ML20197F732
| ML20197F732 | |
| Person / Time | |
|---|---|
| Site: | 07109168 |
| Issue date: | 05/12/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20197F714 | List: |
| References | |
| NUDOCS 8605150657 | |
| Download: ML20197F732 (4) | |
Text
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_ _ - _ ------ ---- ----------- - ----a,_-g I Nac Pones sis U.S. NUCLEAR REOULATO;Y COMMISSION k I *au CERTIFICATE OF COMPLIANCE E Il l
io CFR n FOR RADIOACTIVE MATERIALS PACKAGES E 1.a. CERTIFICATE NUMBER b REVGION NUMBER c. PACKAGE iDENTIFiCAT60N NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES l
Iq 9168 3 USA /9168/R(U) 1 3 R:
l 2 PREAMBLE El ll a This certificate is issued to certify that the packaging and contents described in item 5 Delow, meets tne apphcacie safety st.ndards set forth m Title 10. Coce I) jll g of Federal Regulations. Part 71,' Packaging and Transportation of Radioactive Matenal?
- n. This certificate does not reheve the consignor from comphance witn any requirement of the regulations of the U S. Geoartmant of Transportation or other (Il l
apphcaole regulatory agencies. including the government of any country througn or into which the pacmage wiH be transported 'EI lll l Il 3 THiS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANAL a ISSUE 0 70 rName maaf Aderm llE
- n b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION ?
I in i Chem-fluclear Systens, Inc. Chen-fluclear Systems, Inc. application dated ;E I 220 Stoneridge Drive June 19, 1984, as supplene'nted. !b I Columbia, SC 29210 l )5 l
l c. DOCMET NUMBER a CONOITIONS l This certificate is conditional upon fulfdhng the requirements of 10 CFR Part 71, as apphcable. and the conditions specified below lI lE I s iE j (a) Packaging I lE y (1) Podel No.: CNS 8-120B 1 N
I'I N (2) Description
- I l'N E
l The packaging is a carbon steel-encased, lead shielded 74-inch OD by 88-inch high cask for radioactive waste materials. The cask is a ,y ly right circular cylinder with a 62-inch ID by 75-inch high cavity. The p lg walls of the cask contain a lead thickness of 3.35 inches encased in N
' ll 0.75-inch thick inner steel shell and 1-1/2-inch thick outer steel f I s hel l . The exoosed sides of the package are provided with a thernal barrier consisting of a 5/32-inch diameter wire wrap on 12-inch centers j
1 l and covered with 3/16-inch thick steel jacket. The botton weldment is g !9 g
g made of two, 3-1/4-inch thick carbon steel plates. The primary lid is N l sealed with a double silicone 0-ring and 20 equally spaced 2-inch H I diameter bolts. The 29-inch diameter centered secondary lid is sealed ,h I with a double silicone 0-ring and twelve equally spaced 2-inch diameter bol ts . The optional drain line is sealed with a 3/4-inch diameter cap f l screw and a silicone 0-ring. The lid sealing surfaces are stainless
!b g steel and the space between the double 0-ring seals is provided with a lph I test port for leak testing. lN I :N I The top and bottom of the cask is provided with steel encased, rigid polyurethane foan inpact limiters. The inpact limiters are secured to !jy l each other about the cask with eight 1-inch dianeter ratchet binders. p y
p The impact limiters are 102 inches in diameter and the overall height E I: of the package with the impact limiters attached is 132 inches. E l- I Il The package is provided with four tie-down and two renovable lifting devices . Each lid is provided with three lifting lugs. The gross l y
- weight of the packaging and contents is approximately 74,000 pounds. I I 3 11 !I l
l, C &7 660512 07109168 :N l PDR l
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==mamm ammammum umm - - - -mmm.mmmm - - - - - - = mmmmmmmwr- .= = .ac.naurum um CONolTloNS (contsnued)
Page 2 - Certificate No. 9168 - Revision No. 3 - Docket No. 71-9168 l 9 1
I (a) (3) Drawing The packaging is constructed in accordance with Chem-Nuclear Systems, Inc. Drawing No. C-110-E-0007, Sheets I and 2, Revision D. -
j (b) Contents l (1) Type form of material i
- (i) Byproduct material in the fom of dewatered resins, solids, or
! solidified waste contained within secondary container (s); or N l 7
! (ii) Radioactive material in the fom of activated reactor components.
- (2) Maximun quantity of naterial per package l
Type B quantity of radioactive material, not to exceed 2,000 times a $
Type A quantity,100 thermal watts, and 14,680 pounds including weight .
i of the contents,_ secondary container (s) and shoring. The contents may l include fissile materials provided the mass limits of 10 CFR 971.53
, are not exceeded.
l l
- 6. Except for close fitting contents, wood shoring must be placed between the ,
secondary container (s) (or activated components) and the cask cavity to prevent '
movement during accident conditions of transport.
i 7. The cask primary lid rust be secured by twenty and the secondary lid by twelve, I
2"-8UNC-2A x 4" long hex cap screws with flat washer torqued to 500 ft-lbs +50 _ ,
i f t-Ibs (lubricated). :p 3
- 8. Prior to each shipment (except for the contents neeting the requirements for low lE specific activity naterial which is transported by exclusive use vehicle), the packaging must be leak tested in accordance with Section 8.2.2.2 of t g y
l 9. In addition to the reouirements of Subpart G.of 10 CFR Part 71:
I l
(i) Each package nust meet the acceptance tests and be maintained in accordance j with the Acceptance Tests and Maintenance progran of Section 8.0 of the !
4 application, and )g l 5 I (ii) The seals must be replaced with new seals if inspection shows any defects ;B I or every 12 nonths, whichever occurs first. The test ports and optional lE drain line must be appropriately plugged and sealed prior to transport.
' ]
. g p g 10. (a) For any package containing water and/or organic substances which could ;p radiolytically generate conbustible gases, determination must be made by y Iil tests and neasurements or by analysis of a representative package such that f I #
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the following criteria are net over a neriod of time that is twice the expected shipment time: j (i) The hydrogen generated must be limited to'a molar quantity that would I be no more than 5% by volune (or equivalent limits for other inflamnable if I gases) of the secondary cogtainer gas void if present at STP (i.e., no 'N
]I more than 0.063 g-noles/ft at 14.7 osia and 70"F); or i
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- p -- ----m -----mm mm ---mm mm mmmmm mm----uanam m m m m awnuom - - m m mm mmq lRl lll CONDITIONS (continued) lf Page 3 - Certificate No. 9168 - Revision No. 3 - Docket No. 71-9158
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! II I
nll 10. (continued) lI! (ii) The secondary container and cask cavity nust be inerted with a diluent
! to assure that oxygen must be limited to 5% by . volume in those portions f;g ll of the package which could have hydrogen greater than 5%. 't I E:
For any package delivered to a carrier for transport, the secondary container must be prepared for shipment in the same nanner in which determination for j,{
lgi gas generation is made. Shionent period begins when the package is prepared [4 g
jgj (sealed) and must be conoleted within twice the expected shipment time. p l# :5!
15 (b) For any package containing naterials with radioactivity concentration not !*
!E exceeding that for low specific activity material, and shipped within 10 days of preparation, or within 10 days af ter venting of druns or other p
}l l secondary containers, the determination in (a) above need not be made, and gi l ! the time restriction in (a) above does not apply. 5:
l ! t' i I 11. The package authorized by this certificate is hereby approved for use under the Ej general license provisions of 10 CFR 571.12.
- 12. Expiration date: fiarch 31, 1990. g I in
- REFERENCES ;P lil Chem-Nuclear Systems, Inc., application dated June 19, 1984.
j l Supplements dated: December 7,1984; March 15 and December 9,1985; and April 30, jij 1986. E E
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- E II
]ll FOR THE U.S. NUCLEAR REGULATORY C0fitilSSION j
.I I .El ld, Chie 4 Transportation Certification Branch 8 j Division of Fuel Cycle ard ;j Material Safety, fliSS %
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I Date: MAY l 2 W j}
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' ~' UNITED STATES j* ,, Y'I. j .,
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 e
?,g %. ,o 8 Transoortation Certification Branch Approval Pecord l'odel No. CNS C-120B Package Docket No. 71-9168 By application dated Aoril 30, 1986, Chem-Nuclear, Inc. requested revised 0-ring gasket sizes to the Model No. CNS 8-1208 package design.
The lid 0-ring diameters have been increased in size fron 0.250" to 0.275" with a 70 + 10 -10 durometer rating. The increased diameter should provide a more positive seal to the cask lids.
The revised package design meets the requirements of 10 CFR Part 71.
. /]
Char es . P*aceonaid,~ Chief Transportation Certification Branch Division of Fuel Cycle and fiaterial Safety, HMSS Date: MAY 121996
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