ML20140C917
| ML20140C917 | |
| Person / Time | |
|---|---|
| Site: | 07105026 |
| Issue date: | 06/11/1984 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20140C914 | List: |
| References | |
| NUDOCS 8406190633 | |
| Download: ML20140C917 (4) | |
Text
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- _4ra"m'awsrM".ntsmramersicareramrmemarmmwanerwemoranrucwwurmanananmanaq l l hSC FD= 618 U.S. NUCLEAR REGULATORY COMMISSION w
CERTIFICATE OF COMPLIANCE y to Cr A "
FOR RADIOACTIVE MATERIALS PACKAGES
' 1 a CERT 4lCATE NUMBER D REVISION NUMBER C PACKAGE IDENTIFICATION NUVBER d PAGE NUMBER e TOTAL NUVBER DAGES :
5026 11 USA /5026/B( )
1 3
2 PREAMBLE Thr5 CerttfeCate is #55ued to certif y that the packaging and Contents described in item $ below, meets the apphCable Safet y Standards set forth in Title 10. Code a
of Federal Regulations. Part 71. Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions "
D Thel Certificate does not reheve the Consignor from Compliance with any requiremerit of the regulations of the U S Department of Transportation or other apphCaDie regulatory agencies. includeng the government of any Country thrt. ugh or into wnich the package will be transported.
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EP cL Chen-Nuclear Syste s, Inc.
Chem-Nuclear Systems, Inc.
220 Stoneridge Drive application dated November 19, 1979,
@ Columbia, SC 29210 as supplemented.
51 71-5026 c DOCKET NUMBER 4 CONDITIONS This Certificate is Conditional upon fulfilhng the requirements of 10 CFR Part 71. as appisca~ ole and the Conditions specified below
'5 i
(a)
Packaging
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'Hi (1)
Model No.:
g (2)
Description The packaging is a steel-encased, concrete shielded shipping cask.
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The cask is 94-1/4 inches in diameter by 103-3/4 inches in length.
jN Reinforced concrete occupies the 7-inch annular space between the in shells and the two base plates.
The lid is a 4-3/4 inches thick j
laminated steel cover held in place by 32, high strength 1-1/4-inch
!g diameter bolts. A silicone 0-ring is used to seal the joint between
!E the lid and the cask body.
The outer shell and base plate are 1/4-
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inch thick, rhile inner shell and base plate are 2 inches thick.
The cask is reinforced at the top and bottom with steel rings and is j
equipped with lif ting lugs. The lid is provided with two access i p ports.
Gross weight is about 71,000 pounds.
31 (3)
Drawings j
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The package is constructed in accordance with the following ATCOR, j
Inc. Drawing Nos.:
1000-0-0049; 0146-B-0004, Rev. E; 0146-B-0009;
'y 0146-0-0025, Rev. A; 0146-D-0020-1, Rev. A; and 0146-C-0018, Rev. E.
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(b) Contents
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(1) Type and form of material j
N (i) Byproduct material in the form of dewatered resins, solids, or y
solidified waste contained within secondary container (s).
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j (ii)
Radioactive material in the form of activated reactor components N
packaged in secondary container (s).
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8406190633 040611 3
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xxn&IElETx'~ xxxiaraxi'ii?naarM2fiWx" xrkw&mmMd!!%32';LM CONDITloNS (contmue t)
! Page 2 - Certificate No. 5026 - Revision No.11 - Docket No. 71-5026 s
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! 5.
(b) Contents (continued) l (2) Maximum quantity of material per package I
i Greater than Type A quantity of radioactive material, not to exceed 20 i
thermal watts and 23,000 pounds including weight of the contents, l
secondary container (s) and shoring.
The contents may include fissile materials provided the mass limits of 10 CFR 571.53 are not exceeded.
! 6.
The dose rate from the loaded cask shall not exceed 10 mrem /hr at six feet from the surface of th'e cask.
k l 7.
The access plugs shall be appropriatbly: plugged and sealed prior to transport.
8.
Shoring shall be placed between the secondary container (s) and the cask cavity j
to prevent movement during accident conditions of transport.
l i 9.
For all packages containing water and/or organic substances which could radiolytically i
generate combustible. gasses and which the radioactivity concentration per gram l
j is greater than that permitted for low specific activity material, a determination must be made by tests and measurements of a representative package such that the following criteria-are met over a period of. time that is twice the expected i
l shipment time:
[
(1) The hydrogen generated mst be limited to a molar quantity that would be no more than 5% by volume (or equivalent limits for other inflammable gases) l i
of the secondary 3 container gas void if present at STP (i.e., no more than 0.063 g-moles /ft at 1.4.7 psia.and 70*F); or l
(ii) The secondary container and' cask cavity must' b'e inerted with a diluent to l
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assure that oxygen must be limited to 5% by volume in those portions of the j
j package which could have hydrogen greater than 5%.
i F!
For packages to be delivered to a carrier for transport, the secondary container must be prepared for shipment in the.same manner in which determination for gas
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,l generation is made.
Shipment period begins when the package is prepared (sealed) and must be completed within twice the expected shipment time.
l Shipment of radioactive waste solidified in asphalt is not authorized.
f 1g l 10.
Prior to each shipment, the packaging lid silicone 0-ring shall be inspected.
i l'
j The 0-ring shall be replaced with a new silicone 0-ring if inspection shows any N
defects or every six (6) months, whichever occurs first.
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11.
Packages fabricated after July 31, 1983, shall be constructed of A-516, Grade 70
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carbon steel instead of A-36 and A-516, Grade 60 carbon steels.
E 12.
The package authorized by this certificate is hereby approved for use under the i
general license provisions of 10 CFR 571.12.
l 13.
Expiration date:
January 31, 1985.
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[k l CONDITIONS (continued)
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l Page 3 - Certificate flo. 5026 - Revision No,11 - Docket No. 71-5026 l
,' R REFERENCES iR '
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't Chem-Nuclear Systems, Inc. application dated November 19, 1979.
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l Supplements dated:
April 14 and June 17, 1983; ana January 18, 1984.
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'E FOR THE U.S. NUCLEAR REGULATORY COMMISSION lE E
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- Charles E.,MacDonald, Chie
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" Transportation Certification Branch
- E Division of Fuel Cycle and jf f,
Material Safety, NMSS.
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JUN 111984 E
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- Tra ns po r t a ti on Ce rti f i ca ti,on, 0,ra nch Approval Record" flodel flo. CNS 14-190 fackage,.
Docket No. 71-5026 Since radiation effects for asphalt are limited'at this ti.ne and the requirements of 571.43(d) for asphalt have not been addressed, Condition No.12 has been modified to prohibit the shipment of radioactive waste solidified in asphalt.
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS JUN1 1 y Date:
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