ML20128M591

Certificate of Compliance 9080,Rev 12,for Models HN-600, Nupac 100 & CNS 7-100.Approval Record Encl

ML20128M591
Person / Time
Site:	07109080
Issue date:	05/22/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20128M588	List: ML20128M582 ML20128M591
References
NUDOCS 8506030029
Download: ML20128M591 (5)

Text

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banc roam els U.S. NUCLEAR RE2ULATcRY CoMMISSl!N

. IioC cem CERTIFICATE OF COMPLIANCE ' E

' FOR RADICACTIVE MATERIALS PACKA!ES E

c. PACKAGE IDENTIFICATION NUMBER 1.a CERTIFICATE NUMBER. b REVISION NUMBER d. PAGE NUMBER e. TOTAL NUMist '8 PAGES 9080 12 USA /9080/A 1 4 )

1 PREAMBLE ~dN gL This certificate is issued to certify that the packaging and contents desenbed in item 5 below, meets the apphcable safety standards set forth in Title 10. Code l j of Federal Regulations, Part 11. Packagmg of Radioactive Materials for Transport and Transportation of Radioactive Matenal Under Certain Ccnditions." .g D. This certificate does not reheve the consignor from comphance with any requirement of the regulations of the U.S. Depar"nent of Transportation or omer N appbcable regulatory agenCles. including the government of any country through or into which the package well be transported.

$lk 4a ig 1 THsS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION

. g PREPARED BY (Name and Address # b TITLE ANO ICENTIFICATION OF REPORT OR APPLICATION-E L Westinghouse Hittman Nuclear Westinghouse Hittman Nuclear Incorporated g Incorporated application dated February 27, 1984, as supplemented. E E ;

7 9151 Rumsey Road Columbia, MD 21045 8 E

- r' ID C 771-9080 N

- ceoOCxET NuuBER % ( - .1

!: 4. CON 0lTIONS

' E rr ~ ~ ; a rnis certificate is conditional upon fuifiliina the requirements of io cFR Part 71, as apphcable and the conditions specified below.

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-(a) Packaging e ,

p 7  ; y (1) Model Nos.: 1HN-600, NUPAC 100, and CNS 7-100 N u .. . .

i (2) Description nN _

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! Steel, encased, lead: shielded _ casks 'for low specificiactivity material . p lg The casks are right: circular cylinders 1/2 inches high by 84 inches in diameter. 'Each cask:has a cavity which is' 40-1/4"or 40-3/4 inches I high by 75-1/2 inch'es in adiameter. . The cask = side wall consists of a N 3/8-inch thick inner stegl shell, a 3-inch lead shell., and a 3/4-inch l thick outer steel- shell.+ :The . base ~-is comprised of two steel plates g welded together to fonn a 5-1/2-inch thick base which is integrally .g

-I welded to the inner and' outer? steel shells of the side wall. A steel lI flange is. welded to the inner and outer shells of the side wall at the lN top. The 5-1/2-inch thick lid is comprised of two steel plates welded l together, which are stepped to mate with the steel flange. The cask iljg l

closure is sealed by a Neoprene gasket located between the lid and steel flange. Positive closure is accomplished by eight ratchet p

( binders. The lid contains a 6-1/2-inch thick centrally located shield W plug, comprised of three steel plates stepped and welded. The shield N lu plug is sealed by a Neoprene gasket, and eight, 3/4-inch studs and j nuts or bolts are used to provide positive closure. A vent / test port in the shield plug and a stainless steel cavity sleeve is optionally %g provided. 't h

J Tie-down is accomplished by four tie-down lugs welded .to each cask ;N L body. Each cask is provided with four lifting lugs, three lid lifting E

[ lugs, and one or three shield plug lifting lugs. The cask gross l weight is approximately 48,000 pounds. p W.

L 5-E N l l F 8506030029 850522 g PDR ADOCK 07109080 g C PDR y 5

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I Page 2 - Certificate No. 9080 - Revision No.12 - Docket No. 71-9080 b I E I N I mg :. -

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5. (a) (3) Drawings N

I The Model No.' HN-600 packaging is fabricated in accordance with Hittman b I Nuclear & Development Corporation Drawing Nos.: C001-4-9600, Sheet 1, E Rev. G; C001-4-9601, Sheets 1 and 2, Rev. E; C001-4-9602, Sheets 1 and l l

g 2, Rev. D; C001-4-9603, Sheet 1, Rev. C; and C001-5-9604, Sheet 1, j ja Rev. 1; y lI N I The Model No. NUPAC 100 packaging is fabricated in accordance with R I Nucler Packaging, Incorporated Drawing No.: BA-20-2000, Sheets 1 and R c I 2, Lvision 2; or N The Model No. Cf(S T-lk0 cka in kabricated in accordance with ll Nuclear Packaging In'corporated Drawing NoeBA-20-2000, Sheets 1 and 2, p I

I Revision B. A k

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g (b) Contents m '

Q s a fly Ig (1) Type an'd;fornr'of' material '

/- A !g lI Qi 5 (i) Dewatered,%Q or;solidifie'dwlas?, .n R I solids,s te, meeting the requirements N <

l 'f E Qo,'r low specif,1c>

M activity (E..d material;L iRN in secondary,

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,g l (ii) r Activated . solid f (components 7neeting~the require 6nts for low ly Ig Is ixtcificisctiVitylmatental4;A - Q, a g

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'I (2) M 'f1materialiWM

'o 31 &9il f package fW.#

4 #? I I Maximum C quantity U $4,2$ilperj8(

ii  % E l Greaters than Typedquantitygoffradi'oa~ctive material with the weight l g of the co'ntents',4econdary' containers' and shoring not exceeding 13,000 g i

l pounds. ' Internal decay heat ;mustsot ' exceed 25'thennal watts. p l " ll,  % , '- \, y .

I 6. .(a) For any package containing water and/or organic' substances which could R I radiolytically generate combustible gases, detennination must be made by N I tests and measurements or by-analysis _of a~^ representative package such that '

the following criteria are mettover;a period of time that is twice the l l l p ll expected shipment time: p .

il I I (1) The hydrogen generated must be limited to a molar quantity that would E '

I be no more than 5% by volume (or equivalent limits for other inflam- lE l mable gases) of the secondary contaiger gas void if present at STP ll q (i.e., no more than 0.063 g-moles /ft at 14.7 psia and 70*F); or g I lN I (ii) The secondary container and cask cavity must be inerted with a diluent li I to assure that oxygen must be limited to 5% by volume in those portions R I of the package which could have hydrogen greater than 5%.

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conomons (continu:c) 11 l

I Page 3 - Certificate No. 9080 - Revision No.12 - Dccket No. 71-9080 i I It I i l

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I For any package delivered to a carrier for transport, the secondary container i s y I must be ' prepared for shipment in the same manner in which determination for 1 I gas generation is made. Shipment period begins when the package is prepared W (sealed) and must be completed within twice the expected shipment time.

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

l l !g 1 (a) above need not be made, and the time restriction in (a) above does not 'N I a pply. N I E_

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7. Except for close fitting contents, shor_ing must be placed between secondary containers (or activated components) and ;the l

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I during normal conditions of(tjan' sport.' (,jf ' '~ ]casis cavity to prevent move 1

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i l' 8. The lid and shield plug \l'ifting lugs must not be used for lifting the cask, and E I E must be covered in ,kry lid. transit; and the secondary lid lif ting' lug must not be used l for lifting the pri m . .- - ;

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9. Prior to each.thfpinenththespacka'ging lid seals ,1ffopened (oriif the security 'g l1, seal is broken)kmust be4. inspected. The seals must be replaced with new seals k Il if inspection shows any defects'or every:twelvef(12) months,iwhichever occurs If <

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10. The drain line 'must becappropriatgly' plugged [and Lsealed pricr30 transport. y l lg & C% .,, L.M , f , l

!I 11. Each cask must@ 1eakrtested 'in. accordance with' Appendix 8.3 of the application R

'I on or before September:1,i1984 and at leastconce eve (12) months thereafter. Il 1 The sensitivity ibf; the ' test'musti.betat:1 east?1 x .10-gy atm cm twelvp/sec (STP).

Each I cask which has bsen,damagedior? repaired in'the' area'of a seal must also be tested prior to sub, sequent use.1 g 4 (Q s y o, ,ss -

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12. Fackagings fabricated'$fter August 31,.1980, must be constructed of A-516, Grade 70 carbon steel instead ,of. A-36 carbon steel . '

/ ,, W I 13. Fabrication of packagings without Adrain .line ~is not authorized. l m , c y p 14. The package authorized by this certificate must be transported on a motor p l1 vehicle, railroad car, aircraf t, inland water craf t, or hold or deck of a seagoing i lI vessel assigned for the sole use of the licensee. ,ij 1 B l 15. The package authorized by this certificate is hereby approved for use under the l g general license provisions of 10 CFR 571.12. g lI I 16. Expiration date: November 30, 1988.

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I n I E I ~ Page 4 - Certificate No. 9080 - Revision No.12 - Docket No. 71-9080 It i I I

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1 I I i I REFERENCES I I E Westinghouse Hittman Nuclear Incorporated application dated February 27, 1984.

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l Supplement dated: December 7, 1984.

I g g lI i I Chem-Nuclear Systems, Inc. supplement dated: June 29, 1979. I I K I FOR THE U.S. NUCLEAR REGULATORY COMMISSION #-

I I I sb Charles E. MacDonaldpChief K

I V Transportation Certif.ication Branch I

~g l h Division' of Fuel Cycl'e'a,nd Material Safety,:W.SS/ #-/  !(I st .h%fh

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4 UNITED STATES

! h- NUCLEAR REGULATORY COMMISSION

7. E WASHINGTON, D. C. 20555 A.,.....) r,:

Transportation Certification Branch Approval Record Combustible Gas Mixtures Conditions were imposed on packages containing water and/or organic substances to limit the accumulation of radiolytically generated gases .:

over the shipping period to preclude the possibility of significantly reducing the packaging effectiveness due to explosion.

Part of the conditions included "...it must be detennined by tests and measurements of a representative package whether or not...."

There is no reason to believe that calculational methods could not be used as means of determining gas generation. So as not to preclude a valid analysis, part of the condition to limit the accumulation of radiolytically generated gases is revised to read "...it must be detennined by tests and measurements or by analysis of a representative package <

whether or not...."

The analytic approach involves detennining the hydrogen generated in the waste by radiolysis based on the absorbed dose of the waste over a given period of time. To satisfy the condition to preclude a combustible mixture, the period since closure-and twice the shipping time must be considered. The calculation regulres that the properties of the waste are known. These properties may be determined from test and measurement of representative waste foms or from data that is applicable to the waste form. The determination should be documented and retained as part of the records for the shipment.

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Charles E. MacDonald, Chie Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: MAY 2 2 W

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