ML17130A954
| ML17130A954 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/08/2017 |
| From: | ATI Environmental, Midwest Lab |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17130A954 (77) | |
Text
~*'All Environmental, Inc.
~'(/"'\\I Midwest Laboratory 700 Landwehr Road
- Northbrook, IL 60062-2310 phone (847) 564-0700
- fax (847) 564-45 17 Approved:
XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERA TING PLANT ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2016 Docket No. 50-282 Renewed Operating License No. DPR-42 Docket No. 50-306 Renewed Operating License No. DPR-60 ISFSI Docket No. 72-1 O Renewed License No. SNM-2506 Prepared under Contract by ATI ENVIRONMENTAL,,lnc.
MIDWEST LABORATORY Project No. 8010
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 Preface............. :...................................................................................................................................... ii List of Tables.......................................................................................................................................... iv List of Figures.......................................................................................................................................... v
1.0 INTRODUCTION
..................................................................................................................................... 1 2.0
SUMMARY
............................................. :................................................................................................ 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............................................. :.................................................................... 5 3.5 Program Modifications...... '............................................................................................................. 6 3.6 Land Use Census.......................................................................................................................... 6 4.0 RESULTS AND DISCUSSION................................................................................................................ 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents............................................................ 7 4.2 Summary of Preoperational Data.................................................................................................. 7 4.3 Program Findings.......................................................................................................................... 8 5.0 FIGURES AND TABLES....................................................................................................................... 12
6.0 REFERENCES
CITED.......................................................................................................................... 24 APPENDICES A
lnterlaboratory Comparison Program Results..................................................................................... A-1 Attachment A, Acceptance Criteria for "Spiked" Samples................................................................ A-2 B
Data Reporting Conventions.................................................... :.......................................................... B-1 C
Annual Average Effluent Concentration Limits of Radioactivity in Air and Water Above Background in Unrestricted Areas........................................................................................ C-1 D
Sampling Location Maps..................................................................................................................... D-1 E
Special Well and Surface Water Samples........................................................................................... E-1 iii
LIST OF TABLES No.
5.1 Sample Collection and Analysis Program................................................................................................. 15 5.2 Sampling Locations.............'........................................................ :............................................................. 16 5.3 Missed Collections and Analyses............................................................................................................. 19 5.4 Radiological Environmental Monitoring Program Summary..................................................................... 20 In addition, the following tables can be found in the Appendices:
Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results.................................................. A1-1 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 Average Annual Effluent Concentration Limits of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas.................................................................................. C-2 Appendix E E-4.1 Sample collection and analysis program............................ _.................................................................... E-5 E-4.2 Sampling locations................................................................................................................................. E-6 E-4.3 REMP Summary............................................ :........................................................................................ E-8 E-4.4 REMP Complete Data Tables................................................................................................................ E-9 E-4.5 Supplementary Data Tables................................................................................................................... E-13 iv
LIST OF FIGURES No.
5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control.............................................................................................................................. 13 5.2 Airborne Particulates;.analysis for gross beta, average mean of all indicator locations (P-2,3,4,6,7~ versus control location (P-1).................................................................................. 14
- Appendix D Title Page.
TLD locations within a one mile radius...................................................................................................... D-2 TLD locations, Controls...................................................................................................................'........... D-3 TLD locations, surrounding the ISFSI Area................................................................................................ D-3 TLD locations within a five mile radius..................................................................................................... D-4 REMP sampling points within a one mile radius............................................................................,......... D-5 REMP sampling points within a five mile radius.......................................................................... ~............ D-6 REMP sampling points, Control locations............................................................................................... D-7 Appendix E Groundwater Monitoring Well locations................................................................................................... E~16 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, 2016. 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, 2016b) available at Prairie Island Nuclear Generating Plant.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co.-Minnesota.
The plant has two 575 MWe pressurized water reactors.
Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.
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2.0
SUMMARY
The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRG) Offsite Dose Calculation Manual for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
Results for 2016 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment.
For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content.
In addition, ambient gamma radiation levels are monitored. by the.rmoluminescent 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-
?, 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-? 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 bf corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
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3.1 Program Design and Data Interpretation (continued)
Other means of distinguishing sources of environmental radiation are employed in interpreting the data.
Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
3.2 Program Description The sampling and analysis schedule for the radiological environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2016). Maps of fixed sampling locations are included in Appendix D.
To monitor the airborne environment, air is sampled by continuous pumping at six stations, four site boundary indicators (P-2, P-3, P-4 and P-7), located in the highest calculated D/Q sectors, one community indicator (P-6), and one control (P-1 ). The particulates are collected on membrane filters, airborne iodine is trapped by activated charcoal canisters. Particulate filters are analyzed for gross beta activity and charcoal canisters for iodine-131. Quarterly composites of particulate filters from each location are analyzed for gamma emitting isotopes.
Offsite ambient gamma radiation is monitored at thirty-four locations, using CaS04:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant.
They are replaced and measured quarterly.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI)
Facility by twenty CaS04: Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.
Milk samples are collected monthly from two farms (one indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.
For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131.
Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are co.llected 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.
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.
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3.2 Program Description (continued)
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) Milk:
There was no milk collected after 10/11/16 at locations P-37 and P-43. The P-37 farm had permanently suspended milking operations and the P-43 control samples were no longer required.
(2) Airborne Particulate I Airborne Iodine A partial sample was collected from location P-2 for the week of 4/13/16 and 7/11/16. Power was lost due to a loss of the temporary power source at this location. A permanent power supply was connected on 7/25/16.
A partial sample was collected from location P-1 for the week ending 7/11/16. Power was lost to the sampler due to a storm-induced power outage.
(3) TLD The TLD at location P-098 (south sector) for the third quarter of 2016 was missing in the field.
Deviations from the program are summarized in Table 5.3.
3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method, solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
Levels of iodine-131 in cabbage and natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
Tritium concentrations are determined by liquid scintillation.
Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.
. Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
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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, 2016). The QA Program includes participation in lnterlaboratory Comparison (crosscheck) Programs.
Results obtained in the crosscheck programs are presented in Appendix A 3.5 Program Modifications None.
3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft 2 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 September 30.
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 September 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 conducted 8/10/16 through 9/9/16. The ranking of the highest D/Q garden spot changed in 2016. Samples were taken from this garden. In addition several other close gardens in the vicinity of the plant were sampled, plus a control farm.. This farm does not have calculated doses greater than 1 mrem per year.
No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant. The Minnesota and Wisconsin Departments of Natural Resources were both consulted and both confirmed that no irrigation permits had been issued for water from the Mississippi River.
Therefore, no corn samples were collected for analysis.
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4.0 RESULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3.
The results are summa_rized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2016. The Fukushima Daiichi nuclear accident occurred March 11, 2011.
There were no reported atmospheric nuclear tests in 2016. The last reported test was conducted on October 16, 1980 by the People's Republic of China.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout declined yearly from a level of 12, 167 pCi/ m3 to 1,020 pCi/ m3, and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during pre-operational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m 3.
3 Average present day levels have stabilized at around 0.025 pCi/m. Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored.
In milk samples, low levels of Cs-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.
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4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
Ambient Radiation (TLDs)
Ambient radiation was measured in the general area :of the site boundary, at the outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at one control location. The means ranged from 16.6 mR/91 days at inner ring locations to 16.8 mR/91 days at outer ring locations.
The mean at special interest locations was 15.8 mR/91 days and 17.4 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were comparable to 2015 dose rates and consistent with results from previous years. 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 Rinas)
Control Year Outer Rinas)
Control 1999 16.6 17.5 2008 16.9 17.1 2000 17.0 17.1 2009 15.9 16.3 2001 16.8 17.2 2010 16.0 16.0 2002 17.4 16.9 2011 15.7 15.7 2003 16.2 16.0 2012 16.5 16.2 2004 17.6 17.6 2013 15.1 16.0 2005 16.8 16.3 2014 15.3 16.2 2006 16.6 16.6 2015 16.0 17.4 2007 17.5 17.7 2016 16.7 17.4 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR/91 days).
ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates averaged 168.4 mR/91 days inside the ISFSI earth berm and 24.6 mR/91 days
- outside the ISFSI earth berm. No additional casks were placed on the ISFSI pad in 2016, a total of forty loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.
Ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.9 and 17.2 mR/91 days. Although the skyshine neutron dose rates are not directly measured,. the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7 A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).
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Airborne Particulates Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1999 through 2006, and also in 2008 through 2015. The elevated activity observed in 2007 was attributed to construction activity in the area, an increase in dust and consequent heavier particulate filter loading.
Average annual gross beta concentrations in airborne particulates were 0.027 pCi/m 3 for*both the indicators and the control Ideation and similar to levels observed from 1999 through 2006 and 2008 to 2015. The results are tabulated below.
Average of Year Indicators Control Concentration <oCi/ m3) 1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 2008 0.028 0.027 2009 0.029 0.029 2010 0.025 0.025 2011 0.026 0.027 2012 0.031 0.032 2013 0.027 0.028 2014 0.026 0.026 2015 0.029 0.029 2016 0.027 0.027 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 Al-Salih, 1955) was detected in all samples, with an average activity of 0.076 pCi/m for indicator locations and 0.080 pCi/m 3 at the control locations. All other isotopes were below the lower limit of detection.
There was no indication of a plant effect.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m 3
, in all samples. There was no indication of a plant effect.
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lodine-131 results were below a detection limit of 0.5 pCi/L in all samples.
Cs-137 results were below 5 pCi/L in all samples. No other gamma-emitting isotopes, except naturally occurring potassium-40, were detected in any milk sample.
In summary, the data for 2016 show no radiological effects of the plant operation.
Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below a detection limit of 155 pCi/L for all samples.
Gross beta concentrations averaged 12.3 pCi/L throughout the year, ranging from 9.0-14.8 pCi/L. These concentrations are consistent with levels observed from 1999 through 2015. 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 2016 data of any effect of plant operation.
- Year Gross Beta (pCi/L) 1999 5.3 2000 10.1 2001 8.3 2002 8.7 2003 9.9 2004 9.8 2005 11.5 2006 13.4 2007 11.6 2008 11.6 2009 11.4 2010 11.7 2011 12.4 2012 11.8 2013 12.2 2014 11.5 2015 11.4 2016 12.3 Average annual concentrations; Gross beta in' drinking water.
River Water All river water samples measured below an LLD level of 155 pCi/L for tritium.
Gamma-emitting isotopes were below detection limits in all samples.
In summary, the data for 2016 show no radiological effects from the plant operation.
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Well Water Water samples tested from the control well, P-43 (Peterson Farm) and from four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm )
showed no tritium detected above a detection limit of 192 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2016 show no radiological effects of the plant operation.
Four samples of broad leaf vegetation, cabbage leaves, were collected in August,2016 and one in September 2016 and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.019 pCi/g wet weight in all samples. With exceptions for naturally-occurring beryllium-? 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 were collected in May, June and October, 2016 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 June and October, 2016 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes measured below detection limits except in one instance naturally occurring potassium-40. There was no indication of any plant effect.
Bottom and Shoreline Sediments Upstream and downstream bottom sediments and downstream recreational area shoreline sediments were sampled in May, June and September, 2016 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotope detected was naturally-occurring potassium-40.
There was no indication of a plant effect.
11
5.0 FIGURES AND TABLES 12
Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.
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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)"
Frequencl Frequency 0
Ambient radiation (TLD's) 54 P-01A - P-10A C/Q Ambient gamma P-01B-P-15B P-015-P-08S P-011A - P-081A P-011B - P-081B P-011X-P-041X, P-01C Airborne Particulates 5
P-1(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6, P-7 each location)
Airborne Iodine 5
P-1(C), P-2, P-3, P-4, P-6, P-7 C/W 1-131 Milk 4
P-37, P-43 (C)
G/Md 1-131, GS River water 2
P-5(C), P-6 G/W GS(MC), H-3(QC)
Drinking water 1
P-11 G/W GB(MC), l-131(MC)
Well water 5
P-6, P-8, P-9, P-24, G/Q H-3, GS P-43 (C)
Edible cultivated crops -
3 P-28, P-38(C), P-45 G/A GS (1-131) leafy green vegetables Fish (one species, edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or invertebrates 2
P-40(C), P-6 G/SA GS Bottom sediment 2
P-20(C), P-6 G/SA GS Shoreline sediment 1
P-12 G/SA GS
- Location codes are defined in Table 5.2. 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.
0 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
Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
Distance and Direction Code Type a Collection Site Sample Typeb from Reactor P-1 c
Air Station P-1 AP,AI 11.8 mi @ 316°/NNW P-2 Air Station P-2 AP,AI 0.5 mi @ 294°/WNW P-3 Air Station P-3 AP,AI 0.8 mi@ 313°/NW P-4 Air Station P-4 AP,AI 0.4 mi @ 359°/N P-5 c
Upstream of Plant RW 1.8 mi@ 11°/N P-6 Lock and Dam #3 & Air Station P-6 AP,AI, RW WW, BS, B0° 1.6 mi@ 129°/SE P-7 Air Station P-7 AP,AI 0.5 mi @ 271°/W P-8 Community Center WW 1.0 mi@ 321°/WNW P-9 Plant Well #2 WW 0.3 mi @ 306°/NW P-11 Red Wing Service Center ow 3.3 mi@ 158°/SSE P-12 Downstream of Plant SS 3.0 mi@ 116°/ESE P-13 Downstream of Plant Fe 3.5 mi@ 113°/ESE P-18 Christiansen Farm M
3.8 mi@ 88°/E P-19 c
Upstream of Plant Fe 1.3 mi@0°/N P-20 c
Upstream of Plant BS 0.9 mi@ 45°/NE P-24 Suter Residence WW 0.6 mi @ 158°/SSE P-28 Allyn Residence VE 1.0 mi @ 152°/SSE P-37 Welsch Farm M
4.1 mi @ 87°/E P-38 c
Cain Residence VE 14.2 mi @ 359°/N P-40 c
Upstream of Plant B0° 0.4 mi@0°/N P-43 c
Peterson Farm M,WW 13.9 mi.@ 355°/N P-45 Glazier Residence VE 0.6 mi.@341°/NNW General Area of the Site Boundarv P-01A Property Line TLD 0.4 mi@ 359°/N P-02A Property Line TLD 0.3 mi@ 10°/N P-03A Property Line TLD 0.5 mi@ 183°/S P-04A Property Line TLD 0.4 mi@ 204°/SSW P-05A Property Line TLD 0.4 mi @ 225°/SW P-06A Property Line TLD 0.4 mi @ 249°/WSW P-07A Property Line TLD 0.4 mi @ 268°/W P-08A Property Line TLD 0.4 mi@ 291°/WNW P-09A Property Line TLD 0.7 mi@317°/NW P-10A Property Line TLD 0.5 mi @ 333°/NNW 16
Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Code Typea Collection Site Approximately 4 to 5 miles Distant from the Plant P-018 Thomas Killian Residence P-028 Roy Kinneman Residence P-038 Wayne Anderson Farm P-048 Nelson Drive (Road)
P-058 County Road E and Coulee P-068 William Hauschildt Residence P-078 Red Wing Public Works P-088 David Wnuk Residence P-098 Highway 19 South P-108 Cannondale Farm P-118 Wallace Weberg Farm P-128 Ray Gergen Farm P-138 Thomas O'Rourke Farm P-148 David J. Anderson Farm P-158 Holst Farms Special Interest Locations P-015 Federal Lock & Dam #3 P-02S Charles Suter Residence P-03S Carl Gustafson Farm P-04S Richard Burt Residence P-05S Kinney Store P-06S Earl Flynn Farm P-07S Indian Community P-08S Indian Community P-01C c
Robert Kinneman Farm 17 Sample Typeb TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD Distance and Direction from Reactor 4.7 mi 355°/N 4.8mi@17°/NNE 4.9 mi@ 46°/NE 4.2 mi@ 61°/ENE 4.2 mi@ 102°/ESE 4.4 mi @ 112°/ESE 4.7 mi@ 140°/SE 4.1mi@165°/SSE 4.2 mi@187°/S 4.9 mi @ 200°/SSW 4.5 mi@ 221°/SW 4.6 mi@ 251°/WSW 4.4 mi@ 270°/W 4.9 mi@ 306°/NW 3.8 mi@ 345°/NNW 1.6 mi @ 129°/SE 0.5 mi @ 155°/SSE 2.2mi@173°/S 2.0 mi@202°/SSW 2.0 mi @ 270°/W 2.5 mi @ 299°/WNW 0.7 mi@ 271°/W 0.7 mi@ 287°/WNW 11.1 mi @331°/NNW
Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued).
Code Typea Collection Site Sample Type 0
Distance and Direction from ISFSI Center.
ISFSI Area Inside Earth Berm P-011A ISFSI Nuisance Fence TLD 190'@ 45°/NE P-021A ISFSI Nuisance Fence TLD 360'@82°/E P-031A ISFSI Nuisance Fence TLD 370' @ 100°/E P-041A ISFSI Nuisance Fence TLD 200'@ 134°/SE P-051A ISFSI Nuisance Fence TLD 180'@ 219°/SW P-061A ISFSI Nuisance Fence TLD 320'@ 258°/WSW P-071A ISFSI Nuisance Fence TLD 320'@ 281°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318°/NW P-011X ISFSI Nuisance Fence TLD 140' @ 180°/S P-021X ISFSI Nuisance Fence TLD 310' @ 270°/W P-031X ISFSI Nuisance Fence TLD 140'@0°/N P-041X ISFSI Nuisance Fence TLD 360'@90°/E ISFSI Area Outside Earth Berm P-011B ISFSI Berm Area TLD 340'@3°/N P-021B ISFSI Berm Area TLD 380'@28°/NNE P-031B ISFSI Berm Area TLD 560'@85°/E P-041B ISFSI Berm Area TLD 590'@165°/SSE P-051B ISFSI Berm Area TLD 690' @ 186°/S P-061B ISFSI Berm Area TLD 720'@ 201°/SSW P-071B ISFSI Berm Area TLD 610'@ 271°/W P-081B ISFSI Berm Area TLD 360'@ 332°/NNW a "C" denotes control location. All other locations are indicators.
b Sample Codes:
AP Airborne particulates F
Fish Al Airborne Iodine M
Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates)
VE Vegetation/vegetables DW Drinking water WW Well water
" Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
18
Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.
All required samples were collected and analyzed as scheduled with the following exceptions:
Collection Reason for not Sample Analysis Location Date or conducting REMP
' Plans for Preventing Type Period as required Recurrence AP/Al Beta, 1-131 P-2 4/13/2016 Lost temporary power for Permanent Power greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to be installed AP/Al Beta, 1-131 P-2 7/11/2016 Lost temporary power for Permanent Power greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to be installed AP/Al Beta, 1-131 P-1 7/11/2016 Lost power for greater than 8 Power was restored hours due to storm induced power outage Milk Gamma, 1-131 P-37 10/11/2016 Ceased dairy operations at this location Milk Gamma, 1-131 P-43 10/11/2016 No longer sample this control dairy due to no indicator dairy being sampled.
TLD Gamma P-09B 7/1/16-TLD was missing Replaced TLD 09/30/16 19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units)
Analyses" TLD (Inner Ring, Gamma 40 Area at Site Boundary) mR/91 days)
TLD (Outer Ring, Gamma 59 4-5 mi. distant) mR/91 days)
TLD (Special Gamma 32 Interest Areas) mR/91 days)
, TLD (Control)
Gamma 4
mR/91 days)
Airborne GB 312 Particulates (pCi/m3)
GS 20 Be-7 Mn-54 Co-58 Co-60 Zn-65 Zr-Nb-95.
Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-141 Ce-144 Airborne Iodine 1-131 312 (pCi/m3)
Docket No.
50-282, 50-306 Prairie Island Nuclear Power Station Goodhue, Minnesota Reporting Period January-December, 2016
( Cdunty, State )
Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLDb Mean (F)° Mean (F)c Mean (F)° Routine Rangec Locationd Rangec Rangec Results*
Direct Radiation 3.0 16.6 (40/40)
P-06A 19.4 (4/4)
(See Control 0
( 13.5-19.9) 0.4 mi @ 249° /WSW (18.6-19.9) below.)
3.0 16.8 (59/59)
P-03B 19 (4/4)
(See Control 0
( 13.9-21.2) 4.9 mi @ 460/NE (17.9-20.7) below.)
3.0 15.8 (32/32)
P-03S, Gustafson Farm, 18.1 (4/4)
(See Control 0
( 12.5-19.6) 2.2 mi@ 173° /S (16.7-19.6) below.)
3.0 None P-01C, Robert Kinneman 17.4 (4/4) 17.4 (4/4) 0 11.1 mi@331°/NNW (15.8-18.3)
(15.8-18.3)
Airborne Pathway 0.005 0.027 (260/260)
P-06, Air Station 0.028 (52 /52) 0.027 (52/52) 0 (0.012-0.070) 1.6 mi @ 259° /SE (0.014-0.070)
(0.012-0.049) 0.015 0.076 (20/20)
P-01, Air Station 0.080 (4/4) 0.080 (4/4) 0 (0.051-0.116) 11.8 mi@ 316° /NNW (0.059-0.107)
(0.059-0.107) 0.0009
<LLD
<LLD 0
0.0009
<LLD
<LLD 0
0.0007
<LLD
<LLD 0
0.0013
<LLD
<LLD 0
0.0013
<LLD
<LLD 0
0.0012
<LLD
<LLD 0
0.0088
<LLD
<LLD 0
0.0009
<LLD
<LLD 0
0.0008
<LLD
<LLD 0
0.0046
<LLD
<LLD 0
0.0018
<LLD
<LLD 0
0.0049
<LLD
<LLD 0
0.030
<LLD
<LLD 0
20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units)
Analyses" Milk (pCi/L) 1-131 30 GS 30 K-40 Cs-134 Cs-137 Ba-La-140 Crops - Cabbage 1-131 5
(pCi/gwet)
Well Water H-3 20 (pCi/L)
GS 20 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Goodhue, Minnesota Reporting Period January-December, 2016
( County, State )
Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLDb Mean (F)c Mean (F)c Mean (F)° Routine Rangec Locationd Rangec Rangec Results*
Terrestrial Pathway 0.5
<LLD
<LLD 0
200 1386 (15/15)
P-43 (C), Peterson Farm 1434 (15 /15) 1434 (15/15) 0 (1234-1459) 13.9 mi @ 355° /N (1349-1514)
(1349-1514) 5
<LLD
<LLD 0
5
<LLD
<LLD 0
5
<LLD
<LLD 0
0.019
<LLD
<LLD 0
192
<LLD
<LLD 0
10
<LLD
<LLD 0
30
<LLD
<LLD 0
10
<LLD
<LLD 0
10
<LLD
<LLD 0
30
<LLD
<LLD 0
15
<LLD
<LLD 0
10
<LLD
<LLD 0
10
<LLD
<LLD 0
15
<LLD
<LLD 0
48
<LLD
<LLD 0
21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units)
Analyses*
Drinking Water GB 12 (pCi/L) 1-131 12 H-3 4
GS 12 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 River Water H-3 8
(pCi/L)
GS 24 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Fish GS 6
(pCi/g wet)
K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Goodhue, Minnesota Reporting Period January-December, 2016
( County, State )
Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLDb Mean (F)° Mean (F)° Mean (F) 0 Routine Range 0
Locationd Range 0
Range 0
Results" Waterborne Pathway 1.0 12.3 (12/12)
P-11, Red Wing S.C.
12.3 (12/12)
None 0
(9.0-14.8) 3.3 mi@ 158° /SSE (9.0-14.8) 1.0
<LLD None 0
155
<LLD None 0
10
<LLD None 0
30
<LLD None 0
10
<LLD None 0
10
<LLD None 0
30
<LLD None 0
15
<LLD None 0
10
<LLD None 0
10
<LLD None 0
15
<LLD None 0
39
<LLD None 0
155
<LLD
<LLD 0
10
<LLD
<LLD 0
30
<LLD
<LLD 0
10
<LLD
<LLD 0
10
<LLD
<LLD 0
30
<LLD
<LLD 0
15
<LLD
<LLD 0
10
<LLD
<LLD 0
10
<LLD
<LLD 0
15
<LLD
<LLD 0
53
<LLD
<LLD 0
0.10 2.77 (6/6)
P-13, Downstream 2.77 (6/6) 2.71 (6/6) 0 (2.48-3.16) 3.5 mi @ 113°/ESE (2.48-3.16)
(2.34-3.07) 0.021
<LLD
<LLD 0
0.112
<LLD
<LLD 0
0.029
<LLD
<LLD 0
0.018
<LLD
<LLD 0
0.046
<LLD
<LLD 0
0.050
<LLD
<LLD 0
0.024
<LLD
<LLD 0
0.020
<LLD
<LLD 0
0.41
<LLD
<LLD 0
22
Table 5.4 Radiological Environmental Monitoring Program Summary Docket No.
50-282, 50-306 Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Reporting Period January-December, 2016 (County, State)
Indicator Location with Highest Control Sample Type and Loca9ons Annual Mean Locations Type Number of LLDb Mean:(F)c Mean (F)° Mean (F)° (Units)
Analyses*
Rangec Locationd Rangec Rangec Waterborne Pathway Invertebrates GS 4
. (pCi/g wet)
Be-7 0.38
<LLD
<LLD K-40 1.05 1.24(1/2)
P-6 Downstream 1.24(1/2)
<LLD 1.6 mi@ 129°/SE Mn-54 0.045
<LLD
<LLD Co-58 0.046
<LLD
<LLD Co-60 0.047
<LLD
<LLD Zn-65 0.08
<LLD
<LLD Zr-Nb-95 0.09
<LLD
<LLD Ru-103 0.06
<LLD
<LLD Ru-106 0.36
<LLD
<LLD Cs-134 0.040
<LLD
<LLD Cs-137 0.048
<LLD
<LLD Ba-La-140 0.47
<LLD
<LLD Ce-141 0.12
<LLD
<LLD Ce-144 0.23
<LLD
<LLD Bottom and GS 6
Shoreline Be-7 0.25
<LLD
<LLD Sediments (pCi/g dry)
K-40 0.10 8.72 (4/4)
P-6, Downstream 9.01 (2/2) 8.60 (2/2)
(8.07-9.95) 1.6 mi@ 129°/SE (8.07-9.95)
(7.74-9.47)
Mn-54 0.020
<LLD
<LLD Co-58 0.026
<LLD
<LLD Co-60 0.022
<LLD
<LLD Zn-65 0.039
<LLD
<LLD Zr-Nb-95 0.032
<LLD
<LLD Ru-103 0.038
<LLD
<LLD Ru-106 0.15
<LLD
<LLD Cs-134 0.014
<LLD
<LLD
- cs-137 0.019
<LLD
<LLD Ba-La-140 0.17
<LLD
<LLD Ce-141 0.07
<LLD
<LLD Ce-144 0.12
<LLD
<LLD
- GB = gross beta, GS =gamma scan.
b LLD= nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten times the typical preoperational value for the medium or location.
23 Number Non-Routine Results*
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-? 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.
___ 2001 a *through 2015a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2016.
___ 2001 b through 2015b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2016.
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.
____ 2016.
Quality Manual, Rev. 2, 9 May 2016.
____ 2012.
Quality Assurance Program Manual, Rev. 3, 14 November 2012.
____ 2009.
Quality Control Procedures Manual, Rev. 2, 08 July 2009.
____ 2009.
Quality Control Program, Rev. 2, 12 November2009.
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natur~I Environment, University of Chicago Press, Chicago, Illinois, 369-382.
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, 2013.
Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
24
6.0 REFERENCES
CITED (continued)
U.S. Environmental Protection Agency.
____ 1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
1984.
Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).
___ 2012.
RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981-2009.
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
Xcel Energy Corporation.
___ 2009 to 2015. Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2015. Minneapolis, Minnesota.
___ 2009 to 2015.
Prairie Island Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2015.
Minneapolis, Minnesota.
25
~*I. All E11vironmental, Inc.
~.~ :M.I Midwest Laboratory 700 Landwehr Road* Northbrook. IL 60062-2310 phone (847) 564-0700 *fax (847) 564-4517 NOTE:
APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS 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 lntercomparison 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, 2016 through December, 2016
Appendix A lnterlaboratorv Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (cr<?sscheck) 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 iri Table A-1 were obtained through participation in the RAD PT Study Proficiency Testing 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 irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.
Table A-3 lists results of the analyses on inchouse "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 MRAD PT Study Proficiency Testing 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.
A1
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa Analysis Gamma Emitters Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium lodine-131, lodine-129b Uranium-238, Nickel-63b Technetium-99b lron-55b Other Analyses b Level 5 fo 100 pCi/liter or kg
> 100 pCi/liter or kg 5 to 50 pCi/liter or kg
> 50 pCi/liter or kg 2 to 30 pCi/liter or kg
> 30 pCi/liter or kg
<: 0.1 g/liter or kg
- 20 pCi/liter
> 20 pCi/liter
- 100 pCi/liter
> 100 pCi/liter
- 5 4,000 pCi/liter
> 4,000 pCi/liter
- 0.1 pCi/liter
<: 0.1 pCi/liter, gram, or sample
- 5 55 pCi/liter
> 55 pCi/liter
- 5 35 pCi/liter
> 35 pCi/liter 50 to 1 00 pCi/liter
> 100 pCi/liter a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program", Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
A2 One standard deviation for single determination 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 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
+/- 1a =
169.85 x (known)0*0933 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
TABLEA-1. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".
RAD study Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERW-1392 4/4/2016 Sr-89 43.5 +/- 4.3 48.2 37.8 - 55.6 Pass ERW-1392 4/4/2016 Sr-90 27.5+/-1.9 28.5 20.7 - 33.1 Pass ERW-1394 b 4/4/2016 Ba-133 65.2 +/- 3.8 58.8 48.7 - 64.9 Fail ERW-1394 c 4/4/2016 Ba-133 57.8 +/- 5.3 58.8 48.7 - 64.9 Pass ERW-1394 4/4/2016 Cs-134 43.7 +/- 3.0 43.3 34.6 -47.6 Pass ERW-1394 4/4/2016 Cs-137 86.1 +/- 5.3 78.4 70.6 - 88.9 Pass ERW-1394 4/4/2016 Co-60 108 +/- 44 102 91.8-114 Pass ERW-1394 4/4/2016 Zn-65 240+/-13 214 193 -251 Pass ERW-1397 4/4/2016 Gr. Alpha 52.0 +/- 2.2 62.7 32.9 - 77.8 Pass ERW-1397 4/4/2016 Gr. Beta 33.9+/-1.2 39.2 26.0 - 46.7 Pass ERW-1400 4/4/2016 1-131 24.7 +/- 0.6 26.6 22.1 - 31.3 Pass ERW-1402 4/4/2016 Ra-226 15.6 +/- 0.5 15.2 11.3 -17.4 Pass ERW-1402 4/4/2016 Ra-228 5.28 +/- 0.76 5.19 3.12 - 6.93 Pass ERW-1403 4/4/2016 Uranium 4.02 +/- 0.42 4.64 3.39 - 5.68 Pass ERW-1405 4/4/2016 H-3 8,150 +/-270 7,840 6,790 - 8,620 Pass SPW-2845 7/7/2015 Ba-133 60.3 +/- 5.7 64.7 53.9 - 71.2 Pass SPW-2845 7/7/2015 Cs-134 48.8 +/- 9.3 50.1 40.3 - 55.1 Pass SPW-2845 7/7/2015 Cs-137 101 +/- 8 89.8 80.8 - 101 Pass SPW-2845 7/7/2015 Co-60 65.1 +/- 5.8 59.9 53.9 - 68.4 Pass SPW-2845 7/7/2015 Zn-65 288 +/- 29 265 238 - 310 Pass ERW-3485 7/11/2016 Sr-89 43.3 +/- 6.5 53.3 42.3 - 60.9 Pass ERW-3485 7/11/2016 Sr-90 39.0 +/- 2.8 39.2 28.8 - 45.1 Pass ERW-3487 7/11/2016 Ba-133 83.3 +/- 4.9 82.9 69.7 - 91.2 Pass ERW-3487 7/11/2016 Cs-134 62.5 +/- 4.4 65.3 53.1 -71.8 Pass*
ERW-3487 7/11/2016 Cs-137 98A +/- 5.6 95.2 85.7-107 Pass ERW-3487 7/11/2016 Co-60 122 +/- 5 117 105 -131 Pass ERW-3487 7/11/2016 Zn-65 124 +/- 9 113 102 - 134 Pass ERW-3490 7/11/2016 Gr. Alpha 46.6 +/- 2.2 48.1 25.0 - 60.5 Pass ERW-3490 7/11/2016 Gr. Beta 26.8+/-1.1 28.6 18.2 - 36.4 Pass ERW-3492 7/11/2016 1-131 23.7+/-1.0 24.9 20.7 - 29.5 Pass ERW-3493 7/11/2016 Ra-226 12.9 +/- 0.4 12.3 9.2 - 14.2 Pass ERW-3493 7/11/2016 Ra-228 5.8 +/- 0.8 5.8 3.5 - 7.6 Pass ERW-3493 7/11 /2016 Uranium 32.8 +/- 0.8 25.2 28.4 - 39.3 Pass ERW-3495 7/11/2016 H-3 12,400 +/- 334 12,400 10,800 - 13,600 Pass
- Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b No reason determined for failure of Ba-133 result.
0 The result of reanalysis (Compare to original result, footnoted "b" above).
Al-1
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). ab mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P)
Acceptance a Environmental, Inc.
Group 1 2016-1 10/7/2016 Spike 1 135.0 148.3 0.10 2016-1 10/7/2016 Spike 2 135.0 144.3 0.07 2016-1 10/7/2016 Spike 3 135.0 133.2
-0.01 2016-1 10/7/2016 Spike 4 135.0 139.6 0.03 2016-1 10/7/2016 Spike 5 135.0 128.4
-0.05 2016-1 10/7/2016 Spike 6 135.0 123.9.
-0.08 2016-1 10/7/2016 Spike 7 135.0 124.0
-0.08 2016-1 10/7/2016 Spike 8 135.0 121.5
-0.10 2016-1 10/7/2016 Spike 9 135.0 148.3 0.10 2016-1 10/7/2016 Spike 10 135.0 126.8
-0.06 2016-1 10/7/2016 Spike 11 135.0 123.3
-0.09 2016-1 10/7/2016 Spike 12 135.0 137.9
. 0.02 2016-1 10/7/2016 Spike 13 135.0 126.0
-0.07 2016-1 10/7/2016 Spike 14 135.0 127.2
-0.06 2016-1 10/7/2016 Spike 15 135.0 144.5 0.07 2016-1 10/7/2016 Spike 16 135.0 140.5 0.04 2016-1 10/7/2016 Spike 17 135.0 146.0 0.08 2016-1 10/7/2016 Spike 18 135.0 127.7
-0.05 2016-1 10/7/2016 Spike 19 135.0 146.8 0.09 2016-1 10/7/2016 Spike 20 135.0 122.6
-0.09 2016-1 10/7/2016 Spike 21 135.0 108.6
-0.20 2016-1 10/7/2016 Spike 22 135.0 119.6
-0.11 2016-1 10/7/2016 Spike 23 135.0 135.1 0.00 2016-1 10/7/2016 Spike 24 135.0 116.2
-0.14 2016-1 10/7/2016 Spike 25 135.0 118.9
-0.12 2016-1 10/7/2016 Spike 26 135.0 128.5
-0.05 2016-1 10/7/2016 Spike 27 135.0 115.6
-0.14 2016-1 10/7/2016 Spike 28 135.0 126.4
-0.06 2016-1 10/7/2016 Spike 29 135.0 115.0
-0.15 2016-1 10/7/2016 Spike 30 135.0 147.3 0.09 Mean (Spike 1-30) 130.4 0.03 Pass Standard Deviation (Spike 1-30) 11.5 0.09 Pass a Table A-2 assumes 1 roentgen = 1 rem (NRG -Health Physics Questions and Answers 1 O CFR Part 20 - Question 96 - Page Last Reviewed/Updated Thursday, October 01, 2015).
b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results werffsubmitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.
0 Performance Quotient (P) is calculated as ({reported dose - conventially true value) + conventially true value) where the
- conventially true value is the delivered dose.
d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
A2-1
TABLE A-2 Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). ab mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P)
Acceptance ct Environmental, Inc.
Group 2 2016-2 10/7/2016 Spike 31 87.0 83.0
-0.0.5 2016-2
, 10/7/2016 Spike 32 87.0 88.3 0.01 2016-2 10/7/2016 Spike 33 87.0 83.1
-0.04 2016-2 10/7/2016 Spike 34 87.0 81.4
-0.06 2016-2 10/7/2016 Spike 35 87.0 78.9
-0.09 2016-2 10/7/2016 Spike 36 87.0 80.3
-0.08 2016-2 10/7/2016 Spike 37 87.0 101.1 0.16 2016-2 10/7/2016 Spike 38 87.0 78.3
-0.10 2016-2 10/7/2016 Spike 39 87.0 86.6 0.00 2016-2 10/7/2016 Spike 40 87.0 81.8
-0.06 2016-2 10/7/2016 Spike 41 87.0 84.8
-0.03 2016-2 10/7/2016 Spike 42 87.0 79.9
-0.08 2016-2 10/7/2016 Spike 43 87.0 80.8
-0.07 2016-2 10/7/2016 Spike 44 87.0 80.2
-0.08 2016-2 10/7/2016 Spike 45 87.0 82.7
-0.05 2016-2 10/7/2016 Spike 46
.87.0 104.0 0.20 2016-2 10/7/2016 Spike 47 87.0 86.1
-0.01 2016-2 10/7/2016 Spike 48 87.0 104.0 0.20 2016-2 101712016 Spike 49 87.0 86.1
-0.01 2016-2 10/7/2016 Spike 50 87.0 90.8 0.04 2016-2 10/7/2016 Spike 51 87.0 85.7
-0.01 2016-2 10/7/2016 Spike 52 87.0 86.5
-0.01 2016-2 10/7/2016 Spike 53 87.0 86.4
-0.01 2016-2 10/7/2016 Spike 54 87.0 92.6 0.06 2016-2 10/7/2016 Spike 55 87.0 88.6 0.02 2016-2 10/7/2016 Spike 56 87.0 78.9
-0.09 2016-2 10/7/2016 Spike 57 87.0 82.6
-0.05 2016-2 10/7/2016 Spike 58 87.0 80.6
-0.07 2016-2 10/7/2016 Spike 59 87.0 89.9 0.03 2016-2 10/7/2016 Spike 60 87.0 85.0
-0.02 Mean (Spike 31-60) 86.0 0.01 Pass Standard Deviation (Spike 31-60) 6.9 0.08 Pass a Table A-2 assumes 1 roentgen= 1 rem (NRG -Health Physics Questions and Answers 10 CFR Part 20- Question 96 - Page Last Reviewed/Updated Thursday, October 01, 2015).
b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N 13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.
c Performance Quotient (P) is calculated as ((reported dose - conventially true value).,. conventially true value) where the conventially true value is the delivered dose.
d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
A2-2
TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 ° Activity Limits d Acceptance SPW-290 1/21/2016 Sr-90 38.6 +/- 1.5 37.3 22.4 - 52.2 Pass
- SPW-292 1/21/2016 Sr-90 35.8 +/- 1.6 37.3 22.4 - 52.2 Pass SPW-294 1/21/2016 C-14 4,689+/-18 4,735 2,841 - 6,629 Pass SPW-414 2/1/2016 Ra-228 18.4 +/- 2.2 17.7 10.6 - 24.8 Pass W-020416 2/4/2016 Gr. Alpha 20.8 +/- 0.4 20.1 12.0 - 28.1 Pass W-020416 2/4/2016 Gr. Beta 29.7 +/- 0.3 28.9 17.3 -40.4 Pass W-021716 2/17/2016 Ra-226 17.9 +/- 0.5 16.7 10.0 - 23.4 Pass W-030716 3/7/2016 Gr. Alpha 16.3 +/- 0.8 20.1 12.0 - 28.1 Pass W-030716 3/7/2016 Gr. Beta 27.0 +/- 0.7 28.9 17.3 - 40.4 Pass SPDW-70046 3/29/2016 Ra-226 13.4+/-0.4 16.7 10.0 - 23.4 Pass SPW-1163 3/22/2016 Ra-228 4.2 +/- 0.7
. 4.4 2.6 - 6.2 Pass SPW-1235 3/29/2016 Gr. Alpha 21.0 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-1235 3/29/2016 Gr. Beta 29.4 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-1739 4/21/2016 Ra-228 16.2 +/- 2.0 17.7 10.6 - 24.8 Pass SPW-2052 4/21/2016 Ra-226 16.0 +/- 0.5 16.7 10.0 - 23.4 Pass W-042616 4/21/2016 Fe-55 1,519+/-61 1,482 889 - 2,075 Pass SPW-1823 4/23/2016 Gr. Alpha 21.0 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-1823 4/23/2016 Gr. Beta 26.6 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-1998 4/29/2016 Cs-134 35.9 +/- 6.0 36.2 21.7 - 50.6 Pass SPW-1998 4/29/2016 Cs-137 82.5 +/- 7.6 71.9 43.1 -100.6 Pass SPW-2097 5/3/2016 H-3 3,349 +/- 184 3,280 1,968 - 4,592 Pass SPW-2132 5/4/2016 H-3 3,174+/-178 3,280 1,968 - 4,592 Pass SPW-2229 5/7/2016 H-3 3,182 +/- 179 3,280 1,968 - 4,592 Pass SPW-2313 5/13/2016 H-3 3,183 +/- 179 3,280 1,968 - 4,592 Pass SPW-2341 5/13/2016 H-3 3,201 +/- 178 3,280 1,968 - 4,592 Pass SPW-2374 5/14/2016 H-3 3,037 +/- 175 3,280 1,968 - 4,592 Pass SPW-2411 5/17/2016 Sr-90 37.3+/-1.6 37.3 22.4 - 52.2 Pass SPW-2455 5/19/2016 Gr. Alpha 19.3 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-2455 5/19/2016 Gr. Beta 28.6 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-2457 5/19/2016 U-238 48.2 +/- 2.4 41.7 25.0 - 58.4 Pass SPW-2504 5/20/2016 H-3 3,181 +/- 178 3,280 1,968 - 4,592 Pass SPW-2528 5/23/2016 H-3 2,998 +/- 175 3,280 1,968 - 4,592 Pass SPW-2566 5/24/2016 Gr. Alpha 19.8 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-2566 5/24/2016 Gr. Beta 30.4 +/- 0.3 28.9 17.3-40.4 Pass W-053116 4/29/2016 Cs-134 34.0 +/- 5.0 36.2 21.7 - 50.6 Pass W-053116 4/29/2016 Cs-137 78.8 +/- 7.0 71.9 43.1 -100.6 Pass SPW-2704 6/1/2016 Sr-90 38.0 +/- 1.6 37.3 22.4 - 52.2 Pass SPW-2719 6/2/2016 Ra-228 18.1 :i: 2.1 17.7 10.6 - 24.8 Pass SPW-2749 6/3/2016 H-3 3,197+/-180 3,280 1,968 - 4,592 Pass SPW-2843 6/7/2016 H-3 3,133 +/- 179 3,280 1,968 - 4,592 Pass SPW-3227 6/17/2016 Ra-226 18.6 +/- 0.4 16.7 10.0 - 23.4 Pass W-061716 4/29/2016 Cs-134 37.3 +/- 8.2 36.2 21.7 - 50.6 Pass W-061716 4/29/2016 Cs-137 79.7 +/- 10.8 71.9 43.1 -100.6 Pass SPW-3240 6/28/2016 Gr. Alpha 25.3 +/- 0.5 20.1 12.0-28.1 Pass SPW-3240 6/28/2016 Gr. Beta 27.1 +/- 0.3 28.9 17.3 - 40.4 Pass A3-1
TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-3241 7/1/2016 H-3 8,821 +/- 283 8,650 5, 190 - 12, 110 Pass SPW-3309 7/1/2016 H-3 8,619 +/- 278 8,650 5, 190 - 12, 110 Pass SPW-3313 7/1/2016
. Ra-228 16.6 +/- 2.0 17.7 10.6 - 24.8 Pass SPW-3328 7/6/2016 Sr-89 13.4 +/- 9.2 14.8 8.9 - 20.7 Pass SPW-3328 7/6/2016 Sr-90 12.3+/-1.3 11.4 6.8 - 16.0 Pass SPAP-3365 7/7/2016 Gr. Beta 39.7 +/-0.1 42.2 25.3 - 59.0 Pass SPAP-3367 717/2016 Cs-134 1.2 +/- 0.7 1.2 0.7-1.7 Pass SPAP-3367 717/2016 Cs-137 94.4 +/- 2.8 94.0 56.4 -131.6 Pass SPW-3370 717/2016 C-14 4,444 +/- 17 4,735 2,841 -6,629 Pass SPW-3373 717/2016 Ni-63 446 +/-5 401 241 - 561 Pass SPW-3375 7/7/2016 Tc-99 545 +/-9 539 324 - 755 Pass SPW-3519 7/14/2016 H-3 8,621 +/- 279 8650 5,190 -12,110 Pass SPW-3688 6/29/2016 Ra-226 17.5 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-3711 7/20/2016 H-3 44,368 +/- 612 43,766 26,260 - 61,273 Pass SPW-3774 7/22/2016 H-3 45,259 +/- 619 43,766 26,260 - 61,273 Pass SPW-3776 7/22/2016 Gr. Alpha 23.3 +/- 0.5 20.1 12.0 -28.1 Pass SPW-3776
- 7/22/2016 Gr. Beta 27.5 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-3884 7/26/2016 H-3 45,850 +/- 623 43,766 26,260 - 61,273 Pass SPW-3950 7/28/2016 Ra-228 17.8+/-1.8 16.7 10 - 23 Pass SPW-3982 7/29/2016 H-3 45,273 +/- 619 43,766 26,260 - 61,273 Pass W-073016 4/29/2016 Cs-134 36.5 +/- 6.1 36.2 21.7 - 50.6 Pass W-073016 4/29/2016 Cs-137 80.6 +/- 7.5 71.9 43.1 -100.6 Pass SPW-4134 8/4/2016 Ra-228 5.5 +/- 0.8 6.7 4.0 - 9.3 Pass SPW-4340 8/17/2016 Ra-228 19.9 +/- 2.0 16.7 10.0 - 23.4 Pass SPW-4386 7/15/2016 Ra-226 18.0 +/- 0.4 16.7 10.0 - 23.4 Pass W-082716 4/29/2016 Ra-228 32.5 +/- 5.2 36.2 21.7 - 50.6 Pass W-082716 4/29/2016 Ra-226 78.5 +/- 8.3 71.9 43.1 - 100.6 Pass SPW-4642 9/6/2016 U-238 45.8 +/- 2.5 41.7 25.0 - 58.4 Pass SPW-4999 9/26/2016 Sr-90 35.1 +/- 2.2 36.8 22.1 - 51.5 Pass
. SPW-5091 9/12/2016 Ra-226 18.2 +/- 0.4 16.7 10.0 -23.4 Pass W-092716 4/29/2016 Cs-134 37.3 +/- 11.8 36.2 21.7 -50.6 Pass W-092716 4/29/2016 Cs-137 78.3 +/- 11.2 71.9 43.1 - 100.6 Pass SPW-5165 9/30/2016 Gr. Alpha 22.2 +/- 0.4 20.1 12.0 -28.1 Pass SPW-5165 9/30/2016 Gr. Beta 27.2 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-5426 9/28/2016 Ra-226 18.2 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-5510 10/18/2016 H-3 44,398 +/- 618 43,766 26,260 - 61273 Pass SPW-5553 10/19/2016 U-238 50.0 +/- 2.6 41.7 25.0 - 58.4 Pass SPW-5555 10/19/2016 Ra-228 17.4+/-1.9 16.7 10.0 - 23.4 Pass SPW-5612 10/20/2016 H-3 44,681 +/- 622 43,766 26,260 - 61,273 Pass SPW-5741 10/25/2016 H-3 44,946 +/- 624 43,766 26,260 - 61,273 Pass SPU-5833 10/26/2016 H-3 10,018 +/- 946 8,622 5,173 -12,071 Pass SPW-5862 10/28/2016 H-3 18,061 +/- 374 17,244 10,346 - 24,141 Pass W-103116 4/29/2016 Cs-134 36.0 +/- 4.6 36.2 21.7 - 50.6 Pass W-103116 4/29/2016 Cs-137 81.1 +/-7.3 71.9 43.1 -100.6 Pass A3-2
TABLE A-3. In-House "Spiked" Samples Concentration a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-5984 11/2/2016 H-3 17,727 +/- 399 17,244 10,346 -24,141 Pass SPW-6008 11/4/2016 H-3 17,854 +/- 402 17,244 10,346 - 24,141 Pass SPW-6124 11/8/2016 Ra-228 14.4+/-1.9 16.0 9.6 - 22.4 Pass SPW-6132 11/9/2016 H-3 18,135+/-374 17,243 10,346 -24,140 Pass SPW-6135 10/12/2016 Ra-226 18.9 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-6146 11/10/2016 H-3 17,488 +/- 398 17,243 10,346 - 24,140 Pass SPW-6222 11/12/2016 H-3 17,787 +/- 408 17,243 10,346 - 24, 140 Pass SPW-6318 11/16/2016 H-3 17,379 +/- 408 17,243 10,346 -24,140 Pass SPW-6349 11/17/2016 H-3 17,893 +/- 371 17,243 10,346 -24,140 Pass SPW-6424 11/19/2016 H-3 18,258 +/- 379 17,243 10,346 -24,140 Pass W-112616 4/29/2016 Cs-134 35.0 +/- 6.0 36.2 21.7 -50.6 Pass W-112616 4/29/2016 Cs-137 75.0 +/- 7.1 71.9 43.1 -100.6 Pass SPW-6456 11/28/2016 Sr-90 41.9 +/- 2.5 36.8 22.1 - 51.5 Pass SPW-6486 11/30/2016 Sr-90 35.6 +/- 2.2 36.6 21.9-51.2 Pass SPW-6490 11/29/2016 Ra-226 18.8 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-6519 11/30/2016 Ni-63 438 +/- 4 400 240 -560 Pass SPW-6527 121112016 '
U-238 49.5 +/- 2.5 41.7 25.0 - 58.4 Pass SPW-6616 12/3/2016 H-3 18,018 +/- 374 17,243 10,346 -24,140 Pass SPW-6669 12/5/2016 H-3 18,237 +/- 377 17,243 10,346 -24,140 Pass SPW-6735 12/9/2016 H-3 17,939 +/- 396 17,243 10,346 -24,140 Pass SPW-6880 12/21/2016 H-3 17,835 +/- 396 17,243 10,346 -24,140 Pass SPW-6947 12/22/2016 Ni-63 450 +/-4 400 240 - 560 Pass W-122316 4/29/2016 Cs-134 36.0 +/- 2.2 36.2 21.7 - 50.6 Pass W-122316 4/29/2016 Cs-134 76.1 +/- 2.9 71.9 43.1 - 100.6 Pass SPW-6948 12/30/2016 H-3 17,999 +/- 398 17,243 10,346 -24,140 Pass SPW-6974 12/29/2016 Ra-226 17.6 +/- 0.4 16.7 10.0 - 23.4 Pass a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
c Results are based on single determinations.
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2s.
NOTE: For fish, gelatin is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.
A3-3
TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66a)
Acceptance Type LLD Activityc Criteria (4.66 a)
SPW"289 Water 1/21/2016 Sr-90 0.55 0.28 +/- 0.29 SPW-291 Water 1/21/201,6 Sr-90 0.61 0.15 +/- 0.30 SPW-293 Water 1/21/2016 C-14 147
-12 +/- 89 200 SPW-413 Water 2/1/2016 Ra-228 0.86 1.86 +/- 0.60 2
W-020416 Water 2/4/2016 Gr. Alpha 0.43
-0.17 +/- 0.28 2
W-020416 Water 2/4/2016 Gr. Beta 0.73 0.36 +/- 0.53 4
W-020916 Water 2/9/2016 Ra-226 0.02 0.01 +/- 0.01 2
W-030716 Water 317/2016 Gr. Alpha 0.90
-0.36 +/- 0.32 2
W-030716 Water 317/2016 Gr. Beta 1.59
-0.62 +/- 0.71 4
SPDW-70045 Water 3/29/2016 Ra-226 0.03 0.01 +/- 0.02 2
SPDW-1234 Water 3/30/2016 Gr. Alpha 0.44
-0.05 +/- 0.30 2
SPDW-1234 Water 3/30/2016 Gr. Beta 0.79
-0.54 +/- 0.54 4
SPW-1738 Water 4/21/2016 Ra-228 1.05 0.13 +/- 0.50 2
SPW-1822 Water 4/23/2016 Gr. Alpha 0.50
-0.18 +/- 0.33 2
SPW-1822 Water 4/23/2016 Gr. Beta 0.08
-0.35 +/- 0.51 4
SPW-2051 Water 4/12/2016 Ra-226 0.02 0.03 +/- 0.02 2
SPW-2069 Water 5/3/2016 1-131 0.15 0.06 +/- 0.09 SPW-2133 Water 5/4/2016 H-3 148 55 +/- 76 200 SPW-2230 Water 517/2016 H-3 149
-11"+/-73 200 SPW-2314 Water 5/13/2016 H-3 150
-29 +/- 72 200 SPW-2342 Water 5/13/2016 H-3 143 50 +/- 74 200 SPW-2364 Water 5/13/2016 1-131 0.22
-0.03 +/- 0.12 SPW-2375 Water 5/14/2016 H-3 146 1 +/- 70 200 SPW-2410 Water 5/17/2016 Sr-90 0.59 0.10 +/- 0.29 1
SPW-2454 Water 5/19/2016 Gr. Alpha 0.47
-0.21 +/- 0.31 2
SPW-2454 Water 5/19/2016 Gr. Beta 0.77
-0.49 +/- 0.52 4
SPW-2456 Water 5/19/2016 U-238 0.15 0.00 +/- 0.09 SPW-2485 Water 5/20/2016 1-131 0.18
-0.01 +/- 0.10 SPW-2505 Water 5/20/2016 H-3 144 64 +/- 75 200 SPW-2529 Water 5/23/2016 H-3 152
-3 +/- 75 200 SPW-2530 Water 5/23/2016 Ra-228 0.96
-0.12 +/- 0.43 2
SPW-2565 Water 5/24/2016 Gr. Alpha 0.47 0.03 +/- 0.33 2
SPW-2565 Water 5/24/2016 Gr. Beta 0.77
-0.23 +/- 0.53 4
SPW-2703 Water 6/1/2016 Sr-89 0.68
-0.13 +/- 0.50 5
SPW-2703 Water 6/1/2016 Sr-90 0.55 0.11 +/- 0.27 1
SPW-2718 Water 6/2/2016 Ra-228 0.67 0.23 +/- 0.34 2
SPW-2720 Water 6/2/2016 1-131 0.16 0.01 +/- 0.09 1
SPW-2750 Water 6/3/2016 H-3 151
-31 +/- 73 200 SPW-2844 Water 617/2016 H-3 148
-55 +/- 75 200 SPMl-2959 Milk 6/14/2016 1-131 0.16 0.09 +/- 0.10 SPW-3137 Water 6/23/2016 1-131 0.15
-0.03 +/- 0.08 SPW-3226 Water 6/17/2016 Ra-226 0.02
-0.01 +/- 0.04 2
SPW-3239 Water 6/28/2016 Gr. Alpha 0.40
-0.15 +/- 0.26 2
SPW-3239 Water 6/28/2016 Gr. Beta 0.73 0.14 +/- 0.52 4
SPW-3687 Water 6/29/2016 Ra-226 0.04 0.03 +/- 0.03 2
a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3J, charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b l-131(G); iodine-131 as analyzed by gamma spectroscopy.
0 Activity reported is a net activity result.
A4-1
TABLE A-4. In-House "Blank" Samples Lab Code SPW-3312 SPW-3327 SPW-3327 SPAP-3364 SPW-3370 SPW-3372 SPW-3374 SPW-3710 SPW-3775 SPW-3775 SPW-3884 SPW-3949 SPW-3982 SPW-4133 SPW-4257 SPW-4339 SPW-4385 SPW-4641 SPW-4684 SPW-4872 SPW-4998 SPW-4998 SPW-5090 SPW-5164 SPW-5164
,SPW-5425 SPW-5323 SPW-5552 SPW-5554 SPW-5611 SPW-5613 SPW-5613 SPW-5740 SPW-5743 SPW-5861 SPW-5983 SPW-6007 SPW-6131 SPW-6134 SPW-6145 SPW-6317 SPW-6348 SPW-6423 SPW-6455 SPW-6455 SPW-6489 Sample Type Water Water Water AP Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Date 7/1/2016 7/6/2016 7/6/2016 7/7/2016 7/7/2016 7/7/2016 7/7/2016 7/20/2016 712212016 712212016 7/2612016 7/2812016 7129/2016 81412016 8111/2016 8117/2016 7/1512016 9/612016 91812016 9/1612016 9126/2016 9/26/2016 811912016 9/3012016 9/3012016 9/2812016 10nt2016 1011912016 1011912016 1012012016 1012112016 10121/2016 1012512016 10/2512016 1012812016 111212016 111412016 111912016 1011212016 1111012016 1111612016 1111712016 1111912016 1112812016 1112812016 1112912016 Analysisb Ra-228 Sr-89 Sr-90 Gr.Beta C-14 Ni-63.
Tc-99 H-3 Gr. Alpha Gr. Beta H-3 Ra-228 H-3 Ra-228 1-131 Ra-228
- Ra-226 U-238 H-3 1-131 Sr-89 Sr-90 Ra-226 Gr. Alpha Gr. Beta Ra-226 H-3 U-238 Ra-228 H-3 Gr. Alpha Gr. Beta H-3 Sr-90 H-3 H-3 H-3 H-3 Ra-226 H-3 H-3 H-3 H-3 Sr-89 Sr-90 Ra-226 Concentration a Laboratory results (4.66cr)
LLD Activity 0
0.67 0.67 0.60 0.002 115 122 6.07 147 0.73 0.45 151 0.76 145 0.80 0.17 0.73 0.09 0.21 151 0.21 0.54 0.53 0.03 0.46 0.74 0.02 157 0.18 0.72 153 0.76 0.42 154 1.26 179 156 156 180 0.05 171 180 182 181 0.58 0.67 0.03 0.35 +/- 0.35 0.51 +/- 0.51
-0.14 +/- 0.26 0.005 +/- 0.001 49 +/- 71 115 +/- 76 1.00 +/- 3.70 35 +/- 75 0.41 +/- 0.53
-0.14 +/- 0.30
-1 +/- 73 0.32 +/- 0.39 49 +/- 75 0.26 +/- 0.40
-0.01 +/-0.10 0.36 +/- 0.39 0.75 +/- 0.09 0.00 +/- 0.13 48 +/-78 0.05 +/- 0.11 0.06 +/- 0.39
-0.03 +/- 0.24 0.03 +/- 0.02
-0.05 +/- 0.32
-0.02 +/- 0.52 0.07 +/- 0.05
-12 +/- 75 0.00+/-0.11 0.22 +/- 0.36 67 +/- 80
-0.55 +/- 0.51 0.02 +/- 0.29
-2 +/- 72 0.72 +/- 0.67 129 +/- 91 8 +/- 78
-34 +/- 73 80 +/- 92
-0.02 +/-0.12
-46 +/- 80
-43 +/- 82
-45 +/- 88 8 +/- 95
-0.15+/-0.46 0.09 +/- 0.32 0.03 +/- 0.02 Acceptance Criteria (4.66 cr) 2 5
1 0.01 200 200 10 200 2
4 200 2
200 2
2 2
200 5
2 2
4 2
200 2
200 2
4 200 1
200 200 200 200 2
200 200 200 200 5
2
- Liquid sample results are reported in pCi/Liter, air filters ( pCiim\\ charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b l-131(G); iodine-131 as analyzed by gamma spectroscopy.
' Activity reported is a net activity result.
A4-2
TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66cr)
Acceptance Type LLD Activity 0
Criteria (4.66 er)
SPW-6529 Water 12/1/2016 1-131 0.18
-0.03 +/- 0.10 SPW-6616 Water 12/3/2016 H-3 180 72 +/- 92 200 SPW-6670 Water 12/5/2016 H-3 174 28 +/- 92 200 SPW-6735 Water 12/9/2016 H-3 152 2 +/- 73 200 SPW-6792 Water 12/15/2016 1-131 0.17 0.03 +/- 0.12 SPW-6819 Water 12/16/2016 H-3 158 14 +/- 77 200 SPW-6879 Water 12/21/2016 H-3 147 80 +/- 75 200 SPW-6947 Water 12/22/2016 Ni-63 93 26 +/- 57 200 SPW-6973 Water 12/29/2016 Ra-226 0.03 0.03 +/- 0.02 2
a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b l-131(G); iodine-131 as analyzed by gamma spectroscopy.
c Activity reported is a net activity result.
A4-3
TABLE A-5. In-House "Duplicate" Samples Lab Code AP-010416
_SPS-62, 63 WW-125, 126 SPS-199, 200 SPS-199, 200 AP-011116 AP-011216 WW-262, 263 WW-346, 347 WW-283, 284 AP-011916 AP-012016 AP-020116 SWU-472, 473 SG-493, 494 SG-493, 494 SG-493, 494 AP-020816 AP-020916 SPS-619, 620 WW-640, 641 AP-021916 WW-822, 823 DW-70010, 70011 DW-70010, 70011 SW-934, 935 SPS-913, 914 SPS-913, 914 SPS-913, 914 SPS-913, 914 AP-030716 F-1303, 1304 SG-976, 977 SG-976, 977 PM-1094, 1095 Ml-1042,1043 DW-70023, 70024 DW-70023, 70024 DW-70014, 70015 DW-70026, 70027 DW-70038, 70039 DW-70035, 70036 DW-70035, 70036 AP-031516 AP-032116 AP-1218,1219 AP-1719,1720 AP-033016 SPS-1260, 1261 XW-1467, 1468 XWW-1530, 1531 AP-1827, 1828 AP-1323, 1324 LW-1446,1447 Date 1/4/2016 117/2016 1/7/2016 117/2016 117/2016 1/11/2016 1/12/2016 1/14/2016 1/14/2016 1/18/2016 1/19/2016 1/20/2016 2/1/2016 2/2/2016 2/6/2016 2/6/2016 2/6/2016' 2/8/2016 2/9/2016 2/18/2016 2/18/2016 2/19/2016 2/26/2016 2/29/2016 2/29/2016 3/1/2016 3/3/2016 3/3/2016 3/3/2016 3/3/2016 317/2016 317/2016 3/8/2016 3/8/2016 3/9/2016 317/2016 317/2016 317/2016 317/2016 317/2016 3/8/2016 3/8/2016 3/8/2016 3/15/2016 3/21/2016 3/24/2016 3/28/2016 3/30/2016 3/30/2016 3/30/2016 3/30/2016 3/30/2016 3/31/2016 3/31/2016 Analysis Gr. Beta K-40 H-3 Cs-137 K-40 Gr. Beta Gr. Beta H-3 H-3 H-3 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Ac-228 K-40 Pb-214 Gr. Beta Be-7 K-40 H-3 Gr. Beta H-3 Ra-226 Ra-228 Gr. Beta Cs-137 K-40 Ra-226 Ra-228 Gr. Beta K-40 Ra-226 Ra-228 K-40 K-40 Ra-226 Ra-228 Gr. Alpha Gr. Alpha Gr. Alpha Ra-226 Ra-228 Gr. Beta Gr. Beta Be-7 Be-7 Gr. Beta K-40 H-3 H-3 Be-7 Be-7 Gr. Beta First Result 0.044 +/- 0.006 21.1 +/- 1.9 659+/-102 0.09 +/- 0.02 7.60 +/- 0.60 0.024 +/- 0.005 0.030 +/- 0.004 153 +/- 78 1,036 +/- 117 437 +/- 92 0.042 +/- 0.005 0.023 +/- 0.003 0.023 +/- 0.005 4.37 +/- 0.47 2.10 +/- 0.20 5.79 +/- 0.57 1.84 +/- 0.11 0.020 +/- 0.004 0.032 +/- 0.005 20.0 +/- 1.8 90.1 +/- 75.0 0.021 +/- 0.003 2,770 +/- 173 4.88 +/- 0.29 3.00 +/- 0.77 0.94 +/- 0.52 0.08 +/- 0.03 17.45 +/- 0.94 1.02 +/- 0.08 1.09 +/-0.15 0.018 +/- 0.005 3.320 +/- 0.475 6.75 +/- 0.25 9.21 +/- 0.49 14.01 +/- 0.68 1,684 +/- 124 3.40 +/- 0.43 4.46 +/- 0.83 13.38 +/- 1.58 3.46 +/- 0.79 1.14 +/- 0.89 0.47 +/- 0.10 0.56 +/- 0.45 0.014 +/- 0.003 0.014 +/- 0.004 0.135 +/- 0.065 0.075 +/- 0.008 0.023 +/- 0.004 18.00+/-1.92 310 +/- 87 198 +/- 84 0.069 +/- 0.011 0.206 +/- 0.120 2.36 +/- 0.93 AS-1 Concentration a Second Result 0.051 +/- 0.006 21.2 +/- 2.1 748 +/- 106 0.08 +/- 0.03 8.62 +/- 0.62 0.027 +/- 0.005 0.034 +/- 0.004 141 +/- 78 959 +/- 115 427 +/- 91 0.037 +/- 0.004 0.030 +/- 0.004 0.023 +/- 0.005 4.60 +/- 0.49 2.13 +/- 0.20 5.50 +/- 0.69 1.91 +/- 0.11 0.019 +/- 0.004 0.041 +/- 0.006 19.1 +/- 1.6 153.6 +/- 78.4 0.025 +/- 0.004 2,974 +/- 178 4.93 +/- 0.28 1.90 +/- 0.62 1.36 +/- 0.60 0.10 +/- 0.03 16.83 +/- 0.95 1.13+/-0.17 1.13 +/- 0.17 0.021 +/- 0.005 3.508 +/- 0.396 6.28 +/- 0.22 9.09 +/- 0.49 14.47 +/- 0.72 1,804+/-119 2.68 +/- 0.35 5.74 +/- 0.94 11.40 +/- 1.43 3.08 +/- 0.74 1.73 +/- 0.95 0.45 +/- 0.09 0.47 +/- 0.44 0.016 +/- 0.004 0.020 +/- 0.004 0.167 +/-0.081 0.076 +/- 0.007 0.025 +/- 0.004 19.67+/-1.77 295 +/- 86 162 +/- 82 0.072 +/- 0.011 0.197 +/- 0.091 2.23 +/- 1.01 Averaged Result 0.047 +/- 0.004 21.2 +/- 1.4 703 +/- 74 0.08 +/- 0.02 8.11 +/- 0.43 0.026 +/- 0.003 0.032 +/- 0.003 147 +/- 55 997 +/- 82 432 +/- 65 0.040 +/- 0.003 0.027 +/- 0.002 0.023 +/- 0.004 4.49 +/- 0.34 2.12 +/- 0.14 5.65 +/- 0.45 1.88 +/- 0.08 0.020 +/- 0.003 0.036 +/- 0.004 19.5+/-1.2 121.8 +/- 54.2 0.023 +/- 0.002 2,872 +/- 124 4.91 +/- 0.20 2.45 +/- 0.49 1.15 +/- 0.40 0.09 +/- 0.02 17.14 +/-0.67 1.07 +/- 0.09 1.11 +/- 0.11 0.019 +/- 0.003 3.414 +/- 0.309 6.52 +/- 0.17 9.15 +/- 0.35 14.24 +/- 0.49 1,744+/-86 3.04 +/- 0.28 5.10 +/- 0.63 12.39+/-1.07 3.27 +/- 0.54 1.44 +/- 0.65 0.46 +/- 0.07 0.52 +/- 0.31 0.015 +/- 0.002 0.017 +/- 0.003 0.151 +/- 0.052 0.076 +/- 0.005 0.024 +/- 0.003 18.84+/-1.30 303 +/- 61 180 +/- 59 0.071 +/- 0.008 0.202 +/- 0.076 2.29 +/- 0.69 Acceptance Pass
- Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-5. In-House "Duplicate" Samples Lab Code WW-1740,1741 SPS-1344, 1345 SPS-1344, 1345 SPS-1344, 1345 SPS-1344, 1345 P-1509, 1510 AP-041116 SS-1551, 1552 SS-1551, 1552 SS-1551, 1552 SS-1551, 1552 SS-1551, 1552 SS-1551, 1552 SS-1551, 1552 SS-1593, 1594 WW-1677, 1678 WW-1783,1784 BS-1804, 1805 WW-2021,2022 XWW-2240, 2241 XWW-2109, 2110 SPS-2130, 2131 AP-042516 BS-2065, 2066 AP-042716 SPS-1999, 2000 S0-2153,2154 S0-2153,2154 S0-2153,2154 S0-2153,2154 W-2394,2395 VE-2284,2285 AP-051016 SG-2261, 2262 SG-2261, 2262 BS-2439, 2440 WW-2534,2535 AP-051716 SPS-2945, 2946 SPS-2945, 2946 SPS-2578, 2579 AP-052516 G-2642,2643 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 S0-2663, 2664 SPS-2817, 2818 DW-70091, 70092 DW-70091, 70092 BS-2925,2926 SPS-2796, 2797 SPS-2882, 2883 SPS-2882, 2883 DW-70102, 70103 Date 4/2/2016 4/4/2016 4/4/2016 4/4/2016 4/4/2016 4/8/2016 4/11/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/12/2016 4/14/2016 4/14/2016 4/18/2016 4/18/2016 4/18/2016 4/19/2016 4/25/2016 4/25/2016 4/25/2016 4/27/2016 4/28/2016 5/2/2016 5/2/2016 5/2/2016 5/2/2016 5/5/2016 5/9/2016 5/10/2016 5/10/2016 5/10/2016 5/12/2016 5/16/2016 5/17/2016 5/19/2016 5/19/2016 5/24/2016 5/25/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/26/2016 5/31/2016 6/1/2016 6/1/2016 6/3/2016 6/2/2016 617/2016 617/2016 6/13/2016 Analysis H-3 K-40 Pb-214 Ac-228 Cs-137 H-3 Gr. Beta Gr. Beta K-40 Tl-208 Bi-214 Pb-212 Ra-226 Ac-228 K-40 Ra-226 H-3 K-40 H-3 H-3 H-3 K-40 Gr. Beta K-40 Gr. Beta K-40 K-40 Cs-137 Ra-226 Pb-214 H-3 K-40 Gr. Beta Ac-228 Pb-214 K-40 H-3 Gr. Beta K-40 Be-7 Pb-214 Gr. Beta Be-7 Cs-137 K-40 Tl-208 Pb-212 Ra-226 Ac-228 K-40 Ra-226 Ra-228 K-40 K-40 K-40 Be-7 Ra-226 First Result 21,162+/-120 17.98 +/- 0.93 1.12 +/- 0.09 1.23 +/- 0.15 0.13 +/- 0.03 1,084+/-120 0.020 +/- 0.004 8.71 +/- 1.11 3.50 +/- 0.25 0.05 +/- 0.02 0.10 +/- 0.02 0.13 +/- 0.02 0.35 +/- 0.17 0.16 +/- 0.05 14.80 +/- 0.73 0.23 +/- 0.13 768 +/- 111 0.79 +/- 0.02 5,548 +/- 221 638 +/- 104 3461 +/-185 7.80 +/- 0.84 0.020 +/- 0.004 14.40 +/- 1.50 0.023 +/- 0.003 19.84 +/- 1.76 21.80 +/- 0.81 0.11 +/- 0.03 1.50 +/- 0.29 0.56 +/- 0.06 736 +/- 106 3.50 +/- 0.25 0.020 +/- 0.005 34.4+/-1.2 29.5 +/- 3.0 9.96 +/- 0.91 14,342 +/- 354 0.014 +/- 0.004 30.71 +/- 0.74 1.55 +/- 0.24 0.96 +/-0.12 0.022 +/- 0.004 0.443 +/- 0.178 0.08 +/- 0.03 12.44 +/- 0.68 0.13 +/-0.02 0.43 +/- 0.04 1.19 +/-0.34 0.45 +/- 0.09 12.10 +/- 0.70 5.61 +/- 0.29 1.45 +/- 0.58 7.74 +/- 0.44 20.91 +/- 2.38 14.64 +/- 0.52 2.00 +/- 0.25 0.34 +/- 0.09 AS-2 Concentration a Second Result 21,091 +/-427 17.14 +/- 0.96 1.04 +/- 0.08 1.33 +/- 0.19 0.13 +/- 0.03 1,038 +/- 119 o*.019 +/- 0.004 8.88+/-1.13 3.06 +/- 0.28 0.05 +/- 0.02 0.09 +/- 0.02 0.11 +/- 0.02 0.30 +/- 0.17 0.17 +/- 0.05 14.89 +/- 0.78 0.35 +/- 0.15 632 +/- 107 0.87 +/- 0.19 5,707 +/- 224 543 +/- 101 3250 +/- 180 6.80 +/- 0.60 0.023 +/- 0.004 14.72+/-1.19 0.019 +/- 0.003 18.963 +/- 2.42 21.17 +/- 0.85 0.11 +/- 0.07 1.22 +/- 0.29 0.57 +/- 0.06 631 +/- 102 3.06 +/- 0.28 0.018 +/- 0.005 34.4 +/- 1.4 31.9+/-3.3 10.27 +/- 0.76 14,613 +/- 357 0.015 +/- 0.004 31.75 +/- 0.78 1.90 +/- 0.35 0.80 +/- 0.14 0.022 +/- 0.004 0.247 +/- 0.247 0.07 +/- 0.03 11.64 +/- 0.63 0.14 +/- 0.03 0.41 +/- 0.04 0.87 +/- 0.28 0.53 +/- 0.10 11.05 +/-0.70 5.53 +/- 0.30 1.91 +/- 0.62 7.86 +/- 0.42 21.16 +/- 1.82 14.60 +/- 0.52 1.94 +/- 0.20 0.36 +/- 0.08 Averaged Result 21, 126 +/- 222 17.56 +/- 0.67 1.08 +/- 0.06 1.28 +/- 0.12 0.13 +/-0.02 1,061 +/- 85 0.019 +/- 0.003 8.80 +/- 0.79 3.28+/-0.19 0.05 +/- 0.01 0.10 +/- 0.02 0.12 +/-0.01 0.32 +/- 0.12 0.17 +/- 0.04 14.85 +/- 0.53 0.29 +/- 0.10 700 +/-77 0.83 +/- 0.10 5,627 +/- 157 591 +/- 72 3356 +/- 129 7.30 +/- 0.52 0.022 +/- 0.003 14.56 +/- 0.96 0.021 +/- 0.002 19.40 +/- 1.50 21.48 +/- 0.59 0.11 +/- 0.04 1.36 +/- 0.21 0.57 +/- 0.04 683 +/- 74 3.28 +/-0.19 0.019 +/- 0.003 34.4 +/- 0.9 30.7 +/- 2.2 10.11 +/- 0.59 14,477 +/- 252 0.014 +/- 0.003 31.23 +/- 0.54 1.73 +/- 0.21 0.88 +/- 0.09 0.022 +/- 0.003 0.345 +/- 0.152 0.07 +/- 0.02 12.04 +/- 0.46 0.14+/-0.02 0.42 +/- 0.03 1.03 +/- 0.22 0.49 +/- 0.07 11.58 +/- 0.49 5.57 +/- 0.21 1.68 +/- 0.42 7.80 +/- 0.30 21.04+/-1.50 14.62 +/- 0.37 1.97 +/- 0.16 0.35 +/- 0.06 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-5. In-House "Duplicate" Samples Lab Code DW-70102, 70103 AP-061416 SG-3144, 3145 SG-3144, 3145 SPS-3165, 3166 SPS-3323, 3324 WW-3231, 3232 AP-3830,3831 AP-070516A AP-070516B XWW-3605,3606 DW-70135,70136 DW-70132,70133 DW-70132,70133 AP-071216 DW-70150,70151 SPS-3649,3650 SPS-3649,3650 SPS-3649,3650 SPS-3649,3650 AP-071816 DW-70163,70164 WW-3761,3762 SPS-4003,4004 AP-072516 VE-3936,3937 VE-3936,3937 VE-3936,3937 VE-3959,3960 VE-3959,3960 VE-3959,3960 DW-70169,70170 DW-70169,70170 AP-080116 SS-4131,4132 SS-4131,4132 SPS-4087,4088 WW-4976,4977 SPS-4266,4267 AP-081616 VE-4399,4400 VE-4399,4400 WW-5394,5395 SPS-4441,4442 AP-082216 VE-4462,4463 VE-4462,4463 WW-4594,4595 WW-4663,4664 SPS-4529,4530 AP-083016A AP-083016B VE-4615,4616 Date 6/13/2016 6/14/2016 6/17/20,16 6/17/2016 6/22/2016 6/24/2016 6/27/2016 6/29/2016 7/5/2016 7/5/2016 717/2016 7/8/2016 7/8/2016 7/8/2016 7/12/2016 7/14/2016 7/15/2016 7/15/2016 7/15/2016 7/15/2016 7/18/2016 7/19/2016 7/20/2016 7/23/2016 7/25/2016 7/25/2016 7/25/2016 7/25/2016 7/27/2016 7/27/2016 7/27/2016 7/28/2016 7/28/2016 8/1/2016 8/1/2016 8/1/2016 8/2/2016 8/4/2016 8/10/2016 8/16/2016 8/18/2016 8/18/2016 8/18/2016 8/22/2016 8/22/2016 8/22/2016 8/22/2016 8/26/2016 8/26/2016 8/26/2016 8/30/2016 8/30/2016 8/31/2016 Analysis Ra-228 Gr. Beta Be-7 K-40 K-40 K-40 H-3 Gr. Beta Gr. Beta Gr. Beta H-3 Gr. Alpha Ra-226 Ra-228 Gr. Beta Gr. Alpha Cs-137 K-40 Pb-214 Ac-228 Gr. Beta Gr. Alpha H-3 K-40 Gr. Beta Sr-90 Be-7 K-40 Sr-90 Be-7 K-40 Ra-226 Ra-228 Gr. Beta K-40 Cs-137 K-40 H-3 K-40 Gr. Beta K-40 Be-7 H-3 K-40 Gr. Beta Be-7 K-40 H-3 H-3 K-40 Gr. Beta Gr. Beta K-40 First Result 0.93 +/- 0.47 0.026 +/- 0.004 2.23 +/-0.12 7.57 +/- 0.25 21.14 +/-2.27 18.67 +/- 1.57 414 +/- 104 0.088 +/- 0.012 0.018 +/- 0.002 0.025 +/- 0.005 3,316 +/- 186 3.68 +/- 1.01 1.32+/-0.14 3.92 +/- 0.94 0.014 +/- 0.004 5.00 +/- 1.06 0.12 +/- 0.03 16.68 +/- 0.79 1.20 +/- 0.08 1.28 +/- 0.16 0.022 +/- 0.005 1.08 +/- 0.66 347 +/- 90 7.15 +/- 1.59 0.023 +/- 0.004 0.048 +/- 0.007 0.49 +/- 0.15 4.70 +/- 0.35 0.002 +/- 0.002 0.30 +/- 0.14 4.01 +/- 0.37 0.83 +/- 0.11 1.85 +/- 0.63 0.029 +/- 0.003 12.47 +/- 0.71 0.10 +/- 0.03 17.06 +/- 1.58 17,043 +/- 390 1.06 +/- 0.47 0.029 +/- 0.005 3.85 +/- 0.23 0.30 +/- 0.08 947 +/- 122 20.55 +/- 2.23 0.021 +/- 0.005 0.91 +/- 0.09 7.48 +/- 0.26 675 +/- 107 607 +/- 104 21.98 +/- 2.52 0.030 +/- 0.003 0.032 +/- 0.009 2.96 +/- 0.16 AS-3 Concentration a Second Result 1.11 +/- 0.53 0.023 +/- 0.004 2.24 +/-0.12 7.09 +/- 0.23 22.88 +/- 1.60 21.53+/-1.65 498+/-108 0.093 +/- 0.015 0.014 +/- 0.002 0.026 +/- 0.005 3,316 +/- 181 2.76 +/- 0.98 1.11 +/- 0.15 2.94 +/- 0.90 0.018 +/- 0.004 4.43 +/- 1.04 0.12 +/- 0.03 16.52 +/- 0.86 1.17 +/- 0.08 1.28 +/- 0.16 0.024 +/- 0.005 1.36 +/-0.70 466 +/- 96 6.86 +/- 1.21 0.020 +/- 0.004 0.058 +/- 0.010 0.51+/-0.15 4.86 +/- 0.37 0.003 +/- 0.001 0.25 +/- 0.12 4.16 +/- 0.34 0.69 +/- 0.11 1.31 +/- 0.84 0.033 +/- 0.003 13.24 +/- 0.81 0.13 +/- 0.04 19.5 +/- 1.97 16,821 +/- 388 1.69 +/- 0.52 0.025 +/- 0.004 3.27 +/- 0.41 0.45 +/- 0.20 846+/-119 19.69 +/- 1.74 0.015 +/- 0.005 0.89 +/- 0.11 7.60 +/- 0.23 788 +/- 111 501 +/- 100 21.85 +/- 1.56 0.035 +/- 0.004 0.026 +/- 0.004 3.11 +/-0.17 Averaged Result 1.02 +/- 0.35 0.024 +/- 0.003 2.24 +/- 0.08 7.33+/-0.17 22.. 01 +/- 1.39 20.10+/-1.14 456 +/- 75 0.091 +/- 0.010 0.016 +/- 0.002 0.025 +/- 0.004 3,316 +/- 130 3.22 +/- 0.70 1.22 +/- 0.10 3.43 +/- 0.65 0.016 +/- 0.003 4.72 +/- 0.74 0.12 +/- 0.02 16.6 +/- 0.58 1.19 +/-0.06 1.28 +/- 0.11 0.023 +/- 0.003 1.22 +/- 0.48 407 +/- 66 7.00 +/- 1.00 0.022 +/- 0.003 0.053 +/- 0.006 0.50 +/- 0.10 4.78 +/- 0.25 0.003 +/- 0.001 0.27 +/- 0.09 4.08 +/- 0.25 0.76 +/- 0.08 1.58 +/- 0.53 0.031 +/- 0.002 12.86 +/- 0.54 0.12 +/- 0.02 18.28 +/- 1.26 16,932 +/- 275 1.375 +/- 0.35 0.027 +/- 0.003 3.56 +/- 0.24 0.37 +/- 0.11 896 +/- 85 20.12 +/- 1.41 0.018 +/- 0.003 0.90 +/- 0.07 7.54 +/-0.17 731 +/- 77 554 +/- 72 21.92+/-1.48 0.033 +/- 0.002 0.029 +/- 0.005 3.03 +/- 0.11 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-5. In-House "Duplicate" Samples Lab Code AP-090216 AP-090616 Ml-4751,4752 Ml-4751,4752 SW-4772,4773 WW-5285,5286 Ml-4826,4827 VE-4868,4869 VE-4868,4869 CF-4934,4935 CF-4934,4935 AP-092016 DW-70196,70197 F-4955,4956 VE-5044,5045 VE-5044,5045 WW-5219,5220 SPS-5087,5088 AP-092716 AP-5660,5661 AP-5681,5682 VE-5110,5111 AP-5154,5155 AP-5702,5703 Ml-5264,5265 Ml-5264,5265 SS-5547,5548 SS-5547,5548 SS-5547,5548 SS-5547,5548 SS-5547,5548 SS-5547,5548 AP-101116 WW-5526.5527 WW-5639,5640 WW-5723,5724 F-5811,5812 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 S0-5900,5901 SS-5879,5880 SS-5879,5880 LW-6072,6073 BS-6009, 601 o BS-6009, 6010 F-6211,6212 F-6211,6212 DW-70230, 70231 DW-70230, 70231 F-6093,6094 Date 9/2/2016 9/6/2016 917/2016 9/7/2016 9/8/2016 9/13/2016 9/14/2016 9/15/2016 9/15/2016 9/19/2016 9/19/2016 9/20/2016 9/20/2016 9/20/2016 9/20/2016 9/20/2016 9/20/2016 9/23/2016 9/27/2016 9/28/2016 9/27/2016 9/28/2016 9/29/2016 9/30/2016 10/4/2016 10/4/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/11/2016 10/19/2016 10/18/2016 10/20/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/22/2016 10/25/2016 10/25/2016 10/27/2016 10/27/2016 10/27/2016 10/28/2016 10/28/2016 10/28/2016 10/28/2016 10/31/2016 Analysis Gr. Beta Gr. Beta K-40 Sr-90 H-3 H-3 K-40 Gr. Beta K-40 K-40 Be-7 Gr. Beta Gr. Alpha K-40 Be-7 K-40 H-3 K-40 Gr. Beta Be-7 Be-7 K-40 Be-7 Be-7 K-40 Sr-90 Gr. Beta K-40 Tl-208 Bi-214 Pb-212 Ac-228 Gr. Beta H-3 H-3 H-3 K-40 Cs-137 K-40 Tl-208 Pb-212 Bi-214 Ac-228 Ra-226 Gr. Beta K-40 Cs-137 Gr. Beta Cs-137 K-40 Gr. Beta K-40 Ra-226 Ra-228 K-40 First Result 0.022 +/- 0.004 0.023 +/- 0.005 1,693+/-112 1.23 +/- 0.38 196 +/- 91 18,010 +/-400 1,372.6 +/- 105 2.50 +/- 0.06 2.20 +/- 0.17 11.47+/-0.82 0.43 +/- 0.22 0.021 +/- 0.004 13.8+/-1.36 3.40 +/- 0.44 0.46 +/- 0.05 4.37 +/- 0.12 63,744 +/- 743 21.04 +/- 2.32 0.031 +/- 0.005 0.093 +/- 0.014 0.079 +/- 0.019 1.82 +/-0.15 0.237 +/- 0.116 0.084 +/- 0.015 1,636+/-128 2.00 +/- 0.44 11.27 +/- 1.19 8.03 +/- 0.45 0.04 +/- 0.02 0.14 +/- 0.03 0.12+/-0.02 0.10 +/- 0.05 0.032 +/- 0.004 18,865 +/- 408 192 +/- 103 36,012 +/- 560 0.91 +/- 0.30 0.05 +/- 0.02 9.82 +/- 0.60 0.10 +/-0.02 0.32 +/- 0.03 0.20 +/- 0.04 0.41 +/- 0.08 0.45 +/- 0.23 16.49 +/- 1.01 14.94 +/- 0.83 0.06 +/- 0.03 0.88 +/- 0.49 0.14 +/-0.08 17.04 +/- 1.58 3.25 +/- 0.07 2.45 +/- 0.33 4.00 +/- 0.20 5.30 +/- 0.80 3.77 +/- 0.50 A5-4 Concentration a Second Result 0.027 +/- 0.004 0.023 +/- 0.005 1,760 +/- 99 1.00 +/-'0.33 236 +/- 93 18,686 +/- 407 1,198.1 +/- 97 2.57 +/- 0.06 2.30 +/- 0.17 11.76+/-0.50 0.46 +/-0.13 0.017 +/- 0.004 15.28 +/- 1.36 2.86 +/- 0.39 0.50 +/- 0.11 4.68 +/- 0.24 64,755 +/- 749 18.84 +/-1.88 0.032 +/- 0.005 0.086 +/- 0.019 0.071 +/- 0.015 2.14 +/- 0.18 0.195 +/- 0.096 0.070 +/- 0.018 1,610 +/- 124 1.28 +/- 0.37 9.47 +/- 1.20 7.23 +/- 0.46 0.04 +/- 0.02 0.12 +/-0.03 0.11 +/- 0.02 0.16 +/-0.05 0.028 +/- 0.004 18,904 +/- 408 52 +/- 98 36,207 +/- 561 0.75 +/- 0.22 0.03 +/- 0.02 10.77 +/- 0.61 0.14 +/- 0.03 0.33 +/- 0.03 0.27 +/- 0.04 0.48 +/- 0.09 0.61 +/- 0.27 17.71 +/- 1.03 15.26 +/- 0.84 0.09 +/- 0.04 1.53 +/- 0.56 0.13 +/-0.06 18.30 +/- 1.42 3.27 +/- 0.07 2.49 +/- 0.37 4.10 +/- 0.30 5.20 +/- 0.80 3.51 +/- 0.44 Averaged Result 0.024 +/- 0.003 0.023 +/- 0.003 1,726+/-75 1.11 +/- 0.25 216 +/- 65 18,348 +/- 286 1,285.4 +/- 71 2.53 +/- 0.04 2.25 +/- 0.12 11.61 +/- 0.48 0.45 +/- 0.13 0.019 +/- 0.003 14.54 +/- 0.96 3.13 +/- 0.30 0.48 +/- 0.06 4.53 +/- 0.13 64,250 +/- 527 19.94 +/- 1.49 0.031 +/- 0.003 0.089 +/- 0.012 0.075 +/- 0.012 1.98 +/- 0.12 0.216 +/- 0.075 0.077 +/- 0.012 1,623 +/- 89 1.64 +/- 0.29 10.37 +/- 0.84 7.63 +/- 0.32 0.04 +/- 0.01 0.13 +/- 0.02 0.11 +/- 0.01 0.13+/-0.04 0.030 +/- 0.003 18,884 +/- 289 122 +/- 71 36,110 +/- 396 0.83 +/- 0.19 0.04 +/- 0.02 10.29 +/- 0.43 0.12+/-0.02 0.32 +/- 0.02 0.23 +/- 0.03 0.44 +/- 0.06 0.53 +/- 0.18 17.10 +/- 0.72 15.10 +/- 0.59 0.08 +/- 0.02 1.21 +/- 0.37 0.13 +/-0.05 17.67 +/-1.06 3.26 +/- 0.05 2.47 +/- 0.25 4.05 +/- 0.18 5.25 +/- 0.57 3.64 +/- 0.33 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-110116 11/1/2016 Gr. Beta 0.021 +/- 0.004 0.024 +/- 0.004 0.023 +/- 0.003 Pass S-5963, 5964 11/1/2016 K-40 20.35 +/- 2.29 18.59 +/- 1.90 19.47+/-1.49
- pass SG-6119, 6120 11/1/2016 Ac-228 5.70 +/- 0.44 6.28 +/- 0.57 5.99 +/- 0.36 Pass SG-6119, 6120 11/1/2016 Gr. Alpha 21.59+/-1.88 24.35 +/- 1.93 22.97 +/- 1.35 Pass SG-6119, 6120 11/1/2016 K-40 4.89 +/- 1.10 5.90 +/- 1.08 5.40 +/- 0.77 Pass SG-6119, 6120 11/1/2016 Pb-214 3.99 +/- 0.21 4.35 +/- 0.32 4.17 +/- 0.19 Pass S-6051, 6052 11/4/2016 K-40 7.05 +/- 0.60 7.56 +/- 0.53 7.31 +/- 0.40 Pass WW-6297, 6298 11/8/2016 H-3 207 +/- 98 165 +/- 97 186 +/- 69 Pass WW-6341,6342 11/8/2016 H-3 1,356 +/- 140 1,404+/-141 1,380 +/- 99 Pass S0-6406,6407 11/9/2016 Cs-137 0.36 +/- 0.04 0.43 +/- 0.05 0.40 +/- 0.03 Pass S0-6406,6407 11/9/2016 K-40 10.90 +/- 0.68 11.29 +/- 0.74 11.09 +/- 0.50 Pass AP-111416 11/14/2016 Gr. Beta 0.024 +/- 0.005 0.021 +/- 0.006 0.022 +/- 0.004 Pass WW-6829,6830 11/15/2016 H-3 39,982 +/- 589 40,315 +/- 591 40,149 +/-417 Pass DW-70239, 70240 11/17/2016 Gr. Alpha 7.99 +/- 1.15 6.41 +/-1.05 7.20 +/- 0.78 Pass AP-112216 11/22/2016 Gr. Beta 0.049 +/- 0.005 0.045 +/- 0.005 0.047 +/- 0.003 Pass S-6473, 6474 11/24/2016 K-40 19.37 +/- 1.97 23.80 +/- 3.54 21.58 +/- 2.02 Pass SG-6938, 6939 11/28/2016 Ac-228 18.99 +/- 0.59 19.92 +/- 0.79 19.46 +/- 0.49 Pass SG-6938, 6939 11/28/2016 Pb-214 15.28 +/- 0.34 14.96 +/- 0.43 15.12 +/- 0.27 Pass AP-120116 12/1/2016 Gr. Beta 0.029 +/- 0.003 0.030 +/- 0.003 0.030 +/- 0.002 Pass F-6567,6568 12/1/2016 K-40 3.76 +/- 0.40 3.83 +/- 0.46 3.80 +/- 0.30 Pass S-6522, 6523 12/1/2016 Ac-228 1.08 +/- 0.13 1.29 +/- 0.16 1.19 +/-0.10 Pass S-6522, 6523 12/1/2016 Pb-214 1.00 +/- 0.08 1.01 +/- 0.09 1.01 +/- 0.06 Pass S-6609, 661 O 12/1/2016 K-40 15.57+/-1.01 15.99 +/- 0.78 15.78 +/-0.64 Pass S-6718, 6719 12/7/2016 K-40 18.19 +/-2.13 18.76+/-1.80 18.48 +/- 1.39 Pass WW-6784, 6785 12/7/2016 H-3 922 +/- 117 905+/-116 914 +/- 82 Pass AP-121216 12/12/2016 Gr. Beta 0.026 +/- 0.005 0.028 +/- 0.005 0.027 +/- 0.003 Pass AP-7178,7179 1/3/2017 Be-7 0.047 +/- 0.015 0.062 +/- 0.017 0.054 +/- 0.012 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil and sediment (pCi/g).
AS-5
TABLEA-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-1053 2/1 /2016 Ni-63 1,206 +/- 20 1250 875 -1625 Pass MAS0-1053 2/1 /2016 Sr-90 0.65 +/- 1.27 0.00 NA c Pass MAS0-1053 2/1 /2016 Tc-99 0.1 +/- 5.5 0.0 NA c Pass MAS0-1053 2/1 /2016 Cs-134 908 +/- 26 1030 721 -1339 Pass MAS0-1053 2/1/2016 Cs-137 0.10 +/- 6.20 0.00 NA c Pass MAS0-1053 2/1/2016 Co-57 1058 +/- 26 992 694 - 1290 Pass MAS0-1053 2/1/2016 Co-60 1229 +/- 28 1190 833-1547 Pass MAS0-1053 2/1/2016 Mn-54 1235 +/- 43 1160 812 - 1508 Pass MAS0-1053 2/1 /2016 Zn-65 753 +/- 64 692 484 - 900 Pass MAS0-1053 2/1 /2016 K-40 753 +/- 140 607 425 - 789 Pass MAS0-1053 2/1 /2016 Am-241 79 +/- 6 103 72 - 134 Pass MAS0-1053 2/1 /2016 Pu-238 73.9 +/- 9.2 63.6 44.5 - 82.7 Pass MAS0-1053 2/1 /2016 Pu-239/240 0.76 +/- 1.34 0.21 NAd Pass MAS0-1053 2/1/2016 U-234/233 45.0 +/- 5.1 45.9 32.1 - 59.7 Pass MAS0-1053 2/1/2016 U-238 129 +/- 9 146 102 - 190 Pass MAW-989 2/1/2016 Am-241 0.018 +/- 0.015 0.00 NA c Pass MAW-989 2/1/2016 H-3 0.2 +/- 2.8 0.0 NA c Pass MAW-989 2/1/2016 Ni-63 12.8 +/- 2.7 12.3 8.6 - 16.0 Pass MAW-989 2/1/2016 Sr-90 8.70 +/- 1.20 8.74 6.12 - 11.36 Pass MAW-989 2/1 /2016 Tc-99
-1.1 +/- 0.6 0.0 NA c Pass MAW-989 2/1 /2016 Cs-134 15.5 +/- 0.3 16.1 11.3 +/- 20.9 Pass MAW-989 2/1 /2016 Cs-137 23.7 +/- 0.5 21.2 14.8 - 27.6 Pass MAW-989° 2/1 /2016 Co-57 1.38 +/- 0.12 0.00 NA c Fail MAW-989 2/1/2016 Co-60 12.5 +/- 0.3 11.8 8.3 - 15.3 Pass MAW-989 2/1 /2016 Mn-54 12.2 +/- 0.4 11.1 7.8 - 14.4 Pass MAW-989 2/1 /2016 Zn-65 15.7 +/- 0.7 13.6 9.5 - 17.7 Pass MAW-989 2/1/2016 K-40 288 +/- 5 251 176 - 326 Pass MAW-989 2/1/2016 Fe-55 17.3 +/- 7.0 16.2 11.3-21.1 Pass MAW-989 2/1/2016 Ra-226 0.710 +/- 0.070 0.718 0.503 - 0.933 Pass MAW-989 2/1/2016 Pu-238 1.280 +/- 0.110 1.244 0.871 +/- 1.617 Pass MAW-989 2/1/2016 Pu-239/240 0.640 +/- 0.080 0.641 0.449 - 0.833 Pass MAW-989 2/1/2016 U-234/233 1.39 +/- 0.12 1.48 1.04-1.92 Pass MAW-989 2/1/2016 U-238 1.43 +/- 0.12 1.53 1.07 - 1.99 Pass MAW-893 2/1 /2016 Gross Alpha 0.600 +/- 0.050 0.673 0.202 -1.144 Pass MAW-893 2/1 /2016 Gross Beta 2.10 +/- 0.06 2.15 1.08 - 3.23 Pass MAW-896 2/1 /2016 1-129 3.67 +/- 0.20 3.85 2.70 - 5.01 Pass MAAP-1056 2/1/2016 Gross Alpha 0.39 +/- 0.05 1.20 0.36 - 2.04 Pass MAAP-1056 2/1/2016 Gross Beta 1.03 +/- 0.07 0.79 0.40 - 1.19 Pass A6-1
TABLEA-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-1057 2/1/2016 Sr-90 1.34 +/- 0.15 1.38 0.97 +/- 1.79 Pass MAAP-1057 2/1/2016 Cs-134
-0.01 +/- 0.03
,0.00 NA c Pass MAAP-1057 2/1/2016 Cs-137 2.57 +/- 0.10 2.30 1.61 - 2.99 Pass MAAP-1057 2/1/2016 Co-57 3.01 +/- 0.06 2.94 2.06 - 3.82 Pass MAAP-1057 2/1/2016 Co-60 4.28 +/- 0.10 4.02 2.81 - 5.23 Pass MAAP-1057 2/1/2016 Mn-54 4.90 +/- 0.13 4.53 3.17 - 5.89 Pass MAAP-1057 2/1/2016 Zn-65 4.09 +/- 0.18 3.57 2.50 -4.64 Pass MAAP-1057 2/1/2016 Am-241 0.059 +/- 0.015 0.0805 0.0564 - 0.1047 Pass MAAP-1057 2/1/2016 Pu-238 0.066 +/- 0.020 0.0637 0.0446 - 0.0828 Pass MAAP-1057 2/1/2016 Pu-239/240 '
0.074 +/- 0.020 0.099 NA d Pass MAAP-1057 2/1/2016 U-234/233 0.151 +/- 0.026 0.165 0.116 -0.215 Pass MAAP-1057 2/1/2016 U-238 0.160 +/- 0.026 0.172 0.120 - 0.224 Pass MAVE-1050 2/1/2016 Cs-134 9.83 +/- 0.19 10.62 7.43-13.81 Pass MAVE-1050 2/1/2016 Cs-137 6.06 +/- 0.19 5.62 3.93 - 7.31 Pass MAVE-1050 2/1/2016 Co-57 13.8 +/- 0.2 11.8 8.3 -15.3 Pass MAVE-1050 2/1/2016 Co-60 0.022 +/- 0.040 0.00 NA c Pass MAVE-1050 2/1/2016 Mn-54 0.009 +/- 0.044 0.000 NA c Pass MAVE-1050 2/1/2016 Zn-65 10.67 +/- 0.39 9.60 6.70 - 12.50 Pass MAS0-4780 f 8/1/2016 Ni-63 648 +/- 14 990 693 - 1287 Fail MAS0-4780 9 8/1/2016 Ni-63 902 +/- 46 990 693 - 1287 Pass MAS0-4780 8/1/2016 Sr-90 757 +/- 16 894 626 - 1162 Pass MAS0-4780 8/1/2016 Tc-99 559 +/- 12 556 389 - 723 Pass MAS0-4780 8/1/2016 Cs-134
. 0.93 +/-2.92 0.00 NA c Pass MAS0-4780 8/1/2016 Cs-137
- 1061 +/- 12 1067 747-1387 Pass MAS0-4780 8/1/2016 Co-57 1178 +/- 8 1190 833 - 1547 Pass MAS0-4780 8/1/2016 Co-60 841 +/- 9 851 596 - 1106 Pass MAS0-4780 8/1/2016 Mn-54 0.69 +/- 2.53 0.00 NA c Pass MAS0-4780 8/1/2016 Zn-65 724 +/- 19 695 487 - 904 Pass MAS0-4780 8/1/2016 K-40 566 +/- 52 588 412 - 764 Pass MAS0-4780 8/1/2016 Am-241 0.494 +/- 0.698 0.000 NA c Pass MAS0-4780 8/1/2016 Pu-238 69.7 +/- 7.4 70.4 49.3 - 91.5 Pass MAS0-4780 8/1/2016 Pu-239/240 53.9 +/- 6.3 53.8 37.7 - 69.9 Pass MAS0-4780 h 8/1/2016 U-233/234 46.8 +/- 3.9 122 85 - 159 Fail MAS0-4780 h 8/1/2016 U-238 46.6 +/- 3.9 121 85 - 157 Fail MAW-4776 8/1/2016 1-129 4.40 +/- 0.20 4.54 3.18 - 5.90 Pass MAVE-4782 8/1/2016 Cs-134
-0.01 +/- 0.05 0.00 NA c Pass MAVE-4782 8/1/2016 Cs-137 6.18 +/- 0.20 5.54 3.88 - 7.20 Pass MAVE-4782 8/1/2016 Co-57 8.13 +/-0.16 6.81 4.77 - 8.85 Pass MAVE-4782 8/1/2016 Co-60 5.30 +/- 0.15 4.86 3.40 - 6.32 Pass MAVE-4782 8/1/2016 Mn-54 8.08 +/- 0.24 7.27 5.09 - 9.45 Pass MAVE-4782 8/1/2016 Zn-65 6.24 +/- 0.36 5.40 3.78 - 7.02 Pass A6-2 J
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-4784 8/1/2016 Sr-90 1.18 +/- 0.10 1.03 0.72 - 1.34 Pass MAAP-4784 8/1/2016 Cs-134 1.58 +/- 0.08 2.04 1.43 - 2.65 Pass MAAP-4784 8/1/2016 Cs-137 1.85 +/- 0.09 1.78 1.25 - 2.31 Pass MAAP-4784 8/1/2016 Co-57 2.39 +/- 0.52 2.48 1.74-3.22
- pass MAAP-4784 8/1/2016 Co-60 3.22 +/- 0.08 3.26 2.28 -4.24 Pass MAAP-4784 8/1/2016 Mn-54 2.82 +/-0.12 2.75 1.93 - 3.58 Pass MAAP-4784 8/1/2016 Zn-65
-0.015 +/- 0.062 0.00 NA c Pass MAAP-4784 8/1/2016 Am-241
-0.001 +/- 0.006 0.00 NA c Pass MAAP-4784 8/1/2016 Pu-238 0.075 +/- 0.022 0.069 0.049 - 0.090 Pass MAAP-4784 8/1/2016 Pu-239/240 0.048 +/- 0.015 0.054 0.038 - 0.070 Pass MAAP-4784 8/1/2016 U-234/233 0.151 +/- 0.036 0.150 0.105 - 0.195 Pass MAAP-4784 8/1/2016 U-238 0.147 +/-0.034 0.156 0.109 - 0.203 Pass MAW-4778 8/1/2016 H-3 365 +/- 11 334 234 -434 Pass MAW-4778 8/1/2016 Fe-55 23.6 +/- 16.3 21.5 15.1 +/-28.0 Pass MAW-4778 8/1/2016 Ni-63 17.0 +/- 2.8 17.2 12.0 +/- 22.4 Pass MAW-4778 8/1/2016 Sr-90 0.17 +/-0.28 0.00 NA c Pass MAW-4778 8/1/2016 Tc-99 9.50 +/- 0.41 11.60 8.10 -15.10 Pass MAW-4778 8/1/2016 Cs-134 22.6 +/- 0.4 23.9 16.7 - 31.1 Pass MAW-4778 8/1/2016 Cs-137 0.018 +/- 0.117 0.00 NA c Pass MAW-4778 8/1/2016 Co-57 27.6 +/- 0.2 27.3 19.1 +/- 35.5 Pass MAW-4778 8/1/2016 Co-60 0.018 +/- 0.090 0.00 NA c Pass MAW-4778 8/1/2016 Mn-54 16.2 +/- 0.4 14.8 10.4 - 19.2 Pass MAW-4778 8/1/2016 Zn-65 19.3 +/- 0.7 17.4 12.2 - 22.6 Pass MAW-4778 8/1/2016 K-40 286 +/-6 252 176 - 328 Pass MAW-4778 8/1/2016 Ra-226 1.48 +/- 0.09 1.33 0.93 - 1.73 Pass MAW-4778 8/1/2016 Pu-238 1.09 +/-0.13 1.13 0.79-1.47 Pass MAW-4778 8/1/2016 Pu-239/240 0.003 +/- 0.011 0.016 NA d Pass MAW-4778 8/1/2016 U-234/233 1.80 +/-0.13 1.86 1.30 - 2.42 Pass MAW-4778 8/1/2016 U-238 1.77 +/-0.13 1.92 1.34 -2.50 Pass MAW-4778 8/1/2016 Am-241 0.678 +/- 0.086 0.814 0.570 +/- 1.058 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Sq/total sample (filters, vegetation).
b Laboratory codes as follows: MAW (water}, MAAP (air filter), MASO (soil), MAVE (vegetation).
0 MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
d Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.
0 The laboratory properly identified the Sn-75 interfering peak in the vicinity of Co-57 and stated so in the comment field. MAPEP requires results to be reported as an activity with an uncertainty. Since the calculated uncertainty was less than the activity MAPEP interpreted the submitted result as a "false positive" resulting in a failure.
1 Original analysis for Ni-63 failed.
9 Reanalysis with a smaller aliquot resulted in acceptable results. An investigation is in process to identify better techniques for analyzing samples with complex matrices.
h MAPEP states that samples contain two fractions of Uranium; one that is soluble in concentrated HN03 and HCI acid and one that is "fundamentally insoluble in these acids". They also state that HF treatment can not assure complete dissolution.
Results are consistent with measuring the soluble form.
A6-3
TABLE A-7. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)*.
MRAD Study Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERAP-1101 3/14/2016 Am-241 37.3 45.9 28.3 - 62.1 Pass ERAP-1101 3/14/2016 Co-60 637 623 482 - 778 Pass ERAP-1101 3/14/2016 Cs-134 251 304 193 - 377 Pass ERAP-1101 3/14/2016 Cs-137 1,273 1,150 864-1,510 Pass ERAP-1101 3/14/2016 Fe-55
< 162 126 39.1 - 246 Pass ERAP-1101 3/14/2016 Mn-54
< 2.64
< 50.0 0.00 - 50.0 Pass ERAP-1101 3/14/2016 Pu-238 68.0 70.5 48.3 - 92.7 Pass ERAP-1101 3/14/2016 Pu-239/240 54.1 54.8 39.70 - 71.60 Pass ERAP-1101 3/14/2016 Sr-90 139 150 73.3 - 225.0 Pass ERAP-1101 3/14/2016 U-233/234 59.3 64.8 40.2 - 97.7 Pass ERAP-1101 3/14/2016 U-238 55.5 64.2 41.5-88.8 Pass ERAP-1101 3/14/2016 Zn-65 428 356 255 - 492 Pass ERAP-1101 3/14/2016 Gr. Alpha 98.0 70.1 23.5 -109 Pass ERAP-1101 3/14/2016 Gr. Beta 78.6 54.4 34.4 - 79.3 Pass ERS0-1105 3/14/2016 Am-241 1,030 1,360 796 - 1,770 Pass ERS0-1105 3/14/2016 Ac-228 1,540 1,240 795 - 1,720 Pass ERS0-1105 3/14/2016 Bi-212 1,550 1,240 330 - 1,820 Pass ERS0-1105 3/14/2016 Bi-214 3,100 3,530 2, 130 - 5,080 Pass ERS0-1105 3/14/2016 Co-60 5,600 5,490 3,710 - 7,560 Pass ERS0-1105 3/14/2016 Cs-134 3,030 3,450 2,260 - 4, 140 Pass ERS0-1105 3/14/2016 Cs-137 4,440 4,310 3,300 - 5,550 Pass ERS0-1105 3/14/2016 K-40 10,300 10,600 7,740 - 14,200 Pass ERS0-1105 3/14/2016 Mn-54
< 50.8
< 1000 0.0 - 1,000 Pass ERS0-1105 3/14/2016 Pb-212 1,140 1,240 812 -1,730 Pass ERS0-1105 3/14/2016 Pb-214 3,190 3,710 2, 170 - 5,530 Pass ERS0-1105 3/14/2016 Pu-238 680 658 396 - 908 Pass ERS0-1105 3/14/2016 Pu-239/240 460 496 324 - 0,685 Pass ERS0-1105 3/14/2016 Sr-90 7,740 8,560 3,260 - 13,500 Pass ERS0-1105 3/14/2016 Th-234 3,630 3,430 1,080 - 6,450 Pass ERS0-1105 3/14/2016 U-233/234 3,090 3,460 2, 110 - 4,430 Pass ERS0-1105 3/14/2016 U-238 3,280 3,430 2, 120 - 4,350 Pass ERS0-1105 3/14/2016 Zn-65 2,940 2,450 1,950 - 3,260 Pass ERW-1115 3/14/2016 Gr. Alpha 105.0 117.0 41.5 -181.0 Pass ERW-1115 3/14/2016 Gr. Beta 76.2 75.5 43.2 - 112.0 Pass ERW-1117 3/14/2016 H-3 8,870 8,650 5,800 - 12,300 Pass A7-1
TABLEA-7. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)".
MRAD Study Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERVE-1108 3/14/2016 Am-241 1,930 2,120 1,300 - 2,820 Pass ERVE-1108 3/14/2016 Cm-244.
1,294 1,560 764 - 2,430 Pass ERVE-1108 3/14/2016 Co-60 1, 164 1, 100 759 - 1,540 Pass ERVE-1108 3/14/2016 Cs-134 1,056 1,070 687 - 1,390 Pass ERVE-1108 3/14/2016 Cs-137 930 838 608 - 1, 170 Pass ERVE-1108 3/14/2016 K-40 32,200 31,000 22,400 - 43,500 Pass ERVE-1108 3/14/2016 Mn-54
< 24.5
< 300 0.00 - 300 Pass ERVE-1108 3/14/2016 Zn-65 3,320 2,820 2,030 - 3,960 Pass ERVE-1108 3/14/2016 Pu-238 3,410 2,810 1,680 - 3,850 Pass ERVE-1108 3/14/2016 Pu-239/240 4,120 3,640 2,230 - 5,010 Pass ERVE-1108 3/14/2016 Sr-90 8,120 8,710 4,960 - 11,500 Pass ERVE-1108 3/14/2016 U-233/234 4,350 4,160 2,740 - 5,340 Pass ERVE-1108 3/14/2016 U-238 4,220 4,120 2,750 - 5,230 Pass ERW-1111 3/14/2016 Am-241 113 121 81.5 -162 Pass ERW-1111 3/14/2016 Co-60 1, 120 1,050 912 -1,230 Pass ERW-1111 3/14/2016 Cs-134 806 842 618 - 968 Pass ERW-1111 3/14/2016 Cs-137 1, 190 1, 100 934 - 1,320 Pass ERW-1111 3/14/2016 Mn-54
< 5.89
< 100 0.00 -100 Pass ERW-1111 3/14/2016 Pu-238 159 138 102 -172 Pass ERW-1111 3/14/2016 Pu-239/240 113 98.7 76.6 - 124 Pass ERW-1111 3/14/2016 U-233/234 46.9 52.7 39.6 - 68.0 Pass ERW-1111 3/14/2016 U-238 50.4 52.3 39.9 - 64.2 Pass ERW-1111 3/14/2016 Zn-65 1, 160 1,010 842 - 1,270 Pass ERW-1111 3/14/2016 Fe-55 1,600 1,650 984 - 2,240 Pass ERW-1111 3/14/2016 Sr-90 430 434 283 - 574 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
A7-2
APPENDIX B.
DATA REPORTING CONVENTIONS Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x +/- s where:
x = value of the measurement; s = 2cr 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 4.66cr 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; x1 +/- s1 and Xz +/- s2 Reported result:
x +/- s; where x = (1/2) (x1 + x2) ands= (1/2) J s{ + s; 3.2.
Individual results:
< L1, < L2 Reported result: < L, where L = lower of L1 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 and standard deviation "s" of a set of n numbers x 1, x2... xn are defined as follows:
- -~
s - "\\j--nT 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-1
APPENDIX C Table C-1.
Annual Average effluent concentration limits of radioactivity in air and water above natural Gross alpha Gross beta b
lodine-131 a
a background in unrestricted areas.
Air (pCi/m 3
)
1x10 1
-1 2.8 x 10 Water (pCi/L)
Strontium-89 Strontium-90 Cesium-137 Barium-140 lodine-131 Potassi u m-40 Gross alpha Gross beta Tritium c
8,000 500 1,000 8,000 1,000 4,000 2
10 6
1x10 b
Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
C-1
APPENDIX D Sample Collection and Analysis Program
R D-1 TLD LOCATIONS ONE MILE RADIUS A
J PLANT AREA ENLARGED PLAN El.00 MILE RADIUSJ CNO SCALE]
MONITORING LEGEND!
<.:) PRAIRIE ISLAND TLD POINTS D-2
TLO LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLO LOCATIONS
' I l
~
Ji ( 1 ODD
~
LJ, MO ITORING LEGEND:
0 PRAIRIE ISLAND TLO POINTS D-3
TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
0 PRAIRIE ISLAND TLD POINTS D-4
N n
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS
~!UHGtON L A~
PLANT AREA ENLARGED PLAN U.00 MILE RADIUS]
[NO SCALEJ MONITORING LEGEND MlLK SAMPLING POINT lO NUMBERS P-i$. P-37, P-43 AIR SAMPLING POINT ID NUMBERS P-1.-P-2, P* 3. ? **4, P* S. P-7
\\IATER SAMPLING POINT lO NUMBERS P-5, f'-S. P-8, P-9. P*ll. P-24, IH3 VEGETAT!ON I VEGETABLES IO NUMBERS P-28_ P-38. P-45 D-5 FISH SAMPUNG POINT lO NUMBERS
- >-13, P-lq INVERTEBRATES POINT JO NUMBERS P-6. P -40 SEOIMEN! SAMPLING POINT IO NUMBERS P-8, P-l2, P-20
/
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND MILK SAMPLING POINT lO NUMBERS P-18, P-37, P-42, P-43 AIR SAMPLlNG POINT JO NUMBt:RS P-1, P-2. P-3. P-4. P-*6, P-7 w;,rrn SA:HPLING PO INT 1.0 NUMBERS P-5, P-6. P-8, P-'l, P-11, P-24, P-43 VEGETATION I VEGETABLES 10 NUMBERS P-28, P-38, P-45 D-6
~~;
~ j ne o. l't'it FI SH SAMPLING PO[Ni I D NUMBERS P-13,. P-19 lNV£RTE8RATES POINT ID NUMBERS P-6, P-40 SEDIMENT SAMPLING PO!Nr 10 NUMBERS P-6, P-12, P-20
ENVIRONMENTAL SAMPLING POINTS r-----
1 I
I I
~
- p. *38rti ' I i ~ Ti
~ I
"'--.::f=
I l I !
I I
l 0 <$> P-43, Peterson Farm, W10322 St Rd 29, Rivet Falls, WI i
El P-38, Caln Residence, N7395 950th St, River Falls, WI l
- ----*----*-*--***---*-*--*-----*-*---*-.----***--.... --*--*----*-----1.
CONTROL POINTS PRESCOTT, WISCONSIN D-7 0
0 0
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-6, P-7 WATER SAMPLING POINT IP NUMBERS P-6, P-6, P-8, P-9, P-11, P-43 VEGETATION I VEGETABLES ID NUMBERS P-28, P-38, P-46
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, 2016. 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 2016 are, summarized and discussed.
Program findings for 2016 detected low levels of tritium in nearby residence wells, ground water, surface
- samples, and storage tanks at or near the expected natural.background levels with the exception of ground water sample wells MW-7 and MW-8, D5/6 tank vaults, S-7 and S-9 surface water, and the septic system. The 2016 sample results (except for MW-7, MW-8, D5/6 tank vaults, S-7 and S-9 surface water, and the septic system) ranged from <19 pCi/L to 234 pCi/L. Sample well MW-7 ranged from 22 pCi/L to 741 pCi/L. Sample well MW-8 ranged from 356 pCi/L to 552 pCi/L. D5/6 tank vaults were 871 and 705 pCi/L. S-7 surface water ranged from 95 pCi/L to 1445 pCi/L. S-9 surface water was 605 pCi/L. The septic system sample ranged from 48 pCi/L *to 943 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 Special Tritium Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from the PINGP.
For this purpose, special water samples are collected and analyzed for tritium content.
3.2 Program Description The sampling and analysis schedule for the special water sampling program is summarized in Table E-4.1 and briefly reviewed below. Table E-4.2 defines the additional sample locations and codes for the special water sampling program.
Special well, tank, and surface water samples were collected quarterly (spring, summer, fall) at seven locations, quarterly at one location, monthly at six locatiqns, semi-annually at five locations, and annually at thirty-six locations. The Peterson (P-43) and Hanson (SW-1) farm wells are used as control locations for these special samples.
To detect low levels of tritium at or below natural background levels, analyses of the samples have been contracted to a laboratory (University of Waterloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. Waterloo Laboratories report tritium analyses,results in Tritium Units (1 TU = 3.2 pCi/L). The tritium results in this report are indicated in pCi/L.
3.3 Program Execution The special water sampling was executed as described in the preceding section.
3.4 Program Modifications Changes to the program in 2016 include:
samples were taken from monitoring wells P-10, and MW-8 and snow from S-6, S-7, S-8, S-9, and P-43 arid were sent to Environmental Incorporated for analysis for hard-to-detect nuclides in accordance with American Nuclear Insurers recommendation
- . sample location SW-8 was added for the SGR Building (this well was previously listed as the Restroom Trailer well) sample location SW-9 was added for the FLEX Building samples were taken from the D5/6 Fuel Oil Storage Tank vaults because the area was accessible in 2016 at the request of the homeowner, no samples were taken at P-28 E-3
3.5 Results and Discussion Results show tritium in well water and ground water samples at or near expected natural background levels except the MW-7 and MW-8 ground water sample wells. TableE-4.4 provides the complete data
. table of results for each period and sampling location.
The tritium level annual averages have shown a downward trend since the special sampling began in 1989.
Except for sample wells MW-7 and MW-8, D5/6 tank vaults, S-7 and S-9 surface water, and the septic system, the 2016 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 ahd 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 MW-7 and MW-8 in 2016 may be due to prior leakage from the PINGP liquid radwaste discharge pipe, discharge of turbine building sump water into the landlocked area, or discharge of heating steam condensate from the main warehouse in 1978/1979. The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been terminated, the last discharge took place on 11/14/09. The main warehouse heating system was repaired in 1979. The heating steam system has not been used in the outer plant buildings since the 2011 - 2012 heating season.
The elevated tritium levels in D5/6 tank vaults and S-7 and S-9 surface water are most likely due to tritium recaptured from effluent releases by precipitation. The levels found in the septic system have returned to background levels.
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, 2016.
Medium No.
Location codes Collection type Analysis and type a and frequency b type c P-'8 post-treat, P-8 pre-treat, REMP P-6, REMP P-11, PllC-22, PllC-26, PllC-28, PllC-29, P-7, Well water 26 P-11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, GIA H-3 Annual MW-6, P-26, P-30, SW-3, SW-4, SW-5, SW-6, SW-7, SW-8, SW-9, P-9 Well water 1
P-240 GIQ H-3 quarterly Well water 7
P-2, P-3, P-5, P-6, GIQ' H-3 quarterly' PZ-8, MW-4, MW-5 Well water monthly 5
P-43(C), SW-1 (C),
GIM H-3 MW-7, MW-8, P-10 Surface water S-1, S-2, S-3, S-4, S-5, 8
S-6, S-7, P-31 GI Ad H-3 Storage Tank 7
11 CST, 21 CST, 22 CST, GIS H-3 U112 Oemin Hdr, 0516 vaults Storage Tank 1
Septic System GIM 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: GI = 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, 2016.
Code Collection site Type of Distance and sample a direction from reactor I
i 1.0 mi. @321°/WNW P-8 Pl Community well post treat ow P-8 Pl Community well pre treat ow 1.0 mi. (ci) 321°/WNW REMP P-6 Lock & Dam #3 well ow 1.6 mi. Ca1 129°/SE REMP P-11 Red WinQ Service Center ow 3.3 mi@ 158°/SSE PllC-22 1773 Buffalo SlouQh Rd ow 1mi.@315°/NW PllC-26 1771 Buffalo SlouQh Rd ow 1 mi. Ca1315°/NW PllC-28 1960 Larson Lane ow 1.5 mi @ 288°/WNW PllC-29 Buffalo Project ow 4.3 mi @ 302°/WNW P-240 Suter residence ow 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control) ow 13.9 mi. (ci) 355°/N SW-1 Hanson Farm (Control) ow 2.2 mi. Ca1315°/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-10 Sample well WW See map P-11 Sample well WW
. See map PZ-1 Sample well WW See map PZ-2 Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW-4 Sample well WW See map MW-5 Sample well WW See map MW-6 Sample well WW See map MW-7 Sample well WW See map MW-8 Sample well WW See map P-26 PITCwell ow 0.4 mi. (ci) 258°/WSW P-30 Environ lab well ow 0.2 mi. @ 32°/NNE E-6
Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2016 (continued).
Code Collection site Type of Distance and sample a direction from reactor SW-3 Cooling Tower pump WW See map SW-4 New Admin Bldg DW 0.05 mi. @315°/NW SW-5 Plant Screenhouse well WW 0.05 mi. (fJJ 0°/N SW-6 Site Admin Buildinq well DW 0.2 mi@, 310°/NW SW-7 Distribution Center DW 0.35 mi @ 271 *rw SW-8 SGR Building WW 0.2 mi @ 310°/NW SW-9 FLEX Buildinq WW 0.2 mi (fJJ 238°!WSW P-9 Plant well #2 DW 0.3 mi. @, 306°/NW S-1 Upstream Miss. River SW See map S-2 Recirc/lntake canal SW See map S-3 Cooling water canal SW See map S-4 Discharqe 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°/N S-7 Parkinq Lot Stormwater (also snow)
SW 0.3 mi (fJJ 306°/NW S-8 P-10 area snow SW See map S-9 MW-7/8 area snow SW See map P-31 Birch Lake Seepage SW 0.69 mi.@ 172°/S 11 CST Storaqe Tank ST Turbine Buildinq 21 CST Storaqe Tank ST Turbine Buildinq 22CST Storaqe Tank ST Turbine Buildinq Unit 1/2 demin hdr Storaqe Tank ST Turbine Buildinq Septic System Storage Tank ST Outside #1 Warehouse D5/6 Vault Concrete Vault ST Outside Turbine Bldq a Sample codes: DW =Drinking Water: 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, 2016 (County, State)
Indicator Location with Highest Control Locations Annual Mean Locations Sample Type and" Mean (F) 0 Location d Mean (F) 0 Mean (F) 0 Number Type Number of LLD b Range 0
Range 0
Range 0
Non-(Units)
Analyses a Routine Results e Offsite Well H-3 14 19 29 (7/14)
PllC-29 35 (1/1)
(See Control 0
Water (22-40)
(35)
Below)
(pCi/L)
Onsite H-3 78 19 170 (62/78)
MW-8 465 (12/12)
(See Control 13 Well Water (20-741)
(356-552)
Below)
(pCi/L)
Onsite H-3 17 19 218 (13/17)
S-7 451 (4/4)
(See Control Surface Water (20-1445)
(95-1445)
Below) 2 (pCi/L)
On site H-3 24 19 188 (22/24)
D-5 Fuel Oil 871 (1/1)
(See Control Storage Tank Storage Tank (pCi/L)
(22-943)
Vault (871)
Below) 3 Control (offsite H-3 24 19 none P-43 36 (10/12) 36 (10/24) well water)
(23-54)
(23-54) 0 Control (offsite H-3 1
19 none P-43 42 (1/1) 42 (1/1) snow)
(42)
(42) 0 a H-3 = tritium b LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.
0 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.
- Non-routine results are those which exceed ten times the control station mean value.
E-8
~---------
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2016.
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 CODE SAMPLE LOCATIONS oCi/L pCi/L oCi/L pCi/L oCi/L oCi/L oCi/L pCi/L oCi/L oCi/L oCi/L oCi/L OFFSITE WELLS P-8 Post-treat Pl Comm. Well
<19 P-8 Pre-treat Pl Comm. Well
<19 REMP P-6 Lock & Dam #3 well
<19 Red Wing Service
<19 REMP P-11 Center 1773 Buffalo Slouah Rd 27 PllC-22 1771 Buffalo SlouQh Rd 27 PllC-26 PllC-28 1960 Larson Lane
<19 PIIC-29 Buffalo Proiect 35 P-24D Suter residence
'<19 24
<19 22 31 40 39/42*
28 43 54 33 31 28 38 40 23
<19
<19 P-43 Peterson Farm(Control *snow SW-1 Hanson Farm (Control)
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19
<19 E-9
Table E-4.4 RadioloQical Environmental Monitorina Proaram, Complete Data Table, 2016 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 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 WELLS P-2 Sample well 96 45 69 P-3 Sample well 28
<19 30 P-5 Sample well 126 62 52 P-6 Sample well 48
<19 21 P-7 Sample well 51 P-10 Sample well 126 133 100 85 83 102 110 110 150 219 169 143 P-11 Sample well 95 PZ-1 Sample well
<19 PZ-2 Sample well
<19 PZ-4 Sample well
<19 PZ-5 Sample well 31 PZ-7 Sample well 29
<19 PZ-8 Sample well 72 44 37 MW-4 Sample well 20 20 45 MW-5 Sample well 20
<19 234 MW-6 Sample well 20
<19 MW-7 Sample well 741 408 212 102 28 52 22 116 69 76 98 90 MW-8 Sample well 552 504 408 356 453 474 491 481 485 474 440 464 P-26 PITC well
<19 P-30 Env. lab well
<19 SW-3 CT pump 35 P-9 Plant well# 2 39
<19 SW-4 NewAdmin
<19 SW-5 Pint Scrnhs
<19 SW-6 Site Admin Blda
<19 SW-7 Dist Center
<19 E-10
Table E-4.4 Radioloqical Environmental Monitorinq Proqram, Complete Data Table, 2016 (continued).
SAMPLE DATES JAN FEB MAR
- APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L oCi/L oCi/L pCi/L pCi/L pCi/L ONSITE WELLS SW-8 RSG Bldq
<19 SW-9 FLEX Bldg 28 E-11
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2016 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 2016 2016.
2016 2016 2016 2016 2016 2016 2016 2016 2016 CODE SAMPLE LOCATIONS*
oCi/L oCi/L oCi/L oCi/L oCi/L oCi/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 26 S-4 Discharge Canal (end) 20 S-5 Discharge Canal (midway)
<19 S-6 Stormwater runoff 85*
67 67
<19 S-7 Parking Lot runoff 163*
99 1445 95 S-8 P-10 area snow 72*
S-9 MW-7/8 area snow 605*
P-31 Birch Lake Seepage 36 48
- snow samples E-12
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2016 (continued).
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 2016 CODE SAMPLE LOCATIONS oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L ONSITE STORAGE TANKS 11 CST Storage tank
<19 45 21 CST Storage tank 29 54 22 CST Storage tank 22 45 U1/U2 Demin*
Storage tank
<19/144 28/62 Header Septic Storage tank 62 131 48 110 142 86 68 118 88 943 248 93 System D5/6 D5/6 Fuel Oil Storage Tank 871/705 Vaults E-13
Table E4.5. Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on five samples.
Location P-10 Snow Peterson Snow MW-7/8 Snow OAS Snow Parking Lot Snow Collection Date 01-14-16 01-12-16 01-13-16 01-13-16 01-14-16 Lab Code PXW~356 PXW-357 PXW-358 PXW-359 PXW-360 Isotope Concentration (µCi/ml)
< 6.5 E-07
< 6.5 E-07
< 6.3 E-07
< 6.3 E-07
< 6.6 E-07 Ni-63
< 1.3 E-07
< 1.6 E-07
< 1.1 E-07
< 1.2 E-07
< 1.0 E-07 Sr-90
< 5.0 E-10
< 4.6 E-10
<5.1E-10
< 5.2 E-10
< 4.3 E-10 Pu-238
< 6.4 E-11
< 1.4 E-10
<1.9E-10
< 1.3 E-10
<1.5E-10 Pu-239/240
< 1.1 E-10
< 5.8 E-11
<1.8E-10
< 2.6 E-10
<1.7E-10
- Am-241
< 1.7 E-10
<9.1E-11
<1.3E-10
< 3.9 E-11
< 9.8 E-11 Cm-242
< 1.9 E-10
< 1.8 E-10
< 1.0 E-10
<6.7E-11
<1.8E-10 Cm-243/244
< 5.5 E-11
<3.7E-11
<1.6E-10
< 1.2 E-10
< 2.2 E-10 Less than (<),value is based on a 4.66 sigma counting error for the background sample.
E-14
Table E4.5. Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on four samples.
Location OAS Roof Parking Lot P-10 MW-8 Collection Date 04-28-16 04-28-16 06-09-16 06-09-16 Lab Code PXW-2254 PXW-2255 PXW-3258 PXW-3259 Isotope Concentration (µCi/ml)
< 7.7 E-07
< 8.1 E-07
< 3.6 E-07
< 3.7 E-07 Ni-63
< 1.5 E-07
< 1.4 E-07
< 1.4 E-07
< 1.3 E-07 Sr-90
< 5.2 E-10
<4.7E-10
< 6.0 E-10
< 7.7 E-10 Pu-238
<1.1E-10
<6.6E-11
< 1.3 E-10
< 1.0 E-10 Pu-239/240
< 1.4 E-10
<1.6E-10
< 1.3 E-10
< 6.0 E-11 Am-241
< 1.1 E-10
< 5.2 E-11
< 6.0 E-11
< 1.2 E-10 Cm-242
< 8.0 E-11
< 1.3 E-10
< 6.0 E-11
<1.7E-10 Cm-243/244
< 8.0 E-11
< 1.3 E-10
< 1.0 E-10
< 2.4 E-10 Less than(<), value is based on a 4.66 sigma counting error for the background sample.
E-15
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