ML20199L345
| ML20199L345 | |
| Person / Time | |
|---|---|
| Site: | 07001220 |
| Issue date: | 11/25/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20199L343 | List: |
| References | |
| NUDOCS 9712020002 | |
| Download: ML20199L345 (3) | |
Text
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NRC FORM 374 U.S. NUCLEAR RESULATORY COMMISSION R
(l MATERIALS LICENSE gl
- ig Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10. Code of g g Federal Regulations, Chapter 1, Parts.40,31,32,33,34,35,36,39,40, and 70, and in rehance on statements and representations heretofore made yl gl by the licensee, a license is hereby issued authorizing the licensee to receis e, acquire, possess, and transfer byproduct, s gl material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deiner or transfer such material to g a
fj persoen autnorized to receise it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions k
9g specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, reFulations, and orders of the k 9 Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
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- 3. License Number El
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Vallecitos Nuclear Center SNM-1270, Amendment No.
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M Pleasanton, CA 94566 (Revised in its entirety) gl M
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- 4. Expiration Date September 30, 2002 g
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- 5. Docket or 70-1220 m
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- 6. flypmduct, Source, and/or
- 7. Chemical and/or Ph> sical 8 Maximum Amount that Licemee (l
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Special Nuclear Matenal Form May Possess at Any One Time gl El Under This License g
il Special nuclear material, which Any Quantities as required sl p
may be irradiated, must be for delivery to a il ji contained in fuel pellets, rods carrisr for transport sl d
and rod segments, or fuel and in private carriage.
jl 11 bundles used in General Electric g
il Company research and development i
g j;i activities (as defined in 10 CFR j
I Part 70.4). Source material, byproduct 1
material contained in irradiated S
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!I surveillance capsules, contaminated
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support equipment, or other irradiated s
equipment. All other materials 5
1 subjf.ct to requirements of 10 CFR 3l Part 73 are excluded.
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Authorized Use:
Receipt and possession of materials specified in Items 6 3
through 8, above, in packages approved pursuant to 10 CFR Part 71 for +he E
l purpose of delivery to a carrier for transport and in private carriage in RI accordance with other conditions of this license.
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Authorized place of use: NRC licensed facilities and in private carriage
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between NRC licensed facilities within the United States.
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The licensee must utilize its personnel who have been trained in practices and N
procedures appropriate to the nuclear materials and shipping package involved I
in each instance, to inspect and monitor the loading of each package to verify:
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That nuclear material to be shipped is in accordance with conditions of N
this license and in compliance with requirements of the license.
N Certificate of Compliance, or, DOT specification for the package to be N
employed;
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That the package 'is loaded, sealed, tested, and/or otherwise prepared for N
shipment in accordance with requirements of the. license, certificate of N
Compliance, or DOT specification for the package to be employed.
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The licensee must receive the loaded shipping package at tha-loading dock, or I
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equivalent location, at the NRC licensed facility from which-the shipment will u
originate. Once accepted, legal responsibility for the loaded package must I
rest with General Electric Company. The licensee, in accordance with the N
provisions of 10 CFR 71.12, must then deliver the loaded package to the a
carrier for transport, g
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,GFOR THE U.S. NUCLEAR REGULATORY COMMISSION g
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Cass R. Chappell, Chief J
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' Package Certification Section g
' Spent Fuel Project Office y
I Office of Nuclear:N terial Safety y
and Safeguards"i y
g Date: 11-25-97 l
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+9.....,o APPROVAL RECORD Material License No. SNM-1270, Amendment No. 6 Docket No. 70-1220 By application dated November 24, 1997, General Electric Company requested an amendment to the Materials License No. SNM-1270. The applicant requested the addition of " source material, byproduct material contained in irradiated hardware. reactor components, surveillance capsules, contaminated support equipment, or other irradiated hardware" to the caterials license.
The materials license previously authorized possession of "Special nuclear material, which may ba irradiated, must be contained in fuel pellets, rods and rod segments, fuel bundits..." in packages approved pursuant to 10 CFR Part 71, for the purpose of delivery to a carrier for transport and in private carriage.
Radioactive materials yielded in the process of utilizing special nuclear material are defined as byproduct material, and therefore the license previously authorized byproduct material present as irradiation products in the fuel pellets, rods and rod segments, and fuel bundles. Other radioactive materials, such as source material, or byproduct material yielded by irradiation of non-fuel materials were not specifically identified as authorized materials in the license. However, it is concluded that the intent was to authorize possession of radioactive material produced in utilization facilities, whether the material was produced by irradiating SNM or non-SNM material, explicitly for the purpose of transport.
Source material is usually a component of the fuel which contains the SNM in a I
reactor core. The isotopes of source material are no more hazardous than SNM and its induced fission products and actinides. Byproduct materials specified in the license are typically solid materials or special form samples which are non-dispersible. The addition of these source and byproduct materials to the materials license would not impact public health and safety, since all radioactive contents must be transported in packaging certified under 10 CFR Part 71 for the respective contents. The materials license was therefore revised to clarify that source material and byproduct material in irradiated hardware, reactor components, surveillance capsules, contaminated support equipment or other irradiated equipment, is also authorized.
Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards 11-2W DATE:
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