ML20027C050
| ML20027C050 | |
| Person / Time | |
|---|---|
| Site: | 07109964 |
| Issue date: | 09/24/1982 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20027C046 | List: |
| References | |
| NUDOCS 8210120352 | |
| Download: ML20027C050 (4) | |
Text
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Form NRCC19 U.S. NUCLEAR REGULATORY COMMISSION 7 33 CERTIFICATE OF COMPLIANCE 3,
,y For Radioective Materials Packages 1.(a) Certm.e Number 1.(b) Revision No.
1.(c) Pack 1.(e) T tal No. Pages s964 2
UST/9964/B( )No.
identification 1 (d) Pages No.
1 3
- 2. PREAMBLE 2.(a)
This certificate is issueJ to satisfy Sections 173.393a.173.394.173.395, and 173.396 of the Departrnent of Transportation Hazardous Materials Regulations (49 CFR 170-189 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 requirement 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 certificate is inued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.(b)
Title and identification of report or application:
E. I. duPont de Nemours & Company E.I. duPont de Nemours & Company Savannah River Plant Report No. DPSPU 74-124-3, January 1975.
Aiken, South Carolina 29801 3.(c)
Docket No.
7]_ggg4 l
- 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) Model No.: LP-12-1 (2)
Description:
Packaging for large quantities of tritium.
The containment vessel is a nominal 1 liter stainless steel bottle fitted with a vacuum valve assembly. The primary containment-vessel has a 4-inch 0.D., is 5 *,4
~ inches high and has 1/8-inch thick walls.
It is supported by a hold-down assembly within a nominal 12 liter aluminum bucket, with a 10-inch 0.D; 18.2-inch height and 0.19-inch walls.
The bucket is centered and supported within an 18-gauge,19-1/4-inch 0.D. by 28-5/8-inch steel drum using celotex insulation. The drum is closed using a bolted locking ring..The package gross weight is 140 pounds.
(3) Drawings:
The packaging is fabricated in accordance with DuPont Drawing Nos.:
SS-2-7145, Rev. 0; SS-2-7146, Rev. 0; SS-2-7142, Rev. 0; S5-2-7143, Rev. 0; SS-2-7144, Rev. 0; and S4-2-147; and DuPont Detail 146770 and l
Nuclear Products Company Drawing No. SS-8BG-TSW.
I l
1 8210120352 820924 i
Page 2 - Certificate No. 9964 - Revision No. 2 - Docket.No. 71-9964 5.
- (b) Contents (1) Type and fonn of material Tritium gas in mixture with other gases.
(2) Maximum quantity of material per package 3
Not more than 1121 cm of tritium at. STP (1 atm, 25'C) and a maximum activity of 2881 curies.
6.
The neximum internal fill pressare of the primary containment vessel at loading shall not exceed 19.3 psia at 25*C (77'F).
7.
Each packaging, before first use, and after the third use shall be leak tested to shgw that g/sec when the containment vessel is filled to 47 psia and tested he containment vessel maximum helium leak rate will not exceed 7x10~ atm-cm in an ambient environment of 14.7 psia.
In addition, the primary containment vessel shall have been leak tested as described above, prior to use, within the preceeding 12 month period.
8.
Before each use the primary containment vessel and closure valve shall be leak tested in accordance with-the procedures described below:
(a) The primary containment vessel is evacuated and a rate of rise determi-I nation is made at 50 microns of pressure. The rate of rise shall be less than 1 micron for a 10 minute test period.
(b) After filling the primary containment vessel with its contents the valve closure shall be determined by a pressure rise test. A rise of 8 microns or less over a 20 minute test period into a cavity with '20 microns pressure shall be considered acceptable.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12(b).
10.
Expiration date: September 30, 1987.
4
-Pag 2 3 - Certificato No. 9964 - Revisicn No. 2 - Docket No. 71-9954 REFERENCE E. I. duPont de Nemours and Company Report No. DPSPU-74-124-3, January 1975.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION M %0)A Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
e O
=.
U.S. Nuclear Regulatory Commission Transportation Certification Branch Approval Record Model No. LP-12-1 Packaging Docket llo. 71-9964 By application dated August 13, 1982, Department of Energy, Safety Engineering and Analysis Division, requested renewal of Certificate of Compliance rio. 9964.
No changes have been requested or made to the package since approval of Safety Analysis Report flo. DPSPU-74-124-3 dated January 1975.
The staff concludes that the statements of the original application satisfies the requirement for renewal of the Certificate of Compliance.
Cha il d, Chie Transportation Certification Branch Division of Fuel Cycle and Material Safety, fitSS SEP 9, ' E82 Date:
O
.