ML011380003
| ML011380003 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/15/2001 |
| From: | Sorensen J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| +sunsi/sispmjr=200603, -RFPFR | |
| Download: ML011380003 (68) | |
Text
Committed to Nuclear Excellence~r" Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East
- Welch MN 55089 May 15, 2001 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 50-306 DPR-60 72-10 SNM-2506 2000 Annual Radiological Environmental Monitoring 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 1, 2000 through December 31, 2000.
Please contact us if you have any questions related to the information we have provided.
J T'oel P. Sorensen Site Vice President Prairie Island Nuclear Generating Plant c:
Regional Administrator, III, NRC Region III Attn: Dr. John House NRC Project Manager Director of NMSS Sr. Resident Inspector, NRC State of Minnesota Attn: Tim Donakowski J. Silberg
Attachment:
Annual report to the United States Nuclear Regulatory Commission, Radiation Environmental Monitoring Program, January 1, 2000 through December 31, 2000.
Environmental, Inc.
Midwest Laboratory 11" an Alleheny Technologies Co.
700 Landwehr Road -Noffý IL 60062-2310 ph. (847) 564-0700 fax (847) 564-4517 XCEL ENERGY CORPORATION 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, 2000 Prepared under Contract by ENVIRONMENTAL, Inc.
MIDWEST LABORATORY Project No. 8010 Approved:
3b, M.S.
Manager Oec.-7ýjoe
PREFACE The staff of Environmental, Inc., 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, operated by Nuclear Management Company, LLC for Xcel Energy Corporation. The report was prepared by Environmental, Inc., Midwest Laboratory.
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TABLE OF CONTENTS Section Page 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 Atmospheric Nuclear Detonations and Nuclear Accidents........................................ 7 4.2 Summ ary of Preoperational Data..............................................................................
7 4.3 Program Findings.................................................................................................
8 5.0 FIGURES AND TABLES.....................................................................................................
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6.0 REFERENCES
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
Sampling Location M aps..............................................................................................
D-1 iii
LIST OF TABLES No.
Title Page 5.1 Sample Collection and Analysis Program............................................................................
13 5.2 Sampling Locations................................................................................................................
14 5.3 Missed Collections and Analyses........................................................................................
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-i 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 iv
LIST OF FIGURES No.
Title Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control, 1985-2000...................................................................................
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), 1985-2000........................................
19 v
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January December, 2000. 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 (Environmental, Inc., Midwest Laboratory, 2001b) available at Prairie Island Nuclear Generating Plant.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. 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 2000 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 arise from activation 3
3.1 Program Design and Data Interpretation (continued) 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, 2000).
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-l), 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 EIML 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 two locations, one 4
3.2 Program Description (continued) 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.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1)
No air particulate/air iodine samples were available from location P-3 for the week ending 06-14-00, due to sampler pump failure.
(2)
TLD data was not available from location P-10B for the fourth quarter, 2000.
Both the regular and emergency TLDs were lost in the field, due to unusually deep snow.
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 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 Environmental, Inc. 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.
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the Quality Assurance Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2000). The program includes participation in Interlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.
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3.5 Program Modifications Special tritium sampling of ground and well water was monitored from 1989 through 1999 at several locations. Tritium concentrations in that time have dropped to below detection levels. The program has been discontinued for the year 2000. The Suter residence, (P-24) was retained from the program, and added to the REMP in 2000, as a monitored well water location.
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 ft2 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 2000 Land Use Census was completed in October, 2000. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 2000. The critical receptor location did not change in 2000, based on the results 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 scheduled collections and analyses were made except those listed in Table 5.3.
The 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 2000.
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 2000.
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 1-131 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. 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 2000.
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 16.0 mR/91 days at inner ring locations to 17.6 mRI91 days at outer ring locations. The mean at special locations was 15.8 mR/91 days and 17.1 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 1985. through 1999. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).
Average (Inner Year and Outer Ring-s)
Control 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 2000 17.0 17.1 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 70.0 mR/91 days inside the ISFSI earth berm and 19.0 mR/91 days outside the ISFSI earth berm. Three additional casks were placed on the ISFSI pad in 2000. There were twelve loaded casks on the ISFSI pad during 2000. 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 15.8 and 15.4 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 both indicator and control locations averaged 0.025 pCi/m 3. These averages were similar to average means reported from 1985 through 1999. 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) 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 2000 0.025 0.025 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 1985 through 2000.
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 (Xcel Energy Corp.,
2001a).
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 2000 show no radiological effects of the plant operation.
Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 179 pCi/L in all samples.
Gross beta measurements remained fairly constant throughout the year and averaged 10.1 pCi/L. These concentrations were slightly higher than levels observed from 1985 through 1999 and are most likely contributed by relatively high levels of naturally-occurring radium.
Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2000 data of any effect of plant operation.
Gross Beta Yea.r (pCi/L) 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 2000 10.1 Average annual concentrations; Gross beta in drinking water.
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River Water In one quarterly composite of downstream river water, tritium was measured at a concentration of 297 pCi/L. In all other upstream and downstream collections, quarterly composite tritium levels were below the LLD level of 190 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
Well Water At the control well P-41, Huppert Farm and four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above the LLD level of 180 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2000 show no radiological effects of the plant operation.
Crops Two samples of broadleaf vegetation, cabbage and rutabaga leaves, were collected in August and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.009 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. No collection and analysis of corn samples was not required.
Fish Fish samples were collected in April, May and September, 2000 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 May and September, 2000.
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 May and September, 2000 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)'
Frequencyb Frequency' Ambient radiation (TLD's) 54 P-01A - P-10A C/Q Ambient gamma Airborne Particulates Airborne Iodine Milk Milk River water Drinking water P-01B - P-15B P-01S - P-08S P-011A - P-081A P-01IB - P-081B P-0lIX-P-04IX, P-0lC 5
P-I(C), P-2, P-3, P-4, P-6 5
P-I(C), P-2, P-3, P-4, P-6 4
P-14, P-18,P-37, P-41 (C) 1 P-39 2
P-5(C), P-6 1
P-1I C/W C/W G/Md G/M G/W G/W GB, GS (QC of each location) 1-131 1-131, GS 1-13 1, GS GS(MC), H-3(QC)
GB(MC), I-131 (MC)
Well water Edible cultivated crops leafy green vegetables Fish (one species, edible portion)
Periphyton or invertebrates Bottom sediment Shoreline sediment 5
2 2
2 2
1 P-6, P-8, P-9, P-24, P-41 (C)
P-38(C), P-24 P-19(C), P-13 P40(C), P-6 P-20(C), P-6 P-12 a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.
b 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 codes: 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 G/Q G/A G/SA G/SA G/SA G/SA H-3, GS GS (1-131)
GS GS GS GS
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction from Code Typea Collection Site Sample Typeb Reactor C
Air Station P-I Air Station P-2 Air Station P-3 Air Station P-4 C
Upstream of Plant Lock and Dam # 3 & Air Station P-6 Community Center Plant Well #2 Red Wing Service Center Downstream of Plant Downstream of Plant Gustafson Farm Christiansen Farm C
Upstream of Plant C
Upstream of Plant Suter Residence Welsch Farm C
Cain Residence Born Farm C
Upstream of Plant C
Huppert Farm AP, AI AP, AI AP, AI AP, Al RW AP, AI, RW WW, BS, BOc WW WW DW SS Fc M
M Fc BS VE, WW M
VE M
BOc M,WW 11.8 mi @ 316°/NNW 0.5 mi @ 294°/WNW 0.8 mi @ 313°/NW 0.4 mi @ 3590/N 1.8 mi @ 11/N 1.6 mi @ 129°/SE 1.0 mi @ 321°/WNW 0.3 mi @ 306'/NW 3.3 mi @ 158°/SSE 3.0 mi @ 116°/ESE 3.5 mi @ 113°/ESE 2.3 mi @ 1730/S 3.8 mi @ 88°/E 1.3 mi @ 00 N 0.9 mi @ 45°/NE 0.6 mi @ 158°/SSE 4.1 mi@ 87°/E 14.2 mi @ 359°/N 2.8 mi @ 239°/WSW 0.4 mi @ 0°/N 13.8 mi @ 354°/N General Area of the Site Boundary Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.4 mi @ 359-/N 0.3 mi @ 10I/N 0.5 mi @ 183-/S 0.4 mi @ 204°/SWW 0.4 mi @ 225°/SW 0.4 mi @ 2490/WSW 0.4 mi @ 268°/W 0.4 mi @ 291 °/WNW 0.7 mi @ 317°/NW 0.5 mi @ 333°/NNW 14 P-1 P-2 P-3 P-4 P-5 P-6 P-8 P-9 P-11 P-12 P-13 P-14 P-18 P-19 P-20 P-24 P-37 P-38 P-39 P-40 P-41 P-O0A P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-IOA
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Distance and Direction from Code Typea Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant Thomas Killian Residence Roy Kimneman Residence Wayne Anderson Farm Nelson Drive (Road)
County Road E and Coulee William Hauschiblt Residence Red Wing Public Works David Wnuk Residence Highway 19 South Cannondale Farm Wallace Weberg Farm Ray Gergen Farm Thomas O'Rourke Farm David J. Anderson Farm Holst Farms TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.7 mi @ 355°/N 4.8 mi @ 17°/NNE 4.9 mi @ 460/NE 4.2 mi @ 61°IENE 4.2 mi @ 102°/ESE 4.4 mi @ 112°/ESE 4.7 mi @ 1400/SE 4.1 mi @ 165°/SSE 4.2 mi @ 187°/S 4.9 mi @ 200°/SSW 4.5 mi @ 221°/SW 4.6 mi @ 251I/WSW 4.4 mi @ 270°/W 4.9 mi @ 306°/NW 3.8 mi @ 345°/NNW Special Interest Locations Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm Indian Community Indian Community C
Robert Kinneman Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD 1.6 mi @ 129°/SE 0.5 mi @ 155°/SSE 2.2 mi @ 1730/S 2.0 mi @ 202°/SSW 2.0 mi @ 270V/W 2.5 mi @ 299°/WNW 0.7 mi @ 2710/W 0.7 mi @ 2870/NWW 11.1 mi @ 331°/NNW 15 P-01B P-02B P-03B P-04B P-05B P-06B P-07B P-08B P-09B P-103B P-l1B P-12B P-13B P-14B P-15B P-01S P-02S P-03S P-04S P-05S P-06S P-07S P-08S P-01C
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Approximate Type of Distance and Direction Code Typea Collection Site Sampleb from ISFSI Center.
ISFSI Area Inside Earth Berm P-01IA ISFSI Nuisance Fence TLD 190' @ 45°/NE P-021A 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-051A ISFSI Nuisance Fence TLD 180' @ 219°/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258°/WSW P-071A ISFSI Nuisance Fence TLD 320' @ 28 1°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318 0/NW P-OlIX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 270°/W P-03DX ISFSI Nuisance Fence TLD 140' @ 0O/N P-041X ISFSI Nuisance Fence TLD 360' @ 90°/E ISFSI Area Outside Earth Berm P-OlIB ISFSI Berm Area TLD 340' @ 3°/N P-021B ISFSI Berm Area TLD 380' @ 280/NNE P-031B ISFSI Berm Area TLD 560' @ 85°/E P-041B ISFSI Berm Area TLD 590' @ 165 0/SSE P-05IB ISFSI Berm Area TLD 690' @ 1860/S P-061B ISFSI Berm Area TLD 720' @ 201°/SSW P-07EB ISFSI Berm Area TLD 610' @ 271°/W P-08EB ISFSI Berm Area TLD 360' @ 332°/NNW a "C" denotes control location. All other locations are indicators.
b Sample Codes:
AP Airborne particulates AI Airborne Iodine BS Bottom (river) sediments BO Bottom organisms (periphyton or macroinvertebrates)
DW Drinking water F
M SS SW VE WW Fish Milk Shoreline Sediments Surface Water Vegetation/vegetables Well water C 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 at the Prairie Island Nuclear Generating Plant.
All required samples were collected and analyzed as scheduled with the following exceptions:
Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI
- Beta, P-03 6/14/00 No power due to open fuse.
Replaced fuse and conducted testing.
1-131 All operational testing was satisfactory.
TLD Ambient P-lOB 4th Qtr.
TLD lost in the field due to Isolated incident; no action required.
Gamma unusually deep snow.
17
C>
~
4-:-
C,,
W 1,0 C
1985 1985 ---
1986--
1986
-© 1987-1987---
CD 1988 1988 1989 1989 1990--1990 1-o 1992-*
1992-Z, CL)
S1993 1993 I
1994 1994-199 3
1995--
19965 1996
-/
0 19974-------
1997 -,
1998 1998 5
1999 T 1999 2000 2000-mR / 91 days mR / 91 days
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
0.031 0.029 S0.027 0.025 0.023 0.021 0.019 0.017 0.015 W)
ý10 r-00 a's
ý
'-4 C14 M~
ýt W) 10 00 00 00 00 00 ON Oa% 01 0\\
ON O*
QN a'
C*
O.
O(
ON
- 0)
O\\
OS ON CN CN ON ON Ox
-4
-4
-.4
--4 1-4
-4 1-4 1-00 01%
0 CN 0'*
0 O\\
O*
0 01 CN C:
0.0 0.0:
0.0 S0.0:
S0.0:
0.0 0.0 0.0 0.0 0.0 0.0
-e-- Control (P-l)
I 35 33-31-29--
27 25-(
23
'17
'15-LO C (0 I-O0) 0
.m--
0 Co) l q U
(0 1 "-
M0 O0 0
ccO c
cc CO C0 60 0)J
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0) 0 0')
0')
- 0) 0')
- 0)
- 0)
- 0) 0')
- 0) 0")
- 0)
- 0) 0")
- 0) 0 0
19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota
( County, State)
Docket No.
50-282,50-306 Reporting Period January-December, 2000 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)'
Mean (F)Y Routine (Units)
Analyses' Range' Location" Rangec Range' Results' TLD (Inner Ring, Gamma 40 3.0 16.0 (40/40)
P-06A 16.9 (4/4)
(See Control 0
Area at Site (12.3-18.4) 0.4 mi @ 249* /WSW (15.1-18.4) below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma 59 3.0 17.6 (59/59)
P-02B, Roy Kinneman, 20.5 (4/4)
(See Control 0
4-5 mi. distant)
(13.1-21.8) 4.8 mi @ 17' /NNE (18.2-21.8) below.)
mR/91 days)
TLD (Special Gamma 32 3.0 15.8 (32/32)
P-03S, Gustafson Farm, 18.4 (4/4)
(See Control 0
Interest Areas)
(12.3-19.7) 2.2 mi @ 173' /S (16.5-19.7) below.)
mR/91 days)
TLD (Control)
Gamma 4
3.0 None P-01C, R. Kinneman, 17.1 (4/4) 17.1 (4/4) 0 mR/91 days) 11.1 mi @ 331' /NNW (15.1-18.2)
(15.1-18.2)
Airborne GB 264 0.005 0.025 (211/211)
P-04, Air Station 0.026 (53/53) 0.025 (53/53) 0 Particulates (0.009-0.078) 0.4 mi @ 3590 /N (0.009-0.073)
(0.011-0.083)
(pCi/my)
GS 20 Be-7 0.015 0.061 (16/16)
P-06, Air Station 0.064 (4/4) 0.055 (4/4) 0 (0.040-0.075) 1.6 mi @ 129'/SE (0.040-0.070)
(0.040-0.066)
Mn-54 0.0008
< LLD
< LLD 0
Co-58 0.0011
< LLD LLD 0
Co-60 0.0010
< LLD
< LLD 0
Zn-65 0.0013
< LLD
< LLD 0
Zr-Nb-95 0.0011
< LLD
< LLD 0
Ru-103 0.0009
< LLD
< LLD 0
Ru-106 0.0069
< LLD
< LLD 0
Cs-134 0.0006
< LD
< LLD 0
Cs-137 0.0007
<LLD
<LLD 0
Ba-La-140 0.0024
< LLD
< LLD 0
Ce-141 0.0013
< LLD
< LLD 0
Ce-144 0.0036
< LLD LLD 0
Airborne Iodine 1-131 264 0.07
< LLD
< LLD 0
(pG/rft) 20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No.
50-282, 50-306 Reporting Period January-December, 2000
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)Y Mean (F)'
Mean (F)'
Routine (Units)
Analyses' Range' Locationd Range' Range' Results' Milk (pCi/L) 1-131 76 1.0
< LLD
< LLD 0
GS 76 K-40 200 1481 (57/57)
P-14, Gustafson Farm 1524 (19/19) 1481 (19/19) 0 (1276-1756) 2.3 mi @ 173°/S (1367-1632)
(1347-1588)
Cs-134 15
< LLD
< LLD 0
Cs-137 15
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
River Water H-3 8
179 297(1/4)
P-6, Lock and Dam # 3 297(1/4)
< LLD 0
(pCi/L) 1.6 mi @ 129'/SE 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 58
< LLD I
< LLD 0
21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No.
50-282, 50-306 Reporting Period January-December, 2000 (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)
Analysese Range' Locationd Range' Range' Results' Drinking Water GB 12 1.0
< LLD P-11, Red Wing S.C.
10.1 (12/12)
None 0
(pCi/L) 3.3 mi @ 158' /SSE (5.2-12.9) 1-131 12 1.0
< LLD None 0
H-3 4
179
< 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 59
< LLD None 0
Well Water H-3 20 180
< LLD
< LLD 0
(pCi/L)
GS 20 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 56
< LLD
< LLD 0
Crops - Cabbage 1-131 2
0.009
< LLD
< LLD 0
(pCi/gwet) 22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No.
50-282,50-306 Reporting Period January-December, 2000 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDP Mean (F)'
Mean (F)'
Mean (F)'
Routine (Units)
Analysese Range' Location' Range' Range' Results' Fish GS 4
(pCi/g wet)
K-40 0.10 2.85 (2/2)
P-19, Upstream 3.58 (2/2) 3.28 (2/2) 0 (2.63-3.06) 1.3 mi. @ 0*°/N (3.42-3.73)
(3.07-3.48)
Mn-54 0.018
< LLD
< LLD 0
Fe-59 0.081
< LLD
< LLD 0
Co-58 0.015
< LLD
< LLD 0
Co-60 0.017
< LLD
< LLD 0
Zn-65 0.029
< LLD
< LLD 0
Zr-Nb-95 0.031
< LLD
< LLD 0
Cs-134 0.013
< LLD
< LLD 0
Cs-137 0.013
< LLD
< LLD 0
Ba-La-140 0.77
< LLD
< LLD 0
Invertebrates GS 4
(pCi/g wet)
Be-7 0.55
< LLD
< LLD 0
K-40 1.48
< LLD
< LLD 0
Mn-54 0.063
< LLD LLD 0
Co-58 0.10
< LLD LLD 0
Co-60 0.069
< LLD LLD 0
Zn-65 0.12
< LLD
< LLD 0
Zr-Nb-95 0.13
< LLD
< LLD 0
Ru-103 0.078
< LLD
< LLD 0
Ru-106 0.40
< LLD
< LLD 0
Cs-134 0.071
< LLD
< LLD 0
Cs-137 0.057
< LLD
< LLD 0
Ba-La-140 0.61
< LLD
< LLD 0
Ce-141 0.11
< LLD
< LLD 0
Ce-144 0.24
<LLD
< LLD 0
23
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No.
50-282, 50-306 Reporting Period January-December, 2000 (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' Location' Range' Range' Results' Bottom and GS 6
Shoreline Be-7 0.30
< LLD
< LLD 0
Sediments K-40 0.10 6.94(4/4)
P-20, Upstream 8.79 (4/4) 8.79 (4/4) 0 (pCi/g dry)
(6.51-7.46) 0.9 mi. @ 45' /NE (8.64-8.94)
(8.64-8.94)
Mn-54 0.021
< LLD
< LLD 0
Co-58 0.030
< LLD
< LLD 0
Co-60 0.016
< LLD
< LLD 0
Zn-65 0.066
< LLD
< LLD 0
Zr-Nb-95 0.030
< LLD
< LLD 0
Ru-103 0.023
< LLD
< LLD 0
Ru-106 0.18
< LLD
< LLD 0
Cs-134 0.030
< LLD
< LLD 0
Cs-137 0.024
< LLD
< LLD 0
Ba-La-140 0.062
< LLD
< LLD 0
Ce-141 0.044
< LLD
< LLD 0
Ce-144 0.10
< 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).
d 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.
Environmental, Inc., Midwest Laboratory. 2001a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000.
2001b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000.
2000.
Quality Assurance Program Manual, Rev. 0, 11 October 2000.
2000.
Quality Control Procedures Manual, Rev. 0, 21 September 2000.
2000.
Quality Control Program, Rev. 0, 12 October 2000.
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, No. 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.
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.
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.
25
6.0 REFERENCES
CITED (continued)
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.
1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 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.
Xcel Energy Corporation. 2001. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26
"-.-.. Environmental, Inc.
"""Midwest Laboratory an Allegheny Technologies Co.
700 Landwetr Road
- Norbhbrook, IL 60062-2310 (847) 564-0700 fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental, Inc., 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, 2000 through December, 2000
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly 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 a laboratory's analytical procedures and to alert it of 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 the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.
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.
Results of crosscheck testing with Teledyne Brown Engineering are also 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
12-31-00 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa 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 is = (pCi/liter) =
169.85 x (known)°9
>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
-35 0-C¢'
Ilter 15% of known value Nickel-63.. '--
Technetium-99b 50 to 100 pCi/liter 10 pCi/liter Iron-55b
>100 pCi/liter 10% of known value Others" 20% of known value "a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
A2 I
Table A-1.
Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration in pCi/L Lab Sample Date Laboratory results ERA Resultd Control Code Type Collected Analysis
+/-2 Sigmac Is, N=1 Limits STW-863 WATER Jan, 2000 Gr. Alpha 39.3 +/- 5.2 25.4 +/- 6.4 14.5 - 36.3 The analysis was repeated and recalculated with Am-241 efficiency; result of reanalysis 29.32 +/- 5.79 pCi/L.
Internal spike program results do not indicate a problem.
STW-863 WATER Jan, 2000 Gr. Beta 40.7 +/-1.2 42.1 +/-4.2 33.4 - 50.8 STW-866 WATER Jan, 2000 Sr-89 17.1 +/- 2.2 22.5 +/- 5.0 13.8 - 31.2 STW-866 WATER Jan, 2000 Sr-90 8.1 +/- 0.6 9.6 +/- 5.0 0.9 - 18.3 STW-868 WATER Feb, 2000 Ra-226 7.6 +/- 0.5 8.3 +/- 1.2 6.1 - 10.4 STW-868 WATER Feb, 2000 Ra-228 5.6 +/- 1.0 2.3 +/- 0.6 1.3 - 3.2 Result of reanalysis: 6.34 +/- 0.94. Activity confirmed by gamma spectroscopy (6.00 +/- 1.42 pCi/L ).
STW-868 WATER Feb, 2000 Uranium 5.4+/-0.2 6.1+/-3.0 0.9-11.3 STW-869 WATER Mar, 2000 H-3 23,500.0 +/- 306.0 23,800.0 +- 2,380.0 19,800.0 - 27,800.0 STW-867 WATER Mar, 2000 Gr. Alpha 83.6 +/- 5.8 58.4 +/- 5.8 33.3 - 83.5 Results were recalculated with Am-241 efficiency; 57.80 --+ 5.73 pCi/L. Refer to STW-863.
STW-867 WATER Mar, 2000 Gr. Beta 15.4+/-0.9 16.8+/-1.7 8.1 -25.5 STW-876 WATER Mar, 2000 1-131 18.7+/--0.6 19.9 -+/- 2.0 14.7-25.1 STW-877 WATER Apr, 2000 Gr. Alpha 52.3 +/- 2.3 54.0 +/- 13.5 30.8 - 77.2 STW-877 WATER Apr, 2000 Ra-226 17.5 +/- 1.1 18.6 +/- 2.8 13.8 - 23.4 STW-877 WATER Apr, 2000 Ra-228 3.7 +/- 0.4 3.6 +/- 0.9 2.0 - 5.1 STW-878 WATER Apr, 2000 Co-60 19.2 +/- 0.6 16.9 +/- 5.0 8.2 - 25.6 STW-878 WATER Apr, 2000 Cs-134 81.0 +/- 1.3 86.4 +/- 5.0 77.7 - 95.1 STW-878 WATER Apr, 2000 Cs-137 119.0 +/- 2.6 123.0 +/- 6.2 112.0 - 134.0 STW-878 WATER Apr, 2000 Gr. Beta 276.0 +/- 9.6 289.0 +/- 43.4 214.0 - 364.0 STW-878 WATER Apr, 2000 Sr-89 32.3 +/- 3.3 50.7 +/-5.0 42.0 - 59.4 STW-878 WATER Apr, 2000 Sr-90 11.3 +/- 1.0 32.8 +/- 5.0 24.1 - 41.5 An error was found in calculation. Result of recalculation: Sr-89, 55.5+/- 7.2 pCi/L / Sr-90, 30.7 +/- 3.0 pCi/L.
Results of reanalysis: Sr-89, 47.4 +/- 14.5 pCi/L / Sr-90, 33.0 +/- 1.35 pCi/L. Both results are within limits.
STW-879 WATER Jun, 2000 Ba-133 22.4 +/- 2.1 25.5 +/- 5.0 16.8 - 34.2 STW-879 WATER Jun, 2000 Co-60 69.9 +/- 3.7 65.6 +/- 5.0 56.9 - 74.3 STW-879 WATER Jun, 2000 Cs-134 13.5 +/- 0.8 13.8 +/-5.0 5.1 - 22.5 STW-879 WATER Jun, 2000 Cs-137 232.0 +/- 7.8 238.0 +/- 11.9 217.0 - 259.0 STW-879 WATER Jun, 2000 Zn-65 50.9 +/- 3.8 54.6 +/- 5.5 45.3 - 63.9 STW-880 WATER Jun, 2000 Ra-226 2.8 +/-0.2 3.0 +/-0.5 2.2-3.8 STW-880 WATER Jun, 2000 Ra-228 10.0 +/- 0.9 13.0 +/- 3.3 7.4 - 18.6 STW-880 WATER Jun, 2000 Uranium 57.0 +/- 4.4 63.4 +/- 6.3 52.6 - 74.2 STW-883 WATER Jul, 2000 Gr. Alpha 6.9 +/- 1.1 7.2 +/- 5.0 0.0 - 15.9 STW-883 WATER Jul, 2000 Gr. Beta 88.8 +/- 9.8 87.5 +/- 10.0 70.2 - 105.0 STW-884 WATER Aug, 2000 H-3 8,740.0 +/- 174.0 8,320.0 +/- 832.0 6,910.0 - 9,730.0 STW-891 WATER Sep, 2000 Ra-226 17.9 +/- 1.3 18.9 +/- 2.8 14.0 - 23.8 STW-891 WATER Sep,200 0 Ra-228 5.7 +/-0.5 6.2 +/-1.6 3.5-8.8 Al-1
Table A-1.
Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration in pCi/Lb Lab Sample Date Laboratory results ERA Resultd Control Code Type Collected Analysis
+/-2 Sigmac 1s, N=1 Limits Uranium 1-131 1-131(g)
Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-134 Cs-137 Gr. Beta Sr-89 Sr-90 Gr. Alpha Gr. Beta Ba-133 Co-60 Cs-134 10.3 +/- 0.1 16.9 +/- 0.3 17.1 +/-5.4 66.3 +/- 5.3 10.1+/- 1.0 21.2 +/- 0.5 41.4+/-1.9 93.4 +/- 1.6 54.8 +/- 0.3 45.5 +/-2.3 209.0 +/- 7.9 32.8 +/- 3.0 16.0 +/- 2.4 50.3 +/- 2.6 28.6 +/- 1.3 78.0 +/- 2.0 30.8+/-k 1.7 67.2 +/- 3.3 11.9 +/-3.0 15.9 +/- 1.6 15.9 +/-1.6 74.4 +/- 18.6 10.5 +/- 1.6 19.4+/-4.9 44.5 +/- 4.5 91.1 +/-5.0 59.8 +/- 5.0 45.0 +/-5.0 256.0 +/- 38.4 41.3 +/- 5.0 18.0 +/- 5.0 60.3 +/- 15.1 25.5 +/-5.0 82.2 +/- 8.2 27.8 +/-5.0 76.0 +/-5.0 6.7-17.1 10.7-21.1 10.7-21.1 42.2-107.0 7.8-13.2 11.0- 27.8 36.8 - 52.2 82.4-99.8 51.1 - 68.5 36.3 - 53.7 189.0 - 323.0 32.6-50.0 9.3 - 26.7 34.4-86.2 16.8 - 34.2 68.0- 96.4 19.1 - 36.5 67.3 - 84.7 The mean value for Cs-134 of all participating laboratories was 70.7 pCi/L. Other gamma emitters are within limits, the counting efficiency is not suspect. Library values were reviewed and found to be correct.
WATER Nov, 2000 Cs-137 WATER Nov. 2000 Zn-65 109.0 +/- 1.0 81.5 +/- 7.4 106.0 +/-5.3 79.0 + 7.9 96.8-115.0 65.3 - 92.7 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources 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 laboratory results are given as the mean +/- 2 standard deviations for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
A1-2 STW-891 STW-892 STW-892 STW-893 STW-893 STW-893 STW-893 STW-894 STW-894 STW-894 STW-894 STW-894 STW-894 STW-895 STW-895 STW-896 STW-896 STW-896 WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Sep, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 STW-896 STW-896 STW-896
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).
mR Lab Laboratory results Known Average +/- 2 Sigma Code TLD Type Date Measurement
+/-2 Sigma Value (All Participants)
Environmental. Inc.
1999-1 LiF-100 Chips Mar, 1999 Reader 1, #1 14.5 +/- 0.5 15.4 1999-1 LiF-100 Chips Mar, 1999 Reader 1, #2 29.3 +/- 1.0 31.8 1999-1 LiF-100 Chips Mar, 1999 Reader 1, #3 60.0_L0.2 59.1 Environmental, Inc.
1999-2 CaSO4: Dy Cards Mar, 1999 Reader 1, #1 18.3 +/- 0.5 15.4 1999-2 CaSO 4: Dy Cards Mar, 1999 Reader 1, #2 35.9+/- 1.3 31.8 1999-2 CaSO4: Dy Cards Mar, 1999 Reader 1, #3 66.5 +/- 4.4 59.1 Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 1999.
Environmental, Inc.
2000-1 LiF-100 Chips Mar, 2000 Reader 1, #1 14.4+/- 0.2 17.8 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #2 32.4_+/- 0.1 35.5 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #3 61.8 +/- 0.9 62.2 Environmental, Inc.
2000-2 CaSO4: Dy Cards Mar, 2000 Reader 1, #1 21.3 +/- 0.3 17.8 2000-2 CaSO 4: Dy Cards Mar, 2000 Reader 1, #2 40.1 +/- 1.9 35.5 2000-2 CaSO4: Dy Cards Mar, 2000 Reader 1, #3 69.9 +/-3.5 62.2 Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 2000.
A2-1
Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Laboratory results Known Control' Code Type Collected Analysis 2s, n=lb Activity Limits SPW-271 WATER Jan, 2000 Ra-226 14.81 +/- 0.44 SPW-271 WATER Jan, 2000 Ra-228 16.97 +/- 2.12 SPW-272 WATER Jan, 2000 Gr. Alpha 44.35 +/- 1.95 SPW-272 WATER Jan, 2000 Gr. Beta 31.19 +/- 5.02 SPW-756 WATER Jan, 2000 H-3 56339.00 +/- 666.00 5
SPW-480 WATER Jan, 2000 Co-60 32.33 +/- 2.87 SPW-480 WATER Jan, 2000 Cs-137 35.58 +/- 4.20 SPMI-482 MILK Jan, 2000 Sr-90 16.93 +/- 1.07 SPAP-484 AIR FILTER Jan, 2000 Cs-137 1.84 +/- 0.01 SPW-917 WATER Feb, 2000 Gr. Alpha 16.59 +/- 1.90 An insufficient amount of Am-241 spike was available for an accurate test.
SPW-917 WATER Feb, 2000 Gr. Beta 32.61 +/- 2.06 SPW-918 WATER Feb, 2000 Ra-226 21.15 +/- 0.49 SPW-918 WATER Feb, 2000 Ra-228 14.24+/- 1.64 SPVE-1262 VEGETATION Mar, 2000 1-131(g) 1.17+/- 0.07 SPCH-1264 CHARCOAL Mar, 2000 1-131(g) 0.56 +/- 0.02 CANISTER SPMI-1274 MILK Mar, 2000 1-131 47.02 +/-3.36 SPW-1301 WATER Mar, 2000 1-131 66.03 +/-1.06 SPW-1301 WATER Mar, 2000 1-131(g) 80.31 +/- 6.28 SPW-1477 WATER Mar, 2000 Gr. Alpha 32.09 +/- 1.82 SPW-1477 WATER Mar, 2000 Gr. Beta 29.20+/-1.56 SPW-1478 WATER Mar, 2000 Ra-226 21.78+/- 0.47 SPW-1478 WATER Mar, 2000 Ra-228 14.41 +/- 1.70 SPMI-2275 MILK Apr, 2000 Cs-134 33.53 +/- 2.82 SPMI-2275 MILK Apr, 2000 Cs-137 36.38 +/-4.94 SPMI-2275 MILK Apr, 2000 1-131 46.06 +/- 0.82 SPW-2277 WATER Apr, 2000 Ra-226 20.51 +/- 0.44 SPW-2278 WATER Apr, 2000 Gr. Alpha 40.22 +/-2.50 SPW-2278 WATER Apr, 2000 Gr. Beta 32.63 +/- 1.81 SPW-2278 WATER Apr, 2000 Ra-228 14.91 +/- 1.70 SPW-2279 WATER Apr, 2000 Co-60 37.12_+/- 3.86 SPW-2279 WATER Apr, 2000 Cs-134 34.70+/- 3.32 SPW-2279 WATER Apr, 2000 Cs-137 39.60+/- 5.12 SPW-2279 WATER Apr, 2000 1-131 49.92 +/- 0.67 SPW-2279 WATER Apr, 2000 1-131(g) 60.63 +/- 6.58 SPW-2281 WATER Apr, 2000 H-3 58829.00 +/-682.00 SPAP-3097 AIR FILTER Apr, 2000 Cs-137 1.81 +/- 0.02 SPW-3093 WATER May, 2000 1-131 83.39 +/- 1.06 SPW-3094 WATER May, 2000 Ra-226 20.86-+/- 0.42 SPW-3094 WATER May, 2000 Ra-228 14.17+/- 1.59 qPW-3f95 WATER Mav. 2000 Gr. Aloha 38.99 +/- 2.09 13.76 14.68 41.14 29.50 7667.00 28.36 36.83 14.10 1.72 41.10 29.43 20.68 14.51 1.12 0.53 48.00 76.84 76.84 41.13 29.38 20.69 14.39 32.12 36.66 55.50 20.68 38.44 29.30 14.25 34.54 32.12 36.66 55.50 55.50 56996.00 1.71 85.38 20.68 14.12 38.44 9.63 - 17.89 10.28 - 19.08 20.57 - 61.71 19.50 - 39.50 46133.60 - 69200.40 18.36 - 38.36 26.83 - 46.83 4.10 - 24.10 1.03 - 2.41 20.55 - 61.65 19.43 - 39.43 14.48 - 26.88 10.16 - 18.86 0.67-1.57 0.32 - 0.74 36.00 - 60.00 61.47 - 92.21 66.84 - 86.84 20.57 - 61.70 19.38 - 39.38 14.48 - 26.90 10.07 - 18.71 22.12 - 42.12 26.66 - 46.66 44.40 - 66.60 14.48 - 26.88 19.22 - 57.66 19.30 - 39.30 9.98-18.53 24.54 - 44.54 22.12 - 42.12 26.66 - 46.66 44.40 - 66.60 45.50 - 65.50 45596.80 - 68395.20 1.03-2.39 68.30 - 102.46 14.48 - 26.88 9.88-18.36 19.22 - 57.66 A3-1
,.,*,, *viv
Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Laboratory results Known Controlc Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3095 SPAP-274 SPMI-3138 SPF-3180 SPF-3180 SPAP-3902 SPF-5182 SPF-5182 SPW-3911 SPW-3911 SPW-3910 SPW-3910 SPW-4342 SPW-4342 SPW-4687 SPW-4687 SPW-4688 SPAP-4807 SPAP-4809 SPMI-4856 SPMI-4856 SPMI-4856 SPMI-4856 SPW-5372 SPW-5372 SPW-5372 SPW-4686 SPW-4686 SPW-5564 SPW-5564 SPW-5792 SPW-5792 SPW-6631 SPW-6632 SPW-6632 SPW-6633 SPW-5791 SPW-5791 SPW-6630 SPW-6630 SPW-7744 WATER AIR FILTER MILK FISH FISH AIR FILTER FISH FISH WATER WATER WATER WATER WATER WATER WATER WATER WATER AIR FILTER AIR FILTER MILK MILK MILK MILK WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Aug, 2000 Aug 2000 Aug 2000 Aug 2000 Aug 2000 Aug 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Oct, 2000 Gr. Beta Gr. Beta 1-131 Cs-134 Cs-137 Gr. Beta Cs-134 Cs-137 Ra-226 Ra-228 Gr. Alpha Gr. Beta Sr-89 Sr-90 Ra-226 Ra-228 H-3 Gr. Beta Cs-137 Cs-134 Cs-137 Sr-89 Sr-90 Co-60 Cs-134 Cs-137 Gr. Alpha Gr. Beta Sr-89 Sr-90 Ra-226 Ra-228 Ra-228 Ra-226 Ra-228 Fe-55 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Ra-226 30.65. 1.53 5.08 _ 0.03 85.08 +/- 1.05 0.52 +/- 0.02 0.65 +/- 0.04 5.81 +/- 0.03 0.60 +/- 0.04 0.60 +/- 0.05 23.73 +/- 0.85 20.43 +/- 1.77 38.28 +/- 2.12 35.14 +/- 1.74 73.70 +/- 4.77 58.13 +/- 2.17 21.07 +/- 0.56 16.35 +/- 1.70 56205.00 +/- 663.00 6.07 +/- 0.02 1.82 +/- 0.02 33.24 +/- 3.74 39.80 +/- 6.77 46.35 +/- 5.10 70.47 +/- 2.06 33.31 +/- 4.61 59.70 +/- 4.57 40.00 +/- 5.58 34.12 _ 1.71 35.42 +/- 1.51 62.97 +/- 4.73 65.40 +/- 2.47 12.82 +/- 0.30 15.00 +/- 1.21 22.20+/-2.20 13.58 +/- 0.29 18.84 +/- 2.59 1757.00 +/- 674.00 52.28 +/- 9.41 34.60 +/- 4.71 71.54 +/- 7.15 37.78 +/- 1.62 12.36 +/- 0.25 29.30 5.97 85.38 0.50 0.59 5.35 0.59 0.58 20.68 20.75 38.44 29.22 81.00 55.90 20.68 20.75 56228.00 5.96 1.71 29.56 36.45 56.34 69.73 33.24 58.26 36.42 38.43 29.21 67.61 55.70 13.79 13.69 20.32 13.79 20.32 1852.00 69.00 29.10 69.14 29.04 13.79 19.30 - 39.30
-4.03 - 15.97 68.30 - 102.46 0.30 - 0.70 0.35 - 0.82
-4.65 - 15.35 0.35 - 0.83 0.35- 0.81 14.48 - 26.88 14.53 - 26.98 19.22 - 57.66 19.22 - 39.22 64.80 - 97.20 44.72 - 67.08 14.48 - 26.88 14.53 - 26.98 44982.40 - 67473.60
-4.04 - 15.96 1.03 - 2.39 19.56 - 39.56 26.45 - 46.45 45.07 - 67.61 55.78 - 83.68 23.24 - 43.24 48.26 - 68.26 26.42 - 46.42 19.22 - 57.65 19.21 - 39.21 54.09 - 81.13 44.56 - 66.84 9.65 - 17.93 9.58-17.80 14.22 - 26:42 9.65-17.93 14.22 - 26.42 1481.60 - 2222.40 34.50 - 103.50 19.10 - 39.10 34.57 - 103.71 19.04 - 39.04 9.65-17.93 A3-2
Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Laboratory results Known Controlc Code Type Collected Analysis 2s, nrlb Activity Limits SPW-7744 WATER Oct, 2000 Ra-228 10.37+/- 1.15 13.40 9.38 - 17.42 SPW-7745 WATER Oct, 2000 H-3 54650.00_+/- 643.00 55391.00 44312.80 - 66469.20 SPAP-7764 AIR FILTER Oct, 2000 Gr. Beta 6.14 +/- 0.03 5.91
-4.09 - 15.91 SPAP-7766 AIR FILTER Oct, 2000 Cs-137 1.84 +/- 0.01 1.69 1.01 - 2.37 SPMI-8347 MILK Oct, 2000 Cs-134 29.18 +/- 6.51 26.83 16.83 - 36.83 SPMI-8347 MILK Oct, 2000 Cs-134 29.37 +/-3.63 26.83 16.83 - 36.83 SPMI-8347 MILK Oct, 2000 Cs-137 39.04 +/- 8.76 36.20 26.20 - 46.20 SPMI-8347 MILK Oct, 2000 Cs-137 34.89 +/- 5.71 36.20 26.20 - 46.20 SPF-8349 FISH Oct, 2000 Cs-134 0.56_+/- 0.02 0.54 0.32 - 0.75 SPF-8349 FISH Oct, 2000 Cs-137 0.92 +/- 0.04 0.87 0.52 - 1.22 SPW-8369 WATER Oct, 2000 Co-60 32.49 +/- 1.86 32.19 22.19 - 42.19 SPW-8369 WATER Oct, 2000 Cs-134 55.87 +/- 1.71 53.66 43.66 - 63.66 SPW-8369 WATER Oct, 2000 Cs-137 36.46 +/- 2.73 36.21 26.21 - 46.21 SPW-7743 WATER Oct, 2000 Gr. Alpha 51.28 +/-2.28 69.10 34.55 - 103.65 SPW-7743 WATER Oct, 2000 Gr. Beta 36.86 +/- 1.66 29.00 19.00 - 39.00 SPW-9101 WATER Nov, 2000 Ra-226 14.35 +/- 0.24 13.79 9.65 - 17.93 SPW-9101 WATER Nov, 2000 Ra-228 22.14+/- 1.56 20.09 14.06 - 26.12 SPW-9102 WATER Dec, 2000 Gr. Alpha 77.76 +/- 3.02 69.14 34.57 - 103.71 SPW-9102 WATER Dec, 2000 Gr. Beta 36.71 +/- 1.65 28.99 18.99 - 38.99 SPW-9726 WATER Dec, 2000 Gr. Alpha 43.03 +/- 2.18 69.14 34.57 - 103.71 SPW-9726 WATER Dec, 2000 Gr. Beta 32.17+/- 1.55 28.89 18.89 - 38.89 SPW-9727 WATER Dec, 2000 Ra-226 13.35 +/-0.29 13.79 9.65 - 17.93 SPW-9727 WATER Dec, 2000 Ra-228 15.44 +/- 1.23 19.75 13.83 - 25.68 SPCH-10228 CHARCOAL Dec, 2000 Ba-133 1.80 +/- 0.05 2.11 1.26 - 2.95 CANISTER "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. For vegetation, Sawdust is used for the spike matrix.
A3-3
Table A-4.
In-house "blank" samples.
Lab Code SPW-270 SPW-270 SPW-270 SPW-270 SPW-447 SPW-481 SPW-481 SPW-481 SPMI-483 SPMI-483 Low level of SPAP-485 SPW-919 SPW-919 SPW-919 SPW-919 SPVE-1263 SPVE-1263 SPCH-1265 SPMI-1292 SPMI-1292 SPW-1302 SPW-1479 SPW-1479 SPW-1479 SPW-1479 SPMI-2276 SPMI-2276 SPMI-2276 SPW-2280 SPW-2280 Mar 2000 Mar 2000 Mar 2000 Mar 2000 Mar 2000 Mar 2000 Mar 2000 Apr 2000 Apr 2000 Apr 2000 Apr 2000 Apr 2000 Sample Sample Type Date WATER Jan 2000 WATER Jan 2000 WATER Jan 2000 WATER Jan 2000 WATER Jan 2000 WATER Jan 2000 WATER Jan 2000 WATER Jan 2000 MILK Jan 2000 MILK Jan 2000 Sr-90 concentration in milk (1-5 AIR FILTER Jan 2000 WATER Feb 2000 WATER Feb 2000 WATER Feb 2000 WATER Feb 2000 VEGETATION Mar 2000 VEGETATION Mar 2000 CHARCOAL Mar 2000 Concentration pCi/La.
Laboratory results Acceptance (4.66 Sigma)
Criteria LLD Activityb (4.66 Sigma)
< 0.50 0.52 +/- 0.41
< 1.0
< 1.50
-0.34 +/-_1.11
<3.2 0.06 +/- 0.01
< 1.0
< 0.94 0.14 +/- 0.45
< 2.0
< 184.00
-54.70 +/- 88.60
< 200.0
< 2.42
< 10.0
< 3.99
< 10.0
< 2.90
< 10.0
< 2.73
< 10.0 1.03 +/- 0.40
< 1.0 Analysis Gr. Alpha Gr. Beta Ra-226 Ra-228 H-3 Co-60 Cs-134 Cs-137 Cs-137 Sr-90 pCi/L) is not Cs-137 Gr. Alpha Gr. Beta Ra-226 Ra-228 Cs-134 Cs-137 1-131(g) 1-131 1-131(g) 1-131 Gr. Alpha Gr. Beta Ra-226 Ra-228 Cs-134 Cs-137 1-131 Co-60 Cs-134 0.56 +/- 0.61 0.11 +/- 1.16 0.02 t 0.01 0.02 +/- 0.01 0.05 +/- 0.18 0.01 +/- 0.14
-0.32 +/- 0.53
-1.39 +/- 1.19 0.06
- 0.01 1.17 +/- 0.60 0.32 +/- 0.30
< 100.0
<1.0
<3.2
<1.0
<2.0
< 100.0
< 100.0
<9.6
<0.5
< 20.0
<0.5
<1.0
<3.2
<1.0
<2.0
< 10.0
< 10.0
<0.5
< 10.0
< 10.0 A4-1 unusual.
< 1.64
< 0.80
< 1.65
< 0.02
< 0.60
< 11.48
< 24.82
< 7.00
< 0.32
< 4.60
< 0.30
< 0.84
< 1.86
< 0.01
< 1.00
< 4.20
< 3.33
< 0.50
< 2.78
< 3.56 CANISTER MILK MILK WATER WATER WATER WATER WATER MILK MILK MILK WATER WATER
Table A-4.
In-house "blank" samples.
Sample Date Lab Code SPW-2280 SPW-2280 SPW-2280 SPW-2280 SPW-2280 SPW-2280 SPW-2280 SPW-2282 SPAP-3098 SPW-3096 SPW-3096 SPW-3096 SPW-3096 SPAP-273 SPMI-3139 SPF-3181 SPF-3181 SPAP-3903 SPW-3912 SPW-3912 SPW-3912 SPW-3912 SPMI-4343 SPMI-4343 SPW-4689 SPW-4689 SPW-4690 SPW-4808 SPAP-4810 SPMI-4857 SPMI-4857 ate A4-2 Sample Type WATER WATER WATER WATER WATER WATER WATER WATER AIR FILTER WATER WATER WATER WATER AIR FILTER MILK FISH FISH AIR FILTER WATER WATER WATER WATER MILK MILK WATER WATER WATER WATER AIR FILTER MILK MILK Apr 2000 Apr 2000 Apr 2000 Apr 2000 Apr 2000 Apr 2000 Apr 2000 Apr 2000 Apr 2000 May 2000 May 2000 May 2000 May 2000 May 2000 May 2000 May 2000 May 2000 Jun 2000 Jun 2000 Jun 2000 Jun2000 Jun2000 Jun 2000 Jun 2000 Jul2000 Jul2000 Jul 2000 Jul 2000 Jul 2000 Jul 2000 Jul 2000 Analysis Cs-137 Gr. Alpha Gr. Beta 1-131 1-131(g)
Ra-226 Ra-228 H-3 Cs-137 Gr. Alpha Gr. Beta Ra-226 Ra-228 Gr. Beta 1-131 Cs-134 Cs-137 Gr. Beta Gr. Alpha Gr. Beta Ra-226 Ra-228 Sr-89 Sr-90 Ra-226 Ra-228 H-3 Gr. Alpha Cs-137 Cs-137 1-131(g)
Concentration pCi/La.
Laboratory results Acceptance (4.66 Sigma)
Criteria LLD Activityb (4.66 Sigma)
< 2.81
< 10.0
< 0.60 0.55 + 0.45
< 1.0
< 1.66 0.62 +/- 1.11
< 3.2
< 0.29
-0.16 +/- 0.19
< 0.5
< 3.42
< 20.0 0.03 +/- 0.01
< 1.0
< 0.87 0.65 +/- 0.47
< 2.0
< 151.60
-5.40 +/-74.90
< 200.0
< 1.37
< 100.0
< 0.68
< 1.0
< 1.62
< 3.2 0.05 +/- 0.01
< 1.0
< 0.90 0.05 +/-0.01
< 2.0
< 0.54 0.90 +/- 0.32
< 3.2
< 0.33
< 0.5
< 3.02
< 100.0
< 4.99
< 100.0
< 0.48
< 3.2
< 0.35 0.28 +/- 0.28
< 1.0
< 1.22 0.54 +/- 0.86
< 3.2 0.04 +/- 0.02
< 1.0
< 0.65
< 2.0
< 0.73
< 5.0
< 0.56
< 1.0 0.03 +/- 0.01
< 1.0
< 0.93 1.11 +/- 0.55
< 2.0
< 178.00 18.57 +/- 89.13
< 200.0
< 0.45
< 1.0
< 2.18
< 100.0
< 6.13
< 10.0
< 7.19
< 20.0
Table A-4.
In-house "blank" samples.
Lab Concentration pCi/La.
Laboratory results Acceptance Sample Sample (4.66 Sigma)
Criteria Type Date Analysis LLD Activityb (4.66 Sigma)
Lab Code SPMI-4857 SPMI-4857 Low level of SPF-5183 SPF-5183 SPW-4689 SPW-4689 SPW-5373 SPW-5373 SPW-5373 SPW-5565 SPW-5565 SPW-5793 SPW-5793 SPW-5793 SPW-5793 SPW-6634 SPW-6634 SPW-6634 SPW-6634 SPW-6634 SPSO-10595 SPSO-10595 SPW-7746 SPW-7746 SPW-7747 SPAP-7765 SPAP-7767 SPAP-7767 SPAP-7767 SPMI-8348 SPMI-8348
< 0.66 1.15 +/- 0.32 MILK Jul 2000 Sr-89 MILK Jul2000 Sr-90 Sr-90 concentration in milk (1-5 pCi/L) is not FISH Jul2000 Cs-134 FISH Jul2000 Cs-137 WATER Jul2000 Gr. Alpha WATER Jul2000 Gr. Beta WATER Jul 2000 Co-60 WATER Jul2000 Cs-134 WATER Jul2000 Cs-137 WATER Aug 2000 Sr-89 WATER Aug 2000 Sr-90 WATER Aug 2000 Gr. Alpha WATER Aug 2000 Ra-226 WATER Aug 2000 Ra-228 WATER Aug 2000 Gr. Beta WATER Sep 2000 Fe-55 WATER Sep 2000 Ra-226 WATER Sep 2000 Ra-228 WATER Sep 2000 Gr. Alpha WATER Sep 2000 Gr. Beta SOIL Oct 2000 Cs-134 SOIL Oct 2000 Cs-137 WATER Oct 2000 Ra-226 WATER Oct 2000 Ra-228 WATER Oct 2000 H-3 AIR FILTER Oct 2000 Gr. Beta AIR FILTER Oct 2000 Co-60 AIR FILTER Oct 2000 Cs-134 AIR FILTER Oct 2000 Cs-137 MILK Oct 2000 Cs-134 MILK Oct 2000 Cs-137 unusual.
< 17.71
< 12.81
< 0.50
< 1.20
< 5.20
< 4.80
< 4.00
< 1.56
< 0.59
< 0.51
< 0.95
< 1.40
< 617.00
< 0.01
< 0.99
< 0.67
< 1.60
< 16.87
< 9.40
< 0.03
< 1.08
< 158.00
< 0.64
< 0.19
< 0.32
< 2.32
< 3.35
< 3.07
<5.0
<1.0
< 100.0
< 100.0
<1.0
<3.2
< 10.0
< 10.0
< 10.0
<5.0
<1.0
< 1.0
<1.0
<2.0
<3.2
< 1000.0
<1.0
<2.0
<1.0
<3.2
< 100.0
< 100.0
<1.0
<2.0
< 200.0
<3.2
< 100.0
< 100.0
< 100.0
< 10.0
< 10.0 A4-3
-0.64 +/-1.11 0.17 +/- 0.30 0.02 +/- 0.36 0.05 +/- 0.02 0.26 +/- 0.47
-0.13 +/- 1.01
-105.90 +/-453.40 0.03 +/- 0.01 0.36 +/-0.51
-0.22 +/- 0.45
-0.20 +/- 1.12 0.04 +/- 0.02 0.00 +/-_0.87
-38.00 +/- 77.00 0.00 +/- 0.00
Table A-4.
In-house "blank" samples.
Concentration pCi/La.
Laboratory results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Type Date Analysis LLD Activityb (4.66 Sigma)
SPF-8350 FISH Oct 2000 Cs-134
< 10.26
< 100.0 SPF-8350 FISH Oct 2000 Cs-137
< 10.51
< 100.0 SPW-8370 WATER Oct 2000 Co-60
< 4.67
< 10.0 SPW-8370 WATER Oct 2000 Cs-134
< 5.28
< 10.0 SPW-8370 WATER Oct 2000 Cs-137
< 4.93
< 10.0 SPW-7746 WATER Oct 2000 Gr. Alpha
< 0.46 0.06 + 0.33
< 1.0 SPW-7746 WATER Oct 2000 Gr. Beta
< 1.24 0.00 + 0.87
< 3.2 SPW-9103 WATER Nov 2000 Ra-226
< 0.01 0.02 _ 0.01
< 1.0 SPW-9103 WATER Nov 2000 Ra-228
< 1.00 0.14 +/- 0.48
< 2.0 SPW-9729 WATER Dec 2000 Gr. Alpha
< 0.46 0.23 + 0.36
< 1.0 SPW-9729 WATER Dec 2000 Gr. Beta
< 1.33
-0.46 +/- 0.98
< 3.2 SPW-9729 WATER Dec 2000 Ra-226
< 0.02 0.05 +/- 0.01
< 1.0 SPW-9729 WATER Dec 2000 Ra-228
< 0.70 0.22 +/- 0.35
< 2.0 SPW-9103 WATER Dec 2000 Gr. Alpha
< 0.51
-0.11 +/- 0.37
< 1.0 SPW-9103 WATER Dec 2000 Gr. Beta
< 1.21 0.55 +/- 0.91
< 3.2 SPCH-10583 CHARCOAL Dec 2000 1-131(g)
< 1.49
<9.6 CANISTER aLiquid 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.
A4-4
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes CF-23, 24 CF-23, 24 CF-23, 24 WW-65, 66 WW-65, 66 WW-65, 66 WW-686, 687 AP-1204, 1205 SW-68, 69 MI-277, 278 MI-277, 278 MI-277, 278 SW-728, 729 SW-728, 729 SW-403, 404 SWT-437, 438 PW-637, 638 PW-637, 638 PW-637, 638 SW-587, 588 SW-587, 588 SW-587, 588 SW-611, 612 SW-459, 460 WW-774, 775 WW-774, 775 WW-774, 775 SW-707, 708 SW-707, 708 SW-707, 708 CW-854, 855 SW-881, 882 SW-959, 960 SW-959, 960 PW-1055, 1056 PW-1055, 1056 PW-1055, 1056 A5-1 Sample Date Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Jan, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Feb, 2000 Analysis Gr. Beta K-40 Sr-90 Co-60 Cs-137 H-3 Gr. Beta Be-7 K-40 (FP) 1-131 K-40 Sr-90 Co-60 Cs-137 H-3 Gr. Beta Co-60 Cs-137 Gr. Beta Co-60 Cs-137 Gr. Beta H-3 Gr. Beta Co-60 Cs-137 H-3 Gr. Alpha Gr. Beta H-3 Gr. Beta H-3 Gr. Alpha Gr. Beta Co-60 Cs-137 Gr. Beta First Result 13.05 +/- 0.39 13.00 + 0.90 0.01 +/- 0.00
-0.53 +/- 1.62
-2.13 +/- 1.70 131.62 +/- 84.13 4.76 +/- 1.22 0.19 +/- 0.09 1.30 +/- 0.13
-0.08 +/- 0.27 1,664.70 +/- 113.20 0.63 +/- 0.42 0.39 +/- 1.79
-0.67+/- 1.86 795.21 +/- 109.04 1.73 +/- 0.57 4.90 +/- 2.92 2.73 +/- 2.51 1.67 +/- 1.31
-1.24 +/-- 1.86 1.35 - 1.94 3.80 +/- 1.56 2,229.26 +/-158.61 2.15 +/- 0.94 4.26 +/- 3.48
-1.19 +/- 3.78 2,841.35 +/- 174.48 2.20 +/- 1.73 7.90 +/- 1.70 117.00
- 92.00 2.13 +/- 1.36 1,794.91 +/- 145.81 1.04 +/- 1.00 1.24 +/- 0.89
-0.72 +/- 3.18 0.55 +/- 2.81 2.40 +/- 1.52 Second Result 12.46 +/- 0.36 11.73++/-0.79 0.01 +/- 0.00 0.44 +/- 2.11 0.41 +/- 2.35 182.81 +/- 86.33 4.59 +/-1.27 0.10 + 0.07 1.30 +/- 0.13
-0.00 +/- 0.26 1,431.30 t 90.30 0.51 +/- 0.40 1.04 +/- 1.53 1.22 +/- 1.38 857.22 +/- 111.09 2.60 - 0.58
-2.56 +/- 2.80
-1.68 +/- 2.71 4.00 +/- 1.59
-0.27+/- 1.79 0.23 +/- 1.80 6.76 +/- 1.75 2,115.19 +/-155.80 2.79 +/- 0.94 1.61 +/- 4.46 2.37 + 4.65 2,566.76+/-168.19 0.16 +/- 1.29 7.70-+/-1.70 69.00 +/- 90.00 1.34 +/- 1.25 1,762.31 +/- 144.95 0.92 +/- 0.67 1.79 +/- 0.90 1.73 +/- 1.89 0.90 +/- 1.86 2.20 - 1.50 Averaged Result 12.75 +/- 0.26 12.36 +/- 0.60 0.01 - 0.00
-0.04 + 1.33
-0.86 - 1.45 157.22+/- 60.27 4.67 - 0.88 0.14 : 0.06 1.30. 0.09
-0.04 +/-- 0.19 1,548.00 - 72.40 0.57 - 0.29 0.72
- 1.18 0.27 +/- 1.16 826.22.- 77.83 2.16 - 0.41 1.17 - 2.02 0.53 - 1.85 2.83. 1.03
-0.76. 1.29 0.79. 1.32 5.28 +/- 1.17 2,172.23 - 111.16 2.47 +/- 0.66 2.93 - 2.83 0.59 __ 2.99 2,704.05 - 121.17 1.18 - 1.08 7.80 +/- 1.20 93.00 +/- 64.35 1.74 - 0.93 1,778.61 +/-102.80 0.98 +/- 0.60 1.51 +/-t 0.63 0.51 - 1.85 0.72. 1.69 2.30 -t 1.07
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes MI-1079, 1080 MI-1079, 1080 MI-1079, 1080 CW-1156, 1157 SW-1967, 1968 SW-2468, 2469 WW-1402, 1403 LW-1269, 1270 MI-1541, 1542 AP-2113, 2114 CW-1571, 1572 CW-1693, 1694 SWT-1821, 1822 WW-1916, 1917 AP-2155, 2156 SWU-2547, 2548 CW-1798, 1799 AP-2176, 2177 WW-2046, 2047 SW-1967, 1968 SW-2241, 2242 SW-2241, 2242 WW-2342, 2343 WW-2711, 2712 WW-2711, 2712 WW-2511, 2512 SO-2435, 2436 SS-2669, 2670 SWU-2732, 2733 PW-2605, 2606 PW-2605, 2606 PW-2605, 2606 WW-2711, 2712 WW-2711, 2712 BS-3212, 3213 MI-2810, 2811 SW-3003, 3004 A5-2 Sample Date Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 Apr, 2000 May, 2000 May, 2000 Analysis Calcium K-40 Sr-90 H-3 Gr. Beta Sr-90 H-3 Gr. Beta K-40 Be-7 Gr. Beta Gr. Beta Gr. Beta H-3 Be-7 Sr-90 Gr. Beta Be-7 H-3 K-40 Gr. Alpha Gr. Beta Gr. Beta Cs-137 H-3 H-3 K-40 K-40 Gr. Beta Co-60 Cs-137 Gr. Beta H-3 Co-60 Gr. Beta K-40 Gr. Beta First Result 0.79 +/- 0.08 1,229.00 +/- 138.00 0.90 +/- 0.40 1,994.51 +/- 143.09 11.96 +/- 1.31 0.93 +/- 0.45 93.34 +/- 97.05 1.97 +/- 0.57 1,380.00 +/- 122.00 0.06 +/- 0.01 2.29 +/- 1.48 0.56 +/- 1.18 2.36 +/- 0.65 25.37 +/- 90.21 0.07 +/- 0.01 0.57 +/- 0.24 2.73 +/- 1.85 0.06 +/- 0.01 221.85 +/- 101.64 9.20 +/- 0.90 2.49 +/-1.44 8.37 +/- 1.36 4.20 +/-0.64
-0.76 +/-2.19 3,877.05 +/- 192.54 108.10 +/- 79.80 4.73 +/- 0.38 8.60 +/- 0.55 3.33 +/- 0.68 0.36 +/- 1.10
-0.07 +/- 0.93 1.51 +/- 1.31 3,877.00 +/- 192.50 0.97 +/- 1.93 7.90 +/- 1.97 1,285.00 +/- 111.00 5.06 +/- 0.73 Second Result 0.78 +/- 0.08 1,387.00 +/- 162.00 1.70 +/- 0.50 2,012.54 +/- 143.55 12.57+/-1.31 0.50 +/- 0.29 60.63 +/- 95.75 3.22 +/- 0.69 1,476.00 +/- 158.00 0.07 +/- 0.01 1.35 +/- 1.27 1.91 +/- 1.49 2.01 +/- 0.57 3.90 +/- 89.27 0.07 +/- 0.01 0.55 +/- 0.24 0.76 +/- 1.71 0.08 +/- 0.02 185.19 +/- 100.24 9.10 +/- 0.90 3.15 +/- 1.53 7.20 +/- 1.29 4.68 +/- 0.73 1.43 +/- 3.63 3,951.88 +/- 193.99 127.80 +/-80.70 4.83 +/- 0.53 9.18 +/- 0.45 3.19 +/- 0.69 1.05 +/- 2.03
-0.98 +/- 2.37 2.91 +/- 1.39 3,951.90 +/- 194.00 0.82 +/- 3.64 7.57+/- 1.88 1,338.00 +/- 127.00 5.27+/-0.73 Averaged Result 0.79 + 0.06 1,308.00 + 106.40 1.30 +/- 0.32 2,003.53 +/- 101.34 12.27 + 0.93 0.72 +/- 0.27 76.98 +/- 68.17 2.60 +/- 0.45 1,428.00 +/- 99.81 0.07 +/- 0.01 1.82 +/- 0.98 1.24 +/- 0.95 2.19 +/- 0.43 14.63 +/- 63.46 0.07 + 0.01 0.56 +/- 0.17 1.75 +/- 1.26 0.07 +/- 0.01 203.52 +/- 71.38 9.15 +/- 0.64 2.82 _+ 1.05 7.79 +/- 0.94 4.44 +/- 0.49 0.34 +/- 2.12 3,914.46 +/- 136.66 117.95 +/- 56.75 4.78 +/- 0.33 8.89 +/- 0.36 3.26 +/- 0.48 0.71 +/- 1.16
-0.53 +/- 1.27 2.21 +/- 0.96 3,914.45 - 136.65 0.90 +/- 2.06 7.74 +/- 1.36 1,311.50 +/- 84.34 5.17 +/- 0.52
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes SW-3003, 3004 F-2831, 2832 F-2831, 2832 WW-3128, 3129 BS-3411, 3412 BS-3411, 3412 F-3436, 3437 F-3436, 3437 F-2978, 2979 SS-3482, 3483 SS-3482, 3483 BS-3458, 3459 BS-3458, 3459 MI-3510, 3511 MI-3510, 3511 MI-3510, 3511 SO-3629, 3630 SO-3629, 3630 SO-3629, 3630 SW-3904, 3905 SW-3904, 3905 SW-3904, 3905 SW-3904, 3905 SP-3833, 3834 MI-3105, 3106 VE-3191, 3192 VE-3191, 3192 VE-3191, 3192 VE-3191, 3192 MI-3718, 3719 DW-3770, 3771 MI-3653, 3654 SW-4614, 4615 WW-3883, 3884 WW-3883, 3884 WW-3883, 3884 WW-3883, 3884 A5-3 Sample Date May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 May, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Analysis K-40 Co-60 Cs-137 Gr. Beta Co-60 Cs-137 Co-60 Cs-137 K-40 Cs-137 K-40 Co-60 Cs-137 Co-60 Cs-137 1-131 Cs-137 Gr. Beta K-40 Gr. Beta Co-60 Cs-137 Gr. Beta Gr. Alpha K-40 Be-7 Gr. Alpha Gr. Beta K-40 K-40 Gr. Beta K-40 Sr-90 H-3 Co-60 Cs-137 H-3 First Result 1.30 + 0.13 0.01 +/- 0.01
-0.00 + 0.01 5.41 +/- 1.35
-0.00 +/- 0.01 0.01 +/- 0.01 0.01 +/- 0.01 0.00 +/- 0.01 2.72 +/- 0.26 0.11 +/-0.03 11.26 +/- 0.57 0.01 +/- 0.01 0.04 +/- 0.01 0.48 +/-3.05 1.17 +/- 2.96
-0.06 +/- 0.25 0.23 +/-0.03 20.49 +/- 2.82 13.03 +/- 0.61 6.27 +/- 1.83
-0.65 +/- 1.54 0.19 +/-1.22 6.27 +/- 1.83 4.19 +/- 1.34 1,460.00 +/- 173.00 0.42 +/-0.23 0.15 +/- 0.06 3.76 +/- 0.13 3.58 +/- 0.43 1,447.00 +/- 165.00 5.92 +/- 1.32 1,407.00 +/- 170.00 0.50 +/- 0.27 4,401.80 +/- 204.60 0.91 +/-3.01 0.49 +/- 2.16 4,401.78 +/-204.63 Second Result 1.20 +/- 0.12 0.00 +/- 0.01 0.00 +/- 0.01 4.43 +/- 1.22 0.01 +/- 0.01 0.00 +/- 0.01 0.00 +/- 0.01
-0.00 +/- 0.00 2.14 +/- 0.30 0.12 +/- 0.03 11.37 +/- 0.54 0.02 +/- 0.01 0.03 +/- 0.02
-0.80 +/- 2.74 0.38 +/- 2.60
-0.04 +/- 0.24 0.20 +/-0.03 19.14 +/- 2.73 12.25 +/- 0.57 7.02 +/- 1.90 1.32 _ 1.77
-0.16 +/- 1.15 7.02 +/- 1.90 3.22 +/- 1.20 1,452.00 +/- 110.00 0.39 +/- 0.16 0.28 +/- 0.07 3.88 +/- 0.14 3.47 +/- 0.72 1,444.00 +/- 177.00 4.54 +/- 1.10 1,388.00 +/- 102.00 0.55 +/- 0.27 4,298.00 +/- 202.70
-0.28 +/- 1.52 0.66 +/- 1.82 4,297.96 +/- 202.67 Averaged Result 1.25 +/- 0.09 0.01 +/- 0.01 0.00 +/- 0.01 4.92 +/- 0.91 0.00 +/- 0.01 0.00 +/- 0.00 0.01 +/- 0.00
-0.00 +/- 0.00 2.43 +/- 0.20 0.12 +/- 0.02 11.32 +/- 0.39 0.01 +/- 0.01 0.03 +/- 0.01
-0.16 +/- 2.05 0.77 +/- 1.97
-0.05 +/- 0.17 0.22 +/- 0.02 19.82 +/- 1.96 12.64 +/- 0.42 6.65 +/- 1.32 0.33 +/- 1.17 0.01 +/- 0.84 6.64 +/-1.32 3.71 +/- 0.90 1,456.00 +/- 102.50 0.40 +/- 0.14 0.22 +/- 0.05 3.82 +/- 0.10 3.53 +/- 0.42 1,445.50+/- 120.99 5.23 +/- 0.86 1,397.50 +/- 99.13 0.53 +/- 0.19 4,349.90 +/- 144.00 0.32 +/- 1.69 0.57 +/- 1.41 4,349.87+/- 144.00
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes BS-3980, 3981 BS-3980, 3981 BS-3980, 3981 VE-4065, 4066 WW-4252, 4253 TSWU-4283, 4284 F-4438, 4439 SW-4459, 4460 WW-4480, 4481 SW-4375, 4376 SW-4375, 4376 AP-4712, 4713 AP-4754, 4755 SW-4537, 4538 SL-4636, 4637 SL-4636, 4637 SL-4636, 4637 SL-4636, 4637 G-4667, 4668 G-4667, 4668 G-4667, 4668 WW-4818, 4819 MI-4839, 4840 MI-4949, 4950 LW4991, 4992 MI-4903, 4904 MI-4881, 4882 MI-4881, 4882 G-5388, 5389 G-5388, 5389 G-5388, 5389 SWU-5473, 5474 SW-5410, 5411 PW-5550, 5551 WW-5623, 5624 MI-5529, 5530 VE-5745, 5746 A5-4 Sample Date Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Jul, 2000 Aug, 2000 Aug 2000 Analysis Cs-137 Cs-137 K-40 K-40 H-3 Gr. Beta Gr. Beta H-3 H-3 Gr. Beta Cs-137 Be-7 Be-7 H-3 Be-7 Gr. Beta K-40 Sr-90 Be-7 Gr. Beta K-40 H-3 K-40 K-40 Gr. Beta K-40 K-40 Sr-90 Be-7 K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Beta H-3 K-40 K-40 First Result 0.07 +/- 0.02 0.06 +/- 0.02 1,458.60 +/- 69.40 6.37 +/- 0.54 705.40 +/- 114.10 3.24 + 0.63 2.25 + 0.06 532.20 +/- 108.10 601.50 +/- 99.50 4.53 +/- 1.59
-0.09 +/- 1.61 0.07.-t+/-0.02 0.06 +/- 0.02 584.10 +/- 108.80 0.93 +/- 0.18 2.41 +/- 0.32 1.25 +/- 0.24 0.04 +/- 0.02 0.93 +/- 0.20 6.16 +/- 0.13 7.72 +/- 0.51 13.30 +/- 77.10 1,313.00 +/- 173.00 1,307.00 +/- 56.00 2.78 +/- 0.66 1,383.10 +/- 193.20 1,538.40 +/- 103.00 1.01 +/- 0.37 1.64 +/-0.16 5.51 +/- 0.33 5.64 +/- 0.15 3.50 +/- 0.67 1.95 +/- 0.81 0.71 +/- 1.15 "22,713.90 +/- 429.00 1,396.80 +/- 103.80 1.66 +/- 0.32 Second Result 0.08 +/- 0.02 0.07 +/- 0.02 1,421.90 +/- 52.20 6.34 +/- 0.51 718.90 +/- 114.60 3.11 +/-0.62 2.13 +/- 0.06 670.50 +/- 112.90 573.10 +/- 108.50 4.43+/-1.54
-0.43 +/- 1.39 0.09 +/- 0.02 0.07 +/- 0.01 599.20 +/- 109.30 0.56 +/- 0.12 2.69 +/- 0.32 1.13 +/- 0.30 0.05 +/- 0.03 0.98 +/- 0.31 6.68 +/- 0.14 8.43 +/- 0.83 29.70 +/- 77.90 1,398.00 +/- 161.00 1,346.00 +/- 58.00 2.22 +/- 0.55 1,328.00 +/- 153.10 1,438.00 +/-125.30 1.38 +/-+ 0.42 1.52 +/- 0.21 5.86 +/- 0.49 5.81 +/-0.15 3.17 +/- 0.61 1.89 +/- 1.04 2.50 +/- 1.49 22,265.50 +/- 424.90 1,278.20 +/- 117.50 1.93 +/- 0.33 Averaged Result 0.08 +/- 0.01 0.07 +/- 0.01 1,440.25 +/- 43.42 6.36 +/- 0.37 712.15 +/- 80.86 3.18 +/- 0.44 2.19 +/- 0.04 601.35 +/- 78.15 587.30 +/- 73.61 4.48 +/- 1.11
-0.26 +/- 1.06 0.08 +/- 0.01 0.07 +/- 0.01 591.65 +/- 77.11 0.75 +/- 0.11 2.55 +/- 0.23 1.19 +/- 0.19 0.05 +/- 0.02 0.96 +/- 0.18 6.42 +/- 0.10 8.08 +/- 0.49 21.50 +/- 54.80 1,355.50 +/- 118.16 1,326.50 +/- 40.31 2.50 +/- 0.43 1,355.55 +/- 123.25 1,488.20 +/- 81.10 1.19 +/- 0.28 1.58 +/- 0.13 5.69 +/- 0.30 5.73 +/-0.11 3.34 +/-0.45 1.92 +/- 0.66 1.61 +/- 0.94 22,489.70 +/- 301.90 1,337.50 +/- 78.39 1.80 +/- 0.23
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes MI-5808, 5809 CW-6514, 6515 MI-5933, 5934 MI-5933, 5934 VE-6002, 6003 VE-6002, 6003 PW-6209, 6210 SW-6291, 6292 WW-6312, 6313 WW-5981, 5982 PW-6341, 6342 CW-6514, 6515 MI-6409, 6410 MI-6409, 6410 MI-6409, 6410 MI-6542, 6543 MI-6450, 6451 MI-7102, 7103 MI-7102, 7103 SWT-7262, 7263 SWU-7283, 7284 SWU-7283, 7284 SW-7081, 7082 AP-7685, 7686 AP-7706, 7707 SW-7482, 7483 SP-7347, 7348 SW-7436, 7437 CW-7748, 7749 CW-7748, 7749 BS-7512, 7513 BS-7512, 7513 SL-7304, 7305 SL-7304, 7305 BS-7369, 7370 SO-7950, 7951 SO-7950, 7951 A5-5 Sample Date Aug, 2000 Aug, 2000 Aug, 2000 Aug 2000 Aug 2000 Aug, 2000 Aug, 2000 Aug& 2000 Aug, 2000 Aug, 2000 Aug 2000 Aug, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep,2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Analysis K-40 Gr. Beta Calcium Sr-90 Sr-90 K-40 H-3 Gr. Beta H-3 Gr. Beta Gr. Beta H-3 1-131 K-40 Sr-90 K-40 K-40 1-131 K-40 Gr. Beta Gr. Beta H-3 H-3 Be-7 Be-7 Gr. Beta Gr. Alpha H-3 Gr. Alpha Gr. Beta Cs-137 Gr. Beta Gr. Beta K-40 Cs-137 Ac-228 Bi-214 First Result 1,261.90 + 124.40 1.42 + 0.37 0.88 +/- 0.09 3.29 +/- 0.51 0.00 +0.00 1.44+/-0.23 528.20 +/- 112.70 4.14 +/- 1.58 7,804.20 +/- 262.70 4.85 +/- 0.78 2.45 +/- 1.42 5,600.10 +/- 226.80
-0.04 +/- 0.23 1,367.80 +/- 111.40 1.19 +/- 0.35 1,298.00 +/- 140.10 1,237.20 +/- 102.10
-0.11 +/- 0.23 1,473.10 +/- 101.40 3.45 +/- 0.66 2.75 +/- 0.55 197.76 +/- 94.07 89.32 +/- 92.99 0.07 +/- 0.01 0.06 +/- 0.01 5.31 +/- 1.75 6.12 +/- 1.54 40.60 +/- 79.90 0.47 +/- 0.28 2.35 +/- 0.39 0.84 +/- 0.06 13.52 +/- 1.61 2.94 +/-0.23 1.14 +/- 0.36 10.79 +/- 4.96 0.66 +/- 0.10 0.42 +/- 0.06 Second Result 1,234.40 +/- 152.80 1.44 +/- 0.41 0.89 +/- 0.09 1.72 +/- 0.47 0.00 +/- 0.00 1.78 +/- 0.18 578.50+/-114.50 1.95 +/- 1.32 7,221.70 +/-253.80 5.87 +/- 0.79 2.63 +/- 1.37 5,434.30 +/- 223.90 0.19 +/- 0.24 1,368.60 +/- 107.50 0.80 +/- 0.30 1,470.60 +/- 139.70 1,328.10 +/- 108.30
-0.02 +/- 0.25 1,400.70+/-168.60 2.32 +/- 0.57 2.87 +/- 0.56 172.31 +/- 93.00 42.38 +/-90.37 0.07 +/- 0.01 0.05 +/- 0.01 6.70 +/- 1.85 5.68 +/- 1.49 72.00 +/- 81.40 0.65 +/- 0.36 2.02 +/- 0.38 0.79 +/- 0.06 14.88 +/- 1.80 2.90 +/- 0.23 1.73 +/- 0.58 20.04 +/-- 9.40 0.77 +/- 0.10 0.57+/-0.07 Averaged Result 1,248.15 +/- 98.52 1.43 +/- 0.28 0.89 +/- 0.06 2.51 +/- 0.35 0.00 +/- 0.00 1.61+/- 0.14 553.35 +/- 80.33 3.05 +/- 1.03 7,512.95 +/- 182.64 5.36 +/- 0.56 2.54 +/- 0.99 5,517.20 +/- 159.35 0.08 +/- 0.17 1,368.20+/- 77.41 1.00 +/- 0.23 1,384.30 +/- 98.92 1,282.65 +/- 74.42
-0.07 +/- 0.17 1,436.90 +/- 98.37 2.89 +/- 0.44 2.81 +/- 0.39 185.04 +/- 66.14 65.85 +/- 64.83 0.07 +/- 0.01 0.05 +/- 0.01 6.01 +/- 1.27 5.90 +/- 1.07 56.30 +/- 57.03 0.56 +/- 0.23 2.19 +/- 0.27 0.81 +/- 0.04 14.20.+/- 1.21 2.92 +/- 0.17 1.44 +/- 0.34 15.41 +/- 5.31 0.72 +/- 0.07 0.49 +/- 0.05
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes SO-7950, 7951 SO-7950, 7951 SO-7950, 7951 SO-7950, 7951 SO-7950, 7951 SO-7950, 7951 VE-7554, 7555 MI-7622, 7623 F-8219, 8220 WW-7844, 7845 WW-8240, 8241 WW-8240, 8241 BS-8170, 8171 BS-8170, 8171 MI-8085, 8086 MI-8085, 8086 MI-8149, 8150 SO-8967, 8968 SO-8967, 8968 SO-8967, 8968 MI-8522, 8523 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 RW-8623, 8624 SWU-8894, 8895 MI-8802, 8803 MI-8802, 8803 MI-8802, 8803 MI-8802, 8803 A5-6 Sample Date Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Analysis Cs-137 Gr. Beta K-40 Pb-212 Ra-226 T1-208 Gr. Beta K-40 K-40 H-3 Gr. Beta H-3 Gr. Beta K-40 Calcium Sr-90 K-40 Be-7 Cs-137 K-40 1-131 Ag-110M Co-60 Cs-134 Cs-137 Gr. Alpha H-3 Mn-54 Pu-238 Pu-239/40 Sr-90 Zn-65 Gr. Beta 1-131 K-40 Sr-89 Sr-90 First Result 0.20 +/- 0.31 29.22 +/- 1.98 21.36 +/- 0.93 0.72+/-0.12 1.21 +/- 0.33 0.21 +/- 0.04 0.73 +/- 0.02 1,505.90 +/-142.70 2.94 +/- 0.22
-68.13 +/- 74.09 0.35 +/-1.89 72.46 +/- 92.95 11.96 +/- 2.55 8.36 +/- 0.46 0.94 1.04 +/- 0.35 1,358.10 +/- 95.81 1.25 +/- 0.37 0.05 +/- 0.02 4.53 +/- 0.66
-0.05 +/- 0.23 99.79 +/-18.18 2.47 +/- 0.10 228.46 +/- 17.29 3.59 +/- 0.20 14.57 +/- 5.86 785.70 +/- 5.98 1.06 +/- 0.20 1.24 +/- 0.54 3.45 +/- 0.88 0.92 +/- 0.08 86.33 +/- 46.77 3.63 +/-0.62
-0.22 +/- 0.24 1,340.50 +/- 113.80 0.19 - 1.31 1.10 +/- 0.39 Second Result 0.21 +/- 0.04 28.02 +/- 1.98 21.77 +/- 0.89 0.92 +/- 0.12 1.30 +/- 0.31 0.25 +/- 0.03 0.74+/-0.02 1,453.60+/-172.00 3.39 +/- 0.38 84.23 +/- 81.38 1.61 +/- 2.28 38.87 +/- 91.51 11.30 +/- 2.39 8.76 +/- 0.47 0.94 0.75 +/- 0.31 1,341.80 +/- 178.00 1.27 +/- 0.35 0.05 +/-0.02 4.46 +/- 0.58 0.18 +/- 0.25 118.64 +/- 21.79 2.56 +/- 0.10 229.75 +/-13.39 3.79 +/-0.20 8.07 +/- 4.74 786.80 +/- 5.97 1.31 +/- 0.20 1.11+/-0.47 3.42 +/- 0.81 0.95 +/- 0.10 137.07 +/- 46.07 2.45 +/- 0.61
-0.25 +/- 0.26 1,453.50+/-100.50 0.61+/- 1.34 0.90 +/- 0.38 Averaged Result 0.20 +/- 0.16 28.62 + 1.40 21.56 + 0.64 0.82 +/-0.09 1.26 +/- 0.22 0.23 +/- 0.02 0.74 +/- 0.01 1,479.75 +/- 111.74 3.16+/- 0.22 8.05 +/- 55.03 0.98 +/- 1.48 55.66 +/- 65.22 11.63 + 1.75 8.56 +/- 0.33 0.94 0.90 +/- 0.24 1,349.95 +/- 101.07 1.26 +/- 0.26 0.05 +/- 0.02 4.50 +/- 0.44 0.07 +/- 0.17 109.21 +/- 14.19 2.51 +/- 0.07 229.11 +/- 10.93 3.69 +/- 0.14 11.32 +/- 3.77 786.25 +/- 4.22 1.19 +/- 0.14 1.17 +/- 0.36 3.44 +/- 0.60 0.94 +/- 0.06 111.70 +/- 32.82 3.04 +/- 0.43
-0.24 +/- 0.18 1,397.00 +/- 75.91 0.40 +/- 0.94 1.00 +/- 0.27
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes LW-8823, 8824 VE-9014, 9015 VE-9014, 9015 F-9469, 9470 PW-9991, 9992 SW-9991, 9992 SW-9991, 9992 SW-9991, 9992 DW-9682, 9683 MI-9749, 9750 MIv-9776, 9777 PW-10234, 10235 DW-10302, 10303 AP-10845, 10846 AP-10845, 10846 AP-10845, 10846 AP-10782, 10783 AP-10824, 10825 AP-10866, 10867 AP-10866, 10867 AP-10866, 10867 WW-10424, 10425 SW-10596, 10597 LW-10529, 10530 aAll 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.
A5-7 Sample Date Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Dec, 2000 Analysis Gr. Beta Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Co-60 Cs-134 Cs-137 Gr. Beta K-40 K-40 H-3 Gr. Beta Co-60 Cs-134 Cs-137 Be-7 Be-7 Co-60 Cs-134 Cs-137 H-3 H-3 Gr. Beta First Result 2.13 k 0.55 0.10 _- 0.06 5.59 +/- 0.17 5.51+/-1.34 2.50 +/- 0.01 1.16 +/-1.70
-0.07 +/- 1.85
-0.88 +/- 1.67 1.61 +/- 1.02 1,562.40+/-118.70 1,185.90 +/- 88.05 104.66 +/- 93.36 2.23 +/- 1.62
-0.00 +/- 0.00 0.00 +/- 0.00 0.00 +/- 0.00 0.21 +/- 0.10 0.06 +/- 0.02 0.00 +/- 0.00
-0.00 +/- 0.00 0.00 +/- 0.00 1,690.87 +/- 137.81 445.47 +/- 106.70 2.21 +/- 0.45 Second Result 1.59. 0.52 0.15 +/- 0.07 5.90 +/- 0.19 5.16 +/- 1.12 3.49 +/- 1.18
-2.94 +/- 3.39 2.27 +/- 3.73 3.84 +/- 3.45 2.10 +/- 0.94 1,495.90 +/- 168.30 1,409.60 +/- 175.80 110.62 +/- 93.61 2.08 +/- 1.62 0.00 +/- 0.00 0.00 +/- 0.00
-0.00 +/- 0.00 0.31 +/- 0.14 0.07 +/- 0.01
-0.00 +/- 0.00 0.00 +/- 0.00 0.00 +/- 0.00 1,551.48 +/- 1,339.42 423.46 +/- 105.87 2.06 +/- 0.40 Averaged Result 1.86 + 0.38 0.12 +/- 0.05 5.74 +/- 0.13 5.34 +/- 0.87 3.00 +/- 0.59
-0.89 +/- 1.89 1.10 +/- 2.08 1.48 +/- 1.92 1.86 +/- 0.69 1,529.15 +/- 102.97 1,297.75 _ 98.31 107.64 +/- 66.11 2.16 +/- 1.15
-0.00 +/- 0.00 0.00 + 0.00 0.00 +/- 0.00 0.26 +/- 0.09 0.06 +/- 0.01 0.00 h 0.00
-0.00 k 0.00 0.00 +/- 0.00 1,621.18 +/- 673.25 434.47 +/- 75.16 2.14 +/- 0.30
Table A-6.
Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentrationb Lab Sample Date MAPEP Resulte Control Code Type Collected Analysis Laboratory resultc Is, N=1 Limits STSO-882 SOIL Jan, 2000 Am-241 64.90 +/- 6.49 61.10 STSO-882 SOIL Jan, 2000 Co-57 721.10 +/- 83.80 949.00 The MAPEP soil sample (STSO-882), as received, did not closely match a standard gamma results for gamma-emitting isotopes are reanalyses, with a reduced sample size.
STSO-882 SOIL Jan, 2000 Co-60 1,264.40 +/- 78.60 1,180.00 STSO-882 SOIL Jan, 2000 Cs-134 969.30 +/- 76.90 1,047.00 STSO-882 SOIL Jan, 2000 Cs-137 944.00 +/- 92.00 930.00 STSO-882 SOIL Jan, 2000 K-40 811.70 +/- 79.90 652.00 STSO-882 SOIL Jan, 2000 Mn-54 1,103.30 +/- 64.20 1,023.00 STSO-882 SOIL Jan, 2000 Ni-63 711.00 +/- 71.10 960.00 STSO-882 SOIL Jan, 2000 Pu-239/40 67.90 +/- 6.79 74.40 STSO-882 SOIL Jan, 2000 Sr-90 345.00 +/- 34.50 304.00 STSO-882 SOIL Jan, 2000 U-233/4 62.90 +/- 6.29 90.00 Incomplete dissolution of the sample is suspected.
Results of reanalysis: U-233/234 67.3 +/- 3.3 pCi/g, U-238 68.1 +/- 8.9 pCi/g.
STSO-882 SOIL Jan, 2000 U-238 63.20 + 6.32 STSO-882 SOIL Jan, 2000 Zn-65 1,544.30 +/- 61.50 93.00 1,540.00 42.77 - 79.43 664.30 - 1,233.70 geometry. The 826.00 - 1,534.00 732.90 - 1,361.10 651.00 - 1,209.00 456.40 - 847.60 716.10 - 1,329.90 672.00 - 1,248.00 52.08 - 96.72 212.80 - 395.20 63.00 - 117.00 65.10 - 120.90 1,078.00 - 2,002.00 aResults obtained by Environmental Inc., 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, laboratory results are given as the mean t 1 standard deviations for three determinations.
d Results are presented as the known values, 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)a.
Lab Code STSO-870 STSO-870 STSO-870 STSO-870 STSO-870 STSO-870 STSO-870 STSO-870 STSO-870 STSO-870 STVE-871 STVE-871 STVE-871 STVE-871 STVE-871 STVE-871 STAP-872 STAP-872 STAP-872 STAP-872 STAP-872 STAP-872 STAP-872 STAP-872 STAP-872 Result STAP-872 STAP-872 STW-874 STW-874 Concentration b Date Control Collected Analysis Laboratory resultc EML Result Limitse Saihple Type SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER within activity AIR FILTER AIR FILTER WATER WATER Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000
-h error margin.
Mar, 2000 Mar, 2000 Mar, 2000 Mar, 2000 Ac-228 Bi-212 Bi-214 Cs-137 K-40 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Co-57 Co-60 Cs-137 Gr. Alpha Gr. Beta Mn-54 Pu-238 Pu-239/40 Ru-106 Sr-90 Uranium Am-241 Co-60 98.300 +/- 7.100 98.500 +/- 15.100 88.000 +/-3.800 324.000 +/- 5.000 872.000 +/- 34.000 93.700 +/-2.700 100.100 +/- 3.700 19.800 +/- 3.000 8.100 +/- 1.700 13.600 +/- 3.100 9.800 +/- 0.900 46.500 +/-2.100 1,872.000 +/- 46.000 506.400 +/- 28.000 14.300 +/- 1.500 1,198.000+/-85.000 5.900 +/- 0.100 5.900 +/- 0.100 7.500 +/- 0.100 3.300 +/- 0.100 2.700 +/- 0.100 31.800 +/- 0.300 0.060 +/- 0.030 0.090 +/- 0.010 3.500 +/- 1.000 0.310 +/- 0.160 0.120 _ 0.010 1.700 +/- 0.220 51.000 +/- 1.200 A7-1 97.600 106.000 86.700 339.000 811.000 97.300 86.500 18.600 7.000 20.200 10.400 52.800 1,380.000 521.000 15.500 1,780.000 5.310 5.320 6.100 3.020 2.420 27.200 0.080 0.089 2.010 0.242 0.126 1.950 48.900 0.79-1.75 0.42-1.22 0.75-1.42 0.83-1.32 0.78-1.53 0.74-1.33 0.65-1.45 0.52-2.84 0.69-1.74 0.60- 3.66 0.68 - 2.70 0.69-1.46 0.80- 1.40 0.79-1.42 0.68-1.59 0.50- 1.33 0.65-1.39 0.75-1.32 0.73-1.37 0.50- 1.55 0.72-1.67 0.76-1.33 0.74-1.40 0.76-1.44 0.59-1.30 0.61 - 1.93 0.80 - 3.35 0.75-1.49 0.80- 1.20
Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)a.
Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory resultc EML Resultd Limitse STW-874 STW-874 STW-874 STW-874 STW-874 Analysis STW-874 STW-874 STW-874 STW-874 STW-874 Result r*
STSO-885 STSO-885 STSO-885 STSO-885 STSO-885 STSO-885 STSO-885 STSO-885 STSO-885 STSO-885 STSO-885 STW-886 STW-886 STW-886 STW-886 STW-886 STW-886 STW-886 WATER WATER WATER WATER WATER was repeated; WATER WATER WATER WATER WATER
!ported was for SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL WATER WATER WATER WATER WATER WATER WATER Mar, 2000 Cs-137 108.600 _ 1.800 Mar, 2000 Fe-55 33.000
- 1.200 Mar, 2000 Gr. Alpha 1,217.000 + 35.000 Mar, 2000 Gr. Beta 792.000 + 25.000 Mar, 2000 H-3 147.000 + 26.000 result of reanalysis; 97.5 + 11.6 Bq/1.
Mar, 2000 Ni-63 101.000 +/- 6.000 Mar, 2000 Pu-238 0.750 +/- 0.170 Mar, 2000 Pu-239/40 0.990 +/- 0.090 Mar, 2000 Sr-90 4.460 +/- 0.990 Mar, 2000 Uranium 0.270 +/- 0.020 U-234. Result for U (total); 0.58 +/- 0.02 pCi/L.
Sep, 2000 Ac-228 78.000 +/- 1.500 Sep, 2000 Bi-212 73.000 +/- 3.300 Sep, 2000 Bi-214 91.000 +/- 4.000 Sep, 2000 Cs-137 925.700 +/- 14.200 Sep, 2000 K-40 713.600 +/- 7.100 Sep, 2000 Pb-212 66.100 +/- 4.300 Sep, 2000 Pb-214 100.100 + 3.700 Sep, 2000 Pu-239/40 18.400 +/- 0.400 Sep, 2000 Sr-90 39.900 +/- 5.300 Sep, 2000 Th-234 154.700 :t 9.300 Sep, 2000 Uranium 254.300 +/- 13.000 Sep, 2000 Am-241 1.300 +/- 0.200 Sep, 2000 Co-60 71.900 +/- 7.200 Sep, 2000 Cs-137 62.700 +/- 6.300 Sep, 2000 H-3 92.300 +/- 8.900 Sep, 2000 Pu-238 0.700 +/- 0.100 Sep, 2000 Pu-239/40 0.600 +/-0.100 Sep, 2000 Sr-90 4.600 +/- 0.400 A7-2 103.000 33.100 1,700.000 690.000 79.400 112.000 0.944 0.918 3.390 0.995 80.200 80.500 83.300 1,020.000 713.000 79.300 86.300 16.800 50.400 148.000 327.000 1.190 73.700 67.000 91.300 0.786 0.591 4.530 0.80- 1.26 0.44-1.53 0.61 - 1.32 0.55-1.54 0.71 - 1.79 0.25 - 1.75 0.78 - 1.25 0.80- 1.39 0.75-1.50 0.67-1.42 0.80- 1.50 0.45 - 1.23 0.78 - 1.50 0.80 - 1.29 0.80 - 1.37 0.74-1.36 0.76-1.53 0.71 - 1.33 0.61 - 3.91 0.68 - 2.36 0.62-1.35 0.76 - 1.48 0.80- 1.20 0.80 - 1.24 0.74 - 2.29 0.74 - 1.22 0.75-1.26 0.64-1.50
Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)a.
Concentration b Lab Sample Date Control Code Type Collected Analysis STW-886 STW-887 STW-887 STAP-888 STAP-888 STAP-888 STAP-888 STAP-888 STAP-888 STAP-888 STAP-888 STAP-888 STAP-888 Result STAP-888 STAP-889 STAP-889 STVE-890 STVE-890 STVE-890 STVE-890 STVE-890 STVE-890 WATER WATER WATER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER within activity AIR FILTER AIR FILTER AIR FILTER VEGETATIOI',
VEGETATIOIN VEGETATIO1N VEGETATIOb' VEGETATIOI' VEGETATIOIP Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000 Sep, 2000
-t error margin.
Sep, 2000 Sep, 2000 Sep, 2000 I Sep, 2000 J
Sep, 2000 4
Sep, 2000 J Sep, 2000 4
Sep, 2000
.4 Sep, 2000 Uranium Gr. Alpha Gr. Beta Am-241 Co-57 Co-60 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Gr. Alpha Gr. Beta Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-239/40 EML Result" Limits' Laboratory result' 0.800 +/- 0.100 1,113.700 +/- 17.900 1,129.400 +/- 16.700 0.060 +/- 0.010 16.500 +/- 0.600 9.200 +/- 0.400 8.800 +/- 0.500 50.200 +/- 2.300 0.033 +/-0.010 0.080 +/- 0.010 3.300 +/- 0.100 0.034 +/- 0.001 0.032 + 0.010 0.070 +/- 0.010 2.840 +/- 0.010 2.080 +/- 0.020 5.900. 1.200 3.200 +/- 0.100 29.400 +/- 0.400 739.300 +/- 23.000 597.500 +/- 49.300 4.500 +/- 0.200 No reason for deviation was found with original result. The result of reanalysis; 12.1 +/-k1.1 STVE-890 VEGETATION Sep, 2000 Sr-90 1,201.500 + 117.300 1,150.000 0.916 1,070.000 950.000 0.032 14.500 8.430 7.410 43.200 0.045 0.074 1.640 0.040 0.041 0.083 2.350 1.520 5.600 3.600 32.800 867.000 639.000 9.600 A7-3 0.73-1.37 0.58-1.26 0.56-1.50 0.69 - 2.40 0.69-1.37 0.79-1.30 0.78-1.35 0.80- 1.36 0.66-1.35 0.69-1.29 0.55-2.05 0.80- 1.92 0.80- 1.59 0.80- 2.54 0.57-1.47 0.76-1.52 0.72-2.34 0.61-1.61 0.75-1.51 0.80- 1.37 0.78 - 1.43 0.67-1.49 Bq/kg.
0.52-1.23
Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)a.
Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory result' EML Resultd Limitse 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 intBq/Kg.
C Laboratory 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.
" The control limits are reported by EML as the ratio of Reported Value / EML value.
A7-4
APPENDIX B DATA REPORTING CONVENTIONS B-1
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; Xl +/- Sl and X2 +/- s2 s2
.2 Reported result:
x +/- s; where x = (1/2) (xI + x2) and s = (1/2) s1+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 4-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 x1, x2... xn are defined as follows:
-1x-
)2_
Y-n x
s=
n-1 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/m3 )
Water (pCi/L)
Gross alpha I x 10-3 Strontium-89 8,000 Gross beta 1
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 Sampling Location Maps D-1
TLD LOCATIONS ONE MILE RADIUS J
PLANT AREA ENLARGED PLAN
[1.00 MILE RADIUS]
[NO SCALE]
MONITORING LEGEND:
C) N.S.P. TLD POINTS D-2 TLD0LOGN D-2 TLDOI.DGN
TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGEND:
0 N.S.P. TLD POINTS D-3 TLD02.DGN
TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
0 N.S.P. TLD POINTS D-4 TLD03.DGN
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS J
PLANT AREA ENLARGED PLAN
[1.00 MILE RADIUS]
[NO SCALE]
MONITORING LEGEND MILK SAMPLING POINT IM NUMBERS P-14. P-18. P-37. P-41 A*
AIR SAMPLING POINT ID NUMBERS P-1, P-2. P-3, P-4, P-S WATER SAMPLING POINT ID NUMBERS P-5, P-B, P-8. P-9. P-11, P-24, P-41 El VEGETATION / VEGETABLES ID NUMBERS P-24. P-38 e]
FISH SAMPLING POINT ID NUMBERS P-13, P-19 INVERTEBRATES POINT ID NUMBERS P-6. P-40 SEDIMENT SAMPLING POINT ID NUMBERS P-f. P-12, P-20 D-5 SAMPOI.DGN
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS 4.7 MONITORING LEGEND SAMPLING POINT ID NUMBERS P-14. P-18. P-37, P-41 A*
AIR SAMPLING POINT ID NUMBERS P-i, P-2, P-3, P-4, P-6 SAMPLING POINT ID NUMBERS P-5. P-6. P-B, P-9. P-11, P-24, P-41 r*
VEGETATION / VEGETABLES ID NUMBERS P-24, P-38 FISH SAMPLING POINT ID NUMBERS P-13o P-i9 INVERTEBRATES POINT ID NUMBERS P-6. P-40 SEDIMENT SAMPLING POINT ID NUMBERS P-S. P-12, P-20 D-6 SAMP03.DGN
ENVIRONMENTAL SAMPLING POINTS CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND
- 4.
MILK SAMPLING POINT ID NUMBERS P-14, P-18, P-37, P-41 A
AIR SAMPLING POINT ID NUMBERS P-i. P-2, P-3. P-4. P-6 0
WATER SAMPLING POINT ID NUMBERS P-5, P-6,, P-8, P-% P-11. P-41 n
VEGETATION / VEGETABLES ID NUMBERS P-24, P-38 D-7 SAMP02.DGN P-1
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HUPPERT FARM. W 1430 ST RD 29, FRVER FALLS, WL E] CAIN RESIDENCE, N73%5 %
ST. RIVER FALLS, W*.
D-7 SAMP02.DGN