ML20030B000
| ML20030B000 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 05/12/1981 |
| From: | Reitler E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 19137, NUDOCS 8108050005 | |
| Download: ML20030B000 (3) | |
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1981 6 iy 12, 1981 2,
'nttuc7, WICYgm U. S. Nuclear Regulatory Commission s
Uranium Fuel Licensing Branch g
Division of Fuel Cycle and Material Safe Washington, D. C. 20555 ATTENTION:
Mr. W. T. Crow RE: Construction of a Decontamination Facility within the Existing Waste Storage Building, SNM-1107, Docket No. 70-1151 Gentlemen:
The Waste Stolage Building was authorized by the NRC as Amendment No. 3 to Sm-1107.
The purpose of this building is to serve as a storage area for radioactive materials and as a staging area for dispositioning radioactive wastes and other materiols.
The purpose of this information letter and enclosure is to describe a proposed decontamination facility to be constructed withJn the existing Waste Storage Building to serve as a final cleaning station for the items such as contaminated metals.
The facility is described in the enclosure.
We feel that this facility will represent an overall environmental improvement, in that contaminated
- items, which would normally be transported to a low-level radioactive waste storage site, will be decontaminated and recycled.
All such recycling will be performed in accordance with Annex C of SNM-1107.
Since decontamination operations are adequately described in the existing license, a license amendment application is deemed unnecessary.
We expect to begin construction of the facility in June 1981.
Consequently, your timely attention will be appreciated.
Sincerely, E. K. Reitler 3ellow Engineer EKR/ff 3/#0085E 8108050005 810512 Enclosure PDR ADOCK 07001151 C
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E_fCLOSURE TO TRANSMITTAL OF MAY 12 1981~
- SfN-1107, DOCKET 70-1151-
. WASTE STORAGE BUILDING MODIFICATION
>c PURPOSE-L The Waste Storage Building was authorized by Amendment No. 3 to SPN-1107.- The
. purpose of this facility is to provide a protected area for material' storage
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Land.to serve as a staging areal for the dispositioning.of radioactive wastes.
' The purpose of this submittal-is to. describe a modification.to the : Waste Storage Building for decontaminating contaminated iteras such as molybdenum.
LOCATION The decontamination area will be located within the-existing Waste Storage Building' shown on Figure 1.3.2.1, page 16, in the existirg license.
The facility will consist of a-small ' room, aporoximately 20' - X 20' which will hnuse a sand blasting enclosure and miscellaneous equipment for handling containers.
CONSTRUCTION No changes in the exf sting Waste Storage Building are planned.
The proposed decontamination facility will be constructed within the existing building.
FACILITY USE The primary function of the decontamination facility is to provide a means for decontaminating metallic items 'such cs molybdenum.
Operations will include (1) transport of containerized materials - to che Waste Storage Building, (2) i
transfer of the materials te s ' decontamination
- chamber, (3) actual oecontamination processing; e.g.,
cand
- blasting, and' (4) transfer to
--containers for further' dispositioning such as surveillance.
RADIOLOGICAL SAFETY
- Items to be -decor.tamincbd in this facility typically oriutnate in the Manufacturing Plant.
The radiological safety controls which apply to these materiels are described 'in subparsgraph.l.3.3 of the' existing license and include survey ~ and release by the radiation-protection function and containerization of the naterial as appropriate to prevent tne spread of contamination.
Materials to be decontaminated will be precleai,ad in the Manufacturing Plant to assure that radioactive materials do not become airborne during. the transfer fron. containers to the decontamination chamber.
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e The decontamination equipment consists of a chamber with a rotating drum end sand blasting capabilities.
The chamber is
- sealed, with exhaust air discharged through HEPA filtration.
Air sampling of the chamber exhaust of the HEPA filters and DOP testirg will be per formed in accordance with the
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existing license.
In addition, the room air will be representatively sampled to assure that personnel exposures are minimal.
Contamination surveys are conducted to assess the level of fixed and removable contamination.
In summary, no significant radiological safety problems are anticipated.
Materials to be decontaminated are precleaned to minimize the spread of contamination.
The decontamination chamber has been used successfully in other radioat.tive material applications.
NUCLEAR CRITICALITY SAFETY Containerized materials will be limted to a maximum of 350 grams U-235 per container and a maximum concentration of 5 grams U-235 in any cubic foot.
Sand used in the decontamination process will be recycled.
A sampling program will be established to monitor the buildup of uranium in the sand, with actions established to assure that uranium concentrations are acceptable; e.g., less than 5 grams U-235 in any cubic foot of sand.
The total volume of sand in the system is less than two cubic feet.
I EthIRONMENTAL As indicated above, the decontamination room is an approximately 20' X 20' structure which is totally within the existing Waste Storage Building.
Therefore, no environmental effects are anticipated from construction.
Releases to the environment will be limited to the HEPA filtered ventilation exhaust from the sand blasting chamber.
Effluent concentrations are expected to be a small fraction of the Maximum Permissible for unrestricted areps as defined in 10 CFR 20, Appendix B, Table II.
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