ML19250C216
| ML19250C216 | |
| Person / Time | |
|---|---|
| Site: | 07105740 |
| Issue date: | 01/19/1979 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19250C211 | List: |
| References | |
| 14510, NUDOCS 7911230026 | |
| Download: ML19250C216 (2) | |
Text
s.
U.S.CEPARTMENT OF ENERGY ooE Form c'.*413 (11 771 CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages la. Certificate Numoer
- 10. Revision No.
1c. Pacnage Icentification No.
Id. Page No.
Ie. Total No. Pages.
5740 1
USM5740/3L (DOE-OR) i
?
- 2. PREAMBLE 2a.
This certificate is rssued to satisfy Sections 173.393a.173.394,173.395, and 173.396 of the Department of Transoortation Hazardous Ma'enais Regulations (49 CFR 170-189L 2b.
The pecmaging and contents described en item 5 below, meets the safety standaros set ' orth in Succart C of T:tle Io. Code of Feoeral Requiations, Part 71," Packaging of Radioactive Material for Transoort and Transportation of Radioactive Material Under Certain Conditions.
2c.
This certificate does not relieve the consignor from comoniance with any requirement of 'he regulaticns of tne UJ5. Cepartment of Trar'sportation or other applicacie requiatory agencies, incttding the governrnent of any country througn or into wnicn the package will be transported.
- 3. This cartif.cate s tssued on the cases of a safety analysis report of the package design or application-(1) Prepared by fName and Jadressl:
(2) Title and Identification of report or aposication:
(3) Cate:
(a) The IRU Ten-Ion Californium Shipping (a) Nov. 1971 Oak Ridge National Laboratory Container, Report ORNL-TM-3505.
Post Office Sox I (b) Sar,ety Analysis Report for Packaging (b) To be Oak Ridge, Tennessee 37830 (SARP) of the Oak Ridge National Lab-issued oratory JRU Californium Shipping Con-
- 4. cCNDITICNS Cainer, Report ORNL-5409, Rev. 1.
l This certificate is conditional upon the fulfilling of the reQuwements of Sucoort O of 10 CF R 71, as aopiscacie, and tne conditions specified in item $ Detow.
- 5. Description of Packaging and Authorized Contents, Moces Numcer. Fissue Class, Ctner Conditions,and
References:
(a) Packazing (1) Model: ORNL TRU Californium Shipping Container (2)
Description:
A 304L stainless steel encased concrete shipping cask The outer shell consists of two s-in. thick, 66-12. diameter hemispherical heads joined by a 6-in. cylindrical section. The cylindrical cavity has a 1-in. thick stainless steel wall and is 3-in. diamater x 6-in. long.
Shield-ing consists of 30-in. of Blackburn limonite concrete having a density of
%175 lb/ft3 Upper and icwer level ball valves located at the end of concrete-filled plugs define, isolate, and seal the cavity.
Both of.hese plugs which i
utilize 0-ring seals are bolted in place and are protected with a gasketed cover plate.
Fusible plugs in the cover places and the shell will melt to permit steam release in event of thermal exposure.
The top ball valve and plug may be replaced by other plugs for nultiple source shipments. Sources are contained in DOT Specification 2R or special-form containers.
} J 0.D' 7n~
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The cask is sounted onto a 1-in. thick steel base place by eight steel 2i-in.
NPS Schedule 40 pipe struts. The cask is transported cn its own special trailer.
- he ercqs ve12ht of the cisk is 23.300 lb.
6a. 3 ate of Iss6arce:
January 11, l)M l 6b. Exoiration Cate:
FC A THE U.S. CEPARTMENT CF ENERGY 7a. Address (of CCE isswng C"ical 7b. Signature, Name, a,o T;tle (of CCE Accrorrng Officiail W7 P i[M*
U. S. Department of Energy
'41.
am H. Travis, Director Post Office Box E Safe..y a Environmental Ccatrol Division Oak Ridge, Tennessee 37830 1 M10 7911230 C N
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Certificate 5740, Revision No. 1 2
(3) Drawings:
The package and special trailer are constructed la accordance with Oak Ridge National Laboratory (ORNL) Drawings M-11230-EN-001-D through 008-D, and 017-D, M-12166-CD-019-D and M11369-EM-OllE and 012E.
(b) Contents (1) Type and Form of Material.
The contents consist of isotopes of Americium (Am), Curium (Cs), Berkelium (Sk), Californium (Cf), Einsteinium (ES), and Fermium (Fm) as a solid (metal, oxide, oxysulfate, or dry salt) that is contained in a DOT Spec 1fication 2R inner container (s) or in a special form capsule (s).
(2)
Maxi =um Quantity of Material Per Package.
3g. (large quantity).
(3) Other Limitations.
(1) Maximum heat load - 5'4.
(2) External radiation dose rates - limited to DOT regulations, 49 CFR 173.393.
!335 120 14-10
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