ML19210E647
| ML19210E647 | |
| Person / Time | |
|---|---|
| Site: | 07106678 |
| Issue date: | 09/29/1977 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUDOCS 7912050461 | |
| Download: ML19210E647 (4) | |
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U.S. NUCLE AR RECULATORY CovMts$10N C4sB -
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, l' j73I CERTIFICATE OF COMPLI ANCE D**D D'3' VI gg Fos Rad.oactive Materiais Pa:kapes 1.fal Cetif.cate Number 1.f o) Revision No.
1 (c) Packre identif. cation No.
1.(d) Pases No 1.f el Total No. Page v
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USA /6678/B I
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- 2. PRE AMBLE 2.tal This cevtificate is iuved to satisf y Sections 173 393a.173.394. s73 395. ard 173 395 of the Department of Tramportation nata,dow Mateviain Regulations (49 CF R 170189 and 14 CFR 103) and Sect.ons 146-19-10s and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CF R 146-149). as amendsd.
C of Title 10. Code of The packaging and contents described in stem 5 belove, rneets the safetv. standards set forth in Subpar:
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Federal Regulat.ons. Part 71, **Packag;ng of Rad.oactive Materials for fransport and Transportation of Radioactive Material Under Certain Conde* ions.
' This certificate does not relieve the cort gnor from compt.ance with any reouirement of the regulations of the U.S. Department of i
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Transportat.on or other applicable segulatory agencies. including the go.ernment of any country through or anto which the package s
wealt be transported.
- 3. This certifecate is suved on the basis of a safety analysis report of the package desigri or applicatiore-3.(s)
Prepared by (Name and address):
3.(b)
Title and identification of report or spotication:
E.1. du Pont de Nemours l Company E.I. du Pont de Nemours 2 Company Report No. DPSPU-74-124-5, April 1975.
p Savanah River Plant Ai ken South Carolina 29801 e
- 3. sci oociei No. 71-6678
- 4. CONDITIONS This cart.f.cate is conditionaf upon the fulfi!!.ng of the requirements of Subpart D of 10 CFR 71. ar applicable, and the conditions specified iri item $ belove.
- 5. Descr pt.on of Pacmag.ng and Authorsted Contents. Model Number. Fassile Clats. Other Conditions, and
References:
(a) Packaging (1) Model No: LP-50 (2) Description Packaging for large quantities of tritium. The containment vessel is a nominial 50 liter 304L stainless steel vessel fitted with stainless steel vacuum valve assembly. The containment vessel is 13-5/8-inch 0.D. by 25 inches high with 0.078 inch wall thick-The containment vessel is held within a closed aluminum ness.
bucket with a 14 inch 0.D., 30 inches high and minimum 15/64 inch walls. The aluminum bucket is centered and supported within a 16-gage, 23-1/2 inch 0.D. by 40 inch steel drum using celotex insulation. The drum is closed using a bolted locking r-ring. The package gross weight is 260 pounds.
(3) Drawings The packaging is fabricated in accordance with DuPont
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Drawings Nos.:
S5-2-5733, Rev. 7; S5-2-5734, Rev. 9; 55-2-5735, Rev.1; S4-2-596, Rev. O, 55-2-186, Rev. 46; SS-2.187e i
Rev. 22; and $5-2-147, Rev.13; and Figure 4 of DuPont Report i
No. DPSPU-74-124-5, April 1975.
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Page 2 - Certificate No. 6678 - Revision No. 0 - Docket No. 71-6678 (b) Contents (1) Type and form of material
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Tritium in mixture with other gaies.
4 (2) Maximum quantity of material per package L-Not more than 75,300 cm3 of tritium at STP (1 atm, 25*C), and a maximum activity of 193,500 Curies.
6.
The maximum internal fill pressure in the i-imary containment vessel shall not exceed 24.2 " psia at 25*C (77'F).
7 Acceptance, maintenance and use of the package shall be in accordance with the procedures and requirements of Chapters 6 and 7 of DuPont Report No. DPSPU-74-124-5, April 1975.
8.
The leak test described in paragraph 7.1.3 of DuPont Report No. DPSPU-124-5, April 1975 shall be repeated after the third use of each packaging.
In addition, a primary containment vessel before use of a packaging for i
shipment, shall have been tested in accordance with the above leak test (paragraph 7.1.3, DPSPU-124-5) within the preceeding 12 month period.
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B.
Expiration date: October 31, 1982.
Reference E.I. duPont de Nemours and Company Report No. DPSPU-124-5, April 1975.
FOR THE U.S. NUClF%R REGULATORY COMMISSION l
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Charles E. MacDonald, Chief Transportation Branch l
Division Fuel Cycle and i
i Material Safety
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SEP 2 91977 Date:
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', i DEPARTMENT OF TRANSPORTATION R'2 SEARCH AND SPECI AL PRC'.iRAMS ADMINISTRATION lf j
WASHINGTON. D.C. 2o390 e
f.5 2 '. f U IAEA CERTIFICATE OF COMPETENT AUTHORITY 8tEFEst TO:
Type B Radioactive Material Pacida'e. Design *,'I lC 44 l
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.g Certificate Number USA /6678/B( )
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(Revision 1)
Y, Y. 5lCil0N This establishes that the packaging design described herein, when loaded with the authorized radioactive contents, has been certified by the
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National Competent Authority of the United States as meeting the regulatory requirements for Type B packaging for radioactive materials as prescribed in IAEA Regulatignsandinaccordancewith49CFR99173.393b 1
and 173.395(c)(2) of the USA Regulations for the transport of radioactive materials.
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Package Identification _- Model No. LP-50.
II.
Packaging Description - Packaging authorized by this certificate consists of a nominal 50 liter 304L stainleis steel containment vessel measuring 13-5/8 inches outside diameter by 25 inches in height with a
.078 inch wall thickness which is equipped with a stainless steel vacuum valve assembly and is fitted into an aluminum drum measuring 14 inches in outside diameter by 30 inches in height with a minimum wall thickness of 15/64 inch. The aluminum drum is centered and supported by celotex insulation within a 16-gauge, 23-1/2 inches outside diameter by 40 inches steel drum which is closed with a bolted locking ring. Package gross weight is 260 ; ounds.
III. Authorized Radioactive Contents - The authetized.:ontents cogsist of tritium in mixture with other gases with a maximum of 75,300 cm of tritium at STP and a maximum activity of 193,500 curies. Fill pressure in the primary containment vessel shall not exceed 24.2 psia at 25 C.
IV.
General Conditions -
Each user of this certificate must have in his possession a.
a copy of this certificate.
b.
Each user of this certificate, other than Edlow International Company, Washington, D.C., shall register his identity in writing to the Office of Hazardous Materials Regulation, Materials Transportation Bureau, U.S. Department of Transportation, Washington, D.C.
20590.
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1497 319 14622
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Page 2 Certificate Number USA /6678/B( ), Revision 1 This certificate does not relieve any consignor or carrier c.from compliance with any requirement of the Government of any country through or into which the package is to be transported.
Marking and Labeling - The package cust also bear the marking
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V.USA /6678/BC ) as well as the other marking and labels prescribed by the USA Regulations.
Expiration Date - This certificate, unless renewed, expires on VI.
October 31, 1982.
This certificate is issued in accordance with the requirements of the 12, 1979, IAEA and USA Regulations and in response to the September petition by Edlow In*.ernar.ional Company, and in consideration of the associated information provided in U.S. Nuclear Regulatory Commission Certificate of Compliance No. 5678, Revision 0 (Appendix A).
Certified by:
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R. R. Rawl Designated U.S. Competent Authority for the International Transportation of Radioactive Materials Of fice of Hazardous Material-Regulation Materials Transportation Bureau U.S. Department of Transportation
" Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials,1967 Edition" published by the International Atomic Energy Agency (IAEA), Vienna, Austria.
100-199, USA.
2 Title 49, Code of Federal Regulations, Parts Original issued in response to the Dececber 8, 1977, petition by Edlow International, Washington, D.C.
Revision 1 issued to extend expiration date.
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