ML20215L380
| ML20215L380 | |
| Person / Time | |
|---|---|
| Site: | 07000008 |
| Issue date: | 01/31/1987 |
| From: | Flynn K, Justus A, Sholeen C ARGONNE NATIONAL LABORATORY |
| To: | |
| Shared Package | |
| ML20215L348 | List: |
| References | |
| ANL-OHS-HP-85-1, ANL-OHS-HP-85-103, NUDOCS 8705120218 | |
| Download: ML20215L380 (105) | |
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{{#Wiki_filter:_ _ _ _ - _ PRG AOh LiCATI O A) cop / ! ( Distribution Category: - /^Y Remedial Action and V i Decommissioning Program { (UC-70A) ] [ ANL-OHS /HP-85-103 ARGONNE NATIONAL LABORATORY 9700 South Cass Avenue Argonne, Illinois 60439 POST-REMEDIAL-ACTION RADIOLOGICAL SURVEY REPORT FOR THE PLUTONIUM FACILITY OF THE BATTELLE MEMORIAL INSTITUTE - COLUMBUS DIVISION WEST JEFFERSON COMPLEX WEST JEFFERSON, OHIO April 1980 - June 1982 O Prepared by K. F. Flynn W. H. Smith A. L. Justus R. A. Wynveen C. M. Sholeen Radiological Survey Group Health Physics Section Occupational Health and Safety Division March 1985 Revised January 1987 g l Work Performed under ] Budget Activity DOE HA-01-07-05-2 and ANL 73706 '(O/ k[ C 70 0 C
_3 iii-EXECUTIVE.
SUMMARY
O Support iDivision1'of ' the_. U.S. At the -request of the Engineering Department of Energy, Chicago Operations Office (DOE-CH), and in accordance with DOE's programmatic post-remedial-action (cartification)- responsibili-ties,- the Argonne National Laboratory (ANL) Radiological-Survey Group (RSG) conducted - a series of three radiological. surveys at the Battelle Plutonium Facility in West Jefferson, Ohio, to determine _ if any radioactive
- contami-nation remained following the three phases of Battelle's' decommissioning and decontamination- (D&D) program.
The surveys were cor. ducted in 1980, 1981, and 1982. From the early 1960s through the mid-1970s, various -- research ' and ' processing activities involving studies of plutonium and it's alloys, nuclear-fuels development, heart pacemaker development _ and other programs. were conducted within the Plutonium Facility. The Plutonium Facility was one of. four facilities.that constitute,d the Nuclear Sciences. Area, owned and operated by the Battelle Memorial-Institute, Columbus Division. The radiological surveys conducted in conjunctionLwith the D&D program ~included determinations of surface contamination - levels, 'b'oth fixed ' and removable, through direct instrument and smear surveys; measurements. of ambient external; penetrating radiation at 1-meter heights; and analyses'of air, soil, and other material samples from the areas involved. Following the various D&D phases, several remaining areas of contami-nation within the Plutonium Facility were detected through the_' direct instiru-ment and smear surveys. The radiation readings obtained at the contaminated areas were compared with standards and guidelines in the American National Standard Institute (ANSI) Draft Standard N13.12, " Control of : Radioactive Surface Contamination on Materials, Equipment, and Facilities to be Released for Uncontrolled Use," and in the Nuclear Regulatory Commission's." Guidelines i s 1 for Decontamination of Facilities and ' Equipment Prior to Release for I
- The various types - and sources of radiation mentionel in this report are discussed in more detail in Appendix 7.
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iv Unrestricted Use or Termination of Li' censes for By-Product, Source, or [) Special Nuclear Material." The criteria for plutonium or unknown-contami-v ~ 'Further decontamination was nants were used as the bases for comparison. conducted at these areas, and radiation levels measured. af ter this ' addi-tional decontamination met the permissible surface contamination criteria. Several radiation measurements within the Plutonium Facility were influenced by direct gamma or scattered (i.e., shine) radiation from the adjacent Hot Cell Facility, waste drums, or holding tanks. Air samples collected at the involved areas within the Plutonium Facil-ity indicated that the radon, thoron, and progeny concentrations within the air were.below the limits prescribed by the U.S. Surgeon General, the Environmental Protection Agency, and the Department of Energy. A low level of actinon progeny (0.12 pCi/2) was measured within one air sample; the source of this elevated concentration could not be determined. No actinon progeny were detected in a repeated measurement or in any other air sample. No long-lived radionuclides were detected in any air sample. The interior of the air supply manifold in the Plutonium Facility was found contaminated with plutonium and americium, indicating a contaminated ventilation system. Wet deposits were collected from the floor inside the walk-in supply manifold and from the drain pan of copper cooling coils in the manifold. Radiochemical analyses indicated contaminant concentraticas of up to 1.7 1 0.1 pCi/g for 239:240Pu, 0.07 t 0.01 pCi/g for 238Pu, and 241 0.40 1 0.04 pCi/g for Am in the suspended solids fraction of the samples. The Battelle decommissioning personnel were apprised of these finds and have addressed them. The soil in the excavated pipe races within the Main Laboratory and Rooms 4117 and 4118 contain some residual plutonium and americium. Results of radiochemical analyses of soil collected after final decommissioning of the races indicated concentrations of 239s240Pu of up to 15.0 t 1.5 pCi/g, 2.956 i 0.036 pCi/g for 238 241 Pu, and 3.610.3 pCi/g for Am. These levels are believed to be in keeping with the ALARA philosophy as it relates to this particular project.
v . Analyses of split environmental soil samples collected prior to - de-Q ' commissioning activities near the buried autoclave and old holding tanks. 2ss,240 ~ indicated concentrations of up to'24.30 1-0.34 pCi/g for Pu, 0.731 i O.06 pCi/g for 2ssPu, and 32.5 9.4 pCi/g.241Am. Following excavation of the autoclave and old holding tanks and fcompletion of decommissioning. and decontamination efforts there,. additional soil samples were. collected by Battelle and split with ANL. ' Analyses of these-split environmental -~ soil. I samples indicated radionuclide concentrations. of up.to 13.9 i 0.5 pCi/g for Pu,- 0.36 0.04 pCi/g for 2ssPu, and 9.81 0.50 pCi/g for 241Am. 239,240 -The samples ' were collected from the floor and-walls of the excavated hole prior to backfill with clean soil and are indicative of the current status of. the subsurface soil at these locations. Although there are no uni-versally accepted soil criteria, these levels remaining are consistent with the ALARA philoscphy when one considers worstcase pathway exposure. t ' O O i r ? I l
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vi-TABLE OF CONTENTS t P, age Executive Summary........................ iiii l r. List of. Figures. vii l List of Tables. - vii - Acknowledgements. viii Introduction..... . ~. 'l . Survey, Sampling, and Analytical Techniques.... 3 General.... 3 Direct Instrument' Surveys,. 4 Smear Surveys. 5 Ambient-Penetrating Radiation Measurements. 6 Air Samples....... 7.- Joil and Material Samples.. 7. Survey and. Sampling Results. 9 Direct Instrument and Smear Surveys 9 Ambient Penetrating Radiation Measurements. 11 Air Samples. 11 Soil and Material Samples. 12 t l Conclusions. 15. References. 17 Figures. 18 Tables. 26-APPENDIX-1. Instrumentation. '55 APPENDIX.2. Conversion Factors. 59 APPENDIX 3. Radon, Thoron,land Actinon Daughter Determination-Calculations. 62 APPENDIX 4. Sample Preparation and Analysis Procedures. ,68 APPENDIX 5. Calculation of Uranium Specific Activity. 72 APPENDIX 6. Pertinent Radiological Regulations, Standards, 1 and Guidelines. 73 l APPENDIX 7. Evaluation of Radiation Exposures. 91-
vii LIST OF FIGURES A Figure' Page .V 1 West Jefferson Site. 18
- 2 Nuclear Sciences Area.
19 l 3 Plutonium Facility Before Decommissicning.. 20 .j l 4 Plutonium Facility Contamination Locations... .21 ~ 5 Air Sample and RSS-111 Radiation Measurement Locations 22- ,6 Plutonium Facility soil and Material Sample Locations. 23 7 Plutonium Facility Environmental' Sample Locations-Before Decommissioning.. 24 8 Plutonium Facility Environmental Sample Locations-Following Decommissioning.. 25 LIST OF TABLES Table Page 1 Results of Direct Instrument and Smear Surveys.... 26 2 Results of Direct Instrument and Smear Surveys After Further Decontamination. 36 3 Ambient Penetrating Radiation Measurements. 42 4 Radon Daughter Determinations... 43 5 Soil and Material Sample Weights. 45 6 Gamma-Spectral and Uranium-Fluorometric Analysis of Samples...... 47 7 Plutonium, Americium, and Neptunium Radiochemical Analyses of S, elected Soil and Material Samples... 49 8 Uranium Isotopic Analysis of Selected Samples. 53 i O
m .viii ACKNOWLEDGEMENTS . The. authors gratefully - acknowledge-the _ contributions ~ of the people involved in the production of this report. The surveys _were performed under the auspices of the Health Physics Section -of the Occupational Health and Safety (OHS) Division of Argonne National Laboratory (ANL), Argonne, Illinois, for the U.S. Department of Energy. The following people were responsible for performing the measurements, sample _ collection, and/or sample analyses: J. G. Ello, C. A.
- Hunckler, A. L. Justus,_D. W. Reilly, R.~ Rodriguez, C. M. Sholeen, W. H.l Smith, J. D.
Thereon, and R. A. Wynveen. Thanks are extended to the Battelle personnel; at the West Jefferson Site for their assistance and cooperation.during the - surveys. The radiochemical analyses ' were conducted by LFE Environmental Analysis Laboratories, - Eberline Corporation, the Analytical. Chemistry . Laboratory at ANL, and the Environmental Monitoring and Health Physics Sections of the OHS Division at ANL. Most of the report - figures were drafted by D. W. Reilly. Technical editing was provided by J. 'D. DePue. 3 L. L. Chamberlin was responsible for the typing of the manuscript of:this report. O O O we ~ -w y w w ..m-o_- c.--<- .=
1 RADIOLOGICAL SURVEY REPORT FOR THE PLUTONIUM FACILITY OF THE BATTELLE MEMORIAL' INSTITUTE ~ -h-COLUMBUS DIVISION. WEST JEFFERSON COMPLEXE-WEST JEFFERSON, OHIO INTRODUCTION At the request of the Engineering. Support Division of the U.S. Depart-ment. of Energy, Chicago Operations Office (DOE-CH),. and in.accordance. with DOE's ' programmatic post-remedial-action (certification) responsibilities, the Argonne National Laboratory (ANL) Radiological Survey Group (RSG)l conduct-ed a series of post-remedial-action radiological surveys at the Battelle Plutonium Facility, West Jefferson, Ohio. The facility is owned and opera-ted by Battelle Memorial Institute, Columbus Division. lThese surveys were conducted to determine if any radioactive contamination 1 remained following each. of the three phases of a decommissioning and decontamination (D&D) program carried out at the facility by Battelle-personnel. The Plutonium Facility was located about 17' miles west of downtown = Columbus, Ohio, approximately Ik miles south of Interstate 70 on Ohio State O ae=te 142 csee ris. 1). The facilitv was Part ef the *=c1 ear sciences Area, a 10-acre fenced security area located in-a Battelle-owned tract of approxi-mately 1000 acres used almost exclusively for farming. The location of the Plutonium Facility, along with the other three facilities that constitute the Nuclear Sciences Area, is shown in Figure 2. A 32-acre manemade lake was located just south of the Nuclear Sciences Area on' Battelle property. West Jefferson, Ohio (population of about 6,000) was the' nearest village, located about 2 miles southwest of the site near the ~ intersection of Routes 142 and 40. A predominant geographical feature in the region surrounding the West Jefferson Site is Big Darby Creek, which flows from north to south at the eastern border of the site and about 1380 ft east of the Nuclear Sciences Area. The Plutonium Facility was built in 1960 as part of Battelle's expan-sion into research and processing areas involving studies of metallurgical and ceramic properties of plutonium and its alloys, advanced nuclear fuels development, and other programs. As interest in plutonium research increased, additions to the original facility were built in 1964 and 1967. The major h research activity at the Plutonium Facility, the Mixed-Nitride Reactor Fuel l I
~. "2- - Program,' and smaller experimenta1E studies, whicht included Reactiont Rate Studies of Hydriding Plutonium and the Plutonia Particulate Leak Rate Study,' involved the use of plutonium-239. and/or enriched uranium nitrides,; oxides, . metals,- and hydrides. in pellet,. powder,. solution, and metallic ' forms.
- Another program, Hittman's Heart Pacer Program involved plutonium-238 oxideL powder.
Americium-241 was reportedly _ associated with much of the plutoniumi material. 'With the reduction 'in funds: for ~ plutonium ~ research _ in. the mid 1970s, Battelle decided to close the Plutonium Facility and decontamin-ate the building for unrestricted use~. Decommissioning and decontamination- ~ procedures began in January 1978. l The Plutonium' Facility was a single-story -U-shaped structure of about. 7200 ft2 floor area containing four primary laboratory ~ areas (see Fig. 3), the Main Lab, Old Lab, Met Lab, and Pu-238 Lab, and about 242 ft.of. internal. l drain lines. After the first phase of Battelle D&D activities,. the ANL Radiological Survey Group surveyed the decontaminated portion of the facili - 1 { ty, involving Rooms. 4116, 4117, and 4118 (see Fig. 5). This survey was j conducted April 9-11 and August 12, 1980. On. July 30,.-1981,- following a second phase of Battelle D&D operations, Rooms 4119A,- B, and C.were survey- !Q ed. The rest of the facility was surveyed June 11 17 and June 30-July 1, 1982, following the third phase of Battelle D&D. This survey included the ~ Main Lab, corridors, men's locker room, mechanical room, and -office areas. Excluded from the. survey was the original wing - of the building that had contained the Old Lab and those laboratory areas above the autoclave, that i wing having already been dismantled and moved from the property. This third-survey also dealt, albeit briefly, with the outdoor _ environs at the former - location of the autoclave and old holding tanks. The results of all three r surveys are reported in this document. As the decommissioning and decontamination of. the Plutonium Facility-1 progressed, the building was being converted into a Hazardous Materials j Integrated Facility, to eventually consist of a Hazardous Materials Labora-1 tory and a Special Materials Pilot Plant. By the time of the third survey, the completed Hazardous Materials Laboratory occupied Rooms 4116, 4117, and j 4118, areas that had been assessed during the first ANL~ survey. i T O , :. a _ -
7 l 3. i SURVEY, SAMPLING, AND ANALYTICAL TECHNIQUES q Q General The post-remedial-action surveys conducted by the ANL Radiological Survey Group for the U.S. Department of Energy involved only the remaining, newer segment of the original Plutonium Facility and those outdoor environs at the former location of the buried autoclave and old holding tanks. This remaining section, built in 1967, was constructed of 16-ft-high cement block walls on a concrete floor slab with a roof of reinforced ribbed concrete. A false ceiling which had been installed at the 12-f t. level to provide a 4-ft space for ducts and utility services had been removed by the time of the survey. The floors and walls (to the 12-ft level) in the i ' oratory and corridor portione of the facility were coated with epoxy paint; the overhead ribbed concrete, I beams, and walls above the 12-ft level were uncoated. The removed, older wing of the facility had been constructed of double-layered metal walls with several inches of insultation and a metal roof. The walls common,to the dismantled building and the remaining section had ] been replaced with new concrete block walls, uncoated at the time of the third survey. The assessment activities conducted during the three surveys included determination of surface contamination levels, both fixed and removable, through direct instrument and smear surveys; measurement of ambient external penetrating radiation levels at 1-meter heights throughout the involved areas; measurement of the concentrations of radon, thoron, and actinon daughters and longer-lived radionuclides within air samples; and determi-nation of concentrations of uranium, plutonium, americium, neptunium, the thorium-232 decay chain, and the radium-226 decay chain in soil and other material samples from the involved areas. The direct instrument and smear surveys were performed on all accessible floor, wall, and overhead surfaces and ductwork in the laboratory and corridor areas, mechanical room, and I i men's locker room, where the false ceiling, formerly at the 12-ft level, had been removed. In the office areas, the accessible floors, walls, and overheads were surveyed to the height of the existing 8-ft false ceiling. Although the office areas were adjacent to, not part of, the affected areas, n U 6,.
4 it was possible that radioactive materials could have been carried by the fl ventilation systea, spilled, or otherwise tracked into these adjacent areas. V In some building areas, surfaces might have been retiled, painted, cr other-wise covered since the beginning of use of radioactive materials; however, the instruments used for the direct survey had some capability to detect beta gamma activ:.ty on the underlying surfaces. The locatiens of accessible areas surveyed or sampled are listed in Table 1 and shown in Figures 4 through 6. Direct Instrument Surveys Four types of portable survey instruments were used to conduct the direct radiological surveys. Gas-flow proportional detectors with detection areas of 51 cm2 or 330 cm2 and utilizing Eberline PAC-4G-3 electrcnics were used to monitor for direct alpha and/or beta gamma surface contamination. The larger-area probes were used in Eberline floor monitors (FM-4G), whereas the smaller, hand-held probes (Eberline AC-21) were used to survey the walls, overheads, and other areas inaccessible with the floor monitors. The ' gas-flow instruments were initially used in an alpha, beta, and. gamma sensitive detection mode. Normally, only when an area indicated a count rate above the background was the instrument then switched to an alpha only sensitive detection mode. However, in order to increase the detection probability within the Main Lab for low levels of alpha contacination, the entire lab was surveyed in both detection modes. NaI(TA)-crystal detectors, 2 in (5 cm) diameter by 2 mm thick (Eberline PG-2 with Eberline PRM-5-3 electronics), were used to monitor for low energy x and gamma radiation throughout; additionally, a 5-in (13-cm) diameter by 2-mm-tbick crystal detector (Eberline PG-5) was used to monitor the open pipe races in Rooms 4117 and 4118 during the first survey. An Eberline Model 530 Geiger-Mueller I (GM) detector with an Eberline HP-190 end-window probe was used to obtain a contact exposure rate reading (in mR/h) of contaminated areas. NaI(TA)- crystal detectors, 1 in (2.5 cm) diarater by 1 in thick (Eberline PRM-7 pR meter) and calibrated with a 22sRa standard source, were used to measure the ambient external penetrating radiation field in units of pR/h. These instruments and associated calibration procedures are detailed in Appendices 1 and 2.
Y 5 h Although 239Pu and ' 80Sr 80Y ? standards were 'used: to calibrate the _ . gas-flow. instruments, it should be noted - that the ' numerous isotopes - that i . could be encountered exhibit' emission ~ energies differing from those of the standards used in -the calibration. Shen detecting known isotopes that emit-q alpha and beta energies dif fering ' from those of the standcrds, such as normal uranium *, a conversion factor for those particular radionuclides' was developed'to determine the appropriate yield. The methods used to determine-the ' conversion factors' are. described in Appendix 2. .All readings of-dis-l 2'(dis / min-100 cm ), as reported in Tables 2 integrations per minute per 100 cm 1 and 2, are equated to 239Pu.and 90Sr 90, unless otherwise stated. It. Y should also - be noted that since calibrations are to infinitely-thin flat - plate standards, all readings as reported should. be regarded au minimal i values; no corrections were made for absorption by surface media. Wen possible, the contaminant radionuclides were identified at the-time of the survey by performing gamma-spectral analysis on the contaminated item or on a sample of material taken from the contaminated area. These analyses were performed.with a NaI(TA) crystal or hyperpure germanium (HPGe) O detecter ceuP ed to the aggregriate e1ectrenics and a meitichannel analvser. i This instrumentation (a1so described in ' Appendix 1), along with all other survey and sampling devices, was housed in a mobile laboratory--a specially designed, converted motor home. Smear Surveys Dry smears were taken with 4.25-cm-diameter filter papers (Watman #1) at representative locations throughout the facility to assess removable
- The term " normal uranium" refers to uranium which has been separted from its radioactive decay products and other impurities, and which has the
( normal isotopic percent abundances as ~found in nature. The normal percent abundances are 0.0054% 234U, 0.720% 23sU, and 99.2746% 3sU (Ref. 2)..The 2 less precise definition of normal uranium as 0.7% 23sg,.99.3% 23sU, and a trace of 234U is sometimes used for brevity 'in discussio'ns. The - term " natural ~ uranium" denotes uranium and all decay products as found in a. natural state in the earth, and is sometimes incorrectly referred ' to as normal uranium. Appendix 5 contains the detailed calculation' of the. specific activity of normal uranium.
~ 6 h ~ surface contamination levels. A standard smear sample is obtained by apply-- ing moderate pressure with thE tips of' the first two fingers to the ~back of _ the filter paper and wiping the-surface over _ an area of approximately 2 100 cm. Smears were taken on accessible structures and components such as. walls, floors, overheads, drain pipes, and. ventilation ducts. To expedite - the counting of ? the hundreds of smear ' samples 1 collected,- - two counting techniques were employed ' with two types of counters. A large-area, 10-wire gas-flow proportional counter, sensitive. to alpha and/or beta gamma-radiation, was used to make an. initial count on-groups of ten smears. ' Additionally, at least one smear from each group wasl, selected at random and counted in the more sensitive Nuclear Measurements Corporation, Model PC-3A or 5, gas-flow proportional counter (PC counter) using an aluminized Mylar window (Mylar spun top) over _ the smear. 1A11 smears - from areas or objects with elevated direct instrument readings were individually counted in the PC counter. All smears from any group of ten indicating a reading statistically above the instrument background levels in the 10-wire assembly were counted individually in the PC counter, Smears were counted O in each detector for both alpha and beta gamma activity. A more detailed description of the counters used is presented in t Appendix 1. The factors used to convert instrument counts to disintegra-tions of a particular isotope for all the smears are given in Appendix 2. ,Unless otherwise indicated, all contamination on the smears reported in 239Pu and 90Sr.90Y, as described in Appendix 2. Tables 1 and 2 is equated to f Ambient Penetrating Radiation Measurements The areas being surveyed were monitored for ambient external penetrat-ing radiation levels (in pR/h) at 1-meter heights in selected locations. Integrated measurements of the ambient penetrating radiation field (in pR/h) were taken with a Reuter-Stokes RSS-111 pressurized ionization ~ chamber (PIC), calibrated with an NBS-traceable gamma-ray source (see Fig. 5). Integration periods were minimally about five hours. This instrument and associated calibration procedures are detailed in Appendix 1. O
p n: 7. j Air. Samples 1 - Air ' samples were collected at selected locations with ; a commercial' vacuum cleaner modified at ANL for use as a particulate' air-sampling device 8 (see ' Fig. 5). 'A tott1 volume ofJabout-30 m of. air-was sampled at a flow-8 rate of 40 m /h (670 'A/ min). A 10% portion, 5 cm in diameter, us. removed from the filter medium after collection and counted for both ' alpha and beta gamma activity in the proportional counter, using a Mylar ~ spun top. Concentrations of radon-(222Rn) daughters, thoron (220Rn) daughters,!andlany long-lived airborne radionuclides were determined based on the results L of several counts of each sample at specified intervals. Air particulate-samples were also collected on Millipore membrane filter media using a positive-displacement pu:np operated at a flow rate of - 8 about 1 m /h (17 1/ min). Sampling periods were minimal'ly 80 minutes ~. 'A portion of each filter (approximately 17% of active area) was ' subjected to alpha spectral analysis to determine the ratio of the actinon (21sRn) daughter concentration relative to the radon (222Rn) daughter concentration. Details of the equipment used are given in Appendix 1.. The-' assumptions used and details of the air-sampling techniques and associated calculations-are given in Appendix 3. Soil and Material Samples Sixteen soil samples (11-S-1 through - 16) were collected 'during the - first survey from the excavated open pipe races in Rooms 4117 and 4118 (see Fig. 6). All the samples were collected to a 6-in (15-cm) depth in order to determine if any contaminated soil remained following Battelle's D&D of the contaminated drain Lines and associated soil. During the second survey, a sample of roof gravel (11-Gravel-17) was collected from in area of elevated i radiation levels, ultimately attributed to gamma shine from the nearby Hot-l Cell Facility. During the third survey, _ samples of sand, concrete, and a metallic speck (11-Sand-18, 11-C-19, and 11-MS-37) were collected from contaminated areas as determined by direct instrument survey. Ten soil samples (11-S-27 through 36) were collected to a 2-in (5-cm) depth from the excavated open pipe races in the Main Laboratory and one soil sample (11-S-38) was scraped from the excavated pipe race under the west corridor. }_ 1 =
8 (~') Two samples of wet sludge deposits (11-SS-39 and 40) were collected from the q,i walk-in air supply manifold in the mechanical room. The four ducts at the manifold used to supply air to the Main Laboratory, the office areas, and the west and east sides of the Old Lab wing. Since no butterfly-type valves or filters were used by Battelle on the air supply ductwork, the possibility existed for backdraft from the laboratory areas during power outages. Sample 11-SS-39 was collected from the floor of the air supply manifold; sample 11-SS-40 was collected from the drain pan of the copper cooling coils inside the air supply manifold. Prior to the first survey, Battelle collected a series of predecommis-sioning environmental soil core samples from the environs near the buried autoclave and old holding tanks. Soil samples were taken in sequential 1-or 2-ft sections, most to a depth of 30 to 46 feet. A total of 568 samples were collected from 25 holes. In July 1979, 29 samples (renamed 11-S-51 to 11-S-71), representing 21 holes and 1-ft to 46-ft depths, were split with ANL (see Fig. 7). The autoclave and old holding tanks were excavated by Battelle in November and December 1981. During the third ANL/RSG survey, which followed that excavation, several samples were collected from or near protruding pipes within the remaining hole (samples 11-S-21 through 26) and from the groundwater which had half-filled the hole (sample 11-W-20) (see Fig. 8). After the third survey and following complete decommissioning,10 of the 21 samples collected by Battelle from the floor and walls of the excavated hole were split with ANL (renamed 11-S-41 through 50) (see Fig. 8). Samples were not supplied from the new holding tank area, located to the east of the former location of the autoclave and old holding tanks. All samples were prepared at Argonne National Laboratory. The sample preparation procedures, consisting generally of drying, milling, and siev-ing, are described in detail in Appendix 4. At no point in the preparation of soil samples were rocks and other solid material ground or pulverized, since this material would act as a diluent and, hence, lower the reported concentration of deposited radioactive material in soil. The rocks / dross and the sieved material were segregated, bagged, and weighed separately (weights are given in Table 5). Samples were analyzed by commercial laboratories (LFE Environmental (O Analysis Laboratories; Eberline Corporation, Albuquerque Laboratory) and by ~/ Argonne National Laboratory (Analytical Chemistry Laboratory; Environmental
9 Monitoring and Health Physics Sections of the Occupational Health and Safety Division). Analytical techniques included high-resolution gamma-spectral analysis to determine the concentration (in pCi/g) of the 22sRa decay chain, the 232Th decay chain, and other gamma-emitting radionuclides in the soil, a uranium-fluorometric technique to determine total uranium concentration (in pg/g), and/or radiochemical separation followed by alpha-spectral analyses to quantify isotopic concentrations (in pCi/g) of uranium, plutonium, americium, or neptunium. Analysis details are included in Appendix 4. SURVEY AND SAMPLING RESULTS Direct Instrument and Smear Surveys The results of all direct instrument and smear surveys are given in Table 1. The PAC-4G-3 instrument readings and smear results have been 2 normalized to units of dis / min-100 cm using the factors derived in Appendix 2 and are equated to 239Pu and 90Sr 90Y, unless otherwise stated. The PAC-4G-3 readings and smear data are reported in net disintegration rates, i.e., the background count rates have been subtracted from the gross count 2 rates prior to conversion to dis / min-100 cm. Any alpha contributions have been subtracted from the readings taken in the beta mode so that the corrected values reflect only the beta gamma readings. The low-energy x and gamma readings (in cts / min), measured with the PG-2 detector, the end-window GM response (in mR/h), and the PRM-7 readings (in pR/h) are reported as net rates above the appropriate background. Depending upon the specific instrument, probe, and calibration, background levels varied somewhat from area to area, due in part to differences in and proximity to construction materials and soils. The background readings for all modes of operation of the instruments used are given in the footnotes to Table 1. Elevated levels of radioactivity, as indicated by measurements inter-preted to be above the background, were found at 51 contaminated floor, wall, or overhead areas during the three surveys (see Fig. 4 for locations of all these areas except location 548, the contaminated carpet mat at the main entrance to the office corridor). Several additional measurements within the Plutonium Facility were influenced by waste drums being tempor-AU arily stored within the facility, by gamma shine from the adjacent Hot Cell
10 Facility, or by shine from a buried container in the environs due north of O the effice cerrider. The maximum 1estrement measuremeets et the coetemi-nated areas and at other areas surveyed are given in Table 1. The direct instrument and smear survey results during each survey were compared to the American National Standards Institute (ANSI) Draft Standard N13.12, " Control of Radioactive Surface Contamination on Materials, Equip-ment, and Facilities to be Released for Uncontrolled Use," and to the Nuclear Regulatory Commission (NRC) " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termi-nation of Licenses for By-Product, Source, or Special Nuclear Material" (see Appendix 6). At the time of each survey, only gamma-spectral analysis was immedi-ately available for purposes of specific identification, and this technique 241 did identify Am as a predominant contaminant in one instance. Neverthe-less, most of the contaminants were not immediately identified. It was known, however, that isotopes of plutonium and americium had been.used in the Plutonium Facility. The allowable limits in the ANSI Draft Standard for plutonium and americium isotopes, as well as for cases when the contaminant m (Q cannot be identified, is 20 dis / min-100 cm2 removable, and the limits are such that the total (fixed plus removable) activity must be nondetectable using instruments calibrated to measure at least 100 pCi of the contaminant 2 uniformly spread over 100 cm. The NRC Guidelines for plutonium and americium isotopes are stated as follows: "The average (total activity) is 100 dis / min-100 cm2 2 and the removable is 20 dis / min-100 cm." The allowable limit in the ANSI Draft Standard and the NRC Guidelines for uranium is 5000 dis / min-100 cm2 2 total, of which only 1000 dis / min-100 cm can be re-movable. In both the ANSI and NRC criteria, all levels for total activity 2 may be averaged over 1 m provided the maximum activity in any area of 100 2 cm is less than three times the limit value. All detected areas of alpha contamination rere above the ANSI Draft Standard criteria for plutonium and americium isotopes. During each survey, Batteile was notified of the contaminated areas and began further decon-tamination efforts. The results of subsequent direct instrument and smear surveys following these additional decontamination efforts are presented in ' Table 2. No contamination was detected at any area following final decon-O teminetion efferts.
11 Ambient Penetrating Radiation Measurements The results of the ambient external penetrating radiation measurements with the RSS-111 pressurized ionization chamber are presented in Table 3. Prior to each measurement, all locations chosen were surveyed with the PRM-7 pR meter. These chosen locations gave measurements believed to be repre-sentative of the area's ambient penetrating radiation levels, except for the measurement in the men's locker room (exposure rate of 46.7 pR/h), which was influenced by proximity of the location to the Hot Cell Facility. Exposure rates at the other locations sampled in the Plutonium Facility ranged from 7.54 to 12.4 pR/h, deemed to be representative of natural background radia-tions. l Air Samples Results of the analyses of sir samples collected at selecte'd locations l and under varied conditions of ventilation within the Plutonium Facility are l presented in Table 4. Techniques detailed in Appendix 3 were used to de-O termine the raden (222Rn) dau.hter concentration (in mi111-Workin tevet, mWL) and thoron (220Rn) and actinon (21Nn) daughter concentrations (in I picocuries/ liter, pCi/2) at each location. The radon daughter concentrations ranged from 0.37 to 10.6 mWL. These values are below the limit of 0.02 WL (or 20 mWL), including background for average annual concentration as specified in the Environmental Protection Agency Standard (40 CFR 192). The values also are less than the value of 0.01 WL (or 10 mWL) above background, for which the U.S. Surgeon General's Guidelines in 10 CFR 712 do not indicate a need for remedial action (see l Appendix 6).) If an equilibrium fraction
- of 0.5 is assumed, radon concentrations, as determined from the radon daughter concentrations, ranged from 0.07 to 2.1 pCi/A.
These are below the concentration guide of 3 pCi/2 for an uncontrolled area, as given in the Department of Energy (DOE) Order 5480.1 " Requirements for Radiation Protection" (see Appendix 6).
- The equilibrium fraction is defined as 100 times the radon daughter concen-tration (in WL) divided by the concentration of radon (in pCi/A).
This C fraction typically varies from about 0.3 to 0.7, with an average of about O.S.
12 ~3 The thoron daughter concentrations (ThB and ThC) ranged from 1.1 x 10 AU to 1.8 x 102 pCi/2. If equilibrium between thoron and its daughters is assumed for the air sampled (a conservative assumption), then thoron con-centrations were identical to those listed for thoron daughters. These are far below the concentration guides for thoron (220Rn) and ThB (212Pb) of 10 pCi/A and 0.6 pCi/A, respectively, for an uncontrolled area, as given in the DOE " Requirements for Radiation Protection." All measured concentrations of radon and thoron daughters were well within the range of values normally expected for ventilated and unventilated indoor background concentrations. The concentrations of actinon (219Rn) daughters were below detection limits, except for one concentration of 0.12 pCi/A measured in the Main Laboratory after final D&D efforts. This concentration is not significant (i.e., equivalent to less than 1 mWL). The source of the actinon (the 227Ac decay chain), be it a contaminated surface or soil contamination, could not be located. No actinon daughters were detected in a second air sample collected later on the same day at the same location; the source of the first elevated concentration remains inexplic-able. No long-lived radionuclides were detected in any air sample. Solid and Material Samples Results of the gamma-spectral, uranium-fluorometric, and other radio-chemical analyses performed on the soil samples from the pipe races, the material samples, and the ANL and split environmental soil and coring samples are listed in Tables 6 through 8. Table 6 contains the results of gamma-spectral and uranium-fluorometric analyses of samples; Table 7 the results of plutonium, americium, and neptunium isotopic analyses of samples; and Table 8 the results of uranium isotopic analyses. Pipe Races - Analyses of the initial eight soil samples (11-S-1 through
- 8) collected from Rooms 4117 and 4118 during the first survey yielded 1
concentrations of 0.09 1 0.02 to 6.3 1 0.7 pCi/g for 23sPu, 0.03 1 0.01 to 0.37 1 0.06 pCi/g for 239:240Pu, and 0.02 1 0.02 to 0.10 i 0.03 241 pCi/g for Am, indicating the presence of residual soil contamination within the races. Uranium (including isotopic), cesium-137, and Q l V
.~.., _ _. ~
- 13 r
n thorium and radium decay chain concentrations were within the normally- ..h expected ranges for background concentrations. -When Battelle. was notified of. this contamination, a'dditional-soil was removed from the. 4 pipe races in Rooms ' 4117 and 4118; eight more samples -(11-S-9 through I {
- 16) were then. collected by.
Plutonium analyses : o'f _ these ' soil. ANL. samples indicated concentrations of 0.008 1 0.002 to 2.956 't 0.039 ^ l pCi/g for 23sPu and-0.003 1 0.001 to 0.647 t'0.018 pCi/g for 2se",24oPu,. levels deemed to be as low as reasonably achievable (ALARA). } . Plutonium and americium analyses o f. the ' 11 soil samples -(11-S-27 l through 36 and 38) collected. in the Main Lab from the remaining pipe i races during the third survey indicated ' O.005 10.005 m to.15.0 1.1.5 f pCi/g for 239,240 0.39 10.04' pci/g : for ~ 2sspit, Pu, 0.005 1 0.005 to 241 j 0.004 1 0.004 to 3.6 1 0.3 pCi/g for Am, and 0.005 1 0.003 to 0.03 1-0.02 pCi/g for 287Np. The highest levels were in sample 11-S-34, collected near the east foundation wall where the pipe race led to the - l outdoor environs. Uranium, cesium-137, thorium, radium, and. actinium ]O decay chain coricentrations were within the normally expected ranges for dac=8 e d ce ce tratio s. Material Samples - Analysis of sample 11-Gravel-17, collected from the. j roof during the second survey, indicated only background concentrations of cesium-137 and the thorium and radium decay chains. Analysis. of' ) f contaminated sandblast sand, 11-Sand-18, collected from an overhead I-beam during the third survey, indicated a concentration of 3.4 i 241Am. Concentrations of cesium-137 and the thorium and l 1.5 pCi/g for 7 l radium decay chains were at background levels. Analrsis of contami-f nated concrete, 11-C-9, chipped out of the concrete floor during the l third su ney, indicated 50,000 i 10,000 pCi/g for Am, in addition to 241 { a separate chip containing 30,000 1 5,000 pCi of 241Am. Concentrations I, of cesium-137 and the thorf um and radium decay chains were at back-i ground levels. The loose metallic speck found on the Main Lab floor j was not submitted for radiochemical analysis;. however, analysis ' by i direct survey instrument indicated at least 5300 pCi alpha.'. Analysis-of sample 11-SS-39, the wet sludge deposit collected from the floor of iO 6 + 3 , _ - _ _ _ - - _ - - _ _ = _ _ _ _ - _ _ _ _ _ _ _ _. _. _ _ _ - _ - - -
14 the walk-in air supply manifold, yielded concentrations of 0.057. t 0.007 pCi/g ' for 239,240Pu, 0.013 1 0.005 pCi/g ' for 2ssPu, and 0.046 i 241 ~ 0.008 pCi/g for Am in the suspended solids fraction, indicating that. ~ the ventilation system -was contaminated. = All other measured concen-trations in the suspended and. dissolved solids fractionsLwere at back-ground levels. Analysis of. sample 11-SS-40, the wet sludge deposit collected from the drain pan of the copper cooling coils inside the air supply. manifold, yielded concentrations-of 1.7 1.0.1 pCi/g for 2ss,240 Pu, 0.07 1 0.01 pCi/g for 2ssPu, and 0.40 1 0.04 pCi/g for 241Am in the suspended solids fraction, confirming that the ventilation system contained contamination. All other measured radionuclide con-centrations in the suspended and dissolved solids fractions were at - background levels. Environmental Soil and Coring Samples - Analyses of the split predecom-- missioning environmental soil core samples (11-S-51 through 71) collected from the environs near the buried autoclave and old holding tanks indicated radionuclide concentrations of up to 24.30 1 0.34'pCi/g O fer=== =*aru, ur te 0.731
- 0.060,Cie for===eu, and u, te 32.s
- 9.4 pCi/g for 241Am.
The highest levels were in sample 11-S-70-21, collected at the 21-ft depth near 'or below the autoclave's - concrete pad. Samples 11-W-20 through 11-S-26, collected durf.ng the third survey from the excavated hole, were not analyzed for plutonium and americium isotopes; the other analyses conducted on the samples tended to indicate background concentrations only. Analyses of the split environmental soil samples (11-S-41 through 50), collected from the floor and walls of the excavated hole ' prior to backfill with clean soil, indicated concentrations of 0.047 1 0.010 to 13.9 1 0.5 pCi/g for 239,240Pu, 0.005 1 0.003 to 0.36 1 0.04 pCi/g for 23sPu, and 0.019 1 0.005 .t-9.81 1 0.50 pCi/g for 241Am. Uranium, cesium-137, and thorium and radium decay chain concentrations were within the normally expected f ranges for background concentrations. O
15-CONCLUSIONS AG Results of direct instrument and smear surveys conducted during the post-remedial-action radiological surveys by the ANL Radiological Survey Group indicated the initial presence of several areas of contamination at the Plutonium Facility. Analyses of samples collected from some of the contaminated areas indicated 241Am as among the contaminants. Following final decommissioning and decontamination efforts by Battelle personnel, the interior surfaces surveyed within the Plutonium Facility met both the ANSI Draft Standard N13.12 and NRC Guideline criteria for acceptable plutonium, americium, or unknown contaminant surface contamination levels. Several radiation measurements within the Plutonium Facility were influenced by direct gamma or scattered (i.e., shine) radiation from the adjacent Hot Cell Facility, waste drums, or holding tanks. Analysis of air samples collected at the involved areas within the Plutonium Facility indicated that the radon, thoron, and progeny concen-trations within the air were well below the limits prescribed by the U.S. Surgeon General, the Environmental Protection Agency, and the Department of O Enerav. A 1ew 1evet ef ectinen Presenv <0.12 PC1/2) was measured within ene air sample; the source of this elevated concentration could not be determined. No actinon progeny was detected in a repeated measurement at the same location or in any other air sample. No long-lived radionuclides were detected in any air sample. The interior of the air supply manifold was found contaminated with plutonium and americium, indicating a contaminated ventilation system. Wet deposits were collected from the floor inside the walk-in supply manifold, as well as from the drain pan of copper cooling coils. Radiochemical analyses indicated radionuclide concentrations of up to 1.7 0.1 pCi/g for 241Am in 239,240 Pu, 0.07 i 0.01 pCi/g for 23sPu, and 0.40 1 0.04 pCi/g for the suspended solids fraction. The Battelle decommissioning personnel were apprised of these finds and have addressed them. The excavated pipe races within the Main Laboratory and Rooms 4117 and 4118 are contaminated with plutonium and americium. However, this followed two decommissioning attempts and is deemed to be ALARA in the context of this decontamination effort. Results of radiochemical analyses of soil O
16 - collected after fina1 ' decommissioning of the races indicated concentrations - ~ of up to 15.0 1 1.5 pCi/g for 239,240pt, 2.956 1 0.036 pCi/g for 2ssPu, and 3.6 1 0.3 pCi/g for 241 A Analyses -of split environmental samples collected near. the _ buried autoclave and old holding tanks prior to decommissioning activities indi-- 239,240 cated concentrations in soil of up to 24.30 1 0.34 pci/g for Pu, 0.731 t Q.060 pci/g for 23sPu, and 32.5 9.4 pCi/g for 241Am. Following the excavation of the. autoclave and old holding tanks and the completion of decommissioning and decontamination efforts there, additional' soil samples were collected and split with ANL. -Analyses of these split environmental soil samples indicated concentrations in soil of up to 13.9 i 0.5 pCi/g for 239,240 Pu, 0.36 1.0.04 pCi/g for 23sPu, and 9.81 1 0.50 pCi/g for 241Am. The samples were collected from the - floor and walls of the _ excavated hole prior to backfill with clean soil, and are indicative of the current status of the subsurface soil at these locations. There are no universally accepted soil criteria for transuranics. However, one. may note several suggested criteria in the literature. A derived concentration for 239Pu'of 15 pCi/g can be obtained from an EPA sanctioned (Reference 3) areal limit using reasonable assumptions for soil density and depth of contamination. Recommended limits for 23ss239:240 241,/241Pu of 20 Pu of 100 pCi/g and for A pCi/g are cited in References 4 and 5. The concentrations of plutonium and - americium in the, split environmental soil samples are below these suggested critera and are judged to be ALARA. O
.17. REFERENCES I %e 1. Argonne National Laboratory, " Certification Survey' of the Plutonium l Facility of the -Battelle. Memorial Institute, West ~ Jefferson Complex," . draft final report, October 27, 1980. 2. Holden, N.E. 1977. " Isotopic Composition of the Elements and Their Variation in Nature: A Preliminary Report." BNL-NCS-50605. Brookhaven National Laboratory. 3. U.S. Envrionmental Protection Agency. 1977. " Proposed Guidance on Dose Limits for Personnel Exposed. to Transuranium Elements in the General i -- Environment." EPA-420/4-77-016. 4. J. W. Healy. "A Review of Resuspension Models" in " Transuranium Elements in the Envrionment." W. C. Hanson, Ed. U.S. Department of Energy. TIC-22800. 1980. 4 i 5. U.S. Department of Energy. " Radiological Guidlines for Application to DOE's Formerly Utilized Sites Remedial Action Program." ORO-831. March 1983. .) e i 0 ~ 1 I e 1 I j i s h l l 1 i.
- O I
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O O O ANL-HP DWG. NO. 84-38 71 -G rA COLUMBUS I4 MILES % h BIG DARBY CREEK r F" 142 s l p::::= 7 71 (COLUMBUS s LITTLE DARBY
- lff i CREEK
.,4 l I WEST g JEFFERSON ' _ BATTELLE WEST j JEFFERSON SITE N 9 2 MILES Figure 1. West Jefferson Site.
5 O 5 3 -2 Y 8 T I L O IC N. Y A G IT F Y L T W T I L C U D IL A A I P C F V J A L H F L M E L U C g N I T N A O O T H UL 3 P a / er 7 A E s ~ ) L e / A c J NS C ne i O c / A A N E S E K R p A r O A L a E e SC E l EN L c CE L u NF ET N EIY T CT A SI B 2 R h / RU Y E i e AC T S r LS L Ob_ EE U u I g I ) C C I. H i D F U A M N F R ) 5 A R g U O I. 1 ( G T M C m A 5 K E 1 R ( 4 2 D m E K S R U AM I 4 B
- a #
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r 20 O ANL-HP DWG. NO. 8.4-37 CO_ j, = AUTOCLAVE (BELOW GRADE)N / OLD HOLDING TANKS -h (BELOW GRADE)- MAIN LABORATORY s 7F I / I y 7
- -m oo o
M'-4 h DRAIN LINES Y A /- " ' ^ " O = ~ -~ - v HOT ACCOUNTABILITY C E METALLOGRAPHY LAB g g OFFICE g y COLD Pu238 LAB J jl, MECHANICAL CHANGE ROOM ROOM 4 OFFICE AREA i i Figure 3. Plutonium Facility Before Decommissioning. O i J 9 ,n> .., +,
ANL-HP DWG. NO. 84-48 PIPE TRENCH [ '8' 4,e g \\.6 l ~ SOUTH CORRIDOR j ( ' D 4 -g 8 N -h g i ] ,N o ~ METERS i y,i Ne t _ _3 WEST CMDOR O FEET O u / MAIN LABORATORY 3,, y ~ B,@ " s ui u. .n 5.4 - + S & 5 5Y 5 ._ g --B VE4 21 43ls 5 / 4119 A - .D. ROOM NUMBER ~ C m CONTAMINATION LOCATION l 4109 L"I BY SMEAR NUMBER l 4f198-.. 4118 ns 4117 g OVERHEAD CONTAMINATION LOCATION BY SMEAR NUMBER i l 41 l 9 C - j OFFICE CORRIDOR Figure 4. Plutonium Facility Contamination Locations. l \\
O O U ANL-HP'DWG. NO. 84-32 PIPE TRENCH \\ l I N O m METERS A p L_m5 O Al I MAIN o WORKSHOP -+ LABORATORY O 20 FEET 3 ? O u O A ll WEST CORR. MEN'S LOCKER RM. A 4118 A 43 4116 MECHANICAL 4,,,/ 4ll9A - O goou c==2 Ao 4119B - A AO O A 4117 A 4119C - a t _w OFFICE CORR. ._4112 J n ROOM NUMBER A AO 4' 8 4' S 4' 4 4' 4 4108 O 4 02 A AIR SAMPLE LOCATION j RSS-lil RADIATION 4107 O MEASUREMENT Figure S. Air Sample and RSS-111 Radiation Measurement Locations.
O O O ANL-HP DWG. NO. 84-33 l li-MS37l 1!-S35 Il-S36 1l-S34 Il-SAND 18 l Il-S33 ~ d7 l / Il-S32 i N 1!-S31 \\ 4 / II" N [ Il-S28 \\ MAIN l!-S29 N N LABORATCRY l N l l / il-S27 METERS j Il-S38 \\ / O 5 \\ ll-C19 l O 20 0 II-33 U / FEET \\ It-SiI ~ (PPE TRENCH II-SS39 -SI2 Il-S6 4ll9A 'N / yg ii-Si4 N Nl / 4109 Il-Si -e i1-SS40 y' l1-S9 4119 B 'b y f Il-GRAVEL 17 (OUTSIDE ROOFJ / i X n, ROOM NUMBER Il-S5 1l-S7 il-S8 Il-S2 Il-S13 Il-SIS Il-S16 lll-S SAMPLE IDENTIFICATION Il-SIO Figure 6. Plutonium Facility Soil and Material Sample Locations.
O O O ANL-HP DWG. NO. 84-36 Il-S62 \\ NEW PU l1-S54 FACILITY \\ l1-S55 ll-S63 \\ ll-S57 II~ l l1-S61 Il-S56 11-S51 \\ J Il-S60 Il-S58 OLD HOLDING fS ,- s TANKS / g i s il-S67 I Il-S68 ) ^ \\ / \\ C - - - - +-- i l i / \\ l I ~ j A
l-
~ f Il-S66 [ ( j A i y %j J f /gN,/ i1-S65 UNDERGROUND l1-S7l s AUTOCLAVE / HOLDING TANKS Ii-S69 / OLD PU FACILITY O METERS 5 N ~ Il-S70 l1-S53 OC 11-S52 O FEET 20 Figure 7. Plutonium Facility Environmental Sample Locations Before Decommissioning.
O O O ANL-HP DWG. NO. 84-34 11-S23 Il-S22 NEW PU FACILITY Il-S47 SERVICE ROAD l 11-S2I 11-S41 UNDERGROUND I l-W2O l HOLDING TANKS N d / s f Il-S24 I t I t Il-S46 l l l l [] Il-S43 i e s {f ~ ___~- i1-S42 v D y s OLD HOLDING TANKS y g I f \\ ) ^ ^ LIMIT OF EXCAVATION 4 ) Q OLD PU FACILITY l1-S48 METERS / / / o 5 l l-SSO l l1-S45.l ^ ll-S25 1l-S44 O 20 FEET il-826 Figure 8. Plutonium Facility Environmental Sample Locations Following Decommissioning.
O O O~ r TABLE 1. RESULTS OF DIRECT INSTRUMENT AND SMEAR SURVEYS PAC-4G-3 PG-2 ~ Direct Readings
- GH Reading PRM-7 Low-Energy Smear Result 2
2 (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) Location. Beta-Gamma Alpha @ contact @ l meter (cts / min) Beta-Gamma Alpha Comments BKGD BKGD BKGD 1916 Contaminated area on north wall, 4116 BKGD BKGD smear 146 BKGD BKGD BKGD BKGD BKGD 2517 Contaminated area on south wall, smear 157. BKGD to BKGD BKGD BKGD Rest of survey was background, BKGD BKGD 7 smears 141-200; 7 pR/h near the entrance due to temporarily stored waste. 4117 BKGD BKGD BKGD BKGD BKGD BKGD Survey was background, smears 1-80 d Open trench (pipe races), see BKCD. BKGD BKGD BKGD 11-S-3 through 8, 11 through 16 Drains BKGD BKGD BKGD BKGD 8 BKCD BKGD NRR BKGD BKGD Contaminated area on concrete 4118: BKGD 1.2x10 floor, grid C-5, smear 135 9.8x102 7.6x103 0.02 BKGD 1114 Contaminated area on concrete floor, grid A-3, sacar 201 Open trench'(pipe race), see BKGD BKGD BKGD BKGD 11-S-1 & 2, 9 & 10 BKGD BKGD BKGD BKCD Drain BKGD. BKGD BKGD BKGD ,BKGD BKGD Rest of survey was backgroun'd, smears 81-140 4119A BKGD
- BKGD BKGD to BKGD to BKGD-BKGD
. Gamma shine at ceiling due to-3' 3 12 3.0x10 Hot Cell Facility, smears 241-250 -~.
m O. O 10 TABLE 1 - (cont'd.) PAC-4G-3 PG-2 Direct Readings" GH Reading PRM-7 Low-Energy Smear Results 2 2 (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis /mia-100 cm ) I.oca tion. Be ta-Gaimaa Alpha @ contact @ I meter (cts / min) Beta-Gamma Alpha' Comments 4119A BKGD BKGD BKGD BKGD BKGD BKGD Rest of survey was background, (cont'd.) . smears 2018 - 240 4119B BKGD BKGD 13 3.5x10 BKGD BKCD Shine 'at ceiling due to llot. 8 ' Cell Facility, smear 361 BKGD BKGD BKGD BKGD BKGD BKGD Rest of survey was background,. smears 251-310 4119C BKGD BKCD BKGD-BKGD BKGD BKGD. Smears 311-360 t 50 to 1.4x104 Gamma shine due to nearby llot E3 Roof over 4119 A, 90 Cell Facility. ll-Gravel-11 B, C collected Hain j labora tory i Floor ~ 1.1x10 91 BKGD 1.0x103 BKGD BKGD Contaminated area on concrete 3 floor, grid D-14; smear 375 ' 2 BKGD .BKGD BKGD BKCD Contaminated area on concrete 4.8x102 1.2x10 floor, grids B-2 & 3', smear 363 6.1x102-1.8x102' BKCD BKGD BKGD BKGD Contaminated area'on conre'te j floor,- grids C-4 & 5, smear 369 BKGD 2.0x102 BEGD BKGD BKGD' BKGD ' Contaminated area on' concrete floor, grid F-10, smear 371 4.2x102. 1.8x102 BKGD' BKGD. BKGD BKGD ' Contaminated area ~on concrete floor, grid J-6, smear 367 1 e v sw w
O O n_ 6 TABLE 1 - (cont'd.) 4 PAC-4G-3 PC-2 Direct Readings *' GH Reading PRH-7 Low-Energy Smear Result 2 2 (dis /e.in-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) Location Beta-Gamma Alpha @ contact @ 1 meter tets/ min) Beta-Gamma. Alpha Comments i. Floor 7.2x103 2.3x104 BKGD BKGD Contaminated metallic speck on (cent'd.) floor, grids K & L-1, taken as 11-HS-37 BKGD BKGD BKGD BKGD BKGD BKGD Rest of floor survey was back-ground, smears 363-316 North BKGD 6.9x102 BKGD BKGD BKGD BKCD Contaminated ares on north; wall, 1 Wall grid N-4; smear 415 BKGD 8.8x102 BKGD BKGD BKGD. BKGD' ' Contaminated area on north wall, grids N-3 & 4, smear 416 $3 2 2 BKGD 1.0x10 BKGD 4419 Contaminated area on' north wall, BKGD 3.9x10 grid L-3, smear 414 1 BKGD-6.9x102 . BKGD BKCD 52123' 50110 Contaminated area on north. wall,. grid.1-4, smear 413 BKGD BKGD. . BKGD ,BKGD BKGD BKGD Rest of north wall was background, smears 377, 410-416, 421, 444 ~ BKGD .3.9x102 BKGD BKGD BKGD. 9.614.0 Contaminated area on east wall, Fast . grid C-4, smear 379 Wall BKCD 3.9x102 BKGD BKGD BKGD-BKGD ' Contaminated area on east wall,- grid J-4, smear 391-BKGD BKGD BKGD BKGD.' BKGD BKGD Rest'of east wall was back-ground, smears-378-379, 389-392 . South BKCD ' 98 69123 3718 ' contaminated sewer pipe at south Wall wall, grid D-5, smear 395 BKGD .BKGD BKCD BKGD- .BKGD. UKGD Rest of south wall was backgrounal,' 393-396, 400-403, 417 smears 1 e r -.
O O-O 4 TABLE 1 -.(cont'd.) PAC-4G-3 PG Direct Readings" GH Reading PRM-7 Low-Energy Smear Result 2 2 { dis / min-100 cm ) (mR/h) (R/h) x&y (dis / min-100 cm 7 Location Beta-Gamma Alpha @ contact @ l meter (cts / min) Beta-Gamma Alpha Comments West 4.9x102 4.9x102 0.005 BKGD BKGD. BKGD BKGD Contaminated speaker on west Wall wall, grid G-2, smear 384 BKGD BKGD BKGD BKGD BKGD BKGD Rest of west wall was back-7 ground,' smears 384, 404-409, [ 419, 424 t over-BKGD 1.4x103 BKGD BKGD BKGD BKGD Contaminated I beam'at ceif-head ing.. grid K-9, smears 380 & 381, 11-Sand-18 collected i BKGD 1.4x103 BKGD BKGD BKGD 1916 Contaminated \\" dia. aluminum ' U$ tubing at ceiling, grid H-11, smea r. 386 BKGD '7.8x102 BKGD BKGD BKCD 814 contaminated filter support at ~ ceiling, grid N-10, smear 385. 2 BKCD BKGD BKGD-BKGD Contaminated duct at ceiling hKGD 5.9x10 grid N-12, smear 388 BKGD 1.4x103 0.005 2.5x102 BKGD BKGD' Contaminated duct int'erior at ceiling grid N-16, smear 383 BKCD '677147 530130- Contaminated 5" diameter tub-3- BKG9 UKGD -4.7x10 ing at ceiling, grid 0 - 11,. smear 387 4.5x103 1.2xt04 0.01 5'0x102-38211 2265' Contaminated exhuast duct-in-97 i 81-terior at ceiling, grid P-8, smear 382 BKGD BKGD BKGD Rest of overhead survey was BKCD BKGD background, smears 380-383, '385-388, 397-399, 418, 420,- 4 ? 622-423, 425-431, 437-443, 445, 447-448, 456-457, 678-679 .i l v v
(3 0' O v TABLE 1 - (cont'd.) PAC-4G-3 PG-2 Direct Readings" GH Reading PRM-7 Low-Energy Smear Result 2 2 (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) 1.oca tion Beta-Gamma Alpha @ contact @ l meter (cts / min) Beta-Gamma Alpha Comment s Center liKGD 4.9x102 BKCD BKGD BKGD BKCD Contaminated area on north side Pillar of brick center pillar, grid C-4, c> ear 450 BKGD BKGD BKGD BKGD Rest-of survey was backgri und, llKGD i!KGD smears 432-436, 449-455 Open BKGD BKGD BKGD Survey of open trenches wak Pipe BKGD; see Il-S-27 tNaugh Races throu p 36, 38 w c O Roof over BKGD NS NS. . Survey of roof drains and ex-Hain Lab haust stacks was BKGD Workshop BKCD 5.9x102 BKGD BKGD BKGD BKGD BKGD Contaminated area on epoxy painted concrete floor, grid A-13, smear 498 BKGD 61 LKGD BKGD BKGD BKGD BKGD Contaminated area on epoxy painted concrete floor, griel A-14, smear 492-BKCD 1.4x103 0.005 BKGD BKGB 107125 60111 Contaminated area on' epoxy painted. concrete floor, grid A-18, smear 499 lIKGI) 1.4x103 0.01 BKGD BKGD BKCD BKGD Contaminated area on epoxy painted concrete floor, grid A-21, smears 488 and 490 2 BKGD BKGD BKCD BKGD BKGD Contaminated area on epoxy llKGD. 9.8x10 painted concrete floor, grid B-18, smears 489 and 491 2 BKGD BKGD BKGD BKGD BKGD . Contaminated area on epoxy 3.0x102 1.2x10 painted concrete floor, grid C-7, smear 500
O O O TABLE 1 - (cont.'d.) PAC-4G-3 PG-2 Direct Readings" GH Reading PRti-7 Low-Energy Smear Result 2 2 (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) Location Beta-Gamma Alpha @ contact @ l meter (cts / min) Beta-Gamma Alpha Comments [ Workshop BKCD BKGD BKGD BKGD 53121 BKGD - Smear 538 on ceiling, grid C-8 (con t' d. ) BKGD BKGD BKGD' BKGD BKGD BKGD Rest of survey was background, smears' 488-492, 498-500, 514-518, 533-547, 730-732 South BKGD 2.7x10 BKGD BKGil BKCD BKGD Contaminated area on epoxy 3 Corridor painted concrete floor, grid A-2, ~ smear 480 BKGD 1.9x104 BKGD BKGD 468 1 489 i Contaminated area on epoxy (a 43 29 ' painted concrete floor, grid A-12, smear 481 BKGD 1.2x103 BKGD BKGD BKGD BKGD Contaminated area on epoxy painted concrete floor, grid A-15, smear 483 5.9x102 -1.8x108' BKGD' BKGD BKGD BKGD Contaminated area on epoxy painted concrete floor, Erid B-13, smear 482 BKGD 227 1 168 i ' Contaminated I beam on south 3 ,BKGD .DKGD 1.2x10 31 17 -wall, grid E-1, smear 458 BKGD 85123 2617 ' contaminated shelf on south BKGD BKGD wall, grid I-1, smear 466 BKGD 1.6x103 0.005 (inacces-BKGD BK6D Contaminated I beam at ceiling, ible) grid C-16, smear 459 J BKGD BKGD BKGD 61123 4519 Contaminated unistrut at ceil-ing, grid B-6, smear 468 BKGD to BKGD-BKGD to BKGD to -BKGD BKGD Shine at south windows; rest 3.0x102 40 '2.0x103 of survey interpreted as back-ground, smears 458-474, 4El-4h3
m -. _. _ _ _ _ _.... m. m O O nv -i 1 TABLE 1 - (cont'd.) PG-2 PAC-4G-3 Direct Readings" GM Reading PRM-7 Low-Energy Smear Result 2 (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) 2 Location Beta-Gamma Alpha @ contact @ 1 meter (cts / min) Beta-Gamma Alpha. Comments 2 West BKGD to 98 BKGD to BKGD to BKGD BKGD Contaminated area (15 m ),, 2e 30 2.5x10
- unpainted concrete floor.-grids-e 3
Corridor 3.0x10 ABC-17 to 22, smears 484 (at C-20) and 510 (at-B-20) r BKGD 98 bKGD BKGD BKGD BEGD. Contaminated area on epoxy painted concrete floor, 3 grid B-2, smear 486 ~ 4 4.7x104 111 1 69 i Contaminated area on epoxy BKGD 2.Jx10 25 11 painted concrete floor, grid ta b* B-16, 11-C-19 collected, smear 485 BKGD 7.8x102 BKGD 'BKGD BKGD BKGD Contaminated area on epoxy painted concrete floor, grid-l C-2, smear 487 1.5x104 6.3x104 0.005 BKGD 5549 i 45581 - Contaminated area on south wall-126 86 behind exit sign, grid B-3, smear 478 t 8 BKGD BKGD' BKGD-BKGD' Contaminated 1\\" diameter pipe _ l BKGO 1.8x10 at ceiling, grid C-20, smear 477 l BKGD BKGD BKGD to Contaminated I beam at ceiling, BKGD 1.6x103 BKGD 65111 grid C-20, smears 475-476 BKGD BKGD BKGD to BKGD BKGD BKGD-Shine at outside exits, rest of 10 . survey interpreted as background,- smears 475-479,~484-487, 493-497, 301-513 2.2x103 BKGD' BKGD BKGD to Contaminated duct to Main Lab in Hechani-3.9x102 - cal Room - 512-east wall, waears 623-625
O O O 9 TABLE 1 - (cont'd.) PAC-4G-3 PG-2 Direct Readings
- GH Reading PRM-7
. Low-Energy Smear Result 2 2 (dis / min-100 cm ) (mR/h) (pH/h) x&y (dis / min-100 cm g Location Beta-Gamma Alpha @ contact @ l meter (cts / min) Beta-Gamma Alpha Comments BKGD 69125 BKGD Contaminated blower unit, smears 2 3.9x102 BKGD Hechani-3.9x10 cal Room to 590-593 75126 BKGD BKGD BKGD Contaminated duct at air supply 1.6x103 9.8x102 manifold, smear 628 BKGD BKGD BKGD Rest of walk-in air supply' BKGD BKG0 manifold survey was background, smears 626-630; ll-SS-39 collected from floor of air 'w supply manifold, ll-SS-40 collected from drain pan of copper cooling coils inside i supply manifold. ilKGD BKCD BKGD BKGD BKGD BKGD Rest of mechanical roca survey a was background, smears 707-728, 734-735 BKGD to BKGD to BKGD BKGD Gamma shine from llot Cell 4110 FKGI) to BKGD (Gorri-2x104 70 .3.5x10 Facility, smears 549-551, 8 dor) 674-677 BKGD to BKGD to BKGD -BKGD Camma shine from llot Cell Men's' BKGD to BKCD 1.oc ke r 6x103 '1.1x102 ~4.3x104 Facility, smears 589, 601-610 . Room (4111) 1 Of fice Areas B BKGD BKGI) BKGD Smears 555-557, 580 - ~ Tol BKGD BKGD 3{GDto-4 4102 BKGD BKGD BKGD-BKGD BKGD to BKGD . Smears 558-560,581,594-60i) ~ 82126-
. ~ _ _ _ -. -.. .= ,~ -.. -. ~ O O LO. m 'k TABLE 1,(cont'd.) PAC-4G-3 PC-2 Direct Readings" GH Reading PRH-7 Low-Energy Smear Result 2 d (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 ca ) 1ocation Beta-Gamma Alpha @ contact @ 1 meter (cts / min) Beta-Gamma Alpha Comments 4103 BKGD BKCD BKCD BKGD BKGD BKGD Smears 561-563 582, 631-632, 664-665 B BKGD BKGD BKGD Smears 564-566,583, 657-658, 4104 BKGD BKGD 2{GDto 666-667 B(CD to BKGD BKGD BKGD . Smears 567-569, 584, 659-660, 4105 BKGD BKGD 2' 668-669 4106 BKGD BKGD B{CDto BKGD BKGD to BKGD Smears 570-572, 585, 661-662, 1 35113 670-671 y l 4107 BKGD BKGD B{GDto BKGD BKGD BKGD Smears 573-575, 586, 663, i-2 672-673 B{GDto BKGD BKGD BKGD Smears 576-578, 587 4108 BKGD BKGD 2 3'.0x103 BKGD. BKGD,. Contaminated carpet mat at main Corridor '1.6x104 BKGD 0.5 entrance, smear 548 BKGD BKGD B{CD.to BKGD. BKGD-BKGD Rest.'of survey interpreted as 3
- background, smeare. 519-532, 588 4112 &
BKGD BKGD BKGD BKCD' BKGD Smears 685-693,'695-696,l699 4112A B{GDto 'BKGD BKCD BKGD Smears 552-554, 579 4113 BKGD BKGD 2 3 Near former location of auto-2'.0x10 ' Outdoor 3.9x102 BKGD- ~ Environs to to to' clave and old holding tanks;. 2.4x10 " 1.2x103 1.2x10 " .-II-W-20 through 11-S-26 collected 3 4 ) to 20 At the rope barrier near buried ~- ' holding tanks north of the of fice corridor. i
~. s 35 - l l O TABLE 1 FOCTNOTES
- The beta mode direct readings and alpha mode direct readings were:taken with PAC-4G-3 instruments (see Appendix 1).
The beta mode detects both electromagnetic and particulate radiation. If an area indicated an instru-ment reading higher than background, a beta mode reading was obtained. The instrument was then switched to the alpha mode, in which the instrument only responds to particles with high specific ionization, such as alpha particles. The beta mode readings are compensated for any alpha _ contri-bution by subtracting the alpha mode reading from the beta mode reading. bBKGD = Background. The following are the instrument readings: } Instrument Beta Mode Alp'ua Mode PAC-4G-3 with 51 cm2 2 2 probe 200-400 ets/ min-51 cm 0-50 cts / min-51 cm PAC-4G-3 with 330 cm2 probe I k-3 k cts / min-330 cm2 2 o.50 ets/ min-330 cm PC-4 or 3A 49-106.5 cts / min 0.1-0.3 cts / min 4 10-wire 437-513 cts / min 1.2-3.1 cts / min. GM End Window 0.01-0.03 mR/h PRM-7 6-10 pR/h PRM-5-3 with PG-2 1.4-2.5 k cts / min ( PRM-5-3 with PG-5 8-10 k cts / min, HV-1 gross 100-150. cts / min, HV-1 PHA
- NS = Not Sampled, d2 mm x 5 in NaI(TE), HV-1 gross and PHA modes
- Gamma shine from Hot Cell Facility IShine at windows or south end l
n V
O O O-V TABLE 2. RESULTS OF DIRECT INSTRUMENT AND SMEAR EURVEYS AFTER FURTHER DECONTANINATION PAC-4G-3 PG-2 Direct Readings
- GH Reading PRM-7 Low-Energy Smear Result 2
2 '(dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-IDO cm ) Location Beta-Gamma Alpha @ contact @ 1 meter (cts / min) Beta-Gamma Alpha. Ccoments 4116 BKGD^ BKCD BKGD BKGD NS* NS Former area on north wall 4 l BKGD BKGD BKGD BKGD NS NS Former area on south wall i 4118 BKGD BKCD BKGD BKGD NS NS Former area on floor, grid G-5 BKGD BKGD BKGD BKGD NS NS Former area on floor, grid,A-3 Main Laboratory i Floor BKGD BKGD BKGD BKGD BKGD Former area on floor, grid D-14, ~ g smear 611 BKCD BKGD BKCD-Former area on floor, grids B-2 BKGD BKCD & 3, smears 613 & 649 BKGD BKGD BKGD BKGD BKGD Former area on floor, grids C-4 & 5, smears 612, 647-648' d d d BKGD 'BKGD BKGD NS. NS Former area on floor, grid F-10 BKGD BKGD BKGD NS NS Former area on floor, grid J-6 1 d d d' North BKGD BKGD .BKGD NS NS Former area on' north' wall, Wall grid N-4 j BKCD'I BKCD BKGD NS NS .Former area on north wall, grids N-3 & 4 1-BKGD BECD BKGD BKGD BKGD Former area on north wall, grid L-3, smear 621. BKGD BKGD BKGD Former area on north wall, BKGD BKGD grid I-4, smear b20 East BKGD BKGD BKGD' BKGD BKGD Former area.on east wall, grid j Wall C-4, smear 614
O O O TA:LE 2 - (cont'd.) PAC-4G-3 PG-2 Direct Readings" GM Reading PRM-7 Low-Energy. Smear Results 2 2 (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) Location Beta-Gamma Alpha @ contact @ 1 meter (cts / min) Beta-Gamma Alpha Comments East BKGD BKGD BKGD BKCD BKGD Former area on east wall, grid Wall J-4, samar 615 (cont'd.) South BKCD BKGD BKGD PAGD BKGD Former contaminated sewer pipe Wall at south wall, grid D-5, smears 618-619 BKGD BKGD BKGD Former speaker location on west West BKCD BKGD Wall wall, grid G-2, smears 622 & 682 BKGD* BKCD BKCD Former area at ceiling, grid Over-BKGD BKCD head K-9, smears 646, 697 BKGD BKGD BKGD Former area at ceiling, grid BKGD BKGD M-11, smear 642 BKGD BKGD BKGD Former area at ceiling, grid BKCD BKGD N-10, smear 645 BKCD BKGD BKGD Former area at ceiling, grid BKCD LKGD N-12, smears 641 & 680 BKGD BKCD BKCD BKCD. BKGD Former area at ceiling, grid N-16, smear 681 BKCD BKCD BKGD 'Former area at ceiling, grid BKGD BKGD 0-11, smear 643 BKGD BKGD BKGD BKGD BKGD Former area at ceiling, grid P-8, smear 644 d d d BKGD - NS NS Fermer area on north side of Center BKCD BKGD Pillar center pillar, grid C-4 4
O O O TABI.E 2 - (cont'd.) PAC-4G-3 PG-2 Direct Readings
- GH Reading PRH-7 Low-Energy Smear Result 2
2 (dis /miu-100 rm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) location Beta-Gamma Alpha 8 contact @ l meter (cts / min) Beta-Gamma Alpha Comments Workshop BKGD ltKGD BKGD BKGD BKGD Former area on floor, grid A-13, smear 634 BKGD BKGD BKGD 2219 BKCD Former area on floor, grid A-14,. smear 633 BKCD BKGD-BKGD Former area on floor, grid A-18, BKGD llKGD smear 636 BKCD BKGD BKGD Former area on floor, grid A-21, BKGD BKGD floor, grid A-21, smears 639-640' to ao BKGD BKGD BKGD BKGD BKCD Forier area on floor, ' grid B-18, smears 637-638, 701 BKGD BKGD BKGD BKGD BKGD Former area on floor, grid C-7, smear 635 South IIKGD BKGD BKGD BKGD BKGD Former area on floor, grid A-2, 'Corri-smear 650 dor BKGD BKGD BKGD BKGD BKGD Former area on floor, grid A-12, smear 651 BKGD BKCD BKGD BKGD BKGD Former area on' floor, grid : A-15, smear 653 BKGD BKGD BKGD BKGD BKGD Former area on floor,; grid B-13, - smear 652 BKGD BKGD BKGD BKGD BKGD-Former area on south wall, grid : E-1, smear _704 BKCD .BKGD BKCD Former area on south wall, grid : IlKGD BKCD. 1-1, smear 703
-. ~. _. - - O o o t I = TABLE 2. - (cont'd.) PAC-4G-3 PG-2 Direct Readings
- GH Reading PRM-7 Low-Energy Smear Result 2
2 (dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) Location Beta-Gamma Alpha @ contact @ l meter (cts / min) Beta-Gamma Alpha Comments BKGD NS NS Former area at ceiling, grid B-6 Seuth BKCD BKGD Corri-dor BKGD BKGD BKGD BKGD-BKGD Former area at ceiling, grid.C-16, (cont'd.) smear 705 2 West BKGD BKGD BKGD BKGD BKGD Former area (15 m ) on floor, Corri-south end grids ABC-17 to 22, dor smear 706 BKGD BKGD BKGD BKGD BKGD Former area on floor, g-id B-2, smear 655 gg. BKGD BKGD BKGD BKGD BKGD-.Former area on floor,. grid B-16, amears 654 & 702 BKGD BKGD BKCD Former area on floor, grid C-2 BKGD BKGD smear 656 BKGD BKGD BKGD BKGD BKGD Former area on' south wall, grid B-3, smear 694 1.2x104 7.8x102 ~ BKCD-BKGD 114114 Contaminated area at ceiling, grid C-20 after additional cleanup, smear 684 BKGD BKGD BKGD Former areas at ceiling, grid BKGD BKGD C-20, after final cleanup, smears 698 & 700 4 BKGD BKGD BKGD Fsraer contaminated duct in i Nechani-BKGD BKGD' cal east wall, smears 729 & 733 Room former location of contaminated BKCD BKGD BKGD air blower (removed as waste) i d
_._m O O ks) -s t 4 9 TABLE 2. - (cont'd.) PAC-4G-3 PG-2 Direct Readings
- GH Reading PRM-7 Low-Energy Smear Result 2
2 .(dis / min-100 cm ) (mR/h) (pR/h) x&y (dis / min-100 cm ) Location Beta-Gamma Alpha @ contact @ l acter (cts / min) Beta-Gamma Alpha Comments Hechani-BKGD BKGD BKGD Former location of contaminated cal duct at air supply manifold (removed as waste) Former location of contaminated Office BKCD BKGD BKGD 4 Corri-carpet'ast (removed as waste) dor p. ~ C3 ' i e 1 e I ) l - i t i 4 i j u
. l TABLE 2-FOOTNOTES
- The beta mode direct readir.gs a.d alpha mode direct readings 'were taken with PAC-4G-3 instruments (see Appendix 1).
The beta. mode detects both electromagnetic and particulate radiation. If an area indicated an.instru-ment reading higher than background, a beta mode reading was obtained. The instrument was then switched to the alpha mode, in which the instrument only responds - to particles with high specific ionization, such as alpha particles. The beta mode readings are compensated for any alpha contri-bution by subtracting the alpha mode reading frem the beta mode reading. BKGD = Background. The following are the instrument readings: Instrument Beta Mode Alpha Mode 2 0-50 ets/ min-51 cm2 PAC-4G-3 with 51 ca2 probe 200-400 ets/ min-51 cm 2 probe 1 k-3 k cts / min-330 cm2 o.50 cts / min-330 cm PAC-4G-3 with 330 cm2 PC-4 or 3A 49-106.5 cts / min 0.1-0.3 cts / min 10-wire 437-513 ets/ min .l.2-3.1 cts / min GM End Window 0.01-0.03 mR/h PRM-7 6-10 pR/h PRM-5-3 with PG-2 1.4-2.5 k cts / min O
- ss = *et sasP ed.
~ i d i BKGD readings not recorded in logbook, -but all areas cleaned / monitored.to BKGD before leaving facility. l 1 l 4 O
c 42 TABLE 3. AMBIENT PENETRATING RADIATION MEASUREMENTS ,.. ~. k ~ ~ RSS-111 Integrated Period of Exposure Expogure Integration Rate b Location (pR) (hr) (pR/h)" Comments Room 4118 54 -4.87 11.1 4/09/80, 16:30 Room 4117 158 16.70 9.46 4/10/80, 09:18 Main 78 7.50 10.4 6/12/82, 16':45 Laboratory, H-13 floor grid Main 397 39.42 10.1 6/14/82,08:20 Laboratory, F-5 floor grid
- Workshop, 74 8.42 8.79 6/14/82, 16:55 B-14 floor
' grid West 166 15.17 10.9 6/15/82,_08:10 O corrider. B-7 floor grid Mechanical 171 22.67 7.54 6/16/82, 08:25 Room Men's 323 6.92 46.7 6/16/82, 16:45 Locker Room Room 4102 146 15.50 9.42 6/17/82, 08:25 (Lounge) Room 4107 94 7.58 12.4 6/17/82, 17:10-(Office) 80ne meter above ground. bDate and time at conclusion of measurement. O 9
O O O TABLE 4. RADON DAUGHTER DETERMINATIONS 219Rn (Act.inon) 220Rn (Thoron) 222Rn (Radon) Daughter Daughter Daughter-Concentragion Concentration Concentration d. 3 Location (x10 WL ) (pCi/1) (pCi/2) Comments b Room 4117 0.53 , BDL z 4/10/80,-10:12, VI BDL 4/10/80, 10:26, V Room 4118 0.37 BDL 4/11/80, 11:25, V Room 4116 0.70 c Room 4119A 2.7 2.8x103 NS 7/30/81, 09:40, V 3 Room 4119A 1.9 1.1x10 NS 7/30/81, 10:39, V 3 NS 7/30/81, 09:46, V Roon 4119B 3.6 5.9x10 Main Laboratory, E-8 10.6 1.8x102 BDL 6/12/82, 09:15, U floor grid g 2 NS 6/14/82, 08:58, U 5.3 1.2x10 Main Laboratory, E-8 floor grid West Corridor, B-7 9.2 1.0x102 NS 6/15/82, 08:51, U floor grid Mechanical Room 1.4 2.dx10~3 NS 6/15/82, 10:21, U Workshop, B-15 4.2 BDL BDL 6/16/82, 09:00, U floor grid ~8 NS- '6/16/82,.10:36,U-Men's Locker Roon 5.2 3.7x10 ~3 Room 4102 (Lounge) .2.4 -1.7x10 NS 6/17/82, 09:20, U Room 4107 (Office) 3.1 BDL NS 6/17/82,10:19,U-Main Laboratory, E-8 -9.5 l'.8x102 1.2x10~1 7/01/82, 09:01, U. floor! grid (after -final D&D) BDL' 7/01/82, 15:07, U
O O O. TABLE 4 - (cont'd.). a Working Level (WL) is defined as any combination of short-lived radon-de' cay products in .I
- WL,
5 1 liter of air that will result in the ultimate emission of 1.3 x 10 MeV of alpha energy. The numerical value of the WL is derived from the alpha energy released by the total decay through RaC' of the short-lived radon-daughter products, RaA, RaB, and RaC at radioactive equilibrium with 222 100 pCi of Rn per liter of air. o bBDL = Below Detection Limit.
- NS = Not Sampled.
Date and time at conclusion of measurement; U = Denotes an air sample collected during or immediately following a generally unventilated condition; V = Denotes an air sample collected during or immediately following a generally ventilated condition. + 4 i i n i
45 TABLE 5. S0IL AND MATERIAL SAMPLE WEIGHTS 7,., (grams) () Rocks Sample Wet Dry Sieved and Number Weight Weight Weight Dross 11-S-1 3277 2961 738 2205 11-S-2 3641 3354 687 2659 11-S-3 3079 2728 752 1967 11-S-4 3241 2912 768 2128 11-S-5 3030 2817 691 2116 11-S-6 4120 3754 955 2782 11-S-7 4237 3818 989 2811 11-S-8 3671 3369 781 2574 11-S-9 2453 2297 553 1729 11-S-10 2787 2620 579 2040 11-S-11 2533 2359 598 1759 11-S-12 1946 1806 516 1280 11-S-13 1694 1554 441 1105 11-S-14 2340 2193 494 1694 11-S-15 2237 2108 528 1571 11-S-16 2537 2399 565 1830 11-Gravel-17 571 4.5 566 O (_/ 11-Sand-18 20 20 11-C-19 16 16 11-W-20 1000 m2 11-S-21 573 565 488 63 11-S-22 77 76 63 1 11-S-23 357 319 243 64 11-S-24 626 613 157 441 11-S-25 706 684 513 157 11-S-26 574 572 216 340 11-S-27 343 325 154 167 11-S-28 396 371 181 186 11-S-29 285 272 122. 148 11-S-30 328 314 166 144 11-S-31 339 316 151 161 11-S-32 295 280 145 130 11-S-33 302 283 160 119 11-S-34 381 349 163 185 l 11-S-35 340 320 159 158 11-S-36 324 305 146 155 11-MS-37 3 11-S-38 305 287 128 155 11-SS-39 125 ml 1 (') 11-SS-40 125 m2 v
46 TABLE 5 - (cont'd.) N.] ~ Rocks Sample Wet Dry Sieved and Number Weight Weight Weight Dross 11-S-41 152 141 132 5 11-S-42 138 124 111 8 11-S-43 115 108 98 6 11-S-44 159 54 51 1 11-S-45 149 140 122 8 11-S-46 82 81 37 44 '11-S-47 114 114 97 10 11-S-48 73 72 69 3 45 0 11-S-49 42 0 11-S-50 11-S-51-1 498.8 498.8 488 10.0 11-S-52-11 1546 1409 808 591 11-S-53-1 1137 1056 655 390 11-S-53-15 523 516.5 422 6.0 11-S-53-46 1703 1571 990 571 11-S-54-1 1135 1131 623 490 11-S-54-11 1343 1219 849 367 11-S-55-5 570.5 520.5 412 106 11-S-56-3 548 493 308 185 ([) 11-S-57-17 597.5 558 304 249 11-S-58-13 566 494 342 152 11-S-59-1 484 436.5 351 82 11-S-60-6 624 559 413 117 11-S-61-14 829 753 546 189 11-S-62-11 376 336 304 29 11-S-62-26 611 554 309 240 11-S-63-8 580 526.5 380 45 11-S-63-13 594 542 461 74 11-S-63-20 589 537 .423 101 11-S-64-10 508 472 347 27 11-S-65-13 428 422 230 195 11-S-66-16 696 650.5 501 118 11-S-66-28 579 542 387 129 ll-S-67-19 696 646.5 468 161 11-S-68-11 584 538 365 167 11-S-69-12 774.5 744 729 8.0 11-S-70-8 1712 1708 462 1237 11-S-70-21 725 722 498 223 11-S-71-13 623 535 391 129 O s_-
v O O O TABLE 6. CAMMA-SPECTRAL AND URANIUH-FLUOROMETRIC ANALYSIS OF SAMPLES Gamma Spect.ra, pCi/g i o* 232Th 22sRa Uranium Fluorometric Sample Decay Decay. b 137Cs Chain Chain pg/g i 10%' PCi/g i 10% N
- r-11-S-1
<0.35 <0.74 1.2 10.4 3.2 10.3 2.2 10.2 11-S-2 <0.34 0.7310.44 1.6 10.4 3.1 ~10.3f 2.1 10.1 Il-S-3 <0.36 <0.93 1.3 10.4. 3.4' 10.3 2.3 10.2 Il-S-4 <0.34 1.0 10.5 1.3 io.4 3.8 10.4 2.6 10.3 Il-S-5 <0.29 <0.96 0.8410.42 3.4 10.3 2.3 10.2 11-S-6 <0.32 <0.66 1.3 10.4 3.4 10.3 ' 2.3 10.2 11-S-7 <0.28 <0.65 1.5 10.4 3.9-10.4 2.7 10.3 ' 11-S-8 <0.41 0.8310.46. 1.9 10.4 3.5 10.4. 2.4 10.2 'a-11-G-17 0.4410.07 0.5310.20 1.2 10.3 <0.25 0.8610.45 1.9 10.6 1I-Sandp8" i ll-C-19 <0.49 <l.9 3.2 11.0 I l -N-20". (dissolved solids) <0.03 pCi/mi 0.0210.01 pC1/mi 0.0810.02 pCi/m2 0.001810.0002 pg/mt; 0.001210.0001 pC1/mi ' 11 L <10] .<0.01 <l34 <91 (suspended solids) 0.4210.08
- 1.0610.!!
2.7 10.3 n. 1.8. 10.2: ~.11-S-21 11-S-22 0.1310.04 0.4910.07 1.0110.11 2.3 't0.2 l '. 6 - 10.2 11-S-23 1.0510.10 2.5 10.3 1.7 10.2 ,ll S-24 0.0710.04 .0.9910.10 1.5510.16 3.6
- 10.4
- 2.4 10.2.' . 6J f ' 11-S-25 <0.03-0.5210.08' 1.5810.16 3.2 10.3 2.2
- 10.2-il-S-26 0.0410.02
~0.2210.07 _l"2410.12. 2.8 10.3 1.9 110.'2 ~. 4 .2 Il-S-27 <0.03 0.5810.09 1.5810.16 3.7 10.4 ~ 2.5M 10.3 ~,. s ,II-S-28 <0.03 0.4210.08 1.4210.14 4.1 .10.4. 2.8; -to.3
- x. /[
11-S-29 <0.03 0.2910.09 1.1710.12 -4.1 10.4 2.8 10.3 1.4210.14. 3.7-10.4 2,5, 10.3 II-S-30 . <0.03. j 11-S-31 <0.03 .0.7110.07-1.6210.16
- 3.9 10,tt_-
2;-7 ; 10.3 2.4 20:21 11-S-32 <0.03 0.5410.08 .1.4710.15. 3.6 10.4- ^ 11-S-33 0.0510.02 0.3210.10 1.4410.14~ ?_3.8~ 10.4 ~ ~2.67 10.3' 11-S-34 0.0610.03 0.4310.09 1.3310.13 ,3.8 10.4 j' 2.6 10.3 Il-S-35. 0.0510.02 .0.4910.07 1.3910.14 3.8 10.4. 2.6. 10.3.\\ Il-S-36 <0.03-1.7710.18
- 3. 9., 10.4 2.7. 10~3 i,.f
~ l0.6310.06 1.76!0ct8-4.1. 10.4 2.8 10.3 Il-S-38. p -fa. !s*'
- s. -
i. "<d.
i +y.. f;h, 1 ,}
- al
.;I i c- ~ ~ ~ .p ~ n'w','. ,c* i . A m m / / i i C .C LO-Y' p p y o d a s e 1 2 c l t 0 0 e a a 0 6 d c s 0 0 i s gd N 1 1 2211 1
- 2. I.
m i b 02 0 11 n u s 0 o0 0 0 0000000000 i i y c 1 i1 1 1 1111111111 n l' ~ i 3 4 i a s r 1 1 2 t n e t 0 0 e 2 0 0 c a s a y 0 1 5865434,233 m 0 b'0 8 / l l 'e fo 1 a a J. g. 0 1 1 1 1 1 111 1 21 h r n r
- x. ~
o p t t a u c l t 2 G r e F m m l o p a / / m g g f s r u p p t j a c s i m e r n 2 3 e m p a 0 0 l _g~ - r 0 0 p a' s U 0 0 m g 03 0 2 2322222232 a a s' e m 00 0 0 0000000000 h m 11 1 1 1111111111 l T a 0 5 i C 0 2 3 o 1 0 0 s i 07 0 6 2 6 4 2. r 5' 1 0 0 - 849 h m a r3 2222b1 21 31 n b o4 c e o: g 02 0 1 / s*- e g r l2 t' I f s p f d d o a e e e ti tc h ec ~ / r r n e e c l e v n5 ) o o-s d t t c1 .s y'a e m n 't ' / / 3 9300907697 f; 0 _5 0 01 11 010010 oy a3 n i i l s: c ' C C o p p 0 0000000000 si n g i f s M. ~', o e ( ayn 1 111111111t o n Rai 1 2 1 8 3181 01 0176 i . O rca 00 0 1 9390907686 y g ~ n 2 eh l n n
- i. i s
2 DC 00 0 0 010101 001 O ao ig da d 6 "0 ni n/ Lt At im n l i E L i a aA 'd co o B r s A g ~ m3 4 e .t e T / E sn r2 pp d s s i m ce pi e d d C / i c-i ih d i i p i t n dC hc n l l i C so np c. e o o m p ic a e p s s a / 8 8772091 9 7'9 t s5 t s 'n r i 3 0, 0000000000 su-00011 01 000 ad - . 1 or s e e a ^u d d t C 0 t n 0 t c p i a d d e 0 1 1111111111 . o s1 t p l n n ( p hyu 16 1 7. 3814277683 gr-a. ns t p p ae a e e l S Tai 00 1 2 5672080869 ng b 4 2 ca 1 ik 5 i o s s 0 000l 10l 000 t c d a s eh 00 3 ma t u u a. x n a s s m YDC 0 ab ad t o g m i a i l s o d e nt m l l G 2 m cd n n o _ a a m / a e fi cn 2 t t / i 32 4' 'o t p oa o o o i C 7 0 0. ' 0 c p t i 3 t t t f C p 0 e A n t 00 0 - p do oi y g g 7 p 3 0 11 1 ex r ec d l u e e t s 33 0 1 363 338, d p se d d n 8 3 C 00 9 000 - - - 000 - e a o [3 0 6 y 'i l 3 3 t 00 1 000' 000 nl i sp n 3 7 s 8 6 0. < ol c nm i n i i a p oa o 0 ^ t m . cs s, i n n n 0 a r o _ e cj u i i og t o o i o t 8 )) ) ) vn h l t t 1 dd d d e g t 3 o l. A u dd p d 9: s l i i,~ i i lgl ll e n t 4 o o 1 o o ' oo t f a 2. l a da o S h C a ' s i a ss s s- ' r c t i t l 'l dd d d a n 1C o a a. i 1 e-e e d d 'o d 1 n t t t v$ 8 v d n n i e - 0 't 1 o o 9l n 0l n a i s - t t t 3 oe 4 o e 1 234567890 r ea 'e1 m t er - sp s p 4444444445 s n e l c l t e l e Sss S s s i v pi ii 0 a m i pb Siu Si u SSSSSSSSSS ea n md m 0 mm - d s d s nh o an a0 0 2 u 1 O ai l(( 1( ( l 1 l 1 1 1 1 1 1 l Oc C Si S5 9 5 1 SN I 1 I 1 I 1 1 1 1 11 l b k 8. c 4 j.i L j' ., i
4.. .m-l 49 IP D 8 8 I l' 4 8 I I t 8 I I i 'I l-2 t= c1 4 N. 4
==3 4 'y es e e6 M r/3 CC C CC C C C C E gat M 's 4 M' N N N ta3 3 3: A OE +1 +1 +1 +l +1 +1 +! +1 +1 8 8 8'I 8-8 8 I O< w f/3-Q . C C C'O .C 'O CC C <J E CC - ofe < - 4 6m 4 eg C 'M C M "JO M 'N w on en es m E CC 9 3 ta3 ~m N V V W H 00 2<N dew p Q .% C See ta3 M 2% 1*o es e e e e co e e Oi3 CC CC CC CC CC C.C CC CC 40
- N30 M @ mM jr *M 00 CC CC A@
CC CC 'N 4 'M M CC ~ ** 'N M M i EON S CO
- N M
'N 4 NN NN .. ';t3 * +1 +1 +t +1 +1 +1 &l +1 +1 +1 +l +1 +1 +1 +1 +1 +1+1+1+1+1+l+l+1 i p. E Q Q. DW O M M CC CC .C C CC CC 'OC CC-OC NA30CC4NC U us se CC CC 4m- 'ed - C 90 MM M M NM ' CC CC @T-4N CC @ ed N N 'm ea 'M A4N
- m C ed
'M e* ed - 4@ M #) ea a' M em N @4 NN NN NN m e* en em N - ta3 Ca3 Z: *.13..C ag w e.Ca. V o bm a e n o e e e n
- Ca3 CC CC CC
'O C CC-O C. CC CC 4 "M ** N 2 CO M N 2 C/3 4M MM 4M 44 4M Ne N ev NN ea - C >= 4a D< 2 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1 +1+1+1+1+1+1+1+1 w3 2 A< ov N .C C CC CC CC C'C CC CC. OO .4'm M N m n glC Nm nC MN w t= ,o @ pM 4 'O mn C4 m a 4 em C -N 'M ** ca N N-NM N ee e ce @ m t'3 N =< Fa k 1 C ** N M 4 4 'a C la e' N M 4 4 P= 10 m e*
- M M eg **
-4 0 i e a e a '.s I .s e e e I e e e t-LD TJ3 33 './3 t/3 ' W3 (t3 'A
- /3
'A i,t3 f/3 tt3 t/3 (13 t/3 t/3 ES I e I e t-I ,e. ,e - e. -,e e e e e a e B es e e m e4 c. c.
- e
- e. e
' f,53 M P* P's pe pse ya pg p.s pe ame pse m e p. pse p eine, i 9 e-t
O O O TABLE 7 .(cont'd.) r Sample 237 241Am Np 238Pu 239:240Pu Number 11-S-27 100 i 10 50 1 10 20 1 6 20 110 11-S-28 60 i 10 220 1 20 14
- i. 6 11 i5 11-S-29 80 1 10 35 10 13 1
8 15 i8 11-S-30 16 i 8 .< 10 6 1 3 8 i3 11-S-31 170 20 14 1 6 43 i 10 14 i5 11-S-32 125 1 20 5 5 35 'i 10 8 i4 11-S-33 1000 1 100 20. 10 430 50 7 i4 11-S-34 15000 11500 390-i 40 3600 i 300 20 i10 11-S-35 85 i 20 25 i 5 24 i 7 30 20 11-S-36 8 4 11 i 5 4 i 4 5 13i 11-S-38 5 i 5 10 i 5 4 i 4 5 i3 11-SS-39 (dissolved solids) ~<0.08-fCi/mA -<0.3 fci/m2 -< 0.02 fCi/m2 (lost) (suspended solids) 57 i 7 13 5 46 i 8 < 30 d 11-SS-40 (dissolved solids) < 0.08 fCi/m2 6 i 6 fCi/mt. 0.110.05 fCi/mA (lost)- (suspended solids) 1700 i 100 70 10 400. i ' 40 . < 20 11-S-41 47 1 10 5 .i. 3 - 19 i 5 < 15 11-S-42 1050 100 41 i 8 970 i 70 3 15 - 11-S-43 320 1 30 8 i 5 215 i 25 < 10 11-S-44 9580 i 700 280 .i 25 1580 i'100 7 15 11-S-45 140 20 36 i 10 180 30 7 20 11-S-46 6050 1 500 160 i 20 1570 i 150-7 10 11-S-47 13900 500 360 1 40 9810 i 500 7 18 11-S-48 9450 500 260 20 6160 i 400 l16 11-S-51-1 2.321 0.23. 0.14i 0.10 1.10 0.24 8 8 2.251 0.23 0.17i 0.10 ~
O O O TABLE 7 - (cont'd.) Sample 241Am 237xp 238Pu 239 240Pu Number 11-S-52-11 0.271 0.12 0.501 0.13 0.39i 0.12 11-S-53-1 28.8 i 1.4 4.23i 0.30 10.3 i 1.6 11-S-53-15 6.12i 0.43 0.721 0.17 8.34i 1.03 l 11-S-53-46 9.46i 0.47 0.971 0.15 2.3 0.28 11-S-54-1 0.121 0.04 0 0.12 0.091 0.07 11-S-54-11 0 i 0.08 0 1 0.12 0.30i 0.14 8 8 0.1 0.351 0.09 11-S-55-5 26.3 1.3 1.16i 0.21 21.7 i 1.3 i ~.421 0.10 0.161 0.10 0.431 0.13 11-S-56-3 0 11-S-57-17 0.11i 0.06 0.131 0.10 0.381 0.19 11-S-58-13 0.19t 0.09 0.261 0.08 0.611 0.24 8 a 0.171 G.10 < 0.l 11-S-59-1 19.9 1.0 0.551 0.18 27,1 i 1.6 11-S-60-6 0.571 0.13 0.24i 0.12 0.951-0.24 11-S-61-4 244 i 12 7.321 0.47 293 1 15 a 6.81i 1.81 279 i 16 + 8 317 i 13" 7.81i 2.10 11-S-62-11 88.4 i '4.4 2.87i 0.32 113 1 6 ^ 11-S-62-26 1.391 0.21 0.251 0.11 2.571 0.72 11-S-63-8 13.9 i 0.7 0.371 0.13 13.1 i 0.92 11-S-63 102 1 5 3.491 0.31 1.711 0.26 11-S-63-20 49.5 2.5 1.36i 0.23 154 1 6 + 8 149 i 10" 5.081 1.54 F -162 1 !i" 5.671' 1.838 161 i 5.41i. 1.56 4 8 155 i' 8 5.67i 1.53 L i-, L. + ie
.~ O O O TABLE 7 - (cont'd.) h Sample 237 3 239,240Pu 241Am Np 238Pu -Number
- 11-S-64-10 0.241 0.11 0.351 0.16 0.451 0.16 11-S-65-13 0.541 0.13 0.261 0.24 17.7 1 0.9 11-S-66-16 5.09 0.36 0.401 0.20 7.78
- 1. 2 '
11-S-66-28 3.751 .0.38 0.411 0.22 4.471-1.34 11-S-67-19 3.95 0.32 0.091 -0.13 64.6 i 3.1 11-S-68-11 1.051 0.15 0.511 0.28 5.25 0.74 ~- 11-S-69-12 4.75i 0.38 0.511 0.17 5.201 0.47 11-S-70-8 5.141 0.36 1.081 0.17 7.991 0.55 11-S-70-21 21300 i1000 607 i 30 32500 19400 ~ i a a 24300 .:t 340 731 1 60 11-S-71-13
- 21.3 1 0.1 1.281 0.23 11.2 1 0.7
'U
- Duplicate analyses bAnalysis not requested
- 91 m2 total solution; 33.8 g total suspended solids d52 m2 total solution; 73.3 gLtotal. suspended solids
d ( 53 TABLE 8. URANIUM ISOTOPIC ANALYSIS OF SELECTED SAMPLES .P( Ci/g) () Sample Number 234U 23sU 23sU f 11-S-1 1.03 1.0.15 0.03 0.02 1.07 i 0.46. 1.11.1 0.16 0.13 1.0.04 1.12 0.17 S'-2 1.06 t 0.18~ 0.05 i 0.03 1.04 i 0.18 1.28 -0.18 0.07 0.03 1.24 1 0.18 ] 11-S-3 1.10 i 0.16 0.06 i 0.02' 1~.15 1 0.16 1.21 1 0.16 0.04 i 0.02~ 1.17 i 0.16 11-S-4 1.44 0.22 0.04 t 0.02 1.26 0.20 } 0.99 i 0.13 0.04 t.0.02 1.14 1 0.15: 11-S-5 0.99 i 0.13 0.04 0.02 1.14 1 0.15 0.99 i 0.14 0.03-i 0.02 1.05-t 0.14 3 11-S-6 1.12 i 0.20 0.02 0.02 1.13 t 0.20 1.14 0,.16 0.05 i 0.02 -1.09 i 0.16 11-S-7 1.30 i 0.19 0.04 i 0.02 '1.33 i 0.20 1.22 1 0.18 0.02 1 0.02-1.27-i 0.18 1 O 11-S-8 1.07 0.15 0.05 0.02 1.18 i 0.16 0.96 i 0.13 0.03 .0.01 1.04 0.14-NOTE: Duplicate analysis provided on all samples. 1 4 1 (:) 1
54 a U APPENDICES _ Appendices I through 5 contain detailed descriptions of the array of instruments and computational and analytical procedures typically employed by ANL's Radioloical Survey Group in its comprehensive radiological. assess-ments. Although the specific instruments and techniques used.in a given ~ survey depend on the conditions encountered and the information sought, descriptions of the entire array have been included here for completeness. The exact instruments and methods used in the survey' reported in this document are specified in appropriate discussions in the text. Appendix 6 contains excerpts from numerous regulations, standards, and guidelines relative to radiological conditions and exposure to radiation. Not all these necessarily apply to the site surveyed. Again, however, all have been included for completeness..The pertinent regulations, standards, and guidelines for this survey are cited in the text. Appendix 7 contains a generic discussion of the nature and sources of radiation, its potential danger to humans, and methods utilized to evaluate radiation exposures. O O
~ _. - + '55 1 APPENDIX 1
- O 1xSTRuMEx m 10x d
I. PORTABLE. RADIATION SURVEY EQUIPMENT A. Gas-Flow Proportional' Survey Meters ~ The Eberline PAC-4G-3 was one of the-instruments used for radiologicalJ surveying. -This instrument is a gas-flow proportional counter that utilizes 2 progane-gas-proportional. detector, 51. cm (AC-21 hand-held probe) or. a (AC-22 floor monitor probe). in-effective area, with a thin, double. 330 cm 2 aluminized Mylar window (~ 0.85 mg/cm ), y Since this instrument has multiple - high-voltage settings,- it : can' be ~ used to distinguish between alpha and beta-gamma contamination. This; [ instrument was initially used with headphones 'in the beta -mode. In.that-mode, the detector responds to alpha and beta paticles ' and 'x-- and. gamma-i rays. 'When areas indicated a higher count-rate than'the average instrument background,. the beta-mode reading was recorded, ~ and the instrument waa then [ switched to the alpha mode to determine any alpha contribution. In the alpha mode, the instrument responds only to particles-with high-specific' ioniza-tion. With a 2 mV input discrimination level, the alpha mode voltage is [ 1600 V. This instrument is calibrated in the alpha mode with a flat plate, 239 i. infinitely thin, NBS-traceable Pu standard, and in the beta' mode with.a ~ 80Sr 80Y-standard. The PAC-4G 3 j flat plate, infinitely thin, NBS-traceable
- O i==tr t
re c ti6r ted to PP re t sox aetecti erricie cy-i B. Beta-Gamma End Window Survey: Meter When an area of contaminatien was found with a PAC instrument, a j reading was taken while using headphones with an Eberline Beta gamma Geiger Mueller Counter Model E-530 with a HP-190 probe. This probe has a thin ~ mica ? end window and is, therefore, sensitive to alpha and beta particles and x-and gamma-rays. A thin piece of aluminum is added to the mica, thus taking the window density ~7 mg/cm. At ;this density, the : instrument is not 2 j sensitive to most alpha particles. A maximum-reading.is obtained'with the probe placed in contact with the area of contamination. In this position, the response (in mR/h) to gamma radiatic,a is generally conservative relative 4 to a determination of erad/h at 1.cm; however, the response (in mR/h) to l' beta radiation is nonconservative by a factor' of up to about four relative. 2 F to a determination of mead /h through 7 ag/cm. This instrument is cali-brated in a good geometry ' configuration in mR/h with a 22sRa standard source. C. Low-Energy Gamma Scintillation Survey Meter An1 Eberline Pulse Rate Meter Model PRM-5-3 with a PG-2 low energy - l gamma scintillation detector was used with headphones to detect low-energy x t-and gamma radiation. The PG-2 detector consists of a thin NaI(TA) scin-tillation crystal,- 5' cm (2 in)~ in diameter by 2 am thick, with a 0.001-in 2 (0.025-am) thick aluminum window (~ 7 mg/cm ),-. A larger diameter crystal,- i i E _..__._,i m a
56-9 ' APPENDIX 1 'Q (cont'd.) .'V 13 cm (5 in) in diameter by 2 mm thick (Eberline PG-5), can also - be used. i with the PRM-5-3. This instrument is calibrated with -a 125% window : on energy. regions determined" by NBS-j three - separate discriminators for three 2 sU (185.7 kev) sources. j-traceable 239Pu (17 kev),. 241Am (59.5 kev),. and d j. The PRM-5-3 can be operated in ' either a pulse' height - analysis -(PHA) mode or a gross mode of operation. In the PHA mode, Lit counts only'those energies within the'25% energy window. The PRM-5-3 has three energy sett-T- ings in the PHA mode, HV-1 (centered on 17 kev), HV-2 (centered on 59.5 kev), and HV-3 (centered ' on 185.7 kev). ' In the gross mode, - the upper-level dis-1 it criminator is removed, opening the window to all, the higher energies. i During the radiological survey, the PRM-5-3 was normally. set to the HV-1 187Cs- [ g s mode. The. calibration was checked daily with 'an~ NBS-traceable i a gamma source. -D. High-Energy Micro-R Scintillation Survey Meter An Eberline Micro-R meter, model PRM-7, was used to detect high-energy. gamma radiation. This instrunent contains an internally mounted NaI(TA) scintillation crystal, 2.5 cm diameter by 2.5 cm thick, and can.be used to measure fields of low-level radiation between l10 p'/h and 5000 pR/h'.. This I instrument is used with headphones to survey ambient. penetrating radiation levels. It is normally held 1 m from the surface during. survey. The NaI(TA) detector is highly energy dependent. This instrument is calibrated witig a 226Ra standard source and during use-is checked daily with the 187Cs 137 Ba gamma source. f E. Pressurized Ionization Chamber In addition to the PRM-7, a pressurized ionization chamber -(PIC), i Reuter Stokes Model RSS-111, was used at selected locations to' determine the; i ambient external penetrating radiation field in units of pR/h. The RSS-111 i has three output modes; (1) instantaneous exposure rate digital display, (2) strip chart exposure rate readout,'and (3) integrat'ed exposure display. The. chamber is mounted on a tripod, 1m (~ 3 ft) above the1 surface an. has a i uniform energy response from about 0.2 MeV to about '4 MeV. A five-hour. period of operation is usually sufficient to obtain integrated exposures (in i pR) significant to at least two digits. The PIC is ~ calibrated with an NBS-traceable soCo gamma source. II. SMEAR COUNTING INSTRUMENTATION An ANL-designed large area, 10-wire, gas-flow proportional detector connected to an Eberline Mini Scaler Model MS-2. was used to count multiple - i 2 smears simultaneously. ' This detector has a ' largr. area (400 cm ). double-2 aluminized Mylar window (~ 0.85 mg/cm ) and ~ uses P-10 (90% argon and '10% methane) as the counting gas. The metal sample holder for this detector has ~ been machined to hold ten sicear papers. This particular system consists of ~ two Mini Scalers and two detectors. One is used~to count in the alpha' mode;
- O 1
i a w mm , - ~ ,- --- -.<,_.~., ..+-p i-- ,,7,e ,w.--, %g-,,,, ,.g,.m. ...e-mn..
57 APPENDIX 1 (] (cont'd.) LJ the other is used in the beta mode. Up to 10 samples can be counted simul-taneously in each. Any smear taken from a contaminated area was counted individually in a Nuclear Measurements Corporation PC-5 or 3A gas-flow proportional counter 2 using a double-aluminized Mylar spun top (~0.85 mg/cm window). Tb.s top is placed over non-conducting media (e.g., paper smears) to negate the di-electric effect and hence eliminate spurious counts. This counter also uses P-10 counting gas. Smears are counted in both the alpha and beta modes. 239Pu and 90Sr.90Y sources. This instrument is calibrated using NBS-traceable III. AIR-SAMPLING DEVICES Air samples are collected using a commercially available (Filter Queen) vacuum cleaner modified by ANL for use as an air-sampling device. 3 This device drew air through a filter medium at a flow rate of 40 r2 /h. The filters consist of 200-cm sheets of Hollingsworth-Vose HV-70-0.23 mm or LB5211-9 mil filter paper. The collection efficieacy at these flow rates for 0.3-pm particles is about 99.9%. A separate air sample was taken with a Bell and Gossett positive 3 displacement pump at a flow rate of about 20 liters / minute (1 m /h) through a Millipore membrane (0.5 to 0.8 tm) filter paper for about one hour or more. An alpha spectrum was acquired from a section of this filter paper g;j sample using a 450-mm2 ruggedized silicon surface barrier detector. The ratio of actinon (219Rn) daughters (6.62 MeV a, AcC) to radon (222Rn) daughters (7.69 MeV a, RaC') can be determined from this spectrum. Samples are also collected with an Environmental Working Level Monitor (EWLM), developed at ANL. The EWLM is a microprocessor-based instrument for performing automated series of Rn daughter concentration and Working Level (WL) measurements. A series starts with the measurement of the alpha (silicon diffused junction detector) and beta (plastic scintillator de-tector) backgrounds for three minutes. The EWLM then samples air for three minutes at a flow rate of about 38 f/ min through a section of Gelman Acropor AN1200 membrane (1.2 pm) filter paper. This filter paper is in the form of a continuous, splice-free, 100-ft roll of 2-in width. The filtered air sample it then advanced by the sample transport (13 seconds) to the detector position, where alpha (air inlet side of filter) and beta (exit side) counts are simultaneously measured for three minutes. The system spectroscopically separates the alpha counts from RaA and RaC' and measures the gross beta counts from RaB and RaC. Frc.n the above counts and times, the programmed microprocessor calculates and prints out the Rn daughter concentrations and errors and the WL and error. No assumptions about Rn-daughter equilibrium are required. Calibration of the WL determination is traceable to the DOE Environmental Measurements Laboratory (EML). O
~ l58 l --APPENDIX 1 , cont'd.). ( IV.' GAMMA SPECTRAI. INSTRUMENTATION i A Nuclear Data Multichannel Analyzer Model ND-66 with ; a - 7.6-ca- - j. diameter by 7.6-cm-thick NaI(TA) s~cintillation crystal and the appropriate electronics was used for determining the gamma - spectrum'. Samples :from contaminated areas were' analyzed.using this system to identify contaminating radionuclides. This instrument is calibrated with -NBS-traceable gamma sources. A portable Nuclear Data multichannel analyzer Model ND-6 with a'5.1-cm-diameter by 5.1-cm-thick NaI(TA)' scintillation. crystal and.-the appropriate portable electronics.was used for in-situ determination of the gamma spectrum. ~ Calibrations are to NBS-traceable gamma sources. A Hyperpure Germanium (HPGe). detector (ORTEC - 17% efficiency right- . circular cylinder) was used when gamma-ray analyses-of. greater resolution were required. ~This detector is coupled to the appropriate electronics and to a Nuclear Data Multichannel Analyzer (Model ND-60 or. ND-66) and. cali-brated with NBS-traceable gamma sources. ~ O p O
.59 APPENDIX 2 ' CONVERSION FACTORS l I. DIRECT SURVEY INSTRUMENTATION The factors used to convert the various instrument readings into units. 2 2 of disintegrations per minute per.100 cm (dis / min-100.cm ) and the deriva- . tion of those factors are listed below. A. Conversion Factors PAC-4G-3 with Floor Monitor Hand Probe (AC-21) (FM-4G with AC-22 Probe)' Alpha Beta Alpha _ Beta To 100 cm2 1.96 1.96 0.30 0.30 dis / min per cts / min 2 2 for 239Pu dis / min per cts / min 2 2 i for 90Sr 90Y dis / min per cts / min 3.5 2.7 3.0 2.5 ) for normal uranium i O dis / min per cts / min 1.7 1.7 1.7 1.8 for 22sRa plus daughters B. Derivation of Co, version Factors . Floor Monitor (AC-22) Window Area: ~ 330 cm2 Conversion to 100 cm2 = 0.30 times floor monitor readings . Hand Probe (AC-21) Window Area: ~ 51 cm2 Conversion to 100 cm2 = 1.96 times PAC reading i . 2n Internal Gas-Flow Counter, PC Counter Geometry with Solid Steel Spun Top - 0.50 Geometry with Mylar Spun Top - 0.43 Mylar Spun Tog) counting { double-aluminized Mylar window (~ 0.85 mg/cm } utilizes the well of the PC counter and is a method developed and used by the Argonne National Laboratory Health Physics Section for negating the-diel-ectric effect in counting samples on nonconducting media.
-_ m.. 60-APPENDIX 2 ' Q .(cont'd.) 4 v A 1.25 x 1.25 x 0.005 in (3.2'x 3.2 x 0.013 cm) normal-uranium foil (used as a source of uranium alpha emissions) was counted in the 2n Internal ' Gas-Flow Counter (PC Counter) with ' the source leva'.ed to 'an apparent 2n 239Pu geometry.~ As previously stated, this instrument was calibrated using 4 NBS-traceable sources. The alpha reading was 2.83 x 10 cts / min, or 2.83 x 4 + 0.50 = 5.66 x 10 ' dis / min alpha with the PC counter. 4 10 The same. uranium source, when counted ' in the alpha - mode with the 4 PAC-40-3 instrument. (51 cm2 ' probe), was found to be 1.62 x 10 cts / min at contact. The conversion factor for cts / min to dis / min -for. the PAC instru-i ment is 5.66 x 104+ 1.62 x 104 = 3.5 dis / min alpha per. cts / min alpha. The same normal' uranium source covered with two layers of conducting _ 2 thick to i paper in good electrical contact with the chamber, each 6.31 mg/cm absorb the alpha emissions, was counted. for composite beta and gamma emissions in the PC counter; however, no provision was.made for backscatter. s The composite beta-gamma count was 3.84 x 105 cts / min, or ' 3.84 x lo + 0.50 = 7.68 x 105 dis / min beta gamma. i i When the - covered normal uranium source was counted in the beta mode of the PAC-4G-3, the count rate was 2.85 x 10s cts / min. This indicates a conversion factor of 7.68 x 10s + 2.85 x 10s = 2.7 dis / min beta gamma per j-cts / min beta gamma. O ^ 1 it r ethod was used to determine the conversion factors for 22sRa plus daughters. j II. SMEAR COUNT. 2 for smear The conversion factors for cts / min-100 cm2 to dis / min-100 cm counts are given below. 1 A. Conversion Equation (Alpha) cts / min - (Bkgd) dis /sh alph g x bf x sa x waf i A geometry (g) of 0.43 is standard for all' flat plate counting using a Mylar spun top. I A backscatter factor (bf) of 1.0 was used when determining alpha activity on a filter media. The self-absorption factor (sa) was assumed to be 1, unless other-wise determined. If the energies of the isotope were known, the appropriate window L air factor (waf) was used; if the energies of the isotopes were j unknown, the waf of ~39Pu (0.713) was used. j O 1 i ~.
61: APPENDIX 2. (cont'd.). ' The-waf for normal-uranium alphas is 0.54. The waf for alphas from 22sRa plus daughters is 0.55. B. Conversion Equation (Beta) cts / min --{S Bkad (cts / min) + or cts / min} = dis / min beta g x bf x sa x waf A geometry _ (g) -' of 0.43 'is standard for all' flat-plate : counting using the Mylar spun top. . A backscatter factor (bf) of 1.1 was used when ' determining beta activity on a, filter media. The self-absorption factor (sa) was assumed to be 1, unless other-wise determined. If the energies of the' isotopes were known,'the appropriate window' air factor (waf) was used; if the energies of the isotopes were ~ 80Sr 90Y-(0.85) was used. unknown, the waf of P The waf for normal-uranium' betas is 0.85. The waf for betas from 22sRa plus daughters is 0.85.
- O 1
4
62 APPENDIX 3 ('] \\..- ~ RADON, THORON, AND ACTIN 0N DAUGHTER DETERMINATION CALCULATIONS The basic assumptions and calculations used to derive the radon (222Rn) daughter and thoron (220Rn) daughter concentrations in air are detailed here. The air samples were collected with an ANL-designed air sampler using HV-70-0.23 mm or LB 5211-9 mil filter paper. Sampling times were 3 usually 40 minutes at a flow rate of 40 m /h (670 f/ min). Accordingly, the flow rate through the 10% portion of filter medium counted in the propor-tional counter was usually 67 f/m. The radon-daughter concentrations - (in WL) were determined by a generalized Kusnetz-like technique involving a single integral gross alpha count performed no sooner toan about 100 minutes following the end of sampling. The thoron-daughter concentrations (in pCi/1) were similarly determined by a second integral gross alpha count performed no sooner than about 360 minutes following the cessation of samp-ling. Counting (integration) time was generally two minutes for each count. The measured counts were related to concentrations through equations that describe the expected counts within any arbitrary time interval after sampling from radon and thoron daughters on a fil'ter sample. There are two general approaches in use to derive those equations. One of the approaches involves the solution of two sets of differential equations (Refs. I and 2). The first set describes the growth and decay o.' the daughters during the sampling time to, whereas the second set describes the growth and decay of n '( ) the daughters after sampling and during the counting interval tg to t2 A more recent approach involves the integration of the differential form of the generalized Bateman equation. This method yields one set of generalized equations (Ref. 3) that describe the expected ' counts during the counting due to the build-up of daughters on the filter sample interval tg.to t2 during the sampling time to and their subsequent transformation both during and after that sampling interval. The results of this second approach are utilized here. The equations (from Reference 3) that relate the concen-trations in air of any radioactive daughters A, B, C (A+B+C) to the inte-grated counts during the interval tg to t2 from sampling during a time to are: (* N = 2.22 EQ T A A 'A A \\ [t 3 2 t 7 A 2 EQ gA+ B A N = B kI"B B"IA ) A I s I k ( +I B B B l i i \\ j /~N Y 1
63 1 p APPENDIX 3 d (cont'd.) = 2.22 EQ [i I A N f C-A (T 'I ) ~ A B A C r T I B A + fB (I ~ A (I ~IC B B I I ~ C A + f C C A (I ~IA)(I "IB) C C ~ I I I + fB+ B 'C B C B T ~I I -T B C C B i + I C (1#) C C CI i j. where: N = the integrated counts' contributed directly by the ith daughter, g O e = the detecter vierd. i Q = the air sampling flow rate (liters / min), Cf = the concentration in air of the ith daughters (pCi/A), ] g I = the mean lifetime (min) of the ith daughter, equal to, the half-life divided by In 2, i and f = (1-e i o)(e i 1-e i 2), i=A,B,C and A = 1/tt. g g The radon daughters RaA and RaC' (RaC') contribute the alpha counts. Taking the half-lives of the radon daughters RaA, RaB, and RaC to be 3.05 min, 26.8 min, and 19.7 min, respectively, (Ref.'4), the expression.that relates concentrations to the integral gross alpha counts during the interval ti te from the sampling of radon daughters during a time to is the sum of t2 1 equations (la) and (Ic). After substitution, this is: ) i 3 = (43.99 fA + 1.609 x 10 f ~ 91I'4 I ) C B - C A (2) 4 f - 6.769 x 103 f)C + (1.253 x 10 B C B 3 f C' + 1.793 x 10 C C J 1 ... ~.
64 p APPENDIX 3 d (cont'd.) where: N = the integral gross alpha count (cts), and the other parameters are defined as 'above. It should be noted that since we are describing the gross alpha counts, the coefficient in equation -(2) that precedes the f C term (i.e., 43.99) includes the contributions'to both the RaA and RaC' ar,prias (i.e., the sum of 3 equations (la) and (Ic)). For alpha-spectral analyses, where the 6.003 MeV RaA alphas (equation (la)) are measured separately from the 7.687 MeV RaC' , alphas (equation (Ic)), the coefficient that describes the RaA alpha counts due to the sampled airborne RaA, C, must be separated from the other co-efficients. This separation yields k2.98 f CA (fr m equati n (la)) r that RaA alpha te r:a, with the balance, 1.011 A A, gr uped with the other RaC' alpha terms. The thoron daughter ThC (ThC') contributes the alpha counts. Taking the half-lives of the thoron daughters ThB and ThC to be 10.643 hr and 60.60 min (Ref. 4), respectively, from equation (Ib) the expression that relates ' concentration to the integral gross alpha counts from thoron daughters during an interval ti to L2 from a sampling interval to is: y,g=(2.082x10 f,- 1.875 x 104 8 f.)C' B C B (3) O + 1.697 x 104 f,C C C where the parameters ara defined as in equation (2), with the " primes" denoting thoron ' daughters (ThB and ThC). Although not utilized here, for alpha-spectral analyses, it need only be remembered that 64% of the gross alpha counts are due to an 8.784 MeV alpha and about 35% to 6.051 and 6.090 MeV alphas (Ref. 4), regardless of the time after the cessation of sampling. A similar expression was obtained for actinou (219Rn) daughters, where AcC contributes the alpha counts, taking the half-lives of the actinon. daughters AcB and AcC to be 36.1 min and 2.15 min (Ref 4), respectively: = (6.403 x 103 f,, - 22.71 f ")C " + 21.36 f "C ". (4) B C B C C The " double primes" denote the actinon daughters (AcB and AcC). For alpha-spectral analyses, 84% of the gross alpha counts are due to a 6.623 MeV alpha and 16% to a 6.279 MeV alpha, regardless of the time after the cessation of sampling. In all of the above equations, the counting interval-ti to t2 is referenced to t = 0 at the end of sampling. It is assumed that the sampling does not disturb the ambient concentrations of the daughters and that the concentrations in air remain constant over the relatively short sampling interval. O L
65 _g (cont'd.) APPENDIX 3 v The radon-daughter concentrations, in pCi/A, are related t.o the Working Level
- unit of concentration through the equation:
WL = 0.001046 CA + 0.005161 CB + 0.003M3 C, (5) C de'ived from the definition of a Working Level and the half-lives, alpha r abundances, and energies given in Reference 4. Although the numerical value of the WL unit is derived with the assumption of radioactive equilibrium (i.e., 100 pCi/A of each radon daughter), the unit is applicable for any .nonequilibrium mixture. Nonequilibrium mixtures of daughter concentrations are specified by three numbers called " air indices," defined for radon daughters as the concentration ratio of RaA, RaB, and RaC to RaA (i.e., 1:C /C /C ). B A C g The integral gross-alpha-count technique currently utilized by ANL is simpler than multiple-measurement or alpha-spectroscopic techniques. However, an uncertainty is introduced due to the lack of knowledge of the state of disequilibrium among the radon daughters during sampling. The three concentrations C ' B, and CC in equation (2) cannot be determined by A a single count. A conversion error, therefore, is introduced *when assumed daughter ratios are substituted into equation (2). Forty minute air-sampling data (as collected for most of the samples) were processed for heuristic purposes with 11 different daughter ratios ranging from three-h3 minute-young air (1:0.042:0.0015) through aged air (1:1:1). It was found that at about 100 minute decay times, the daughter ratio 1:1:1 yielded a slightly more conservative WL value (+8.5% above the mean) and was, there-fore, used in the calculation of all reported values (Ref. 5). A thoron daughter ratio can be similarly defined as the concentration ratio of ThB and ThC to ThB (i.e., 1:C,/C A thoron daughter ratio of 1:1 was chosen for equation (3) and use$.). C in the calculation of all reported values. This assumption is only slightly conservative (Ref. 6). In order to assess the ratio of actinon daughter concentration to radon daughter concentration within the air, samples were collected on a membrane filter media using a postive displacement pump. The membrane filter media samples were counted by alpha-spectral analysis for norraally 50 minutes, usually begun within three minutes following the cessation of sampling. Integrals (each typically of about 200 kev width) were obtained over both the 7.687 MeV RaC' peak and the 6.62 MeV AcC peak. The sampling, delay, and integral times were substituted into the alpha spectral forms of equations
- A Working Level (WL) is defined as any combination of short-lived radon-decay products in one liter of air that will result in the ultimate emission of 1.3 x 105 MeV of alpha energy.
The numerical value of the WL is derived from the alpha energy released by the total decay through RaC' of the short-lived radon-daughter roducts, RaA, RaB, and RaC at radio-active equilibrium with 100 pCi of p22Rn per liter of air. v
66 i 4. APPENDIX 3 (cont'd.) -(2).and (4). The actinon daughter to radon daughter concentration ratio was y then calculated under conditions of daughter equilibrium, and the resultant l ratio used to correct the WL value as determined by the. gross alpha tech-i nique. Example WL Calculation: An air sample.was collected in the ' Main Lab. f.or '45' minutes at a flow 3 ] rate of 40 m /h (6701/ min).. The flow rate through the 10% portion of' the , filter. medium counted in the ' proportional counter was 67.1/ min. The detector yield is the composite of a geometry factor (0.43), backscatter factor (1.0), sample absorption factor (0.77 for RaC'), and window-air detector yield of 0.265. A factor (0.8 for RaC'). These factors give a l single integral gross alpha count of two minutes duration, beginning 105 l minutes after the end of sampling, yielded 519 net - counts. A second integral. gross alpha count of two minutes duration, beginning 381 minutes after the end of sampling, yielded -46 net counts. From equations (2) and. (3), the total radon and thoron daughter counts during the_ interval tt =,105 minutes to t2 = 107 minutes from the sampling interval to = 45 minutes are: i l N 1 g = 2.466 CA + 19.65 CB + 2.408 CC + 140.7 C, + 46 A6-C ' B C i 4 = 24.52 C + 187.2 C', l where CA=CB=CC = C (i.e.,1:1:1) and C '
- C, = C' (i.e.,1:1).
B i I Similarly, the total counts during the second interval t2 = 381 minutes to f t2 = 383 minutes are: j N = 2.9 x 103 CA + 2.2x10 ' CB + 1.5 x 10 CC + 140.1 C '
- I'9 C'
7 B j = 2.5x102 C + 142.1 C', where C and C' are defined above. .i i With the conservatively assumed radon and thoron daughter ratios of 1:1:1 and.1:1, respectively, these equations yield results of 1.8 x 10 2 pCi/1~of ThB and C and 1.06 pCi/A of RaA, B, and C. Equation (5) then yields a WL of l. 0.0106 or 10.6 mWL (milliWorking Level). O 4 e i 1
= _ _ _...... 67 APPENDIX 3 (cont'd.) REFERENCES FOR APPENDIX 3 1.
- Martz, D.
E., D. F.
- Holleman, D.
E. McCu:dy, and K.. J. Schiager. " Analysis ' of Atmospheric Concentrations of RaA, RaB, and RaC by Alpha Spectroscopy." Health Physics E, 131 (1969). 2. Raabe, 0.G. and M. E. Wrenn. " Analysis of the Activity of Radon Daughter Samples by Weighted Least Squares." Health Physics J7_, 593 (1969). L' ' 3. Fu-Chia, Y. and T. Chia-Yong. "A General Formula for the Measurement of Concentrations of Radon and Thoron Daughters in Air." Health Physics 34,501-(1978). 4. Lederer, C.H. and V. S. Shirley. Table ut Isotopes, Seventh Edition. John Wiley & Sons, Inc. (1978). t 5. Justus, A.L., Unpublished notes. (1985). 6. Porsthnd6rfer, J., A. Wicke, and.A. Schraub. "The Influence of Ex-halation, 222 Ventilation and Deposition Processes Upon the Concentration of Radon ( Rn), Thoron (220Rn) and Their Decay Products-in Room Air." ] Health Physics M, 465 (1978). lO ) 4 '{ l 4 1 .I l0 N -,. ~ _.. ~..., .._.._.~,,,,.-e..
68 APPENDIX 4 3(V SAMPLE PREPARATION AND ANALYSIS PROCEDURES I. SOIL-SAMPLE PREPARATION Standard procedures for preparation of soil samples acquired during a radiological survey are described in this section. These samples are bagged and identified at the collection site,nd returned to ANL. If there is an indication of radioactive contaminatica, the sample is sealed in a Nalgene jar. At ANL, the soil samples are logged into the sample book, and each sample is weighed (on a tared balance scale) and the weight is marked on the container. This weight is recorded in the sample book as a " wet weight." Af ter all samples are marked, weighed, and recorded, they are dried. Each sample is placed in a pyrex beaker marked with the sample identifi-cation number. If more than one beaker is necessary, additional numbers (e.g., 1-3, 2-3, 3-3) are used. The original containers are saved for repackaging the dried somples. The beaker is set in an 80 C oven until the soil is dry (usually about 24 hours). The sample is returned to the original container and reweighed using a tared balance scale. This weight is also marked on the container and in the sample book, where it is referred to as a " dry weight." Af te.c all the samples are returned to their original containers, the milling process is started. Each dried sample is transferred to a 2.3-O 8 'te" (8 7 2) cer ic itt J r ce t t=t=8 i t 6 tt- (25"
- 2*"
6"r="d"- cylinders). The mill jar number is marked on the original container. The jars are sealed and the samples are milled for two hours or until sufficient material is produced to obtain 100-g and 5-g samples for analyses, if possible. The samples are milled six at a time. A second set of six jars is prepared while the milling of the first set is proceeding. After each sample is milled, the mill balls are removed with tongs and placed in a tray. A large plastic bag is inverted over the mill jar. Both are inverted and shaken until all the soil is transferred to the bag. If the soil plates the inside of the mill jar, a small paint brush is used to loosen the soil before the jar is inverted. A separate brush is used for each jar to pre-vent cross-contamination of the soil samples. After milling, each sample is sieved through a No. 30 (600 pm) Standard Testing sieve and transferred to a 12 in x 12 in ziplock bag. Rocks and j dross are bagged separately. The bags are marked with the sample number, the sieve vunber and the designation R(rocks) or S(soil). The balance is tared and the weights of the soil (or rocks) are measured and recorded in the sample book. A 100 g or less sample of the sieved material is trans-ferred to a 4-cz. (125-mt) Nalgene bottle. These samples are analyzed by suitable analytical techniques, including, as a minimum, high resolution gamma spectroscopy (GeLi or HPGe). A 5 g sample of the sieved material is i transferred to a 1-oz (30-mt) Nalgene bottle. One gram of this sample is used for the determination of uranium by laser fluorometry and the remainder i for radiochemical analysis for Pu, Am, and Th, if these analyses are p required. The bottles containing these weighed samples are marked with G
69 APPENDIX 4 (cont'd.). sample number and date, and this information is recorded in the sample book. The rocks (and dross) and remaining soil are placed in storage. The sieves, mill jars, and burundum milling balls used in this work are classified in two sets. One set is used for background samples exclusively. The other set is used for all samples from suspect areas. Soil samples with elevated levels of radioactivity based on instrument measurements are milled in one-gallon Nalgene bottles using burundum balls from the - set used for suspect samples. After use, these balls are either decontaminated (see below) or disposed of as radioactive waste. The Nalgene bottles are always disposed of as radioactive waste. The sieves used for these samples are also from the set used for suspect samples and are decontaminated after use. II. ROCK / CONCRETE SAMPLE PREPARATION Rock / concrete samples are collected, bagged, and identified at the collection site and returned to ANL. The samples are then logged into the j sample book; each sample is weighed on a tared balance scale and the weight recorded in the sample book. Rock / concrete samples are normally crushed to about minus-\\ in. mesh with a cold chisel and hammer. Samples can then be fed into a motor-driven } pulverizer utilizing 6 in. diameter parallel grinding plates. Samples are i normally ground to about minus-1/16 in, mesh. Plates are wiped or scrubbed
- O cte a.
ce rv-s Pte or too 8 er te a s i re tr rerred to 4-oz. (125-st) and 1-oz. (30-m2) Nalgene bottles, respectively, as in soil-sample processing. III. EQUIPMENT DECONTAMINATION The care of the milling apparatus is as important as the actual sample preparation. Proper care prevents cross-contamination of successive samples. The beakers used to dry the samples are washed thoroughly by placing a small 4 amount of Haemo-Sol in each beaker and filling it with warm water. The beaker is then scrubbed thoroughly on the inside and scoured on the outside with scouring powder. The beakers are rinsed three times with tap water and three times with demineralized water, and finally dried thoroughly before reuse. The milling equipment (tongs, brushes, milling jars,' lids, and milling balls) is rinsed. 'The tongs and brushes are washed thoroughly with j j Haemo-Sol. Eight burundum balls are returned to each milling jar along with about one pint of c1'ean road gravel, one spoon of Haemo-Sol, one spoon of j scouring powder with bleach, and one quart of water. The lid is tightened - l ( on the jar and the jar is placed on the rolling mill and rolled for approxi-mately two hours or until the balls and the inside of the jar appear to be i physically clean. After this time, the mill jar is removed from the rolling mill and its contents are dumped into a screen or basket. The lid and balls j are then rinsed thoroughly three times - with tap water followed by three times with demineralized water. The inside of the jar is rinsed until it is k m- ~.---,,s--=...---- - - -,, - - + .w -.r,. s-- ,..,... - - - - ~. - -,,, -,, ,..-,-o-- - -. - - - - ~, - ..w-w-e -g-- --wm=
70 APPENDIX 4 (cont'd.) q V absolut.ely clean. The milling apparatus is air-dried with warm air. Room air is drawn through the mill jars with a hose attached to a fume hood or specially constructed drying box. The sieves are rinsed, washed in Haemo-Sol, thoroughly rinsed again i (three times with tap water, followed by three times with demineralized water), and then air dried as above before reuse. IV. WATER AND SLUDGE Water samples are collected in 0.125-liter, 0.5-liter, and/or 1-liter quantities as deemed appropriate. These samples are logged in the sample book and then forwarded directly to a certified radiochemistry laboratory for preparation and analysis. The customary analysis procedure consists of filtration to obtain the suspended solids, followed by evaporation to obtain the dissolved solids. Both suspended and dissolved solids are analyzed by appropriate radiochemical analytical techniques. Sludge samples are collected in 0.125-liter bottles and are processed as outlined above for water samples. V. VEGETATION, MATERIAL, AND RUBBLE Samples of potentially contaminated vegetation, material (e.g. tile, piping, ducts, conduit), and rubble are collected, bagged, and labeled at the site and returned to ANL for specific processing and analysis. Vegetation samples are initially weighed, logged in the sample book, and transferred to Marinelli beakers for gamma spectrometric analysis. Then they are ashed, reweighed, and analyzed by appropriate analytical tech-niques. Material and rubble samples are initially weighed and logged in the sample book. Processing is sample-specific, consisting of drying, ashing, grinding, milling, and/or sieving. The samples are then forwarded to a certified radiochemistry laboratory for further specific processing and analysis as required. VI. TRITI,UM FROM SOLID MATERIALS Samples of solid materials (e.g., concrete) suspected of containing tritium are collected, broken into small pieces, and submitted to a certi-fied radiochemistry laboratory for analysis. The standard analytical proce-dure consists of transferring a 20 to 40 g sample to a ceramic boat followed by heating in a tube furnace at 425*C for two hours (~ 40 min to reach temperature and ~ 80 min heating at temperature). Helium is used as a flow gas through the tube during heating, and the tritium is collected in two traps on the downstream side of the furance. The first trap is immersed in an ordinary ice bath (0*C); the second trap is immersed in a CO -Freon bath 2
71 APPENDIX 4 y (cont' d. ) i i V (-57*C). The collected tritiated water from both traps is combined, made up to a known volume, and an aliquot taken for liquid scintillation counting of-the tritium. 1 VII. ANALYSIS PROCEDURES A subsample of 100-g or less from each' soil or other sample is analyzed i by high-resolution gamma-ray spectroscopy using a germanium crystal detector coupled to the appropriate electronics and a multichannel analyzer. - This analysis allows for a quantitative determination of the 22sRa decay chain .(via the 609 kev y-ray of 214Bi), the 232Th decay chain (via the 911 kev y-ray of 22 sac), and the 227Ac decay chain (via the 269.6 and 271.2 kev j y-rays of 223Ra and 219 187 other Rn, respectively), as well as an gamma-emitting radionuclide (e.g., 59.5 kev 2 Cs) present.in. Am, 661.6 kev the soil. The total uranium (elemental) present in the sample is determined by an acid leach of the mass of sample followed by laser fluorometry of the leached
- sample, i
Thorium analysis consists of an acid leach of the soil or other sample (using an appropriate Th spike for yield determination) followed by plating l a thin source of the radiochemically2sTh, 230 separated thorium and' determining the l 232 activity of the ~ thorium isotopes ( Th, and Th) by alpha spec-troscopy. 1 Plutonium, americium, and/or neptunium analysis consists of an acid leach of the soil or other sample (using an appropriate Pu, Am, and/or Np i spike for yield determination), followed by - plating a thin source of the i radiochemically separated plutonium americium, or neptunium and determining l the activity of the isotopes (23gPu, 239,2 O 2 1 237 Pu, Am, Np) by alpha spectroscopy. i The results of these various measurements allow for quantitative de-termination of the relative amounts of plutonium, americium, neptunium, normaluranium,naturaluranium, tailings (i.e.,22sRadeca{Th) decay. chains i chain), and the thorium (232Th), mesothorium (22sRa), and radiothorium (22 i present in the contaminated material. A mass spectrometric analysis of the uranium or plutonium fraction is conducted when it is deemed necessary to - know the relative isotopic abun-j dances (in atom %). An alternative approach for the uranium isotopes is radiochemical separation followed by alpha' spectral' analysis. 4 i i j LO 4 i I .,,,..--,,r-m, r-u -,y.n,, ,--r,-,,,,r n -, - - .,,-v -,w --,.-ry--vr-,.-
,1,-re--.ry--+
+ T---yww-., -w-w- r w-1r r--.-
72 APPENDIX 5 CALCULATION OE. URANIUM SPECIFIC ACTIVITY The specific activity for uranium of the presumed. normal isotopic abundance encountered during the survey was obtained by summing the specific activities for the individual contributing isotopen <=ighted accordingasU to their normal abundances. Best values for the specifi-activities of-and 23sU were taken from A. H. Jaffey et al., Phys. Rev. C 4 1889. (1971). The half-life for each isotope was taken from the " Table of Isotopes," 7th Edition, by C. M. Lederer and V. S. Shirley (1978). The percent -bundances of normal uranium were taken from N. E. Holden, BNL-NCS-50605 (1977). Atomic weights were taken from the " Handbook of Chemistry and Physics," 52nd Edition (1971). The specific activity of 234U - wa s calculated from the 23 s 1 half-life with Avogadro's number = 6.0225 x 10 per mole and 5.2595 x lo min per year. Specific-Activity Half-life Atomic Weight 4 Isotope (dis / min-pg) (years) (grams) 234U 1.386x104 2.446 x 105 234.0409 23sU 4.798 7.038 x 108 235.0439 1 23sU 0.746 4.4683x 109 238.0508 Specific activity for normal uranium: O s ectric ^ctivitv v Abundance Abundance of Contribution Activity. Isotope (atom %) (wt. %) Isotopes Contribution 234U 0.0054 0.0053 x 1.386 x 104 dis / min-pg = 0.736 dis / min-pg 23sU 0.720 0.711 x 4.798 = 0.034 238U 99.2746 99.2837 x 0.746 = 0.740 Total = 1.510 dis / min-pg or 0.680 pCi/pg i where (wt%)g = I(atom %)) (atomic weight) _ (ato.n %)g (atomic weight)g, (atom %)g (atomic weight)g 238.0289 g Note that 2.26% of the total activity is due to 23sU and 48.87% each is due to 2340 and 238U. O 9
73 APPENDIX 6 ( PERTINENT RADIOLOGICAL REGULATIONS STANDARDS, AND GUIDELINES I. Excerpts From DRAFT AMERICAN NATIONAL STANDARD' N13.12 Control of Radioactive Surface Contamination On Materials, Equipment, and Facilities to be Released for Uncontrolled Use Where potentially contaminated surfaces are not accessible for measure-ment (as in some pipes, drains, and ductwork), such property shall not be released pursuant to this standard, but shall be made the. subject of case-by-case evaluation. Property shall not be released for uncontrolled use unless measurements - show the total and-removable. contamination levels to be no greater than the values in Table 1 or Table 2. (The values in Table 2 are easier to apply when the contaminants cannot be individually identified.) Coatings used to cover the contamination shall not be considered a solu-tion to the contamination problem. That is, the monitoring techniques shall be sufficient to determine, and such determination shall be made, that the total amount of contamination present on and under any coating does not exceed the Table 1 or Table 2 values before release. O .. m m
O O O TABLE 1 SURFACE CONTAMINATION LIMITS
- Limit (Activityg),
^ (dis / min-100 cm Contaminants Total Nuclides (Fixed plus Group Description (Note 1) Removable Removable) 227Ac 20 Nondetectable 1 Nuclides for which the non-241,242m,243Am (Note 3) ^ occupational MPC (Note 2) is 2 x 10 13 Ci/$3 or less 249 250,251,252cf 243 244,245,24s 247,248Cm -or.for which the nonoccupa-125,1297 tional MPC (Note 4) is. a 237 II 7 CY/m I 2 x 10 3 or less Np 1 231Pa 210Pb 238 239,240 242 244Pu 22s,228Ra 228,230Th 254Es 200 2000 a 2 Those nuclides not in Group 'l for which the nonoccupa-25sFm Nondetectable : 12s,131,1331 p,y tional MPC (Note 2).is or less or 21oPo (Note 5)' 1 x 10 12 gij,3 223Ra l for which the nonoccupa. 90 tional MPC (Note 4) is Sr ~8 CY/m 232Th 3 or less 1 x 10 232g 3 Those nuclides not in Group 1000 5000 1 or Group _2 1 4 e i a e
75 APPENDIX 6 (cont'd.) SUREACE'CONTAMINATIONLIMITS*
- The levels may be averaged over one square meter provided the maximum activ-ity in any area of 100 cm2 is 1ess than three times the limit vaine.
For purposes of averaging with regard to iso 1ated spots of activity, any square meter of surface shal1 be considered to be contaminated above the limit L, 2 applicable to 100 cm, if (1) from measurements of a representative number n of sections it is determined that 1/n I S. 2 L, where S. is the dis / min-100 determined from measurement of secPlod i;- or (2) it is determined that l 2 cm 2 the activity of all isolated spots or particles in any area less than 100 cm exceeds 3 L. + Disintegrations per minute per square decimeter. NOTES: (1) Vaines presented here are obtained from the Code of Federal Regulations, Title 10, Part 20, April 30,1975. The most limiting of all given MPC values (for example, so1ubie versus insoluble) are to be used. In the event of the occurrence of mixtures of radionuc1 ides, the fraction con-tributed by each constituent of its own limit shall be determined and the sum of the fraction shal1 be less than 1. O (2) Meximem Permissib1e concentration in air APP 11 cab 1e to centinuous exPe-sure of members of the public as published by or derived from an authori-tative source such as the Nationa1 Committee on Radiation Protection and Measurements (NCRP), the International Commission on Radiological Protec-tion (ICRP), or the Nuclear Regulatory Commission (NRC). From the Code of Federal Regulations, Titie 10, Part 20, Appendix B, Table 2, Column 1. (3) The instrument utilized for this measurement shalt be calibrated to measure at least 100 pCi of any Group 1 contaminants uniformly ~ spread 2 over 100 cm, (4) Maximum permissib1e concentration in water applicable to members of the public. (5) The instrument utilized for this measurement shall be calibrated to. measure at least I nCi of any Group 2 beta or gamma contaminants uni-j formly spread over an area equivalent to the sensitive area of the detector. Direct survey for unconditional release'should be performed in areas where the background is 5 100 counts per minute. When the survey must be performed in a background exceeding 100 counts per minute, it may j be necessary to use the indirect survey method to provide the additional sensitivity required. J
76 APPENDIX 6 (cont'd.) O- ~ ALTERNATE SURFACE CONTAMINATION LIMITS (All Alpha Emitters, except U and Thnat, Considered as a Group)* Limit (Activity), 2 (dis / min-100 cm ) -Total-(Fixed Plus Contamination Contingencies Removable Removable) If'the contaminant cannot be identi-20 Nondetectable fied; or if alpha emitters other - (Note-2) presenE" or(Note 1) and Thifthebetaemikters than U are 227Ac or 22sRa. comprise If it is known that all alpha emit-200 2000 a ters are generated from U Nondetectable (Note 1) and Thnat;andiE" beta ,y emitters are present that, (Note 3) while not identified, do not include 227Ac, 12s1,,22sRa, and 228Ra. d If it is known that alpha emitters 1000 5000 ~ are generated only from U (Note 1) and Th inequff[- briumwithits0$bayproducts; and if the beta emitters, while not identified, do not include 1251, 1297 90Sr, 223Ra,
- 227Ac, 22sRa, 12s1, 131I and 138I.
O
77 APPENDIX 6 q (cont'd.) v ALTERNATE SURFACE CONTAMINATION LIMITS
- The levels may be averaged over one square meter provided the maximum activ-ity in any area of 100 cm2 is less than three times the limit value.
For purposes of averaging with regard to isolated spots of activity, any square meter of surface shall be considered to be contaminated above the limit L, 2 applicable to 100 cm, if (1) from measurements of a representative number n of sections it is determined that 1/n I S 2: L, where S is the dis / min-100 g g determined from measurement of secElon i; or (2) it is determined that 2 cm 2 the activity of all isolated spots or particles in any area less than 100 cm exceeds 3 L. + Disintegrations per minute per square decimeter. NOTES: (1) U and decay products. nat (2) The instrument utilized for this measurement shall be calibrated to measure at least 100 pCi of any Group 1 contaminants uniformly spread 2 'over 100 cm, (3) The instrument utilized for this measurement shall be calibrated to ]' measure at least I nCi of any Group 2 beta or gamma contaminants uni-formly spread over an area equivalent to the sensitive area of the detector. Direct survey of unconditional release should be performed in areas where the background is 5 100 counts per minute. When the survey must be performed in a background exceeding 100 counts per minute, it may be necessary to use the indirect survey method to provide the additional sensitivity required. O v
- ~. 78 APPENDIX 6 (cont' d. ) II. GUIDELINES FOR 5ECONTAMINATION'0F FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BY-PRODUCT SOURCE, OR:SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Commission, July 1982 (These have been retyped for purposes of this report.) i. i The instructions in this guide, in conjunction with Table 1, specify the I radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces - or premises and equipment prior to [ abandonment or release for unrestricted - use._ The : limits in Table 1 do not j apply to premises, equipment, or scrap containing induced radioactivity for l which the radiological considerations pertinent to their use may be different. ] The release of such facilities or items from regulatory control will be con-sidered on a case-by-case basis. j j 1. The licensee shall make a reasonable effort to eliminate residual'contam-1 ination. 2. Radioactivity on equipment or surfaces shall not be covered by paint, l plating, or other covering material-unless-contamination levels, as i determined by a survey and documented, are-below the limits specified'in j Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering. 3. The radioactivity on the interior surfaces of pipes, drain lines, or duct' work shall be determined by making measurements at all traps, and.other i appropriate access points, provided that contamination at these' locations is likely to be representative of contamination on the interior of the pipes, drain lines, or duct work. Surfaces of premises, equipment, or l scrap which are likely to be contaminated but are of such size, construc-i tion, or location as to make the ' surface inaccessible for purposes of I measurement shall be presumed to be contaminated in excess'.of the limits. i j 4. Upon request, the Commission may authorize a licensee to relinquish possession or control 'of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may i i_ include, but would not be limited to, special' circumstances such as i razing of buildings, transfer of premises to another organization contin-I uing work with radioactive. materials, or conversion of facilities to a long-term storage or standby status. Such request must: a. Provide detailed, specific information describing the premises, equipment 'or scrap, radioactive contaminants, and the nature,. ) extent, and degree of residual surface contamination. O j i
t 1 l j 79 i. APPENDIX 6 ) (cont'd.) O ~ b. Provide a detailed health and safety analysis which reflects that the residual amounts of ; materials on surface areas,' together with other considerations such as prospective use of the premises, equip-ment or scrap, are unlikely~to result in an unreasonable risk to the health and safety of the public. i 5. Prior to release of premises for unrestricted use, the licensee shall-make a comprehensive radiation survey which establishes that contamina-- tion is within the limits specified in. Table 1. A copy of the survey i report shall be filed with the Division of Fuel - Cycle and Material j Safety, USNRC, Washington, D C. 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at. 4 least 30 days prior to the planned date of abandonment. The survey j report shall: i a. Identify the premises. j b. Show that. reasonable effort has been made to eliminate residual con-tamination. ] c. Describe the scope of the survey and general procedures followed. l i d. State the findings of the survey in units specified in the instruc-tion. 1 O v Following review of the report, the NRC will consider visiting the facilities l l to confirm the survey. 4 l i i i } l 4 i lO i 1 ? 1 )
i O O O APPENDIX 6 (cont'd.) TABE 1 ACCEPTABE SURFACE CONTAMINATION EVELS l l l bef bdf bef NUCLIDES* AVERAGE gyg REMOVABE 2 2 2 U-nat, 23sU, 238U and 5,000 dis / min-100 cm a 15,000 dis / min-100 cm a 1,000 dis / min-100 cm a associated decay products 2 2 2 Ra, 100 dis / min-100 cm 300 dis / min-100 cm 20 dis / min-100 cm l 226 Transuranics, 22sTh, 22sRa, 230Th, l 231 227 Pa,129 Ac, 125 1, 1 l 8-232 80 2 2 2 l Th-nat,224 Th,232Sr, 1,000 dis / min-100 cm 3,000 dis / min-100 cm 200 dis / min-100 cm 223Ra Ra U, l 12sy,,1327, 1331 Beta-gamma emitters ~ 5,000 dis / min-100 cm Sy 15,000 dis / min-100 cm2 py 1,000 dis / min-100 cm2 py 2 (nuclides with decay - modes other than alpha emission or spontaneous 90 fission) except Sr and others noted above. I
81 APPENDIX 6 A (cont'd.) V TABLE 1 (Footnotes) ACCEPTABLE SURFACE CONTAMINATION LEVELS aWhere surface contamination by both alpha and beta gamma emitting nuclides exists, the limits established for alpha and beta gamma emitting nuclides should apply independent 1y. bAs used in this table, dis / min (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation. CMeasurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object. d 2 The maximum contamination level applies to an area of not more than 100 cm, "The amount of removable radioactive material per 100 cm2 of surface area O shou 1d be determined bv i in that aree ith dry fitter or soft absorbent P paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. IThe average and maximum radiation levels associated with surface contamina-tion resulting from beta gamma emitters should not exceed 0.2 mrad /h at 1 em and 1.0 mrad /h at I cm, respectively, measured through not more than 7 milli-grams per' square centimeter of total absorber. O
I-g i APPENDIX 6 (cont'd.) III. 40 CFR 192 - HEALTH AND ENVIRONMENTAL PROTECTION STANDARDS FOR URANIUM MILL TAILINGS Authority: Section 275 of the Atomic Energy Act of 1954, 42 U.S.C. 2022, as added by the Uranium Mill Tailings Radiation Control Act of 1978, PL 95-604. Standards for Cleanup of Land and Buildings Contaminated with Subpart B Residual Radioactive Materials from Inactive Uranium Processing Sites 192.10 Applicability This subpart applies to land and buildings that are part of any processing site designated by the Secretary of Energy under Section 102 of the Act. Section 101 of the Act, states, in part, that " processing site" means - (a) any site, including the mill, containing residual radioactive r materials at which all or substantially of the uranium was produced for sale to any Federal agency prior to January 1,1971, under a contract with any Federal agency, except in the case of a site at or near Slick Rock, Colorado, unless -- (1) such site was owned or controlled as of January 1,1978,. or is Q thereafter owned or controlled, by any Federal Agency, or (2) a license (issued by the { Nuclear Regulatory} Commission or its predecessor agency under the Atomic Energy Act of 1954 or by a State as permitted under Section 274 of such Act) for the production at site of any l uranium or thorium product dervied' from ores is in effect on January 1,1978, or is issued or renewed after such date; and (b) any other real property or improvement thereon which -- (1) is in the vicinity of such site, and l (2) is determined by the Secretary, in consultation with the Commission, to be contaminated with residual radioactive materials derived from such site. 192.11 Definitions (a) Unless otherwise indicated in this subpart, all terms shall have the same meaning as defined in Title I of the Act or in Subpart A. (b) Land means any surface or subsurface land that is not part of a disposal site and is not covered by an occupiable building. (c) Working Level (WL) means any combination of short-lived radon decay products in one liter of air that will result in the ultimate emission of alpha particles with a total energy of 130 billion electron volts. l
83 APPENDIX 6 Q (cont'd.) (d) Soil means all unconsolidated materials normally found on or near the surface of the earth including, but not limited to, silts, clays, sands, gravel, and small rocks. 192.12 Standards Remedial actions shall be conducted so as to provide reasonable assurance that, as a result of residual radioactive materials from any designated proces-sing site: (a) the concentration of radium-226 in land averaged over any area of 100 square meters shall not exceed the background level by more than -- (1) 5,pci/g, averaged over the first 15 cm of soil below the sur-(2) 15 pCi/g, averaged over 15 cm thick layers of soil more than 15 cm below the surface. (b) in any occupied or habitable building -- (1) the objective of remedial action shall be, and reasonable l effort shall be made to achieve, an annual average (or equivalent) radon decay product concentration (including background) not to exceed 0.02 WL. In any g case, the radon decay product concentration (including background) shall not exceed 0.03 WL, and (2) the level of gamma radiation shall not exceed the background level by more than 20 microroentgens per hour. l l l O
84 APPENDIX 6 (') (cont'd.) v ~ IV. SURGEON GENERAL'S GUIDELINES as included in 10 CFR Part 712 Grand Junction Remedial Action Criteria 712.1 Purpose l (a) The regulations in this part establish the criteria determination by DOE of the need for, priority of and selection of appropriate reme-dial action to limit the exposure of individuals in the area of Grand Junction, Colorado, to radiation emanating from uranium mill l tailings which have been used as construction-related material. (b) The regulations in this part are issued pursuant to Pub. L. 92-314 (86 Stat. 222) of June 16, 1972. l 712.2 Scope l The regulations in this part apply to all structures in the area of Grand Junction, Colorado, under or adjacent to which uranium mill tailings l have been used as a construction-related material between January 1, 1951, and June 16, 1972, inclusive. l 712.3 Definitions gv As used in this part: (a) " Administrator" means the Administrator of. Energy Research and Development or his duly authorized representati.ve. (b) " Area of Grand Junction, Colorado," means Hesa County, Colorado, l I (c) " Background" means radiation arising from cosmic rays and radio-active material other than uranium mill tailings. l (d) "D0E" means the U. S. Department of Energy or any duly authorized representative thereof. (c) " Construction-related material" means any material used in the l construction of a structure. (f) " External gamma radiation level" means the average gamma radiation exposure rate for the habitable area of a structure as measured near floor level. (g) " Indoor radon daughter concentration Icvel" means that concentration of radon daughters determined by: (1) averaging the results of six air samples each of at least 100 hours duration, and taken at a minimum of 4-week intervals throughout the year in a habitable area pJ (2) utilizing some other procedure approved by of a structure, or l the Commission. 1
85 APPENDIX 6 (cont'd.) ~ (h) "P.illiroentgen" (mR) means a unit equal to one-thousandth (1/1000) of a roentgen which roentgen is defined as an exposure dose of X or genna radiation such that the associated corpuscular emission per 0.001293 gram of air produces, in air, ions carrying one electro-static unit of quantity of electricity of either sign. (i) " Radiation" means the electromagnetic energy (gamma) and the partic-ulate radiation (alpha and beta) which emanate from the radioactive decay of radium and its daughter products. (j) " Radon daughters" means the consecutive decay products of radon-222. Generally, these include Radium A (polonium-218), Radium B (lead-214), Radium C (bismuth-214), and Radium C' (polonium-214). (k) " Remedial action" means any action taken with a reasonable expec-tation of reducing the radiation exposure resulting f rom uranium mill tailings which have been used as construction-related material in and around structures in the area of Grand Junction, Colorado. (1) " Surgeon General's Guidelines" means radiation guidelines related to uranium mill tailings prepared and released by the Office of the U.S. Surgeon General, Department of Health, Education and Welfare on July 27, 1970. O. (m) "urani m mitt taitinas" means tattines frem a urani m mittins ePera-tion involved in the Federal uranium procurement program. (n) " Working Level" (WL) means any combination of short-lived radon daughter products in 1 liter of air that will result in the ultimate emission of 1.3 x 105 MeV of potential alpha energy. 712.4 Interpretations Except as specifically authorized by the Administrator in writing, no interpretation of the meaning of the regulations in this part by an of ficer or employee of DOE other than a written interpretation by the General Counsel will be recognized to be binding upon DOE. 712.5 Communications Except where otherwise specified in this part, all communications con-cerning the regulations in this part should be addressed to the Director, Division of Safety, Standards, and Compliance, U.S. Department of Energy, Washington, D.C. 20545. 712.6 General radiation exposure level criteria for remedial action. The basis for undertaking remedial action shall be the applicable guide-lines published by the Surgeon General of the United States. These guidelines recommended the following graded action levels for remedial action in terms of
86 APPENDIX 6 C (cont'd.) ~ external gamma radiation level (EGR) and indoor radon daughter concentration level (RDC) above background found within dwellings constructed on or with uranium mill tailings. EGR RDC Recommendation Greater than Greater than Remedial action 0.1 mR/h 0.05 WL indicated From 0.05 to From 0.01 to Remedial action 0.1 mR/h 0.05 WL may be suggested. Less than Less than No remedial 0.05 mR/h 0.01 WL action indi-cated. 712.7 Criteria for determination of possible need for remedial action Once it is determined that a possible need for remedial action exists, the record owner of a structure shall be notified of that structure's eligi-bility for an engineering assessment to confirm the need for remedial action O and to ascertain the most appropriate remedial measure, if any. A determina-tion of possible need will be made if as a result of the presence of uranium mill tailings under of adjacent to the structure, one of the following cri-teria is met: (a) Where DOE approved data on indoor radon daughter concentration levels are available. (1) For dwellings and schoolrooms: An indoor radon daughter con-centration level of 0.01 WL or greater above background. (2) For other structures: An indoor radon daughter concentration level of 0.03 WL or greater above background. (b) Where DOE approved data on indoor radon daughter concentration levels are not availabic: (1) For dwellings and schoolrooms: (i) An external gamma radiation level of 0.05 mR/h or greater above background. (ii) An indoor radon daughter concentration level of 0.01 WL or greater above background (presumed). (A) It may be presumed that if the external gamma radia-O tion level is equal to or exceed 0.02 mR/h above background, the indoor radon daughter concentration level equals or exceeds 0.01 WL above background.
87 APPENDIX 6 (] (cont'd.) ~ (B) It should be presumed that if the external gamma radiation level is less than 0.001 mR/h above back-ground, the indoor radon daughter concentration level I is less than 0.01 WI above background, and no pos-sible need for remedial action exists. I (C) If the external gamma radiation level is equal to or i greater than 0.001 mR/h above backgrond but is less than 0.02 mR/h above background, measurements will be required to ascertain the indoor radon daughter concentration level. I (2) For other structures: (i) An external gamma radiation level of 0.15 mR/h above background averaged on a room-by-room basis. (ii) No presumptions shall be made on the external gamma radia-tion IcVel/ indoor radon daughter concentration level relationship. Decisions will be made in individual cases based upon the results of actual measurements. 712.8 Determination of possible need for remedial action where criteria have not been met. The possible need for remedial action may be determined where the cri-teria in 712.7 have not been met if various other factors are present. Such factors include but are not necessarily limited to, size of the affected area, distribution of radiation levels in the affected area, amount of tailings, age of individuals occuping affected area, occupancy time, and use,of the affected area. 1 712.9 Factors to be considered in determination of order of priority for remedial action. In determining the order or priority for execution of remedial action, consideration shall be given, but not necessarily limited to, the following factors (a) Classification of structure. Dwellings and schools shall be consid-cred first. (b) Availability of data. Those structures for which data on indoor radon daughter concentration levels and/or external gamma radiation levels are available when the program starts and which meet the criteria in 712.7 will be considered first. (c) Order of application. insofar as feasible remedial action will be taken in the order in which the application is received. l l l
88 APPENDIX 6 Q (cont'd.) (d) Magnitude of radiation level. In general, those structures with the highest radiation levels will be given primary consideration. (e) Geographical location of structures. A group of structures located in the same immediate geographical vicinity may be given priority consideration particularly where they involve similar remedial efforts. (f) Availability of structures. An attempt will be made to schedule remedial action during those periods when remedial action can be taken with minimum interference. 1 (g) Climatic conditions. Climatic conditions or other seasonable con-siderations may affect the scheduling of certain remedial measures. 712.10 Selection of appropriate remedial action. (a) Tallings will be removed from those structures where the appro-priately averaged external gamma radiation level is equal to or greater than 0.05 mR/h above background in the case of dwellings and schools and 0.15 mR/h above background in the case of other struc-l tures. (b) Where the criterion in paragraph (a) of. this section is not met, other remedial action techniques, including but not limited to scalants, ventilation, and shielding may be considered in addition to that of tailings removal. DOE shall select the remedial action technique or combination of techniques, which it determines to be i the most appropriate under the circumstances. i i I
- O I
i i l
r-1 89 APPENDIX 6 (cont'd.) V. EXCERPTS FROM DOE 5480.1 Chg. 6, Chapter XI " Requirements for Radiation Protection" Exposure of Individuals and Population Groups in Uncontrolled Areas. Exposures to members of the public shall be as low as reasonably achievable levels within the standards prescribed below. Radiation Protection Standards for Internal and External Exposure of Members of the Public Annual Dose Equivalent or Dose Committment Based on Dose to Based on Average Dose Individuals at to a Suitable Sample Points of Maximum of the Exposed Type of Exposure Probable Exposure Population Whole body. 0.5 rem 0.17 rem gonads, or (or 500 mrem) (or 170 mrem) bone marrow O Other organs 1.5 rem 0.5 rem (or 1500 mrem) (or 500 mrem) CONCENTRATION IN AIR AND WATER AB0VE NATURAL BACKGROUND Table 1 Table Il Controlled Area Uncontrolled Area Element Isotope Column 1 Column 2 Column 1 Column 2 (Atomic Soluble (S) Air Water Air Water Number) Insoluble (I) (pCi/2) (pC1/2) (pCi/2) (pCi/2) Radon (86) Rn 220 S 300 10 Rn 222 S 100 3 Lead (82) Pb 212 S 20 0.6 O
90 APPENDIX 6 (cont'd.) {, VI. EXCERPTS FROM LA-UR-79-1865-Rev., Table XXIII. Recosunended Soil Limits"InterimSoilLimitsfor (in pCi/g) Ingestion Home fulf External All Inhalation Gardener Diet Radiation Pathways" 23tPa 50 227Ac d 740 150 250 40 200 4,900 1,000 300 120 .232 Th 45 670 140 40 20 228 Th j 1,000 37,000 7,800 55 50 230 Th 23sg.2{NoDaught.) 300 4,400 940 36,000 280 4U 750 44 8 6,000 40 88Sr c 2x106 137Cs 100 19 7x108 100 800 1 90 80 " Soil limits for 241Am and 230,240 and a soil limit for 22 era has been reported by llcaly and Rodgers.P b limits are to apply to only one nuclide present in the soil. one is present, a weighted average should apply, If more than i O c 8 asea en a diet a a home ardener. 1 d Modified from LA-UR-79-1865-Rev. values to correct error, i O
l 91 APPENDIX 7 l Od EVALUATION OF RADIATION EXPOSURES l I I. INTRODUCTION A. Types of Radiation Radiation is the emission or transmission of energy in the form of waves or particles. Examples are acoustic waves (i.e., sound), electromag-netic waves (such as radio, light, x-and gamma-rays), and particulate radiations (such as alpha particles, beta particles, neutrons, protons, and the elementary particles). l The class of radiation of importance to this report is known as ioniz-ing radiation. Ionizing radiations are those, either electromagnetic or particulate, with sufficient energy to ionize matter, i.e., to remove or displace electrons from atoms and molecules. The most common types of ionizing radiation are x-and gamma-rays, alpha particles, beta particles, and neutrons. X-and gamma-rays are electromagnetic waves of pure energy, having no charge and no mass or existence at rest. Gamma-rays and x-rays are identi-cal except that x-rays originate in the atom and gamma-rays originate in the nucleus of an atom. X-and gamma-rays are highly penetrating and can pass through relatively thick materials before interacting. Upon ir.teraction, O some or all of the energy is transferred to electrons, which, in turn, i produce additional ionizations while coming to rest. Alpha particles are positively charged particulates composed of two neutrons and two protons, identical to the nucleus of a helium atom. Due to its comparatively large mass and double charge, an alpha particle interacts readily with matter and penetrates only a very short distance before coming to rest, causing intense ionization along its path. Beta particles are negatively charged free electrons moving at high speeds. Due to its comparatively small mass and single charge, a beta particle's penetration through matter is intermediate between that of the alpha particle and the gamma-ray, causing fewer ionizations per unit path length than an alpha particle, i B. Sources of Radiation Ionizing radiations arise from terrestrial radioactive materials (both naturally occurring and man-made), extra-terrestrial (cosmic) so'urces, and radiation producing machines. The sources of ionizing radiation important to this report are radioactive materials and cosmic sources, j Host atoms of the elements in our environment remain structurally stable. With time, an atom of potassium, for instance, may change its association with other atoms in chemical reactions and become part of other O l
92 APPENDIX 7 (cont'd.) ~ compounds, but it will always remain a potassium atom. Radioactive atoms, i on the other hand, are not stable and will spontaneously emit radiation in order to achieve a more stable state. As a result of spontaneous trans-formation, the ratio of protons and neutrons in the nucleus is altered toward a more stable condition. Radiation may be emitted from the nucleus as alpha particles, beta particles, neutrons, or ganwaa-rays, depending l uniquely upon each particular radionuclide. Radionuclides decay at charac- ~ teristic rates dependent upon the degree of stability and characterized by a period of time called the half-life. In one half-life, the number of radioactive atoms and, therefore, the amount of radiation emitted, decrease by one half. The exposure of man to terrestrial radiation is due to naturally occuring radionuclides end also to " man-made" or technologically enhanced radioactive materials. Several dozen radionuclides occur naturally, some having half-lives of at 1 cast the same order of magnitude as the estimated age of the earth. The majority of these naturally occurring radionuclides are isotopes of the heavy elements and belong to three distinct radioactive series headed by uranium-238, uranium-235, and thorium-232. Each of these decays to stable isotopes of lead (Pb) through a sequence of radionuclides of widely varying half-lives. Other naturally occurring radionuclides that decay directly to a stable nuclide are potassium-40 and rubidium-87. It should be noted that even though the isotopic abundance of potassium-40 is less than 0.0127, potassium is so widespread that potassium-40 contributes O about one-third of the radiation dose received by(dose) of man to external man from natural back-ground radiation. A major portion of the exposure terrestrial radiation is due to the radionuclides in the soil, primarily potassium-40 and the radioactive decay chain products of thorium-232 and uranium-238. The naturally occurring radionuclides deposited internally in man through uptake by inhalation / ingestion of air, food, and drinking water containing the natural radioactive material also contribute significantly to his total dobe. Many other radionuclides are referred to as " man-made" in the sense that they can be produced in large quantities by such means as operating nuclear reactors or accelerators, or conducting nuclear weapons tests. The term " cosmic radiation" refers both to the primary energetic par-ticles of extra-terrestrial origin that are incident on the earth's atmos-phere and to the secondary particles that are generated by the interaction of these primary particles with the atmosphere and subsequently reach ground level. Primary radiation consists of " galactic" particles, externally incident on the solar system, and " solar" particles emitted by the sun. This radiation is composed primarily of energetic protons and alpha particles. The first generation of secondary particles (secondary cosmic radiation), produced by nuclear interactions of the primary particles with the atmos-phere, consists predominantly of neutrons, protons, and pions. Pion decay, in turn, results in the production of electrons, photons, and muons. At the lower elevations, the highly penetrating muons and their associated decay and collision electrons are the dominant components of the cosmic-ray O l l L
93 t l APPENDIX 7 (cont'd.) particle flux density. These particles, together with photons from the gamma-emitting, naturally occurring radionuclides in the local environment, form the external penetrating component of the background environmental radiation field which produces a significant portion of the whole-body radiation dose to man. In addition to the direct cosmic radiation, cosmic sources include cosmic-ray produced radioactivity, i.e., cosmogenic radionuclides. The major production of cosmogenic radionuclides is through interaction of the cosmic rays with the atmospheric gases through a variety of spallation or neutron-capture reactions. The four cosmogenic radionuclides that contri-bute a measurable radiation dose to man are carbon-14, sodium-22, bery11 Lum-7, and hydrogen-3 (tritium), all produced in the atmosphere. II. BACXGROUND RADIATION DOSES Background radiation doses consist of an external component of radia-tion impinging on man from outside the body and an internal component due to i radioactive materials taken into the body by inhalation or ingestion. Radiation dose may be expressed in units of rods or rems, depending l upon whether the reference is to the energy deposited or to the biological i effect. A rad is the amount of radiation that deposits a certain amount of energy in each gram of material. It applies to all radiations and to all Q materials which absorb that radiation. Since different types of radiation produce ionizations at different rates as they pass through tissue, differences in damage to tissues, and hence the biological effectiveness of, dif ferent radiations, has been no-ticed. A rem is defined as the amount of energy absorbed (in rads) from a given type of radiation multiplied by the factor appropriate for the partic-ular type of radiation in order to approximate the biological damage that it causes relative to a rad of x or gamma radiation. The rem permits evalua-tion of potential effects from radiation exposure without regard to the type of radiation or its source. One rem received from cosmic radiation results in the same biological ef fects as one rem from medical x-rays or one rem from the radiations emitted by naturally occurring or man-made radioactive materials. The external penetrating radiatiod dose to man derives from both ter-restrial radioactivity and cosmic radiation. The terrestrial component is due primarily to the gamma dose f rom potassium-40 and the radioactive decay products of thorium-232 and uranium 238 in soil, as well as from the beta-gamma dose f rom radon daughters in the atmosphere. Radon is a gaseous member of the uranium-238 chain. The population weighted external dose to an individual's whole body f rom terrestrial sources in the United States has been estimated as 15 mrem per year for the Atlantic and Gulf Coastal Plain, 57 mrcm per year for an indeterminate area along the Rocky Hountains, and 29 mrem per year for the majority of the rest of the United States. The over-O
r 94 APPENDIX 7 (cont'd.) all population-weighted external dose for the U.S. population as a whole has been estimated to be 26 arem per year. The cosmic radiation dose, due to the charged particles and neutrons from secondary cosmic rays, is typically about 30% to 50% of the total from all external environmental radiation. The cosmic-ray dose to the population is estimated to be 26 mrem per year for those living at sea level, and increases with increasing altitude. Considering the altitude distribution of the U.S. population, the population-weighted external cosmic-ray dose is 28 mrem per year. The population-weighted total external dose from terrestrial plus cosmic sources is thus 54 mrem per year for the U.S. population as a whole. The internal radiation doses derive from terrestrial and cosmogenic radionuclides deposited within the body through uptake by inhalation / ingestion of air, food, and drinking water. Once deposited in the body, many radioactive materials can be incorporated into tissues because the chemical properties of the radioisotopes are identical or similar to the properties of stable isotopes in the tissues. Potassium-40, for instance, is incorporated into tissues in the same manner as stable potassium atoms because the chemical properties are identical; radioactive radium arid strontium can be incorporated into tissues in the same manner as calcium because their chemical properties are similar. Once deposited in tissue, these radionuclides emit radiation that results in the internal dose to O individual organs and/or the whole body as long as the source is in the body. The internal dose to the lung is due primarily to the inhalation of polonium-218 and -214 (radon daughters), lead-212 and bismuth-212 (thoron daughters), and polonium-210 (one of the longer-lived radon decay products). The dose to the lung is about 100 mrem per year from Inhaled natural radio-activity. The internal dose from subsequent incorporation of inhaled or ingested radioactivity is due to a beta-gamma dose from incorporation of potassium 40, rubidium-87, and cosmogenic nuclides, and an alpha dose from incorporation of primarily polonium 210, radium-226 and -228, and uranium-238 and -234. The dose to man from internally incorporated radionuclides is about 28 mrem por year to the gonads, about 25 mrem per year to the bone marrow, lung, and other sof t tissues, and about 117 mrem per year to the bone (osteocytes). The bone dose arises primarily from the alpha-emitting members of the naturally occurring series, with polonium-210 being the largest contributor. The gonadal and soft tissue doses arise primarily from the beta and gamma emissions from potassium 40. The total internal dose from inhaled plus incorporated radioactivity is about 28 mrem per year to the gonads (or whole-body dose), about 125 mrem per year to the lung, about 25 mrem per year to the bone marrow, and about 117 mrem per year to the bone (osteocytes). The total natural background radiation dose is the sum of the external and internal components. The population weighted dose for the U.S. popula-tion as a whole is about 82 mrem per year to the gonads or whole body, about
( i 95 l APPENDIX 7 (cont'd.) l 179 mrem per year to the lung, about 79 mrem per year to the bone marrow, and about 171 mrem per year to the bone (osteocytes) (Ref.1). l Besides the natural background radiation, background radiation doses include contributions from man-made or technologically enhanced sources of i radiation. By far, the most significant sources are x-ray and radiopharma-1 ceutical medical examinations. These contribute a population-averaged dose estimated to be 70 mrem per year for the U.S. population as a whole. Fall-out from nuclear weapons testing through 1970 has contributed 50-year dose commitments estimated as 80 mrem external, and 30, 20, and 45 mrem internal to the gonads, lung, and bone marrow, respectively. Contributions from the use of fossil fuels (natural gas and coal) and nuclear reactors; mining, milling, and tailings piles; television sets, smoke detectors, and watch dials could be responsible for an additional 5 mrem per year, averaged over the U.S. population as a whole. In addition, the use of radiation or radio-activity for scientific, industrial, or medical purposes may cause workers in the industry and, to a lesser extent, members of the general public to receive some radiation exposure above natural background. III. EVA!.UATION OF RADIATION DOSE AND POTENTIAI.IIAZARD Radiation, regardless of its sources, is considered to be a hazard because of its potential for producing adverse effects on human life. Very large amounts of radiation received over a brief period, e.g., hundreds of O rem delivered within a few hours, can produce severe injury or death within days or weeks. Distributed over longer intervals, however, these same doses would not cause early illness or fatality. At doses and rates too low to produce these immediate symptoms, chronic or repeated exposure to radiation can bring about biological damage which does not appear until years or decades later. These low-level effects are stochastic in nature--their probability rather than their neverity increases with dose. Primary among these latent or delayed ef f ects are somatic ef fects, where insults such as cancers occur directly to the individual exposed, and genetic defects, where, through damage to the reproductive cells of the exposed individual, disability and disease ranging from subtle to severe are transmitted to the exposed individual's offspring. Clinical or observed evidence of a relationship between radiation and human cancers arise f rom several sources. The most important data come from the victims of Iliroshima and Nagasaki, patients exposed during medical i therapy, radium dial painters, and uranium miners. Data exist only for relatively large doses; there have been no direct measurements of increased incidence of cancer for low-level radiation exposures. Evaluation of the availabic data has lead to estimates of the risk of radiation-induced i cancer estimated risks for the lower doses have been derived by linear txtrapolation from the higher doses. All radiation exposures then, no matter how small, are assumed to be capable of increasing an individual's risk of contracting cancer. O 4
( 96 APPENDIX 7 (cont'd.) l Data on gwetic defects resulting from radiation exposure of humans is not available to the extent necessary to allow an estimate of the risk of l radiation-induced effects. Instead, data from animals, along with general l knowledge of genetics, have been used to derive an estimate of the risks of genetic effects. Estimates of health effects from radiation doses are usually based on l risk factors as provided in reports issued by the International Commission on Radiological Protection (ICRP) (Ref. 2), National Research Council l Advisory Committee on the Biological Effects of Ionizing Radiation (BEIR) (Refs. 3 and 4), or the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) (Ref. 5). Multiplying the estimated dose by the appropriate risk factor provides an estimate of the risk or probability of induction of health effects to an individual or his descendants as a result of that exposure. The evaluation of these risk factors is presently subject to large uncertainties and, therefore, potential continual revision. The risk factors recommended by the ICRP for cancer mortality and hereditary 4 ill health to the first and second generations are 10 per rem of whole body dose and 4 x 10~8 per rem of gonadal dose, respectively. As an example, a whole-body dose of I rem would be estimated to add a risk of cancer mortality to the exposed invididual of 10~4, i.e., 1 chance in 10,000. However, a precise numerical value cannot be assigned with any certainty to a particular individual's increase in risk attributabic to radiation exposure. The reasons for this are numerous and include the O followings (1) uncertainties over the influence of the individual's age, state of health, personal habits, family medical history, and previous or concurrent exposure to other cancer-causing agents, (2) the variability in the latent period (time between exposure and physical evidence of disease), and (3) the uncertainty in the risk factor itself. To be meaningful, an attempt should be made to view such risk estimates in the appropriate context. One useful comparison is with risks encountered in normal life. Another comparison, potentially more useful, is with an estimation of the risks attributable to natural background radiation. Radiation from natural external and internal radioactivity results in the same types of interactions with body tissues as that from ' man-made" radio-activity. llence, the riska from a specified dose are the same regardless of the source. Rather than going through an intermediate step involving risk factors, doses can also be compared directly to natural background radiation doses. Besides being used as the basis for estimation of risks and comparisons to natural background, doses may be compared to standards and regulations. The appropriate standards, the Department of Energy " Requirements for Radiation Protection," give limits for external and internal exposure for the whole body and rpecified organs which are expressed as the permissible done or dose commitment annually in addition to natural background and medical exposures. There are in general two sets of limits, one applicable to occupationally exposed persons and the second applicable to individuals O
97 APPENDIX 7 (cont'd.) and population groups of the general public. The limits for individuals of the public are one-tenth of those permitted for occupationally exposed individuals. The set of limits important to this report are those applic-able to individuals and population groups of the public. The limits for individuals of the public are 500 mrem per year to the whole body, gonads, or bone marrow and 1500 mrem per year to other organs. The limits for population groups of the public are 170 mrem to the whole body, gonads, or bone marrow and 500 mrem per year to other organs, averaged over the group. In either case, exposures are to be limited to the lowest levels reasonably achievable within given limits. REFERENCES FOR APPENDIX 7 1. National Council on Radiation Protection and Measurements. " Natural Background Radiation in the United States." NCRP Report No. 45. 1975. 2. International Conunission on Radiological Protection. " Recommendations of the International Commission on Radiological Protection." Annals of the ICRP, Vol. 1. No. 3, ICRP Publication 26, Pergamon Press, New York. 1977. 3. National Research Council Advisory Committee on the Biological Ef fects of Ionizing Radiation (BEIR).. "The Effects on Populations of Exposure O 'e~ t or t i i = a at ti "tt t^cdev rsci c 1972. 4. National Research Council Committee on the Biological Effects of Ioniz-ing Radiation (BEIR). "The Effects on Populations of Exposure to Low-Levels of Ionizing Radiation: 1980." National Academy of Sciences. 1980. 5. United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). " Sources and Ef fects of Ionizing Radiation,1977 Report to the General Assembly." United Nations Publication E.77.!X.1. 1977. O C J
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