ML19106A235

606 - Final Report - Confirmatory Survey of the Phase I Unaffected Areas, Kerr-McGee Corportation, Cimarron Facility, Crescent, Ok

ML19106A235
Person / Time
Site:	07000925
Issue date:	03/29/1996
From:	Abelquist E Oak Ridge Institute for Science & Education
To:	Fauver D Office of Nuclear Material Safety and Safeguards
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0 RISE OAK RIDGE INSTITUTE FOR SCIENCE ANO EDUCATION March 29, 1996 Mr. David Fauver U.S. Nuclear Regulatory Commission Division of Waste Management - NMSS Two White Flint North T-8F3 7 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

FINAL REPORT - CONFIRMATORY SURVEY OF THE PHASE I UNAFFECTED AREAS, KERR-McGEE CORPORATION, CIMARRON FACILITY, CRESCENT, OKLAHOMA (DOCKET NO. 79-0925; RFTA 96-01)

Dear Mr. Fauver:

The Environmental Survey and Site Assessment Program (ESSAP) of ORISE conducted a confirmatory survey of the Phase I Unaffected Areas at Kerr-McGee's Cimarron Facility in Crescent, Oklahoma on October 17 through 19, 1995. Confirmatory survey activities included surface scans, exposure rate measurements, and soil sampling.

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,

i;

Eric W. Abelquist Assistant Program Director Envirpnmental Survey and Site Assessment Program EWA:tsf Enclosure cc:

R. Uleck, NRC/NMSS/TWFN 7F27 D. Tiktinsky, NRC/NMSS/TWFN 8A23 W. Beck, ORISE/ESSAP J. Payne, ORISE/ESSAP IBite/606 P. 0. BOX 117, OAK RIDGE, TENNESSEE 37831-0117 Managed and operated by Oak Ridge Associated Universities for the U.S. Department of Energy

CONFIRMATORY SURVEY OF THE PHASE I UNAFFECTED AREAS KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA

[DOCKET 70-0925]

J. L.PAYNE Prepared for the Division of Waste Management U.S. Nuclear Regulatory Commission Headquarters Office

The Oak Ridge Institute for Science and Education (ORISE) was established by the U.S. Department of Energy to undertake national and international programs in science and engineering education, training and management systems, energy and environment systems, and medical sciences. ORISE and its programs are operated by Oak Ridge Associated Universities (ORAU) through a management and operating contract with the U.S. Department of Energy. Established in 1946, ORAU is a consortium of 82 colleges and universities.

NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.

This report was prepared as an account of work sponsored by the United States Government. Neither the United States Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights.

Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

CONFIRMATORY SURVEY OF THE PHASE I UNAFFECTED AREAS KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT,OKLAHOMA Prepared by J. L. Payne Environmental Survey and Site Assessment Program Environmental and Health Sciences Division 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 MARCH1996 FINAL REPORT ORISE 96/C-49 This report is based on work performed under an Interagency 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-ACOS-760R00033 with the U.S. Department of Energy.

Kerr-McGee Corporation, Cresent, OK - March 4, 1996 h:\\essap\\reports\\cimarron\\cimarron.003

CONFIRMATORY SURVEY OF THE PHASE I UNAFFECTED AREAS KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA Prepared by: -fr.r~* ~

J.~Payne, Field Surv~ader Environmental Survey and Site Assessment Program Reviewed by:

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M. J. Laudeman, Radiochemistry Laboratory Supervisor Environmental Survey and Site Assessment Program Reviewed by:

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A. T. Payne, Administrativ~ ~anager Safety and Quality Assurance Officer Environmental Survey and Site Assessment Program

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Reviewed by:

E. W. Abelquist, Assistantograml)ictor Environmental Survey and Site Assessment Program Reviewed by: ~

W. L. Beck, Program Director Environmental Survey and Site Assessment Program Kerr-McGee Corporation, Cresent, OK - March 4, 1996 Date: 3/J~Ju 1

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ACKNOWLEDGMENTS The author would like to acknowledge the significant contributions of the following staff members:

Kerr-McGee Corporation. Cresent, OK - March 4. 1996 FIELD STAFF T. D. Herrera A. L. Mashburn LABORATORY STAFF R. D. Condra J.

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Cox M. J.

Laudeman S. T. Shipley CLERICAL STAFF T. S.

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TABLE OF CONTENTS PAGE List of Figures............................................................... ii List of Tables................................................................ iii Abbreviations and Acronyms................................................... iv Introduction and Site History..................................................... 1 Site Description............................................................... 2 Objectives................................................................... 2 Document Review............................................................. 2 Procedures................................................................... 2 Findings and Results........................................................... 4 Comparison of Results with Guidelines............................................ 5 Summary.................................................................... 5 References.................................................................. 20 Appendices:

Appendix A:

AppendixB:

Appendix C:

Major Instrumentation Survey and Analytical Procedures Guidelines for Residual Concentrations of Thorium and Uranium Wastes in Soil Kerr-McGee Corporation, Crescnt, OK-March 4, 1996 i

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LIST OF FIGURES PAGE FIGURE 1:

Location of the Cimarron Facility, Crescent, Oklahoma.................. 6 FIGURE 2:

Plot Plan of the Cimarron Facility - Phase I Areas Showing Grid Blocks Surveyed............................................. 7 FIGURE 3:

Unaffected Area A, Grid 200S,OE-Measurement and Sampling Locations.............................................. 8 FIGURE 4:

Unaffected Area A, Grid 400S,300E-Measurement and Sampling Locations.............................................. 9 FIGURE 5:

Unaffected Area B, Grid 300N,800E-Measurement and Sampling Locations............................................. 10 FIGURE 6:

Unaffected Area B, Grid 500N,1200E-Measurement and Sampling Locations............................................. 11 FIGURE 7:

Unaffected Area C, Grid 900N,IOOOE-Measurement and Sampling Locations............................................. 12 FIGURE 8:

Unaffected Area C, Grid 800N,400E-Measurement and Sampling Locations............................................. 13 FIGURE 9:

Unaffected Area D, Grid 900N,200E-Measurement and Sampling Locations............................................. 14 FIGURE 10:

Unaffected Area D, Grid 600N,IOOE-Measurement and Sampling Locations............................................. 15 FIGURE 11:

Unaffected Area E, Grid 800N,IOOW-Measurement and Sampling Locations............................................. 16 FIGURE 12:

Unaffected Area E, Grid 500N,200W-Measurement and Sampling Locations............................................. 17 Kerr-McGee Corporation, Cresent, OK-March 4, 1996 ii h:\\essap\\reports\\cimarron\\cimarron.003

LIST OF TABLES PAGE TABLE 1:

Exposure Rates and Uranium Concentrations in Soil Samples............ 18 Kerr-McGee Corporation, Cresent, OK - March 4, 1996 iii h:\\essap\\reports\\cimarron\\cimarron.003

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ABBREVIATIONS AND ACRONYMS

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MDC MOFF Nal NIST NRC ORISE pCi/g SFC U-Plant Kerr-McGee Corporation, Cresent, OK - March 4, 1996 microroentgens per hour microrem per hour Atomic Energy Commission American Society of Mechanical Engineers centimeter decontamination and decommissioning Department of Energy Environmental Measurements Laboratory Environmental Protection Agency Environmental Survey and Site Assessment Program Global Positioning System kilogram kilometer Kerr-McGee Corporation meter minimum detectable concentration Mixed Oxide Fuel Fabrication sodium iodide National Institute of Standards and Technology Nuclear Regulatory Commission Oak Ridge Institute for Science and Education picocuries per gram Sequoyah Fuels Corporation Uranium Fuel Fabrication Facility iv h:\\essap\\reports\\cimarron\\cimarron.003

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CONFIRMATORY SURVEY OFTHE PHASE I UNAFFECTED AREAS KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA INTRODUCTION AND SITE IDSTORY The Kerr-McGee Corporation (KMC) operated two plants at the Cimarron Facility between 1965 and 1975 under two Atomic Energy Commission (AEC) licenses. License SNM-928 was issued in 1965 for the Uranium Fuel Fabrication (U-Plant) Facility and license SNM-1174 was issued in 1970 for the Mixed Oxide Fuel Fabrication (MOFF) Facility. In 1983, Sequoyah Fuels Corporation (SFC) became the owner of the Cimarron Facility, when KMC was divided into SFC and Quivira Mining Corporation. Subsequently, Cimarron Corporation, a subsidiary of KMC, became responsible for the Cimarron Facility.

The decontamination and decommissioning (D&D) work began in 1976. D&D activities at the MOFF Facility were completed in 1990. KMC applied to the Nuclear Regulatory Commission (NRC), formerly the AEC, on August 20,

• 1990 for the termination of license SNM-1174 and it was terminated on February 5, 1993. However, the NRC did not release the land formerly licensed under SNM-1174 and contained within the bounds of the Cimarron Facility and license SNM-928. A large portion of the land contained within the bounds of license SNM-928 was divided into five areas totaling approximately 240 hectares (Cimarron 1995).

KMC had no evidence that would suggest that radioactive materials were disposed of in any of these five areas during nuclear fuel fabrication operations and/or subsequent decommissioning activities.

Therefore, KMC classified the areas (A,B,C,D, and E) as unaffected and refers to them as the Phase I unaffected areas in their final status survey report (Cimarron 1995). Unaffected areas are defined as those areas that are not expected to contain residual contamination.

It is the policy of the NRC to perform confirmatory surveys of facilities that have undergone decommissioning and have requested NRC license termination. The NRC's Division of Waste Management requested that the Environmental Survey and Site Assessment Program Kerr-McGee Corporation, Cresent, OK - March 4, 1996 h: \\essap\\reports\\cimarron\\cimarron.003

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(ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conduct a confirmatory survey of the land areas designated as the Phase I unaffected areas at the Cimarron Corporation Facility in Crescent, Oklahoma. This report describes the results of the survey.

SITE DESCRIPTION The Cimarron Facility is located approximately 8 kilometers (km) south of the city of Crescent, Oklahoma and approximately 0.8 km north of the intersection of Oklahoma State Highways #33 and

1. 7 4 in Logan County (Figure 1 ). The terrain of the region is rolling pasture land. Site elevations range from 286 to 309 meters above sea level. The entire Cimarron site encompasses approximately 340 hectares. The total size of the five unaffected areas, which consist of mostly pastureland and newly planted winter wheat fields, is approximately 240 hectares. The respective land areas for the unaffected areas A, B, C, D, and E are approximately 64, 56, 46, 18, and 59 hectares (Figure 2).

OBJECTIVES The objectives of the confirmatory survey were 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 radiological survey results.

DOCUMENT REVIEW ESSAP reviewed the licensee's survey report on the Phase I unaffected areas of the Cimarron Facility (Cimarron 1995). Procedures and methods utilized by the licensee were reviewed for adequacy and appropriateness. The data were reviewed for accuracy, completeness, and compliance with guidelines.

Kerr-McGee Corporation, Crescnt, OK-March 4, 1996 2

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PROCEDURES Owing the period October 17 through 19, 1995, an ESSAP team visited the Cimarron Facility and performed visual inspections, gamma scans, exposure rate measurements, and soil sampling of the Phase I unaffected areas. Surveys were performed in accordance with a survey plan dated October 10, 1995, submitted to and approved by the NRC (ORISE 1995a).

REFERENCE GRID ES SAP randomly selected two 100 m x 100 m grid blocks in each of the five Phase I areas for measurement and sampling (Figure 2). The comers of each grid block selected were re-established by KMC using a global positioning system (OPS). Measurement and sampling locations were also referenced in each grid block by this method. In this report, individual grid blocks were referenced according to the southwest grid intersection coordinate.

SURFACE SCANS Surface scans for gamma radiation were performed over 75 to 100% of the area in each grid block selected (2 blocks per area). Particular attention was given to areas adjacent to site access roads, natural drainage pathways, and other areas where material may have accumulated. Scans were performed using Nal scintillation detectors coupled to ratemeters with audible indicators.

EXPOSURE RATE MEASUREMENTS Background exposure rates were performed at six locations within a 0.5 to 10 km radius of the site dwing a previous ESSAP survey (ORISE 1995b ). Site exposure rate measurements were performed at each soil sample location at 1 m above the surface using a microrem meter (Figures 3 through 12).

SOIL SAMPLING Background soil samples were collected from each location of background exposure rate measurement during a previous ESSAP survey (ORISE 1995b). Three surface (0-15 cm) soil Kerr-McGee Corporation, Cresent, OK - March 4, 1996 3

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samples were collected from randomly selected locations in each grid block (Figures 3 through 12). Due to uncertainties in sampling locations because the OPS was unavailable to establish exact grid block comers, one sample location is not within the selected grid block (Figure 3). The OPS was used to identify grid block comers and exact sample locations for all other grids selected.

SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and survey data were returned to ORISE's ESSAP laboratory in Oak Ridge, Tennessee for analysis and interpretation. Soil samples were analyzed by gamma spectrometry. The radionuclides of interest were U-235 and U-238; however, spectra were reviewed for other identifiable photopeaks.

Gamma spectrometry data were reported in units of picocuries per gram (pCi/g). Exposure rate measurements were reported in units of microroentgens per hour (µR/h). Additional information concerning major instrumentation, sampling equipment, and analytical procedures is provided in Appendices A and B. Results were compared to the licensee's documentation and NRC guidelines established for release to unrestricted use, provided in Appendix C.

FINDINGS AND RESULTS SURFACE SCANS Surface scans for gamma activity in the 10 randomly selected grid blocks did not identify any locations of elevated direct radiation.

EXPOSURE RATES Background exposure rates at 1 m above the surface, measured on a previous ESSAP site survey, ranged from 6 to 8 µR/h, with an average of 7 µR/h. Exposure rates at the 30 surface soil sampling locations are presented in Table 1 and ranged from 4 to 12 µR/h.

Kerr-McGee Corporation, Cresent, OK - March 4, 1996 4

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• URANIUM CONCENTRATIONS IN SOIL Uranium concentrations in background soil samples, collected during a previous ESSAP site survey, ranged from 0.8 to 2.3 pCi/g for total uranium. Uranium concentrations in soil samples collected from the Phase I unaffected areas are summarized in Table 1. Concentrations were all less than 0.1 pCi/g for U-235, were less than or equal to 2.5 pCi/g for U-238, and were all less than 4.6 pCi/g for total uranium.

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 Branch Technical Position on "Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations" (USNRC 1981). Specifically, the Option 1 average soil guideline for enriched uranium is 30 pCi/g. Total uranium concentrations in all of the surface soil samples collected from the Phase I unaffected areas were at levels consistent with natural background and therefore, below the average guideline level.

The exposure rate guideline, measured at 1 m from the surface, is 10 µR/h above background.

Exposure rates measured in the Phase I areas were all within this guideline.

SUMMARY

During the period October 17 through 19, 1995, the Environmental Survey and Site Assessment Program ofORISE performed a confirmatory survey of the Phase I Unaffected Areas at the Kerr-McGee Cimarron Facility in Crescent, Oklahoma. Survey activities included surface scans, exposure rate measurements, and soil sampling.

The ES SAP confirmatory measurements are consistent with the licensee's measurements and support the licensee's conclusion that total uranium concentrations and exposure rates within the Phase I areas satisfies NRC guidelines for release to unrestricted use.

Kerr-McGee Corporation, Cresent, OK - March 4, 1996 5

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EXPOSURE RATES AND URANIUM CONCENTRATIONS IN SOIL SAMPLES FROM PHASE I UNAFFECTED AREAS KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA Exposure Rate Uranium Concentrations (pCi/g)

Location atl mAbove Total Surface (µR/h)

U-235 U-238 Uranium8 Unaffected Area Ah 200S OE, Location #1 7

<0.1 2.4 +/- 1.7c

<4.5 200S, OE, Location #2 6

<0.1 2.5 +/- 1.6

<4.6 200S, OE, Location #3 5

<0.1 0.6+/-0.8

<2.7 400S, 300E, Location #1 7

<0.1 1.4 +/- 1.6

<3.5 400S, 300E, Location #2 7

<0.1 0.8 +/- 1.4

<2.9 400S, 300E, Location #3 7

<0.1

<1.1

<3.2 Unaffected Area Bd 300N, 800E, Location #1 5

<0.1

<1.6

<3.7 300N, 800E, Location #2 5

<0.1

<1.2

<3.3 300N, 800E, Location #3 4

<0.1

<1.5

<3.6 SOON, 1200E, Location #1 4

<0.1

<1.5

<3.6 SOON, 1200E, Location #2 4

<0.1 1.6 +/- 1.3

<3.7 SOON, 1200E, Location #3 4

<0.1 1.2 +/- 1.0

<3.3 Unaffected Area ce 900N, lOOOE, Location #1 4

<0.1 0.9+/-0.9

<3.0 900N, 1 OOOE, Location #2 9

<0.1

<1.4

<3.5 900N, 1 OOOE, Location #3 12

<0.1 1.7 +/- 1.1

<3.8 800N, 400E, Location # 1 5

<0.1 0.7 +/- 1.1

<2.8 SOON, 400E, Location #2 7

<0.1

<1.5

<3.6 SOON, 400E, Location #3 7

<0.1 1.1 +/- 1.2

<3.2 Kerr-McGee Corporation, Cresent, OK - March 4, 1996 18 h:\\essap\\reports\\cimarron\\cimarron.003

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EXPOSURE RATES AND URANIUM CONCENTRATIONS IN SOIL SAMPLES FROM PHASE I UNAFFECTED AREAS KERR-McGEE CORPORATION, CIMARRON FACILITY CRESCENT, OKLAHOMA Exposure Rate Uranium Concentrations (pCi/g)

Location at 1 mAbove Total Surface (µR/h)

U-235 U-238 Uraniuma Unaffected Area D' 900N, 200E, Location # 1 6

<0.1

<1.5

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<0.1

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<0.1 1.5 +/- 1.1

<3.6 600N, lOOE, Location #1 6

<0.1 1.6 +/- 1.2

<3.7 600N, 1 OOE, Location #2 5

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<1.4

<3.5 600N, 1 OOE, Location #3 6

<0.1 1.1 +/- 1.2

<3.2 Unaffected Area EB 800N, IOOW, Location #1 6

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<0.1 1.1 +/- 1.1

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<0.1 1.2 +/- 1.2

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<0.1

<1.6

<3.7 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 (from reference ORISE 1995b). The U-235 concentration was used to estimate the U-234 concentration because the ratio ofU-234:U-235 is fairly consistent at both background concentrations and at positive levels of enriched uranium.

bRefer to Figures 3 and 4.

'Uncertainties represent the 95% confidence level, based only on counting statistics.

dRefer to Figures 5 and 6.

~efer to Figures 7 and 8.

fRefer to Figures 9 and 10.

gRefer to Figures 11 and 12.

Kerr-McGee Corporation. Cresent, OK - March 4, 1996 19 h:\\essap\\repons\\cimarron\\cimarron.003

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REFERENCES Cimarron Corporation (Cimarron 1995). Final Status Survey Report Phase I Areas at the Cimarron Facility. Cimarron Corporation, Oklahoma City, OK; July 1995.

Oak Ridge Institute for Science and Education (ORISE 1995a). Confirmatory Survey Plan for the Phase I Unaffected Areas at the Cimarron Facility, Cimarron Corporation, Crescent, Oklahoma (Docket File No. 70-0925). Oak Ridge, 1N; October 1995.

Oak Ridge Institute for Science and Education (ORISE 1995b ). Draft Report - Confirmatory Survey for the South Uranium Yard Remediation, Kerr-McGee Corporation, Cimarron Facility, Crescent, Oklahoma. Oak Ridge, 1N; June 1995.

U.S. Nuclear Regulatory Commission (USNRC 1981). Disposal or Onsite Storage of Thorium and Uranium Wastes from Past Operations. Washington, D.C.: Federal Register 46 (205): 52061-52063; October 1981.

Kerr-McGee Corporation, Cresent, OK - March 4, 1996 20 b:\\essap\\reports\\cimarron\\cimarron.003

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APPENDIXA MAJOR INSTRUMENTATION Kerr-McGee Corporation, Cresent, OK - March 4, 1996 h:\\essap\\reports\\cbnarron\\c~n.003

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APPENDIXA 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 ModelPRM-6 (Eberline, Santa Fe, NM)

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)

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, Cresent, OK - March 4, 1996 A-1 h:\\essap\\reports\\cimarron\\cimarron.003

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APPENDIXB SURVEY AND ANALYTICAL PROCEDURES Kerr-McGee Corporation, Cresent, OK - March 4, 1996 h:\\essap\\reports\\cimarron\\cimarron.003

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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 minimwn. Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating instrwnent.

The detector and instrwnent combination used for scans was:

Gamma - Nal scintillation detector with ratemeter.

Exposure Rate 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.

Soil Sampling Approximately 1 kg of soil was collected at each sample location. Surface soil samples were collected at a depth of 0-15 cm. Collected samples were placed in a plastic bag, sealed, and labeled in accordance with ESSAP survey procedures.

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 determined and the samples counted using intrinsic germanium detectors coupled to a pulse height analyzer system.

Kerr-McGee Corporation, Cresent, OK-March 4, 1996 B-1 h:\\essap\\reports\\cimarron\\cimarron.003

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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 0.186 Me V U-238 0.063 MeV from Th-234*

• Secular equilibrium assumed.

Spectra were also reviewed for other identifiable photopeaks.

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 concentration (MDC), 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 MDC of the measurement procedure, the result was reported as less than MDC.

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.

Kerr-McGee Corporation, Cresent, OK-March 4, 1996 B-2 h:\\cssap\\reports\\cimarron\\cimarron.003

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• Survey Procedures Manual, Revision 9 (April, 1995)

• 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 requirements of DOE Order 5700.6C and ASME NQA-1 for Quality Assurance and contain measures to assess processes during their performance.

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, Cresent, OK - March 4, 1996 B-3 h:\\essap\\reports\\cimarron\\cimarron.003

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APPENDIXC GUIDELINES FOR RESIDUAL CONCENTRATIONS OF THORIUM AND URANIUM WASTES IN SOIL Kerr-McGee Corporation. Cresent, OK-March 4, 1996 h:\\essap\\reports\\cimarron\\cimarron.003

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APPENDIXC 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." This docwnent established guidelines for concentrations of uranium and thorium in soil, that will limit maximwn radiation received by the public under various conditions of future land usage. These concentrations are as follows:

Maximum Concentrations (pCi/g)

Material for various options l8 2b 3c 4d Natural Thorium (Th-232 + Th-228) 10 50 500 with daughters present and in equilibriwn Natural Uranium (U-238 + U-234) with 10 40 200 daughters present and in equilibrium Depleted Uranium:

Soluble 35 100 1,000 Insoluble 35 300 3,000 Enriched Uranium:

Soluble 30 100 1,000 Insoluble 30 250 2,500 aBased 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.

hBased 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.

Kerr-McGee Corporation, Cresent, OK-March 4, 1996 C-1 h:\\essap\\reports\\cimarron\\cimarron.003

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