ML20023D611
| ML20023D611 | |
| Person / Time | |
|---|---|
| Site: | 07106550 |
| Issue date: | 05/03/1983 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20023D610 | List: |
| References | |
| 22266, NUDOCS 8305240556 | |
| Download: ML20023D611 (2) | |
Text
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Form NRCC18 U.S. NUCLEAR REGULATORY COMMISSION H2 733 CERTIFICATE OF COMPLIANCE g gpq 7, For Radioactive Materials Packages 141 Certificate N 1.(b) Revision No.
1 (c) P k e1 i ion No.
1.(d) Pag No. 1.(e) Tot No. Pages
- 2. PREAMBLE 2.(a)
This certificate is issued to satisfy Sections 173.393a,173.304,173.395, and 173.396 of the Copartment of Transportation Hazardous Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10e and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulatione (46 CFR 146.-149), as amended.
2.lb)
De neckaging and contents desaibed in item 5 below, rneets the safety standards set forth in Subpert C of Title 10 Code of Federen Regulations, Part 71, **Pockaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions.**
2.(c)
This certificato does not relieve the consignor from cornpliance with any requirement of the regulations of the U.S. Department of Transportation or other esplicable regulatory agencies, including the governenent of any country through or into which the package will be transported.
- 3. This certificate le issued on the basis of a safety analysis report of the package design or application-3 (a) Prepared by (Name and addrese):
3.(b)
Title and identification of report or application:
University of California Report No. LBL-2168, February 1974.
Lawrence Berkeley Laboratory Berkeley, California 94720 3.(c)
Docket No.
- 4. CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpert O of 10 CFR 71, as applicable, and the renditions specified in item 5 below.
- 5. Description of Packaging and Authorized Contents, Model Number, Fissile Cl_ ass, Other Conditions, and
References:
(a) Packaging (1) Model No.: 6-GS-1 (2) Description Shielded packaging for sealed source. An outer gypsum-spodumene filled cask with 1/4-inch thick steel walls, 24-inch 0.D., and
- 34. inch overall height which includes a 34-inch square steel pallet base. The outer. cask has a bolted plug closure. The inner cavity is ll-inches diameter by 15 inches deep, containing a sealed source within a nestable stainless steel and depleted uranium ganina shield assembly; or within an internal mounting rack.
Package gross weight is 1,840 pounds; or 1,230 pounds when the inner nested ' gamma shield assembly is not used.
(3) Drawings Tha packaging is fabricated in accordance with Lawrence Radiation Laboratory Drawings Nos.
HCD 56952 HCD 61081A HCD 60604A HCD 58291 HCD 60081 8J8573D HCD 60061 HCD 60091 8J8583A HCD 60071 HCD 60596D 8J8684E HCD 61076 HCD 63464 13J6212A B305240556 830503 PDR ADOCK 07106550 C
PDR 330 1
b
2 - Certificate of Compliance Nc. 6550 Revision No. 0 - Docket No. 71-6550 (b) Contents (1) Type and form of material Radioactive material contained within capsules which meet the requirements of special form material as defined in 10 CFR 571.4(o).
(2) Maximum quantity of material per package Not to exceed 5,000 curies of radioactive material,15 grams fissile material and 243 watts inter:a1 decay heat, except that the total mass for any of the following isotopes shall not exceed:
Am-242 6.0g Cm-245 0.5g Am-242m 0.2g Cm-244 10 g Am-241 115 g Cm-243 3.0g Cf-252 85 pg Cm-242 2.0g Cf-251 0.06g Cm-240 338 g Cf-250 20 mg Es-255 200 pg Cf-249 0.4g Es-254 700 mg Cf-248 10 mg Es-253 270 mg 4
Cm-250 20 mg Fm-257 100 pg Cm-248 5 g Np-237 40 g Cm-247 2.4g Pu-240 150 g Cm-246 20 g 6.
For mixtures of isotopes the sum of the ratios of the content isotope masses to their respective approved mass limits shall not exceed unity.
7.
Expiration date: September 30, 1983.
REFERENCE University of California, Lawrence Berkeley Laboratory, Report No. LBL-2168, February 1974.
FOR THE U.S. NUCLEAR REGULATORY C0KMISSION b
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety SEPT.
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