ML19339A181
| ML19339A181 | |
| Person / Time | |
|---|---|
| Site: | 07106568 |
| Issue date: | 10/24/1980 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19339A178 | List: |
| References | |
| NUDOCS 8011030207 | |
| Download: ML19339A181 (3) | |
Text
G Form NRC418 U.S. f4UCLEAR REGULATORY COMMISSloN CERTIFICATE OF COMPLIANCE 10 c R71 For Radioactive Materials Packages 1.tal Certificate Nember 1.(b) Revision No.
1.(c) Package identification No.
1 (d) Pages No. 1.(e) Total No. Pages 6568 2
USA /6568/B( J _
1 3
- 2. PREAMBLE 2.f a)
This certificate is inued to satisfy Sections ?73.393a.173.394.173.39s. and 173.396 of the Oeoartment of Transoortation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Ceoartment of Transoortation Dangerous Cargo,es Regulations (46 CFR 146-149). as amended.
2.lb)
The packaging arb contents describoo in item 5 below, meets the safety standards set forth in Subpart C of Title 10. Code of Federal Regulations. Part 71, "Pacmaging of Radioactive Materiais for Transport and Transoortation of Radioactive Material Under Certain Conditions /*
2.(c)
This certificate does not relieve the consignor from comoiiance with any requirement of the regulations of the U.S. Oeoartment of Transportation or other soolicaole s egulatory. agencies including the government of any country through or into wnich the package well be transported.
- 3. This certificate is is.aed on the basis of a safety analysis report of th package design or aposication-3.la)
Prepared by (Name and address):
3.(b)
Title and' identification of report or acotication:
Tennessee Valley Authority Tennessee Valley Authority application dated 500C Chestnut Street, Tower II August 16, 1976, as supplemented.
Chattanooga, TN 37401 3.lc)
Doctet No. 7].gggg 4 CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart O of 10 CFR 71. as acclicaolo, and the conditions specified in item 5 betow.
- 5. Oescriotion of Packaging and Autnorized Contents. Model Numoer. Fissaie Class. Ctner Conditions, and
References:
(a) Packaging (1) Model No.:
LL-60-150 (2) Description The cask is cylindrical in shape 93 inches long and 82.5 inches in diameter.
Lead shielding, 3.1/2 inches thick, is encased within the inner and outer steel shells that are welded to a laminated steel base plate assembly.,
The cover is a steel plate assembly secured to the top flange by 36 steel bolts.
Encircling the top of the cask is a partial length steel shell of 1/2 inch thickness.
Silicone 0-rings provide seals at the top cover and at all plugs.
The inner container is a right circular steel cylinder with a capacity of 150 cu. ft.
The total weight, when loaded, is approxi-mately 73,000 pounds.
(3) Drawings j
The packaging is constructed in accordance with the following ATCOR Inc.
Drawing Nos.:
0568-B-0005, Rev. H; 0568-C-0008, Rev. E; 0568-B-0010, Rev. E; 0568-B-0016, Rev. 0; 0568-B-0018, Rev. A; 0568-B-0025; 0568-R-0001, Rev. J.
I l
8011030 RO7
Page 2 - Certificate No. 6568 - Revision No. 2 - Docket No. 71-6568 4
5.
(b) Contents (1) Type and form of material Process solids, either dewatered, solid, or solidified, capable of compressing at least 30% on impact in secondary containers constructed in accordance with:
ATCOR, Inc. Drawing No. 0568-D-002; TVA Drawing No. CH-M-2081, Rev. 2, or 49 CFR 6178.350 (Specification 7A).
(2) Maximum quantity of material per package The package contents and secondary containers shall be limited to 12,500
.l pounds with a curie content not to exceed 1,300 curies, and the decay heat not to exceed 20 watts.
6.
Operating procedures shall be followed to assure that:
(i) All threaded pipe plugs in the cask and liner are sealed, using an appropriate sealant.
(ii) The liner (drums) is inspected and/or tested to assure leak tightness.
(iii) The space between the liner (drums) and cask cavity is dry prior to delivery to a carrier for transport.
(iv) 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 normal or accident conditions.
(v) Prior to each shipment the silicone 0-ring lid gasket shall be inspected.
This gasket shall be replaced if inspection shows any defects or every twelve (12) months, whichever occurs first.
7.
The external dose rate shall not exceed 125 mrem /hr at 3 feet from the surface of the cask at the time it is delivered to a carrier for transport.
8.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CCR $71.12(b).
9.
Expiration date:
October 31, 1981.
o Page 3 - Certificate No. 6568 - Revision No. 2 - Docket No. 71-6568 REFERENCES Tennessee Valley Authority application dated August 16, 1976.
Supplement dated: October 8, 1976; October 5, 1979; and October 23, 1980.
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION 4
Charles E. MacDonald, Chief Transportation Certification Branch
~
Division of Fuel Cycle and Material Safety OCT 2 4 20 Date:
4
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