ML20057A507

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Confirmatory Radiological Survey of Wet Ceramics Area, Cimarron Corp Facility,Crescent,Ok, Final Rept
ML20057A507
Person / Time
Site: 07000925
Issue date: 07/31/1993
From: Landis M
OAK RIDGE ASSOCIATED UNIVERSITIES
To:
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ML20057A505 List:
References
ORISE-93-H-33, NUDOCS 9309140318
Download: ML20057A507 (39)
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{{#Wiki_filter:. l. r 'h' 'n/ CONFIRMATORY RADIOLOGICAL SURVEY N OFTHE l WET CERAMICS AREA CIMARRON CORPORATION FACILITY l CRESCENT, OKLAHOMA l M. R. LANDIS

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~, $i 1 R i l P 1 1 r bI' t j I. j t 5 i The Oak Ridge Institute for Science and Eduention (ORISE) was established by the U.S. Department of Energy to E 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 r Universities (ORAU) through a management and operating contract with the U.S. Department of Energy. Established i in 1946, ORAU is a consortium of 65 colleges and universities. ( NOTICES 5 l The opmions apressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge i Associated Universities. i, 1 This report was prepared as an account of work sponsored by the United States Government. Neither the United States i Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, s or assumes any legal liabibty or remonsibility for the accuracy, completeness. or usefulness of any information, l apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights. i Reference herein to any specific commercial product, proecss, or service by trade name, mark, manufacturer, or gi i otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S. Government g 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. I

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ORISE 93/H-33 ( CONFIRMATORY RADIOLOGICAL SURVEY OF THE WET CERAAUCS AREA CIMARRON CORPORATION FACILITY CRESCENT, OKLAIIOMA [ Prepared by M. R. Landis l Envimnmental Survey and Site Assessment Program Energy / Environment System Division Oak Ridge Institute for Science and Education [ Oak Ridge, Tennessee 37831-0117 Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region III Office FINAL REPORT JULY 1993 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-AC05-760R00033 with the U.S. Department of Energy. MIT CFAOUCS AREA 4uly 30.1993

l CONFIR5IATORY RADIOLOGICAL SURVEY l OF TIIE WET CERA31ICS AREA l I CI51ARRON CORPORATION FACILITY i L CRESCENT, OxtAiiO3rA Prepared by. _A Date: V f3 M'. Ti. Landis, project %fanager // I Environmental Survey and Site Assessment Program B L i Reviewed by: Date: 8///9.3 TC L. Beck, Acting Laboratory Manager Environmental Survey and Site Assessment Program B P Ax_ w _ Date: 9/'// 9 3 Reviewed by:

4. T. Payne, Quality Assurande Officer Environmental Survey and Site Assessment Program j

Reviewed by: # Date: M3 D. Berger, Proffam Director // / Energy / Environment Systems Division L I B iI WET CDtOUCS AREAJuly 30,1993 L--- ---------- ------ ----

I ACKNOWLEDGEMENTS I The author would like to acknowledge the significant contributions of the following staff members: FIELD STAFF I S. F. Barnett E. N. Huber B. M. Smith l LABORATORY STAFF R. D. Condra

l l

1. S. Cox R. L. Epperson l M. J. Lauceman 3 S. T. Shipley ~ F. E. Weaver l ILLUSTRATOR E. A. Powell .I CLERICAL STAFF T. T. Claiborne D. A. Cox R. D. Ellis I K. E. Waters E E I I I WLT CFAAMICS AREA-July 30.1993

TABLE OF CONTENTS PAGE List of Figures............................................. ii e List of Tables ...tu Abbreviation s.............................................. iv A cronyms............... ................................V Introduction and Site History.................................... I a Facility Description............................ ............ 2 1 Docu ment Review.......................................... 2 Obj ec ti ve............................................... 2 Procedures ............................................. 2 Findings and Results ....................................... 4 Compadson of Results with Guidelines............................. 5 L S u m m ary............................................... 6 References .............................................20 Appendices: Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: Guidelines for Residual Concentrations of Thorium and Uranium Wastes in Soil wrr ctrones arru, an. im i

l LIST OF FIGURES PAGE FIGURE 1: Location of the Cimarron Facility, Crescent, Oklahoma.......... 7 FIGURE 2: Plot Plan-Cimarron Facility.......................... 8 l l FIGURE 3: Wet Ceramics Area, Concrete Pads, and Girders.............. 9 FIGURE 4: Wet Ceramics Area, Concrete Pads and Girders-Areas of Excavations.............................. 10 FIGURE 5: Wet Ceramics Area, Concrete Pads and Girders-Surface Soil Sampling Locations................................ 11 FIGURE 6: Wet Ceramics Area, Concrete Pads and Girders-Subsurface Soil Sampling Locations............................... 12 l i f FIGURE 7: Background Measurement and Sampling Locations............ 13 ,I fI I l E ,I )I I E ii

I LIST OF TABLES PAGE I TABLE 1: Isotopic Uranium Concentrations in Soil Samples............. 14 TABLE 2: Radionuclide Concentrations in Surface Soil Samples.......... 15 I TABLE 3: Radionuclide Concentrations in Subsurface Soil Samples........ 17 TABLE 4: Background Exposure Rates and Radionuclide Concentrations in Soil.. 19 I I i I I ,I I I E .I 'I I E iii l u

I ABBREVIATIONS I cm centimeter 2 em square centimeter epm counts per minute 2 dpm/100 cm disintegrations per minute /100 square centimeters I GM Geiger-Mueller kg kilogram m meter 2 m square meter MeV megavolts NaI(TI) sodium iodide (thallium activated) I pCi/g picoeuries per gram I I I I I I I - c2 - c. _,,,..-, iv

il i l ACRONDIS !I ESSAP Environmental Survev and Site Assessment Program ig E NRC Nuclear Regulatory Commission i ORISE Oak Ridge Institute for Science and Education i 1 SFC Sequoyah Fuels Corporation ] P lI I ) I I I I I I I I I I __.c._,...,

I CONFIRMATORY RADIOLOGICAL SURVEY OF THE I WET CERAMICS AREA CIA 1AREON CORPORATION FACILITY CRESCENT, OKLAIIOMA I INTRODUCTION AND SITE IIISTORY I The Kerr-McGee Corporation operated the Cimarron Facility in Crescent, Oklahoma to produce l slightly enriched (approximately 3%) uranium fuel and mixed oxide (uranium plus plutonium) fuel between 1965 and 1975. These activities were conducted under license SNM-928 with the l Atomic Energy Commission, predecessor to the Nuclear Regulatory Commission (NRC). In 1983, Sequoyah Fuels Corporation (SFC) became the owner of the Cimarron Facility, when l Kerr-McGee Nuclear Corporation was divided into SFC and Quivira Mining Corporation. Later, Cimarron Corporation, a subsidiary of the Kerr-McGee Nuclear Corporation, became responsible for the Cimarron Facility. Decontamination of the Cimarron Facility began in 1979 with the goal of removing all contaminated equipment and materials so the facility could be released for unrestricted use. Cimarron Corporation has discontinued license activities and is in the process of performing the decontamination to terminate the NRC licensing restrictions. The decontamination and decommissioning project was divided into several phases, which involved the Mixed Oxide Plant, the Uranium Plant, the on-site Burial Grourd, and the Sanitary Lagoons. Decontamination and decommissioning activities involving the Mixed Oxide Plant have been completed, and activities involving the Uranium Plant, Burial Grounds, and Sanitary Lagoons are nearing completion. I At the request of the NRC's Region III Office, the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conducted an independent confirmatory radiological survey of the Wet Ceramics Area of the Uranium Plant at the Cimarron Corporation Facility. This report summarizes the procedures and results of the sun ey. .I MIT Cf.RANDCS ARr.A-July 30.1993

I FACILITY DESCRIPTION I The Cimarron Corporation Facility is located on a site of approximately 450 hectares in Logan County, Oklahoma, about 8 kilometers south of the town of Crescent (Figure 1). The Site includes the Mixed Oxide Plant, the Uranium Plant, an on-site Burial Ground, two Sanitary Lagoons, and an Evaporation Pond (Figure 2). I 2 The Uranium Plant Wet Ceramics Area is approximately 670 m and is part of the ground floor of the Uranium Plant (Figure 3). The floor aree has been extensively excavated (as deep as 5 meters in ponions) as part of the decontamination efforts (Figure 4). Decontamination efforts for the overhead area require that the floor be filled and levelled to facilitate movement of equipment. DOCUMENT REVIEW ESSAP reviewed the licensee's post-remedial action data for accuracy, completeness, and compliance with the guidelines. OBJECTIVE I The objective of the confirmatory survey was to develop independent document reviews and l l radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's radioPgical status repon, relative to established guidelines. E PROCEDURES I During the period June 22-24, 1992, ESSAP performed a conBrmatory survey of the Wet Ceramics Area at the Cimarron Corporation Facility. The survey was in accordance with a plan dated May 29,1992, submitted to and approved by the NRC Region III OfDee.' I WET Cl3tA%BCS ARMJuh 36 im 2

REFERENCE GRID A reference grid system (2 m x 2 m) was established by ESSAP for referencing measurements and sampling. SURFACE SCANS Gamma surface scans were performed using NaI(TI) scintillation detectors. Girders were scanned using GM detectors. Detectors were coupled to ratemeter-scalers with audible indicators. Areas of elevated contact radiation were marked for further investigation. SOIL SAMPLING 1 I Surface soil samples (0-15 cm) were collected from grid line intersections, areas of elevated contact radiation identified by the surface scans, and areas of elevated activity identified by the licensee prior to remediation (Figure 5). Subsurface soil samples were collected at 6 locations from depths ranging from 1 m to 2.8 m below the normal surface (0.3-2 m below the actual excavated surface). The samples were { collected from previous locations of elevated activity, identified by the licensee prior to remediation. These sampling locations are shown on Figure 6. SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and survey data were returned to the ESSAP laboratory in Oak Ridge, TN for analyses and interpretation. Soil samples were analyzed by gamma spectrometry. Jpectra were reviewed for the radionuclides of interest (U-235 and U-238) and any other identifiable photopeaks. Approximately 10% of the soil samples were analyzed by alpha spectrometry for isotopic uranium. Soil concentrations were reported in units of pCi/g. WET CDtANDCS AREA July 30,1993 3

FINDINGS AND RESULTS DOCUMENT REVIEW I The licensee provided preliminary and post remediation soil sample analysis results. This information was reviewed and indicated that poc remediation soil concentrations were below the NRC guideline values. However, all of the locations which ex, eeded the NRC guidelines in the preliminary survey were not resampled in the post remediation phase. Therefore, it cannot be determined from the data provided by the licensee whether the current conditions of Wet Ceramics Area door and sub0oor meet the NRC guidelines. I SURFACE SCANS I Surface scans identified several areas of elevated direct radiation; these were marked for further investigation. I RADIONUCLIDE CONCENTRATIONS IN SOIL I Six samples were analyzed by alpha spectrometry for isotopic uranium. The uranium concentrations for these samples are summarized in Table 1. Isotopic uranium concentrations ranged from 8.1 to 156.7 pCieg for U-234,0.3 to 9.6 pCi/g for U-235, and 2.2 to 101.0 pCi/g for U-238. The total uranium concentrations ranged from 10.5 to 267.3 pCi/g. On the basis of alpha spectrometry analysis, the ratio of U-234 to U-235 activity is approximately 25:1.0. - l This ratio was used to calculate the total uranium concentrations in soil samples, analyzed only by gamma spectrometry. I Concentrations of radionuclides in surface soil samples are summarized in Table 2. Concentrations ranged from 0.1 to 6.1 pCi/g for U-235,1.0 to 49 pCi/g for U-238, and 3.6 to 200 pCi/g for total uranium. The highest concentration was identified at grid coordinate 72N, 88.6E. I WI:7 elRAMies AldAjay 30.190 4

il Radionuclide concentrations in subsurface soil samples are summarized in Table 3. Concentrations ranged from 0.1 to 4.3 pCi/g for U-235,1.5 to 45 pei/g for U-238, and 4.3 to 160 pCi/g for total uranium. The highest concentration was at coordinate 82N,84E, at a depth of 0-30 cm. COMPARISON OF RESULTS WITil GUIDELINES Surface activity guidelines established for the release of a licensed facility for unrestricted use l and the guidelines for residual concentrations of uranium wastes in soil are presented in g Appendix C. E The primary contaminant of concern is enriched uranium, with a soil concentration guideline of 30 pCi/g. This guideline is expressed in terms of concentration above normal background levels. Background radionuclide concentrations in soil were determined during the 1988 Oak Ridge Associated Universities (now ORISE) survey (Table 4). Total uranium concentrations ranged from <l.2 to 2.0 pCi/g (1.6 pCi/g, average). Therefore, the sample analysis result indicating that the N'RC guideline has been exceeded is 31.6 pCi/g for total uranium. Il Gamma spectrometry analysis identified 15 surface soil samples and 1 subsurface soil sample with total uranium concentrations exceeding the guideline value. The surface soil samples which exceed the guidelines were collected from 70N,74E; 70N,88E; 70N,88.6E; 72N,74E; 72N, 88.6E; 76N, 64.2E; 78N, 88.6E; 82N, 76E; 82N, 84E; 82N, 88.6E; 86N, 59E; 87N, 72E; 88N,58E; 88N,82E; and 88N,88.6E. The subsurface soil sample which exceeds the guideline l value was collected from 82N, 84E (0-30 cm). Alpha spectrometry analysis identified one surface soil sample which exceeded the guideline value for uranium (82N, 88E). ,'l Five samples contained total urariium concentrations exceeding 3 times the guideline level, i.e., greater then 90 pCi/g; four of these five samples were obtained adjacent to the east wall of the building. Further evaluation of soil concentrations, performed at the request of Region III, indicated two - 100 m areas with a weighted average uranium concentration above 39 pCi/g; 2 these were 80-90N, 68-78E (37 pCi/g) and 80-90N,78-d8E (88 pCi/g).2 = WFT CERANDCS AREA-July 30, im 5

I I

SUMMARY

I In June 1992, ESSAP performed a confirmatory radiological survey of the Wet Ceramics Area at the Cimarron Corporation Facility in Crescent, Oklahoma. Survey activities included document reviews, surface scans, surface activity measurements, and soil sampling. E The documentation provided by the licensee was not complete and did not adequately address I the current radiological status of this area. The results of the survey performed by ESSAP indicated that soil concentrations still exist in the Wet Ceramics Area which exceed the NRC guideline values. The 6ndings, therefore, did not support the Enal survey performed by the Cimarron Corporation, and in ESSAP's opinion, indicated that the radiological conditions of the Wet Cermnics Area did not satisfy the NRC guidelines for release without radiological restrictions. I I I I I I I I I I wu cimenes armi n. im 6

OKLAHOMA ,I I I I Y, O f 9 I 5 CPESCENTg I KING FISHER CUTHR:E PLANT SITE EDMOND e- 'l 40 ~ OKLAHOMA-l jTY ' ~ l c. mr To scur Ie i G I 9 e I I I I FIGURE 1: Location of the Cimarron Facility, Crescent Oklahomo

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TABLE 1 I ISOTOPIC URANIU31 CONCENTRATIONS IN SOIL SA31PLES WET CERASIICS AREA I CI51ARRON CORPORATION FACILITY CRESCENT, OKLAIIONIA l I Radionuclide Concentration (pCi/gf Location' U-234 U-235 U-238 Total U I 76N, 64E 10.1 1 0. 65 0.4 0.2 3.4 i 0.4 13.9 0.7 80N, 84E 8.1 0.6 0.3 i 0.2 2.2 0.3 10.5 i 0.7 .I 82N, 64E 12.3 0.7 0.4 1 0.2 4.4 0.4 17.1 0.9 82N, 82N 19.2 1 0.8 0.9 t 0.2 3.7 0.4 23.8 0.9 82N, 88E 156.7 3.4 9.6 1.0 101.0 2.7 267.3 4.5 88N, 88E 14.0 1 0.6 0.5 0.2 3.7 i 0.3 18.2 0.7 ' Refer to Figure 5. I

  • Based on alpha spectrometry analysis.

' Uncertainties represent the 95% confidence level, based only on counting statistics. I I I I I I 4 I " " " ~ " ~ " " " ' I j

3 i I i TABLE 2 I RADIONUCLIDE CONCENTRATIONS 1 IN SURFACE SOIL SA51PLES I WET CERA31ICS AREA CI51ARRON, CORPORATION FACILITY CRESCENT, OKLAIIO51A Radionuclide Concentration (pCi/g) I Location' S U.235 U-238 Total U 70N, 58E 0.2 0.1 1.4 1.0 6.6 70N, 64E 0.5 1 0.1 4.3 1.6 17 70N, 70E 0.6 i 0.1 6.2 2.4 22 70N, 74E 1.0 0.2 8.2 i 2.4 34 70N, 76E 0.9 1 0.2 8.0 2.3 31 70N, 82E 0.6 0.1 4.3 1.7 20 70N, 88E 1.8 0.3 9.8 ! 2.8 57 70N, 88.6E 5.8 ! 0.8 44.3 i 9.8 200 72N, 74E 1.5 0.2 7.7 i 2.4 47 72N, 86.6E 6.1 0.8 45 10 200 74N, 88.6E 0.6 0.1 3.2 1.6 19 76N, SSE 0.5 1 0.1 4.3 ! 16 17 76N, 64E 76N, 64.2E 1.0 0.2 8.4 ! 2.5 34 76N, 70E 0.5 ! 0.1 5.7 2.1 19 76N, 76E 0.6 ! 0.1 6.0 i 1.9 22 76N, 82E 0.3 i 0.1 3.5 1.7 11 76N, 88E 0.3 0.1 4.3 1 2.1 12 76N, 88.6E 0.7 1 0.1 5.3 1.9 24 78N, 88.6E 2.3 1 0.3 14.9 3.8 75 80N, 84E 80N, 88E 0.5 0.1 3.8 1.9 17 82N, 58E 0.4 0.1 1.5 i 1.1 12 82N, 64E 0.7 0.1 6.5 2.2 25 82N, 70E 1.3 0.2 13.1 3.3 47 g

TABLE 2 (Continued) ,g RADIONUCLIDE CONCENTRATIONS E IN SURFACE SOIL SA51PLES WET CERA5fICS AREA CI51ARRON, CORPORATION FACILITY I CRESCENT, OKLAIIO51A J Radionuclide Concentration (pCilg)

  1. "I' "

6 U-235 U-238 Total U - I 82N, 76E 1.7 1 0.3 14.8 3.8 59 82N, 76.3E 0.3 0.1 1.8 1.5 9.6 I i 82N, 82E 0.9 0.1 4.6 1 1.8 28 82N, 88E 82N, 88.6E 4.3 ! 0.6 49 1 11 160 86N, 59E 0.7 0.1 14.4 4.2 33 87N, 72E 1.2 0.2 5.3 41 88N, 58E 1.2 1 0.2 5.> 1.9 37 88N, 60E 0.1 0.1 4.7 ! 3.2 7.3 88N, 64E 1.0 ! 0.2 3.0 1 8.3 29 88N, 70E 0.8 0.1 6.6 1 2.4 27 88N, 76E 0.1 0.1 1.0 0.8 3.6 88N, 82E 1.0 0.2 8.5 1 2.8 35 88N, 88E I 88N, 88.6E 1.1 0.2 7.9 2.2 37 94N, 88E 0.3 0.1 1.2 1.3 9.0 I ' Refer to Figure 5. ' Calculated using a U-234:U-235 activity ratio of 25:1.0. ,I ' Uncertainties represent the 95% confidence level, based only on counting statistics.

  • ---Indicates analysis was performed by alpha spectrometry, see Table 2.

I I I is

TABLE 3 RADIONUCLIDE CONCENTRATIONS I IN SUBSURFACE SOIL SA51PLES 1 WET CERAAIICS AREA I CIAIARRON CORPORATION FACILITY CRESCENT, OKLAIIO51A i b I Radionuclide Concentration (pCi/g) + Location" Depth 6 U-235 U-238 Total U (cm) 80N, 78E 0-100 1.0 0.2 5.1 2.1 31 80N, 84E 30-60 -- d 82N, 59E 0-30 0.2 1 0.1 2.1 2.4 7.3 30-60 0.3 i 0.1 1.5 i 1.1 9.3 60-90 0.4 i 0.2 4.5 5.9 15 90-120 0.5 1 0.1 3.2 2.0 16 120-150 0.3 ! 0.1 2.6 1 1.7 10 150-180 0.5 0.1 2.7 i 1.6 16 i 82N, 82E 0-30 30-60 0.7 i 0.1 3.3 1.5 22 60-90 0.7 0.1 3.2 1 1.7 21 90-120 0.6 1 0.1 3.6 1.7 19 i 120-150 0.4 1 0.1 5.4 2.8 16 I 150-180 0.4 i 0.1 3.0 1.4 13 82N, 84E 0-30 4.3 1 0.6 45 10 160 30-60 0.7 0.1 3.9 1.7 22 6C-90 0.8 ! 0.2 2.6 1.5 23 I I I I wu ca.noucs ratw,2n. m) 17 I

TABLE 3 (Continued) I R ADIONUCLIDE CONCENTRATIONS IN SUBSURFACE SOIL SAMPLES WET CERAMICS AREA I CLMARRON CORPORATION FACILITY CRESCENT, OKLAHOMA Radionuclide Concentration (pCi/g) Location

  • Depth (cm)

U-235 U-238 Total U I 83N, 60E 0-30 0.1 0.1 1.7 2.0 4.3 30-60 0.4 0.1 2.7 1.5 13 60-90 0.5 1 0.1 2.0 i 1.3 15 90-120 0.8 0.2 2.3 1.7 23 120-150 0.3 0.1 5.5 t 3.4 13 150-180 0.4 i 0.1 2.4 i 1.8 13 ' Refer to Figure 6. l '6 Calculated using a U-234:U-235 activity ratio of 25:1.0. Uncertainties represent the 95% confidence level, based only on counting staustics. d-Indicates analysis was performed by alpha spectrometry, see Table 2. i I MIT CIRANUCS AKLojuly 30,1943 18 I

TABLE 4 BACKGROUND EXPOSURE RATES AND RADIONUCLIDE CONCENTRATIONS IN SOIL I WET CERAAIICS AREA CIA 1ARRON CORPORATION FACILITY CRESCENT, OKLAIIONIA Exposure Rate ( R/h) Total Uranium Location

  • at 1 m Concentration above the surface (pCi/g)

1 10 1.5 2 9 1.3 3 9 <1.7 4 10 2.0 5 10 1.9 6 10 < 1.2 Average 10 1.6 I ' Refer to Figure 7.

  • Based on gamma spectrometry analysis.

' Calculated based on natural activity ratios. I I I I I I nrr cononcs Anr_uay 3a. ins 19 4

- - _ ~ I i REFERENCES i I 1. " Confirmatory Radiological Survey PILI for the Uranium Plant, Wet Ceramics Area, Cimarron Corporation Facility, Cresent, Oklahoma" Betty M. Smith, May 29, 1992, ] revised June 5,1992. 2. Letter, J. D. Berger, ORISE, to G. M. France, NRC Region III, " Average Soil Activities - Cimarron Wet Ceramics Facility," November 4,1992. I I

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i i .I I I APPENDIX A 51AJOR INSTRU31ENTATION I I I I ,:I

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'I i k I !I I

APPENDIX A MAJOR INSTRUMILJTATION I The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the authors or their employers. I DIRECT RADIATION MEASUREMENT l Lastruments Eberline Pulse Ratemeter l Model PRM-6 (Eberline, Santa Fe, NM) Eberline " Rascal" Ratemeter-Scaler Model PRS-1 (Eberline, Santa Fe, NM) I Detecto_rs Eberline GM Detector Model HP-260 I 2 Effective Area,15.5 cm (Eberline, Santa Fe, NM) Victoreen Nal Scintillation Detector Model 489-55 3.2 cm x 3.8 cm Crystal I (Victoreen, Cleveland, OH) i I 1 LABORATORY ANALYTICAL LNSTRUMENTATION I Alpha Spectrometry System Tennelec Electronics Model (Tennelec, Oak Ridge, TN) I Used in conjunction with: 4 Surface Barrier Detectors (EG&G ORTEC, Oak Ridge, TN) and l' Multichannel Analyzer ND 66 (Nuclear Data, Schaunburg, IL) wrretaones Axumo,im A-1 I

I I High-Purity Germanium Detector Model GMX-23195-S,23% Eff. I (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 l (Canberra, Meriden, CT) High-Purity Germanium Coaxial Well Detector l Model GWL-110210-PWS-S,23% Eff. (EG&G ORTEC, Oak Ridge, TN) Used in conjunction with: l Lead Shield Model G-16 (Applied Physical Technology, Atlanta, GA) and Multichannel Analyzer I 3100 Vax Workstation (Canberra, Meriden, CT) I I I I 1 I I 1 I I I I wrr crxoacs at.wa n, ma A-2 I r

I i I i, I l i I APPENDIX B SURVEY AND ANALYTICAL PROCEDURES I I )

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I I I I I WET CrJtAMICS AREA-July 30,1993 -i

I I APPENDLX B SURVEY AND ANALYTICAL PROCEDURES I SURVEY PROCEDURES I Surface Scans Surface scans were performed by passing the probes slowly over the surface; the distance between the probe and the surface was maintained at a minimum - nominally about 1 cm. Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating instrument. Combinations of detectors and instruments used for the scans were: Beta pancake GM detector with ratemeter-scaler I Gamma NaI scintillation detector with ratemeter I Soil Samoling I Approximately I kg of soil was collected at each sample location. Collected samples were placed in a plastic bag, sealed, and labeled in accordance with ESSAP survey procedures. I ANALYTICAL PROCEDURES Gamma Spectrometry I Samples of solid material (soil) were dried, mixed, crushed, and/or homogenized as l 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. l Net material weights were determined and the samples counted using intrinsic germanium wrr crxoucs ar.wpo. no B-1

I I detectors coupled to a pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the I computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were: U-235 0.143 MeV or 0.186 MeV U-238 0.063 MeV or 0.093 MeV from Th-234 *or 1.001 MeV from Pa-234 m*

  • Secular equilibrium assumed.

Spectra were also reviewed for other identinable photopeaks. Aloha Socctrometry 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 precipitated with barium sulfate. Barium sulfate precipitate 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 l multichannel analyzer (Nuclear Data). l 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. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than 2.71 + 4.66 times the statistical deviation of the background count, the sample concentration was reported as less than the detection limit of the measurement procedures. I u n cr. m ocsAn m y x. m3 B-2

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. Additional uncertainties, associated with sampling and ) measurement procedures, have not been propagated into the data presented in this report. CALIBRATION AND QUALITY ASSURANCE Analytical and field survey activities were conducted in accordance with procedures from the following documents of the Environmental Survey and Site Assessment Program: -Survey Procedures Manual Revision 7 (May 1992) -Laboratory Procedures Manual Revision 7 (April 1992) -Quality Assurance Manual Revision 5 (May 1992) 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. l 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 was used. l 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, and a Periodic internal and external audits. ,I Mrr CrJLAMICS AREA-July 30,1993 B-3 I

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.EE APPENDIX C i e GUIDELINES FOR RESIDUAL CONCENTRATIONS OF TIIORIUM AND URANIUM WASTES IN SOIL I I I i I I I I 1 I I !I MIT CIAO 11CS ARI:A. July 30,190

I I GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT I PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL I I U.S. Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety Washington, D.C. 20555 I I l August 1987 l I I I I I un catones rat 4-Jori se. im C-1 .I

~ I l t 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 document establishes 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: I Maximum Concentrations (pCi/g) for various options Material l' 2" 3' 4' E Natural Thorium (Th-232 + Th-228) v ith daughters present and in I equilibrium 10 50 500 Natural Uranium (U-238 + U-234) with daughters present and in equilibrium 10 40 200 Depleted Uranium: Soluble 35 100 1,000 Inscluble 35 300 3,000 ) Enriched Uranium: I Soluble 30 100 1,000 Insoluble 30 250 2,500 ' Based on EPA cleanup standards which limit radiation to 1 mradlyr to lung and 3 mrad /yr to bone from ingestion and inhalation and 10 R/h above background from direct external exposure. 6Based on limiting individual dose to 170 mrem /yr. ' Based 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. un caoncs aux, n. im C-2 I 1}}

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