ML20153F835
| ML20153F835 | |
| Person / Time | |
|---|---|
| Site: | 07109168 |
| Issue date: | 02/12/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20153F830 | List: |
| References | |
| NUDOCS 8602270544 | |
| Download: ML20153F835 (4) | |
Text
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I* NRC FORM s1s U.S. NUCLEA7 CE2ULATO.7Y CoMMISSl!N N +=> CERTIFICATE CF C5MPLlANCE h I to crR FOR RADIOACTIVE MATERIALS PACKAGES N 1 a CERrlF. CARE NUMBER O REvisiCN NUMBER C PACM AGE iCENrW4CAriON NUMBER d PAGE NUMBER e ToratNi,NatRracEs y 9168 2 USA /9168/B(U) 1 3 gj l! 2 PREAustE b l a This certificate is issued to certify that the packaging and contents described in item $ below. meets ttie appbcabie safety standards set fortn in Titie to Code [E :
of Federal Reguiations. Part 11. ' Packaging and Transportation of Radioactive Material-ll $)
' I' b This certificate does not reheve the consignor from comphance with any requirement of the regulations of tee U S Department of Transportation or otner I?
I apphcacie regulatory agencies. encluding the government of any country tvough or into enich tne package will be transported I.
I n I;: If k 3 rsis esRrwicare is issuco ou rse easis os a sarerv anatysis RePoRr or rse eacxace oesics om amicarm E I e issvEo to m 4, e rirte *~o iceurwicarios or REPoRr CR AMiCArtoN 1
'I I I L l Chem-Nuclear Systens, Inc. Chen-Nuclear Systens, Inc. application dated 1 Il 220 Stoneridge Drive June 19, 1984, as supplemented. f lj Columbia, SC 29210 %
I t 71-9168 5 I e coc er~uwecR 1 lI a co~oirious I
'I This certificate is conditional upon fulfilhng the requirements of to CFR Part 71. as apphcable and the conditions specified below !
I ,1)
I! s Packaging (L, (a) 4 I; 1 Ij (1) Podel No.: CNS 8-1208 ll l 1, I (2) Description l
I q The packaging is a carbon steel-encased, lead shielded 74-inch OD by A[I g 88-inch high cask for radioactive waste materials. The cask is a flI,l l right circular cylinder with a 62-inch 10 by 75-inch high cavity. The I walls of the cask contain a lead thickness of 3.35 inches encased in l 0.75-inch thick inner steel shell and 1-1/2-inch thick outer steel fy s hel l . The exposed sides of the package are provided with a themal li g barrier consisting of a 5/32-inch diameter wire wrap on 12-inch centers
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ll g! and covered with 3/16-inch thick steel .iacket. The botton weldnent is A ll nade of two, 3-1/4-inch thick carbon steel plates. The primary lid is l' l I! sealed with a double silicone 0-ring and 20 equal'y spaced 2-inch I diameter bolts. The 24-inch dianeter centered secondary lid is sealed
%( with a double silicone 0-ring and twelve equally spaced 2-inch dianeter [i g!
bol ts . The optional drain line is sealed with a 3/4-inch diameter cap p
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t g screw and a silicone 0-ring. The lid sealing surfaces are stainless B l It steel and the space between the double 0-rina seals is provided with a i l If test port for leak testing. I ll >-
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The top and bottom of the cask is provided with steel encased, rigid 'p!
polyurethane foan impact limiters. The inpact limiters are secured to
( p-l each other about the cask with eight 1-inch diameter ratchet binders. ;f l l The impact limiters are 102 inches in diameter and the overall height 8 I of the package with'the inpact limiters attached is 132 inches. l l The package is provided with four tie-down and two renovable lif ting The gross j
g d evices . Each lid is provided with three lifting lugs. ;p weight of the packaging and contents is approximately 74,000 pounds. ,)
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,ll: CONDITIONS (continoea) g f Page 2 - Certificate No. 9158 - Revision No. 2 - Docket No. 71 4168 h{
(a) (3) Drawing I
The packaging is constructed in accordance with Chen-Nuclear Systems, 1 Inc. Drawing No. C-110-E-0007, Sheets 1 and 2, Revision C. l3 (5) Contents Type fom of material h}
F (1) p}
Bj (i) Byproduct naterial in the fom of dewatered resins, solids, or El solidified waste contained within secondary container (s); or h bi (ii) Radioactive naterial in the tbm of activated reactor components. I h
(2) Maxinun quantity of naterial per package Type 8 quantity of radioactive naterial, not to exceed 2,000 tines a h Type A quantity,100 themal watts, and 14,680 pounds including weight gj of the contents, secondary container (s) and shoring. The contents may I include fissile materials provided the nass limits of 10 CFR 971.53 F are not exceeded.
- 6. Except for close fitting contents, wood sharing must be placed between the h secondary container (s) (or activated components) and the cask cavity to prevent gj novement during accident conditions of transoort. I E
- 7. The cask primary lid must be secured by twenty and the secondary lid hv twelve, i 2"-8UNC-2A x 4" long hex cap screws with flat washer torqued to 500 f t-lbs +50 i f t-lbs (lubricated ) . h t)
- 8. Prior to each shionent (except for the contents meeting the reouirements for low II specific activity naterial which is transported by exclusive use vehicle), the Il packaging rust be leak tested in accordance with Section 3.2.2.2 of the application. [
- 9. In addition to the recuirements of Subpart G of 10 CFR Part 71: h 0
(i) Each package nust meet the acceptance tests and be maintained in accordance 3D with the Acceptance Tests and Maintenance prooran of Section 8.0 of the k application, and [i l (ii) The seals nust be replaced with new seals if inspection shows any defects p) or every 12 nonths, whichever occurs first. The test ports and optional >l drain line must be appropriately plugged and sealed prior to transport. II Bl
- 10. (a) For any package conta'ining water and/or organic substances which could [(
radiolytically oenerate conbustible gases, detemination rust be nade by !
tests and neasurenents or by analysis of a representative package such that ,!
the following criteria are net over a period of time that is twice the L expected shipment tine:
(i) The hydrocen generated nust be linited to a nolar quantity that would be no nore than 5" by volume (or equivalent limits for other inflannable [s g
g gases) of the secondary cogtainer gas void if present at STP (i.e., no nore than 0.063 g-noles/ft at 14.7 psia and 70 Fl; or k:
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Pace 3 - Certificate No. 4163 - Revision rio. 2 - Docket No. 71-9168 M d
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- 10. (continued)
(ii) The secondary container and cask cavity must be inerted with a diluent N to assure that oxygen nust be limited to 5" by volume in those portions !
of the package which could have hydrogen greater than 5*,.
For any package delivered to a carrier for transport, the secondary container y must be prepared for shipnent in the same manner in which detemination for
, gas generation is made. Shipment period begins when the package is prepared d>
(sealed) and must be completed within twice the expected shipment time. E q t
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(b) For any packaae containing materials with radioactivity concentration not exceeding that for low specific activity material, and shipped within 10 days of preparation, or within 10 days af ter venting of drums or other secondary containers, the detemination in (a) above need not be nade, and the time restriction in (a) above does not apply.
- 11. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12.
- 12. Expiration date: t'. arch 31,1990.
REFERErlCES Chen-Nuclear Systens, Inc. , application da ted June 19, 1984.
Supplements dated: December 7,1994; and March 15 and Decenber 0, 1985.
FOP THE U.S. NUCLEAR '1ECULATORY C0f tf tISSION ill. [
Charles E. 'facDonald, Chief (i
Transportation Certification Branch Division of Fuel Cycle and t'aterial Safety, titSS Date: FEB 121966 -
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, pt 9)g UNITED STATES y .c g NUCLEAR REGULATORY COMMISSION
- C WASHINGTON, D. C. 20555
%.....) Transportation certification Rranch Acoroval 9ecord Model No. CNS 8-120R Packaqe Docket No. 71-9168 By application dated December 9,1985, Chen-Nuclear, Inc. requested several ninor changes to the Model No. CMS 8-120R package design. These changes include substitution of naterials of eqLal or better properties and increasing the bolt ring thickness from 2-1/2" to 3". The temperature range for the silicone gaskets was slightly decreased but well within the temperature range the seals would see under nomal or accident conditions of transport. The package design neets the requirements of 10 CFR Part 71.
l Charles E. MacDonald, Chief Transportation Certification Rranch Division of Fuel Cycle and Ma terial Safety, NMSS Date: FEB 12 W6 <
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