ML20128F454

Certificate of Compliance 4909,rev 12,for Model GE-21PF-1 Package

ML20128F454
Person / Time
Site:	07104909
Issue date:	02/05/1993
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20128F448	List: ML20128F446 ML20128F454
References
NUDOCS 9302110398
Download: ML20128F454 (4)

Text

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' l eene roeiaseis u,S, NUCLEAR REOULATORY C0tteetSSION I

== CERTIFICATE CF C2MPLIANCE I C C'A ". I F R E'A!12 ACTIVE MATERIAL.S PACKACES e nevisum wouun s # AuAc.s n,tNiitecatam wouun . .Aos wuuea n .1of At wuw. rAct.

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. T ni. c.ri,vic.i. i. ..u.a io c. rise r in.t in. p.c6.ging .no eoni.ni. oneritw in ei. s d.io., .i. in. .ppiic.ei. .tr i.no.ro. ..t vorin in Titi. io, coo. I I of Feo.r.i Regui.iion.. F.rt 7t, *P.cuging .nd Tr.n.podstson of R.o80.CH4 M t.n.l? i I e, ini. c.rirew. on.. not r.n.4 in. con..gnor irem comp.nc. .rin en, r.uva.m.nt ei me r.gvi iion of in, u.s o.p.nm.n or tr n.non.non or om r I I Applic.bl. F.edt. tory .g.nce . including th. poornin.ni of ny Country through or snio which th. (4Ck.a. Will b. ir.nSpori.d i I I I I I

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. nsuso io <=.=is is,su.t0 ON tH8 BASIS OF A SAFETY ANALY$lt NtPORt of THE PAC. AGE DESIGN 04 APritCATION6 tina Awo notNwicAtem or narcat on Aceuc 4 #.w l

General E1cetric Company General Electric Company application dated I P.O. Box 780 November 19, 1982, as supplemented. l Wilmington, NC 28401 , p ,, y c 't i I D h p'71-4909 d coc rt wouun -l

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k This t.filfic.t. 4. condefion.1 upon fulfillmg th6 f quir m.nts of 10 CF A P rt 71. .s ppisc.ble, .nd th. corhiition. .pecified teiow. l I - I

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I I (a) Packaging ', ,

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4 I (1) Model No.:

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)$_* O l l  :, t . , 7 I I Packaging as described and-constructed in accordance with DOT I I Specification ElPT-l'except:as shown in General Electric company Drawing i I

I No. -769E237 (GE-21PF-1) e Shbet Hos. I and 2, Rev.14. In addition, the l 1ength ;of the 8" x:2.5"'ticidown' support channel;may be from 43 to 55 l

l inches long and vent holes in the' exterior shellemay be sealed with i I plastic plugs. Maximum gr o ss weight-of the package is 8,600 pounds.

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(b) Contents O_. : .

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i (1) Typeandformofmjterial , j i I . .

.l 5 I I Uranium hexafluoride enriched in'U-235 isotope. I I I I (2) Maximum quantity of material per package j I I l

i (i) Model No. 30A cylinder: -4,950 pounds UF 6 enriched to not more than i l 5 w/o in the U-235 isotope. I

! I I Model No. 308 cylinder: 5,020 pounds UF enriched to not mere than I

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! 5 w/o in the U-235 isotope. l l

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. CONDlilONS (continued) s

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• Page 2 - Certificate No. 4909 - Revision No. 12 - Docket No. 71-4909 [l i l

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I (c) Fissile Class  !! WL!

I I !l Minimum transport index 5.0 l ii l

i I i 6. In addition to the requirements of Subpart G of 10 CfR Part 71: I I I I (a) Prior to each shipment, the overpack gaskets must be inspected. These 1 I gaskets must be replaced if inspection shows any defects or every 12 l j, months, .<hichever occurs first. ,

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n (b) Each packaging must meet the Acceptance Tests and Maintenance I 1 Program of Sections 11 and 111 of General Electric Company supplement I dated October 21, 1987. b L i i.: U/j, I '

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q (c) The package shal1 5 prepared for shipment and operated in accordance y g with the Operhting Procedures of Section 1 of General Electric Company- p i supplementfdated October 21, 1987.  ;. I I s

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( 7. (i) for packagings which are not seal welded, the joints between the inner and outer shells.(ends) and the side (end)1 panel moldings must be I silicone' sealed.!,The inner and outer overpack gaskets must cover side l (end)t panel molding 'jointsJ(unless ;sealswelded). Except for joints y q covered by a glued down' gasket, jvisually inspect all. silicone sealed i A joints'.and maintain;in~goodtrepair prior to each shipment or outside I

( storage (loaded or empty). . L ,, ,.

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(ii)PriorToJune 3'0,1985, allIbo'dyr seam's and joints forl the inner and outer l shells ends):and the side;(end); panel moldings must be continuous a q

welds.(,(Welding must be~ byL a: fusion -process in accordance with the I

( American; Welding' Society Code or American Society of Mechanical I I

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q Engineers'. Code.'

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8. The 30-inch dia$e(er UF 6 cylinders must be fabricated, inspected, tested and l maintained in accordance with American National Standard N14.1 (1990 g I version). Cylinders' shipped after December?31, 1992 must be fabricated in accordance with Section Vill, Division;I; of'the ASME (American Society of Mechanical Engineers) Boiler ;and Pressure Vessel Code and be ASME Code

9. At least once overy five years, each packaging must be inspected to verify the presence and condition of the insulation. The inspection shall consist of II l i l inserting a probe through each vent hole in both the lid and base to confirm R the presence and rigidity of the insulation, for packagings which require I drying, the inspection must be performed after drying. l I

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I . Page 3 - Certificate 110. 4009 - Revision No. 12 - Docket flo. 71-4909 [

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W s 10. The packages authorized by this certificate are hereby approved for use under >l N the general license provisions of 10 CFR 671.12. >l s

11. Expiration date: February 28, 1994. l l f,

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REFERENCES General Electric Company appilcation dated flovember 19, 1982.  !

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' Supplements dated: September 23, 1983; February 15 and May 22, 1984; October 21, q

i 1987; flovember 14, 1990; August 10, 1992;,and January ll, 1993. l 4 - 5/ l , l ..

d fluclear Containers, incorporAtdd = supplement . - / , , August 22, 1986.

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q FOR THE U.S. NUCLEAR REGULATORY COMMISS10ft i a

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fkQY Charles E. MacDonald, Chief jf l

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APPROVAL RECORD Model No. GE-21PF-1 Package Certificate of Compliance No. 4909 Revision No. 12 By application dated January ll,1993, General Electric Company (GE) requested renewal of Certificate of Compliance No. 4909, for the Model No. GE-21PF 1 package. No changes in package design or authorized contents were requested.

The Certificate has been renewed for a one-year term which expires on February 28, 1994. This term was chosen to provide GE sufficient time to provide a consolidated safety analysis report for the package. The safety analysis report should be complete in itself and should include drawings of the package design and information which shows that the package design meets the requirements of 10 CFR Part 71. Preferably, the safety analysis report should be in the format of Regulatory Guide 7.9. The safety analysis report should also include procedures for operating and maintaining the package. The Certificate of Compliance may be conditioned to specifically cite the operating and maintenance procedures.

To assure continued use of the package, an application for renewal, including the consolidated safety analysis report, should be submitted at least 30 days prior to the Certificate of Compliance expiration date.

8(4 %g (4 Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and FEB 5 1993 Transportation, NMss Date