ML20203H495

Certificate of Compliance 9151,rev 17,for Model HN-100 Series 3 & Ln 14-170 Series I Packages

ML20203H495
Person / Time
Site:	07109151
Issue date:	12/08/1997
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203H468	List: ML20203H462 ML20203H495
References
NUDOCS 9712180416
Download: ML20203H495 (6)

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CERTIFICATE OF COMPLIANCE '

l TOR RADIOACTIVE MATERI ALS PACKAGr.S ,

I e CLWiiF1CA11 NUMeila b RJ vluoN NUMBLR c. PACA4GE IDENTIFICAT10N NUMbl.A d FAGE NUMtilk e TOT AL SUMist k F AGE 5 g g'l e 9151 17 tlSA/9151/A 1 5 g,

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a TM tertshcait to issued to certify that 04 px Lating and contents descrded in liem $ below, enects ow applaable safety standards set farth in Tsile 10. O i 9l 9

Cofe of f ederal kegulaixes. Par 171. Ta:Lagirig and 1ranspetaixe cd RaJuective Material *  ! '

b This temhcate does rga reiwwe the umsirr6v from cornpiiance with any requirernent of on regulaixes of on U.s Department of Transpcetatue en oder N i)g appigable eerulattry agencie6. 6tgluding the governenent of es.) country dirough cs into o hich on px Lage will tw transpnrsed. U

$ l ) TH15a 151UID CEDTH1C ATL il 155U1D ON THE D A115 Of A S AftTY Ah AL1815 ktf9R1 OF THE PACAAGE DL5tGN OR AftL.lc AT10N 10 # Aame sW AWys0 N 6 TTT11 ANDIDENTUICATIONOF ALPORT OR APPLJCAT10N

+1 8, Holten Metal Technology, Inc. Scientific Ecology Group, Inc. application e

v 1009 Commerce Park Drive dated September 21, 1992.

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4 4 CONDffioN5 etoCrn uPMer, 71-9151 l

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$ Thse certshcate is condiineal upe ful6thng Ow teoirernenta of 10 Cllt Pvt 71, as applicable,and the condstons specified belom l

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,I (a) Packaging g (1) Model Nos.: HN-100 Series 3 end LN 14-170 Series !

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(2) Description 9 l

'I Steel e .:ased, lead shielded casks for radioactive material. The casks are N

'l right circular cylinders 81-1/2 inches high by 81-3/4 inches in diameter. The E

'l cask cavities are 73-3/8 inches high by 75-1/2 inches in diameter. The cask I

't side walls consist of a 3/8-inch thick inner steel shell, a 1-7/8-inch lead 4

• t shell, and a 7/8-inch thick outer steel shell. The base is com)rised of two, N

• i 2-inch thick steel plates welded togetner to form a 4-inch thic( base which is I

• integrally welded to the inner and outer steel shells of the side wall. A E

• i steel flange is welded to the inner and outer steel shells of the side wall at G

• t the top. The lid is comprised of two, 2-inch thick steel plates, which are d

't stepped and welded together to mate with the steel flange. The cask closure 4

• I is sealed by a Neoprene gasket located between the lid and steel flange, I

• t positive closure of the lid is accomplished by eight, 1-3/4-inch ratchet 4 i binders. The lid contains a centrally located shield plug comprised of two, t 6 2-inch thick steel plates and one,1-inch thick steel plate stepped and E 5 welded. The shield plug is sealed by a Neoprene gasket, and eight, 3/4-inch I

'i stu(s and nuts are used to provide positive closure. The packagings are e i # constra ted of A-516, Grade 70 or A-537, Class 1, carbon steel. The outer a

• i shell will have a minimum yield strength of 46,000 psi. Tie-down is e i i e

i accomplished by four tie-down lugs welded to the cask body. There are four u 9; cask lifting lugs, three lid lifting lugs, and one shield plug lifting lug. E s The package gross weight is approximately 53,000 pounds, a

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Page 2 - Certificate No. 9151 - Revision No. 17 - Docket No. 71-9151 r 6 1 l

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1. li 5. (a) (3) Drawings r

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i el f The Model No. HN-100 Series 3 packaging is fabricated in accordance with Hittman Nuclear & Develcpment Corp. Drawing Nos.: C001-5-9138, Rev. 13; L

1 5, l 6, C001-5-9139, Rev. 8; C001-5-9140, Rev. 9; C001-5-914), Rev. 3; L ,

$j C001-5-9142 Rev. 1; C001-5-9143, Rev 8; and C001-5-9144, Rev. 3. r l

• , Optional stainless steel shielding insert .n accordance with Drawing 1 6, Nos.: STD-02-035, Rev. A; STD-02-036, Rev. A; and STD-02-037, Rev. 2. I

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$ The Model No. LN 14-170 Series ! packaging is fabricated in accordance 1

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with LN Technologies Corporation Drawing Nos.: 8916 M 2001, Rev. 1; 8916 M 2002, Rev. 0; 8916 M 2003, Rev. 0; 8916 M 2004, Rev. 0; E

j 8916 M 2005, Rev. 0; and 8916 M 2006, Rev. O. I

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pl (b) Contents 1 l

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$ (1) Type and form of material j  ;

• l Process solids, either dewatered, solid or solidified, in secondary 1'

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e containers, and limited to the following: j

$l (i) Materials in which the radioactivity is essentially uniformly L

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g/ distributed and in which the estimated average concentration per t gram of contents does not exceed: i 4l '

h O.0001 millicurie of radionuclides for which the A quantity in l

/ Appendix A of 10 CFR Part 71 is not more than 0.05, curie; j_

i quantity in l g 0.005 millicurie A>perdix A of 10 of CFRradionuclides for which Part 71 is more than 0.05the cur A,ie, but not more j

,1 t1an I curie; or 3

i 0,3 millicurie of radiowclides for whien the A q r i Appendix A of 10 CFR Part 71 is more than I curie.uantity in 7

I (ii) Objects of nonradioactive material externally contaminated with I g radioactive material, provided that the radioactive material is not I-1 i readily dispersible and the surface contamination, when averaged

,4 over an area of I square meter, does not exceed 0.0001 millicurie J

• (220,000 disintegrations )er minute) per square centimeter of I

't radionuclides for which tie A, quantity in Appendix A of I

• Il 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie 1

't (2,200,000 disintegrations per minute) per square centimeter for I other radionuclides.

(2) Maximum quantity of material per package j

't Greater than Type A quantity of radioactive material which may contain 1

'l fissile material provided the fissile material does not exceed the limits 1

[ in 10 CFR 67).53. The weight of the contents, optional shield insert, and secondary containers shall not exceed 17,800 pounds. When the shield 1:

I lI i insert is not installed in the cask, the internal decay neat load shall l I I not exceed 7 watts. When the shield insert is installed in the cask, the I ,

internal decay heat load shall not exceed 28 watts.

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1. 1 pl Page 3 - Certificate No. 9151 - Revision No. 17 - Docket No. 71-9151 i I, I I

• i 6. (a) For any package containing water and/or organic substances which could p' i e radiolytically generate combustible gases, determination must be made by ,

tests and measurements or by analysis of a representative package such that t

/'n the following criteria are met over a period of time that is twice the , ,

p expected shipment time: i j

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l (1) The hydrogen generated must be limited to a molar quantity that would be no more than 5% by volume (or equivalent limits for other inflammable ll q,1 gases)ofthesecondarycontainergafvoidifpresentatSTP (i.e., no more than 0.063 g-moles /ft at 14.7 psia and 70'F); or (2) The secondary container and cask cavity must be inerted with a diluent ll I

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,' to assure that oxygen must be limited to 5% by volume in those portions of the package which could have hydrogen greater than 5%.

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'l For any pack % delivered to a carrier for transport, the secondary container I I

g must be prepared for shipment in the same manner in which determination for gas generation is made. Shipment period begins when the lackage .

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,1 15 prepared (sealed) and must be completed within twice tie expected shipment I I

,1 time.

• i (b) For any package shipped within 10 days of preparation, or within 10 days i 4 after venting of drums or other secondary containers, the determination in I

$ (a) above need not be made, and the time restriction in (a) above does not I apply. I 4, 7. In addition to the requirements of Subpart G of 10 CFR Part 71: I 4 I

• (a) Prior to each shi> ment, the packaging lid seals, if opened (or if r 4 security seal is )roken), must be inspected. The seals must be re) laced with I h new seals if inspection shows any defecir or every 12 months, whiciever occurs I h first. I h I h (b) Each package must meet the Acceptance Tests and Maintenance Program of

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h Section 7.0 of the application. Gamma scan for the shielding acceptance may I h be based on lead equivalence for lead and steel with all I readings within 2.3 inches i 10% on a 4-inch grid, i

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I f, Model No. LN 14-170 Series I i

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% LN Technologies Corporation Procedures WM-Oll, Rev. H; WM-012, Rev. H; WM-W3, I

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>' 7. r (c) The package shall be prepared for shipment and operated in a accordance .vith the Operating Procedures of:

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( s LN Technologies Corporation Procedure WM-014, Rev. L.

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, P. Torque requirements f

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(a) Primary 11d ratchet binders must be torqued to 175-200 ft-lbs.

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(b) Secondary lid bolts must be torqued to 120 i 10 ft-lbs. ,"

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9. Seals which show any visual defects (cracking, gouging, tearing, etc.) must be gi repaired in accordance with: ,

I Model Nos. HN-100 Series 3 I Note No. 3 on Hittma's Drawing No. C001-5-9138, Rev. 13; or, replaced with a new I seal,

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tipdel No. LN 14-170 Series I E

• t LN Technologies Corporation Procedure WM-012, Rev. H, Section 7.1 (joint angle must I ll be approximately 45'); or, replaced with a new seal. I

'i 10. The package authorized by this certificate must be transported on a motor vehicle, t

$ railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel I assigned for the sole use of the licensee. I

'I# 11. The package authorized by this certificate is hereby approved for use under the f i general license provisions of 10 CFR 571.12. E

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% 12. Expiration date. April 1, 1999. This certificate is not renewable. I

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1. d M Page 5 - Certificate No. 9151 - Revision No. 17 - Docket No. 71-9151 g p'l N p REFERENCES g l

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/ Scientific Ecology Group, Inc. application dated September 21, 1992. g 4 -I

/ Suppletaent dated October 10, 1997. g M, d h

M FOR THE U.S. NUCLEAR REGULATORY COMMISSION f E

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Cass R. Chappe 1, Chief li _ Package Certification Section l g ,

i Spent Fuel Project Office I

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Office of Nuclear Material Safety I and Safeguards l

December 8, 1997 liDate: '

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g o WASHINGTON. D.C. 30006-0001 APPROVAL RECORD Model Nos. HN-100 Series 3 and LN 14-170 Series I Certificate of Compliance No. 9151 Revision No. 17 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. 9151 for the Model Nos. HN-100 Series 3 and LN 14-170 Series I packages be changed from Scientific Ecology Group, Inc., w Holten Metal Technology, Inc. Molten Metal Technology, Inc., has accepted responsibility for the completeness 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 designs, and the quality assurance records in accordance with 10 CFR 671.91(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR 671.91(c) for the package designs will be maintained at their document control center in Oak Ridge, Tennessee. Molten Metal Technology, Inc., has been issued Quality Assurance Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71.

The Certificate has been revised to show Holten Metal Technology, Inc., as certificate holder. These changes do not affect the ability of the packages to meet the requirements of 10 CFR Part 71.

<2+# / ' ':'k Cass R. Chappellkhief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date: December 8. 1997 l

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