L-PI-11-040, Independent Spent - 2010 Annual Radiological Environmental Monitoring Program (REMP) Report
| ML11133A369 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/12/2011 |
| From: | Schimmel M Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| L-PI-11-040 | |
| Download: ML11133A369 (77) | |
Text
&Xcel Energye MAY 1, 2 2`011 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 L-PI-1 1-040 TS 5.6.2 ISFSI TS 6.2 Prairie Island Independent Spent Fuel Storage Installation Docket 72-10 Materials License No. SNM-2506 2010 Annual Radiologqical Environmental Monitoring Program (REMP) Report Pursuant to Prairie Island Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License SNM-2506, the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy (hereafter "NSPM"),
submits one copy of the Annual Radiological Environmental Monitoring Program report for the period January 1, 2010 through December 31, 2010 as Enclosure 1.
Summary of Commitments This letter contains no new and no revisions to existing commitments.
Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:
Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Billy Dickson, USNRC, Region III Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator 1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121
~LA~5~Q
ENCLOSURE 1 Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program January 1, 2010 through December 31, 2010 75 pages follow
14A Environmental, Inc.
-%*-ATMidwest Laboratory 700 Landwehr Rood - Northbrook, IL. 60062-2310 phone 1847) 564-0700 - fax (847) 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, 2010 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 ronia ro b, M.S.
aborato 1 nager Approved:
PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by 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 P re fa c e.....................................................................................................................................................
ii L ist o f T a b le s...........................................................................................................................................
iv L is t o f F ig u re s..........................................................................................................................................
v 1.0 INTRODUCTIO N......................................................................................................................................
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 Modifications..........................................................................................................
6 3.6 Land Use Census..........................................................................................................................
6 4.0 RESULTS AND DISCUSSIO N........................................................................................................
7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents......................................................
7 4.2 Sum mary of Preoperational Data..............................................................................................
7 4.3 Program Findings...........................................................................................................................
8 5.0 FIG URES AND TABLES........................................................................................................................
12
6.0 REFERENCES
CITED...........................................................................................................................
25 APPENDICES A
Interlaboratory Com parison Program Results..................................................................................
A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Sam ples.................................................................
A-2 B
Data Reporting Conventions................................................................................................................
B-1 C
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas.......................................................................
C-1 D
Sam pling Location Maps......................................................................................................................
D-1 E
Special W ell and Surface W ater Sam ples.......................................................................................
E-1 iii
LIST OF TABLES No.
Title Page 5.1 Sample Collection and Analysis Program.............................................................................................
15 5.2 S a m p ling Locatio n s...................................................................................................................................
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.............................................
Al-1 A-2 Program Results; (TLDs).......................................................................................................................
A2-1 A-3 In-house "Spiked" Samples...................................................................................................................
A3-1 A-4 In-house "Blank" Samples.....................................................................................................
... A4-1 A-5 In-house "Duplicate" Samples.........................................................................................
A5-1 A-6 Department of Energy MAPEP comparison results.......................................................................
A6-1 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-6 E -4.2 S a m p ling loca tio ns..................................................................................................................................
E -7 E-4.3 REMP Summary......................................................................................................................................
E-8 E-4.4 REMP Complete Data Tables.................................................................................................................
E-9 E-4.5 Supplementary Data Tables..................................................................................................................
E-12 iv
LIST OF FIGURES No.
Title Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator lo catio n s ve rsus co ntro l..............................................................................................................................
13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i).................................................................................
14 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 Onsite Tritium Sam pling 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, 2010.
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, 2011 b) 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.
1
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 2010 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) 3V1 Program Desiqn 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-131. 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-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).
Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope.
They were chosen as calibration monitors and should not be considered radiological impact indicators.
The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141.
These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -
60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
3
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, 2010). Maps of fixed sampling locations are included in Appendix D.
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Airborne iodine is collected by continuous pumping through charcoal filters at these same locations.
Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-1 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy.
One of the five locations is a control (P-i), and four are indicators (P-2, P-3, P-4, and P-6).
Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO 4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant.
They are replaced and measured quarterly.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI)
Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.
Milk samples are collected monthly from four farms (three 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.
4
3.2 Program Description (continued)
Drinking water is collected weekly from the City of Red Wing well.
Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
All samples were collected and analyzed as scheduled.
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 and solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
Levels of iodine-1 31 in cabbage and natural vegetation and concentrations of airborne iodine-1 31 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 inspectiorn.
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, 2009). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs.
Results obtained in the crosscheck programs are presented in Appendix A.
3.5 Program Modifications There were no modifications to the REMP in 2010.
3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles.
This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the 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 September, 2010. There were no changes to any of the highest D/Q locations for nearest residence, milk animal or garden sites.
No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant.
Therefore, no corn samples were collected for analysis.
6
4.0 RESULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3.
The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2010. The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents involving any significant release to the environment at nuclear reactor facilities in 2010.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in 2
2 fallout declined yearly from a level of 12,167 pCi/m to 1,020 pCi/m, and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mPR4 weeks during pre-3 operational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m.
3 Average present day levels have stabilized at around 0.025 pCi/m. Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g.
The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish, aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium 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 15.8 mR/91 days at inner ring locations to 16.1 mR/91 days at outer ring locations.
The mean at special interest locations was 15.4 mR/91 days and 16.0 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 1994 through 2009. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).
Average (Inner and Average (Inner and Year Outer Rinqs)
Control Year Outer Rinqs)
Control 1995 15.6 16.6 2003 16.2 16.0 1996 14.8 16.4 2004 17.6 17.6 1997 15.1 16.0 2005 16.8 16.3 1998 16.7 17.3 2006 16.6 16.6 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 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR/91 days).
ISFSI Facility Operations Monitorinq Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates averaged 102.0 mRI91 days inside the ISFSI earth berm and 20.5 mR/91 days outside the ISFSI earth berm. Four additional casks were placed on the ISFSI pad in 2010, 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. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.2 and 14.7 mRI91 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 ISFS1 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 1995 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 identical at the indicators 3
versus control locations (0.025 pCi/m ) and similar to levels observed from 1995 through 2006 and 2008 to 2009. The results are tabulated below.
Year Average of Indicators Control 3
Concentration ()Ci/m 1995 1996 0.022 0.022 0.023 0.020 1997 0.021 0.021 1998 0.022 0.018 1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 2008 0.028 0.027 2009 2010 0.029 0.025 0.029 0.025
+/-
-I 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 0.078 pCi/m3 for all locations. All other gamma-emitting isotopes were below their respective LLD limits.
Airborne Iodine Weekly levels of airborne iodine-1 31 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 the LLD level of 5 pCi/L in all samples.
No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
In summary, the milk data for 2010 show no radiological effects of the plant operation.
Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 159 pCi/L in all samples.
Gross beta concentrations averaged 11.7 pCi/L throughout the year, ranging from 4.7-17.2 pCi/L. These concentrations are consistent with levels observed from 1995 through 2009. 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 2010 data of any effect of plant operation.
Year I
Gross Beta (pCi/L) 1995 I
3.9 1996 1
6.3 1997 5.1 1998 5.4 1999 5.3 2000 10.1 2001 8.3 2002 8.7 2003 9.9 2004 9.8 2005 11.5 2006 13.4 2007 11.6 2008 11.6 2009 11.4 2010 11.7 Average annual concentrations; Gross beta in drinking water.
10
River Water Measurable tritium slightly higher than the LLD level of 182 pCi/L, was detected in one of the four downstream river water composite samples, at a concentration of 230 pCi/L. This is well below the U.S. Environmental Protection Agency's drinking water standard of 20,000 pCi/L. All other samples tested measured below detection limits.
Gamma-emitting isotopes were below detection limits in all samples.
Well Water At control well, P-43 (Peterson Farm) and the four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above a concentration level of 154 pCi/L.
Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2010 show no radiological effects of the plant operation.
Crops Three samples of broadleaf vegetation, cabbage leaves, were collected in July, 2010 and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.021 pCi/g wet weight in all samples. With the exception of 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 November, 2010 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 October, 2010 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes were below detection limits.
There was no indication of a plant effect.
Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediments were sampled in May and October, 2010 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotopes detected were naturally-occurring beryllium-7 and 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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0 0D 0D 0
0 0
0 0ý CD (D
CO C
I CC C) 0 CD 0
0 0
0 0
0 (1
(M
-4J OD (0
0
ý w)
C,)
U1C
- 0)
-4 OD CD 14
PRAIRIE ISLAND Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.
Collection Analysis Location Type and Type and Medium No.
Codes (and Type)
Frequencyb Frequencyc Ambient radiation (TLD's)
Airborne Particulates 54 P-OIA - P-IOA P-OIB - P-15B P-OIS - P-08S P-OIIA - P-O81A P-OIB - P-081B P-OIlX-P-041X, P-O1C 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 Milk 4
P-18, P-37, P-42, P-43 (C)
C/W C/W G/Md G/W G/W 1-131 1-131, GS River water Drinking water 2
GB(MC), 1-131(MC)
GS (MC), H-3 (QC) 1 P-11 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 1
P-12 G/Q G/A H-3, GS G/SA G/SA G/SA G/SA GS (1-131)
GS GS GS GS o Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.
b Collection type is coded as follows: C/ = continuous, G/ - grab. Collection frequency is coded as follows:
W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 = iodine-131.
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d Milk is collected biweekly during the grazing season (May - October).
15
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction Code Type8 Collection Site Sample Typeb 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-42 P-43 P-45 C
Air Station P-1 Air Station P-2 Air Station P-3 Air Station P-4 C
Upstream of Plant Lock and Dam #3 & Air Station P-6 Community Center Plant Well #2 Red Wing Service Center Downstream of Plant Downstream of Plant Christiansen Farm C
Upstream of Plant C
Upstream of Plant Suter Residence Allyn Residence Welsch Farm C
Cain Residence C
Upstream of Plant Rother Farm C
Peterson Farm Glazier Residence AP, Al AP, Al AP, Al AP, Al RW AP, Al, RW WW, BS, BOO WW WW DW SS Fc M
Fc BS WW VE M
VE BOc M
M, WW VE 11.8 ml @ 3160/NNW 0.5 mi @ 2940/WNW 0.8 mi @ 3130 /NW 0.4 mi @ 359°/N 1.8 mi @ 110/N 1.6 mi @ 129 0/SE 1.0 mi @ 321°/WNW 0.3 mi @ 3060/NW 3.3 mi @ 1580/SSE 3.0 mi @ 116 0/ESE 3.5 mi @ 1130/ESE 3.8 mi @ 880/E 1.3 ml @ O/N 0.9 ml @ 450/NE 0.6 mi @ 1580/SSE 1.0 mi @ 1520/SSE 4.1 mi @ 870/E 14.2 mi @ 3590/N 0.4 mi @ O°/N 4.3 mi. @ 2640/W 13.9 mi. @ 3550/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-O8A 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 ml @ 3590/N 0.3 ml @ 100/N 0.5 ml @ 183 0/S 0.4 mi @ 204°/SWW 0.4 mi @ 2250/SW 0.4 ml @ 2490/WSW 0.4 mi @ 2680/W 0.4 mi @ 2910/WNW 0.7 mi @ 3170/NW 0.5 mi @ 3330/NNW 16
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Type 0 Collection Site Sample Typeb from Reactor Approximately 4 to 5 miles Distant from the Plant P-01B Thomas Killian Residence TLD 4.7 mi @ 3550/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 170/NNE P-03B Wayne Anderson Farm TLD 4.9 ml @ 460/NE P-04B Nelson Drive (Road)
TLD 4.2 ml @ 610/ENE P-05B County Road E and Coulee TLD 4.2 ml @ 1020/ESE P-06B William Hauschiblt Residence TLD 4.4 ml @ 112°/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 1400/SE P-08B David Wnuk Residence TLD 4.1. mi @ 1650/SSE P-09B Highway 19 South TLD 4.2 mi @ 1870/S P-lOB Cannondale Farm TLD 4.9 ml @ 2000/SSW P-113 Wallace Weberg Farm TLD 4.5 mi @ 2210/SW P-12B Ray Gergen Farm TLD 4.6 mi @ 2510/WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 2700/W P-14B David J. Anderson Farm TLD 4.9 mi @ 3060/NW P-15B Hoist Farms TLD 3.8 ml @ 3450/NNW Special Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 ml @ 1290/SE P-02S Charles Suter Residence TLD 0.5 ml @ 1550/SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 1730/S P-04S Richard Burt Residence TLD 2.0 mi @ 2020/SSW P-05S Kinney Store TLD 2.0 mi @ 270 0/W P-06S Earl Flynn Farm TLD 2.5 mi @ 2990/WNW P-07S Indian Community TLD 0.7 mi @ 2710/W P-08S Indian Community TLD 0.7 mi @ 2870/NWW P-01C C
Robert Kinneman Farm TLD 11.1 mi @ 331°/NNW 17
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Distance and Direction Code Type" Collection Site Sample Typeb from ISFSI Center.
ISFSI Area Inside Earth Berm P-OIIA P-021A P-031A P-041A P-051A P-061A P-071A P-081A P-0:1IX P-021X P-031X P-041X ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence TLD TLD TLD TLD TLD TLD TOD TLD TLD TLD TLD TLD 190' @ 450 /NE 360' @ 82°/E 370' @ I00 0/E 200' @ 134 0/SE 180' @ 2190/SW 320' @ 258 0/WSW 320' @ 281°/WNW 190' @ 3180 /NW 140'@ 1800/S 310' @ 270°/W 140'@ O/N 360' @ 900/E 340'@ 3'/N 380' @ 28 0/NNE 560' @ 850/E 590' @ 1650/SSE 690' @ 186°/S 720' @ 201°/SSW 610' @ 271°/W 360' @ 3320 /NNW ISFSI Area Outside Earth Berm P-01113 P-021B P-031B P-041B P-0511B P-061B P-071B P-081B ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area TLD TLD TLD TLD TLD TLD TLD TLD a "C" denotes control location. All other locations are Indicators.
b Sample Codes:
AP Airborne particulates F
Fish Al Airborne Iodine M
Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates)
VE Vegetation/vegetables DW Drinking water WW Well water c Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
18
Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.
All required samples were collected and analyzed as scheduled with the following exceptions:
Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence 19
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, 2010
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)
Analysesa Rangec Locationd Rangec Rangec Resultse TLD (Inner Ring, Gamma 40 3.0 15.8 (40/40)
P-06A 17.3 (4/4)
(See Control 0
Area at Site (12.0-18.1) 0.4 mi @ 249° /WSW (15.6-18.1) below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma 60 3.0 16.1 (60/60)
P-01B, Killian Res.
17.5 (4/4)
(See Control 0
4-5 mi. distant)
(12.4-19.5) 4.7 mi @ 355'/N (16.1-18.1) below.)
mR/91 days)
TLD (Special Gamma 32 3.0 15.4 (32/32)
P-03S. Gustafson Farm, 17.4 (4/4)
(See Control 0
Interest Areas)
(12.9-18.9) 2.2 mi @ 173'/S (16.1-18.8) below.)
mR/91 days)
TLD (Control)
Gamma 4
3.0 None P-01C, Robert Kinneman 16.0 (4/4) 16.0 (4/4) 0 mR/91 days) 11.1 mi @ 331°/NNW (15.4-17.0)
(15.4-17.0)
Airborne GB 260 0.005 0.025 (208/208)
P-06, Air Station 0.026 (52 /52) 0.025 (52/52) 0 Particulates (0.009-0.057) 1.6 mi @ 1290 /SE (0.009-0.057)
(0.008-0.048)
(pCi/m3)
GS 20 Be-7 0.015 0.078 (16/16)
P-02, Air Station 0.080 (4/4) 0.077 (4/4) 0 (0.054-0.097) 0.5 mi @ 2940 [WNW (0.054-0.097)
(0.062-0.088)
Mn-54 0.0007
< LLD
< LLD 0
Co-58 0.0007
< LLD
<- LLD 0
Co-60 0.0007
< LLD
< LLD 0
Zn-65 0.0013
< LLD
< LLD 0
Zr-Nb-95 0.0010
< LLD
< LLD 0
Ru-103 0.0009
< LLD
< LLD 0
Ru-106 0.0065
< LLD
< LLD 0
Cs-134 0.0006
< LLD
< LLD 0
Cs-137 0.0007
< LLD
< LLD 0
Ba-La-140 0.0022
< LLD
< LLD 0
Ce-141 0.0017
< LLD
< LLD 0
Ce-144 0.0041
< LLD
< LLD 0
Airborne Iodine 1-131 260 0.03
< LLD
< LLD 0
(pCi/mi) 20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No.
50-282, 50-306 Reporting Period January-December, 2010
( 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)'
Mean (F)'
Routine (Units)
Analysesa Rangec Locationd Rangec Rangec Resultse Milk (pCi/L) 1-131 72 0.5
< LLD
< LLD 0
GS 72 K-40 200 1364 (54/54)
P-43 (C), Peterson 1421 (18/18) 1421 (18/18) 0 (1232-1505) 13.9 mi Q 3550 /N (1296-1495)
(1296-1495)
Cs-134 5
< LLD
< LLD 0
Cs-137 5
< LLD
< LLD 0
Ba-La-140 5
< LLD
< LLD 0
River Water H-3 8
182 230(1/4)
P-6, Lock and Dam #3 230 (1/4)
< LLD 0
(pCi/L) 1.6 mi @ 129°/SE 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 42
< LLD
< LLD 0
21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Location of Facility Goodhue, Minnesota Power Station Docket No.
50-282, 50-306 Reporting Period January-December, 2010 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 Rangec Rangec Resultse Drinking Water GB 12 1.0 11.7 (12/12)
P-11, Red Wing S.C.
11.7 (12/12)
None 0
(pCi/L)
(4.7-17.2) 3.3 mi @ 158° /SSE (4.7-17.2) 1-131 12 1.0
<LLD None 0
H-3 4
159
<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
Well Water H-3 20 154
< 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 46
< LLD
< LLD 0
Crops - Cabbage 1-131 3
0.021
< LLD
< LLD 0
(pCi/gwet) 22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Location of Facility Goodhue, Minnesota rPower Station Docket No.
50-282, 50-306 Reporting Period January-December, 2010
( 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' Range' Locationd RangeC Rangec Resultse Fish GS 4
(pCi/g wet)
K-40 0.10 2.78 (2/2)
P-13, Downstream 2.78(2/2) 2.73 (2/2) 0 (2.74-2.82) 3.5 mi @ 113 0/ESE (2.74-2.82)
(2.68-2.79)
Mn-54 0.016
< LLD
< LLD 0
Fe-59 0.038
< LLD
< LLD 0
Co-58 0.015
< LLD
< LLD 0
Co-60 0.014
< LLD
< LLD 0
Zn-65 0.017
< LLD
< LLD 0
Zr-Nb-95 0.018
< LLD
< LLD 0
Cs-134 0.012
< LLD
< LLD 0
Cs-137 0.014
< LLD
< LLD 0
Ba-La-140 0.057
< LLD
< LLD 0
Invertebrates GS 4
(pCi/g wet)
Be-7 0.91
< LLD
< LLD 0
K-40 1.50
< LLD
< LLD 0
Mn-54 0.064
< LLD
< LLD 0
Co-58 0.069
< LLD
< LLD 0
Co-60 0.060
< LLD
< LLD 0
Zn-65 0.093
< LLD
< LLD 0
Zr-Nb-95 0.086
< LLD
< LLD 0
Ru-103 0.090
< LLD
< LLD 0
Ru-105 0.50
< LLD
< LLD 0
Cs-134 0.044
< LLD
< LLD 0
Cs-137 0.054
< LLD
< LLD 0
Ba-La-140 0.25
< LLD
< LLD 0
Ce-141 0.10
< LLD
< LLD 0
Ce-144 0.34
< LLD
< LLD 0
23
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota (County, State)
Docket No.
50-282, 50-306 Reporting Period January-December, 2010 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 Bottom and GS 6
Shoreline Be-7 0.28 0.46(1/4)
P-6. Lock and Dam #3 0.46(1/2)
< LLD 0
Sediments 1.6 mi @ 129 0/SE (pCi/g dry)
K-40 0.50 7.42 (4/4)
P-20, Upstream 9.58 (2/2) 9.58 (2/2) 0 (5.40-8.65) 0.9 mi @ 45c/NE (8.68-10.48)
(8.68-10.48)
Mn-54 0.023
< LLD
< LLD 0
Co-58 0.030
< LLD
< LLD 0
Co-60 0.019
< LLD
< LLD 0
Zn-65 0.058
< LLD
< LLD 0
Zr-Nb-95 0.045
< LLD
< LLD 0
Ru-103 0.036
< LLD
< LLD 0
Ru-106 0.16
< LLD
< LLD 0
Cs-134 0.020
< LLD
< LLD 0
Cs-137 0.018
< LLD
< LLD 0
Ba-La-140 0.136
< LLD
< LLD 0
Ce-141 0.053
< LLD
< LLD 0
Ce-144 0.12
< LLD
< LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.
Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.
24
6.0 REFERENCES
CITED Arnold, J. R. and H. A. AI-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.
Environmental, Inc., Midwest Laboratory.
2001a through 2011a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2010.
2001b through 2011b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2010.
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.
2009.
Quality Assurance Program Manual, Rev. 2, 10 November 2009.
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, 2010.
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.
25
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).
2007.
RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981-2005.
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
Xcel Energy Corporation.
2009 to 2011. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January I to December 31, 2008 through 2010. Minneapolis, Minnesota.
2009 to 2011.
Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2010.
Minneapolis, Minnesota.
26
AT Environmental, Inc.
A I Midwest Laboratory 700 LenoWehr Rood
- Nowfhbrok, IL 60062-23 10 phone (847) 564-0700
- far (847) 56"4-4517 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, 2010 through December, 2010
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interiaboratory 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 ANALYSES' One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter
> 100 pCi/liter or kg 5% of known value Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium Iodine-131, Iodine-1 29b Uranium-238, Nickel.63b Technetium-99b Iron-55b Other Analyses b 5 to 50 pCi/liter or kg
> 50 pCi/liter or kg 5.0 pCi/liter 10% of known value 2 to 30 pCi/liter or kg
> 30 pCi/liter or kg 0.1 g/liter or kg
-< 20 pCi/liter
> 20 pCi/liter
- s 100 pCi/liter
> 100 pCi/liter
_5 4,000 pCi/liter
> 4,000 pCi/liter
? 0.1 pCi/liter a 0.1 pCi/liter, gram, or sample
-5 55 pCi/liter
> 55 pCi/liter S 35 pCi/liter
> 35 pCi/liter 50 to 100 pCi/liter
> 100 pCi/liter 5.0 pCI/liter 10% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value 169.85 x (known)0°,933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 10 pCI/liter 10% of known value 20% of known value From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Result" Limits Acceptance STW-1205 STW-1205 STW-1206 STW-1206 STW-1206 STW-1206 STW-1206 04/05/10 04/05/10 04/05110 04/05/10 04/05/10 04/05/10 04/05/10 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 63.0 +/- 5.7 37.4 +/- 2.4 63.6 +/- 3.3 83.3 +/- 2.9 71.0 +/- 3.4 145.5 +/- 5.1 194.9 +/- 7.8 60.4 41.3 65.9 84.5 71.6 146.0 186.0 32.9 37.5 STW-1207 04105/10 Gr. Alpha 26.5 +/- 1.7 STW-1207 04/05110 Gr. Beta 34.5 +/- 1.6 STW-1208 04/05/10 1-131 STW-1209 STW-1209 STW-1209 STW-1210 04/05/10 04/05110 04/05/10 04/05/10 Ra-226 Ra-228 Uranium H-3 STW-1224 10104/10 Sr-89 STW-1224 10/04/10 Sr-90 22.7 +/- 0.8 15.2 +/- 0.7 15.6 +/- 1.8 59.5 +/- 0.7 12955 +/- 332 65.3 +/- 5.7 39.9 +/- 2.3 67.2 +/- 4.3 53.2 +/- 3.3 47.3 +/- 5.1 118.0 +/- 5.9 107.0 +/- 8.7 STW-1225 STW-1225 STW-1225 STW-1225 STW-1225 10/04/10 10/04/10 10/04110 10/04/10 10/04/10 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 26.4 14.6 15.1 62.3 12400.0 68.5 43.0 68.9 53.4 43.2 123.0 102.0 42.3 36.6 27.5 11.4 9.9 36.8 12900.0 48.6 - 68.2 30.4 - 47.4 54.9 - 72.5 76.0 - 95.3 58.4 - 78.8 131.0 - 163.0 167.0 - 219.0 16.9 -42.6 24.7 -45.0 21.9 -31.1 10.9 - 16.8 10.1 - 18.3 50.7 - 69.1 10800 - 13600 55.8 - 76.7 31.7 -49.3 57.5 - 75.8 48.1 -61.3 34.5 - 47.5 111.0 - 138.0 91.8 -122.0 21.9 -53.7 24.0 - 44.2 22.9 - 32.3 8.5 - 13.2 6.4 -12.3 29.8 -41.0 11200 - 14200 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-1226 10/04/10 Gr. Alpha 30.7 +/- 2.9 STW-1226 10/04/10 Gr. Beta 32.7 +/- 0.8 STW-1227 10/04/10 1-131 STW-1228 STW-1228 STW-1228 STW-1229 10/04/10 10/04/10 10/04/10 10/04/10 Ra-226 Ra-228 Uranium H-3 28.6 +/- 1.1 11.8 +/-0.6 12.0 +/- 1.8 34.8 +/- 0.4 13682 +/- 352 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 ior three determinations.
'Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
Al-1
TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value
+/- 2 sigma Limits Acceptance Environmental, Inc.
2010-1 6/81.
2010-1 6/81 2010-1 6/8/
2010-1 6/8/
2010-1 6/81 2010-1 6/8/
2010-1 6/8/
2010-1 618/
2010-1 6181 2010-1 6181 2010-1 6/8/
2010-1 6/81 2010-1 618)
Environmental. Inc.
2010-2 1211 2010-2 12/1 2010-2 12/1:
2010-2 12/1:
2010-2 12/1 2010-2 12/1; 2010-2 12/11 2010-2 12/1.
2010-2 12/1.
2010-2 12/1 2010-2 1211 2010 2010 2010 2010 2010 2010 2010 2010 2010
/2010
'2010
'2010 2010 30 cm.
40 cm.
50 cm.
60 cm.
70 cm.
75 cm.
80 cm.
90 cm.
100 cm.
110 cm.
120 cm.
150 cm.
180 cm.
75.07 42.23 27.03 18.77 13.79 12.01 10.56 8.34 6.76 5.58 4.69 3.00 2.09 90.78 +/- 3.60 50.88 +/- 3.59 32.12 +/- 1.90 21.80 +/- 0.90 15.38 +/- 1.39 11.30 +/- 1.07 10.90 +/- 0.61 7.84 +/- 0.83 6.61 +/- 0.52 4.29 +/- 0.55 3.64 +/- 0.33 2.82 +/- 0.84 1.55 +/- 0.23 52.55 - 97.59 29.56 - 54.90 18.92 -35.14 13.14 -24.40 9.65 - 17.93 8.41 - 15.61 7.39 - 13.73 5.84 - 10.84 4.73 - 8.79 3.91 - 7.25 3.28 -6.10 2.10 - 3.90 1.46 -2.72 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 3/2010 3/2010 3/2010 3/2010 3/2010 3/2010 3/2010 3/2010 3/2010 3/2010 3/2010 100 cm.
110 cm.
120 cm.
150 cm.
180 cm.
40 cm.
50 cm.
60 cm.
60 cm.
80 cm.
90 cm.
4.94 4.09 3.43 2.2 1.53 30.89 19.77 13.73 13.73 7.72 6.1 4.65 +/- 0.57 3.50 +/- 0.74 2.68 +/- 0.36 1.75 +/- 0.42 1.32 +/- 0.52 38.56 +/- 2.11 23.35 +/- 1.82 14.53 +/- 1.24 15.84 +/- 1.53 8.33 +/- 0.74 5.93 +/- 0.73 3.46 - 6.42 2.86 - 5.32 2.40 - 4.46 1.54 - 2.86 1.07 - 1.99 21.62 - 40.16 13.84 - 25.70 9.61 -17.85 9.61 - 17.85 5.40 - 10.04 4.27 - 7.93 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A2-1
TABLE A-3. In-House "Spike" Samples Concentration (pCiIL)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 '
Activity Limitsd Acceptance SPW-12648 SPW-279 SPW-391 W-21210 W-21710 W-21710 SPAP-669 SPAP-671 SPAP-671 SPMI-674 SPMI-674 SPMI-674 SPW-676 SPW-676 SPW-676 SPW-678 SPF-680 SPF-680 SPW-682 SPW-2871 W-40510 W-40510 SPW-2083 W-51310 SPW-3181 SPW-3272 SPW-3278 SPW-3280 SPAP-3270 SPAP-3270 SPW-3274 SPW-3274 SPW-3274 SPW-3274 SPMI-3276 SPMI-3276 SPMI-3276 SPMI-3276 1/20/2010 1/27/2010 2/4/2010 211212010 2117/2010 2/1712010 2/25/2010 2125/2010 2/25/2010 2/25/2010 2125/2010 2125/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2125/2010 2/25/2010 4/5/2010 4/5/2010 4/5/2010 4/28/2010 5/13/2010 6117/2010 6/25/2010 612512010 6/25/2010 6/2812010 612812010 612812010 612812010 6128/2010 6/28/2010 6/2812010 6/2812010 6/28/2010 6/2812010 Ra-228 U-238 Ni-63 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 H-3 Cs-134 Cs-137 Tc-99 Ra-228 Gr. Alpha Gr. Beta U-238 Ra-226 Tc-99 H-3 Fe-65 C-14 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Sr-90 Co-60 Cs-134 Cs-137 Sr-90 40.04 +/- 2.99 4.52 +/- 0.22 179.70 +/- 2.96 16.05 +/- 0.39 17.54 +/- 0.37 42.47 +/- 0.39 45.78 +/- 0.11 10.56 +/- 3.15 105.36 +/- 3.15 67.38 +/- 5.65 60.61 +/- 6.28 173.80 +/- 10.30 66.13 +/- 5.22 51.54 +/- 5.97 179.30 +/- 9.95 59213.70 +/- 709.90 402.56 +/- 22.40 2267.90 +/- 75.60 29.70 +/- 1.51 33.91 + 2.85 20.65 +/- 0.42 44.72 +/- 0.40 4.20 +/- 0.32 17.04 +/- 0.50 29.87 +/- 1.09 5489.00 +/- 224.00 17054.00 +/- 348.00 3410.60 +/- 9.75 12.24 + 3.13 103.92 +/- 7.14 67.48 +/- 5.53 49.55 +/- 6.11 58.85 +/- 6.54 41.59 +/- 1.83 66.80 +/- 5.25 48.20 +/- 3.88 62.46 +/- 6.33 43.32 +/- 1.63 40.54 4.17 209.62 16.77 20.00 45.20 49.24 10.38 109.20 68.79 51.91 163.80 68.79 51.91 163.80 60407.70 415.00 2180.00 32.34 36.80 20.00 45.20 4.17 16.77 32.34 5928.00 19614.00 4738.00 10.38 109.20 65.84 46.38 54.17 42.72 65.84 46.38 54.17 42.72 28.38 - 52.70 0.00 - 16.17 146.73 - 272.51 11.74 - 21.80 10.00 - 30.00 35.20 - 55620 29.54 - 68.94 0.38 -20.38 98.28 - 120.12 58.79 - 78.79 41.91 - 61.91 147.42 - 180.18 58.79 - 78.79 41.91 -61.91 147.42 - 180.18 48326.16 -72489.24 373.50 - 456.50 1962.00 - 2398.00 20.34 - 44.34 25.76 - 47.84 10.00 - 30.00 35.20 - 55.20 0.00 - 16.17 11.74 - 21.80 20.34 - 44.34 4742.40 -7113.60 15691.20 - 23536.80 2842.80 - 6633.20 0.38 - 20.38 98.28 - 120.12 55.84 -75.84 36.38 - 56.38 44.17 -64.17 34.18 -51.26 55.84 - 75.84 36.38 - 56.38 44.17 -64.17 34.18 -51.26 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 "Spike" Samples Concentration (pCi/L)'
Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limitsc Acceptance SPW-5081 W-90910 W-90910 W-91010 SPW-2874 XWW-5302 XWW-5302 XWW-5302 XWW-5302 SPW-6035 W-120110 W-1 20110 W-121610 9/9/2010 9/9/2010 9/9/2010 9/10/2010 9/23/2010 10/6/2010 10/6/2010 10/612010 10/6/2010 10121/2010 1211/2010 12/1/2010 12/16/2010 Tc-99 Gr. Alpha Gr. Beta Ra-226 Ra-228 Ba-133 Co-60 Cs-134 Cs-137 U-238 Gr. Alpha Gr. Beta Ra-226 30.22 +/- 1.06 20.95 f 0.43 45.20 +/- 0.41 17.48 0 0.50 34.60 +/- 2.68 154.13 +/- 8.90 24.65 +/- 4.11 14.03 +/- 3.87 61.16 +/- 6.08 4.52 +/- 0.20 20.27 +/- 0.41 46.75 +/- 0.41 17.99 +/- 0.43 32.34 20.00 45.20 16.77 36.80 155.21 23.28 13.95 59.22 4.17 20.00 45.20 16.77 20.34 - 44.34 10.00 - 30.00 35.20 - 55.20 11.74 - 21.80 25.76 - 47.84 139.69 - 170.73 13.28 - 33.28 3.95 -23.95 49.22 - 69.22 0.00 - 16.17 10.00 - 30.00 35.20 - 55.20 11.74 - 21.80 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCiImP), and solid samples (pCi/g).
' Laboratory codes as follows: W (water), Ml (milk), AP (air filter), SO (soil), VE (vegetation),
CH (charcoal canister), F (fish).
Results are based on single determinations.
Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2G.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
A3-2
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)8 Lab Code Sample Date Analysisb Laboratory results (4.66o)
Acceptance Type LLD Activityc Criteria (4.66 a)
SPW-12658 SPW-280 SPW-392 W-21210 W-21710 W-21710 SPAP-668 SPAP-670 SPAP-670 SPMI-672 SPMI-672 SPW-675 SPW-675 SPW-675 SPF-679 SPF-679 SPW-681 SPW-2881 W-4051 0 W-4051 0 SPW-2084 W-5131 0 SPW-3271 SPW-3278 SPW-3279 SPAP-3269 SPAP-3269 SPW-3273 SPW-3273 SPW-3273 SPW-3273 SPMI-3275 SPMI-3275 SPMI-3275 SPMI-3275 Water Water Water Water Water Water Air Filter Air Filter Air Filter Milk Milk Water Water Water Fish Fish Water Water Water Water Water Water Water Water water Air Filter Air Filter Water Water Water water Milk Milk Milk Milk 1/20/2010 1/27/2010 2/4/2010 2/1212010 2/17/2010 2/17/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 4/5/2010 4/5/2010 4/5/2010 4/28/2010 5/13/2010 6/25/2010 6/25/2010 6/2512010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/25/2010 6/28/2010 6128/2010 6/28/2010 6/2812010 Ra-228 U-238 Ni-63 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Cs-137 Cs-137 1-131(G)
Cs-134 Cs-137 Tc-99 Ra-228 Gr. Alpha Gr, Beta U-238 Ra-226 H-3 Fe-55 C-14 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 Sr-90 Cs-134 Cs-137 1-131(G)
Sr-90 0.79 0.18 15.90 0.03 0.41 0.73 0.11 1.87 2.31 3.52 6.09 1.55 2.69 5.68 10.94 18.37 16.11 0.89 0.40 0.75 0.14 0.03 151.60 634.50 8.57 1.71 2.42 1.64 3.89 4.29 0.50 3.33 3.82 3.71 0.58 0.61 +/- 0.44 0.07 +/- 0.13
-11.80 +/- 9.40 0.06 +/- 0.02 0.09 +/- 0.30 0.23 +/- 0.52 0.008 +/- 0.002
-10.75 +/- 9.53 0.22 +/- 0.44
-0.20 1 0.26
-0.09 +/- 0.52 0.03 +/- 0.10 0.06 +/- 0.02
-58.10 +/- 71.90 256.80 +/- 396.40
-1.84 +/- 5.18
-0.04 +/- 0.22 0.81 +/- 0.36 2
1 20 3.2 3.2 100 100 10 20 10 10 20 100 100 10 2
1 3.2 1
1 200 1000 200 100 100 10 10 10 1
10 10 20 1
A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)8 Lab Code Sample Date Analysisb Laboratory results (4.66o)
Acceptance Type LLD Activityc Criteria (4.66 a)
SPW-5080 W-90910 W-90910 W-91010 SPW-2884 SPW-6036 W-120110 W-1 20110 W-121610 BKW-120610 BKW-120610 BKW-120610 BKW-120610 W-121610 Water Water Water Water Water Water Water Water Water water water water water Water 9/9/2010 9/9/2010 9/9/2010 9/10/2010 9/23/2010 10/21/2010 12/1/2010 12/1/2010 12/16/2010 12/6/2010 12/6/2010 1216/2010 12/6/2010 12/16/2010 Tc-99 Gr. Alpha Gr. Beta Ra-226 Ra-228 U-238 Gr. Alpha Gr. Beta Ra-226 Ba-133 Co-60 Cs-1 34 Cs-1 37 Ra-226 2.15 0.39 0.78 0.04 0.71 0.11 0.43 0.75 0.03 5.66 4.49 4.41 5.33 0.03
-0.71 + 1.29 0.10 + 0.28
-0.09 +/- 0.55 0.07 +/- 0.03 1.14 + 0.46 0.07 +/- 0.10
-0.05 +/- 0.29
-0.08 + 0.53 0.04 +/- 0.02 10 1
3.2 1
2 1
1 3.2 1
10 10 10 10 1
0.04 +/- 0.02 9 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b 1-131(G): iodine-131 as analyzed by gamma spectroscopy.
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)f Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 CF-20, 21 CF-20, 21 CF-41, 42 CF-41, 42 CF-41, 42 MI-111, 112 DW-10010, 10011 DW-10010, 10011 WW-215, 216 DW-10022, 10023 DW-10022, 10023 WW-424, 425 DW-10034, 10035 DW-10034, 10035 SW-382, 383 DW-10046, 10047 DW-10046, 10047 WW-693,694 SW-782, 783 SW-782, 783 MI-946, 947 W-1035, 1036 W-1035, 1036 SW-1285, 1286 W-1103, 1104 WW-1193, 1194 LW-1909, 1910 LW-1909, 1910 DW-10068, 10069 DW-10070, 10071 DW-10070, 10071 AP-1729, 1730 AP-1782, 1783 E-1392, 1393 E-1392, 1393 WW-1422, 1423 SW-1464, 1465 XW-1666, 1667 SG-1532, 1533 SG-1532, 1533 1/412010 114/2010 1/4/2010 1/4/2010 1/4/2010 1/4/2010 1/1212010 1/13/2010 1113/2010 1/18/2010 1/21/2010 1/21/2010 1/28/2010 1/28/2010 1/28/2010 2/1/2010 2/2/2010 2/2/2010 2/23/2010 3/1/2010 3/1/2010 3/9/2010 3/17/2010 3/17/2010 3/17/2010 3/18/2010 3/18/2010 3/24/2010 3/25/2010 3/25/2010 3/29/2010 3/29/2010 3/30/2010 3/30/2010 4/1/2010 4/1/2010 4/1/2010 4/1/2010 4/1/2010 4/6/2010 4/6/2010 Gr. Beta K-40 Sr-90 Be-7 Gr. Beta K-40 K-40 Ra-226 Ra-226 H-3 Ra-226 Ra-228 H-3 Ra-226 Ra-228 Gr. Beta Ra-226 Ra-228 H-3 Gr. Beta K-40 K-40 Ra-226 Ra-228 H-3 H-3 H-3 H-3 H-3 Gr. Alpha Ra-226 Ra-228 Be-7 Be-7 Gr. Beta K-40 Gr. Beta H-3 Fe-55 Ac-228 Pb-214 10.96 +/- 0.27 8.88 +/- 0.48 0.02 +/- 0.01 0.45 +/- 0.11 3.26 +/- 0.10 2.85 +/- 0.36 1276.00 +/- 98.96 0.48 +/- 0.10 1.59 +/- 0.61 211.16 +/- 87.57 8.57 +/- 0.91 5.68 +/- 1.36 422.30 +/- 95.90 0.93 +/- 0.13 1.16 +/- 0.62 2.22 +/- 0.68 6.11 +/- 0.91 5.84 +/- 1.11 1458.00 +/- 131.00 1.05 +/- 0.42 1.50 +/- 0.15 1485.00 +/- 109.30 11.78 +/- 1.51 5.31 +/- 2.42 377.60 +/- 104.50 12690 +/- 333 227.38 +/- 95.19 1529.40 +/- 144.60 2.40 +/- 0.97 1.08 +/- 1.02 1.58 +/- 0.17 1.16 +/- 0.47 0.08 +/- 0.01 0.08 +/- 0.01 1.59 +/- 0.07 902.30 +/- 179.00 22.23 +/- 1.58 262.06 +/- 98.96 7.05 +/- 0.71 19.45 +/- 1.14 12.66 +/- 0.52 11.30 +/- 0.28 8.27 +/- 0.78 0.02 +/- 0.01 0.41 +/- 0.14 3.33 +/- 0.11 3.04 +/- 0.22 1334.80 +/- 105.00 0.43 +/- 0.10 1.13 +/- 0.47 291.90 +/- 91.31 10.20 +/- 1.08 3.59 +/- 1.17 484.20 +/- 98.50 0.90 +/- 0.11 1.29 +/- 0.62 1.18 +/- 0.71 7.88 +/- 1.17 6.13 +/- 1.14 1531.00 +/- 133.00 1.60 + 0.43 1.52 +/- 0.15 1347.40 +/- 108.30 9.76 +/- 1.26 8.45 +/- 2.78 282.70 +/- 100.70 12679 +/-333 251.81 +/- 96.15 1404.40 +/- 140.80 1.99 +/- 1.03 1.35 +/- 1.05 1.69 +/- 0.16 1.34 +/- 0.49 0.08 +/- 0.01 0.09 +/- 0.01 1.66 +/- 0.08 1076.70 +/- 202.90 19.42 +/- 1.40 233.18 +/- 97.75 7.25 +/- 0.74 20.07 +/- 1.19 13.32 +/- 0.54 11.13 +/-_0.19 8.58 +/- 0.46 0.02 +/- 0.00 0.43 +/- 0.09 3.30 +/- 0.07 2.95 +/- 0.21 1305.40 +/- 72.14 0.46 +/- 0.07 1.36 +/- 0.39 251.53 +/- 63.26 9.39 +/- 0.71 4.64 +/- 0.90 453.25 + 68.74 0.92 +/- 0.09 1.23 +/-0.44 1.70 +/- 0.49 7.00 + 0.74 5.99 +/- 0.80 1494.50 +/- 93.34 1.33 +/- 0.30 1.51 +/-0.11 1416.20 +/- 76.93 10.77 +/- 0.98 6.88 +/- 1.84 330.15 +/- 72.56 12685 +/-235 239.60 +/- 67.65 1466.90 +/- 100.91 2.20 +/- 0.71 1.22 +/- 0.73 1.64 +/- 0.12 1.25 +/- 0.34 0.08 +/- 0.01 0.09 +/- 0.01 1.63 +/- 0.05 989.50 +/- 135.29 20.83 +/- 1.06 247.62 +/- 69.55 7.15 +/- 0.51 19.76 +/- 0.82 12.99 +/- 0.38 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 A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)'
Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-1506, 1507 SG-1506. 1507 SW-1645. 1646 DW-10095, 10096 DW-10095, 10096 W-2013, 2014 W-2013, 2014 WW-2431, 2432 SO-2037, 2038 W-2325, 2326 AP-2149, 2150 LW-2191, 2192 G-2170, 2171 G-2170, 2171 G-2170, 2171 SWT-2282, 2283 WW-2233, 2234 WW-2233, 2234 TD-2410,2411 SG-2347, 2348 F-2463, 2464 XW-2834, 2835 WW-2597, 2598 MI-2639, 2640 SL-2771, 2772 SL-2771, 2772 SW-2879, 2880 SG-2904, 2905 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 WW-3060, 3061 VE-3351, 3352 VE-3351, 3352 W-3469, 3470 SG-3539, 3540 SG-3539, 3540 AP-3743, 3744 4/7/2010 4/7/2010 4/14/2010 411412010 4/14/2010 4/1612010 4/16/2010 4/19/2010 4/22/2010 4/26/2010 4/29/2010 4/29/2010 5/3/2010 5/312010 5/3/2010 5/4/2010 5/512010 5/5/2010 5/10/2010 5/13/2010 5/17/2010 5/20/2010 5/25/2010 5/25/2010 6/1/2010 6/1/2010 6/1/2010 6/7/2010 6/812010 6/8/2010 6/8/2010 6/8/2010 6/8/2010 6/8/2010 6/14/2010 6/21/2010 6/21/2010 6/25/2010 6/29/2010 6/29/2010 6130/2010 Ac-228 Pb-214 H-3 Ra-226 Ra-228 Gr. Alpha Gr. Beta H-3 K-40 H-3 Be-7 Gr. Beta Be-7 Gr. Beta K-40 Gr. Beta Gr. Alpha Gr. Beta H-3 Ra-226 K-40 H-3 H-3 K-40 Gr. Beta K-40 H-3 Gamma Be-7 Cs-137 Gr. Beta K-40 U-233/4 U-238 H-3 Be-7 K-40 H-3 Ac-228 Pb-214 Be-7 1.28 +/- 0.15 1.24 +/- 0.10 312.00 +/- 100.00 4.87 +/- 0.53 2.49 +/- 0.56 33.45 +/- 3.98 14.83 +/- 0.96 400.40 +/- 98.10 2.89 +/- 0.40 399.00 +/- 92.00 0.14 +/- 0.08 1.16 +/- 0.56 0.91 +/- 0.32 8.73 +/- 0.22 7.24 +/- 0.44 0.73 +/- 0.52 1.56 +/- 1.47 2.33 +/- 1.14 431.92 +/- 96.50 37.34 +/- 0.42 2.69 +/- 0.56 209.53 +/- 83.34 288.10 +/- 98.20 1428.80 +/- 110.60 5.33 +/- 0.18 4.67 +/- 0.46 335.60 +/- 92.60 5.20 +/- 0.20 0.12 +/- 0.03 0.01 +/- 0.00 22.80 +/- 2.05 11.30 +/- 1.20 0.12 +/- 0.02 0.12 +/- 0.01 199.16 +/- 95.13 1.86 +/- 0.25 6.10 +/- 0.52 573.00 +/- 110.00 14.55 +/- 0.51 15.50 +/- 1.56 0.07 +/- 0,01 1.15 +/- 0.14 1.22 +/- 0.09 352.00 +/- 102.00 5.57 +/- 0.61 2.76 +/- 0.60 39.11 +/- 4.54 16.07 +/- 0.96 377.70 +/- 97.10 2.89 +/- 0.51 429.00 +/- 94.00 0.26 +/- 0.12 0.79 +/- 0.52 0.86 +/- 0.26 9.01 +/- 0.23 7.48 +/- 0.78 1.58 +/- 0.57 2.27 +/- 1.65 4.08 +/- 1.24 403.05 +/- 95.26 37.91 +/- 0.36 2.65 +/- 0.38 263.11 +/- 85.95 155.80 +/- 93.40 1408.60 +/- 107.40 5.30 +/- 0.18 4.88 +/- 0.46 356.40 +/- 93.60 5.50 +/- 0.10 0.13 +/- 0.08 0.01 +/- 0.00 23.84 +/- 2.44 11.70 +/- 1.20 0.13 + 0.01 0.13 +/- 0.01 203.59 +/- 95.34 1.85 +/- 0.27 6.10 +/- 0.57 525.00 +/- 108.00 14.57 +/- 0.44 16.80 +/- 1.71 0.07 +/- 0.01 1.22 +/- 0.10 1.23 +/- 0.07 332.00 +/- 71.42 5.22 +/- 0.40 2.63 +/- 0.41 36.28 +/- 3.02 15.45 +/- 0.68 389.05 +/- 69.01 2.89 +/- 0.32 414.00 +/- 65.76 0.20 +/- 0.07 0.97 +/- 0.38 0.89 +/- 0.21 8.87 +/- 0.16 7.36 +/- 0.45 1.16 +/- 0.39 1.92 +/- 1.10 3.21 +/- 0.84 417.48 +/- 67.80 37.63 +/- 0.28 2.67 +/- 0.34 236.32 +/- 59.86 221.95 +/- 67.76 1418.70 +/- 77.08 5.32 +/- 0.13 4.78 +/- 0.33 346.00 +/- 65.83 5.35 +/- 0.11 0.13 +/- 0.04 0.01 +/- 0.00 23.32 +/- 1.59 11.50 +/- 0.85 0.13 +/- 0.01 0.13 +/- 0.01 201.38 +/- 67.34 1.85 +/- 0.18 6.10 +/- 0.39 549.00 +/- 77.08 14.56 +/- 0.34 16.15 +/- 1.16 0.07 +/- 0.01 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)o Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-3427,3428 G-3427,3428 SW-3512, 3513 AP-3680, 3681 VE-3791, 3792 WW-3934,3935 DW-10135, 10136 DW-10135, 10136 W-4063,4064 DW-10143,10144 DW-10148, 10149 DW-10148, 10149 DW-10159, 10160 DW-10159,10160 SL-4106, 4107 SL-4106, 4107 SL-4106, 4107 SG-4085, 4086 SG-4085, 4086 SWT-4304, 4305 BS-4398, 4399 BS-4398,4399 VE-4531, 4532 VE-4531, 4532 VE-4531, 4532 VE-4531, 4532 DW-10170,10171 OWn10 1 7 0,10171 AP-4766, 4767 DW-10182, 10183 VE-4928, 4929 SL-4883, 4884 SL-4883,4884b W-5135,5136 SW-5071, 5072 XWW-5246, 5247 7/11/2010 7/1/2010 71612010 7/8/2010 7/1212010 7/12/2010 7/13/2010 7/13/2010 7/14/2010 7/19/2010 7/2312010 7/23/2010 7/23/2010 7123/2010 8/2f2010 8/212010 8/2/2010 8/3/2010 8/3/2010 8/3/2010 8/10/2010 8110/2010 8/1112010 8/11/2010 8/11/2010 8/11/2010 8113/2010 8/13/2010 8/26/2010 8/27/2010 9/11/2010 9/1/2010 9/1/2010 9/6/2010 9/13/2010 9/14/2010 Be-7 K-40 H-3 Be-7 K-40 H-3 Ra-226 Ra-228 H-3 Gr. Alpha Ra-226 Ra-228 Ra-226 Ra-228 Be-7 Gr. Beta K-40 Ra-226 Ra-228 Gr. Beta Cs-137 K-40 Gr. Beta K-40 U-23314 U-238 Ra-226 Ra-228 Be-7 Ra-226 K-40 Gr. Beta K-40 H-3 H-3 H-3 1.18 +/- 0.29 8.79 +/- 0.64 441.00 +/- 103.00 0.16 +/- 0.08 4.37 +/- 0.38 3091.00 +/- 187.00 0.18 +/- 0.07 0.76 +/- 0.44 469.00 +/- 104.00 2.84 +/- 0.74 2.08 +/- 0.39 1.90 +/- 0.61 0.91 +/- 0.14 1.41 +/- 0.54 2.05 +/- 0.20 5.06 +/- 0.32 1.89 +/- 0.24 20.23 +/- 2.04 15.88 +/- 0.41 2.08 +/- 1.07 78.80 +/- 33.50 13708 +/- 795 36.20 +/- 0.90 27.31 +/- 0.70 0.014 +/- 0.003 0.012 +/- 0.003 1.32 +/- 0.14 2.55 +/- 0.78 0.18 +/- 0.09 0.15 +/- 0.08 2.99 +/- 0.41 6.90 +/- 0.20 7.15 +/- 0.99 658.60 +/- 110.80 186.70 +/- 101.10 1990.60 +/- 157.70 1.06 +/- 0.25 7.85 +/- 0.65 423.00 +/- 102.00 0.13 +/- 0.07 4.23 +/- 0.35 3242.00 +/- 191.00 0.26 +/- 0.07 0.81 +/- 0.41 351.00 + 99.00 2.49 +/- 0.73 2.97 +/- 0.55 2.00 +/- 0.61 0.79 +/- 0.21 1.30 +/- 0.53 2.05 +/- 0.18 4.62 +/- 0.30 1.70 +/- 0.17 21.45 +/- 2.16 16.24 +/- 0.36 2.44 +/- 0.98 94.30 +/- 51.90 12091 +/- 1110 35.80 +/- 0.90 27.58 +/- 0.62 0.014 +/- 0.003 0.010 +/- 0.002 1.26 +/- 0.14 1.76 +/- 0.71 0.25 +/- 0.13 0.11 +/- 0.07 3.18 +/- 0.28 7.10 +/- 0.20 5.07 +/- 0.51 600.90 +/- 108.50 267.30 +/- 104.40 1986.20 +/- 157.60 1.12 +/- 0.19 8.32 +/- 0.46 432.00 +/- 72.48 0.15 + 0.05 4.30 +/- 0.26 3166.50 +/- 133.65 0.22 +/- 0.05 0.79 +/- 0.30 410.00 +/- 71.79 2.67 +/- 0.52 2.53 +/- 0.34 1.95 +/- 0.43 0.85 +/- 0.13 1.36 +/- 0.38 2.05 +/- 0.13 4.84 +/- 0.22 1.80 +/- 0.15 20.84 +/- 1.49 16.06 +/- 0.27 2.26 +/- 0.73 86.55 +/- 30.89 12900 +/-683 36.00 +/- 0.64 27.45 +/- 0.47 0.014 +/- 0.002 0.011 +/- 0.002 1.29 +/- 0.10 2.16 t 0.53 0.22 +/- 0.08 0.13 +/- 0.05 3.09 +/- 0.25 7.00 +/- 0.14 6.11 +/- 0.56 629.75 +/- 77.54 227.00 +/- 72.66 1988.40 +/- 111.48 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 Fail Pass Pass Pass A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCiVL)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-5114, 5115 VE-5114, 5115 VE-5114, 5115 VE-5114, 5115 VE-5114, 5115 MI-5267, 5268 SO-5357, 5358 AP-5357, 5358 DW-10194, 10195 DW-10194, 10195 WW-5442, 5443 VE-5469,5470 BS-5886, 5887 BS-5886.5887 G-5513,5514 E-5492, 5493 E-5492, 5493 G-5512, 5513 G-5512, 5513 MI-5541, 5542 MI-5541, 5542 F-6061, 6062 F-6061, 6062 VE-5740, 5741 VE-5761, 5762 VE-5761.5762 AP-5910, 5911 WW-6294, 6295 P-6038,6039 AP-6195, 6196 WW-6366, 6367 SWU-6315,6316 SO-6336, 6337 SO-6336, 6337 SO-6336, 6337 AP-6453, 6454 BS-6475,6476 F-6658, 6659 F-6565, 6566 F-6565,6566 F-6565, 6566 SS-5761,5762 WW-7056,7057 9/9/2010 9/9/2010 9/9/2010 919/2010 9/9/2010 9/20/2010 9/2312010 9/23/2010 9123/2010 9123/2010 9/29/2010 9/29/2010 9/29/2010 9/29J2010 10/4/2010 10/4/2010 10/4/2010 1014/2010 10/4/2010 10/4/2010 10/4/2010 10/9/2010 10/9/2010 10/10/2010 10/12/2010 10/12/2010 10/14/2010 10/18/2010 10/19/2010 10121/2010 10/2312010 10/26/2010 10128!2010 10/28/2010 10/28/2010 10/28/2010 11/11/2010 11/3/2010 11/4/2010 11/4/2010 11/4/2010 11116/2010 11/30/2010 Be-7 Gr. Beta H-3 K-40 U-233/4 K-40 K-40 Be-7 Ra-226 Ra-228 H-3 K-40 Cs-137 K-40 Be-7 Gr. Beta K-40 Gr. Beta K-40 K-40 Sr-90 H-3 K-40 K-40 Be-7 K-40 Be-7 H-3 H-3 Be-7 H-3 Gr. Beta Cs-137 Gr. Beta K-40 Be-7 Gr. Beta K-40 Cs-137 Gr. Beta K-40 K-40 Gr. Beta 1.14 +/- 0.35 34.72 +/- 1.29 79367 +/- 837 22.13 +/- 0.67 0.08 +/- 0.01 1281.10 +/- 118.90 10894.00 +/- 560.00 0.11 +/- 0.02 0.40 +/- 0.10 1.61 +/- 0.65 6706.00 +/- 252.00 2.86 +/- 0.38 83.36 +/- 23.31 13913.00 +/- 775.40 6.73 +/- 0.40 1.74 +/- 0.05 1.57 +/- 0.17 10.86 +/- 0.44 7.10 +/- 0.54 1090.60 +/- 106.70 1.44 +/- 0.38 7.64 +/- 0.23 2.81 +/- 0.40 4.92 +/- 0.53 1.05 +/- 0.29 3.45 +/- 0.45 0.23 +/- 0.09 1681.49 +/- 146.32 2131.90 +/- 159.50 0.27 +/- 0.11 477.28 +/- 102.02 1.85 +/- 1.00 0.23 +/- 0.03 26.36 +/- 1.67 13.43 +/- 0.76 0.23 +/- 0.12 13.13 +/- 1.83 2.79 +/- 0.40 0.06 +/- 0.02 3.90 +/- 0.10 2.63 + 0.45 15.42 +/- 1.57 2.09 +/- 0.84 1.48 +/- 0.26 33.38 +/- 1.23 79421 +/- 837 21.93 +/- 0.58 0.06 +/- 0.01 1218.60 +/- 110.80 11175.00 +/- 760.00 0.09 +/- 0.02 0.20 +/- 0.10 0.88 +/- 0.47 6510.00 +/- 249.00 2.57 +/- 0.37 58.97 +/- 21.16 13582.00 +/- 710.30 6.36 +/- 0.41 1.77 +/- 0.05 1.55 +/- 0.18 10.39 +/- 0.39 7.41 +/- 0.59 1246.10 +/- 102.60 1.11 +/- 0.35 7.49 +/- 0.23 2.56 +/- 0.50 4.61 +/- 0.34 0.69 +/- 0.15 3.34 +/- 0.29 0.30 +/- 0.12 1637.41 +/- 144.98 2212.00 +/- 161.70 0.26 +/- 0.13 529.99 +/- 104.27 1.40 +/- 0.90 0.23 +/- 0.04 24.78 +/- 1.52 13.73 +/- 0.81 0.30 +/- 0.15 12.75 +/- 1.67 2.94 +/- 0.44 0.04 +/- 0.01 4.10 +/- 0.10 2.57 +/- 0.35 15.87 t 1.21 2.22 +/- 0.80 1.31 +/- 0.22 34.05 t 0.89 79394 +/- 592 22.03 + 0.44 0.07 +/- 0.01 1249.85 t 81.26 11034.50 +/- 472.02 0.10 +/- 0.01 0.30 +/- 0.07 1.25 +/- 0.40 6608.00 +/- 177.13 2.72 +/- 0.26 71.17 +/- 15.74 13747.50 +/- 525.78 6.55 +/- 0.29 1.76 +/- 0.04 1.56 +/- 0.12 10.63 +/- 0.29 7.26 +/- 0.40 1168.35 +/- 74.01 1.27 +/- 0.26 7.57 +/- 0.16 2.68 +/- 0.32 4.77 +/- 0.32 0.87 +/- 0.16 3.40 +/- 0.27 0.26 +/- 0.08 1659.45 +/- 102.99 2171.95 +/- 113.56 0.26 +/- 0.09 503.64 +/- 72.94 1.62 +/- 0.67 0.23 +/- 0.02 25.57 +/- 1.13 13.58 +/- 0.56 0.26 +/- 0.10 12.94 +/- 1.24 2.86 +/- 0.30 0.05 +/- 0.01 3.96 +/- 0.06 2.60 +/- 0.29 15.65 +/- 0.99 2.16 +/- 0.58 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 A5-4
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SO-7166, 7167 11/30/2010 Cs-137 0.12 +/-0.04 0.11 +/-0.03 0.11 +/-0.03 Pass SO-7166, 7167 11/3012010 K-40 14.93 +/- 0.88 14.49 +/- 0.86 14.71 +/- 0.61 Pass WW-7412, 7413 12/6/2010 H-3 469.78 +/- 146.32 503.57 +/- 93.96 486.68 +/- 86.94 Pass MI-7187, 7188 12/8/2010 K-40 1495.10 +/- 129.00 1398.40 +/- 109.10 1446.75 +/- 84.47 Pass MI-7187, 7188 1218/2010 Sr-90 0.57 +/- 0.31 0.66 +/- 0.28 0.62 +/- 0.21 Pass WW-7255, 7256 12/8/2010 H-3 243.46 +/- 90.39 327.34 +/- 94.11 285.40 +/- 65.24 Pass AP-7276, 7277 12/9/2010 Be-7 0.13 +/- 0.07 0.18 +/- 0.10 0.16 +/- 0.06 Pass XWW-7297, 7298 12/9/2010 H-3 686.00 +/- 102.00 764.60 +/- 105.00 725.30 +/- 73.19 Pass AP-7344, 7345 12/16/2010 Be-7 0.16 +/- 0.09 0.17 +/- 0.09 0.16 +/- 0.06 Pass SWT-7480, 7481 12/28/2010 Gr. Beta 0.90 +/- 0.40 1.03 +/- 0.41 0.97 +/- 0.29 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.
Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).
Analysis was repeated, result of reanalysis: 4.83 +/- 0.29 pCi/L.
A5-5
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Code Date Analysis Laboratory result Activity Limits d Acceptance STVE-1 199 STVE-1 199 STVE-1199 STVE-1 199 STVE-1 199 STVE-1 199 03/01/10 03/01/10 03101/10 03/01/10 03/01/10 03/01/10 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 0.01 +/- 0.03 3.39 +/- 0.12 4.74 +/- 0.15 3.32 +/- 0.17 0.01 +/- 0.05 8.03 +/- 0.33 0.40 +/- 0.05 3.03 +/- 0.07 0.00 3.27 4.39 3.06 0.00 7.10 0.68 3.09 2.29 - 4.25 3.07 - 5.71 2.14 - 3.98 4.97 - 9.23 0.00 - 1.35 1.55 - 4.64 STW-1200 03/01/10 Gr. Alpha STW-1200 03/01/10 Gr. Beta STW-1201 STW-1201 STW-1201 STW-1201 STW-1 201 STW-1 201 STW-1201 STW-1201 STW-1201 STW-1201 STW-1201 STW-1201 STW-1201 STW-1201 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STAP-1203 STAP-1 203 STAP-1203 STAP-1203 STAP-1203 STAP-1203 STAP-1203 STAP-1203 03/01/10 03/01/10 03101/10 03/01/10 03101/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03101/10 03/01/10 03/01/10 03101/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03101/10 03/01/10 03/01/10 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 H-3 Mn-54 Ni-63 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Sr-90 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 1.05 + 0.08 28.90 +/- 0.40 0.06 +/- 0.05
-0.03 +/- 0.09 60.60 + 0.60 3.00 +/- 14.40 93.20 + 18.30 27.80 +/- 0.40 49.10 +/- 3.50
-0.10 +/- 0.60 0.50 +/- 0.50 1.21 +/- 0.05 1.20 +/- 0.05 42.70 +/- 0.80 520.00 +/- 10.80 599.10 +/- 2.80 666.10 +/- 4.70 774.40 +/- 4.50 562.00 +/- 15.30 866.20 _ 4.60 225.50 +/- 11.80 59.90 +/- 2.50 62.10 +/- 2.60
-1.23 +/- 1.96 0.10 + 0.01 0.01 +/- 0.02 2.63 +/- 0.19 2.21 +/- 0.34 1.66 +/- 0.22 3.42 +/- 0.26 0.02 +/- 0.06
-0.05 +/- 0.11 1.30 28.30 0.00 0.00 60.60 0.00 90.80 26.90 59.90 0.00 0.00 1.22 1.25 40.70 522.00 622.00 733.00 779.00 559.00 849.00 288.00 60.00 64.00 0.00 0.15 0.00 2.47 2.13 1.53 3.02 0.00 0.00 0.91 -1.69 19.80 - 36.80 42.40 - 78.80 63.60 - 118.00 18.80 - 35.00 41.90 - 77.90 0.85 - 1.59 0.88 - 1.63 28.50 - 52.90 365.00 - 679.00 435.00 - 809.00 513.00 - 953.00 545.00 - 1013.00 391.00 - 727.00 594.00 - 1104.00 202.00 - 374.00 42.00 - 78.00 45.00 - 83.00 0.10 -0.19 1.73 - 3.22 1.49 -2.77 1.07 - 1.99 2.11 - 3.93 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 A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits' Acceptance STAP-1204 03/01110 Gr. Alpha STAP-1204 03/01/10 Gr. Beta 0.13 +/- 0.03 1.46 +/- 0.07 0.43 1.29 0.00 -0.85 0.65 -1.94 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 08/01/10 08/01/10 08/01/10 08/01/10 08/01110 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 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 STW-1212 08/01110 Gr. Alpha STW-1212 08/01/10 Gr. Beta 0.02 +/- 0.02 36.40 +/- 4.80 28.30 +/- 1.00 29.30 +/- 2.10 44.60 +/- 1.80 48.50 +/- 20.10 503.60 +/- 12.80 38.50 +/- 2.50 0.10 +/- 0.30 49.30 +/- 3.10 1.49 +/- 0.15 1.20 +/- 0.10 9.20 +/- 1.30 28.10 +/- 0.90 2.04 +/- 0.14 2.05 +/- 0.14 32.80 +/- 3.00 1.54 +/- 0.09 4.13 +/- 0.15 9.60 +/- 0.54 0.05 +/- 0.08 4.83 1 0.26 6.45 +/- 0.66 7.12 +/- 0.66 6.05 +/- 0.74 0.10 +/- 1.60 370.00 +/- 6.00 1005.00 +/- 21.00 755.00 +/- 15.00 783.00 +/- 54.00 942.00 +/- 15.00 69.20 +/- 6.20 76.50 +/- 6.20 3.50 +/- 8.00 76.50 +/- 6.20 271.40 +/- 9.00 310.00 +/- 18.00 0.00 36.00 28.30 31.40 44.20 60.20 453.40 38.90 0.00 56.10 1.81 1.35 8.30 33.60 2.01 2.07 31.00 1.92 4.39 8.27 0.00 4.79 5.88 6.29 5.39 0.00 343.00 940.00 670.00 699.00 820.00 64.00 71.00 0.00 71.00 289.00 265.00 25.20 - 46.80 19.80 - 36.80 22.00 - 40.80 30.90 - 57.50 42.10 - 78.30 317.40 - 589.40 27.20 - 50.60 39.30 - 72.90 1.27-2.35 0.95 - 1.76 5.80 - 10.80 23.50 - 43.70 1.41 -2.61 1.45 -2.69 21.70 - 40.30 0.58 - 3.26 2.20 - 6.59 5.79 - 10.75 3.35 - 6.23 4.12 -7.64 4.40 -8.17 3.77 - 7.01 240.00 - 446.00 658.00 - 1222.00 469.00 - 871.00 489.00 - 909.00 574.00 - 1066.00 45.00 - 83.00 50.00 - 92.00 50.00 - 92.00 202.00 - 376.00 186.00 - 345.00 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 Pass Pass Pass Pass Pass Pass STVE-1213 STVE-1213 STVE-1213 STVE-1213 STVE-1213 STVE-1213 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 08101/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01110 08/01/10 08101/10 08/01/10 08/01/10 08/01/10 08101/10 08/01/10 08/01/10 08/01/10 08/01/10 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-50 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STAP-1215 08101110 Co-57 4.47 +/- 0.21 4.08 2.86 -5.30 Pass STAP-1215 08101110 Co-60 3.15 +/- 0.30 2.92 2.04 -3.80 Pass STAP-1215 08101/10 Cs-134 3.03 +/- 0.17 2.98 2.09 -3.87 Pass STAP-1215 08101/10 Cs-137 0.01 +/- 0.05 0.00 Pass STAP-1215 08/01/10 Mn-54 3.69 +/- 0.39 3.18 2.23 -4.13 Pass STAP-1215 08101/10 Sr-90 1.00 +/- 0.12 1.01 0.71 -1.31 Pass STAP-1215 08101/10 Zn-65 0.03 +/- 0.15 0.00 Pass STAP-1216 08101110 Gr. Alpha 0.01 +/- 0.01 0.00 Pass STAP-1216 08/01/10 Gr. Beta 0.54 +/- 0.05 0.50 0.25 -0.75 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
d 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.
A6-3
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8.
Concentration (pCi/L)
Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1 217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 09/20/10 09/20/10 09120/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/234 U-238 Uranium Zn-65 STAP-1218 09/20/10 Gr. Alpha STAP-1218 09/20/10 Gr. Beta STSO-1219 09120/10 STSO-1219 09/20/10 STSO-1219 09/20/10 STSO-1219 09120/10 STSO-1219 09/20/10 STSO-1219 09120/10 STSO-1219 09/20/10 STSO-1219 09/20110 STSO-1219 09/20/10 STSO-1219 09120/10 STSO-1219 09/20/10 STSO-1219 09/20/10 STSO-1219 09/20/10 STSO-1219' 09120/10 STSO-1219e 09/20110 STSO-1219 e 09/20/10 STSO-1219 09/20/10 STVE-1220 09/20/10 STVE-1220 09/20/10 STVE-1220 09120/10 STVE-1220 09/20110 STVE-1220 09/20/10 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 U-233/234 U-238 Uranium Zn-65 Co-60 Cs-134 Cs-137 K-40 Mn-54 55.6 +/- 2.9 517.1 +/- 9.1 384.6 +/- 33.7 589.4 +/- 7.1 0.0 +/- 0.0 76.5 +/- 4.0 73.0 +/- 3.8 172.9 +/- 21.3 64.9 +/- 3.9 68.0 +/- 4.0 135.5 +/- 8.7 563.1 +/- 15.3 66.1 +/- 3.2 69.9 +/- 2.5 1632.0 +/- 80.4 1063.0 +/- 120.9 1752.0 +/- 255.6 909.3 +/- 38.9 4852.0 +/- 153.5 2190.0 +/- 50.7 3584.0 +/- 42.5 10017.0 +/- 274.5 0.0 +/- 0.0 1573.0 +/- 28.2 999.0 +/- 39.2 1568.0 +/- 155.0 1445.0 +/- 142.9 599.4 +/- 69.4 633.8 +/- 71.3 1248.0 +/- 152.7 2447.0 +/- 60.1 1108.0 +/- 38.7 1161.0 +/- 57.3 1400.0 +/- 43.0 27400.0 +/- 683.4 0.0 +/- 0.0 74.1 479.0 388.0 514.0 72.9 69.6 159.0 71.8 71.2 146.0 465.0 52.3 52.7 1830.0 1120.0 2070.0 983.0 4780.0 2240.0 3530.0 10700.0 1640.0 969.0 1280.0 1180.0 1360.0 1340.0 2770.0 2300.0 1010.0 1040.0 1260.0 22600.0 43.3 -102.0 371.0 -598.0 253.0 - 480.0 386.0 - 675.0 50.0 -95.8 50.5 -90.1 70.0 -247.0 45.2 -106.0 45.6 -101.0 74.6 -232.0 322.0 - 644.0 27.1 -78.7 32.5 -77.0 1170.0 - 2580.0 669.0 - 1440.0 543.0 - 3100.0 603.0 - 1410.0 3480.0 - 6420.0 1440.0 -2700.0 2700.0 - 4580.0 7760.0 - 14500.0 1060.0 - 2310.0 580.0 - 1440.0 733.0 -1800.0 805.0 - 1570.0 862.0 - 1690.0 819.0 - 1700.0 1580.0 - 3740.0 1820.0 - 3080.0 683.0 - 1450.0 595.0 - 1440.0 924.0 - 1750.0 16200.0 - 32000.0 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 Fail Fail Fail Pass Pass Pass Pass Pass Pass A7-1
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)0.
Concentration (pCiiL)
Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 09/20/10 09120/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09120/10 09120110 09/20/10 09/20/10 09120110 09/20/10 09120/10 09/20/10 09/20110 09/20/10 09/20/10 09/20110 09/20/10 Am-241 Cm-244 Pu-238 Pu-239/40 Sr-90 U-233/234 U-238 Uranium Zn-65 Am-241 Co-60 Cs-134 Cs-137 Fe-55 Mn-54 Pu-238 Pu-239/40 Sr-90 U-2331234 U-238 Uranium Zn-65 4185.0 +/- 180.0 2329.0 +/- 132.5 4912.0 +/- 194.0 4765.0 +/- 111.0 7706.0 +/- 583.9 3862.0 +/- 203.0 3926.0 +/- 205.3 7671.0 +/- 201.2 1443.0 +/- 81.0 127.9 +/- 4.2 697.8 +/- 10.4 437.5 +/- 13.3 612.8 +/- 11.6 936.8 +/- 508.2 0.0 +/- 0.0 148.1 +/-6.0 154.1 +/-6.2 872.3 +/- 13.4 99.1 +/-4.4 103.7 +/-4.5 206.5 +/- 9.8 489.1 +/- 16.2 110.6 +/-3.5 134.6 +/-2.6 23500.0 +/- 1438.0 4760.0 2740.0 4740.0 4470.0 7810.0 4010.0 3980.0 8180.0 1210.0 176.0 714.0 492.0 625.0 825.0 162.0 148.0 921.0 109.0 108.0 221.0 489.0 146.0 143.0 2710.0 - 6540.0 1350.0 - 4270.0 2560.0 - 6940.0 2770.0 - 6100.0 4360.0 - 10400.0 2750.0 - 5320.0 2800.0 - 5030.0 5620.0 - 10600.0 874.0 - 1650.0 120.0 - 238.0 622.0 - 844.0 363.0 - 565.0 531.0 - 749.0 480.0 - 1100.0 122.0 -201.0 114.0 - 183.0 585.0 - 1230.0 82.2 - 140.0 82.5 - 134.0 159.0 - 294.0 414.0 - 610.0 64.8 -216.0 83.6 - 210.0 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 STW-1222 09/20/10 Gr. Alpha STW-1222 09120/10 Gr, Beta STW-1223 09/20/10 H-3 21600.0 14100.0 - 31900.0 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).
Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" Indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.
e Analysis was repeated using total dissolution. Results of the reanalysis, U-233/234: 1137.+/- 254 pCi/kg. U-238: 1193i +/-116 pCi/kg. Total Uranium: 2379 +/- 254 pCi/kg.
A7-2
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data Reportingq 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;xs
+/- S, and x2 +/-s2 Reported result:
x +/- s; where x = (1/2) (x1 + x2) and s = (1/2) s +
2 3.2.
Individual results:
< L1 I< 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 x,, x2.2. x are defined as follows:
1 x;n Tx S=n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1.
If the 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 a
background in unrestricted areas Air (pCi/m 3)
Water (pCi/L)
-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1
Strontium-90 500 b
-1 Iodine-1 31 2.8 x 10 Cesium-1 37 1,000 Barium-140 8,000 Iodine-131 1,000 C
Potassium-40 4,000 Gross alpha 2
Gross beta 10 6
Tritium 1 x 10 a
Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
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
TLO LOCATIONS ONE MILE RADIUS J
PLANT AREA ENLARGED PLAN
[1.00 MILE RADIUS)
[NO SCALE]
MONITORING LEGEND:
Q PRAIRIE ISLAND TLD POINTS TLO0l.DGN R*-"V. 1 D-2 REV 1
TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLO LOCATIONS MONITORING LEGEND:
) PRAIRIE ISLAND TLD POINTS REV.
TLO2.DGN
TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
() PRAIRIE ISLAND TLD POINTS REV. I D-4 TL003.DGN REV.1 D-4 TL003.OGN
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS PLANT AREA ENLARGED PLAN
[1.00 MILE RADIUS]
[NO SCALE]
MONITORING LEPENO MILK SAMPLING POINT ID NUMBERS P-IB. P-37..P-42. P-43 AIR SAMPLING POINT I1 NUMBERS P-1, P-2. P-3. P-4. P-6 hWATER SAMPLING POINT I1 NUMBERS P.5. P-6. P-8. P-q, P-l1. P-24. P-43 VEGETATION / VEGETABLES ID NUMBERS P-28, P-38. P-45 FI'SH SAMPLING POINT 10 NUMBERS P-13, P-19 INVERTEBRATES POINT 10 NUBERS P-B. P-40 SEOIMENT SAMPLING POINT ID NUMBERS P-.P1,P-20 D-5
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS t;
4' rJ MONITORING LEGENO MILK SAMPLING POINT 10 NUM1BERS P-1B, P-37. P-42, P-43
/
AIR SAMPLING POINT ID NUMBERS P-I, P-2. P-3. P-4, P-6 WATER SAMPLING POINT I1 NUMBERS P-5, P-G.P-B
. P-P-24, P-43 VEGETATION /
VEGETABLES 10 NUMBERS P-25. P-38. P-45 FISH SAMPLING POINT ID NUM4BERS P-13, P-19 INVERTEBRATES POINT ID NUMBERS P-6, P-40 SEDIMENT SAMPLING POINT 10 NUMBERS P-G, P-12, P-20
ENVIRONMENTAL SAMPLING POINTS CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND MILK SAMPLING POINT ID NUMBERS P-18, P-37, P-41, P-42, P.43 AIR SAMPLING POINT ID NUMBERS P-1, P-2. P-3, P-4, P-4 O
WATER SAMPLING POINT ID NUMBERS P-S. P-6. P-9, P-4, Pll, P-43
]
VEGETATION I VEGETABLES ID NUMBERS P-28, 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, 2010. 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 2010 are summarized and discussed.
Program findings for 2010 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 2010 sample results (except for P-10 and MW-8) ranged from <19 pCi/L to 178 pCi/L.
Sample well P-10 ranged from 172 pCi/L to 2980 pCi/L. Sample well MW-8 ranged from 181 pCi/L to 436 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 Soecial Tritium Samolino Proaram 3.1 Progqram 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 and surface water samples were collected quarterly at one location, monthly at five locations, semi-annually at 6 locations, and annually at thirty-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 Proqram Execution The special water sampling was executed as described in the preceding section. Documentation of gamma analyses using a PI plant spectrometer on samples from P-10, MW-7, and S-6 (sent for hard-to-detect nuclide analysis) could not be found. AR 1276964 was written to document this event and determine corrective actions.
3.4 Pro-gram Modifications Changes to the program in 2010 include:
added sampling at the Birch Lake seepage (P-31) with the intent to take quarterly (spring, summer, fall) samples but only the summer and fall samples were taken in 2010 added annual sampling of 3 additional Prairie Island Indian Community locations PIIC-03, PIIC-19, and PIIC-24 Samples were taken from monitoring wells P-10 and MW-7 and S-6 stormwater runoff and were sent to Environmental Incorporated for analysis for hard-to-detect nuclides in accordance with American Nuclear Insurers recommendations added annual snow sampling at S-6, S-7, S-8, S-9, and P-43 added spring and fall sampling for monitoring wells P-2, P-3, P-5, P-6, PZ-8, MW-4 and MW-5, in addition to the summer annual samples extra sampling was conducted in November for monitoring wells P-2, P-3, P-5, P-7, PZ-5, MW-4 and MW-5 E-3
3.5 Results and Discussion Results obtained 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 begun in 1989.
Except for sample wells P-10 and MW-8, the 2010 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 2010 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 stream condensate to the ground 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.
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, 2010.
Medium No.
Location codes Collection type Analysis and type 8 and frequency b type c P-8, REMP P-6, PIIC-02, PIIC-03, PIIC-19, PIIC-20, PIIC-22, PIIC-23, Well water PIIC-24, PIIC-26, PIIC-28, P-7, 27 P-1 1, PZ-1, PZ-2, PZ-3, PZ-4, PZ-5, G/A H-3 PZ-7, MW-6, P-26, SW-2, P-30, SW-3, SW-4, SW-5, P-9 Well water 1
P-24D G/Q H-3 quarterly Well water 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-I(C),
G/M H-3 MW-7, MW-8, P-10 Surface water S-1, S-2, S-3, S-4, S-5, S
S-6, S-7, P-31 G/Ad H-3 Storage Tank 4
11 CST, 21 CST, 22 CST, G/S H-3 U1/2 demin hdr Storage Tank 1
Septic Tank G/M H-3 Snow 5
S-6, S-7, S-8, S-9, P-43(C)
GIA 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.
c Analysis type is coded as follows: H-3 = tritium.
d 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, 2010.
Code Collection site Type of Distance and sample 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. @ 293°/WNW PIIC-20 2158 Holmquist Road WW 1.6 mi @ 300VWNW 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. @ 2931WNW PIIC-26 1771 Buffalo Slough Rd WW 1 mi. @ 315°/NW 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-1 0 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, Nuclear Generating Plant, 2010 (continued).
and surface water samples, Prairie Island Code Collection site Type of Distance and sample a direction from reactor SW-2 STA House WW See map 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. @ ON P-9 Plant well # 2 WW 0.3 mi. @ 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. @ 0"1N S-7 Parking Lot Stormwater (also snow)
SW 0.3 mi P_ 306°/NW S-8 P-10 are 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 demin hdr Storage Tank ST Turbine Building Septic System Storage Tank ST Outside #1 Warehouse a 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 Docket No.
50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January -December 2010 (County, State)
Indicator Location with Highest Control Locations Annual Mean Locations Sample Type and Mean (F)
Location d Mean (F) c Mean (F) c Number Type Number of LLD b Range c Range '
Range C Non-(Units)
Analyses a Routine Results e Offsite Well H-315 19 28(3/15)
PIIC-26 32 (1/1)
(See Control Water (22-32) 0 (pCi/L)
Below)
Onsite H-3 79 19 199(72/79)
P-10 721 (12/12)
(See Control Well Water (22-2980)
(172-2980)
Below) 22 (pCi/L)
Onsite H-3 15 19 54(9/15)
S-6 (See Control Surface Water (23-125) 84(3/3)
Below)
(pCi/L)
(29/125)
Onsite k
H-3 19 19 77(14/19)
Septic System 91 (11/11)
(See Control Storage Tank (20-178)
(48-178)
Below)
(pCi/L)
Control (offsite H-3 24 19
<LLD
<LLD 0
well water) 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).
d 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, 2010.
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 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
<19 PIIC-20 2158 Holmquist Rd
<19 PIIC-22 1773 Buffalo Slough Rd 22 PIIC-23 2.7 miles NW of plant 31 PIIC-24 6424 Sturgeon Lake Rd
<19 PIIC-26 1771 Buffalo Slough Rd 32 PIIC-28 1960 Larson Lane
<19 P-24D Suter residence
<19
<19
<19
<19 P-43 Peterson Farm(Control
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19 SW-1 Hanson Farm (Control)
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19 E-9
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2010 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE WELLS P-2 Sample well 42 48 50 72 P-3 Sample well 22 24 33 55 P-5 Sample well 68 54 85 57 P-6 Sample well 26
<19 41 P-7 Sample well 30 88 P-10 Sample well 252 172 212 222 370 293 606 290 337 2980 2526 388 P-1I Sample well 27 PZ-1 Sample well 32 PZ-2 Sample well 46 PZ-4 Sample well 30 PZ-5 Sample well
<19 36 PZ-7 Sample well 38 38 PZ-8 Sample well 21 31
.117 MW-4 Sample well 55 25 20 60 MW-5 Sample well 37 31
<19 32 MW-6 Sample well 28 MW-7 Sample well 108 85 43 61 68 52 54 41 46 70 56 50 MW-8 Sample well 321 336 304 436 253 260 231 233 181 299 297 201 P-26 PITC well
<19 P-30 Env. lab well
<19 SW-3 CT pump
<19 P-9 Plant well # 2 41 SW-4 New Admin
<19 SW-5 PIn Scmhs 34 E-10
Table E-4.4 Radiological Environmental Monitoring Program Complete Data Table, 2010 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE SURFACE WATER
<19 S-1 Mississippi River upstream S-2 Recirculation/Intake canal
<19 S-3 Cooling water canal 23 S-4 Discharge Canal (end) 35 S-5 Discharge Canal (midway)
<19 S-6 Stormwater runoff 125*
29 97 S-7 Parking Lot runoff 46*
<19 23 S-8 P-10 area snow 46 S-9 MW-7/8 area snow 66 P-31 Birch Lake Seepage
<19
<19
- snow samples E-11
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2010 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 2010 CODE SAMPLE LOCATIONS pCi/L pCi/L pCiIL pCi/L p/L pCi/L pCifL pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE STORAGE TANKS 11 CST Storage tank
<19 30 21 CST Storage tank
<19
<19 22 CST Storage tank 20 26 U1/U2 Demin Storage tank
<19
<19 Header Septic System Storage tank 48 93 69 178 112 116 89 76 109 55 61 E-12
Report No. 8010-100-139 Page 1 of 1 Table E-4.5. Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium in three samples.
Location P-10 MW-7 Old Admin Bldg.
Run off Collection Date 07-14-10 07-14-10 07-29-10 Lab Code PXW-4164 PXW-4165 PXW-4166 Isotope Concentration (pCi/mL)
< 7.4 E-07
< 8.4 E-07
< 7.3 E-07 Ni-63
< 1.2 E-08
< 8.1 E-09
< 7.9 E-09 Sr-90
< 4.6 E-10
< 4.6 E-10
< 4.4 E-10 Pu-238
< 1.5 E-10
< 9.6 E-11
< 8.4 E-1 1 Pu-239/240
< 1.5 E-10
< 1.9 E-10
< 8.4 E-11 Am-241
< 2.5 E-10
< 2.5 E-10
< 2.5 E-10 Cm-242
< 6.0 E-1 1
< 5.7 E-1 1
< 9.0 E-1 1 Cm-243/244
< 1.6 E-10
< 8.0 E-11
< 5.2 E-11 The error given is the probable counting error with a 95% confidence level. Less than (<), value is based on a 4.66 sigma counting error for the background sample.
E-13
&,.'ey by os.
efOdb N-f,*e Pl. ?M7l Top of Riser Wen North East Pipe Slev MW-4 592236 2355090 693,02 MW-S 592201 235556M 686.83 MW-6 591642 2357597 682.33 MW-7 593585 2355714 095.54 MW-8 593944 2355654 697.47 P-10 593538 2355497 693.16 P-I 1 594949 2355297 698.19 P-2 594449 2354002 697.72 P-3 592998 2353997 698.19 P-5 594002 2354501 695.51 P-6 595250 2354802 699.3 P-7 594449 2355235 697.97 PZ-1 596790 2354934 682.91 PZ-2 596743 2352589 689.05 PZ-4 594262 2352599 696.53 PZ-5 591502 2356299 695.93 PZ-7 594469 2356158 697.85 PZ-8 595471 2353662 696.52 D.
b
- 7. Poe?
E-14