L-PI-04-061, Annual Radiological Environmental Monitoring Report
| ML041410077 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/14/2004 |
| From: | Solymossy J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| +sunsi/sispmjr=200603, -RFPFR, L-PI-04-061 | |
| Download: ML041410077 (66) | |
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M O
Praiie Island Nuclear Generating Plant Committed tof NdarExc Operated by Nuclear Management Company, LLC MAY 1 4 2004 L-PI-04-061 TS 5.6.2 ISFSI TS 6.2 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282, 50-306 and 72-10 License Nos. DPR-42, DPR-60 and SNM-2506 2003 Annual Radioloqical Environmental Monitoring Report Pursuant to Prairie Island Nuclear Generating Plant Technical Specification (Pi TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and pursuant to Prairie Island 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 Report for the period January 1, 2003 through December 31, 2003.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Please address any comments or questions regarding this letter to Mr. Jack Leveille at 651-388-1121.
Joseph M. Solymossy Site Vice-President, Prairie Island Nuclear Generating Plant Units 1 and 2 Nuclear Management Company, LLC Enclosure (1)
CC Regional Administrator, USNRC, Region IlIl Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Dr. John House, USNRC, Region IlIl Director of NMSS, USNRC Tim Donakowski, State of Minnesota 1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121 l?
Z5
4' ENCLOSURE 1 Annual report to the United States Nuclear Regulatory Commission Radiation Environmental Monitoring Program January 1 to December 31, 2003 (64 pages follow)
Environmental, Inc.
Midwest Laboratory an Aflegheny Teduiogld es Co.
700 LUndwehr Road
- Nortbrok. IL a0062-2310 rph.
(847) 564-0700
- ax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ISFSI Docket No.72-10 SNM-2506 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 2003 Prepared under Contract by ENVIRONMENTAL, Inc.
MIDWEST LABORATORY Project No. 8010 Approved:
bon rrap M.S.
\\ ibrawlanager
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.
Ii
TABLE OF CONTENTS Section Paqe 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 3.1 Program Design and Data Interpretation......................................................
3 3.2 Program Description......................................................
4 3.3 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-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 Maps.D-1 lii
LIST OF TABLES No.
Title Page 5.1 Sample Collection and Analysis Program............................
15 5.2 S
m ln Lo a i
n
,16 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:
ADpendix A A-1 U.S. Environmental Protection Agency's Crosscheck Program results.
Al-1 A-2 Crosscheck Program Results; (TLDs).
A2-1 A-3 In-house "Spiked" Samples.
A3-1 A-4 In-house "Blank" Samples.
A4-1 A-5 In-house 'Duplicate" Samples.
A5-1 A-6 Department of Energy MAPEP comparison results....................................................................... A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results.......................................................................................................... A7-1 ADpendix 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 Paqe 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-1)..................................
14 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, 2003. 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, 2004b) 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.
I
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 2003 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.
2
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-1 31. 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 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
I 3.1 Program Desicn 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 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, 2003). 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-1
- 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy.
One of the five locations is a control (P-1), and four are Indicators (P-2, P-3, P4, and P-6).
Offsite ambient gamma radiation Is monitored at thirty-four locations, using CaSO 4: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 lodine-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.
4
3.2 Program Description (continued)
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) A partial air particulate/air iodine sample was collected from location P-I, the week ending 10-14-03. The low volume was due to sampler pump failure.
(2) No air particulate/air iodine sample was available from location P-6 for the week ending 11-14-03, due to a sampler pump failure.
(3) Milk samples were not available from P-37 (Welsch Farm) for the months of January, February and March of 2003.
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-131 in charcoal samples are measured by gamma spectroscopy.
Levels of iodine-1 31 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 Interlaboratory Comparison (Crosscheck) programs and results are presented In Appendix A.
5
3.5 Pro-ram Modifications One extra garden location was sampled for broadleaf vegetation in 2003.
3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census Is conducted In order to Identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft 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 2003 Land Use Census was completed in September, 2003. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 2003. The critical receptor location did not change In 2003, 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.
6
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 2003.
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 2003.
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 22 fallout declined yearly from a level of 12,167 pCiM to 1,020 pCVMi
, 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 3
pCVm3. Average present day levels have stabilized at around 0.025 pCVM. 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 pCVL. Present day measurements for both Cs-1 37 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pC/g for gross beta and 0.47 pC/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 pCVL 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 pCVL in downstream Mississippi River water, 8.2 pCVL for well water, and 11.0 pCVL 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 pCi/g. Cs-137 activity during preoperational studies In 1973 measured 0.25 pCig upstream and 0.21 pCig 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.
7
4.3 Proaram Findings 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 15.4 mR/91 days at Inner ring locations to 16.7 mRI91 days at outer ring locations. The mean at special locations was 15.5 mRI9I days and 16.0 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 1988 through 2002. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).
Average (Inner and Year Outer Rins)
Control 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 2001 16.8 17.2 2002 17.4 16.9 2003 16.2 16.0 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mRJ91 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 79.7 mR/91 days Inside the ISFSI earth berm and 18.9 mRI91 days outside the ISFSI earth berm. No additional casks were placed on the ISFSI pad in 2003, a total of seventeen 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. 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 14.8 and 14.3 mR/91 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 ISFSI 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).
8
Airborne Particulates The average annual gross beta concentrations In airborne particulates were slightly higher at the indicator versus the control locations (0.027 pCiMr and 0.025 pCiMr, respectively) and similar to levels observed from 1988 through 2002. The results are tabulated below.
Average of Year Indicators Control Concentration (DCi/m )
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 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 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.
Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1988 through 2003.
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., 2004).
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 AI-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 0.07 pCrM3 in all samples. There was no indication of a plant effect.
9
Milk lodine-131 results were below the detection limit of 1.0 pCVL in all samples. Cs-137 results were below the LLD level of 15 pCVL 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 2003 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 182 pCiVL In all samples.
Gross beta concentrations averaged 9.9 pCiIL throughout the year, ranging from 8.1-14.3 pCVL. These concentrations were similar to or slightly higher than levels observed from 1988 through 2002. 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 2003 data of any effect of plant operation.
Year Gross Beta 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 2001 8.3 2002 8.7 2003 9.9
=-
Average annual concentrations; Gross beta in drinking water.
10
River Water For the second and third quarters of 2003, measurable tritium was detected in downstream river water composites, at concentrations of 1135 and 259 pCVL, respectively. This is well below the Environmental Protection Agency's drinking water standard of 20,000 pCiL.
For the remaining upstream and downstream collections, tritium levels measured below the LLD level of 161 pCiIL.
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 163 pCiIL. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2003 show no radiological effects of the plant operation.
cro1s Three samples of broadleaf vegetation, cabbage leaves, were collected in July and analyzed for gamma-emitting isotopes, including iodine-1 31. The 1-131 level was below 0.026 pCilg 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 Fish samples were collected In May and September, 2003 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 Periphvton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2003. 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, 2003 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotope detected was naturally-occurring potassium-40. There was no indication of a plant effect.
11
5.0 FIGURES AND TABLES 12
Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.
--- Indicator 20 19 18
===_
-=iiji!
I I I I I I HI I I I 17 I
IN i
E 16 15 14 13
~I-rI-I I
I 1I 12 11 10 k-
}
I l_l____
1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 20 -
-i 18-17 --
155 -
1 141-13----
12---
11 ------------
j--~
10 I!
2001 2002 2003 E
1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 13
rigure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
Indicators (P-2,3,4,6) 0.I 0.I 0.I o0.
0.t 0.t
)35-Ien rJ1 i
i i
D31 I
I._
_29I II
)25 I
I I_
E C.)
C.,
E VC.
0.023 -
0.021 -
0.019 0.017 0.015 19Iiii I
- t1
IJf JL B8 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 I--
Control (P-i) 0.017-l l
1988 19 1990 199t1 I-9I i
i i
I It I
19i2 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 14
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 Frequencyc Ambient radiation (TLD's)
Airborne Particulates 54 P-alA - P-iOA P-.0+/ P-15B P.0+/-5S - P.085 P-0+/-IA - P.OSIA P.0lB -P-081B P-OtIX-P-04IX, P-01 C C/Q Ambient gamma GB, GS (QC of each location) 5 P-iCC), P-2, P-3, P-4, P-6 C/W Airborne Iodine 5
P-1(C), P-2, P-3, P-4, P-6 C/W G/Md 1-:13i 1i31, GS Milk 5
P-14, P-18, P-37, P-41 (C), P-42 River water 2
P-5(C), P-6 G/W Drinking water 1
G8(MC), 1-131(MC)
H-3, GS Well water 5
P46, P-8, P-9, P-24, P41 (C)
G/Q Edible cultivated crops -
leafy green vegetables Fish (one species, edible portion)
Periphyton or Invertebrates Bottom sediment Shoreline sediment 2
P-38(C), P-24 2
P-19(C), P-13 2
P-40(C), P-6 2
P-20(C), P-6
+/-
P-12 G/A G/SA GS (1-131)
GS GS GS GS G/SA G/SA
- G/SA
- 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 Is coded as follows: GB - gross beta, GS - gamma spectroscopy, H tritium, -3+/-
- lodine-ISI.
Analysis frequency Is coded as follows: MC - monthly composite, QC - quarterly composite.
dMilk Is collected biweekly during the grazing season (May -October).
15
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction from Code Type' Collection Site Sample Type" Reactor P-i P-2 P-3 P-4 P-5 P-6 P-8 P-9 P-ll P-12 P-13 P-14 P-18 P-19 P-20 P-24 P-37 P-38 P.40 P-41 P42 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 Christlansen Farm C
Upstream of Plant C
Upstream of Plant Suter Residence Welsch Farm C
Cain Residence C
Upstream of Plant C
Huppert Farm Rother Farm AP, Al
. AP, Al, RW WW, BS, BOC WW WW DW Ss M
M M
BS VE, WW M
VE BO' M,WW M
11.8 ml @ 316°/NNW 0.5 ml @ 2940/WNW 0.8 ml @ 3130/NW 0.4 ml @ 3590/N 1.8 ml@ I°/N 1.6 ml @ 1290/SE 1:0 ml @ 321°/WNW 0.3 ml 306°/NW 3.3 ml@ 158°/SSE 3.0 ml @ 1160/ESE 3.5 ml @ 1130/ESE 2.3 ml @1730/S 3.8 ml @ 880/E 1.3 ml @ 0°/N 0.9 ml0 45°/NE 0.6 ml 0 1580/SSE 4.1 ml @ 87°/E 14.2 ml @ 3590/N 0.4 ml 0 °0/N 13.8 ml @ 354°/N 4.3 ml. @ 2640/W General Area of the Site Boundary P-OiA P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-1OA Property Une 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 ml @
3590/N 0.3 ml @ 10°/N 0.5 ml 01830/S 0.4 ml 0 2040/SWW 0.4 ml 0 2250/SW 0.4 ml 0 2490/WSW 0.4 ml 0 2680/W 0.4 ml 0 291°/WNW 0.7 ml 0 317°/NW 0.5 ml 0 333°/NNW 16
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Distance and Direction from Code Type' Collection Site Sample Typeb Reactor ADproximately 4 to 5 miles Distant from the Plant P41B8 P-02B P-03B P-04B P-05B P-06B P-07B P-08B P-09B P-1OB P-llB P-12B P-13B P-14B P-15B Thomas Killian Residence Roy Kinneman Residence Wayne Anderson Farm Nelson Drive (Road)
County Road E and Coulee WillIam Hauschlblt 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 Hoist Farms TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.7 ml @ 355°/N 4.8 ml @ 170/NNE 4.9 ml @ 460/NE 4.2 ml 6 61°/ENE 4.2 ml @ 102°/ESE 4.4 ml @ 112°/ESE 4.7 ml @ 140°/SE 4.1 ml @ 1650/SSE 4.2 ml @ 1870/S 4.9 ml @ 2000/SSW 4.5 ml 0 221°/SW 4.6 ml 0 2510/WSW 4.4 ml 0 270°/W 4.9 ml 0 306°/NW 3.8 ml @ 3450/NNW Soeclal Interest Locations P-Ois P-02S P-03S P-04S P-05S P.065 P-07S P-8SS P-Oic Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm Indian Community Indian Community C
Robert Klnneman Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD 1.6 ml @ 129 0/SE 0.5 ml 0 155°/SSE 2.2 ml 0 173°/S 2.0 ml 0 202°/SSW 2.0 ml 0 270°/W 2.5 ml @ 299°/WNW 0.7 ml i 271°/W 0.7 ml 0 2870/NWW 11.i ml 0 331°/NNW 17
PRAIRIE ISLAND Table 52. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Approximate Type of Distance and Direction Code Type' Collection Site Sampleb from ISFSI Center.
ISFSI Area Inside Earth Berm P-QUA P-021A P-031A P-041A P-051A P-061A P-071A P-081A P.Oilx P-021X P-031X P-041X ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 190' @ 45°/NE 360' @ 82°/E 370' @ 100°/E 200'+/-1340/SE 180' © 219°/SW 320'0 258°/WSW 320' @ 2810/WNW 190' © 318°/NW 140' © +/-80°/S 3+/-0' © 270°/W 140' © 0°/N 360'@ 900/E ISFSI Area Outside Earth Berm P-0+/-IB P-021B P-03I8 P-041B P-051B P-0 GIB P-071B P-08 lB ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area TLD TLD TLD TLD TLD TLD TLD TLD 340'© 3°/N 380' © 28°/NNE 560' © 85°/E 590' © 165°/SSE 690' © 1860/S 720' © 201°/SSW 610'Q 271°/W 360' © 332 0/NNW
' C" denotes control location. All other locations are Indicators.
b Sample Codes:
AP Airborne particulates Al 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
' Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
18
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 Ml
- Gamma, P-37 1/15/2003 Welsch farm temporarily Welsch will Inform the PINGP 1-131 through out of dairy business.
upon resumption of operation 314/2003 In Spring, 2003.
AP/AI Beta, 1-131 P-01 10/14/2003 Partial sample collected; low Sampler pump was replaced.
volume due to open fuse.
AP/AI Beta, 1-131 P-06 11/14/2003 Sampler pump failure; Sampler pump was replaced.
open fuse.
19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Docket No.
50-282. 50-306 Reporting Period January-December. 2003 Goodhue, Minnesota (County, State)
Indicator Location with Highest Control Number Sample Type and
.Locations Annual Mean Locations Non-Type Number of LLDb Mean (Ff Mean (F)c Mean (Ff Routine (Units)
Analyses' Range Locationd Rangec Range Results TLD (Inner Ring. Gamma 40 3.0 15.4 (40140)
P-06A 16.2 (4/4)
(See Control 0
Area at Site (12.7-17.5)
OA ml @ 2490 /WSW (14.5-17.5) below.)
Boundary) mR191 days)
TLD (Outer Ring, Gamma 60 3.0 16.7 (60/60)
P-02B, Roy Kinneman, 18.9 (414)
(See Control 0
4-5 ml. distant)
(12.9-20.1) 4.8 ml @ 17' NNE (18.0-19.9) below.)
mR191 days)
TLD (Special Gamma 32 3.0 15.5 (32/32)
P-03S, Gustafson Farm, 18.5 (414)
(See Control 0
Interest Areas)
(12.6-20.2) 2.2 mi @ 173 /S (16.6-20.2) below.)
mR191 days)
TLD (Control)
Gamma 4
3.0 None P-O1C, R. Kinneman, 16.0 (4/4) 16.0 (414) 0 mR191 days) 11.1 mi @331' /NNW (15.0-17.0)
(15.0-17.0)
Airborne GB 259 0.005 0.027 (207/207)
P-06, Air Station 0.028 (51 /51) 0.025 (52/52) 0 Particulates (0.005-0.049) 1.6 mi @ 129' /SE (0.014-0.048)
(0.011-0.047)
(pCUmn)
GS 20 Be-7 0.015 0.064 (16/16)
P-06, Air Station 0.067 (414) 0.055 (4/4) 0 (0.036-0.083) 1.6 mi @ 129' /SE (0.051-0.076)
(0.034-0.067)
Mn-54 0.0007
<LLD
<LLD 0
Co-58 0.0006
< LLD
<LLD 0
Co-60 0.0007
<LLD
-<LLD 0
Zn-65 0.0011
<LLD
<LLD 0
Zr-Nb-95 0.0010
<LLD
<LLD 0
Ru-1i03 0.0007
<LLD
<LLD 0
Ru-1 06 0.0063
<LLD
<LLD 0
Cs-1 34 0.0007
<LLD
< LLD 0
Cs-1 37 0.0006
< LLD
< LLD 0
Ba-La-140 0.0016
< LLD
< LLD 0
Ce-141 0.0014
<LLD
<LLD 0
Ce-144 0.0039
<LLD
< LLD 0
Airbome Iodine 1-131 259 0.07
<LLD
<LLD 0
(pCUmn3) 20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nudear Power Station Docket No.
50-282, 50-306 Reporting Period January-December, 2003 Goodhue, Minnesota
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'
Mean (F)c Mean (F)c Routine (Units)
Analysesa Range' Locationd Range' Range' Results' Milk (pCUL) 1-131 87 1.0
< LLD
< LLD 0
GS 87 K-40 200 1403 (69169)
P-37, Welsch Farm 1439 (15 115) 1381 (18118) 0 (1197-1602) 4.1 mi @ 87 IE (1275-1602)
(1202-1584)
Cs-134 15
< LLD
< LLD 0
Cs-137 15
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
River Water H-3 8
161 697 (2/4)
P-6, Lock and Dam #3 697 (2/4)
< LLD 0
(pCUL)
(259-1135) 1.6 mi @ 129°/SE (259-1135)
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 57
< LLD
< LLD 0
21
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, 2003 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)
Analysesa Range Locationd Range Range' Results' Drinking Water GB 12 1.0 9.9 (12112)
P-i1. Red Wing S.C.
9.9 (12112)
None 0
(pCUL)
(8.1-14.3) 3.3 mi @ 158' ISSE (8.1-14.3) 1-131 12 1.0
< LLD None 0
H-3 4
161
< 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 18
< LLD None 0
Ba-La-140 15
< LLD None 0
Ce-144 57
< LLD None 0
Well Water H-3 20 163
< LLD
< LLD 0
(pCiL)
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 55
< LLD
< LLD 0
Crops-Cabbage 1-131 3
0.026
< LLD
< LLD 0
(pClgwet) 22
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, 2003 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'
Mean (F)'
Mean (F)c Routine (Units)
Analyses' Range' Locationd Range' Range' Results!
Fish GS 4
(pCig wet)
K-40 0.10 2.84 (2/2)
P-19, Upstream 2.86 (2/2) 2.86 (2/2) 0 (2.39-3.29) 1.3 ml. @ 0 /N (2.59-3.13)
(2.59-3.13)
Mn-54 0.016
< LLD
< LLD 0
Fe-59 0.046
< LLD
< LLD 0
Co-58 0.015
< LLD
< LLD 0
Co-60 0.016
< LLD
< LLD 0
Zn-65 0.042
< LLD
< LLD 0
Zr-Nb-95 0.025
< LLD
< LLD 0
Cs-134 0.020
< LLD
< LLD 0
Cs-137 0.017
< LLD
< LLD 0
Ba-La-140 0.19
< LLD
< LLD 0
Invertebrates GS 4
(pCIg wet)
Be-7 0.44
< LLD
< LLD 0
K-40 0.98
< LLD P-40, Upstream 1.59 (1t2) 1.59 (1/2) 0 0.4 ml @ 0°/N Mn-54 0.045
< LLD
< LLD 0
Co-58 0.049
< LLD
< LLD 0
Co-60 0.044
< LLD
< LLD 0
Zn-65 0.080
< LLD
< LLD 0
Zr-Nb-95 0.060
< LLD
< LLD 0
Ru-103 0.058
< LLD
< LLD 0
Ru-106 0.32
< LLD
< LLD 0
Cs-134 0.045
< LLD
< LLD 0
Cs-137 0.039
< LLD
< LLD 0
Ba-La-140 0.26
< LLD
< LLD 0
Ce-141 0.079
< LLD
< LLD 0
Ce-144 0.20
< 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
( County, State)
Docket No.
50-282, 50-306 Reporting Period January-December. 2003 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)
Mean (F)c Mean (F)
Routine (Units)
Analyses' Rangec Locationd Range' Range' Results' Bottom and GS 6
Shoreline Be-7 0.18
< LLD
< LLD 0
Sediments (pCVg dry)
K-40 0.10 6.96 (414)
P-20. Upstream 9.05 (212) 9.05 (2/2) 0 (5.89-7.85) 0.9 mi. @ 45 /NE (8.79-9.30)
(8.79-9.30)
Mn-54 0.022
< LLD
< LLD 0
Co-58 0.026
< LLD
< LLD 0
Co-60 0.016
< LLD
< LLD 0
Zn-65 0.063
< LD
< LLD 0
Zr-Nb-95 0.040
< LLD
< LLD 0
Ru-103 0.027
< LLD
< LLD 0
Ru-106 0.17
< LLD
< LLD 0
Cs-134 0.028
< LLD
< LLD 0
Cs-137 0.020
< LLD
< LLD 0
Ba-La-140 0.17
< LLD
< LLD 0
Ce-141 0.047
< LLD
< c LLD 0
Ce-144 0.11
< LLD
< LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations Is Indicated In parentheses (F).
d Locations are specified: (1) by name, and/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. 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 2004a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2003.
2001b through 2004b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2003.
2000.
Quality Assurance Program Manual, Rev. 0, 01 October 2003.
2000.
Quality Control Procedures Manual, Rev. 0, 21 September 2000.
2000.
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 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.
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 2003.
Prairie Island 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.
25
6.0 REFERENCES
CITED (continued)
Prairie Island Nuclear Generating Plant, 2003. Radiological Environmental Monitoring for Prairie Island 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-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 EnergyAgency. p.125.
Xcel Energy Corporation. 2004. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2003 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26
e PRAIRIE ISLAND Table D-1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.
Collection Analysis Location Type and Type and Medium No.
Codes (and Type)a Frequencyb Frequency' Ambient radiation (TLD s)
Airborne Particulates 54 P-01A-P-10A P-01B - P-15B P-01S - P-08S P-01 IA - P-081A P-011B - P-0818 P-01 IX-P-041X, P-01 C C/Q Ambient gamma GB, GS (QC of each location) 5 P-1(C), P-2, P-3, P-4, P-6 C/W Airborne Iodine Milk 5
P-1(C), P-2, P-3, P-4, P-6 5
P-14, P-18, P-37, P-42 P-41 [C]
C/W G/Md 1-131 1-131, GS River water 2
P-5(C), P-6 GNW GS(MC), H-3(QC)
Drinking water Well water I
P-1I G/W GB(MC), 1-131(MC)
H-3, GS 5
P-6, P-8, P-9, P-24, P-41 (C)
GIQ Edible cultivated crops -
leafy green vegetables Fish (one species, edible portion)
Periphyton or invertebrates Bottom sediment Shoreline sediment 2
P-38(C), P-24 GIA 2
P-19(C), P-13 2
P-40(C), P-6 2
P-20(C), P-6.
G/SA G/SA G/SA G/SA GS (1-131)
GS GS GS GS I
P-12 8 Location codes are defined In Table D-2. Control stations are Indicated by (C). All other stations are Indicators.
bCollection type Is coded as follows: C/ = continuous, GI = grab. Collection frequency Is coded as follows: W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
cAnalysis type Is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =
Iodine 131. Analysis frequency Is coded as follows: MC = monthly composite, QC = quarterly composite.
d Milk is collected biweekly during the grazing season (May - October).
D-1
T PRAIRIE ISLAND Table D-2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction from Code Typea Collection Site Sample Typeb Reactor P-1 P-2 P-3 P4 P-5 P-6 P-8 P-9 P-1I P-12 P-13 P-14 P-1 8 P-19 P-20 P-24 P-37 P-38 P-40 P-41 P-42 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 C
Huppert Farm Rother Farm AP, Al AP, Al AP, Al AP, Al RW AP, Al, RW WW, BS, BOo WW WW DW SS Fe M
M Fc BS VE, WW M
VE BOEC M,WW M
11.8 mi @ 3160/NNW 0.5 mi @ 2940/WNW 0.8 ml @ 313 0/NW 0.4 ml @ 3590/N 1.8 mi @ 11°/N 1.6 ml @ 1290/SE 1.0 mi @ 321 0/WNW 0.3 mi @ 3060/NW 3.3 mi @ 158°/SSE 3.0 ml @ 1160/ESE 3.5 ml @ 1130/ESE 2.3 ml @ 1730/S 3.8 ml @ 880/E 1.3 mi @ 0/1N 0.9 ml @ 450/NE 0.6 mi @ 158°/SSE 4.1 mi @ 870/E 14.2 ml @ 3590/N 0.4 mi @ 0°/N 13.8 ml @ 3540/N 4.3 ml. @ 264°/W General Area of the Site Boundarv P-01A P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-10A 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 ml © 3590/N 0.3 ml @ 100/N 0.5 ml @ 1830/S 0.4 mi @ 2040/SWW 0.4 ml @ 2250/SW 0.4 ml @ 249°/WSW 0.4 mi @ 268°/W 0.4 mi @ 291°/WNW 0.7 ml @ 31r/NW 0.5 ml @ 333°/NNW D-2
PRAIRIE ISLAND Table D-2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Distance and Direction from Code Type" Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant P-01B P-02B P-03B P-04B P-05B P-06B P-07B P-08B P-09B P-1OB P-11B P-12B P-13B P-14B P-15B Thomas Killian Residence Roy Kinneman Residence Wayne Anderson Farm Nelson Drive (Road)
County Road E and Coulee William Hauschbilt 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 Hoist Farms TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.7 mi @ 355°/N 4.8 mi @ 170/NNE 4.9 ml @ 46°/NE 4.2 mi @ 61°/ENE 4.2 mi @ 102°/ESE 4.4 ml 0 112°/ESE 4.7 mi @ 140°/SE 4.1 ml @ 165 0/SSE 4.2 ml @ 187°/S 4.9 ml @ 200°/SSW 4.5 ml @ 221°/SW 4.6 ml @ 251°/WSW 4.4 mi @ 270°/W 4.9 ml @ 3060/NW 3.8 ml @ 3450/NNW Special Interest Locations P.015 P-02S P-03S P-04S P-05S P-06S P-07S P-085 P-O1 C 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 ml @ 1290/SE 0.5 mi @ 155 0/SSE 2.2 ml @ 1730/S 2.0 ml © 2020/SSW 2.0 ml @ 270°NW 2.5 ml @ 2990 1WNW 0.7 ml @ 2710°W 0.7 ml © 287°/NWW 11.1 ml @ 3310/NNW D-3
PRAIRIE ISLAND Table D-2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Approximate Type of Distance and Direction Code Type" Collection Site Sampleb from ISFSI Center.
ISFSI Area Inside Earth Berm P-0IIA ISFSI Nuisance Fence TLD 190' @ 45°/NE P-021A ISFSI Nuisance Fence TLD 360' @ 820°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' @ 2190/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258°/SW P-071A ISFSI Nuisance Fence TLD 320' @ 281°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318°/NW P-01IX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 2700°W P-031X ISFSI Nuisance Fence TLD 140' @ 00/N P-041X ISFSI Nuisance Fence TLD 360' @ 9001E ISFSI Area Outside Earth Berm P-011B ISFSI Berm Area TLD 340' @30/N P-021B ISFSI Berm Area TLD 380' @ 280/NNE P-031B ISFSI Berm Area TLD 560' @ 850/E P-041B ISFSI Berm Area TLD 590' @ 1650/SSE P-051B ISFSI Berm Area TLD 690' @ 186°/S P-061B ISFSI Berm Area TLD 720' @ 2010/SSW P-071B ISFSI Berm Area TLD 610' @ 271°/W P-081B ISFSI Berm Area TLD 360' @ 332°/NNW a C denotes control location. All other locations are Indicators.
b Sample Codes:
AP Airborne particulates F
Fish Al Alrbome 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.
D-4
Environmental, inc.
Mdw est Laboratory to AJbgheny Techotoges Co.
700Ladwetr Road *I Nthbmck IL a0002-(847) 540700 z (847) 584-4517 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, 2003 through December, 2003
ApDendix A Interlaboratorv 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 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-1 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 were obtained for Thermoluminescent Dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of internal laboratory testing Is 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. 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
Analys Gammi Stronti Strontii Potass Gross; Attachment A ACCEPTANCE CRITERIA FOR OSPIKED' SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One standard deviation is Level for single determination a Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter
> 100 pCi/liter or kg 5% of known value um_89b 5 to 50 pCi/iter or kg 5.0 pCi/liter
> 50 pCiliter or kg 10% of known value um.90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
> 30 pCi/liter or kg 10% of known value ium40
> 0.1 g/liter or kg 5% of known value alpha 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value beta 100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 5% of known value 4,000 pCi/liter Is = (pCi/liter) 169.85 x (known)0 933
> 4,000 pCi/liter 10% of known value n-226,-228 0.1 pCi/liter 15% of known value uum 0.1 pCi/liter, gram, or sample 10% of known value
- 131, 55 pCi/liter 6.0 pCi/liter e-1 2 9b
> 55 pCi/liter 10% of known value m-238, 35 pCi/liter 6.0 pCi/liter
-b>
35 pCiliter 15% of known value Gross I Tritium Radiun Plutoni Iodine-Iodin Uraniui Nick(
Techn Iron-55 etium-99b
- b 50 to 100 pCi/liter
> 100 pCi/liter 10 pCi/liter 10% of known value Othersb 20% of known value
' From EPA publication, Environmental Radioactivity Laboratory Intercomparlson Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8.
Concentration (pCiIL)
Lab Code Date Analysis Laboratory ERA Control Resutb.
Result' Limits STW-973 STW-973 STW-974 STW-974 STW-974 STW-974 S1W-974 STW-975 STW-975 STW-976 STW-976 S1W-976 02117/03 02/17/03 02/17/03 02/17/03 02/17/03 02117/03 02/17/03 02/17/03 02117103 02117/03 02117/03 02/17/03 Sr-89 Sr-90 Ba-133 Co-60 Cs-1 34 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium 17.0
- 0.5 8.9
- 0.3 14.5 +/- 0.9 37.5 +/- 0.9 18.2 +/-0.6 42.7
- 1.0 56.8 +/- 2.2 18.4 +/-0.3 11.7 +/-0.5 4.1 +/- 0.1 7.6 +/- 0.5 52.9 +/-1.9 15.9 +/- 5.0 9.0 +/- 5.0 19.5 +/- 5.0 37.4 +/- 5.0 17.8 +/- 5.0 44.2 +/- 5.0 60.3 +/- 6.0 37.6 +/- 9.4 8.6 +/- 5.0 4.7 *0.7 6.5 +/- 1.6 53.7 +/- 5.4 7.2 - 24.6 0.4 - 17.7 10.8 - 28.2 28.7 - 46.1 9.1 - 26.5 35.5 - 52.9 49.9 - 70.7 21.3 - 53.9 0.0 - 17.2 3.5 - 6.0 3.7 -9.3 44.4 - 63.0 STW-983 05/19103 STW-984 05/19103 STW-985 05/19/03 STW-985 05119/03 STW-985 05/19/03 STW-985 05/19103 STW-986 051i9/03 STW-986' 05119/03 STW-986 05/19103 STW-986 05119103 STW-986 05/19/03 STW-986 05119/03 H-3 1-131 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-I 34 Cs-I 37 Gr. Beta Sr-89 Sr-90 1290.0 +/- 25.0 19.7 +/-1.3 54.4 +/- 3.0 14.9
- 0.2 13.1 +/- 0.6 14.5 +/- OA 56.9 +/- 8.6 61.6 +/- 6.6 143.0 +/- 1.2 309.0 +/- 2.7 33.1 +/-0.2 28.8 +/-1.3 1250.0 +/- 331.0 20.8 +/- 3.0 70.3 +/- 17.6 16.5 +/-2.5 10.3
- 2.6 15.1 +/-3.0 63.8 +/- 5.0 75.7 +/- 5.0 150.0 +/- 7.5 363.0 +/- 54.5 31.3 +/- 5.0 27.4 +/- 5.0 678.0 - 1820.0 15.6 - 26.0 39.9 - 101.0 12.2 - 20.8 5.8 - 14.8
- 9.9 - 20.3 55.1 - 72.5 67.0 - 84.4 137.0 - 163.0 269.0 - 457.0 22.6 - 40.0 18.7 - 36.1 STW-988 08/18/03 S1W-988 08/18/03 S1W-988 08118/03 STW-989 08/18/03 STW-989 08/18/03 STW-989 08/18/03 STW-989 08/18103 STW-989 08/18/03 STW-990 08/18/03 STW-990 ' 08/18/03 STW-991 08/18/03 STW-991 08/18/03 Ra-226 Ra-228 Uranium Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Sr-89 Sr-90 13.3 +/- 1.1 11.5 +/- 1.0 12.3 +/- 0.4 18.1 *1.9 35.9 +/- 1.3 32.6 +/- 1.8 48.3
- 0.6 58.9 *2.1 41.8 +/- 3.4 51.3 +/- 3.0 57.2 +/-4.3 21.2
- 0.9 13.4 +/-2.0 12.5 +/- 3.1 11.4 +/-L 3.0 20.7 *t 5.0 37.4 +/- 5.0 32.6 +/- 5.0 44.3 +/-E 5.0 60.2
- 6.0 56.2 +/- 16.3 31.6 +/- 5.0 58.8 +/- 5.0 20.6 +/- 5.0 9.9 -16.9 7.1 - 17.9 6.2 -16.6 12.0 - 29.4 28.7 - 46.1 23.9 - 41.3 35.6 - 53.0 49.8 - 70.6 36.9 - 93.3 22.9 - 40.3 50.1 - 67.5 11.9 - 29.3 Al-I
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCUL)
Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits STW-997 11/18/03 S1W-997 11/18/03 STW-998 11/18103 STW-999 11/18/03 STW-999 11/18103 STW-999 11/18103 STW-1000 11/18103 STW-1001 11/18/03 STW-1001 11/18/03 STW-1001 11/18/03 STW-1001 11/18/03 STW-1002 11/18103 STW-1002 11/18/03 STW-1002 11/18/03 STW-1002 11/18/03 STW-1002 11/18/03 STW-1002 11118/03 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-134 Cs-137 Gr. Beta Sr-89 Sr-90 37.0 ::2.0 26.5 *h 0.8 14.8 +/-0.3 17.2
- 1.1 6.6
- 0.3 11.7 +/-0.3 15900.0 +/- 174.0
- 32.9 +/- 0.3 16.5 +/- 0.9 6.2
- 0.5 9.7 +/- 1.5 27.7 : 1.9 21.5 +/-1.1 66.3 *2.8 159.0 +/- 2.5 48.5 0.4 10.1 +/-3.0 29.5 +/- 7.4 26.3 +/- 5.0 16.5
- 3.0 17.8
- 2.7 6.8
- 1.7 11.7 *3.0 14300.0 +/- 1430.0 54.2 *3.0 16.1 +/-2.4 5.5
- 1.4 9.3 +/-13.6 27.7 +/- 5.0 23.4
- 5.0 64.2
- 5.0 168.0 i 5.0 50.4
- 5.0 10.2 +/- 25.2 16.7 - 42.3 17.6 - 35.0 11.3 -21.7 13.2 - 22.4 3.8 - 9.7 6.5 - 16.9 11800.0 - 16800.0 30.7 - 77.7 11.9 - 20.3 3.1 -7.9 4.1 -14.5 19.0 - 36.4 17.6 - 29.2 55.5 - 72.9 124.0 - 212.0 41.7 - 59.1 1.5 - 18.9
' Results obtained by Environmental. Inc., Midwest Laboratory as a participant In the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).
- b 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 (I sigma, I determination) and control limits as provided by ERA d Recount of the original sample still low. The ERA blank was spiked In the lab; known value of 20.1 pCUL, measured 21.5 +/- 1.1 pCVL No explanaton for ERA test failure.
- Lower bias observed for gamma spectroscopic analysis. The undiluted sample was reanalyzed; Results of reanalysis, Co-60: 62.3 pCUL., Cs-134: 69.2 pCUL., Cs-137: 152.3 pCUL
'Reason for devIation unknown. A recount of the original planchets averaged 43.4 pCUL.
Cs-137activity by gamma spectroscopy; 28.3 pCUL. Result of reanalysis: 29.3 pCUL.
A1-2
TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).
rnR Lab Code TLD Type Date Known Lab Result Control Description Value
+/- 2 sigma Limits Environmental. Inc.
2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 81812003 81812003 818/2003 818/2003 81812003 818/2003 81812003 8/8/2003 818/2003 Reader 1,120 Reader 1,150 Reader 1,180 Reader 1,180 Reader 1,30 Reader 1,60 Reader 1,60 Reader 1,90 Reader 1,90 4.69 3.00 2.08 2.08 75.00 18.75 18.75 8.33 8.33 4.74 +/-t 0.54 3.02 +/- 0.20 1.89 +/- 0.45 2.11 + 0.22 84.40 +/- 4.87 19.11 +/- 1.86 22.82 +/- 5.41 9.05 +/- 1.17 7.60 i 1.08 3.28 - 6.10 2.10 - 3.90 1.46 - 2.70 1.46 - 2.70 52.50 - 97.50 13.13 - 24.38 13.13 - 24.38 5.83 - 10.83 5.83 - 10.83 Environmental, Inc.
2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 1/1212004 1/12/2004 1/12/2004 1/12/2004 1/1212004 111212004 111212004 1/1212004 1/1212004 Reader 1,30 Reader 1,60 Reader 1,60 Reader 1,90 Reader 1,90 Reader 1,120 Reader 1,150 Reader 1,150 Reader 1,180 61.96 15.49 15.49 6.88 6.88 3.87 2.48 2.48 1.72 73.50 +/- 2.58 19.70 +/-E 0.51 16.93 +/- 1.37 8.06 +/- 0.60 6.64 i 0.58 4.39 +/- 0.17 2.34 +/- 0.18 2.51 +/- 0.16 2.01 +/- 0.13 43.37 - 80.55 10.84 - 20.14 10.84 - 20.14 4.82 - 8.94 4.82 - 8.94 2.71 - 5.03 1.74 - 3.22 1.74 - 3.22 1.20 - 2.24 A2-1
TABLE A-3. In-House 'Spikew Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=lb Activity Limits" SPW-356 W-10303 W-1 1303 W-12103 SPAP-446 SPW-468 W-20703 SPU-1 347 DW-30303 SPCH-964 SPMI-1086 SPMI-1086 SPMI-1086 SPW-1088 SPW-1088 SPW-1 088 SPW-1088 SPVE-1110 SPW-1194 SPW-1194 SPW-1 194 W-32103 SPCH-1429 W-40103 SPF-1407 SPF-1407 SPAP-1409 SPU-41203 SPU-41703 SPW-2022 SPW-2053 SPW-2053 SPMI-2055 SPMI-2055 W-50603 W-60303 SPW-3960 SPMI-4019 SPMI-4019 SPMI-4019 SPW-4023 SPW-4023 SPW-4023 SPW-4518 water water water water Air Filter water water Urine water Charcoal Milk Milk Milk water water water water Vegetation, water water water water Charcoal water Fish Fish Air Filter Urine Urine water water water Milk Milk water water water Milk Milk Milk water water water water 1/2/2003 1/3/2003 1/1312003 1/21/2003 1/31/2003 1/31/2003 2/7/2003 3/1/2003 3/3/2003 3/8/2003 3/13/2003 3113/2003 3/1312003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/14/2003 3/21/2003 3/21/2003 3/21/2003 3/21/2003 4/1/2003 4/1/2003 4/2/2003 4/2/2003 4/2/2003 4/12/2003 4117/2003 4/25/2003 4/28/2003 4/28/2003 4/28/2003 4/28/2003 5/6/2003 6/3/2003 7/15/2003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 8/8/2003 Sr-90 Gr. Beta Gr. Beta Gr. Beta Gr. Beta H-3 Fe-55 H-3 Gr. Beta 1-131(G)
Cs-137 1-131 1-131 (G)
Co-60 Cs-137 1-131 (G) 1-131 1-131 (G)
C-14 1-131 (G)
Gr. Beta Cs-1 34 Cs-137 Gr. Beta H-3 H-3 H-3 Cs-137 Sr-90 Cs-137 Sr-9o Gr. Beta Gr. Beta H-3 Cs-137 Sr-89 Sr-90 Cs-137 Sr-89 Sr-90 Fe-55 34.04 i 1.57 63.24 +/- 1.20 59.75 +/- 1.10 61.56 +/- 1.59 1.49 +/-0.02 95982.00 +/- 865.00 9095.00 +/- 114.00 1724.00 +/-412.00 65.44 +/- 0.59 73.37 +/- 0.28 57.18 +/- 8.03 75.13 +/- 12.01 65.81 +/- 1.06 27.16 +/- 4.79 51.74 +/- 9.15 68.14 +/- 12.92 76.94 +/- 1.13 122.80 +/- 16.80 31.09 +/- 6.28 55.11 +/- 0.13 66.17 +/- 9.15 5201.00
- 16.60 8.83 +/- 0.11 67.74 +/- 0.52 0.58
- 0.03 1.29 i 0.06 1.44 +/- 0.02 1798.50 +/- 409.30 1625.10 +/- 401.30 89007.00 +/- 798.00 45.70 +/- 9.44 47.51
- 1.87 61.65
- 7.17 38.45 +/-1.59 70.95 +/- 0.53 63.00 +/- 0.51 88700.00 +/- 822.00 47.17 *7.22 40.95
- 4.88 45.30 +/- 1.73 51.92 +/- 6.24 42.49
- 10.23 49.69 +/- 3.04 8176.00 +/- 107.00 30.93 63.90 63.90 63.99 1.52 89607.00 10587.00 1784.33 63.90 69.45 49.50 67.60 67.56 28.20 49.50 67.60 67.56 124.00 28.15 49.50 67.60 4966.00 9.18 63.39 0.59 1.32 1.51 1784.33 1784.33 88463.00 49.35 44.47 65.80 44.74 63.39 65.73 87369.00 49.11 49.49 44.24 49.11 49.49 44.24 9330.00 24.74 - 37.12 53.90 - 73.90 53.90 - 73.90 53.99 - 73.99
-8.48 -11.52 71685.60 - 107528.40 8469.60 - 12704.40 1101.27 - 2467.39 53.90 - 73.90 59.45 - 79.45 39.50 - 59.50 54.08 - 81.12 57.56 - 77.56 18.20 - 38.20 39.50 - 59.50 57.60 - 77.60 54.05 - 81.07 111.60 -136.40
.18.15 - 38.15 39.50 - 59.50 57.60 - 77.60 2979.60 - 6952.40
-0.82 - 19.18 53.39 - 73.39 0.35 - 0.83 0.79 - 1.85
-8.49 - 11.51 1101.27 - 2467.39 1101.27 - 2467.39 70770A0 - 106155.60 39.35 - 59.35 35.58 - 53.36 55.80 - 75.80 35.79 - 53.69 53.39 - 73.39 55.73 - 75.73 69895.20 - 104842.80 39.11 - 59.11 39.49 - 59.49 35.39 - 53.09 39.11 - 59.11 39.49 - 59.49 35.39 - 53.09 7464.00 - 11196.00 A3-1
TABLE A-3. In-House "Spike Samples Concentration (pCVL)
Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Llmitsc SPW-6197 water 10/16/2003 Tc-99 540.14 t 54.00 539.73 377.81 -701.65 SPAP-3958 Air Filter 10/28/2003 Gr. Beta 1.45 i 0.02 1.50
-8.50 - 11.50 SPW-6401 water 10/28(2003 H--3 84867.00
- 826.00 85984.00 68787.20 - 103180.80 SPAP-6403 Air Filter 10128/2003 Gr. Beta 1.71 t 0.02 1.49
-8.51 -11.49 SPF-6418 Fish 10/28/2003 Cs-1 34 0.50
- 0.02 0.49 0.29 -0.69 SPF-6418 Fish 10/28/2003 Cs-137 1.37 +/- 0.05 1.30 0.78 - 1.82 SPW-6421 water 10/28/2003 Fe-55 104.18 +/-E 1.26 88.18 68.18 - 108.18 SPMI-7459 Milk 12112/2003 Cs-134 41.06 +/-t 2.45 41.88 31.88 - 51.88 SPMI-7459 Milk 1211212003 Cs-137 48.48 +/- 4.99 48.64 38.64 - 58.64 SPMI-7459 Milk 1211212003 Sr-89 55.94
- 4.12 65.80 52.64 -78.96 SPMI-7459 Milk 1211212003 Sr-90 41.86 +/- 1.57 43.80 35.04 - 52.56 SPW-7461 water 12/12/2003 Cs-134 44.07 +/- 1.A9 41.88 31.88 - 51.88 SPW-7461 water 12/12/2003 Cs-137 50.26
- 2.67 48.64 38.64 - 58.64 SPW-7461 water 12/12/2003 Sr-89 56.41 +/-4.87 65.80 52.64 -78.96 SPW-7461 water 12112/2003 Sr-90 48.44 +/- 1.84 43.80 35.04 - 52.56 c 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.
A3-2
TABLE A-4. In-House 'Blank' Samples Concentration (pCi/VLr Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 a)
SPW-357 W-10303 W-11303 W-12103 SPAP-447 SPW-469 W-20103 W-20703 DW-30303 water water water water Air Filter water water water 1/2w2003 1/3/2003 1113/2003 1/13/2003 1/21/2003 1/31/2003 1/31/2003 2/1/2003 2/7/2003 3/3/2003 SPCH-965 Charcoal Cani: 3/8/2003 SPMI-1087 SPMI-1087 SPMI-1087 SPMI-1087 SPW-1089 SPW-1089 SPW-1089 SPW-1089 SPVE-1111 W-32103 Milk Milk Milk Milk water water water water Vegetation water 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3113/2003 3/13/2003 3/13/2003 3/13/2003 3/14/2003 3/21/2003 SPCH-1430 Charcoal Cani: 4/1/2003 W-40103 SPF-1408 SPF-1408 SPAP-1410 SPU-41203 SPU-41703 SPW-2054 SPW-2054 SPW-2054 SPMI-2056 '
SPMI-2056 SPMI-2056 W-50603 W-60303 SPW-3960 SPMI-4018 SPMI-4018 SPMI-4018 SPW-4024 SPW-4024 SPW-4519 SPW-6401 water Fish Fish Air Filter Urine Urine water water water Milk Milk Milk water water water Milk Milk Milk water water water water 4/1/2003 4/2/2003 4/2/2003 4/2/2003 4/12/2003 4/17/2003 4/28/2003 4/28/2003 4/28/2003 4/28/2003 4/28/2003 4/28/2003 5/6/2003 6/3/2003 7/15/2003 7/1812003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 8/812003 10/28/2003 Sr-9o Gr. Beta Gr. Beta Gr. Beta Gr. Beta H-3 Gr. Beta Fe-55 Gr. Beta 1-131 (G)
Cs-134 Cs-137 1-131 1-131(G)
Co-60 Cs-I 34 Cs-I 37 1-131 1-131 (G)
C-14 1-131 (G)
Gr. Beta Cs-I 34 Cs-1 37 Gr. Beta H-3 H-3 Cs-1 37 Sr-89 Sr-90 Sr-90 Cs-137 1-131 (G)
Gr. Beta Gr. Beta H-3 Cs-137 Sr-89 Sr-90 Sr-89 Sr-90 Fe-55 H-3 0.50 0.12 0.14 0.12 0.00 160.20 0.17 802.00 0.15 0.01 7.49 7.90 0.33 7.76 4.48 5.60 4.32 0.29 7.53 17.50 0.01 0.14 0.01 0.01 0.00 653.99 648.35 3.16 0.55 0.55 0.77 2.74 3.54 0.12 0.14 156.60 4.10 0.73 0.51 0.83 0.62 527.00 163.80 0.12 i 0.25 0.022 +/- 0.10 0.035
- 0.10 0.029 +/- 0.09
-0.0034 + 0.00 19.3 +/- 80.30 0.0 +/- 0.12 149 +/- 498.00 0.007
- 0.11
-0.013 +/- 0.18
-0.050 i 0.16
-0.4 +/- 9.200
-0.11 +/-0.100
-0.0029 i 0.002 542.28 +/- 364.780 100.1 +/-344.800 0.45 i 0.50 0.072
- 0.260 0.66 +/- 0.430 0 0.090
-0.035 +/- 0.095 53.4 +/- 80.200 0.39 +/- 0.880 0.93 +/- 0.340 0.21 +/- 0.730 0.09 +/- 0.300 87 +/- 369.000
-23.8 +/- 85.000 1
3.2 3.2 3.2 3.2 200 3.2 1000 3.2 9.6 10 10 0.5 20 10 10 10 0.5 20 200 9.6 3.2 100 100 3.2 200 200 10 5
1 1
10 20 3.2 3.2 200 10 5
1 5
1 1000 200 A4-1
TABLE A-4. In-House t Blank" Samples Concentration (pCVL)a Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 a)
SPAP-6404 SPF-641 9 SPF-6419 SPMI-7460 SPMI-7460 SPMI.7460c Air Filter Fish Fish Milk Milk Milk 10128/2003 Gr. Beta 10/28/2003 Cs-134 10/28/2003 Cs-137 12/12/2003 Cs-134 12/12/2003 Cs-137 12/12/2003 Sr-90 0.87 0.01 0.01 4.52 5.77 0.50
-0.99
- 0.440 1.26 i 0.370 3.2 100 100 10 10 1
I
' Uquid sample results are reported In pCILIIter, air filters( pCIfilter), charcoal (pCIcharcoal canister), and solid samples (pCIkg).
b The acUvity reported Is the net activity result.
' Low levels of Sr-90 are still detected in the environment A concentration of (1-5 pCVL) In milk Is not unusual.
A4-2
TABLEA-5. In-House'Duplicate'Sarribles Concentration (pCUL)'
Averaged Lab Code Date Analysis First Result Second Result Result MI-24, 25 MI-24, 25 CF-47,48 CF-47,48 AP-8827, 8828 AP-8869, 8870 MI-119,120 MI-119,120 MI-213,214 MI-213, 214 MI-262,263 S-696,697 S-696, 697 MI-448,449 SW-470,471 SW-470,471 SW-470,471 MI-517, 518 MI-541, 542 MI-620, 621 DW-922,923 CF-1048,1049 b LW-1152,1153 F-1120,1121 F-1120,1121 F-1120,1121 DW-1278,1279 SO-1380, 1381 LW-1299,1300 LW-1320, 1321 W-1403,1404 AP-2019, 2020 MI-1422,1423 MI-2170, 2171 MI-1422,1423 AP-1633,1634 AP-1871,1872 AP-1 974, 1975 LW-1828,1829 S-1544,1545 DW-1913,1914 MI-1996,1997 MI-1996,1997 112/2003 112/2003 11212003 1/2/2003 1212003 112/2003 118/2003 1/8/2003 1/14/2003 1/14/2003 1/15/2003 112912003 1/29/2003 2/3/2003 2/3/2003 213/2003 2/3/2003 2/412003 2/5/2003 2/11/2003 3/4/2003 3/10/2003 3113/2003 3/1412003 311412003 3114/2003 3/25/2003 3125/2003 3/27/2003 3/27/2003 3/31/2003 3/31/2003 4/1/2003 411/2003 4/2/2003 4/212003 41212003 4/2/2003 4/11/2003 4/1512003 4/15/2003 4/21/2003 4/22/2003 K-40 Sr-90 Gr. Beta K-40 Be-7 Be-7 K-40 Sr-90 K-40 Sr-9o K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 (ICP)
K-40 K-40 K-40 K-40 1-131 K-40 H-3 Cs-137 Gr. Beta K40 1-131 Gr. Beta Gr. Beta H-3 Sr-90 Be-7 K-40 K-40 Sr-90 Be-7 Be-7 Be-7 Gr. Beta K-40 1-131 Sr-90 K-40 1362.00 i 117.00 1.45 +/- 0.40 2.72 +/- 0.10 2.61 +/- 0.31 0.06 +/- 0.01 0.04 +/- 0.02 1351.90 +/-116.10 2.22 +/- 0.43 1372.30 +/- 104.80 1.81 +/-0.41 1399.20 +/- 200.70 24.70 +/- 4.89 22.89 +/- 2.67 1159.70 +/- 157.90 13.62 +/- 1.23 5.10 +/- 0.51 5.80 +/- 0.51 1437.70 +/- 125.50 1443.00 +/- 194.80 1294.70 +/- 115.10 0.67 +/- 0.16 3.09 +/- 0.12 1147.26 +/- 122.56 0.04 +/- 0.02 2.04 +/- 0.06 1.93 +/- 0.38 0.37 i 0.22 18.60 +/- 2.68 2.35 +/- 0.55 487.12 +/- 104.43 0.96 +/- 0.32 0.07 +/- 0.01 1410.00 +/- 176.00 1452.30 +/- 129.10 1.84 +/- 0.42 0.05 +/- 0.01 0.07 +/- 0.01 0.08 +/- 0.02 2.49 +/- 0.58 15.84 +/- 2.36 0.29 +/- 0.21 2.05 +/- 0.74 1580.20 +/- 118.90 1377.00 +/- 188.00 2.21 +/- 0.50 2.84 +/- 0.10 2.32 +/- 0.12 0.05 +/- 0.02 0.05 +/- 0.02 1234.70 +/- 108.70 1.88 +/- 0.40 1303.80 +/- 109.10 2.29 +/- 0.45 1347.70 +/- 126.40 23.23 +/- 4.64 22.71 +/- 2.73 1396.40 +/- 106.20 15.21 +/- 1.21 5.20 +/- 0.52 5.90 +/- 0.52 1357.70 +/- 188.00 1385.20 +/- 190.10 1234.10 +/- 165.10 0.79 +/- 0.16 2.67 +/- 0.07 1094.42 +/- 120.92 0.05 +/- 0.01 2.11 +/- 0.06 1.89 +/- 0.25 0.34 +/- 0.29 20.53 +/- 2.83 2.48 +/- 0.56 422.00 +/- 102.00 1.10 +/-0.42 0.08 +/- 0.01 1340.00 +/- 114.00 1472.50 +/- 191.00 1.15 +/- 0.39 0.06 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.02 3.42 +/- 0.63 15A1 +/- 2.02 0.42 +/- 0.19 3.25 +/- 0.91 1602.10 +/- 120.40 1369.50 +/- 110.72 1.83 +/- 0.32 2.78 +/- 0.07 2.47 +/- 0.17 0.05 +/- 0.01 0.05 +/- 0.01 1293.30 +/- 79.52 2.05 +/- 0.30 1338.05 +/- 75.64 2.05 +/- 0.31 1373.45 +/- 118.59 23.97 +/- 3.37 22.80 +/- 1.91 1278.05 +/- 95.15 14.42 +/- 0.86 5.15 +/- 0.36 5.85 +/- 0.36 1397.70 +/- 113.02 1414.10 +/- 136.09 1264.40 +/- 100.63 0.73 +/- 0.11 2.88 +/- 0.07 1120.84 +/- 86.09 0.05 +/- 0.01 2.08 +/- 0.04 1.91 +/- 0.23 0.36 +/-0.18 19.57 +/- 1.95 2.42 +/- 0.39 454.56 +/- 72.99 1.03 +/- 0.26 0.07 +/- 0.01 1375.00 +/- 104.85 1462.40 +/- 115.27 1.50 +/- 0.29 0.06 +/- 0.01 0.07 +/- 0.01 0.08 +/- 0.01 2.96 +/- 0.43 15.63 +/-1.55 0.36 +/- 0.14 2.65 +/- 0.58 1591.15 +/- 84.61 A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCVL)8 Averaged Lab Code Date Analysis First Result Second Result Result LW-2063, 2064 SWU-2275, 2276 G-2149, 2150 TD-2339, 2340 SO-2381, 2382 SO-2381, 2382 SO-2381, 2382 SO-2381, 2382 SO-2381, 2382 DW-2317, 2318 BS-2595,2596 BS-2595, 2596 U-2484, 2485 SO-2645, 2646 S0-2645,2646 SO-2645,2646 MI-2696. 2697 MI-2696, 2697 SO-2787, 2788 SO-2787, 2788 SO-2787, 2788 MI-2840,2841 SWU-2864, 2865 BS-2888, 2889 BS-2888,2889 W-3230, 3231 TD-3036,3037 SL-2909, 2910 b SL-2909, 2910 SW-3080,3081 SW-3080,3081 VE-3172, 3173 F-3742, 3743 F-3742,3743 SO-3325,3326 MI-3253,3254 MI-3297,3298 WW-3380, 3381 SWT-3403,3404 MI-3424,3425 SW-3862,3863 G-3479, 3480 G-3479,3480 LW-3809, 3810 4/28/2003 4t2812003 4/3012003 5/1/2003 5/112003 5/1/2003 5/1/2003 5/1/2003 5/1/2003 5/6/2003 5/6/2003 5/6/2003 5/9/2003 5/14/2003 5/14/2003 5/14/2003 5119/2003 5/19/2003 5/28/2003 5/28/2003 5/28/2003 5/28/2003 5/28/2003 5/29/2003 5/29/2003 5/30/2003 6/2/2003 6/3/2003 6/3/2003 6/10/2003 6/10/2003 6/111/2003 6/11/2003 6/11/2003 6/13/2003 6/17/2003 6/17/2003 6/23/2003 6/24/2003 6/24/2003 6/24/2003 6/25/2003 6/25/2003 6/30/2003 Gr. Beta Gr. Beta Be-7 H-3 Cs-137 Gr. Alpha Gr. Beta K-40 Sr-90 1-131 Cs-137 K-40 H-3 Be-7 Cs-137 K-40 K-40 Sr-90 Cs-I 37 Gr. Beta K-40 K-40 Gr. Beta Cs-137 K-40 Gr. Beta H-3 Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Beta Gr. Beta K-40 Gr. Beta Be-7 K-40 Gr. Beta 2.33 +/- 0.66 3.62
- 0.67 0.71 *0 0.19 221.00 +/- 91.00 0.11 0.03 11.14 *5.15 35.18 *4.69 18.29 +/- 0.84 0.06 +/- 0.02 1.77 +/- 0.27 0.06 +/- 0.02 13.74 +/-0.62 512.00 +/- 100.00 1.18 +/- 0.42 0.11 +/- 0.04 16.50
- 1.13 1320.40 +/- 124.50 1.49 +/- 0.47 0.27 +/- 0.04 19.62 +/- 1.73 14.77
- 1.02 1179.50 +/- 167.80 3.39 +/- 0.59 0.05 +/- 0.02 9.70
- 0.83 4.33 +/- 1.00 529.50
- 100.00 7.10 +/-0.15 3.90 +/- 0.67 4.63
- 1.90 9.07
- 1.29 2.62 +/- 0.35 3.47 +/- 0.13 2.94 +/- 0.39 20.95
- 1.88 1329.40 +/- 121.80 2.14 +/- 0.57 5.58 +/- 0.69 2.80 +/- 0.56 1422.80 +/- 185.40 3.66 +/- 1.18 1.52 +/- 0.25 5.02 +/- 0.45 2.12 +/- 0.76 2.68 +/- 0.60 4.60 +/- 0.71 0.69 +/- 0.20 161.00
- 88.00 0.10 +/- 0.02 10.39 +/- 5.60 39.66 +/- 5.24 17.83 +/- 0.84 0.10
- 0.02 1.47 +/- 0.26 0.06 +/- 0.02 14.10
- 0.73 370.00 +/- 95.00 1.21
- 0.35 0.09
- 0.05 15.33 *1.09 1394.10 +/- 113.00 2.01 i 0.45 0.23 +/- 0.04 20.81
- 1.72 14.41
- 1.00 1401.70 +/- 120.20 3.41 +/- 0.64 0.07 +/- 0.04 10.17
- 0.87 3.28 +/- 1.22 585.50 +/- 102.00 7.60 +/- 0.16 3.49 +/- 0.52 4.47 +/- 1.71 8.98 +/- 1.28 3.17 +/- 0.58 3.71 +/- 0.14 2.70 +/- 0.40 19.97 i 2.01 1417.60
- 130.90 2.27
- 0.50 5.03
- 0.69 2.63 i 0.55 1216.20
- 170.10 3.70
- 1.22 1.43
- 0.28 5.10
- 0.48 2.39 +/- 0.72 2.51
- 0.45 4.11 +/-0.49 0.70 +/- 0.14 191.00 +/- 63.29 0.10 +/- 0.02 10.77 +/- 3.80 37.42 +/- 3.52 18.06 +/- 0.59 0.08 +/- 0.01 1.62 +/- 0.19 0.06 +/- 0.02 13.92 +/- 0.48 441.00 +/- 68.97 1.19 +/- 0.27 0.10 +/- 0.03 15.91 +/-0.79 1357.25 +/- 84.07 1.75 +/- 0.32 0.25 +/- 0.03 20.21 +/- 1.22 14.59
- 0.71 1290.60 +/- 103.20 3.40 +/- 0.43 0.06 +/- 0.02 9.93 +/- 0.60 3.81 +/- 0.79 557.50
- 71.42 7.35 +/- 0.11 3.70
- 0.42 4.55 +/- 1.28 9.02 +/- 0.91 2.90 +/- 0.34 3.59 +/- 0.10 2.82 +/- 0.28 20.46 +/- 1.38 1373.50 +/- 89.40 2.21 +/- 0.38 5.31 +/- 0.49 2.72 +/- 0.39 1319.50 +/- 125.80 3.68 +/- 0.85 1.47 +/- 0.19 5.06 +/- 0.33 2.25
- 0.52 A5-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)s Averaged Result Lah Code Daqte Analvsis First Result Second Result LW-3809, 3810 AP-4105,4106 G-3572,3573 G-3572,3573 G-3572,3573 G-3572,3573 MI-3601, 3602 MI-3601, 3602 AP-3933, 3934 AP-4061, 4062 AP-4147,4148 AP-4084,4085 LW-3786,3787 WW-4168, 4169 CF-3975, 3976 CF-3975, 3976 MI-4020,4021 DW-4272,4273 SWU-4461,4462 SL-4398,4399 SL-4398,4399 b SL-4398,4399 G-4419.4420 G-4419,4420 G-4419,4420 TD-4550,4551 MI-4482,4483 MI-4482,4483 G-4526,4527 G-4526,4527 SWU-4609,4610 CW-4694,4695 CW-4694,4695 LW-4673,4674 MI-4735,4736 MI-4756,4757 VE-4832,4833 MI-4860,4861 SO-5082, 5083 SO-5082,5083 CW-5349,5350 CW-5349, 5350 ME-4968,4969 ME-4968,4969 6/3012003 6/30/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7/2/2003 7/2/2003 7/3/2003 7/9/2003 7/11/2003 7/14/2003 7/14/2003 7/16/2003 7/29/2003 7/30/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/13/2003 8/19/2003 8/19/2003 8/20/2003 8/26/2003 8/28/2003 8/28/2003 8/31/2003 8/31/2003 9/2/2003 9/2/2003 H-3 Be-7 Be-7 Gr. Beta K-40 Sr-90 K-40 Sr-90 Be-7 Be-7 Be-7 Be-7 Gr. Beta Gr. Beta Be-7 K-40 K-40 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 Gr. Beta K-40 H-3 K-40 Sr-90 Be-7 K-40 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 Sr-90 K-40 K-40 Cs-137 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 2814.09
- 167.99 0.07 +/- 0.01 0.91 +/-0.24 6.35 +/- 0.15 5.44 +/-0.55 0.01 +/- 0.00 1318.60 +/- 117.40 0.86 +/- 0.51 0.07 +/- 0.01 0.07 : 0.01 0.08 +/- 0.01 0.09 +/- 0.02 2.13 +/-0.56 3.79 +/- 1.87 1.64 +/- 0.81 6.54 +/-t 0.75 1350.90 +/- 174.90 2.35 +/- 0.92 2.28 +/- 0.44 4.55 +/- 1.05 3.41 +/- 0.12 2.47 +/- 0.67 3.98 + 0.63 5.38 f 0.14 4.42 +/- 0.66 327.30 i 95.10 1301.40
- 115.20 0.81 +/-0.30 1.47
- 0.29 5.42 + 0.56 3.22 +/- 0.63 1.48
- 0.34 22776.41
- 428.73 2.86
- 0.65 1396.30 +/- 127.90 1.66
- 0.47 1.96
- 0.50 1312.10 +/- 191.80 0.01 *0.00 20.02
- 1.84 1.45
- 0.39 24429.50
- 444.42 4.90 +/- 0.23 2.46 F 0.41 2812.17 +/- 167.94 0.07 + 0.01 0.81 i0.28 6.35 +/- 0.15 5.68 +/- 0.28 0.02 +/- 0.00 1435.10 +/- 117.80 1.74 +/- 0.60 0.07 +/- 0.01 0.08 i 0.01 0.07 i 0.01 0.08 i 0.02 2.93 +/- 0.62 4.48 +/- 1.98 1.66 +/- 0.57 6.19 +/- 0.50 1199.80 +/- 153.20 2.29 +/- 0.89 1.93 +/- 0.43 4.50 +/- 1.10 3.12 +/- 0.11 2A4 +/- 0.87 3.93 +/- 0.57 5.35 +/- 0.16 4.32 +/- 0.74 390.20 +/- 92.10 1370.30 +/- 116.80 0.85 +/- 0.31 1.42 +/- 0.28 5.21 +/- 0.63 2.67 +/- 0.64 1.09 +/- 0.34 21831.75 +/- 420.10 3.75 +/- 0.71 1410.10 +/- 120.20 1.53 +/- 0.44 1.43 +/- 0.47 1307.80 +/- 109.30 0.01 +/- 0.00 20.92 +/- 2.03 1.55 +/- 0.45 24744.25 +/-447.18 5.18 +/- 0.24 2.68 +/- 0.37 2813.13 +/- 118.77 0.07 +/- 0.01 0.86 +/- 0.18 6.35 +/- 0.11 5.56 +/- 0.31 0.01 +/- 0.00 1376.85 +/- 83.16 1.30 +/- 0.39 0.07 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 0.08 +/- 0.01 2.53 +/- 0.42 4.14 +/- 1.36 1.65 +/- 0.50 6.36 +/- 0.45 1275.35 +/- 116.25 2.32 +/- 0.64 2.10 +/- 0.31 4.53 +/- 0.76 3.27 +/- 0.08 2.46 +/- 0.55 3.96 +/- 0.42 5.37 +/- 0.11 4.37 +/- 0.50 358.75 +/- 66.19 1335.85 +/- 82.03 0.83 +/- 0.21 1.45 +/- 0.20 5.31 +/- 0.42 2.95 +/- 0.45 1.29 +/- 0.24 22304.08 +/- 300.12 3.30 +/- 0.48 1403.20 +/- 87.76 1.60 +/- 0.32 1.70 +/- 0.34 1309.95 +/- 110.38 0.01 +/- 0.00 20.47 +/- 1.37 1.50 +/- 0.30 24586.88 +/-315.23 5.04 +/- 0.17 2.57. 0.28 A5-3
TABLEA-5. In-House"Duplicate"SSarples Concentration (pCVL)-
Averaged Lab Code Date Analysis First Result Second Result Result*
DW-4989, 4990 MI-5154, 5155 MI-5154, 5155 AP-6177, 6178 SWU-5773, 5774 AP-6102, 6103 G-5631, 5632 G-5631, 5632 G-5631, 5632 S0-5660, 5661 SO-5660, 5661 SO-5660, 5661 SO-5660, 5661 SO-5660, 5661 AP-6334, 6335 AP-6363, 6364 MI-5794. 5795 MI-5838, 5839 MI-5838, 5839 BS-5938, 5939 BS-5938, 5939 SS-5959, 5960 MI-6011, 6012 MI-6034, 6035 VE-6055, 6056 VE-6055, 6056 MI-6291, 6292 MI-6291, 6292 SS-6435, 6436 SS-6435, 6436 CF-6313, 6314 SO-6528, 6529 SO-6528, 6529 SO-6393, 6394 SO-6393, 6394 SO-6393, 6394 SWT-6507, 6508 DW-6647, 6648 BS-6603, 6604 BS-6603, 6604 S0-6670, 6671 S0-6670, 6671 S-7067, 7068 MI-6818, 6819 9/212003 9/8/2003 918/2003 9/29/2003 9/30/2003 9/30/2003 10/1/2003 10/1/2003 10/11/2003 10/1/2003 10/1/2003 1011/2003 1011/2003 10/1/2003 10/1/2003 10/212003 10/6/2003 10/8/2003 10/8/2003 1018/2003 10/812003 10113/2003 10113/2003 10/14/2003 1011512003 10/15/2003 10/21/2003 10/21/2003 10/21/2003 10121/2003 10/22/2003 10/22/2003 10/22/2003 10125/2003 10125/2003 10125/2003 1012812003 10/31/2003 11/3/2003 11/3/2003 11/512003 11/512003 11/1012003 11/11/2003 Gr. Beta K-40 Sr-90 Be-7 Gr. Beta Be-7 Be-7 Gr. Beta K-40 Cs-137 Gr. Alpha Gr. Beta K-40 Sr-90 Be-7 Be-7 Sr-90 K-40 Sr-90 Cs-I 37 K-40 K-40 K-40 Sr-90 Gr. Beta K-40 K-40 Sr-90 Cs-I 37 K-40 K-40 Cs-I 37 K-40 Cs-I 37 Gr. Beta K-40 Gr. Beta 1-131 Cs-137 Gr. Beta Cs-137 K-40 Cs-137 K-40 2.20 +/- 1.04 1365.50 +/- 116.70 1.19 +/-0.39 0.07 +/- 0.01 2.55 +/- 0.63 0.07 +/- 0.01 1.88 +/-0.48 5.87 +/- 0.09 5.24 *d 0.77 0.15 +/- 0.04 12.72 +/- 3.72 32A2 +/- 3.09 18.93 +/- 0.87 0.03
- 0.01 0.06 *E 0.01 0.07
- 0.02 1.37 +/- 0.37 1364.30
- 124.10 0.76 +/- 0.30 0.18 +/- 0.03 15.59 +/- 0.70 7A9 +/- 0.42 1165.20 +/- 118.70 0.86 +/- 0.33 5.18 +/- 0.18 5.31 +/- 0.57 1935.60 +/- 147.70 1.22
- 0.39 0.05
- 0.02 14.08
- 0.54 14.56 +/- 0.45 0.15
- 0.03 17.46 +/- 0.69 0.09 +/- 0.03 23.21
- 1.98 13.98 +/- 0.80 2.64
- 0.52 0.46 +/- 0.27 9.03 +/- 0.82 26.83 +/- 1.94 0.15
- 0.04 12.96 +/- 0.66 0.21 +/- 0.05 1695.50 -t 129.80 3.19 +/- 1.14 1456.70 +/- 119.10 1.39 +/- 0.39 0.06 +/- 0.01 2.83 +/- 0.60 0.05 +/- 0.01 2.21 +/- 0.40 5.85 +/- 0.08 5.26 +/- 0.58 0.16 +/- 0.05 14.86 +/- 3.88 33.60 +/- 3.04 18.25 +/- 1.19 0.03 i 0.01 0.06 +/- 0.01 0.07 +/- 0.02 1.02 +/- 0.37 1414.40 +/-110.40 1.00 +/- 0.34 0.20 +/- 0.05 16.69 +/- 0.80 7.29 +/- 0.63 1191.20 +/- 99.50 0.90 +/- 0.34 5.33 +/- 0.18 4.52 +/- 0.51 1936.10
- 116.50 1.41 +/- 0.37 0.05 +/- 0.03 14.28 +/- 0.80 14.70 +/- 0.95 0.16 +/- 0.05 17.90 +/- 1.05 0.10 +/- 0.04 21.76 +/- 1.91 14.57 +/- 0.86 2.63 +/- 0.53 0.61 i0.31 8.60 +/- 1.13 27.18 +/- 1.95 0.13 +/- 0.04 12.95 +/- 0.72 0.19 i 0.08 1709.40 +/- 143.00 2.70 +/- 0.77 1411.10 i 83.37 1.29 i 0.28 0.06
- 0.01 2.69 +/- 0.44 0.06 i 0.01 2.05 i 0.31 5.86
- 0.06 5.25 i 0.48 0.16
- 0.03 13.79 +/- 2.69 33.01 +/- 2.17 18.59
- 0.74 0.03 i 0.01 0.06 i 0.01 0.07 +/-0.01 1.19 i0.26 1389.35 i 83.05 0.88 i 0.23 0.19 i 0.03 16.14 i0.53 7.39 i 0.38 1178.20 i77A4 0.88 +/- 0.24 5.25 +/- 0.13 4.92 +/- 0.38 1935.85 +/- 94.06 1.31 +/- 0.27 0.05 +/- 0.02 14.18 +/- 0.48 14.63 +/- 0.53 0.16 +/- 0.03 17.68 +/- 0.63 0.10 +/- 0.03 22.48 +/- 1.38 14.27 i0.59 2.63 i 0.37 0.53 i 0.21 8.82 i 0.70 27.01 +/- 1.38 0.14 +/- 0.03 12.96 +/- 0.49 0.20
- 0.05 1702.45 +/- 96.56 A5-4
TABLEA-5. In-House"Duplicate Samples Concentration (pCVL)a Averaged Lab Code Date Analysis First Result Second Result Result MI-6818,6819 WL-6987, 6988 SO-7156, 7157 SO-7156, 7157 SO-7156,7157 SO-7156, 7157 S-7281, 7282 SWU-7198, 7199 DW-7221, 7222 SW-7133, 7134 SW-7133,7134 W-7519, 7520 SW-7805,7806 VE-7399, 7400 VE-7399, 7400 SW-7540, 7541 SW-7540,7541 LW-7736, 7737 AP-7868,7869 AP-7952,7953 AP-7994, 7995 11/11/2003 11117/2003 11/21/2003 11/21/2003 11/21/2003 11/21/2003 11/24/2003 11/25/2003 11/25/2003 12/1/2003 12/1/2003 12/1/2003 12/1/2003 12/9/2003 12/9/2003 12/9/2003 12/9/2003 12/26/2003 12/30/2003 12/30/2003 12/31/2003 Sr-90 Fe-55 Cs-1 37 Gr. Alpha Gr. Beta K-40 Cs-1 37 Gr. Beta Gr. Beta Gr. Beta K-40 Fe-55 Sr-90 Gr. Beta K-40 Gr. Alpha Gr. Beta Gr. Beta Be-7 Be-7 Be-7 2.01
- 0.41 603.49 +/- 53.32 0.74 +/- 0.08 14.90 i 4.24 22.97 +/- 3.12 12.51 *E 1.06 0.82
- 0.15 2.60 +/- 0.53 12.32 +/- 1.40 2.10
- 0.23 1.50 +/- 0.15 3.03 +/- 0.65 0.59 +/- 0.32 4.99 +/- 0.15 5.04 +/- 0.46 2.64 +/- 1.36 6.62 +/-1.22 2.62 +/- 0.54 0.05 +/- 0.01 0.04 +/- 0.01 0.05 +/- 0.02 1.59
- 0.39 619.65 +/-53.97 0.77
- 0.07 19.25 *4.45 25.51 +/- 2.98 12.94
- 1.07 1.16 +/- 0.20 2.54 +/- 0.55 12.38 +/- 1.43 2.46 +/- 0.23 1.40 +/- 0.14 3.12 +/- 0.64 0.56
- 0.33 5.24 +/- 0.15 5.34 +/- 0.74 2.10 +/- 1.19 5.89
- 1.35 2.83 +/- 0.56 0.04
- 0.01 0.04
- 0.01 0.05
- 0.01 1.80 +/- 0.28 611.57 + 37.93 0.76 +/- 0.06 17.07 +/- 3.07 24.24 +/- 2.16 12.73 +/- 0.75 0.99 +/- 0.12 2.57 +/- 0.38 12.35 +/- 1.00 2.28 +/- 0.16 1.45 +/- 0.10 3.08 +/- 0.46 0.58 +/- 0.23 5.11 +/-0.11 5.19.+/- 0.43 2.37 +/-0.91 6.25 +/- 0.91 2.73 +/- 0.39 0.04 +/- 0.01 0.04 +/- 0.01 0.05 +/- 0.01 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 pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCifg).
b 200 minute count time or longer, resulting In lower error.
A5-5
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)f.
Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limits' STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STW-972 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 STSO-987 water water water water water water water water water water water water water water water soil soil soil soil soil soil soil soil soil soil soil soil soil 12101/02 12101102 12/01/02 12/01/02 12/01/02 12/01/02 12/01102 12/01/02 12/01/02 12/01/02 12/01/02 12/01/02 12101/02 12/01/02 12/01102 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 01/01/03 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-23314 U-238 Zn-65 0.56 + 0.06 57.10 i 1.90 38.30 i 0.60 395.30 i 10.10 316.40 +/-5.30 94.90 +/- 24.50 33.40 +/- 0.10 123.80 +/- 5.50 0.66 +/- 0.06 0.061 +/- 0.001 13.80 +/- 1.00 128.10 +/- 3.80 1.60 +/- 0.09 1.64 +/- 0.09 540.40 +/- 9.90 534.36 +/- 2.61 442.16 +/- 2.31 211.00 +/- 2.30 849.50 +/- 3.30 716.50 +/- 12.80 148.76 +/- 2.84 597.10 +/- 23.50 67.05 +/- 3.10 52.80 +/- 3.60 609.50 +/- 9.80 99.50 +/- 7.60 508.60 +/- 42.20 492.70 +/- 28.10 0.58 +/- 0.09 57.00 +/- 5.70 38.20 +/- 3.82 421.00 +/- 42.10 329.00 +/- 32.90 96.00
- 9.60 32.90
- 3.29 136.50 +/- 13.70 0.83 +/- 0.08 0.000 +/- 0.000 12.31 +/- 1.23 132.00
- 13.20 1.54
- 0.15 1.60 +/- 0.16 516.00 +/- 51.60 530.00
- 53.00 420.00 +/- 42.00 238.00
- 23.80 832.00 +/- 83.20 652.00
- 65.20 137.00 +/- 13.70 770.00 +/- 77.00 66.90 +/- 6.70 52.70 +/- 5.30 714.00 +/- 71.40 89.00 +/- 8.90 421.00 +/-42.10 490.00 +/-49.00 0.40 - 0.75 39.90 - 74.10 26.74 - 49.66 294.70 - 547.30 230.30 - 427.70 67.20 - 124.80 23.03 -42.77 95.55 - 177.45 0.58 - 1.08 0.000 - 0.005 8.62 - 16.00 92.40 - 171.60 1.08 - 2.00 1.12 - 2.08 361.20 - 670.80 371.00 - 689.00 294.00 - 546.00 166.60 - 309.40 582.40 - 1081.60 456.40 - 847.60 95.90 - 178.10 539.00 - 1001.00 46.83 - 86.97 36.90 - 68.50 499.80 - 928.20 62.30 - 115.70 294.70 - 547.30 343.00 - 637.00
' Results 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.
' MAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.
A6-1
TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)
Concentration" EML Control Lab Code Type Date Analysis Laboratory results Result0 Limits' STW-977 water 03101103 Gr. Alpha 304.30 *h 53.10 377.50 0.58 - 1.29 STW-977 water 03/01103 Gr. Beta 615.80 +/- 14.70 627.50 0.61 - 1.43 STW-978 water 03/01103 Am-24i 2.00 +/- 0.10 2.13 0.79 - 1A1 STW-978 water 03/01103 Co-60 221.30 +/- 1.20 234.00 0.80 - 1.20 STW-978 water 03101iO3 Cs-134 23.30 +/- 1.10 30.50 0.80 - 1.30 STW-978 water 03/01/03 Cs-137 61.40 *k 0.60 63.80 0.80 - 1.22 STW-978 e water 03101/03 H-3 341.90 i 22.70 390.00 0.78 - 2.45 STW-978 water 03/01/03 Pu-238 3.70 +/- 0.20 3.33 0.74 - 1.20 STW-978 water 03/01/03 Pu-239/40 4A.0 +/- 0.10 3.92 0.79 - 1.20 STW-978 water 03/01/03 Sr-90 4.60 +/- 0.30 4.34 0.69 - 1.34 STW-978 water 03/01103 Uranium 5.10 +/- 0.60 4.29 0.75 - 1.33 STSO-979 soil 03/01/03 Ac-228 55.60 +/-2.50 57.60 0.80 - 1.38 STSO-979 soil 03/01/03 Am-241 12.42 +/- 0.90 15.60 0.65 - 2.28 STSO-979 soil 03/01/03 BI-212 57.70 +/-3.20 60.60 0.50 - 1.34 STSO-979 soil 03/01/03 Bi-214 60.40 +/- 3.20 67.00 0.78 - 1.42 STSO-979 soil 03/01/03 Cs-137 1416.80 +/- 70.00 1450.00 0.80 - 1.25 STSO-979 soil 03101/03 K-40 653.80 +/- 11.90 636.00 0.80 - 1.32 STSO-979 soil 03/01/03 Pb-212 51.10 +/- 5.20 57.90 0.78 - 1.32 STSO-979 soil 03/01/03 Pb-214 64.70 +/- 5.10 71.10 0.76 - 1.46 STSO-979 soil 03/01/03 Pu-239/40 24.40 +/- 0.30 23.40 0.71 - 1.30 STSO-979 soil 03/01/03 Sr-90 54.50 +/- 2.60 64.40 0.67 - 2.90 STSO-979 soil 03/01103 Uranium 245.00 +/- 1.50 249.00 0.71 - 1.32 STVE-980 Vegetation 03/01/03 Am-241 3.10 +/- 0.20 3.51 0.73 -2.02 STVE-980 Vegetation 03/01/03 Cm-244 1.40 +/- 0.50 2.01 0.61 - 1.59 STVE-980 Vegetation 03/01/03 Co-60 12.60 +/- 0.40 12.10 0.80 - 1.44 STVE-980 Vegetation 03/01/03 Cs-137 449.70 +/- 6.20 444.00 0.80 - 1.31 STVE-980 Vegetation 03/01/03 K-40 1159.00 +/-38.60 1120.00 0.79 -1.39 STVE-980 Vegetation 03/01103 Pu-239140 4.80 +/- 0.40 5.17 0.69 - 1.31 STVE-980 Vegetation 03/01/03 Sr-90 659.70 +/- 50.40 650.00 0.55 -1.21 STAP-981 Air Filter 03/01/03 Arn-241 0.27 +/- 0.10 0.34 0.70 -2.34 STAP-981 Air Filter 03/01/03 Co-60 30.20 +/- 0.30 33.50 0.80 - 1.26 STAP-981 Air Filter 03/01/03 Cs-137 90.30
- 1.30 99.70 0.80 - 1.32 STAP-981 Air Filter 03/01/03 Mn-54 41.80 +/- 0.60 43.80 0.80 - 1.35 STAP-981 Air Filter 03101/03 Pu-238 0.52 +/- 0.10 0.52 0.67 - 1.33 STAP-981 Air Filter 03/01/03 Pu-239/40 0.35 +/- 0.10 0.33 0.73 - 1.26 STAP-981 Air Filter 03/01/03 Sr-90 2.50 +/- 0.10 2.80 0.53 - 1.84 STAP-981 Air Filter 03/01103 Uranium 0.51 +/- 0.10 0.50 0.79 -2.10 STAP-982 Air Filter 03/01103 Gr. Alpha 0.90 i 0.10 1.17 0.73 - 1.43 STAP-982 Air Filter 03/01/03 Gr. Beta 1.50 +/- 0.10 1.50 0.76 - 1.36 A7-1
TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)'
Concentration' EML Control Lab Code Type Date Analysis Laboratory results Result limits0 STW-992 water 09102103 Am-241 9.78
- 0.32 8.76 0.79 - 1.41 The September, 2003 results are preliminary. Control limits used were taken from the March, 2003 data.
Control limits may vary slightly when the final study is published.
STW-992 water 09/02/03 Co-60 468.30
- 4.10 513.00 0.80 - 1.20 STW-992 water 09/02103 Cs-134 53.90 i 0.80 63.00 0.80 - 1.30 STW-992 water 09/02/03 Cs-137 76.10
- 1.40 80.30 0.80 - 1.22 STW-992 water 09/02/03 H-3 355.20
- 12.80 446.30 0.78 - 2A5 STW-992 water 09102/03 Pu-238 1.71
- 0.07 2.07 0.74 -1.20 STW-992 water 09/02103 Pu-239140 4.24 +/- 0.01 4.99 0.79 - 1.20 STW-992 water 09/02/03 Sr-90 6.70
- 0.50 7.04 0.69 - 1.34 STW-992 water 09/02103 Uranium 6.03 + 0.14 5.69 0.75 - 1.33 STW-993 water 09/02/03 Gr. Alpha 688.00 i 7.60 622.00 0.58 - 1.29 STW-993 water 09/02103 Gr. Beta 1985.00
- 111.00 1948.00 0.61 - 1.43 STSO-994 soil 09/02/03 Am-241 19.70
- 1.50 18A0 0.65 - 2.28 STSO-994 soil 09/02103 Cs-137 1928.00 *E 19.00 1973.00 0.80 -1.25 STSO-994 soil 09102/03 K-40 533.00
- 79.00 488.00 0.80 - 1.32 STSO-994 soil 09102/03 Pu-238 15.30
- 0.80 14.60 0.59 - 2.88 STSO-994 soil 09/02103 Pu-239140 32.50 i 2.30 30.40 0.71 - 1.30 STSO-994 soil 09102103 Sr-90 69.80 i 2.30 80.30 0.67 - 2.90 STSO-994 soil 09/02103 Uranium 228.30 +/- 17.10 259.30 0.71 - 1.32 STAP-995 Air Filter 09/02103 Am-241 0.64
- 0.05 0.44 0.70 - 2.34 STAP-995 Air Filter 09/02/03 Co-60 48.50
- 0.40 55.10 0.80 - 1.26 STAP-995 Air Filter 09/02/03 Cs-137 51.20 +/- 1.10 54.80 0.80 - 1.32 STAP-995 Air Filter 09/02103 Mn-54
- 53.70
- 1.10 58.00 0.80 -1.35 STAP-995 Air Filter 09/02/03 Pu-238 0.24 i 0.05 0.23 0.67 - 1.33 STAP-995 Air Filter 09102/03 Pu-239140 0.41 +/-0.10 0.40 0.73 - 1.26 STAP-995 Air Filter 09/02/03 Sr-90 1.90 I 0.10 2.06 0.53 -1.84 STAP-995 Air Filter 09102103 Uranium 0.80 : 0.06 0.82 0.79 -2.10 STAP-996 Air Filter 09/02/03 Gr. Aipha 3.23
- 0.07 3.11 0.73 - 1.43 STAP-996 Air Filter 09102/03 Gr. Beta 4.168
- 0.03 3.89 0.76 - 1.36 Results are reported In Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetation (Bq/kg).
b The EML result listed Is the mean of replicate determinations for each nuclide
- the standard error of the mean.
c Control limits are reported by EML as the ratio of Reported Value / EML value.
d A low bias for Cs-134 activity has been observed In the past. No errors have been found In the library or efficiency.
Additional spike analyses will be performed and a correction factored Into the calculation.
- Reporting error.
A7-2
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; xi +/- st and X2 +/- s2 Reoorted result:
x +/- s; where x = (1/2) (xi + x2) and s = (1/2) 1 +52 3.2.
Individual results:
<LI, <2 Reported result: <L, where L = lower of Li and L2 3.3.
Individual results:
x + s, AL Reported result:
x i s if x aL; <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 xi, x2.
xn are defined as follows:
x =
EX
- S=,
x x~\\
Lx.
n-i 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values In the averaging group are less than the highest LLD, the highest LLD Is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error Is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the 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 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 permissibte concentrations of radioactivity in air and water above natural background In unrestricted areasa.
Air (pCVm 3)
Water (pCiL)
Gross alpha Gross beta Iodine-I 31b I xIO0-3 1
2.8 x 10-1 Strontium-89 Strontium-90 Cesium-137 Barium-140 Iodine-131 Potassium-40c 8,000 500 1,000 8,000 1,000 4,000 2
10 I x106 Gross alpha Gross beta Tritium 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.
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
TLD LOCATIONS ONE MILE RADIUS JI PLANT AREA ENLARGED PLAN
[1.00 MILE RADIUS)
ENO SCALE]
MONITORING LEGEND:
Q N.S.P. TLO POINTS D-2 TL.O01.DGN D-2 TL001.DGN
TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGEND:
Q N.S.P. TLD POINTS D-3 TL002.OGN
TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
(i) N.S.P. TLD POINTS D4 TLOO3.DGN D-4 TL003.OGN
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS I
' I PLANT AREA ENLARGED PLAN (1.00 MILE RADIUS]
[NO SCALE]
MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS P-14. P-18. P-25, P-37. P-39 A
AIR SAMPLING POINT 10 NUMBERS P-l. P-2, P-3, P-4. P-6 waTER SAMPLING POINT IO NUMBERS
.P-5, P-. P-8. P-i. P-ll, P-25 E
VEGETATION / VEGETABLES ID NUMBERS El P-24, P-38 0
FISH SAMPLING POINT ID NUMBERS P-13. P-l1 INVERTEBRATES POINT IO NUMBERS P-E. P-40 SEDIMENT SAMPLING POINT IO NUMBERS P-6. P-12. P-20 D-5 SAMP01.OGN D-5 SAMP01.OGN
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGENO A
MILX SAMPLMG POINT I0 JOMERS v
P-34. P-1S. P-25. P-37. P-3
^
AIR SAMPLING POINT 10 SBEAS A
P P2.
P.3.
P-4.P-6 WATER SAHPLING POINT 10 MJMBERS 0
P.
P-C. 10-11.
- % t; teP-25 f
VECETATION / VEGETABLES 10 ERS FISH SAMPLNG POINT I0 "BERS P-Pl-li INVERTESRATES POINT 10 N"ERS P-.SP.48 SECIMENT SAMPLING POINT 10 SIEURS P-4 P-12. P-21 D-6 SAMP03.DGN
I ENVIRONMENTAL SAMPLING POINTS
)Huppert Far., W10430 St Rd 29, River Falls, WI Cain Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN Monitoring Legend A
Milk Sampling Point ID Numbers P-14, P-18, P-37, P-39, P-41
^
Air Sampling Point ID Numbers P-1, P-2, P-3, P-4, P-6 Q Water Sampling Point ID Numbers P-5, P-6, P-8, P-9, P-11, P.41 Ef Vegetation I Vegetables Point ID Numbers P-24, P.38 D-7 SAMP02.DGN' D-7 SAMP02.DGN