ML13133A247
| ML13133A247 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/2012 |
| From: | Environmental |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13133A247 (73) | |
Text
- WATI Environmental, Inc.
700 Landwehr Road - Northbrookc, IL 60062-2310 phone (847) 564-0700 - fox (8471 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2012 Docket No. 50-282 50-306 ISFSI Docket No.72-10 License No. DPR-42 DPR-60 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.
MIDWEST LABORATORY Project No. 8010 Approved:
B ni Grob, M.S.
Lab a ory 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 Northern States Power Co. -Minnesota, for XCEL Energy Corporation.
The report was prepared by Environmental, Inc., Midwest Laboratory.
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TABLE OF CONTENTS Section Page Preface....................................................................................................................................................
ii List of Tables..........................................................................................................................................
iv List of Figures..........................................................................................................................................
v
1.0 INTRODUCTION
1 2.0 SUM MARY..............................................................................................................................................
2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)........................................
3 3.1 Program Design and Data Interpretation..................................................................................
3 3.2 Program Description......................................................................................................................
4 3.3 Program Execution........................................................................................................................
5 3.4 Laboratory Procedures.........................................................................................................
6 3.5 Program M odifications...................................................................................................................
6 3.6 Land Use Census..........................................................................................................................
6 4.0 RESULTS AND DISCUSSIO N.........................................................................................................
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..........................................................................................................................
24 APPENDICES A
Interlaboratory Com parison Program Results.................................................................................
A-1 Attachm ent A, 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 Background in Unrestricted Areas...................................................................................
C-1 D
Sam pling Location M aps.....................................................................................................................
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 Sampling Locations...................................................................................................................................
16 5.3 Missed Collections and Analyses........................................................................................................
19 5.4 Radiological 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.............................................
A -I A-2 Program Results; (TLDs)......................................................................................................................
A2-1 A-3 In-house "Spiked" Samples..................................................................................................................
A3-1 A-4 In-house "Blank" Samples.....................................................................................................................
A4-1 A-5 In-house "Duplicate" Samples........................................................................................................
A5-1 A-6 Department of Energy MAPEP comparison results......................................................................
A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement)......... A7-1 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-5 E-4.2 Sampling locations.................................................................................................................................
E-6 E-4.3 REMP Summary.....................................................................................................................................
E-8 E-4.4 REMP Complete Data Tables.................................................................................................................
E-9 E-4.5 Supplementary Data Tables...................................................................................................................
E-1 3 iv
LIST OF FIGURES No.
Title Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control..............................................................................................................................
13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i)................................................................................
14 MAPS Appendix D Title Page TLD locations within a one m ile radius.....................................................................................................
D-2 TLD locations, Controls..............................................................................................................................
D-3 TLD locations, surrounding the ISFSI Area................................................................................................
D-3 TLD locations within a five m ile radius.....................................................................................................
D-4 REM P sam pling points within a one m ile radius......................................................................................
D-5 REM P sam pling points within a five m ile radius.......................................................................................
D-6 REM P sam pling points, Control locations...............................................................................................
D-7 Appendix E Groundwater M onitoring W ell locations..................................................................................................
E-14 v
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiological 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, 2012. 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, 2013b) 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 Northern States Power Co.-Minnesota. 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 Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Offsite Dose Calculation Manual for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
Results for 2012 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 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological 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 radiological 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, 2012). Maps of fixed sampling locations are included in Appendix D.
To monitor the airborne environment, air is sampled by continuous pumping at five stations, three site boundary indicators (P-2, P-3, and P-4), located in the highest calculated D/Q sectors, one community indicator (P-6), and one control (P-I). The particulates are collected on membrane filters, airborne iodine is trapped by activated charcoal. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are analyzed for gamma emitting isotopes.
Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant.
They are replaced and measured quarterly.
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 three farms (two indicators 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 Program Description (continued)
Drinking water is collected weekly from the City of Red Wing well.
Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes.
Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) Airborne Particulates / Airborne Iodine:
No air particulate / air iodine sample was available from location P-01 for the week ending May 16, 2012. There was no power to the sampler, due to an open fuse. The sampler pump was replaced.
A partial sample was collected from location P-04 for the week ending 8/22/12. Sampler run-time was reduced by approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> due to a tripped breaker.
Air samples were not collected from the site boundary location of the highest calculated annual average ground level D/Q during 2012. The annual average ground level D/Q values were updated during 2011 for the station and the west sector became the new highest D/Q location. The second and third highest sectors were sampled with the current REMP air sample stations.
(2) Thermoluminescent Dosimeters:
The TLD for location PI-08B was missing in the field for the third quarter, 2012.
Deviations from the program are summarized in Table 5.3.
5
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, 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, 2012). 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 program modifications in 2012.
3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May I 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 radiological 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 radiological environmental monitoring program should sampling locations change within the 5 mile radius from the plant.
The Land Use Census was completed in October, 2012. There were no changes to any of the highest D/Q locations for nearest milk animal, garden sites, or nearest residence.
No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant.
Therefore, no corn samples were collected for analysis.
6
4.0 RESULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3.
The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2012. The Fukushima Daiichi nuclear accident occurred March 11, 2011.
There were no reported atmospheric nuclear tests in 2012. The last reported test was conducted on October 16, 1980 by the People's Republic of China.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/ m3 to 1,020 pCi/m 3, 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 pre-operational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m 3.
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-1 37, 1-131, and Sr-90 were detected. Cs-1 37 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-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 measure below a detection limit of approximately 160 pCi/L. 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.
7
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 16.2 mR/91 days at inner ring locations to 16.7 mR/91 days at outer ring locations.
The mean at special interest locations was 15.6 mR/91 days and 16.2 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 1997 through 2011. 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 Rings)
Control Year Outer Rings)
Control 1997 15.1 16.0 2005 16.8 16.3 1998 16.7 17.3 2006 16.6 16.6 1999 16.6 17.5 2007 17.5 17.7 2000 17.0 17.1 2008 16.9 17.1 2001 16.8 17.2 2009 15.9 16.3 2002 17.4 16.9 2010 16.0 16.0 2003 16.2 16.0 2011 15.7 15.7 2004 17.6 17.6 2012 16.5 16.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mRJ91 days).
ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates averaged 100.7 mR/91 days inside the ISFSI earth berm and 19.9 mR/91 days outside the ISFSI earth berm. No additional casks were placed on the ISFSI pad in 2012, a total of twenty-nine 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. The cumulative average of the two special Prairie Island Indian Community TLDs measured 14.9 and 14.3 mR/91 days. Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).
8
Airborne Particulates Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1996 through 2006, and also in 2008 through 2010. The elevated activity observed in 2007 was attributed to construction activity in the area, an increase in dust and consequent heavier particulate filter loading.
Average annual gross beta concentrations in airborne particulates were 0.031 pCi/m 3 at the indicators and 0.032 pCi/m 3 at the control location and similar to levels observed from 1997 through 2006 and 2008 to 2011. The results are tabulated below.
Average of Year Indicators Control Concentration (pCi/
3) 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 2007 0.037 0.031 2008 0.028 0.027 2009 0.029 0.029 2010 0.025 0.025 2011 0.026 0.027 2012 0.031 0.032 Average annual gross beta concentrations in airborne particulates.
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.077 pCi/m3 for all locations. All other isotopes were below the lower limit of detection.
There was no indication of a plant effect.
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.
9
Milk Iodine-131 results were below a detection limit of 0.5 pCi/L in all samples.
Cs-137 results were below 5 pCi/L in all samples. No other gamma-emitting isotopes, except naturally occurring potassium-40, were detected in any milk sample.
In general, radiocontaminants from cattlefeed are not found in milk, due to the selective metabolism of the cow. The common exceptions are isotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
In summary, the data for 2012 show no radiological effects of the plant operation.
Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below a detection limit of 152 pCi/L for all samples.
Gross beta concentrations averaged 11.8 pCi/L throughout the year, ranging from 7.6-14.3 pCi/L.
These concentrations are consistent with levels observed from 1997 through 2011. 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 2012 data of any effect of plant operation.
Year Gross Beta (pCi/L) 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 2007 11.6 2008 11.6 2009 11.4 2010 11.7 2011 12.4 2012 11.8 Average annual concentrations; Gross beta in drinking water.
River Water Tritium in river water samples tested measured below an LLD level of 152 pCi/L in all samples.
Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2012 show no radiological effects of the plant operation.
10
Well Water Water samples tested from the control well, P-43 (Peterson Farm) and from four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm )
showed no tritium detected above a detection limit of 152 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2012 show no radiological effects of the plant operation.
crop~s Three samples of broadleaf vegetation, cabbage leaves, were collected in July and August, 2012 and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.022 pCi/g wet weight in all samples. With exceptions for naturally-occurring beryllium-7 and 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 September, 2012 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, 2012 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes, with the exception of naturally-occurring potassium-40, were below detection limits. There was no indication of any plant effect.
Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediments were sampled in May and October, 2012 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotope detected was naturally-occurring potassium-40.
There was no indication of a plant effect.
11
5.0 FIGURES AND TABLES 12
Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.
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Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
-- Indicators (P-2,3,4,6) 0.039 0.037 0.035 0.033 0.031 0.029 0.027 E
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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)0 Frequency" Frequency' Ambient radiation (TLD's)
Airborne Particulates 54 P-OiA - P-bLA P-IB -P-i15B P-0+/-1S - P-08S P-OLIA - P-0811A P.0118B - P-081B P-01iX-P-041X, P-OIC C/Q Ambient gamma GB, GS (QC of each location) 5 P-I(C), P-2, P-3, P-4, P-6 Airborne Iodine 5
P-I(C), P-2, P-3, P-4, P-6 4
P-18, P-37, P-43 (C)
Milk c/W C/W G/M' G/W G/W 1-131 1-131, GS River water 2
P-S(C), P-6 Drinking water 1
GB(MC), 1-131(MC)
H-3, GS Well water Edible cultivated crops -
leafy green vegetables Fish (one species, edible portion)
Periphyton or invertebrates Bottom sediment Shoreline sediment 5
P-6, P-8, P-9, P-24, P-43 (C) 3 P-28, P-38(C), P-45 2
P-19(C), P-13 2
P-40(C), P-6 2
P-20(C), P-6 I
P-12 G/Q G/A G/SA G/SA G/SA G/SA GS (1-131)
GS GS GS GS 0 Location codes are defined In Table D-2. Control stations are Indicated by (C). All other stations are Indicators.
b Collection type Is coded as follows: C/ = continuous, G/ = grab. Collection frequency Is coded as follows:
W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
' Analysis type is coded as follows: GB = gross beta, GS - gamma spectroscopy, H-3 = tritium, 1-431 = 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 Code Type' Collection Site Sample Type' from Reactor P-1 P-2 P-3 P-4 P-5 P-6 P-8 P-9 P-11 P-12 P-13 P-18 P-19 P-20 P-24 P-28 P-37 P-38 P-40 P-43 P-45 C
Air Station P-i Air Station P-2 Air Station P-3 Air Station P-4 C
Upstream of Plant Lock and Dam #3 & Air Station P-6 Community Center Plant Well #2 Red Wing Service Center Downstream of Plant Downstream of Plant Christiansen Farm C
Upstream of Plant C
Upstream of Plant Suter Residence Allyn Residence Welsch Farm C
Cain Residence C
Upstream of Plant C
Peterson Farm Glazier Residence AP, Al AP, Al AP, Al AP, Al RW AP, Al, RW WW, BS, B0O*
M F'
BS WW VE M
VE B0O M, WW VE 11.8 ml @ 316°/NNW 0.5 mi @ 294"/WNW 0.8 mi @ 3i3"/NW 0.4 mi @ 359"/N 1.8 mi @ 111'/N 1.6 mi @ 129/SE 1.0 mi @ 3210/WNW 0.3 mi @ 3067/NW 3.3 ml @ 1580/SSE 3.0 mi @ 116"/ESE 3.5 mi @ 1:13°/ESE 3.8 mi @ 88'/E 1.3 mi @ O"/N 0.9 ml @ 45°/NE 0.6 mi @ 158°/SSE 1.0 mi @ 152*/SSE 4.1 mi @ 87/E 14.2 mi @ 359'/N 0.4 mi @ O'/N 13.9 mi. @ 355"/N 0.6 mi. @ 341°/NNW General Area of the Site Boundary P-OIA P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-IOA Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.4 mi @ 359"/N 0.3 mi @ 10"/N 0.5 mi @ 1830/S 0.4 mi @ 2040 /SWW 0.4 mi @ 225u/SW 0.4 mi @ 249'/WSW 0.4 mi @ 268"/W 0.4 ml @ 291°/WNW 0.7 mi @ 317o/NW 0.5 ml @ 3330 /NNW 16
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Type8 Collection Site Sample Type' from Reactor Approxlmatelv 4 to 5 miles Distant from the Plant P-O1B P-02B P-03B P-04B P-05B P-06B P-07B P-OBB P-09B P-lOB P-11B P-12B P-13B P-14B P-i5B Thomas Killian Residence Roy Kinneman Residence Wayne Anderson Farm Nelson Drive (Road)
County Road E and Coulee William Hauschiblt Residence Red Wing Public Works David Wnuk Residence Highway 19 South Cannondale Farm Wallace Weberg Farm Ray Gergen Farm Thomas O'Rourke Farm David J. Anderson Farm Hoist Farms TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.7 mi @ 355"/N 4.8 mi @ 17'/NNE 4.9 mi @ 46u/NE 4.2 mi @ 6i1/ENE 4.2 mi @ 102°/ESE 4.4 mi @ 1i2/ESE 4.7 ml @ 140"/SE 4.1 mi @ 165"/SSE 4.2 mi @ 187"/S 4.9 ml @ 200"/SSW 4.5 mi @ 22i1'/SW 4.6 ml @ 2510 /WSW 4.4 mi @ 270o/W 4.9 mi @ 306'/NW 3.8 ml @ 3450 /NNW 1.6 mi @ 129"/SE 0.5 mi @ 155"/SSE 2.2 ml @ 173"/S 2.0 mi @ 202"/SSW 2.0 mi @ 270°/W 2.5 mi @ 2990 /WNW 0.7 mi @ 271L/W 0.7 ml @ 2870 /NWW 11.1 mi @ 331"/NNW Special Interest Locations P-ois P-02S P-03S P-04S P-05S P-06S P-07S P-8SS P-01.C Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm Indian Community Indian Community C
Robert Kinneman Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD 17
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Type' Collection Site Sample Typeo from ISFSI Center.
ISFSI Area Inside Earth Berm P-OllA ISFSI Nuisance Fence TLD 190' @ 45"/NE P-021A ISFSI Nuisance Fence TLD 360' @ 82'/E P-031A ISFSI Nuisance Fence TLD 370- @ 100-/E P-041A ISFSI Nuisance Fence TLD 200' @ 134'/SE P-051A ISFSI Nuisance Fence TLD 180' @ 219'/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258"/WSW P-071A ISFSI Nuisance Fence TLD 320' @ 281"/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318"/NW P-OIIX ISFSI Nuisance Fence TLD 140' @ 1807/S P-021X ISFSI Nuisance Fence TLD 310' @ 270-/W P-031X ISFSI Nuisance Fence TLD 140' @ 0'/N P-041X ISFSI Nuisance Fence TLD 360' @ 90-/E ISFSI Area Outside Earth Berm P-OUlB ISFSI Berm Area TLD 340' @ 3u/N P-021B ISFSI Berm Area TLD 380' @ 28"/NNE P-031B ISFSI Berm Area TLD 560' @ 85°/E P-041B ISFSI Berm Area TLD 590' @ 165"/SSE P-051B ISFSI Berm Area TLD 690' @ 186°/S P-061B ISFS! Berm Area TLD 720' @ 201u/SSW P-071B ISFSI Berm Area TLD 610' @ 271"/W P-O81B ISFSI Berm Area TLD 360' @ 332-/NNW a "C" denotes control location. All other locations are Indicators.
b Sample Codes:
AP Airborne particulates F
Fish Al Airborne Iodine M
Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates)
VE Vegetation/vegetables DW Drinking water WW Well water Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
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 AP/AI Beta, 1-131 P-3 5/16/2012 No sample, due to power loss.
Replaced pump.
Sampler pump failed, open fuse.
AP/AI Beta, 1-131 P-4 8/22/2012 Partial sample due to tripped breaker. None required.
Run-time reduced by approx. 20 hrs.
AP/AI Beta, 1-131 Highest D/Q 2012 March, 2011 meteorological data Sampler to be installed sector indicated that the highest D/Q site in West sector for 2013.
was located in the West sector.
TLD Gamma PI-8B 3rd Qtr. 2012 TLD missing in the field TLD replaced.
19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota (County, State)
Docket No.
50-282, 50-306 Reporting Period January-December, 2012 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 Direct Radiation TLD (Inner Ring, Gamma 40 3.0 16.2 (40/40)
P-06A 17.7 (4/4)
(See Control 0
Area at Site (11.6-19.4) 0.4 mi @ 249* /WSW (16.5-19.4) below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma 59 3.0 16.7 (59/59)
P-12B, R. Gergen Farm.,
18.4 (4/4)
(See Control 0
4-5 mi. distant)
(12.5-20.3) 4.6 mi @ 2510 AISW (17.6-20.3) below.)
mR/91 days)
TLD (Special Gamma 32 3.0 15.6 (32/32)
P-03S, Gustafson Farm, 18.4 (4/4)
(See Control 0
Interest Areas)
(12.0-19.2) 2.2 mi @ 1730 /S (16.6-19.1) below.)
mR/91 days)
TLD (Control)
Gamma 4
3.0 None P-01C, Robert Kinneman 16.2 (4/4) 16.2 (4/4) 0 mR/91 days) 11.1 mi @ 3310 /NNW (15.4-17.0)
(15.4-17.0)
Airborne Pathway Airborne GB 259 0.005 0.031 (208/208)
P-01, Air Station 0.032 (51 /51) 0.032 (51/51) 0 Particulates (0.010-0.090) 11.8 mi @ 3160 /NNW (0.014-0.084)
(0.014-0.084)
(pCi/mi)
GS 20 Be-7 0.015 0.076 (16/16)
P-04, Air Station 0.079 (4/4) 0.078 (4/4) 0 (0.045-0.106) 0.4 mi @ 359'/N (0.045-0.106)
(0.045-0.104)
Mn-54 0.0006
< LLD LLD 0
Co-58 0.0007
< LLD
< LLD 0
Co-60 0.0009
< LLD LLD 0
Zn-65 0.0013
< LLD LLD 0
Zr-Nb-95 0.0009
< LLD LLD 0
Ru-103 0.0008
< LLD LLD 0
Ru-106 0.0068
< LLD
< LLD 0
Cs-134 0.0005
< LLD
< LLD 0
Cs-137 0.0007
< LLD
< LLD 0
Ba-La-140 0.0018
< LLD
< LLD 0
Ce-141 0.0015
< LLD
< LLD 0
Ce-144 0.0040
< LLD LLD 0
Airborne Iodine 1-131 259 0.030
< LLD LLD 0
(pCi/m3) 20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Reporting Period January-December, 2012 Location of Facility Goodhue, Minnesota
( 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)
Analyses8 Rangec Locationd Rangec Rangec Resultse Terrestrial Pathway Milk (pCi/L) 1-131 54 0.5
< LLD
< LLD 0
GS 54 K-40 200 1413 (36/36)
P-43 (C)Peterson Farm 1442 (18 /18) 1442 (18/18) 0 (1240-1536) 13.9 mi @ 355' /N (1353-1527)
(1353-1527)
Cs-134 5
< LLD LLD 0
Cs-137 5
< LLD
< LLD 0
Ba-La-140 5
< LLD
< LLD 0
Crops - Cabbage 1-131 2
0.022
< LLD
< LLD 0
(pCi/gwet)
Well Water H-3 20 152
< 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 43
< 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 Reporting Period January-December, 2012 Location of Facility Goodhue, Minnesota
( 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 Waterborne Pathway Drinking Water GB 12 1.0 11.8 (12/12)
P-11, Red Wing S.C.
11.8 (12/12)
None 0
(pCi/L)
(7.6-14.3) 3.3 mi @ 1580 /SSE (7.6-14.3) 1-131 12 1.0
< LLD None 0
H-3 4
152
< 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 39
< LLD None 0
River Water H-3 8
152
< 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 29
< LLD
< LLD 0
Fish GS 4
(pCi/g wet)
K-40 0.10 3.29 (2/2)
P-13, Downstream 3.29 (2/2) 3.07 (2/2) 0 (3.26-3.33) 3.5 mi @ 113 0/ESE (3.26-3.33)
(2.73-3.41)
Mn-54 0.021
< LLD LLD 0
Fe-59 0.11
< LLD LLD 0
Co-58 0.030
< LLD LLD 0
Co-60 0.019
< LLD LLD 0
Zn-65 0.052
< LLD
< LLD 0
Zr-Nb-95 0.066
< LLD
< LLD 0
Cs-1 34 0.016
< LLD
< LLD 0
Cs-137 0.018
< LLD
< LLD 0
Ba-La-140 0.25
< LLD
< LLD 0
22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No.
50-282, 50-306 Reporting Period January-December, 2012
( 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)
Analyses' Rangec Locationd Range' Rangec Resultse Waterborne Pathway Invertebrates GS 4
(pCi/g wet)
Be-7 0.74
< LLD
< LLD 0
K-40 0.49 1.51 (1/2)
P-06, Lock & Dam #3, 1.51 (1/2) 1.33 (1/2) 0 1.6 mi. @ 129'/SE Mn-54 0.055
< LLD
< LLD 0
Co-58 0.096
< LLD
< LLD 0
Co-60 0.069
< LLD
< LLD 0
Zn-65 0.11
< LLD
< LLD 0
Zr-Nb-95 0.23
< LLD
< LLD 0
Ru-103 0.15
< LLD
< LLD 0
Ru-106 0.46
< LLD
< LLD 0
Cs-134 0.049
< LLD
< LLD 0
Cs-1 37 0.045
< LLD
< LLD 0
Ba-La-140 1.06
< LLD
< LLD 0
Ce-141 0.37
< LLD
< LLD 0
Ce-144 0.22
< LLD
< LLD 0
Bottom and GS 6
Shoreline Be-7 0.17
< LLD
< LLD 0
Sediments (pCi/g dry)
K-40 0.10 8.91 (4/4)
P-20, Upstream 9.50 (2/2) 9.50 (2/2) 0 (8.36-9.42) 0.9 mi. @ 450 /NE (9.26-9.74)
(9.26-9.74)
Mn-54 0.017
< LLD
< LLD 0
Co-58 0.017
< LLD
< LLD 0
Co-6O 0.016
< LLD
< LLD 0
Zn-65 0.033
< LLD
< LLD 0
Zr-Nb-95 0.022
< LLD
< LLD 0
Ru-103 0.020
< LLD
< LLD 0
Ru-106 0.13
< LLD
< LLD 0
Cs-134 0.013
< LLD
< LLD 0
Cs-137 0.014
< LLD
< LLD 0
Ba-La-140 0.050
< LLD
< LLD 0
Ce-141 0.044
< LLD
< LLD 0
Ce-144 0.078
< LLD
< LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and/or station code 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 times the typical preoperational value for the medium or location.
23
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 2013a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2012.
2001b through 2013b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2012.
1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation)
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.
1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation)
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December, 1978 through 1982.
2012.
Quality Assurance Program Manual, Rev. 3, 14 November 2012.
2009.
Quality Control Procedures Manual, Rev. 2, 08 July 2009.
2009.
Quality Control Program, Rev. 2, 12 November 2009.
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.
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 2008.
Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2007.
Minneapolis, Minnesota.
Prairie Island Nuclear Generating Plant, 2012.
Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
24
6.0 REFERENCES
CITED (continued)
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).
2012.
RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981-2009.
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.
2009 to 2013.
Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012.
Minneapolis, Minnesota.
2009 to 2013.
Prairie Island Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012.
Minneapolis, Minnesota.
25
- T IEnvironmental, Inc.
Midwest Laboratory 700 Land wetv Road - Naetbroo)k IL 60062-23W.
phone (847) 564-0700
- fax (847) W64-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:
Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2012 through December, 2012
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.
Table A-2 lists 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 lists REMP specific analytical results from 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.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 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 Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.
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 ANALYSESa 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
-5 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
+ l0 =
169.85 x (known) 00 933
> 4,000 pCi/liter 10% of known value Radium-226,-228 a 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 pCi/liter Iodine-1 2 9 b
> 55 pCi/liter 10% of known value Uranium-238,
< 35 pCi/liter 6 pCi/liter Nickel-63b
> 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter
> 100 pCi/liter 10% of known value Other Analyses b 20% of known value From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004.
Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1 783 04/09/12 Sr-89 ERW-1783 04/09/12 Sr-90 ERW-1786 ERW-1786 ERW-1786 ERW-1786 ERW-1786 04/09/12 04/09/12 04/09/12 04/09/12 04/09/12 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 62.2 +/- 6.0 33.7 +/- 2.1 75.7 +/- 4.1 71.9 +/- 4.0 70.0 +/- 4.3 151.5 +/--6.1 108.3 +/- 89.0 58.5 37.4 82.3 72.9 74.2 155.0 105.0 62.9 44.2 5.7 4.6 61.5 46.9 -66.3 27.4 -43.1 69.1 - 90.5 65.6 - 82.6 60.6 -81.6 140.0 - 172.0 94.5 - 125.0 33.0 - 78.0 29.6 - 51.5 4.3 -6.9 2.7 -6.3 50.0 - 68.2 ERW-1789 04/09/12 Gr. Alpha 55.0 +/- 2.4 ERW-1789 d 04/09/12 Gr. Beta 76.2 +/- 1.8 ERW-1795 ERW-1795 ERW-1 795 04/09/12 04/09/12 04/09/12 Ra-226 Ra-228 Uranium ERW-1798 04/09/12 H-3 ERW-6283 10/05/12 Sr-89 ERW-6283 10/05/12 Sr-90 6.4 +/- 0.4 5.4 +/- 1.2 56.2 +/- 2.6 16023 +/- 355 41.5 +/- 4.1 19.7 +/- 1.6 82.7 +/- 4.4 77.2 +/- 3.7 74.4 +/- 1.5 183.0 +/- 6.2 211.0 +/- 9.9 15800 13800 -17400 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass ERW-6286 ERW-6286 ERW-6286 ERW-6286 ERW-6286 10/05/12 10/05/12 10/05/12 10/05/12 10/05/12 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 39.1 20.1 84.8 78.3 76.6 183.0 204.0 29.7 -46.1 14.4 - 23.8 71.3 -93.3 70.5 - 88.5 62.6 - 84.3 165.0 - 203.0 184.0 - 240.0 30.6 - 72.9 26.0 -46.7 20.6 - 29.4 11.2 -17.2 2.7 -6.2 50.8 - 69.3 ERW-6288 10/05/12 Gr. Alpha 47.0 +/- 2.3 ERW-6288 10/05/12 Gr. Beta 33.4 +/- 1.2 ERW-6290 10/05/12 1-131 ERW-6295 e ERW-6295 e ERW-6295 10/05/12 10/05/12 10/05/12 Ra-226 Ra-228 Uranium 23.3 +/- 1.0 17.5 +/- 0.7 7.4 +/- 1.5 61.2 +/- 1.8 58.6 39.2 24.8 15.0 4.6 62.5 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d Result of reanalysis: 38.3 +/- 1.3 pCi/L. Sample dilution problem suspected. A new dilution was prepared.
e Results of reanalyses, original submission (pCi/L): Ra-226, 16.5 +/- 0.7 Ra-228, 4.9 +/- 1.1 A new test was ordered from Environmental Resources Associates, results will be updated for first quarter, 2013.
Al-1
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value
+ 2 sigma Limits Acceptance Environmental, Inc.
2012-1 2/7/2012 30 cm.
74.87 87.22 + 2.86 52.41 - 97.33 Pass 2012-1 2/7/2012 40 cm.
42.12 53.70 +/- 4.53 29.48 - 54.76 Pass 2012-1 2/7/2012 50 cm.
26.95 33.04 +/- 1.96 18.87 - 35.04 Pass 2012-1 2/7/2012 70 cm.
13.75 13.26 +/- 1.15 9.63 - 17.88 Pass 2012-1 2/7/2012 75 cm.
11.98 13.38 +/- 1.68 8.39 -15.57 Pass 2012-1 2/7/2012 80 cm.
10.53 11.27 +/- 0.95 7.37 - 13.69 Pass 2012-1 2/7/2012 90 cm.
8.32 7.79 + 0.83 5.82 - 10.82 Pass 2012-1 2/7/2012 100 cm.
6.74 5.91 +/- 0.25 4.72 - 8.76 Pass 2012-1 2/7/2012 110 cm.
5.57 4.63 +/- 0.83 3.90 -7.24 Pass 2012-1 2/7/2012 120 cm.
4.68 3.96 +/- 1.68 3.28 -6.08 Pass 2012-1 2/7/2012 150 cm.
2.99 2.41 +/- 0.08 2.09 - 3.89 Pass 2012-1 2/7/2012 180 cm.
2.08 2.02 +/- 0.25 1.46 -2.70 Pass Environmental, Inc.
2012-2 9/11/2012 40 cm.
33.75 43.74 +/- 1.31 23.63 - 43.88 Pass 2012-2 9/11/2012 50 cm.
21.6 25.37 +/- 0.82 15.12 -28.08 Pass 2012-2 9/11/2012 60 cm.
15 16.63 +/- 0.45 10.50 - 19.50 Pass 2012-2 9/11/2012 70 cm.
11.02 10.58 +/- 0.20 7.71 -14.33 Pass 2012-2 9/11/2012 80 cm.
8.44 8.55 +/- 1.18 5.91 -10.97 Pass 2012-2 9/11/2012
.90 cm.
6.67 5.75 +/- 0.33 4.67 -8.67 Pass 2012-2 9/11/2012 100 cm.
5.4 4.44 +/- 0.22 3.78 -7.02 Pass 2012-2 9/11/2012 110 cm.
4.46 3.85 +/- 0.05 3.12 -5.80 Pass 2012-2 9/11/2012 120 cm.
3.75 3.03 +/- 0.71 2.63 -4.88 Pass 2012-2 9/11/2012 150 cm.
2.4 1.82 +/- 0.10 1.68 -3.12 Pass 2012-2 9/11/2012 180 cm.
1.67 1.19 +/- 0.34 1.17 -2.17 Pass A2-1
TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-41824 W-22712 W-22712 SPAP-1 032 SPAP-1032 SPAP-1 034 SPW-1036 SPW-1036 SPW-1036 SPMI-1 038 SPM1-1038 SPW-1045 SPW-1047 SPW-1049 W-31412 SPW-1520 SPW-41825 WW-1 547 WW-1 547 WW-1 547 W-51712 W-61112 W-61112 SPAP-4418 SPAP-4420 SPAP-4420 SPMI-4422 SPMI-4422 SPMI-4422 SPMI-4422 SPW-4424 SPW-4424 SPW-4424 SPF-4426 SPF-4426 SPW-4428 SPW-4430 SPW-4432 W-81712 SPW-5407 SPW-18022 2/15/2012 2/27/2012 2/27/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/14/2012 3/23/2012 4/10/2012 4/16/2012 4/16/2012 4/16/2012 5/17/2012 6/11/2012 6/11/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012
.7/25/2012 7/25/2012 7/25/2012 7/25/2012 8/17/2012 8/29/2012 9/10/2012 Ra-228 Gr. Alpha Gr. Alpha Cs-1 34 Cs-1 37 Gr. Beta Cs-1 34 Cs-1 37 Sr-90 Cs-1 34 Cs-137 H-3 Ni-63 C-14 Ra-226 U-238 Ra-228 Ba-1 33 Cs-1 34 Cs-137 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Sr-90 Co-60 Cs-137 Sr-90 Cs-1 34 Cs-1 37 C-14 H-3 Ni-63 Ra-226 U-238 Ra-228 24.85 +/- 2.14 14.59 +/- 0.34 43.57 +/- 0.40 7.06 +/- 1.71 102.63 +/- 3.13 44.30 +/- 0.11 43.23 +/- 3.84 57.44 +/- 4.60 60.51 +/- 1.93 37.79 +/- 4.06 54.75 +/- 5.09 68022 +/- 746 217.10 +/- 3.64 3858.90 +/- 12.79 13.13 +/-0.36 45.67 +/- 2.02 28.48 +/- 2.51 18.99 +/- 4.67 9.28 +/- 2.82 27.77 +/- 4.49 17.29 +/- 0.43 22.16 +/- 0.45 43.57 +/- 0.40 43.74 +/- 0.11 4.54 +/- 0.73 104.70 +/- 2.77 31.43 +/- 2.12 16.50 +/- 1.17 29.60 +/- 2.61 31.60 +/- 1.35 38.52 +/- 1.76 33.23 +/- 2.27 36.56 +/- 1.58 947.50 +/- 42.50 2692.00 +/- 62.40 4325.70 +/- 15.80 70119.40 +/- 773.40 187.20 +/- 3.85 14.94 +/- 0.40 42.95 +/- 0.11 29.03 +/- 2.80 28.75 20.00 41.70 5.26 104.24 46.88 39.42 52.12 61.52 39.42 52.12 69048 206.54 4738.80 16.70 41.70 28.35 26.70 8.68 29.70 16.70 20.00 45.20 46.50 4.60 103.30 31.62 16.15 26.64 30.47 37.95 32.01 40.60 1025.00 2480.00 4738.80 67570.00 206.80 16.70 41.70 28.21 20.13 -37.38 10.00 -30.00 20.85 - 62.55 0.00 -15.26 93.82 - 114.66 28.13 - 65.63 29.42 - 49.42 42.12 -62.12 49.22 - 73.82 29.42 - 49.42 42.12 -62.12 55238 - 82858 144.65 - 268.63 2843.28 - 6634.32 11.69 - 21.71 29.19 - 54.21 19.85 - 36.86 16.70 - 36.70 0.00 - 18.68 19.70 - 39.70 11.69 - 21.71 10.00 - 30.00 35.20 - 55.20 27.90 -65.10 2.76 - 6.44 92.97 - 113.63 21.62 -41.62 6.15 -26.15 16.64 -36.64 24.38 - 36.56 27.95 -47.95 22.01 -42.01 32.48 - 48.72 922.50 -1127.50 2232.00 -2728.00 2843.28 - 6634.32 54056.00 - 81084.00 144.76 - 268.84 11.69 - 21.71 29.19 - 54.21 19.75 - 36.67 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1
TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)"
Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance W-91012 W-91012 9/10/2012 Gr. Alpha 9/10/2012 Gr. Beta W-1 00312 W-1 00312 W-101812 ESO-7235 SPW-7753 SPW-18023 10/3/2012 10/3/2012 10/18/2012 12/6/2012 12/6/2012 12/18/2012 Gr. Alpha Gr. Beta Ra-226 Sr-90 U-238 Ra-228 19.95 +/- 0.42 43.47 +/- 0.40 19.95 +/- 0.41 44.21 +/- 0.40 18.80 +/- 0.43 138.79 +/- 2.67 45.55 +/- 5.05 31.59 +/- 2.99 20.00 45.20 20.00 45.20 16.70 161.05 41.70 25.98 10.00 - 30.00 35.20 - 55.20 10.00 -30.00 35.20 - 55.20 11.69 -21.71 128.84 -193.26 29.19 -54.21 18.19 -33.77 Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).
b Laboratory codes: W (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
c Results are based on single determinations.
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2 a.
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)a Lab Code Sample Date Analysisb Laboratory results (4.66a)
Acceptance Type LLD Activityc Criteria (4.66 a)
SPW-41814 Water W-22712 Water W-22712 Water SPAP-1031 Air Filter SPAP-1031 Air Filter SPAP-1033 Air Filter SPW-1035 Water SPW-1035 Water SPW-1035 Water SPW-1035 Water SPMI-1037 Milk SPMI-1037 Milk SPMI-1037 Milk SPW-1044 Water SPW-1046 Water SPW-1048 Water SPW-1166 water W-31412 Water SPW-1521 Water W-51712 Water W-61112 Water W-61112 Water SPW-41815 Water SPAP-4417 Air Filter SPMI-4421 Milk SPMI-4421 Milk SPMI-4421 Milk SPMI-4421 Milk SPW-4423 Water SPW-4423 Water SPW-4423 Water SPW-4423 water SPF-4425 Fish SPF-4425 Fish SPF-4425 Fish SPW-4427 Water SPW-4431 Water W-81712 Water SPW-5408 Water 2/15/2012 Ra-228 2/27/2012 Gr. Alpha 2/27/2012 Gr. Beta 3/5/2012 Cs-1 34 3/5/2012 Cs-1 37 3/5/2012 Gr. Beta 3/5/2012 Cs-1 34 3/5/2012 Cs-1 37 3/5/2012 1-131(G) 3/5/2012 Sr-90 3/5/2012 Cs-1 34 3/5/2012 Cs-1 37 3/5/2012 1-131(G) 3/5/2012 H-3 3/5/2012 Ni-63 3/5/2012 C-14 3/9/2012 C-14 3/14/2012 Ra-226 3/23/2012 U-238 4/24/2012 Ra-226 6/11/2012 Gr. Alpha 6/11/2012 Gr. Beta 7/712011 Ra-228 7/25/2012 Gr. Beta 7/25/2012 Co-60 7/25/2012 Cs-1 34 7/25/2012 Cs-1 37 7/25/2012 Sr-90 7/25/2012 Co-60 7/25/2012 Cs-134 7/25/2012 Cs-137 7/25/2012 Sr-90 7/25/2012 Co-60 7/25/2012 Cs-134 7/25/2012 Cs-137 7/25/2012 C-14 7/25/2012 Ni-63 8/17/2012 Ra-226 8/29/2012 U-238 0.65 0.42 0.74 1.89 1.16 0.003 2.40 2.88 2.35 0.60 2.85 3.73 3.24 146.10 19.07 5.70 6.79 0.034 0.10 0.04 0.47 0.71 0.77 0.001 4.29 3.58 4.60 0.45 1.88 2.38 2.80 0.45 6.74 7.47 9.62 10.93 19.00 0.038 0.039 0.49 +/- 0.36
-0.04 +/- 0.29
-0.54 +/- 0.50 0.013 +/- 0.003
-0.11 +/- 0.26 37.10 +/--74.40 8.30 +/- 11.79 2.99 +/- 3.04 1.11 0.043 +/- 0.027 0.09 +/- 0.11 0.04 +/- 0.03
-0.14 +/- 0.32 0.29 +/- 0.51 0.52 +/- 0.42 0.021 +/- 0.003 0.53 +/- 0.27 0.08 +/- 0.22 3.54 +/- 5.84 5.50 +/- 11.70 0.035 +/- 0.030 0.015 +/- 0.057 2
1 3.2 100 100 0.01 10 10 20 1
10 10 20 200 20 200 200 1
3.2 2
0.01 10 10 10 1
10 10 10 1
100 100 100 200 20 1
1 A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis' Laboratory results (4.66a)
Acceptance Type LLD Activityc Criteria (4.66 o)
SPW-18032 Water 9/10/2012 Ra-228 0.78 0.85 +/- 0.46 2
W-91012 Water 9/10/2012 Gr. Alpha 0.42 0.027 +/- 0.29 1
W-91012 Water 9/10/2012 Gr. Beta 0.75
-0.13 +/- 0.52 3.2 W-100312 Water 10/3/2012 Gr. Beta 0.77
-0.32 +/- 0.53 3.2 W-100312 Water 10/3/2012 Gr. Beta 0.43 0.06 +/- 0.30 3.2 W-101812 Water 10/18/2012 Ra-226 0.04 0.038 +/- 0.031 1
SPW-7754 Water 12/6/2012 U-238 0.10 0.022 +/- 0.075 1
SPW-18033 Water 12/18/2012 Ra-228 0.98 0.43 +/- 0.50 2
a Liquid sample results are reported in pCi/Liter, air filters( pCilfilter), 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.
A4-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 CF-20, 21 CF-20, 21 P-9133, 9134 U-302, 303 S-386, 387 S-386, 387 S-386, 387 S-386, 387 S-386, 387 WW-619, 620 MI-702, 703 WW-892, 893 S-850, 851 S-850, 851 W-1251, 1252 W-1251, 1252 W-1251, 1252 W-1251, 1252 AP-1209, 1210 XWW-1564, 1565 SG-1438, 1439 SG-1438, 1439 WW-1585, 1586 AP-2103, 2104 AP-2166, 2167 AP-1632, 1633 E-1 653, 1654 E-1653, 1654 SG-1677, 1678 SG-1677, 1678 SWU-1719, 1720 W-1698, 1699 W-1698, 1699 W-1698, 1699 SG-1761, 1762 SG-1761, 1762 AP-2019, 2020 DW-2272, 2273 DW-2356, 2357 1/3/2012 1/3/2012 1/3/2012 1/3/2012 1/17/2012 1/23/2012 1/23/2012 1/23/2012 1/23/2012 1/23/2012 1/31/2012 2/6/2012 2/17/2012 2/22/2012 2/22/2012 3/6/2012 3/6/2012 3/6/2012 3/6/2012 3/8/2012 3/14/2012 3/19/2012 3/19/2012 3/19/2012 3/28/2012 3/28/2012 3/29/2012 4/2/2012 4/2/2012 4/2/2012 4/2/2012 4/3/2012 4/5/2012 4/5/2012 4/5/2012 4/10/2012 4/10/2012 4/12/2012 4/20/2012 4/24/2012 Gr. Beta K-40 Sr-90 H-3 Beta (-K40)
Ac-228 Bi-214 Pb-214 TI-208 U-235 H-3 K-40 Gr. Beta Cs-1 34 Cs-1 37 Gr. Alpha Gr. Beta H-3 Tc-99 Be-7 H-3 Ac-228 Pb-214 H-3 Be-7 Be-7 Be-7 14.50 +/- 0.29 12.88 +/- 0.55 0.01 +/- 0.01 108.86 +/- 83.03 6.84 +/- 2.91 0.77 +/- 0.11 0.80 +/- 0.07 0.74 +/- 0.06 0.21 +/- 0.02 0.05 +/- 0.02 257.20 +/- 86.00 1337.00 +/- 123.00 3.46 +/- 0.56 0.14 +/- 0.02 0.21 +/- 0.03 1.20 +/- 0.62 16.86 +/- 1.43 5235.52 +/- 230.91 19.67 +/- 3.60 0.24 +/- 0.12 308.00 +/- 88.00 6.01 +/- 0.30 4.69 +/- 0.49 3124.50 +/- 176.96 0.080 +/- 0.016 0.061 +/- 0.020 0.26 +/- 0.12 15.02 +/- 0.30 12.40 +/- 0.53 0.01 +/- 0.01 206.60 +/- 86.38 5.24 +/- 2.56 0.79 +/- 0.14 0.73 +/- 0.11 0.75 +/- 0.11 0.21 +/- 0.04 0.12 +/- 0.05 305.80 +/- 88.30 1460.40 +/- 102.00 3.77 +/- 0.59 0.13 +/- 0.02 0.22 +/- 0.03 1.27 +/- 0.92 15.14 +/- 1.34 4893.24 +/- 224.55 14.46 +/- 3.51 0.20 +/- 0.11 293.00 +/- 87.00 6.23 +/- 0.31 5.20 +/- 0.54 2982.38 +/- 173.62 0.076 +/- 0.013 0.071 +/- 0.016 0.24 +/- 0.12 14.76 +/- 0.21 12.64 +/- 0.38 0.01 +/- 0.00 157.73 +/- 59.91 6.04 +/- 1.94 0.78 +/- 0.09 0.77 +/- 0.07 0.75 +/- 0.06 0.21 +/- 0.02 0.09 +/- 0.03 281.50 +/- 61.63 1398.70 +/- 79.90 3.61 +/- 0.41 0.14 +/- 0.01 0.22 +/- 0.02 1.24 +/- 0.55 16.00 +/- 0.98 5064.38 +/- 161.05 17.07 +/- 2.51 0.22 +/- 0.08 300.50 +/- 61.87 6.12 +/- 0.22 4.95 +/- 0.36 3053.44 +/- 123.96 0.078 +/- 0.010 0.066 +/- 0.013 0.25 +/- 0.08 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Gr. Beta K-40 Ac-228 Pb-214 Gr. Beta Gr. Beta Ra-226 Ra-228 Ac-228 Pb-214 Be-7 1-131 Gr. Beta 1.53 +/- 0.05 1.34 +/- 0.13 6.63 +/- 0.37 4.77 +/- 0.16 1.16 +/- 0.41 10.86 +/- 1.49 0.41 +/- 0.15 1.46 +/- 0.76 16.26 +/- 0.53 14.16 +/- 1.44 0.17 +/- 0.10 0.52 +/- 0.24 12.82 +/- 2.01 1.55 +/- 0.04 1.36 +/- 0.14 6.49 +/- 0.33 5.07 +/- 0.14 1.53 +/- 0.44 9.42 +/- 1.32 0.67 +/- 0.18 1.48 +/- 0.74 16.55 +/- 0.44 15.40 +/- 1.56 0.17 +/- 0.08 0.49 +/- 0.27 9.47 +/- 1.74 1.54 +/- 0.03 1.35 +/- 0.10 6.56 +/- 0.25 4.92 +/- 0.11 1.35 +/- 0.30 10.14 +/- 1.00 0.54 +/- 0.12 1.47 +/- 0.53 16.41 +/- 0.34 14.78 +/- 1.06 0.17 +/- 0.07 0.51 +/- 0.18 11.14 +/- 1.33 A5-11
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-2403, 2404 G-2403, 2404 BS-2445, 2446 BS-2445, 2446 SWU-2550, 2551 WW-2614, 2615 WW-2614, 2615 BS-2656, 2657 BS-2656, 2657 SO-2635, 2636 SO-2635, 2636 MI-2677, 2678 VE-2719, 2720 SWU-3221, 3222 SWU-3221, 3222 WW-3073, 3074 AP-2968, 2969 F-3031, 3032 F-3031, 3032 G-3094, 3095 F-3412, 3413 F-3412, 3413 MI-3067, 3068 SO-3305, 3306 SO-3305, 3306 SO-3305, 3306 LW-3454, 3455 BS-3697, 3698 BS-3697, 3698 BS-3697, 3698 VE-3798, 3799 WW-4790, 4791 DW-30103, 30104 DW-30103, 30104 LW-3970, 3971 DW-3949, 3950 SG-4075, 4076 SG-4075, 4076 SG-4075, 4076 AP-4390, 4391 AP-4390, 4391 AP-4012, 4013 SW-4033, 4034 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/2/2012 5/2/2012 5/3/2012 5/3/2012 5/7/2012 5/7/2012 5/8/2012 5/8/2012 5/14/2012 5/17/2012 5/22/2012 5/22/2012 5/23/2012 5/23/2012 5/23/2012 5/24/2012 5/30/2012 5/30/2012 5/30/2012 5/31/2012 6/14/2012 6/14/2012 6/14/2012 6/20/2012 6/20/2012 6/27/2012 6/27/2012 6/28/2012 6/29/2012 7/2/2012 7/2/2012 7/2/2012 7/3/2012 7/3/2012 7/5/2012 7/5/2012 Be-7 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta H-3 Cs-1 37 K-40 Cs-1 37 K-40 K-40 K-40 Gr. Beta H-3 H-3 Be-7 H-3 K-40 Gr. Beta Gr. Beta K-40 K-40 Cs-1 37 Gr. Beta TI-208 Gr. Beta Be-7 Cs-1 37 K-40 K-40 H-3 Ra-226 Ra-228 Gr. Beta 1-131 Ac-228 K-40 Pb-214 Be-7 Be-7 Be-7 H-3 1.77 +/- 0.21 6.38 +/- 0.50 8.92 +/- 1.52 5.86 +/- 0.38 2.07 +/- 0.65 2.03 +/- 1.04 750.60 +/- 106.20 0.13 +/- 0.07 10.15 +/- 0.97 0.046 +/- 0.024 13.20 +/- 0.74 1415.30 +/- 131.40 4.15 +/- 0.36 1.67 +/- 0.47 236.90 +/- 101.90 339.12 +/- 145.45 0.25 +/- 0.12 11291.00 +/- 372.80 3528.90 +/- 372.80 7.89 +/- 0.16 3.46 +/- 0.10 2.40 +/- 0.38 1267.20 +/- 105.00 0.024 +/- 0.013 10.95 +/- 0.89 0.068 +/- 0.018 2.12 +/- 0.86 2.05 +/- 0.19 2.32 +/- 0.39 6.67 +/- 0.28 5.93 +/- 0.38 251.33 +/- 86.51 0.30 +/- 0.08 0.76 +/- 0.54 1.49 +/- 1.06 0.54 +/- 0.26 0.33 +/- 0.09 6.71 +/- 0.58 0.46 +/- 0.05 0.09 +/- 0.02 0.11 +/- 0.02 0.27 +/- 0.09 614.99 +/- 107.99 1.55 +/- 0.33 6.93 +/- 0.72 9.29 +/- 1.63 6.22 +/- 0.48 1.59 +/- 0.62 2.36 +/- 1.14 653.20 +/- 102.30 0.07 +/- 0.04 11.13 +/- 0.90 0.050 +/- 0.027 14.01 +/- 0.67 1348.10 +/- 109.00 4.19 +/- 0.38 1.39 +/- 0.45 281.90 +/- 103.70 337.23 +/- 98.19 0.21 +/- 0.09 11167.00 +/- 315.00 3677.20 +/- 392.40 8.01 +/- 0.16 3.33 +/- 0.10 2.55 +/- 0.43 1305.70 +/- 109.80 0.030 +/- 0.015 10.86 +/- 0.89 0.062 +/- 0.017 2.27 +/- 0.77 2.27 +/- 0.38 2.26 +/- 0.66 6.64 +/- 0.42 6.03 +/- 0.37 372.48 +/- 92.27 0.42 +/- 0.09 0.78 +/- 0.54 0.72 +/- 0.53 0.25 +/- 0.26 0.34 +/- 0.06 7.20 +/- 0.32 0.49 +/- 0.03 0.09 +/- 0.01 0.10 +/- 0.01 0.29 +/- 0.16 512.31 +/- 103.83 1.66 +/- 0.20 6.66 +/- 0.44 9.11 +/- 1.11 6.04 +/- 0.31 1.83 +/- 0.45 2.20 +/- 0.77 701.90 +/- 73.73 0.10 +/- 0.04 10.64 +/- 0.66 0.048 +/- 0.018 13.61 +/- 0.50 1381.70 +/- 85.36 4.17 +/- 0.26 1.53 +/- 0.33 259.40 +/- 72.69 338.18 +/- 87.74 0.23 +/- 0.07 11229.00 +/- 244.03 3603.05 +/- 270.63 7.95 +/- 0.11 3.40 +/- 0.07 2.48 +/- 0.29 1286.45 +/- 75.96 0.027 +/- 0.010 10.91 +/- 0.63 0.065 +/- 0.012 2.20 +/- 0.58 2.16 +/- 0.21 2.29 +/- 0.38 6.66 +/- 0.25 5.98 +/- 0.26 311.90 +/- 63.24 0.36 +/- 0.06 0.77 +/- 0.38 1.11 +/-0.59 0.40 +/- 0.18 0.34 +/- 0.05 6.96 +/- 0.33 0.48 +/- 0.03 0.09 +/- 0.01 0.11 +/- 0.01 0.28 +/- 0.09 563.65 +/- 74.91 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4054, 4055 VE-4222, 4223 VE-4222, 4223 DW-30113, 30114 DW-30115, 30116 DW-30124, 30125 DW-30124, 30125 DW-30126, 30127 AP-4433, 4434 SG-4475, 4476 SG-4475, 4476 WW-4685, 4686 AP-4706, 4707 SO-4748, 4749 SO-4748, 4749 SO-4748, 4749 VE-4832, 4833 DW-30149, 30150 DW-30149, 30150 SG-4916, 4917 SG-4916, 4917 F-5313, 5314 F-5313, 5314 F-5313, 5314 VE-5166, 5167 VE-5376, 5377 VE-5334, 5335 VE-5481, 5482 VE-5481, 5482 VE-5481, 5482 DW-30164, 30165 DW-30164, 30165 VE-5166, 5167 ME-5607, 5608 ME-5607, 5608 SW-5901, 5902 BS-6048, 6049 AP-6482, 6483 7/9/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/19/2012 7/19/2012 7/19/2012 7/24/2012 7/26/2012 7/26/2012 7/26/2012 7/26/2012 8/1/2012 8/1/2012 8/1/2012 8/3/2012 8/3/2012 8/9/2012 8/9/2012 8/9/2012 8/15/2012 8/22/2012 8/27/2012 8/28/2012 8/28/2012 8/28/2012 8/30/2012 8/30/2012 9/4/2012 9/4/2012 9/4/2012 9/17/2012 9/24/2012 9/27/2012 K-40 Be-7 K-40 Ra-228 Gr. Alpha Ra-226 Ra-228 Gr. Alpha Be-7 Gr. Alpha Gr. Beta H-3 Be-7 Gr. Beta U-233/4 U-238 K-40 Ra-226 Ra-228 Ac-228 K-40 Cs-137 Gr. Beta K-40 K-40 Gr. Beta K-40 Be-7 K-40 Sr-90 Ra-226 Ra-228 K-40 Gr. Beta K-40 H-3 K-40 Be-7 7.28 +/- 0.56 0.16 +/- 0.08 7.20 +/- 0.30 1.93 +/- 0.66 7.46 +/- 1.21 1.16 +/- 0.15 1.38 +/- 0.56 6.23 +/- 1.16 0.17 +/- 0.09 17.03 +/-4.17 13.23 +/- 2.61 289.00 +/- 99.00 0.28 +/- 0.14 20.45 +/- 1.04 0.11 +/-0.02 0.12 +/- 0.02 4.06 +/- 0.22 2.69 +/- 0.22 2.77 +/- 0.75 11.03 +/- 0.33 6.39 +/- 0.80 0.05 +/- 0.02 4.12 +/- 0.08 3.07 +/- 0.42 4.26 +/- 0.28 7.72 +/- 0.17 1.65 +/- 0.17 2.52 +/- 0.19 5.05 +/- 0.37 0.01 +/- 0.00 1.33 +/-0.15 2.76 +/- 0.66 2.05 +/- 0.32 2.92 +/- 0.08 2.06 +/- 0.32 10909.00 +/- 311.00 1.24 +/- 0.20 0.09 +/- 0.02 7.42 +/- 0.63 0.22 +/- 0.09 6.60 +/- 0.30 1.03 +/- 0.53 7.02 +/- 1.14 0.90 +/- 0.12 1.72 +/- 0.60 6.75 +/- 1.29 0.21 +/- 0.10 15.56 +/- 3.96 14.36 +/- 2.47 375.00 +/- 103.00 0.24 +/- 0.14 19.22 +/- 0.94 0.10 +/- 0.01 0.11 +/- 0.01 4.08 +/- 0.24 2.79 +/- 0.22 1.61 +/- 0.57 11.08 +/- 0.44 6.98 +/- 0.88 0.05 +/- 0.02 4.10 +/- 0.08 3.14 +/- 0.40 3.66 +/- 0.47 7.61 +/- 0.16 1.72 +/- 0.15 2.65 +/- 0.21 4.79 +/- 0.39 0.01 +/- 0.01 1.59 +/- 0.17 1.54 +/- 0.56 2.53 +/- 0.36 2.89 +/- 0.08 2.53 +/- 0.36 10817.00 +/- 310.00 1.18 +/- 0.21 0.09 +/- 0.03 7.35 +/- 0.42 0.19 +/- 0.06 6.90 +/- 0.21 1.48 +/- 0.42 7.24 +/- 0.83 1.03 +/- 0.10 1.55 +/- 0.41 6.49 +/- 0.87 0.19 +/- 0.07 16.30 +/- 2.88 13.80 +/- 1.80 332.00 +/- 71.43 0.26 +/- 0.10 19.84 +/- 0.70 0.11 +/- 0.01 0.12 +/- 0.01 4.07 +/- 0.16 2.74 +/- 0.16 2.19 +/- 0.47 11.06 +/- 0.28 6.69 +/- 0.59 0.05 +/- 0.01 4.11 +/- 0.06 3.11 +/- 0.29 3.96 +/- 0.27 7.67 +/- 0.12 1.68 +/- 0.12 2.59 +/- 0.14 4.92 +/- 0.27 0.01 +/- 0.00 1.46 +/- 0.11 2.15 +/- 0.43 2.29 +/- 0.24 2.90 +/- 0.06 2.29 +/- 0.24 10863.00 +/- 219.56 1.21 +/- 0.14 0.09 +/- 0.02 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-6090, 6091 G-6090, 6091 G-6090, 6091 SO-6111, 6112 SO-6111, 6112 W-6795, 6796 AP-6461, 6462 WW-6279, 6280 W-6346, 6347 VE-6503, 6504 WWN-6606, 6607 WW-6606, 6607 WW-7237, 7238 F-6627, 6628 VE-6669, 6670 VE-6669, 6670 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 WW-7258, 7259 WW-7655, 7656 WW-7747, 7748 MI-6963, 6964 MI-7174, 7175 SG-7221, 7222 DW-30216, 30217 DW-30216, 30217 DW-30216, 30217 MI-7363, 7364 CF-7384, 7385 VE-7489, 7490 AP-7531, 7532 BS-7573, 7574 LW-7865, 7866 SG-8095, 8096 SG-8095, 8096 10/1/2012 10/1/2012 10/1/2012 10/1/2012 10/1/2012 10/1/2012 10/2/2012 10/3/2012 10/3/2012 10/9/2012 10/10/2012 10/10/2012 10/12/2012 10/15/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/22/2012 10/25/2012 10/25/2012 10/28/2012 11/5/2012 11/9/2012 11/9/2012 11/9/2012 11/9/2012 11/13/2012 11/13/2012 11/16/2012 11/21/2012 11/24/2012 12/5/2012 12/19/2012 12/19/2012 Be-7 Gr. Beta K-40 Cs-137 K-40 H-3 Be-7 Gr. Beta Ra-226 K-40 Gr. Beta H-3 H-3 K-40 Be-7 K-40 Ac-228 Bi-214 Gr. Beta Pb-212 TI-208 H-3 H-3 H-3 K-40 K-40 Pb-214 Gr. Alpha Ra-226 Ra-228 K-40 K-40 K-40 Be-7 K-40 Gr. Beta Ac-228 Gamma 3.74 t 0.33 10.81 +/- 0.34 5.99 +/- 0.47 0.06 +/- 0.03 19.66 +/- 0.84 215.20 +/- 88.00 0.07 +/- 0.01 1.54 +/- 0.68 0.30 +/- 0.10 5.23 +/- 0.83 3.18 +/- 1.31 273.10 +/- 85.70 175.44 +/- 99.84 3.05 +/- 0.39 0.48 +/- 0.26 4.06 +/- 0.28 0.16 +/- 0.05 0.13 +/- 0.03 14.20 +/- 0.89 0.15 +/- 0.06 0.06 +/- 0.02 214.69 +/- 85.42 159.00 +/- 86.10 156.50 +/- 84.70 1384.60 +/- 111.70 1283.60 +/- 97.45 31.49 +/- 0.70 2.23 +/- 0.86 0.72 +/- 0.12 0.92 +/- 0.52 1304.40 +/- 103.30 11.75 +/- 0.52 2.22 +/- 0.23 0.19 +/- 0.10 7.21 +/- 0.41 2.16 +/- 0.56 25.15 +/- 0.73 26.98 +/- 2.72 3.54 +/- 0.30 10.72 +/- 0.33 5.45 +/- 0.44 0.04 +/- 0.02 20.09 +/- 0.80 292.80 +/- 91.60 0.07 +/- 0.02 1.67 +/- 0.75 0.36 +/- 0.10 6.00 +/- 0.45 2.42 +/- 1.27 219.80 +/- 83.10 180.75 +/- 100.03 3.23 +/- 0.37 0.50 +/- 0.13 3.68 +/- 0.26 0.17 +/- 0.06 0.16 +/- 0.03 12.67 +/- 0.88 0.13 +/- 0.02 0.04 +/- 0.02 314.60 +/- 90.25 159.00 +/- 86.10 170.20 +/- 85.30 1421.60 +/- 107.60 1293.20 +/- 91.37 30.11 +/- 0.80 2.31 +/- 0.92 0.82 +/- 0.14 1.26 +/- 0.53 1496.10 +/- 121.30 10.94 +/- 0.59 1.91 +/- 0.22 0.29 +/- 0.17 7.57 +/- 0.39 1.64 +/- 0.62 25.47 +/- 0.54 28.68 +/- 2.89 3.64 +/- 0.22 10.77 +/- 0.24 5.72 +/- 0.32 0.05 +/- 0.02 19.88 +/- 0.58 254.00 +/- 63.51 0.07 +/- 0.01 1.61 +/- 0.51 0.33 +/- 0.07 5.04 +/- 0.27 2.80 +/- 0.91 246.45 +/- 59.69 178.10 +/- 70.66 3.14 +/- 0.27 0.49 +/- 0.15 3.87 +/- 0.19 0.17 +/- 0.04 0.14 +/- 0.02 13.44 +/- 0.63 0.14 +/- 0.03 0.05 +/- 0.01 264.65 +/- 62.13 159.00 +/- 60.88 163.35 +/- 60.10 1403.10 +/- 77.55 1288.40 +/- 66.79 30.80 +/- 0.53 2.27 +/- 0.63 0.77 +/- 0.09 1.09 +/- 0.37 1400.25 +/- 79.66 11.35 +/- 0.39 2.06 +/- 0.16 0.24 +/- 0.10 7.39 +/- 0.28 1.90 +/- 0.42 25.31 +/- 0.45 27.83 +/- 1.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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).
A5-4
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance STW-1670 02/01/12 1-129 9.31 +/- 0.31 12.29 8.60 - 15.98 STSO-1 766 d STSO-1766 STSO-1766 STSO-1 766 STSO-1766 STSO-1766 STSO-1 766 STSO-1766 STSO-1766 STSO-1766 STSO-1 766 STSO-1 766 STSO-1 766 STSO-1 766 STSO-1 766 STAP-1 772 STAP-1 772 STAP-1772 STAP-1772 STAP-1772 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1772 STAP-1772 e STAP-1772 STAP-1772 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Am-241 Co-57 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 88.50 +/- 8.30 1352.10 +/- 4.00 1.70 +/- 0.70 842.20 +/- 4.30 0.40 +/- 0.90 1729.60 +/- 22.20 647.60 +/- 4.20 781.50 +/- 9.70 142.40 +/- 9.70 66.10 +/- 6.40 383.20 +/- 15.30 289.60 +/- 10.90 63.20 +/- 5.40 310.80 +/- 12.10 766.70 +/- 6.70 0.062 +/- 0.02 0.010 +/- 0.01 2.40 +/- 0.08 2.33 +/- 0.13 2.07 +/- 0.10 3.77 +/- 0.14 0.003 +/- 0.004 0.098 +/- 0.017
-0.010 +/- 0.060 0.016 +/- 0.006 0.11 +/- 0.02 3.67 +/- 0.20 159.00 1179.00 1.56 828.00 0.00 1491.00 558.00 862.00 136.00 65.80 392.00 374.00 68.10 329.00 642.00 0.073 0.00 2.18 2.38 1.79 3.24 0.002 0.097 0.000 0.019 0.12 2.99 111.00 - 207.00 825.00 - 1533.00 1.00 - 2.00 580.00 - 1076.00 0.00 -1.00 1044.00 - 1938.00 391.00 - 725.00 603.00 - 1121.00 97.00 - 177.00 46.10 - 85.50 274.00 - 510.00 262.00 - 486.00 47.70 - 88.50 230.00 - 428.00 449.00 - 835.00 0.051 -0.10 0.000 -1.00 1.53 -2.84 1.67 -3.09 1.25 - 2.33 2.27 - 4.21 0.000 -0.10 0.07 -0.13
-0.10 -0.13 0.013 - 0.024 0.09 -0.16 2.09 - 3.89 Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1 773 02/01/12 Gr. Alpha STAP-1 773 02/01/12 Gr. Beta STVE-1776 STVE-1776 STVE-1776 STVE-1776 STVE-1 776 STVE-1 776 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 0.51 +/- 0.05 2.75 +/- 0.10 14.57 +/- 0.28 6.45 +/- 0.23 8.39 +/- 0.29 0.01 +/- 0.09 0.03 +/- 0.08 10.31 +/- 0.67 1.68 +/- 0.09 6.33 +/- 0.10 1.20 2.40 12.00 6.05 8.43 0.00 0.00 8.90 2.14 6.36 0.40 - 2.00 1.20 - 3.60 8.40 - 15.60 4.24 - 7.87 5.90 - 10.96 0.00 -0.10 0.00 -0.10 6.23-11.57 0.64 - 3.64 3.18 -9.54 STW-1 960 02/01/12 Gr. Alpha STW-1960 02/01/12 Gr. Beta A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration '
Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance STW-1 964 STW-1964 STW-1 964 STW-1 964 STW-1 964 STW-1 964 STW-1 964 STW-1 964 STW-1 964 STW-1964 STW-1964 STW-1964 STW-1 964 ST1W-1 964 STW-1964 STW-1964 STW-1 964 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 1.28 +/- 0.12 33.30 +/- 0.40 23.20 +/- 0.40 0.30 +/- 3.00 40.10 +/- 0.60 65.10 +/- 9.50 460.00 +/- 12.10 153.00 +/- 4.20 32.70 +/- 0.60 49.80 +/- 2.90 0.58 +/- 0.06 1.30 +/- 0.15 0.10 +/- 0.20 23.70 +/- 0.80 0.40 +/- 0.05 2.67 +/- 0.13 0.01 +/- 0.20 5.73 +/- 0.28 129.30 +/- 12.70 376.20 +/- 20.60 118.70 +/- 9.30 140.70 +/- 9.90 483.52 +/- 16.47 432.50 +/- 23.10 1528.00 +/- 4.10 592.00 +/- 3.20 933.60 +/- 5.82 1319.80 +/- 5.50 737.30 +/- 17.70 1083.20 +/- 5.20 55.80 +/- 4.20 231.20 +/- 8.60 696.10 +/- 7.00 1.63 32.90 23.72 0.00 39.90 81.90 437.00 142.00 31.80 60.00 0.63 1.34 0.00 27.90 0.39 2.76 0.00 6.82 111.00 406.00 105.80 134.00 508.00 469.00 1316.00 531.00 939.00 1150.00 632.00 920.00 60.30 263.00 606.00 1.14 -2.12 23.00 - 42.80 16.60 - 30.84 0.00 - 1.00 27.90 - 51.90 57.30 - 106.50 306.00 - 568.00 99.00 - 185.00 22.30 - 41.30 42.00 - 78.00 0.44 - 0.82 0.94 -1.74 0.00 - 1.00 19.50 - 36.30 0.27 - 0.51 1.93 -3.59 0.00 -1.00 4.77 - 8.87 78.00 - 144.00 284.00 - 528.00 74.10 - 137.50 94.00 - 174.00 356.00 - 660.00 328.00 - 610.00 921.00 - 1711.00 372.00 - 690.00 657.00 - 1221.00 805.00 - 1495.00 442.00 - 822.00 644.00 - 1196.00 42.20 - 78.40 184.00 - 342.00 424.00 - 788.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-5391 08/01/12 1-129 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 Am-241 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 U-233/4 U-238 Zn-65 A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)
Concentration B Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance STVE-5395 g 08/01/12 Co-57 7.44 +/- 0.17 5.66 3.96 -7.36 Fail STVE-5395 08/01/12 Co-60 5.90 +/- 0.15 5.12 3.58 -6.66 Pass STVE-5395 08/01/12 Cs-1 34 7.40 +/- 0.31 6.51 4.56 -8.46 Pass STVE-5395 08/01/12 Cs-137 5.45 +/- 0.18 4.38 3.07 -5.69 Pass STVE-5395 08/01/12 Mn-54 4.06 +/- 0.21 3.27 2.29 -4.25 Pass STAP-5398 08/01/12 Gr. Alpha 0.41 +/- 0.05 0.97 0.29 - 1.65 Pass STAP-5398 08/01/12 Gr. Beta 2.11 +/- 0.09 1.92 0.96 -2.88 Pass STAP-5401 h 08/01/12 Am-241 0.12 +/- 0.02 0.08 0.05 -0.10 Fail STAP-5403 08/01/12 Co-57 1.96 +/- 0.05 1.91 1.34 -2.48 Pass STAP-5403 08/01/12 Co-60 1.76 +/- 0.07 1.73 1.21 -2.25 Pass STAP-5403 08/01/12 Cs-1 34 2.74 +/- 0.18 2.74 1.92 -3.56 Pass STAP-5403 08/01/12 Cs-1 37 0.00 +/- 0.03 0.00
-0.01 -0.01 Pass STAP-5403 08/01/12 Mn-54 2.52 +/- 0.10 2.36 1.65 -3.07 Pass STAP-5403 08/01/12 Pu-238 0.050 +/- 0.015 0.063 0.044 - 0.081 Pass STAP-5403 08/01/12 Pu-239/40 0.001 +/- 0.004 0.00081 0.000 - 0.010 Pass STAP-5403' 08/01/12 U-233/4 0.009 +/- 0.011 0.014 0.010 -0.018 Fail STAP-5403 08/01/12 U-238 0.08 +/- 0.02 0.10 0.070 - 0.130 Pass STAP-5403 08/01/12 Zn-65 0.01 +/- 0.06 0.00
-0.010 - 0.010 Pass STW-5445 08/01/12 Fe-55 79.80 +/- 4.10 89.30 62.50 - 116.10 Pass STW-5445 08/01/12 Ni-63 74.30 +/- 3.40 66.30 46.40 - 86.20 Pass STW-5445 08/01/12 U-233/4 0.46 +/- 0.05 0.45 0.32 - 0.59 Pass STW-5445 08/01/12 U-238 3.14 +/- 0.14 3.33 2.33 -4.33 Pass STW-5445' 08/01/12 Am-241 0.64 +/- 0.04 1.06 0.74 - 1.38 Fail 8 Results are reported in units of Bq/kg (soil), Bq/L (water) or Bqltotal sample (filters, vegetation).
b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
d Investigation was inconclusive, there was not enough sample for reanalysis. ERA results (A-7) for the same matrix were acceptable.
e No errors found in calculation or procedure, original analysis result; 0.010 +/- 0.010 Bq/filter.
f Reanalysis results were within limits, but low. ERA results (A-7) for the same matrix were acceptable.
The efficiency factor was recalculated for the second round of MAPEP testing. Original analysis results 55.8 +/- 12.6 Bq/L.
g Result of reanalysis; 6.74 +/- 0.15 Bq/sample. Gamma emitters for the vegetation matrix exhibited a high bias, only Co-57 exceeded acceptance limits. Recounted using a geometry more closely matched to the MAPEP sample size.
h Result of reanalysis; 0.070 +/- 0.013 Bq/filter.
Result of reanalysis; 0.013 +/- 0.005 pCi/filter. A larger sample size was used to reduce the counting error.
Result of reanalysis 1.07 +/- 0.06 pCi/L. The analyses of the MAPEP sample matrix resulted in recovery factors greater than 100%.
A correction was made using recovery based on analysis of blank samples. A new tracer solution is on order, future samples for MAPEP testing will include batch spike and blank samples.
A6-3
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a.
Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1393 03/19/12 ERAP-1 393 03/19/12 ERAP-1 393 03/19/12 ERAP-1393 03/19/12 ERAP-1393 03/19/12 ERAP-1394 03/19/12 ERAP-1394 03/19/12 ERAP-1394 03/19/12 ERAP-1 394 03/19/12 ERAP-1394 03/19/12 ERAP-1 394 03/19/12 ERAP-1394 03/19/12 ERAP-1396 03/19/12 ERAP-1396 03/19/12 ERSO-1 397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1 397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1 397 03/19/12 ERSO-1 397 03/19/12 ERSO-1397 03/19/12 ERSO-1397 03/19/12 ERSO-1 397 03/19/12 ERSO-1 397 03/19/12 ERSO-1397 03/19/12 ERSO-1 397 03/19/12 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Am-241 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Gr. Alpha Gr. Beta Ac-228 Am-241 Bi-212 Bi-214 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Th-234 U-233/4 U-238 Uranium Zn-65 917.5 +/- 7.0 586.6 +/- 7.4 1255.9 +/- 9.4
< 3.4 1085.2 +/- 18.0 86.9 +/- 2.9 70.2 +/- 3.6 66.0 +/- 1.0 112.5 +/- 15.4 43.4 +/- 0.8 44.0 +/- 1.2 89.1 +/- 2.2 81.1 +/- 1.5 68.4 +/- 0.7 1303.4 +/- 89.3 856.0 +/- 123.7 1379.2 +/- 247.2 965.2 +/- 38.4 3693.6 +/- 32.1 2257.3 +/- 45.4 9444.5 +/- 58.4 11277.0 +/- 275.1
< 21.0 1208.4 +/- 26.3 1041.6 +/- 46.9 921.0 +/- 112.6 1028.0 +/- 112.6 8128.0 +/- 329.0 2711.3 +/- 253.6 1859.3 +/- 126.6 2003.3 +/- 130.3 3939.5 +/- 283.8 4200.4 +/- 65.9 880.0 656.0 1130.0 0.0 897.0 68.8 63.2 63.0 89.6 47.5 47.1 96.7 77.8 52.5 1570.0 938.0 1550.0 1100.0 3500.0 2180.0 8770.0 11600.0 0.0 1510.0 1110.0 984.0 879.0 8800.0 2000.0 1960.0 2000.0 4030.0 3650.0 681.0 - 1100.0 417.0 - 814.0 849.0 - 1480.0 642.0 - 1240.0 42.4 - 93.1 43.3 - 83.1 45.6 - 82.4 43.8 - 134.0 29.4 -71.6 30.4 - 65.1 53.5 - 147.0 26.1 -121.0 33.2 - 76.5 1010.0 - 2180.0 549.0 - 1220.0 413.0 - 2280.0 665.0 - 1590.0 2370.0 - 4820.0 1420.0 - 2620.0 6720.0 - 11300.0 8470.0 - 15600.0 992.0 - 2110.0 647.0 - 1650.0 592.0 - 1360.0 575.0 - 1210.0 3360.0 - 13900.0 632.0 - 3760.0 1200.0 - 2510.0 1240.0 - 2540.0 2190.0 - 5320.0 2910.0 - 4850.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A7-1
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result a Limits Acceptance ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1405 ERW-1405 ERW-1405 ERW-1405 ERW-1405 ERW-1405 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 Am-241 Cm-244 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Fe-55 Pu-238 Pu-239/40 U-233/4 U-238 Uranium Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 4194.8 +/- 199.5 1471.2 +/- 113.1 2347.8 +/- 47.9 2847.5 +/- 64.0 1503.5 +/- 52.5 34105.7 +/- 745.3
< 26.8 2509.0 +/- 213.6 2690.4 +/- 208.9 7881.5 +/- 470.8 3149.6 +/- 165.2 3203.6 +/- 166.5 6463.7 +/- 363.2 2701.9 +/- 105.5 119.9 +/- 3.2 713.7 +/- 127.4 131.9 +/- 6.4 108.9 +/- 10.2 93.1 +/- 7.9 96.9 +/- 5.5 190.0 +/- 13.8 858.7 +/- 5.6 560.4 +/- 4.4 1239.9 +/- 7.4
< 7.4 944.3 +/- 26.2 786.9 +/- 20.6 85.9 +/- 3.0 45.7 +/- 1.6 9045.0 +/- 284.0 4540.0 1590.0 2210.0 2920.0 1340.0 28600.0 0.0 2350.0 2570.0 8520.0 3610.0 3580.0 7350.0 2310.0 135.0 863.0 135.0 112.0 105.0 104.0 214.0 875.0 609.0 1250.0 0.0 989.0 749.0 103.0 43.7 2780.0 - 6040.0 779.0 - 2480.0 1520.0 -3090.0 1880.0 - 3790.0 972.0 - 1860.0 20700.0 - 40100.0 1400.0 - 3220.0 1580.0*- 3540.0 4860.0 - 11300.0 2370.0 -4640.0 2390.0 - 4550.0 4980.0 - 9150.0 1670.0 - 3240.0 91.0 - 181.0 514.0 - 1170.0 99.9 -168.0 86.9-141.0 78.9 - 135.0 79.3 - 128.0 157.0 - 277.0 760.0 - 1020.0 447.0 - 700.0 1060.0 - 1500.0 644.0 - 1310.0 624.0 - 945.0 36.6 - 160.0 25.0 - 64.7 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass ERW-1406 03/19/12 Gr. Alpha ERW-1406 03/19/12 Gr. Beta ERW-1409 03/19/12 H-3 9150.0 6130.0 - 13000.0 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).
Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a '"false positive". Control limits are not provided.
A7-2
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x +/- s where:
x = value of the measurement; s = 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 If duplicate analyses are reported, the convention is as follows.:
3.1 Individual results: For two analysis results; x, +/- si and x 2 +/-s 2 Reported result:
x +/-s; where x = (1/2) (x, + x2) and s = (1/2)
+ S2 3.2.
Individual results:
< Li,
< L2 Reported result: < L, where L = lower of Li and L2 3.3.
Individual results:
x +/- s, < L Reported result:
x +/- s if x >: L; < L otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s" of a set of n numbers x1, x2... xn are defined as follows:
x =
Xx n-i 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1.
If the number following those to be retained is less than 5, the number is dropped, and the retained numbers 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 background in unrestricted areasa Air (pCi/m3)
Water (pCi/L)
Gross alpha Gross beta b
Iodine-1I31
-3 1 x 10 I
-1 2.8 x 10 Strontium-89 Strontium-90 Cesium-1 37 Barium-140 Iodine-1 31 c
Potassium-40 Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2
10 6
1 x 10 a
Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
C A natural radionuclide.
C-2
APPENDIX D Sampling Location Maps
TLD LOCATIONS ONE MILE RADIUS E
PLANT AREA ENLARGED PLAN
[1.00 MILE RADIUS]
[NO SCALE3 MONITORING LEGEND:
(D PRAIRIE ISLAND TLD POINTS D-2
TLO LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLO LOCATIONS
-MONITORING LEGEND:
(2) PRAIRIE ISLAND TLD POINTS D-3
TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
(2) PRAIRIE ISLAND TLD POINTS D-4
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS RADIUS]
PLANT AREA ENLARGEO PLAN
[1.00 MILE
[NO SCALE]
MONITORING LEGENO MILK SAMPLING POINT ID NUMBERS P-18, P-37. P-43 AIR SAMPLING POINT ID NUMBERS P-1. P-2. P-3. P-,. P-6
~)
WATER SAMPLING POINT ID NUMBERS 0
P.5, P-G. P-8. P-S, PAI, P-24, P-43 VEGETATION / VEGETABLES ID NUMBERS P-28, P-38, P-45 FISH SAMPLING POINT 10 NUMBERS P-13. P-19 INVERTEBRATES POINT 10 NUMBERS P-G. P-40 SEDIMENT SAMPLING POINT ID NUMBERS PýG, P-12, P-20 REV. I D-5 SAMPOI.DGNI REV. I 0-5 SAMP01.DGN
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND
(>
MILK SAMPLING POINT 10 NUMBERS P-I8. P-37. P-43 A
AIR SAMPLING POINT I0 NUMBERS P-I. P-2. P-3,.P-4. P-6 O
WATER SAMPLING POINT I0 NUMBERS P-5, P-S, P,-q P-I1. P-24. P-43 E
VEGETATION / VEGETABLES ID NUMBERS P-2g. P-3B, P-45 FISH SAMPLING POINT ID NUMBERS P-13, P-I9 S
INVERTEBRATES POINT 10 NUMBERS P-S. P-40 S
SEDIMENT SAMPLING POINT 10 NiUMBERS P-G, P-12. P-20 0-6
ENVIRONMENTAL SAMPLING POINTS S>)
P-43, Peterson Farm, W10322 St Rd 29, River Falls, Wil n'J P-38, Cain Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND MILK SAMPLING POINT ID NUMBERS P-18, P-37, P-41, P.42, P-43 A
AiR SAMPLING POINT ID NUMBERS P-1, P-2, P-.3, P-4, P-6 O
WATER SAMPLING POINT ID NUMBERS P-5, P-G, P-1, P-9, P1I. P-43 0
VEGETATION I VEGETABLES ID NUMBERS P-26, P-38, P-45 D-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 Nuclear 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, 2012. 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.
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 2012 are summarized and discussed.
Program findings for 2012 detected 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 wells P-10 and MW-8. The 2012 sample results (except for P-10 and MW-8) ranged from <19 pCi/L to 83 pCi/L.
Sample well P-10 ranged from 41 pCi/L to 247 pCi/L. Sample well MW-8 ranged from 229 pCi/L to 398 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.
None of the water samples monitored for gamma-emitting isotopes showed any activity greater than the LLD.
E-2
3.0 SDecial Tritium SamDlina Proaram 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 E-4.1 and briefly reviewed below. Table E-4.2 defines the additional sample locations and codes for the special water sampling program.
Special well, tank, and surface water samples were collected quarterly (spring, summer, fall) at seven locations, quarterly at one location, monthly at six locations, semi-annually at five locations, and annually at forty-two locations. The Peterson (P-43) and Hanson (SW-1) 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 in the preceding section.
3.4 Program Modifications Changes to the program in 2012 include:
" samples were taken from monitoring wells P-10 and MW-8 and stormwater runoff S-6 and S-7 and were sent to Environmental Incorporated for analysis for hard-to-detect nuclides in accordance with American Nuclear Insurers recommendation samples were taken from PIIC-21, PIIC-27, SW-6, and SW-7 because these wells became available for sampling in 2012 no samples were taken from the warehouse septic or the D5 Fuel Oil Storage Tank vault because these locations were not required to be sampled E-3
3.5 Results and Discussion Results show tritium in well water and ground water samples at or near expected natural background levels except the P-10 and MW-8 sample wells. Table E-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 began in 1989.
Except for sample wells P-10 and MW-8, the 2012 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 the Suter residence 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.
The elevated tritium levels in sample wells P-10 and MW-8 in 2012 may be due to prior leakage from the PINGP liquid radwaste discharge pipe, discharge of turbine building sump water into the landlocked area, or discharge of heating steam condensate from the main warehouse in 1978/1979.
The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been terminated, the last discharge took place on 11/14/09. The main warehouse heating system was repaired in 1979. An additional discharge of 27 gallons of heating steam condensate was released in 2012 from the main warehouse. Corrective actions were taken to repair the main warehouse condensate return pumps. The heating steam system was not used in the outer plant buildings during the 2012 -2013 heating season.
None of the water samples monitored for gamma-emitting isotopes showed any activity greater than the LLD.
E-4
Table E-4.1. Sample collection and analysis program for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2012.
Medium No.
Location codes Collection type Analysis and type a and frequency b type c P-8, REMP P-6, PIIC-02, PIIC-03, PIIC-19, PIIC-20, PIIC-21, PIIC-22, PIIC-23, PIIC-24, PIIC-26, PIIC-27, Well water 29 PIIC-28, P-7, Annual P-I11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, G/A H-3 MW-6, P-26, P-30, SW-3, SW-4, SW-5, SW-6, SW-7, P-9 Well water 1
P-24D GIQ H-3 quarterly Well water 7
P-2, P-3, P-5, P-6, G/Q' H-3 quarterly' PZ-8, MW-4, MW-5 Well water monthly 5
P-43(C), SW-1(C),
G/M H-3 MW-7, MW-8, P-10 Surface water S-1, S-2, S-3, S-4, S-5, 8
S-6, S-7, P-31 G/Ad H-3 Storage Tank 5
11 CST, 21 CST, 22 CST, G/S H-3 UL1/2 Demin Hdr Storage Tank 1
Septic Tank G/M H-3 Snow 5
S-6, S-7, S-8, S-9, P-43(C)
G/A H-3 a Location codes are defined in table D-4.2. Control Stations 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; Q' = quarterly (spring, summer, and fall), S= semiannually: A = annually.
CAnalysis type is coded as follows: H-3 = tritium.
Location S-6 and S-7 are sampled semi-annually.
E-5
Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2012.
Code Collection site Type of Distance and sample a 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-03 6096 Whipple Way WW 1.4 mi. @ 310°/NW PIIC-19 6372 Sturgeon Lake Rd WW 1.7 mi. @ 293MNVNW PIIC-20 2158 Holmquist Road WW 1.6 mi @ 300"/WNW PIIC-21 1802 Messiah Road WW 0.9 mi Q 281'/W PIIC-22 1773 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-23 2.7 miles NW WW 2.7 mi @315"/NW PIIC-24 6424 Sturgeon Lake Rd WW 1.7 mi. @ 293"/WNW PIIC-26 1771 Buffalo Slough Rd WV 1 mi. @ 315°/NW PIIC-27 6372 Sturgeon Lake Rd WW 1.7 mi. @ 293"/WNW PIIC-28 1960 Larson Lane WW 1.5 mi @ 288"NWNW 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-5 Sample well WW See map P-6 Sample well WW See map P-7 Sample well WW See map P-1O 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 MW-7 Sample well WW See map MW-8 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 E-6
Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2012 (continued).
Code Collection site Type of Distance and sample a direction from reactor SW-3 Cooling Tower pump WW See map SW-4 New Admin Bldg WW 0.05 mi. @ 315"/NW SW-5 Plant Screenhouse well WW 0.05 mi. @ O0"N SW-6 Restroom Trailer well WW 0.2 mi @ 310/NW SW-7 Distribution Center WW 0.35 mi a 271 /W P-9 Plant well # 2 WW 0.3 mi. Q 306°/NW S-1 Upstream Miss. River SW See map S-2 Recirc/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end)
SW See map S-5 Mid Discharge Canal SW See map S-6 Roof Stormwater Runoff (also snow)
SW 0.05 mi. @: ON S-7 Parking Lot Stormwater (also snow)
SW 0.3 mi Q 306"/NW S-8 P-10 area snow SW See map S-9 MW-7/8 area snow SW See map P-31 Birch Lake Seepage SW 11 CST Storage Tank ST Turbine Building 21 CST Storage Tank ST Turbine Building 22 CST Storage Tank ST Turbine Building Unit 1/2 demin hdr Storage Tank ST Turbine Building Septic System Storage Tank ST Outside #1 Warehouse Warehouse Septic Storage Tank ST Outside #1 Warehouse D5 Vault Concrete Vault ST Outside Turbine Bldg B Sample codes: WW = Well water; SW = Surface Water: ST = Storage Tank.
E-7
Table E-4.3 Radiation Environmental Monitoring Program Summary: Special well, storage tank, and surface water samples.
Name of Facility Prairie Island Nuclear Power Station Location of Facility Goodhue, Minnesota Docket No.
Reporting Period 50-282, 50-306 January - December, 2012 (County, State)
Indicator Location with Highest Control Locations Annual Mean Locations Sample Type and Mean (F) c Location d Mean (F) c Mean (F) c Number Type Number of LLD b Range C Rangec Range c Non-(Units)
Analyses a Routine Results e Offsite Well H-3 17 19 30(7/17)
PIIC-23 39(1/1)
(See Control Water (20-48)
Below)
(pCi/L)
Onsite H-3 74 19 112 (55/74)
MW-8 306 (12/12)
(See Control 14 Well Water (20-398)
(229-398)
Below)
(pCi/L)
Onsite H-3 15 19 59 (8/15)
S-9 180(1/1)
(See Control Surface Water (23-180)
Below) 0 (pCi/L)
Storage Tank H-3 22 19 100 (13/22) 114 (11/12)
(See Control Stoitae (25-238)
Septic System (31-238)
Below) 1 (pCi/L)
Control (offsite H-3 24 19 none P-43 20(1/12) 20(1/24) well water) 0 a H-3 = tritium b LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
Locations are specified by code.
e Non-routine results are those which exceed ten times the control station value.
E-8
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2012.
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 CODE SAMPLE LOCATIONS Concentration H-3 ( pCi/L-OFFSITE WELLS P-8 PI Comm. Well
< 19 REMP P-6 Lock & Dam #3 well
< 19 PIIC-02 2077 Other Day Road
< 19 PIIC-03 6096 Whipple Way
< 19 PIIC-19 6372 Sturgeon Lake Rd 20 PIIC-20 2158 Holmquist Rd 26 PIIC-21 1802 Messiah Road
< 19 PIIC-22 1773 Buffalo Slough Rd 22 PIIC-23 2.7 miles NW of plant 39 PIIC-24 6424 Sturgeon Lake Rd
< 19 PIIC-26 1771 Buffalo Slough Rd 33 PIIC-27 6372 Sturgeon Lake Rd
< 19 PIIC-28 1960 Larson Lane
< 19 P-24D Suter residence 48
<19
<19 24 P43 PtersonFarm(Control
< 19
< 19
< 19
< 19
< 19 20
<19
< 19
< 19
< 19
< 19
< 19 SW-i HansonFarm(Control)
<19
< 19
< 19
< 19
< 19
< 19
< 19
< 19
< 19
< 19
< 19
<19 E-9
Table E-4.4 Radiological Environmental Monitorinq Program Complete Data Table, 20122 ((ctinued)._
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 CODE SAMPLE LOCATIONS Concentration H-3 (pCi/
ONSITE WELLS P-2 Sample well 83 49
< 19 P-3 Sample well 23 20
< 19 P-5 Sample well 69 49 28 P-6 Sample well 23
< 19
< 19 P-7 Sample well 53 P-10 Sample well 234 247 191 122 96 75 41 46 56 60 115 103 P-11 Sample well 27 PZ-1 Sample well
< 19 PZ-2 Sample well
< 19 PZ-4 Sample well 24 PZ-5 Sample well 23 PZ-7 Sample well 32 PZ-8 Sample well 31 39
< 19 MW-4 Sample well 32
< 19
< 19 MW-5 Sample well
< 19 32
< 19 MW-6 Sample well
< 19 MW-7 Sample well 39 31 30 25 55 21 23 27 51
< 19 43 31 MW-8 Sample well 270 398 373 319 349 284 252 253 273 229 327 338 P-26 PITC well 36 P-30 Env. lab well
< 19 SW-3 CT pump 32 P-9 Plant well # 2 27 SW-4 New Admin
< 19 SW-5 Pint Scmhs
< 19 SW-6 Restroom Trailer
< 19
< 19 SW-7 Dist Center
< 19 E-1 0
Table E-4.4 Radiological Environmental Monitoring Program Complete Data Table, 2012 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 CODE SAMPLE LOCATIONS Concentration H-3 ( pCi/L-ONSITE SURFACE WATER S-1 Mississippi River upstream 38 S-2 Recirculation/Intake canal
<19 S-3 Cooling water canal
<19 S-4 Discharge Canal (end)
<19 S-5 Discharge Canal (midway) 28 S-6 Stormwater runoff
<19 26 S-7 Parking Lot runoff 76 58
<19 S-8 P-10 area snow 46
- S-9 MW-7/8 area snow 180
- P-31 Birch Lake Seepage
<19 23
< 19
- snow samples E-11
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2012 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 2012 CODE SAMPLE LOCATIONS Concentration H-3 ( pCi/L-ONSITE STORAGE TANKS 11 CST Storage tank
<19
<19 21 CST Storage tank
< 19
<19 22 CST Storage tank
<19
<19 U1/U2 28/
25/
Demin Storage tank
< 19
<19 Header Septic Storage tank
< 19 43 238 175 92 64 146 89 56 31 180 137 SystemII E-1 2
Table E-4.5. Results of analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium in four samples.
Location S-6 S-7 P-10 Well MW-8 Well Collection Date 05-05-12 05-02-12 06-19-12 06-19-12 Lab Code PXW-3056 PXW-3057 PXWW-3769 PXWW-3770 Isotope Concentration (pCi/mL)
< 9.1 E-07
< 7.7 E-07
< 8.9 E-07
< 8.6 E-07 Ni-63
< 8.2 E-09
< 8.2 E-09
< 9.9 E-09
< 1.0 E-08 Sr-90
< 6.6 E-10
< 5.3 E-10
< 4.8 E-10
< 4.8 E-10 Pu-238
< 1.3 E-10
<8.7 E-11
< 1.1 E-10
< 1.1 E-10 Pu-239/240
< 1.3 E-10
< 1.7 E-10
< 1.1 E-10
< 1.1 E-10 Am-241
< 6.3 E-10
< 8.9 E-11
< 1.0 E-10
< 1.5 E-10 Cm-242
< 6.3 E-10
< 8.9 E-11
< 1.0 E-10
< 1.0 E-10 Cm-243/244
< 6.3 E-10
< 8.9 E-11
< 1.0 E-10
< 1.0 E-10 The error given is the probable counting error at 95% confidence level. Less than (<), value is based on a 4.66 sigma counting error for the background sample.
E-1 3
+
4 Groundwater Monitoring Well Locations E-14