ML19331D166
| ML19331D166 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 06/16/1980 |
| From: | Olsen A BABCOCK & WILCOX CO. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 16636, NUDOCS 8008270399 | |
| Download: ML19331D166 (3) | |
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Mr. W. T. Crow, Section Leader Div. of Fuel Cycle % Material Safety Office of Nuclear Macerial Safety 2
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and Safeguards
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U. S. Nuclear Regulatory Cocnission A
Washington, D. C.
20555 4
'b Ref. License SNM-778, docket 70-824
Dear M. Crow:
I am enclosing revision 13 to the renewal application for the reference.
This revision adda a partial sentence at the top of page A-29 which was inadvertently deleted in Revision 12, page A-28.
Please remove pages A-29 and A-30 dated May, 1980 and November 1979 respectively and insert pages A-29 dated June, 1980 and November, 1979 respectively.
Yours very truly, BABCOCK & WILCOX COMPANY Lynchburg Research Center
%b A. F. Olsen License Administrator AFO:cef Enclosure
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crea will rsceiv2 ct least a quartsrly visual and radiological inspection.
l A gamma nonitor in the waste storage building meets the requirements
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for a criticality monitor as defined in 10 CFR 70.24.
Each drum with fissile material is gamma scanned on a drum counter to verify the fissile content.
The drum monitor has a limit of sensitivity of 2 grams U-235 and 2 grams of Pu.
Each vaste container will be labeled so that the contents of each drum can be identified and drums will not be opened without specific approval of the LRC health physicist and the facility supervisor, Material stored in the high level vaste storage tubes shall be in closed metal containers and limi ted to that resulting from hot cell operations.
The Health and Safety group shall control access to the tubes. Health and Safety shall perform surveys of the tubes each time waste is removed or inserted.
A.9.3.5 Environmental Sampling.The environment surrounding the LRC and the Mount Athos plant site is sampled periodically to determine whether the radiation and radioactive material levels in the area surrounding the site have changed or increased as a result of the operations at this location. The frequency of these surveys will be a function of the work taking place on the
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site. Environmental samples are collected and analyzed by LRC personnel or qualified commercial concerns. As a minimum, the environmental program will include the following:
1.
One continuous on-site background air sample.
2.
Monthly water sampling of grab samples taken from the James River below the discharge point.
3.
Continuous sampling of rain water.
4.
Annual grab sampling of river silt and plant life.
A.9.4 Special Conditions A.9.4.1 Restricted Area - The restricted area at the LRC is defined as any area within a building or enclosed by chain-link fence or a single-strand fence and properly marked with radiation area signs.
Lictnse No.
SNM-778 Docket No.70-824 Date June, 1980 Page A-29 Am2ndnent No.
Revision No. 13 Babcock & Wilcox
A.9.4.2 Records Retention - The following records will L's maintained for at least two years.
1.
Records showing the results of surveys made to evaluate the radiation hazard incident to the production. use, release, disposal, lor presence'of radioactive' materials or other sources of radiation, as required by 10 CFR 20.401 (b).
2.
Records used to preparc Form NRC-4 " Occupational External Radiation Exposure History" as required by 10 CFR 20.102, 3.
Records showing receipt, transfer, export, and disposal of by-product material.
4.
Records showing the results of leak tests of sealed sources as required by license.
5.
Records showing the receipt, inventory, and transfer of special nuclear materials as required by 10 CFR 70.5.1.
6.
Records shewing the receipt, transfer, export, and disposal of source =aterial as required by 10 CFR 40.61.
7.
Records of the SRC meetings.
8.
Records of instrument calibration.
9.
Safety audit records.
10.
Records of training and retraining.
11.
Records shall be maintained to reflect the quantities of material in categories A-E and I-Q specified in section A.3.
When personnel monitoring is required by 10 CFR 20.202, as required by 10 CFR 20.401(a), records showing th9 radiation exposure of each. individual will be retained in accordance with 10 CFR 20.401(.c).
A.9.4.3 Area Decontamination - Areas prey'iously used for handling radioactive material (including contaminated glove boxes and equipment) will be removed from service, held in a standby condition, or decontaminated in accordance with current health physics procedures and special procedures and practices approved by the SRC. These procedures and practices will describe the following activities.
License No.
SNM-778 Decket No.70-824 Date November 1979 Page A-30 Am:ndment No.
Revision No.
3 Babcock & Wilcox
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