ML19332A958
| ML19332A958 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 06/30/1980 |
| From: | Reitler E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP., WESTINGHOUSE ELECTRIC CORP. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 16781, NUDOCS 8009190108 | |
| Download: ML19332A958 (3) | |
Text
m.
'A,
'/O-l[5/
e pytWED D8 Westinghouse Electric Ccrporation Power Systems ne e n.n.
g ego p,.axf acts ;'J ;artnut
,o b
dh 0:3wR 4
Co'umt a Stan cycbm 2T?2
,,., r * $
C3'11C 25 t3 U
ncu y,'..
. June 30, 1980 b
S\\
g U. S. Nuclear Regulatory Commission p
DOCKETED' 9
Office of Nuclear Material Safety & Safeguards USNRC Division of Fuel Cycle and Material Safety Washington, D. C.
20555 t
jul 2 31930 > g
\\..
NM9 Mall. 5ECTION
\\.h, DOCKET CLERK Attention:
Mr. W. T. Crow, Section Leader Uranium Processing Licensing Section Gentlemen:
Subject:
License SNM-1107, Docket 70-1151 UF Cylinder Recertification Facility 6
The Westinghouse Electric Corporation hereby submits information concerning cyUnders the construction and use of a new facility for recertification of UF6 in accordance with 49 CFR 173.396 and DOE Report No. OR0-651. The new facility will be an extension to the existing Waste Storage Building which is described in the existing License.
Environmental effects of the building construction are minimal as described in the enclosure to this letter.
Cylinder recertification is currently authorized in subparagraph 2.1.2 of SNM-1107 as a quality assurance testing operation.
Consequently, we feel that a license amendment is not necessary. Construction is expected to begin as early as mid-August.
If you have any questions re-garding this matter, please write to me at the above address or telephone me at (803) 776-2610 Ext. 395.
Very truly yours, WESTINGHOUSE ELECTRIC CORP.
w E. K. Reitler Fellow Engineer EKR/Le a
cc:
R. P. DiPiazza,Mananer NES License Administration y,,
- a. C:.
._,.._m_..
i
ur y
ENCLOSURE TO TRANSMITTAL OF JUNE 30, 1980 SNM 1107, DOCKET 70-1151
,w UF LINDER RECERTIFICATION FACILITY 6
PURPOSE The purpose of the UF Cylinder Recertification Facility is to provide an area 6
for inspecting and testing UF cylinders in accordance with 49 CFR 173.396 and 6
DOE Report No. ORO-651.
LOCATION The UF Cylinder Recertification Facility is an approximately 44' X 30' extension 6
to the existing Waste Storage Building.
BUILDING CONSTRUCTION The building is a " Butler" design which is structurally similar to the contiguous Waste Storage Building, except that the UF Cylinder Recertification Area is com-6 pletely enclosed. The building is constrected on a concrete stab, with floor drains which are connected to the adjacent lagoon.
BUILDING USE The building is used for the recertification of UF cylinders as required by 49 CFR g
173.396 and DOE Report No. ORO-651.
Cylinders to 5e recertified are washed by a vendor and shipped to the Westinghouse Columbia Plant. The cylinders are then in-spected, tested for wall thickness, hydrostatic tested, pressure tested with nitro-gen, equipped with new cylinders valves, etc. in accordance with DOE Report No.
ORO-651.
Building services include electricity, nitrogen and city water for testing purposes.
Storage tanks are provided for hydro-test water and for hold-up capability to permit radiological analyses following hydro-testing.
RADIOLOGICAL SAFETY Since the cylinders are washed by a vendor prior to recertification, radiological concerns are limited to residual radioactivity inside the cylinders.
Upon receipt of the cylinders at the Westinghouse Columbia Plant, an external beta gamma survey will be performed for each cylinder as a screening method to assure that gross radio-activity has been removed in the washing process.
The hydro-test water will be transferr ed to a hold tank, sampled and analyzed for alpha and beta gamma prior to dispositioning in accordance with SNM-1107.
7 _.,, -
P
.y
~
. 1>
Bekause of the small quantities-of radioactive materials involved, surface con-tamination and airborne radioactivity problems are not anticipated. However, the Radiation Protection Component will evaluate the operation and initiate the appropriate protective actions, e.g. contamination controls, air sampling, etc.-
in accordance with SNM-1107.
In summary, no significant radiological safety problems are expected.
. NUCLEAR CRITICALITY SAFETY Since the cylinders are' washed by a vendor prior to recers.fication, nuclear criticality safety concerns are minimal. The external monitoring screening check described above will verify _that SNM has been removed.
ENVIRONMENTAL The environmental impact of buildjng construction will be limited to the excava-tion of an approximately 1,300 ft area.
Conventional construction techniques will be used. The total commited land area remains well below that estimated in the 1975 Westinghouse Environmental Evaluation.
All water used in the hydro-testing will be sampled and analyzed prior to discharge to assure that radioactivity concentrations do not exceed 10 CFR 20, Appendix B, Table II limits.
If these concentration limits are exceeded, the liquid is treated to reduce levels to permissible limits.
Consequently, environmental concerns are expected to be minimal.
1G731
_