ML20135G204
| ML20135G204 | |
| Person / Time | |
|---|---|
| Site: | 07109096 |
| Issue date: | 09/11/1985 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20135G198 | List: |
| References | |
| NUDOCS 8509180281 | |
| Download: ML20135G204 (4) | |
Text
P 'ledC Pones s1s U.S. NUCLEAR REGULATORY COMMISSION s
CERTIFICATE CF CZPLIANCE f
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gu o cra n FOR RADIOACTIVE MATERIALS PACKAGES I
i a cEaTiF(CATE NUMBEJ E REYmON WVdEJ c e ACAAGE 10ENitricatioN NvWu
. KGE NUMBG s T074 NUMm N.Ga5 gi 9096 9
USA /9096/A 1
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lj a inis certit. cat... insu.o to cert.ty mai in. pacmagmo no contents o.scrio.o m hem s e.io*. meet:in.pouc.e4.
t.ty siano.ros set forta m Titi. io. coo.
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of r.o.r., n gs.iion.. Part ri. e.ca.gma ano transportation of a.o o.ctiv. u t.ri.i.-
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o ini. c.rtific t. oo.. not r..
- m. con.,anor trom compi..nc...in any requirement of in reaviations of ine u s o.o.w.at of Tr n,portation er otn.,
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I appiic.el. regui. tory.a.nc.
. inciuomo ine governm.nt of any country enrouan or mio.nica ine pack.a...ii e. transport o.
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T sgaTig. cays issgoM THE SA$ls O. A SAFETV AN4YS43,mE, T,0 C,
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I Chem-Nuclear Systems, Inc.
Chem-Nuclear Systems, Inc. application I!
220 Stoneridge Drive dated August 26, 1985.
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Columbia, SC 29210 I!
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nt oe to cra part ri....ppuc.oi...no in, conetions so.ciri.o e.io.
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Packaging lll Ii il j
(1) Model No.:
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(2)
Description
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ll A steel encased lead shielded cask 1for low specific activity radioactive lI li ma terial.
The' cask is a right circular cylinder with 86-3/4-inch OD
'l by ll7-1/4-inch height.'and a ' cavity '83-inch ID by 109-1/4-inch height.
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j The,1-inch thick lead ' shield.is supported by outer and inner steel y
gj shells 3/4-inch and 1/8-inch thick.
The inner plates of the lid and lJ t
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base are laminated steel plates with a total thickness of 1/2-inch, l
Positive closure of the silicone rubber sealed lid is provided by ltI I;
twelve,1-1/4-inch diameter cap screws. A secondary lid with a Neoprene il l
seal uses eighteen. 3/4-inch diameter bolts for closure.
The cask is li welded to a 96-inch square base plate and has two lifting trunnions,
'g three lid. lif t rings and one secondary lid lift ring.
Package gross k
p weight is 57.450 pounds.
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l-(3) Drawi ngs I
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The packaging is fabricated in accordance with Chem-Nuclear Systems, Inc. Drawing Nos. 1-298-101, Rev. K, and C-ll4-D-0006, Rev. C.
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CcNDITlcNS (continu1dl f
b Page,2 - Certificate No. 9096 - Revision No. 9 - Docket No. 71-9096 t'
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(b) Contents (1) Type and form of material y
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(i)
Process solids, either dewatered, solid or solidified in secondary l
containers, meeting the requirements for low specific activity material; or g
h-(ii) Solid reactor components in secondary containers, as required R
that meet the requirements for low specific activity material.
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(2) Maximum quantity of material-per. package
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Greater than Type A quantity of radioactive material with the weight g;
of the contents, secondary containers, auxiliary shield, and shoring
.h not exceeding 27,250 pounds.
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Y 6.
(a) For any package containing water and/or organic substances which could radiolytically generate combustible gases, detemination must be made by g
tests and measurements or by analysis of a representative package such that p.
the following criteria are met over a period of time that is twice the k:
expected shipment time:
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[i (i) The hydrogen generated nust-be-liinited to a molar quantity that would be no more than 5% by volume (or equivalent limits for other inflam-g mable gases) of the secondary contaiger gas void if present at STP y
(i.e., no more than 0.063 g-moles /ft
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at 14.7 psia and 70'F); or t
,5 (ii) The secondary container and cask cavity must be inerted with a diluent I:
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to assure that oxygen cust be limited to 5% by volume in those portions 4
of the package which could have hydrogen greater than 5%.
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For any package delivered to a carrier for transport, the secondary container D-must be prepared for shipment in the same manner in which detemination for D'
jl gas generation is made.
Shipment. period begins when the package is prepared e
i (sealed) and rust be completed within twice the expected shipment time.
B-(b)
For any package shipped within 10 days of preparation, or within 10 days I
after venting of drums or other secondary containers, the determination in 1
(a) above need not be made, and the time restriction in (a) above does not apply.
l; 7.
Shoring must be placed between secondary containers (or activated components),
I auxiliary shield, and the cask cavity to prevent movement during nomal conditions p:
of transport.
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8.
The auxiliary shield shown in Drawing No. C-114-E-0004, Rev. No. B, may be used for the shipment of solidified wastes and solid reactor components.
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Page 3 - Certificate No. 9096 - Revision No. 9 - Docket No. 71-9096 F.
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9.
The lid lifting lugs rust not be used for lif ting the cask and shall be covered E
in transit.
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10.
Prior to each shipment the lid gaskets if opened (or if security seal is broken),
lg.k y1 must be inspected.
The gaskets shall be replaced if inspection shows any defects E.
or every twelve (12) months, whichever occurs first.
(j 11.
Fabrication of additional packagings is not authorized.
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12.
The package authorized by this certificate nust be transported on a notor F
vehicle, railroad car, aircraf t, inland wat_er craft, or hold or deck of a seagoing 1
vessel assigned for sole use.of:_the slicensee.. j,,
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13.
The package authorized by this certificate is hereby approved for use under the f
general license provisions of 10 CFR $71.12.
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14 Expiration date:
Septenber 30, 1990.
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REFERENCE Chen-Nuclear Systens, Inc. application dated August 26, 1985.
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FOR THE U.S. NUCLEAR REGULATORY C0ftISS10N
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E Charles E. MacDonald, Chief 5
Transportation Certification Branch R
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Division of fuel Cycle and fiaterial Safety, fdSS w
Date: SEP 111985
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f ;j NUCLEAR REGULATORY COMMISSION WASmNGTON, D. C. 20555 e..av.
Transportation Certification Branch Approval Record Model No. CNS 21-300 Package Docket No. 71-9096 By application dated August 26, 1985, Chem-Nuclear Systems, Inc. requested renewal of Certificate of Compliance No. 9096 for the Model No. CNS 300.
A consolidated application was submitted which incorporated the previous application dated April 14, 1980, as supplemented June 28, 1983.
A review of the consolidated application confirmed that all pertinent supplement infomation and the application dated April 14, 1980, had been incorporated into the consolidated safety analysis report. The applicant has made a revision. Revision C, to Drawing No.114-D-0006 i
which provides for an optional single lift point on the load distribution pallet. This change has no effect on the safety function of the load distribution pellet.
The applicant stated that additional units of the packaging will not be 4
fabricated and, therefore, the safety analysis report does not contain a section on acceptance testing.
Accordingly, the certificate of compliance has been conditioned to preclude the fabrication of additional packagings.
Based on' the staff's review of the consolidated safety analysis report and the conditions stated in the certificate of compliance, the staff concludes that the requirement for renewal of the certificate of compliance has been satisfied.
a Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NHSS SEP1 1 M Date:
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