ML20009H137
| ML20009H137 | |
| Person / Time | |
|---|---|
| Site: | 07109851 |
| Issue date: | 07/10/1981 |
| From: | Travis W ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20009H136 | List: |
| References | |
| 19398, NUDOCS 8108060104 | |
| Download: ML20009H137 (3) | |
Text
1 s
'u U.S. QEPARTMENT CF ENERGY (11-77)
CERTIFICATE OF COMPLIANCE I
- I For Radioactive Materials Packages la. Certificate Nurnoer i Ib. Revision No.
Ic. Pacxage identification No.
Id. Page No.
le. Total No. Fsges.
9851 l
1 USA /9851/BLF (DOE-ORC )
1 2
2.PREAM8LE 2a.
This certificate is issued to ratisfy Sections 173.393a,17334,173.335, and 173.396 of the Department of Transportation Hazardous Meterials Regulations (49 CFR 170-189).
2b.
The packaging and contents described in item 5 below, meets tne safety standards set forth in Suopert C of Title 10. Code of Federal Regulations. Part 71," Packaging of Radioactive Material for Transport and Transportation of Radioactive Material Under Cartain Conoitions."
2c.
This certificate does not resieve the consignor from compliance with any requirement ef the regulations of the U.S. Department of Transportation or other aophcaote regulatory agencies, including tne government of any country througn or into whicn the packasi.
will be transporters.
- 3. This certificate is issued on tne basis of a safety analysis report of the package design or application-(1) Prepared by (Name and addressl:
(2) Title and identification of report or application:
(3) Date:
Neverber 1977 Oak Ridge National Laboratory Safety Analysis Report for Post Office Box X Packaging for the ORNL Lithiun Oak Ridge, TN 37830 Hydroxide Fire and Impact Shield Recort No.-
ORNL/ENG/'IM-8
- 4. CON 0lTIONS This certificate is condituanai upon the fusfilling of the reouirements of S coart O of to CFR 71, as applica' le, and the conditions specified c
in item 5 below.
- 5. Description of Packaging and Authorized Contents.Model Numoer. Fissile C: ass.Other Conditions, and Ref erences:
l (a) Packaging:
(1) 2el: Lithium Hydroxide Fire and Brpact Shield I
(2)
Description:
Packaging for irner Type A and DOT Specification 55 packages to pennit transport of Type B and lan;;e qualtities of radioactive materials and 2.imited quantities of fissile materials, which are cmtained within inner special fonn encapsula-tion or DOT Specification 2R containers. The irner vessels will be blocked to minimize movement during transport.
The inner cavity of the shield is a cylincier 27 in. diameter x 26 in. high.
The outer shell is 36 in. diameter x 30-3/4 in, high.
The lid is 4-5/8 in, thick. The shield is fabricated frun 1/8 in. thick 304-L stainless steel with the 4-1/4 in. noninal space between inner and outer clad-ding being filled with LiOH H O crystals. The outer surface of the shield has 2
92 vertical cooling fins. The flanged closure is h71d in positicn by tvienty l-inch alloy steel bolts.
The gross weight of the package.is 4,000 lbs.
6a. Date of lisuance:
July 10. 1981 l 6b. Expiration Date:
FOR THE U.S. DEPARTMENT OF ENERGY la. Address (of DOE Issuing Offical 7b. S,gnature, Name.and Titte (of COE Aoprawng 0fficiai)
U.S. Department of Enengy J
LO*II' m M W A P.O. Box E William H. Travis, Director Oak Ridge, Tennessee 37830 Safety & Environmental Control Division 8100060104 810714 PDRADOCK07109g C
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. Page 2 - Certificate of Ccmpliance, No. USA /9851/BLF (DOE-OR), Rev.1 l
(3) Drawirgs:
The overpack is described and fabricated in accordance with Unicn Carbide Corp.,
Nuclear Division, Oak Ridge Natimal Laboratory drawings:
~
l D-RD-2760-D thruxjh D-RD-2764-D and X3D-1091-lO9 (b) Contents:
l (1) Type and form of material:
Any' solid, larg quantity of radioactive materials, fissile and nonfissile, meeting special form or packaged in DOT Specificaticn 2R inner container ard whose decay heat load does not exceed 300 watts.
(2) Extemal radiaticn levels will be within the levels prescribed in DOT Regula-tions, Title 49.
(3) Specific limits of ccntents:
(i) 5 g of:
242 244 245 247 249 251 Cf, or Cf (ii) 100 g of:
235 233 U or U.
(c) Fissile Class:
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e w
m amm e a e,.
w a.
y
-p M*4%
M e-W a 4e=e
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a f
LiOH Fire and Imoact Shield General 1.
Section 1.7 fully describes the inner containers used for normal form i
shipments. The analysis of the inner container performance under both nor-mal conditions and accident conditions, demonstrate that the inner con-tainers has no detectable leak.
2.
Attached is a drawing of the gamma shield.
t-Containment l
1,2,3 - The ar.alysis of the inner containers demonstrate that the normal and i
accident ' conditions will not cause a detectable leak.
If no detectable leak will be present, no specific containmr.nt criteria is needed.
4
- Plutonium is no longer shipped in this cask. The report will be revised 5
to indicate this.
I l'
Testing and Maintenance l
1.
All special form or DOT or containers are leak tested before shipment. The test is the air bubble, vacuum and glycol described in ANSI standard i
N14.5-A3.6. _ Attached is a copy of the procedure used.
i Shielding 1.
All containers are checked prior to shipment to insure radiation levels are within allowable limits. Due to the presence of LiOH shield, no reduction in gamma shielding is expected as a result of accident conditions.
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