ML20128M573

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Certificate of Compliance 9179,Rev 3,for Models Nupac 6/100L & Nupac 6/100H.Approval Record Encl
ML20128M573
Person / Time
Site: 07109179
Issue date: 05/22/1985
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20128M571 List:
References
NUDOCS 8506030024
Download: ML20128M573 (4)


Text

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  • CERTIFICATE CF COMPLIANCE l F09 CA!!2 ACTIVE MATERIALS PACKA7ES

- 1.c, CERT!FICATE NUMBER - D.REVISloN NUMBER c. PACKAGE IDENTIFICATION NUMBER d.PAGE NUMBER l e TOTAL NUMBER PAGES {

q 9179 3 USA /9179/A 1 3 lg I z PRuusta - qu -

l e. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set fortn in Title 10. Code l u of Federal Regulations. Part 71,' Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certam Conditions." gl

b. .This certificate does not reheve the Consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other I I apphcable regulatory agencies, including the government of any country through or into which the package will be transported. M I b I  %
  • '50"Ifel^e'y'5*.2.*Sfo"2,' *** ' ^ **" ^"*"*i E"E fNo'50*Jeff o3,iE,"on's,lffilf,"c4 Tion g! Nuclear Packaging, Inc. NUPAC application dated October 29, 1982, i; as supplemented. !g I 1010 South 336th Street 1 Federal Way, WA 98003 (g-E N f I . r 7Cm, 71-9179 i 1 . c occxEr NuueER % -

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This certificate is conditional upon fulfilling the requirements of to CFA Part 71, as applicable, and the conditions specified below q' s' s s y y (a) Packaging s.f y

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!gp lE (1) Model Nos.: NVPAC 6/100L and NUPAC 6/100H

.. 'E (2) Description

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y i Steel, encased lead shielded casks for low specific activity material.

The casks are right circular cylinders with a 61.0-inch ID by 62.0-

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, 1 inch 'IH cavity.- The walls of the casks contain a lead thickness ;I lI ranging, from,2.43 to 3.56 inches encased in 0.50-inch ~ thick inner lN lI steel'shell and '1.13-inch thick outer steel shell. The top cover and lj h cask bottom are made up.of two steel plates ranging ;in thickness from y g' 2.0 to 3.0 inches. ,The primary cask lid .is secured to the cylindrical y g cask body: by eight,1-1/4-inch rachet' binders. An optional secondary n I lid is centered in the. primary lid and is secured to the primary lid i II with eight, 3/4-inch studs and nuts. Each lid is provided with a N

$j Ne'oprene gasket seal . The casks may be provided with an optional 12 lj l

f gauge stainless steel liner (seal welded along all edges), an optional i

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l lid vent line with pipe plug, and an optional 3/4-inch drain line and g pipe plug. The casks are provided with four equally spaced lifting / tie- lg 5

!i down devices. The primary lid is provided with three lifting lugs and jN lI the optional secondary lid is provided with one lifting lug. The N l casks gross weights range from 42,900 to 53,900 pounds. l l E I 00, Lead Tk, Top Tk, Bottom Tk, Gross Wt, i q Model s l Number inches inches inches inches , pounds I ,

I N 69.11 2.43 4.5 4.5 42,900 l NUPAC 6/100L 3.56 6.0 6.0 53,900 l

]l NUPAC 6/100H 71 .37 g

! (3) Drawing E

5 e The packages are fabricated in accordance with Nuclear Packaging, Inc. f j

Drawing No. X-20-2040, Sheets 1 and 2, Revision No. D. l i

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I 0506030024 85C522 N

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I Page 2 - Certificate No. 9179 - Revision No. 3 - Docket No. 71-9179 R I t I L l , y..

l (b) Contents  !

1 E I (1) Type and fonn of material i 1 t j

l (1) Dewatered, solids, or solidified waste, meeting the requirements for low specific activity material, in secondary containers; or j

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1 i I (ii) Activated solid components meeting the requirements for low K l specific activity material, in secondary containers. I l t_

j ,(2) Maximum quantity of material per package (

1 d R l2 Di t material which may contain Greater than Typeiquantity of radioac. ive t

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1 fissile mater,ial%provided the fissile material does not exceed the i 1 limits in 10,CFR 971.53. The decay heat load >is limited to 9 watts K E

l for the Mo' dei No. NUPAC 6/100L cask and 61 wit 3 for the Model No.

3 NUPAC 6/l p cask. 4 (

) 6. (a) For any pacIage c ining water and/or organi stanc'es which could I 1 radiolyticaTJy generateicombustible gases (detennination rust be made by J tests and. measurements?or by analysis of/a representativeJpackage such that . l E< !r l the followin'g criteria aiy E

] expected djpment timeg3e met JQ over a!M p[eriodfofZtime that*is twice the (

s t, Nhx t 35 f . g

) (i) The hydrogen generatedan&st be,.lidiiYed;to a , molar qu<antity that would 1 be n6/more than;5% b9#iolumej (orj e'q'uifalentilimits -for other inflam- ly l 3

mable gases))ofithel s'econda'ryncontaiger gas; void if2present at STP 1

- l 1

(ii) The secondary container and, cask'cav,ity .must beuinerted with a diluent

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g 1 to assure that oxygen must' be(liniited'to 5% by(volume in those portions g 1 of the package which could'have' hydrogen greater than 5%. t

] jg p t For any package delivered 4to a carrier forytransport, the secondary container (-

] must be prepared for shipient tn,the3 same' manner in which detennination for g 1

1 gas generation is made. Shipment ' period begins when the package is prepared g I (sealed) and must be completed within twice the expected shipment time. I_

} t 1 (b) For any package shipped within 10 days of preparation, or within 10 days K l after venting of drums or other secondary containers, the detennination in E l (a) above need not be nade, and the time restriction in (a) above does not (

) a pply. g

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) 7. Maximum gross weight of the contents, secondary containers, and sharing is K

} limited to 12,000 pounds.  !

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) 8. Except for close fitting contents, shoring must be placed between secondary j}E 1

containers and the cask cavity to minimize movement during nonnal conditions of g 1 transport. I I I I 9. The lid and shield plug lifting lugs must not be used for lifting the cask, and E l shall be covered in transit. (I

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L____________________________________________________!

I * * "*"^ U T " *" * * * * '

I conosinins (continu:c) n I '

R I Page 3 - Certificate No. 9179 - Revision No. 3 - Docket No. 71-9179 N I E I N I n g:

1 N I 10. The cask shall be provided with either (or both) a drain line or a lid vent line Iy I as shown in the drawing in order to provide a method to leak test the package. n I E

11. In addition to the requirements of Subpart G of 10 CFR Part 71: g l

I g (1) Prior to each shipment, the packaging Neoprene lid seals must be inspected. ,

lg The seals must be replaced with new seals if inspection shows any defects  !

ll or every twelve (12) months, whichever occurs first. Cavity drain and vent '

I lines shall be sealed with appropriate sealant applied to the pipe plug I' threads. i I g-

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(ii) Each cask must meet the Acceptance [ Tests'and Maintenance Program of Section 8.0 ~*jg lI l

of the application. In aidditiori, th'elask 'sh'all be leak tested at least months M fn accordance with Appendix 8.4 of the application.

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I every twelve '12)Q - ls l#

I 12. The cask body and eachscask lid shall be marked in accordance with 10 CFR 671.85(c).

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13. The package authorjze'd q bysthis certificate shall be transported on a motor j vehicle, railroad' car, aircraf t,sinland watercraf t, or hold or deck of a seagoing I vessel assigned for the soletuse,of the licensee;, ., lg N
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14. The packages authIrized by this ' certificate' is. hereby approved. for use under the L+  ;>E c
  • 8 general license 4rovisions ofcl0 CFR 971.12. ~~ ) 73 A 15.

tj MQ 21', 1988 s di',23 r

N f , ?4 Expiration datei@Marchj$ .

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!$18' MM idt l . D I Qa REFERENChS m.m :==; w y J

Nuclear Packaging, Inc."applic%. ation dated ' October 29,1982*. (

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Supplements dated: February;18 and March 24p1983*. s -> p v + y

  • See Docket File No. 71-9159'p / , , ,

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"'t ,FOR THE U.S. NUCLEAR REGULATORY COMMISSION I

N 9 l l Charl es . conadIchief' 8

                                                                              ~ Transportation Certification Branch                     l Division of Fuel Cycle and                             y Material Safety, NMSS                                p k

MAY 2 p inne E Date: F W p lI N 11 i l R . 11 N ll F N lI p 11 II 5 i l_ , , . . . . , , ,,,.. ,c.,, ., ,,,.-------------- mr...--------n N l

r- [ 8 9,j o NUCLEAR REGULATORY COMMISSION - UNITED STATES 5 g WASHINGTON, D. C. 20555

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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 a 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 determined 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 detemined 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 requires that the properties of'the waste are known. These properties may be detennined from test and measurement of representative waste foms or from data that is applicable to the waste fonn. The detennination should be documented and retained as part of.the records for the shipment. Charles E. MacDonald, Chief. [ Transportation Certification Branch Division of Fuel Cycle and ~ Material Safety, NMSS 4 Date: h , i g-

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