ML19106A230
| ML19106A230 | |
| Person / Time | |
|---|---|
| Site: | 07000925 |
| Issue date: | 12/20/1995 |
| From: | Abelquist E Oak Ridge Institute for Science & Education |
| To: | Fauver D Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML19106A222 | List: |
| References | |
| Download: ML19106A230 (58) | |
Text
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION December 20, 1995 Mr. David Fauver Division of Waste Management - NMSS U.S. Nuclear Regulatory Commi~sion Two White Flint North T-8F37 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
FINAL REPORT - CONFIRMATORY SURVEY FOR THE SOUTH URANIUM YARD REMEDIATION, KERR-McGEE CORPORATION, CIMARRON FACILITY, CRESCENT, OKLAHOMA (DOCKET NO.79-925)
Dear Mr. Fauver:
The Environmental Survey and Site Assessment Program (ESSAP) of ORISE conducted a confirmatory survey of the south uranium yard remediation at Kerr-McGee's Cimarron Facility in Crescent, Oklahoma on April 24 and 25, 1995. Confirmatory survey activities included surface scans, exposure rate measurements, soil sampling, and confirmatory analyses of licensee's soil samples.
Enclosed are 5 copies of the subject document. The draft report was revised as requested. If you have any questions, please direct them to me at (423) 576-3740 or W. L. (Jack) Beck at (423) 576-5031.
Sincerely, Eric W. Abelquist Project Leader Environmental Survey and Site Assessment Program EWA:tsf Enclosure cc:
R. Uleck, NRC/NMSS/TWFN 7F27 D. Tiktinsky, NRC/NMSS/TWFN 8A23 PMDA, NRC/NMSS/TWFN 8A23 W. Beck, ORISE/ESSAP File/293 P. 0. BOX 117, OAK RIDGE, TENNESSEE 37831-0117 Managed and operated by Oak Ridge Associated Universities for the U.S. Department of Energy
\\-: ',i
- r-...
- .'* ~~.:.. F i *.
- .:*r:'
- ,.~. I *
\\*.,
,..1,1.:
~...
. ~
- - *.. ;
- 1
........ ** I'~
'*,1 *** *'
-~:,.:.* '-*-*
.' ~.
I
~..
- ~ '
'*'i
. ~
J.**
(.,
~. '
CONFIRMATORY SURVEY FOR THE SOUTH URANIUM YARD REMEDIATION KERR-McGEE CORPORATION, CIMARRON FACILITY CRF.SCENT, OKLAHOMA Prepared by E.W. Abelquist Environmental Survey and Site Assessment Program Environmental and Health Sciences Group Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for the Division of Waste Management U.S. Nuclear Regulatory Commission Headquarters Office FINAL REPORT NOVEMBER 1995 ORISE 95/L-21 This report is based on work performed under an lnteragency Agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute for Science and Education performs complementary work under contract number DE-AC05-760R00033 with the U.S. Department of Energy.
Kerr-McGee Ccnpomtion, Crcsent OK-November 13, 1995 h:\\c:uap\\rcporta\\cimarron\\cimarron.002
CONFIRMATORY SURVEY FOR THE SOUTH URANIUM YARD REMEDIATION KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA Prepared by: s..:.,.. w. oQ_~
E.W. Abelquist, Projectder Environmental Survey and Site Assessment Program Reviewed by:
N-o.tK L~ W\\.Gv-.__
M. J. Laudeman, Radiochemistry Laboratory Supervisor Environmental Survey and Site Assessment Program Reviewed by:
[~ 7 P ~"-'
A. T. Payne, Administra ~ervices Manager, Quality Assurance/Health & Safety Manager Environmental Survey and Site Assessment Program Reviewed by: ~
W. L. Beck, Program Director Environmental Survey and Site Assessment Program Date:
II f ~g/q'S' Date: /I Pefts Kerr-McGee Corporation, Cracot OK-November 13, 1995 h: \\cssap\\rcports\\cimarroo\\cimarroo.002
"*(:*.. -
- *\\1:. *.*
.\\.
I -, ~~
- i:
\\ ***.. '.~.
I***~*.),*' i '.*: 4_* :',) -,'. \\
j
...... ~;... ;;.,......
.--:..... t
,_*1,*
- .. ~*. -~....
ACKNOWLEDGMENTS The author would like to acknowledge the significant contributions of the following staff members:
Kerr-McGee Corporation, Creacnt OK-November 13, 1995 FIELD STAFF G. R. Foltz R. B. Slaten LABORATORY STAFF R. D. Condra J.
S. Cox R. L. Epperson M. J.
Laudeman S. T. Shipley CLERICAL STAFF D. A. Adams K. E. Waters ILLUSTRATOR T. D. Herrera h:\\C888p\\rq,ort.a\\cimarron\\cimnrron.002
TABLE OF CONTENTS PAGE f.
List o Figures.................................................. 11 List of Tables................................................. iii Abbreviations and Acronyms....................................... iv Introduction and Site History........................................ 1 Site Description................................................. 3 Objectives.................................................... 3 Document Review............................................... 3 Procedures.................................................... 3 Findings and Results.............................................. 6 Comparison of Results with Guidelines.................................. 8 Summary..................................................... 8 References...............................................*.... 21 Appendices:
Appendix A:
Major Instrumentation Appendix B:
Survey and Analytical Procedures Appendix C:
Guidelines for Residual Concentrations of Thorium and Uranium Wastes in Soil Kerr-McGee Corponltion, Creaent OK-November 13, 1995 h: \\easap\\rcporta\\cimarron\\cimarron.002
LIST OF FIGURES PAGE FIGURE 1:
Location of the Cimarron Facility, Crescent, Oklahoma............ 10 FIGURE 2:
The Cimarron Facility-Plot Plan.......................... 11 FIGURE 3:
South Uranium Yard-Measurement and Sampling Locations......... 12 FIGURE 4:
Designated Area Pile #3-Measurement and Sampling Locations....... 13 FIGURES:
Cimarron Site-Background Measurement and Sampling Locations..... 14 Kerr-McGee Corporation, Creamt OK-November 13, 1995 ii h: \\csaap\\rq,orta\\cimarron\\cimarron.002
TABLE 1:
TABLE 2:
LIST OF TABLES PAGE Uranium Concentrations in Soil Samples..................... 15 Isotopic Uranium Concentrations in Soil Samples................ 20 Kerr-McGee Corporation. Crescnt OK-November 13, 199S iii b: \\csaap\\repor18\\cimarron\\cimam,n.002
ABBREVIATIONS AND ACRONYMS
µR/h
µrem/h AEC ASME cm cm2 cpm D&D OAP DOE EML EPA ESSAP ft' km m
m2 m3 MDA Nal NIST NMSS NRC ORISE pCi/g SFC UF6 Kerr-Mc:Gec Corporation, Cresent OK-November 13, 1995 microroentgens per hour microrem per hour Atomic Energy Commission American Society of Mechanical Engineers centimeter square centimeter counts per minute Decontamination and Decommissioning Designated Area Pile Department of Energy Environmental Measurements Laboratory Environmental Protection Agency Environmental Survey and Site Assessment Program cubic feet kilometer meter square meter cubic meter minimum detectable activity sodium iodide National Institute of Standards and Techµology Office of Nuclear Material Safety and Safeguards Nuclear Regulatory Commission Oak Ridge Institute for Science and Education picocuries per gram Sequoyah Fuels Corporation uranium hexafluoride iv h:\\esaap\\reporta\\cimam>n\\cimarron.002
CONFIRMATORY SURVEY FOR THE SOUTH URANIUM YARD REMEDIATION KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT,OKLAHOMA INTRODUCTION AND SITE HISTORY The Kerr-McGee Corporation operated the Cimarron facility in Crescent, Oklahoma to produce slightly enriched (approximately 3% U-235) uranium fuel and mixed oxide (uranium plus plutonium) fuel between 1965 and 1975. These activities were conducted under License SNM-928 with the Atomic Energy Commission (AEC), predecessor to the Nuclear Regulatory Commission (NRC). In 1983, Sequoyah Fuels Corporation (SFC) became the owner of the Cimarron Facility, when Kerr-McGee Nuclear Corporation was divided into SFC and Quivira Mining Corporation.
Subsequently, Cimarron Corporation, a subsidiary of the Kerr-McGee Nuclear Corporation, became responsible for the Cimarron Facility.
Cimarron Corporation has discontinued fuel production activities and is in the process of performing the decontamination to terminate the NRC licensing restrictions. The decontamination and decommissioning (D&D) project was divided into several phases, which involved the Mixed Oxide Plant, the Uranium Plant, the On-site Burial Ground, and the Sanitary Lagoons.
As part of the overall D&D effort, remediation of contaminated soil at the Cimarron Facility began as early as 1976. This soil is contaminated, primarily, with low-enrichment uranium; however, areas of thorium-contaminated soil, presumed to have been brought to the Cimarron Facility from the Kerr-McGee site at Cushing, have been identified (Cimarron 1994a). Plutonium contamination was confined, primarily, to the interior surfaces of the Mixed Oxide Plant as well as isolated locations in the soil areas immediately adjacent to the building. There were no elevated levels of plutonium identified in the survey of the Sanitary Lagoons (ORISE 1991a,b); therefore, plutonium is not considered as a likely contaminant in this area.
The restricted area south of the Uranium Plant (Building 1), referred to as the South Uranium Yard, contained the Tank Storage Facility (Building 2), the Solvent Extraction Facility Kcrr*McGcc Corporation, Cn:aent OK*Novcmbcr 13, 1995 h: \\caaap\\reporta\\cimarron\\cimarron. 002
(Building 3), the UF6 (uranium hexafluoride) Receiving Area (Vaporizer Room in Building 1),
and adjacent yard areas. Site operations resulted in a number of spills and overflows that caused contamination of soil beneath the flooring in these structures and the adjacent yard areas.
Remediation of the South Uranium Yard area was initiated with the removal of Buildings 2 and 3 in 1989 and 1990. The concrete floor of the Vaporizer Room was removed in 1992 and soil characterization was performed from May to June 1992. The South Uranium Yard areas were characterized in 1993 (Cimarron 1994b).
The contaminated soil at this facility was characterized and sorted into Option 1, Option 2, and Option 4 categories, according to the NRC Branch Technical Position on "Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations" (U.S. NRC 1981). The Option 1 soil was left in place. Option 2 soil has been stockpiled, in anticipation of being permanently relocated to the on-site disposal cells. Option 4 soil has been removed and shipped off-site for disposal.
On May 4 and 5, 1994, the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) performed a confirmatory survey of two Option 2 soil piles, adjacent to the Uranium Plant (ORISE 1994). Since the time of that survey, further soil excavation at the site has resulted in the establishment of one additional Option 2 soil pile, referred to as Designated Area Pile 3 (DAP-3).
At the request of the NRC's Division of Waste Management, Office of Nuclear Material Safety and Safeguards (NMSS), ESSAP performed an independent confirmatory survey of the South Uranium Yard area and the new Option 2 soil pile (DAP-3) at the Kerr-McGee Cimarron Facility, in Crescent, Oklahoma on April 24 and 25, 1995.
Kerr-McGee Corporation, CreacntOK-November 13, 1995 2
b:\\esaap\\reporta\\cimarron\\cimarron.002
SITE DESCRIPTION The Kerr-McGee Corporation, Cimarron Facility is located on a site of approximately 450 hectares (1,100 acres) in Logan County, Oklahoma, about 8 kilometers (km [5 miles]) south of Crescent (Figure 1). The main facilities at this site were the Uranium Plant and the Mixed Oxide Plant (Figure 2). Directly south of the Uranium Plant, the South Uranium Yard remediation includes the soil area beneath the previous Vaporiz.er Room, the excavated soil beneath the former Building 2 location, and adjacent yard areas. Additionally, the Option 2 soil pile (DAP-3),
created since the time of the last ES SAP survey, is located on-site (Figure 4).
OBJECTIVES The objectives of the confirmatory process are to provide independent document reviews and radiological data, for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and final status survey results.
DOCUMENT REVIEW As part of the confirmatory activities, ESSAP reviewed the licensee's analytical procedures and methods for adequacy and appropriateness.
Licensee's data were reviewed for accuracy, completeness, and compliance with applicable NRC guidelines.
PROCEDURES On April 24 and 25, 1995, ESSAP performed a confirmatory survey of the South Uranium Yard area and the DAP-3 soil pile at the Kerr-McGee Cimarron Facility, in Crescent, Oklahoma. The survey was conducted in accordance with a survey plan dated April 19, 1995, submitted to and approved by the NRC's Division of Waste Management, NMSS (ORISE 1995). This report summarizes the procedures and results of the survey.
Kerr-McGee Corporation, Creacot OK-November 13, 1995 3
h: \\esaap\\rcporta\\cimarron\\cimarron.002
SURVEY PROCEDURES Reference Grid FSSAP used the reference grid system (10 m x 10 m) established by the licensee for referencing survey data. Measurement and sampling locations on ungridde.d surfaces were referenced to either prominent site features or the existing grid.
Surface Stans Exterior soil surfaces were scanned for gamma radiation using NaI scintillation detectors. A 50%
area coverage scan of the South Uranium Yard and the DAP-3 soil pile was performed. All detectors were coupled to ratemeters with audible indicators. Locations of elevated direct radiation detected by scans were marked for further investigation.
EXl)osure Ra1i: Measurements Exposure rates were measured at 1 m above the surface at twenty-eight surface and subsurface locations and at nine locations in the DAP-3 soil pile using a microrem meter. Background exposure rate measurements were performed at six locations within a 0.5 to 10 km radius of the site. Measurement locations are shown on Figures 3 through 5.
S.oil Sampling A total of 25 surface soil samples (0 to 15 cm), in addition to ten subsurface soil samples from three boreholes, was collected at randomly selected locations from soil excavations beneath the Vaporizer Room, the former Building 2 location, and adjacent yard areas. Sample locations are shown on Figure 3. Sampling depths for the three boreholes are indicated in Table 1.
Kerr-McGee Corporation, Crcscnt OK-November 13, 1995 4
h: \\Cllllllp\\rq,orta\\cimam>n\\cimarron.002
Nme soil samples were collected from the DAP-3 soil pile. Measurement locations are shown on Figure 4.
Background soil samples were collected from each background exposure rate measurement location (Figure 5).
Confirmatory Analyses Six soil samples were selected from the licensee's sample archive for confirmatory analysis. The basis for selection of these samples was to provide a range of activities, from approximately 100 to 800 pCi/g of total uranium. Analytical results for these samples were compared to those reported by the licensee.
SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data were returned to ORISE' s ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Soil samples were.analyzed by gamma spectrometry and alpha spectrometry.
Spectra were reviewed for U-235 and U-238, and any other identifiable photopeaks. Selected soil samples were also analyzed by alpha spectrometry for uranium. All six background soil samples were analyzed by both alpha and gamma spectrometry. Soil sample results were reported in units of picocuries per gram (pCi/ g). Exposure rate measurements were reported in units of microroentgens per hour (µR/h). Results were compared with the licensee's documentation and NRC guidelines established for release to unrestricted use.
Kerr-McGee Corporation, Crcscnt OK-November 13, 1995 5
b: \\cuap\\rcporta\\cimarron\\cimarron. 002
FINDINGS AND RESULTS SURVEY REsuLTS Surface Scans Surface scans for gamma activity within the South Uranium Yard soil area resulted in the identification of one area of elevated direct radiation originating at the middle of the Uranium Plant (at approximately the 115E line) and extending to the south fenceline. A whitish material, to a depth of 0.5 m, was noted within this area. Samples #6 and #21 from the South Uranium Yard were collected from this material (Figure 3).
Surface scans for gamma activity within the DAP-3 soil pile did not identify any locations of elevated direct radiation.
E;xposure~
Background exposure rates at 1 m above the surface ranged from 6 to 8 µR/h, with an average of 7 µR/h.
Exposure rates at the twenty-five surface soil locations and the three borehole locations in the South Uranium Yard ranged from 6 to 13 µR/h and 7 to 8 µR/h, respectively.
Exposure rates at the nine locations in the DAP-3 soil pile ranged from 8 to 9 µR/h.
Radionuclide Concentrations in Sml Samples Radionuclide concentrations in background soil samples are summarized in Tables 1 and 2, for gamma and alpha spectrometry analyses, respectively. The total uranium concentrations in background soil samples determined by gamma spectrometry ranged from 0.8 to 2.3 pCi/g (with an average of 1.6 pCi/g), and alpha spectrometry ranged from 0.80 to 1.86 pCi/g.
Kerr-McGee Corpol'lltion, Crcacnt OK-November 13, 1995 6
h:\\csaap\\rcporta\\cimarron\\cimarron.002
For this survey, five samples from the South Uranium Yard and DAP-3 soil pile were analyzed by alpha spectrometry for isotopic uranium. The uranium concentrations for these samples are summarized in Table 2. This analysis indicated an average U-234 to U-235 ratio of approximately
- 20. This same U-234 to U-235 ratio was used by ESSAP to calculate the total uranium concentrations in soil samples that were analyzed by gamma spectrometry.
Concentrations of radionuclides in soil samples from the South Uranium Yard and DAP-3 soil pile are summariz.ed in Table 1. Concentrations of radionuclides in surface soil samples ranged from
< 0.1 to 1.2 pCi/g for U-235, 0.9 to 5.6 pCi/g for U-238, and 2. 7 to 29.6 pCi/g for total uranium. The average total uranium concentration for surface soil samples was 11 pCi/g.
Concentrations of radionuclides in subsurface soil samples ranged from <0.1 to 1.5 pCi/g for U-235, 0.3 to 6.9 pCi/g for U-238, and 1.2 to 38.4 pCi/g for total uranium, with an average total uranium concentration of 9.5 pCi/g. Concentrations of radionuclides in the DAP-3 soil pile ranged from 0.7 to 1.8 pCi/g for U-235, 3.5 to 6.5 pCi/g for U-238, and 18. 7 to 41.8 pCi/g for total uranium, with an average total uranium concentration of 29 pCi/g.
Confinnatoa Analyses The results of the confirmatory analyses of soil samples, which were selected by ESSAP and provided by the licensee, are also presented in Table 1. Previously, a disagreement between ESSAP and the licensee for samples with total uranium concentrations greater than 100 pCi/ g was identified (ORISE 1994). Thus, the confirmatory samples were selected to provide a range of activities between 100 and 800 pCi/g, total uranium.
Consequently, the radionuclide concentration values in these samples are not normally distributed. Therefore, in order to compare ESSAP and the licensee's analytical results, the nonparametric Wilcoxon Signed Ranks test was performed. The null hypothesis was that there were no differences between the licensee's and ES SAP' s analytical results. The results of the Wilcoxon Signed Ranks test indicated, as a whole, ESSAP's and the licensee's analytical results are statistically identical (p>0.6).
Kerr-McGee Corpontion, Creacot OK-November 13, 1995 7
h: \\cuap\\rcporta\\cimarron\\cimarron.002
COMPARISON OF RESULTS WITH GUIDELINES The primary contaminant of concern for this site is enriched uranium. The generic guidelines for residual concentrations of uranium in soil are provided in the NRC Branch Technical Position on "Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations" (NRC 1981).
Specifically, the Option 1 average soil guideline for enriched uranium is 30 pCi/g, and the Option 2 average soil guideline is 100 pCi/ g.
With the exception of the soil sample (0-15 cm) collected from borehole #1 (38.4 pCi/g total uranium), all soil samples collected from the South Uranium Yard were within the average soil guideline for enriched uranium. This sample was averaged with the results of the twenty-five surface soil samples (12 pCi/g total uranium) to demonstrate that compliance had been achieved.
The soil samples collected from the DAP-3 soil pile were all within the Option 2 average soil guideline.
The exposure rate guideline, measured at 1 m from the surface, is 10 µR/h above background.
Exposure rates measured in the South Uranium Yard were all within this guideline.
SUMMARY
On April 24 and 25, 1995, the Environmental Survey and Site Assessment Program of ORISE performed a confirmatory survey of the South Uranium Yard area and the new Option 2 soil pile (DAP-3) at the Kerr-McGee Cimarron Facility, in Crescent, Oklahoma.
Survey activities included surface scans, exposure rate measurements, and soil sampling.
The ESSAP confirmatory measurements support the licensee's conclusion that residual radioactivity within the South Uranium Yard satisfies NRC guidelines for release to unrestricted use. In addition, the soil contained in DAP-3 meets the Option 2 soil guideline for disposal in on-site cells.
Kerr-McGee Corporation, Cttacnt OK-November 13, 1995 8
h:\\cssap\\rq,orts\\cimarron\\cimarron.002
Results of confirmatory analyses performed on six of the licensee's soil samples indicates that there is no longer a disagreement between ESSAP and the licensee for samples with total uranium concentrations in excess of 100 pCi/g.
Kerr-McGee Corporation, Cresent OK-November 13, 1995 9
h:\\essap\\reporta\\cimarron\\cimarron.002
293-005 (x)
OKLAHOMA N
NOT TO SCALE FIGURE 1: Location of the Cimarron Facility, Crescent, Oklahoma KerT-McGcc Corporation, Creacnt OK-November 13, 1995 10 h: \\esaap\\rcpo11a\\ciman'on\\cimarron.002
293-004 (x)
DAP3 EAST SOIL PILE SOUTH URANIUM YARD
~x~---1)~( ~-)*-( FENCE 1
TO FORMER BURIAL GROUND AREA N
...lL
'Jr' NOT TO SCALE FIGURE 2: The Cimarron Facility -
Plot Plan Kerr-McGee Corporation, Crcaent OK-November 13, 1995 11 h:\\easap\\rcports\\cimarron\\cimarron.002
-~ t *
- .* l t.
... J
- ...I
293-001 (3) 80N 70N SON 50N 2 )I(
40N t
- x*************x************)f.................................. x*************x*************x*.. **********~c*************x............. )i{.JON
@42.5N, 40E 50E 27.5E 60E 70E BOE 90E 100E 110E 120E 1JOE 140E 150E MEASUREMENT /SAMPLING LOCATIONS EXPOSURE RATE MEASUREMENT AND SURFACE SOIL SAMPLE
- ..._ EXPOSURE RATE MEASUREMENT Ja... AND BOREHOLE SAMPLES N
~
'llr' FEET I
METERS FIGURE 3: South Uranium Yard -
Measurement and Sampling Locations Kerr-McGee Corporation. Creacnt OK-November 13. 1995 12 b:\\csaap\\n:porta\\cimarron\\cimarron.002
293-002 (4) 170N 165N 160N 155N 150N w
I.LI 0
tO
<O MEASUREMENT /SAMPLING LOCATIONS
- . EXPOSURE RATE MEASUREMENT AND SURFACE SOIL SAMPLE l.&J tO (0
~>(~----,)~(~----*-)( FENCE GRADIENT/
BOUNDARY 0
N
..JL
'1 ("
FEET 30 O
METERS 10 FIGURE 4: Designated Area Pile #3 -
Measurement and Sampling Locations Kerr-McGee Corporation. Creaent OK-November 13. 1995 13 b:\\c:asap\\reporta\\cimarron\\cimarron.002
I i:
- i f
.,, t,,*...
.-.I*.
l
293-00.3 ( 1 )
CRESCENT CRESCENT SCHOOL 2
- 74 CIMARRON PLANT SITE 4
- MEASUREMENT /SAMPLING LOCATIONS EXPOSURE RATE MEASUREMENT AND SOIL SAMPLE 5
- 6 3
- 0 N
'""1L
'1['
MILES O KILOMETERS 4 77 3
FIGURE 5: Cimarron Site -
Background Measurement and Sampling Locations Kerr-McGee Corporation. Crcaent OK-November 13. 1995 14 h: \\esaap\\reports\\cimarron\\cimarron.002
Location TABLEl URANIUM CONCENTRATIONS IN SOIL SAMPLES (USING GAMMA SPECTROMETRY)
KERR-McGEE CORPORATION,CIMARRON FACILITY CRESCENT, OKLAHOMA Uranium Concentration (pCi/2)
U-238 U-235 South Uranium Yard - Surface Soilb 1
3.8 + 0.9c 0.9 + 0.1 2
3.3 + 0.8 0.5 + 0.1 3
3.1 + 0.8 0.7 + 0.1 4
4.3 + 0.9 0.7 +/- 0.1 5
1.5 + 0.9 0.2 + 0.1 6
5.6 + 1.1 1.2 + 0.1 7
1.1 +0.9
<0.1 8
3.2 + 1.2 0.7 + 0.1 9
3.5 + 1.1 0.7 + 0.1 10 0.9 + 0.7
<0.1 11 1.9 + 1.0
<0.1 12 1.2 + 0.7
<0.1 13 1.9 + 0.7 0.3+/-0.1 14 1.4 + 0.8
<0.1 Total Uranium 8
22.3 14.2 16.4 18.2 6.5 29.6 3.2 17.6 18.0 2.9
.3.4.
2.7 8.4 2.9
I I
J
§ Location 15 16 17 18 19 20 21 22 23 24 25 TABLE 1 (Continued)
URANIUM CONCENTRATIONS IN SOIL SAMPLES (USING GAMMA SPECTROMETRY)
KERR-MCGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA Uranium Concentration (pCi/2)
<0.1 3.4 + 1.2 0.4 + 0.1 1.5 + 0.7 0.3 + 0.1 2.9 + 1.0 0.6 + 0.1 2.1 + 0.9
<0.1 4.4 + 1.1 0.7 + 0.1 2.6 + 1.1
<0.1 3.0 + 1.0 0.5 + 0.1 4.5 + 1.0 0.6 +/- 0.1 1.9 + 0.9 0.4 + 0.1 1.5 + 1.3
<0.1 Avera~e for South Uranium Yard-Surface Soil South Uranium Yard - Subsurface Soilb
- 1 (0 - 15 cm) 6.9 + 1.1 1.5 + 0.1
- 1 (35 - 50 cm) 2.6 + 1.2
<0.1 Total Uranium 8
3.5 12.3 6.9 15.6 3.8 19.2 4.6 12.3 17.1 9.6 3.4 11 38.4 4.0
~
Location
- 1 (85 -100 cm)
- 1 (135 - 150 cm)
- 2 (0 - 15 cm)
- 2 (35 - 50 cm)
- 2 (85 - 100 cm)
- 3 (0 - 15 cm)
- 3 (35 - 50 cm)
- 3 (85 - 100 cm)
TABLE 1 (Continued)
URANIUM CONCENTRATIONS IN SOIL SAMPLES (USING GAMMA SPECTROMETRY)
KERR-MCGEE CORPORATION, CIMARRON FACILITY CRESCENT,OKLAHOMA Uranium Concentration (pCi/2)
<0.1 1.3 + 1.0
<0.1 3.9 + 1.2 0.7 + 0.1 0.8 + 0.9
<0.1 0.3 + 0.6
<0.1 3.8 + 0.9 0.7 + 0.1 1.0 + 0.5 0.2 + 0.1 0.7 + 0.6
<0.1 Average for South Uranium Yard-Subsurface Soil DAP-3 Soil Piled 1
5.1 + 1.3 1.2 +/- 0.1 2
5.4 + 1.4 1.8 + 0.1 3
3.8 + 1.1 0.7 + 0.1 4
3.5 + 1.0 0.9 + 0.1 5
4.7 + 1.2 1.2 +/- 0.1 Total Uranium 8
3.5 2.8 18.2 2.2 1.2 18.8 4.2 2.2 9.5 29.7 41,8 19.1 21.6 28.5
- ~.
... ~
~ \\ ** I
- ,,4'*'
.* J.
I.
. i '"
. ~...
L l,
- -"'r i
t....
. j i)
'l
-i I
I!
1:
- -*-..d' i,
.... -~ -.. : -.,
. '~--.
t
~*..
..... ~
P.' f I f
§ Location 6
7 8
9 Average for DAP-3 Soil Pile Background Soil Samplese,r 1
2 3
4 5
6 TABLE 1 (Continued)
URANIUM CONCENTRATIONS IN SOIL SAMPLES (USING GAMMA SPECTROMETRY)
KERR-MCGEE CORPORATION, CIMARRON FACILITY CRESCENT,OKLAHOMA Uranium Concentration (pCi/2)
U-238 U-235 6.2 +/- 1.2 1.3 + 0.1 4,1 + l.1 1.2 + 0.1 6.5 + 1.0 1.5 + 0.1 4.1 + 1.0 0.7 + 0.1 0.4 + 0.4
<0.1 0.4 + 0.5
<0.1 0.5 + 0.4
<0.1 1.1 + 0.6
<0.1 1.1 +/- 0.7
<0.1 1.1 + 0.6
<0.1 A--, -* fnr :""'
- ~....... ~ ~nil 'L.. -~- -
Total Uranium 8
33.2 29.3 37.1 18.7 29 0.8 0.9 1.0 2.2 2.3 2.2 1 Ii
!.**1
- i
,1......
- i *..
g i\\
' '... ~
t **
j
- \\*
- -
)
,\\*
l!,,f'
.... ~ r*-.. *--.
,_f j
i
'* I
!i 1 -*-~
w Location Confirmatory Analyses
- 212
- 153
- 147
- 457
- 453
- 420 TA.ISLE I (l,;Ontinued)
URANIUM CONCENTRATIONS IN SOIL SAMPLES (USING GAMMA SPECTROMETRY)
KERR-MCGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA Uranium Concentration (pCi/2)
Total Uranium 8
U-238 U-235 ESSAP 35.87 + 1.39 7.69 + 0.12 195.1 21.30 + 0.98 3.58 + 0.07 95.4 162.90 + 1.91 30.75 + 0.20 799.4 8.46 + 1.03 10.85 + 0.15 233.1 16.67 + 0.64 4.79 + 0.08 115.8 21.67 + 0.91 11.39 + 0.12 257.4 Licensee 215 99 786 249 135 197 8Total uranium was calculated by the sum of U-238, U-235, and U-234, using an U-234:U-235 activity ratio of 20, based on alpha spectrometry results.
bRefer to Figure 3.
cuncertainties represent the 95 % confidence level, based only on counting statistics.
dRefer to Figure 4.
eRefer to Figure 5.
rTotal uranium concentrations for background samples are based on natural isotopic abundances.
. -~
. :~.;...
~....
E:
It
- .*.1 n
.i.
- j~* *
(\\1
- ~. :~
I.
,.J r
,J*
. '~*~.
- _\\
TABLE2 ISOTOPIC URANIUM CONCENTRATIONS IN SOIL SAMPLES KERR-MCGEE CORPORATION, CIMARRON FACILITY CRESCENT,OKLAHOMA Uranium Concentration (pCi/ ~)
Location U-238 U-235 U-234 South Uranium Yard-Surface Soilb 6
4.57 + 0.33c 1.04 +/- 0.18 20.92 + 0.70 20 4.15 + 0.27 0.66 + 0.12 15.31 + 0.53 South Uranium Yard - Boreholeb
- 1 (0-15 cm) 7.53 + 0.44 1.81 + 0.24 31.54 + 0.90
- 3 {0-15 cm) 3.28 +/- 0.25 0.65 + 0.13 13.65 + 0.52 DAP-3 Soil Piled 2
5.28 + 0.30 2.34 +/- 0.22 46.61 + 0.89 Backeround Soil Samplese 1
0.41 + 0.11
<0.07 0.55 + 0.13 2
0.38 + 0.10
<0.08 0.42 + 0.11 3
0.49 + 0.11
<0.07 0.57 + 0.13 4
0.79 + 0.13
<0.06 0.90 + 0.14 5
0.90 + 0.15
<0.11 0.91 + 0.16 6
0.71 +/- 0.13
<0.06 0.59 + 0.12 Confirmatory Analyses
- 457 9.93 + 0.75 10.00 + 0.86 283.7 + 4.0 8Total uranium calculated based on the sum of U-238, U-235, and U-234.
~efer to Figure 3.
Total Uranium8 26.52 + 0.80 20.12 +/- 0.61 40.9 + 1.0 17.58 + 0.59 54.23 +/- 0.96 0.97 + 0.18 0.80 +/- 0.15 1.09 + 0.18 1.72 + 0.19 1.86 + 0.23 1.34 +/- 0.19 303.6 + 4.2 cuncertainties represent the 95 % confidence level, based only on counting statistics..
- dRefer to Figure 4.
"Refer to Figure 5.
Kerr-McGee Corpo111tion. Creacnt OK-November 13. 199S 20 h: \\caaap\\reporta\\cimarron\\cimarron.002
jl*-*****-***
l:*
I:....
~ i r*
,.. -.... i.
I,*..
i,.-*
i}
~
,* ~... _; *'....
-~.::. }
- 1 ***
,.... : ~...
..,... \\.
REFERENCES Cimarron Corporation, "Report of Characterization of Option 2 Stockpiled Soil," prepared by Karen Morgan, May 4, 1994a.
Cimarron Corporation, "Report on the South Uranium Yard Remediation at the Cimarron Facility," November 1994b.
Oak Ridge Institute for Science and Education, "Confirmatory Survey of the Cimarron Corporation Mixed Oxide Fuel Fabrication Plant, Crescent, Oklahoma," January 1991a.
Oak Ridge Institute for Science and Education, "Confirmatory Radiological Survey of the Sanitary Lagoons at the Cimarron Corporation Facility, Crescent, Oklahoma," November 1991b.
Oak Ridge Institute for Science and Education, "Confirmatory Radiological Survey of Two Soil Piles Proposed for On-Site Storage, Kerr-McGee Corporation, Cimarron Facility, Crescent, Oklahoma," October 1994.
Oak Ridge Institute for Science and Education, "Confirmatory Survey Plan for the South Uranium Yard Remediation, Kerr-McGee Corporation, Cimarron Facility, Crescent, Oklahoma (Docket No.79-925)," April 19, 1995.
U.S. Nuclear Regulatory Commission, "Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations," 46 FR 52061, Washington, D.C., October 23, 1981.
Kerr-McGee Corporation. Creacnt OK-November 13, 1995 21 h: \\cuap\\rcporta\\cimarron\\cimarron.002
. *.;*, :~: i./ * *J ' *. ~.
l
~ :
i
, \\
J; *-
,.*-. i
.*:--*.. * ** **1,
. *',. ~.. :
- ',t.'
). ~*
tl * 't;,-*-*;I j.
..:.... t.
1.:..
- ! ! ~.
- ~. ;
I
- ~. t
... ~ _:....
- 1
.,,/
~ !I*..
r,;.,
- I f,._: ~ '.
- .1 1* -'
. <: r:,.-!*
1....
,'. 1. *~.
APPENDIX A MAJOR INSTRUMENTATION Kerr-McGee Corporation, Crcscnt OK-November 13, 1995 h: \\cssap\\rcports\\cimarron\\cimarron.002
.'\\.
APPENDIX A MAJOR INSTRUMENTATION The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the author or his employer.
DIRECT RADIATION MEASUREMENT Instruments Bicron Micro-Rem Meter (Bicron Corporation, Newbury, OH)
Eberline Pulse Ratemeter Model PRM-6 (Eberline, Santa Fe, NM)
Ludlum Ratemeter-Scaler Model 12 (Ludlum Measurements, Inc.,
Sweetwater, TX)
Detectors Victoreen Nal Scintillation Detector Model 489-55 3.2 cm x 3.8 cm Crystal (Victoreen, Cleveland, OH)
Laboratory Analytical Instrumentation High Purity Extended Range Intrinsic Detectors Model No: ERVDS30-25195 (Tennelec, Oak Ridge, TN)
Used in conjunction with:
Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, TN) and Multichannel Analyzer 3100 Vax Workstation (Canberra, Meriden, CT}
Kcrr*MeGce Corporation, Crcscnt OK*Novcmbcr 13, 1995 A-1 h:\\essap\\reporta\\cimarron\\cimanon.002
' * '\\~ I *
,.\\,:.
, ~: ;,
r' ; ~...,;.::._ " J
- r,~... " *.. '..
- ,
' * ; *,,1. I'
.,.~
-.\\* i..
~..
" ** : i ** \\.{'.~::
- ._ ~...,
i: ~~-. ' :_ *-
'+.
- ~.~
- ~.,-.:. '*.:.-~ f !._\\ f)..
- ;.~-*-
.~ :. :
.. i
'~.
High-Purity Germanium Detector Model GMX-23195-S, 23% Eff.
(EG&G ORTEC, Oak Ridge, TN)
Used in conjunction with:
Lead Shield Model G-16 (Gamma Products, Palos Hills, IL) and Multichannel Analyzer 3100 Vax Workstation (Canberra, Meriden, CT)
Kerr-McGee Corporation, Crcaent OK-November 13, 1995 A-2 b:\\c:asap\\rq,orts\\cinwron\\cimarron.002
. !~ ' '..'
- r**
!~ :.*
- _; I * '.
'. ~*
- ',,} *:.
l
.' ~
APPENDIXB SURVEY AND ANALYTICAL PROCEDURES Kerr-McGee Corporation, Creacnt OK-November 13, 1995 h: \\C8118p\\rcporta\\cimarron\\cimarron.002
\\,*':'*
- ,*1.1
<r:*,.
APPENDIXB SURVEY AND ANALYTICAL PROCEDURES SURVEY PROCEDURES Surface Scans Surface scans for gamma activity were performed by passing the probes slowly over the surface; the distance between the probe and the surface was maintained at a minimum. The boreholes were also scanned for elevated direct radiation. Identification of elevated levels was based on increases in the audible signal from the recording and/ or indicating instrument. Combinations of detector and instruments used for scans were:
Gamma - NaI scintillation detector with ratemeter.
Exposure ~
Measurements Measurements of gamma exposure rates were performed using a microrem meter. The microrem meter was positioned one meter above the surface and allowed to stabilize. Although the microrem meter displays data in µrem/h, the µrem/h to µR/h conversion factor is essentially unity.
5.ml Sampling Approximately 1 kg of soil was collected at each sample location. Surface soil samples were collected at 0-15 cm depth. Samples from boreholes were collected from the surface (0-15 cm),
the center (85-100 cm), and the bottom (185-200 cm) of each borehole. Collected samples were placed in a plastic bag, sealed, and labeled in accordance with ESSAP survey procedures.
Kerr-McGee Corporation, Creacnt OK-November 13, 1995 B-1 h:\\easap\\rcporta\\cimarron\\cimarron.002
- ., '~
- . ;,:.' (.,.
1 * ~~*.....,
- ,~;*; ;
't'-'
, *-~ '
,1**.
- -i::.
d
'~
i J
.,I, i.',.. ~.
~. I
- I
\\
._:. ~' '
,.* l':':
f*,_.
- '.h
- .:.t; l '"*
- .. "~~. ! : ; *
- .... ~" ~ *,
l-,*
- -~
11*.. *,*
- -~
,.* 1;*.
ANALYTICAL PROCEDURES Gamma Spectrometry Samples of soil were dried, mixed, crushed, and/or homogenized as necessary, and a portion sealed in 0.5-liter Marinelli beaker or other appropriate container. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry. Net material weights were detennined and the samples counted using intrinsic germanium detectors coupled to a pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:
U-235 U-238 0.186 MeV 0.063 MeV from Th-234*
- Secular equilibrium assumed.
Spectra were also reviewed for other identifiable photopeaks.
Alpha Spectrometry Soil samples were crushed, homogenized and analyzed for isotopic uranium. Samples were dissolved by potassium fluoride and pyrosulfate fusion and the elements of interest were participated with barium sulfate. Barium sulfate participate was redissolved and the specific elements of interest were individually separated by liquid-liquid extraction and re-precipitated with a cerium fluoride carrier. The precipitate was then counted using surface barrier and ion implanted detectors (ORTEC), alpha spectrometers (Tennelec and Canberra), and a multichannel analyzer (Nuclear Data).
Kerr-McGee Corporation, Crcscnt OK-November 13, 1995 B-2 b: \\cuap\\rcports\\cimarron \\cimarron.002
~ j/ 41 L
- .r----*
,,.l i';
r,:
- -,**t:.
- .i.. t..
.,_... -~ '\\
. r* ; ****
- , "'~
,.~ :.
,,.i*
.J'
.i!~
~.. *,
- . ~.. ~-...
i'l*,:
J ; * *..
r ;,:.:...; __
'.I
UNCERTAINTIES AND DETECTION LIMITS The uncertainties associated with the analytical data presented in the tables of this report represent the 95 % confidence level for that data based only on counting statistics. Additional uncertainties associated with sampling and measurement procedures have not been propagated into the data presented in this report.
Detection limits, referred to as minimum detectable activity (MDA), were based on 2.71 plus 4.65 times the standard deviation of the background count. When the activity was determined to be less than the MDA of the measurement procedure, the result was reported as less than MDA.
Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.
CALIBRATION AND QUALITY ASSURANCE Calibration of all field and laboratory instrumentation was based on standards/sources, traceable to NIST, when such standards/ sources were available. In cases where they were not available, standards of an industry recognized organization were used.
Analytical and field survey activities were conducted in accordance with procedures from the following ESSAP documents:
Survey Procedures Manual, Revision 8 (December, 1993)
Laboratory Procedures Manual, Revision 9 (January, 1995)
Quality Assurance Manual, Revision 7 (January, 1995)
The procedures contained in these manuals were developed to meet the requireme~ts of DOE Order 5700.6C and ASME NQA-1 for Quality Assurance and contain measures to assess processes during their performance.
Kerr-McGee Corporation, Creaent OK-November 13, 1995 B-3 b:\\esaap\\reporta\\cimarron\\cimarron.002
,.,.',l
. i.:
~.. : /'....
. *J.
t,:;*
lj,
.,,J._ ** _
~ J * : :. : *.
- i.,*.
- ,*i:-.:,_-
-**~*.; :: ~
~ i.
,.~.-:--!.-
~ ~.*
- _... _*l..
- r.
,I
... { ~
- '.lt, *
- f
- ., *_* I -;:..:::
.J.
~ :..-
- .\\ :_,*
... *. ! ~'
t-7.. -..,:. )
I
~.. ' '*
i-i.*
,,"1.*,._.:,,*:.::,
- . ~*
_: (
_,.i
.. ~-.
Quality control procedures include:
Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations.
Participation in EPA and EML laboratory Quality Assurance Programs.
Training and certification of all individuals performing procedures.
Periodic internal and external audits.
Kerr-McGee Corporation, Creaent OK-November 13, 1995 B-4 h:\\caaap\\rcporta\\c~n\\cimanon.002
- ,.*1--:*
'111,*.*.... !. :
/
- .\\..
,.*-a,
, }
..~ !.
'.'t;' i
.. :, _.., ~** *.
APPENDIXC GUIDELINES FOR RESIDUAL CONCENTRATIONS OF THORIUM AND URANIUM WASTES IN SOIL Ke,r.McGcc Corpomtion. CRIICDt OK-November 13. 1995 b: \\eaaap\\reporta\\cimarron\\cimarron.002
-.... *,* : :..'.*... ~,.
... -~....
\\':., c '. ;*:,;:
~
~..
GUIDELINES FOR RESIDUAL CONCENTRATIONS OF THORIUM AND URANIUM WASTES IN SOIL On October 23, 1981, the Nuclear Regulatory Commission published in the Federal register a notice of Branch Technical Position on "Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations.
0 This document established guidelines for concentrations of uranium and thorium in soil, that will limit maximum radiation received by the public under various conditions of future land usage.
These concentrations are as follows:
Material Natural Thorium (Th-232 + Th-228) with daughters present and in equilibrium Natural Uranium (U-238 + U-234) with daughters present and in equilibrium Depleted Uranium:
Soluble Insoluble Enriched Uranium:
Soluble Insoluble Maximum Concentrations (pCi/g) for various options 10 10 35 35 30 30 50 100 300 100 250 40 500 200 1,000 3,000 1,000 2,500 8Basecf on EPA cleanup standards which limit radiation to 1 mrad/yr to lung and 3 mrad/yr to bone from ingestion and inhalation and 10 µR/h above background from direct external exposure.
bBased on limiting individual dose to 170 mrem/yr.
cBased on limiting equivalent exposure to 0.02 working level or less.
dBased on limiting individual dose to 500 mrem/yr and in case of natural uranium, limiting exposure to 0.02 working level or less.
Kcrr-McGc:c Corpomtion, Crcsent OK-November 13, 1995 C-l h:\\caaap\\reporta\\cimarron\\c:imarron.002
\\. ' ':
~"\\
'\\.. ~ :
- 4
- .\\*,* ()
l
~ *.. ;
- ,[
.:_t
- i.
. :: u
'.'.tf~
~
', '.i ~
\\,.\\': * *.
~
,. ~.;
j.