ML20031C870
| ML20031C870 | |
| Person / Time | |
|---|---|
| Site: | 07105950 |
| Issue date: | 09/17/1981 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20031C867 | List: |
| References | |
| NUDOCS 8110090062 | |
| Download: ML20031C870 (3) | |
Text
.
Form NRC418 U.S. NUC6E AR REG'.tLAToRY COMMISSION u2 3)
CERTIFICATE OF COMPLlANCE
,g c 7,
e For Radioactive Materials Packages 1.fo) Ce tificate N ember 1.(b) Revision No.
1 (c) Packaoe identification No.
1,(d) Pages No. 1.(e) Total No. Pages ti950 3
USA /5950/B( ) F 1
3
- 2. PRE AMBLE 2.(a)
This certificate is issued to satisf y Sections 173.393a,173.394,173.395, 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 Treasportation Dangerous Cargoes Regulations 146 CFR 146-149), as amended.
2.(b)
The packaging and contents described in item 5 below, sneets the safety standards set forth in Subpart C of Title 10, Code of Federal Regulations, Part 71, ** Packaging of Radioactive Materials for Transport at Transpur+snon of Radioactive Material Under Certain Conditions."
2.(c)
This certificate does not seleeve the consignor from compliance with any reovirement 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 issued on the basis of a safety analysis report of the package design or application-3.(a)
Prepared by (Name and address):
3.tol Title and identification of report or application:
Battelle Columbus Labc.atories Battelle Columbu.s Laboratories application 505 King Avenue dated August 7, 1981.
Columbus, OH 43201 3.(c)
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 Nurnber, Fissile Class, Other Conditions, and
References:
(a)
Packaging (1) Model No.:
BCL-4 (2) Description l
Steel encased lead shielded shipping package.
The package is provided with recessed plug-type lid and gasketed, bolted closure, lif ting and tie-down devices and relief valve, vent line, and drain line penetra-tions.
Containment for the contents'is provided by an inner can assembly or by material in special fonn.
The. packaging has dimensions, I
weight, and shielding as follows:
I Exterior height, in 64.8 l
Exterior diameter, in 26.4 Cavity height, in 42.5 Cavity diameter, in 6.1 Lead shielding, in 8.4 Loaded weight, lbs 13,200 (Incl 270-lb skid)
(3) Drawing
~
The packaging is constructed in accordance with Battelle Memorial Institute Drawing No. BCL4-01, Sheet 1 and 2, Rev. J.
8110090062 010917 PDR ADOCK 07105989 C
(
Page 2 - Certificate No. 5950 - Revision No. 3 - Docket No. 71-5950 i
F-1 5.
(b)
Contents Type and form and maximum quantity of material per package.
Byproduct material, source material and special nuclear material nct to exceed 400 watts decay heat in solid metal or oxide form packaged within an inner can assembly or the material is in special form meeting the l
requirements of 10 CFR 571.4(o) and limitations on fissile loading for the Fissile Class as follows:
1 Inner can assembly:
I Battelle Memorial Institute Drawing No. BCL4-49, Rev. C.
Fissile Class I 650*
Fissile Class III 2000*
- (grams U-235 equivalent mass)
(c)
Fissile Class I and III Maximum number of packages per shipment for Class III One (1) 6.
The U-235 equivalent mass must be determined by the following method:
i U-235 equivalent mass equals U-235 mass plus 1.75 times U-233 mass plus 1.60 times Pu mass.
7.
At the time of delivery of the loaded package to a carrier for trans-port, the package contents must be (1) dry (contents of inner can assembly must not decompose up to a temperature of 750*F) and the fissile material unmoderated (H to X atomic ratio less than 2) and (2) so limited that the dose rate will not exceed 10 millirem per hour at i
three (3) feet from the external surface of the package.
8.
The maximum gross weight of the cavity contents must not exceed 180 pounds (inner can assembly, radioactive material, etc.).
l l.
b
Page 3 - Certificatt No. 5950 - Revision No. 3 - Docket No. 71-5950 9.
In addition to the requirements of Subpart D of 10 CFR Part 71, each package must meet all of the acceptance and periodic tests specified in Section 8.0 of this Application.
The following item in the thennal acceptance tests (8.1.6) is changed as follows:
(4)
The acceptance criteria must be that the maximum measured temper 6ture of any portion of the cask must not exceed the temperatures indicated in Figure 3.3 of this application by more than 25'F.
In this comparison, solar heating and ambient temperature differences between Figure 3.3 and the test data must be taken into account.
- 10. The following item in the Test Procedure (8.1.3), Section 8.0 of the.
Application, is changed as follows:
g.
Remove pressurization _line and insert plug in pressure port according to the loading procedure.
Use teflon tape or other compatible sealant in threads.
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- 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: September 30, 1986.
REFERENCE Battelle Columbus Laboratories application dated August 7,1981.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
[b Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Date:
SEP 171981
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