07109224
Issue date:	12/08/1997
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203F887	List: ML20203F881 ML20203F890
References
NUDOCS 9712170481
Download: ML20203F890 (4)

Text

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• I 6 f OR RADIDACTWE M4TERIALS PACKAGES g l 1 a C1RHOCATI Ntubik t, MvisKnN MutiR e. PACl5 AGE lDINHOC ATION NtNkljt d PAGt M'Mbl k e 101AL MMblR PAOLi gl

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% a This temficate is lasued to cemf) thai Ow pmLating and contents desented is liem s below, snects de appl.c Ode safer) standards set forth in Title 10. I

1. Code of f ederal Regulateons. Pan 71 *PacLagiris and Transponalma cd Radioactive Mai nal *  !

ti This cemficate dues nce relette de consignw from cornphance with an) requirement of de regulations of ew U.S Departrnent of Transpanation or oder N i

$gl apphcable regulator) agencws, including one gosemment of any country through or into which the package will to transpaned N I 3 TH11(1 RiinCAllIl tilti.D ON THE li A51s or A $ AITTY AN AD$11 MPORT OF DIE PACKAGE DLilON OR APrt[C ATION I a 151L'LD TO f Aame and Adderni b 77T11 AND EDLNT10CA"ON Of REK)RT OR API 1JCAllON N ,

• 'l Holten Metal Technology, Inc. Scientific Ecology Group, Inc. I e y

+' 1009 Commerce Park Drive application dated May 18, 1993. g 4lOakRidge,TN37830 g e toCuTMunR 71-9224 l

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$ 4 CONDITIONS g

$ This tem &csie is condmonal upon fulfilhng Ow requirernents of 10 CT1t Pan 71, en opphcable, and the conditions specined below.

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(a) Packaging l

(1) Model Nos.: HN-190-2 (2) Description l

't Steel encased, lead shielded cask for radioactive material. The cask is a N

$ right circular cylinder 81-1/2 inches high by 81-3/4 inches in diameter, The I

• I cask cavity is 73-3/8 inches high by 75-1/2 inches in dianeter. The cask I ,

$ side walls consist of a 3/8-inch thick inner steel shell, a 1-3/4-inch lead W

$ shell, and a 7/8-inch thick outer steel shell. Each base is comprised of 4

• ! two, 2-inch thick steel plates welded together to form a 4-inch thick base I h which is integrally welded to th inner and outer steel shells of the side I h wall. A steel flange is welded to the inner and outer steel shells of the I side wall at the top. The lid is comprised of two, 2-inch thick steel plates N

'hI which are stepped and welded together to mate with the steel flange. The E

'I t.ask closures are sealed by a Neoprene gasket located between the lid and I

• t steel flange, positive closure of the lid is accomplished by eight rachet E

% binders. The lid contains a centrally located shield plug cotrprised of two, E h 2-inch thick steel plates and one,1-inch thick steel plate stepped and u

'i welded. The shield plug is sealed by a Neoprene gasket, and eight, 3/4-inch I h studs and nuts are used to provide positive closure, q  !

% Tie-down is accomplished by four tie-down lugs welded to the cask body. 4

% There are four cask lifting lugs, three lid lifting lugs, and one shiel' plug a

$ lifting lug. The package gross weight is approximately 48,000 pounds. t N

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% (3) Drawing g I

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% The Model No. HN-190-2 packaging is fabricated in accordance with Hittman a

% Nuclear & Development Corp. Drawing Nos.: STD-02-080, STD-02-081, and STD- g

% 02-082, all Rev. O. gl

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p- q i e 5. (b) Contents g:

$l ' (1) Type and form of material e y

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, Process solids, either dewatered, solid or solidified, in secondary y j containers, and limited to the following: g el ,

I (1) Materials in which the radioactivity is essentially unii'ormly l- ;

g distributed and in which the estimated average concentration per g y gram of contents does not exceed: g i 0.0001 millicurie of radionuclides for which the A quanti'.y in U l Appendix A of 10 CFR Part 71 is not more than 0.05, curie; y l 1 0.005 millicurie of radionuclides for which the A quantity in U I Appendix A of 10 CFR Part 71 is more than 0.05 cu,rie, but not more than 1 curie; or

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0.3 millicurie of radionuclides for which the A q U Appendix A of 10 CFR Part 71 is more than I curie.uantity in

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'i (ii) Objects of nonradioactive material externally contaminated with N radioactive material, provided that the radioactive material is N

'l not readily dispersible and the surface contamination, when N ,

• I, averaged over an area of I square meter, dnes not exceed d'

• i 0.0001 millicurie (220,000 disintegrations per minute) per square N

• i centimeter of radionuclides for which the A quantity in d.

% Appendix A of 10 CFR Part 71 is not more th,an 0.05 curie, or 4

% 0.001 millicurie (2,200,000 disintegrations per minute) per 8 ,

1 square centimeter for other radionuclides. E , ,

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% (2) Maximum quantity of material per package d

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% Greater than Type A quantity of radioactive material which may contain d h fissile material provided the fissile material does not exceed the limits N

% in 10 CFR 671.53. The weight of the contents and secondary containers a l # shall not exceed 14,200 pounds and the internal decay heat load shall not ql r

4 exceed 7 watts. p l % gl

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8 N 6,e Page 3 - Certificate No. 9224 - Revision No. 4 - Docket No. 71-9224 g- i I

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I. i e, 6. (a) for any package containing water and/or organic substances which could u I g radiolytically generate combustible gases, determination must be made by a tests and measurements or by analysis of a representative package such that a

>' the following criteria are met over a period of time that is twice the g t

+ expected shipment time: a'

$l (1) The hydrogen generated must be limited to a molar quantity that would be d

e' g p' no mort than 5% by volume (or equivalent limits for other inflammable y n' gases) of the secondary coptainer gas void if present at STP (i.e., no a pl more than 0.063 g-moles /ft at 14.7 psia and 70'F); or g E

p (2) The secondary container and cask cavity must be inerted with a diluent to g gl assure that oxygen must be limited to 5% by volume in those portions of g  ;

g l the package which could have hydrogen greater than 5%. g ,

' For any package delivered to a carrier for transport, the secondary container l

,I must be prepared for shipment in the same manner in which determination for g

,1 gas generation is made. Shipment seriod begins when the package is prepared y q (sealed) and must be completed wit 1in twice the expected shipment time. ,

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(b) For any package shipped within 10 days of preparation, or within 10 days U

,' after venting of drums or other secondary containers, the determination in

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(a) above need not be made, and the time restriction in (a) above does not apply, fg f7.

,i Except for close fitting contents, shoring must be placed between secondary containers and the cask cavity to prevent movement during normal conditions of 8

N transport.

l qll8. The lid and the shield plug lifting lugs must not be used for lifting the cask, and 8 must be covered in transit.

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i 9. In addition to the requirements of Subpart G of 10 CFR Part 71:

$ (a) Prior to each shipment, the packaging lid seals if opened (or if security E;

• i seal is broken), must be inspected. The seals must se replaced with new I ,

h seals if inspection shows any defects or every twelve (12) months, which ever W h occur first. Cavity drain line and optional vent / test connection must be N h sealed with appropriate sealant applied to the pipe plug threads. 4 ,

4 (b) Each packaging must meet the Acceptance Tests and Maintenance Program of I

1. ( Section 8.0 of the application. in addition, the cask must be leak tested at E least once every twelve (12) months in accordance with Subsection 8.1.3 of E 4

the application. 4 l; E

h (c) The package shall be prepared for shipment and operated in accordance with E(

h the Operating Procedures of Section 7.0 of the application. El

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'i Page 4 - Certificate No. 9224 - Revision No. 4 - Docket No. 71-9224

• i The cask body and each cask lid must be marked in accordance with 10 CFR 671.85(c).

fl10.

t 11. The package authorized by this certificate must be transported on a motor vehicle,

• ! railroad car, aircraft, inland watercraf t, 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 provisions of 10 CFR 67).12.

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

+, REFERENCES ,

9

+lScientificEcologyGroup,Inc.,applicationdatedMay

+ 18, 1993.

4.,

+; Supplements dated: June 23, 1993 and October 10, 1997.

+%

+ FOR THE U.S. NUCLEAR REGULATORY COMMISSION hl Cass R. Chappell, Chief f

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Package Certification Section g/' Spent Fuel Project Office Office of Nuclear Material Safety g

g and Safeguards 4

d Date: December 8, 1997 il il h

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%g\ UNITSO STATES g ,

NUCLEAR REGULATORY COMMISSION W ASHiteQTON, D.C. EsteMgM APPROVAL RECORD Model No. HN-190-2 Certificate of Compliance No. 9224 Revision No. 4 By letter dated October 10, 1997, Scientific Ecology Group, Inc., and Molten Metal Technology, Inc., requested that the certificate holder for Certificate '

i of Compliance No. 9224 for the Model No. HN-190-2 package be changed from Inc.. Molten Metal i

• Scientific Technology, EcolInc...has

%y Group..

accepted Inc., to Molten MetalforTechnologyleteness responsibility the comp and.  !

accuracy of the statements and representations of the previous certificate ,

holder. Molten Metal Technology, 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 .

i Technology, package design Inc.,ll wi be maintained at their document control center in Oakstated that the re Ridge, Tennessee. Molten Metal Technology, Inc., has been issued Quality Assurance Program Aparoval 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.

7 Cass R. Chappell, Chief

< Package Certification Section Spent Fuel Project Office Office of Nuclear Material

Safety and Safeguards Date

December 8, 1997 i

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