ML003714654
| ML003714654 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/04/2000 |
| From: | Sorensen J Northern States Power Co |
| To: | NRC/OCIO/IMD/RMB |
| References | |
| +sunsi/sispmjr=200603, -RFPFR, Project 8010 | |
| Download: ML003714654 (73) | |
Text
4W Northern States Power Company ftup 1717 Wakonade Drive East Welch, MN 55089 Telephone 651-388-1121 May 4, 2000 Prairie Island Technical Specifications 6.6.B US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 Docket Nos. 50-306 License Nos. DPR-60 ISFSI Docket No. 72-10 License No. SNM-2506 1999 Annual Radiological Environmental Monitorinq Report In accordance with the Prairie Island Nuclear Generating Plant Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, and in accordance with the Prairie Island Independent Spent Fuel Storage Installation Technical Specifications, Appendix A to Materials License DNM 2506, we are submitting one copy of the Annual Radiological Environmental Monitoring Report covering the period January, 1999 through December 31, 1999.
Please contact us if you have any questions related to the information we have provided.
?ol.Sorensen Site General Manager Prairie Island Nuclear Generating Plant c: Regional Administrator, EIl, NRC Region mI Attn: Dr. John House NRC Project Manager Director of NMSS Sr. Resident Inspector, NRC State of Minnesota Attn: James Bernstein J. Silberg
Attachment:
Annual report to the United States Nuclear Regulatory Commission, Radiation Environmental Monitoring Program, January 1, 1999 through December 31, 1999.
'rk TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES MIDWEST LABORATORY 700 LANDWEHR ROAD NORTHBROOK, ILLINOIS 60062-2310 (847) 564-0700
- FAX (847) 5644517 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 1999 Project No. 8010 Prepared Under Contract by TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES MIDWEST LABORATORY Project No. 8010 Approved by:
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- I PREFACE The staff of Teledyne Brown Engineering Environmental Services, Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, Northern States Power Company. The report was prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory.
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TABLE OF CONTENTS Section Pae Preface ................................................................................................................................. ii List of Tables ....................................................................................................................... iv List of Figures ........................................................................................................................ v
1.0 INTRODUCTION
.................................................................................................................. 1 2.0 SUM M ARY ............................................................................................................................ 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) ............................. 3 3.1 Program Design and Data Interpretation ....................................................................... 3 3.2 Program Description .................................................................................................. 4 3.3 Program Execution ............................................................................................................ 5 3.4 Laboratory Procedures .............................................................................................. 6 3.5 Program M odifications ............................................................................................. 6 3.6 Land Use Census ............................................................................................................... 6 4.0 RESULTS AND DISCUSSION ............................................................................................ 7 4.1 Atm ospheric Nuclear Detonations and Nuclear Accidents ............................................ 7 4.2 Sum mary of Preoperational Data ................................................................................ 7 4.3 Program Findings ...................................................................................................... 8 5.0 FIGURES AND TABLES ................................................................................................... 12 6.0 REFEREN CES CITED ........................................................................................................... 25 APPENDICES A Interlaboratory Comparison Program Results ................................................................... A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Samples ................................................. A-2 B Data Reporting Conventions ............................................................................................ B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ............................................................ C-1 D Special Ground and Well Water Sam ples ........................................................................... D-1 E Sampling Location Maps ................................................................................................. E-1 iii
LIST OF TABLES No. Title Pae 5.1 Sample Collection and Analysis Program, 1999 ........................................................................ 13 5.2 Sampling Locations .................................................................................................................... 14 5.3 Missed Collections and Analyses, 1999 .................................................................................... 17 5.4 Radiation Environmental Monitoring Program Summary .......................................................... 20 In addition, the following tables are in the Appendices:
Appendix A A-1 U.S. Environmental Protection Agency's Crosscheck Program results ........................................ Al-1 A-2 Crosscheck Program Results; (TLDs)....................................................................................... A2-1 A-3 In-house "Spiked" Samples ................................................................................................... A3-1 A-4 In-house "Blank" Samples ..................................................................................................... A4-1 A-5 In-house "Duplicate" Samples ........................................................................................... A5-1 A-6 Department of Energy MAPEP comparison results ......................................................... A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results ........................................................................................... A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ................................................................. C-2 Appendix D D-4.1 Sample collection and analysis program ................................................................................ D-6 D-4.2 Sampling locations ............................................................................................................... D-7 D-4.3 REMP Summary .................................................................................................................... D-8 D-4.4 REMP Complete Data Table ................................................................................................. D-9 iv
LIST OF FIGURES No. Title Pge 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control,1984-1999 ............................................................................................. 18 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i), 1984-1999 ..................................................... 19 v
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Brown Engineering Environmental Services, Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 1999. This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulations of the individual analyses made during the year are not included in this report.
These data are included in a reference document (Teledyne Brown Engineering Environmental Services, Midwest Laboratory, 2000b) available at Northern States Power Company, Prairie Island Nuclear Generating Plant.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, and operated by Northern States Power Company. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.
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2.0
SUMMARY
The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
Results for 1999 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment.
For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
Sources of environmental radiation include the following:
(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium 95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium 137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered radiological impact indicators.
The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and 3.
3.1 Program Design and Data Interpretation (continued) arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the Plant became operational. Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
3.2 Program Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 1999). Maps of fixed sampling locations are included in Appendix E.
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. A quarterly composite of the particulate filters from each location is gamma scanned on an HPGe detector. One of the five locations is a control (P-i), and four are indicators (P-2, P-3, P-4, and P-6).
Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for the inner ring, outer ring and special interest locations are placed in the field at the same time as regular sets. The emergency set is returned to TBEESML quarterly for annealing and repackaging.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.
Milk samples are collected monthly from five farms (four indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.
For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes.
Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes. River water is collected weekly at 4
3.2 Program Description (continued) two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma emitting isotopes.
Due to detectable levels of tritium in a well south of the plant in 1989, special tritium sampling has been implemented. A summary of the special tritium sampling of ground and well water is included in Appendix D.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) No air particulate/air iodine sample was available for air station P-1 for the week ending April 21, 1999, due to sampler pump failure.
(2) No surface water samples were available for locations P-6 and P-11 for the week ending July 28, 1999. The samples were collected, but damaged in shipment.
(3) Approximately 10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of sampling time were lost from the air particulate/air iodine sample location (P-6) for the week ending 08-25-99, due to a power interruption.
(4) No milk sample was available for location P-25 for the week ending 10-12-99. Dairy operations at this location were discontinued.
(5) Approximately 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> of sampling time were lost from the air particulate/air iodine sample location (P-i) for the week ending 11-09-99, due to sampler pump failure.
(6) No air particulate/air iodine sample was available from air station P-3 for the week ending 12-28-99, due to sampler pump failure.
Deviations from the program are summarized in Table 5.3.
3.4 Laboratory Procedures All iodine-131 analyses in milk and drinking water were made by using a sensitive radiochemical procedure which involves separation of the element by use of an ion exchange resin and subsequent beta counting. All gamma-spectroscopic analyses were 5
3.4 Laboratory Procedures (continued).
performed with an HPGe detector. Levels of airborne iodine-131 in charcoal samples were measured by gamma spectrometry.
Levels of iodine-131 in cabbage and were determined by gamma spectrometry.
Tritium levels were determined by liquid scintillation technique.
Analytical Procedures used by TBEESML are on file and are available for inspection.
Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S.
Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
Teledyne Brown Engineering Environmental Services, Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of TBEESML's Quality Assurance Program are presented elsewhere (Teledyne Brown Engineering Midwest Laboratory, 1999). The TBEESML Quality Assurance Program includes participation in Interlaboratory Comparison (Crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.
3.5 Program Modifications The control location,(P-25, Rohl Farm) discontinued dairy operations in October, 1999. It was replaced by the Huppert Farm (P-41).
3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft 2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiation environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.
This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.
The 1999 Land Use Census was completed in October, 1999. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 1999.
The critical receptor location did not change in 1999 due to the requirements of the land use census.
No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant. Therefore, no corn samples were collected for analysis.
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4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.
All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1999. The last reported test was conducted on October 16, 1980 by the People's Republic of China.
There were no reported accidents at nuclear reactor facilities in 1999.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/m 2 to 1,020 pCi/m 2 , and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m 3 . Average present day levels have stabilized at around 0.025 pCi/m 3 . Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and I 131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g.
The aqueous environment was monitored by testing of river , well and lake waters, bottom sediments, fish, aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible.
However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. The special tritium sampling program, described in Appendix D, employs a very sensitive detection method, and indicates tritium levels at or near the natural background levels. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well waters, and 11.0 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g,respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g, 46.0 pCi/g, and 13.6 pCi/g, respectively.
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4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 1999.
Offsite Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi distant from the Plant, at special interest areas and at one control location. The means ranged from 15.7 mR/91 days at inner ring locations to 17.2 mR/91 days at outer ring locations. The mean at special locations was 15.8 mR/91 days and 17.5 mR/91 days at the control location. The dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1984 through 1998. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).
Average (Inner Year and Outer Rings) Control 1984 15.0 15.4 1985 14.0 15.3 1986 17.1 17.3 1987 16.9 17.0 1988 15.4 16.0 1989 16.5 16.7 1990 15.9 16.3 1991 14.9 14.5 1992 16.3 14.8 1993 15.9 15.4 1994 15.2 16.0 1995 15.6 16.6 1996 14.8 16.4 1997 15.1 16.0 1998 16.7 17.3 1999 16.6 17.5 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR/91 days).
ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates measured 60.1 mR/91 days inside the ISFSI earth berm and 18.5 mR/91 days outside the ISFSI earth berm. Two additional casks were placed on the ISFSI pad in 1999. There were nine loaded casks on the ISFSI pad during 1999. The higher levels inside the earth berm are expected due to the loaded spent fuel casks being in direct line-of-sight from the TLDs. The ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.5 and 15.6 mR/91 days. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).
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Airborne Particulates The annual gross beta concentration in airborne particulates for indicator locations averaged 0.024 pCi/m 3 and for the control location,0.022 pCi/m 3 . These averages were similar to or slightly lower than the average means observed from 1984 through 1998. The results are tabulated below. The data for 1986 does not include the results from May 19 to June 9, 1986, which were influenced by the accident at Chernobyl. (Figure 5-2).
Average of Year Indicators Control Concentration (pCi/m 3 )
1984 0.025 0.027 1985 0.025 0.025 1986 0.024 0.029 1987 0.024 0.023 1988 0.030 0.030 1989 0.028 0.027 1990 0.024 0.023 1991 0.025 0.025 1992 0.023 0.021 1993 0.022 0.019 1994 0.022 0.022 1995 0.022 0.022 1996 0.023 0.020 1997 0.021 0.021 1998 0.022 0.018 1999 0.024 0.022 Average annual gross beta concentrations in airborne particulates.
A spring peak in beta activity had been observed almost annually for many years (Wilson et al., 1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983. The highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1984 through 1999.
Two pieces of evidence indicate conclusively that the elevated activity observed during the winter months was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations.
Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Northern States Power Company, 2000a).
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955),
was detected in all samples. All other gamma-emitting isotopes were below their respective LLD limits.
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Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m 3 in all samples. There was no indication of a plant effect.
Milk Iodine-131 results were below the detection limit of 1.0 pCi/L in all samples. Cs-137 results were below the LLD level of 15 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples.
This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
In summary, the milk data for 1999 show no radiological effects of the plant operation.
Drinking Water In drinking water from the City of Red Wing well, tritium activity was below the LLD level of 190 pCi/L in all samples. As with the other well water samples, all analyses for gamma-emitting isotopes yielded results below detection limits. Gross beta averaged 5.3 pCi/L and was similar to levels observed from 1984 through 1998. In summary, drinking water data for 1999 show no effects of plant operation.
Gross Beta (pCi/L) 1984 7.9 1985 7.1 1986 6.8 1987 7.9 1988 8.0 1989 7.0 1990 7.0 1991 8.0 1992 7.6 1993 7.5 1994 5.8 1995 3.9 1996 6.3 1997 5.1 1998 5.4 1999 5.3 Average annual concentrations; Gross beta in drinking water.
River Water At both the upstream and downstream collection sites, quarterly composite tritium levels were below the LLD level of 190 pCi/L. Gamma-emitting isotopes were below detection limits in all samples. There was no indication of a plant effect.
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Well Water At the control well P-25, Rohl Farm and the three indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, and P-9, Plant Well No. 2 ) no tritium was detected above the LLD level of 183 pCi/L in all samples. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 1999 show no radiological effects of the plant operation.
Crops Two samples of cabbage were collected in August and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.021 pCi/g wet weight in both samples. With the exception of naturally-occurring potassium-40, all other gamma emitting isotopes were below their respective detection limits.There was no indication of a plant effect.
The field sampling personnel conducted an annual land use survey and found that there was no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. Therefore, it was not necessary to collect and analyze corn samples.
Fish Fish samples were collected in May and September, 1999 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.
Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in July and September, 1999.
All gamma-emitting isotopes were below their respective detection limits. There was no indication of any plant effect.
Bottom and Shoreline Sediments Sediment collections were made in June and September, 1999 and analyzed for gamma emitting isotopes. All other gamma-emitting isotopes, excepting naturally-occurring potassium-40, were below their respective LLDs. No plant effect was indicated.
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5.0 FIGURES AND TABLES 12
PRAIRIE ISLAND Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant Collection Analysis Location Type and Type and Medium No. Codes (and Type)' Frequency' Frequency' Ambient radiation (TLD's) 54 P-01A-P-10A C/Q Ambient gamma P-01B - P-15B P-01S - P-08S P-01IA - P-081A P-01IB - P-081B P-O1IX- P-04IX, P-O1C Airborne Particulates 5 P-I (C), P-2, P-3, P-4, P-6 C/W GB, GS (QC of each location)
Airborne Iodine 5 P-1(C), P-2, P-3, P-4, P-6 C/W 1-131 Milk 4 P-14, P-18, P-37 G/Md 1-131, GS P-25 (C), P-41 (C)
Milk 1 P-39 G/M 1-131, GS River water 2 .P-5(C), P-6 G/W GS(MC), H-3(QC)
Drinking water 1 P-11 G/W GB(MC), 1-131(MC)
Well water 5 P-6, P-8, P-9, P-24, P-41 (C) G/Q H-3, GS Edible cultivated crops 2 P-38(C), P-24 G/A GS (1-131) leafy green vegetables Fish (one species, edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or invertebrates 2 P-40(C), P-6 G/SA GS Bottom sediment 2 P-20(C), P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.
'Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows:
W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
'Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 = iodine-131.
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d Milk is collected biweekly during the grazing season (May - October).
13
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction from Code Type' Collection Site Sample Type" Reactor P-1 C Air Station P-1 AP, Al 11.8 mi @ 316"/NNW P-2 Air Station P-2 AP, AI 0.5 mi @ 294'/WNW P-3 Air Station P-3 AP, AI 0.8 mi @ 313"/NW P-4 Air Station P-4 AP, AI 0.4 mi @ 359'/N P-5 C Upstream of Plant RW 1.8 mi @ 11°/N P-6 Lock and Dam #3 & Air AP, AI, RW Station P-6 WW, BS, BO' 1.6 mi @ 129°/SE P-8 Community Center WW 1.0 mi @ 321'/WNW P-9 Plant Well #2 WW 0.3 mi @ 3060/NW P-11 Red Wing Service Center DW 3.3 mi @ 158°/SSE P-12 Downstream of Plant SS 3.0 mi @ 116°/ESE P-13 Downstream of Plant F' 3.5 mi @ 113°/ESE P-14 Gustafson Farm M 2.3 mi @ 1730/S P-18 Christiansen Farm M 3.8 mi @ 88"/E P-19 C Upstream of Plant F' 1.3 mi @ 0"/N P-20 C Upstream of.Plant BS 0.9 mi @ 45"/NE P-24 Suter Residence VE, WW 0.6 mi @ 158"/SSE P-25 C Rohl Farm M, WW 12.9 mi @ 352"/N P-37 Welsch Farm M 4.1 mi @ 87"/E P-38 C Cain Residence VE 14.2 mi @ 359"/N P-39 Born Farm M 2.8 mi @ 239"/WSW P-40 C Upstream of Plant BO' 0.4 mi @ 0"/N P-41 C Huppert Farm M, WW 13.8 mi @ 354"/N General Area of the Site Boundary P-01A Property Line TLD 0.4 mi @ 359°/N P-02A Property Line TLD 0.3 mi @ 10'/N P-03A Property Line TLD 0.5 mi @ 183'/S P-04A Property Line TLD 0.4 mi @ 204'/SWW P-05A Property Line TLD 0.4 mi @ 225"/SW P-06A Property Line TLD 0.4 mi @ 249"/WSW P-07A Property Line TLD 0.4 mi @ 268"/W P-08A Property Line TLD 0.4 mi @ 291"/WNW P-09A Property Line TLD 0.7 mi @ 317"/NW P-10A Property Line TLD 0.5 mi @ 333"/NNW 14
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Distance and Direction from Code Type' Collection Site Sample Type' Reactor Approximately 4 to 5 miles Distant from the Plant P-01B Thomas Killian Residence TLD 4.7 mi @ 355"/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 17"/NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 460/NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 610/ENE P-05B Country Road E and Coulee TLD 4.2 mi @ 102"/ESE P-06B William Hauschiblt Residence TLD 4.4 mi @ 112"/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 1400/SE P-08B David Wnuk Residence TLD 4.1 mi @ 1650/SSE P-09B Highway 19 South TLD 4.2 mi @ 1870/S P-10B Cannondale Farm TLD 4.9 mi @ 200°/SSW P-11B Wallace Weberg Farm TLD 4.5 mi @ 221°/SW P-12B Ray Gergen Farm TLD 4.6 mi @ 251°/WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 2700/W P-14B David J. Anderson Farm TLD 4.9 mi @ 306°/NW P-15B Holst Farms TLD 3.8 mi @ 345°/NNW Special Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 mi @ 1290/SE P-02S Charles Suter Residence TLD 0.5 mi @ 155"/SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 1730/S P-04S Richard Burt Residence TLD 2.0 mi @ 202"/SSW P-05S Kinney Store TLD 2.0 mi @ 270'/W P-06S Earl Flynn Farm TLD 2.5 mi © 299O/WNW P-07S Indian Community TLD 0.7 mi @ 271'/W P-08S Indian Community TLD 0.7 mi @ 287°/NWW P-01C C Robert Kinneman Farm TLD 11.1 mi @ 331°/NNW 15
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Approximate Type of Distance and Direction Code Type' Collection Site Sampleb from ISFSI Center.
ISFSI Area Inside Earth Berm P-O1IA ISFSI Nuisance Fence TLD 190' @ 45"/NE P-02IA ISFSI Nuisance Fence TLD 360' @ 82-/E P-031A ISFSI Nuisance Fence TLD 370' @ 100°/E P-041A ISFSI Nuisance Fence TLD 200' @ 134°/SE P-05IA ISFSI Nuisance Fence TLD 180' @ 219°/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258"/WSW P-07IA ISFSI Nuisance Fence TLD 320' @ 281"/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318°/NW P-01Ix ISFSI Nuisance Fence TLD 140' @ 180"/S P-021X ISFSI Nuisance Fence TLD 310' @ 270°/W P-031X ISFSI Nuisance Fence TLD 140' @ 0"/N P-041X ISFSI Nuisance Fence TLD 360' @ 90°/E ISFSI Area Outside Earth Berm P-01IB ISFSI Berm Area TLD 340' @ 3'/N P-021B ISFSI Berm Area TLD 380' @ 28"/NNE P-031B ISFSI Berm Area TLD 560' @ 85"/E P-041B ISFSI Berm Area TLD 590'@ 165°/SSE P-051B ISFSI Berm Area TLD 690' @ 186°/S P-061B ISFSI Berm Area TLD 720' @ 201°/SSW P-07IB ISFSI Berm Area TLD 610' @ 271°/W P-081B ISFSI Berm Area TLD 360' @ 332"/NNW "C" denotes control location. All other locations are indicators.
Sample Codes:
AP Airborne particulates F Fish AI Airborne Iodine M Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates) VE Vegetation/vegetables DW Drinking water WW Well water
'Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
16
Table 5.3. Missed collections and analyses, 1999. Prairie Island Nuclear Generating Plant.
All required samples were collected and analyzed as scheduled except the following:
Sample Analysis Location Collection Reason for not Plan for Preventing Type Date or Conducting REMP Recurrence Period as Required AP/AI Gross Beta, P-1 04-21-99 No flow through air Replaced sampler with 1-131 sampler. Vacuum pump previously calibrated unit.
failure.
SW Gamma P-6, 07-28-99 Samples collected, but Isolated incident, none P-11 damaged in shipping. planned at this time.
AP/AI Gross Beta, P-6 08-25-99 Approximately 10.5 hrs. None - Power interruption 1-131 run-time lost. from utility company.
MI Gamma, P-25 10-12-99 Dairy operations New control location 1-131 discontinued, established.
AP/AI Gross Beta, P-1 11-09-99 Air sampler failure, Open fuse; Sampler tested 1-131 approximately 110 hrs. satisfactorily and was run-time lost. returned to service.
AP/AI Gross Beta, P-3 12-28-99 Sampler pump failure. Replaced sampler with 1-131 previously calibrated unit.
17
Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.
I I - Indicator I
"0)
E CO CO (0 CO CO CO O0O M CO 00) 0") 0D
- 03) CO
- 0) Si')0)*- M-
- 0) W 0") II-
- 0) CO M
- 0) 0))
S --e- Control (P-01C)
A 2
19--
1
- , 186 -- _ _
>' 1, 4
1-1 3-2 10 1(
1O (0 CoCO N* CO CO 0)
CO O0 0 )O '- C0 CO *I 10 (0 N* CO 0")
CO CO 0) 0) 0) 0") 0) 0') 0) 0)
- 0) 0) 0 )* 0) 0) 0 ") 0) 0') 0) 0 )* 0) 0) ) 0 ') 0 )' 0 18
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
0.5 Indicators (P-2,3,4,6) 0 .03 5 - -_-- - - -
0.033-0.031 - \
co 0.029- -,
E 0.027- -
0.025 "-4 0.023 __
0.021-- --- - - -_
0.019 0.017-0.015-1"I.'*L (0
,O r- O M3 0 ,I 0M 't" 1O (4D: I-* wO M co GD GO CO CO CO 0') 033) 0) 0') 0') 0') 0') 0') 0) 0")
0") 0) 0) 0) 0') 0) 0") 03 0) 0") 0') 0) 0) 0) 0) 0)
-e-- Control (P-i) 0.035-0.033 CO0.031 E 0.029- - -
0.027-'
0.025 NZ 0.023 0.021 0.019---------------- -_
0.017-0.015 Ct CO CO 1-CO O0 O0 0) 0) 0) 0) 0) 0) 0) 0) 0) 00 0 0) 00) 0 0) 0) 0) 0) 0) 0) 0M 0M 0) 0M 19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 1999 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)c Mean (F)' Routine (Units) Analyses' Range' Location' Range' Range' Results' TLD (Inner Ring, Gamma 40 3.0 15.7 (40/40) P-04A 16.4 (4/4) (See Control 0 Area at Site (12.6-17.5) 0.4 mi @ 2040 /WSW (14.8-17.5) below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma 60 3.0 17.2 (60/60) P-02B, Roy Kinneman, 19.7 (4/4) (See Control 0 4-5 mi. distant) (13.4-22.1) 4.8 mi @ 17' /NNE (16.1-22.1) below.)
mR/91 days)
TLD (Special Gamma 32 3.0 15.8 (32/32) P-03S, Gustafson Farm, 18.3 (4/4) (See Control 0 Interest Areas) (12.2-19.7) 2.2 mi @ 173' /S (16.1-19.6) below.)
mR/91 days)
TLD (Control) Gamma 4 3.0 None P-01C, R. Kinneman, 17.5 (4/4) 17.5 (4/4) 0 mR/91 days) 11.1 mi@ 331' /NNW (15.7-18.8) (15.7-18.8)
Airborne GB 259 0.005 0.024 (208/208) P-02, Air Station 0.024 (52 /52) 0.022 (51/51) 0 Particulates (0.007-0.048) 0.5 mi @ 294' /WNW (0.007-0.048) (0.011-0.045)
(pCi/m 3 )
GS 20 Be-7 0.015 0.070 (16/16) P-04, Air Station 0.074 (4/4) 0.064 (4/4) 0 (0.052-0.087) 0.4 mi @ 3590 /N (0.055-0.087) (0.045-0.084)
Mn-54 0.0009 < LLD <LLD 0 Co-58 0.0010 < LLD <LLD 0 Co-60 0.0011 < LLD - - < LLD 0 Zn-65 0.0021 <LLD < LLD 0 Zr-Nb-95 0.0021 < LLD - - < LLD 0 Ru-103 0.0014 <LLD < LLD 0 Ru-106 0.0071 < LLD <LLD 0 Cs-134 0.0009 < LLD - - < LLD 0 Cs-137 0.0010 < LLD < LLD 0 Ba-La-140 0.0035 < LLD - - <LLD 0 Ce-141 0.0025 < LLD - - < LLD 0 Ce-144 0.0058 < LLD - - < LLD 0 Airborne Iodine 1-131 259 0.07 <LLD - - < LLD 0 3
(pCi/mi) 20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 1999 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLD' Mean (F)c Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Locationd Rangec Range' Results' Milk (pCi/L) 1-131 71 1.0 < LLD < LLD 0 GS 71 K-40 200 1445 (54/54) P-37, Welsch Farm 1480 (18 /18) 1386 (17/17) 0 (1223-1677) 4.1 mi @ 87 /E (1366-1677) (1115-1260)
Cs-134 15 <LLD - - < LLD 0 Cs-137 15 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 River Water H-3 8 190 < LLD < LLD 0 (pCi/L)
GS 24 Mn-54 15 < LLD < LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 15 < LLD < LLD 0 Co-60 15 < LLD -< LLD 0 Zn-65 30 < LLD -< LLD 0 Zr-Nb-95 15 < LLD -< LLD 0 Cs-134 15 < LLD -< LLD 0 Cs-137 18 < LLD - <LLD 0 Ba-La-140 15 <LLD - - < LLD 0 Ce-144 55 <LLD <LLD 0 21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 1999 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLD" Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysesa Range' Location' Rangec Rangec Results' Drinking Water GB 12 1.0 5.3 (12/12) P-11, Red Wing S.C. 5.3 (12/12) None 0 (pCi/L) (1.8-11.1) 3.3 mi @ 1580 /SSE (1.8-11.1) 1-131 12 1.0 <LLD None 0 H-3 4 190 <LLD None 0 GS 12 Mn-54 15 < LLD None 0 Fe-59 30 <LLD - - None 0 Co-58 15 <LLD None 0 Co-60 15 <LLD - - None 0 Zn-65 30 < LLD - - None 0 Zr-Nb-95 15 < LLD - - None 0 Cs-134 10 < LLD - - None 0 Cs-137 10 < LLD - - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 64 < LLD - None 0 Well Water H-3 16 183 < LLD < LLD 0 (pCi/L)
GS 16 Mn-54 15 < LLD < LLD 0 Fe-59 30 < LLD <LLD 0 Co-58 15 < LLD <LLD 0 Co-60 15 < LLD <LLD 0 Zn-65 30 <LLD < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - -< LLD 0 Cs-137 18 < LLD - - <LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 93 < LLD - - <LLD 0 Crops - Cabbage 1-131 2 0.021 < LLD < LLD
- - 0 (pCi/gwet) 22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 1999 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Locationd Range' Range' Results' Fish GS 4 (pCi/g wet) K-40 0.10 3.45 (2/2) P-19, Upstream 3.58 (2/2) 3.58 (2/2) 0 (3.40-3.50) 1.3 mi. @ 0* /N (3.42-3.73) (3.42-3.73)
Mn-54 0.012 < LLD - - <LLD 0 Fe-59 0.093 < LLD - - <LLD 0 Co-58 0.033 <LLD - - <LLD 0 Co-60 0.017 <LLD - - <LLD 0 Zn-65 0.042 <LLD - - <LLD 0 Zr-Nb-95 0.032 <LLD - - <LLD 0 Cs-134 0.017 <LLD - - <LLD 0 Cs-137 0.016 <LLD - -< LLD 0 Ba-La-140 0.89 < LLD - -< LLD 0 Invertebrates GS 4 (pCi/g wet) Be-7 0.65 < LLD - - < LLD 0 K-40 1.47 < LLD - - <LLD 0 Mn-54 0.057 < LLD - - < LLD 0 Co-58 0.050 < LLD - - < LLD 0 Co-60 0.067 < LLD - - < LLD 0 Zn-65 0.24 < LLD - - < LLD 0 Zr-Nb-95 0.10 < LLD - - <LLD 0 Ru-103 0.097 < LLD - - <LLD 0 Ru-106 0.52 < LLD - - <LLD 0 Cs-134 0.071 < LLD - - < LLD 0 Cs-137 0.055 <LLD - - <LLD 0 Ba-La-140 0.34 <LLD - - <LLD 0 Ce-141 0.14 < LLD - - <LLD 0 Ce-144 0.28 < LLD - - <LLD 0 23
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 1999 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLIY Mean (F)c Mean (F)' Mean (F)' Routine (Units) Analyses' Rangec Locationd Rangec Rangec Results' Bottom and GS 6 Shoreline Be-7 0.27 < LLD <LLD 0 Sediments K-40 0.10 8.11 (4/4) P-20, Upstream 10.03 (4/4) 10.03 (4/4) 0 (pCi/g dry) (7.65-8.37) 0.9 mi. @ 450 /NE (9.64-10.42) (9.64-10.42)
Mn-54 0.019 <LLD < LLD 0 Co-58 0.022 < LLD <LLD 0 Co-60 0.019 < LLD <LLD 0 Zn-65 0.088 < LLD <LLD 0 Zr-Nb-95 0.039 <LLD < LLD 0 Ru-103 0.028 <LLD <LLD 0 Ru-106 0.21 < LLD <LLD 0 Cs-134 0.040 < LLD - <LLD 0 Cs-137 0.024 < LLD - <LLD 0 Ba-La-140 0.063 < LLD - < LLD 0 Ce-141 0.052 < LLD < LLD 0 Ce-144 0.15 <LLD < LLD 0
'GB = gross beta, GS = gamma scan.
'LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
'Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
Locations are specified: (1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.
'Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.
24
6.0 REFERENCES
CITED Arnold, J. R. and H. A. A1-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
Hazleton Environmental Sciences Corporation. 1979a to 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
Hazleton Environmental Sciences Corporation. 1979b to 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. 1986. "Chernobyl,"
Chemtech October 1986, pp. 596-605.
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.
Northern States Power Company. 1972. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971. Minneapolis, Minnesota.
1973. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1972 to December 31, 1972. Minneapolis, Minnesota.
- 1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1, 1973 to December 31, 1973. Minneapolis, Minnesota.
Northern States Power Company. 1979 to 1983. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 1982 (prepared by Hazleton Environmental Sciences).
Minneapolis, Minnesota.
Northern States Power Company. 1984 to 2000. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Minneapolis, Minnesota.
Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1983 through 1999.
25
Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1983 through 1999.
Northern States Power Company. 1999. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures 4700.
Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1995. Quality Control Program, Revision 0.
20 July 1995.
- 1994. Quality Control Procedures Manual, Revision 18, 27 September 1994.
- 1999. Quality Assurance Program Manual, Revision 1, 26 April 1999.
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
U.S. Environmental Protection Agency. 1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
26
APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Teledyne Brown Engineering - Environmental Services, Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 1999 through December, 1999
Appendix A Interlaboratory Comparison Program Results Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g.,
milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.
This program was conducted by Environmental Resources Associates and serves to replace studies conducted by the U.S. Environmental Protection Agency.
The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2.
Also Teledyne testing results are listed.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.
Attachment A lists acceptance criteria for "spiked" samples.
Out-of-limit results are explained directly below the result.
Al
12-31-99 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter
>100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
>50 pCi/liter or kg 10% of known value Strontium_90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
>30 pCi/liter or kg 10% of known value Potassium-40 >0.1 g/liter or kg 5% of known value Gross alpha <20 pCi/liter 5.0 pCi/liter
>20 pCi/liter 25% of known value Gross beta <100 pCi/liter 5.0 pCi/liter
>100 pCi/liter 5% of known value Tritium <4,000 pCi/liter ls = (pCi/liter) =
169.85 x (known) 0'°933
>4,000 pCi/liter 10% of known value Radium-226,-228 <0.1 pCi/liter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, <_55 pCi/liter 6.0 pCi/liter Iodine_129b >55 pCi/liter 10% of known value Uranium-238, <_35 pCi/liter 6.0 pCi/liter Nickel_63b >35 pCi/liter 15% of known value Technetium-99b Iron_55b 50 to 100 pCi/liter 10 pCi/liter
>100 pCi/liter 10% of known value Othersb - 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Teledyne limit.
A2
Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA), comparison of ERA and Teledyne Midwest Laboratory resultsa.
Concentration in pCi/Lb Lab Sample Date Teledyne Results ERA Resultd Control Code Type Collected Analysis +/-2 Sigmac is, N=i Limits STW-861 WATER Sep, 1999 Ra-226 15.6 +/- 0.3 16.5 +/- 1.7 12.2 - 20.8 STW-861 WATER Sep, 1999 Ra-228 3.2 +/- 0.3 2.2 +/- 0.2 1.2 - 3.1 The activity reported is the average of three separate analyses. Individual results : 2.6, 2.9 and 4.0.
STW-861 WATER Sep, 1999 Uranium 39.4 +/- 1.2 45.4 +/-4.5 37.7 - 53.1 STW-862 WATER Nov, 1999 1-131 23.9 +/- 0.1 23.3 +/- 2.3 18.1 - 28.5 aResults obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sample crosscheck program operated by Environmental Resource Associates(ERA).
b All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/Filter.
Unless otherwise indicated, the TBEESML results are given as the mean +/- 2 standard deviations for three determinations.
dERA results are presented as the known values and expected laboratory precision (is, 1 determination) and control limits as defined by ERA.
Al-1
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).
mR Lab Teledyne Results Known Average +/- 2 Sigma Code TLD Type Date Measurement + 2 Sigma Value (All Participants)
Teledyne Testing 98-1 LiF-100 Chips May, 1998 Lab, 1 15.5 +/- 1.3 16.7 98-1 LiF-100 Chips May, 1998 Lab, 2 23.9 +/- 0.9 32.4 98-1 LiF-100 Chips May, 1998 Lab, 3 59.8 +/- 1.9 60.2 98-1 CaSO 4: Dy May, 1998 Reader 1, #1 18.5 +/- 0.8 16.7 Cards 98-1 CaSO 4: Dy May, 1998 Reader 1, #2 27.3+/-1.7 32.4 Cards 98-1 CaSO 4: Dy May, 1998 Reader 1, #3 70.0+/- 4.7 60.2 Cards Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in May, 1998.
Teledyne Testing 99-1 LiF-100 Chips Mar, 1999 Lab, 1 14.5 +/- 0.5 15.4 99-1 LiF-100 Chips Mar, 1999 Lab, 2 29.3 +/- 1.0 31.8 99-1 LiF-100 Chips Mar, 1999 Lab, 3 60.0 +/- 0.2 59.1 99-1 CaSO 4: Dy Mar, 1999 Reader 1, #1 18.3 + 0.5 15.4 Cards 99-1 CaSO 4: Dy Mar, 1999 Reader 1, #2 35.9 +/- 1.3 31.8 Cards 99-1 CaSO 4: Dy Mar, 1999 Reader 1, #3 66.5 +/- 4.4 59.1 Cards Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 1999.
A2-1
Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Teledyne Results Known Controlc Code Type Collected Analysis 2s, n=lb Activity Limits SPW-140 WATER Jan, 1999 Ra-226 14.51 +/- 0.52 13.79 9.65- 17.93 SPW-140 WATER Jan, 1999 Ra-228 9.47 . 1.49 8.28 5.80- 10.76 SPW-142 WATER Jan, 1999 Gr. Alpha 30.82 +/- 2.49 33.97 16.99 - 50.96 SPW-142 WATER Jan, 1999 Gr. Beta 30.87 +/- 1.91 30.18 20.18 - 40.18 SPW-254 WATER Jan, 1999 H-3 37752.00 +/- 540.00 38559.00 30847.20 - 46270.80 SPAP-270 AIR FILTER Jan, 1999 Cs-137 2.04 +/- 0.02 1.82 1.09- 2.55 SPAP-787 AIR FILTER Jan, 1999 Gr. Beta 5.97 +/- 0.02 5.38 0.00- 15.38 SPW-789 WATER Jan, 1999 Co-60 44.83 +/- 7.11 40.46 30.46 - 50.46 SPW-789 WATER Jan, 1999 Cs-137 45.17+/- 8.63 37.70 27.70 - 47.70 SPW-791 WATER Feb, 1999 Ra-226 15.50 +/- 0.60 13.80 9.66- 17.94 SPW-791 WATER Feb, 1999 Ra-228 6.36 +/- 1.39 8.20 5.74- 10.66 SPW-792 WATER Feb, 1999 Gr. Alpha 24.36 +/- 2.08 33.97 16.99 - 50.96 SPW-792 WATER Feb, 1999 Gr. Beta 28.98 +/- 1.79 30.13 20.13 - 40.13 SPU-1030 WATER Feb, 1999 Ra-226, 38.81 +/- 1.30 34.45 24.12- 44.79 SPW-1460 WATER Mar, 1999 Ra-226 13.26 +/- 0.55 13.79 9.65- 17.93 SPW-1460 WATER Mar, 1999 Ra-228 12.53 +/- 1.47 16.26 11.38 - 21.13 SPW-1466 WATER Mar, 1999 Gr. Alpha 61.00 +/- 3.08 49.44 24.72 - 74.15 SPW-1466 WATER Mar, 1999 Gr. Beta 35.52 +/- 1.86 30.07 20.07 - 40.07 SPMI-1677 MILK Mar, 1999 Cs-137 17.17 +/- 2.08 18.78 8.78 - 28.78 SPMI-1677 MILK Mar, 1999 Sr-90 34.94 +/- 1.53 31.85 25.48 - 38.22 SPW-1681 WATER Mar, 1999 Sr-89 49.30 +/- 3.85 59.20 47.36 - 71.04 SPW-1681 WATER Mar, 1999 Sr-90 29.00 +/- 1.65 31.85 25.48 - 38.22 SPW-2264 WATER Apr, 1999 Ra-226 12.44 +/- 0.14 13.80 9.66- 17.94 SPW-2264 WATER Apr, 1999 Ra-228 18.73 +/- 1.92 16.08 11.26 - 20.90 SPAP-2395 AIR FILTER Apr, 1999 Cs-137 1.86 +/- 0.02 1.81 1.09- 2.53 SPW-2265 WATER Apr, 1999 Gr. Alpha 62.89 +/- 5.90 49.40 24.70 - 74.10 SPW-2265 WATER Apr, 1999 Gr. Beta 34.52 +/- 3.24 30.00 20.00 - 40.00 SPW-2574 WATER Apr, 1999 H-3 56548.00 +/- 648.00 57517.00 46013.60 - 69020.40 SPMI-2686 MILK Apr, 1999 Cs-134 23.56 +/- 5.30 22.30 12.30 - 32.30 SPMI-2686 MILK Apr, 1999 Cs-137 40.21+/- 7.19 37.50 27.50 - 47.50 SPW-2688 WATER Apr, 1999 Co-60 20.79 +/- 5.61 19.64 9.64- 29.64 SPW-2688 WATER Apr, 1999 Cs-134 23.16 +/- 6.13 22.29 12.29 - 32.29 SPW-2688 WATER Apr, 1999 Cs-137 37.49 +/- 3.75 31.60 21.60 - 41.60 SPAP-2653 AIR FILTER Apr, 1999 Gr. Beta 8.96 +/- 0.05 8.19 0.00- 18.19 SPVE-2977 VEGETATION May, 1999 Cs-134 0.67 +/- 0.04 0.68 0.41 - 0.95 SPVE-2977 VEGETATION May, 1999 Cs-137 0.55 +/- 0.05 0.58 0.35- 0.81 SPW-3314 WATER May, 1999 Ra-226 13.62 +/- 0.35 13.79 9.65- 17.93 SPW-3314 WATER May, 1999 Ra-228 16.57+/- 1.73 15.93 11.15 - 20.71 SPSO-3317 SOIL May, 1999 Cs-134 0.09 +/- 0.01 0.07 0.04- 0.10 SPSO-3317 SOIL May, 1999 Cs-137 0.54 +/- 0.05 0.42 0.25 - 0.59 SPSO-3318 SOIL May, 1999 Cs-134 0.09 +/- 0.02 0.07 0.04- 0.10 A3-1
Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Teledyne Results Known Controlc Code Type Collected Analysis 2 s, n=lb Activity Limits SPS 0-3318 ZuVL May, 1999 Cs-137 0.54+/- 0.02 0.42 0.25- 0.59 SPVAV-3315 WATER May, 1999 Gr. Beta 32.57_+/- 1.63 29.95 19.95 - 39.95 SPF.-3777 FISH May, 1999 Cs-134 0.43 +/- 0.03 0.52 0.31 - 0.73 SPF.-3777 FISH May, 1999 Cs-137 0.57_+/- 0.04 0.60 0.36- 0.84 SPVV-3721 WATER Jun, 1999 Rn-222 553.52 +/- 46.70 610.35 366.21 - 854.49 SPVAV-4005 WATER Jun, 1999 Ra-226 13.85 +/- 0.42 13.79 9.65- 17.93 SPV4V-4005 WATER Jun, 1999 Ra-228 16.42 +/- 1.81 15.77 11.04 - 20.50 SPy *-4006 WATER Jun, 1999 Gr. Alpha 46.32 +/- 2.80 49.41 24.71 - 74.12 SPVa-4006 WATER Jun, 1999 Gr. Beta 32.12_+/- 1.83 29.90 19.90 - 39.90 SPV4 -4869 WATER Jul, 1999 Ra-226 14.00 +/- 0.47 13.79 9.65- 17.93 SPy V-4869 WATER Jul, 1999 Ra-228 14.96+/- 1.53 15.62 10.93 - 20.31 SPVA i-4870 WATER Jul, 1999 Gr. Alpha 70.07 +/- 3.45 29.84 14.92 - 44.76 SPVV-4870 WATER Jul, 1999 Gr. Beta 84.01 +/- 2.62 41.18 31.18 - 51.18 Results for gross alpha and beta appear to be approximately 2x the spike level. The sample volume or spike level is suspect.
SPW-4964 WATER Jul, 1999 H-3 60442.00 +/- 679.00 56807.00 45445.60 - 68168.40 SPAP-5001 AIR FILTER Jul, 1999 Cs-137 2.03 +/- 0.02 1.79 1.07- 2.51 SPAP-5003 AIR FILTER Jul, 1999 Gr. Beta 7.48 +/- 0.02 8.15 0.00- 18.15 SPMI-5348 MILK Jul, 1999 Sr-89 46.85 +/- 4.96 55.53 44.42 - 66.64 SPMI-5348 MILK Jul, 1999 Sr-90 31.47 +/- 1.65 31.60 25.28 - 37.92 SPW-5502 WATER Jul, 1999 Sr-89 43.27_+/- 2.81 51.15 40.92 - 61.38 SPW-5502 WATER Jul, 1999 Sr-90 31.80+/- 1.56 31.59 25.27 - 37.91 SPF-5676 FISH Jul, 1999 Cs-134 0.67 +/- 0.04 0.65 0.39 - 0.91 SPF-5676 FISH Jul, 1999 Cs-137 0.63 +/- 0.05 0.60 0.36- 0.83 SPCH-5833 CHARCOAL Aug, 1999 1-131(g) 1.46 +/- 0.06 1.40 CANISTER 0.84- 1.96 SPVE-5826 VEGETATION Aug, 1999 1-131(g) 1.43 +/- 0.09 1.25 0.75- 1.75 SPMI-5828 MILK Aug, 1999 Cs-134 31.46 +/- 5.05 30.23 20.23 - 40.23 SPMI-5828 MILK Aug, 1999 Cs-137 39.22 +/- 7.60 37.23 27.23 - 47.23 SPMI-5828 MILK Aug, 1999 1-131 72.33 +/- 1.06 79.17 63.34- 95.00 SPMI-5828 MILK Aug, 1999 1-131(g) 77.99 +/- 8.12 79.17 47.50 - 89.17 SPW-5830 WATER Aug, 1999 Ra-226 13.82 +/- 0.34 13.79 9.65- 17.93 SPW-5830 WATER Aug, 1999 Ra-228 13.59 +/- 1.80 15.46 10.82 - 20.10 SPW-5831 WATER Aug, 1999 Gr. Alpha 46.05 +/- 2.93 41.17 20.59 - 61.76 SPW-5831 WATER Aug, 1999 Gr. Beta 35.66 +/- 2.01 29.78 19.78 - 39.78 SPW-6076 WATER Aug, 1999 1-131 83.72 +/- 0.98 99.30 79.44 - 119.16 SPW-6076 WATER Aug, 1999 I-131(g) 105.38 +/- 18.30 99.30 59.58- 109.30 SPW-6542 WATER Sep, 1999 Ra-226 15.38 +/- 0.52 13.79 9.65- 17.93 SPW-6542 WATER Sep, 1999 Ra-228 16.48 +/- 2.25 15.46 10.82 - 20.10 SPW-6543 WATER Sep, 1999 Gr. Alpha 47.77_+/- 2.69 41.17 20.59 - 61.76 SPW-6543 WATER Sep, 1999 Gr. Beta 35.25 +/- 1.86 29.78 19.78 - 39.78 SPW-7468 WATER Oct, 1999 Ra-226 14.36 +/- 0.41 13.79 9.65- 17.93 A3-2
Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Teledyne Results Known Controlc Code Type Collected Analysis 2s, n=lb Activity Limits SPW-6543 WATER Sep, 1999 Gr. Beta 35.25 +/- 1.86 29.78 19.78 - 39.78 SPW-7468 WATER Oct, 1999 Ra-226 14.36 +/- 0.41 13.79 9.65- 17.93 SPW-7468 WATER Oct, 1999 Ra-228 13.41+/-1.45 15.16 10.61 - 19.71 SPW-7469 WATER Oct, 1999 Gr. Beta 31.37 +/- 3.16 29.68 19.68 - 39.68 SPW-7486 WATER Oct, 1999 1-131 49.26 +/- 0.89 48.82 36.82 - 60.82 SPMI-7488 MILK Oct, 1999 1-131 49.54 +/- 0.89 48.82 36.82 - 60.82 SPSO-7761 SOIL Oct, 1999 Cs-134 0.06 +/- 0.01 0.07 0.04- 0.10 SPSO-7761 SOIL Oct, 1999 Cs-137 0.53 +/- 0.01 0.49 0.29 - 0.69 SPAP-7763 AIR FILTER Oct, 1999 Cs-137 1.84 +/- 0.02 1.79 1.07- 2.51 SPW-7469 WATER Oct, 1999 Gr. Alpha 43.55 +/- 4.67 41.16 20.58 - 61.74 SPF-8545 FISH Oct, 1999 Cs-134 0.60 +/- 0.03 0.59 0.36- 0.83 SPF-8545 FISH Oct, 1999 Cs-137 0.60 +/- 0.04 0.59 0.36- 0.83 SPMI-9028 MILK Oct, 1999 Cs-134 39.43 +/- 6.37 37.43 27.43 - 47.43 SPMI-9028 MILK Oct, 1999 Cs-137 40.93 +/- 9.42 37.05 27.05 - 47.05 SPW-8773 WATER Nov, 1999 Ra-226 11.30 +/-0.14 13.79 9.65 - 17.93 SPW-8773 WATER Nov, 1999 Ra-228 15.18 +/- 2.26 15.00 10.50 - 19.50 SPW-8774 WATER Nov, 1999 Gr. Alpha 43.12 +/- 3.09 41.15 20.58 - 61.73 SPW-8774 WATER Nov, 1999 Gr. Beta 31.98 +/- 2.06 29.62 19.62 - 39.62 SPW-9133 WATER Nov, 1999 Co-60 30.70 +/- 4.43 29.06 19.06 - 39.06 SPW-9133 WATER Nov, 1999 Cs-134 40.56 +/- 4.53 36.59 26.59 - 46.59 SPW-9133 WATER Nov, 1999 Cs-137 38.20 +/- 6.14 36.98 26.98 - 46.98 SPW-9720 WATER Nov, 1999 H-3 57335.00 +/- 657.00 58177.00 46541.60 - 69812.40 SPW-9717 WATER Dec, 1999 Ra-228 18.88 +/- 1.80 14.80 10.36 - 19.24 SPW-9719 WATER Dec, 1999 Ra-226 14.91 +/- 0.48 13.79 9.65- 17.93 SPCH-9806 CHARCOAL Dec, 1999 1-131(g) 0.06 +/- 0.01 CANISTER 0.06 0.04- 0.09 SPW-9718 WATER Dec, 1999 Gr. Alpha 44.82 +/- 2.39 44.81 22.41 - 67.22 SPW-9718 WATER Dec, 1999 Gr. Beta 33.93 +/- 1.72 29.54 19.54 - 39.54 SPW-9718 WATER Dec, 1999 Gr. Beta 33.93 +/- 1.72 29.54 19.54 - 39.54 a All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, which are in pCi/Filter; and food products, which are in mg/kg.
bAll samples are the results of single determinations.
'Control limits are based on Attachment A, page A2 of this report.
NOTE: For fish, Jello is used for the spike matrix.
A3-3
Table A-4. In-house "blank" samples.
Concentration pCi/La.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activityb (4.66 Sigma)
SPW-141 WATER Jan 1999 Gr. Alpha < 0.470 0.207 +/- 0.320 < 1.00 SPW-141 WATER Jan 1999 Gr. Beta < 0.890 0.234 +/- 0.591 < 3.20 SPW-141 WATER Jan 1999 Ra-226 < 0.064 0.054 +/- 0.030 < 1.00 SPW-141 WATER Jan 1999 Ra-228 < 1.000 0.460 +/- 0.530 < 1.00 SPW-255 WATER Jan 1999 H-3 < 178.000 23.455 +/- 94.510 < 200.00 SPW-790 WATER Feb 1999 Gr. Alpha < 0.440 -0.130 +/-_0.250 < 1.00 SPW-790 WATER Feb 1999 Gr. Beta < 1.010 -0.250 +/- 0.610 < 3.20 SPW-790 WATER Feb 1999 Ra-226 < 0.036 0.026 +/- 0.017 < 1.00 SPW-790 WATER Feb 1999 Ra-228 < 0.850 0.355 +/- 0.440 < 1.00 SPW-1461 WATER Mar 1999 Gr. Alpha < 0.800 0.060 +/- 0.540 < 1.00 SPW-1461 WATER Mar 1999 Gr. Beta < 1.600 0.460 +/- 1.080 < 3.20 SPW-1461 WATER Mar 1999 Ra-226 < 0.044 0.071 +/- 0.028 < 1.00 SPW-1461 WATER Mar 1999 Ra-228 < 0.700 0.280 _ 0.350 < 1.00 SPMI-1678 MILK Mar 1999 Sr-89 < 0.590 -0.190 +/- 0.670 < 5.00 SPMI-1678 MILK Mar 1999 Sr-90 1.020 +/- 0.360 < 1.00 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPW-1682 WATER Mar 1999 Sr-89 < 0.530 -0.310 +/- 0.450 < 5.00 SPW-1682 WATER Mar 1999 Sr-90 < 0.590 0.256 +/- 0.307 < 1.00 SPW-2263 WATER Apr 1999 Gr. Alpha < 0.380 -0.160 +/- 0.240 < 1.00 SPW-2263 WATER Apr 1999 Gr. Beta < 0.880 0.320 +/- 0.580 <3.20 SPW-2263 WATER Apr 1999 Ra-226 < 0.013 0.023 +/- 0.009 < 1.00 SPW-2263 WATER Apr 1999 Ra-228 < 0.680 0.310 +/- 0.360 < 1.00 SPW-2575 WATER Apr 1999 H-3 < 158.000 23.150 +/- 79.380 < 200.00 SPAP-2652 AIR FILTER Apr 1999 Gr. Beta < 0.003 -0.000 +/- 0.001 < 3.20 SPW-3316 WATER May 1999 Ra-226 < 0.027 0.030 +/- 0.014 < 1.00 SPW-3316 WATER May 1999 Ra-228 < 0.800 0.192 +/- 0.397 < 1.00 SPW-3316 WATER May 1999 Gr. Alpha < 0.830 0.310 +/- 0.600 < 1.00 SPW-3316 WATER May 1999 Gr. Beta < 1.580 0.220 +/- 1.110 < 3.20 SPW-4004 WATER Jun1999 Gr. Alpha < 0.870 -0.030 +/- 0.570 < 1.00 SPW-4004 WATER Jun 1999 Gr. Beta < 1.740 0.470 +/- 1.150 < 3.20 SPW-4004 WATER Jun 1999 Ra-226 < 0.023 0.036 +/- 0.014 < 1.00 SPW-4004 WATER Jun 1999 Ra-228 < 0.990 0.770 +/- 0.551 < 1.00 SPW-4871 WATER Jul 1999 Gr. Alpha < 0.660 -0.420 +/- 0.470 < 1.00 SPW-4871 WATER Jul 1999 Gr. Beta < 1.420 0.400 +/- 1.060 < 3.20 SPW-4871 WATER Jul 1999 Ra-226 < 0.019 0.021 +/- 0.013 < 1.00 SPW-4871 WATER Jul 1999 Ra-228 < 0.620 0.610 +/- 0.360 < 1.00 A4-1
- Table A-4. In-house "blank" samples.
Concentration pCi/La.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activityb (4.66 Sigma)
SPW-4965 WATER Jul1999 H-3 < 176.000 8.100 -t 87.800 < 200.00 SPMI-5349 MILK Jul1999 Sr-89 < 0.410 -0.750 +/- 0.540 < 5.00 SPMI-5349 MILK Jul1999 Sr-90 1.140 t 0.360 < 1.00 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPW-5501 WATER Jul1999 Sr-89 < 0.450 0.150 +/- 0.450 < 5.00 SPW-5501 WATER Jul1999 Sr-90 < 0.580 0.280 +/- 0.310 < 1.00 SPMI-5829 MILK Aug 1999 1-131 < 0.240 0.140 +/- 0.140 < 0.50 SPW-5832 WATER Aug 1999 Gr. Alpha < 0.890 0.570 +/- 0.600 < 1.00 SPW-5832 WATER Aug 1999 Gr. Beta < 2.000 0.590 +/- 1.230 < 3.20 SPW-5832 WATER Aug 1999 Ra-226 < 0.020 0.090 +/- 0.010 < 1.00 SPW-5832 WATER Aug 1999 Ra-228 < 0.780 0.110 +/- 0.370 < 1.00 SPW-6067 WATER Aug 1999 1-131 < 0.250 0.017 +/- 0.170 < 0.50 SPW-6541 WATER Sep 1999 Gr. Alpha < 0.770 0.360 +/- 0.530 < 1.00 SPW-6541 WATER Sep 1999 Gr. Beta < 1.690 0.410 +/- 1.130 < 3.20 SPW-6541 WATER Sep 1999 Ra-226 < 0.020 0.160 +/- 0.020 < 1.00 SPW-6541 WATER Sep 1999 Ra-228 < 1.280 0.018 +/- 0.594 < 1.00 SPW-7467 WATER Oct 1999 Ra-226 0.069 +/- 0.014 < 1.00 SPW-7467 WATER Oct 1999 Ra-228 < 0.892 0.461 +/- 0.467 < 1.00 SPW-7487 WATER Oct 1999 1-131 < 0.260 0.080 +/- 0.150 < 0.50 SPMI-7489 MILK Oct 1999 1-131 < 0.250 0.140 +/- 0.150 < 0.50 SPW-8775 WATER Nov 1999 Ra-226 0.050 +/- 0.012 < 1.00 SPW-8775 WATER Nov 1999 Ra-228 < 0.989 0.380 +/- 0.500 < 1.00 SPW-9721 WATER Nov 1999 H-3 < 158.000 51.400 +/- 80.600 < 200.00 SPW-9719 WATER Dec 1999 Ra-226 0.031 +/- 0.013 < 1.00 a Liquid sample results are reported in pCi/Liter, air filter sample results are in pCi/filter, charcoal sample results are in.pCi/charcoal, and solid sample results are in pCi/kilogram.
b The activity reported is the net activity result.
A4-2 .
Table A-5. In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result E-47, 48 Jan, 1999 Gr. Beta 1.206 +/- 0.056 1.265 +/- 0.061 1.236 +/- 0.041 E-47, 48 Jan, 1999 K-40 1.283 +/- 0.136 1.394 +/- 0.182 1.339 +/- 0.114 SW-68, 69 Jan, 1999 K-40 (FP) 1.300 +/- 0.130 1.300 +/- 0.130 1.300 +/- 0.092 LW-153, 154 Jan, 1999 Gr. Beta 1.509 +/- 0.647 1.619 +/- 0.646 1.564 +/- 0.457 WW-373, 374 Jan, 1999 H-3 171.100 +/- 83.600 131.700 +/- 81.800 151.400 +/- 58.481 SW-867, 868 Jan, 1999 H-3 1,149.300 +/- 122.100 1,225.000 +/- 124.400 1,187.150 +/- 87.155 SWT-425, 426 Jan, 1999 Gr. Beta 2.572 +/- 0.639 2.646 +/- 0.598 2.609 +/- 0.438 CW-450, 451 Jan, 1999 Gr. Beta 0.600 +/- 1.100 0.700 +/- 1.100 0.650 +/- 0.778 SW-570, 571 Feb, 1999 K-40 (FP) 1.730_+/-0.173 1.644 +/- 0.164 1.687 +/- 0.119 LW-614, 615 Feb, 1999 Gr. Alpha 0.354 +/- 0.369 0.666 +/- 0.390 0.510 +/- 0.268 LW-614, 615 Feb, 1999 Gr. Beta 2.213 +/- 0.406 2.613 +/- 0.442 2.413 +/- 0.300 MI-682, 683 Feb, 1999 Co-60 0.200 +/- 0.600 -0.400 +/- 2.700 -0.100+/- 1.383 MI-682, 683 Feb, 1999 Cs-137 0.300 +/- 3.700 0.600 +/- 2.700 0.450 +/- 2.290 MI-682, 683 Feb, 1999 1-131 0.200 +/- 0.300 0.200 +/- 0.300 0.200 +/- 0.212 WW-968, 969 Feb, 1999 H-3 199.300 +/- 89.600 80.900 +/- 84.500 140.100 +/- 61.580 CW-1042, 1043 Feb, 1999 Gr. Beta 3.200 +/- 1.500 3.500 +/- 1.530 3.350 +/- 1.071 LW-1523, 1524 Feb, 1999 Gr. Beta 1.930 +/- 0.567 2.197 +/- 0.584 2.063 +/- 0.407 MI-1627, 1628 Mar, 1999 K-40 1,340.200 +/- 118.000 1,409.300 +/- 112.000 1,374.750 +/- 81.345 WW-1808, 1809 Mar, 1999 H-3 4.400 +/- 83.400 47.400 +/- 85.300 25.900 +/- 59.648 LW-2937, 2938 Mar, 1999 Gr. Beta 3.044 _ 0.663 3.242 +/- 0.660 3.143 +/- 0.468 AP-2155, 2156 Mar, 1999 Be-7 0.078 +/- 0.017 0.073 +/- 0.015 0.075 +/- 0.011 AP-2357, 2358 Mar, 1999 Be-7 0.081 +/- 0.016 0.086 +/- 0.020 0.084 +/- 0.013 AP-1991, 1992 Mar, 1999 Be-7 0.218 +/- 0.079 0.149 +/- 0.062 0.184 +/- 0.050 AP-1991, 1992 Mar, 1999 Be-7 0.083 +/- 0.011 0.082 +/- 0.015 0.083 +/- 0.009 LW-2405, 2406 Mar, 1999 Gr. Beta 3.322 +/- 0.473 2.292 +/- 0.468 2.807 +/- 0.333 LW-2474, 2475 Mar, 1999 Gr. Beta 2.003 +/- 0.592 2.742 +/- 0.648 2.372 +/- 0.439 LW-2474, 2475 Mar, 1999 H-3 124.016 +/- 84.129 151.507+/- 85.318 137.762 +/- 59.910 MI-2019, 2020 Apr, 1999 K-40 1,277.300 +/--173.000 1,377.800 +/- 107.000 1,327.550 +/- 101.708 MI-2019, 2020 Apr, 1999 Sr-90 0.615 +/- 0.366 1.126 +/- 0.368 0.871 +/- 0.260 WW-2040, 2041 Apr, 1999 Gr. Beta 1.424 +/- 0.316 1.233 +/- 0.329 1.329 +/- 0.228 WW-2040, 2041 Apr, 1999 K-40 (FP) 1.100 +/- 0.110 1.100 +/- 0.110 1.100 +/- 0.078 MI-2134, 2135 Apr, 1999 K-40 1,316.000 +/- 147.000 1,485.100 +/- 168.000 1,400.550 +/- 111.617 AP-2658, 2659 Apr, 1999 Be-7 0.134 +/- 0.067 0.175 +/- 0.105 0.154 +/- 0.062 MI-2019, 2020 Apr, 1999 Calcium 0.850 +/-0.085 0.880 +/- 0.088 0.865 +/- 0.061 MI-2251, 2252 Apr, 1999 K-40 1,261.900 +/- 156.000 1,320.800 +/- 141.000 1,291.350 +/- 105.139 A5-1
Table A-5. In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result MI-2451, 2452 Apr, 1999 K-40 1,647.700 +/- 201.000 1,706.300 +/- 159.000 1,677.000 +/- 128.142 SS-2528, 2529 Apr, 1999 Gr. Beta 7.724 +/- 1.978 9.287 +/- 1.970 8.505 +/- 1.396 SS-2528, 2529 Apr, 1999 K-40 7.530 +/- 0.520 8.073 +/- 0.388 7.802 +/- 0.324 SS-2758, 2759 Apr, 1999 Gr. Beta 6.540+/- 2.200 4.960 +/- 2.190 5.750 _ 1.552 SS-2758, 2759 Apr, 1999 K-40 7.483 +/- 0.416 7.357 +/- 0.432 7.420 +/- 0.300 SS-2758, 2759 Apr, 1999 Sr-90 0.006 +/- 0.008 -0.005 +/- 0.007 0.000 +/- 0.005 BS-3093, 3094 Apr, 1999 Gr. Beta 5.180 +/- 1.350 5.960 +/- 1.370 5.570 +/- 0.962 F-3072, 3073 Apr, 1999 K-40 2.991 +/- 0.332 2.438 +/- 0.347 2.714 +/- 0.240 MI-3001, 3002 Apr, 1999 K-40 1,485.800 +/- 142.000 1,564.900 +/- 162.000 1,525.350 +/- 107.713 LW-3149, 3150 Apr, 1999 Gr. Beta 1.982 +/- 0.595 2.120 +/- 0.612 2.051 +/- 0.427 SW-3047, 3048 May, 1999 Gr. Beta 2.281 +/- 0.585 2.194 +/- 0.567 2.238 +/- 0.407 SW-3047, 3048 May, 1999 K-40 (FP) 1.300 +/- 0.130 1.400 +/- 0.140 1.350 +/- 0.096 F-3238, 3239 May, 1999 Gr. Beta 3.329 +/- 0.135 3.388 +/- 0.144 3.358 +/- 0.099 F-3238, 3239 May, 1999 K-40 2.866 +/- 0.366 2.792 +/- 0.337 2.829 +/- 0.249 BS-3195, 3196 May, 1999 K-40 8.610 +/- 0.620 9.320 +/- 0.540 8.965 +/- 0.411 AP-3769, 3770 May, 1999 Be-7 0.135 +/- 0.075 0.188 +/- 0.097 0.161 +/- 0.061 MI-3259, 3260 May, 1999 K-40 1,444.800 +/- 94.200 1,460.300 +/- 166.000 1,452.550 +/- 95.433 AP-3304, 3305 May, 1999 Be-7 0.104 +/- 0.083 0.095 +/- 0.068 0.099 +/- 0.054 G-3461, 3462 May, 1999 Be-7 0.454 +/- 0.210 0.350 +/- 0.154 0.402 +/- 0.130 G-3461, 3462 May, 1999 K-40 5.341 +/- 0.492 4.837+/- 0.619 5.089 +/- 0.395 SW-3217, 3218 May, 1999 Gr. Alpha 1.223 +/- 1.323 2.490 +/- 1.230 1.857 +/- 0.903 SW-3217, 3218 May, 1999 Gr. Beta 4.956 +/- 1.232 5.715 +/- 1.221 5.336 +/- 0.867 LW-2937, 2938 May, 1999 Gr. Beta 2.379 +/- 0.626 2.864 +/- 0.641 2.622 +/- 0.448 SWU-2853, 2854 May, 1999 Gr. Beta 2.860 +/- 0.539 3.065 +/- 0.577 2.962 +/- 0.395 DW-2878, 2879 May, 1999 Gr. Beta 0.706 +/- 0.319 0.849 +/- 0.335 0.777 +/- 0.231 G-3461, 3462 May, 1999 Gr. Beta 5.205 +/- 0.169 5.166 +/-0.110 5.186 +/- 0.101 SO-3482, 3483 May, 1999 Cs-137 0.456 +/- 0.059 0.467 +/- 0.048 0.461 +/- 0.038 SO-3482, 3483 May, 1999 Gr. Beta 24.880 +/- 1.980 26.170 +/- 2.150 25.525 +/- 1.461 SO-3482, 3483 May, 1999 K-40 20.631 +/- 1.240 20.077 +/- 0.906 20.354 +/- 0.768 SO-2832, 2833 May, 1999 Cs-137 0.390 +/- 0.052 0.403 +/- 0.031 0.397 +/- 0.030 SO-2832, 2833 May, 1999 K-40 26.000 +/- 0.660 24.673 +/- 1.240 25.337 +/- 0.702 SWT-3675, 3676 May, 1999 Gr. Beta 2.439 +/- 0.598 2.530 +/- 0.630 2.484 +/- 0.434 LW-3699, 3700 May, 1999 Gr. Beta 2.488 +/- 0.596 3.002 +/- 0.654 2.745 +/- 0.442 MI-3748, 3749 Jun, 1999 K-40 1,553.800 +/- 178.000 1,408.600 +/- 149.000 1,481.200 +/- 116.066 SW-4107, 4108 Jun, 1999 Gr. Alpha 3.993 +/- 0.919 3.606 +/- 0.875 3.800 +/- 0.635 A5-2
Table A-5. In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result SW-4107, 4108 Jun, 1999 Gr. Beta 6.271 + 0.754 6.910 +/- 0.807 6.591 +/- 0.552 SS-4065, 4066 Jun, 1999 K-40 7.350 +/- 0.400 7.945 +/- 0.370 7.648 +/-0.272 AP-3986, 3987 Jun, 1999 Be-7 0.272 +/- 0.147 0.182 +/- 0.085 0.227+/- 0.085 G-4007, 4008 Jun, 1999 Be-7 0.830 +/- 0.210 0.950 +/- 0.200 0.890 +/- 0.145 G-4007, 4008 Jun, 1999 K-40 5.790 +/- 0.460 4.990 +/- 0.400 5.390 +/- 0.305 MI-4172, 4173 Jun, 1999 K-40 1,423.600 +/- 115.000 1,481.300 +/- 129.000 1,452.450 +/- 86.409 MI-4293, 4294 Jun, 1999 K-40 1,397.200 +/- 179.000 1,388.100 +/- 130.000 1,392.650 +/- 110.613 AP-4317, 4318 Jun, 1999 Be-7 0.201 +/- 0.125 0.213 +/- 0.088 0.207 +/- 0.076 AP-4894, 4895 Jun, 1999 Be-7 0.092 +/- 0.019 0.091 +/- 0.014 0.092 +/- 0.012 G-4426, 4427 Jun, 1999 Be-7 0.730 +/- 0.210 0.630 +/- 0.170 0.680 +/- 0.135 G-4426, 4427 Jun, 1999 K-40 3.230 +/- 0.350 3.400 +/- 0.440 3.315 +/- 0.281 AP-4454, 4455 Jun, 1999 Be-7 0.205 +/- 0.120 0.238 +/- 0.087 0.222 +/- 0.074 SWU-4601, 4602 Jun, 1999 Gr. Beta 2.209 +/- 0.568 1.980 +/--t 0.589 2.094 +/- 0.409 SWU-4601, 4602 Jun, 1999 Gr. Beta 2.209 +/- 0.568 1.980 +/- 0.589 2.094 +/-t 0.409 SW-4622, 4623 Jun, 1999 Gr. Beta 2.130 +/- 0.854 2.267 +/- 0.803 2.198 +/- 0.586 AP-4915, 4916 Jun, 1999 Be-7 0.089 +/- 0.012 0.094 +/- 0.015 0.091 +/- 0.010 LW-4974, 4975 Jun, 1999 Gr. Beta 1.916 +/- 0.578 2.617 +/- 0.644 2.267 +/- 0.433 LW-5039, 5040 Jun, 1999 Gr. Beta 2.170 +/- 0.610 2.030 +/- 0.580 2.100 +/- 0.421 LW-5039, 5040 Jun, 1999 H-3 90.659 +/- 81.800 162.800 +/- 85.000 126.730 +/- 58.984 G-4643, 4644 Jul, 1999 Be-7 1.326 +/- 0.460 1.555 +/- 0.390 1.441 +/- 0.302 G-4643, 4644 Jul, 1999 Gr. Beta 5.870 +/- 0.151 5.798 +/- 0.150 5.834 +/- 0.106 G-4643, 4644 Jul, 1999 K-40 5.738 +/- 0.780 6.200 +/- 0.733 5.969 +/- 0.535 SW-4664, 4665 Jul, 1999 Gr. Beta 1.956 +/- 0.415 1.836 +/- 0.429 1.896 +/- 0.298 SW-4664, 4665 Jul, 1999 K-40 1.120 1.120 1.120 WW-4690, 4691 Jul, 1999 Co-60 0.860 +/- 1.840 0.374 +/- 0.344 0.617 +/- 0.936 WW-4690, 4691 Jul, 1999 Cs-137 -0.806 +/- 3.130 -2.010 +/- 2.610 -1.408 +/- 2.038 WW-4690, 4691 Jul, 1999 H-3 399.519 +/- 103.570 564.249 +/-109.428 481.884 +/- 75.335 WW-4808, 4809 Jul, 1999 Co-60 -0.360 +/- 1.910 1.420 +/- 25.700 0.530 +/- 12.885 WW-4808, 4809 Jul, 1999 Cs-137 0.446 t 2.260 -1.060 +/- 1.720 -0.307+/- 1.420 WW-4808, 4809 Jul, 1999 H-3 72.004 +/- 90.621 94.545 +/- 91.551 83.274 +/- 64.409 MI-4742, 4743 Jul, 1999 K-40 1,344.000 +/- 66.000 1,375.000 +/- 112.000 1,359.500 +/- 65.000 CW-5018, 5019 Jul, 1999 H-3 364.162 +/- 92.219 430.163 +/- 94.673 397.163 +/- 66.082 VE-4873, 4874 Jul, 1999 Be-7 2.023 +/- 0.294 1.882 +/- 0.338 1.953 +/- 0.224 VE-4873, 4874 Jul, 1999 K-40 7.894 +/- 0.650 7.394 +/- 0.655 7.644 +/- 0.461 F-5124, 5125 Jul, 1999 K-40 2.394 +/- 0.364 2.802 +/- 0.360 2.598 +/- 0.256 A5-3
Table A-5. In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result VE-5187, 5188 Jul, 1999 K-40 2.990 +/- 0.422 3.265 +/- 0.446 3.128 +/- 0.307 VE-5187, 5188 Jul, 1999 Sr-90 0.005 +/- 0.002 0.002 +/- 0.002 0.004 +/- 0.002 CW-5212, 5213 Jul, 1999 Gr. Beta 2.187+/- 1.449 2.452 +/- 1.381 2.320 +/- 1.001 CW-5212, 5213 Jul, 1999 Gr. Beta -0.405 +/- 1.220 -0.438 +/- 1.196 -0.422 +/- 0.854 MI-5260, 5261 Jul, 1999 K-40 1,367.000 +/- 172.000 1,462.000 +/- 161.000 1,414.500 . 117.797 MI-5287, 5288 Jul, 1999 K-40 1,417.900 +/- 89.000 1,280.700 +/- 163.000 1,349.300 . 92.857 PW-5237, 5238 Jul, 1999 H-3 189.773 +/- 96.797 220.943 +/- 97.971 205.358 +/- 68.862 AP-5329, 5330 Jul, 1999 Be-7 0.168 +/- 0.065 0.140 +/- 0.122 0.154 +/- 0.069 SWU-5379, 5380 Jul, 1999 Gr. Beta 2.571 +/- 0.605 2.219 +/- 0.611 2.395 +/- 0.430 SWU-5379, 5380 Jul, 1999 H-3 484.749 +/- 105.455 520.309 +/- 106.709 502.529 +/- 75.013 G-5354, 5355 Jul, 1999 Be-7 1.120 +/- 0.270 1.030 +/- 0.160 1.075 +/- 0.157 G-5354, 5355 Jul, 1999 K-40 6.160 +/- 0.450 5.990 +/- 0.530 6.075 +/-0.348 MI-5520, 5521 Jul, 1999 Co-60 -1.180 +/- 3.460 -2.330 +/- 2.740 -1.755 +/- 2.207 MI-5520, 5521 Jul, 1999 Cs-137 1.450 +/- 2.200 3.160 +/- 2.660 2.305 +/- 1.726 MI-5520, 5521 Jul, 1999 1-131 0.184 +/- 0.283 0.009 +/- 0.285 0.096 +/- 0.201 AP-5499, 5500 Jul, 1999 Be-7 0.181 +/- 0.070 0.175 +/- 0.066 0.178 +/- 0.048 CW-5550, 5551 Jul, 1999 Gr. Beta 1.858 +/- 1.362 1.361 +/- 1.329 1.609 +/- 0.952 CW-5550, 5551 Jul, 1999 Gr. Beta 1.208 +/-1.334 -0.174 +/- 0.933 0.517 +/- 0.814 WW-5575, 5576 Jul, 1999 H-3 224.412 +/- 93.866 220.812 +/- 93.728 222.612 +/- 66.325 MI-5596, 5597 Jul, 1999 K-40 1,355.200 +/- 157.000 1,370.900 +/- 191.000 1,363.050 +/- 123.622 MI-5644, 5645 Jul, 1999 Calcium 0.830 +/- 0.083 0.840 +/- 0.084 0.835 +/- 0.059 MI-5644, 5645 Jul, 1999 K-40 1,327.000 +/- 141.000 1,488.000 +/- 169.000 1,407.500 +/- 110.048 MI-5644, 5645 Jul, 1999 Sr-90 1.300 +/- 0.350 1.070 +/- 0.350 1.185 +/- 0.247 MI-4742, 4743 Aug, 1999 Sr-90 0.502 +/- 0.243 0.702 +/- 0.303 0.602 +/- 0.194 MI-5666, 5667 Aug, 1999 K-40 1,639.000 +/- 161.000 1,724.800 +/- 207.000 1,681.900 +/- 131.120 WW-5756, 5757 Aug, 1999 Gr. Beta 1.704 +/- 0.568 2.432 +/- 0.567 2.068 +/- 0.401 CW-5712, 5713 Aug, 1999 Gr. Beta 1.906 +/- 1.360 1.608 +/- 1.270 1.757 +/- 0.930 CW-5712, 5713 Aug, 1999 Gr. Beta -0.269 +/- 1.174 -0.634 +/- 1.076 -0.451 +/- 0.796 G-5735, 5736 Aug, 1999 Be-7 2.961 +/- 0.296 3.295 +/- 0.492 3.128 +/- 0.287 G-5735, 5736 Aug, 1999 K-40 6.731 +/- 0.548 6.997 +/- 0.492 6.864 +/- 0.368 LW-8450, 8451 Aug, 1999 Sr-90 0.390 +/- 0.310 0.570 +/- 0.310 0.480 +/- 0.219 SW-5841, 5842 Aug, 1999 Gr. Alpha 2.850 +/- 1.675 2.500 +/- 1.685 2.675 +/- 1.188 SW-5841, 5842 Aug, 1999 Gr. Beta 9.343 +/- 1.425 12.378 +/- 1.634 10.860 +/- 1.084 VE-5905, 5906 Aug, 1999 Co-60 0.013 +/- 0.066 -0.000 +/- 0.002 0.006 +/- 0.033 VE-5905, 5906 Aug, 1999 Cs-137 0.006 +/- 0.008 0.001 +/- 0.009 0.004 +/- 0.006 A5-4
Table A-5. In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result CW-6148, 6149 Aug, 1999 H-3 141.545 +/- 89.443 74.402 +/- 86.675 107.974 +/- 62.275 PW-5968, 5969 Aug, 1999 H-3 1,625.921 + 147.401 1,698.481 +/- 149.269 1,662.201 +/- 104.891 MI-6072, 6073 Aug, 1999 K-40 1,478.600 +/- 163.000 1,675.400 +/- 202.000 1,577.000 +/- 129.782 G-6116, 6117 Aug, 1999 Be-7 4.178 +/- 0.306 4.319 +/- 0.378 4.248 +/- 0.243 G-6116, 6117 Aug, 1999 K-40 5.525 +/- 0.548 5.657 +/- 0.486 5.591 +/- 0.366 AP-6200, 6201 Aug, 1999 K-40 8.465 +/- 0.356 8.822 +/- 0.666 8.643 +/- 0.378 DW-6121, 6122 Aug, 1999 Gr. Beta 1.229 +/- 0.325 1.022 +/- 0.332 1.126 +/- 0.233 SWU-6345, 6346 Aug, 1999 Gr. Beta 2.417_+/- 0.582 1.870 +/- 0.587 2.144 +/- 0.413 MI-6242, 6243 Aug, 1999 Co-60 -1.160 +/- 3.210 -0.075 +/- 0.105 -0.617 +/- 1.606 MI-6242, 6243 Aug, 1999 Cs-137 -0.395 +/- 2.610 0.534 +/- 2.270 0.070 +/- 1.730 MI-6242, 6243 Aug, 1999 1-131 -0.112+/-0.226 0.119 +/- 0.239 0.003 +/- 0.164 VE-6263, 6264 Aug, 1999 Co-60 0.001 +/- 0.002 0.009 +/- 0.027 0.005 +/- 0.013 VE-6263, 6264 Aug, 1999 Cs-137 0.010 +/- 0.010 -0.004 +/- 0.009 0.003 +/- 0.007 SW-6389, 6390 Aug, 1999 K-40 (FP) 13.000 +/- 1.300 12.000 +/- 1.200 12.500 +/- 0.885 SWU-6452, 6453 Aug, 1999 Gr. Beta 2.587 +/- 0.598 2.053 +/- 0.561 2.320 +/- 0.410 WW-6604, 6605 Aug, 1999 Gr. Beta 2.199 +/- 0.578 1.878 +/- 0.594 2.039 +/- 0.414 WW-6677, 6678 Aug, 1999 H-3 202.838 +/- 101.400 122.240 +/- 98.143 162.539 +/- 70.559 WW-6506, 6507 Sep, 1999 Co-60 -0.789 +/- 7.010 0.416 +/- 1.310 -0.187+/- 3.566 WW-6506, 6507 Sep, 1999 Cs-137 0.568 +/- 3.270 0.834 +/- 3.180 0.701 +/- 2.281 WW-6506, 6507 Sep, 1999 H-3 29,273.964 +/- 494.519 30,525.051 +/- 504.610 29,899.507 +/- 353.264 MI-6410, 6411 Sep, 1999 K-40 1,128.500 +/- 159.000 1,355.900 +/- 174.000 1,242.200 +/- 117.853 VE-6431, 6432 Sep, 1999 Gr. Beta 1.880 +/- 0.053 1.917 +/- 0.053 1.899 +/- 0.037 VE-6431, 6432 Sep, 1999 K-40 1.697 +/- 0.202 1.603 +/- 0.192 1.650 +/- 0.139 VE-6558, 6559 Sep, 1999 K-40 2.200 +/- 0.204 2.222 +/- 0.189 2.211 +/- 0.139 AP-6704, 6705 Sep, 1999 Be-7 0.020 +/- 0.055 0.018 +/- 0.081 0.019 +/- 0.049 VE-6649, 6650 Sep, 1999 Co-60 0.008 +/- 0.015 -0.001 +/- 0.004 0.004 +/- 0.008 VE-6649, 6650 Sep, 1999 Cs-137 -0.001 +/- 0.007 -0.001 +/- 0.007 -0.001 +/- 0.005 AP-6727, 6728 Sep, 1999 Be-7 0.109 +/- 0.043 0.158 +/- 0.089 0.134 +/- 0.049 VE-6793, 6794 Sep, 1999 Gr. Beta 1.115 +/- 0.037 1.139 +/- 0.035 1.127 +/- 0.025 SO-6937, 6938 Sep, 1999 Cs-137 0.225 +/- 0.027 0.260 +/- 0.040 0.243 +/- 0.024 SO-6937, 6938 Sep, 1999 K-40 10.450 +/- 0.520 10.428 +/- 0.760 10.439 +/- 0.460 SO-6937, 6938 Sep, 1999 Sr-90 0.041 +/- 0.017 0.034 +/- 0.014 0.038 +/- 0.011 SWU-7045, 7046 Sep, 1999 Gr. Beta 2.623 +/- 0.606 2.720 +/- 0.593 2.672 +/- 0.424 AP-7087, 7088 Sep, 1999 Be-7 0.091 +/- 0.068 0.119 +/- 0.054 0.105 +/- 0.043 PW-7013, 7014 Sep, 1999 H-3 3,002.639 +/- 183.527 3,038.815 +/- 184.318 3,020.727 +/- 130.053 A5-5
Table A-5. In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result SWT-7964, 7965 Sep, 1999 Sr-90 0.826 +/- 0.411 0.501 +/- 0.285 0.664 +/- 0.250 W-7302, 7303 Sep, 1999 H-3 364.860 +/- 109.550 221.740 +/- 104.150 293.300 +/- 75.578 SS-7432, 7433 Sep, 1999 K-40 8.619 . 0.487 8.049 +/- 0.508 8.334 +/- 0.352 AP-7541, 7542 Sep, 1999 Be-7 0.086 . 0.012 0.092 +/- 0.014 0.089 +/- 0.009 AP-7520, 7521 Sep, 1999 Be-7 0.087 +/- 0.012 0.091 +/- 0.011 0.089 +/- 0.008 PW-7228, 7229 Oct, 1999 H-3 6,053.000 +/- 243.000 6,177.000 +/- 245.000 6,115.000 +/- 172.536 SW-7252, 7253 Oct, 1999 H-3 544.000 +/- 116.000 659.000 +/- 120.000 601.500 +/- 83.451 SO-7344, 7345 Oct, 1999 Cs-137 0.067 +/- 0.020 0.066 +/- 0.023 0.067 +/- 0.015 SO-7344, 7345 Oct, 1999 Gr. Beta 27.800 +/- 3.580 26.320 +/- 3.550 27.060 +/- 2.521 SO-7344, 7345 Oct, 1999 K-40 18.510 +/- 0.690 19.680 +/- 0.810 19.095 +/- 0.532 SO-7344, 7345 Oct, 1999 Sr-90 0.020 +/- 0.009 0.014 +/- 0.008 0.017 +/- 0.006 WW-7365, 7366 Oct, 1999 Gr. Beta 1.712 +/- 0.500 1.341 +/- 0.482 1.527 +/- 0.347 WW-7365, 7366 Oct, 1999 K-40 1.200 +/- 0.120 1.100 +/- 0.110 1.150 +/- 0.081 MI-7323, 7324 Oct, 1999 K-40 1,404.100 +/- 111.000 1,374.200 +/- 181.000 1,389.150 +/- 106.163 F-7478, 7479 Oct, 1999 Co-60 0.010 +/- 0.050 0.000 +/- 0.010 0.005 +/- 0.025 F-7478, 7479 Oct, 1999 Cs-137 0.000 +/- 0.010 -0.010 +/- 0.010 -0.005 +/- 0.007 MI-7728, 7729 Oct, 1999 K-40 1,567.700 +/- 170.000 1,471.900 +/- 125.000 1,519.800 +/- 105.505 MI-7587, 7588 Oct, 1999 K-40 1,263.200 +/- 162.000 1,449.800 +/- 122.000 1,356.500 +/- 101.400 AP-7619, 7620 Oct, 1999 Be-7 0.166 +/- 0.071 0.110 +/- 0.090 0.138 +/- 0.057 SL-7749, 7750 Oct, 1999 Gr. Beta 3.088 +/- 0.278 3.320 +/- 0.285 3.204 +/- 0.199 SL-7749, 7750 Oct, 1999 K-40 1.190 +/- 0.560 2.160 +/- 0.500 1.675 +/- 0.375 BS-7943, 7944 Oct, 1999 Gr. Beta 13.816 +/- 2.943 14.263 +/- 2.888 14.040 +/- 2.062 BS-7943, 7944 Oct, 1999 K-40 11.681 +/- 0.551 12.691 +/- 0.754 12.186 +/- 0.467 G-7898, 7899 Oct, 1999 Be-7 1.315 +/- 0.188 1.342 +/- 0.186 1.329 +/- 0.132 G-7898, 7899 Oct, 1999 K-40 6.436 +/- 0.449 6.292 +/- 0.486 6.364 +/- 0.331 CW-8058, 8059 Oct, 1999 Gr. Beta 2.520 +/- 1.490 2.320 +/- 1.490 2.420 +/- 1.054 F-8379, 8380 Oct, 1999 K-40 2.980 +/- 0.240 3.063 +/- 0.262 3.021 +/- 0.178 F-8171, 8172 Oct, 1999 Co-60 -0.010 +/- 0.020 -0.010 +/- 0.010 -0.010 +/- 0.011 F-8171, 8172 Oct, 1999 Cs-137 -0.010 +/- 0.010 0.000 +/- 0.010 -0.005 +/- 0.007 SWU-8316, 8317 Oct, 1999 Gr. Beta 2.310 +/- 0.690 2.248 +/- 0.691 2.279 +/- 0.488 SWU-8316, 8317 Oct, 1999 H-3 187.623 +/- 94.958 223.391 +/- 96.366 205.507 +/- 67.645 SP-8954, 8955 Oct, 1999 Gr. Beta 6.535 +/- 1.721 4.745 +/- 1.412 5.640 +/- 1.113 CW-8425, 8426 Oct, 1999 Gr. Beta 1.720 +/- 1.430 1.510 +/- 1.410 1.615 +/- 1.004 SS-8474, 8475 Oct, 1999 K-40 9.117 +/- 0.719 9.634 +/- 0.542 9.376 +/- 0.450 LW-8747, 8748 Oct, 1999 Gr. Beta 1.984 +/- 0.431 2.120+/- 0.476 2.052 +/- 0.321 A5-6
Table A-5. In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result G-8572, 8573 Oct, 1999 Be-7 3.500
- 0.338 3.410 +/- 0.235 3.455 +/- 0.206 G-8572, 8573 Oct, 1999 Gr. Beta 6.249 +/- 0.167 6.679 +/- 0.171 6.464 +/- 0.120 G-8572, 8573 Oct, 1999 K-40 6.900 +/- 0.518 6.961 +/- 0.374 6.930 +/- 0.319 SW-8506, 8507 Oct, 1999 H-3 5,114.000 +/- 212.000 5,279.000 +/- 215.000 5,196.500 +/- 150.971 LW-8747, 8748 Oct, 1999 H-3 4,144.300 +/- 194.900 4,392.700 +/- 199.513 4,268.500 +/- 139.456 SW-8614, 8615 Nov, 1999 Gr. Beta 3.884 +/- 0.886 3.386 +/- 0.836 3.635 +/- 0.609 CW-8641, 8642 Nov, 1999 Gr. Beta 1.310 +/- 1.400 2.250 +/- 1.470 1.780 +/- 1.015 AP-8688, 8689 Nov, 1999 Be-7 0.153 +/- 0.083 0.144 +/- 0.058 0.149 +/- 0.051 SW-8975, 8976 Nov, 1999 H-3 -70.000 + 85.000 -68.000 +/- 85.000 -69.000 +/- 60.104 MI-8928, 8929 Nov, 1999 K-40 1,328.300 +/- 144.000 1,366.000 +/- 163.000 1,347.150 +/- 108.749 AP-9179, 9180 Nov, 1999 Be-7 0.145 t 0.097 0.103 +/- 0.055 0.124 +/- 0.056 SW-9151, 9152 Nov, 1999 H-3 3,208.000 +/- 174.000 3,517.000 +/- 180.000 3,362.500 +/- 125.176 SW-9227, 9228 Nov, 1999 Co-60 -1.320 +/- 12.400 0.120 t 0.330 -0.600 +/- 6.202 SW-9227, 9228 Nov, 1999 Cs-137 0.060 +/- 2.330 -0.530 +/- 1.660 -0,235 +/- 1.430 SW-9227, 9228 Nov, 1999 Gr. Beta 8.590 +/- 1.880 9.810 +/- 1.980 9.200 +/- 1.365 SWU-9275, 9276 Nov, 1999 Gr. Beta 1.590 . 0.586 1.404 +/- 0.529 1.497 +/- 0.395 CW-9307, 9308 Dec, 1999 Gr. Beta 0.700 +/- 1.500 2.050 +/- 1.630 1.375 +/- 1.108 CW-9358, 9359 Dec, 1999 Gr. Beta 3.610 +/- 0.460 4.210 +/- 0.510 3.910 +/- 0.343 CW-9358, 9359 Dec, 1999 H-3 14,646.000 +/- 339.000 14,764.000 +/- 340.000 14,705.000 +/- 240.063 MI-9402, 9403 Dec, 1999 K-40 2,074.100 +/- 174.000 1,967.700 +/- 134.000 2,020.900 +/- 109.809 CW-9423, 9424 Dec, 1999 Gr. Beta 1.870 +/- 1.610 1.930 +/- 1.610 1.900 +/- 1.138 AP-9478, 9479 Dec, 1999 Be-7 0.156 +/- 0.098 0.091 +/- 0.058 0.123 +/- 0.057 BS-9587, 9588 Dec, 1999 K-40 11.890 +/- 0.550 11.624 +/- 0.740 11.757 +/- 0.461 LW-9525, 9526 Dec, 1999 Be-7 2.690 +/- 0.630 2.340 +/- 0.620 2.515 +/- 0.442 AP-9767, 9768 Dec, 1999 Be-7 0.104 +/- 0.072 0.144 +/- 0.085 0.124 +/- 0.056 SWU-9837, 9838 Dec, 1999 Gr. Beta 1.530 +/- 0.530 2.504 +/- 0.607 2.017 +/- 0.403 CW-9870, 9871 Dec, 1999 H-3 1,221.000 +/- 123.000 1,027.000 +/- 117.000 1,124.000 +/- 84.879 SW-9964, 9965 Dec, 1999 Co-60 -0.740 +/- 2.710 0.950 +/- 2.110 0.105 +/- 1.717 SW-9964, 9965 Dec, 1999 Cs-137 -2.910 +/- 3.140 1.830 +/- 2.230 -0.540 +/- 1.926 AP-10027, 10028 Dec, 1999 Be-7 0.059 +/- 0.008 0.064 +/- 0.011 0.062 +/- 0.007 SW-9912, 9913 Dec, 1999 H-3 29.000 +/- 87.000 113.000 +/- 91.000 71.000 +/- 62.948 WW-10069, 10070 Dec, 1999 Gr. Beta 2.539 +/- 0.664 2.223 +/- 0.591 2.381 +/- 0.445
' All concentrations are reported in pCi/liter, except solid samples, which are reported in pCi/gram.
b Lab codes are comprised of the sample media and the sample numbers. Client codes have been eliminated to protect client anonymity.
A5-7
Table A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP),
comparison of MAPEP and Teledyne's Midwest Laboratory results for various sample media'.
Concentrationb Lab Sample Date MAPEP Resultd Control Code Type Collected Analysis Teledyne Result' 1s, N=1 Limits SPW-846 WATER Jan, 1999 Co-57 337.60+/- 33.76 358.00 250.60 - 465.40 SPW-846 WATER Jan, 1999 Cs-137 656.60 +/- 65.66 637.00 445.90 - 828.10 SPW-846 WATER Jan, 1999 Fe-55 724.50 +/- 72.45 664.00 464.80 - 863.20 SPW-846 WATER Jan, 1999 Mn-54 234.20 +/- 23.42 229.00 160.30 - 297.70 SPW-846 WATER Jan, 1999 Pu-238 1.10 +/- 0.11 1.45 1.02 - 1.89 SPW-846 WATER Jan, 1999 Pu-239/40 3.20 +/- 0.32 4.04 2.83 - 5.25 SPW-846 WATER Jan, 1999 Sr-90 40.90 +/- 4.09 39.50 27.65 - 51.35 SPW-846 WATER Jan, 1999 U-233/4 2.70 +/- 0.27 2.67 1.87 - 3.47 SPW-846 WATER Jan, 1999 U-238 20.80 +/- 2.08 21.20 14.84 - 27.56 SPW-846 WATER Jan, 1999 Zn-65 1,508.90 +/- 150.90 1,560.00 1,092.00 - 2,028.00 STSO-854 SOIL Jan, 1999 Am-241 6.16 +/- 0.70 6.55 4.59 - 8.52 STSO-854 SOIL Jan, 1999 Co-57 311.11 +/- 3.60 360.00 252.00 - 468.00 STSO-854 SOIL Jan, 1999 Co-60 134.57+/- 2.15 131.00 91.70 - 170.30 STSO-854 SOIL Jan, 1999 Cs-134 682.35 +/- 4.50 752.00 526.40 - 977.60 STSO-854 SOIL Jan, 1999 Cs-137 319.50 +/- 3.60 331.00 231.70 - 430.30 STSO-854 SOIL Jan, 1999 K-40 667.04 +/- 21.50 652.00 456.40 - 847.60 STSO-854 SOIL Jan, 1999 Mn-54 349.01 +/- 7.00 345.00 241.50 - 448.50 STSO-854 SOIL Jan, 1999 Pu-238 25.28 +/- 1.00 27.50 19.25 - 35.75 STSO-854 SOIL Jan, 1999 Pu-239/40 45.66 +/- 1.00 48.10 33.67 - 62.53 STSO-854 SOIL Jan, 1999 U-233/4 139.56 +/- 1.80 157.00 109.90 - 204.10 STSO-854 SOIL Jan, 1999 U-238 23.47 +/- 0.75 40.70 28.49 - 52.91 The analysis was repeated. Result of reanalysis; 29.5+/-6.3 Bq/kg.
STSO-854 SOIL Jan, 1999 Zn-65 2,697.20 +/- 25.00 2,840.00 1,988.00 - 3,692.00 a Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.
b All results are in Bq/kg or Bq/L as requested by the Department of Energy.
Unless otherwise indicated, the TBEESML results are given as the mean +/- 1 standard deviations for three determinations.
d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
A6-1
Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),
comparison of EML and Teledyne's Midwest Laboratory results for various sample mediaa.
b Concentration Lab Sample Date Control Code Type Collected Analysis Teledyne Resultc EML Resultd Limitse STAF-848 AIR FILTER Mar, 1999 Gr. Alpha 1.24 +/- 0.03 1.61 +/- 0.16 0.60- 1.64 STAF-848 AIR FILTER Mar, 1999 Gr. Beta 1.98 +/- 0.04 1.56 +/- 0.16 0.60- 1.64 STW-850 WATER Mar, 1999 Am-241 1.22 +/- 0.16 1.15 +/- 0.05 0.73- 2.58 STW-850 WATER Mar, 1999 Co-60 54.40 +/- 2.00 51.10 +/- 3.00 0.92- 1.18 STW-850 WATER Mar, 1999 Cs-137 43.50 +/- 2.00 39.38 +/- 2.41 0.90- 1.28 STW-850 WATER Mar, 1999 Fe-55 81.50 +/- 19.50 97.40 +/- 1.65 0.31 - 1.54 STW-850 WATER Mar, 1999 Gr. Alpha 1,169.00 +/- 37.00 1,090.00 +/- 20.00 0.50- 1.29 STW-850 WATER Mar, 1999 Gr. Beta 1,274.60 +/- 33.30 1,100.00 +/- 40.00 0.50- 1.29 STW-850 WATER Mar, 1999 H-3 90.30 +/- 24.80 121.08 +/- 6.78 0.65- 1.91 STW-850 WATER Mar, 1999 Ni-63 125.80 +/- 6.30 114.00 +/- 10.00 0.50- 1.50 STW-850 WATER Mar, 1999 Pu-238 0.80 +/- 0.01 0.77 +/- 0.04 0.78- 1.42 STW-850 WATER Mar, 1999 Pu-239/40 1.03 +/- 0.07 1.01 +/- 0.06 0.78- 1.42 STW-850 WATER Mar, 1999 Sr-90 3.63+/- 1.20 4.10 +/- 0.05 0.50- 1.50 STW-850 WATER Mar, 1999 U-233/4 0.33 +/- 0.08 0.27 +/- 0.02 0.77- 1.35 STW-850 WATER Mar, 1999 U-238 0.33 +/- 0.08 0.26 +/- 0.02 0.77- 1.35 STVE-851 VEGETATION Mar, 1999 Am-241 3.35 +/- 0.85 3.52 +/- 0.59 0.68 - 2.78 STVE-851 VEGETATION Mar, 1999 Cm-244 0.56 +/- 0.41 1.67 +/- 0.54 0.49- 1.69 STVE-851 VEGETATION Mar, 1999 Co-60 21.00 +/- 1.90 21.45 +/- 1.00 0.62- 1.42 STVE-851 VEGETATION Mar, 1999 Cs-137 453.90 +/- 5.70 467.00 +/- 20.00 0.81 - 1.45 STVE-851 VEGETATION Mar, 1999 K-40 667.60 +/- 33.70 656.50 +/- 20.00 0.79- 1.50 STVE-851 VEGETATION Mar, 1999 Sr-90 704.80 +/- 27.80 736.10 +/- 7.70 0.48- 1.29 STSO-852 SOIL Mar, 1999 Ac-228 45.10 +/- 7.40 47.15 +/- 2.99 0.50- 1.50 STSO-852 SOIL Mar, 1999 Am-241 5.65 +/- 2.41 4.89 +/- 0.97 0.52- 2.65 STSO-852 SOIL Mar, 1999 Bi-214 67.30 +/- 3.30 69.90 +/- 5.66 0.50- 1.50 STSO-852 SOIL Mar, 1999 Cs-137 620.50 +/- 5.90 659.50 +/- 24.95 0.80- 1.34 STSO-852 SOIL Mar, 1999 K-40 355.70 +/- 24.60 362.75 +/- 20.16 0.73- 1.67 STSO-852 SOIL Mar, 1999 Pb-212 47.90 +/- 3.00 47.93 +/- 2.57 0.50- 1.50 STSO-852 SOIL Mar, 1999 Pb-214 70.10 +/- 4.80 71.00 +/- 7.04 0.50- 1.50 STSO-852 SOIL Mar, 1999 Pu-239/40 7.32 +/- 1.32 8.11 +/- 1.07 0.66- 1.93 STSO-852 SOIL Mar, 1999 Sr-90 28.30 +/- 3.50 32.40 +/- 0.53 0.46- 2.84 STSO-852 SOIL Mar, 1999 Th-234 227.40 +/- 35.20 138.00 +/- 4.08 0.50- 2.00 STSO-852 SOIL Mar, 1999 U-233/4 132.90 +/- 6.90 140.67 +/- 1.16 0.35- 1.55 STSO-852 SOIL Mar, 1999 U-238 139.40 +/- 7.00 145.00 +/- 1.73 0.35- 1.55 STAF-853 AIR FILTER Mar, 1999 Am-241 0.14 +/- 0.02 0.13 +/- 0.01 0.68- 2.41 STAF-853 AIR FILTER Mar, 1999 Co-57 3.32 +/- 0.06 3.01 +/- 0.14 0.62- 1.22 STAF-853 AIR FILTER Mar, 1999 Co-60 5.28 +/- 0.15 4.96 +/- 0.28 0.62- 1.42 STAF-853 AIR FILTER Mar, 1999 Cs-137 6.96 +/- 0.15 6.05 +/- 0.30 0.72- 1.32 STAF-853 AIR FILTER Mar, 1999 Pu-238 0.26 +/- 0.02 0.27 +/- 0.00 0.62- 1.46 A7-1
Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),
comparison of EML and Teledyne's Midwest Laboratory results for various sample mediaa.
b Concentration Lab Sample Date Control Code Type Collected Analysis Teledyne Resultc EML Resultd Limitse STA F-853 AIR FILTER Mar, 1999 Pu-239/40 0.12 +/- 0.02 0.12 +/- 0.00 0.62- 1.46 STA F-853 AIR FILTER Mar, 1999 Sb-125 4.35 +/- 0.30 3.59 +/- 0.31 0.62- 1.39 STA F-853 AIR FILTER Mar, 1999 Sr-90 0.65 +/- 0.19 0.64 +/- 0.01 0.66- 2.65 STA F-853 AIR FILTER Mar, 1999 U-233/4 0.07+/- 0.03 0.06 +/- 0.00 0.78 - 3.00 STA F-853 AIR FILTER Mar, 1999 U-238 0.07 +/- 0.03 0.06 +/- 0.00 0.78 - 3.00 STW -855 WATER Sep, 1999 Am-241 1.13 +/- 0.24 0.85 +/- 0.10 0.75- 1.49 STW -855 WATER Sep, 1999 Co-60 54.10 +/- 1.10 52.40 +/- 2.20 0.80- 1.20 STW r-855 WATER Sep, 1999 Cs-137 77.10 +/- 1.40 76.00 +/- 3.40 0.80- 1.26 STW -855 WATER Sep, 1999 Fe-55 48.60 +/- 6.80 53.00 +/- 2.00 0.44- 1.53 1-855 WATER Sep, 1999 H-3 136.00 +/- 25.00 80.70 +/- 3.70 STW 0.71- 1.79 STW'-855 WATER Sep, 1999 Pu-238 0.78 +/- 0.05 0.79 +/- 0.08 0.78- 1.25 STW'-855 WATER Sep, 1999 Pu-239/40 0.84 +/- 0.07 0.87 +/- 0.10 0.80- 1.39 STW'-855 WATER Sep, 1999 Sr-90 2.20 +/- 1.00 1.72 +/- 1.00 0.75- 1.50 STW'-855 WATER Sep, 1999 U-233/4 0.50 +/- 0.09 0.37 +/- 0.02 0.80- 1.40 STW'-855 WATER Sep, 1999. U-233/4 0.50 +/- 0.09 0.37 +/- 0.02 0.83- 1.92 STW'-855 WATER Sep, 1999 U-238 0.46 +/- 0.09 0.36 +/- 0.02 0.80- 1.26 Increasing the sample counting time achieved acceptable results (0.42_+/-0.07 Bq/L).
STW-856 WATER Sep, 1999 Gr. Alpha 1,543.00 __44.00 1,580.00 +/- 20.00 .0.61 - 1.32 STW-856 WATER Sep, 1999 Gr. Beta 1,053.00 +/- 31.00 740.00 +/- 40.00 0.55- 1.54 STSO-857 SOIL Sep, 1999 Ac-228 127.30 +/- 7.50 124.00 +/- 4.80 0.79- 1.75 STSO-857 SOIL Sep, 1999 Bi-212 107.40 +/- 2.60 140.00 +/- 14.00 0.42- 1.22 STSO-857 SOIL Sep, 1999 Bi-214 90.10 +/- 4.20 69.50 +/- 1.80 0.75- 1.42 STSO-857 SOIL Sep, 1999 Cs-137 195.90 +/- 4.00 204.00 +/- 5.00 0.83- 1.32 STSO-857 SOIL Sep, 1999 K-40 744.70 +/- 37.70 780.00 +/- 27.00 0.78- 1.53 STSO-857 SOIL Sep, 1999 Pb-212 123.40 +/- 3.70 127.00 +/- 4.80 0.74- 1.33 STSO-857 SOIL Sep, 1999 Pb-214 96.50 +/- 5.00 72.00 +/- 0.42 0.65- 1.45 STSO-857 SOIL Sep, 1999 Sr-90 12.99 +/- 1.44 13.00 +/- 0.47 0.60- 3.66 STSO-857 SOIL Sep, 1999 Th-234 298.70 +/- 24.60 198.00 +/- 5.60 0.59- 1.85 STSO-857 SOIL Sep, 1999 U-233/4 184.40 +/- 8.50 190.00 +/- 5.20 0.47- 1.30 STSO-857 SOIL Sep, 1999 U-238 184.80 +/- 8.50 190.00 +/- 5.20 0.47- 1.30 STVE-858 VEGETATION Sep, 1999 Am-241 3.30 +/- 0.88 2.88 +/- 0.22 0.68- 2.70 STVE-858 VEGETATION Sep, 1999 Cm-244 2.12 +/- 0.86 1.61 +/- 0.36 0.47- 1.74 STVE-858 VEGETATION Sep, 1999 Co-60 17.60 +/- 1.90 17.60 +/- 1.00 0.69- 1.46 STVE-858 VEGETATION Sep, 1999 Cs-137 414.60 +/- 5.70 440.00 +/- 20.00 0.80- 1.40 STVE-858 VEGETATION Sep, 1999 K-40 502.80 +/- 34.70 513.00 +/- 20.00 0.79- 1.42 STVE-858 VEGETATION Sep, 1999 Pu-239/40 4.13+/- 1.00 4.30 +/- 0.46 0.68- 1.59 STAP-859 AIR FILTER Sep, 1999 Am-241 0.14 +/- 0.05 0.13 +/- 0.01 0.73 - 2.58 STAP-859 AIR FILTER Sep, 1999 Co-57 8.10 +/- 0.10 7.73 +/- 0.03 0.65- 1.39 A7-2
Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),
comparison of EML and Teledyne's Midwest Laboratory results for various sample mediaa.
Concentration b Lab Sample Date Control Code Type Collected Analysis Teledyne Result' EML Resulta Limitse STAP-859 AIR FILTER Sep, 1999 Co-60 6.70 +/- 0.10 6.35 +/- 0.41 0.75 - 1.32 STAP-859 AIR FILTER Sep, 1999 Cs-137 7.10 +/- 0.20 6.43 +/- 0.42 0.73 - 1.37 STAP-859 AIR FILTER Sep, 1999 Mn-54 8.80 +/- 0.20 7.91 +/- 0.45 0.76 - 1.42 STAP-859 AIR FILTER Sep, 1999 Pu-238 0.05 +/- 0.04 0.10 +/-0.01 0.74- 1.40 STAP-859 AIR FILTER Sep, 1999 Pu-239/40 0.07+/- 0.02 0.14 +/- 0.01 0.76 - 1.44 Insufficient sample volume (15 ml.) for accurate plutonium analyses.
STAP-859 AIR FILTER Sep, 1999 Ru-106 5.90 +/- 0.80 5.50 +/- 1.76 0.59 - 1.30 STAP-859 AIR FILTER Sep, 1999 Sr-90 0.60+/-0.20 0.34 +/-0.01 0.61 - 1.93 STAP-859 AIR FILTER Sep, 1999 U-233/4 0.09 +/- 0.03 0.07 +/- 0.00 0.83 - 1.92 STAP-859 AIR FILTER Sep, 1999 U-238 0.07 +/- 0.03 0.07_+/- 0.01 0.84 - 2.61 STAP-860 AIR FILTER Sep, 1999 Gr. Alpha 3.18 +/- 0.06 2.77 +/- 0.26 0.50 - 1.55 STAP-860 AIR FILTER Sep, 1999 Gr. Beta 3.65 +/- 0.06 2.66 +/- 0.26 0.72 - 1.67 a The Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soil, Vegetation and Water.
b Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.
'Teledyne results are reported as the mean of three determinations+/-standard deviation.
d The EML result listed is the mean of replicate determinations for each nuclide+/-the standard error of the mean.
SThe control limits are reported by EML as the ratio of Reported Value / EML value and are established from percentiles of historic data distributions (1982-1992). The evaluation of this historic data and the development of the control limits is presented in DOE report EML-564.
A7-3
APPENDIX B DATA REPORTING CONVENTIONS B-I
Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows: x+/- s where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xi +/- sl and x2 - s2 Reported result: x +/- s; where x= (1/2) (xI + x2) and s = (1/2) s2 + 2 3.2. Individual results: <Li , <L2 Reported result: <L, where L = lower of LI and L2 3.3. Individual results: x+/--s, <L Reported result: x +/- s if x> L; <L otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x 1 , x2 ... xn are defined as follows:
n xx n-I 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45.
B-2
APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1
Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.
Air (pCi/m 3 ) Water (pCi/L)
Gross alpha 1 x 10-3 Strontium-89 8,000 Gross beta I Strontium-90 500 Iodine-131b 2.8 x 10-1 Cesium-137 1,000 Barium-140 8,000 Iodine-131 1,000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium 1 x 106 a Taken from Table II of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
C-2
APPENDIX D Special Ground and Well Water Samples D-1
1.0 INTRODUCTION
This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Regulatory Commission summarizes and interprets results of the special well and seepage water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 1999. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.
Tabulations of the special sampling program individual analyses made during the year are included in this appendix. A summary table of tritium analyses is also included in this appendix.
D-2
2.0
SUMMARY
This special sampling program was established following the detection of tritium in a residence well water sample south of the PINGP during 1989. This program is described and the results for 1999 are summarized and discussed.
The program findings for 1999 detected tritium in nearby residence wells and ground water seepage samples at expected natural background levels. The 1999 sample results ranged from
<19 pCi/L to 147 pCi/L. These results are far below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to any members of the public.
The special sampling program was terminated as of December, 1999, based on findings of the USGS Water Resources Investigation Report 99-4069. The report concludes that the level of ground water tritium measured south of the plant's property is most likely the result of past nuclear device testing and naturally-produced tritium from precipitation.
The nearest residence well south of the PINGP will be added to the regular well water sampling and incorporated into the Radiological Environmental Monitoring Program (REMP).
D-3
3.0 Special Tritium Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program was to assess the impact of any tritium possibly leaching into the environment (ground water system) from the PINGP discharge canal. For this purpose, special water samples were collected and analyzed for radioactive content.
3.2 Program Description The sampling and analysis schedule for the special water sampling program is summarized in Table 4.1 and briefly reviewed below. Table 4.2 defines the additional sample locations and codes for the special water sampling program.
Special well and ground water samples were collected semi-annually at nine locations:
one sample from the PINGP Environmental Laboratory (P-30); one from the nearest residence deep well (P-24d, Suter residence); two ground water seepages from near Birch Lake (P-31 and P-32); well water from the Prairie Island Training Center (P-26); well water from the Prairie Island Indian Community (P-8); and three other nearby residences (P-27, Nauer residence; P-28, Allyn (Perkins) residence; P-29, Childs residence). The Rohl farm well (part of the quarterly REMP sampling) is used as a control location for these special samples.
In order to detect low levels of tritium at or below natural background levels, analyses of the samples have been contracted to a laboratory (University of Waterloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. Waterloo Laboratories report tritium analyses results in Tritium Units (1 TU = 3.2 pCi/L). The tritium results in this report are indicated in pCi/L.
3.3 Program Execution The special water sampling was executed as described in the preceding section.
3.4 Program Modifications There were no changes to the program in 1999.
3.5 Results and Discussion Results obtained show tritium in well water and ground water samples at expected background levels. Table 4.4 provides the complete data table of results for each period and sampling location.
Tritium levels have decreased yearly from 1989 through 1995, and since 1996 have measured at or below expected background levels. Averages for the nearest resident south of the plant measured: 1430 pCi/L in 1989, 1360 pCi/L in 1990, 960 pCi/L in 1991, 835 pCi/L in 1992, 516 pCi/L in 1993, 370 pCi/L in 1994, 170 pCi/L in 1995, 64 pCi/L in 1996, 61 pCi/L in 1997, <19 pCi/L in 1998 and 76 pCi/L in 1999.
The 1999 levels fall within the range of expected background tritium levels for shallow ground water and surface water due to tritium concentrations measured in precipitation.
D-4
Results and Discussion (continued)
The USGS 1999 Water Study Report (Water Resources Investigations Report 99-4069, "Water Resources of the Prairie Island Indian Reservation, Minnesota, 1994-97", USGS, 1999) concluded that tritium in precipitation, both natural and from nuclear device testing, most reasonably explains the tritium in the off-site samples. At its peak in 1964, the tritium concentration in precipitation in southeastern Minnesota was 14,400 pCi/L.
The water in the Mississippi River most likely provided this source of tritium into the local aquifer.
D-5
Table D-4.1 Sample collection and analysis program for special well and seepage water samples, Prairie Island Nuclear Generating Plant, 1999.
Medium No. Location codes Collection type Analysis typec and typea and frequencyb Well water 8 P-24d, P-25 (C), G/SA H-3 semi-annual P-26, P-27, P-28, P-29, P-30, P-8 Ground water 2 P-31, P-32 G/SA H-3 a Location codes are defined in table D-4.2. Control Station are indicated by (C). All other stations are indicators.
b Collection type is codes as follows: C/ = continuous; G/ = grab. Collection frequency is coded as follows: W = weekly; M = monthly; Q = quarterly; SA = semi-annually; A
= annually; X = no specified frequency or one time.
c Analysis type is coded as follows: GB = gross beta; GS = gamma spectroscopy; H-3 =
D-6
Table D-4.2. Sampling locations for special well and seepage water samples, Prairie Island Nuclear Generating Plant, 1999.
Code typea Collection site Type of sampleb Distance direction and from reactor P-24d Suter residence, deep well WW 0.6 mi. @ 158 0/SSE P-25 C Rohl farm WW 12.9 mi @ 352 0 /N P-26 PITC WW 0.4 mi. @ 258°/WSW P-27 Nauer residence WW 0.9 mi. @ 154 0 /SSE P-28 Allyn (Perkins) WW 1.0 mi. @ 152°/SSE residence P-29 Childs residence WW 1.2 mi. @ 149 0 /SSE P-30 PINGP Environmental Laboratory WW 0.2 mi. @ 32 0/NNE P-31 Birch Lake Seepage #1 GW 0.7 mi. @ 179°/S P-32 Birch Lake Seepage #2 GW 0.8 mi. @ 169°/SSE P-8 Prairie Island Indian Community Well WW 1.0 mi. @ 321 0/WNW a "C" denotes control location. All other locations are indicators.
b Sample codes: WW = Well water; GW = Ground Water.
D-7
Table D-4.3 Radiation Environmental Monitoring Program Summary: Special well and seepage water samples.
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January - December 1999 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Semi-Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Range Resultse Well Water H-3 15 19 102 (9/13) P-29, 145 (2/2) 76 (2/2) 0 (pCi/L) (64-147) Childs well, (144-147) (74-77) 1.2 mi. @ 149 0 /SSE Ground Water H-3 4 19 122 (2/2) P-32, Birch Lake 128 (1/1) 76 (2/2) 0 (pCi/L) (115-128) Seepage #2, (74-77) 0.8 mi. @ 169°/SSE a H-3 = tritium b LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and code (Table 2) and (2) by distance, direction and sector relative to reactor site.
e Non-routine results are those which exceed ten times the control station value.
D-8
Table D-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 1999.
SAMPLE DATES MAY, JUNE OCT.
1999 1999 SAMPLE LOCATIONS pCi/L I pCi/L Suter residence 77 74 Rohl Farm (Control) 77 74 PITC 102 93 Nauer residence 64 -
Allyn (Perkin) residence 138 77 Childs residence 147 144 Environmental Lab <19 <19 Birch Lake Seepage #1 -- 115 Birch Lake Seepage #2 -- 128 Prairie Island Indian Community Well <19 <19 D-9
APPENDIX E Sampling Location Maps E-1
- TLD LOCATIONS ONE MILE RADIUS E
J PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS]
(NO SCALE]
MONITORING LEGEND:
0 N.S.P. TLO POINTS F,-2 TLDOl.DGN E-2 TLD01 .DGN
TLO LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGENO:
0 N.S.P. TL0 POINTS F-3 TLOO2.OON E-3 TL002.DON
TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
0 N.S.P. TLD POINTS E-4 TLD03.DGN
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS E
PLANT AREA ENLARGED PLAN (1.00 MILE RADIUS)
(NO SCALE)
MONITORING LEGEND
<* MILK SAMPLING POINT 10 NUMBERS P-14. P-18. P-25. P-37. P-39 0 FISH SAMPLING POINT ID NUMBERS P-13, P-19 A AIR SAMPLING POINT I1 NUMBERS INVERTEBRATES POINT 10 NUMBERS P-6. P-40 P-I. P-2, P-3. P-4. P-6 O WATER SAMPLING POINT 10 NUMBERS SEDIMENT SAMPLING POINT ID NUMBERS P-6. P-12. P-20 P-5. P-6. P-8. P-9. P-11. P-25 0 [a VEGETATION /
P-24. P-38 VEGETABLES 10 NUMBERS E-5 SAMP01.DGN a,
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND MILK SAMPLING POINT I0 NUMBERS FISH SAMPLING POINT 10 NUMBERS P-14. P-18. P-25, P-37. P-3q P-13. P-li AIR SAMPLING POINT 10 NUMBERS 1 INVERTEBRATES POINT 10 NUMBERS P-I. P-2. P-3. P-4. P-6 P-6. P-40
(>WATER SAMPLING POINT 10 NUMBERS P-5. P-S. P-B. P-1. P-I1. P-25 O SEOIMENTSAMPLING POINT 10 NUMBERS P-G. P-12. P-20 13 El VEGETATION P-24. P-38
/ VEGETABLES I1 NUMBERS F-6 SAMPO3.DGN E-6 SAMP03.DGN
ENVIRONMENTAL SAMPLING POINTS P-25 O4 Rohi Farm (P-25)W10630 St. Rd. 29, River Falls, WI., Huppert Farm (P-41) W10430 St. Rd. 29, River Falls, WI.
a Cain reidence, N7395 950th St., River Falls, WI.
CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND
<>Milk Sampling Point ID Numbers P-14, P-18, P-25, P-37, P-39, P-41 A Air Sampling Point ID Numbers P-I, P-2, P-3, P4, P-6 Water Sampling Point Numbers S P-5, P-6, P-8, P-9, P-11, P-25, P-41 Vegetation/Vegetables IDNumbers 0 P-24, P-38 F.-? SAMPO2.DGN E-7 SAMP02.DGN