L-PI-07-035, 2006 Annual Radiological Environmental Monitoring Program (REMP) Report
| ML071350517 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/07/2007 |
| From: | Thomas J. Palmisano Nuclear Management Co |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| FOIA/PA-2010-0209, L-PI-07-035 | |
| Download: ML071350517 (73) | |
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CORRESPONDENCE, CONTROL PROGRAM STANDARD DIISTRIBUTION Outgoing Correspondence Letter Number: L---/-07 -0 - Document Date: " /
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Nu C Prairie Island Nuclear Generating Plant Committed to NuclearExcellene Operated by Nuclear Management Company, LLC MAY 0',7 200?
L-PI-07-035 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 2006 Annual Radiological Environmental Monitorinq Program (REMP) Report Pursuant to Prairie Island Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and PINGP Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License SNM-2506, the Nuclear Management Company, LLC (NMC) submits one copy of the Annual Radiological Environmental Monitoring Program report for the period January 1, 2006 through December 31, 2006.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Thomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Dr. John House, USNRC, Region III Director of NMSS, USNRC Tim Donakowski, State of Minnesota P1 Dakota Community Environmental Coordinator 1717 Wakonade Drive East 9 Welch, Minnesota 55089-9642 Telephone: 651.388.1121 .I 5Dt
ENCLOSUREI Annual Report to the United States Nuclear Regulatory Commission Radiation Environmental Monitoring Program January 1, 2006 through December 31, 2006 70 pages to follow
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT To the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 2006 Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ISFSI Docket No.72-10 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.
MIDWEST LABORATORY Project No. 8010 Approved:
Bro aGrb M.aS Labo to Manager
PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by Nuclear Management Company, LLC for XCEL Energy Corporation.
The report was prepared by Environmental, Inc., Midwest Laboratory.
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TABLE OF CONTENTS Section PaQe P re fa c e ............................................................................................................................................. ii List of T a b le s ................................................................................................................................... iv List of F ig u re s ................................................................................................................................... v 1.0 INTRO DUCTIO N .............................................................................................................................. 1 2.0 SUM MARY ....................................................................................................................................... 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 M odifications ........................................................................................................ 6 3.6 Land Use Census ........................................................................................................... 6 4.0 RESULTS AND DISCUSSION .......................................................................................... . ... 7 4.1 Atm ospheric Nuclear Detonations and Nuclear Accidents ............................................... 7 4.2 Sum m ary of Preoperational Data ..................................................................................... 7 4.3 Program Findings .......................................................................................................... 8 5.0 FIGURES AND TABLES .............................................................................. ......................... 12
6.0 REFERENCES
CITED ................................................................................................................... 25 APPENDICES A Interlaboratory Com parison Program Results .......................................................................... A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Sam ples ......................................................... 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 Sam pling Location Maps .............................................................................................................. D-1 E Special W ell and Surface W ater Sam ples .............................................................................. E-1 iii
LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program ..................................................................................... 15 5 .2 S a m pling Lo ca tio n s ............................................................................................................................. 16 5.3 Missed Collections and Analyses ............................................. 19 5.4 Radiation Environmental Monitoring Program Summary ............................................................. 20 In addition, the following tables can be found in the Appendices:
Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results ...................................... Al-1 A-2 Program Results; (TLDs) ............................................................................................................... A2-1 A-3 In-house "Spiked" Samples ........................................................................................................... A3-1 A-4 In-house "Blank" Samples ................................................ A4-1 A-5 In-house "Duplicate" Samples ................................................................................................... A5-1 A-6 Department of Energy MAPEP comparison results ...................................................................... A6-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ........................................................................... C-2 Appendix E E-4.1 Sample collection and analysis program ........................................................................................ E-6 E -4 .2 S a m p lin g lo ca tio n s .......................................................................................................................... E -7 E-4.3 REMP Summary ............................................................................................................................. E-8 E-4.4 REMP Complete Data Table ........................................................................................................... E-9 iv
LIST OF FIGURES No. Title PaQe 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator lo ca tio n s ve rs u s co ntro l ...................................................................................................................... 13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i) .......................................................................... 14 In addition, the following figure can be found in the Appendices:
E-1 Onsite Tritium Sampling Well locations ............................................................................................ E-8 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, 2006. 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, 2007b) available at Prairie Island Nuclear Generating Plant.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.
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2.0
SUMMARY
The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
Results for 2006 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
Sources of environmental radiation include the following:
(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-1 31. Most samples are 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-1 37 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.
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3.1 Program Design 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, 2006). 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, P-4, 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.
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 six farms (five indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.
For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes.
River water is collected weekly at two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
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3.2 Proaram Descriotion (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) Air Particulates / Air Iodine:
No air particulate / air iodine samples were available from location P-2 for the week ending 12-04-06. The sampler failed after 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> run-time.
A partial sample was collected from location P-3 for the week ending 12-04-06. A torn filter allowed flow to bypass the filter.
(2) Milk:
No milk was available from location P-44 for the months of January, February, March, and April, 2006.
(3) Thermoluminescent Dosimeters:
The TLD for location P-06S was missing for the second quarter, 2006. The TLD was lost in the field.
Deviations from the program are summarized in Table 5.3.
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3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
Levels of iodine-131 in cabbage and natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
Tritium concentrations are determined by liquid scintillation.
Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.
Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.
3.5 Program Modifications There were no modifications to the REMP in 2006.
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 of2 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 Land Use Census was completed in August through October, 2006. There were no changes to any of the highest D/Q locations for nearest residence, milk animal or garden sites. A goat dairy location was established in 2005 with a higher D/Q than the other dairy farms. A new critical receptor location was identified in 2006, based on the results of the land use census.
However, the REMP will continue to designate the former critical receptor location as the critical receptor location for 2007. This designation will result in a conservative dose calculation for the critical receptor since the new location is in a lower annual averaged radionuclide concentration.
No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant.
Therefore, no corn samples were collected for analysis.
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4.0 RESULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3.
The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2006. 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 2006.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in 2 2 fallout declined yearly from a level of 12,167 pCi/m to 1,020 pCi/m , and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/mr 3
Average present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored.
In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-1 37 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-1 37. Gross beta measured in soil averaged 52 pCi/g.
The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish , aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well water, and 11.0 pCi/L 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 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout.
Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g , 46.0 pCi/g, and 13.6 pCi/g, respectively.
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4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at one control location. The means ranged from 16.1 mR/91 days at inner ring locations to 16.9 mR/91 days at outer ring locations.
The mean at special interest locations was 15.8 mRI91 days and 16.6 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1991 through 2005. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).
Average (Inner and Average (Inner and Year Outer Rinqs) Control Year Outer Rings) Control 1991 14.9 14.5 1999 16.6 17.5 1992 16.3 14.8 2000 17.0 17.1 1993 15.9 15.4 2001 16.8 17.2 1994 15.2 16.0 2002 17.4 16.9 1995 15.6 16.6 2003 16.2 16.0 1996 14.8 16.4 2004 17.6 17.6 1997 15.1 16.0 2005 16.8 16.3 1998 16.7 17.3 2006 16.6 16.6 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR-91 days).
ISFSI Facility Operations Monitorinq 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 90.2 mR/91 days inside the ISFSI earth berm and 21.1 mR/91 days outside the ISFSI earth berm. Two additional casks were placed on the ISFSI pad in 2006, a total of twenty-two 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.
Ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.4 and 15.1 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).
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Airborne Particulates Average annual gross beta concentrations in airborne particulates were nearly identical at the 3 3 indicators versus control locations (0.026 pCi/m and 0.025 pCi/m , respectively) and similar to levels observed from 1991 through 2005. The results are tabulated below.
Average of Year Indicators Control 3
Concentration (pCi/m 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 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 Average annual gross beta concentrations in airborne particulates.
For many years, a spring peak in beta activity had been observed (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 1991 through 2006.
Two pieces of evidence indicate conclusively that seasonal elevated activities observed are 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., 2007).
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 3(Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.070 pCi/m for all locations. All other gamma-emitting isotopes were below their respective LLD limits.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m 3 in all samples. There was no indication of a plant effect.
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Milk Iodine-1 31 results were below the detection limit of 0.5 pCi/L in all samples. Cs-1 37 results were below the LLD level of 5 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
In summary, the milk data for 2006 is consistent with previous results and show no radiological effects of the plant operation.
Drinkinq Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 500 pCi/L in all samples.
Gross beta concentrations averaged 13.4 pCi/L throughout the year, ranging from 8.2-16.0 pCi/L. These concentrations were slightly higher than levels observed, from 1991 through 2005.
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 2006 data of any effect of plant operation.
Year Gross Beta (pCi/L) 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 2004 9.8 2005 11.5 2006 13.4 Average annual concentrations; Gross beta in drinking water.
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River Water For 2006, no measurable tritium activity was detected in river water composites, above the concentration level of 500 pCi/L.
Gamma-emitting isotopes were below detection limits in all samples.
Well Water At control well, P-43 (Peterson Farm) and the four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, SuterFarm ) no tritium was detected above a concentration level of 500 pCi/L.
Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2006 show no radiological effects of the plant operation.
Crops Three samples of broadleaf vegetation, cabbage leaves, were collected in July and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.020 pCi/g wet weight in all samples. With the exception of naturally-occurring potassium-40, all other gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.
Field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required.
Fish Fish were collected in May and October, 2006 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.
Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2006. With the exception of naturally occurring potassium-40, all gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.
Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area.shoreline sediments were sampled in May and October, 2006 and analyzed for gamma-emitting isotopes. With the exception of naturally occurring potassium-40, all gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.
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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 ~I~_ i _
18K__ ---- . .-
16 ~ -- ----- *- --- __ ._ _-
15__
E a o) 0 0 0 0 0 C D C (0 ID D C0 CD CD o 0 0 0 C0 0 0 N) W n ) -.1 CO w o O M w .: 0 0)
-.-- Control_(P-O1C)1 20 19 18 17 16 w15
- 14 r 13 E
12 11 10 DCD 0 0 0 0 0 0 0 CD CD (D CD (D CD CD CD 0 0 0 0 0 0 0 N~ w0 CO
-N UI a) -4 CO CD 0 - ~ w0 41 (7" (3) 13
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
Indicators (P-2,3,4,6) 0.035 0.033 0.031 0.029 0.027 0.025 E 0.023
" 0.021 0.019 0.017 0.015
,D CO ,.o CD C C ,D CO 01 0 0 0 0 0 0 CD (D (0 (0 .C (.D CD C D 0 0 0 0 0 0 N w, 4ý 01 0) ',1 0O (D 0 - NJ w) 4 01 0) s-Control (P-l)]
0.035 0.033 0.031 0.029 0.027 0.025 CI)
E 0.023 a 0.021 0.019 0.017 0.015 D CD C CD -.-
CD ~-. -CD~ -.CD -.
CD NJ 0 N 00 C)N N) 0 Ili 0
N) 0 N
0 CD
- w. CD, ( CD CD CD CD CD 0 0 0 0 0)
- NJ w~ .D. L 0) -IJ CO CD 0 NJ w~ (n 0) 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)a Frequencyb Frequency' Ambient radiation (TLD's) 54 P-1A - P-10A C/Q Ambient gamma P-0113 - P-:15B P-O1S - P-08S P-OIIA - P-081A P-O1I13 - P-08113 P-0IIX- P-041X, P-OIC Airborne Particulates 5 P-A(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6 each location)
Airborne Iodine 5 P4I(C), P-2, P-3, P-4, P-6 C/W 1-131 Milk 5 P-14, P-18, P-37, P-42, P-44, G/Md 1-131, GS P-43 (C)
River water 2 P-5(C), P-6 G/W GS(MC), H-3(QC)
Drinking water 1 P-il G/W GB(MC), 1-131(MC)
Well water 5 P-6, P-8, P-9, P-24, G/Q H-3, GS P-43 (C)
Edible cultivated crops - 2 P-38(C), P-24 G/A GS (1-131) leafy green vegetables Fish (one species, edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or invertebrates 2 P-40(C), P-6 G/SA GS Bottom sediment 2 P-20(C), P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.
b Collection type Is coded as follows: C/= continuous, G/ = grab. Collection frequency is coded as follows:
W= weekly, M - monthly, Q = quarterly, SA = semiannually, A = annually.
c Analysis type Is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 = iodine-131.
Analysis frequency Is coded as follows: MC = monthly composite, QC = quarterly composite.
d Milk Is collected biweekly during the grazing season (May - October).
15
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction from Code Typea Collection Site Sample Typeb Reactor P-1 C Air Station P-I AP, Al 11.8 mi @ 3160/NNW P-2 Air Station P-2 AP, Al 0.5 mi @ 2940 /WNW P-3 Air Station P-3 AP, Al 0.8 mi @ 3130 /NW P-4 Air Station P-4 AP, Al 0.4 mi @ 3590 /N P-5 C Upstream of Plant RW 1.8 mi @ 110/N P-6 Lock and Dam #3 & Air AP, Al, RW Station P-6 WW, BS, BOC 1.6 mi @ 1290 /SE P-8 Community Center WW 1.0 mi @ 3210 /WNW P-9 Plant Well #2 WW 0.3 mi @ 3060 /NW P-11 Red Wing Service Center DW 3.3 mi @ 1580 /SSE P-12 Downstream of Plant SS 3.0 mi @ 1160 /ESE P-13 Downstream of Plant Fc 3.5 mi @ 1130 /ESE P-14 Gustafson Farm M 2.3 mi @ 1730/S P-18 Christiansen Farm M 3.8 mi @ 88°/E P-19 C Upstream of Plant F¢ 1.3 mi @ O°/N P-20 C Upstream of Plant BS 0.9 mi @ 45 0/NE P-24 Suter Residence VE, WW 0.6 mi @ 1580 /SSE P-37 Welsch Farm M 4.1 mi @ 87 0/E P-38 C Cain Residence VE 14.2 mi @ 3590 /N P-40 C Upstream of Plant BOO 0.4 mi @ 00/N P-42 Rother Farm M 4.3 mi. @ 2640 /W P-43 C Peterson Farm M, WW 13.9 mi. @ 3550 /N P-44 Yoemans Farm M 2.0 mi. @ 2140 /SW General Area of the Site Boundary P-OIA Property Line TLD 0.4 mi @ 3590/N P-02A Property Line TLD 0.3 mi @ 10 0/N P-03A Property Line TLD 0.5 mi @ 1830/S P-04A Property Line TLD 0.4 mi @ 2040/SWW P-05A Property Line TLD 0.4 mi @ 225 0/SW P-06A Property Line TLD 0.4 mi @ 249 0/WSW P-07A Property Line TLD 0.4 mi @ 268 0/W P-08A Property Line TLD 0.4 mi @ 2910/WNW P-09A Property Line TLD 0.7 mi @ 3170/NW P-IOA Property Line TLD 0.5 mi @ 3330/NNW 16
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Distance and Direction from Code Type 8 Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant P-OIB Thomas Killian Residence TLD 4.7 mi @ 3550/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 17 0/NNE 0
P-03B Wayne Anderson Farm TLD 4.9 mi @ 46 /NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 610 /ENE P-05B County Road E and Coulee TLD 4.2 mi @ 102 0/ESE P-06B William Hauschiblt Residence TLD 4.4 mi @ 112 0/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140 0/SE P-08B David Wnuk Residence TLD 4.1 mi @ 165 0/SSE P-09B Highway 19 South TLD 4.2 mi @ 187°/S P-lOB Cannondale Farm TLD 4.9 mi @ 200 0/SSW P-11B Wallace Weberg Farm TLD 4.5 mi @ 221 0/SW 0
P-12B Ray Gergen Farm TLD 4.6 mi @ 251 /WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270 0/W P-14B David J. Anderson Farm TLD 4.9 mi @ 306 0/NW P-15B Hoist Farms TLD 3.8 mi @ 345 0/NNW Special Interest Locations P-0 1S Federal Lock & Dam #3 TLD 1.6 mi @ 129 0/SE P-02S Charles Suter Residence TLD 0.5 mi @ 1550/SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 1730/S P-04S Richard Burt Residence TLD 2.0 mi @ 2020/SSW P-05S Kinney Store TLD 2.0 mi @ 270 0/W P-06S Earl Flynn Farm TLD 2.5 mi @ 299 0/WNW P-07S Indian Community TLD. 0.7 ml @ 271 0/W P-08S Indian Community TLD 0.7 mi @ 287 0/NWW 0
P-O1C C Robert Kinneman Farm TLD 11.1 mi @ 331 /NNW 17
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Approximate Type of Distance and Direction Code Type" Collection Site Sampleb from ISFSI Center.
ISFSI Area Inside Earth Berm P-OIIA ISFSI Nuisance Fence TLD 190' @ 450/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 0/SE P-051A ISFSI Nuisance Fence TLD 180'@ 2190/SW P-061A ISFSI Nuisance Fence TLD 320' @ 2580/WSW P-071A ISFSI Nuisance Fence TLD 320'@ 2810 /WNW P-081A ISFSI Nuisance Fence TLD 190' @ 3180/NW P-O1Ix ISFSI Nuisance Fence TLD 140'@ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 270 0/W P-031X ISFSI Nuisance Fence TLD 140' @ O/N P-041X ISFSI Nuisance Fence TLD 360'@ 90 0/E ISFSI Area Outside Earth Berm PmOIUB ISFSI Berm Area TLD 340'@ 30/N P-021B ISFSI Berm Area TLD 380' @ 280 /NNE P-031B ISFSI Berm Area TLD 560' @ 85 0/E P-041B ISFSI Berm Area TLD 590'@ 165 0/SSE P-051B ISFSI Berm Area TLD 690' @ 1860/S P-061B ISFSI Berm Area TLD 720' @ 201 0/SSW P-071B ISFSI Berm Area TLD 610' @ 271 0/W P-081B ISFSI Berm Area TLD 360' @ 3320/NNW a "C" denotes control location. All other locations are indicators.
b Sample Codes:
AP Airborne particulates F Fish Al Airborne Iodine M Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates) VE Vegetation/vegetables DW Drinking water WW Well water c 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-44 Jan, - Apr. 2006 Goats were dry. None, The goat milk is available during 1-131 the grazing season.
TLD Ambient P-06S 2nd. Qtr. TLD lost in field. None required.
Gamma 2006 AP/AI Beta, P-02 12/4/2006 Only 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> None required.
1-131 run-time logged.
AP/AI Beta, P-03 12/4/2006 Partial sample Discontinued use of this type of filter.
1-131 collected due to due to torn filter.
19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2006
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse TLD (Inner Ring, Gamma 40 3.0 16.1 (40/40) P-06A 17.3 (4/4) (See Control 0 Area at Site (13-18.4) 0.4 mi @ 2490/WSW (16.3-18.4) below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma 60 3.0 16.9 (60/60) P-02B, Roy Kinneman, 19 (4/4) (See Control 0 4-5 mi. distant) (13.8-20.6) 4.8 mi @ 17' /NNE (17.8-20.6) below.)
mR/91 days)
TLD (Special Gamma 31 3.0 15.8 (31/31) P-03S, Gustafson Farm, 18.0 (4/4) (See Control 0 Interest Areas) (13.3-19.6) 2.2 mi @ 173°/S (16.7-19.6) below.)
mR/91 days)
TLD (Control) Gamma 4 3.0 None P-01C, R. Kinneman, 16.6 (4/4) 16.6 (4/4) 0 mR/91 days) 11.1 mi @ 331' /NNW (15.2-17.6) (15.2-17.6)
Airborne GB 260 0.005 0.026 (207/208) P-04, Air Station 0.026 (52 /52) 0.025 (52/52) 0 Particulates (0.008-0.055) 0.4 mi @ 3590/N (0.008-0.052) (0.008-0.058)
(pCi/m 3)
GS 20 Be-7 0.015 0.071 (16/16) P-06, Air Station 0.074 (4/4) 0.070 (4/4) 0 (0.047-0.104) 1.6 mi @ 1290 /SE (0.055-0.104) (0.051-0.094)
Mn-54 0.0007 < LLD < LLD 0 Co-58 0.0010 < LLD <.LLD 0 Co-60 0.0007 < LLD < LLD 0 Zn-65 0.0012 < LLD - < LLD 0 Zr-Nb-95 0.0014 < LLD - < LLD 0 Ru-103 0.0010 < LLD - < LLD 0 Ru-106 0.0065 < LLD - < LLD 0 Cs-134 0.0006 < LLD - < LLD 0 Cs-137 0.0007 < LLD - < LLD 0 Ba-La-140 0.0055 < LLD - < LLD 0 Ce-141 0.0021 < LLD - < LLD 0 Ce-144 0.0040 < LLD - < LLD 0 Airborne Iodine 1-131 260 0.03 < LLD - < LLD 0 (pCi/m 3 )
20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2006
( County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Range' Location" Rangec Range' Resultse Milk (pCi/L) 1-131 104 0.5 < LLD < LLD 0 GS 104 K-40 200 1434 (86/86) P-44, Yoemans Farm 1632 (14/14) 1374 (18/18) 0 (339-2008) 2.0 mi @ 214° /SW (339-2008) (1239-1550)
Cs-134 5 < LLD - - < LLD 0 Cs-137 5 < LLD - - < LLD 0 Ba-La-140 5 < LLD - - < LLD 0 River Water H-3 8 500 < LLD - - < LLD 0 (pCi/L)
GS 24 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - -< LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - -< LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 47 < LLD - -< LLD 0 21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2006
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Range' Locationd Rangec Rangec Resultse Drinking Water GB 12 1.0 13.4 (12/12) P-11, Red Wing S.C. 13.4 (12/12) None 0 (pCi/L) (8.2-16.0) 3.3 mi @ 158' /SSE (8.2-16.0)
-131 12 1.0 < LLD None 0 H-3 4 500 < LLD - None 0 GS 12 Mn-54 10 < LLD - None 0 Fe-59 30 < LLD - None 0 Co-58 10 < LLD - None 0 Co-60 10 < LLD - None 0 Zn-65 30 < LLD - None 0 Zr-Nb-95 15 < LLD - None 0 Cs-134 10 < LLD - None 0 Cs-137 10 < LLD - None 0 Ba-La-140 15 < LLD - None 0 Ce-144 53 < LLD - None 0 Well Water H-3 20 500 < LLD - < LLD 0 (pCi/L)
GS 20 Mn-54 10 < LLD - < LLD 0 Fe-59 30 < LLD - < LLD 0 Co-58 10 < LLD - < LLD 0 Co-60 10 < LLD - < LLD 0 Zn-65 30 < LLD - < LLD 0 Zr-Nb-95 15 < LLD <-LLD 0 Cs-134 10 < LLD - < LLD 0 Cs-137 10 < LLD - -< LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 54 < LLD - - < LLD 0 Crops - Cabbage 1-131 3 0.020 < LLD - - < LLD 0 (pCi/gwet) 22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2006 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Fish GS 4 (pCi/g wet) K-40 0.10 3.61 (2/2) P-13, Downstream 3.61 (2/2) 2.87 (2/2) 0 0
(3.39-3.83) 3.5 mi @ 113 /ESE (3.39-3.83) (2.42-3.32)
Mn-54 0.028 < LLD < LLD 0 Fe-59 0.064 < LLD - < LLD 0 Co-58 0.035 < LLD <-LLD 0 Co-60 0.026 < LLD <-LLD 0 Zn-65 0.046 < LLD - - < LLD 0 Zr-Nb-95 0.062 < LLD - - < LLD 0 Cs-134 0.030 < LLD - - < LLD 0 Cs-137 0.027 < LLD - - < LLD 0 Ba-La-140 0.45 < LLD - - < LLD 0 Invertebrates GS 4 (pCi/g wet) Be-7 0.44 < LLD < LLD 0 K-40 1.14 2.42 (2/2) P-06, Downstream of 2.42 (2/2) < LLD 0 (1.62-3.22) Plant, 1.6 mi @ 129 0 /SE (1.62-3.22)
Mn-54 0.046 < LLD < LLD 0 Co-58 0.041 < LLD < LLD 0 Co-60 0.042 < LLD < LLD 0 Zn-65 0.079 < LLD < LLD 0 Zr-Nb-95 0.055 < LLD < LLD 0 Ru-103 0.037 < LLD < LLD 0 Ru-106 0.37 < LLD - < LLD 0 Cs-134 0.047 < LLD <-LLD 0 Cs-137 0.043 < LLD - < LLD 0 Ba-La-140 0.13 < LLD - < LLD 0 Ce-141 0.070 < LLD - < LLD 0 Ce-144 0.24 < LLD - < LLD 0 23
Table 5.4 Radiological Environmental. Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2006
( County, State Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Range' Range' Resultse
-Bottom and GS 6 Shoreline Be-7 0.30 < LLD - - < LLD 0 Sediments (pCi/g dry) K-40 0.10 9.34 (4/4) P-20, Upstream 8.82 (2/2) 8.82 (2/2) 0 (8.18-10.08) 0.9 mi. @ 450 /NE (8.29-9.35) (8.29-9.35)
Mn-54 0.025 < LLD < LLD 0 Co-58 0.026 < LLD <LLD
<- 0 0o-60 0.019 < LLD - -*<LLD: 0 Zn-65 0.069 < LLD - < LLD 0 Zr-Nb-95 0.038 < LLD *< LLD 0 Ru-103 0.038 < LLD < LLD 0 Ru-106 0.19 < LLD < LLD 0 Cs-134 0.032 < LLD - - < LLD 0
.Cs.-i 37 0.027 .. LLD . . LLD 0 Ba-La-140 0.086 < LLD - - < LLD 0 Ce-141 0.069 < LLD < LLD 0 Ce-144 0.15 < 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.
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.
e 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.AI-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 2007a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2006.
2001 b through 2007b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2006.
2003. Quality Assurance Program Manual, Rev. 0, 01 October 2003.
2005. Quality Control Procedures Manual, Rev. 1, 17 September 2005.
2003. Quality Control Program, Rev. 0, 21 August 2003.
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
Hazleton Environmental Sciences Corporation.
1979a to 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
1979b to 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. 1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, No. 12, 730-746.
Northern States Power Company.
1972 through 1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971, 1972, 1973. Minneapolis, Minnesota.
1979 to 2006. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2005.
Minneapolis, Minnesota.
Prairie Island Nuclear Generating Plant, 2006. 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.
25
6.0 REFERENCES
CITED (continued)
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).
2007. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981- 2005.
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
Xcel Energy Corporation. 2006. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2005 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26
- ,Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-23 10 ph. (847) 564-0700 fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated fourtimes a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2006 through December, 2006
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-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 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Attachment A lists acceptance criteria for "spiked" samples.
Out-of-limit results are explained directly below the result.
Al
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter
> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
> 30 pCi/liter or kg 10% of known value Potassium-40 > 0.1 g/liter or kg 5% of known value Gross alpha : 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta < 100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter + la = (pCi/liter) =
0 0 933 169.85 x (known) °
> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium > 0.1 pCi/liter, gram, or sample 10% of known value Iodine-1 31, < 55 pCi/liter 6.0 pCi/liter Iodine-1 2 9 b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6.0 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Techneti um-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter
> 100 pCi/liter 10% of known value Othersb 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 078 01/16/06 Sr-89 49.9 +/- 3.5 50.2 41.5 -58.9 Pass STW-1078 01/16/06 Sr-90 31.5 +/- 1.5 30.7 22.0 - 39.4 Pass STW-1079 01/16/06 Ba-1 33 86.5 +/- 4.1 95.0 78.6 -111.0 Pass STW-1 079 01/16/06 Co-60 96.3 +/- 4.1 95.3 86.6 - 104.0 Pass STW-1079 01/16/06 Cs-1 34 22.6 +/- 3.0 23.1 14.4 -31.8 Pass STW-1 079 01/16/06 Cs-137 109.0 +/- 5.9 111.0 101.0 - 121.0 Pass STW-1 079 01/16/06 Zn-65 198.0 +/- 11.2 192.0 159.0 - 225.0 Pass STW-1 080 01/16/06 Gr. Alpha 10.8 +/- 1.4 9.6 1.0 -18.3 Pass STW-1 080 01/16/06 Gr. Beta 56.9 +/- 1.9 61.9 44.6 - 79.2 Pass STW-1 081 01/16/06 Ra-226 4.3 +/- 0.4 4.6 3.4 - 5.8 Pass STW-1081 01/16/06 Ra-228 7.1 +/- 1.8 6.6 3.7 - 9.5 Pass STW-1 081 01/16/06 Uranium 20.7 +/- 0.5 22.1 16.9 -27.3 Pass STW-1088 04/10/06 Sr-89 29.0 +/- 1.8 32.4 23.7 -41.1 Pass STW-1 088 04/10/06 Sr-90 8.7 +/- 1.0 9.0 0.3 - 17.7 Pass STW-1089 04/10/06 Ba-1 33 10.3 +/- 0.4 10.0 1.3 -18.7 Pass STW-1089 04/10/06 Co-60 114.0 +/- 2.8 113.0 103.0 - 123.0 Pass STW-1 089 04/10/06 Cs-1 34 41.9 +/- 1.4 43.4 34.7 -52.1 Pass STW-1 089 04/10/06 Cs-1 37 208.0 +/- 1.1 214.0 195.0 - 233.0 Pass STW-1089 04/10/06 Zn-65 154.0 +/- 0.8 152.0 126.0- 178.0 Pass STW-1 090 04/10/06 Gr. Alpha 13.4 +/- 1.1 21.3 12.1 -30.5 Pass STW-1 090 04/10/06 Gr. Beta 27.7 +/- 2.1 23.0 14.3 -31.7 Pass STW-1091 04/10/06 1-131 22.0 +/- 0.3 19.1 13.9 -24.3 Pass STW-1092 04/10/06 H-3 7960.0 +/- 57.0 8130.0 6720.0 - 9540.0 Pass STW-1092 04/10/06 Ra-226 2.9 +/- 0.4 3.0 2.2 - 3.8 Pass STW-1 092 04/10/06 Ra-228 20.9 +/- 1.2 19.1 10.8 -27.4 Pass STW-1092 04/10/06 Uranium 68.6 +/- 3.4 69.1 57.1 -81.1 Pass STW- 1094 07/10/06 Sr-89 15.9 +/- 0.7 19.7 11.0 -28.4 Pass STW-1 094 07/10/06 Sr-90 24.3 +/- 0.4 25.9 17.2 -34.6 Pass STW-1 095 07/10/06 Ba-133 94.9 +/- 8.9 88.1 72.9 -103.0 Pass STW-1 095 07/10/06 Co-60 104.0 +/- 1.8 99.7 91.0 -108.0 Pass STW-1 095 07/10/06 Cs-134 48.7 +/- 1.3 54.1 45.4 - 62.8 Pass STW-1095 07/10/06 Cs-137 236.0 +/-3.0 238.0 217.0 -259.0 Pass STW-1 095 07/10/06 Zn-65 126.0 + 8.0 121.0 100.0 - 142.0 Pass STW-1 096 07/10/06 Gr. Alpha 10.9 +/- 1.0 10.0 1.3-18.6 Pass STW-1 096 07/10/06 Gr. Beta 9.7 +/- 0.4 8.9 0.2 - 17.5 Pass STW-1097 07/10/06 Ra-226 11.0 +/- 0.5 10.7 7.9 - 13.5 Pass STW-1 097 07/10/06 Ra-228 12.2 +/- 0.8 10.7 6.1 -15.3 Pass STW-1097 07/10/06 Uranium 43.4 +/- 0.1 40.3 33.3 -47.3 Pass Al-1
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 104 10/06/06 Sr-89 38.4 +/- 1.3 39.9 31.2 - 45.7 Pass STW-1104 10/06/06 Sr-90 15.5 +/- 0.5 16.0 7.3 - 24.7 Pass STW-1105 10/06/06 Ba-133 64.9 +/- 2.8 70.2 58.1 - 82.3 Pass STW-1105 10/06/06 Co-60 61.6 +/- 1.0 62.3 53.6 -71.0 Pass STW-1 105 10/06/06 Cs-134 29.0 +/- 0.9 29.9 21.2 -38.6 Pass STW- 1105 10/06/06 Cs-137 77.8 +/- 2.4 78.2 69.5 - 86.9 Pass STW-1 105 '10/06/06 Zn-65 293.0 +/- 2.4 277.0 229.0 - 325.0 Pass STW-1 106 10/06/06 Gr. Alpha 23.9 +/- 2.5 28.7 16.3 -41.1 Pass STW-1 106 10/06/06 Gr. Beta 237 +/- 1.4 20.9 12.2 - 29.6 Pass STW-1107 d 10/06/06 1-131 28.4 +/- 1.2 22.1 16.9 - 27.3 Fail STW-1 108 10/06/06 Ra-226 14.5 +/- 0.5 14.4 10.7 -18.1 Pass STW-1 108 10/06/06 Ra-228 6.6 +/- 0.4 5.9 3.3 -8.4 Pass STW-1 108 10/06/06 Uranium 2.9 +/-0.1 3.2 0.0 -8.4 Pass STW-1109 10/06/06 H-3 3000.0 +/- 142.0 3050.0 2430.0 - 3670.0 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
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 (1 sigma, 1 determination) and control limits as provided by ERA.
d The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.
A fourth analysis was performed, result of analysis, 24.89 pCi/L.
A1-2
TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value +/- 2 sigma Limits Acceptance Environmental, Inc.
2006-1 6/5/2006 30 cm 54.81 70.73 +/- 0.69 38.37 - 71.25 Pass 2006-1 6/5/2006 60 cm 13.70 16.71 +/-1.89 9.59 - 17.81 Pass 2006-1 6/5/2006 60 cm 13.70 16.69 +/- 0.94 9.59 - 17.81 Pass 2006-1 6/5/2006 90 cm 6.09 6.57 +/- 0.82 4.26 - 7.92 Pass 2006-1 6/5/2006 120 cm 3.43 3.65 +/- 0.22 2.40 - 4.46 Pass 2006-1 6/5/2006 120 cm 3.43 3.09 +/- 0.33 2.40 -4.46 Pass 2006-1 6/5/2006 150 cm 2.19 2.35 +/- 0.38 1.53 -2.85 Pass 2006-1 6/5/2006 150 cm 2.19 1.98 +/- 0.10 1.53 -2.85 Pass 2006-1 6/5/2006 180 cm 1.52 1.56 +/- 0.26 1.06 -1.98 Pass Environmental, Inc.
2006-2 11/6/2006 30 cm. 55.61 60.79 +/- 1.32 38.93 - 72.29 Pass 2006-2 11/6/2006 40 cm. 31.28 35.93 +/- 3.70 21.90 -40.66 Pass 2006-2 11/6/2006 50 cm. 20.02 21.55 +/- 1.20 14.01 - 26.03 Pass 2006-2 11/6/2006 60 cm. 13.90 14.90 +/- 1.42 9.73 - 18.07 Pass 2006-2 11/6/2006 75 cm. 8.90 8.03 +/- 0.51 6.23 -11.57 Pass 2006-2 11/6/2006 90 cm. 6.18 6.88 +/- 0.68 4.33 - 8.03 Pass 2006-2 11/6/2006 120 cm. 3.48 2.90 +/- 0.20 2.44 - 4.52 Pass 2006-2 11/6/2006 150 cm. 2.22 1.99 +/- 0.07 1.55 - 2.89 Pass 2006-2 11/6/2006 180 cm. 1.54 1.79 +/- 0.94 1.08 -2.00 Pass A2-1
TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-301 1/20/2006 Fe-55 2700.10 +/- 70.00 2502.50 2002.00 - 3003.00 Pass SPAP-1224 3/7/2006 Cs-1 34 37.13 +/- 3.70 39.52 29.52 - 49.52 Pass SPAP-1224 3/7/2006 Cs-1 37 118.25 +/- 8.97 119.30 107.37 - 131.23 Pass SPAP-1224 3/7/2006 Gr. Beta 520.32 +/- 7.42 455.00 364.00 - 637.00 Pass SPW-1 228 3/7/2006 H-3 70891.00 +/- 719.00 75394.00 60315.20 -90472.80 Pass SPW-1 230 3/7/2006 Cs-1 34 38.58 +/- 2.10 39.51 29,51 -49.51 Pass SPW-1230 3/7/2006 Cs-1 37 59.44 +/- 4.51 59.65 49.65 - 69.65 Pass SPMI-1232 3/7/2006 Cs-134 41.20 +/- 1.33 39.51 29.51 - 49.51 Pass SPMI-1232 3/7/2006 Cs-1 37 57.82 +/- 3.96 59.65 49.65 - 69.65 Pass W-30906 3/9/2006 Gr. Alpha 24.24 +/- 0.47 20.08 10.04 -30.12 Pass W-30906 3/9/2006 Gr. Beta 63.79 +/- 0.48 65.73 55.73 - 75.73 Pass SPW-2750 4/27/2006 Ni-63 116.00 +/- 2.49 100.00 60.00 - 140.00 Pass SPW-2869 5/1/2006 Fe-55 19473.00 +/- 188.00 23332.00 18665.60 - 27998.40 Pass SPAP-2871 5/1/2006 Cs-1 34 33.97 +/- 1.10 37.50 27.50 - 47.50 Pass SPAP-2871 5/1/2006 Cs-1 37 114.44 +/- 2.81 118.90 107.01 - 130.79 Pass SPW-2875 5/1/2006 H-3 71057.00 +/-.730.20 75394.00 60315.20 - 90472.80 Pass STSO-3155 5/1/2006 Co-60 7950.80 +/- 67.29 7750.00 6975.00 - 8525.00 Pass STSO-3155 5/1/2006 Cs-1 34 12.49 +/- 0.13 11.59 1.59 -21.59 Pass STSO-3155 5/1/2006 Cs-1 37 14.10 +/- 0.12 11.63 1.63 -21.63 Pass SPAP-2873 5/2/2006 Gr. Beta 1724.80 +/- 4.51 1744.00 1395.20 -2441.60 Pass SPF-3183 5/10/2006 Cs-137 2.47 +/- 0.03 2.38 1.43 - 3.33 Pass SPF-3183 5/10/2006 Cs-134 0.73 +/- 0.01 0.74 0.44 -1.04 Pass SPW-3460 5/26/2006 C-14 4009.60 +/- 14.43 .4741.00 2844.60 - 6637.40 Pass W-60606 6/6/2006 Gr. Alpha 21.94 +/- 0.46 20.08 10.04 -30.12. Pass W-60606 6/6/2006 Gr. Beta 58.17 +/- 0.49 65.73 55.73 - 75.73 Pass SPW-3988 6/16/2006 Cs-134 35.56 +/- 1.40 36.00 26.00 - 46.00 Pass SPW-3988 6/16/2006 Cs-1 37 60.23 +/- 2.72 59.27 49.27 - 69.27 Pass SPW-3988 6/16/2006 1-131(G) 94.01 +/- 4.38 99.30 89.30 - 109.30 Pass SPW-3988 6/16/2006 Sr-89 52.40 +/- 4.23 58.16 46.53 - 69.79 Pass SPW-3988 6/16/2006 Sr-90 45.35 +/- 1.95 41.21 32.97 - 49.45 Pass SPMI-3990 6/16/2006 Cs-1 34 35.52 +/- 5.05 36.00 26.00 - 46.00 Pass SPMI-3990 6/16/2006 Cs-137 56.78 +/- 3.86 59.27 49.27 - 69.27 Pass SPMI-3990 6/16/2006 1-131(G) 95.04 +/- 5.05 99.30 89.30 - 109.30 Pass SPMI-3991 6/16/2006 1-131 96.55 +/- 0.87 99.30 79.44 - 119.16 Pass SPW-4356 7/5/2006 1-131 80.88 +/- 1.09 77.23 61.78 -92.68 Pass W-90506 9/5/2006 Gr. Alpha 23.11 +/- 0.45 20.08 10.04 -30.12 Pass W-90506 9/5/2006 Gr. Beta 65.01 +/- 0.51 65.73 55.73 - 75.73 Pass SPAP-6950 9/30/2006 Cs-134 28.93 +/- 1.56 32.65 22.65 - 42.65 Pass SPAP-6950 9/30/2006 Cs-1 37 116.62 +/- 2.97 117.75 105.98 -129.53 Pass SPAP-6952 9/30/2006 Gr. Beta 52.96 +/- 0.14 53.50 42.80 - 74.90 Pass A3-1
TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)
Lab Code Date Analysis Laboratory results Known Control 2s, n=1 b Activity Limitsc' Acceptance SPW-6954 9/30/2006 Cs-1 34 63.29 +/- 8.24 65.30 55.30 - 75.30 Pass SPW-6954 9/30/2006 Cs-1 37 60.41 +/- 7.53 58.87 48.87 - 68.87 Pass SPMI-6956 9/30/2006 Cs-1 34 69.26 +/- 4.85 65.31 55,31 - 75.31 Pass SPMI-6956 9/30J2006 Cs-1 37 61.35 +/- 7.62 58.87 48.87 - 68.87 Pass W-1 20106 12/1/2006 Gr. Alpha 22.40 +/- 1.03 20.08 10.04 -30.12 Pass W-1 20106 12/1/2006 Gr. Beta 63.70 +/- 1.14 65.73 55.73 -.75.73 Pass SPAP-9476 12/29/2006 Gr. Beta 57.51 +/- 0.14 53.16 42.53 - 74.42 Pass SPAP-9478 12/29/2006 Cs-1 34 26.84 +/- 1.23 30.06 20.06 - 40.06 Pass SPAP-9478 12/29/2006 Cs-137 110.54 +/- 3.12 117.10 105.39 - 128.81 Pass SPW-9480 12/29/2006 H-3 68972.20 +/- 748.00 72051.60 57641.28- 86461.92 Pass SPW-9483 12/29/2006 Tc-99 29.43 +/- 0.84 32.98 20.98 - 44.98 Pass SPW-9488 12/29/2006 Cs-1 34 61.35 +/- 1.65 60.10 50.10 -70.10 Pass SPW-9488 12/29/2006 Cs-137 60.30 +/- 2.76 56.80 46.80 - 66.80 Pass SPMI-9490 12/29/2006 Cs-1 34 58.99 +/- 5.43 .60.10 50.10 -70.10 Pass SPMI-9490 12/29/2006 Cs-137 54.16 +/- 7,85 56.80 46.80 - 66.80 Pass SPF-9492 12/29/2006 Cs-134 0.64 +/- 0.01 0.60 0.36 - 0.84 Pass SPF-9492 12/29/2006 Cs-1 37 2.61 +/- 0.03 2.34 1.40 -3.28 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/rn 3), and solid samples (pCi/g).
b Laboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil),
VE (vegetation),
CH (charcoal canister), F (fish).
c Results are based on single determinations.
d 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/L)8 Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activity' Criteria (4,66 a)
SPW-302 water 1/20/2006 Fe-55 21.21 -1.82 +/- 12.75 1000 SPAP-1225 Air Filter 3/7/2006 Gr. Beta 1.16 -0.512 +/- 51.20 3.2 SPW-1231 water 3/7/2006 Cs-1 34 2.71 10 SPW-1231 water 3/7/2006 Cs-137 2.05 10 W-30906 witer 3/9/2006 Gr. Alpha 0.037 0,005 +/- 0.026 1 W-30906 water 3/9/2006 Gr. Beta 0,076 -0.016 +/- 0.052 3.2 SPW-2751 water 4/27/2006 Ni-63 1.48 0.37 +/- 0.91 20 SPW-2868 water 5/1/2006 Fe-55 18.07 4.33 +/- 11.27 1000 SPW-2874 water 5/1/2006 H-3 166,00 -8,3 +/- 86.9 200 SPAP-2872 Air Filter 5/2/2006 Gr. Beta 1.18 -3.65 +/- 0.64 3.2 SPF-3154 Fish 5/10/2006 Cs-1 34 16.4 100 SPF-3154 Fish 5/10/2006 Cs-1 37 13.7 100 SPW-3461 water 5/26/2006 C-14 10.20 -7.9 +/- 5.20 200 W-60606 water 6/6/2006 Gr. Alpha 0.05 0.013 +/- 0,037 1 W-60606 water 6/6/2006 Gr. Beta 0.16 -0.044 +/- 0.11 3.2 SPW-3989 water 6/16/2006 Cs-1 34 3.00 10 SPW-3989 water 6/16/2006 Cs-1 37 3.65 10 SPW-3989 water 6/16/2006 1-131 0.21 0.045 +/- 0.14 0.5 SPW-3989 water 6/16/2006 1-131(G) 8.34 20 SPW-3989 water 6/16/2006 Sr-89 0.54 0.005 +/- 0.45 5 SPW-3989 water 6/16/2006 Sr-90 0,58 -0,079 +/- 0.26 1 SPMI-3991 Milk 6/16/2006 Cs-134 4.42 10 SPMI-3991 Milk 6/16/2006 Cs-137 3.88 10 SPMI-3991 Milk 6/16/2006 1-131 0.28 -0.22 +/- 0.19 0,5 SPMI-3991 Milk 6/16/2006 1-131(G) 3.76 20 SPMI-3991 Milk 6/16/2006 Sr-89 0.61 -0.25 +/- 0.76 5 SPMI-3991 d Milk 6/16/2006 Sr-90 0.52 0.88 +/- 0.34 1 W-90506 water 9/5/2006 Gr. Alpha 0.06 0.00 +/- 0.04 1 W-90506 water 9/5/2006 Gr. Beta 0.16 0.05 +/- 0.11 3.2 SPMI-6383 Milk 9/14/2006 Sr-89 0.97 -0.18 +/- 0.92 5 SPMI-6383 d Milk 9/14/2006 Sr-90 0.57 0.65 +/- 0.33 1 SPAP-6949 Air Filter .9/30/2006 Cs-134 0.89 100 SPAP-6949 Air Filter 9/30/2006 Cs-137 0.91 100 SPAP-6951 Air Filter 9/30/2006 Gr. Beta 1.12 -0.54 +/- 0.64 3.2 SPW-6953 water 9/30/2006 Cs-1 34 3.91 10 SPW-6953 water 9/30/2006 Cs-1 37 5.61 10 SPW-6953 water 9/30/2006 Sr-89 0.79 -0.14 +/- 0.64 5 SPW-6953 water 9/30/2006 Sr-90 0.60 0.11 +/- 0.29 1 A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a)
SPMI-6955 Milk 9/30/2006 Cs-1 34 2.86 10 SPMI-6955 Milk 9/30/2006 Cs-1 37 2.39 10 SPMI-6955 Milk 9/30/2006 1-131(G) 9.98 0.5 W-1 20106 water 12/1/2006 Gr. Alpha 0.11 0.066 +/- 0.072 1 W-120106 water 12/1/2006 Gr. Beta 0.30 0.093 +/- 0.16 3.2 SPAP-9477 Air Filter 12/29/2006 Gr. Beta 1.13 -0.37 +/- 0.66 3.2 SPAP-9479 Air Filter 12/29/2006 Cs-1 37 0.87 100 SPW-9481 water 12/29/2006 H-3 146.2 63.2 +/- 80.1 200 SPW-9483 water 12/29/2006 Tc-99 0.95 -1.20 +/- 0.56 10 SPW-9489 water 12/29/2006 Cs-1 34 2.30 10 SPMI-9491 Milk 12/29/2006 Cs-1 34 3.10 10 SPMI-9491 Milk 12/29/2006 Cs-137 2.90 10 SPMI-9491 Milk 12/29/2006 1-131(G) 8.00 20 SPF-9493 Fish 12/29/2006 Cs-1 34 7.6 100 SPF-9493 Fish 12/29/2006 Cs-1 37 7.9 100 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b 1-131(G); iodine-131 as analyzed by gamma spectroscopy.
c Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported d Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.
A4-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7466, 7467 1/3/2006 Be-7 0.053 +/- 0.015 0.057 +/- 0.011 0.055 +/- 0.009 Pass AP-7513, 7514 1/3/2006 Be-7 0.033 +/- 0.008 0.036 +/- 0.008 0.035 +/- 0.006 Pass AP-7555, 7556 1/3/2006 Be-7 0.053 +/- 0,007 0.054 +/- 0.008 0.053 +/- 0.005 Pass MI-154, 155 1/10/2006 K-40 1254.20 +/- 87.75 1369.60 +/- 102.80 1311.90 +/- 67.58 Pass MI-217, 218 1/11/2006 K-40 1258.00 +/- 118.00 1313.00 +/- 98.00 1285.50 +/- 76.69 Pass MI-217, 218 1/11/2006 Sr-90 1.27 +/- 0.37 0.92 +/- 0.33 1.10 +/- 0.25 Pass MI-287, 288 1/17/2006 K-40 1383.10 +/- 110.90 1457.80 +/- 119.10 1420.45 +/- 81.37 Pass MI-287, 288 1/17/2006 Sr-90 0.74 +/- 0.38 0.94 +/- 0.37 0.84 +/- 0.27 Pass WW-314, 315 1/19/2006 Gr. Beta 9.21 +/- 1.72 11.52 +/- 1.93 10.37 +/- 1.29 Pass WW-314, 315 1/19/2006 H-3 168.64 +/- 94.94 210.12 +/- 96.51 189.38 +/- 67.69 Pass SWT-577, 578 1/31/2006 Gr. Beta 3.06 +/- 0.66 3.68 +/- 0.64 3.37 +/- 0.46 Pass SWU-598, 599 1/31/2006 Gr. Beta 2.03 +/- 0.39 1.97 +/- 0.40 2.00 +/- 0.28 Pass SWU-598, 599 1/31/2006 H-3 260.10 +/- 98.20 134.10 +/- 93.50 197.10 +/- 67.80 Pass F-3311, 3 3 1 2 b 2/9/2006 Gr. Beta 4.12 +/- 0.14 3.82 +/- 0.13 3.97 +/- 0.10 Fail F-3311, 3312 2/9/2006 K-40 2.68 +/- 0.37 2.76 +/- 0.39 2.72 +/- 0.27 Pass SW-780, 781 2/14/2006 Gr. Alpha 4.09 +/- 1.52 3.22 +/- 1.37 3.66 +/- 1.03 Pass SW-780, 781 2/14/2006 Gr. Beta 5.91 +/- 0.90 5.89 +/- 0.92 5.90 +/- 0.64 Pass DW-934, 935 2/17/2006 1-131 0.35 +/- 0.22 0.31 +/- 0.25 0.33 +/- 0.16 Pass DW-1024, 1025 2/24/2006 1-131 0.24 +/- 0.26 0.53 +/- 0.24 0.39 +/- 0.18 Pass MI-1078, 1079 3/1/2006 Sr-90 1.42 +/- 0.39 1.30 +/- 0.62 1.36 +/- 0.37 Pass F-1357, 1358 3/10/2006 Gr. Beta 3.77 +/- 0.07 3.71 +/- 0.07 3.74 +/- 0.05 Pass F-1357, 1358 3/10/2006 K-40 2.46 +/- 0.32 2.32 +/- 0.44 2.39 +/- 0.27 Pass MI-1469, 1470 3/14/2006 K-40 1396.30 +/- 120.80 1335.60 +/- 113.80 1365.95 +/- 82.98 Pass CF-1538, 1539 3/21/2006 K-40 13.66 +/- 0.81 13.97 +/- 0.68 13.81 +/- 0.53 Pass WW-1583, 1584 3/22/2006 Gr. Beta 7.66 +/- 0.73 8.87 +/- 0.75 8.26 +/- 0.52 Pass DW-1 955, 1956 3/27/2006 Gr. Beta 2.25 +/- 0,60 3.15 +/- 0.59 2.70 +/- 0.42 Pass MI-1760, 1761 3/29/2006 K-40 1271.00 +/- 89.00 1378.00 +/- 113.00 1324.50 +/- 71.92 Pass AP-2603, 2604 3/29/2006 Be-7 0.067 +/- 0.015 0.056 +/- 0.010 0.062 +/- 0.009 Pass E-1997, 1998 4/3/2006 Gr. Beta 1.82 +/- 0.07 1.87 +/- 0.07 1.85 +/- 0.05 Pass E-1 997, 1998 4/3/2006 K-40 1.28 +/- 0.15 1.24 +/- 0.21 1.26 +/- 0.13 Pass AP-2818, 2819 4/3/2006 Be-7 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass SWU-2863, 2864 4/3/2006 Gr. Beta 3.20 +/- 1.26 4.77 +/- 1.30 3.99 +/- 0.91 Pass SS-2389, 2390 4/11/2006 Gr. Beta 10.53 +/- 0.96 9.38 +/- 0.84 9.96 +/- 0.64 Pass SS-2389, 2390 4/11/2006 K-40 5.51 +/- 0.42 5.79 +/- 0.40 5.65 +/- 0.29 Pass DW-2773, 2774 4/21/2006 1-131 0.74 +/- 0.23 0.53 +/- 0.40 0.63 +/- 0.23 Pass SL-2932, 2933 5/1/2006 Be-7 1.28 +/- 0.19 1.27 +/- 0.17 1.28 +/- 0.13 Pass SL-2932, 2933 5/1/2006 Gr. Beta 6.09 +/- 0.33 5.65 +/- 0.31 5.87 +/- 0.23 Pass SL-2932, 2933 5/1/2006 K-40 3.13 +/- 0.41 3.09 +/- 0.36 3.11 +/- 0.27 Pass BS-3103, 3104 5/1/2006 Gr. Beta 8.27 +/- 1.46 9.03 +/- 1.59 8.65 +/- 1.08 Pass BS-3103, 3104 5/1/2006 K-40 6288.20 +/- 585.20 5643.70 +/- 599.80 5965.95 +/- 418.99 Pass MI-3037, 3038 5/2/2006 K-40 1238.90 +/- 98.59 1301.00 +/- 103.90 1269.95 +/- 71.62 Pass MI-3037, 3038 5/2/2006 Sr-90 1.76 +/- 0.42 1.48 +/- 0.42 1.62 +/- 0.29 Pass A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-3124, 3125 5/9/2006 K-40 1032.30 +/- 91.12 1103.60 +/- 120.50 1067.95 +/- 75.54 *Pass SW-3145, 3146 5/9/2006 Gr. Alpha 4.85 +/- 1.68 4.12 +/- 1.62 4.48 +/- 1.17 Pass SW-3145, 3146 5/9/2006 Gr. Beta .8.94 +/- 1.46 9.14 +/- 1.36 9.04 +/- 1.00 Pass MI-3236, 3237 5/10/2006 K-40 1412.40 +/- 119.10 1427.90 +/- 127.70 1420.15 +/- 87.31 Pass F-3422, 3423 5/19/2006 H-3 8175.00 +/- 252.00 8268.00 +/- 253.00 .8221.50 +/- 178.54 Pass G-3491, 3492 5/24/2006 Gr. Beta 8.89 +/- 0.18 9.03 +/- 0.19 8.96 +/- 0.13 Pass.
G-3491, 3492 5/24/2006 K-40 5.60 +/- 0.71 6.30 +/- 0.78 5.95 +/- 0.53 Pass SO-3539,3540 5/24/2006 Gr. Beta 19.57 +/- 1.99 18.98 +/- 1.91 19.27 +/- 1.38 Pass SO-3539, 3540 5/24/2006 K-40 12.55 +/- 0.89 11.49 +/- 0.59 12.02 +/- 0.53 Pass WW-3751, 3752 5/25/2006 Gr. Beta 9.85 +/- 0.79 8.96 +/- 0.74 9.41 + 0.54 Pass F-3617, 3618 5/30/2006 K-40 2.42 +/- 0.38 2.53 +/- 0.37 2.47 +/- 0.27 Pass SL-3641, 3642 6/1/2006 Be-7 1.41 + 0.19 1.31 +/- 0.27 1.36 +0.17 Pass SL-3641, 3642 6/1/2006 Gr. Beta 5.03 +/- 0.18 5.30 +/- 0.19 5.17 +/-0.13 Pass SL-3641, 3642 6/1/2006 K-40 2.21 + 0.26 2.14 +/- 0.37 2.18 +/- 0.23 Pass MI-3886, 3887 6/12/2006 K-40 1424.20 + 118.20 1318.80 +/- 110.50 1371.50 +/- 80.90 Pass VE-3949, 3950 6/13/2006 Gr. Alpha 0.13 +/- 0.06 0.16 +/- 0.07 0.15 +/- 0.05 Pass VE-3949, 3950 6/13/2006 Gr. Beta 4.53 +/- 0.19 4.47 +/- 0.18 4.50 +/-0.13 Pass VE-3949, 3950 6/13/2006 K-40 6.02 +/- 0.66 5.33 +/- 0.66 5.67 +/- 0.47 Pass BS-4016, 4017 6/13/2006 Co-60 0.18 + 0.03 0.15 +/- 0.03 0.16 +/- 0.02 Pass BS-4016, 4017 6/13/2006 Cs-1 37 1.97 _ 0.09 2.01 +/- 0.09 1.99 +/- 0.06 Pass BS-4016, 4017 6/13/2006 K-40 11.03 +/- 0.76 10.45 +/- 0.78 10.74 +/- 0.54 Pass MI-3992, 3993 6/14/2006 K-40 1358.50 +/- 166.40 1395.80 +/- 122.70 1377.15 +/- 103.37 Pass LW-4175, 4176 6/16/2006 H-3 482.11 +/- 90.25 397.50 +/- 86.88 439.81 +/- 62.63 Pass W-4130,4131 6/21/2006 H-3 401.50 +/- 87.85 236.28 +/- 80.89 318.89 +/- 59.71 Pass AV-4330, 4331 6/26/2006 K-40 1717.10 +/- 244.30 1893.10 +/- 223.30 1805.10 +/- 165.49 Pass SWU-4489, 4490 6/27/2006 Gr. Beta 1.70 +/- 0.38 1.93 +/- 0.38 1.82 +/- 0.27 Pass AP-4909, 4910 6/29/2006 Be-7 0.11 +/- 0.01 0.11 +/- 0.02 0.11 +/- 0.01 Pass AP-4952, 4953 6/29/2006 Be-7 0.08 +/- 0.02 0.10 +/- 0.02 0.09 + 0.01 Pass AP-4930, 4931 7/3/2006 Be-7 0.08 +/- 0.02 0.07 +/- 0.01 0.08 +/- 0.01 Pass E-4399, 4400 7/5/2006 Gr. Beta 1.85 +/- 0.05 1.85 +/- 0.05 1.85 +/- 0.04 Pass E-4399, 4400 7/5/2006 K-40 1.25 +/- 0.19 1.24 +/- 0.18 1.25 +/- 0.13 Pass G-4420, 4421 7/5/2006 Be-7 0.82 +/- 0.20 0.61 +/- 0.14 0.72 +/- 0.12 Pass G-4420, 4421 7/5/2006 Gr. Beta 13.20 +/- 0.40 14.00 +/- 0.40 13.60 +/- 0.28 Pass G-4420, 4421 7/5/2006 K-40 9.96 +/- 0.44 10.06 +/- 0.82 10.01 +/- 0.47 Pass DW-60432, 60433 7/6/2006 Gr. Alpha 3.24 +/- 1.35 2.49 +/- 1.33 2.87 +/- 0.95 Pass DW-60514, 60515 7/10/2006 Gr. Alpha 3.70 +/- 1.12 3.09 +/- 1.16 3.40 +/- 0.81 Pass DW-60449, 60450 7/11/2006 Gr. Alpha 6.87 +/- 1.26 4.77 +/- 1.09 5.82 +/- 0.83 Pass MI-4599, 4600 7/12/2006 K-40 1403.50 +/- 118.80 1330.40 +/- 116.50 1366.95 +/- 83.20 Pass MI-4599, 4600 7/12/2006 Sr-90 0.59 +/- 0.34 0.70 +/- 0.35 0.65 +/- 0.24 Pass MI-4667, 4668 7/12/2006 K-40 1286.60 +/- 92.62 1358.60 +/- 158.40 1322.60 +/- 91.75 Pass LW-4823, 4824 7/14/2006 Gr. Beta 1.75 +/- 0.60 2.51 +/- 0.59 2.13 +/- 0.42 Pass A5-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance DW-60502, 60503 7/19/2006 Gr. Alpha 16.27 +/- 2.49 21.41 +/- 3.21 18.84 +/- 2.03 Pass DW-60526, 60527 7/21/2006 Gr. Alpha 14.06 +/- 1.82 15.57 +/- 1.77 14.82 +/- 1.27 Pass DW-60539, 60540 7/21/2006 Gr. Alpha 5.09 +/- 0.95 6.23 +/- 1.05 5.66 +/- 0.71 Pass MI-5125, 5126 7/25/2006 K-40 1480.60 +/- 118.30 1402.60 +/- 120.80 1441.60 +/- 84.54 Pass DW-60609, 60610 7/26/2006 Gr. Alpha 1.00 +/- 1.10 2.70 +/- 1.30 1.85 +/- 0.85 Pass DW-60621, 60622 7/31/2006 Gr. Alpha 3.70 +/- 1.00 1.90 +/- 0.80 2.80 +/- 0.64 Pass SL-5265, 5266 8/1/2006 Be-7 1.10 +/- 0.46 1.38 +/- 0.52 1.24 +/- 0.35 Pass SL-5265, 5266 8/1/2006 Sr-90 0.10 +/- 0.03 0.16 +/- 0.03 0.13 +/- 0.02 Pass SL-5265, 5266 8/1/2006 Gr. Beta 4.41 +/- 0.41 3.46 +/- 0.57 3.94 +/- 0.35 Pass SL-5265, 5266 8/1/2006 K-40 1.19 +/- 0.52 0.87 +/- 0.52 1.03 +/- 0.37 Pass VE-5286, 5287 8/1/2006 Be-7 1.21 +/- 0.30 1.32 +/- 0.20 1.27 +/- 0.18 Pass VE-5286, 5287 8/1/2006 Gr. Beta 9.67 +/- 0.35 9.37 +/- 0.35 9.52 +/- 0.25 Pass VE-5286, 5287 8/1/2006 K-40 6.25 +/- 0.81 6.50 +/- 0.48 6.38 +/- 0.47 Pass SW-5383, 5384 8/8/2006 Gr. Alpha 3.24 +/- 1.35 2.94 +/- 1.35 3.09 +/- 0.96 Pass SW-5383, 5384 8/8/2006 Gr. Beta 4.86 +/- 0.86 5.46 +/- 0.87 5.16 +/- 0.61 Pass SW-5971, 5972 8/8/2006 H-3 119.90 +/- 78.14 144.41 +/- 79.23 132.15 +/- 55.64 Pass VE-5404, 5405 8/10/2006 Be-7 0.77 +/- 0.24 1.01 +/- 0.26 0.89 +/- 0.18 Pass VE-5404, 5405 8/10/2006 K-40 4.71 +/- 0.63 4.01 +/- 0.58 4.36 +/- 0.43 Pass DW-5480, 5481 8/11/2006 H-3 169.08 +/- 85.52 133.65 +/- 83.96 151.36 +/- 59.92 Pass DW-60645, 60646 8/15/2006 Gr. Alpha 10.41 +/- 1.78 10.97 +/- 1.85 10.69 +/- 1.28 Pass W-5602, 5603 8/16/2006 H-3 2118.79 +/- 151.55 2181.82 +/- 153.09 2150.30 +/- 107.71 Pass DW-60634, 60635 8/18/2006 Gr. Alpha 12.99 +/- 1.84 9.67 +/- 1.61 11.33 +/- 1.22 Pass DW-60634, 60635 8/18/2006 Gr. Beta 10.51 +/- 1.33 8.61 +/- 1.18 9.56 +/- 0.89 Pass MI-5793, 5794 8/22/2006 K-40 1264.00 +/- 115.00 1377.00 +/- 121.00 1320.50 +/- 83.47 Pass SWU-6150, 6151 8/29/2006 Gr. Beta 1.84 +/- 0.28 1.81 +/- 0.28 1,82 +/- 0.20 Pass DW-60657, 60658 8/29/2006 Gr. Alpha 2.33 +/- 0.80 2.90 +/- 0.78 2.62 +/- 0.56 Pass CF-7450, 7451 9/5/2006 Be-7 0.78 +/- 0.45 0.78 +/- 0.27 0.78 +/- 0.26 Pass SL-6085, 6086 9/5/2006 Co-60 0.22 +/- 0.03 0.21 +/- 0.02 0.22 +/- 0.02 Pass SL-6085, 6086 9/5/2006 Gr. Beta 5.47 +/- 0.69 4.63 +/- 0.58 5.05 +/- 0.45 Pass SL-6085, 6086 9/5/2006 K-40 1.91 +/- 0.28 2.06 +/- 0.41 1.99 +/- 0.25 Pass DW-60695, 60696 9/11/2006 Gr. Alpha 3.93 +/- 1.17 4.62 +/- 1.12 4.28 +/- 0.81 Pass LW-6266, 6267 9/13/2006 Gr. Beta 3.09 +/- 0.48 2.98 +/- 0.48 3.03 +/- 0.34 Pass MI-6424, 6425 9/19/2006 Sr-90 0.78 +/- 0.38 1.11 +/- 0.37 0.95 +/- 0.27 Pass DW-60715, 60716 9/19/2006 Gr. Alpha 1.30 +/- 1.00 2.23 +/- 1,01 1.77 +/- 0.71 Pass SO-6597, 6598 9/22/2006 Cs-1 37 0.18 +/- 0.04 0.18 +/- 0.04 0.18 +/- 0.03 Pass SO-6597, 6598 9/22/2006 K-40 10.25 +/- 0.66 10.11 +/- 0.64 10.18 +/- 0.46 Pass SWU-6718, 6719 9/26/2006 Gr. Beta 3.45 +/- 1.21 2.78 +/- 1.19 3.12 +/- 0.85 Pass SO-6668, 6669 9/27/2006 Cs-1 37 0.13 +/- 0.04 0.13 +/- 0.02 0.13 +/- 0.02 Pass SO-6668, 6669 9/27/2006 K-40 13.04 +/- 0.90 12.41 +/- 0.54 12.72 +/- 0.53 Pass A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis *First Result Second Result Result Acceptance MI-6760, 6761 10/2/2006 K-40 1413.10 +/- 113.20 1187.30 +/- 155.20 1300.20 + 96.05 Pass G-6797, 6798 10/2/2006 Be-7 4.70 +/- 0.31 4.56 +/- 0.41 4.63 + 0.26 Pass G-6797,6798 10/2/2006 Gr. Beta 6.89 +/- 0.26 7.04 +/- 0.24 6.97 +/- 0.18 Pass G-6797, 6798 b 10/2/2006 K-40 5.39 +/- 0.35 4.36 +/- 0.47 4.88 +/- 0.29 Fail AP-7531, 7532 10/3/2006 Be-7 0.07 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-7552, 7553 10/3/2006 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-7573, 7574 10/3/2006 Be-7 . 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass SO-7103, 7104 10/4/2006 Cs-137 0.25 +/- 0.05 0.27 +/- 0.06 0.26 +/- 0.04 Pass SO-7103, 7104 10/4/2006 K-40 12.95 +/- 1.12 12.22 +/- 1.07 12.58 +/- 0.77 Pass DW-60759, 60760 10/5/2006 Gr. Alpha 4.93 +/- 0.97 5.04 +/- 1.03 4.99 +/- 0.71 Pass MI-7037, 7038 10/10/2006 K-40 1326.10 +/- 115.20 1251.40 +/- 115.70 1288.75 +/- 81.64 Pass VE-7058, 7059 10/10/2006 Gr. Alpha 0.18 +/- 0.11 0.32 +/- 0.14 0.25 +/- 0.09 Pass VE-7058, 7059 10/10/2006 Gr. Beta 9.21 +/- 0.34 8.83 +/- 0.36 9.02 +/- 0.25 Pass VE-7058, 7059 10/10/2006 K-40 10.90 +/- 0.65 10.42 +/- 0.80 10.66 +/- 0.52 Pass SS-7079, 7080 10/10/2006 Cs-137 0.04 +/- 0.01 0.04 +/- 0.02 0.04 +/- 0.01 Pass SS-7079, 7080 10/10/2006 Gr. Beta 12.23 +/- 2.46 11.76 +/- 2.23 11.99 +/- 1.66 Pass SS-7079, 7080 10/10/2006 K-40 7.23 +/- 0.36 7.37 +/- 0.40 7.30 +/- 0.27 Pass MI-7208, 7209 10/11/2006 K-40 1295.20 +/- 116.90 1386.90 +/- 119,10 1341.05 +/- 83.44 Pass CF-7450, 7451 10/18/2006 K-40 20.40 +/- 0.84 .19.54 +/- 0.99 19.97 +/- 0.65 Pass LW-7945, 7946 10/26/2006 Gr. Beta 1.30 +/- 0.37 1.44 +/- 0.36 1.37 +/- 0.26 Pass F-7971, 7972 10/29/2006 K-40 3.63 +/- 0.54 3.33 +/- 0.43 3.48 +/- 0.34 Pass SWU-8194, 8195 10/31/2006 Gr. Beta 1.84 +/- 0.28 1.43 +/- 0.28 1.64 +/- 0.20 Pass BS-8017, 8018 11/1/2006 Gr. Beta 10.54 +/- 1.72 10.17 +/- 1.73 10.36 +/- 1.22 Pass BS-8017, 8018 11/1/2006 K-40 10.00 +/- 0.53 9.60 +/- 0.69 9.80 +/- 0.44 Pass LW-8215, 8216 11/1/2006 Gr. Beta 2.23 +/- 0.61 1.64 +/- 0.37 1.93 +/- 0.35 Pass F-8345, 8346 11/2/2006 K-40 2.84 +/- 0.42 2.89 +/- 0.40 2.86 +/- 0.29 Pass BS-8366, 8367 11/2/2006 K-40 13.69 +/- 0.66 13.61 +/- 0.78 13.65 +/- 0,51 Pass MI-8083, 8084 11/6/2006 K-40 1295.00 +/- 121.20 1374.80 +/- 162.80 1334.90 +/- 101.48 Pass WW-8259, 8260 11/7/2006 H-3 337.00 +/- 95.00 295.00 +/- 93.00 316.00 +/- 66.47 Pass MI-8484, 8485 11/22/2006 K-40 1405.80 +/- 87.06 1390.70 +/- 103.60 1398.25 +/- 67.66 Pass SO-8619,8620 11/27/2006 Cs-1 37 0.74 +/- 0.08 0.69 +/- 0.06 0.71 +/- 0.05 Pass SO-8619,8620 11/27/2006 Gr. Alpha 16.54 +/- 5.65 12.24 +/- 4.90 14.39 +/- 3.74 Pass SO-8619, 8620 11/27/2006 Gr. Beta 24.99 +/- 3.88 28.66 +/- 3.95 26.82 +/- 2.77 Pass SO-8619, 8620 11/27/2006 K-40 12.21 +/-+1.11 12.92 +/- 0.83 12.57 +/- 0.69 Pass SWT-8641, 8642 11/29/2006 Gr. Beta 2.83 +/- 0.47 2.89 +/- 0.45 2.86 +/- 0.33 Pass SWT-9436, 9437 12/26/2006 Gr. Beta 2.39 +/- 0.64 2.25 +/- 0.60 2.32 +/- 0.44 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities'that measure below the LLD.
a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).
b 200 minute count time or longer, resulting in lower error.
A5-4
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1082 01/01/06 Am-241 0.16 +/- 0.06 0.16 0.11 -0.20 Pass STVE-1082 01/01/06 Co-57 10.40 +/- 0.20 8.58 6.00 -11.15 Pass STVE-1082 01/01/06 Co-60 5.00 +/- 0.20 4.52 3.16 -5.88 Pass STVE-1 082 01/01/06 Cs-134 < 0.20 0.00 Pass STVE-1 082 01/01/06 Cs-i 37 3.40 +/- 0.20 3.07 2.15 -4.00 Pass STVE-1082 01/01/06 Mn-54 6.90 +/- 0.20 6.25 4.37 -8.12 Pass STVE- 1082 01/01/06 Pu-238 0.08 +/- 0.03 0.14 0.10 - 0.18 Fail STVE-1082 01/01/06 Pu-239/40 0.17 +/- 0.03 0.16 0.11 -0.21 Pass STVE-1082 01/01/06 Sr-90 1.40 +/- 0.20 1.56 1.09 - 2.03 Pass STVE-1 082 01/01/06 U-233/4 0.24 +/- 0.05 0.21 0.15 - 0.27 Pass STVE-1082 01/01/06 U-238 0.19 +/- 0.04 0.22 0.15 - 0.28 Pass STVE-1082 01/01/06 Zn-65 11.10 +/- 0.50 9.80 6.86 -12.74 Pass STSO-1083 01/01/06 Am-241 54.60 + 5.50 57.08 39.96 - 74.20 Pass STSO-1083 01/01/06 Co-57 762.90 + 12.70 656.29 459,40 -853.18 Pass STSO-1083 01/01/06 Co-60 504.90 + 3.10 447.10 312.97 -581.23 Pass STSO-1083 e 01/01/06 Cs-134 < 1.70 0.00 Pass STSO-1083 01/01/06 Cs-137 406.50 + 3.70 339.69 237.78 -441.60 Pass STSO-1083 01/01/06 K-40 719.20 +/- 18,40 604.00 422.80 - 785.20 Pass STSO-1 083 01/01/06 Mn-54 415.60 +/- 4.80 346.77 242.74 - 450.80 Pass STSO-1083 01/01/06 Ni-63 261.40 +/- 14.70 323.51 226.46 -420.56 Pass STSO-1083 01/01/06 Pu-238 14.60 +/- 2.90 61.15 42.81 - 79.50 Fail STSO-1083 01/01/06 Pu-239/40 14.60 +/- 2.40 45.85 32.09 -59.61 Fail STSO-1 083 01/01/06 U-233/4 13.50 +/- 1.70 37.00 25.90 -48.10 Fail STSO-1083 01/01/06 U-238 15.40 +/- 1.80 38.85 27.20 - 50.50 Fail STSO-1 083 01/01/06 Zn-65 783.40 +/- 7.00 657.36 460.15 -854.57 Pass STAP-1 084 01/01/06 Gr. Alpha 0.26 +/-,0.02 0.36 0.00 - 0.72 Pass STAP-1084 01/01/06 Gr. Beta 0.51 +/- 0.03 0.48 0.24 - 0.72 Pass STAP-1 085 01/01/06 Am-241 0.12 +/- 0.02 0.09 0.07 -0.12 Pass STAP-1 085 01/01/06 Co-57 4.32 +/- 0.10 4.10 2.87 - 5.32 Pass STAP-1085 01/01/06 Co-60 2.24 +/- 0.16 2.19 1.53 - 2.84 Pass STAP-1 085 01/01/06 Cs-1 34 2.96 +/- 0.19 2.93 2,05 -3.81 Pass STAP-1 085 01/01/06 Cs-i 37 2.64 +/- 0.20 2.53 1.77 - 3.29 Pass STAP-1 085' 01/01/06 Pu-238 0.03 +/- 0.01 0.07 0.05 - 0.09 Fail STAP-1 085 e 01/01/06 Pu-239/40 <0.01 0.00 Pass STAP-1085 01/01/06 Sr-90 0.77 +/- 0.21 0.79 0.55 -1.03 Pass STAP-1 085 01/01/06 U-233/4 0.03 + 0.01 0.02 0.01 - 0.03 Pass STAP- 1085 01/01/06 U-238 0.02 + 0.01 0.02 0.01 - 0.03 Pass STAP-1 085 01/01/06 Zn-65 3.94 +0.44 3.42 2.40 -4.45 Pass A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
b Concentration Known Control Lab Code' Date Analysis Laboratory result Activity Limits d Acceptance STW-1 086 01/01/06 Am-241 1.29 +/- 0.05 1.30 0.91 - 1.69 Pass STW-1086 01/01/06 Co-57 177.10 +/- 1.00 166.12 116.28 -215.96 Pass STW-1086 01/01/06 Co-60 158.30 +/- 1.00 153.50 107.45 - 199.55 Pass STW-1086 01/01/06 Cs-1 34 96.40 +/- 1.50 95.10 66.57 - 123.63 Pass STW-1086 e 01/01/06 Cs-1 37 < 0.80 0.00 Pass STW-1086 01/01/06 Fe-55 102.50 +/- 18.10 129.60 90.72 - 168.48 Pass STW-1 086 01/01/06 H-3 956.60 +/- 16.50 952.01 666.41 - 1238.00 Pass STW-1086 01/01/06 Mn-54 335.30 +/- 2.20 315.00 220.50 - 409.50 Pass STW-1086 01/01/06 Ni-63 62.90 +/- 3.60 60.34 42.24 - 78.44 Pass STW-1 086 01/01/06 Pu-238 0.96 +/- 0.07 0.91 0.70 - 1.30 Pass STW-1086 e 01/01/06 Pu-239/40 < 0.20 0.00 Pass STW-1 086 01/01/06 Sr-90 12.80 +/- 1.60 13.16 9.21 -17.11 Pass STW-1086 01/01/06 Tc-99 22.30 +/- 1.20 23.38 16.37 - 30.39 Pass STW-1086 01/01/06 U-233/4 2.02 +/- 0.12 2.09 1.46 -2.72 Pass STW-1 086 01/01/06 U-238 2.03 +/- 0.12 2.17 1.52 - 2.82 Pass STW-1086 01/01/06 Zn-65 249.50 +/- 3.40 228.16 159.71 -296.61 Pass STW-1087 01/01/06 Gr. Alpha 0.59 +/- 0.10 0.58 0.00 -1.16 Pass STW-1087 01/01/06 Gr. Beta 1.69 +/- 0.07 1.13 0.56 - 1.70 Pass STVE-1 0988 07/01/06 Co-57 <0.14 0.00 Pass STVE-1 098 g 07/01/06 Co-60 6.89 +/- 0.17 5.81 4.06 - 7.55 Pass 8TVE-1 098 07/01/06 Cs-134 8.46 + 0.16 7.49 5.24 - 9.73 Pass STVE-1098 07/01/06 Cs-1 37 6.87 +/- 0.29 5.50 3.85 -7.14 Pass STVE-1098 07/01/06 Mn-54 10.36 + 0.29 8.35 5.85 - 10.86 Pass STVE-1098 07/01/06 Zn-65 7.46 + 0.50 5.98 4,19 -7.78 Pass STSO-1 099 07/01/06 Am-241 130.00 +/- 11.60 105.47 73.83 -137.11 Pass STSO-1 099 07/01/06 Co-57 784.90 +/- 3.80 676.33 473.43 -879.23 Pass STSO-1 099 07/01/06 Co-60 2.10 +/- 0.90 1.98 0.00. -5.00 Pass STSO-1 099 07/01/06 Cs-1 34 500.70 +/- 7.40 452.13 316.49 -587.77 Pass STSO-1 099 07/01/06 Cs-I 37 624.20 +/- 4.90 525.73 368.01 -683.45 Pass STSO-1 099 07/01/06 K-40 701.30 +/- 3.40 604.00 423.00 -785.00 Pass STSO-1099 07/01/06 Mn-54 699.20 +/- 5.20 594.25 415.98 -772.52 Pass STSO-1 099 07/01/06 Ni-63 614.40 +/- 17.10 672.30 470.60 -874.00 Pass STSO-1099 07/01/06 Pu-238 79.90 +/- 5.80 82.00 57.00 -107.00 Pass STSO-1099 07/01/06 Pu-239/40 < 0.70 0.00 Pass STSO-1099 07/01/06 U-233/4 150.50 +/- 5.90 152.44 106.71 -198.17 Pass STSO-1 099 07/01/06 U-238 151.60 +/- 6.00 158.73 111.11 -206.35 Pass STSO-1099 07/01/06 Zn-65 1021.90 +/- 9.20 903.61 632.53 -1175.00 Pass STAP-1100 07/01/06 Am-241 0.16 +/- 0.03 0.14 0.10 -0.19 Pass STAP-1 100 07/01/06 Co-57 2.17 +/- 0.06 2.58 1.81 -3.36 Pass STAP-1100 07/01/06 Co-60 1.38 +/- 0.07 1.58 1.10 -2.05 Pass STAP- 1100 07/01/06 Cs-134 2.52 +/- 0.13 3.15 2.20 -4.09 Pass A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP-1 100 07/01/06 Cs-137 1.64 +/- 0.08 1.81 1.26 - 2.35 Pass STAP-I 100 07/01/06 Mn-54 1.76 +/- 0.18 1.92 1.34 -.2.50 Pass STAP-1100 07/01/06 Pu-238 0.09 +/- 0.02 0.12 0.08 -0.15 Pass STAP-1 100 07/01/06 Sr-90 0.66 +/- 0.21 0.62 0.43 - 0.81 Pass STAP-1100 07/01/06 U-233/4 0.15 +/- 0.02 0.13 0.09 -0.17 Pass STAP-1100 07/01/06 U-238 0.13 +/- 0.02 0.14 0.10 -0.18 Pass STAP-1100 07/01/06 Zn-65 < 0.07 0.00 Pass STAP-1101 07/01/06 Gr. Alpha 0.08 +/- 0.03 0.29 0.00 - 0.58 Pass STAP-1101 07/01/06 Gr. Beta 0.41 +/- 0.05 0.36 0.18 -0.54 Pass STW-1 102 07/01/06 Gr. Alpha 0.76 +/- 0.07 1.03 0.00 - 2.07 Pass STW-1 102 07/01/06 Gr. Beta 1.23 +/- 0.06 1.03 0.52 -1.54 Pass STW-1103 07/01/06 Am-241 1.86 +/- 0.09 2.31 1.62 -3.00 Pass STW-1103 07/01/06 Co-57 224.10 +/- 1.20 213.08 149.16 -277.00 Pass STW-1103 07/01/06 Co-60 49.40 +/- 0.50 47.50 33.20 -61.80 Pass STW-1 103 07/01/06 Cs-134 112.70 +/- 0.90 112.82 .78.97 - 146.66 Pass STW-1 103 07/01/06 Cs-137 206.60 +/- 1.40 196.14 137.30 -254.98 Pass STW-1103 07/01/06 Fe-55 138.40 +/- 5.40 165.40 115.80 -215.00 Pass STW-1 103 07/01/06 H-3 446.50 +/- 11.80 428.85 300.20 - 557.50 Pass STW-1103 e 07/01/06 Mn-54 < 0.30 0.00 Pass STW-1 103 07/01/06 Ni-63 116.70 +/- 3.60 118.62 83.03 - 154.21 Pass STW-1103 07/01/06 Pu-238 1.27 +/- 0.07 1.39 0.97 - 1.81 Pass STW-1 103 07/01/06 Pu-239/40 1.67 +/- 0.08 1.94 1.36 -2.52 Pass STW-1103 07/01/06 Sr-90 16.40 +/- 1.90 15.69 10.98 -20.40 Pass STW-1 103 07/01/06 Tc-99 29.40 +/- 1.10 27.15 19.00 - 35.29 Pass STW-1 103 07/01/06 U-233/4 1.97 +/- 0.08 2.15 1.50 -2.80 Pass STW-1103 07/01/06 U-238 1.97 +/- 0.08 2.22 1.55 - 2.89 Pass STW-1 103 07/01/06 Zn-65 192.50 +/- 2.40 176.37 123.46 -229.28 Pass a 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 Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
0 Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
e Included in the MAPEP as a false positive.
f Difficulties with the analyses for transuranics isotopes in solid samples (Filters, Soil and vegetation),
were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:
Pu-238, 53.1 +/- 5.3 bq/kg. Pu-239/240, 42.4 +/- 4.7 bq/kg. U-233/4, 33.3 +/- 3.5 bq/kg. U-238, 35,5 +/- 3.6 bq/kg.
9 The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.
A6-3
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data ReDortinci 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 = 2a 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 4.66a uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xi +/- s, and x2 +/- s2 Reported result: x +/- s; where x= (1/2) (x+x 2)ands= (1/2) +S 2 3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of L, and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x > L; <L otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x, x2 . . . xn are defined as follows:
xn I -x s=
x- x 2 n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the 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 permissible concentrations of radioactivity in air and water above natural a
background in unrestricted areas Air (pCi/m 3) Water (pCi/L)
-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b
Iodine-1 31 2.8 x10 -1 Cesium-137 1,000 Barium-140 8,000 Iodine-1 31 1,000 C
Potassium-40 4,000 Gross alpha 2 Gross beta 10 6
Tritium 1 x 10 a
Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
b Concentrations may be averaged over a period not greater than one year.
Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
C A natural radionuclide.
C-2
APPENDIX D Sampling Location Maps
TLD LOCATIONS
.ONE MILE RADIUS E
PLANT AREA ENLARGED PLAN ELM0 MILE RADIUS)
[NO SCALE]
MONITORING LEGEND:
) PRAIRIE ISLAND TLD POINTS
[ REV. I tM,'. TLD01.DGN
. -- A--. I1- FO - -
TLO LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS
- MONITORING LEGEND:
(0) PRAIRIE ISLAND TLO POINTS REV,,I D-3 TLD02.DGN REV. .1 TLD~2.DGN
TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
PRA]?RIE ISLAND TLD POINTS
.REV ..I D3-4 REV. 1...,.TL,-3..,
TLO003.DGN
,ENVIRONMENTAL SAMPLING PO INTS ONE MILE RADIUS PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS]
[NO SCALE]
.MONITORING., LEOGEND
. MILK SAMPLING POINT to NUMBERS FISH SAMPLING POINT ID NUMBERS P-"13,P-Iq P-4l, P-.IB P-3.7. P-42, P-43.,P-44 A.. AIR SAMPLING POINT .ID NUMBERS Pl~,: P-2, P-3, P-4,.P-6
.INVERTEBRATES POINT' I0 NUMBERS P-G, P-40 Q WATER SAMPLING POINT ID NUMBERS .SEDIMENT SAMPLING: POINT ID NUMBERS P-ig, P;4I2, P;,20 VEGETATION / VEGETABLES I NUMBERS P-24, P-36, P-45 REV. I b-5 SAMPGIýDGN b-S SA'NP01.OGN~
ENVIRONMENTAL SAMPLING POINTS
.FIVE MILE RADIUS
£ -
(~
MONITORING LEGEND S MILK SAMPLING. POINT 10 NUMBERS FISH SAMPLING POINT ID NUMBERS PI4, P-18. P-37, P-42,?P-43. P-144 :P-1O,.P-Iq AIR SAMPLING POINT IO NUMBERS INVERTEBRATESPOINT ID NUMBERS P-1 P-2.
. P13..P-4. P6' P-6, P-40 WATER SAMPLING POINT 40: NUMBERS SEDIMENT .SAMPL-ING POINT ID NUMBERS
,S.P-B., P8,d P-q, R-11. P-24. P-43 P-BG,.P.12. P-2B VEGETATION / VEGETABLES .1. NUMBERS no P-24, P,'381 P-45 REVý 1: 5AMP0.3,DGN REV.1 S~MP~3.DGN
ENVIRONMENTAL SAMPLING POINTS
(*)(> P-41, Huppert Farm, W10430 St Rd 29, River Falls, WI P.43, Peterson Farm, W10322 St Rd 29, River Falls, WI EJ P.38, Cain Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND
< MILK SAMPLING POINT ID NUMBERS P-14, P-48, P-37, P.41, P-42, P.43, P-44 A AIR SAMPLING POINT ID NUMBERS P-I, P-2, P-3, P-4, P-6 WATER SAMPLING POINT IDNUMBERS P4, P.6, P.8, P-9, P11, P.43 El VEGETATION I VEGETABLES IDNUMBERS P-24, P-38, P.45 0-7
APPENDIX E Special Well and Surface Water Samples E-1
1.0 INTRODUCTION
This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2006. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.
Tabulations of the special sampling program individual analyses made during the year are included in this appendix. A summary table of tritium analyses is also included in this appendix.
E-2
2.0
SUMMARY
This special sampling program was established following the detection of tritium in a residence well water sample south of the PINGP during 1989. This program is described and the results for 2006 are summarized and discussed.
Program findings for 2006 detect low levels of tritium in nearby residence wells and ground water surface samples at or near the expected natural background levels with the exception of sample well P-10. The 2006 sample results ranged from <19 pCi/L to 107 pCi/L and sample well P-10 ranged from 432 pCi/L to 3773 pCi/L. All tritium results are far below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to any members of the public.
E-3
3.0 Special Tritium Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to assess the impact of any tritium leaching into .the environment (ground water system) from the PINGP. For this purpose, special water samples are collected and analyzed for tritium content.
3.2 Program Description The sampling and analysis schedule for the special water sampling program is summarized in Table 4.1 and briefly reviewed below. Table 4.2 defines the additional sample locations and codes for the special water sampling program.
Special well and surface water samples were collected quarterly at one location, quarterly at three locations up to September, 2006 when the frequency was changed to monthly for these three locations, and annually at thirty-one locations. The Peterson (P-43) and Hanson farm wells are used as control locations for these special samples.
To detect low levels of tritium at or below natural background levels, analyses of the samples have been contracted to a laboratory (University of Waterloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. Waterloo Laboratories report tritium analyses results in Tritium Units (1 TU = 3.2 pCi/L). The tritium results in this report are indicated in pCi/L.
3.3 Program Execution The special water sampling was executed as described inthe preceding section.
3.4 Program Modifications The only change to the program in 2006 was the change in sampling frequency from quarterly to monthly for sample well P-10 and the two control wells.
3.5 Results and Discussion Results obtained show tritium in well water and ground water samples at or near expected natural background levels, except for the P-10 sample well. Table 4.4 provides the complete data table of results for each period and sampling location.
The tritium level annual averages have shown a downward trend since the special sampling begun in 1989.
E-4
Results and Discussion (continued)
Except for sample well P-10, the 2006 sample results are within the range of expected background tritium levels in shallow ground water and surface water, due to tritium concentrations measured in precipitation. Sampling points in North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No. 10; World Survey of Isotope Concentration in Precipitation (1988-1991)).
The higher level results at Suter and Birch Lake in 1989 were possibly due to seepage from the PINGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River and the discharge canal. The Suter residence is located between the discharge canal and Birch Lake, which connects to the Vermillion River. The PINGP discharge canal piping was lengthened during 1991, so that liquid discharges from the plant are released near the end of the discharge canal, diffused and discharged to the Mississippi River. In 1992, the underground liquid discharge pipe from the plant to the discharge canal piping was replaced with a double walled leak detectable piping system. This year's sample results continue to indicate that these modifications have eliminated the suspected radioactive effluent flow into the local ground water.
E-5
Table E-4.1 Sample collection and analysis program for special well and surface water samples, Prairie Island Nuclear Generating Plant, 2006.
Medium No. Location codes Collection type Analysis typeC a b and type and frequency P-8, REMP P-6, PIIC-02, PIIC-22, PIIC-26, P-2, P-3, P-4, P-5, P-6, P-7, Well water 26 P-11, PZ-1, PZ-2, PZ- G/A H-3 3, PZ-4, PZ-5, PZ-7, PZ-8, MW-4, MW-5, MW-6, P-26, P-30, SW-2, SW-3, P-9 Well water 1 P-24D G/Q H-3 Well water 3 P-43(C), SW-1(C), G/M dH-3 P-10G Surface water 5 S-1, S-2, S-3, S-4, S-5 G/A H-3 a
Location codes are defined in table D-4.2. Control Station are indicated by (C). All other stations are indicators.
b Collection type is codes as follows: G/ = grab. Collection frequency is coded as follows: M = monthly; Q = quarterly; A =
annually.
C Analysis type is coded as follows: H-3 = tritium.
d The frequency changed for these three locations from quarterly to monthly starting in September, 2006.
E-6
Table E-4.2. Sampling locations for special well and surface water samples, PINGP, 2006.
Code Collection site Sample type a Distance and direction from reactor P-8 PI Community well WW 1.0 mi. @ 321 °/WNW REMP P-6 Lock & Dam #3 well WW 1.6 mi. @ 129°/SE PIIC-02 2077 Other Day Road WW 1.4 mi. @ 315°/NW PIIC-22 1773 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-26 1771 Buffalo Slough Rd WW 1 mi. @ 315°/NW P-24D Suter residence WW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control) WW 13.9 mi. @ 355°/N SW-1 Hanson Farm (Control) WW 2.2 mi. @ 315°/NW P-2 Sample well WW See map P-3 Sample well WW See map P-4 Sample well WW See map P-5 Sample well WW See map P-6 Sample well WW See map P-7 Sample well WW See map P-10 Sample well WW See map P-11 Sample well WW See map PZ-1 Sample well WW See map PZ-2 Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW-4 Sample well WW See map MW-5 Sample well WW See map MW-6 Sample well WW See map P-26 PITC well WW 0.4 mi. @ 258°/WSW P-30 Environ lab well WW 0.2 mi. @ 32°/NNE SW-2 STA House WW See map SW-3 Cooling Tower pump WW See map P-9 Plant well # 2 WW 0.3 mi. @ 306°/NW S-1 Mississippi River SW See map upstream S-2 Recirculation/Intake SW See map canal S-3 Cooling water canal SW See map S-4 Discharge Canal (end) SW See map S-5 Discharge Canal SW See map (midway) a Sample codes: WW = Well water; SW = Surface Water.
E-7
Figure E-1. Onsite Tritium Sampling Well Locations Pkuoni92.atp E-8
Table E-4.3 Radiation Environmental Monitoring Program Summary: Special well and surface water samples.
Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January - December 2006 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Semi-Annual Mean Locations Non-Type Number of LLDb Mean (F) d Mean (F) Mean (F)c Routine (Units) Analyses " Rangec Location Range Range Resultse Offsite H-3 23 19 60 (7/9) PIIC-22 102 (1/1) 32 (3/14) 0 Well Water (26-102) (102) (22-45)
(pCi/L)
Onsite H-3 42 19 625 (22/28) P-10 1837 (7/7) 32 (3/14) 7 Well Water (33-3773) (432-3773) (22-45)
(pCi/L)
Onsite H-3 19 19 36 (2/5) Recirc/intake 42 (1/1) 32 (3/14) 0 Surface Water (30-42) canal (42) (22-45)
LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and code (Table 2) and (2) by distance, direction and sector relative to reactor site.
e Non-routine results are those which exceed ten times the control station value.
E-9
Table E-4.4 Radiological Environmental Monitoring Program , Complete Data Table, 2006.
SAMPLE DATES JAN APR JUL SEP OCT NOV DEC 2006 2006 2006 2006 2006 2006 2006 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L OFFSITE WELLS P-8 PI Community well <19 REMP P-6 Lock & Dam #3 well <19 PIIC-02 2077 Other Day Road 43 PIIC-22 1773 Buffalo Slough Rd 102 PIIC-26 1771 Buffalo Slough Rd 76 P-24D Suter residence 84 26 48 44 P-43 Peterson Farm (C) 29 45 <19 <19 <19 <19 <19 SW-1 Hanson Farm (C) <19 <19 <19 <19 <19 22 <19 ONSITE WELLS P-2 Sample well 107 P-3 Sample well 59 P-4 Sample well 93 P-5 Sample well 70 P-6 Sample well 35 P-7 Sample well 46 P-10 Sample well 931 432 2876 3773 2588 1568 692 P-11 Sample well 53 PZ-1 Sample well <19 PZ-2 Sample well <19 PZ-4 Sample well 73 PZ-5 Sample well 35 E-10
Table E-4.4 Radiological Environmental Monitoring Program , Complete Data Table, 2006, (continued).
SAMPLE DATES JAN APR JUL SEP OCT NOV DEC 2006 2006 2006 2006 2006 2006 2006 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE WELLS PZ-7 Sample well 50 PZ-8 Sample well <19 MW-4 Sample well <19 MW-5 Sample well 87 MW-6 Sample well 33 P-26 PITC well 65 P-30 Environ lab well <19 SW-2 STA House 44 SW-3 Cooling Tower pump 42 P-9 Plant well # 2 <19 ONSITE SURFACE WATER Mississippi River S-1 upstream <1.9 Recirculation/Intake S-2 canal 42 S-3 Cooling water canal <19 S-4 Discharge Canal (end) <19 Discharge Canal S-5 (midway) 30 E-11