ML20054H189
| ML20054H189 | |
| Person / Time | |
|---|---|
| Site: | 07106722 |
| Issue date: | 06/15/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20054H187 | List: |
| References | |
| NUDOCS 8206230089 | |
| Download: ML20054H189 (4) | |
Text
Form NRC418 U.S. NUCLEAR REGULATORY CoMMISSloN
(
CERTIFICATE OF COMPLIANCE 10 C R For Radioactive Miterials Pickages 1.(1) Certificate Number 1.(b) Revision No.
1.(c) Package Identification No.
1.(d) Pages No. 1.(e) Total No. Pages 6722 5
USA /6722/A 1
3
- 2. PRE AMBLE
~2.fa)
This certificate is issued to satisfy Sections 173.393a,173.334,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended.
2.!b)
The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, ** Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions."
2.(c)
This certificate does not relieve the consignor from compliance with any requirament of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
- 3. This certifieste is issued on the basis of a safety analysis report of the package design or applicatiort-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
Tennessee Valley Authority Tennessee Valley Authority application dated 500C Chestnut Street, Tower II July 9,1975, as supplemented.
Chattanooga, Tfl 37401
~
71-6722; 3.fc)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable. and the conditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Class, other Conditions, and
References:
(a)
Packaging (1) Mode'l tio.:
BS-33-180 (2) Description The shipping cask is a cylindrical steel weldment with overall dimensions of 84 inches in diameter and 97-1/4 inches in length.
The effective cavity is 76-1/2 inches in diameter by 79-1/4 inches long. The outer shell it fabricated of concentric layers consisting of three, one-inch thick and 1/2-inch thick carbon steel plates. The inner half-inch thick shell is separated from the one-inch thick shells by a 1/4-inch thick asbestos sheet. The flange is three inches thick, with 36 tapped holes and a groove to acconmodate a silicone 0-ring. The top l
cover is secured to the flange ring by 36, ASTM-A-320, Grade L7 1-1/2-inch bolts. A 10-inch deep steel impact limiter is mounted to the top cover to act as a shock absorber. The cask is mounted to a tie-down frame by sixteen,1-1/4-inch high strength steel bolts.
Other cask features include a drain line, access port to the inner container (s) and a reinforcing steel shell to protect the c_ask seal.
Threaded access plugs are installed on the top of the ' liner.
A bottom side drain is also provided. Maximum gross weight is approximately 51,100 pounds.
I 8206230089 820615 PDR ADOCK 07106722 C
r Page 2 - Certificate No. 6722 - Revision No. 5 - Docket No. 71-6722 5.
(a)
Packaging (continued)
(3) Drawings The packaging is c'onstructed in accordance with the following ATCOR
^
Inc. Drawing Nos.: 0568-C-0024, Rev. E; 0568-D-0022, Rev. E; 0568-D-0023, Rev. D; 0568-C-0026, Rev. B; 0568-A-D013, Rev. B; and 0568-D-0002, Rev. K.
(b) Contents (1) Type and form of material Solids or. solidified waste, meeting the requirements for low specific activity radioactive material as defined in 10 CFR 571.4(g).
(2) Maximum quantity of material per package Greater than Type A quantities of radioactive material with the weight of the contents (including containers and shoring) limited to 18,000 pounds and 20 thermal watts.
6.
Dunnage must be provided in the shipping cask cavity sufficient to prevent significant movement of the inner container (s) relative to the outer packaging under normal conditions of transport.
7.
Operating procedures must assure that:
(i)
All threaded pipe plugs in the cask are sealed using an appropriate sealant.
(ii)
The space between the inner container (s) and cask cavity must be dry prior to delivery to a carrier for transport.
8.
Prior to each shipment, the package lid seal must be inspected.
The seal must be replaced with a new silicone 0-ring if inspection shows any defects or every twelve (12) months, whichever occurs first.
9.
All eight (8) lifting shackles will be shrouded by the appropriate covers prior to transport to prevent its use as tie-down devices.
- 10. The package authorized by this certificate must be transported on a motor vehicle, railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel assigned for the sole use of the licensee.
- w.
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c-r.w.p 7
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a Pace 3 - Certificate No. 6722 - Revision No. 5 - Docket No. 71-6722 11. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
12.
Expiration date: November 30, 1985.
1 REFERENCES Tennessee Valley Authority application dated July 9,1975.
Supplement dated: February 10, 1977.
ATCOR Supplements dated: October 29 and November 5,1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
= =Y Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
JUN 151982
U.S. Nuclear Regulatory Commission Transportation Certification Branch Approval Record Model No. BS-33-180 Packaging Docket No. 71-6722 By application dated May 2.1, 1982, Tennessee Valley Authority requested deletion of Items 5.b.2(i) and 6 of Certificate of Compliance No. 6722, Revision No. 4.
These approval conditions pertain.to specifying a specific liner or DOT Specification containers within the package.
Because the package had been downgraded from a Type B to a Type A package, the applicant did not believe it is necessary to specify the inner containers. Also, deletion of the maximum curie limit is requested.
We are in agreement with the applicant and have deleted the specified inner containers from the package approval. Because the inner containers, are no longer specified, we are requiring replacement of the seal at least every twelve (12) months. This is in addition'to the requirements of 10 CFR 571.54. The curie limit need not be specified because the package is limited to LSA material and a maximum heat load has been specified and considered in the analysis.
Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS JUN 151982 Date:
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