ML19318B295
| ML19318B295 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 03/31/1980 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML19318B292 | List: |
| References | |
| BAW-381, BAW-381-R11, NUDOCS 8006250211 | |
| Download: ML19318B295 (3) | |
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1-Instruction Sheet For BAW-381 Demonstration and Conditions for License SNM-778 Revision 11 March, 1980 I
Remove Old Page Insert.';ew Page Page Rev.
Date Page
.Rev.
Date A-1 1
9/79 A-1 11 3/80 A-2 1
9/79 A-2 11 3/80 6
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8 0062 503ll
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e A.1 AUTHORIZED USE A.1.1 Special nuclear material shall be used in the perfor=ance of research and development activities as defined in 10 CFR 70.4(j).
A.1.2 Byproduct material shall be used in the performance of research and development activities as defined in 10 CFR 30.4(q).
A.1.3 Source material shall be used in' the performance of research and development activities as defined in 10 CFR 30.4(q).
A.l.4 Receipt, storabe, destructive, and nondestructive examination of fuel assemblies is permitted in the hot cells in irradiated UO2 accordance with other statements in this appendix and the following.
A.1.4.1 The bridge crane used for cask handling at the hot cell pool shall be certified to satisfy the requirements of the standard USAS B 30.3.0-1967, and shall have a rated load of 25 tons in accordance with the standard. Use and operation of the crane shall be in accordance with the standard.
A.l.4.2 The maximum force applied to the 18-inch thick impact slab resulting from the accidental drop of the loaded shipping' container from 23.33 feet above the slab shall not exceed 402 psi punching shear. This shall be demonstrated by an engineering evaluation performed or veri-fled by a Mechanical, Civil or Structural engineer. The evaluation shall take into account any impact limiting devices installed in the pool or on the container.
A.l.4.3 Transfer of the shipping cask into and out of the~ hot cell pool shall be performed only over the region of the pool protected by the 18-inch thick impact slab (total floor thickness 42 inches).
A.1.4.4 The maximum vertical distance between the cask bottom and the pool impact slab shall be limited to 24-1/2 feet during cask transfer operations.
A-1 License No.
SNM-778 Docket No.70-824 Date March,1980 Page Amendment No.
Revision No.
8 4...
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Babcock & Wilcox
A.l.4.5 Lateral transfer of the cask within the pool shall be administrative 1y controlled to limit the maximum elevation of the cask to a nominal 4-inch height above the impact slab.
... A.l.4.6 A maximum of 1 curie of31utoniumand8gramsofzircaloy,inthe
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form of exposed fines resulting from fuel rod sawing operations, shall be permitted in any one hot cell at any one time. These fines shall be collected and disposed of by methods described in 4.6.1.5.
-A.l.4.7 A gamma-neutron radiation survey shall be conducted when the first fuel assembly is unloaded and shall be repeated each time for fuel assemblies which have been irradiated at higher MWD / ton levels, in order to assure that radiation exposures of personnel conform with the exposure limits specified in 10 CFR 20..
A.1.5 Transportation of Licensed Material The LRC may deliver licensed material to a carrier and transport and possess licensed material in private carriage between NRC licensed facilities l
l within the United States, pursuant to the regulations in 10 CFR 71 and 49 CFR I
and in accordance with the following.
A.l.5.1 The licensed user of the cask will provide the LRC with the detailed characteristics of the radioactive material to be shipped.
A.l.5.2 This information will be reviewed by the LRC to assure that such shipments fall within the limitations of 10 CFR 71 and the particular package.
A.l.5.3 The licensed user shall physically load and test the package as required. This shall be in accordance with NRC, DOT package approval and loading requirements and under any specific site license conditions.
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A.l.5.4 Prior to delivery to a carrier by the licensee, the shipper will l
i' ensure that the package meets the applicable rules and regulations of 10 CFR 71 and 49 CFR. If the LRC is delivering to a carrier, the LRC representative will follow the LRC shipping procedures and will ensure that the package and its contents meet the applicable rules and regulations of 10 CFR 71 and 49 CFR.
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' License No.
SNH-778 Docket No.70-824 Date March, 1980 Page A-2 Amendment No.
Revision No.
8 Babcock & Wilcox
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