ML061280040
| ML061280040 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/05/2006 |
| From: | Thomas J. Palmisano Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2010-0209, L-PI-06-037 | |
| Download: ML061280040 (61) | |
Text
U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie lsland Nuclear Generating Plant Units 1 and 2 Dockets 50-282, 50-306 and 72-1 0 License Nos. DPR-42, DPR-60 and SNM-2506 2005 Annual Radiological Environmental Monitorinq Program (REMP) Report Pursuant to Prairie lsland Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and pursuant to Prairie lsland Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License SNM-2506, the Nuclear Management Company, LLC submits one copy of the Annual Radiological Environmental Monitoring Program report for the period January 1,2005 through December 31,2005.
Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
Thomas J. Palmisano Site Vice President, Prairie lsland Nuclear Generating Plant Nuclear Management Company, LLC Enclosure (1) cc:
Regional Administrator, USNRC, Region Ill Project Manager, Prairie lsland Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie lsland Nuclear Generating Plant Dr. John House, USNRC, Region Ill Director of NMSS, USNRC Tim Donakowski, State of Minnesota PI Dakota Community Environmental Coordinator 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121
ENCLOSURE 1 Annual Report to the United States Nuclear Regulatory Commission Radiation Environmental Monitoring Program January 1,2005 through December 31,2005 59 pages to follow
Midwest Laboratorv
/
an Allegheny Technologies Co. '
700 Landwehr Rmd Northbmok, 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 lSFSl Docket No.72-10 SNM-2506 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31,2005 Prepared under Contract by ENVIRONMENTAL, Inc.
MIDWEST LABORATORY Project No. 8010 Approved:
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.
Section TABLE OF CONTENTS Preface........................................................................................................................................ ii List of Tables................................................................................................................................ iv List of Figures................................................................................................................................... v
1.0 INTRODUCTION
.............................................................................................................................. 1 2.0
SUMMARY
........................................................................................................................................ 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP)............................................ 3 Program Design and Data Interpretation................................................................................ 3 Program Description............................................................................................................... 4 Program Execution................................................................................................................. 5 3.4 Laboratory Procedures............................................................................................................ 5 3.5 Program Modifications............................................................................................................ 6 3.6 Land Use Census................................................................................................................... 6 4.0 RESULTS AND DISCUSSION......................................................................................................... 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents..................................................... 7 4.2 Summary of Preoperational Data............................................................................................ 7 4.3 Program Findings.................................................................................................................... 8 5.0 FIGURES AND TABLES................................................................................................................ 12
6.0 REFERENCES
CITED................................................................................................................... 25 APPENDICES A
Interlaboratory Comparison Program Results.............................................................................. A-I. Acceptance Criteria for "Spiked" Samples...................................................... A-2 B
Data Reporting Conventions...................................................................................................... B-I C
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas C-1 D
Sampling Location Maps.............................................................................................................. D-I iii
LIST OF TABLES No. -
Title Pane 5.1 Sample Collection and Analysis Program 15 5.2 Sampling Locations............................................................................................................................
16 5.3 Missed Collections and Analyses.......................................................................................................
19 5.4 Radiation Environmental Monitoring Program Summary................................................................... 20 In addition, the following tables are in the Appendices:
Appendix A A-1 Environmental Resources Associates. Crosscheck Program Results.......................................... Al-I A-2 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 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas........................................................................... C-2
LIST OF FIGURES No. -
j-i&
Pane 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control...................................................................................................................... 13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-I).............................................................................. I 4
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, 2005. 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, 2006b) 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.
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 2005 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.
3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Proaram 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-1 37, 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 of corrosion products.
They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
3.1 Proaram Desian and Data Interpretation (continued)
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 Proaram Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie lsland 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 lSFSl 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, 2005). Maps of fixed sampling locations are included in Appendix D.
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Airborne iodine is collected by continuous pumping through charcoal filters at these same locations. Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (P-I), and four are indicators (P-2, P-3, P-4, and P-6).
Offsite ambient gamma radiation is monitored at thirty-four locations, using CaS04: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 ElML quarterly for annealing and repackaging.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaS04: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 six farms (five 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 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.
3.2 Proqram Description (continued)
Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-1 31, 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 Pronram Execution The Program was executed as described in the preceding section with the following exceptions:
(1) No milk was available from location P-44 for the months of January, February, March, November and December, 2005.
Deviations from the program are summarized in Table 5.3.
3.4 Laboratory Procedures Analyses for iodine-131 in milk and drinking water utilize a sensitive radiochemical procedure involving the separation of the element by ion-exchange and subsequent beta counting. Gamma-spectroscopic analysis is performed using a high-purity germanium (HPGe) detector. Levels of airborne iodine-1 31 in charcoal samples are measured by gamma spectroscopy.
Levels of iodine-131 in cabbage are determined by gamma spectrometry.
Tritium levels are 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 the data obtained. Details of the Quality Assurance Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003). The program includes participation in lnterlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.
3.5 Proaram Modifications The Yoemans' Farm (P-44) was added to the program in January, 2005, as an indicator location for goat milk.
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 of2the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft 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 Land Use Census was completed in August and September, 2005. There were no changes to any of the highest DIQ locations for nearest residence, milk animal or garden sites. A goat dairy location was established in 2005 with a higher DIQ than the other dairy farms. The critical receptor location did not change in 2005, 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.
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 Atmos~heric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2005. The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents involving a release to the environment at nuclear reactor facilities in 2005.
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 2
2 fallout declined yearly from a level of 12,167 pCiIm to 1,020 pCiIm, and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mRl4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 p~ilm3.
Average present day levels have stabilized at around 0.025 p~ilmd.
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, 1-1 31, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCiIL. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCiIg for gross beta and 0.47 pCiIg for Cs-137. Gross beta measured in soil averaged 52 pCiIg.
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 pCiIL to 490 pCi1L. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCiIL in downstream Mississippi River water, 8.2 pCilL for well water, and 11.0 pCilL for lake water.
Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCiIg. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCilg upstream and 0.21 pCiIg 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 pCilg, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCiIg, 46.0 pCiIg, and 13.6 pCilg, respectively.
4.3 Proararn Findinqs Slight tritium activity was detected in two downstream river water composites (pg. 11). It was determined that the collections coincided with planned radioactive discharges from the plant. All other results indicate background levels of radioactivity in environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
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 16.3 mR191 days at inner ring locations to 17.2 mRI91 days at outer ring locations. The mean at special locations was 16.1 mW91 days and 16.3 mW91 days at the control location.
Dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1990 through 2004. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).
Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR191 days).
Year ISFSl Facilitv Operations Monitoring Ambient radiation was measured inside the ISFSl earth berm, outside the ISFSl earth berm and at two special locations between the plant ISFSl and the Prairie Island Indian Community. The mean dose rates measured 86.2 mR191 days inside the ISFSl earth berm and 20.2 mW91 days outside the ISFSl earth berm. Three additional casks were placed on the ISFSl pad in 2005, a total of twenty loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.
Average (Inner and Outer Rinqs)
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 ISFSl Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.9 and 15.5 mRl91 days.
Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSl SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).
Control Year Average (Inner and Outer Rings)
Control
Airborne Particulates Average annual gross beta concentrations in airborne particuiates were slightly higher at 3
indicator versus control locations (0.027 pCi/m and 0.025 pCi/m, respectively) and similar to levels observed from 1990 through 2004. The results are tabulated below.
3 Concentration (~Cilm )
I I
Year Average annual gross beta concentrations in airborne particulates.
A spring peak in beta activity had been observed almost annually for many years (Wilson et a/.,
1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et a/., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983.
Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1990 through 2005.
Average of Indicators 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., 2006).
Control 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.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m3 in all samples. There was no indication of a plant effect.
Iodine-131 results were below the detection limit of 0.5 pCi/L in all samples. Cs-137 results were below the LLD level of 5 pCilL 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 2005 show no radiological effects of the plant operation.
Drinkinq Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 179 pCi1L in all samples.
Gross beta concentrations averaged 11.5 pCilL throughout the year, ranging from 8.3-14.0 pCi1L. These concentrations were similar to or slightly higher than levels observed from 1990 through 2004. The most likely contribution is the 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 2005 data of any effect of plant operation.
Average annual concentrations; Gross beta in drinking water Year Gross Beta
( pCilL)
River Water For the first and fourth quarters of 2005, measurable tritium was detected in downstream river water composites, at concentrations of 478 and 214 pCi/L, respectively. This is well below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L. For the remaining upstream and downstream collections, tritium levels measured below the LLD level of 173 pCi/L.
Gamma-emitting isotopes were below detection limits in all samples.
Well Water At the control well P-43, 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 194 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2005 show no radiological effects of the plant operation.
Crops Three samples of broadleaf vegetation, cabbage leaves, were collected in July and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.013 pCi/g wet weight in all 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.
Field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required.
Fish samples were collected in May and September, 2005 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 Peri~hVton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2005. With the exception of naturally occurring potassium-40, all gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.
Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in May and September, 2005 and analyzed for gamma-emitting isotopes. Trace levels of cesium-137 were detected in two of the six samples collected, measuring 0.026 pCi/g dry weight in one downstream sample and one control sample, indicating the influence of fallout deposition.
The only other gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.
5.0 FIGURES AND TABLES
Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.
I --t Indicator /
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
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)'
~requency~
FrequencyC Ambient radiation OLD'S) 5 4 P41A - P-10A c/Q Ambient gamma P-OIB - P-15B P-OIS - P-OS P-OIIA - P-081A P-OIIB - P-0818 P-OlIX-P-O41X, P-01C Airborne Particulates Airborne Iodine Milk River water Drinking water Well water Edible cultivated crops -
leafy green vegetables c/w GB, GS (QC of each location) 5 P-14, P-18, P-37, P-42, P-44, G / M ~
1-131, GS P-43 (C) 5 P-6, Pa, P-9, P-24, P-43 (C)
G/w GB(MC), C131(MC)
Fish (one species, edible portion) 2 P-19(C), P-13 Periphyton or invertebrates 2
P40(C), P-6 Bottom sediment 2
P-20(C), P-6 Shoreline sediment 1 P-12 a Location codes are defined in Table D2. Control stations are indicated by (C). All other stations are indicators.
Collection type is coded as follows: C/ = continuous, G/ - grab. Collection frequency is coded as follows:
W-weekly, M = monthly, Q -quarterly, SA - semlannualiy, A = annually.
Analysis type is coded as follows: GB - gross beta, GS - gamma spectroscopy, H tritium, 1-131 = iodine-131.
Analysis frequency is coded as follows: MC - monthly composite, QC - quarterly composite.
Milk is collected biweekly during the grazing season (May - October).
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Code Typea Collection Site Distance and Direction from Sample ~ y p e ~
Reactor C
Air Station P-1 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 C
Upstream of Plant Rother Farm C
Peterson Farm Yoemans Farm 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 AP, Al AP, Al AP, Al AP, Al RW AP, Al, RW WW, BS, BOC WW WW DW ss F~
M M
F~
BS VE, WW M
VE BOC M
M, WW M
TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 1.6 mi @ 12g0/SE 1.0 mi @ 3 2 I 0 / w ~ W 0.3 mi Q 306O/NW 3.3 mi @ 15S0/SS~
3.0 mi @ l l G O / ~ S E 3.5 mi Q 113O/ESE 2.3 mi Q 173O/S 3.8 mi @ 88O/~
1.3 mi Q OO/N 0.9 mi Q 45O/NE 0.6 mi 8 15g0/SSE 4.1 mi 8 87"/E 14.2 mi Q 35g0/N 0.4 mi @ OO/N 4.3 mi. @ 264O/W 13.9 mi. @ 355'/N 2.0 mi. @ 214O/SW
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Code Typea Collection Site Distance and Direction from Sample ~ype' Reactor Thomas Killian Residence Roy Kinneman 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 S~ecial Interest Locations Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm lndian Community Indian Community C
Robert Kinneman Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Code Typea Collection Site Approximate Type of Distance and Direction sampleb from lSFSl Center.
lSFSl Area Inside Earth Berm lSFSl Nuisance Fence ISFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Nuisance Fence ISFSl Nuisance Fence lSFSl Nuisance Fence lSFSl Area Outside Earth Berm lSFSl Berm Area lSFSl Berm Area lSFSl Berm Area ISFSI Berm Area ISFSl Berm Area lSFSl Berm Area lSFSl Berm Area lSFSl Berm Area TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD
" "C" denotes control location. All other locations are indicators.
Sample Codes:
AP Airborne particulates F
Fish Al Airborne Iodine M
Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates)
VE Vegetation/vegetables DW Drinking water WW Well water Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
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:
Plans for Preventing Recurrence None, The goat milk is available during the grazing season.
None, The goat milk is available during the grazing season.
Sample TY pe MI MI Analysis
- Gamma, 1-131
- Gamma, 1-131 Location P-44 P-44 Collection Date or Period Jan. - Mar. 2005 Nov. - Dec. 2005 Reason for not conducting REMP as required Goats were dry.
Goats were dry.
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2005
( County, State )
Sample Type (Units)
TLD (Inner Ring, Area at Site Boundary) mW91 days)
TLD (Outer Ring.
4-5 mi. distant) mW91 days)
TLD (Special Interest Areas) mW91 days)
TLD (Control) mR/91 days)
Airborne Particulates (pci/m3)
Airborne Iodine (pcilm3)
Type and Number of Analysess Gamma 40 Gamma 60 Gamma 32 Gamma 4
GB 265 GS 20 Be-7 Mn-54 CO-58 CO-60 21-1-65 Zr-Nb-95 Ru-103 Ru-106 Cs-134 CS-137 Ba-La-140 Ce-141 Ce-144 1-131 265 LLD~
3.0 3.0 3.0 3.0 0.005 0.015 0.0006 0.0006 0.0006 0.0008 0.0008 0.0008 0.0052 0.0007 0.0007 0.0017 0.0015 0.0041 0.03 Indicator Locations Mean (F)'
Rangec 16.3 (40140)
( 13.2-17.9) 17.2 (60160)
( 14.1-19.6) 16.1 (32132)
( 13.9-19.3)
None 0.027 (2121212)
(0.009-0.069) 0.068 (16116)
(0.035-0.091)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD Location with Annual Mean
~ocation~
P-06A 0.4 mi @ 249' IWSW P-02B, Roy Kinneman, 4.8 mi @ 17" INNE P-03S, Gustafson Farm, 2.2 mi @ 173" IS P-OIC, R. Kinneman, 11.1 mi@33l0/NNW P-06, Air Station 1.6 mi @ 129" ISE P-03, Air Station 0.8 mi @ 313" INW Control Locations Mean (F)'
RangeC (See Control below.)
(See Control below.)
(See Control below.)
16.3 (414)
(15.4-16.9) 0.025 (53153)
(0.01 1-0.061) 0.060 (414)
(0.032-0.085)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD Highest Mean (F)'
RangeC 17.5 (414)
(17.5-17.5) 19.0 (414)
(18.6-19.6) 18.6 (414)
(1 8.4-1 9.3) 16.3 (414)
(15.4-16.9) 0.027 (53 153)
(0.01 1-0.066) 0.072 (414)
(0.043-0.091)
Number Non-Routine Results' 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2005
( County, State )
Sample TY pe (Units)
Milk (pCilL)
River Water (pCilL)
Type and Number of Analysesa 1-131 103 GS 103 K-40 CS-134 CS-137 Ba-La-140 H-3 8
GS 24 Mn-54 Fe-59 Co-58 Co-60 211-65 Zr-Nb-95 CS-1 34 CS-137 Ba-La-140 Ce-144 LLD~
1.0 200 15 15 15 179 10 30 10 10 30 15 10 10 15 50 Indicator Locations Mean (F)'
RangeC c LLD 1474 (85185)
(1219-2191)
< LLD
< LLD
< LLD Location with Highest Control Locations Mean (F)'
RangeC c LLD 1382 (1 811 8)
< LLD
< LLD
~ocation~
P-44, Yoemans Fann 2.0 mi. I SW P-6, Lock and Dam #3 1.6 mi @ 129°1SE Number Non-Routine Results' 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Mean (F)'
RangeC 1973 (1 3 11 3)
(1 800-21 91) 346 (2/4)
(214-478)
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2005
( County, State )
Sample TY pe (Units)
Drinking Water (pCilL)
Well Water (pCi1L)
Crops - Cabbage (pCi/gwet)
Type and Number of Analysesa GB 12 1-131 12 H-3 4
GS 12 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-1 37 Ba-La-140 Ce-144 H-3 20 GS 20 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 CS-134 CS-1 37 Ba-La-140 Ce-144 1-131 3
LLD~
1.0 1.0 179 10 30 10 10 30 15 10 10 15 46 194 10 30 10 10 30 15 10 10 15 53 0.013 Indicator Locations Mean (F)'
RangeC 11.5(112)
(8.3-14.0)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD LLD
< LLD
< LLD
< LLD
< LLD Location with Annual
~ocation~
P-11,RedWingS.C.
3.3 mi @ 158" ISSE Control Locations Mean (F)'
RangeC None None None None None None None None None None None None None
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD Highest Mean Mean (F)'
RangeC 11.5(12/12)
(8.3-14.0)
Number Non-Routine Resultse 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
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2005
( County, State )
Sample Type (Units)
Fish (pCi1g wet)
Invertebrates (pCilg wet)
Type and Number of Analysesa GS 4
K-40 Mn-54 Fe-59 CO-58 Co-60 Zn-65 Zr-Nb-95 CS-I 34 CS-137 f3a-La-140 GS 4
Be-7 K-40 Mn-54 Co-58 Co-60 21-1-65 Zr-Nb-95 Ru-1 03 Ru-1 06 CS-1 34 CS-1 37 Ba-La-140 Ce-141 Ce-144 LLD~
0.10 0.018 0.049 0.022 0.013 0.034 0.027 0.018 0.019 0.047 0.51 0.90 0.047 0.047 0.047 0.10 0.09 0.076 0.41 0.054 0.046 0.16 0.13 0.25 Indicator Locations Mean (F)'
RangeC 2.92(2/2)
(2.79-3.04) c LLD c LLD c LLD c LLD c LLD c LLD c LLD c LLD c LLD
< LLD 0.96 (112) c LLD c LLD c LLD cLLD
< LLD
< LLD c LLD Location with Highest Control Locations Mean (F)'
RangeC 3.26 (212)
(3.16-3.35)
< LLD c LLD C LLD c LLD c LLD c LLD C LLD C LLD c LLD
< LLD c LLD c LLD C LLD C LLD C LLD c LLD
< LLD
< LLD Annual
~ocation~
P-19, Upstream 1.3 mi @ OO/N P-6, Lock and Dam #3 I
.6 mi @ 1 2g01SE Number Non-Routine Resultse 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Mean Mean (F)'
RangeC 3.26 (2/2)
(3.16-3.35) 0.96 (112)
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Location of Facility Goodhue, Minnesota Docket No.
50-282, 50-306 Reporting Period January-December, 2005
( County, State )
a GB = gross beta, GS = gamma scan.
LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
Locations are specified: (1) by name, andlor 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.
Number Non-Routine Resultse 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Control Locations Mean (F)'
RangeC 0.48 (112) 10.33 (212)
(8.67-1 1.98)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 0.026 (112)
< LLD
< LLD
< LLD Sample TY pe (Units)
Bottom and Shoreline Sediments
(~Ci/g dry)
Type and Number of Analysesa GS 6
Be-7 K-40 Mn-54 CO-58 CO-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 CS-134 CS-137 Ba-La-140 Ce-141 Ce-144 0.22 0.10 0.016 0.021 0.015 0.061 0.025 0.030 0.12 0.015 0.023 0.058 0.061 0.13 Indicator Locations Mean (F)'
RangeC 0.40 (114) 7.48 (414)
(6.01-8.74)
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 0.026 (112)
< LLD
< LLD
< LLD Location with Highest Annual Mean
~ocation~
P-20, Upstream 0.9 mi. @ 45" INE P-20, Upstream 0.9 mi. @ 45" INE P-06, P-20 Mean (F)'
RangeC 0.48 (112) 10.33 (212)
(8.67-1 1.98) 0.026 (112)
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-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 through 2006a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2005.
2001 b through 2006b. Radiation Environmental Monitoring for Prairie lsland Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2005.
2003.
Quality Assurance Program Manual, Rev. 0, 01 October 2003.
2005.
Quality Control Procedures Manual, Rev. 1, 17 September 2005.
2003.
Quality Control Program, Rev. 0, 21 August 2003.
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.
1979b to 1983b. Radiation Environmental Monitoring for Prairie lsland 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 lsland Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971. Minneapolis, Minnesota.
1973.
Prairie lsland Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1972 to December 31, 1972. Minneapolis, Minnesota.
1974.
Prairie lsland Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1, 1973 to December 31, 1973. Minneapolis, Minnesota.
1979 to 2003.
Prairie lsland Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2002. Minneapolis, Minnesota.
6.0 REFERENCES
CITED (continued)
Prairie lsland Nuclear Generating Plant, 2005. Radiological Environmental Monitoring for Prairie lsland Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.
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-60014-80-032).
1984.
Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-52015-84-006).
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. 2006. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2005 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois
0 nmental, Inc.
" Midwest Laboratory an Allegheny Technolog~es Co.
700 Landwehr Road Northbd, IL 60062-2310 ph. (847) 564-0700 fax (847) 5644517 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, 2005 through December, 2005
Interlaboratow Com~arison Program Results Environmental, Inc., 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 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.
Results in Table A-I were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NlST 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.
Attachment A lists acceptance criteria for "spiked" samples.
Out-of-limit results are explained directly below the result.
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pcilliter or kg 5.0 pcilliter
> 100 pCi1liter or kg 5% of known value 5.0 pcilliter 10% of known value 2 to 30 pcilliter or kg 5.0 pcilliter
> 30 pcilliter or kg 10% of known value Potassium-40 2 0.1 glliter or kg 5% of known value Gross alpha Gross beta Tritium 5.0 pcilliter 25% of known value 5.0 pcilliter 5% of known value k l a = (pcilliter) =
169.85 x 10% of known value Radium-226,-228 r 0.1 pcilliter 15% of known value Plutonium r 0.1 pcilliter, gram, or sample 10% of known value 6.0 pcilliter 10% of known value 6.0 pcilliter 15% of known value 10 pcilliter 10% of known value othersb 20% of known value
" From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004.
Laboratory limit.
TABLE A-I. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a Lab Code Date STW-1051 STW-1051 STW-1052 STW-1052 STW-1052 STW-I 052 STW-1052 STW-1053 STW-1053 STW-1054 STW-1054 STW-1054 STW-1067 STW-1067 STW-1068 STW-1068 STW-1068 STW-1068 STW-1068 STW-I 069 STW-1069 STW-1070 STW-1070 STW-1070 Concentration (pCilL)
Analysis Laboratory ERA Control
~ e s u l t ~
ResultC Limits Acceptance Sr-89 Sr-90 Ba-133 Co-60 CS-1 34 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 9-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 S r-8 9 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-I. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a Concentration (pCilL)
Lab Code Date Analysis Laboratory ERA Control
~ e s u l ?
ResultC Limits Acce~tance Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-1 31 Ra-226 Ra-228 Uranium H-3 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Fail Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
Unless otherwise indicated, the laboratory result is given as the mean
- standard deviation for three determinations.
Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
The original samples were calculated using an Am-241 efficiency. The samples were spiked with Th-232. Samples were recounted and calculated using the Th-232 efficiency. Results of the recount: 27.01 2 2.35 pCilL.
'Decay of short-lived radium daughters contributed to a higher counting rate. Delay of counting for 100 minutes provided better results.
The reported result was the average of the first cycle of 100 minutes, the average of the second cycle counts was 4.01 pCilL
TABLE A-2. Crosscheck program results; Thermolurninescent Dosimetry, (TLD, CaS04: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value
+ 2 sigma Limits Acceptance Environmental. Inc.
2005-1 41412005 2005-1 41412005 2005-1 41412005 2005-1 4/4/2005 2005-1 41412005 2005-1 41412005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 Environmental. Inc.
2005-2 911 212005 2005-2 911 212005 2005-2 911 212005 2005-2 911 212005 2005-2 911 212005 2005-2 911 212005 2005-2 911 212005 2005-2 911 212005 2005-2 911 212005 30 cm 60 cm 60 crn 90 crn 90 cm 120 crn 120 crn 150 cm 180 cm Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-3. In-House "Spike" Samples Lab Code Date Analysis SPW-1836 SPW-1836 SPMI-1838 SPMI-1838 SPMI-1838 SPMI-1838 SPMI-1838 SPMI-1838 SPVE-I 932 SPCH-1935 SPAP-1966 SPAP-1966 SPAP-1966 SPAP-1968 SPAP-1968 SPW-2098 SPW-2922 SPW-2922 SPW-2922 SPW-2922 SPAP-2892 SPW-2895 W-601 05 W-60 1 05 SPF-3089 SPF-3089 SPW-SPW-47731 SPW-47732 SPW-4775 SPMI-4834 SPMI-4834 SPMI-4834 SPMI-4834 Gr. Alpha Gr. Beta H-3 Gr. Beta Tc-99 Gr. Alpha Gr. Beta 1-131 1-1 31 (G)
Cs-134 CS-1 37 1-131 1-131 (G)
Sr-89 Sr-90 1-1 31 (G) 1-131 Cs-134 CS-1 34 Cs-137 Cs-134 Cs-137 Fe-55 CS-1 34 Cs-134 Sr-89 Sr-90 Gr. Beta H-3 Gr. Alpha Gr. Beta CS-1 34 CS-137 Concentration (PC~IL)~
Laboratory results Known 2s. n=l Activitv Control Limits Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-3. In-House "Spike" Samples Lab Code Concentration (pCilL)
Date Analysis Laboratory results Known Control 2s, n=lb Activity LimitsC Acceptance Cs-134 Cs-137 Sr-89 Sr-90 H-3 Gr. Alpha Gr. Beta C-14 Ni-63 Tc-99 CS-1 34 CS-1 37 CS-1 34 CS-1 37 Gr. Beta H-3 Gr. Alpha Gr. Beta Cs-134 CS-137 CS-1 34 Cs-137 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCilLiter, air filters( pcilfilter), charcoal (p~ilrn3),
and solid samples (pCilg).
Laboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation),
CH (charcoal canister), F (fish).
Results are based on 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, cabbage is used for the Spike matrix.
TABLE A-4. In-House "Blank" Samples Lab Code SPW-SPW-4774 SPW-4776 SPMI-4835 SPMI-4835 SPMI-4835 SPMI-4835 SPMI-4835 SPMI-4835 SPW-4837 SPW-4837 SPW-4837 SPW-4837 SPW-4837 SPW-5015 SPW-5238 Sample Type water water water Air Filter water water water water water water water Milk Milk Milk Charcoal water water water water water water Fish Fish water water water Milk Milk Milk Milk Milk Milk water water water water water water water Concentration (PC~/L)~
Date Analysis Laboratory results (4.660)
Acceptance LLD
~ctivit$'
Criteria (4.66 a) 111 112005 Gr. Alpha 0.055 0.00 + 0.038 1
111 112005 Gr. Beta 0.15
-0.016 i 0.10 3.2 211 812005 H-3 165.8 7.4 + 82.5 200 211 812005 Gr. Beta 0.72 0.29 + 0.48 3.2 2/28/2005 Tc-99 1.32 0.45 + 0.81 10 3/1/2005 Gr. Alpha 0.067
-0.007 r 0.043 1
3/1/2005 Gr. Beta 0.18
-0.04 + 0.1 1 3.2 Cs-134 Cs-137 1-131 1-1 31 (G) 1-131 Sr-89 Sr-90 I-131(G)
Fe-55 Cs-134 CS-1 37 H-3 Gr. Alpha Gr. Beta Cs-134 Cs-137
TABLE A-4. In-House "Blank" Samples Lab Code Sample T V D ~
Date Analysis water water water water water Fish Fish Air Filter Air Filter Air Filter water water Milk Milk Milk water water water water Milk Milk Gr. Alpha Gr. Beta C-14 Ni-63 Tc-99 Cs-134 Cs-137 CS-134 CS-137 Gr. Beta Gr. Alpha Gr. Beta Co-60 Cs-137 I-131(G)
Co-60 Cs-137 CS-1 34 CS-1 37 Cs-134 Cs-137 Concentration (PC~/L)~
Laboratory results (4.660)
Acceptance LLD
~ c t i v i t ~ ~
Criteria (4.66 0) a Liquid sample results are reported in pCilLiter, air filters( pcilfilter), charcoal (pcilcharcoal canister), and solid samples (pCilg).
Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported 1-1 31 (G); iodine-131 as analyzed by gamma spectroscopy.
- Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCilL) in milk is not unusual.
TABLE A-5. In-House "Duplicate" Samples Concentration f ~ C i l L ) ~
Lab Code Date Analvsis Averaged First Result Second Result Result Gr. Beta K-40 Gr. Beta K-40 Be-7 Gr. Beta H-3 Gr. Beta K-40 1-1 31 H-3 Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta 1-1 31 Gr. Alpha 1-1 31 Be-7 Be-7 Be-7 K-40 Be-7 Be-7 Gr. Beta Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Gr. Beta 1-131 Cs-137 Gr. Alpha Gr. Beta K-40 Sr-90 K-40 K-40 Gr. Alpha Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-5. In-House "Duplicate" Samples Concentration (PC~/L)~
Lab Code Date Analysis Gr. Beta K-40 Be-7 K-40 Cs-137 K-40 Cs-137 K-40 K-40 Cs-137 Gr. Beta K-40 1-1 31 Gr. Beta Be-7 Gr. Beta K-40 Co-60 Cs-137 Gr. Alpha K-40 K-40 Co-60 Cs-137 K-40 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 Be-7 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 1-1 31 H-3 1-1 31 K-40 K-40 1-1 31 First Result 3.81 i 0.10 3.79 i 0.40 0.81 i 0.39 9.43 i 1.oo 0.13 i 0.04 12.44 i 0.76 0.18 i 0.04 20.06 i 1.I0 6.06 + 0.44 0.18 i 0.04 32.95 i 2.48 21 -93 i 0.97 0.51 i 0.34 3.29 i 0.49 1.06 i 0.40 8.06 i 0.07 5.93 i 0.73 0.11
- 0.02 0.60 i 0.05 11.58 i 1.31 6.34 i 0.59 1215.40 i 110.20 0.20 i 0.04 2.59 i 0.10 11.57 i 0.81 0.97 f 0.54 2.12 i 0.53 38717 i 382 7.53 i 0.18 5.70 i 0.52 0.09 i 0.02 1.37 i 0.35 9.70 i 1.63 Second Result 3.86 i 0.10 4.30 i 0.59 1.25 + 0.38 7.96 i 0.85 0.14 + 0.05 13.33 + 0.83 0.17 i 0.01 21.73 + 0.36 5.96 k 0.61 0.18 i 0.03 33.88 i 2.36 22.32 i 0.98 0.56 i 0.30 3.75 i 0.66 1.21 + 0.28 7.79 i 0.07 6.05 i 0.28 0.10 i 0.02 0.62 i 0.05 13.52 i 1.43 7.29 i 0.68 1250.70 i 106.70 0.22 i 0.04 2.51 i 0.07 11.82 i 0.76 1.67 i 0.58 1.62
- 0.56 3801 7 i 535 7.56 i 0.18 5.64 + 0.53 0.08 i 0.02 1.40 i 0.36 9.77 i 1.61 Averaged Result Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-5. In-House "Duplicate" Samples Lab Code Date Analvsis Gr. Alpha Gr. Beta Gr. Beta H-3 Be-7 Gr. Beta K-40 K-40 H-3 Gr. Beta K-40 Gr. Beta Gr. Alpha Gr. Beta K-40 Cs-137 Gr. Beta K-40 1-131 K-40 Sr-90 K-40 Sr-90 H-3 Gr. Beta K-40 Gr. Alpha K-40 K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta 1-1 31 Gr. Beta 1-1 31 Be-7 K-40 K-40 Be-7 CS-137 Concentration (PC~/L)~
Averaged First Result Second Result Result Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-5. In-House "Duplicate" Samples Concentration (PC~IL)~
Averaged Lab Code Date Analysis First Result Second Result Result Acceptance BS-5340, 5341 912312005 K-40 12404 + 1 154 13033 + 983 1271 9 + 758 Pass DW-5382, 5383 912312005 1-1 31 0.79 f 0.31 0.53 + 0.31 0.66 + 0.22 Pass MI-5405, 5406 9/27/2005 K-40 1324.80 f 112.20 1366.80 f 99.44 1345.80 f 74.96 Pass AP-5769, 5770 912712005 Be-7 0.08 f 0.01 0.09 f 0.02 0.08 f 0.01 Pass AP-5983, 5984 912712005 Be-7 0.08
- 0.01 0.08 + 0.01 0.08 + 0.01 Pass AP-5878, 5879 9/29/2005 Be-7 0.06 + 0.01 0.07 f 0.01 0.07 f 0.01 Pass Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 Be-7 K-40 Gr. Beta H-3 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Gr. Beta Cs-137 Gr. Beta K-40 H-3 Gr. Beta K-40 1-131 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Alpha Gr. Beta Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCilL, except for air filters (pCiIFilter), food products, vegetation, soil, sediment (pCi/g).
600 minute count time or longer, resulting in lower error.
Recount of W-5748, 2.38 f 0.85 pCilL Averaged result; 2.14 f 0.45 pCilL
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a Lab CodeC STSO-1 048 STSO-1 048 STSO-1 048 STSO-1 048 STSO-1 048 STSO-1 048 STSO-1048 STSO-1048 STSO-1 048 STSO-1048 STSO-1 048 STSO-1 048 STSO-1 048 STSO-I 048 Date 01/01/05 01101/05 01101105 01101105 01/01/05 01/01/05 01/01/05 01101105 01/01/05 01/01/05 01/01/05 01101105 01101105 01/01/05 01/01/05 01/01/05 01101105 01101105 01/01/05 01101105 01/01/05 01/01/05 01/01/05 01/01/05 01101105 01/01/05 01/01105 01/01/05 01101105 01/01105 01/01/05 01/01/05 01101105 01101105 01101105 01101105 01/01/05 01/01/05 01101105 01/01/05 Concentration Analvsis Laboratorv result Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Known Activity Control Limits Acceptance 0.00 - 1.05 Pass 0.84 - 2.51 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 6.92 - 12.84 Pass 2.21 -4.10 Pass 3.50 - 6.50 Pass 2.88 - 5.34 Pass 3.63 - 6.73 Pass 4.40 - 8.18 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 0.00 - 0.46 Pass 0.15 - 0.45 Pass
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)=.
Lab CodeC Date 01/01/05 01/01/05 01101105 01101105 01/01/05 01101105 01101105 01101105 01101105 01101105 01101105 01101105 07101105 0710 1 105 0710 1105 0710 1105 07101 105 0710 1105 07101105 0710 1 105 07/01/05 0710 1 105 07101 105 07101 105 0710 1105 0710 1105 0710 1 105 07101 105 Analysis Am-241 CO-57 Co-60 CS-1 34 Cs-137 Mn-54 Pu-238 Pu-239140 Sr-90 U-23314 U-238 Zn-65 Gr. Alpha Gr. Beta Concentration Known Laboratory result Activity 0.10
- 0.04 0.10 4.76 i 0.64 4.92 2.84 i 0.22 3.03 3.54 i 0.37 3.51 2.20
- 0.27 2.26 3.15 i 0.21 3.33 0.16
- 0.04 0.20 0.17 k 0.02 0.17 2.24
- 0.34 1.35 0.34 i 0.02 0.34 0.35 & 0.02 0.35 3.12 i 0.15 3.14 Control Limits Acceptance 0.07 - 0.13 Pass 3.44 - 6.40 Pass 2.12 - 3.94 Pass 2.46 - 4.56 Pass 1.58 - 2.94 Pass 2.33 - 4.33 Pass 0.14 - 0.25 Pass 0.14 - 0.25 Pass 0.95 - 1.76 Fail 0.24 - 0.44 Pass 0.25 - 0.46 Pass 2.20 - 4.08 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Lab CodeC STVE-I 064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STAP-1065 STAP-1065 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 STAP-1066 Date Concentration Known Control Analysis Laboratory result Activity Limits Acceptance Gr. Alpha Gr. Beta Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, ldaho Operations office, ldaho Falls, ldaho b Results are reported in units of Bqlkg (soil), BqlL (water) or Bqltotal sample (filters, vegetation) as requested by the Department of Energy.
Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), S N E (vegetation).
MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
The strontium carbonate precipitates were redissolved and processed. The average of the three analyses was 1.34 1 although the recovery was only 30%. The result of a new analysis was 1.56 pCi/L.
Incorrect sample weight used in calculation. Result of recalculation: 97.0 i 7.8 Bqlkg.
APPENDIX B DATA REPORTING CONVENTIONS
Data Reportina 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. Sinqle Measurements Each single measurement is reported as follows:
x + s where:
x = value of the measurement; s = 20 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 4.660 uncertainty for a background sample.
3.0. Duplicate analvses 3.1 Individual results: For two analysis results; x, + s, and x, + s, Reaorted result:
x + s; where x = (112) (x, + x,) and s = (112) 4s: + si 3.2.
Individual results:
< L1,
Lz Reported result: < L, where L = lower of L, and L, 3.3.
Individual results:
x + s, < L Re~orted result:
x + s if x 2 L; <L otherwise.
4.0. computation of Averaaes and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x,. x2... xn are defined as follows:
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 number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 1 1.45.
APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas
Table C-I.
Maximum permissible concentrations of radioactivity in air and water above natural a
background in unrestricted areas.
Air (p~i/rn3)
Water (pCilL)
Gross alpha 1 x loJ Strontium-89 8,000 Gross beta 1
Strontium80 500 Gross alpha 2
Gross beta 10 Tritium 1 x lo6 a
Taken from Table 2 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.
Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway, A natural radionuclide.
APPENDIX D Sampling Location Maps
PLANT AREA ENLARGED PLAN E1.OO MILE RAOIUSI
[NO SCALE1
TLO LOCATIONS CONTROL POINTS PRESCOTT, WlSCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGEND:
I
@ PRAIRIE ISLAND TLD POINTS REV. 1
~3 TLDi32.DGN
~
l n
~
n a
t
~
~
-0.n rrr\\. i en*, rooor n d
n*.r o r
TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
@ PRAIRIE ISLbNO TLD POINTS REV. 1 0-4
,,--...A,.-,
-fie..-.,
....'A
- ,...,A?
A A,,--
m a,
TLD03.DGN
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS PLANT AREA ENLARGED PLAN Cl.00 MILE RADIUS1
[NO SCALE3 MONITORING LEGEND MILK SAMPLING POINT I 0 NUMBERS a
FISH SAMPLING POINT ID NW8ERS P-14. P-I& P-37. P-12. P-43, P-44 P-13, P-19 QlR SHPL[WG W l N f ID NUMBERS INVERTEBRATES POINT 10 WMEERS P-1, P-2. P-3, P-4. P-6 P-6. P-40 WATER SMLING WtNT tO NUMBERS SEDIMENT S W L U i G ViINT 10 NUMBERS P-3.P-6, P-8, P-9. P-11. P-24, P-43 P-6, P-12, P.20 REV, 1 D-5 SAMP0I.DGN 1
\\ -.. n, n, r r r *.. r r -.
F.,..,
n n r r r ~ n l \\.. r n',.a
.-.--a.
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONlTORIMG LEGEND MILK WMPLING POINT 10 NUMBERS P-14. P-18. P-31. P - 4 2 P-43, P-44 a
&1R SAMPLING POINT I D NUMBERS WllTER SAMPLlffi POINT ID NUMBERS P-5, P-6. P-8. P-9. P-LI. P-24. P-43 1
YEGETP710N / VEGETABLES fO NUMBERS P-24, P-38, P-45 REV 1 D 6
,-,-",..*..A
..,mr.,.
...,..c
.-,-,a
.,m..,.-
FISH SAMPLING POINT ID NUH&ERS P-13, P-19 INVERI'E~RATES POINT ID NUMBERS P-6. P-40 SEDIMENT SCIMPLING POINT 10 NUMBERS P-6. P-12, P-20
ENVIRONMENTAL SAMPLING POINTS 0-7 t
t P41, Hupprt Farm, W10430 St Rd 20, Rlver Falls, WI P a, Peterson Farm, W10322 St Rd 29, Rlver Falls,WI P38, Caln Residence, N73M 960th St, Rlver Palls, WI I
CONTROL POINTS PRESCOTT, WISCONSIN
@ MILK SAMPLING POINT ID NUMBERS P-14, P-18, P37, P41, P42, P 4, P44 AIR SAMPLING POINT ID NUMBERS n
WATER SAMPLING POMT ID NUMBERS P4, Pa, P-8, Pa. Pli, P 4 MQETATlON I VEGETABLES ID NUMBERS P a, P-38, P46