ML18134A012
| ML18134A012 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/14/2018 |
| From: | Sharp S Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| L-Pl-18-022 | |
| Download: ML18134A012 (82) | |
Text
{{#Wiki_filter:1717 Wakonade Drive Welch, MN 55089 Xcel Energy RESPONSIBLE BY NATURE 800.895.4999 xcelenergy.com L-Pl-18-022 MAY *1 ~ 2018 TS 5.6.2 ISFSI TS 5.2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Prairie Island Independent Spent Units 1 and 2 Fuel Storage Installation Docket Nos. 50-282 and 50-306 Docket 72-10 Renewed Facility Operating License Materials License No. SNM-2506 Nos. DPR-42 and DPR-60 2017 Annual Radiological Environmental Monitoring Program Report Pursuant to Prairie Island Nuclear Generating Plant Technical Specification (TS) 5.6.2, Appendix A, to Renewed Operating Licenses DPR-42 and DPR-60, and Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 5.2, Appendix A, to Materials License SNM-2506, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submits one copy of the annual Radiological Environmental Monitoring Program report for the period January 1, 2017, through December 31, 2017, as Enclosure 1. Summary of Commitments This letter makes no new commitments and no revisions to existing commitments. Scott Sharp Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Billy Dickson, USNRC, Region 111 Director of NMSS, USNRC Department of Health, State of Minnesota Pl Dakota Community Environmental Coordinator
ENCLOSURE 1 Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program January 1 to December 31, 2017. 80 Pages Follow
ATI Environmental, Inc .
./""\I Midwest Laboratory 700 Landwehr Road , Northbrook, IL 60062-2310 phone (847) 564-0700 , fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2017 Docket No. 50-282 Renewed Operating License No. DPR-42 Docket No. 50-306 Renewed Operating License No. DPR-60 ISFSI Docket No. 72-10 Renewed License No. SNM-2506 Prepared under Contract by ATI ENVIRONMENTAL, Inc.
MIDWEST LABORATORY Project No. 8010 Approved: Forrest G. Shaw Ill Quality Assurance Manager
PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by Northern States Power Co. -Minnesota, for XCEL Energy Corporation. The report was prepared by Environmental, Inc., Midwest Laboratory. ii
TABLE OF CONTENTS Preface .................................................................................................................................................... ii List of Tables .......................................................................................................................................... iv List of Figures .......................................................................................................................................... v
1.0 INTRODUCTION
..... :............................................................................................................................... 1 2.0
SUMMARY
.............................................................................................................................................. 2 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ............................................ 3 3.2 Program Design and Data Interpretation ....................................................................................... 3 3.3 Program Description ...................................................................................................................... 4 3.4 Program Execution ................................ ;....................................................................................... 5 3.5 Laboratory Procedures .................................................................................................................. 5 3.6 Program Modifications ................................................................................................................... 6
- 3. 7 Land Use Census .......................................................................................................................... 6 4.1 RESULTS AND DISCUSSION ................................................................................................................ 7 4.2 Atmospheric Nuclear Detonations and Nuclear Accidents ............................................................ 7 4.3 Summary of Preoperational Data .................................................................................................. 7 4.4 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 OFTABLES 5.1 Sample Collection and Analysis Program ................................................................................................. 15 5.2 Sampling Locations ................................................................................................................................... 16 5.3 Missed Collections and Analyses ............................................................................................................... 19 5.4 Radiological Environmental Monitoring Program Summary ...................................................................... 20 In addition, the following tables can be found in the Appendices: Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results .................................................... A 1-1 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) ........... A?-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-17 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, 2017. 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, 2017b) available at Prairie Island Nuclear Generating Plant. Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co.-Minnesota. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974. 1
2.0
SUMMARY
The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Offsite Dose Calculation Manual for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described. Results for 2017 are summarized and discussed. Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant. 2
3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.2 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs). Sources of environmental radiation include the following: (1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents. In interpreting the data, effects due to the plant must be distinguished from those due to other sources. A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources. An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium- 7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4: 1:0.03 (Eisenbud, 1963). Beryllium-? 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 envir<;mment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and - 60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations. 3
3.1 Program Design and Data Interpretation (continued) Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations. 3.2 Program Description The sampling and analysis schedule for the radiological environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2017). 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 CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly. Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly. To monitor the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from five 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. 4
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) Airborne Particulates/ Airborne Iodine Partial sample collected from location P-2 for the week ending on 4/25/17. The air sampler failed in the field. (2) TLD The TLD at location P-1 OA, NNW Sector, Inner Ring, for the fourth quarter was missing. This deviation from the program is summarized in Table 5.3. 3.4 Laboratory Procedures The iodine-131 analyses in 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 were 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 were 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. 5
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, 2017). 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 2 animal, the nearest residence, and the nearest garden. of greater than 500 ft producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and 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 7/15/17 through 8/15/17. There were no changes to the highest D/Q locations for the gardens or nearest resident. No milk animals were identified within five miles of the plant. The last dairy within the five mile radius suspended operations in 2016. 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. 6
4.1 RES ULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3. The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown. 4.2 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2017. The Fukushima Daiichi nuclear accident occurred March 11, 2011. There were no reported atmospheric nuclear tests in 2017. The last reported test was conducted on October 16, 1980 by the People's Republic of China. 4.3 Summary of Preoperational Data The following constitutes a summary of preciperational 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/ m 3 to 1,020 pCi/m 3 , and these declining values are reflected throughout the various media tested. In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during pre-operational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m 3 . Average present day levels have stabilized at around 0.025 pCi/m 3
- Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g. The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish, aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium measure below a detection limit of approximately 160 pCi/L. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well water, and 11.0 pCi/L for lake water. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g , 46.0 pCi/g, and 13.6 pCi/g, respectively. 7
4.4 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant. Ambient Radiation (TLDs) Ambient radiation was measured in the general area of the site boundary,* at the outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at one control location. The means ranged from 15.8 mR/91 days at inner ring locations to 16.3 mR/91 days at outer ring locations. The mean at special interest locations was 15.5 mR/91 days and 16.3 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were comparable to 2016 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 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 2008 16.9 17.1 2017 16.1 16.3 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 155.7 mR/91 days inside the ISFSI earth berm and 23.4 mR/91 days outside the ISFSI earth berm. No additional casks were placed on the ISFSI pad in 2017, 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(Locations P-07S and P-08S) measured 15.5 and 16.6 mR/91 days. Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1). 8
Airborne Particulates Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1999 through 2006, and also in 2008 through 2015. The elevated activity obseNed in 2007 was attributed to construction activity in the area, an increase in dust and consequent heavier particulate filter loading. 3 Average annual gross beta concentrations in airborne particulates were 0.026 pCi/m for the indicator locations and 0.025 for the control location and similar to levels obseNed from 1999 through 2006 and 2008 to 2016. The results are tabulated below. Average of Year Indicators Control 3 Concentration foCi/ m ) 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 2017 0.026 0.025 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-?, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, 3 3 with an average activity of 0.078 pCi/m for indicator locations and 0.076 pCi/m 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. 9
Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below a detection .limit of 183 pCi/L for all samples. Gross beta concentrations averaged 10.1 pCi/L throughout the year, ranging from 4.0-14. 7 pCi/L. These concentrations are consistent with levels observed from 1999 through 2016. 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 2017 data of any effect of plant operation.
Gross Beta Year (pCi/L) 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 2017 10.1 Average annual concentrations; Gross beta in drinking water. River Water All river water samples measured below a detection limit of 183 pCi/L for tritium. Gamma-emitting isotopes were below detection limits in all samples. In summary, the data for 2017 show no radiological effects from the plant operation. 10
Well Water Water samples tested from the control well, P-43 (Peterson Farm) and from four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) showed no tritium detected above a detection limit of 158 pCi/L. Gamma-emitting isotopes were below detection limits in all samples. In summary, well water data for 2017 show no radiological effects of the plant operation. Five samples of broadleaf vegetation, cabbage leaves, were collected in August 2017 and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.017 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, September and October, 2017 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 September, 2017 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes measured below detection limits except in all four samples tested with the exception that naturally occurring potassium-40 was detected in September 2017 samples. 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 June and September, 2017 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotope detected was naturally-occurring potassium-40. There was no indication of a plant effect. 11
5.0 FIGURES AND TABLES 12
Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.
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Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
- Indicators (P-2,3,4,6,7)
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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) Frequenc/ Frequency° Ambient radiation (TLD's) 54 P-01A- P-10A C/Q Ambient gamma P-01B - P-15B P-01S - P-0SS P-01IA- P-0SIA P-01IB - P-0SIB P-01IX- P-04IX, 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 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) GS (MC), H-3 (QC) 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.
- 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. 15
Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant. Distance and Direction Code Type* 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,Al,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 DW 3.3 mi @ 158°/SSE P-12 Downstream of Plant ss 3.0 mi@ 116°/ESE P-13 Downstream of Fe 3.5 mi@ 113°/ESE 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-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 WW 13.9 mi. @355°/N P-45 Glazier Residence VE 0.6 mi.@341°/NNW General Area of the Site Boundary 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). Distance and Direction 8 Code Type Collection Site Sample Typeb from Reactor Approximately 4 to 5 miles Distant from the Plant P-018 Thomas Killian Residence TLD 4.7 mi@355°/N P-028 Roy Kinneman Residence TLD 4.8 mi@ 17°/NNE P-038 Wayne Anderson Farm TLD 4.9 mi@ 46°/NE P-048 Nelson Drive (Road) TLD 4.2 mi @61°/ENE P-058 County Road E and Coulee TLD 4.2 mi@ 102°/ESE P-068 William Hauschildt Residence TLD 4.4 mi@ 112°/ESE P-078 Red Wing Public Works TLD 4.7 mi@140°/SE P-088 David Wnuk Residence TLD 4.1 mi@165°/SSE P-098 Highway 19 South TLD 4.2 mi@ 187°/S P-108 Cannondale Farm TLD 4.9 mi@ 200°/SSW P-118 Wallace Weberg Farm TLD 4.5 mi @221°/SW P-128 Ray Gergen Farm TLD 4.6 mi@251°/WSW P-138 Thomas O'Rourke Farm TLD 4.4 mi@ 270°/W P-148 David J. Anderson Farm TLD 4.9 mi @306°/NW P-158 Holst Farms TLD 3.8 mi@ 345°/NNW Special Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 mi@ 129°/SE P-02S Charles Suter Residence TLD 0.5 mi@155°/SSE P-03S Carl Gustafson Farm TLD 2.2 mi@173°/S P-04S Richard Burt Residence TLD 2.0 mi@ 202°/SSW P-05S Kinney Store TLD 2.0 mi@ 270°/W P-06S Earl Flynn Farm TLD 2.5 mi @299°/WNW P-07S Indian Community TLD 0.7mi@271°/W P-08S Indian Community TLD 0.7 mi@287°/WNW P-01C C Robert Kinneman Farm TLD 11.1 mi@ 331°/NNW 17
Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant (continued). Distance and Direction Code Type* Collection Site Sample Typeb from ISFSI Center. ISFSI Area Inside Earth Berm P-01IA ISFSI Nuisance Fence TLD 190'@45°/NE P-02IA ISFSI Nuisance Fence TLD 360'@82°/E P-03IA ISFSI Nuisance Fence TLD 370'@ 100°/E P-04IA ISFSI Nuisance Fence TLD 200'@ 134°/SE P-05IA ISFSI Nuisance Fence TLD 180'@ 219°/SW P-06IA ISFSI Nuisance Fence TLD 320'@ 258°/WSW P-07IA ISFSI Nuisance Fence TLD 320'@ 281°/WNW P-08IA ISFSI Nuisance Fence TLD 190'@ 318°/NW P-01IX ISFSI Nuisance Fence TLD 140'@ 180°/S P-02IX ISFSI Nuisance Fence TLD 310'@ 270°/W P-03IX ISFSI Nuisance Fence TLD 140'@0°/N P-04IX ISFSI Nuisance Fence TLD 360'@90°/E ISFSI Area Outside Earth Berm P-01IB ISFSI Berm Area TLD 340'@3°/N P-02IB ISFSI Berm Area TLD 380'@ 28°/NNE P-03IB ISFSI Berm Area TLD 560'@85°/E P-04IB ISFSI Berm Area TLD 590'@ 165°/SSE P-05IB ISFSI Berm Area TLD 690'@ 186°/S P-06IB ISFSI Berm Area TLD 720'@ 201°/SSW P-07IB ISFSI Berm Area TLD 610'@ 271°/W P-08IB 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 ss Shoreline Sediments BS Bottom (river) sediments SW Surface Water BO Bottom organisms VE Vegetation/vegetables (periphyton or macroinvertebrates) WW Well water DW Drinkingwater c Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location. 18
Table 5.3. Missed collections and analyses at the Prairie sland 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 Bela, 1-131 P-2 4/25/17 Air sampler failed. Replaced air sampler. TLD Gamma P-10A 4th Quarter 2017 TLD was missing Replaced TLD 19
Table 5.4 Radiological Environmental Monitoring Program Summary Name ofFacility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location ofFacility Goodhue, Minnesota Reporting Period January-December, 2017 ( County, State ) Indicator Location.with Highest Control Number Sample Type and Locations Annual Mean Locations Non-0 0 0 Type Number of LLDb Mean (F) Mean (F) Mean (F) Routine 0 0 0 (Units) Analyses" Range Locationd Range Range Results* Direct Radiation TLD (Inner Ring, Gamma 39 3.0 15.8 (39/39) P-06A 18.4 (4/4) (See Control 0 Area at Site ( 12.9-19.7) 0.4 mi @ 249° /WSW (16.8-19.7) below.) Boundary) mR/91 days) TLD (Outer Ring, Gamma 60 3.0 16.3 (60/60) P-03B, Anderson Fann 18.3 (4/4) (See Control 0 4-5 mi. distant) ( 13. 7-20.5) 4.9 mi @ 46°/NE (16.8-20.3) below.) mR/91 days) TLD (Special Gamma 32 3.0 15.5 (32/32) P-03S, Gustafson Farm, 17.7 (4/4) (See Control 0 Interest Areas) ( 12.3-19.8) 2.2 mi@ 173° JS (16.4-19.8) below.) mR/91 days) TLD (Control) P-01 C, Robert Kinneman 16.3 (4/4) 16.3 (4/4) 0 Gamma 4 3.0 None mR/91 days) 11.1 mi@331° /NNW (15.3-17.2) (15.3-17.2) Airborne Pathway Airborne GB 318 0.005 0.026 (265/265) P-02, Air Station 0.027 (53 /53) 0.025 (53/53) 0 Particulates (0.011-0.054) 0.5 mi@ 294° /WNW (0.011-0.054) (0.012-0.050) 3 (pCi/m ) GS 20 Be-7 0.015 0,078 (20/20) P-07, Air Station 0.082 (4/4) 0.076 (4/4) 0 (0.050-0.11) 0.5 mi @271° /W (0.058-0.11) (0.051-0.095) Mn-54 0.0007 < LLD - - < LLD 0 Co-58 0.0007 < LLD - - < LLD 0 Co-60 0.0006 < LLD - - < LLD 0 Zn-65 0.0015 < LLD - - < LLD 0 Zr-Nb-95 0.0010 < LLD - - < LLD 0 Ru-103 0.0010 < LLD - - < LLD 0 Ru-106 0.0055 < LLD - - < LLD 0 Cs-134 0.0007 < LLD - - < LLD 0 Cs-137 0.0007 < LLD - - < LLD 0 Ba-La-140 0.0027 < LLD - - < LLD 0 Ce-141 0.0015 < LLD - - < LLD 0 Ce-144 0.0037 < LLD - - < LLD 0 Airborne Iodine (pCi/m 3) 1-131 312 0.030 <LLD - - < LLD 0 20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2017 ( County, State) Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of Mean (F)° 0 LLDb Mean (F) Mean (F)° Routine (Units) Analyses" 0 Range Locationd Range 0 Range* Results* Terrestrial Pathway Crops - Cabbage (pCi/gwet) 1-131 5 0.017 < LLD - - < LLD 0 Well Water H-3 20 158 < LLD - - < LLD 0 (pCi/L) GS 20 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 49 < LLD - - < LLD 0 21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear ,Power station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2017 ( County, state ) Indicator Location with Highest Control Number Sample Type and Locations Numberof Annual Mean Locations Non-Type Mean(F) 0 Analyses' LLDb Mean (F}° Mean (F)c Routine (Units) Range0 Range 0 Locationd Range* Results* Waterborne Pathway Drinking Water GB 12 1.0 10.1 (12/12) P-11, Red Wing S.C. 10.1 (12/12) None 0 (pCi/L) (4.0-14.7) 3.3 mi@ 158° /SSE (4.0-14.7) 1-131 12 1.0 < LLD - - None 0 H-3 4 183 < LLD - - None 0 GS 12 - - Mn-54 10 < LLD - - None 0 Fe-59 30 < LLD - - None 0 Co-58 10 < LLD - - None 0 Co-60 10 < LLD - - None 0 Zn-65 30 < LLD - - None 0 Zr-Nb-95 15 < LLD - - None 0 Cs-134 10 < LLD - - None 0 Cs-137 10 < LLD - - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 38 < LLD - - None 0 River Water H-3 8 183 < LLD - - < LLD 0 (pCi/L) GS 24 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 39 < LLD - - < LLD 0 Fish GS 12 (pCi/gwet) K-40 0.10 2.72 (6/6) P-19, Upstream 2.87 (6/6) 2.87 (6/6) 0 (2.37-3.12) 1.3 mi@ O'/N (2.48-3.14) (2.48-3.14) Mn-54 0.018 < LLD - - < LLD 0 Fe-59 0.046 < LLD - - < LLD 0 Co-58 0.020 < LLD - - < LLD 0 Co-60 0.020 < LLD - - < LLD 0 Zn-65 0.038 < LLD - - < LLD 0 Zr-Nb-95 0.030 < LLD - - < LLD 0 Cs-134 0.019 < LLD - - < LLD 0 Cs-137 0.020 < LLD - - < LLD 0 Ba-La-140 0.14 < LLD - - < LLD 0 22
Table 5.4 Radiological Environmental Monitoring Program Summary Name ofFacility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location ofFacility Goodhue, Minnesota Reporting Period January-December, 2017 ( County, State) Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-0 Type Numberof LLDb Mean (F) Mean(F)° Mean (F)° Routine 0 (Units) Analyses" Range 0 Locationd Range 0 Range Results* Waterborne Pathway Invertebrates GS 4 (pCi/gwet) Be-7 0.57 < LLD - - < LLD 0 K-40 0.37 2.69 (1/2) P-40 Upstream 4.50 (1/2) 4.50 (1/2) 0 0.4 mi. @0° IN Mn-54 0.045 < LLD - - < LLD 0 Co-58 0.053 <LLD - - < LLD 0 Co-60 0.041 < LLD - - < LLD 0 Zn-65 0.089 < LLD - - < LLD 0 Zr-Nb-95 0.086 < LLD - - <LLD 0 Ru-103 0.075 < LLD - - <LLD 0 Ru-106 0.33 < LLD - - < LLD 0 Cs-134 0,037 <LLD - - < LLD 0 Cs-137 0.039 < LLD - - < LLD 0 Ba-La-140 0,889 < LLD - - < LLD 0 Ce-141 0.138 < LLD - - < LLD 0 Ce-144 0.233 < LLD - - < LLD 0 Bottom and GS 6 Shoreline Be-7 0.12 - - 0 Sediments (pCi/g dry) K-40 7.88 (4/4) P-20 Upstream 9.77 (2/2) 9.77 (2/2) 0 (6.88-9.03) 0.9 mi. @ 45° /NE (9.43-10.1) (9.43-10.1) Mn-54 0.018 < LLD - - < LLD 0 Co-58 0.017 < LLD - - < LLD 0 Co-60 0.028 < LLD - - <LLD 0 Zn-65 0.038 < LLD - - <LLD 0 Zr-Nb-95 0.023 < LLD - - <LLD 0 Ru-103 0.016 < LLD - - < LLD 0 Ru-106 0.112 <LLD - - < LLD 0 Cs-134 0.014 < LLD - - < LLD 0 Cs-137 0.010 < LLD - - < LLD 0 Ba-La-140 0.13 < LLD - - < LLD 0 Ce-141 0,055 <LLD - - < LLD 0 Ce-144 0.084 < LLD - - < LLD 0
- GB= gross beta, GS= gamma scan.
b LLD= nominal lower limit of detection based on a 4.66 sigma counting error for background sample. 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: (1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
- Non-routine results are those which exceed ten limes the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten limes the typical preoperalional value for the medium or location.
23
6.0 REFERENCES
CITED Arnold, J. R. and H. A. AI-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453. Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276. Environmental, Inc., Midwest Laboratory. ____2001a through 2017a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2016. ____2001b through 2017b. 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. _ _ _ _.2017. Quality Manual, Rev. 4, 19 June 2017. _ _ _ _.2012. Quality Assurance Program Manual, Rev. 3, 14 November 2012. _ _ _ _.2009. Quality Control Procedures Manual, Rev. 2, 08 July 2009. _ _ _ _2009. Quality Control Program, Rev. 2, 12 November 2009. Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382. 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 2016. Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2016. Minneapolis, Minnesota. ____2009 to 2016. Prairie Island Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2016. Minneapolis, Minnesot 25
~*, ATI Environmental, Inc. "*lf.. /'"'\I Midwest Laboratory 700 Landwehr Road
- Northbrook, IL 60062-2310 phone (847)564-0700
- fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS AND INTRALABORATORY COMPARISON PROGRAM RESULTS NOTE: Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.
January, 2017 through December, 2017
Appendix A lnterlaboratory/ lntralaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems. Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. Results in Table A-1 were obtained through participation in the 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 in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request. Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request. Table A-5 lists 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 ANALYSES 8 One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter
> 100 pCi/liter or kg 10% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
> 30 pCi/liter or kg 10% of known value Potassium-40 ;:: 0.1 g/liter or kg 10% of known value Gross alpha s 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta s 100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 10% of known value Tritium s 4,000 pCi/liter +/- 1a =
0933 169.85 x (known)°-
> 4,000 pCi/liter 10% of known value Radium-226,-228 ;:: 0.1 pCi/liter 15% of known value Plutonium ;:: 0.1 pCi/liter, gram, or sample 10% of known value lodine-131, s 55 pCi/liter 6 pCi/liter lodine-129b > 55 pCi/liter 10% of known value Uranium-238, s 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b lron-55b 50 to 100 pCi/liter 1O pCi/liter
> 100 pCi/liter 10% of known value Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program", Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit. A2
8 TABLE A-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-95 1/9/2017 Sr-89 51.9 +/- 4.6 55.5 44.3 - 63.2 Pass ERW-95 1/9/2017 Sr-90 43.6 +/- 2.4 43.1 31.8 - 49.5 Pass ERW-97 1/9/2017 Ba-133 78.2 +/- 4.1 85.6 72.0 - 94.2 Pass ERW-97 1/9/2017 Cs-134 53.9 +/- 3.8 52.6 42.4 - 57.9 Pass ERW-97 1/9/2017 Cs-137 122 +/-6 112 101 -126 Pass ERW-97 1/9/2017 Co-60 117 +/-4 113 102 -126 Pass ERW-97 1/9/2017 Zn-65 208 +/- 13 189 170 - 222 Pass ERW-99 1/9/2017 Gr. Alpha 48.9 +/- 2.4 52.3 27.3 - 65.5 Pass ERW-99 1/9/2017 Gr. Beta 37.1 +/- 1.3 41.6 27.7 - 49.0 Pass ERW-101 1/9/2017 1-131 22.3 +/- 0.6 24.3 20.2 - 28.8 Pass ERW-103 1/9/2017 Ra-226 11.3 +/-0.4 12.7 9.5 - 14.7 Pass ERW-103 1/9/2017 Ra-228 6.10 +/- 0.90 6.20 3.8 - 8.1 Pass ERW-103 1/9/2017 Uranium 11.8 +/- 0.8 12.6 9.9 - 14.4 Pass ERW-106 1/9/2017 H-3 12,600 +/- 300 12,500 10,900 -13,800 Pass ERW-3344 7/10/2017 Sr-89 29.0 +/- 10.0 26.4 18.4 - 32.9 Pass ERW-3344 7/10/2017 Sr-90 33.8 +/- 3.3 36.0 26.4 - 41.5 Pass ERW-3346 7/10/2017 Ba-133 66.4 +/- 4.1 66.3 55.2 - 72.9 Pass ERW-3346 7/10/2017 Cs-134 27.0 +/- 4.3 24.4 18.7 - 27.2 Pass ERW-3346 7/10/2017 Cs-137 57.4 +/- 4.5 51.6 46.4 - 59.6 Pass ERW-3346 7/10/2017 Co-60 92.6 +/- 4.4 88.6 79.7 - 99.8 Pass ERW-3346 7/10/2017 Zn-65 32.4 +/- 6.0 32.7 27.3-41.6 Pass ERW-3348 7/10/2017 Gr. Alpha 23.7 +/- 1.9 25.7 13.0-34.1 Pass ERW-3348 7/10/2017 Gr. Beta 54.6 +/- 1.6 63.0 43.5 - 69.6 Pass ERW-3350 7/10/2017 1-131 25.4 +/- 1.3 25.5 21.2 - 30.1 Pass ERW-3352 7/10/2017 Ra-226 1.38 +/- 0.15 1.29 1.07 -1.95 Pass ERW-3352 7/10/2017 Ra-228 6.70 +/- 0.93 5.66 3.45 - 7.47 Pass ERW-3352 7/10/2017 Uranium 58.4 +/- 0.9 66.7 54.3 - 73.9 Pass ERW-3354 7/10/2017 H-3 5,254 +/- 224 5,060 4,340 - 5,570 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA). Al-1
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4 : Dy Cards). a mrem b 0 Lab Code Irradiation Delivered Reported Performance Date Description Dose Dose Quotient (P) Environmental. Inc. Group 1 2017-1 10/16/2017 Spike 1 59.0 49.3 -0.16 2017-1 10/16/2017 Spike 2 59.0 53.2 -0.10 2017-1 10/16/2017 Spike 3 59.0 52.7 -0.11 2017-1 10/16/2017 Spike 4 59.0 53.4 -0.09 2017-1 10/16/2017 Spike 5 59.0 51.8 -0.12 2017-1 10/16/2017 Spike 6 59.0 54.0 -0.08 2017-1 10/16/2017 Spike 7 59.0 52.0 -0.12 2017-1 10/16/2017 Spike 8 59.0 52.6 -0.11 2017-1 10/16/2017 Spike 9 59.0 54.6 -0.07 2017-1 10/16/2017 Spike 10 59.0 50.4 -0.15 2017-1 10/16/2017 Spike 11 59.0 53.9 -0.09 2017-1 10/16/2017 Spike 12 59.0 55.7 -0.06 2017-1 10/16/2017 Spike 13 59.0 50.2 -0.15 2017-1 10/16/2017 Spike 14 59.0 52.4 -0.11 2017-1 10/16/2017 Spike 15 59.0 54.3 -0.08 2017-1 10/16/2017 Spike 16 59.0 53.2 -0.10 2017-1 10/16/2017 Spike 17 59.0 50.1 -0.15 2017-1 10/16/2017 Spike 18 59.0 52.3 -0.11 2017-1 10/16/2017 Spike 19 59.0 50.3 -0.15 2017-1 10/16/2017 Spike 20 59.0 50.7 -0.14 2017-1 10/16/2017 Spike 21 59.0 53.1 -0.10 2017-1 10/16/2017 Spike 22 59.0 51.5 -0.13 2017-1 10/16/2017 Spike 23 59.0 54.4 -0.08 2017-1 10/16/2017 Spike 24 59.0 53.3 -0.10 2017-1 10/16/2017 Spike 25 59.0 53.7 -0.09 2017-1 10/16/2017 Spike 26 59.0 51.6 -0.13 2017-1 10/16/2017 Spike 27 59.0 51.5 -0.13 2017-1 10/16/2017 Spike 28 59.0 51.6 -0.13 2017-1 10/16/2017 Spike 29 59.0 49.9 -0.15 2017-1 10/16/2017 Spike 30 59.0 55.3 -0.06 Mean (Spike 1-30) 52.4 -0.11 Passd Standard Deviation (Spike 1-30) 1.7 0.03 Passd a 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 were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose. b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 1;1t the reference dose point H*(1 0)Ka = 1.20 . mrem/cGy = 1000. c Performance Quotient (P) is calculated as ((reported dose - conventially true vaIu*e) + 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, CaSO 4 : Dy Cards).
- mrem b
Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Environmental, Inc. Group 2 2017-2 10/16/2017 Spike 31 186.0 164.7 -0.11 2017-2 10/16/2017 Spike 32 186.0 172.0 -0.08 2017-2 10/16/2017 Spike 33 186.0 167.3 -0.10 2017-2 10/16/2017 Spike 34 186.0 160.6 -0.14 2017-2 10/16/2017 Spike 35 186.0 171.7 -0.08 2017-2 10/16/2017 Spike 36 186.0 177.0 -0.05 2017-2 10/16/2017 Spike 37 186.0 176.7 -0.05 2017-2 10/16/2017 Spike 38 186.0 165.5 -0.11 2017-2 10/16/2017 Spike 39 186.0 174.6 -0.06 2017-2 10/16/2017 Spike 40 186.0 172.7 -0.07 2017-2 10/16/2017 Spike 41 186.0 167.8 -0.10 2017-2 10/16/2017 Spike 42 186.0 161.0 -0.13 2017-2 10/16/2017 Spike 43 186.0 166.3 -0.11 2017-2 10/16/2017 Spike 44 186.0 172.4 -0.07 2017-2 10/16/2017 Spike 45 186.0 173.0 -0.07 2017-2 10/16/2017 Spike 46 186.0 169.5 -0.09 2017-2 10/16/2017 Spike 47 186.0 169.0 -0.09 2017-2 10/16/2017 Spike 48 186.0 166.9 -0.10 2017-2 10/16/2017 Spike 49 186.0 165.9 -0.11 2017-2 10/16/2017 Spike 50 186.0 166.7 -0.10 2017-2 10/16/2017 Spike 51 186.0 161.1 -0.13 2017-2 10/16/2017 Spike 52 186.0 173.4 -0.07 2017-2 10/16/2017 Spike 53 186.0 173.1 -0.07 2017-2 10/16/2017 Spike 54 186.0 160.0 -0.14. 2017-2 10/16/2017 Spike 55 186.0 166.1 -0.11 2017-2 10/16/2017 Spike 56 186.0 164.5 -0.12 2017-2 10/16/2017 Spike 57 186.0 163.8 -0.12 2017-2 10/16/2017 Spike 58 186.0 159.9 -0.14 2017-2 10/16/2017 Spike 59 186.0 165.6 -0.11 2017-2 10/16/2017 Spike 60 186.0 165.0 -0.11 Mean (Spike 31-60) 167.8 -0.10 Passd Standard Deviation (Spike 31-60) 5.0 0.03 Passd a 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 were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose. b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(1 0)Ka = 1.20 . mrem/cGy = 1000. 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 c Activity Limits d Acceptance W-010417 4/29/2016 Cs-134 38.2 +/- 8.1 36.2 29.0 -43.4 Pass. W-010417 4/29/2016 Cs-137 78.0 +/- 8.8 71.9 57.5 - 86.3 Pass SPW-306 1/4/2017 Ra-226 18.1 +/- 0.4 16.7 13.4 - 20.1 Pass SPW-32 1/6/2017 H-3 17,849 +/- 393 17,243 10,346 - 24,140 Pass SPW-46 1/9/2017 Gr. Alpha 20.0 +/- 0.4 20.1 16.1 - 24.1 Pass SPW-46 1/9/2017 Gr. Beta 29.0 +/- 0.3 28.9 23.1 - 34.6 Pass SPW-92 1/11/2017 H-3 18,095 +/- 397 17,243 10,346 - 24,140 Pass SPW-142 1/12/2017 Sr-90 39.4 +/- 2.3 36.6 29.3 - 43.9 Pass SPW-155 1/19/2017 H-3 17,974 +/- 400 17,243 10,346 - 24,140 Pass SPW-186 1/23/2017 H-3 17,383 +/- 366 17,243 10,346 -24,140 Pass SPW-232 1/19/2017 H-3 17,542 +/- 368 17,243 10,346 - 24,140 Pass SPW-304 1/26/2017 H-3 17,782 +/- 400 17,243 10,346 - 24,140 Pass SPW-333 1/30/2017 H-3 17,910 +/-406 17,243 10,346 - 24,140 Pass SPW-353 2/2/2017 U-234 47.8 +/- 2.3 41.7 33.4 - 50.0 Pass SPW-353 2/2/2017 U-238 50.4 +/- 2.4 41.7 33.4 - 50.0 Pass W-020217 4/29/2016 Cs-134 33.7 +/- 6.1 36.2 29.0 -43.4 Pass W-020217 4/29/2016 Cs-137 78.4 +/- 7.3 71.9 57.5 - 86.3 Pass SPW-412 2/6/2017 Sr-90 36.2 +/- 2.4 36.6 29.3 - 43.9 Pass SPW-465 2/8/2017 H-3 17,573 +/- 396 17,243 10,346 - 24,140 Pass SPW-561 2/15/2017 H-3 17,358 +/- 395 17,243 10,346-24,140 Pass SPW-605 2/16/2017 H-3 17,820 +/- 401 17,243 10,346 - 24,140 Pass SPW-657 2/17/2017 H-3 17,614 +/-376 17,243 10,346 - 24,140 Pass SPW-714 2/23/2017 H-3 17,662 +/- 400 17,243 10,346 - 24, 140 Pass SPW-737 2/28/2017 H-3 17,196 +/-395 17,243 . 10,346 - 24,140 Pass SPAP-740 2/28/2017 Gr. Beta 38.9 +/- 0.1 41.5 33.2 -49.8 Pass SPAP-742 2/24/2017 Cs-134 1.05 +/- 0.60 0.98 0.78 -1.18 Pass SPAP-742 2/24/2017 Cs-137 90.4 +/- 2.5 92.9 74.3-111.5 Pass SPW-746 2/28/2017 Sr-90 42.8 +/- 2.5 36.6 29.3 - 43.9 Pass SPW-748 2/28/2017 C-14 4270 +/- 17 4735 3788 - 5682 Pass SPW-750 2/28/2017 Ni-63 463 +/-4 400 240 - 560 Pass SPF-752 2/28/2017 Cs-134 1033 +/- 38 1090 870 - 1300 Pass SPF-752 2/28/2017 Cs-137 3071 +/- 61 2820 2250 - 3380 Pass SPW-781 3/1/2017 Ra-226 18.1 +/- 0.4 16.7 13.4-20.1 Pass SPW-783 3/1/2017 H-3 17,653 +/- 400 17,243 13,794 - 20,692 Pass W-030517 4/29/2016 Cs-134 38.0 +/- 9.0 36.2 29.0 -43.4 Pass W-030517 4/29/2016 Cs-137 80.9 +/- 9.2 71.9 57.5 - 86.3 Pass SPW-1010 3/14/2017 H-3 17,312 +/- 395 17,243 13,794 - 20,692 Pass SPW-1026 3/16/2017 Gr. Alpha 22.4 +/- 0.5 20.1 12.0-28.1 Pass SPW-1026 3/16/2017 Gr. Beta 29.2 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-1092 3/21/2017 H-3 17,252 +/- 390 17,243 13,794 - 20,692 Pass SPW-1151 3/24/2017 H-3 17,009 +/- 388 17,243 13,794 - 20,692 Pass SPW-1163 3/28/2017 Sr-90 39.0 +/- 2.3 36.3 29.0 - 43.5 Pass SPW-1178 3/29/2017 Ra-228 15.1 +/- 1.9 16.0 9.6 - 22.4 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-1232 3/30/2017 H-3 17,150 +/- 390 17,243 13,794 - 20,692 Pass SPW-1246 3/31/2017 l-131(G) 33.0 +/- 7.3 36.6 29.3 - 43.9 Pass SPW-1246 3/31/2017 Cs-134 28.9 +/-4.6 26.6 21.3 - 31.9 Pass SPW-1246 3/31/2017 Cs-137 80.6 +/- 8.2 70.4 56.3 - 84.5 Pass SPMl-1248 3/31/2017 l-131(G) 39.8 +/- 7.0 36.6 29.3 - 43.9 Pass SPMl-1248 3/31/2017 Cs-134 26.9 +/- 5.9 26.6 21.3 - 31.9 Pass SPMl-1248 3/31/2017 Cs-137 70.4 +/- 6.9 70.4 56.3 - 84.5 Pass SPMl-1248 3/31/2017 1-131 36.2 +/- 0.6 36.6 29.3 -43.9 Pass SPW-1295 3/31/2017 Ra-226 17.9 +/- 0.4 16.7 13.4 - 20.1 Pass SPW-1304 4/4/2017 H-3 17,741 +/- 398 17,243 13,794 - 20,692 Pass SPW-1359 4/5/2017 1-131 44.3 +/- 0.5 47.6 38.1 - 57.1 Pass SPW-1378 4/7/2017 H-3 17,528 +/- 395 17,243 13,794 -20,692 Pass SPW-1391 4/7/2017 Gr. Alpha 21.1 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-1391 4/7/2017 Gr. Beta 27.8 +/- 0.3 28.2 17.3 - 40.4 Pass SPW-1480 4/12/2017 H-3 17,399 +/- 392 17,243 13,794 - 20,692 Pass W-041317 4/29/2016 Cs-134 34.6 +/- 5.6 36.2 29.0 - 43.4 Pass W-041317 4/29/2016 Cs-137 81.9 +/- 8.0 71.9 57.5 - 86.3 Pass SPW-1480 4/12/2017 H-3 17,399 +/- 392 17,243 13,794 -20,692 Pass SPW-1575 4/18/2017 H-3 17,419 +/-393 17,243 13,794 - 20,692 Pass SPW-1626 4/20/2017 Sr-90 37.2 +/- 2.4 36.3 29.0 - 43.5 Pass SPW-1658 4/21/2017 H-3 17,194 +/-391 17,243 13,794 - 20,692 Pass SPW-1776 4/26/2017 H-3 16,609 +/- 386 17,243 13,794 - 20,692 Pass SPW-1806 4/27/2017 H-3 17,203 +/- 390 17,243 13,794 - 20,692 Pass SPW-1937 5/3/2017 H-3 16,690 +/- 385 17,243 13,794 - 20,692 Pass SPW-1971 5/5/2017 Sr-90 41.5 +/-2.2 36.3 29.0 - 43.5 Pass SPW-2033 5/8/2017 H-3 16,780 +/- 386 17,243 13,794 -20,692 Pass SPW-2420 5/9/2017 Ra-226 16.3 +/- 0.5 16.7 13.4 - 20.1 Pass W-051517 4/29/2016 Cs-134 36.3 +/- 5.0 36.2 29.0 - 43.4 Pass W-051517 4/29/2016 Cs-137 68.9 +/- 6.6 71.9 57.5 - 86.3 Pass SPW-2284 5/22/2017 H-3 16,935 +/- 389 16,703 13,362 - 20,043 Pass SPW-2354 5/23/2017 H-3 17,006 +/- 390 16,700 13,360 - 20,040 Pass SPW-2891 5/23/2017 Ra-226 17.5 +/- 0.4 16.7 13.4 -20.1 Pass SPW-2418 5/23/2017 Ra-228 14.0+/-1.8 16.0 11.2 - 20.8 Pass SPW-2439 5/25/2017 Ra-228 13.0+/-1.8 16.0 11.2 - 20.8 Pass SPMl-2378 5/24/2017 Sr-89 83.7 +/- 4.9 98.4 78.7 - 118.1 Pass SPMl-2378 5/24/2017 Sr-90 39.5 +/- 1.5 36.1 28.9 -43.4 Pass SPW-2468 5/26/2017 H-3 17,065 +/- 391 16,692 13,354 - 20,031 Pass SPW-2848 5/26/2017 1-131 56.4 +/- 0.6 58.3 46.6 - 70.0 Pass SPW-2502 6/1/2017 H-3 17,596 +/- 396 16,677 13,342 - 20,012 Pass SPW-2659 6/5/2017 H-3 17,027 +/- 390 16,677 13,342 - 20,012 Pass SPW-2790 6/9/2017 H-3 17,101 +/- 392 17,101 13,325 - 19,988 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-2798 6/12/2017 H-3 16,683 +/- 364 16,649 13,319 - 19,978 Pass SPW-2943 6/19/2017 Sr-90 39.2 +/- 2.3 36.1 28.9 - 43.4 Pass SPW-3509 6/15/2017 Ra-226 17.6 +/- 0.5 16.7 13.4 - 20.1 Pass W-061317 4/29/2016 Cs-134 35.0 +/- 6.2 36.2 29.0 -43.4 Pass W-061317 4/29/2016 Cs-137 77.4 +/- 7.8 71.9 57.5 - 86.3 Pass SPW-3041 6/23/2017 H-3 16,419 +/- 378 16,620 13,296 -19,945 Pass SPW-3511 6/23/2017 Ra-226 15.5 +/- 0.6 16.7 13.4 - 20.1 Pass SPW-3103 6/28/2017 H-3 16,507 +/- 380 16,507 13,286 - 19,929 Pass SPW-3117 6/29/2017 Tc-99 112.7 +/- 1.9 107.8 86.2 - 129.4 Pass SPW-3513 6/29/2017 Ra-226 17.8 +/- 0.5 16.7 13.4 - 20.1 Pass SPW-3188 7/3/2017 Sr-90 38.1 +/- 2.2 36.1 28.9 - 43.4 Pass SPW-3283 7/11/2017 H-3 16,057 +/- 347 16,649 13,319 - 19,978 Pass SPW-4054 7/11/2017 Ra-226 17.7 +/- 0.4 16.0 11.2 - 20.8 Pass SPW-3467 7/14/2017 Gr. Alpha 22.3 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-3467 7/14/2017 Gr. Beta 29.1 +/- 0.3 28.2 17.3 -40.4 Pass SPW-3449 7/15/2017 H-3 17,196 +/- 393 16,507 13,286 - 19,929 Pass SPW-3548 7/19/2017 H-3 16,764 +/- 386 16,507 13,286 - 19,929 Pass SPW-3728 7/24/2017 H-3 16,117 +/- 354 16,507 13,286 - 19,929 Pass SPW-3794 7/28/2017 H-3 16,645 +/- 384 16,507 13,286 - 19,929 Pass W-072817 4/29/2016 Cs-134 38.6 +/- 5.6 36.2 29.0 -43.4 Pass W-072817 4/29/2016 Cs-137 76.5 +/- 7.6 71.9 57.5 - 86.3 Pass SPW-3905 8/3/2017 Gr. Alpha 22.3 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-3905 8/3/2017 Gr. Beta 27.6 +/- 0.3 28.2 17.3 - 40.4 Pass SPW-4030 8/9/2017 H-3 17,636 +/- 403 16,507 13,286 - 19,929 Pass SPW-4086 8/14/2017 H-3 17,472 +/- 401 16,507 13,286 - 19,929 Pass SPW-4207 8/17/2017 H-3 17,013 +/- 393 16,507 13,286 - 19,929 Pass W-083017 4/29/2016 Cs-134 34.7 +/- 6.4 36.2 29.0 -43.4 Pass W-083017 4/29/2016 Cs-137 78.2 +/- 6.7 71.9 57.5 - 86.3 Pass SPW-4241 8/19/2017 H-3 17,222 +/- 371 16,507 13,286 - 19,929 Pass SPW-4458 9/1/2017 Ra-226 14.1 +/-1.8 16.7 13.4 - 20.1 Pass SPW-4466 9/6/2017 Sr-89 22.8 +/- 8.5 26.4 21.1 - 31.7 Pass SPW-4466 9/6/2017 Sr-90 32.5 +/- 2.1 33.8 27.0 - 40.6 Pass SPW-4512 9/8/2017 Gr. Alpha 19.2 +/- 0.4 20.1 10.1 - 30.2 Pass SPW-4512 9/8/2017 Gr. Beta 27.8 +/- 0.3 27.9 22.3 - 33.5 Pass SPW-4586 9/9/2017 H-3 16,586 +/- 362 16,507 13,286 - 19,929 Pass SPW-4720 9/16/2017 H-3 16,439 +/- 362 16,507 13,286 - 19,929 Pass SPW-4834 9/22/2017 H-3 16,238 +/- 378 16,507 13,286 - 19,929 Pass SPW-4935 9/27/2017 H-3 16,595 +/-381. 16,507 13,286 - 19,929 Pass SPW-4937 9/27/2017 Ra-228 5.7 +/- 0.9 5.8 4.1 - 7.5 Pass W-092717 4/29/2016 Cs-134 36.0 +/- 5.9 36.2 29.0 - 43.4 Pass W-092717 4/29/2016 Cs-137 82.6 +/- 8.5 71.9 57.5 - 86.3 Pass SPW-5001 9/29/2017 H-3 16,446 +/- 358 16,507 13,286 - 19,929 Pass A3-3
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-5134 10/6/2017 H-3 16,128 +/- 373 16,507 13,286 - 19,929 Pass SPW-5274 10/12/2017 H-3 16,108 +/- 374 16,507 13,286 - 19,929 Pass W-101217S 10/12/2017 Fe-55 1,491 +/- 77 1,482 1,186 -01,778 Pass SPW-5408 10/18/2017 Ni-63 203 +/-3 199 159 -238 Pass SPW-5430 10/19/2017 H-3 16,453 +/- 380 16,507 13,286 - 19,929 Pass W-102017 4/29/2016 Cs-134 31.3 +/- 4.9 36.2 29.0 - 43.4 Pass W-102017 4/29/2016 Cs-137 80.4 +/- 6.9 71.9 57.5 - 86.3 Pass SPW-5674 10/25/2017 H-3 16,313 +/- 380 16,507 13,286 - 19,929 Pass SPW-5719 10/27/2017 H-3 16,113 +/- 350 16,507 13,286 - 19,929 Pass SPW-5730 10/31/2017 H-3 16,776 +/- 387 16,507 13,286 - 19,929 Pass SPW-5944 10/27/2017 Ra-226 16.4 +/- 0.5 16.7 13.4 - 20.1 Pass SPW-5915 11/9/2017 H-3 16,930 +/- 390 16,507 13,286 - 19,929 Pass SPW-5989 11/11/2017 H-3 16,084 +/- 352 16,507 13,286 - 19,929 Pass W-111417 4/29/2016 Cs-134 38.1 +/- 6.2 36.2 29.0 - 43.4 Pass W-111417 4/29/2016 Cs-137 74.0 +/- 7.5 71.9 57.5 - 86.3 Pass SPW-6121 11/16/2017 H-3 16,276 +/- 378 16,507 13,286 - 19,929 Pass SPW-6132 11/20/2017 H-3 15,897 +/- 374 16,507 13,286 - 19,929 Pass SPW-6249 11/30/2017 Ra-226 12.2 +/- 0.4 12.3 9.8-14.8 Pass SPW-6226 12/1/2017 H-3 16,164 +/- 378 16,507 13,286 - 19,929 Pass SPW-6318 12n/2017 H-3 15,779 +/- 372 16,507 13,286 - 19,929 Pass W-120817 4/29/2016 Cs-134 29.5 +/- 5.6 36.2 29.0 - 43.4 Pass W-120817 4/29/2016 Cs-137 78.8 +/- 9.6 71.9 57.5 - 86.3 Pass SPW-65 12/11/2017 Ra-226 12.5 +/- 0.4 12.3 9.8 -14.8 Pass SPW-6437 12/13/2017 Gr. Alpha 19.6 +/- 0.4 20.1 10.1 - 30.2 Pass SPW-6437 12/13/2017 Gr. Beta 28.2 +/- 0.3 27.9 22.3 - 33.5 Pass SPW-6463 12/15/2017 H-3 15,560 +/- 372 16,507 13,286 - 19,929 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). 0 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. A3-4
TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activity° Criteria (4.66 cr) SPW-31 Water 1/6/2017 H-3 143 71 +/- 75 200 SPW-45 Water 1/9/2017 Gr. Alpha 0.41 0.09 +/- 0.30 2 SPW-45 Water 1/9/2017 Gr. Beta 0.74 -0.56 +/- 0.50 4 SPW-91 Water 1/11/2017 H-3 151 -23 +/- 71 200 SPW-141 Water 1/12/2017 Sr-89 0.55 0.29 +/- 0.47 5 SPW-141 Water 1/12/2017 Sr-90 0.67 -0.02 +/- 0.31 SPW-154 Water 1/19/2017 H-3 155 -17 +/- 73 200 SPW-185 Water 1/23/2017 H-3 176 44 +/- 94 200 SPW-231 Water 1/19/2017 H-3 179 26 +/- 87 200 SPW-303 Water 1/26/2017 H-3 160 8 +/- 77 200 SPW-305 Water 1/4/2017 Ra-226 0.02 0.02 +/- 0.01 2 SPW-307 Water 1/27/2017 1-131 0.21 0.01 +/- 0.11 1.00 SPW-332 Water 1/30/2017 H-3 169 -52 +/- 86 200 SPW-352 Water 2/2/2017 U-234 0.14 0.00 +/- 0.08 SPW-352 Water 2/2/2017 U-238 0.14 0.12 +/- 0.15 SPW-411 Water 2/6/2017 Sr-89 0.49 0.30 +/- 0.35 5 SPW-411 Water 2/6/2017 Sr-90 0.52 -0.22 +/- 0.21 1 SPW-464 Water 2/8/2017 H-3 155 2 +/- 74 200 SPW-560 Water 2/15/2017 H-3 156 38 +/- 77 200 SPW-604 Water 2/16/2017 H-3 154 59 +/- 77 200 SPW-656 Water 2/17/2017 H-3 187 28 +/- 94 200 SPW-713 Water 2/23/2017 H-3 161 20 +/- 81 200 SPW-736 Water 2/28/2017 H-3 161 -75 +/- 76 200 SPAP-739 AP 2/28/2017 Gr. Beta 0.002 0.004 +/- 0.001 0.01 SPAP-741 AP 2/24/2017 Cs-134 2.27 -0.95 +/- 1.29 100 SPAP-741 AP 2/24/2017 Cs-137 2.65 0.17 +/- 1.67 100 SPW-747 Water 2/28/2017 C-14 161 -28 +/- 97 200 SPW-749 Water 2/28/2017 Ni-63 17 -3 +/- 10 200 SPF-751 Fish 2/28/2017 Cs-134 0.008 0.002 +/- 0.004 100 SPF-751 Fish 2/28/2017 Cs-137 0.008 0.000 +/- 0.005 100 SPW-780 Water 3/1/2017 Ra-226 0.02 0.02 +/- 0.01 2 SPW-782 Water 3/1/2017 H-3 154 35 +/- 78 200 SPW-3506 Water 3/1/2017 Ra-226 0.03 0.02 +/- 0.02 2 SPW-836 Water 3/3/2017 1-131 0.38 0.04 +/- 0.18 1 SPW-1009 Water 3/14/2017 H-3 154 -31 +/- 72 200 SPW-1025 Water 3/16/2017
- Gr. Alpha 0.43 -0.16 +/- 0.28 2 SPW-1025 Water 3/16/2017 Gr. Beta 0.75 -0.24 +/- 0.52 4 SPW-1091 Water 3/21/2017 H-3 145 60 +/- 73 200 SPW-1150 Water 3/24/2017 H-3 152 -31 +/- 71 200 SPW-1162 Water 3/28/2017 Sr-89 0.61 -0.39 +/- 0.45 5 SPW-1162 Water 3/28/2017 Sr-90 0.52 0.18+/-0.27 1
- Liquid sample results are reported in pCi/Liter, air filters ( pCiim3), 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 Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activity° Criteria (4.66 cr) SPW-1177 Water 3/29/2017 Ra-228 0.83 -0.14 +/-0.36 2 SPW-1231 Water 3/30/2017 H-3 150 24 +/- 73 200 SPW-1245 Water 3/31/2017 Cs-134 3.73 0.43 +/- 2.18 100 SPW-1245 Water 3/31/2017 Cs-137 3.01 -1.23 +/- 2.12 100 SPW-1245 Water 3/31/2017 1-131 (G) 5.39 0.92 +/- 2.15 100 SPW-1245 Water 3/31/2017 i-131 0.32 0.03 +/- 0.18 SPMl-1247 Milk 3/31/2017 Cs-134 3.70 1.23 +/- 1.96 100 SPMl-1247 Milk 3/31/2017 Cs-137 3.62 -0.84 +/-2.15 100 SPMl-1247 Milk 3/31/2017 l-131(G) 4.42 0.39 +/-2.14 100 SPW-1294 Water 3/31/2017 Ra-226 0.02 0.18 +/-0.02 2 SPW-1303 Water 4/4/2017 H-3 151 8 +/- 75 200 SPW-1377 Water 4/7/2017 H-3 150 29 +/- 72 200 SPW-1390 Water 4/7/2017 Gr. Alpha 0.42 0.15 +/-0.31 2 SPW-1390 Water 4/7/2017 Gr. Beta 0.73 -0.17 +/- 0.51 4 SPW-1479 Water 4/12/2017 H-3 151 89 +/- 77 200 SPW-1574 Water 4/18/2017 H-3 144 55 +/- 79 200 SPW-1625 Water 4/20/2017 Sr-89 0.59 -0.01 +/- 0.50 5 SPW-1625 Water 4/20/2017 Sr-90 0.71 0.16 +/- 0.35 1 SPW-1657 Water 4/21/2017 H-3 147 34 +/- 73 200 SPW-1775 Water 4/26/2017 H-3 155 67 +/- 80 200 SPW-1805 Water 4/27/2017 H-3 153 15 +/- 74 200 SPW-1936 Water 5/3/2017 H-3 148 33 +/- 71 200 SPW-1970 Water 5/5/2017 Sr-89 0.66 0.34 +/- 0.54 5 SPW-1970 Water 5/5/2017 Sr-90 0.62 -0.08 +/- 0.28 1 SPW-2032 Water 5/8/2017 H-3 147 66 +/- 73 200 SPW-2419 Water 5/9/2017 Ra-226 0.03 0.01 +/- 0.03 2 SPW-2283 Water 5/22/2017 H-3 155 24 +/- 78 200 SPW-2353 Water 5/23/2017 H-3 151 56 +/- 76 200 SPW-2890 Water 5/23/2017 Ra-226 0.03 -0.01 +/- 0.02 2 SPMl-2377 Milk 5/24/2017 Sr-89 0.78 0.86 +/- 0.93 5 SPMl-2377 Milk 5/24/2017 Sr-90 0.49 0.95 +/- 0.33 SPW-2438 Water 5/25/2017 Ra-228 0.90 -0.28 +/- 0.38 2 SPW-2467 Water 5/26/2017 H-3 152 27 +/- 77 200 SPW-2417 Water 5/26/2017 Ra-228 0.80 1.58 +/- 0.54 2 SPW-2447 Water 5/26/2017 1-131 0.21 -0.05 +/- 0.12 1 SPW-2501 Water 6/1/2017 H-3 151 -23 +/- 70 200 SPW-2658 Water 6/5/2017 H-3 152 107 +/- 78 200 SPW-2789 Water 6/9/2017 H-3 150 52 +/- 77 200 SPW-2797 Water 6/12/2017 H-3 177 7 +/- 93 200 SPW-2847 Water 6/14/2017 1-131 0.18 0.03 +/- 0.10 1
- Liquid sample results are reported in pCi/Liter, air filters ( pCitm\ 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. A4-2
TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activity° Criteria (4.66 er) SPW-3508 Water 6/15/2017 Ra-226 0.03 0.00 +/- 0.02 2 SPW-2942 Water 6/19/2017 Sr-89 0.58 0.80 +/- 0.53 5 SPW-2942 Water 6/19/2017 Sr-90 0.50 0.15+/-0.25 SPW-3042 Water 6/23/2017 H-3 146 25 +/- 74 200 SPW-3510 Water 6/23/2017 Ra-226 0.02 0.03 +/- 0.02 2 SPW-3102 Water 6/28/2017 H-3 148 -7 +/- 73 200 SPW-3116 Water 6/29/2017 Tc-99 5.91 -0.39 +/- 3.58 10 SPW-3512 Water 6/29/2017 Ra-226 0.02 -0.01 +/- 0.02 2 SPW-3187 Water 7/3/2017 Sr-89 0.62 0.00 +/- 0.48 5 SPW-3187 Water 7/3/2017 Sr-90 0.48 0.07 +/- 0.23 SPW-3282 Water 7/11/2017 H-3 178 -37 +/- 84 200 SPW-4053 Water 7/11/2017 Ra-226 0.03 0.02 +/- 0.02 2 SPW-3466 Water 7/14/2017 Gr. Alpha 0.42 -0.09 +/- 0.28 2 SPW-3466 Water 7/14/2017 Gr. Beta 0.76 -0.18 +/- 0.53 4 SPW-3448 Water 7/15/2017 H-3 150 54 +/- 77 200 SPW-3727 Water 7/27/2017 Ni-63 90 18 +/- 55 200 SPW-3793 Water 7/28/2017 H-3 151 47 +/- 82 200 SPW-3904 Water 8/3/2017 Gr. Alpha 0.47 -0.02 +/- 0.33 2 SPW-3904 Water 8/3/2017 Gr. Beta 0.75 -0.11 +/- 0.52 4 SPW-4029 Water 8/9/2017 H-3 159 11 +/- 79 200 SPW-4206 Water 8/17/2017 H-3 157 55 +/- 76 200 SPW-4241 Water 8/19/2017 H-3 190 61 +/- 96 200 SPW-4085 Water 8/14/2017 H-3 159 -28 +/- 77 200 SPW-4206 Water 8/17/2017 H-3 157 55 +/- 76 200 SPW-4241 Water 8/19/2017 H-3 190 61 +/- 96 200 SPW-4457 Water 9/1/2017 Ra-228 0.78 -0.02 +/- 0.36 2 SPW-4465 Water 9/6/2017 Sr-89 0.51 0.30 +/- 0.37 5 SPW-4465 Water 9/6/2017 Sr-90 0.46 -0.09 +/- 0.20 1 SPW-4585 Water 9/9/2017 H-3 187 -86 +/- 83 200 SPW-5720 Water 9/13/2017 Ra-226 0.02 0.13+/-0.02 2 SPW-4703 Water 9/15/2017 1-131 0.17 0.10 +/- 0.10 1 SPW-4719 Water 9/16/2017 H-3 184 -86 +/- 93 200 SPW~4833 Water 9/22/2017 H-3 150 5 +/- 72 200 SPW-4934 Water 9/27/2017 H-3 148 5 +/- 70 200 SPW-4936 Water 9/27/2017 Ra-228 0.80 0.55 +/- 0.44 2 SPW-5000 Water 9/29/2017 H-3 183 -13 +/- 90 200 SPW-5133 Water 10/6/2017 H-3 144 64 +/- 71 200 SPW-5273 Water 10/12/2017 H-3 142 106 +/- 72 200
- Liquid sample results are reported in pCi/Liter, air filters ( pCi!m\ charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b I-131(G); iodine-131 as analyzed by gamma spectroscopy. 0 Activity reported is a net activity result. A4-3
TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activity" Criteria (4.66 a) SPW-5407 Water 10/18/2017 Ni-63 69 43 +/- 43 200 SPW-5429 Water 10/19/2017 H-3 148 54 +/- 72 200 SPW-5603 Water 10/23/2017 Sr-89 0.57 0.16 +/- 0.47 5 SPW-5603 Water 10/23/2017 Sr-90 0.70 -0.12 +/-0.31 1 SPW-5673 Water 10/25/2017 H-3 156 -36 +/- 71 200 SPW-5718 Water 10/27/2017 H-3 182 45 +/- 92 200 SPW-5943 Water 10/27/2017 Ra-226 0.02 0.08 +/- 0.02 2 SPW-5723 Water 10/30/2017 1-131 0.10 0.03 +/- 0.07 1 SPW-5914 Water 11/09/17 H-3 149 -39 +/- 68 200 SPW-5988 Water 11/11/2017 H-3 183 -8 +/- 88 200 SPW-6120 Water 11/16/2017 H-3 146 83 +/- 75 200 SPW-6131 Water 11/20/2017 H-3 151 16 +/- 72 200 SPW-6197 Water 11/29/2017 1-131 0.38 0.01 +/- 0.18 1 SPW-6248 Water 11/30/2017 Ra-226 0.03 0.15 +/-0.03 2 SPW-6225 Water 12/1/2017 H-3 154 -10 +/- 72 200 SPW-6317 Water 12/7/2017 H-3 148 44 +/- 74 200 SPW-64 Water 12/11/2017 Ra-226 0.03 0.18 +/- 0.03 2 SPW-6436 Water 12/13/2017 Gr. Alpha 0.54 -0.17 +/- 0.37 2 SPW-6436 Water 12/13/2017 Gr. Beta 0.74 0.12 +/- 0.52 4 SPW-6464 Water 12/15/2017 H-3 148 31 +/- 75 200
- Liquid sample results are reported in pCi/Liter, air filters ( pCi/m'}, charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy. 0 Activity reported is a net activity result. A4-4
TABLE A-5. *in-House "Duplicate" Samples Concentration a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7178, 7179 1/3/2017 Be-7 0.047 +/- 0.015 0.062 +/- 0.017 0.054 +/- 0.012 Pass SW-6986,6987 1/3/2017 Gr. Beta 1.39 +/- 0.41 0.77 +/-0.41 1.08 +/- 0.29 Pass E-66,67 1/3/2017 Gr. Beta 1.62 +/- 0.05 1.45 +/- 0.04 1.54+/-0.11 Pass E-66,67 1/3/2017 K-40 1.26+/-0.14 1.39+/-0.16 1.32+/-0.11 Pass CF-87,88 1/3/2017 Be-7 0.25 +/- 0.11 0.30 +/- 0.12 0.28 +/- 0.08 Pass CF-87,88 1/3/2017 K-40 7.77 +/- 0.39 6.84 +/- 0.37 7.31 +/- 0.27 Pass AP-011217 1/12/2017 Be-7 0.137 +/- 0.078 0.139+/-0.082 0.138 +/- 0.056 Pass Ml-212,213 1/16/2017 K-40 1,515+/-98 1,347 +/- 107 1,431 +/- 73 Pass WW-321,322 1/19/2017 H-3 675 +/- 118 506 +/- 133 590 +/- 89 Pass WW-674,675 1/20/2017 H-3 7,326 +/- 254 7,717 +/-259 7,522 +/- 181 Pass AP-012317 1/23/2017 Gr. Beta 0.034 +/- 0.005 0.038 +/- 0.005 0.036 +/- 0.004 Pass WW-298,299 1/24/2017 H-3 5,916 +/- 239 5764 +/- 237 5840 +/- 168 Pass AP-013117 1/30/2017 Gr. Beta 0.027 +/- 0.004 0.028 +/- 0.004 0.028 +/- 0.003 Pass WW-500,501 1/31/2017 H-3 1,058 +/- 122 1,054 +/- 121 1,056 +/-86 Pass SW-391,392 1/31/2017 Gr. Beta 1.40 +/- 0.56 1.62 +/- 0.61 1.51 +/- 0.41 Pass SPS-370,371 2/1/2017 K-40 23.47 +/- 0.66 23.11 +/- 0.72 23.29 +/- 0.49 Pass AP-456,457 2/2/2017 Be-7 0.129 +/- 0.076 0.167 +/-0.092 0.148 +/- 0.060 Pass AP-020217 2/2/2017 Gr. Beta 0.021 +/- 0.004 0.027 +/- 0.004 0.024 +/- 0.003 Pass SPS-414,415 2/3/2017 K-40 19.45 +/- 1.85 21.58 +/- 1.99 20.52 +/- 1.36 Pass AP-020617 2/6/2017 Gr. Beta 0.023 +/- 0.004 0.023 +/- 0.004 0.023 +/- 0.003 Pass AP-021417A 2/14/2017 Gr. Beta 0.031 +/- 0.004 0.030 +/- 0.004 0.030 +/- 0.003 Pass SPW-543 2/14/2017 Gr. Beta 7.99 +/- 0.82 9.45 +/- 0.88 8.72 +/- 0.60 Pass AP-021417B 2/14/2017 Gr. Beta 0.024 +/- 0.004 0.028 +/- 0.004 0.026 +/- 0.003 Pass WW-718,719 2/14/2017 H-3 737 +/- 113 643 +/- 110 690 +/- 79 Pass AP-022017 2/20/2017 Gr. Beta 0.018 +/- 0.005 0.021 +/- 0.005 0.020 +/- 0.004 Pass WW-755,756 2/22/2017 H-3 3,709 +/- 196 3,823 +/- 198 3,766 +/- 139 Pass AP-022717 2/27/2017 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.004 0.020 +/- 0.003 Pass SPDW-80011,2 3/2/2017 Ra-226 7.29 +/- 0.32 6.76 +/- 0.30 7.03 +/- 0.22 Pass SPDW-80011,2 3/2/2017 Ra-228 4.68 +/- 0.82 6.29 +/- 1.03 5.49 +/- 0.66 Pass SPDW-80013,4 3/2/2017 *Gr.Alpha 13.57 +/- 1.43 12.44 +/- 1.37 13.01 +/- 0.99 Pass WW-845,846 3/2/2017 H-3 314 +/- 93 249 +/- 90 281 +/- 65 Pass AP-030617 3/6/2017 Gr. Beta 0.022 +/- 0.004 0.019 +/- 0.004 0.020 +/- 0.003 Pass WW-1050, 1051 3/8/2017 H-3 14,994 +/- 364 14,745 +/- 362 14,870 +/- 257 Pass SPS-920,921 3/9/2017 K-40 23.30 +/- 1.76 23.13+/-1.64 23.21 +/- 1.20 Pass WW-1004, 1005 3/13/2017 H-3 182 +/- 80 158 +/- 79 170 +/- 56 Pass SPS-1029, 1030 3/15/2017 K-40 11.82 +/- 0.68 12.01 +/- 0.68 11.92 +/- 0.48 Pass AP-031517 3/15/2017 Gr. Beta 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.002 Pass SPDW-80037,8 3/20/2017 Gr. Alpha 4.54 +/- 0.82 5.29 +/- 0.91 4.91 +/- 0.61 Pass AP-032017 3/20/2017 Gr. Beta 0.021 +/- 0.006 0.021 +/- 0.006 0.021 +/- 0.005 Pass WW-1094, 1095 3/20/2017 H-3 1,571 +/- 137 1,595 +/- 138 1,583+/-175 Pass AS-1
TABLE A-5. In-House "Duplicate" Samples Concentration
- Averaged Lab Code Date Analysis First Result Second Result Result Acceptance WW-1175,1176 3/20/2017 H-3 218 +/- 84 211 +/- 84 214 +/- 59 Pass WW-1129,1130 3/21/2017 Gr. Beta 3.51 +/- 1.24 2.99 +/- 1.17 3.25 +/- 0,85 Pass WW-1219,1220 3/22/2017 H-3 11,467 +/- 322 11,516 +/-323 11,492 +/- 200 Pass SPS-1152, 1153 3/27/2017 Ac-228 20.39 +/- 0.75 20.43 +/- 0.88 20.41 +/- 0.58 Pass SPS-1152, 1153 3/27/2017 Pb-214 17.22 +/- 0,50 16.44 +/- 0.52 16.83 +/- 0.36 Pass SPDW-80047,8 3/28/2017 Ra-226 2.06 +/- 0.23 1.60 +/- 0.32 1.83 +/- 0.20 Pass SPDW-80047,8 3/28/2017 Ra-228 0.53 +/- 0.48 0.78 +/- 0.49 0.66 +/- 0.34 Pass SWU-1242,1243 3/28/2017 Gr. Beta 2.04 +/- 0.81 2.47 +/- 0,69 2.26 +/- 0.53 Pass SPS-1198, 1199 3/29/2017 K-40 16.95 +/- 1.85 18.33 +/- 1.71 17.64 +/- 1.26 Pass SPDW-80050, 1 3/29/2017 Gr. Alpha 3.19 +/- 0.80 3.39 +/- 0,78 3.29 +/- 0.56 Pass SPDW-80050, 1 3/29/2017 Gr. Beta 1.58 +/- 0,60 2.08 +/- 0.63 1.83 +/- 0.44 Pass AP-1706, 1707 3/30/2017 Be-7 0.068 +/- 0.018 0.072 +/- 0.017 0.070 +/- 0.012 Pass SW-1381, 1382 4/5/2017 H-3 402 +/- 92 309 +/- 88 356 +/- 64 Pass WW-1446,1447 4/6/2017 H-3 305 +/- 89 358 +/- 91 332 +/- 64 Pass WW-1532, 1533 4/10/2017 H-3 19,124 +/-412 18,991 +/- 410 19,058 +/- 291 Pass WW-1618,1619 4/12/2017 H-3 4,187 +/- 203 4,305 +/- 205 4,246 +/- 144 Pass SS-1553, 1554 4/13/2017 Gr. Beta 7.16 +/-0.99 6.09 +/- 0.91 6,63 +/- 0.67 Pass SS-1553,1554 4/13/2017 K-40 4,60 +/- 0,32 4.84 +/- 0.34 4.72 +/- 0.23 Pass SS-1553, 1554 4/13/2017 Tl-208 0.038 +/- 0.016 0,032 +/- 0.011 0.035 +/- 0.010 Pass SS-1553, 1554 4/13/2017 Pb-212 0.101 +/- 0.015 0,096 +/- 0,015 0.098 +/- 0.010 Pass SS-1553, 1554 4/13/2017 Bi-214 0.094 +/- 0.032 0.109 +/- 0,022 0.101 +/- 0.019 Pass SS-1553, 1554 4/13/2017 Ac-228 0.089 +/- 0.042 0.111 +/- 0.046 0.100 +/- 0,031 Pass P-2015,2016 5/4/2017 H-3 189 +/- 80 212 +/- 81 200 +/- 57 Pass WW-2336,2337 5/8/2017 H-3 422 +/- 97 298 +/- 91 360 +/- 66 Pass AP-051117 5/11/2017 Gr. Beta 0.018 +/- 0.003 0.025 +/- 0.004 0.021 +/- 0,002 Pass WW-2497,2498 5/23/2017 H-3 1,268+/-127 1,247 +/- 126 1,257 +/- 89 Pass WW-2583,2584 5/23/2017 H-3 5,159 +/-224 5,223 +/- 126 5,191 +/- 129 Pass WW-2732,2733 5/23/2017 H-3 8,559 +/- 282 8,570 +/- 283 8,564 +/- 200 Pass XW-1218,1219 5/23/2017 H-3 11,467 +/- 282 11,516 +/- 283 11,492 +/- 200 Pass Ml-2428,2429 5/24/2017 K-40 1,752 +/- 137 1,805+/-132 1,778 +/- 95 Pass S0-2562,2563 5/24/2017 K-40 7.87 +/- 0.50 8,64 +/- 0.49 8.25 +/- 0.35 Pass WW-3023,3024 5/24/2017 H-3 27,398 +/- 486 27,733 +/- 489 27,565 +/- 344 Pass S0-2453,2454 5/25/2017 Gr. Beta 14.38 +/- 0,93 15.70 +/- 1.06 15.04 +/- 0,70 Pass S0-2453,2454 5/25/2017 Cs-137 0.17 +/-0.03 0.18 +/- 0,03 0.17 +/- 0.02 Pass S0-2453,2454 5/25/2017 K-40 9.80 +/- 0.50 9.19 +/- 0,57 9.50 +/- 0.38 Pass S0-2453,2454 5/25/2017 Tl-208 0.09 +/- 0.02 0.10 +/- 0.03 0.09 +/- 0.02 Pass S0-2453,2454 5/25/2017 Pb-212 0.29 +/- 0,03 0.30 +/- 0.03 0.29 +/- 0.02 Pass S0-2453,2454 5/25/2017 Bi-214 0.24 +/- 0,03 0.18 +/-0.04 0.21 +/- 0,03 Pass S0-2453,2454 5/25/2017 Ra-226 0.82 +/- 0.22 0.62 +/- 0.27 0.72 +/-0.17 Pass S0-2453,2454 5/25/2017 Ac-228 0.32 +/- 0.07 0.28 +/- 0,08 0.30 +/- 0.05 Pass AS-2
TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SWT-2625,2626 5/30/2017 Gr. Beta 0.64 +/- 0.53 1.08 +/- 0.55 0.86 +/- 0.38 Pass AP-053117 5/31/2017 Gr. Beta 0.013 +/- 0.003 0.011 +/- 0.003 0.012 +/- 0.002 Pass G-2646,2647 6/1/2017 Be-7 1.02 +/- 0.17 1.06 +/- 0.26 1.04 +/- 0.15 Pass G-2646,2647 6/1/2017 K-40 7.51 +/- 0.49 6.55 +/- 0.51 7.03 +/- 0.36 Pass SL-2669,70 6/1/2017 Be-7 0.34 +/- 0.06 0.30 +/- 0.06 0.32 +/- 0.04 Pass SL-2669,70 6/1/2017 K-40 4.35 +/- 0.14 4.39 +/- 0.15 4.37 +/- 0.10 Pass F-2711,2712 6/2/2017 K-40 2.56 +/- 0.32 2.77 +/- 0.44 2.66 +/- 0.27 Pass AP-060617 6/6/2017 Gr. Beta 0.026 +/- 0.005 0.027 +/- 0.005 0.027 +/- 0.004 Pass SW-2849,50 6/8/2017 H-3 8,178 +/- 273 8,563 +/- 279 8,371 +/- 195 Pass AP-061217 6/12/2017 Gr. Beta 0.027 +/- 0.005 0.027 +/- 0.005 0.027 +/- 0.004 Pass BS-3446,3447 6/12/2017 K-40 8.30 +/- 0.47 8.57 +/- 0.47 8.44 +/- 0.33 Pass VE-2870,2871 6/13/2017 K-40 3.65 +/- 0.25 3.90 +/- 0.26 3.77 +/- 0.18 Pass AP-2914,5 6/15/2017 Be-7 0.269 +/- 0.146 0.212 +/- 0.123 0.240 +/- 0.095 Pass AP-3067,8 6/15/2017 Be-7 0.204 +/- 0.113 0.328 +/- 0.126 0.266 +/- 0.085 Pass AP-061917 6/19/2017 Gr. Beta 0.020 +/- 0.004 0.019 +/- 0.004 0.020 +/- 0.003 Pass AP-3610,1 6/26/2017 Be-7 0.107 +/- 0.015 0.116 +/- 0.021 0.111 +/- 0.013 Pass AP-062617 6/26/2017 Gr. Beta 0.017 +/- 0.004 0.021 +/- 0.004 0.019 +/- 0.003 Pass AP-3673,3674 7/3/2017 Be-7 0.087 +/- 0.008 0.078 +/- 0.008 0.083 +/- 0.006 Pass AP-3287,3288 7/6/2017 Be-7 0.207 +/- 0.112 0.244 +/- 0.096 0.226 +/- 0.074 Pass WW-3308,3309 7/7/2017 H-3 549 +/- 108 501 +/- 107 525 +/- 76 Pass VE-3362,3363 7/12/2017 K-40 2.32 +/- 0.17 2.40 +/- 0.16 2.36 +/-0.12 Pass VE-3589,3590 7/18/2017 K-40 5.25 +/- 0.33 4.64 +/- 0.33 4.94 +/- 0.23 Pass SG-3631,3632 7/18/2017 Pb-214 3.03 +/- 0.11 2.97 +/- 0.11 3.00 +/- 0.08 Pass SG-3631,3632 7/18/2017 Ac-228 2.47 +/- 0.22 2.56 +/- 0.23 2.52 +/- 0.16 Pass WW-3846,3847 7/25/2017 H-3 505 +/- 101 446 +/- 98 475 +/- 70 Pass F-4509,4510 7/26/2017 K-40 0.85 +/- 0.25 1.00 +/- 0.25 0.93 +/- 0.18 Pass F-4509,4510 7/26/2017 Gr. Beta 1.19 +/- 0.03 1.18+/-0.03 1.18 +/- 0.02 Pass G-3804,3805 7/27/2017 Be-7 3.72 +/- 0.39 3.47 +/- 0.40 3.59 +/- 0.28 Pass G-3804,3805 7/27/2017 K-40 4.21 +/- 0.52 4.46 +/- 0.52 4.34 +/- 0.33 Pass SL-3888,3889 8/1/2017 Be-7 0.77 +/- 0.04 0.73 +/- 0.07 0.75 +/- 0.04 Pass SL-3888,3889 8/1/2017 K-40 0.94 +/- 0.04 0.87 +/- 0.08 0.90 +/- 0.23 Pass WW-4158,4159 8/8/2017 H-3 321 +/- 90 270 +/- 88 295 +/- 63 Pass VE-4179,4180 8/14/2017 K-40 1.84 +/- 0.18 1.90 +/- 0.21 1.87 +/- 0.14 Pass AP-4289,4290 8/17/2017 Be-7 0.212 +/- 0.095 0.162 +/- 0.080 0.187 +/-0.062 Pass F-4333,4334 8/18/2017 K-40 3.22 +/- 0.41 3.62 +/- 0.42 3.42 +/- 0.29 Pass CF-4310,4311 8/21/2017 K-40 10.94 +/- 0.74 11.48 +/- 0.50 11.21 +/- 0.45 Pass DW-80161,80162 8/22/2017 Ra-226 1.22 +/- 0.15 1.19 +/- 0.17 1.21 +/- 0.11 Pass DW-80161,80162 8/22/2017 Ra-228 1.99 +/- 0.63 0.70 +/- 0.49 1.35 +/- 0.40 Pass VE-4398,4399 8/28/2017 Be-7 0.13 +/- 0.07 0.13 +/- 0.08 0.13 +/- 0.05 Pass AS-3
TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4398,4399 8/28/2017 K-40 3.32 +/- 0.22 3.48 +/- 0.25 3.40 +/- 0.17 Pass SW-4463,4464 8/29/2017 H-3 495 +/- 106 491 +/- 106 493 +/- 75 Pass LW-4486,4487 8/31/2017 Gr. Beta 0.425 +/- 0.471 1.358 +/- 0.571 0.892 +/- 0.370 Pass VE-4561,4562 9/6/2017 Be-7 5.89 +/- 0.29 5.76 +/- 0.25 5.83 +/- 0.19 Pass VE-4561,4562 9/6/2017 K-40 3.73 +/- 0.34 3.77 +/- 0.29 3.75 +/- 0.22 Pass BO-5122,5123 9/8/2017 K-40 4.50 +/- 0.36 4.50 +/- 0.36 4.50 +/- 0.25 Pass VE-4692,4693 9/12/2017 K-40 5.16 +/- 0.13 5.31 +/- 0.36 5.24 +/- 0.19 Pass SS-4650 ,4651 9/12/2017 K-40 10.55 +/- 0.51 10.41 +/- 0.54 10.48 +/- 0.37 Pass Ml-4671,4672 9/13/2017 K-40 1,347+/-115 1,283 +/- 118 1,315 +/- 82 Pass Ml-4671,4672 9/13/2017 Sr-90 0.7 +/- 0.3 0.5 +/- 0.3 0.6 +/- 0.2 Pass VE-4973,4974 9/17/2017 K-40 1.11 +/- 0.15 1.17 +/- 0.13 1.14 +/- 0.10 Pass F-4928,4929 9/19/2017 K-40 1.84 +/- 0.31 1.68 +/- 0.34 1.76 +/- 0.23 Pass S-4865,4866 9/20/2017 K-40 21.07 +/- 2.39 19.09 +/- 2.51 20.08 +/- 1.73 Pass VE-4907,4908 9/20/2017 K-40 3.83 +/- 0.44 4.28 +/- 0.31 4.05 +/- 0.27 Pass VE-4844,4845 9/21/2017 K-40 1.81 +/- 0.22 1.88 +/- 0.21 1.84 +/- 0.15 Pass AP-5572,5573 9/27/2017 Be-7 0.082 +/- 0.015 0.075 +/- 0.014 0.078 +/- 0.010 Pass LW-5145,5146 9/28/2017 Gr. Beta 0.84 +/- 0.49 1.47 +/- 0.57 1.16+/-0.38 Pass AP-092917 9/29/2017 Gr. Beta 0.038 +/- 0.004 0.031 +/- 0.004 0.035 +/- 0.003 Pass WW-5080,5081 10/2/2017 H-3 208 +/- 79 223 +/- 80 215 +/- 56 Pass AP-100217 10/2/2017 Gr. Beta 0.025 +/- 0.005 0.028 +/- 0.005 0.026 +/- 0.003 Pass AP-100317 10/3/2017 Gr. Beta 0.037 +/- 0.004 0.033 +/- 0.004 0.035 +/- 0.003 Pass S-5165,5166 10/4/2017 K-40 15.93 +/- 2.30 20.34 +/- 3.15 18.14 +/- 1.95 Pass VE-5228,5229 10/5/2017 K-40 3.25 +/- 0.25 2.82 +/- 0.24 3.04 +/- 0.17 Pass AP-100917 10/9/2017 Gr. Beta 0.021 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.003 Pass VE-5293,5294 10/10/2017 K-40 3.89 +/- 0.30 4.08 +/- 0.34 3.99 +/- 0.22 Pass DW-80184,80185 10/11/2017 Gr. Alpha 2.17 +/- 0.81 2.50 +/- 0.81 2.34 +/- 0.57 Pass DW-80184,80185 10/11/2017 Gr. Beta 9.45 +/- 0.79 10.20 +/- 0.83 9.83 +/- 0.57 Pass S-5421,5422 10/12/2017 K-40 8.82 +/- 1.94 7.97 +/- 0.72 8.40+/-1.03 Pass AP-101617 10/16/2017 Gr. Beta 0.025 +/- 0.005 0.022 +/- 0.004 0.024 +/- 0.003 Pass F-5658,5659 10/19/2017 K-40 2.44 +/- 0.41 2.57 +/- 0.39 2.51 +/- 0.28 Pass SO-5704,5705 10/25/2017 Cs-137 0.05 +/- 0.02 0.04 +/- 0.02 0.04 +/- 0.01 Pass SO-5704,5705 10/25/2017 K-40 10.08 +/- 0.51 9.57 +/- 0.56 9.83 +/- 0.38 Pass SO-5704,5705 10/25/2017 Tl-208 0.10 +/- 0.02 0.09 +/- 0.02 0.10 +/- 0.01 Pass SO-5704,5705 10/25/2017 Bi-214 0.34 +/- 0.04 0.27 +/- 0.04 0.30 +/- 0.03 Pass SO-5704,5705 10/25/2017 Pb-212 0.28 +/- 0.03 0.27 +/- 0.03 0.27 +/- 0.02 Pass SO-5704,5705 10/25/2017 Ra-226 1.15 +/- 0.52 0.59 +/- 0.22 0.87 +/- 0.28 Pass SO-5704,5705 10/25/2017 Ac-228 0.33 +/- 0.05 0.31 +/- 0.07 0.32 +/- 0.04 Pass SO-5704,5705 10/25/2017 Gr. Beta 18.34 +/- 1.80 16.50 +/- 1.03 17.42 +/- 1.04 Pass AP-5732,5733 10/26/2017 Be-7 0.139 +/- 0.064 0.175 +/- 0.075 0.157 +/-0.049 Pass AS-4
TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SW-5753,5754 10/31/2017 H-3 220 +/- 83 279 +/- 86 249 +/- 60 Pass. SWU-5816,5817 10/31/2017 Gr. Beta 1.51 +/- 1.00 2.02 +/- 1.02 1.76 +/- 0.71 Pass AP-103117 10/31/2017 Gr. Beta 0.015 +/- 0.004 0.014 +/- 0.004 0.015 +/- 0.003 Pass SO-5923,5924 11/1/2017 Cs-137 0.30 +/- 0.04 0.31 +/- 0.04 0.31 +/- 0.03 Pass SO-5923,5924 11/1/2017 K-40 10.52 +/- 0.61 10.56 +/- 0.67 10.54 +/- 0.45 Pass AP-5858,5859 11/2/2017 Be-7 0.145 +/- 0.075 0.146 +/- 0.084 0.145 +/- 0.056 Pass AP-110717 11/7/2017 Be-7 0.026 +/- 0.004 0.030 +/- 0.004 0.028 +/- 0.003 Pass WW-6032,6033 11/7/2017 H-3 204 +/- 86 298 +/- 80 251 +/- 59 Pass WW-6074,6075 11/8/2017 H-3 72,247 +/- 786 73,062 +/- 791 72,655 +/- 558 Pass BS-6053,6054 11/13/2017 K-40 7.99 +/- 0.62 9.20 +/- 0.68 8.60 +/- 0.46 Pass BS-6053,6054 11/13/2017 Cs-137 0.07 +/- 0.03 0.08 +/- 0.03 0.07 +/- 0.02 Pass DW-80211,80212 11/14/2017 Gr. Alpha 2.30 +/- 0.80 3.60 +/- 1.00 2.95 +/- 0.64 Pass DW-80211,80212 11/14/2017 Gr. Beta 9.32 +/- 0.81 8.99 +/- 0.81 9.16 +/- 0.57 Pass DW-80214,80215 11/14/2017 Ra-226 1.36 +/- 0.22 1.35 +/- 0.15 1.355 +/- 0.13 Pass DW-80214,80215 11/14/2017 Ra-228 1.41+/-0.51 0.90 +/- 0.45 1.16 +/- 0.34 Pass WW-6152,6153 11/15/2017 H-3 416 +/- 94 328 +/- 90 372 +/- 65 Pass SWU-6219,6220 11/28/2017 Gr. Beta 1.04 +/- 0.54 1.75 +/- 0.58 1.39 +/- 0.39 Pass SS-6242,6243 11/29/2017 K-40 24.17 +/- 1.05 22.31 +/-1.03 23.24 +/- 0.74 Pass SS-6242,6243 11/29/2017 Cs-137 0.11 +/- 0.03 0.08 +/- 0.03 0.10 +/- 0.02 Pass SG-6938,6939 11/28/2017 Pb-214 15.28 +/- 0.34 14.96 +/- 0.43 15.12 +/-0.27 Pass SG-6938,6939 11/28/2017 Ac-228 18.99 +/- 0.59 19.92 +/- 0.79 19.46 +/- 0.49 Pass AP-112817 11/28/2017 Gr. Beta 0.026 +/- 0.004 0.030 +/- 0.004 0,028 +/- 0.003 Pass SQ-6286,6287 12/1/2017 Gr. Alpha 70.6 +/- 6.2 60.9 +/- 6.0 65.8 +/- 4.3 Pass SQ-6286,6287 12/1/2017 Gr. Beta 48.9 +/- 2.7 53.7 +/- 2.8 51.3 +/- 1.9 Pass SQ-6286,6287 12/1/2017 Ra-226 11.3 +/- 0.4 10.7 +/- 0.5 11.0 +/- 0.3 Pass SQ-6286,6287 12/1/2017 Ra-228 13.5 +/- 0.9 13.2 +/- 1.0 13.4 +/- 0.7 Pass SG-6286,6287 12/1/2017 K-40 5.10 +/- 1.82 6.65 +/- 1.53 5.88 +/- 1.19 Pass AP-120417 12/4/2017 Gr. Beta 0.037 +/- 0.006 0.035 +/- 0.005 0.036 +/- 0.004 Pass WW-6548,6549 12/19/2017 H-3 8,428 +/- 280 8,604 +/- 282 8,516 +/- 199 Pass AP-122717 12/27/2017 Gr. Beta 0.047 +/- 0.004 0.043 +/- 0.004 0.045 +/- 0.003 Pass XAP-6762,6763 12/31/2017 Co-60 2.43 +/- 1.30 2.24 +/- 0.82 2.34 +/- 0.77 Pass XAP-6762,6763 12/31/2017 Cs-137 4.21 +/- 1.11 4.05 +/- 0.96 4.14+/-0.73 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
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 MASO-903 2/1/2017 Am-241 60.9 +/- 6.9 67.0 46.9 - 87.1 Pass MASO-903 2/1/2017 Cs-134 1360 +/- 14 1550 1085 -2015 Pass MASO-903 2/1/2017 Cs-137 678 +/- 13 611 428 - 794 Pass MASO-903 2/1/2017 Co-57 1.63 +/- 1.69 0.00 NA C Pass MASO-903 2/1/2017 Co-60 909 +/- 12 891 624 - 1158 Pass MASO-903 2/1/2017 Mn-54 1052 +/- 17 967 677 - 1257 Pass MASO-903 2/1/2017 K-40 657 +/- 68 607 425 - 789 Pass MASO-903 2/1/2017 Zn-65 -0.52 +/- 7.40 0.00 NA C Pass MASO-903 2/1/2017 Ni-63 3.25 +/- 7.17 0.00 NA C Pass 0 MASO-903 2/1/2017 Pu-238 0.46 +/- 0.69 0.41 NA Pass MASO-903 2/1/2017 Pu-239/240 56.8 +/- 5.9 59.8 41.9 - 77.7 Pass MASO-903 2/1/2017 Sr-90 501 +/- 17 624 437 -811 Pass MASO-903 2/1/2017 Tc-99 748 +/- 16 656 459 - 853 Pass MAW-849 2/1/2017 1-129 -0.05 +/-0.12 0.00 NA C Pass MAVE-905 2/1/2017 Cs-134 6.61 +/- 0.16 6.95 4.87 - 9.04 Pass MAVE-905 2/1/2017 Cs-137 4.97 +/- 0.18 4.60 3.22 - 5.98 Pass MAVE-905 2/1/2017 Co-57 -0.01 +/- 0.03 0.00 NA C Pass MAVE-905 2/1/2017 Co-60 9.51 +/-0.17 8.75 6.13-11.38 Pass MAVE-905 2/1/2017 Mn-54 3.67 +/- 0.17 3.28 2.30 -4.26 Pass MAVE-905 2/1/2017 Zn-65 6.12 +/- 0.44 5.39 3.77 - 7.01 Pass MAW-847 2/1/2017 Am-241 0.679 +/- 0.079 0.846 0.592 - 1.100 Pass MAW-847 2/1/2017 Cs-134 0.03 +/- 0.10 0.00 NA C Pass MAW-847 2/1/2017 Cs-137 12.7 +/- 0.4 11.1 7.8 - 14.4 Pass MAW-847d 2/1/2017 Co-57 2.7 +/- 0.3 28.5 20.0 - 37.1 Fail MAW-847 2/1/2017 Co-60 13.5 +/- 0.3 12.3 8.6 - 16.0 Pass MAW-847 2/1/2017 Mn-54 16.5 +/- 0.4 14.9 10.4 - 19.4 Pass MAW-847 2/1/2017 K-40 287 +/-6 254 178 - 330 Pass MAW-847 2/1/2017 Zn-65 -0.15 +/- 0.23 0.00 NA C Pass MAW-847 2/1/2017 H-3 275 +/- 10 249 174 - 324 Pass 0 MAW-847 2/1/2017 Fe-55 2.4 +/- 13.6 1.7 NA Pass MAW-847 2/1/2017 Ni-63 10.1 +/- 2.8 12.2 8.5 - 15.9 Pass MAW-847 2/1/2017 Pu-238 0.729 +/- 0.097 0.703 0.492 - 0.914 Pass MAW-847 2/1/2017 Pu-239/240 0.866 +/-0.102 0.934 0.654 -1.214 Pass MAW-847 2/1/2017 Ra-226 0.506 +/- 0.053 0.504 0.353 - 0.655 Pass MAW-847 2/1/2017 Sr-90 10.0 +/- 0.8 10.1 7.1 -13.1 Pass A6-1
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 MAW-847 2/1/2017 Tc-99 4.77 +/- 0.62 6.25 4.38 - 8.13 Pass MAW-847 2/1/2017 U-234/233 1.19 +/- 0.10 1.16 0.81 - 1.51 Pass MAW-847 2/1/2017 U-238 1.15 +/- 0.10 1.20 0.84 -1.56 Pass MAAP-90i 2/1/2017 Am-241 0.0540 +/- 0.0140 0.0376 0.0263 - 0.0489 Fail MAAP-907 2/1/2017 Cs-134 1.31 +/- 0.06 1.42 0.99 -1.85 Pass MAAP-907 2/1/2017 Cs-137 0.797 +/- 0.080 0.685 0.480 - 0.891 Pass MAAP-907 2/1/2017 Co-57 1.86 +/- 0.06 1.70 1.19 -2.21 Pass MAAP-907 2/1/2017 Co-60 0.86 +/- 0.05 0.78 0.55 - 1.01 Pass MAAP-907 2/1/2017 Mn-54 0.01 +/- 0.03 0.00 NA C Pass MAAP-907 2/1/2017 Zn-65 1.62 +/- 0.13 1.29 0.90 -1.68 Pass MAAP-907 2/1/2017 Pu-238 0.0530 +/- 0.0190 0.0598 0.0419 - 0.0777 Pass MAAP-907 2/1/2017 Pu-239/240 0.0490 +/- 0.0160 0.0460 0.0322 - 0.0598 Pass MAAP-907 2/1/2017 Sr-90 0.648 +/- 0.120 0.651 0.456 - 0.846 Pass MAAP-907 2/1/2017 U-234/233 0.086 +/- 0.024 0.104 0.073 - 0.135 Pass MAAP-907 2/1/2017 U-238 0.097 +/- 0.024 0.107 0.075 - 0.139 Pass MASO-4515 8/1/2017 Am-241 45.9 +/- 7.0 58.8 41.2 - 76.4 Pass 9 MASO-4515 8/1/2017 Cs-134 409 +/- 7 448 314 - 582 Pass 9 MASO-4515 8/1/2017 Cs-137 798 +/- 12 722 505 - 939 Pass 9 MASO-4515 8/1/2017 Co-57 1572 +/- 10 1458 1021 -1895 Pass 9 MASO-4515 8/1/2017 Co-60 0.2 +/- 1.4 0.00 NAC Pass 9 MASO-4515 8/1/2017 Mn-54 934 +/- 13 825 578 - 1073 Pass 9 MASO-4515 8/1/2017 K-40 704 +/- 53 592 414 - 770 Pass 9 MASO-4515 8/1/2017 Zn-65 667 +/- 17 559 391 - 727 Pass 9 MASO-4515 8/1/2017 Pu-238 101 +/- 9 92 64 - 120 Pass 9 MASO-4515 8/1/2017 Pu-239/240 74.8 +/- 7.7 68.8 48.2 - 89.4 Pass 9 MASO-4515 8/1/2017 Sr-90 252 +/-7 289 202 - 376 Pass 9 MAW-4494 8/1/2017 1-129 2.31 +/- 0.10 2.31 1.62 - 3.00 Pass MAVE-4517 8/1/2017 Cs-134 2.40 +/- 0.10 2.32 1.62 - 3.02 Pass MAVE-4517 8/1/2017 Cs-137 -0.002 +/- 0.048 0.000 NA C Pass MAVE-4517 8/1/2017 Co-57 3.3 +/- 0.1 2.8 2.0 - 3.6 Pass MAVE-4517 8/1/2017 Co-60 2.10 +/-0.10 2.07 1.45 - 2.69 Pass MAVE-4517 8/1/2017 Mn-54 3.00 +/- 0.20 2.62 1.83 - 3.41 Pass MAVE-4517 8/1/2017 Zn-65 5.90 +/- 0.30 5.37 3.76 - 6.98 Pass A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). 8 Concentration Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-4513 8/1/2017 Am-241 0.820 +/- 0.220 0.892 0.624 -1.160 Pass MAW-4513 8/1/2017 Cs-134 10.3 +/- 0.3 11.5 8.1 -15.0 Pass MAW-4513 8/1/2017 Cs-137 17.2 +/- 0.5 16.3 11.4-21.2 Pass MAW-4513 8/1/2017 Co-57 12.7 +/- 0.4 12.1 8.5-15.7 Pass MAW-4513 8/1/2017 Co-60 10.6 +/- 0.3 10.7 7.5 -13.9 Pass MAW-4513 8/1/2017 Mn-54 15.6 +/- 0.4 14.9 10.4-19.4 Pass MAW-4513 8/1/2017 Zn-65 15.9 +/- 0.7 15.5 10.9 - 20.2 Pass MAW-4513 8/1/2017 H-3 255 +/- 9 258 181 - 335 Pass MAW-4513 8/1/2017 Fe-55 21.6 +/- 6.6 19.4 13.6 - 25.2 Pass MAW-4513 8/1/2017 Ni-63 -0.1 +/-2.0 0.0 NA C Pass MAW-4513 8/1/2017 Pu-238 0.590 +/- 0.080 0.603 0.422 - 0.784 Pass MAW-4513 8/1/2017 Pu-239/240 0.740 +/- 0.090 0.781 0.547 -1.015 Pass MAW-4513 8/1/2017 Ra-226 1.000 +/- 0.100 0.858 0.601 -1.115 Pass MAW-4513 8/1/2017 Sr-90 7.80 +/- 0.60 7.77 5.44 - 10.10 Pass MAW-4513 8/1/2017 Tc-99 6.70 +/- 0.40 6.73 4.71 - 8.75 Pass MAW-4513 8/1/2017 U-2344/233 0.94 +/- 0.06 1.01 0.71-1.31 Pass MAW-4513 8/1/2017 U-238 0.97 +/- 0.07 1.04 0.73 - 1.35 Pass MAAP-4519h 8/1/2017 Am-241 0.0400 +/- 0.0100 0.0612 0.0428 - 0.0796 Fail MAAP-4519 8/1/2017 Cs-134 0.90 +/- 0.10 1.00 0.70 -1.30 Pass MAAP-4519 8/1/2017 Cs-137 0.90 +/- 0.10 0.82 0.57 -1.07 Pass MAAP-4519 8/1/2017 Co-57 0.01 +/- 0.01 0.00 NA C Pass MAAP-4519 8/1/2017 Co-60 0.70 +/- 0.10 0.68 0.48 - 0.88 Pass MAAP-4519 8/1/2017 Mn-54 1.50 +/- 0.10 1.30 0.91 - 1.69 Pass MAAP-4519 8/1/2017 Zn-65 1.30 +/- 0.10 1.08 0.76 - 1.40 Pass MAAP-4519 8/1/2017 Pu-238 0.0300 +/- 0.0100 0.0298 0.0209 - 0.0387 Pass MAAP-4519 8/1/2017 Pu-239/240 0.0400 +/- 0.0200 0.0468 0.0328 - 0.0608 Pass MAAP-4519 8/1/2017 Sr-90 0.800 +/- 0.100 0.801 0.561 - 1.041 Pass MAAP-4519 8/1/2017 U-234/233 0.070 +/- 0.010 0.084 0.059 - 0.109 Pass MAAP-4519 8/1/2017 U-238 0.090 +/- 0.010 0.087 0.061 - 0.113 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation). b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation). c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits. ct Decimal point was misplaced while performing a unit conversion. The result is within control limits when the proper unit conversion is performed.
- Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.
1 Sample was reanalyzed in duplicate with acceptable results. Original plating was inferior to platings obtained during reanalysis. It is believed that isotopic tracer was not accurately quantified due to poor resolution of its peak. 9 Data were erroneously submitted in units of Bq/g. All results pass MAPEP criteria when evaluated in units of Bq/Kg. h Laboratory is not currently offering analysis for Am-241 in Air Particulate samples. A6-3
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 c Acceptance ERAP-1112 3/20/2017 Am-241 55.3 +/- 2.8 76.4 47.1 -103.0 Pass ERAP-1112 3/20/2017 Co-60 1,230 +/- 8 1030 797 - 1290 Pass ERAP-1112 3/20/2017 Cs-134 1,110 +/- 9 1100 700 - 1360 Pass ERAP-1112 3/20/2017 Cs-137 1,810 +/- 12 1,390 1,040 - 1,830 Pass ERAP-1112 d 3/20/2017 Fe-55 590 +/- 385 256 79.4 - 500 Fail ERAP-1112 3/20/2017 Mn-54 < 5.14 < 50.0 0.00 - 50.0 Pass ERAP-1112 3/20/2017 Pu-238 54.6 +/- 2.8 54.3 37.2 - 71.4 Pass ERAP-1112 3/20/2017 Pu-239/240 63.6 +/- 3.0 62.0 44.9 - 81.0 Pass ERAP-1112 3/20/2017 Sr-90 55.3 +/- 8.3 52.4 25.6 - 78.5 Pass ERAP-1112 3/20/2017 U-233/234 65.7 +/- 3.0 73.1 45.3 - 110 Pass ERAP-1112 3/20/2017 U-238 67.3 +/- 3.0 72.4 46.8 - 100 Pass ERAP-1112 3/20/2017 Zn-65 1,355 +/- 16 984 705 - 1,360 Pass ERAP-1114 3/20/2017 Gr. Alpha 106 +/- 5 85.5 28.6 - 133 Pass ERAP-1114
- 3/20/2017 Gr. Beta 67.6 +/- 3.0 45.2 28.6 - 65.9 Fail ERSO-1116 3/20/2017 Am-241 418 +/- 98 448 262 - 582 Pass ERSO-1116 3/20/2017 Ac-228 1,540 +/- 260 1,240 795 -1,720 Pass ERSO-1116 3/20/2017 Bi-212 1,550 +/- 90 1,240 330 - 1,820 Pass ERSO-1116 3/20/2017 Bi-214 2,560 +/- 20 2,750 1,660 - 3,960 Pass ERSO-1116 3/20/2017 Co-60 4,620 +/- 100 4,430 3,000 - 6,100 Pass ERSO-1116 3/20/2017 Cs-134 8,340 +/- 100 8,860 5,790 - 10,600 Pass ERSO-1116 3/20/2017 Cs-137 8,420 +/- 100 7,500 5,750 - 9,650 Pass ERSO-1116 3/20/2017 K-40 13,600 +/- 900 10,600 7,740 - 14,200 Pass ERSO-1116 3/20/2017 Mn-54 < 68.1 < 1000 0.00 - 1,000 Pass ERSO-1116 3/20/2017 Pb-212 1,060 +/- 70 1,240 812 - 1,730 Pass ERSO-1116 3/20/2017 Pb-214 2,620 +/- 160 2,890 1,690 -4,310 Pass ERSO-1116 3/20/2017 Pu-238 424 +/- 154 648 390 - 894 Pass ERSO-1116 1 3/20/2017 Pu-239/240 252 +/- 112 484 316 - 669 Fail ERSO-1116 9 3/20/2017 Pu-239/240 436 +/- 106 484 316 - 669 Pass ERSO-1116 3/20/2017 Sr-90 7,930 +/- 250 9,150 3,490 - 14,500 Pass ERSO-1116 3/20/2017 Th-234 1,820 +/- 200 1,940 614 - 3,650 Pass ERSO-1116 h 3/20/2017 U-233/234 1,030 +/- 130 1,950 1,190 -2,500 Fail 1
ERSO-1116 3/20/2017 U-233/234 1,820 +/- 200 1,950 1,190 -2,500 Pass ERSO-1116 3/20/2017 U-238 1,240 +/- 140 1,940 1,200 - 2,460 Pass 1 ERSO-1116 3/20/2017 U-238 1,930 +/- 200 1,940 1,200 - 2,460 Pass ERSO-1116 3/20/2017 Zn-65 7,190 +/- 240 6,090 4,850 - 8,090 Pass ERW-1122 3/20/2017 Gr. Alpha 65.3 +/- 2.4 89.5 31.8-139 Pass ERW-1122 3/20/2017 Gr. Beta 54.8 +/- 1.5 61.0 34.9 - 90.4 Pass ERW-1124 3/20/2017 H-3 19,000 +/- 410 19,400 13,000 - 27,700 Pass A7-1
TABLE A-7. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)*. MRAD Study Concentration
- Lab Code b Date Analysis Laboratory ERA Control Result Result Limits c Acceptance ERVE-1118 3/20/2017 Am-241 1,560 +/- 140 1,860 1,140 - 2,470 Pass ERVE-1118 3/20/2017 Cm-244 530 +/- 80 734 360 - 1,140 Pass ERVE-1118 3/20/2017 Co-60 1,400 +/- 350 1,390 959 -1,940 Pass ERVE-1118 3/20/2017 Cs-134 1,650 +/- 460 1,830 1,180 -2,380 Pass ERVE-1118 3/20/2017 Cs-137 2,580 +/- 540 2,500 1,810 - 3,480 Pass ERVE-1118 3/20/2017 K-40 32,100 +/- 700 30,900 22,300 - 43,400 Pass ERVE-1118 3/20/2017 Mn-54 < 27.3 < 300 0.00 - 300 Pass ERVE-1118 3/20/2017 Zn-65 889 +/- 64 853 615 -1,200 Pass ERVE-1118 3/20/2017 Pu-238 3,250 +/- 210 3,250 1,940 - 4,450 Pass ERVE-1118 3/20/2017 Pu-239/240 2,180 +/- 170 2,150 1,320 - 2,960 Pass ERVE-1118 3/20/2017 Sr-90 665 +/- 135 726 414 - 963 Pass ERVE-1118 3/20/2017 U-233/234 2,840 +/- 200 3,090 2,030 - 3,970 Pass ERVE-1118 3/20/2017 U-238 2,990 +/- 200 3,060 2,040 - 3,890 Pass ERW-1120 3/20/2017 Am-241 108 +/- 7 140 94.3 - 188 Pass ERW-1120 3/20/2017 Co-60 2,600 +/- 198 2,540 2,210 - 2,970 Pass ERW-1120 3/20/2017 Cs-134 2,380 +/- 250 2,510 1,840 - 2880 Pass ERW-1120 3/20/2017 Cs-137 1,470 +/- 243 1,400 1,190 -1,680 Pass ERW-1120 3/20/2017 Mn-54 < 12.3 < 100 0.00 -100 Pass ERW-1120 3/20/2017 Pu-238 117 +/- 4 128 94.7 -159 Pass ERW-1120 3/20/2017 Pu-239/240 74.8 +/- 3.3 85.8 66.6 -108 Pass ERW-1120 3/20/2017 U-233/234 75.3 +/- 3.2 90.3 67.8 -116 Pass ERW-1120 3/20/2017 U-238 76.4 +/- 3.2 89.5 68.2 - 110 Pass ERW-1120 3/20/2017 Zn-65 2,130 +/- 378 1,960 1630 - 2,470 Pass ERW-1120J 3/20/2017 Fe-55 1,400 +/- 403 984 587 - 1,340 Fail ERW-1120k 3/20/2017 Fe-55 1,081 +/- 383 984 587 - 1,340 Pass ERW-1120 3/20/2017 Sr-90 652 +/- 12 714 465 - 944 Pass
- Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, seiving 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). 0 Results are presented as the known values, expected laboratory precision (2 sigma, 1 determin<'ltion) and control limits as provided by ERA. d Fe-55 analysis result was outside the acceptable ranQe. RecountinQ the sample disk for 1000 minutes resulted in 254 +/- 364 with an LLD calculation of< 342. Insufficient sample was available after performing other required analyses on the sample to quantify the activity with an uncertainty less than the activity.
- ERA appears to have applied the standard material to the filter in a pattern closer to the center of the filter compared to previous studies and different from the filter efficiency utilized by the laboratory. This likely caused the efficency used the calculation to be understated and the result obtained by the laboratory to be overstated. For comparison the in-house spike for gross beta in AP (table A-3 SPAP-740 2/28/17) was acceptable with a ratio of 0.94 of lab result to known.
r Analysis result for Plutonium-239/240 was below the lower limit of acceptance. 9 Samples were reanalyzed in duplicate with acceptable results for each. Original analysis had poor resolution possibly due to a poor elctroplating and is suspected in contributing to poor results. h Analysis result for U-233/234 was below the lower limit of acceptance. 1 The reanalysis result for U-233/234 was within the acceptance limits and U-238 reanalysis result was closer to the known value. Original analysis had poor resolution possibly due to a poor electroplating and is suspected in contributing to poor results. 1 Fe-55 analysis result was outside acceptable range. k Result of recounting was acceptable. Using available aliquot after dividing sample for other analyses leaves insufficient sample to reliably determine the activity present in sample. 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; x 1 +/- s 1 and x2 +/- s2 Reported result: x +/- s; where x = (1/2) (x1 + x2 ) ands= (1/2) .Js~ + s; 3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of L 1 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-- -
. \/ ~
~
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 a background in unrestricted areas . 3 Air (pCi/m ) Water (pCi/L) Gross alpha 1 X 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 lodine-131 2.8 X 10 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 C Potassium-40 4,000 Gross alpha 2 Gross beta 10 6 Tritium 1 X 10 a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes. Concentrations may be averaged over a period not greater than one year. b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway. C A natural radionuclide. C-1
APPENDIX D Sample Collection and Analysis Program
D-1 TLO LOCATIONS ONE MILE RADIUS PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS] (NO SCALE} MONITORING LEGEND: 0 PRAIRIE ISLAND TLD POINTS D-2
TLO LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ~~~==r::r-------,r---**~ ~ l LOCATIONS MONITORJNG LEGEND: 0 PRAIRIE ISLAND TLO POINTS D-3
TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND: 0 PRAIRIE ISLAND TLD POINTS D-4
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS] [NO SCALE] MONITORING LEGEND
~
FISH SAMPLING POINT ID NUMBERS ~ AJR SAMPLING POfNT ID NUMBERS P-1.-P-2, P*3, P 4, P*S,P-7 0 P*\3, P*l'l 0 \./ATER SAMPLING PO!NT to NUMBERS
?*5, M,, P*8, P-9, P*ll, P-24, P*43
$ INVERTEBRATES POINT ID NUMBERS P*6, P-40 0 VEGETAllON I VEGETABLES ID NUMBERS P-28. P-38. P*45
@ SEOIME:N! SAMPL!NO POINT IO NUMBERS P*G, P*l2, P-20 D-5
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND AIR SAMPLING POINT ID NUMBl:RS PO[NT & P-l, P-2, P-3, P-4. P--6, P*7 FISH SAMPLING P*l3, P*l'l ID NUMBERS WAT(R SAMPLING POINT 10 NUM9tRS INVERTEBRA1'ES POINT ID NUMBERS 0 P-5, P*S, P-8, P*"l, P-11, P-24, P-43 P*S,P-40 VEGETATION I VEGETABLES 10 NUMBERS SEDIMENT SAMPLING POINT 10 NUMBERS G P*28,P*38,P*45 P-6, P-12, P-20 D-6
ENVIRONMENTAL SAMPLING POINTS
----\_
0 P-43, Peterson Farm, W10322 St Rd 29, River Falls, WI El P-38, Caln Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND AIR SAMPLING POINT ID NUMBERS 11 P*1, P-2, P-3, P-4, P-6,P-7 WATER SAMPLING POINT ID NUMBERS 0 P-5, P-6, P-8, P-$, P-11, P-43 0 VEGETATION/ VEGETABLES ID NUMBERS P-28, P-38, P-46 D-7
APPENDIX E Special Well and Surface Water Samples E-1
1.0 INTRODUCTION
This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2017. 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 2017 are summarized and discussed. Program findings for 2017 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 well MW-8, 05 tank vault, S-7 surface water, and the septic system. The 2017 sample results (except for MW-8, 05 tank vault, S-7 surface water, and the septic system) ranged from <19 pCi/L to 193 pCi/L. Sample well MW-8 ranged from 143 pCi/L to 523 pCi/L. 05 tank vault was 1176 pCi/L. S-7 surface water ranged from 23 pCi/L to 315 pCi/L. The septic system sample ranged from 49 pCi/L to 1490 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 locations, 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 2017 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 and were sent to Environmental Incorporated for analysis for hard-to-detect nuclides in accordance with American Nuclear Insurers recommendation
- samples were taken from the 05 Fuel Oil Storage Tank vault because the area was accessible in 2017 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-8 ground water sample well. Table E-4.4 provides the complete data table of results for each period and sampling location. The tritium level annual averages have shown a downward trend since the special sampling began in 1989. Except for sample well MW-8, 05 tank vault, S-7 surface water, and the septic system, the 2017 sample results are within the range of expected background tritium levels in shallow ground water and surface water due to tritium concentrations measured in precipitation. Sampling points in North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No. 10; World Survey of Isotope Concentration in Precipitation ( 1988-1991)). The higher level results at the Suter residence and Birch Lake in 1989 were possibly due to seepage from the PINGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River and the discharge canal. The Suter residence is located between the discharge canal and Birch Lake, which connects to the Vermillion River. The PINGP discharge canal piping was lengthened during 1991, so that liquid discharges from the plant are released near the end of the discharge canal, diffused and discharged to the Mississippi River. In 1992, the underground liquid discharge pipe from the plant to the discharge canal piping was replaced with a double walled leak detectable piping system. This year's sample results continue to indicate that these modifications have eliminated the suspected radioactive effluent flow into the local ground water. The elevated tritium levels in sample well MW-8 in 2017 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 05 tank vault and S-7 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, 2017. 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, PIIC-22, PIIC-26, PIIC-28, PIIC-29, P-7, Well water P-11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, Annual 26 MW-6, P-26, P-30, SW-3, SW-4, GIA H-3 SW-5, SW-6, SW-7, SW-8, SW-9, P-9 Well water quarterly 1 P-24O GIQ H-3 Well water P-2, P-3, P-5, P-6, 7 GIQ' H-3 quarterly' PZ-8, MW-4, MW-5 P-43(C), SW-1 (C), Well water monthly 5 GIM H-3 MW-7, MW-8, P-10 S-1, S-2, S-3, S-4, S-5, Surface water GIAd H-3 8 S-6, S-7, P-31 11 CST, 21 CST, 22 CST, Storage Tank 7 U112 Demin Hdr, 0516 vaults GIS H-3 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, 2017. Code Collection site Type of Distance and sample a direction from reactor P-8 Pl Community well post treat ow 1.0 mi. @321°/WNW P-8 Pl Community well pre treat ow 1.0 mi.@ 321°/WNW REMP P-6 Lock & Dam #3 well ow 1.6 mi.@ 129°/SE REMP P-11 Red Wino Service Center ow 3.3 mi@ 158°/SSE PIIC-22 1773 Buffalo Slouqh Rd ow 1 mi.@ 315°/NW PIIC-26 1771 Buffalo Slough Rd ow 1 mi.@ 315°/NW PIIC-28 1960 Larson Lane ow 1.5 mi @288°/WNW PIIC-29 Buffalo Project ow 4.3 mi @ 302°/WNW P-24D Suter residence ow 0.6 mi.@ 158°/SSE P-43 Peterson Farm (Control) ow 13.9 mi.@ 355°/N SW-1 Hanson Farm (Control) ow 2.2 mi.@ 315°/NW P-2 Sample well WW See map P-3 Sample well WW See map P-5 Sample well WW See map P-6 Sample well WW See map P-7 Sample well WW See map P-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. @, 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, 2017 (continued). Code Collection site Type of Distance and sample a direction from reactor SW-3 Coolinq Tower pump WW See map SW-4 New Admin Bldq DW 0.05 mi.@ 315°/NW SW-5 Plant Screenhouse well WW 0.05 mi. @ 0°/N SW-6 Site Adm in BuildinQ well DW 0.2 mi@ 31Q°/NW SW-7 Distribution Center DW 0.35 mi @271°/'N SW-8 SGR Buildinq WW 0.2 mi@ 31Q°/NW SW-9 FLEX Buildinq WW 0.2 mi @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 Coolinq 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 @ 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 Seepaqe SW 0.69 mi.@ 172°/S 11 CST Storage Tank ST Turbine Building 21 CST StoraQe Tank ST Turbine Building 22 CST Storage Tank ST Turbine Buildinq Unit 1/2 demin hdr Storaqe Tank ST Turbine Buildinq Septic Svstem Storaqe Tank ST Outside #1 Warehouse D5/6 Vault Concrete Vault ST Outside Turbine Bldg 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, 2017 (County, State) Indicator Location with Highest Control Locations Annual Mean Locations 0 0 Sample Type and Mean (F) Locationd Mean (F) Mean (F) 0 Number 0 0 0 Type Number of LLD b Range Range Range Non-(Units) Analyses a Routine Results* Offsite Well H-3 13 19 34 (5/13) P-24D 36 (4/5) (See Control 0 Water (26-44) (29-44) Below) (pCi/L) Onsite H-3 75 19 129 (63/75) MW-8 352 (12/12) (See Control 8 Well Water (20-523) (143-523) Below) (pCi/L) Onsite H-3 16 19 55 (15/16) S-7 131 (3/3) (See Control Surface Water (19-315) (23-315) Below) 0 (pCi/L) Onsite D-5 Fuel Oil H-3 23 19 202 (22/23) 1176(1/1) (See Control Storage Tank Storage Tank (20-1490) (1176) Below) 3 (pCi/L) Vault Control (offsite H-3 24 19 none P-43 34 (6/12) 33 (8/24) well water) 0 (26-42) (26-42) Control (offsite H-3 1 19 none P-43 (0/1) (0/1) snow) 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, 2017. SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 CODE SAMPLE LOCATIONS oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L oCi/L pCi/L pCi/L pCi/L pCi/L pCi/L OFFSITE WELLS
<19 P-8 Post-treat Pl Comm. Well
<19 P-8 Pre-treat Pl Comm. Well
<19 REMP P-6 Lock & Dam #3 well Red Wing Service <19 REMP P-11 Center
<19 PIIC-22 1773 Buffalo Slough Rd 26 PIIC-26 1771 Buffalo Slouqh Rd
<19 PIIC-28 1960 Larson Lane
<19 PIIC-29 Buffalo Project 44 29 32 37 <19 P-24D Suter residence
<19/
<19* 27 42 39 <19 32 <19 35 <19 <19 <19 26 P-43 Peterson Farm(Control *snow
<19 28 <19 <19 <19 <19 <19 <19 <19 <19 36 <19 SW-1 Hanson Farm (Control)
E-9
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT *Nov DEC 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 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 22 50 53 P-3 Sample well <19 24 <19 P-5 Sample well 99 56 48 P-6 Sample well <19 34 59 P-7 Sample well 106 P-10 Sample well 97 120 144 124 119 101 132 85 90 193 150 179 P-11 Sample well 102 PZ-1 Sample well 20 PZ-2 Sample well 59 PZ-4 Sample well <19 PZ-5 Sample well <19 PZ-7 Sample well 55 PZ-8 Sample well 21 <19 64 MW-4 Sample well 26 29 60 MW-5 Sample well <19 31 39 MW-6 Sample well 52 MW-7 Sample well 76 76 113 87 69 80 101 88 86 96 77 106 MW-8 Sample well 419 523 317 396 266 143 420 408 366 194 398 378 P-26 PITCwell 30 P-30 Env. lab well <19 SW-3 CT pump 33 P-9 Plant well #2 38 SW-4 NewAdmin 24 SW-5 Pint Scrnhs 62 SW-6 RSG Bldq <19 SW-7 Dist Center <19 E-10
SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 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 SW-8 Site Admin Bldq <19 SW-9 FLEX Bldq <19 E-11
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2017 (continued). SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 CODE SAMPLE LOCATIONS pCi/L oCi/L oCi/L oCi/L oCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE SURFACE WATER 26 S-1 Mississiooi River uostream S-2 Recirculation/Intake canal 23 S-3 Cooling water canal 20 S-4 Discharge Canal (end) 40 S-5 Discharge Canal (midway) 32 S-6 Stormwater runoff 76* 19 37 S-7 Parking Lot runoff 54* 23 315 S-8 P-1 O area snow 21* S-9 MW-7/8 area snow 53* P-31 Birch Lake Seepage 66 24 <19
- snow samples E-12
Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2017 (continued). SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 2017 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L oCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L oCi/L ONSITE STORAGE TANKS 11 CST Storage tank 66 20 21 CST Storage tank 45 <19 22CST Storage tank 36 22 U1/U2 Demin Storage tank 41/66 38/61 Header Septic Storage tank 81 118 49 108 81 134 96 87 172 1490 409 53 System D5/6 Fuel Oil Storage Tank 1176/ D5/6 Vaults NA E-13
Table E-4.5. Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on five samples. Location S-8 P-43 S-9 S-6 S-7 Collection Date 01-17-17 01-11-17 01-17-17 01-11-17 01-11-17 Lab Code PXW-258 PXW-259 PXW-260 PXW-261 PXW-262 Isotope Concentration (µCi/ml) Fe-55 < 6.5 E-07 < 6.3 E-07 < 6.2 E-07 < 6.5 E-07 < 6.3 E-07 Ni-63 < 1.3 E-07 < 1.1 E-07 < 1.3 E-07 < 1.2 E-07 < 1.1 E-07 Sr-90 <6.4E-10 < 6.1 E-10 < 6.9 E-10 <5.6E-10 < 7.8 E-10 Pu-238 < 1.9 E-10 < 1.9 E-10 < 1.8 E-10 <2.2E-10 < 2.8 E-10 Pu-239/240 < 2.7 E-10 < 1.9 E-10 < 1.8 E-10 <3.0E-10 < 2.0 E-10 Am-241 <9.0E-11 < 7.9 E-11 < 1.3 E-10 < 5.8 E-11 < 9.9 E-11 Cm-242 <1.6E-10 < 1.4 E-10 < 1.7 E-10 <1.3E-10 < 3.6 E-10 Cm-243/244 < 2.0 E-10 <7.9E-10 < 7.7 E-11 < 5.8 E-11 < 9.9 E-11 Less than (<), value is based on a 4.66 sigma counting error for the background sample. E-14
Table E-4.5. Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on two samples. Location S-6 S-7 Collection Date 05-02-17 05-02-17 Lab Code PXW-2025 PXW-2026 Isotope Concentration (µCi/ml) Fe-55 < 7.7 E-07 < 7.9 E-07 Ni-63 < 1.2 E-07 < 1.0 E-07 Sr-90 <5.2E-10 <5.6E-10 Pu-238 < 7.6 E-11 < 1.1 E-10 Pu-239/240 <1.3E-10 < 6.6 E-11 Am-241 < 4.5 E-11 < 4.4 E-11 Cm-242 < 7.9 E-11 < 1.7 E-10 Cm-243/244 < 4.5 E-11 < 7.6 E-11 Less than (<), value is based on a 4.66 sigma counting error for the background sample. E-15
Table E-4.5. Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on two samples. Location P-10 Well MW-8Well Collection Date 06-02-17 06-02-17 Lab Code PXW-2939 PXW-2940 Isotope Concentration (µCi/ml) Fe-55 < 7.8 E-07 < 7.8 E-07 Ni-63 < 9.0 E-08 < 9.2 E-08 Sr-90 <5.2E-10 < 4.9 E-10 Pu-238 < 3.1 E-10 <4.6E-10 Pu-239/240 <3.1 E-10 < 4.6 E-10 Am-241 < 1.5 E-10 < 8.3 E-11 Cm-242 < 6.2 E-11 < 1.4 E-10 Cm-243/244 < 6.2 E-11 < 5.8 E-11 Less than (<), value is based on a 4.66 sigma counting error for the background sample. E-16
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