ML19262A032
| ML19262A032 | |
| Person / Time | |
|---|---|
| Site: | 07106568 |
| Issue date: | 10/05/1979 |
| From: | Calhoun J TENNESSEE VALLEY AUTHORITY |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 14348, NUDOCS 7910260167 | |
| Download: ML19262A032 (2) | |
Text
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PoA oby TENNESSEE VALLEY AUTHORITY gg CH ATTANOoGA. TENNESSEE 374ot 716 Edriey Yuilding 6
October 5,1979
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' } C g,{ g C N n-Mr. Charles E. MacDonald Chief, Transportation Branch Division of Material and Fuel
{
Cycle Licensing U.S. Nuclear Regulatory Commission
,j Washington, DC 20555 I
Dear Mr. MacDonald:
Under the conditions set forth in Certificate of Compliance No. 6568 (Revision O), Tennessee Valley Authority (IVA) shipping cask Model No., LL-60-150 is licensed for shipment of radioactive material contained in a secondary, right circular steel cylinder disposable liner of 150 cubic foot capacity and constructed in accordance with TVA Drawing No.
CH-M-2081, Rev. 2, or ATCOR, Inc., Drawing No. 0568-D-0002.
It is requested that a revision to this certificate of compliance be issued to also permit this shipping cask to be used for shipment of radioactive material in smaller disposable leak-tight steel liners, provided dunnage is placed betwean the secondary container and the inner surface of the cask to prevent rovement during transport. This request is being made
' to allow the use of this package by General Public Utilities Service Corporation for transportation of radioactive materials frem their Three Mile Island Nuclear Station.
The analysis under which the LL-60-150 was licensed took no credit for the structural integrity of the secondary liner in demonstrating analytically that the shipping cask would remain leak-tight after hypothetical accident conditions. Since the proposed revision would reduce the total weight of the package when liners smaller than 150 cubic feet are used, the only effect on the cask analysis would be to increase the degree of conservatism in the results.
The specific changes requested in Certificate of Compliance No. 6568 are as follows:
1.
Subparagraph 5. (a) (3), revise to read:
The shipping cask is constructed in accordance with the following ATCOR, Inc., Drawings:
9568-B-0005, Rev. H; 0568-C-0008, Rev. E; 0568-B-0010, Rev. E; 0568-B-0016, Rev. D; 0568-B-0018, Rev. A; 0568-B-0025; and 0568-R-0001, Rev. J.
The secondary containers are constructed in accordance with ATCCR, Inc., Drawing No.
0568-D-002, TVA Drawing No. CH-M-2081, Rev. 2, Department of Trans-portation (DOT) specifications, or other container designs, as needea-voicesm c 7
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2 Mr. Charles E. MacDonald October 5, 1979 2.
Subparagraph 5. (b) (1), revise to read:
(1)
TYPE AND FORM OF MATERIAL (i)
Process solids, either dewatered, solid, or solidified in secondary containers, or (ii)
Solid nuclear components in secondary containers as required.
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3.
Add subparagraph 6.(iv) to read as follows:
Dunnage shall be provided in the shipping cask cavity sufficient to prevent significant movement of the secondary container (s) relative to the outer packaging under nor:xal or accident conditions.
We would appreciate your immediate attention to this request as it directly impacts the Three Mile Island recovery efforts.
If you have any questions, please contact Ben Rogers at (615) 755-3558 or FTS 854-3558 in Chattanooga.
Very truly yours, TE.
SSEE VALLEY AUTHORITY a
LP -
( J, R. Calhoun Y1 rector of Nuclear Power i
I 1215 079 1G313
.