ML19327A777
| ML19327A777 | |
| Person / Time | |
|---|---|
| Site: | 07001193 |
| Issue date: | 10/09/1989 |
| From: | Wical S OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | Gary Comfort NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 26021, NUDOCS 8910180095 | |
| Download: ML19327A777 (6) | |
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i Oak. Ridge.
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Office of Nuclear Material S y Matt SJON and-Safeguards' g Docxu cux,.q '
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Subject:
PROPOSED SURVEY' PLAN: ' MIXED OXIDE FACILITY AT SEQUOYAH FUELS CORPORATION CIMARRON PLANT
Dear Mr. Comfort:
Enclosed is the proposed survey plan for the Mixed Oxide Facility at Sequoyah
. Fuels' Corporation Cimarron Plant, which is to be surveyed October 12-30, 1989, Contac:: me at FTS 626-5073 or Jim Berger rt: FTS 626-3305,,if there are any qaestions or comments, Since ly, i
-d 6Q' Scott A. Wical Staff Health Physicist
-Environmental Survey and Site-Assessment. Program.
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.L. Rouse, NRC/6H3 G,-France, NRC/ Region III D. Tiktinsky, NRC/6A4 E. Davis, NRC/6A4 i
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PROFOSED SURVEY PLAN FOR THE MIXED OXIDE FACILITY SEQUOYAH FUELS CORPORATION CIMARP.ON PIANT.
CRESCENT, OKIJNOMA I.
Site History and Description
'The Sequoyah1 Fuels Corporation Cimarron' Plant is located on an approximately 450 hectare site in Logan County, Oklahoma, about 10 kilometers south of the town of Crescent. The plant was operated by Kerr-McGee between 1965 and 1975, for the production of enriched (about 3%)
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uranium and mixed oxide (uranium and plutonium) reactor fuel.
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-There ~are two main processing buildings on the site - the Uranium Plant and the. Plutonium Plant. Kerr-McGee is in the process of decomraissioning this site..All equipment has been removed from the Plutonium Plant; the
. building has been characterized, and decontamination of intorior surfaces l
are' complete. Final survey data have been developed by the licensee'for all' building areas and the fenced-in grounds immediately outside the Plutonium Plant.
1 Oak Ridge Associated Universities (ORAU) has been requested by the l'
L Nucleat Regulatory - Commission to perform a confirmatory survey of the plutonium facility and the asuociated grounds.
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Purpose The purpose of the survey is to confirm the decontamination efforts by Kerr-McGee, relative to' release of the plutonium facility and the fenced in grounds immediately outside the facility.
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Prepared by the Energy / Environment Systems Division of Oak Ridge Associated Universities, Oak Ridge, Tennessee, under NRC Fin. No. A-9076 between the U.S.
Nuclear' Regulatory Commission and the'U.S. Department of Energy.
October 9, 1988
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IIII. Responsibility-
-I Wo'k.descr'ibed _in Lthis survey -plan will be performed <:under the r
- stipervision' 'of, J.D. _ Berger, Manager, and' L.F.
Friedwan,' Assistant t
' xn Manager, 'of 'the Environmental' Survey and Site, Assessment Program of the i
Energy / Environment Systems Division of Oak Ridge Associated Universities'.
e IV.
Procedures 1
A.
Document Review tb Oak.uidte ' Associated-Universities: will review Kerr McGee's final-
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L surveyf data and. supporting documentation concerning decommissioning L
~ activities.
~ B. : ' Facility Survey-
' The = existing ' 1 m x l'm grid will be used on the floor cnd lower 1.
- walls of the laboratory room: and other areas where' potential for contamination is suspecc.
The ceilings will not be gridded; howevet, - measurements and samples from the ungrioded areas and surfaces will be referenced ta the floor and wall. grid, or to i
x pertinent building surfaces, c
1 2.
- Building surfaces will be scanned using gas proportional and.ZnS scintillation alpha detectors and thin (low energy) NaI gamma t
reintillation detectors.
Floors and lower walls will receive 100s scans; upper walls, ceilings, and other overhead surfaces l
will be randomly stanned, with efforts concentrated at locations L
of highest centamination potential and suspect surfaces as L "M determined. as. the survey progresses.
Locations of elevated l'
direct 241ngs will be identified for.urther investigation.
3.
Measurements of total end removable alpha contamination will be L
performed on a minimum of 10% of the floor and lower wall grid
- blocks, selected at random. One set of five direct measurements 4
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t will be. obtained for each survey grid block, and one smear will
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be" Ltaken - at '~ th'e highest reading' for Teach set of five measurements.-
The. direct measurements will be systematically-performed at--the ' center and at four points, midway between thei q
center and the block corners. Ad<'itional measurements will be j
l; performed at locations of elevated radiation levels identified by' the surface scan.
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4.- Direct measurements = and sasars= will be obtained.on the upper D
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walls. and ceilings.
Particular attention will be given to cracks,. beams, piping, ledgec, ducts, and other surfaces where-
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material might settle or accumulate. These surveys will include the faside surfaces of e.ny drains, exhaust air ducts, or floor penetrations.
The nweber of survey locations will be determined =
j by results as the survey progresses; however, a minimum of 1
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2 of surface area.
measurement will be performed for every 10 m l.9 L
'5.
Exposure rate measurements will be made at one meter from the i
1 floor at.a minimum of 10 locations-in the facility.
A i
h pressurized ionization chamber and/or Na1
- detector, cross-calibrated against a pressurized' ionization chamber,.will Id be-used for these maasurements.
6.
Samples of residues will. be collected from floor cracks or I
joints, beams, inside and outside of piping, ledges, air ducts, l
l' floor pe.mtrations, and other surfaces as appropriate.
'7.
Samples of paint will be collected, as available, from a minimum i.
of two locations in each room.
8.
Excavated areas for piping removal will be gamma scanned and soil samples collected from representative locations.
Floor coring for 'the purpose of subfloor sampling will be performed, if scanning results or other surface measurements indicate the potential for subfloor contamination.
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Additional sampling and measurements will be performed, as deemed-necessary,; based on findings as the survey progresses.
-C.
Outdoor Survey-s L1.. A 10 m grid system will be established and used to reference ORAU g
measurement and sampling locations.
2.
Walkover scans at one to two meter intervals will be conducted over the area using gamma scintillation detectors and rate meters with audible indicators. Locations of elevatad contact radiation levels will be identified for further investigacion.
1.
Exposure rate measurements will be made at the surface and at 1 m
- above the surface at each -grid interval and at locations of elevated readings.
These measurements will be performed using-.
l portable' gamma scintillation detectors calibrated onsite against l
a pressurized ionization chamber.
4 Surfaca (0-15 cm) soil samples will be collected at each grid.
line intersection and from areas of elevated surface contact
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levels, identified by the wallrover s.:an, l ',
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'5.
Shallow
-(1-2 m) boreholes will be drilled to facilitate l
subsurface sampling, using a post hole digger. A minimum of 10 1
representative locations will be sampled within the fenced in 1
area.
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D.
Any locations of residual contamination, found by direct maasurements to exceed the NRC guidelines, will be brought to the immediate 3
attention of the licensea's representatives.
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E.
The scope of the survey L. decrease or increase based on findings as the survey progresses.
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Lack [roundandBaselineDeterminations Soil-samples were collected on a previous: site visit'from areas within 0.5-to 10 ka' of :the site to provide baseline concentrations of
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. radionuclides for comparison purposes.
Direct radiation levels were measured at locations where baseline soil samples were collected.
lI Th'e. background exposure rates for.inside the Plutonium facility will be established with the pressurized ionization chamber, in an area that is not radiologically contaminated, outside the restricted area, and cf similar construction history and material.
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'VI.
Sample Analysis and Interpretation of Results n
Samples and' di.ect measurement data will be returned to Oak Ridge, Tennessee,- for analysis and interpretaticn.
Soil, sediment,-and residue I
samples-will-be analyzed by solid state gamma spectrometry.
Radionuclides of primary interest are U-235, U-238, and Th-232; however, spectra 7 will.be' reviewed for other identifiable photopeaks.
Composite.
o'her selected samples will he ana1.yzed for plutonium.
Smears will l
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be counted on a'
low background gas proportional alpha / beta counter.
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- Pcint, residue, and soil samples, from tha Plutonium Building will be analyzed for isotopic plutonium.
q VII. Tentative Schedule Site Survey October 10-30, 1989 l
l Complete Sample Analyses November 30, 1989 Draft Report December 31, 1989 l
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