NG-20-0038, 2019 Annual Radiological Environmental Operating Report

2019 Annual Radiological Environmental Operating Report

ML20135H088
Person / Time
Site:	Duane Arnold
Issue date:	05/14/2020
From:	Dean Curtland NextEra Energy Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-20-0038
Download: ML20135H088 (140)

Text

May 14, 2020 NG-20-0038 TS 5.6.2 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Renewed Op . License No. DPR-49

Subject:

2019 Annual Radiological Environmental Operating Report Please find as Enclosure 1 to this letter, a copy of NextEra Energy Duane Arnold, LLC's 2019 Annual Radiological Environmental Operating Report for the Duane Arnold Energy Center, pursuant to the requirements of ODAM Section 8.2.2 and Technical Specification Section 5.6.2.

This letter contains no new commitments nor does it revise any existing commitments.

Should you have any questions regarding this matter, please contact Michael Casey at (319) 851-7606 .

Sincerely,

~~J/

Dean Curtland Site Director NextEra Energy Duane Arnold, LLC Enclosure cc: Regional Administrator, USNRC, Region Ill Resident Inspector, USNRC, Duane Arnold Energy Center Project Manager, USNRC, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

Enclosure to NG-20-0038 Duane Arnold Energy Center 2019 Annual Radiological Environmental Operating Report 133 pages follow

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DUANE ARNOLD Fact Sheet Duane Arnold Energy Center SITE ADDRESS 3277 DAEC Road Palo, IA 52324 CORPORATE MEDIA LINE (561) 694-4442 Safety Information General Information Built in a low-risk seismic zone: Duane Designed with multiple safety systems: The Duane Arnold Energy Center (DAEC)

Arnold is in a very seismically stable area The Nuclear Regulatory Commission has is located in Palo, Iowa, approximately of the country. mandated several structural improvements nine miles northwest of Cedar Rapids. It over time, enhancing Duane Arnold's ability is bordered by cornfields of neighboring Constructed to withstand earthquakes to deal with significant events: farms and the banks of the Cedar River.

and tornados: Despite the low risk from seismic events, the plant is designed to >> Fouroffsite power lines power the site's cooling system >>Workforce withstand earthquakes, tornados and other

>> Two on-site diesel generators are available 600 during normal operations; nearly events stronger than ever recorded in to provide back-up emergency power to 1,500 during outage operations the region .

plant safety equipment >>Salaries Protected from flooding: The plant is

>> Multiple steam-driven cooling pumps Approximately $85 million annually elevated 20 feet above river level to protect are available to power cooling systems against flooding . >> Economic impact (do not require external power)

>> During 2008's historic 500-year flood, the Stimulates $255 million in economic

>> Back-up batteries for all critical cooling and Cedar River crested 14 feet below the activity in Iowa, $514 million nationally control room systems are stored on-site plant's design flood level

>> External cooling options (i.e. injection and >> Property taxes paid

>> During this event, DAEC was able to fire pumps) are pre-staged on-site; can use Approximately $3 million annually continue safe and reliable operations river water for cooling Seven-day power supply: Safety and >> Construction permit granted Highly trained plant operators: For one full June 1970 cooling systems can be powered for seven week out of every six weeks, plant operators days without requiring any offsite power or >> Full power operating license must prove their ability to safely operate the additional fuel. February 1974 plant in a variety of worst-case scenarios that include earthquakes, severe storms, flooding, >> Commercial operation loss-of-power and loss of reactor core cooling. February 1975 System Information PRIMARY SYSTEM One General Electric Boiling Water Reactor with Reactor Type a net electrical output of 615 MWe Reactor Core 368 fuel assemblies Reactor Vessel 67' high; 15' wide Reactor Design General Electric Mark 1 SECONDARY SYSTEM For More Information :

Turbine/Generator General Electric nexteraenergyresources.com Mechanical draft type - two towers, 12 cells each, duanearnold .com Cooling Towers makeup water from Cedar River nrc.gov 41825

Al l Environmental, Inc.

• /"\I Midwest Laboratory 700 Landwe hr Road* Northbrook, IL 60062-2310 phone (8-17) 561-0700 , fax (817) 56-1-1117 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA DOCKET NO. 50-331 REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Annual Radiological Environmental Operating Report January 1 to December 31, 2019 Prepared by ATI ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8001 Ashok Banavali, Ph.D ..

Laboratory Manager

PREFACE Staff members of the Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report, with the exception of Appendices D and E which were completed by DAEC personnel. All environmental samples, with the exception of aquatic, were collected by personnel of DAEC. Aquatic samples were collected by the University of Iowa Hygienic Laboratory.

The report was prepared by Environmental, Inc., Midwest Laboratory, with the exception of Appendices D and E, which were prepared by DAEC personnel.

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TABLE OF CONTENTS PARTI No.

PREFACE ..................................................................................................................... ii List of Tables .................................................................................................................v List of Figures ............................................................................................................... vi

1.0 INTRODUCTION

........................................................................................................... 1 2.0

SUMMARY

....................................................................................................................2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............................... 3 3.1 Program Design and Data Interpretation .......................................................... 3 3.2 Program Description ............................................................................................. 4 3.2.1 Environmental Monitoring ....................................................................... .4 3.2.2 Groundwater Protection Program ............................................................ 5 3.3 Program Execution ............................................................................................... 5 3.4 Laboratory Procedures ..................................................................................... 6 3.5 Program Modifications .......................................................................................... 6 4.0 RESULTS AND DISCUSSION ...................................................................................... ?

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ..................................... 7 4.2 Program Findings ................................................................................................. 7 4.3 Groundwater Protection Program Findings ......................................................... 9 5.0 TABLES AND FIGURES ............................................................................................. 11

6.0 REFERENCES

CITED ................................................................................................27 APPENDICES A lnterlaboratoryComparison Program Results .......................................................... A-1 B Data Reporting Conventions ........................................................................................ B-1 C Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas ............................................................................ C-1 D Summary of the Land Use Census ............................................................................ D-1 E Annual Radiation Dose Assessment. ........................................................................ E-1 iii

TABLE OF CONTENTS (continued)

PARTll Data Tabulations and Analyses ...................................................................................... i iv

LIST OF TABLES 5.1 Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic Analyses .................................................................................................................... 12 5.2 Sample Collection and Analysis Program ..................................................................... 13 5.3 Sampling Locations, DAEC .......................................................................................... 15 5.4 Type and Frequency of Collections .............................................................................. 17 5.5 Sample Codes for Tables 5.4 and 5.6 .......................................................................... 18 5.6 ProgramDeviations .......................................................................................................... 19 5.7 Radiological Environmental Monitoring Program Summary ......................................... 21 In addition, the following tables are included in the Appendices:

Appendix A A-0 Attachment A................................................................................................................. A0-2 A-1 Environmental Resource Associates (RAD) ............................................................ A 1-1 A-2 lnterlaboratoryComparison Program Results, Thermoluminescent Dosimeters (TLDs) ......................................................................................A2-1 A-3 In-house Spiked Samples ........................................................................................... A3-1 A-4 ln-house"Blank"Samples ....................................................................................... A4-1 A-5 ln-house"Duplicate"Samples ................................................................................. A5-1 A-6 DepartmentofEnergyMAPEPcomparison results ................................................. A6-1 A-7 Environmental Resource Associates (MRAD) ......................................................... A 7-1 AppendixC C-1 Effluent Concentration Limits for Radioactivity in Air and Water Above Background in UnrestrictedAreas .............................................................. C-2 v

LIST OF FIGURES 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center ......................................................................... 25 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles ......................................................................................................... 26 vi

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Duane Arnold Energy Center, Palo, Iowa, during the period January - December, 2019. 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.

The REMP fulfills the requirements of Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50 for the operation of the plant. The REMP also fulfills the requirements of 10 CFR 72.44(d)(2) for operation of the ISFSI.

Tabulations of individual analyses made during the year are included in Part II of this report.

The Duane Arnold Energy Center (DAEC) is a boiling water reactor, located in Linn County, Iowa, on the Cedar River, and owned and operated by NextEra Energy Resources. Initial criticality was attained on March 23, 1974. The reactor reached 100% power on August 12, 1974. Commercial operation began on February 1, 1975.

2.0

SUMMARY

The Radiological Environmental Monitoring Program, as required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Duane Arnold Energy Center, is herein described.

Results for the year 2019 are summarized and discussed. Information regarding DAEC effluents and the Offsite Dose Assessment Manual (ODAM) can be found in the 2019 Annual Radiological material release Report (ARMRR).

Program findings show only background levels of radioactivity in the environmental samples collected in the vicinity of the Duane Arnold Energy Center.

No effect on the environment is indicated in the areas surrounding the site of the Duane Arnold Energy Center.

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program at the Duane Arnold Energy Center (DAEC) 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; and (4) Industrial and medical radioactive waste.

In interpreting the data, effects due to the DAEC operation 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 DAEC 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 station 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 DAEC site. The DAEC's monitoring program includes analyses for strontium-90 and iodine-131, which are fission products, and tritium, which is produced by cosmic rays, atmospheric nuclear detonations, and also by nuclear power plants. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, and cerium-144. These 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 ten (10) days after reactor shutdown. On the other hand, ten (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). The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the next group, manganese-54, cobalt-58 and-60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of nuclear power plant effluents, but are not produced in significant quantities by nuclear detonations. Nuclides of the final group, beryllium-?,

which is of cosmogenic origin, and potassium-40, a naturally-occurring isotope, were chosen as calibration monitors and provide a comparison between levels of naturally occurring radionuclides and radionuclides that could be attributed to the operation of the plant.

Characteristic properties of isotopes quantified in gamma-spectroscopic analysis are presented in Table 5.1. Other means of distinguishing sources of environmental radiation can be employed in interpreting the data. Current radiation levels can be compared with previous levels, including those measured before the Plant became operational. Results of the DAE C's Monitoring Program 3

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 3.2.1 Environmental Monitoring The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the DAEC is summarized in Table 5.2 and is briefly reviewed below. Table 5.3 defines the sampling location codes used in Table 5.2 and specifies for each location its distance, direction, and sector relative to the reactor site. The types of samples collected at each location and the frequency of collections are presented in Table 5.4 using codes defined in Table 5.5.

To monitor the air environment, a continuous air sampler is employed. Airborne particulates and activated charcoal canisters are mounted on the intake of the air sampler to collect airborne particulates and airborne iodine respectively at ten sampling locations. Nine locations are indicators and one is a control (D-13). Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity. If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic analysis is performed. Quarterly composites of airborne particulates from each location are analyzed for gamma emitting isotopes. Charcoal canister samples are analyzed weekly for iodine-131.

Ambient gamma radiation is monitored at a total of 52 locations. A TLD is placed at each location and exchanged and analyzed quarterly. The TLD locations are distributed as follows:

• Two on-site locations

• Eighteen in a circle within a 0.5 mi. radius from the DAEC stack.

• Six in 22.5° sectors within 1 mi. from the DAEC stack.

• Ten in 22.5° sectors between 1 and 3 miles from the DAEC stack.

• Twelve control locations greater than 3 miles from the DAEC stack.

• Four along sections of the Independent Spent Fuel Storage Installation (ISFSI) fence line.

Surface water is collected monthly from five river locations, D-49 (Lewis Access, Control, 4 mi.

upstream), D-50 (Inlet), D-51 (Discharge) and D-61 (downstream of Discharge) and also from Pleasant Creek Lake (D-99). The monthly samples are analyzed for tritium and gamma-emitting isotopes. Additional analyses are performed on samples collected from the control and indicator locations, D-49 and D-61. Analyses for low-level iodine-131 are performed on monthly collections and quarterly composites are prepared and analyzed for strontium-89 and strontium-90.

The aquatic environment is also monitored by upstream and downstream (D-49 and D-61) semiannual collections of fish.

River bottom sediment is collected semiannually at the plant's intake (D-49) and discharge (D-51) and the site's north drainage ditch (D-107a). The samples are analyzed for gamma-emitting isotopes.

Potable groundwater is collected monthly from the Cedar Rapids treated municipal water system (D-53), the inlet to the Cedar Rapids municipal water treatment system (D-54), four indicator locations (D-52, D-55, D-57, D-58) and one control location (D-72). The samples are analyzed for tritium and gamma emitting isotopes. Any positive identification of a reactor by-product material initiates analyses for hard to detect isotopes of Ni-63, Sr-89, Sr-90, Fe-55 and gross alpha. The samples are analyzed for tritium, 1-131 by chemical separation to an MDC of 1 pCi/L, and gamma emitting isotopes.

For 2019, dairy cow milk was collected monthly from one indicator (D-110) and one control location (D-138) from January to December. Monthly sampling was determined to be sufficient due to the milk sampling locations more than five miles from the facility. The samples are analyzed for iodine-131 and gamma-emitting isotopes. This sampling is supplemented with goat's milk when available from indicator location (D-76).

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Additional monitoring of the terrestrial environment, grain, hay, grass and broadleaf vegetation samples are collected annually, as available, from nine locations: one control (D-138) and seven indicators (D-57, D-58, D-77, D-96, D-109, D-110 and D-118). Grain, hay and broadleaf (green leafy) vegetation samples are analyzed for gamma-emitting isotopes and at least two broad leaf vegetation samples are analyzed for iodine-131. Vegetation control samples are purchased from local grocery and feed stores provided the sample source is outside the State of Iowa.

If any of the cattle grazing on-site are slaughtered for home use, a meat sample is collected.

The sample is analyzed for gamma-emitting isotopes. A single deer meat sample from a legally harvested animal was collected near D-58.

3.2.2 Groundwater Protection Program Environmental, Inc., Midwest Laboratory provides laboratory services for the Duane Arnold Energy Center Groundwater Protection Program (GWPP). The GWPP is formally included within REMP and the standards are set forth in the ODAM, Table 6.3-2. The Groundwater Protection Program encompasses activities to ensure the protection of groundwater within the owner controlled area by sampling the groundwater, soil, precipitation, electrical vault and sewage effluent. For sewage effluent results only, refer to the Duane Arnold Energy Center, 2019 Annual Radioactive Material Release Report and Table 23 of Part 11 of this report for groundwater, soil, electrical vault, and precipitation sample results.

3.3 Program Execution The program was executed as described in the preceding section with the following exceptions:

(1) Airborne Particulates I Airborne Iodine:

The air station at location D-16 had a mechanical pump failure (02/01/19). The air station at location D-11 experienced pump failures 03/29/19 and 04/05/19. Details of the failures are listed in table 5.6.

(2) Thermo luminescent Dosimetry The TLD from location D-17 was found missing for the second quarter of 2019.

(3) Milk Goat's milk was unavailable at location D-76 throughout 2019 due to limited herd production.

Details of the missed scheduled collections are listed in table 5.6.

(4) WellWater Well water was not collected at location D-55 for the 5/14/19 collection.

(5) Surface Water Surface water was unavailable at locations D-50 and D-99 for the 02/21/19 and the 12/18/19 sampling event due to freezing.

3.4 Laboratory Procedures 5

The lodine-131 analyses in milk and water were made using a sensitive radiochemical procedure involving separation of iodine using an ion-exchange method, solvent extraction and subsequent beta counting. Levels of iodine-131 in vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.

Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.

The gamma isotopic analysis provides a spectrum with an energy range from 80 to 2048 KeV.

Specific isotopes included in the gamma library are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as Be-7, K-40 and Ra daughters, are frequently detected but may not be listed.

Tritium was measured by liquid scintillation spectrometry.

Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2018). The QA Program includes participation in lnterlaboratory Comparison (crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

3.5 Program Modifications There were a few changes to the REMP program in 2019. R EMP and GWPP standards and requirements can be found in the Duane Arnold Energy Center 2019 Annual Radiological Material Release Report in Attachment 2, ODAM.

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4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled, except for those listed in Table 5.6.

Results are summarized in Table 5.7 as recommended by the Nuclear Regulatory Commission.

For each type of analysis and sample medium, the table lists the mean and range of all indicator and control locations, as well as that location with the highest mean and range.

Tabulated results of measurements are not included in this section, although reference to these results will be made in discussion. A complete tabulation of results for 2019 is contained in Part II of the Annual Report on the Radiological Environmental Monitoring Program for the Duane Arnold Energy Center.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2019. The Fukushima Daiichi nuclear accident occurred March 11, 2011.

There were no reported atmospheric nuclear tests in 2019. The last reported test was conducted on October 16, 1980 by the People's Republic of China. However, a failed Russian weapon test in August 2019 did release strontium-91, barium-139, barium-140, and lanthanum-140. These isotopes have half-lives of 83 minutes to 12.8 days.

4.2 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected outside of the Owner Controlled Area in 2019. The trace levels of cesium-137, still measurable in soil, are attributed to deposition of fallout from nuclear weapons testing from previous decades.

Airborne Particulates The average annual gross beta concentrations in airborne particulates were similar at indicator and control locations (0.026 and 0.025 pCi/m 3 , respectively) and similar to levels observed from 1995 through 2018. The results are tabulated below.

Year Indicators Controls Year Indicators Controls 3 3 Concentration (pCi/m ) Concentration (pCi/m )

2000 0.026 0.027 2010 0.028 0.028 2001 0.026 0.026 2011 0.030 0.029 2002 0.027 0.027 2012 0.030 0.029 2003 0.029 0.029 2013 0.028 0.025 2004 0.028 0.028 2014 0.026 0.025 2005 0.031 0.031 2015 0.027 0.024 2006 0.029 0.027 2016 0.027 0.023 2007 0.031 0.031 2017 0.028 0.025 2008 0.029 0.029 2018 0.028 0.026 2009 0.031 0.030 2019 0.026 0.025 Average annual gross beta concentrations in airborne particulates.

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4.2 Program Findings, Airborne Particulates (continued)

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7,produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples, with an average activity of 0.080 pCi/m 3 for indicator locations and 0.077 pCi/m 3 for the control location.

No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the ODAM.

Airborne Iodine 527 weekly air samples were collected in 2019 from ten air monitoring stations. Levels of airborne 3

iodine-131 measured below the required limit of 0.030 pCi/m with the exception of the samples collected at location D-16 for the week ending 02/01/19 (pump failure) and at location D-11 for the weeks ending 3/29/19 (Pump failure) and 4/05/19 (pump failure).

Ambient Radiation (TLDs) 207 TLDs were collected and analyzed in 2019. At twelve control locations, thermoluminescent dosimeter (TLD) readings averaged 20.0 mR/quarter. At locations within a half mile, one mile and three mile radius of the stack, the measurements averaged 19.2, 18.4 and 17.2 mR/quarter, respectively. The two on-site locations D-15 and D-16 averaged 16.8 and 18.9 mR/quarter respectively. These average measurements are similar to the estimated average natural background radiation for Middle America, 19.5 mR/quarter, which is based on data on Pages 71 and 108 of the report, "Natural Background Radiation in the United States" (National Council on Radiation Protection and Measurements, 1975). The terrestrial absorbed dose (uncorrected for structural and body shielding) ranges from 8.8 to 18.8 mrad/quarter and averages 11.5 mrad/quarter for Middle America. Cosmic radiation and cosmogenic radionuclides contribute 8.0 mrad/quarter for a total average of 19.5 mrad/quarter. No plant effect is indicated.

ISFSI Facility Operations Monitoring Four TLDs, placed directionally along the ISFSI fence line, averaged 32.7 mR/quarter. The TLD site D-30, located between the nearest residence and the ISFSI site averaged 19.7 mR/quarter.

Calculated dose rates indicate the site is in compliance with 10 CFR 72.104 and 40 CFR 190.

24 milk samples were collected from two commercial dairies in 2019. lodine-131 concentrations in milk samples were less than the LLD level of 1.0 pCi/L.

No gamma-emitting isotopes, excepting naturally occurring potassium-40, were detected in any milk samples. This is consistent with findings that most radio-contaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).

No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the ODAM.

Groundwater (drinking water-potable) 51 drinking water samples from seven locations were collected in 2019. Tritium concentrations in ground water samples were less than the MDC of 160 pCi/L in all samples analyzed. Gamma-emitting isotopes were below detection limits.

No reactor by-product radionuclides could be identified. All samples met required lower limits of detection as specified in the ODAM.

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4.2 Program Findings (continued)

Vegetation Eleven vegetation samples from six locations were collected in 2019. lodine-131 concentrations in vegetation samples were less than the LLD level of 0.058 pCi/g wet weight in all samples analyzed.

Samples of both broadleaf vegetation as well as grain and forage types were analyzed.

With the exception of potassium-40, which was observed in all vegetation samples, all other gamma-emitting isotopes were below detection limits. No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the ODAM.

Surface Water 57 surface water samples were collected from five locations in 2019. Surface water was tested for tritium and gamma emitting isotopes. No measurable tritium activity was detected above an LLD of 160 pCi/L.

Analyses for 1-131 were performed on samples from locations D-49 (control) and D-61 (0.5 mi.

downstream, indicator). No measurable 1-131 was detected above an LLD of 0.5 pCi/L.

Quarterly composites were also prepared from the samples collected at locations D-49 and D-61 and tested for strontium-89 and strontium-90. All samples tested below detection limits.

No plant effect on surface water is indicated.

Ten fish samples from five sport fish species were collected in June and August, 2019, and analyzed for gamma-emitting isotopes. With the exception of naturally-occurring potassium-40, no gamma-emitting isotopes were identified in edible portions of fish. The potassium-40 level was similar at both the indicator and control locations (3.82 and 4.04 pCi/g wet, respectively).

No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the ODAM.

River Sediments Six river sediment samples from three locations were collected in 2019 during the months of April and October, and analyzed for gamma-emitting isotopes. Potassium-40 activity ranged from 5.22 to 8.19 pCi/g dry weight at the indicator locations and between 7.11 and 7.71 pCi/g dry weight at the control location.

All samples met required lower limits of detection as specified in the ODAM.

4.3 Ground Water Protection Program Findings Environmental, Inc., Midwest Laboratory provides laboratory services for the Duane Arnold Energy Center Ground Water Protection Program except for sewage effluent results; refer to Appendix E.

Sewage effluent sample results can be found in the Duane Arnold Energy Center 2019 Annual Radiological Material Release Report.

Groundwater 270 groundwater samples (non-potable water) were collected from 56 permitted monitoring wells and three permitted extraction wells in 2019. Tritium was the only plant by-product identified.

Concentrations of tritium ranged from less than 148 pCi/L to 95,396 pCi/L at D-66A, monitoring 9

well MW-22A. An explanation of tritium mitigation can be found in the Duane Arnold Energy Center 2019 Radioactive Material Release Report. Tritium was not identified in any drinking water well on-site or at off-site wells or Cedar Rapids municipal drinking water samples. Lastly, the monitoring well farthest down gradient prior to the boundary of the owner controlled area and the Cedar River, MW-33A, did not indicate tritium above the lower level of detection, less than 155 pCi/L.

Two soil samples were collected in 2019, from D-15a and from D-16. Both samples were positive for cesium-137 with an average level of 0.12 pCi/g dry weight which is consistent with previous results at these locations. The cesium-137 source is determined to be from nuclear weapons testing and not from plant activities.

Precipitation 83 precipitation samples were collected in 2019 from seven precipitation collection locations. Tritium was consistently identified at locations D-127 and D-128. Tritium concentrations range from less than 363 pCi/L to 2,256 pCi/L (+/-155 pCi/L) from D-127. The proximity of the plant gaseous effluent release points coupled with atmospheric conditions enables recapture of gaseous effluent, specifically tritiated water vapor, to be entrained in precipitation and deposited within the protected area. Occasionally, tritiated precipitation collects in a basin or pit. This water is then sampled and released in accordance with the Offsite Dose Assessment Manual (ODAM), "Clean" system batch release of a liquid effluent as documented in ODAM, Table 7.1-2.

Electrical Vaults 25 electrical vaults samples were collected in 2019 from nine electrical vaults. Electrical vaults are below grade structures designed for electrical cabling. Surface water and groundwater may seep into the vaults. Tritium concentrations range from less than 150 pCi/L to 295 pCi/L (+/- 88 pCi/L) from D-120, which is consistent with rainfall recapture of tritiated water vapor from plant gaseous effluent release points.

Storm Drains. Sluice Pond. and Drainage Ditches.

21 samples were collected in 2019 from storm drains, sluice ponds and drainage ditches. Surface water sampling from these locations is consistent with non-point source runoff sampling activities.

Similar to electrical vaults, tritium recapture is the source for tritium. Tritium concentrations range from less than 150 pCi/L to 3, 77 4 pCi/L( +/- 193 pCi/L) from D-125.

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5.0 TABLES AND FIGURES 11

Table 5.1 Characteristic properties of isotopes quantified in gamma-spectroscopic analyses.

Designation Comment Isotope Half-life a Naturally Occurring A. Cosmogenic Produced by interaction of cosmic rays Be-7 53.2d with atmosphere 9

B. Terrestrial Primordial K-40 1.26x10 y II. Fission Products b Nuclear accidents and detonations constitute the major environmental source.

A. Short-lived 1-131 8.04 d Ba-140 12.8 d B. Other than Short-lived Nb-95 35.15d Zr-95 65 d Ru-103 39.35 d Ru-106 368.2 d Cs-134 2.061 y Cs-137 30.174 y Ce-141 32.5 d Ce-144 284.31 d Ill. Activation Products Typically found in nuclear power plant Mn-54 312.5 d effluents Fe-59 45.0 d Co-58 70.78 d Co-60 5.26y Zn-65 245 d Half-lives are taken from Appendix E of Environmental Quarterly, 1 January 1978, EML-334 (U. S. Department of Energy, 1978).

Includes fission-product daughters.

12

Table 5.2 Sample collection and analysis program.

Sampling Location a Exposure Sample Description Sampling and Collection Type and Frequency Pathway and/or Point Frequency of Analysis b Sample Type Airborne 3 Hiawatha Continuous operation of Analyze for gross beta activity Particulates 4 Pleasant Creek SRA sampler with sample more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after filter 5A Palo collection at least once per change. Perform gamma isotopic 6 Center Point week or as required analysis on each sample having 7 Shellsburg by dust loading gross beta activity greater than 11 Toddville ten times the yearly mean of the 13 Alburnett (C) control samples.

15 On-site North 16 On-site South Composite weekly samples to 40 Wickiup Hill form a quarterly composite (by location). Analyze quarterly composite for gamma isotopic.

Airborne 3 Hiawatha Continuous operation of Analyze each cartridge for Iodine 4 Pleasant Creek SRA sampler with sample iodine-131.

5A North Palo collection at least once per 6 Center Point week.

7 Shellsburg 11 Toddville 13 Alburnett (C) 15 On-site North 16 On-site South 40 Wickiup Hill Ambient 1-3, 5A, (Controls) One dosimeter continuously Read gamma radiation dose Radiation 6-8 (Controls) at each location. quarterly.

10,11,13 (Indicators)

Dosimeters are changed at 15-23, Within 0.5 mile of least quarterly.

28-32, Stack 4, 33-42 Within 3.0 miles of Stack 43-48 Within 1.0 mile of 82-86, 91 Stack 161-164 ISFSI Fence line Surface Water 49 Lewis Access (C) Once per month. Gamma isotopic and tritium 50 Plant Intake analysis for each sample (by 51 Plant Discharge location).

61 - ~mi. downstream from Plant Discharge Locations 49 and 61, analyses for low-level 1-131. Quarterly 99 Pleasant Creek Lake composites for Sr-89, Sr-90.

13

Table 5.2 Sample collection and analysis program, (continued).

Sampling Location a Exposure Sample Description Sampling and Collection Type and Frequency Pathway and/or Point Frequency of Analysis b Sample Type 52 Plant potable water Ground Water 53 Treated Municipal Grab sample at least Analysis gamma emitting isotopes, Water once per quarter iodine-131 and tritium on quarter!~

54 Inlet to Municipal Water samples.

Treatment System 55 On-site well If reactor by-product gamma 57,58 Wells off-site and emitters are identified, or if tritium 72 (C) within 4 km of DAEC concentrations measure > MDA, then analyze for Ni-63, Sr-89, Sr-90 and alpha emitters.

River 49 Lewis Access At least once every six Gamma isotopic analysis of each Sediment months. sample 50 Plant Intake (C) 51 Plant Discharge 107a North Drainage Ditch (on-site)

Vegetation 16,57 Farms raising food Annually at harvest Gamma isotopic analysis, 56, 57, crops time. Two samples of including iodine-131, on each 58,77, each: grain, green leafy, sample.

96,108, and forage.

110,118 138 (C)

Fish 49 Cedar River upstream One sample per 6 Gamma isotopic analysis on edible of DAEC not months (once during portions.

influenced by effluent January through June (C) and once during July through December).

56 Downstream of DAEC 61 in influence of effluent Milk 138 (C) Farm near Newhall, IA Monthly. Gamma isotopic and iodine-131 analyses of each sample.

110 Dairy Farm within 7.8 Monthly.

miles from Site 76 Goat Farm ENE of site. Monthly depending on availability.

• (C) denotes control location. All other locations are indicators.

b Gamma isotopic analysis and analysis for gamma-emitting nuclides refer to high resolution gamma ray spectrum analysis.

14

Table 5.3 Sampling locations, Duane Arnold Energy Center.

Sampling Location Code Location Description Distance and Direction from Site Stack D-1 Cedar Rapids 20,800 meters SE D-2 Marion 16,900 meters ESE D-3 Hiawatha 10,800 meters SE D-5 Palo 4,500 meters SSW D-4 Pleasant Creek SRA 4,960 meters NW D-5A Palo 3,470 meters SSW D-6 CenterPoint 9,660 meters N D-7 Shellsburg 7,950 meters W D-8 Urbana 15,000 meters NNW D-10 Atkins 13,600 meters SSW D-11 Toddville 4,980 meters E D-13 Alburnett 14,500 meters ENE D-15 On-site, North-Northwest 1,050 meters NNW D-16 On-site, South-Southeast 520 meters SSE D-17 On-site, N 1,050 meters N D-18 On-site, NNE 630 meters NNE D-19 On-site, NE 590 meters NE D-20 On-site, ENE 550 meters ENE D-21 On-site, ENE 515 meters ENE D-22 On-site, ESE 535 meters ESE D-23 On-site, SE 490 meters SE D-28 On-site, WSW 730 meters WSW D-29 On-site,W 630 meters W D-30 On-site, WNW 640 meters WNW D-31 On-site, NW 1,020 meters NW D-32 On-site, NNW 1, 110 meters NNW D-33 3 mile rinq 4,340 meters N D-34 3 mile rinq 3,930 meters NNE D-35 3 mile ring 2,800 meters NE D-36 3 mile ring 3,500 meters ENE D-37 3 mile ring 2, 960 meters E D-38 3 mile rinq 3, 180 meters ESE D-39 3 mile ring 2,510 meters SE D-40 3 mile ring 2,430 meters SSE D-41 3 mile rinq 5,680 meters S D-42 3 mile ring 4,380 meters SSE D-43 1 mile ring 1,590 meters SSW D-44 1 mile rinq 1,580 meters WSW D-45 1 mile rinq 1,420 meters W D-46 1 mile rinq 1,580 meters WNW D-47 1 mile rinq 1,760 meters NW D-48 1 mile rinq 1,680 meters NNW 15

Table 5.3 Sampling locations, Duane Arnold Energy Center (continued).

Sampling Location Code Location Description Distance and Direction from Site Stack D-49 Lewis Access, upstream of DAEC 6,750 meters NNW D-50 Plant Intake 560 meters SE D-51 Plant DischarQe 600 meters SE D-52 Plant potable water On-site D-53 Treated Municipal Water 13,900 meters SE D-54 Inlet, Municipal Water Treatment System 13,900 meters SE D-55 Production Well Production wells A-D D-56 Control samples from various locations Sample location varies D-57 Farm (Off-site Well) 805 metersW D-58 Farm (Off-site Well) 97 4 meters WSW-SW D-61 Downstream of plant discharge 670 meters SSE D-72 Farm 3,200 meters SSW D-76 Farm 2,888 meters ENE D-77 Farm 2,288 meters SW D-82 On-site, SSE 660 meters SSE D-83 On-site, SSE 620 meters SSE D-84 On-site, S 610 meters S D-85 On-site, SSW 660 meters SSW D-86 On-site, SW 850 meters SW D-91 On-site, NNW 1,090 meters NNW D-96 Farm 11,400 meters SSW D-99 Pleasant Creek Lake 3,880 meters WNW D-107a North Drainage Ditch On-site D-109 Farm 5,890 meters SW D-110 Farm 12,700 meters SW D-118 Farm 2,230 meters NW D-138 Farm 21,600 meters WSW D-161 ISFSI Fence East On-site D-162 ISFSI Fence South On-site D-163 ISFSI Fence West On-site D-164 ISFSI Fence North On-site 16

Table 5.4 Type and Frequency of collection.

Location Weekly Monthly Quarterly Semiannually Annually D-1 TLD D-2 TLD D-3 AP.Al TLD D-4 AP,AI TLD D-5 TLD D-5A AP,AI TLD D-6 AP,AI TLD D-7 AP,AI TLD D-8 TLD D-10 TLD D-11 AP,AI TLD D-13 AP,AI TLD D-15 AP.Al TLD D-15a so D-16 AP.Al TLD G,SO D-17 to D-23 TLD D-28 to D-39 TLD D-40 AP.Al TLD D-41 to D-48 TLD D-49 SW F D-50 SW BS D-51 SW BS D-52 WW D-53 WW D-54 WW D-55 WW D-56 D-57 WW G D-58 WW D-61 SW F D-72 WW D-76 Mi' D-77 G D-82 to D-86 TLD D-91 TLD D-99 SW ME**

D-107A BS D-108 G D-110 Ml G D-118 G D-138 Ml G D-161 to D-164 TLD On-site

• Goat's milk sampled when available.

• • Meat sampled when available.

17

Table 5.5. Sample codes used in Table 5.4 and Table 5.6.

Code Description AP Airborne Particulates Al Airborne Iodine TLD Thermoluminescent Dosimeter Ml Milk

\NW Well Water G Vegetation ME Meat SW Surface Water F Fish BS River Sediment so Soil 18

Table 5.6. Program Deviations, Duane Arnold Energy Center.

Sample Collection Date Type Analysis Location(s) or Period Comments Goat's milk unavailable due to limited herd Ml D-76 01-15-19 production.

Filter very light due to mechanical pump AP/Al D-16 02-01-19 failure. Samples discarded.

Goat's milk unavailable due to limited herd Ml D-76 02-14-19 production.

SW D-50 02-21-19 No Sample; river frozen.

SW D-99 02-21-19 No sample; river frozen.

AP/Al D-11 03-29-19 No samples; pump failure.

Ml D-76 03-12-19 Goat's milk unavailable due to limited herd production.

AP/Al D-11 04-05-19 No samples; pump failure.

Goat's milk unavailable due to limited herd Ml D-76 04-09-19 production.

Goat's milk unavailable due to limited herd Ml D-76 05-14-19 production.

WW D-55 05-14-19 Sample not collected.

Goat's milk unavailable due to limited herd Ml D-76 06-11-19 production.

TLD D-17 07-01-19 Sample missing in field.

Goat's milk unavailable due to limited herd Ml D-76 07-16-19 production.

Goat's milk unavailable due to limited herd Ml D-76 08-13-19 production.

19

Table 5.6. Program Deviations, Duane Arnold Energy Center.(Continued).

Sample Collection Date Type Analysis Location( s) or Period Comments Goat's milk unavailable due to limited herd Ml D-76 09-10-19 production.

Goat's milk unavailable due to limited herd Ml D-76 10-15-19 production.

Goat's milk unavailable due to limited herd Ml D-76 11-13-19 production.

SW D-50 12-18-19 No sample; river frozen.

SW D-99 12-18-19 No sample; river frozen.

20

Table 5.7 Radiological Environmental Monitoring Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2019 Indicator Control Number Sample Type and Location with Highest Annual Mean Locations Locations Non-Type Number of LLD b Mean (F)' Mean (F)' Mean (F) c Routine (Units) Analyses a Location d Range' Range' Range c Results*

Airborne Pathway Airborne 0 Particulates GB 527 0.003 0.026 (474/474) D-15 0.026 (52/52) 0.025 (53/53) 3 (0.004-0.060) (0.007-0.047) (0.008-0.046)

(pCi/m )

GS 40 Be-7 0.020 0.072(36/36) D-3 0.079 (4/4) 0.064(4/4) 0 (0.050-0.091) (0.068-0.091) (0.045-0.085)

Mn-54 0.0013 <LLD - <LLD 0 Fe-59 0.0028 <LLD - - <LLD 0

- - 0 Co-58 0.0012 <LLD - <LLD

- 0 Co-60 0.0012 <LLD - - <LLD Zn-65 <LLD

- - <LLD 0 0.0032 - - 0 Nb-95 0.0036 <LLD - - <LLD Zr-95 0.0024 <LLD -

- <LLD 0 Ru-103 0.0016 <LLD - <LLD 0 Ru-106 0.0124 <LLD - <LLD 0 Cs-134 0.0014 <LLD - - <LLD 0 Cs-137 0.0011 <LLD

- <LLD 0

- 0

<LLD <LLD Ce-141 0.0032 - -

Ce-144 0.0063 <LLD

- - <LLD 0

Airborne Iodine 1-131 527 0.030 0

<LLD - - <LLD (pCi/m 3 )

Direct Radiation TLDs (m R/quarter)

Gamma 48 1.0 None D-5 20.0 (4/4) 17.7 (48/48) 0 Control Locations (16.9-27.4) (12.7-27.4)

Within 0.5 mi. of Gamma 79 1.0 19.2 (79/79) D-17 None 0 22.5 (3/4)

Stack (12.9-31.2) (16.9-31.2)

Within 1.0 mi. of Gamma 24 1.0 18.4 (24/24) D-48 19.6(4/4) None 0 Stack (13.1-26.5) (14.4-24.2)

Within 3.0 mi.of Gamma 40 1.0 17.2 (40/40) D-37 19.1 (4/4) None 0 Stack (10.9-27.1) (16.7-22.4) 16 32.7(16/16) D-161 48.4 (4/4) None ISFSI border Gamma 1.0 0 (13.9-54.4) (43.4-53.7) 21

Table 5.7 Radiological Environmental Monitoring Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2019 Indicator Location with Highest Annual Mean Control Number Sample Type and Locations Locations Non-Type Number of LLD b Mean (F)' Mean (F) 0 Mean (F) c Routine (Units) Analyses* Location Range' d Range' Range c Results*

Waterborne Pathway Surface Water H-3 57 177 <LLD - - <LLD 0 (pCi/L) l-131chem 24 0.5 <LLD - - <LLD 0 Sr-89 8 0.81 <LLD - - <LLD 0 Sr-90 8 0.58 <LLD - - <LLD 0 GS 57 Mn-54 6.8 <LLD - - <LLD 0 Fe-59 12.4 <LLD - - <LLD 0 Co-58 5.0 <LLD - - <LLD 0 Co-60 4.7 <LLD - - <LLD 0 Zn-65 14.5 <LLD - - <LLD 0 Nb-95 9.6 <LLD - - <LLD 0 Zr-95 8.5 <LLD - - <LLD 0 1-131 10.4 <LLD - - <LLD 0 Cs-134 6.0 <LLD - - <LLD 0 Cs-137 5.8 <LLD - - <LLD 0 Ba-140 24.2 <LLD - - <LLD 0 La-140 17.8 <LLD - - <LLD 0 GS Sediments 6 (pCi/gdry) 6.74 (4/4) D-51 8.16 (2/2) 7.71 (2/2) 0 K-40 1.0 (8.12-8.19) (7.11-7.71)

(5.22-8.19)

Mn-54 0.017 <LLD - - <LLD 0

Fe-59 0.058 <LLD - - <LLD 0 Co-58 0.020 <LLD - - <LLD 0 Co-60 0.017 <LLD - - <LLD 0 Zn-65 0.039 <LLD <LLD Nb-95 0.047 <LLD

-- -- <LLD

()

0 Zr-95 0.032 <LLD - - <LLD 0 Ru-103 0.029 <LLD - - <LLD 0 Ru-106 0.107 <LLD - - <LLD 0 Cs-134 0.013 <LLD - - <LLD 0 Cs-137 0.016 <LLD - - <LLD 0 Ce-141 0.073 <LLD <LLD Ce-144 0.100 <LLD

-- -- <LLD

()

0 22

Table 5.7 Radiological Environmental Monitoring Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2019 Indicator Location with Highest Annual Mean Control Number Sample Type and Locations Locations Non-Type Number of LLD b Mean (F) c Mean (F) c Mean (F) c Routine (Units) Analyses a Location d Range c Range c Range c Results*

Waterborne Pathway 0

Ground Water, 1-131 51 0.5 <LLD - - <LLD potable (pCi/L)

H-3 51 160 <LLD - - <LLD 0 GS 51 Mn-54 7.3 <LLD - - <LLD 0 Fe-59 10.8 <LLD - - <LLD 0 Co-58 5.7 <LLD - - <LLD 0 Co-60 6.9 <LLD - - <LLD 0 Zn-65 15.2 <LLD - - <LLD 0 Nb-95 8.8 <LLD - - <LLD 0 Zr-95 10.6 <LLD - - <LLD 0 1-131 8.9 <LLD - - <LLD 0 Cs-134 8.2 <LLD - - <LLD 0 Cs-137 6.4 <LLD - - <LLD 0 Ba-140 32.2 <LLD - - <LLD 0 La-140 7.2 <LLD - - <LLD 0 Ingestion Pathway Milk 1-131 24 0.5 <LLD - - <LLD 0 (pCi/L)

GS 24 K-40 100 1436(12/12) D-110 1436(12/12) 1392(12/12) 0 (1388-1561) (1388-1561) (1388-1561)

Cs-134 5 <LLD - - <LLD 0 Cs-137 5 <LLD - - <LLD 0 Ba-140 60 <LLD - - <LLD 0 La-140 5 <LLD - - <LLD 0 Broadleaf GS 9 Vegetation K-40 0.05 4.70 (9/9) D-57 6.46(1/1) None 0 (pCi/gwet) (2.23-6.93)

Mn-54 0.041 <LLD - - 0 Fe-59 0.063 <LLD - - 0 Co-58 0.046 <LLD - - 0 Co-60 0.039 <LLD - - 0 Zn-65 0.091 <LLD - - 0 Nb-95 0.038 <LLD - - 0 Zr-95 0.089 <LLD - - 0 Ru-103 0.047 <LLD - - 0 Ru-106 0.401 <LLD - - 0 1-131 0.058 <LLD - - 0 Cs-134 0.046 <LLD - - 0 Cs-137 0.059 <LLD - - 0 Ce-141 0.057 <LLD - - 0 Ce-144 0.215 <LLD - - 0 23

Table 5.7 Radiological Environmental Monitoring Program Summary.

Name of Facility Duane Arnold Energy Center Docket No. 50-331 Location of Facility Linn, Iowa Reporting Period January-December, 2019 (County, State)

Indicator Location with Highest Annual Mean Control Number Sample Type and Locations Locations Number of Non-Type LLD b Mean (F) c Mean (F)' Mean (F) c Routine (Units) Analyses a Location d Range c Range' Range c Results*

Ingestion Pathway (cont.)

GS 2 Vegetation K-40 0.05 D-57 0 (Grain and Forage) 23.23 (2/2) 24.13 (1/1) None (22.33-24.13)

(pCi/gwet)

Mn-54 0.033 <LLD - - 0 Fe-59 0.068 <LLD - - 0 Co-58 0.020 <LLD - - 0 Co-60 0.027 <LLD - - 0 Zn-65 0.070 <LLD - - 0 Nb-95 0.030 <LLD - - 0 Zr-95 0.064 <LLD - - 0 Ru-103 0.032 <LLD - - 0 Ru-106 0.27 <LLD - - 0 1-131 0.054 <LLD - - 0 Cs-134 0.035 <LLD - - 0 Cs-137 0.036 <LLD - - 0 Ce-141 0.039 <LLD - - 0 Ce-144 0.21 <LLD - - 0 GS 10 Fish (pCi/gwet) K-40 1.0 3.82 (5/5) D-49 4.19 (4/4) 4.04 (5/5) 0 (3.54-4.30) (3.40-4.78) (3.40-4.78) 0 Mn-54 0.025 <LLD - - <LLD 0 0.101 0 Fe-59 <LLD

- - <LLD 0.038 0 Co-58 <LLD - - <LLD 0.025 0 Co-60 <LLD - - <LLD 0.053 0 Zn-65 <LLD - - <LLD 0.066 0 Nb-95 <LLD - - <LLD 0.068 0 Zr-95 <LLD

- - <LLD 0.053 0 Ru-103 <LLD

- - <LLD 0.258 0 Ru-106 <LLD - - <LLD Cs-134 0.027 <LLD

- - <LLD 0 Cs-137 0.023 <LLD

- - <LLD 0 0.105 0 Ce-141 <LLD

- - <LLD 0.171 0 Ce-144 <LLD

- - <LLD

• GB = Gross beta; GS =Gamma spectroscopy b LLD = Nominal lower limit of detection based on 4.66 sigma counting error for the background sample.

c Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified by: (1) Name and code (Table 5.3); and (2) distance, direction and sector relative to reactor site.

• Non-routine results are those which exceed ten times the control station value for the location. If a control station value is not available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.

24

Figure 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center.

Figure 5-1 Environmental Monitoring Programs Sampling Near the Duane Arnold Energy Center rtI

,.- - - - *a1 I

32 I  ! t64

~@

I I

I I 0  !!?

31 I

~ *1u I

I 1S..o::

I 0 30 w

I I ~

I I

II I 113 I

&1 29 I

I I

ia L-----

116 GATE 2000t""1t

~

10 N

OAEC nlll U1 IM

!U ITO

.. fot tl!I See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

25

Figure 5.2. Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles.

Figure 5-2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles from DAEC 39 109 05n PALO:

110 ATKINS

• 10 CEDAR RA.ROS See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

26

6.0 REFERENCES

CITED Arnold, J. R. and H. A. Al-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, 275-276.

Environmental, Inc., Midwest Laboratory.

____2015 Study Plan, SP-DAEC-8001, rev1s1on 24 February 12, 2015, The Operational Radiological Environmental Monitoring Program for the Duane Arnold Energy Center, Cedar Rapids, Iowa

____2001 through 2018. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 2001 - 2018.

____ 1984 to 2000. (formerly Teledyne Brown Engineering, Environmental Services, Midwest Laboratory)

Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report

- Part II, Data Tabulations and Analyses, January - December, 1983 - 1999.

____ 1982 to 1984. (formerly Hazleton Environmental Sciences Corporation) Environmental Radiation Monitoring for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December 1981 - 1983.

_ _ _2018. Quality Manual, Rev. 6, 20 June 2018.

____2012. Quality Assurance Program Manual, Rev. 3, 14 November 2012.

____.2020. Quality Control Procedures Manual, Rev. 3, 15 January 2020.

____.2009. Quality Control Program, Rev. 2, 12 November 2009.

Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.

National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.

U. S. Department of Energy. 1978. Environmental Quarterly, Appendix E. Half-Life Tables, 1 January 1978, EML-334.

U. S. Nuclear Regulatory Commission. 1977. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I.

Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.

https://www. busi nessinsider. com/russian-missile-disaster-shows-signs-n uke-reactor-blew-up-experts-2019-8, last accessed on April 30, 2020.

27

Al l Environmental, Inc.

• /"\I Midwest Laboratory 700 Landwehr Road, Northbrook, IL 60062-2310 phone (817) 5M*0700, fax (817) 564*1517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA Docket No. 50-331 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

ANNUAL REPORT- PART II DATA TABULATIONS AND ANALYSES January 1 to December 31, 2019 Prepared by ATI ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8001 Reviewed and Approved Ashok Banavali, Ph.D.

Laboratory Manager

TABLE OF CONTENTS Section Page List of Tables ............................................................................................................... iii

1.0 INTRODUCTION

......................................................................................................... iv 2.0 PROGRAM DEVIATIONS ............................................................................................. v 3.0 DATA TABLES ............................................................................................................ vii ii

LIST OF TABLES No.

Airborne particulates and iodine, Location D-3, analyses for gross beta and iodine-131 ............ 1-1 2 Airborne particulates and iodine, Location D-4, analyses for gross beta and iodine-131 ............ 2-1 3 Airborne particulates and iodine, Location D-5A, analyses for gross beta and iodine-131 .......... 3-1 4 Airborne particulates and iodine, Location D-6, analyses for gross beta and iodine-131 ........... .4-1 5 Airborne particulates and iodine, Location D-7, analyses for gross beta and iodine-131 ............ 5-1 6 Airborne particulates and iodine, Location D-11, analyses for gross beta and iodine-131 .......... 6-1 7 Airborne particulates and iodine, Location D-13, analyses for gross beta and iodine-131 .......... 7-1 8 Airborne particulates and iodine, Location D-15, analyses for gross beta and iodine-131 ........... 8-1 9 Airborne particulates and iodine, Location D-16, analyses for gross beta and iodine-131 ........... 9-1 10 Airborne particulates and iodine, Location D-40, analyses for gross beta and iodine-131 ......... 10-1 11 Airborne Particulate samples, quarterly composites of weekly samples, analyses for gamma emitting isotopes ............................................................................. 11-1 12 Ambient gamma radiation by thermoluminescent dosimeters (TLD), quarterly exposure ........... 12-1 13 Milk samples, analysis for iodine-131 and gamma emitting isotopes ........................................... 13-1 14 Groundwater samples, analysis for iodine-131, tritium and gamma-emitting isotopes ............... 14-1 15 Vegetation samples (broadleaf), analysis for iodine-131 and gamma-emitting isotopes .............................................................................................. 15-1 16 Vegetation samples (hay and grain), analysis for iodine-131 and gamma-emitting isotopes ............................................................................................ 16-1 17 Surface water samples, analysis for iodine-131, tritium and gamma emitting isotopes ............. 17-1 18 Surface water samples, quarterly composites of monthly samples, analysis for strontium ......... 18-1 19 Fish samples, analysis for gamma emitting isotopes ................................................................ 19-1 20 River sediment samples, analysis for gamma-emitting isotopes .......................................... 20-1 21 Soil samples, analysis for gamma emitting isotopes ........................................................... 21-1 22 Meat samples, analysis for gamma emitting isotopes ......................................................... 22-1 23 Groundwater Protection Program ................................................................................... 23-1 iii

1.0 INTRODUCTION

The following constitutes a supplement to the Annual Report for the Radiological Environmental Monitoring Program conducted at the Duane Arnold Energy Center, Palo, Iowa in 2019. Results of completed analyses are presented in the attached tables.

For information regarding sampling locations, type and frequency of collection, and sample codes, please refer to Part I, Tables 5.3 - 5.5 and Figures 5.1 and 5.2.

All concentrations, except gross beta and airborne iodine, are decay corrected to the time of collection.

Airborne 1-131 is decayed to the midpoint of the collection period.

The required values for lower limits of detection (LLD) for gamma emitting isotopes are established through the Offsite Dose Assessment Manual (ODAM). Naturally occurring radioisotopes, such as Be-7, K-40 and Ra daughters, are frequently detected, but may not be listed for every sample medium.

iv

2.0 PROGRAM DEVIATIONS Sample Collection Date Type Analysis Location(s) or Period Comments Goat's milk unavailable due to limited herd Ml D-76 01-15-19 production.

Filter very light due to mechanical pump AP/Al D-16 02-01-19 failure. Samples discarded.

Goat's milk unavailable due to limited herd Ml D-76 02-14-19 production.

SW D-50 02-21-19 No Sample; river frozen.

SW D-99 02-21-19 No sample; river frozen.

AP/Al D-11 03-29-19 No samples; pump failure.

Ml D-76 03-12-19 Goat's milk unavailable due to limited herd production.

AP/Al D-11 04-05-19 No samples; pump failure.

Goat's milk unavailable due to limited herd Ml D-76 04-09-19 production.

Goat's milk unavailable due to limited herd Ml D-76 05-14-19 production.

WW D-55 05-14-19 Sample not collected.

Goat's milk unavailable due to limited herd Ml D-76 06-11-19 production.

TLD D-17 07-01-19 Sample missing in field.

Goat's milk unavailable due to limited herd Ml D-76 07-16-19 production.

Goat's milk unavailable due to limited herd Ml D-76 08-13-19 production.

v

2.0 PROGRAM DEVIATIONS Sample Collection Date Type Analysis Location( s) or Period Comments Goat's milk unavailable due to limited herd Ml D-76 09-10-19 production.

Goat's milk unavailable due to limited herd Ml D-76 10-15-19 production.

Goat's milk unavailable due to limited herd Ml D-76 11-13-19 production.

SW D-50 12-18-19 No sample; river frozen.

SW D-99 12-18-19 No sample; river frozen.

vi

3.0 DATA TABLES vii

Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 °.

Location: D-3 (Hiawatha)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 b

01-04-19 282 0.035 +/- 0.004 07-05-19 271 0.006 +/- 0.003 01-11-19 286 0.044 +/- 0.004 07-12-19 273 0.021 +/- 0.003 01-18-19 285 0.039 +/- 0.004 07-19-19 276 0.023 +/- 0.004 01-24-19 246 0.030 +/- 0.004 07-26-19 275 0.021 +/- 0.004 02-01-19 327 0.038 +/- 0.004 08-02-19 273 0.026 +/- 0.004 02-08-19 288 0.042 +/- 0.004 08-09-19 274 0.034 +/- 0.004 02-15-19 283 0.030 +/- 0.004 08-15-19 237 0.026 +/- 0.004 02-22-19 295 0.025 +/- 0.004 08-23-19 311 0.024 +/- 0.004 03-01-19 277 0.033 +/- 0.004 08-30-19 273 0.017 +/- 0.003 03-08-19 284 0.031 +/- 0.004 09-06-19 275 0.034 +/- 0.004 03-15-19 285 0.031 +/- 0.004 09-13-19 279 0.031 +/- 0.004 03-22-19 272 0.027 +/- 0.004 09-20-19 280 0.032 +/- 0.004 03-29-19 274 0.024 +/- 0.004 09-26-19 238 0.028 +/- 0.004 1st Quarter Mean+/- s.d. 0.033 +/- 0.006 3rd Quarter Mean +/- s.d. 0.025 +/- 0.008 04-05-19 274 0.015 +/- 0.004 10-04-19 320 0.017 +/- 0.003 c

04-12-19 274 0.013 +/- 0.004 10-11-19 279 0.004 +/- 0.003 04-19-19 274 0.013 +/- 0.003 10-19-19 320 0.020 +/- 0.003 04-26-19 275 0.018 +/- 0.004 10-24-19 200 0.023 +/- 0.005 05-03-19 277 0.011 +/- 0.003 11-01-19 323 0.023 +/- 0.003 05-10-19 270 0.020 +/- 0.003 11-08-19 279 0.028 +/- 0.004 05-17-19 276 0.027 +/- 0.004 11-15-19 280 0.039 +/- 0.004 05-24-19 276 0.007 +/- 0.003 11-22-19 280 0.037 +/- 0.004 05-30-19 231 0.009 +/- 0.003 11-27-19 199 0.027 +/- 0.005 06-07-19 321 0.029 +/- 0.004 12-06-19 360 0.015 +/- 0.003 06-14-19 266 0.020 +/- 0.004 12-12-19 240 0.026 +/- 0.004 06-21-19 274 0.022 +/- 0.004 12-20-19 320 0.042 +/- 0.004 06-28-19 277 0.023 +/- 0.004 12-27-19 281 0.047 +/- 0.005 01-03-20 279 0.034 +/- 0.004 2nd Quarter Mean +/- s.d. 0.017 +/- 0.007 4th Quarter Mean +/- s.d. 0.027 +/- 0.012 Cumulative Average 0.026 0

lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

1-1

Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: D-4 (NW Sector)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 306 0.035 +/- 0.004 07-05-19 308 0.024 +/- 0.003 01-11-19 308 0.043 +/- 0.004 07-12-19 310 0.018 +/- 0.003 01-18-19 308 0.039 +/- 0.004 07-19-19 313 0.020 +/- 0.003 01-24-19 266 0.034 +/- 0.004 07-26-19 311 0.022 +/- 0.003 02-01-19 352 0.041 +/- 0.004 08-02-19 311 0.025 +/- 0.003 02-08-19 316 0.026 +/- 0.003 08-09-19 309 0.030 +/- 0.004 02-15-19 300 0.031 +/- 0.004 08-15-19 265 0.029 +/- 0.004 02-22-19 324 0.037 +/- 0.004 08-23-19 352 0.019 +/- 0.003 03-01-19 299 0.027 +/- 0.004 08-30-19 307 0.017 +/- 0.003 03-08-19 310 0.028 +/- 0.004 09-06-19 309 0.028 +/- 0.004 03-15-19 309 0.032 +/- 0.004 09-13-19 306 0.031 +/- 0.004 03-22-19 312 0.026 +/- 0.003 09-20-19 308 0.035 +/- 0.004 03-29-19 311 0.021 +/- 0.004 09-26-19 272 0.028 +/- 0.004 1st Quarter Mean+/- s.d. 0.032 +/- 0.007 3rd Quarter Mean +/- s.d. 0.025 +/- 0.006 04-05-19 311 0.018 +/- 0.003 10-04-19 345 0.014 +/- 0.003 04-12-19 311 0.013 +/- 0.003 10-11-19 308 0.022 +/- 0.004 04-19-19 311 0. 009 +/- 0. 003 10-19-19 353 0.016 +/- 0.003 04-26-19 312 0.016 +/- 0.003 10-24-19 220 0.019 +/- 0.004 05-03-19 314 0.009 +/- 0.003 11-01-19 356 0.019 +/- 0.003 05-10-19 308 0.015 +/- 0.003 11-08-19 307 0.024 +/- 0.004 05-17-19 305 0.021 +/- 0.003 11-15-19 308 0.033 +/- 0.004 05-24-19 310 0.007 +/- 0.002 11-22-19 309 0.036 +/- 0.004 05-30-19 265 0.009 +/- 0.003 11-27-19 219 0.020 +/- 0.004 b

06-10-19 362 0.020 +/- 0.003 12-06-19 397 0.015 +/- 0.003 c

06-14-19 172 0.023 +/- 0.005 12-12-19 264 0.031 +/- 0.004 06-21-19 311 0.016 +/- 0.003 12-20-19 353 0.036 +/- 0.004 d

06-28-19 278 0.020 +/- 0.004 12-27-19 309 0.038 +/- 0.004 01-03-20 271 0.028 +/- 0.004 2nd Quarter Mean +/- s.d. 0.015 +/- 0.005 4th Quarter Mean+/- s.d. 0.025 +/- 0.008 Cumulative Average 0.024 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

b Sample collected 3 days later due to power failure.

c Lower volume due to 4 days collection period.

d Lower volume due to power failure.

2-1

Table 3. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 8 .

Location: D-5A (Palo)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 284 0.035 +/- 0.004 07-05-19 291 0.027 +/- 0.004 01-11-19 284 0.040 +/- 0.004 07-12-19 293 0.021 +/- 0.003 01-18-19 283 0.033 +/- 0.004 07-19-19 296 0.022 +/- 0.003 01-24-19 245 0.025 +/- 0.004 07-26-19 296 0.022 +/- 0.004 02-01-19 324 0.042 +/- 0.004 08-02-19 292 0.028 +/- 0.004 02-08-19 282 0.022 +/- 0.003 08-09-19 295 0.035 +/- 0.004 02-15-19 285 0.008 +/- 0.003 08-15-19 251 0.032 +/- 0.004 02-22-19 289 0.031 +/- 0.004 08-23-19 303 0.023 +/- 0.004 03-01-19 280 0.033 +/- 0.004 08-30-19 293 0.017 +/- 0.003 03-08-19 282 0.031 +/- 0.004 09-06-19 296 0.033 +/- 0.004 03-15-19 281 0.028 +/- 0.004 09-13-19 292 0.031 +/- 0.004 03-22-19 284 0.026 +/- 0.004 09-20-19 283 0.036 +/- 0.004 03-29-19 294 0.024 +/- 0.004 09-26-19 245 0.031 +/- 0.004 1st Quarter Mean +/- s.d. 0.029 +/- 0.009 3rd Quarter Mean +/- s.d. 0.027 +/- 0.006 04-05-19 294 0.018 +/- 0.004 10-04-19 319 0.015 +/- 0.003 04-12-19 294 0.016 +/- 0.004 10-11-19 282 0.026 +/- 0.004 04-19-19 294 0.005 +/- 0.003 10-19-19 323 0.021 +/- 0.003 04-26-19 295 0.016 +/- 0.003 10-24-19 203 0.024 +/- 0.005 05-03-19 298 0.011 +/- 0.003 11-01-19 325 0.024 +/- 0.003 05-10-19 289 0.019 +/- 0.003 11-08-19 281 0.024 +/- 0.004 05-17-19 297 0.025 +/- 0.004 11-15-19 283 0.039 +/- 0.004 05-24-19 291 0.008 +/- 0.003 11-22-19 283 0.031 +/- 0.004 05-30-19 253 0.004 +/- 0.003 11-27-19 201 0.026 +/- 0.005 06-07-19 337 0.023 +/- 0.003 12-06-19 364 0.017 +/- 0.003 06-14-19 293 0.018 +/- 0.003 12-12-19 242 0.044 +/- 0.005 06-21-19 294 0.020 +/- 0.003 12-20-19 324 0.042 +/- 0.004 06-28-19 297 0.022 +/- 0.003 12-27-19 281 0.049 +/- 0.005 01-03-20 285 0.031 +/- 0.004 2nd Quarter Mean +/- s.d. 0.016 +/- 0.007 4th Quarter Mean+/- s.d. 0.029 +/- 0.010 Cumulative Average 0.025 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

b Power off at the station; appr. 20 hrs less than other stations.

3-1

Table 4. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 8

• Location: D-6 (Center Point) 3 Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 280 0.033 +/- 0.004 07-05-19 280 0.024 +/- 0.004 01-11-19 283 0.048 +/- 0.005 07-12-19 282 0.020 +/- 0.003 01-18-19 282 0.039 +/- 0.004 07-19-19 284 0.020 +/- 0.003 01-24-19 244 0.028 +/- 0.004 07-26-19 271 0.023 +/- 0.004 02-01-19 323 0.039 +/- 0.004 08-02-19 271 0.027 +/- 0.004 02-08-19 284 0.025 +/- 0.004 08-09-19 272 0.029 +/- 0.004 02-15-19 280 0.022 +/- 0.004 08-15-19 235 0.035 +/- 0.005 02-22-19 289 0.034 +/- 0.004 08-23-19 308 0.024 +/- 0.004 03-01-19 277 0.030 +/- 0.004 08-30-19 270 0.020 +/- 0.004 03-08-19 282 0.033 +/- 0.004 09-06-19 272 0.025 +/- 0.004 03-15-19 280 0.029 +/- 0.004 09-13-19 269 0.026 +/- 0.004 03-22-19 283 0.025 +/- 0.004 09-20-19 271 0.022 +/- 0.004 03-29-19 283 0.022 +/- 0.004 09-26-19 232 0.026 +/- 0.004 1st Quarter Mean +/- s.d. 0.031 +/- 0.008 3rd Quarter Mean +/- s.d. 0.025 +/- 0.004 04-05-19 282 0.021 +/- 0.004 10-04-19 310 0.017 +/- 0.003 04-12-19 283 0.011 +/- 0.003 10-11-19 271 0.026 +/- 0.004 04-19-19 282 0.013 +/- 0.003 10-19-19 310 0.021 +/- 0.003 04-26-19 283 0.017 +/- 0.003 10-24-19 194 0.028 +/- 0.005 05-03-19 286 0.006 +/- 0.003 11-01-19 313 0.018 +/- 0.003 05-10-19 279 0.016 +/- 0.003 11-08-19 270 0.025 +/- 0.004 05-17-19 284 0.023 +/- 0.004 11-15-19 271 0.036 +/- 0.004 05-24-19 284 0.008 +/- 0.003 11-22-19 272 0.035 +/- 0.004 05-30-19 238 0.006 +/- 0.003 11-27-19 193 0.026 +/- 0.005 06-07-19 330 0.023 +/- 0.003 12-06-19 349 0.016 +/- 0.003 06-14-19 275 0.021 +/- 0.004 12-12-19 237 0.040 +/- 0.005 06-21-19 282 0.024 +/- 0.004 12-20-19 317 0.039 +/- 0.004 06-28-19 285 0.018 +/- 0.003 12-27-19 278 0.043 +/- 0.005 01-03-20 277 0.032 +/- 0.004 2nd Quarter Mean +/- s.d. 0.016 +/- 0.006 4th Quarter Mean +/- s.d. 0.029 +/- 0.009 Cumulative Average 0.025 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

4-1

Table 5. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 8 .

Location: D-7 (Shellsburg)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 272 0.033 +/- 0.004 07-05-19 302 0.025 +/- 0.003 01-11-19 272 0.040 +/- 0.005 07-12-19 305 0.016 +/- 0.003 01-18-19 271 0.040 +/- 0.004 07-19-19 307 0.020 +/- 0.003 01-24-19 234 0.025 +/- 0.004 07-26-19 292 0.026 +/- 0.004 02-01-19 310 0.044 +/- 0.004 08-02-19 289 0.028 +/- 0.004 02-08-19 270 0.028 +/- 0.004 08-09-19 292 0.040 +/- 0.004 02-15-19 307 0.022 +/- 0.003 08-15-19 249 0.031 +/- 0.004 02-22-19 311 0.018 +/- 0.003 08-23-19 334 0.024 +/- 0.003 03-01-19 301 0.029 +/- 0.004 08-30-19 290 0.017 +/- 0.003 03-08-19 304 0.029 +/- 0.004 09-06-19 293 0.033 +/- 0.004 03-15-19 303 0.032 +/- 0.004 09-13-19 290 0.034 +/- 0.004 03-22-19 306 0.021 +/- 0.003 09-20-19 292 0.034 +/- 0.004 03-29-19 306 0.019 +/- 0.004 09-26-19 247 0.031 +/- 0.004 1st Quarter Mean +/- s.d. 0.029 +/- 0.008 3rd Quarter Mean +/- s.d. 0.028 +/- 0.007 04-05-19 305 0.023 +/- 0.004 10-04-19 334 0.015 +/- 0.003 04-12-19 305 0.015 +/- 0.003 10-11-19 294 0.022 +/- 0.004 04-19-19 305 0.011 +/- 0.003 10-19-19 333 0.021 +/- 0.003 04-26-19 306 0.017 +/- 0.003 10-24-19 208 0.031 +/- 0.005 05-03-19 306 0.012 +/- 0.003 11-01-19 336 0.018 +/- 0.003 05-10-19 304 0.017 +/- 0.003 11-08-19 290 0.024 +/- 0.004 05-17-19 309 0.023 +/- 0.003 11-15-19 291 0.039 +/- 0.004 05-24-19 304 0.007 +/- 0.003 11-22-19 291 0.035 +/- 0.004 05-30-19 260 0.010 +/- 0.003 11-27-19 207 0.024 +/- 0.005 06-07-19 354 0.023 +/- 0.003 12-06-19 375 0.019 +/- 0.003 06-14-19 300 0.021 +/- 0.003 12-12-19 249 0.037 +/- 0.005 06-21-19 305 0.020 +/- 0.003 12-20-19 333 0.037 +/- 0.004 06-28-19 309 0.019 +/- 0.003 12-27-19 298 0.044 +/- 0.004 01-03-20 294 0.026 +/- 0.004 2nd Quarter Mean +/- s.d. 0.017 +/- 0.006 4th Quarter Mean +/- s.d. 0.028 +/- 0.009 Cumulative Average 0.025 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

5-1

8 Table 6. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .

Location: D-11 (Toddville)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 277 0.041 +/- 0.004 07-05-19 274 0.023 +/- 0.004 01-11-19 280 0.038 +/- 0.004 07-12-19 276 0.023 +/- 0.004 01-18-19 279 0.035 +/- 0.004 07-19-19 278 0.022 +/- 0.004 01-24-19 241 0.024 +/- 0.004 07-26-19 278 0.025 +/- 0.004 02-01-19 320 0.037 +/- 0.004 08-02-19 276 0.028 +/- 0.004 02-08-19 282 0.016 +/- 0.003 08-09-19 277 0.032 +/- 0.004 02-15-19 277 0.016 +/- 0.003 08-15-19 240 0.034 +/- 0.005 02-22-19 289 0.031 +/- 0.004 08-23-19 315 0.023 +/- 0.003 03-01-19 272 0.032 +/- 0.004 08-30-19 276 0.022 +/- 0.004 03-08-19 279 0.030 +/- 0.004 09-06-19 278 0.034 +/- 0.004 03-15-19 278 0.028 +/- 0.004 09-13-19 276 0.025 +/- 0.004 03-22-19 280 0.024 +/- 0.004 09-20-19 278 0.036 +/- 0.004 03-29-19 NSb 09-26-19 239 0.033 +/- 0.005 1st Quarter Mean +/- s.d. 0.029 +/- 0.008 3rd Quarter Mean +/- s.d. 0.028 +/- 0.005 04-05-19 NSb 10-04-19 313 0.019 +/- 0.003 04-12-19 280 0.013 +/- 0.004 10-11-19 276 0.026 +/- 0.004 04-19-19 280 0.012 +/- 0.003 10-19-19 317 0.020 +/- 0.003 04-26-19 280 0.016 +/- 0.003 10-24-19 198 0.030 +/- 0.005 05-03-19 280 0.013 +/- 0.003 11-01-19 320 0.020 +/- 0.003 05-10-19 273 0.016 +/- 0.003 11-08-19 276 0.026 +/- 0.004 05-17-19 278 0.027 +/- 0.004 11-15-19 277 0.038 +/- 0.004 05-24-19 280 0.013 +/- 0.003 11-22-19 277 0.034 +/- 0.004 05-30-19 233 0.011 +/- 0.004 11-27-19 197 0.023 +/- 0.005 06-07-19 324 0.026 +/- 0.003 12-06-19 357 0.019 +/- 0.003 06-14-19 269 0.023 +/- 0.004 12-12-19 237 0.040 +/- 0.005 06-21-19 276 0.020 +/- 0.004 12-20-19 317 0.043 +/- 0.004 06-28-19 280 0.023 +/- 0.004 12-27-19 278 0.049 +/- 0.005 01-03-20 277 0.023 +/- 0.004 2nd Quarter Mean +/- s.d. 0.018 +/- 0.006 4th Quarter Mean +/- s.d. 0.029 +/- 0.010 Cumulative Average 0.026 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

b No sample; pump problems.

6-1

Table 7. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 8 .

Location: D-13 (Alburnett)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 271 0.032 +/- 0.004 07-05-19 274 0.025 +/- 0.004 01-11-19 274 0.044 +/- 0.005 07-12-19 276 0.018 +/- 0.003 01-18-19 274 0.034 +/- 0.004 07-19-19 278 0.017 +/- 0.003 01-24-19 236 0.025 +/- 0.004 07-26-19 277 0.019 +/- 0.004 02-01-19 314 0.046 +/- 0.004 08-02-19 277 0.024 +/- 0.004 02-08-19 276 0.027 +/- 0.004 08-09-19 277 0.028 +/- 0.004 02-15-19 272 0.028 +/- 0.004 08-15-19 240 0.031 +/- 0.004 02-22-19 282 0.034 +/- 0.004 08-23-19 315 0.024 +/- 0.004 03-01-19 266 0.031 +/- 0.004 08-30-19 276 0.019 +/- 0.003 03-08-19 274 0.039 +/- 0.004 09-06-19 278 0.026 +/- 0.004 03-15-19 272 0.032 +/- 0.004 09-13-19 266 0.027 +/- 0.004 03-22-19 277 0.020 +/- 0.003 09-20-19 269 0.037 +/- 0.005 03-29-19 277 0.017 +/- 0.004 09-26-19 231 0.028 +/- 0.004 1st Quarter Mean +/- s.d. 0.031 +/- 0.008 3rd Quarter Mean +/- s.d. 0.025 +/- 0.006 04-05-19 277 0.019 +/- 0.004 10-04-19 305 0.018 +/- 0.003 04-12-19 277 0.012 +/- 0.004 10-11-19 268 0.023 +/- 0.004 04-19-19 277 0.011 +/- 0.003 10-19-19 307 0.019 +/- 0.003 04-26-19 277 0.015 +/- 0.003 10-24-19 192 0.030 +/- 0.005 05-03-19 280 0.011 +/- 0.003 11-01-19 310 0.016 +/- 0.003 05-10-19 273 0.016 +/- 0.003 11-08-19 267 0.025 +/- 0.004 05-17-19 278 0.020 +/- 0.003 11-15-19 269 0.036 +/- 0.004 05-24-19 278 0.008 +/- 0.003 11-22-19 269 0.037 +/- 0.004 05-30-19 233 0.009 +/- 0.003 11-27-19 191 0.019 +/- 0.005 06-07-19 324 0.020 +/- 0.003 12-06-19 346 0.019 +/- 0.003 06-14-19 269 0.019 +/- 0.004 12-12-19 230 0.036 +/- 0.005 06-21-19 277 0.017 +/- 0.004 12-20-19 307 0.043 +/- 0.004 06-28-19 280 0.018 +/- 0.003 12-27-19 269 0.046 +/- 0.005 01-03-20 268 0.032 +/- 0.004 2nd Quarter Mean +/- s.d. 0.015 +/- 0.004 4th Quarter Mean+/- s.d. 0.028 +/- 0.010 Cumulative Average 0.025 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

7-1

Table 8. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 8 .

Location: D-15 (On-site, north)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 264 0.025 +/- 0.004 07-05-19 271 0.026 +/- 0.004 01-11-19 266 0.047 +/- 0.005 07-12-19 273 0.019 +/- 0.003 01-18-19 265 0.036 +/- 0.004 07-19-19 276 0.025 +/- 0.004 01-24-19 229 0.030 +/- 0.004 07-26-19 274 0.024 +/- 0.004 02-01-19 303 0.042 +/- 0.004 08-02-19 274 0.021 +/- 0.003 02-08-19 267 0.025 +/- 0.004 08-09-19 274 0.034 +/- 0.004 02-15-19 264 0.030 +/- 0.004 08-15-19 236 0.031 +/- 0.005 02-22-19 278 0.037 +/- 0.004 08-23-19 313 0.021 +/- 0.003 03-01-19 254 0.026 +/- 0.004 08-30-19 273 0.021 +/- 0.004 03-08-19 265 0.037 +/- 0.004 09-06-19 275 0.033 +/- 0.004 03-15-19 263 0.036 +/- 0.004 09-13-19 272 0.034 +/- 0.004 03-22-19 266 0.026 +/- 0.004 09-20-19 305 0.037 +/- 0.004 03-29-19 274 0.023 +/- 0.004 09-26-19 269 0.030 +/- 0.004 1st Quarter Mean+/- s.d. 0.032 +/- 0.007 3rd Quarter Mean +/- s.d. 0.028 +/- 0.006 04-05-19 274 0.019 +/- 0.004 10-04-19 341 0.018 +/- 0.003 04-12-19 274 0.014 +/- 0.004 10-11-19 305 0.028 +/- 0.004 04-19-19 274 0.011 +/- 0.003 10-19-19 349 0.022 +/- 0.003 04-26-19 275 0.021 +/- 0.004 10-24-19 218 0.028 +/- 0.005 05-03-19 276 0.013 +/- 0.003 11-01-19 353 0.019 +/- 0.003 05-10-19 271 0.018 +/- 0.003 11-08-19 304 0.023 +/- 0.004 05-17-19 268 0.024 +/- 0.004 11-15-19 306 0.038 +/- 0.004 05-24-19 279 0.007 +/- 0.003 11-22-19 306 0.038 +/- 0.004 05-30-19 227 0.010 +/- 0.004 11-27-19 217 0.026 +/- 0.004 06-07-19 319 0.024 +/- 0.003 12-06-19 393 0.019 +/- 0.003 06-14-19 268 0.024 +/- 0.004 12-12-19 261 0.040 +/- 0.005 06-21-19 274 0.019 +/- 0.004 12-20-19 350 0.040 +/- 0.004 06-28-19 277 0.017 +/- 0.003 12-27-19 305 0.042 +/- 0.004 01-03-20 307 0.023 +/- 0.004 2nd Quarter Mean+/- s.d. 0.017 +/- 0.006 4th Quarter Mean +/- s.d. 0.029 +/- 0.009 Cumulative Average 0.027 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

8-1

Table 9. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 8 .

Location: D-16 (On-site)

Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 270 0.028 +/- 0.004 07-05-19 274 0.027 +/- 0.004 01-11-19 271 0.036 +/- 0.004 07-12-19 276 0.021 +/- 0.003 01-18-19 271 0.034 +/- 0.004 07-19-19 278 0.025 +/- 0.004 01-24-19 234 0.030 +/- 0.004 07-26-19 277 0.025 +/- 0.004 02-01-19 317 NSb 08-02-19 277 0.026 +/- 0.004 02-08-19 265 0.018 +/- 0.003 08-09-19 277 0.041 +/- 0.004 02-15-19 273 0.027 +/- 0.004 08-15-19 238 0.033 +/- 0.005 02-22-19 286 0.030 +/- 0.004 08-23-19 317 0.023 +/- 0.003 03-01-19 265 0.033 +/- 0.004 08-30-19 276 0.022 +/- 0.004 03-08-19 276 0.040 +/- 0.004 09-06-19 278 0.032 +/- 0.004 03-15-19 275 0.036 +/- 0.004 09-13-19 277 0.034 +/- 0.004 03-22-19 277 0.029 +/- 0.004 09-20-19 277 0.038 +/- 0.005 03-29-19 277 0.020 +/- 0.004 09-26-19 244 0.033 +/- 0.004 1st Quarter Mean +/- s.d. 0.030 +/- 0.006 3rd Quarter Mean +/- s.d. 0.029 +/- 0.007 04-05-19 277 0.021 +/- 0.004 10-04-19 309 0.017 +/- 0.003 04-12-19 277 0.019 +/- 0.004 10-11-19 276 0.024 +/- 0.004 04-19-19 277 0.012 +/- 0.003 10-19-19 317 0.020 +/- 0.003 04-26-19 277 0.022 +/- 0.004 10-24-19 198 0.026 +/- 0.005 05-03-19 279 0.011 +/- 0.003 11-01-19 320 0.026 +/- 0.003 05-10-19 274 0.020 +/- 0.003 11-08-19 276 0.025 +/- 0.004 05-17-19 277 0.024 +/- 0.004 11-15-19 277 0.037 +/- 0.004 05-24-19 285 0.008 +/- 0.003 11-22-19 277 0.029 +/- 0.004 05-30-19 229 0.012 +/- 0.004 11-27-19 197 0.026 +/- 0.005 06-07-19 321 0.025 +/- 0.003 12-06-19 357 0.018 +/- 0.003 06-14-19 272 0.020 +/- 0.004 12-12-19 237 0.041 +/- 0.005 06-21-19 276 0.018 +/- 0.004 12-20-19 317 0.033 +/- 0.004 06-28-19 280 0.019 +/- 0.003 12-27-19 277 0.046 +/- 0.005 01-03-20 284 0.028 +/- 0.004 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.028 +/- 0.008 Cumulative Average 0.026 a lodine-131 concentrations are< 0.03 pCi/m 3 unless noted otherwise.

b Sample very light; discarded per station request.

9-1

8 Table 10. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 .

Location: D-40 (Wickiup Hill)

Units: pCifm 3 Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 Required LLD 0.010 01-04-19 299 0.032 +/- 0.004 07-05-19 291 0.025 +/- 0.004 01-11-19 303 0.017 +/- 0.003 07-12-19 293 0.018 +/- 0.003 01-18-19 302 0.039 +/- 0.004 07-19-19 296 0.023 +/- 0.004 01-24-19 261 0.028 +/- 0.004 07-26-19 295 0.022 +/- 0.004 02-01-19 346 0.039 +/- 0.004 08-02-19 292 0.027 +/- 0.004 02-08-19 307 0.024 +/- 0.003 08-09-19 295 0.030 +/- 0.004 02-15-19 298 0.028 +/- 0.004 08-15-19 255 0.027 +/- 0.004 02-22-19 313 0.032 +/- 0.004 08-23-19 334 0.020 +/- 0.003 03-01-19 295 0.060 +/- 0.005 08-30-19 293 0.018 +/- 0.003 03-08-19 305 0.030 +/- 0.004 09-06-19 296 0.030 +/- 0.004 03-15-19 296 0.030 +/- 0.004 09-13-19 293 0.035 +/- 0.004 03-22-19 304 0.027 +/- 0.004 09-20-19 295 0.033 +/- 0.004 03-29-19 303 0.017 +/- 0.003 09-26-19 254 0.029 +/- 0.004 1st Quarter Mean +/- s.d. 0.031 +/- 0.011 3rd Quarter Mean +/- s.d. 0.026 +/- 0.005 04-05-19 302 0.020 +/- 0.004 10-04-19 333 0.016 +/- 0.003 04-12-19 303 0.016 +/- 0.003 10-11-19 268 0.026 +/- 0.004 04-19-19 302 0.014 +/- 0.003 10-19-19 307 0.023 +/- 0.004 04-26-19 303 0.018 +/- 0.003 10-24-19 191 0.027 +/- 0.005 05-03-19 298 0.010 +/- 0.003 11-01-19 310 0.020 +/- 0.003 05-10-19 290 0.019 +/- 0.003 11-08-19 267 0.024 +/- 0.004 05-17-19 295 0.022 +/- 0.003 11-15-19 269 0.035 +/- 0.004 05-24-19 299 0.011 +/- 0.003 11-22-19 269 0.038 +/- 0.004 05-30-19 262 0.011 +/- 0.003 11-27-19 191 0.027 +/- 0.005 06-07-19 345 0.024 +/- 0.003 12-06-19 345 0.017 +/- 0.003 06-14-19 284 0.019 +/- 0.003 12-12-19 230 0.041 +/- 0.005 06-21-19 294 0.015 +/- 0.003 12-20-19 307 0.045 +/- 0.004 06-28-19 297 0.019 +/- 0.003 12-27-19 269 0.047 +/- 0.005 01-03-20 269 0.030 +/- 0.004 2nd Quarter Mean +/- s.d. 0.017 +/- 0.004 4th Quarter Mean +/- s.d. 0.030 +/- 0.010 Cumulative Average 0.026 a lodine-131 concentrations are< 0.03 pCifm 3 unless noted otherwise.

10-1

Table 11. Airborne particulates, analyses for gamma-emitting isotopes.

0 Collection: Quarterly Composite Units: pCi/m Location D-3 Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Lab Code DAP- 1296 OAP- 2689 DAP- 4075 DAP- 5052 Volume (m 3 ) 3684 3565 3537 3960 Be-7 0.083 +/- 0.015 0.075 +/- 0.018 0.091 +/- 0.019 0.068 +/- 0.013 Mn-54 < 0.0006 < 0.0012 < 0.0010 < 0.0007 Fe-59 < 0.0010 < 0.0011 < 0.0024 < 0.0007 Co-58 < 0.0009 < 0.0009 < 0.0011 < 0.0004 Co-60 < 0.0010 < 0.0007 < 0.0009 < 0.0005 Zn-65 < 0.0008 < 0.0008 < 0.0012 < 0.0007 Nb-95 < 0.0010 < 0.0015 < 0.0010 < 0.0012 Zr-95 < 0.0010 < 0.0021 < 0.0022 < 0.0017 Ru-103 < 0.0008 < 0.0008 < 0.0016 < 0.0011 Ru-106 < 0.0064 < 0.0075 < 0.0081 < 0.0064 Cs-134 < 0.0010 < 0.0012 < 0.0010 < 0.0009 Cs-137 < 0.0007 < 0.0009 < 0.0011 < 0.0007 Ce-141 < 0.0017 < 0.0017 < 0.0017 < 0.0011 Ce-144 < 0.0045 < 0.0043 < 0.0048 < 0.0039 Location D-4 Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Lab Code DAP- 1297 OAP- 2691 DAP- 4076 DAP- 5053 3

Volume (m ) 4021 3869 3981 4320 Be-7 0.083 +/- 0.014 0.068 +/- 0.016 0.079 +/- 0.014 0.058 +/- 0.012 Mn-54 < 0.0007 < 0.0009 < 0.0009 < 0.0005 Fe-59 < 0.0014 < 0.0024 < 0.0021 < 0.0009 Co-58 < 0.0005 < 0.0009 < 0.0005 < 0.0005 Co-60 < 0.0008 < 0.0008 < 0.0007 < 0.0004 Zn-65 < 0.0014 < 0.0013 < 0.0016 < 0.0010 Nb-95 < 0.0010 < 0.0010 < 0.0010 < 0.0008 Zr-95 < 0.0015 < 0.0014 < 0.0014 < 0.0016 Ru-103 < 0.0005 < 0.0009 < 0.0011 < 0.0009 Ru-106 < 0.0054 < 0.0073 < 0.0057 < 0.0044 Cs-134 < 0.0007 < 0.0014 < 0.0010 < 0.0007 Cs-137 < 0.0007 < 0.0007 < 0.0006 < 0.0005 Ce-141 < 0.0015 < 0.0015 < 0.0014 < 0.0015 Ce-144 < 0.0032 < 0.0029 < 0.0035 < 0.0042 Location D-5A Lab Code DAP- 1298 OAP- 2692 DAP- 4077 DAP- 5054 3

Volume (m ) 3697 3825 3726 3996 Be-7 0.070 +/- 0.015 0.071 +/- 0.016 0.090 +/- 0.015 0.058 +/- 0.011 Mn-54 < 0.0009 < 0.0009 < 0.0008 < 0.0006 Fe-59 < 0.0015 < 0.0015 < 0.0020 < 0.0012 Co-58 < 0.0007 < 0.0007 < 0.0007 < 0.0007 Co-60 < 0.0006 < 0.0004 < 0.0007 < 0.0004 Zn-65 < 0.0006 < 0.0016 < 0.0016 < 0.0007 Nb-95 < 0.0008 < 0.0009 < 0.0009 < 0.0009 Zr-95 < 0.0010 < 0.0017 < 0.0015 < 0.0019 Ru-103 < 0.0008 < 0.0011 < 0.0011 < 0.0006 Ru-106 < 0.0057 < 0.0074 < 0.0069 < 0.0040 Cs-134 < 0.0010 < 0.0012 < 0.0009 < 0.0009 Cs-137 < 0.0006 < 0.0006 < 0.0008 < 0.0005 Ce-141 < 0.0010 < 0.0015 < 0.0013 < 0.0011 Ce-144 < 0.0041 < 0.0034 < 0.0035 < 0.0029 11-1

Table 11. Airborne particulates, analyses for gamma-emitting isotopes.

Collection: Quarterly Composite Units: pCi/m, Location D-6 Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Lab Code DAP- 1299 DAP- 2693 DAP- 4078 DAP- 5055 3

Volume (m ) 3670 3674 3516 3861 Be-7 0.084 +/- 0.014 0.071 +/- 0.015 0.067 +/- 0.015 0.050 +/- 0.011 Mn-54 < 0.0010 < 0.0009 < 0.0008 < 0.0006 Fe-59 < 0.0009 < 0.0016 < 0.0015 < 0.0010 Co-58 < 0.0010 < 0.0007 < 0.0009 < 0.0004 Co-60 < 0.0010 < 0.0007 < 0.0009 < 0.0006 Zn-65 < 0.0008 < 0.0014 < 0.0014 < 0.0006 Nb-95 < 0.0013 < 0.0010 < 0.0014 < 0.0012 Zr-95 < 0.0013 < 0.0018 < 0.0021 < 0.0010 Ru-103 < 0.0013 < 0.0010 < 0.0011 < 0.0008 Ru-106 < 0.0080 < 0.0093 < 0.0064 < 0.0036 Cs-134 < 0.0011 < 0.0011 < 0.0010 < 0.0010 Cs-137 < 0.0010 < 0.0007 < 0.0006 < 0.0004 Ce-141 < 0.0014 < 0.0019 < 0.0015 < 0.0017 Ce-144 < 0.0053 < 0.0032 < 0.0034 < 0.0027 Location D-7 Lab Code DAP- 1300 DAP- 2694 DAP- 4079 DAP- 5056 Volume (m 3 ) 3765 3973 3782 4135 Be-7 0.078 +/- 0.014 0.073 +/- 0.014 0.077 +/- 0.014 0.054 +/- 0.011 Mn-54 < 0.0009 < 0.0010 < 0.0008 < 0.0004 Fe-59 < 0.0015 < 0.0025 < 0.0022 < 0.0011 Co-58 < 0.0007 < 0.0008 < 0.0005 < 0.0005 Co-60 < 0.0006 < 0.0007 < 0.0009 < 0.0005 Zn-65 < 0.0009 < 0.0007 < 0.0011 < 0.0010 Nb-95 < 0.0008 < 0.0008 < 0.0010 < 0.0009 Zr-95 < 0.0017 < 0.0006 < 0.0012 < 0.0011 Ru-103 < 0.0010 < 0.0006 < 0.0011 < 0.0012 Ru-106 < 0.0045 < 0.0060 < 0.0078 < 0.0050 Cs-134 < 0.0009 < 0.0010 < 0.0010 < 0.0008 Cs-137 < 0.0006 < 0.0009 < 0.0005 < 0.0008 Ce-141 < 0.0011 < 0.0013 < 0.0015 < 0.0012 Ce-144 < 0.0051 < 0.0036 < 0.0035 < 0.0037 Location D-11 Lab Code DAP- 1301 DAP- 2695 DAP- 4080 DAP- 5057 Volume (m 3 ) 3353 3334 3560 3916 Be-7 0.076 +/- 0.022 0.078 +/- 0.019 0.075 +/- 0.015 0.060 +/- 0.013 Mn-54 < 0.0013 < 0.0010 < 0.0009 < 0.0007 Fe-59 < 0.0021 < 0.0027 < 0.0015 < 0.0011 Co-58 < 0.0012 < 0.0010 < 0.0008 < 0.0008 Co-60 < 0.0012 < 0.0006 < 0.0011 < 0.0005 Zn-65 < 0.0032 < 0.0009 < 0.0014 < 0.0005 Nb-95 < 0.0036 < 0.0015 < 0.0014 < 0.0010 Zr-95 < 0.0024 < 0.0015 < 0.0020 < 0.0016 Ru-103 < 0.0016 < 0.0014 < 0.0013 < 0.0009 Ru-106 < 0.0124 < 0.0092 < 0.0063 < 0.0066 Cs-134 < 0.0012 < 0.0011 < 0.0012 < 0.0007 Cs-137 < 0.0009 < 0.0005 < 0.0005 < 0.0005 Ce-141 < 0.0032 < 0.0017 < 0.0016 < 0.0011 Ce-144 < 0.0052 < 0.0040 < 0.0035 < 0.0034 11-2

Table 11. Airborne particulates, analyses for gamma-emitting isotopes.

Collection: Quarterly Composite Units: pCi/m" Location D-13 Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Lab Code DAP- 1302 DAP- 2696 DAP- 4081 DAP- 5058 Volume (m 3 ) 3565 3600 3534 3797 Be-7 0.085+/- 0.018 0.060 +/- 0.014 0.063+/- 0.013 0.045 +/- 0.015 Mn-54 < 0.0011 < 0.0011 < 0.0011 < 0.0007 Fe-59 < 0.0010 < 0.0023 < 0.0024 < 0.0014 Co-58 < 0.0006 < 0.0011 < 0.0008 < 0.0006 Co-60 < 0.0008 < 0.0005 < 0.0009 < 0.0010 Zn-65 < 0.0010 < 0.0012 < 0.0008 < 0.0007 Nb-95 < 0.0018 < 0.0009 < 0.0014 < 0.0016 Zr-95 < 0.0008 < 0.0022 < 0.0020 < 0.0020 Ru-103 < 0.0011 < 0.0009 < 0.0013 < 0.0011 Ru-106 < 0.0083 < 0.0074 < 0.0068 < 0.0061 Cs-134 < 0.0011 < 0.0010 < 0.0012 < 0.0010 Cs-137 < 0.0009 < 0.0010 < 0.0009 < 0.0007 Ce-141 < 0.0018 < 0.0015 < 0.0015 < 0.0018 Ce-144 < 0.0061 < 0.0039 < 0.0037 < 0.0029 Location D-15 Lab Code DAP- 1303 DAP- 2697 DAP- 4082 DAP- 5059 Volume (m") 3458 3556 3585 4316 Be-7 0.088 +/- 0.016 0.067 +/- 0.016 0.067 +/- 0.014 0.066 +/- 0.015 Mn-54 < 0.0007 < 0.0012 < 0.0009 < 0.0008 Fe-59 < 0.0016 < 0.0028 < 0.0023 < 0.0028 Co-58 < 0.0006 < 0.0006 < 0.0009 < 0.0006 Co-60 < 0.0005 < 0.0009 < 0.0008 < 0.0010 Zn-65 < 0.0018 < 0.0017 < 0.0014 < 0.0019 Nb-95 < 0.0015 < 0.0009 < 0.0015 < 0.0005 Zr-95 < 0.0012 < 0.0016 < 0.0017 < 0.0012 Ru-103 < 0.0007 < 0.0009 < 0.0011 < 0.0011 Ru-106 < 0.0076 < 0.0090 < 0.0083 < 0.0068 Cs-134 < 0.0009 < 0.0010 < 0.0008 < 0.0009 Cs-137 < 0.0010 < 0.0006 < 0.0009 < 0.0008 Ce-141 < 0.0019 < 0.0018 < 0.0018 < 0.0019 Ce-144 < 0.0031 < 0.0042 < 0.0040 < 0.0045 Location D-16 Lab Code DAP- 1304 DAP- 2698 DAP- 4083 DAP- 5060 Volume (m 3 ) 3557 3602 3565 3918 Be-7 0.074 +/- 0.018 0.080 +/- 0.016 0.077 +/- 0.017 0.063 +/- 0.012 Mn-54 < 0.0011 < 0.0009 < 0.0008 < 0.0011 Fe-59 < 0.0012 < 0.0020 < 0.0018 < 0.0013 Co-58 < 0.0011 < 0.0009 < 0.0010 < 0.0006 Co-60 < 0.0011 < 0.0004 < 0.0009 < 0.0009 Zn-65 < 0.0028 < 0.0016 < 0.0014 < 0.0007 Nb-95 < 0.0016 < 0.0017 < 0.0015 < 0.0007 Zr-95 < 0.0021 < 0.0017 < 0.0013 < 0.0013 Ru-103 < 0.0009 < 0.0009 < 0.0012 < 0.0012 Ru-106 < 0.0079 < 0.0062 < 0.0087 < 0.0066 Cs-134 < 0.0011 < 0.0011 < 0.0011 < 0.0010 Cs-137 < 0.0011 < 0.0006 < 0.0008 < 0.0011 Ce-141 < 0.0028 < 0.0018 < 0.0017 < 0.0013 Ce-144 < 0.0063 < 0.0035 < 0.0035 < 0.0050 11-3

Table 11. Airborne particulates, analyses for gamma-emitting isotopes.

3 Collection: Quarterly Composite Units: pCi/m Location D-40 Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Lab Code DAP- 1305 DAP- 2699 DAP- 4084 DAP- 5062 Volume (m 3 ) 3931 3875 3780 3824*

Be-7 0.074 +/- 0.016 0.081 +/- 0.015 0.080 +/- 0.017 0.053 +/- 0.011 Mn-54 < 0.0005 < 0.0010 < 0.0004 < 0.0005 Fe-59 < 0.0016 < 0.0015 < 0.0026 < 0.0014 Co-58 < 0.0004 < 0.0008 < 0.0005 < 0.0005 Co-60 < 0.0005 < 0.0007 < 0.0011 < 0.0005 Zn-65 < 0.0016 < 0.0007 < 0.0011 < 0.0006 Nb-95 < 0.0006 < 0.0010 < 0.0015 < 0.0010 Zr-95 < 0.0008 < 0.0013 < 0.0017 < 0.0011 Ru-103 < 0.0013 < 0.0010 < 0.0009 < 0.0009 Ru-106 < 0.0060 < 0.0079 < 0.0068 < 0.0054 Cs-134 < 0.0009 < 0.0009 < 0.0011 < 0.0008 Cs-137 < 0.0008 < 0.0007 < 0.0007 < 0.0005 Ce-141 < 0.0014 < 0.0015 < 0.0014 < 0.0009 Ce-144 < 0.0032 < 0.0036 < 0.0035 < 0.0041 11-4

Table 12. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD).

Quarterly collection. Units: mR/91 days Control Locations 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

D-1 15.6+/-1.7 14.4 +/- 1.7 16.6+/-1.7 22.2 +/- 0.8 D-2 14.7+/-1.6 13.4 +/- 1.2 15.6+/-1.1 22.2+/-1.0 D-3 13.9 +/- 2.2 13.4 +/- 1.2 14.5 +/- 0.6 23.5 +/- 1.5 D-4 15.0 +/- 0.4 14.7+/-1.6 16.5+/-1.7 24.3 +/- 1.3 D-5 17.3 +/-2.1 16.9+/-1.1 18.6+/-1.3 27.4+/-1.5 D-5A 15.9+/-1.2 18.8+/-1.1 16.5 +/- 0.7 20.6 +/- 0.8 D-6 15.1 +/-1.3 15.6 +/- 1.2 15.6 +/- 0.8 25.0 +/- 1.0 D-7 12.7+/-1.7 14.4+/-1.2 13.4 +/- 0.6 23.8 +/- 1.0 D-8 18.0+/-1.6 16.9+/-1.7 18.9+/-1.1 26.2 +/- 1.7 D-10 17.1 +/- 1.6 16.8+/-1.7 18.3+/-1.0 24.6 +/- 1.4 D-11 13.4 +/- 1.4 13.5 +/- 1.7 13.4 +/- 0.7 21.5+/-1.1 D-13 15.8+/-1.4 15.4+/-1.6 16.4 +/- 0.8 23.2 +/- 1.4 Mean+/- s.d. 15.4+/-1.6 15.4+/-1.7 16.2+/-1.8 23.7 +/- 1.9 Within 0.5 mi. of Stack D-15 14.9+/-1.6 16.0+/-1.0 15.0+/-1.0 21.5 +/- 0.8 D-16 16.1 +/-1.7 16.7+/-1.3 17.6 +/- 1.1 25.4+/-1.3 D-17 16.9+/-1.3 ND8 19.5+/-1.0 31.2 +/- 1.2 D-18 15.1 +/- 1.9 17.2+/-1.1 17.3+/-1.4 25.7+/-1.0 D-19 14.8+/-1.7 16.0+/-1.1 15.9+/-1.2 24.8 +/- 0.9 D-20 17.9+/-1.5 16.6+/-1.3 18.4 +/- 1.1 26.8 +/- 1.6 D-21 15.9 +/- 1.3 18.0+/-1.5 18.1 +/-0.8 27.5+/-1.3 D-22 16.6+/-1.6 18.2 +/- 1.0 16.6 +/- 0.9 26.8 +/- 1.0 D-23 13.0+/-1.7 17.3+/-1.7 13.8+/-1.0 21.2+/-1.1 D-28 16.6+/-1.6 19.7 +/- 1.2 19.4 +/- 0.9 29.1 +/- 1.4 D-29 16.3+/-1.4 18.8+/-1.6 19.9 +/- 1.0 28.9+/-1.5 D-30 14.4+/-1.6 21.8 +/- 2.8 17.3+/-1.3 25.4 +/- 2.3 D-31 15.4+/-1.5 19.7 +/- 2.0 19.4+/-1.3 29.4+/-1.8 D-32 16.8+/-1.6 21.2+/-1.6 18.3 +/- 1.1 25.6 +/- 1.3 D-82 16.3+/-1.5 15.7 +/-2.0 17.0 +/- 0.9 24.7 +/- 1.5 D-83 12.9+/-1.4 18.0+/-1.4 15.5 +/- 0.7 21.6 +/- 1.3 D-84 15.6+/-1.4 18.0+/-1.6 16.5 +/- 1.1 26.4+/-1.2 D-85 16.5+/-1.1 20.4+/-1.9 18.4 +/- 0.5 24.9+/-1.3 D-86 14.9+/-1.8 14.0 +/- 2.6 15.6 +/- 1.0 22.3+/-1.4 D-91 16.0+/-1.6 19.7 +/- 2.2 17.6 +/- 0.9 25.3 +/- 2.0 Mean+/- s.d. 15.7+/-1.3 18.1 +/-2.0 17.4+/-1.7 25.7 +/- 2.7 8

"ND" =No data; see Table 2.0, Program Deviations.

12-1

Table 12. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD).

Quarterly collection. Units: mR/91 days Within 1.0 mi. of 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Stack D-43 13.1 +/- 1.4 14.3 +/- 2.2 16.3+/-1.2 22.1 +/- 0.8 D-44 14.5+/-1.4 17.9+/-1.1 17.5 +/- 0.9 26.5 +/- 0.9 D-45 13.7 +/- 1.4 15.2 +/- 1.5 15.8 +/- 0.9 23.7+/-1.4 D-46 15.3 +/- 1.8 19.0+/-2.1 18.8+/-1.3 24.1 +/- 1.6 D-47 14.5+/-1.5 18.0+/-1.2 17.8+/-1.1 25.6+/-1.4 D-48 14.4+/-1.8 20.9+/-1.3 18.6 +/- 1.5 24.2 +/- 1.1 Mean+/- s.d. 14.3 +/- 0.8 17.5 +/- 2.4 17.5+/-1.2 24.4 +/- 1.6 Within 3.0 mi. of Stack D-33 10.9+/-1.3 13.5+/-1.2 13.4 +/- 0.8 22.7 +/- 0.9 D-34 11.5+/-1.4 13.5+/-1.5 13.7 +/- 0.7 22.6 +/- 1.6 D-35 12.6+/-1.4 14.1 +/-1.3 14.5 +/- 0.7 23.4 +/- 1.5 D-36 13.6+/-1.7 14.8+/-1.4 14.7 +/- 0.7 22.8 +/- 1.5 D-37 16.7+/-1.8 20.1 +/- 2.1 17.4+/-1.2 22.4 +/- 1.3 D-38 14.3+/-1.5 18.1 +/- 1.7 16.7+/-1.0 27.1 +/- 1.7 D-39 14.2+/-1.4 16.9+/-1.0 16.8 +/- 1.1 25.7 +/- 0.8 D-40 13.7 +/- 1.2 16.1 +/- 1.2 15.6 +/- 0.5 25.2 +/- 1.3 D-41 14.6+/-1.5 15.9+/-1.5 18.4 +/- 0.8 25.2 +/- 1.4 D-42 11.7+/-1.3 15.5+/-1.2 14.0 +/- 1.1 23.7 +/- 1.2 Mean+/- s.d. 13.4+/-1.7 15.8 +/- 2.1 15.5 +/- 1.7 24.1 +/- 1.6 ISFSI Fenceline D-161 48.2 +/- 2.8 48.4 +/- 2.6 43.4+/-1.6 53.7 +/- 2.0 D-162 18.6+/-1.4 16.8 +/- 2.3 16.8 +/- 1.1 22.0+/-1.6 D-163 42.8 +/- 2.7 45.4 +/- 2.9 41.1 +/- 1.9 54.4 +/- 2.3 D-164 13.9 +/- 1.5 20.2 +/- 2.1 15.5 +/- 0.9 22.0 +/- 1.3 Mean+/- s.d. 30.9 +/- 17.1 32.7 +/- 16.5 29.2+/-15.1 38.0 +/- 18.5 12-2

Table 13. Milk samples, analyses for iodine-131 and gamma emitting isotopes.

Collection: Milk samples are collected monthly throughout the year.

Location D-76 Date Lab Concentration (pCi/L)

Collected Code 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 01-15-19 NDa 02-14-19 NDa 03-12-19 NDa 04-09-19 NDa 05-14-19 NDa 06-11-19 NDa 07-16-19 NDa 08-13-19 NDa 09-10-19 NDa 10-15-19 NDa 11-13-19 NDa 12-10-19 NDa Location D-110 Date Lab Concentration (pCi/L)

Collected Code 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 01-15-19 DMI- 165 < 0.5 1416 +/- 120 < 4.2 < 4.2 < 12.8 < 2.0 02-14-19 DMI- 440 < 0.4 1392+/-121 < 4.6 < 3.6 < 16.6 < 2.8 03-12-19 DMI- 705 < 0.3 1466 +/- 116 < 3.1 < 3.4 < 19.8 < 3.5 04-09-19 DMI- 1083 < 0.3 1482 +/- 129 < 5.7 < 5.9 < 20.2 < 3.6 05-14-19 DMI- 1653 < 0.4 1394+/-115 < 3.0 < 3.1 < 9.5 < 4.3 06-11-19 DMI- 2044 < 0.3 1472 +/- 122 < 4.9 < 2.9 < 13.8 < 3.2 07-16-19 DMI- 2555 < 0.3 1411 +/-113 < 0.1 < 0.7 < 0.2 < 0.1 08-13-19 DMI- 2995 < 0.5 1425 +/- 122 < 4.1 < 4.3 < 8.8 < 2.6 09-10-19 DMI- 3360 < 0.5 1418+/-119 < 3.7 < 3.4 < 19.2 < 2.6 10-15-19 DMI- 3926 < 0.3 1403+/-119 < 0.0 < 0.0 < 0.1 < 0.0 11-13-19 DMI- 4371 < 0.3 1388 +/- 108 < 4.6 < 5.2 < 16.1 < 2.5 12-10-19 DMI- 4679 < 0.4 1561 +/- 148 < 4.8 < 4.8 < 16.6 < 1.9 "ND"= No data; see Table 2.0, Program Deviations.

13-1

Table 13. Milk samples, analyses for iodine-131 and gamma emitting isotopes.

Collection: Milk samples are collected monthly throughout the year.

Location D-138 Date Lab Concentration (pCi/L)

Collected Code 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 01-15-19 DMI- 166 < 0.4 1362 +/- 123 < 4.3 < 3.4 < 15.3 < 2.3 02-14-19 DMI- 441 < 0.5 1366 +/- 123 < 4.3 < 4.3 < 16.2 < 2.9 03-12-19 DMI- 706 < 0.3 1416+/-116 < 3.1 < 3.4 < 19.8 < 3.5 04-09-19 DMI- 1084 < 0.5 1240 +/- 116 < 5.7 < 5.9 < 20.2 < 3.6 05-14-19 DMI- 1654 < 0.4 1377+/-118 < 3.0 < 3.1 < 9.5 < 4.3 06-11-19 DMI- 2045 < 0.3 1316 +/- 120 < 4.3 < 4.3 < 8.9 < 2.9 07-16-19 DMI- 2556 < 0.4 1460 +/- 128 < 0.1 < 0.7 < 0.2 < 0.1 08-13-19 DMI- 2996 < 0.4 1413 +/- 116 < 3.6 < 4.2 < 11.9 < 2.4 09-10-19 DMI- 3361 < 0.3 1555 +/- 119 < 3.7 < 3.4 < 19.2 < 2.6 10-15-19 DMI- 3927 < 0.3 1460 +/- 115 < 0.0 < 0.0 < 0.1 < 0.0 11-13-19 DMI- 4372 < 0.4 1387 +/- 104 < 4.6 < 5.2 < 16.1 < 2.5 12-10-19 DMI- 4680 < 0.3 1348 +/- 123 < 4.1 < 4.5 < 15.1 < 2.9 13-2

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Monthly Units: pCi/L Location D-52 Drinking Water Lab Code DWW- 200 DWW- 455 DWW- 831 DWW- 1329 Date Collected 01-16-19 02-19-19 03-19-19 04-16-19 H-3 < 159 < 155 < 153 <152 1-131 < 0.4 < 0.4 < 0.3 < 0.3 Mn-54 < 2.1 < 7.3 < 3.0 < 2.7 Fe-59 < 5.3 < 10.8 < 3.8 < 4.5 Co-58 < 3.1 < 5.7 < 2.8 < 2.3 Co-60 < 3.0 < 6.9 < 2.1 < 1.5 Zn-65 < 1.8 < 6.0 < 5.7 < 6.7 Nb-95 < 3.0 < 5.8 < 2.6 < 3.2 Zr-95 < 4.2 < 10.6 < 4.2 < 5.0 1-131 < 7.7 < 8.9 < 4.1 < 2.9 Cs-134 < 3.8 < 8.2 < 3.4 < 3.4 Cs-137 < 2.6 < 6.1 < 2.2 < 2.5 Ba-140 < 19.1 < 32.2 < 15.0 < 10.9 La-140 < 1.6 < 7.2 < 4.0 < 2.1 Lab Code DWW- 1663 DWW- 2156 DWW- 2593 DWW- 3065 Date Collected 05-14-19 06-17-19 07-16-19 08-19-19 H-3 < 154 < 150 < 159 < 152 1-131 < 0.4 < 0.4 < 0.2 < 0.2 Mn-54 < 5.1 < 3.1 < 3.9 < 2.2 Fe-59 < 9.0 < 5.5 < 3.9 < 5.0 Co-58 < 3.6 < 2.2 < 2.5 < 1.9 Co-60 < 5.4 < 2.5 < 2.9 < 2.6 Zn-65 < 8.3 < 4.1 < 5.9 < 1.9 Nb-95 < 5.7 < 3.1 < 2.9 < 3.0 Zr-95 < 9.0 < 4.9 < 6.3 < 2.1 1-131 < 6.1 < 5.4 < 4.2 < 3.0 Cs-134 < 5.0 < 3.6 < 4.4 < 4.4 Cs-137 < 4.0 < 3.2 < 3.8 < 3.5 Ba-140 < 17.1 < 14.9 < 15.0 < 12.2 La-140 < 1.6 < 1.7 < 2.8 < 2.9 14-1

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Monthly Units: pCi/L Location D-52 Drinking Water Lab Code DWW- 3451 DWW- 3934 DWW- 4374 DWW- 4748 Date Collected 09-16-19 10-15-19 11-12-19 12-16-19 H-3 < 153 < 151 < 155 < 160 1-131 < 0.5 < 0.2 < 0.5 < 0.3 Mn-54 < 3.2 < 2.9 < 3.3 < 3.5 Fe-59 < 4.7 < 4.8 < 5.7 < 2.6 Co-58 < 2.2 < 1.5 < 4.1 < 4.0 Co-60 < 2.4 < 2.9 < 1.7 < 1.9 Zn-65 < 1.9 < 6.6 < 5.8 < 4.0 Nb-95 < 4.6 < 3.9 < 5.9 < 2.3 Zr-95 < 4.8 < 4.1 < 6.6 < 5.3 1-131 < 4.7 < 3.8 < 5.6 < 4.8 Cs-134 < 4.4 < 3.0 < 4.2 < 3.4 Cs-137 < 3.6 < 4.2 < 3.8 < 3.2 Ba-140 < 16.0 < 13.2 < 14.9 < 14.1 La-140 < 2.0 < 2.5 < 3.6 < 2.1 14-2

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Monthly Units: pCi/L Location D-53 Treated Municipal Water, Drinking Water Lab Code DWW- 201 DWW- 525 DWW- 832 DWW- 1330 Date Collected 01-16-19 02-19-19 03-19-19 04-16-19 H-3 < 159 < 158 < 153 < 152 1-131 < 0.3 < 0.5 < 0.3 < 0.4 Mn-54 < 2.9 < 2.8 < 3.1 < 2.3 Fe-59 < 3.5 < 5.6 < 5.0 < 3.1 Co-58 < 3.0 < 2.1 < 2.2 < 3.2 Co-60 < 1.7 < 1.4 < 1.5 < 2.3 Zn-65 < 5.4 < 1.7 < 4.5 < 5.6 Nb-95 < 3.8 < 3.3 < 2.4 < 4.9 Zr-95 < 5.1 < 6.2 < 4.6 < 5.8 1-131 < 4.9 < 6.5 < 2.4 < 4.6 Cs-134 < 3.9 < 3.3 < 2.9 < 3.8 Cs-137 < 3.6 < 3.2 < 2.6 < 4.5 Ba-140 < 11.3 < 11.1 < 10.2 < 12.1 La-140 < 3.5 < 3.5 < 3.1 < 4.2 Lab Code DWW- 1664 DWW- 2157 DWW- 2594 DWW- 3066 Date Collected 05-14-19 06-17-19 07-16-19 08-19-19 H-3 < 154 < 150 < 159 < 152 1-131 < 0.3 < 0.3 < 0.2 < 0.2 Mn-54 < 2.7 < 2.7 < 2.9 < 3.1 Fe-59 < 3.6 < 4.7 < 4.6 < 3.1 Co-58 < 1.9 < 1.6 < 2.1 < 3.1 Co-60 < 2.1 < 2.8 < 3.8 < 2.4 Zn-65 < 7.9 < 5.1 < 4.4 < 7.2 Nb-95 < 2.6 < 4.0 < 2.8 < 3.4 Zr-95 < 3.9 < 5.3 < 6.0 < 3.0 1-131 < 4.2 < 4.7 < 3.5 < 4.6 Cs-134 < 4.1 < 3.7 < 3.1 < 3.2 Cs-137 < 2.7 < 3.4 < 2.9 < 2.4 Ba-140 < 11.6 < 13.2 < 13.3 < 9.4 La-140 < 3.1 < 1.7 < 2.5 < 1.2 14-3

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Monthly Units: pCi/L Location D-53 Treated Municipal Water, Drinking Water Lab Code DWW- 3452 DWW- 3935 DWW- 4303 DWW- 4749 Date Collected 09-16-19 10-15-19 11-07-19 12-16-19 H-3 < 153 < 151 < 154 < 160 1-131 < 0.5 < 0.2 < 0.3 < 0.3 Mn-54 < 2.6 < 3.4 < 2.2 < 3.3 Fe-59 < 4.3 < 5.5 < 2.2 < 1.5 Co-58 < 1.8 < 0.9 < 2.0 < 2.9 Co-60 < 2.0 < 2.4 < 1.2 < 2.6 Zn-65 < 3.1 < 4.0 < 4.5 < 6.7 Nb-95 < 3.6 < 1.6 < 1.7 < 3.3 Zr-95 < 4.3 < 4.2 < 5.0 < 3.6 1-131 < 5.0 < 3.1 < 5.7 < 4.5 Cs-134 < 4.2 < 3.2 < 3.0 < 3.2 Cs-137 < 2.2 < 2.3 < 2.2 < 1.9 Ba-140 < 9.1 < 11.6 < 14.6 < 13.3 La-140 < 3.2 < 2.9 < 2.3 < 2.6 14-4

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Monthly Units: pCi/L Location D-54 Untreated Municipal Water, Drinking Water Lab Code DWW- 202 DWW- 526 DWW- 833 DWW- 1331 Date Collected 01-16-19 02-19-19 03-19-19 04-16-19 H-3 < 159 < 158 < 153 < 152 1-131 < 0.3 < 0.5 < 0.3 < 0.5 Mn-54 < 4.0 < 2.4 < 4.8 < 3.3 Fe-59 < 4.1 < 4.1 < 8.9 < 7.1 Co-58 < 2.7 < 2.6 < 4.7 < 3.4 Co-60 < 2.8 < 1.8 < 3.7 < 1.8 Zn-65 < 4.1 < 2.7 < 13.8 < 5.6 Nb-95 < 2.7 < 3.7 < 7.2 < 5.4 Zr-95 < 8.5 < 6.4 < 5.2 < 6.9 1-131 < 5.3 < 7.9 < 7.3 < 6.5 Cs-134 < 4.9 < 3.4 < 5.7 < 4.9 Cs-137 < 3.1 < 3.3 < 5.9 < 3.1 Ba-140 < 19.5 < 19.8 < 20.2 < 16.5 La-140 < 5.1 < 4.3 < 3.6 < 3.3 Lab Code DWW- 1665 DWW- 2158 DWW- 2595 DWW- 3067 Date Collected 05-14-19 06-17-19 07-16-19 08-19-19 H-3 < 154 < 150 < 159 < 152 1-131 < 0.3 < 0.3 < 0.3 < 0.5 Mn-54 < 4.2 < 7.0 < 2.9 < 3.5 Fe-59 < 3.7 < 9.1 < 4.2 < 7.3 Co-58 < 2.0 < 3.9 < 1.9 < 2.2 Co-60 < 2.3 < 6.9 < 2.5 < 3.7 Zn-65 < 5.0 < 15.2 < 5.7 < 6.9 Nb-95 < 3.2 < 8.8 < 3.4 < 3.0 Zr-95 < 5.8 < 8.7 < 3.9 < 6.2 1-131 < 3.3 < 7.1 < 4.0 < 5.7 Cs-134 < 4.2 < 6.5 < 3.2 < 5.1 Cs-137 < 3.4 < 6.4 < 3.1 < 5.8 Ba-140 < 12.9 < 24.3 < 11.9 < 20.1 La-140 < 2.6 < 6.9 < 2.7 < 3.3 14-5

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Monthly Units: pCi/L Location D-54 Untreated Municipal Water, Drinking Water Lab Code DWW- 3453 DWW- 3936 DWW- 4304 DWW- 4750 Date Collected 09-16-19 10-15-19 11-07-19 12-16-19 H-3 < 153 < 151 < 154 <160 1-131 < 0.5 < 0.4 < 0.4 < 0.4 Mn-54 < 1.9 < 4.2 < 2.9 < 2.9 Fe-59 < 5.8 < 2.4 < 3.5 < 3.9 Co-58 < 3.4 < 3.7 < 3.3 < 2.1 Co-60 < 3.3 < 3.6 < 2.4 < 1.6 Zn-65 < 5.3 < 6.9 < 6.4 < 6.7 Nb-95 < 4.1 < 2.5 < 3.6 < 2.7 Zr-95 < 3.4 < 6.1 < 6.3 < 5.4 1-131 < 4.4 < 4.6 < 7.1 < 6.8 Cs-134 < 3.5 < 4.9 < 3.9 < 4.3 Cs-137 < 4.5 < 5.2 < 1.7 < 3.9 Ba-140 < 11.5 < 17.1 < 14.6 < 14.2 La-140 < 1.2 < 2.7 < 2.8 < 3.4 14-6

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Quarterly Units: pCi/L Location D-55 On-site Treated Drinking Water 8

Lab Code DWW- 527 NS DWW- 3117 DWW- 4305 Date Collected 02-19-19 05-14-19 08-21-19 11-07-19 H-3 < 158 < 151 < 154 1-131 < 0.5 < 0.4 < 0.5 Mn-54 < 2.8 < 2.6 < 4.5 Fe-59 < 1.8 < 5.4 < 7.2 Co-58 < 2.9 < 3.0 < 3.7 Co-60 < 2.4 < 3.4 < 1.7 Zn-65 < 3.7 < 7.4 < 7.5 Nb-95 < 2.8 < 3.0 < 3.3 Zr-95 < 5.0 < 7.5 < 3.6 1-131 < 5.9 < 4.8 < 4.8 Cs-134 < 2.9 < 4.1 < 4.7 Cs-137 < 3.2 < 2.6 < 2.9 Ba-140 < 12.0 < 12.3 < 22.6 La-140 < 4.1 < 3.0 < 4.2 Location D-57 Untreated Drinking Water Lab Code DWW- 456 DWW- 1666 DWW- 3118 DWW- 4306 Date Collected 02-19-19 05-14-19 08-21-19 11-07-19 H-3 < 155 < 154 < 151 < 154 1-131 < 0.5 < 0.3 < 0.4 < 0.4 Mn-54 < 2.6 < 2.7 < 3.5 < 4.3 Fe-59 < 5.7 < 5.0 < 6.3 < 5.6 Co-58 < 3.8 < 2.4 < 3.0 < 4.6 Co-60 < 2.6 < 3.0 < 2.4 < 4.9 Zn-65 < 5.7 < 5.5 < 4.6 < 6.4 Nb-95 < 5.2 < 4.8 < 2.4 < 5.4 Zr-95 < 5.3 < 3.5 < 4.1 < 7.6 1-131 < 4.9 < 3.4 < 5.5 < 6.7 Cs-134 < 4.8 < 3.7 < 3.8 < 4.8 Cs-137 < 5.4 < 2.7 < 3.1 < 4.4 Ba-140 < 19.9 < 10.0 < 16.0 < 13.3 La-140 < 3.9 < 2.7 < 2.9 < 3.5 NSa - Sample not collected 14-7

Table 14. Well water samples, analyses for gamma emitting isotopes iodine-131 and tritium.

Collection: Quarterly Units: pCi/L Location D-58 Untreated Drinking Water Lab Code DWW- 458 DWW- 1667 DWW- 3119 DWW- 4307 Date Collected 02-19-19 05-14-19 08-21-19 11-07-19 H-3 < 155 < 154 < 151 < 154 1-131 < 0.3 < 0.3 < 0.5 < 0.4 Mn-54 < 2.4 < 2.5 < 3.9 < 2.8 Fe-59 < 7.3 < 6.1 < 6.8 < 4.0 Co-58 < 1.8 < 1.6 < 4.6 < 2.2 Co-60 < 2.3 < 2.5 < 3.8 < 2.0 Zn-65 < 5.5 < 6.5 < 9.7 < 4.8 Nb-95 < 3.1 < 2.4 < 6.0 < 4.3 Zr-95 < 3.1 < 4.6 < 8.0 < 4.5 1-131 < 4.2 < 4.2 < 4.1 < 5.5 Cs-134 < 3.3 < 3.4 < 5.6 < 3.4 Cs-137 < 2.0 < 4.4 < 5.4 < 3.9 Ba-140 < 12.9 < 11.2 < 21.8 < 15.5 La-140 < 2.1 < 2.3 < 4.2 < 2.9 Location D-72(C) Untreated Drinking Water Lab Code DWW- 459 DWW- 1668 DWW- 3120 DWW- 4308 Date Collected 02-19-19 05-14-19 08-21-19 11-07-19 H-3 < 155 < 154 < 151 < 154 1-131 < 0.3 < 0.3 < 0.3 < 0.3 Mn-54 < 3.1 < 4.1 < 3.3 < 3.9 Fe-59 < 2.0 < 6.0 < 2.8 < 5.5 Co-58 < 2.4 < 2.7 < 2.6 < 3.6 Co-60 < 3.1 < 3.5 < 2.7 < 3.7 Zn-65 < 5.0 < 7.3 < 5.1 < 4.9 Nb-95 < 1.7 < 3.3 < 2.9 < 3.1 Zr-95 < 4.9 < 5.8 < 5.5 < 6.9 1-131 < 4.6 < 5.9 < 4.0 < 7.3 Cs-134 < 3.4 < 4.8 < 2.9 < 4.6 Cs-137 < 2.9 < 3.5 < 3.5 < 5.2 Ba-140 < 11.1 < 15.2 < 10.6 < 16.1 La-140 < 1.5 < 3.4 < 2.1 < 2.5 14-8

Table 15. Vegetation (broadleaf), analyses for iodine-131 and other gamma-emitting isotopes.

Collection: Annually Units: pCi/g wet Location D-57 D-77 D-108 D-108 Lab Code DVE- 3433 DVE- 3619 DVE- 3486 DVE- 3487 Date Collected 09-12-19 09-30-19 09-16-19 09-16-19 Sample Type Rhubarb Leaves Herbs leaves (lovage) Kale Cabbage K-40 6.46 +/- 0.69 6.23 +/- 0.44 4.10 +/- 0.54 4.92 +/- 0.56 Mn-54 < 0.016 < 0.011 < 0.019 < 0.013 Fe-59 < 0.028 < 0.042 < 0.041 < 0.043 Co-58 < 0.019 < 0.016 < 0.014 < 0.019 Co-60 < 0.011 < 0.021 < 0.011 < 0.013 Zn-65 < 0.048 < 0.040 < 0.048 < 0.044 Nb-95 < 0.020 < 0.021 < 0.021 < 0.020 Zr-95 < 0.032 < 0.027 < 0.039 < 0.039 Ru-103 < 0.015 < 0.019 < 0.014 < 0.016 Ru-106 < 0.184 < 0.164 < 0.191 < 0.166 1-131 < 0.029 < 0.023 < 0.037 < 0.033 Cs-134 < 0.020 < 0.018 < 0.024 < 0.023 Cs-137 < 0.028 < 0.021 < 0.024 < 0.026 Ce-141 < 0.031 < 0.031 < 0.027 < 0.043 Ce-144 < 0.153 < 0.075 < 0.150 < 0.108 Location D-110 D-110 D-118 D-118 Lab Code DVE- 3260 DVE- 3261 Date Collected 08-30-19 08-30-19 Sample Type Rhubarb leaves Cabbage K-40 3.77 +/- 0.20 2.23 +/- 0.33 Mn-54 < 0.009 < 0.012 Fe-59 < 0.011 < 0.018 Co-58 < 0.009 < 0.011 Co-60 < 0.010 < 0.007 Zn-65 < 0.021 < 0.018 Nb-95 < 0.011 < 0.014 Zr-95 < 0.014 < 0.020 Ru-103 < 0.008 < 0.016 Ru-106 < 0.085 < 0.070 1-131 < 0.016 < 0.034 Cs-134 < 0.008 < 0.015 Cs-137 < 0.009 < 0.014 Ce-141 < 0.017 < 0.033 Ce-144 < 0.052 < 0.117 15-1

Table 15. Vegetation (broadleaf), analyses for iodine-131 and other gamma-emitting isotopes.

Collection: Annually Units: pCi/g wet Location D-138 D-58 D-58 D-58 Lab Code DVE- 3406 DVE- 3407 DVE- 3408 Date Collected 09-09-19 09-09-19 09-09-19 a

Sample Type Cucumber Leaves Cantaloupe Leaves Radish Leaves b K-40 6.93 +/- 0.30 4.56 +/- 0.81 3.06 +/- 0.60 Mn-54 < 0.012 < 0.041 < 0.020 Fe-59 < 0.019 < 0.061 < 0.063 Co-58 < 0.011 < 0.046 < 0.018 Co-60 < 0.011 < 0.039 < 0.024 Zn-65 < 0.026 < 0.091 < 0.066 Nb-95 < 0.013 < 0.038 < 0.037 Zr-95 < 0.018 < 0.089 < 0.055 Ru-103 < 0.010 < 0.047 < 0.036 Ru-106 < 0.127 < 0.401 < 0.262 1-131 < 0.018 < 0.058 < 0.045 Cs-134 < 0.012 < 0.046 < 0.032 Cs-137 < 0.009 < 0.059 < 0.038 Ce-141 < 0.025 < 0.055 < 0.057 Ce-144 < 0.110 < 0.203 < 0.215 a Very small sample (40.82 g wet.)

b Very small sample (55.11 g wet.)

15-2

Table 16. Vegetation (hay and grain), analyses for iodine-131 and other gamma-emitting isotopes.

Collection: Annually Units: pCi/g wet Location D-57 Lab Code DVE- 3488 Date Collected 09-17-19 Sample Type Hay K-40 24.13 +/- 1.43 Mn-54 < 0.033 Fe-59 < 0.064 Co-58 < 0.017 Co-60 < 0.027 Zn-65 < 0.070 Nb-95 < 0.030 Zr-95 < 0.064 Ru-103 < 0.020 Ru-106 < 0.266 1-131 < 0.052 Cs-134 < 0.035 Cs-137 < 0.036 Ce-141 < 0.039 Ce-144 < 0.213 Location D-110 Lab Code DVE- 3259 Date Collected 08-30-19 Sample Type Hay K-40 22.33 +/- 0.81 Mn-54 < 0.026 Fe-59 < 0.068 Co-58 < 0.020 Co-60 < 0.024 Zn-65 < 0.070 Nb-95 < 0.028 Zr-95 < 0.035 Ru-103 < 0.032 Ru-106 < 0.203 1-131 < 0.054 Cs-134 < 0.026 Cs-137 < 0.029 Ce-141 < 0.035 Ce-144 < 0.190 16-1

Table 17. Surface water samples, analyses for iodine-131, tritium and gamma-emitting isotopes.

Collection: Monthly Units: pCi/L Location: D-49 Lab Code DSW- 167 DSW- 571 DSW- 824 DSW- 1360 DSW- 1870 DSW- 2185 Date Collected 01-15-19 02-28-19 03-18-19 04-18-19 05-23-19 06-18-19 H-3 < 177 < 157 < 153 < 156 < 153 < 150 l-131(Chemistry) < 0.4 < 0.3 < 0.3 < 0.4 < 0.4 < 0.3 Mn-54 < 1.8 < 3.9 < 3.8 < 3.4 < 3.2 < 3.8 Fe-59 < 3.4 < 6.0 < 2.8 < 5.0 < 6.7 < 4.0 Co-58 < 1.7 < 2.2 < 3.0 < 3.9 < 2.1 < 2.9 Co-60 < 2.2 < 2.4 < 3.1 < 1.8 < 1.3 < 1.9 Zn-65 < 4.4 < 4.6 < 5.5 < 6.8 < 3.9 < 5.2 Nb-95 < 2.8 < 2.2 < 1.6 < 3.1 < 2.3 < 3.2 Zr-95 < 2.5 < 5.1 < 4.7 < 5.0 < 4.5 < 5.3 1-131 < 3.2 < 5.6 < 5.1 < 4.9 < 6.5 < 4.9 Cs-134 < 2.3 < 4.5 < 4.4 < 3.4 < 3.7 < 3.9 Cs-137 < 2.4 < 2.5 < 2.3 < 4.1 < 3.5 < 3.1 Ba-140 < 10.7 < 13.8 < 10.4 < 17.0 < 13.0 < 14.1 La-140 < 1.9 < 4.1 < 2.3 < 3.0 < 2.2 < 2.3 Lab Code DSW- 2650 DSW- 3138 DSW- 3443 DSW- 3929 DSW- 4426 DSW- 4756 Date Collected 07-18-19 08-22-19 09-12-19 10-15-19 11-14-19 12-18-19 H-3 < 159 < 151 < 147 < 151 < 155 < 160 1-131 (Chemistry) < 0.4 < 0.3 < 0.4 < 0.3 < 0.5 < 0.2 Mn-54 < 2.1 < 3.2 < 4.0 < 5.3 < 1.7 < 1.9 Fe-59 < 4.8 < 7.3 < 4.0 < 3.5 < 3.1 < 5.0 Co-58 < 3.3 < 5.0 < 1.6 < 2.9 < 2.4 < 3.7 Co-60 < 2.8 < 3.6 < 2.5 < 4.2 < 1.7 < 3.1 Zn-65 < 8.8 < 3.6 < 4.1 < 8.9 < 2.7 < 5.5 Nb-95 < 4.8 < 3.7 < 2.7 < 3.5 < 1.9 < 3.1 Zr-95 < 5.9 < 5.1 < 3.4 < 7.4 < 6.4 < 5.9 1-131 < 6.7 < 6.7 < 4.6 < 5.1 < 3.7 < 5.0 Cs-134 < 4.1 < 4.5 < 3.3 < 4.4 < 3.6 < 4.6 Cs-137 < 3.3 < 3.0 < 2.8 < 4.6 < 3.8 < 2.6 Ba-140 < 14.7 < 17.5 < 10.6 < 8.1 < 14.4 < 17.8 La-140 < 3.3 < 3.0 < 3.1 < 3.7 < 2.9 < 2.1 17-1

Table 17. Surface water samples, analyses for tritium and gamma-emitting isotopes.

Collection: Monthly Units: pCi/L Location: D-50 Lab Code DSW- 168 NDa DSW- 825 DSW- 1361 DSW- 1871 DSW- 2186 Date Collected 01-15-19 02-21-19 03-18-19 04-18-19 05-23-19 06-18-19 H-3 < 177 < 153 < 156 < 153 < 150 Mn-54 < 3.2 < 2.3 < 2.8 < 3.4 < 2.8 Fe-59 < 3.3 < 4.1 < 7.6 < 2.4 < 5.3 Co-58 < 3.3 < 3.2 < 3.4 < 2.6 < 2.2 Co-60 < 2.2 < 3.1 < 2.3 < 1.6 < 2.5 Zn-65 < 3.7 < 5.0 < 3.4 < 6.8 < 2.9 Nb-95 < 3.3 < 1.9 < 3.0 < 4.1 < 4.3 Zr-95 < 3.6 < 5.1 < 6.5 < 4.1 < 7.4 1-131 < 5.4 < 5.1 < 6.3 < 7.2 < 4.8 Cs-134 < 2.7 < 4.0 < 4.4 < 4.1 < 4.6 Cs-137 < 3.1 < 3.4 < 3.4 < 3.1 < 2.7 Ba-140 < 13.7 < 9.5 < 12.8 < 21.6 < 13.6 La-140 < 1.7 < 2.9 < 3.1 < 3.2 < 2.8 8

Lab Code DSW- 2651 DSW- 3139 DSW- 3444 DSW- 3930 DSW- 4427 ND Date Collected 07-18-19 08-22-19 09-12-19 10-15-19 11-14-19 12-18-19 H-3 < 159 < 151 < 147 < 151 < 155 Mn-54 < 2.6 < 2.2 < 2.6 < 2.6 < 3.0 Fe-59 < 2.8 < 2.9 < 6.4 < 2.2 < 5.6 Co-58 < 2.2 < 1.8 < 1.6 < 1.9 < 1.5 Co-60 < 2.3 < 2.6 < 1.5 < 1.8 < 2.7 Zn-65 < 4.6 < 4.5 < 3.4 < 5.8 < 4.6 Nb-95 < 3.1 < 2.3 < 2.4 < 3.4 < 1.8 Zr-95 < 3.5 < 5.7 < 4.1 < 4.6 < 4.8 1-131 < 3.4 < 4.5 < 4.1 < 5.9 < 7.0 Cs-134 < 2.8 < 3.1 < 3.0 < 3.1 < 3.9 Cs-137 < 2.8 < 2.3 < 3.3 < 3.0 < 2.3 Ba-140 < 10.0 < 10.6 < 13.9 < 13.8 < 15.8 La-140 < 1.7 < 1.6 < 3.8 < 2.6 < 2.7 a "ND" = No data; see Table 2.0, Program Deviations.

17-2

Table 17. Surface water samples, analyses for tritium and gamma-emitting isotopes.

Collection: Monthly Units: pCi/L Location: D-51 Lab Code DSW- 169 DSW- 476 DSW- 572 DSW- 826 DSW- 1362 DSW- 1872 Date Collected 01-15-19 02-21-19 02-28-19 03-18-19 04-18-19 05-23-19 H-3 < 177 < 157 < 157 < 153 < 156 < 153 Mn-54 < 2.2 < 2.6 < 3.1 < 2.3 < 2.7 < 2.6 Fe-59 < 5.4 < 2.4 < 4.3 < 4.9 < 2.8 < 6.7 Co-58 < 2.9 < 2.9 < 3.0 < 3.3 < 1.5 < 1.9 Co-60 < 2.2 < 1.5 < 3.2 < 2.2 < 3.2 < 3.3 Zn-65 < 3.9 < 4.5 < 3.1 < 6.7 < 4.2 < 6.1 Nb-95 < 2.7 < 2.3 < 1.9 < 3.3 < 4.3 < 3.2 Zr-95 < 2.3 < 3.8 < 5.8 < 5.4 < 4.8 < 4.0 1-131 < 3.9 < 4.8 < 4.8 < 4.8 < 5.2 < 6.2 Cs-134 < 3.5 < 3.2 < 3.1 < 3.1 < 3.1 < 3.7 Cs-137 < 2.9 < 2.3 < 2.2 < 3.3 < 3.0 < 3.1 Ba-140 < 14.0 < 13.3 < 17.2 < 15.8 < 13.4 < 17.9 La-140 < 1.5 < 3.5 < 3.1 < 2.2 < 2.6 < 4.1 Lab Code DSW- 2187 DSW- 2652 DSW- 3140 DSW- 3446 DSW- 3931 DSW- 4428 Date Collected 06-18-19 07-18-19 08-22-19 09-12-19 10-15-19 11-14-19 H-3 < 150 < 159 < 151 < 147 < 151 < 155 Mn-54 < 6.8 < 2.5 < 3.0 < 2.7 < 3.0 < 2.3 Fe-59 < 12.4 < 3.3 < 8.9 < 4.8 < 3.2 < 5.7 Co-58 < 3.8 < 2.7 < 4.0 < 3.1 < 2.3 < 2.0 Co-60 < 4.7 < 1.3 < 3.4 < 1.9 < 1.3 < 2.0 Zn-65 < 10.9 < 3.0 < 6.9 < 2.4 < 3.6 < 6.1 Nb-95 < 7.9 < 2.8 < 2.3 < 2.6 < 3.1 < 1.6 Zr-95 < 7.5 < 5.8 < 5.5 < 3.8 < 2.8 < 3.8 1-131 < 7.1 < 4.3 < 5.9 < 4.5 < 6.9 < 7.9 Cs-134 < 6.0 < 3.1 < 4.4 < 3.3 < 3.1 < 3.1 Cs-137 < 5.2 < 3.2 < 3.5 < 3.4 < 2.0 < 3.5 Ba-140 < 20.4 < 16.5 < 17.0 < 10.8 < 15.1 < 19.7 La-140 < 3.6 < 2.8 < 4.5 < 2.8 < 3.7 < 2.2 17-3

Table 17. Surface water samples, analyses for iodine-131, tritium and gamma-emitting isotopes.

Collection: Monthly Units: pCi/L Location: D-61 Lab Code DSW- 170 DSW- 573 DSW- 827 DSW- 1363 DSW- 1873 DSW- 2188 Date Collected 01-15-19 02-28-19 03-18-19 04-18-19 05-23-19 06-18-19 H-3 < 177 < 157 < 153 < 156 < 153 < 150 1-131 (Chemistry) < 0.3 < 0.3 < 0.3 < 0.4 < 0.5 < 0.3 Mn-54 < 3.0 < 2.3 < 2.4 < 2.4 < 3.6 < 3.9 Fe-59 < 4.6 < 5.9 < 2.6 < 1.6 < 5.8 < 4.2 Co-58 < 3.2 < 3.0 < 1.2 < 3.1 < 3.6 < 2.1 Co-60 < 2.5 < 1.2 < 2.2 < 3.5 < 3.2 < 2.6 Zn-65 < 7.2 < 3.6 < 3.7 < 6.7 < 14.5 < 5.3 Nb-95 < 4.4 < 3.4 < 2.0 < 3.7 < 9.6 < 4.9 Zr-95 < 6.0 < 5.2 < 4.5 < 3.7 < 8.3 < 6.9 1-131 < 4.3 < 6.4 < 5.5 < 4.3 < 9.0 < 5.0 Cs-134 < 4.2 < 3.7 < 3.4 < 3.1 < 6.0 < 5.2 Cs-137 < 3.1 < 2.7 < 3.4 < 2.7 < 5.8 < 3.0 Ba-140 < 10.7 < 15.7 < 6.7 < 11.6 < 22.2 < 17.9 La-140 < 5.7 < 3.5 < 1.7 < 2.6 < 9.7 < 3.6 Lab Code DSW- 2653 DSW- 3141 DSW- 3447 DSW- 3932 DSW- 4429 DSW- 4758 Date Collected 07-18-19 08-22-19 09-12-19 10-15-19 11-14-19 12-18-19 H-3 < 159 < 151 < 147 < 151 < 155 < 160 1-131 (Chemistry) < 0.4 < 0.5 < 0.4 < 0.3 < 0.4 < 0.4 Mn-54 < 2.9 < 2.2 < 3.3 < 3.0 < 3.9 < 3.3 Fe-59 < 6.1 < 6.0 < 5.5 < 3.9 < 4.8 < 3.4 Co-58 < 2.1 < 2.1 < 3.0 < 2.1 < 3.9 < 2.3 Co-60 < 2.6 < 1.5 < 1.9 < 1.7 < 4.0 < 1.8 Zn-65 < 5.5 < 3.4 < 4.4 < 3.6 < 6.0 < 6.4 Nb-95 < 2.1 < 3.0 < 3.9 < 2.8 < 2.6 < 5.8 Zr-95 < 4.1 < 3.0 < 4.5 < 4.4 < 8.5 < 4.9 1-131 < 5.0 < 6.8 < 4.4 < 2.9 < 7.2 < 3.2 Cs-134 < 3.0 < 3.2 < 3.8 < 3.6 < 4.8 < 3.9 Cs-137 < 3.0 < 2.4 < 2.5 < 3.2 < 3.9 < 4.2 Ba-140 < 14.8 < 11.1 < 16.7 < 11.9 < 7.7 < 8.3 La-140 < 2.3 < 1.7 < 2.9 < 2.0 < 3.4 < 3.2 17-4

Table 17. Surface water samples, analyses for tritium and gamma-emitting isotopes.

Collection: Monthly Units: pCi/L Location: D-99 8

Lab Code DSW- 171 ND DSW- 828 DSW- 1364 DSW- 1874 DSW- 2189 Date Collected 01-15-19 02-21-19 03-18-19 04-18-19 05-23-19 06-18-19 H-3 < 177 < 153 < 156 < 153 < 150 Mn-54 < 2.3 < 3.4 < 3.6 < 3.6 < 4.1 Fe-59 < 5.8 < 2.8 < 5.6 < 11.4 < 5.9 Co-58 < 2.1 < 2.0 < 2.1 < 4.1 < 2.7 Co-60 < 3.0 < 1.4 < 1.8 < 3.0 < 4.1 Zn-65 < 5.3 < 6.5 < 8.0 < 9.2 < 7.0 Nb-95 < 2.3 < 3.1 < 4.6 < 6.2 < 4.7 Zr-95 < 3.4 < 5.2 < 7.8 < 8.5 < 6.9 1-131 < 4.6 < 3.1 < 8.6 < 10.4 < 5.2 Cs-134 < 3.2 < 3.1 < 5.0 < 5.6 < 4.4 Cs-137 < 3.3 < 2.7 < 4.1 < 5.3 < 3.3 Ba-140 < 9.8 < 12.7 < 24.1 < 23.9 < 18.3 La-140 < 2.5 < 3.2 < 3.2 < 3.7 < 4.2 8

Lab Code DSW- 2654 DSW- 3142 DSW- 3448 DSW- 3933 DSW- 4430 ND Date Collected 07-18-19 08-22-19 09-12-19 10-15-19 11-14-19 12-18-19 H-3 < 159 < 151 < 147 < 151 < 155 Mn-54 < 3.9 < 2.0 < 3.9 < 1.9 < 1.7 Fe-59 < 3.6 < 4.6 < 8.5 < 3.0 < 4.3 Co-58 < 1.4 < 1.6 < 4.9 < 1.4 < 1.7 Co-60 < 2.9 < 2.2 < 2.7 < 2.3 < 1.4 Zn-65 < 2.0 < 4.6 < 10.2 < 1.8 < 3.5 Nb-95 < 2.0 < 1.9 < 5.9 < 2.3 < 2.1 Zr-95 < 3.6 < 3.6 < 5.3 < 4.2 < 4.5 1-131 < 3.1 < 3.5 < 7.9 < 5.5 < 4.8 Cs-134 < 3.2 < 2.9 < 5.4 < 3.0 < 3.3 Cs-137 < 3.4 < 2.8 < 4.9 < 2.8 < 2.5 Ba-140 < 13.8 < 16.3 < 23.1 < 19.6 < 15.5 La-140 < 2.4 < 3.5 < 4.3 < 3.3 < 4.1 a "ND" =No data; see Table 2.0, Program Deviations.

17-5

Table 18. Surface water, analysis for strontium.

Collection: Quarterly composites of monthly samples.

Units: pCi/L Location D-49 Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code DSW-878 DSW-2219 DSW-3490 DSW-4853 Sr-89 < 0.65 < 0.50 < 0.60 < 0.53 Sr-90 < 0.46 < 0.46 < 0.42 < 0.53 Location D-61 Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code DSW-879 DSW-2220 DSW-3491 DSW-4854 Sr-89 < 0.66 < 0.76 < 0.65 < 0.64 Sr-90 < 0.44 < 0.44 < 0.50 < 0.58 18-1

Table 19. Fish, analyses of edible portion for gamma-emitting isotopes.

Collection: Semiannually Units: pCi/g wet Location Upstream, D-49 Control, D-56 Lab Code DF- 2088 DF- 2089 DF- 2443 Date Collected 06-11-19 06-11-19 06-11-19 Sample Type Largemouth bass Channel catfish Largemouth bass K-40 4.17 +/- 0.48 3.40 +/- 0.39 3.44 +/- 0.57 Mn-54 < 0.014 < 0.013 < 0.018 Fe-59 < 0.048 < 0.040 < 0.051 Co-58 < 0.016 < 0.012 < 0.026 Co-60 < 0.019 < 0.010 < 0.017 Zn-65 < 0.033 < 0.038 < 0.028 Nb-95 < 0.020 < 0.021 < 0.027 Zr-95 < 0.029 < 0.022 < 0.027 Ru-103 < 0.020 < 0.022 < 0.034 Ru-106 < 0.168 < 0.122 < 0.206 Cs-134 < 0.020 < 0.015 < 0.025 Cs-137 < 0.016 < 0.013 < 0.022 Ce-141 < 0.069 < 0.037 < 0.047 Ce-144 < 0.114 < 0.079 < 0.161 Location Upstream, D-49 Lab Code DF- 3075 DF- 3076 Date Collected 08-16-19 08-16-19 Sample Type Northern pike Channel catfish K-40 4.78 +/- 0.59 4.39 +/- 0.55 Mn-54 < 0.017 < 0.021 Fe-59 < 0.069 < 0.035 Co-58 < 0.013 < 0.025 Co-60 < 0.016 < 0.008 Zn-65 < 0.045 < 0.039 Nb-95 < 0.032 < 0.019 Zr-95 < 0.026 < 0.030 Ru-103 < 0.025 < 0.019 Ru-106 < 0.131 < 0.226 Cs-134 < 0.021 < 0.022 Cs-137 < 0.019 < 0.017 Ce-141 < 0.043 < 0.044 Ce-144 < 0.115 < 0.138 19-1

Table 19. Fish, analyses of edible portion for gamma-emitting isotopes.

Collection: Semiannually Units: pCi/g wet Location Downstream, D-61 Lab Code DF- 2090 DF- 2091 Date Collected 06-11-19 06-11-19 Sample Type Smallmouth bass Northern pike K-40 3.92 +/- 0.49 4.30 +/- 0.41 Mn-54 < 0.008 < 0.017 Fe-59 < 0.044 < 0.035 Co-58 < 0.020 < 0.015 Co-60 < 0.010 < 0.016 Zn-65 < 0.010 < 0.030 Nb-95 < 0.024 < 0.022 Zr-95 < 0.024 < 0.033 Ru-103 < 0.025 < 0.023 Ru-106 < 0.161 < 0.163 Cs-134 < 0.017 < 0.017 Cs-137 < 0.020 < 0.015 Ce-141 < 0.027 < 0.028 Ce-144 < 0.119 < 0.086 Location Downstream, D-61 Lab Code DF- 3073 DF- 3074 DF- 3077 Date Collected 08-16-19 08-16-19 08-16-19 Sample Type White crappie Channel catfish Smallmouth bass K-40 3.52 +/- 0.45 3.67 +/- 0.45 3.67 +/- 0.36 Mn-54 < 0.017 < 0.016 < 0.018 Fe-59 < 0.050 < 0.053 < 0.059 Co-58 < 0.017 < 0.025 < 0.016 Co-60 < 0.011 < 0.014 < 0.022 Zn-65 < 0.014 < 0.018 < 0.042 Nb-95 < 0.026 < 0.019 < 0.027 Zr-95 < 0.027 < 0.025 < 0.031 Ru-103 < 0.019 < 0.025 < 0.025 Ru-106 < 0.183 < 0.217 < 0.165 Cs-134 < 0.018 < 0.020 < 0.017 Cs-137 < 0.013 < 0.020 < 0.019 Ce-141 < 0.045 < 0.049 < 0.050 Ce-144 < 0.080 < 0.111 < 0.109 19-2

Table 20. River sediment, analysis for gamma-emitting isotopes.

Collection: Semiannually Units: pCi/g dry Location D-49 (Control)

Lab Code DBS- 1476 DBS- 4029 Date Collected 04-01-19 10-18-19 K-40 7.11 +/- 0.41 7.71 +/- 0.46 Mn-54 < 0.010 < 0.014 Fe-59 < 0.037 < 0.053 Co-58 < 0.011 < 0.018 Co-60 < 0.008 < 0.017 Zn-65 < 0.026 < 0.036 Nb-95 < 0.022 < 0.047 Zr-95 < 0.025 < 0.023 Ru-103 < 0.021 < 0.024 Ru-106 < 0.063 < 0.099 Cs-134 < 0.008 < 0.010 a

Cs-137 < 0.008 0.027 +/- 0.012 Ce-141 < 0.065 < 0.060 Ce-144 < 0.054 < 0.074 Location D-51 (Discharge)

Lab Code DBS- 1477 DBS- 4031 Date Collected 04-01-19 10-18-19 K-40 8.19 +/- 0.46 8.12+/-0.48 Mn-54 < 0.011 < 0.013 Fe-59 < 0.057 < 0.050 Co-58 < 0.020 < 0.018 Co-60 < 0.014 < 0.010 Zn-65 < 0.029 < 0.030 Nb-95 < 0.041 < 0.034 Zr-95 < 0.025 < 0.020 Ru-103 < 0.029 < 0.021 Ru-106 < 0.097 < 0.056 Cs-134 < 0.011 < 0.010 Cs-137 < 0.008 < 0.014 Ce-141 < 0.058 < 0.048 Ce-144 < 0.100 < 0.074 Source determined to be from atmospheric deposition from nuclear weapons testing.

20-1

Table 20. River sediment, analysis for gamma-emitting isotopes.

Collection: Semiannually Units: pCi/g dry Location D-107A (North Drainage Ditch)

Lab Code DBS- 1478 DBS- 4032 Date Collected 04-01-19 10-18-19 K-40 5.44 +/- 0.38 5.22 +/- 0.35 Mn-54 < 0.017 < 0.014 Fe-59 < 0.035 < 0.058 Co-58 < 0.020 < 0.017 Co-60 < 0.012 < 0.012 Zn-65 < 0.039 < 0.026 Nb-95 < 0.042 < 0.031 Zr-95 < 0.032 < 0.029 Ru-103 < 0.026 < 0.017 Ru-106 < 0.102 < 0.107 Cs-134 < 0.013 < 0.012 Cs-137 < 0.016 < 0.013 Ce-141 < 0.073 < 0.049 Ce-144 < 0.075 < 0.077 20-2

Table 21. Soil, analysis for strontium-90 and gamma-emitting isotopes.

Collection: Annually Units: pCi/g dry Location D-15a D-16 Lab Code DSO- 2221 DSO- 2222 Date Collected 06-20-19 06-20-19 Sr-90 < 0.037 < 0.037 H-3 (pCi/L) < 150 < 150 K-40 9.58 +/- 0.47 13.55 +/- 0.62 Mn-54 < 0.017 < 0.026 Fe-59 < 0.045 < 0.065 Co-58 < 0.020 < 0.020 Co-60 < 0.015 < 0.014 Zn-65 < 0.041 < 0.052 Nb-95 < 0.041 < 0.039 Zr-95 < 0.038 < 0.038 Ru-103 < 0.023 < 0.018 Ru-106 < 0.158 < 0.125 Cs-134 < 0.015 < 0.015 Cs-137 0.114+/-0.019 a 0.120+/-0.022 a Ce-141 < 0.055 < 0.073 Ce-144 < 0.101 < 0.143 a Source determined to be from atmospheric deposition from nuclear weapons testing.

21-1

Table 22. Supplemental meat sample, analysis for gamma emitting isotopes. Free range chicken collected from location D-58.

Location D-058 Lab Code DME- 4373 Date Collected 11-12-19 K-40 2.39 +/- 0.59 Mn-54 < 0.02 Fe-59 < 0.05 Co-58 < 0.02 Co-60 < 0.02 Zn-65 < 0.05 Nb-95 < 0.03 Zr-95 < 0.05 Ru-103 < 0.03 Ru-106 < 0.23 Cs-134 < 0.02 Cs-137 < 0.03 Ce-141 < 0.04 Ce-144 < 0.11 22-1

Table 23. Groundwater Protection Program Summary.

Precipitation samples for tritium analysis. Units: pCi/L Lab Code Date H-3 Lab Code Date H-3 D-016 D-111 DP- 79 01/07/19 < 148 DP- 81 01/07/19 167 +/- 78 DP- 344 02/05/19 < 150 DP- 347 02/05/19 205 +/- 82 DP- 665 03/05/19 < 155 DP- 667 03/05/19 < 155 DP- 985 04/01/19 < 155 DP- 987 04/01/19 < 155 DP- 1546 05/02/19 < 154 DP- 1548 05/02/19 224 +/- 85 DP- 1970 06/04/19 < 154 DP- 1972 06/04/19 280 +/- 87 DP- 2317 07/01/19 < 149 DP- 2319 07/01/19 < 149 DP- 2876 08/01/19 260 +/- 90 DP- 2878 08/01/19 < 152 DP- 3273 09/03/19 < 155 DP- 3275 09/03/19 < 155 DP- 3671 10/01/19 < 151 DP- 3673 10/01/19 < 147 DP- 4208 11/04/19 < 151 DP- 4210 11/04/19 231 +/- 84 DP- 4583 12/02/19 < 150 DP- 4585 12/02/19 < 156 D-112 D-114 DP- 82 01/07/19 < 147 ND a DP- 348 02/04/19 913+/-112 NDa DP- 668 03/05/19 < 155 NDa DP- 988 04/01/19 < 155 NDa DP- 1549 05/02/19 < 147 ND a DP- 1973 06/04/19 198 +/- 83 NDa DP- 2320 07/01/19 < 149 NDa DP- 2879 08/01/19 160 +/- 80 NDa DP- 3276 09/03/19 182 +/- 82 ND a DP- 3674 10/01/19 < 147 NDa DP-4211 11/04/19 332 +/- 89 NDa DP- 4586 12/02/19 < 156 NDa D-127 D-128 DP- 84 01/07/19 794 +/- 107 DP- 85 01/07/19 157 +/-77 DP- 350 02/04/19 2256 +/- 155 DP- 351 02/04/19 1411 +/- 130 DP- 671 03/05/19 785 +/- 109 DP- 672 03/05/19 200 +/- 83 DP- 990 04/01/19 785 +/- 110 DP- 991 04/01/19 241 +/- 86 DP- 1552 05/02/19 1400 +/- 131 DP- 1553 05/02/19 < 153 DP- 1975 06/04/19 1208 +/- 124 DP- 1976 06/04/19 420 +/- 94 DP- 2322 07/01/19 1130+/-121 DP- 2323 07/01/19 316 +/- 88 DP- 2881 08/01/19 517 +/- 97 DP- 2882 08/01/19 327 +/- 88 DP- 3278 09/03/19 1076 +/- 121 DP- 3280 09/03/19 236 +/- 85 DP- 3676 10/01 /19 363 +/- 91 DP- 3677 10/01/19 259 +/- 85 DP- 4212 11/04/19 1010+/-118 DP- 4213 11/04/19 705 +/- 106 DP- 4588 12/02/19 647 +/- 105 DP- 4589 12/02/19 < 156 D-081 D-115 DP- 80 01/07/19 169 +/- 78 DP- 83 01/07/19 < 147 DP- 345 02/04/19 245 +/- 84 DP- 349 02/05/19 < 150 DP- 666 03/05/19 < 155 DP- 669 03/05/19 < 155 DP- 986 04/01/19 < 155 DP- 989 04/01/19 < 155 DP- 1547 05/02/19 < 147 DP- 1551 05/02/19 < 147 DP- 1971 06/04/19 < 154 DP- 1974 06/04/19 < 154 DP- 2318 07/01/19 < 149 DP- 2321 07/01/19 < 149 DP- 2877 08/01 /19 165 +/- 80 DP- 2880 08/01/19 < 152 DP- 327 4 09/03/19 < 155 DP- 3277 09/03/19 < 155 DP- 3672 10/01/19 < 147 DP- 3675 10/01/19 < 147 DP- 4209 11/04/19 198 +/- 83 11/04/19 NSt DP- 4584 12/02/19 < 156 DP- 4587 12/02/19 < 156

• No sampler at the location. t No sample collected due to broken collection container.

23-1

Table 23. Groundwater Protection Program Summary.

Precipitation, monthly collections, analyses for gamma emitting isotopes.

Location: D-16 Concentration (pCi/L}

Lab Code Date 54Mn 59Fe 58Co so Co sszn ssNb 95zr 1311 134Cs 137Cs 140Ba 140La DP- 79 01/07/19 < 2.5 < 4.9 < 3.2 < 4.0 < 5.7 < 2.7 < 7.3 < 4.3 < 3.8 < 4.0 < 17.3 < 4.2 DP- 344 02/05/19 < 6.4 < 12.9 < 4.5 < 5.8 < 11.0 < 5.7 < 9.6 < 7.1 < 8.1 < 4.9 < 20.3 < 9.0 DP- 665 03/05/19 < 3.3 < 6.0 < 2.6 < 3.1 < 6.2 < 3.2 < 6.3 < 5.8 < 3.1 < 3.4 < 19.8 < 3.5 DP- 985 04/01/19 < 5.2 < 9.9 < 5.8 < 3.5 < 9.4 < 5.2 < 10.0 < 8.1 < 5.0 < 6.4 < 17.9 < 7.6 DP- 1546 05/02/19 < 3.1 < 4.0 < 3.0 < 3.1 < 5.6 < 3.4 <4.6 < 4.6 < 3.0 < 3.1 < 9.5 < 4.3 DP- 1970 06/04/19 < 4.6 < 4.0 < 5.0 < 3.5 < 8.2 < 5.5 < 5.9 < 6.0 < 4.3 < 6.1 < 14.2 < 2.6 DP- 2317 07/01/19 < 3.6 < 4.0 < 3.0 < 3.0 < 6.3 <4.2 < 5.7 < 5.7 < 3.2 < 4.3 < 13.8 < 4.2 DP- 2876 08/01/19 < 5.3 < 8.6 < 3.7 < 4.4 < 5.9 < 3.0 < 8.6 < 8.3 < 4.2 < 5.6 < 19.3 < 7.8 DP- 3273 09/03/19 < 3.9 < 3.9 < 3.8 < 2.8 < 6.3 < 3.9 < 6.0 < 5.8 < 3.7 < 3.4 < 19.2 < 2.6 DP- 3671 10/01/19 < 6.1 < 7.0 < 4.4 < 5.2 < 10.7 < 6.1 < 14.0 < 11.6 < 8.6 < 5.5 < 20.5 < 6.8 DP- 4208 11/04/19 < 5.3 < 10.5 < 4.9 < 4.3 < 11.5 < 5.3 < 8.9 < 5.7 < 6.6 < 4.9 < 17.4 < 8.7 DP- 4583 12/02/19 < 5.6 < 11.7 < 7.2 < 7.7 < 10.5 < 7.8 < 9.5 < 9.8 < 7.5 < 6.4 < 27.1 < 7.0 23-2

Table 23. Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium*.

Lab Code Date H-3 (pCi/L) Lab Code Date H-3 (pCi/L)

D-111A (01A)

DWW- 750 03/12/19 158 +/- 81 DWW- 1773 05/07/19 197 +/- 82 DWW- 3088 08/13/19 < 152 DWW- 4322 11/06/19 < 154 D-1118 (018)

DWW- 751 03/12/19 < 154 DWW- 4323 11/06/19 < 154 DWW- 1725 05/07/19 < 150 DWW- 3089 08/13/19 < 152 D-112A (02A)

DWW- 752 03/11/19 < 155 DWW- 4324 11/07/19 < 154 DWW- 1774 05/07/19 < 151 DWW- 3090 08/13/19 < 152 D-1128 (028)

DWW- 753 03/11/19 < 155 DWW- 4325 11/07/19 < 154 DWW- 1726 05/07/19 < 150 DWW- 3078 08/13/19 < 152 D-113A (03A)

DWW- 754 03/12/19 < 154 DWW- 4326 11/07/19 < 154 DWW- 1775 05/07/19 < 151 DWW- 3079 08/13/19 < 152 D-1138 (038)

DWW- 755 03/12/19 < 154 DWW- 4327 11/07/19 < 154 DWW- 1728 05/07/19 < 150 DWW- 3081 08/13/19 < 152 D-114A (04A)

DWW- 767 03/14/19 230 +/- 85 DWW- 4328 11/06/19 207 +/- 83 DWW- 1807 05/07/19 189 +/- 81 DWW- 3082 08/14/19 163 +/- 80 D-1148 (048)

DWW- 768 03/14/19 < 154 DWW- 4329 11/06/19 < 154 DWW- 1729 05/07/19 < 150 DWW- 3083 08/14/19 < 152 D-115A (05A)

DWW- 757 03/12/19 < 154 DWW- 4330 11/06/19 < 154 DWW- 1776 05/07/19 < 151 DWW- 3093 08/13/19 < 152 D-1158 (058)

DWW- 758 03/12/19 < 154 DWW- 4331 11/06/19 < 154 DWW- 1730 05/07/19 < 150 DWW- 3094 08/13/19 < 152 D-116A (06A)

DWW- 759 03/12/19 < 154 DWW- 4332 11/07/19 < 154 DWW- 1777 05/09/19 < 151 DWW- 3095 08/13/19 < 152 D-1168 (068)

DWW- 760 03/12/19 < 154 DWW- 4333 11/07/19 < 154 DWW- 1731 05/09/19 < 150 DWW- 3096 08/13/19 < 152 a Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L.

23-3

Table 23. Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium *.

Lab Code Date H-3 (pCi/L) Lab Code Date H-3 (pCi/L)

D-127A (07A)

DWW- 87 01/08/19 1936 +/- 150 DWW- 761 03/11/19 3150+/-179 DWW- 1196 04/09/19 1106+/-120 DWW- 1778 05/06/19 1476 +/- 133 DWW- 3216 08/14/19 2713 +/- 169 DWW- 3500 09/11/19 13115 +/- 350 DWW- 4065 10/07/19 4197 +/- 205 DWW- 4287 11/06/19 2294 +/- 159 D-127B (07B)

DWW- 762 03/11/19 < 155 DWW- 4288 11/06/19 < 154 DWW- 1784 05/06/19 < 151 DWW- 3169 08/14/19 < 151 D-128A (08A)

DWW- 88 01/08/19 2984 +/- 177 DWW- 462 02/14/19 31343 +/- 520 DWW- 763 03/11/19 17373 +/- 392 DWW- 1197 04/09/19 45337 +/- 625 DWW- 1808 05/06/19 59075 +/- 713 DWW- 2168 06/05/19 42592 +/- 604 DWW- 2632 07/09/19 17644 +/- 402 DWW- 3501 09/11/19 3218 +/- 185 DWW- 4066 10/07/19 1188 +/- 124 DWW- 4431 11 /13/19 1050 +/- 121 DWW- 4912 12/18/19 2491 +/- 166 D-128B (08B)

DWW- 764 03/11/19 991+/-117 DWW- 1785 05/06/19 911+/-113 DWW- 3170 08/14/19 739 +/- 107 DWW- 4289 11/06/19 492 +/- 97 D-129A (09A)

DWW- 765 03/11/19 309 +/- 89 DWW- 1766 05/06/19 990+/-116 DWW- 3171 08/14/19 761 +/- 108 DWW- 4291 11/05/19 528 +/- 99 D-129B (09B)

DWW- 766 03/11/19 281 +/- 88 DWW- 1826 05/21/19 305 +/- 87 DWW- 3172 08/14/19 349 +/- 89 DWW- 4293 11/05/19 227 +/- 84 D-130A (10A)

DWW- 775 03/11/19 < 155 DWW- 1767 05/06/19 < 151 DWW- 3179 08/14/19 171 +/- 80 DWW- 4294 11/05/19 < 154

• Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L.

23-4

Table 23. Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium *.

D-1308 (108)

DWW- 776 03/11/19 < 155 DWW- 1787 05/06/19 < 151 DWW- 3180 08/14/19 < 151 DWW- 4295 11/05/19 < 154 D-131A (11A)

DWW- 769 03/14/19 < 154 DWW- 1768 05/07/19 < 151 DWW- 3097 08/14/19 157 +/- 80 DWW- 4335 11/06/19 < 154 D-1318 (118)

DWW- 770 03/14/19 < 154 DWW- 1788 05/07/19 < 151 DWW- 3098 08/14/19 < 152 DWW- 4336 11/06/19 < 154 D-132A (12A)

DWW- 771 03/14/19 < 154 DWW- 1770 05/07/19 272 +/- 86 DWW- 3099 08/14/19 205 +/- 82 DWW- 4337 11/06/19 195 +/- 83 D-1328 (128)

DWW- 772 03/14/19 390 +/- 93 DWW- 1789 05/07/19 400 +/- 92 DWW- 3100 08/14/19 401+/-92 DWW- 4338 11/06/19 559 +/- 101 D-133A (13A)

DWW-773 03/14/19 < 154 DWW- 1771 05/07/19 < 151 DWW- 3102 08/14/19 < 152 DWW- 4339 11/06/19 161 +/- 81 D-1338 (138)

DWW- 774 03/14/19 < 154 DWW- 1745 05/07/19 < 150 DWW- 3103 08/14/19 < 152 DWW- 4340 11/06/19 < 155 D-134A (14A)

DWW- 778 03/11/19 9549 +/- 294 DWW- 1198 04/09/19 640 +/- 102 DWW- 1772 05/06/19 1746 +/- 141 DWW- 3217 08/14/19 20724 +/- 432 DWW- 3502 09/11/19 19742 +/- 427 DWW- 4296 11/05/19 372 +/- 92

'Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L.

23-5

Table 23. Groundwater Protection Program Summary.

0 Ground water, Monitoring wells, analyses for tritium

• D-1348 (148)

DWW- 779 03/11/19 < 155 DWW- 1746 05/06/19 283 +/- 87 DWW- 3174 08/14/19 316 +/- 88 DWW- 4297 11/05/19 556 +/- 100 D-135A (15A)

DWW- 785 03/14/19 < 154 DWW- 1754 05/07/19 < 151 DWW-3113 08/14/19 < 151 DWW- 4348 11/06/19 < 155 D-1358 (158)

DWW- 786 03/14/19 < 154 DWW- 1747 05/07/19 < 150 DWW- 3114 08/14/19 < 151 DWW- 4349 11/06/19 < 155 D-136A (16A)

DWW- 780 03/11/19 < 155 DWW- 1755 05/06/19 < 151 DWW- 3175 08/14/19 < 151 DWW- 4298 11/06/19 < 154 D-1368 (168)

DWW- 781 03/11/19 < 155 DWW- 1809 05/06/19 < 151 DWW- 3176 08/14/19 < 151 DWW- 4350 11/06/19 < 155 D-137 (17C)

DWW- 782 03/11/19 < 155 DWW- 1749 05/06/19 < 150 DWW- 3177 08/14/19 < 151 DWW- 4290 11/06/19 < 154 D-62 (18A)

DWW- 783 03/11/19 1213 +/- 125 DWW- 1756 05/13/19 734 +/- 106 DWW- 3178 08/14/19 1282 +/- 127 DWW- 4299 11/05/19 1231 +/- 126 D-63 (19A)

DWW- 89 01/08/19 < 148 DWW- 784 03/11/19 520 +/- 99 DWW- 1200 04/09/19 156 +/- 79 DWW- 1757 05/06/19 214 +/- 83 DWW- 3173 08/14/19 < 151 DWW- 4067 10/07/19 222 +/- 83 DWW- 4300 11/05/19 405 +/- 93

• Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L.

23-6

Table 23. Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium *.

Lab Code Date H-3 (pCi/L) Lab Code Date H-3 (pCi/L)

D-64 (20A)

DWW- 90 01/08/19 < 148 DWW- 792 03/11/19 433 +/- 95 DWW- 1201 04/09/19 173 +/- 80 DWW- 1758 05/06/19 < 151 DWW- 3181 08/14/19 199 +/- 81 DWW- 4301 11/05/19 < 154 D-65 (21A)

DWW- 91 01/08/19 1027 +/- 121 DWW- 463 02/14/19 722 +/- 110 DWW- 791 03/11/19 480 +/- 97 DWW- 1202 04/09/19 1458 +/- 132 DWW- 1810 05/06/19 266 +/- 85 DWW- 2169 06/05/19 < 150 DWW- 2633 07/09/19 2218+/-158 DWW- 3182 08/14/19 608 +/- 101 DWW- 4302 11/05/19 2801 +/- 172 D-66 (22A)

DWW- 92 01/08/19 57663 +/- 701 DWW- 464 02/14/19 7714 +/- 267 DWW- 793 03/11/19 13094 +/- 340 DWW- 1203 04/09/19 21985 +/- 438 DWW- 1804 05/06/19 95396 +/- 905 DWW- 2170 06/05/19 32092 +/- 525 DWW- 2634 07/09/19 20950 +/- 437 DWW- 3218 08/14/19 23111 +/- 456 DWW- 3503 09/11/19 10742 +/- 319 DWW- 4068 10/07/19 12197 +/- 335 DWW- 4490 11/20/19 33257 +/- 549 DWW- 4915 12/18/19 90728 +/- 899 D-67 (23A)

DWW- 93 01/08/19 11280 +/- 318 DWW- 465 02/14/19 33310 +/- 536 DWW- 794 03/11/19 11662 +/- 322 DWW- 1204 04/09/19 17577 +/- 393 DWW- 2171 06/05/19 7477 +/- 261 DWW- 2635 07/09/19 34435 +/- 557 DWW- 3504 09/11/19 13590 +/- 356 DWW- 4069 10/07/19 7305 +/- 263 DWW- 4491 11/19/19 7229 +/- 264 DWW- 4916 12/18/19 5070 +/- 224 D-165 (24A)

DWW- 787 03/14/19 < 154 DWW- 1805 05/07/19 < 151 DWW- 3115 08/14/19 156 +/- 79 DWW- 4351 11/06/19 < 155

' Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L .

23-7

Table 23. Groundwater Protection Program Summary*

Ground water, Monitoring wells, analyses for tritium *.

0-167 (26A)

OWW- 790 03/15/19 245 +/- 86 OWW- 1759 05/07/19 176 +/- 81 OWW- 3116 08/14/19 243 +/- 84 OWW- 4352 11/06/19 315 +/- 89 0-168A (27A)

OWW- 795 03/12/19 196 +/- 82 OWW- 1750 05/07/19 262 +/- 86 OWW- 3091 08/13/19 < 152 OWW- 4353 11/06/19 261 +/- 87 OWW- 4432 11 /13/19 253 +/- 86 0-1688 (278)

OWW- 796 03/12/19 < 153 OWW- 1760 05/07/19 < 151 OWW- 3092 08/13/19 < 152 OWW- 4354 11/06/19 < 155 0-169A (28A)

OWW- 797 03/12/19 222 +/- 83 OWW- 1751 05/07/19 216 +/- 83 OWW- 3104 08/13/19 487 +/- 96 OWW- 4356 11/06/19 441 +/- 95 0-1698 (288)

OWW- 799 03/12/19 < 153 OWW- 1761 05/07/19 < 151 OWW- 3105 08/13/19 < 152 OWW- 4357 11/06/19 < 155 0-170A (29A)

OWW- 466 02/14/19 259 +/- 90 OWW- 788 03/14/19 219 +/- 85 OWW- 1752 05/08/19 265 +/- 85 OWW- 3106 08/13/19 621 +/- 102 OWW- 3505 09/11/19 709 +/- 108 OWW- 4070 10/07/19 808 +/- 110 OWW- 4433 11/13/19 696 +/- 107 0-1708 (29B)

OWW- 789 03/14/19 < 154 OWW- 1762 05/08/19 < 151 OWW- 3107 08/13/19 388 +/- 91 OWW- 4434 11/13/19 560 +/- 101 0171A (30A)

OWW- 800 03/11/19 262 +/- 85 OWW- 1753 05/09/19 < 151 OWW- 3108 08/13/19 < 152 OWW- 4358 11/07/19 161 +/- 81

• Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L.

23-8

Table 23. Groundwater Protection Program Summary*

Ground water, Monitoring wells, analyses for tritium *.

D-1718 (308)

DWW- 801 03/11/19 < 153 DWW- 1763 05/09/19 < 151 DWW- 3109 08/13/19 < 152 DWW- 4359 11/07/19 < 155 D172A (31A)

DWW- 802 03/12/19 < 153 DWW- 1779 05/09/19 < 151 DWW- 3110 08/13/19 < 152 DWW- 4360 11/07/19 < 155 D-1728 (318)

DWW- 803 03/12/19 < 153 DWW- 1764 05/09/19 < 151 DWW- 3111 08/13/19 < 151 DWW- 4361 11/07/19 < 155 D-173A (32A)

DWW- 804 03/12/19 258 +/- 85 DWW- 1780 05/07/19 314 +/- 88 DWW- 3112 08/13/19 871+/-112 DWW- 4362 11/06/19 519 +/- 99 D-1738 (328)

DWW- 805 03/12/19 156 +/- 80 DWW- 1765 05/07/19 204 +/- 82 DWW- 3084 08/13/19 159 +/- 80 DWW- 4363 11/06/19 321 +/- 90 D-79 MW-33A DWW- 806 03/11/19 < 153 DWW- 1781 05/08/19 < 151 DWW- 3085 08/13/19 < 152 DWW- 4364 11/06/19 < 155 D-80 MW-34A DWW- 807 03/11/19 < 153 DWW- 1782 05/08/19 < 151 DWW- 3086 08/13/19 < 152 DWW- 4365 11/06/19 < 155 D-81 MW-35A DWW- 467 02/14/19 < 155 DWW- 808 03/13/19 194 +/- 82 DWW- 1205 04/09/19 171 +/- 80 DWW- 1783 05/08/19 < 151 DWW- 2172 06/05/19 < 150 DWW- 2636 07/09/19 < 159 DWW- 3087 08/13/19 < 152 DWW- 4366 11/06/19 219 +/- 84 DWW- 4913 12/18/19 < 158 D-68 EW-01b

• Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L.

b EW-01 is a permanent extraction well. No sample taken in 2019.

23-9

Table 23. Groundwater Protection Program Summary.

Surface water, analysis for tritium.

D-119 (2MH209)

DSW- 949 03/25/19 246 +/- 84 DWW- 1517 04/25/19 266 +/- 86 DSW- 1733 05/09/19 262 +/- 86 DSW- 3144 08/20/19 258 +/- 85 DSW- 4492 11/19/19 264 +/- 87 D-120 (2MH210)

DSW- 950 03/25/19 246 +/- 84 DWW- 1518 04/25/19 295 +/- 88 DSW- 1734 05/09/19 194 +/- 82 DSW- 3145 08/20/19 239 +/- 83 DSW- 4495 11/19/19 264 +/- 87 D-121 (2MH211)

DSW- 951 03/25/19 < 153 DWW- 1519 04/25/19 < 150 DSW- 1735 05/09/19 < 150 DSW- 3146 08/20/19 < 151 DSW- 4496 11/19/19 159 +/- 81 D-122 (Sluice Pond)

DSW- 952 03/25/19 218 +/- 83 DSW- 1736 05/09/19 372 +/- 91 DSW- 1979 05/29/19 < 154 DSW- 3147 08/20/19 173 +/- 80 DSW- 4375 10/24/19 < 155 D-123 (S. Drainage Ditch)

DSW- 953 03/25/19 < 153 DSW- 1737 05/09/19 < 150 DSW- 3148 08/20/19 < 151 DSW- 4497 11/19/19 < 156 D-124 (N. Drainage Ditch)

DSW- 954 03/25/19 < 153 DSW- 1738 05/09/19 < 150 DSW- 3149 08/20/19 < 151 DSW- 4498 11/19/19 < 156 D-125 (Onsite S. Storm Drain Outfall)

DSW- 955 03/25/19 1232 +/- 124 DSW- 1806 05/09/19 3775 +/- 193 DSW- 3219 08/20/19 2558 +/- 165 DSW- 4489 11/19/19 2825 +/- 174 0

D-89 (MH221) 0 No sample taken in 2019.

23-10

Table 23. Groundwater Protection Program Summary.

Surface water, analysis for tritium.

D-101 (1MH109)

DSW- 1484 04/24/19 281 +/- 87 D-102 (1MH110)

DSW- 1485 04/24/19 < 150 D-25 (MH105)

DWW- 1480 04/24/19 < 150 DWW- 4102 10/21/19 < 152 D-27 (MH-107)

DWW- 1482 04/24/19 < 150 DWW- 4104 10/21/19 < 152 D-24 (MW-104)

DWW- 1479 04/24/19 173 +/- 82 DWW- 4101 10/21/19 < 152 D-26 (MW-106)

DWW- 1481 04/24/19 188 +/- 82 DWW- 4103 10/21/19 234 +/- 85 23-11

Table 23. Groundwater Protection Program Summary.

Monitoring wells, analyses for gamma-emitting isotopes.

Collection Lab Code Date 54Mn 59Fe ssco soco sszn gs Nb 95zr 134Cs 131cs 140 8 a 140La D-127A (MW-07A)

DWW- 87 1/8/2019 < 0.8 < 3.4 < 1.5 < 1.3 < 2.3 < 1.8 <2.6 < 1.5 < 1.7 < 9.5 < 2.0 DWW- 761 3/11/2019 < 2.4 <6.5 < 3.4 < 2.7 < 5.6 < 4.3 <6.9 < 3.5 <4.2 < 24.0 < 9.2 DWW- 1196 4/9/2019 < 2.4 < 5.7 < 1.4 < 1.5 < 4.4 < 2.1 < 3.4 < 2.7 < 1.9 < 14.3 <4.3 DWW- 1778 5/6/2019 < 1.5 <4.6 < 1.3 < 1.2 < 2.9 < 3.5 <4.0 < 1.5 < 1.6 < 47.5 < 14.0 DWW- 3216 8/14/2019 < 1.9 <4.9 < 1.5 < 1.2 < 1.5 < 2.6 < 3.8 < 1.5 < 1.8 < 38.0 < 9.4 DWW- 3500 9/11/2019 < 1.5 < 4.3 < 1.9 < 1.6 < 3.4 < 2.3 < 3.8 < 1.5 < 1.5 < 16.2 < 8.6 DWW- 4065 101712019 < 1.9 < 3.7 < 3.6 < 1.6 < 2.7 <4.8 < 5.0 < 3.2 < 3.0 < 39.8 < 9.7 DWW- 4287 11/6/2019 < 2.3 < 3.8 < 1.8 < 1.8 <4.0 < 3.1 < 5.2 < 2.6 < 1.9 < 17.6 < 5.4 D-128A (MW-08A)

DWW- 88 1/8/2019 < 2.9 < 6.1 < 2.6 < 2.8 < 3.9 < 3.3 < 4.4 <2.7 < 3.4 < 15.9 <2.7 DWW- 462 2/14/2019 < 3.6 < 4.0 < 2.7 < 4.0 < 3.1 < 3.2 < 5.2 <4.2 < 3.9 < 21.8 < 5.0 DWW- 763 3/11/2019 < 2.7 < 5.7 < 3.2 < 2.8 < 6.2 < 3.1 < 4.9 < 3.3 < 3.6 < 33.6 < 7.6 DWW- 1197 4/9/2019 < 1.8 < 3.5 < 2.2 < 2.0 < 2.0 < 1.6 < 3.7 < 2.0 < 2.4 < 18.5 < 6.8 DWW- 1808 5/6/2019 < 1.2 < 5.0 < 1.9 < 1.3 < 3.6 < 2.3 < 4.4 < 1.4 < 1.5 <61.2° < 11.2 DWW- 2168 6/5/2019 < 1.5 <4.2 < 1.6 < 1.6 < 2.7 < 3.0 <4.0 < 1.5 < 1.7 < 40.7 < 6.5 DWW- 2632 7/9/2019 < 1.8 <4.8 < 1.6 < 1.5 < 3.4 < 2.3 < 3.7 < 1.4 < 1.4 <24.3 < 7.2 DWW- 3501 9/11/2019 < 1.5 < 3.7 < 1.4 < 1.3 < 2.3 < 2.6 < 3.2 < 1.4 < 1.9 < 21.9 <4.6 DWW- 4066 10/7/2019 < 3.2 < 4.9 <2.0 < 2.9 < 3.2 <6.0 < 7.3 < 3.9 < 3.7 < 53.1 < 9.1 DWW- 4431 11/13/2019 < 1.6 < 5.8 < 2.1 < 1.5 < 3.2 < 3.4 < 3.4 < 1.6 < 1.3 < 41.0 < 5.6 DWW- 4912 12/18/2019 < 1.6 < 3.2 < 2.2 < 1.3 <4.2 <4.9 < 3.8 < 1.7 < 2.4 < 37.2 < 13.3 D-1288 (MW-088)

D-129A (MW-09A)

D-1298 (MW-098)

D-130A (MW-10A)

D-1308 (MW-108)

D-132A (MW-12A) 0 LLDs not reached due to age and small sample volume.

23-12

Table 23. Groundwater Protection Program Summary.

Monitoring wells, analyses for gamma-emitting isotopes.

Collection Lab Code Date D-132B (MW-12B)

D-134A (MW-14A)

DWW- 778 3/11/2019 <2.5 < 3.5 < 2.3 < 2.8 < 4.6 < 2.6 < 4.5 < 2.3 < 2.2 < 27.7 <4.8 DWW- 1772 5/6/2019 < 1.8 < 3.3 < 2.2 < 1.2 < 3.5 <4.0 < 3.8 < 1.5 < 1.5 < 58.5 < 12.9 DWW- 3217 8/14/2019 < 1.9 < 5.9 < 1.8 < 1.8 < 2.9 < 3.1 < 3.7 < 1.5 < 1.3 < 36.6 < 9.0 DWW- 3502 9/11/2019 < 1.9 < 5.8 < 1.6 < 1.4 < 3.8 < 2.1 < 5.0 <2.0 < 1.5 < 20.3 < 6.4 D-134B (MW-14B)

D-62 (MW-18A)

DWW- 783 3/11/2019 < 2.0 < 3.9 < 1.8 < 1.5 < 3.4 < 2.8 < 3.7 < 1.6 < 1.7 < 21.9 <8.3 DWW- 3178 8/14/2019 < 1.8 < 3.0 < 1.7 < 1.5 < 3.0 < 2.5 < 2.8 < 1.5 < 1.7 < 30.8 < 11.3 DWW- 4299 11/5/2019 < 2.4 < 3.1 < 1.8 < 2.0 < 3.9 <4.0 < 4.2 < 2.1 < 1.7 < 24.1 <4.3 D-63 (MW-19A)

D-64 (MW-20A)

D-65 (MW-21A)

DWW- 91 1/8/2019 < 2.5 < 2.6 < 1.5 < 1.8 < 4.9 < 3.0 <4.7 < 2.9 < 3.2 < 12.3 <4.6 DWW- 1202 4/9/2019 < 1.9 < 4.0 < 2.2 < 1.9 < 3.6 < 3.5 < 2.0 < 2.1 < 1.9 < 20.0 < 3.2 DWW- 2633 7/9/2019 < 3.3 < 8.4 < 2.8 < 2.7 < 4.1 < 4.0 < 7.9 < 3.6 <4.0 < 39.8 < 13.0 DWW- 4302 11/5/2019 < 2.1 < 3.6 < 2.7 < 1.3 < 2.2 < 2.9 < 3.8 < 2.0 < 2.0 < 13.1 < 5.7 23-13

Table 23. Groundwater Protection Program Summary.

Monitoring wells, analyses for gamma-emitting isotopes.

Collection Lab Code Date s4Mn ssFe ssco so Co sszn ssNb sszr 134Cs 131Cs l4oBa 140La D-66 (MW-22A)

DWW- 92 1/8/2019 < 2.2 < 5.7 < 2.6 < 2.0 <4.3 < 3.3 < 2.9 < 2.9 < 2.3 < 17.0 < 2.8 DWW- 464 2/14/2019 < 5.1 < 5.4 < 3.1 < 1.9 < 7.7 <4.9 < 8.1 < 5.6 < 3.3 < 34.2 < 3.7 DWW- 793 3/11/2019 < 1.6 < 3.7 < 1.8 < 1.4 < 3.5 < 2.0 < 2.8 < 1.5 < 1.4 < 23.1 < 3.4 DWW- 1203 4/9/2019 < 1.8 <4.2 < 1.7 < 1.0 < 3.6 < 2.9 < 3.4 < 2.1 < 1.9 < 18.0 < 5.4 DWW- 1804 5/6/2019 < 1.9 <4.2 <2.0 < 1.4 < 3.2 < 4.2 < 2.5 < 1.5 < 1.8 < 50.5 < 17.4 a DWW- 2170 6/5/2019 < 2.0 < 4.4 < 2.3 < 1.7 <4.0 < 2.8 < 4.7 < 2.3 < 1.2 < 47.3 < 13.1 DWW- 2634 7/9/2019 < 3.6 < 5.6 < 2.1 < 2.6 < 3.2 < 5.1 < 5.0 < 3.3 < 3.2 < 52.7 < 10.8 DWW- 3218 8/14/2019 < 1.7 < 3.0 < 2.3 < 1.7 < 2.7 < 3.5 < 2.9 < 1.5 < 1.5 <42.6 < 9.4 DWW- 3503 9/11/2019 < 1.9 < 3.8 < 1.5 < 1.5 < 3.5 < 3.2 < 2.6 < 1.5 < 1.4 < 26.1 <6.7 DWW- 4068 10/7/2019 < 3.5 <6.8 < 4.8 < 2.7 < 3.6 <4.3 < 5.9 < 3.7 < 3.3 <41.9 < 8.3 DWW- 4490 11/20/2019 < 1.2 < 3.3 < 1.3 < 0.9 < 3.4 < 2.8 < 3.3 < 1.5 < 1.5 < 22.6 < 7.6 DWW- 4915 12/18/2019 < 2.2 < 6.3 < 2.7 < 1.8 < 3.6 < 5.1 < 4.5 < 1.9 < 1.9 < 53.8 < 12.9 D-67 (MW-23A)

DWW- 93 1/8/2019 < 2.7 <6.2 < 3.0 < 1.8 < 5.5 < 3.7 < 3.6 < 3.0 < 2.2 < 13.2 < 2.5 DWW- 465 2/14/2019 <4.6 < 8.6 < 4.4 < 2.7 < 3.9 < 3.2 < 8.4 < 4.9 < 3.1 < 38.0 < 8.3 DWW- 794 3/11/2019 < 1.9 <4.0 < 1.8 < 1.2 < 2.5 < 2.7 < 2.2 < 1.6 < 1.7 < 21.8 < 5.6 DWW- 1204 4/9/2019 < 1.3 < 3.6 < 1.9 < 0.9 < 3.7 < 2.7 < 3.6 < 1.7 < 1.5 < 16.8 < 2.6 DWW- 2171 6/5/2019 < 1.4 < 5.2 < 1.6 < 1.2 < 2.7 < 2.9 < 4.0 < 1.5 < 1.2 < 50.0 < 8.8 DWW- 2635 7/9/2019 < 2.1 < 4.9 < 1.9 < 2.4 < 3.1 < 4.4 < 4.0 < 2.9 < 3.2 < 48.8 < 9.7 DWW- 3504 9/11/2019 < 1.6 < 4.5 < 1.7 < 1.5 < 2.7 < 2.3 < 3.4 < 1.5 < 1.6 < 17.9 <4.7 DWW- 4069 10/7/2019 < 3.0 < 5.3 < 2.3 < 1.8 < 5.0 < 3.6 < 5.4 < 3.1 < 3.6 < 43.9 < 6.7 DWW- 4491 11/19/2019 < 1.5 < 4.3 < 1.4 < 1.8 < 3.4 <2.1 < 3.8 < 1.5 < 2.0 < 24.4 < 4.4 DWW- 4916 12/18/2019 < 1.4 <4.3 < 1.8 < 1.0 < 2.5 < 2.3 < 2.2 < 1.2 < 1.4 < 46.3 < 11.1 D-165 (MW-24A)

D-167 (MW-26A)

D-168 (MW-27A)

D-168 (MW-27B) a LLDs for Ba-140 and/or La-140 not reached due to age of samples and smaller sample size.

23-14

Table 23. Groundwater Protection Program Summary.

Monitoring wells, analyses for gamma-emitting isotopes.

Collection Lab Code Date D-169 (MW-28A)

D-169 (MW-288)

D-170 (MW-29A)

D-170 (MW-298)

D-171 (MW-30A)

D-171 (MW-308)

D-172 (MW-31A)

D-172 (MW-318)

D-173 (MW-32A)

D-173 (MW-328) 23-15

Table 23. Groundwater Protection Program Summary.

Monitoring wells, analyses for gamma-emitting isotopes.

Collection Lab Code Date D-79 (MW-33A)

D-80 (MW-34A)

D-81 (MW-35A)

D-111 (MW-01A)

D-111 (MW-01B)

D-112 (MW-02A)

D-112 (MW-02B)

D-113 (MW-03A)

D-113 (MW-03B)

D-114 (MW-04A)

D-114 (MW-04B) 23-16

Table 23. Groundwater Protection Program Summary.

Monitoring wells, analyses for gamma-emitting isotopes.

Collection Lab Code Date D-115 (MW-05A)

D-115 (MW-05B)

D-116 (MW-06A)

D-116 (MW-06B)

D-131 (MW-11A)

D-131 (MW-11B)

D-133 (MW-13A)

D-133 (MW-13B)

D-135 (MW-15A)

D-135 (MW-15B) 23-17

Table 23. Groundwater Protection Program Summary.

Monitoring wells, analyses for gamma-emitting isotopes.

Collection Lab Code Date D-136 (MW-16A)

D-136 (MW-168)

D-137 (MW-17C)

D-68 (EW-01) 23-18

Table 23. Groundwater Protection Program Summary.

8 Monitoring wells, conditional analyses for gross alpha, iron-55, nickel-63, strontium-89 and strontium-90

• Collection Lab Code Date Location Gross Alpha DWW- 87 1/8/2019 d-127a 0.9 +/- 0.7 < 606 < 64 < 1.1 < 1.0 DWW- 88 1/8/2019 d-128a < 1.1 < 589 < 64 < 1.5 < 1.3 DWW- 91 1/8/2019 mw-21a < 2.2 < 555 < 71 < 1.1 < 1.0 DWW- 92 1/8/2019 mw-22a 1.4+/-0.1 < 589 < 65 < 1.3 < 1.1 DWW- 93 1/8/2019 mw-23a < 1.5 < 555 < 63 < 1.1 < 1.1 DWW- 462 2/14/2019 d-128a < 1.2 < 610 < 71 < 1.1 < 1.0 DWW- 464 2/14/2019 mw-22a < 2.1 < 597 < 68 < 1.1 < 0.9 DWW- 465 2/14/2019 mw-23a < 1.4 < 623 < 69 < 1.0 < 0.9 DWW- 761 3/11/2019 d-127a < 1.1 < 530 < 69 < 1.6 < 1.0 DWW- 763 3/11/2019 d-128a 1.8 +/- 1.2 < 506 < 75 < 1.7 < 1.0 DWW- 778 3/11/2019 d-134a < 1.2 < 530 < 67 < 1.4 < 0.9 DWW- 783 3/11/2019 mw-18a 3.8 +/- 2.1 < 595 < 67 < 1.5 < 1.0 DWW- 793 3/11/2019 mw-22a < 4.9 < 603 < 70 < 1.5 < 0.8 DWW- 794 3/11/2019 mw-23a < 2.5 < 611 < 68 < 1.4 < 0.9 DWW- 1196 4/9/2019 d-127a < 1.1 < 607 < 66 < 1.4 < 1.1 DWW- 1197 4/9/2019 d-128a < 1.2 < 580 < 67 < 1.3 < 1.0 DWW- 1202 4/9/2019 mw-21a < 2.3 < 603 < 67 < 1.4 < 1.1 DWW- 1203 4/9/2019 mw-22a < 2.4 < 623 < 67 < 1.6 < 1.2 DWW- 1204 4/9/2019 mw-23a < 2.0 < 623 < 67 < 1.3 < 1.0 DWW- 1772 5/6/2019 d-134a < 1.1 < 581 < 67 < 1.9 < 1.1 DWW- 1778 5/6/2019 d-127a < 1.0 < 574 < 67 < 1.9 < 1.1 DWW- 1804 5/6/2019 mw-22a 3.3 +/- 1.8 < 588 < 66 < 1.7 < 0.9 DWW- 1808 5/6/2019 d-128a < 1.2 < 581 < 66 < 1.9 < 1.0 DWW- 2168 6/5/2019 d-128a < 2.1 < 608 < 63 < 1.8 < 0.9 DWW- 2170 6/5/2019 mw-22a 6.7 +/- 3.3 < 676 < 63 < 2.0 < 1.0 DWW- 2171 6/5/2019 mw-23a 5.1 +/- 3.3 < 638 < 63 < 1.7 < 0.9 DWW- 2632 7/9/2019 d-128a < 2.0 < 558 < 64 < 1.7 < 1.0 DWW- 2633 7/9/2019 mw-21a < 2.6 < 606 < 64 < 1.9 < 1.0 DWW- 2634 7/9/2019 mw-22a < 4.0 < 576 < 64 < 1.5 < 0.9 DWW- 2635 7/9/2019 mw-23a < 2.0 < 579 < 64 < 1.5 < 0.9 DWW- 3178 8/14/2019 mw-18a < 4.3 < 595 < 63 < 1.8 < 0.9 DWW- 3216 8/14/2019 d-127a < 0.9 < 595 < 68 < 2.1 < 1.0 DWW- 3217 8/14/2019 d-134a < 2.0 < 569 < 65 < 2.3 < 1.0 DWW- 3218 8/14/2019 mw-22a < 4.1 < 569 < 63 < 1.9 < 0.9 DWW- 3500 9/11/2019 d-127a < 0.9 < 710 < 69 < 1.7 < 1.2 DWW- 3501 9/11/2019 d-128a < 0.7 < 701 < 70 < 1.8 < 1.2 DWW- 3502 9/11/2019 d-134a 2.0 +/- 1.3 < 679 < 67 < 1.5 < 1.0 DWW- 3503 9/11/2019 mw-22a < 2.3 < 663 < 65 < 1.4 < 0.9 DWW- 3504 9/11/2019 mw-23a 2.4+/-1.6 < 720 < 68 < 1.4 < 1.1 DWW- 4065 10/7/2019 d-127a < 2.5 < 633 < 70 < 1.8 < 1.3

• Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1 K pCi/L .

NOTE: Gross alpha values are related to the natural radioactive decay of radon gas held dissolved in groundwater.

23-19

Table 23. Groundwater Protection Program Summary.

Monitoring wells, conditional analyses for gross alpha, iron-55, nickel-63, strontium-89 and strontium-90 ".

Collection Lab Code Date Location Gross Alpha ssFe 63Ni e9Sr go Sr DWW- 4066 10/7/2019 d-128a < 2.1 < 637 < 69 < 1.7 < 1.1 DWW- 4068 10/7/2019 mw-22a < 2.5 < 625 < 67 < 1.8 < 1.3 DWW- 4069 10/7/2019 mw-23a < 2.5 < 662 < 69 < 1.4 < 1.0 DWW- 4299 11/5/2019 mw-18a 2.1+/-1.0 < 690 < 69 < 3.1 < 2.1 DWW- 4302 11/5/2019 mw-21a < 3.8 < 666 < 68 < 1.3 < 1.0 DWW- 4287 11/6/2019 d-127a < 1.1 < 674 < 69 < 2.0 < 1.1 DWW- 4431 11/13/2019 d-128a < 2.2 < 701 < 65 < 1.7 < 1.0 DWW- 4491 11/19/2019 mw-23a < 2.5 < 694 < 65 < 1.5 < 1.0 DWW- 4490 11/20/2019 mw-22a < 3.2 < 655 < 65 < 1.7 < 1.1 DWW- 4912 12/18/2019 d-128a < 1.6 < 652 < 71 < 2.0 < 1.0 DWW- 4915 12/18/2019 mw-22a 7.8 +/- 2.1 < 640 < 69 < 2.3 < 1.0 DWW- 4916 12/18/2019 mw-23a < 2.0 < 660 < 70 < 2.0 < 0.9 a Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity > 1K pCi/L .

NOTE: Gross alpha values are related to the natural radioactive decay of radon gas held dissolved in groundwater.

23-20

~*' All Environmental, Inc.

'+~ /'"'\I Midwest Laboratory 700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 584-0700 *fax (847) 584-4517 APPENDIX A INTERLABORATORY 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, 2019 through December, 2019 A-1

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 Resource Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Results in Table A-2 were obtained through participation in the New York Department of Health Environmental Laboratory Approval Program (ELAP) PT Table A-3 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-4 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-5 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-6 lists analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the each result being with 25% of the mean of the two results or the two sigma uncertanties of each result overlap.

The results in Table A-7 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-8 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory acceptance criteria for various analyses.

Out-of-limit results are explained directly below the result.

A-2

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES Analysis Ratio of lab result to known value.

Gamma Emitters 0.8 to 1.2 Strontium-89, 0.8 to 1.2 Strontium-90 Potassium-40 0.8 to 1.2 Gross alpha 0.5 to 1.5 Gross beta 0.8 to 1.2 Tritium 0.8 to 1.2 Radium-226, 0.7to1.3 Radium-228 Plutonium 0.8 to 1.2 lodine-129, 0.8 to 1.2 lodine-131 Nickel-63, 0.7to1.3 Technetium-99, Uranium-238 lron-55 0.8 to 1.2 Other Analyses 0.8 to 1.2 A-3

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-71 1/7/2019 Ba-133 97.9 +/- 4.5 99.5 84.1 -109 Pass ERW-71 1/7/2019 Cs-134 45.4 +/- 3.1 49.1 39.5 - 54.0 Pass ERW-71 1/7/2019 Cs-137 129 +/- 6 125 112 - 140 Pass ERW-71 1/7/2019 Co-60 98.1 +/- 4.1 96.4 86.8-108 Pass ERW-71 1/7/2019 Zn-65 80.4 +/- 7.8 77.4 69.5 +/- 93.2 Pass ERW-73 1/7/2019 Gr. Alpha 22.2+/-1.6 21.8 10.9 - 29.5 Pass ERW-73 1/7/2019 Gr. Beta 46.4+/-1.4 55.7 38.1 - 62.6 Pass ERW-75 1/7/2019 Ra-226 7.19 +/-0.30 7.37 5.55 +/- 8.72 Pass ERW-75 1/7/2019 Ra-228 4.02 +/- 0.70 4.28 2.48 - 5.89 Pass ERW-75 1/7/2019 Uranium 50.2 +/- 2.9 68.2 55.7 - 75.0 Failb ERW-77 1/7/2019 H-3 2,129 +/- 158 2,110 1,740 - 2,340 Pass ERW-397 2/11/2019 1-131 27.2+/-1.0 25.9 25.1 - 30.6 Pass ERW-1141 4/8/2019 Ra-226 7.58 +/- 0.53 7.15 5.39 - 8.48 Pass ERW-1141 4/8/2019 Ra-228 2.64 +/- 0.79 2.94 1.54 - 4.35 Pass ERW-1141 4/8/2019 Uranium 67.0 +/- 0.9 55.9 45.6 - 61.5 Failc ERW-2471 7/8/2019 Ba-133 66.5 +/- 4.0 66.9 55.8 - 73.6 Pass ERW-2471 7/8/2019 Cs-134 29.6 +/- 2.6 32.0 25.1 - 35.2 Pass ERW-2471 7/8/2019 Cs-137 21.3 +/- 3.6 21.4 17.6 - 26.7 Pass ERW-2471 7/8/2019 Co-60 99.9 +/- 4.4 95.1 85.6 -107.0 Pass ERW-2471 7/8/2019 Zn-65 43.7 +/- 6.2 41.2 35.3 - 51.4 Pass ERW-2473 7/8/2019 Gr. Alpha 41.7+/-2.1 70.6 37.1 - 87.1 Pass ERW-2473 7/8/2019 Gr. Beta 57.0+/-1.6 63.9 44.2 - 70.5 Pass ERW-2477 7/8/2019 Ra-226 16.2 +/- 0.5 18.5 13.8 - 21.1 Pass ERW-2477 7/8/2019 Ra-228 6.2 +/- 0.8 8.2 5.2 - 10.3 Pass ERW-2477 7/8/2019 Uranium 63.8 +/- 3.6 68.3 55.8 - 75.1 Pass ERW-2479 7/8/2019 H-3 8,630 +/- 200 16,700 14,600 -18,400 Failct ERW-2475 7/8/2019 1-131 33.6 +/- 1.3 29.6 24.6 - 34.6 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 Resource Associates (ERA).

b In order to get to the root cause of the above "Fail" resolution the U-232 tracer was standardized using a known concentration of NIST U-238 solution. A duplicate analysis was performed and the results obtained were well within the acceptance range (Known value for Total Uranium=68.2 pCi/L, acceptance range of (55.7-75 pCi/L). The results obtained were 63.3 pCi/L and 66.0 pCi/L respectively.

c The standardized U-232 value utilized on ERA sample ERW-1141 above was found to be estimated high due to interferences in the U-238 solution causing ERW-1141 to fail the study. After performing U-isotopic chemistry on the NIST-Uranium solution to remove interferences a more accurate U-232 tracer concentration was obtained.

The Uranium result in the subsequent ERA PT study was acceptable. See ERW-2477 Uranium result above.

d EIML's routine H-3 analysis does include a blank sample. The ERA provided blank was paired with a H-3 standard vial and EIML's blank was also paired with a standard vial. Inadvertently the efficiency was overestimated by a factor of 2.

This understated the calculated results by half. The result of reanalysis (17,400 pCi/L) is within the control limits for the study.

A-4

8 TABLE A-2. lnterlaboratory Comparison Crosscheck program, New York Department of Health (ELAP) .

Concentration (pCi/L)

Lab Code Date Analysis Laboratory Assigned Acceptance Result Value Limits Acceptance Shipment 427R NYW-3472 9/17/2019 H-3 5250 +/- 229 4991 4280 - 5490 Pass NYW-3476 9/17/2019 Gross Alpha 18.0 +/- 1.2 20.1 9.99 - 27.5 Pass NYW-3476 9/17/2019 Gross Beta 22.7+/-1.0 27.2 17.1 - 35.1 Pass NYW-3478 9/17/2019 1-131 18.7+/-1.8 15.6 12.8 - 19.3 Pass NYW-3480 9/17/2019 Ra-226 5.02 +/- 0.37 4.41 3.37 - 5.43 Pass NYW-3480 9/17/2019 Ra-228 16.0+/-1.9 18.3 12.3 -21.9 Pass NYW-3480 9/17/2019 Uranium 13.7 +/-0.9 13.9 11.0 -15.7 Pass NYW-3482 9/17/2019 Co-60 63.9 +/-4.0 63.0 56.7 -71.8 Pass NYW-3482 9/17/2019 Zn-65 108 +/-9 113 97.2 - 129 Pass NYW-3482 9/17/2019 Ba-133 53.3 +/- 4.3 61.9 51.4 68.2 Pass NYW-3482 9/17/2019 Cs-134 47.2 +/- 3.4 55.8 45.1 - 61.4 Pass NYW-3482 9/17/2019 Cs-137 52.0 +/-4.6 53.8 48.4 - 62.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by the New York Department of Health Laboratory Approval Program(NY ELAP).

A-5

8 TABLE A-3. Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards).

mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P)

Environmental. Inc. Group 1 2019-1 11/11/2019 Spike 1 126.0 128.3 0.02 2019-1 11/11/2019 Spike 2 126.0 122.2 -0.03 2019-1 11/11/2019 Spike 3 126.0 122.5 -0.03 2019-1 11/11/2019 Spike 4 126.0 119.3 -0.05 2019-1 11/11/2019 Spike 5 126.0 116.9 -0.07 2019-1 11/11/2019 Spike 6 126.0 109.5 -0.13 2019-1 11/11/2019 Spike 7 126.0 114.6 -0.09 2019-1 11/11/2019 Spike 8 126.0 121.8 -0.03 2019-1 11/11/2019 Spike 9 126.0 120.2 -0.05 2019-1 11/11/2019 Spike 10 126.0 126.4 0.00 2019-1 11/11/2019 Spike 11 126.0 125.0 -0.01 2019-1 11/11/2019 Spike 12 126.0 109.0 -0.13 2019-1 11/11/2019 Spike 13 126.0 123.4 -0.02 2019-1 11/11/2019 Spike 14 126.0 118.2 -0.06 2019-1 11/11/2019 Spike 15 126.0 134.3 0.07 2019-1 11/11/2019 Spike 16 126.0 120.1 -0.05 2019-1 11/11/2019 Spike 17 126.0 131.3 0.04 2019-1 11/11/2019 Spike 18 126.0 120.4 -0.04 2019-1 11/11/2019 Spike 19 126.0 121.1 -0.04 2019-1 11/11/2019 Spike 20 126.0 122.8 -0.03 Mean (Spike 1-20) 121.4 -0.04 Passd Standard Deviation (Spike 1-20) 6.2 0.05 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*(10)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 the mean of the P values, nor the standard deviation of the P values exceed 0.15.

A-6

TABLE A-3. Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards). 8 mrem 0

Lab Code Irradiation Delivered Reportedb Performance Date Description Dose Dose Quotient (P)

Environmental, Inc. Group 2 2019-2 11/11/2019 Spike 21 79.0 78.8 0.00 2019-2 11/11/2019 Spike 22 79.0 71.8 -0.09 2019-2 11/11/2019 Spike 23 79.0 75.8 -0.04 2019-2 11/11/2019 Spike 24 79.0 71.3 -0.10 2019-2 11/11/2019 Spike 25 79.0 74.5 -0.06 2019-2 11/11/2019 Spike 26 79.0 71.6 -0.09 2019-2 11/11/2019 Spike 27 79.0 73.3 -0.07 2019-2 11/11/2019 Spike 28 79.0 74.0 -0.06 2019-2 11/11/2019 Spike 29 79.0 73.8 -0.07 2019-2 11/11/2019 Spike 30 79.0 76.0 -0.04 2019-2 11/11/2019 Spike 31 79.0 76.7 -0.03 2019-2 11/11/2019 Spike 32 79.0 77.8 -0.02 2019-2 11/11/2019 Spike 33 79.0 75.2 -0.05 2019-2 11/11/2019 Spike 34 79.0 69.1 -0.13 2019-2 11/11/2019 Spike 35 79.0 68.7 -0.13 2019-2 11/11/2019 Spike 36 79.0 68.2 -0.14 2019-2 11/11/2019 Spike 37 79.0 67.9 -0.14 2019-2 11/11/2019 Spike 38 79.0 68.9 -0.13 2019-2 11/11/2019 Spike 39 79.0 78.1 -0.01 2019-2 11/11/2019 Spike 40 79.0 68.6 -0.13 Mean (Spike 21-40) 73.0 -0.08 Passd Standard Deviation (Spike 21-40) 3.6 0.05 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*(10)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 the mean of the P values, nor the standard deviation of the P values exceed 0.15.

A-7

TABLE A-4. In-House "Spiked" Samples Concentration*

Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPW-61 1/5/2019 Ra-226 13.4+/-0.4 12.3 9.8 - 14.8 Pass 1.09 SPW-118 1/14/2019 H-3 15,463 +/- 369 16,507 13,206 - 19,808 Pass 0.94 SPW-178 1/16/2019 Ra-228 17.7 +/- 2.1 15.1 12.10-18.14 Pass 1.17 SPW-199 1/18/2019 Sr-90 17.6+/-1.2 17.9 14.3 - 21.5 Pass 0.98 SPW-250 1/24/2019 Ni-63 356.3 +/- 44.5 465 326 - 605 Pass 0.77 SPW-256 1/15/2019 Ra-226 12.0+/-0.4 12.3 9.8 -14.8 Pass 0.98 SPW-271 3/18/2019 H-3 22,035 +/- 450 21,700 17,360 - 26,040 Pass 1.02 SPW-281 1/25/2019 Ra-226 11.6 +/- 0.4 12.3 9.8 - 14.8 Pass 0.94 W-012119 4/29/2016 Cs-134 37.3 +/- 10.6 36.2 29.0 - 43.4 Pass 1.03 W-012119 4/29/2016 Cs-137 82.7 +/- 8.0 71.9 57.5 - 86.3 Pass 1.15 W-012319 4/29/2016 Cs-134 33.4 +/- 10.1 36.2 25.3-47.1 Pass 0.92 W-012319 4/29/2016 Cs-137 79.1 +/- 9.6 71.9 57.5 - 86.3 Pass 1.10 W-012519 4/29/2016 Cs-134 35.0 +/- 7.7 36.2 29.0 - 43.4 Pass 0.97 W-012519 4/29/2016 Cs-137 79.2 +/- 7.9 71.9 57.5 - 86.3 Pass 1.10 W-012919 4/29/2016 Cs-134 32.3 +/- 8.3 36.2 29.0 - 43.4 Pass 0.89 W-012919 4/29/2016 Cs-137 82.3 +/- 8.3 71.9 57.5 - 86.3 Pass 1.14 SPW-370 3/19/2019 H-3 21,689 +/- 444 21,700 17 ,360 - 26,040 Pass 1.00 SPW-400 1/31/2019 Ra-226 11.6 +/- 0.4 12.3 8.6 -16.0 Pass 0.95 SPW-461 2/12/2019 Ra-226 11.1 +/- 0.4 12.3 8.6 -16.0 Pass 0.90 W-020619 4/26/2016 Cs-134 35.0 +/- 14.9 36.2 29.0 -43.4 Pass 0.97 W-020619 4/29/2016 Cs-137 72.8 +/- 8.9 71.9 57.5 - 86.3 Pass 1.01 W-020819 4/26/2016 Cs-134 36.7 +/- 8.6 36.2 29.0 - 43.4 Pass 1.01 W-020819 4/29/2016 Cs-137 76.7 +/- 8.7 71.9 57.5 - 86.3 Pass 1.07 SPW-568 2/21 /2019 Ra-226 10.3 +/- 0.3 12.3 8.6 -16.0 Pass 0.84 W-021319 4/29/2016 Cs-134 37.7+/-11.5 36.2 29.0 - 43.4 Pass 1.04 W-021319 4/26/2016 Cs-137 75.8 +/- 9.6 71.9 57.5 - 86.3 Pass 1.05 SPW-469 3/19/2019 H-3 21,696 +/- 447 21,700 17,360 - 26,040 Pass 1.00 SPW-600 3/6/2019 H-3 20,710 +/- 425 21,700 17,360 - 26,040 Pass 0.95 SPW-837 3/21/2019 Ra-228 11.7+/-1.5 15.1 10.58 - 19.66 Pass 0.78 SPW-709 3/19/2019 H-3 20,369 +/- 421 21,700 17 ,360 - 26,040 Pass 0.94 SPW-818 3/19/2019 H-3 20,457 +/- 424 21,700 17 ,360 - 26,040 Pass 0.94 SPW-845 3/22/2019 U-234 15.1 +/- 0.5 13.6 9.5 -17.7 Pass 1.11 SPW-845 3/22/2019 U-238 15.3+/-0.5 13.1 9.2 -17.0 Pass 1.17 SPW-934 3/19/2019 H-3 20,487 +/- 421 21,700 17,360 - 26,040 Pass 0.94 SPW-1061 3/1 /2019 Ra-226 10.6 +/- 0.3 12.3 8.6 - 16.0 Pass 0.86 SPW-1091 4/10/2019 H-3 20,323 +/- 421 21,700 17,360 - 26,040 Pass 0.94 SPW-1093 4/8/2019 Ra-228 14.9+/-1.9 15.1 10.6 -19.6 Pass 0.98 SPW-1267 4/16/2019 H-3 20,302 +/- 421 21,700 17,360 - 26,040 Pass 0.94 SPW-1339 4/18/2019 H-3 19,924 +/- 417 21,700 17,360 - 26,040 Pass 0.92 SPW-1403° 4/25/2019 Gr. Alpha 56.7 +/- 2.6 72.4 36.2 - 108.6 Pass 0.78 SPW-1403° 4/25/2019 Gr. Beta 43.2 +/- 1.4 54.8 43.8 - 65.8 Fail 0.79 SPW-1427 4/26/2019 H-3 20,119+/-418 21,700 15, 190 - 28,210 Pass 0.93 SPW-1537 5/6/2019 Sr-90 19.9+/-1.2 17.9 14.3 - 21.5 Pass 1.11 W-050719 4/29/2016 Cs-134 38.5 +/- 9.0 36.2 29.0 - 43.4 Pass 1.06 W-050719 4/26/2016 Cs-137 85.2 +/- 8.5 71.9 57.5 - 86.3 Pass 1.18 SPW-1582 5/9/2019 H-3 20,492 +/- 423 21,700 15, 190 - 28,210 Pass 0.94 A-8

TABLE A-4. In-House "Spiked" Samples Concentration*

Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1° Activity Limits ct Acceptance Lab/Known W-050919 4/29/2016 Cs-134 37.4 +/- 8.9 36.2 29.0 - 43.4 Pass 1.03 W-050919 4/26/2016 Cs-137 81.5+/-7.8 71.9 57.5 - 86.3 Pass 1.13 SPW-1596 5/8/2019 Ra-228 14.1+/-1.7 15.1 10.6 -19.6 Pass 0.94 W-051419 4/29/2016 Cs-134 36.2+/-11.7 36.2 29.0 - 43.4 Pass 1.00 W-051419 4/26/2016 Cs-137 75.8 +/- 10.0 71.9 57.5 - 86.3 Pass 1.05 SPW-1676 5/17/2019 H-3 20,233 +/- 420 21,700 15,190 - 28,210 Pass 0.93 SPW-1799 5/20/2019 H-3 20,428 +/- 422 21,700 15,190 - 28,210 Pass 0.94 SPW-1858 5/28/2019 H-3 20,367 +/- 522 21,700 15,190 - 28,210 Pass 0.94 SPW-1890 5/30/2019 H-3 20,206 +/-419 21,700 15,190 -28,210 Pass 0.93 SPW-2014 5/31/2019 Ra-226 11.9 +/- 0.3 12.3 8.6 - 16.0 Pass 0.97 SPW-2030 6/12/2019 Ni-63 377 +/- 45 464.8 325 - 604 Pass 0.81 SPW-2093 6/18/2019 H-3 20,158 +/- 418 21,700 17 ,360 - 26,040 Pass 0.93 W-062419 4/29/2016 Cs-134 33.0 +/- 12.4 36.2 29.0 - 43.4 Pass 0.91 W-062419 4/26/2016 Cs-137 66.0 +/- 10.4 71.9 57.5 - 86.3 Pass 0.92 SPW-2338 6/26/2019 H-3 20,032 +/- 417 21,700 17 ,360 - 26,040 Pass 0.92 SPW-2552 7/1/2019 Gr.Alpha 20.4 +/- 1.5 21.8 10.9 - 32.7 Pass 0.94 SPW-2552 7/1/2019 Gr. Beta 46.1 +/- 1.3 55.7 44.6 - 66.8 Pass 0.83 W-072619 4/29/2016 Cs-134 36.3 +/- 9.2 36.2 29.0 -43.4 Pass 1.00 W-072619 4/26/2016 Cs-137 79.7 +/- 7.6 71.9 57.5 - 86.3 Pass 1.11 SPW-3188 7/30/2019 Ra-226 11.9+/-0.3 12.3 8.6 -16.0 Pass 0.97 SPW-2947 8/9/2019 H-3 20,128 +/- 425 21,700 17,360 - 26,040 Pass 0.93 SPW-3003 8/14/2019 H-3 20,588 +/- 435 21,700 17,360 - 26,040 Pass 0.95 W-081519 4/26/2019 Cs-134 36.2 +/- 9.2 36.2 29.0 - 43.4 Pass 1.00 W-081519 4/26/2019 Cs-137 78.1 +/- 8.4 71.9 57.5 - 86.3 Pass 1.09 W-082119 4/26/2019 Cs-134 32.8 +/- 9.1 36.2 29.0 - 43.4 Pass 0.91 W-082119 4/26/2019 Cs-137 79.1 +/- 7.9 71.9 57.5 - 86.3 Pass 1.10 SPW-3151 8/26/2019 H-3 20,329 +/- 428 21,700 17,360 - 26,040 Pass 0.94 W-082619 4/26/2019 Cs-134 33.3 +/- 17.8 36.2 29.0 - 43.4 Pass 0.92 W-082619 4/26/2019 Cs-137 82.6 +/- 13.2 71.9 57.5 - 86.3 Pass 1.15 W-082719 4/26/2019 Cs-134 33.9 +/- 7.0 36.2 29.0 - 43.4 Pass 0.94 W-082719 4/26/2019 Cs-137 81.4 +/- 6.0 71.9 57.5 - 86.3 Pass 1.13 SPW-3359 8/30/2019 Gr. Alpha 54.2 +/- 0.3 72.4 36.2 - 108.6 Pass 0.75 SPW-3359 8/30/2019 Gr. Beta 59.7 +/- 0.2 54.8 43.8 -65.8 Pass 1.09 SPW-3323 9/6/2019 Ra-228 12.7+/-1.8 15.1 10.6 -19.6 Pass 0.84 W-091019 4/26/2019 Cs-134 31.0+/-11.3 36.2 29.0 - 43.4 Pass 0.86 W-091019 4/26/2019 Cs-137 80.5 +/- 10.0 71.9 57.5 - 86.3 Pass 1.12 SPW-3349 9/10/2019 H-3 19,851 +/- 422 21,700 17,360 - 26,040 Pass 0.91 SPW-3410 9/13/2019 H-3 20,267 +/- 431 21,700 17 ,360 - 26,040 Pass 0.93 W-091719 4/26/2019 Cs-134 39.3 +/- 12.6 36.2 29.0 - 43.4 Pass 1.09 W-091719 4/26/2019 Cs-137 81.1+/-9.9 71.9 57.5 - 86.3 Pass 1.13 SPW-3450 9/17/2019 H-3 20,036 +/- 427 21,700 17,360 - 26,040 Pass 0.92 W-091919 9/19/2019 Cs-134 40.0 +/- 10.7 36.2 29.0 - 43.4 Pass 1.10 W-091919 9/19/2019 Cs-137 71.0 +/- 8.7 71.9 57.5 - 86.3 Pass 0.99 SPW-3569 8/28/2019 Ra-226 11.9+/-0.3 12.3 8.6 -16.0 Pass 0.97 SPW-3571 9/27/2019 H-3 21,026 +/- 440 21,700 17,360 - 26,040 Pass 0.97 A-9

TABLE A-4. In-House "Spiked" Samples 8

Concentration Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsct Acceptance Lab/Known SPW-3615 10/1/2019 Ra-228 18.9 +/- 2.5 14.9 10.4-19.3 Pass 1.27 SPW-3706 10/8/2019 H-3 20,082 +/- 427 21,700 17 ,360 - 26,040 Pass 0.93 SPW-4093 10/14/2019 Gr. Alpha 20.8 +/- 0.1 19.7 9.9 -29.6 Pass 1.06 SPW-4093 10/14/2019 Gr. Beta 63.2 +/- 0.1 61.1 48.9 - 73.3 Pass 1.03 SPW-4095 10/24/2019 H-3 20,684 +/- 432 21,700 17 ,360 - 26,040 Pass 0.95 SPW-4144 9/26/2019 Ra-226 12.8 +/- 0.3 12.3 8.6 -16.0 Pass 1.04 W-091719 3/19/2018 H-3 22,291 +/- 470 21,700 17 ,360 - 26,040 Pass 1.03 SPW-4239 10/30/2019 Ra-228 12.4 +/- 1.8 14.9 10.4 -19.3 Pass 0.84 SPW-4254 11/8/2019 H-3 20,187 +/- 427 21,700 17,360 - 26,040 Pass 0.93 SPW-4368 11/14/2019 H-3 20,386 +/- 429 21,700 17 ,360 - 26,040 Pass 0.94 SPW-4370 10/30/2019 Ra-226 12.8 +/- 0.4 12.3 8.6 -16.0 Pass 1.04 SPW-4472 11/21/2019 H-3 20,479 +/- 432.0 21,700 17,360 - 26,040 Pass 0.94 SPW-4474 11/22/2019 Sr-90 18.9 +/- 1.2 17.9 14.3 - 21.5 Pass 1.06 SPW-4602 12/5/2019 H-3 20,187 +/- 429 21,700 17,360 - 26,040 Pass 0.93 W-121119 3/19/2018 H-3 22,734 +/- 477 21,700 17 ,360 - 26,040 Pass 1.05 SPW-4663 12/11/2019 Ra-228 11.2 +/- 1.6 14.9 10.4 -19.3 Pass 0.75 SPW-4688 12/13/2019 H-3 20,506 +/- 431 21,700 17,360 - 26,040 Pass 0.94 SPW-4734 11/15/2019 Ra-226 12.6 +/- 0.3 12.3 8.6 -16.0 Pass 1.02 SPW-4743 12/5/2019 Ra-226 10.0 +/- 0.3 12.3 8.6 -16.0 Pass 0.81 SPW-4745 12/19/2019 H-3 20,067 +/- 427 21,700 17,360 - 26,040 Pass 0.92 SPW-4889 12/19/2019 Ra-226 9.3 +/- 0.3 12.3 8.6 -16.0 Pass 0.76 SPW-4636 12/27/2019 Tc-99 94.3 +/- 8.2 90.3 72.2 - 108.4 Pass 1.04 SPW-4899 1/3/2020 H-3 20,386 +/- 432 21,700 17,360 - 26,040 Pass 0.94 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 & SPW (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 listed in Attachment A of this report.

e The LCS sample was prepared from an Environmental Resource Associates (ERA) sample of known activity. While the analysis did satisfy the acceptance criteria of the ERA study from which it was sourced, it did not satisfy EIML's internal LCS acceptance criteria. An investigation is in process to determine the reason for the low bias and to evaluate the acceptance criteria.

NOTE: For fish, gelatin is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.

A-10

TABLE A-5. In-House "Blank" Samples Concentration*

0 Lab Codeb Sample Date Analysis Laboratory results (4.66cr) Acceptance Type LLD Activity Criteria (4.66 cr)

SPW-5449 Water 1/7/2019 Gr. Alpha 0.76 -0.30 +/- 0.52 2 SPW-5449 Water 1/7/2019 Gr. Beta 0.42 0.19 +/- 0.31 4 SPW-34 Water 1/7/2019 1-131 0.36 0.13 +/- 0.18 1 SPW-60 Water 11/5/2018 Ra-226 0.03 0.15 +/- 0.03 2 SPW-119 Water 1/14/2019 H-3 148 42 +/- 80 200 SPW-177 Water 1/16/2019 Ra-228 0.93 -0.10+/-0.42 2 SPW-198 Water 1/18/2019 Sr-89 0.67 0.25 +/- 0.50 5 SPW-198 Water 1/18/2019 Sr-90 0.67 -0.16 +/- 0.29 SPW-249 Water 1/24/2019 Ni-63 67 31 +/- 41 200 SPW-255 Water 1/15/2019 Ra-226 0.04 0.16 +/-0.03 2 SPW-280 Water 1/25/2019 Ra-226 0.06 -0.09 +/- 0.14 2 SPW-399 Water 1/31/2019 Ra-226 0.03 0.15 +/- 0.03 2 SPW-460 Water 2/12/2019 Ra-226 0.03 0.15 +/-0.02 2 SPW-567 Water 2/21/2019 Ra-226 0.03 0.13 +/- 0.02 2 SPW-844 Water 3/22/2019 U-234 0.19 0.04 +/- 0.14 SPW-844 Water 3/22/2019 U-238 0.19 0.00+/-0.11 SPW-836 Water 3/21/2019 Ra-228 0.74 0.53 +/- 0.41 2 SPW-1060 Water 3/31/2019 Ra-226 0.04 -0.02 +/- 0.03 2 SPW-1090 Water 4/10/2019 H-3 155 -14 +/- 72 200 SPW-1092 Water 4/8/2019 Ra-228 0.82 0.75 +/- 0.46 2 SPW-1266 Water 4/16/2019 H-3 152 67 +/- 74 200 SPW-1338 Water 4/18/2019 H-3 152 66 +/- 79 200 SPW-1386 Water 4/8/2019 Ra-226 0.03 0.09 +/- 0.03 2 SPW-1426 Water 4/26/2019 H-3 156 34 +/- 75 200 SPW-1536 Water 5/6/2019 Sr-89 0.66 -0.07 +/- 0.45 5 SPW-1536 Water 5/6/2019 Sr-90 0.59 -0.10 +/- 0.26 1 SPW-1581 Water 5/9/2019 H-3 147 73 +/- 77 200 SPW-1644 Water 4/22/2019 Ra-226 0.02 0.15 +/- 0.02 2 SPW-1675 Water 5/17/2019 H-3 154 -30 +/- 71 200 SPW-1798 Water 5/20/2019 H-3 149 24 +/- 73 200 SPW-1857 Water 5/28/2019 H-3 150 54 +/- 74 200 SPW-1889 Water 5/30/2019 H-3 152 45 +/- 73 200 SPW-2013 Water 5/31/2019 Ra-226 0.01 0.13 +/- 0.02 2 SPW-2029 Water 6/12/2019 Ni-63 66 10 +/- 40 200 SPW-2092 Water 6/18/2019 H-3 154 -42 +/- 70 200 SPW-2237 Water 6/26/2019 H-3 150 -9 +/- 69 200 SPW-2107 Water 6/18/2019 1-131 0.16 0.04 +/- 0.09 SPW-2152 Water 6/19/2019 1-131 0.16 0.04 +/- 0.09 A-11

TABLE A-5. In-House "Blank" Samples Concentration" Lab Codeb Sample Date Analysisc Laboratory results (4.66cr) Acceptance Type LLD Activity Criteria (4.66 cr)

SPW-3187 Water 7/30/2019 Ra-226 0.02 0.17 +/- 0.02 2 SPW-2924 Water 8/6/2019 Sr-89 0.71 -0.06 +/- 0.57 5 SPW-2924 Water 8/6/2019 Sr-90 0.59 0.08 +/- 0.28 SPW-2946 Water 8/9/2019 H-3 152 33 +/- 72 200 SPW-3002 Water 8/14/2019 H-3 152 -22 +/- 74 200 SPW-3150 Water 8/26/2019 H-3 151 115 +/- 77 200 SPW-3358 Water 8/30/2019 Gr. Alpha 0.44 -0.08 +/- 0.30 2 SPW-3358 Water 8/30/2019 Gr. Beta 0.72 -0.31 +/- 0.49 4 SPW-3568 Water 8/28/2019 Ra-226 0.03 0.16 +/- 0.03 2 SPW-3322 Water 9/6/2019 Ra-228 0.82 0.46 +/- 0.43 2 SPW-3348 Water 9/10/2019 H-3 150 107 +/- 76 200 SPW-3409 Water 9/13/2019 H-3 154 133 +/- 79 200 SPW-3449 Water 9/17/2019 H-3 147 102 +/- 79 200 SPW-3570 Water 9/27/2019 H-3 151 70 +/- 77 200 SPW-3614 Water 10/1/2019 Ra-228 1.29 1.03 +/- 0.73 2 SPW-3705 Water 10/8/2019 H-3 147 107 +/- 77 200 SPW-4238 Water 10/30/2019 Ra-228 0.99 0.58 +/- 0.52 2 SPW-4253 Water 11/8/2019 H-3 151 80 +/- 76 200 SPW-4367 Water 11/14/2019 H-3 154 42 +/- 74 200 SPW-4369 Water 10/30/2016 Ra-226 0.03 0.14 +/- 0.03 2 SPW-4471 Water 11/21/2019 H-3 155 81 +/- 77 200 SPW-4474 Water 11/21/2019 C-14 12 0+/-7 200 SPW-4476 Water 11/22/2019 Sr-89 0.62 0.23 +/- 0.45 5 SPW-4476 Water 11/22/2019 Sr-90 0.57 -0.16 +/- 0.24 1 SPW-4601 Water 12/5/2019 H-3 155 28 +/- 74 200 SPW-4635 Water 12/9/2019 Tc-99 12 -6 +/- 7 20 SPW-4662 Water 12/17/2019 Ra-228 0.77 0.55 +/- 0.42 2 SPW-4687 Water 12/13/2019 H-3 150 143 +/- 78 200 SPW-4733 Water 11/15/2019 Ra-226 0.03 0.13 +/- 0.03 2 SPW-4742 Water 12/5/2019 Ra-226 0.04 0.10+/-0.10 2 SPW-4744 Water 12/19/2019 H-3 151 119 +/- 81 200 SPW-4888 Water 12/19/2019 Ra-226 0.03 0.15 +/- 0.02 2 SPW-4898 Water 1/3/2020 H-3 159 19 +/- 78 200 a Liquid sample results are reported in pCi/Liter, air filters ( pCiim\ charcoal (pCi/charcoal canister), and solid samples (pCi/g).

b Laboratory codes: W & SPW (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

0 l-131(G); iodine-131 as analyzed by gamma spectroscopy.

d Activity reported is a net activity result.

A-12

TABLE A-6. In-House "Duplicate" Samples Concentration*

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance AP-5499,5500 1/2/2019 Fe-55 941 +/- 220 1027 +/- 226 984 +/- 158 Pass AP-5499,5500 1/2/2019 Sr-89 20.2 +/- 7.3 14.9 +/- 5.7 17.5 +/- 4.7 Pass AP-5499,5500 1/2/2019 Ni-63 12.1 +/- 8.5 15.6 +/- 8.5 13.8 +/- 6.0 Pass CF-20,21 1/2/2019 Gr. Beta 10.0 +/- 0.2 10.7 +/- 0.2 10.3 +/- 0.2 Pass CF-20,21 1/2/2019 Sr-90 0.005 +/- 0.002 0.005 +/- 0.002 0.005 +/- 0.001 Pass CF-20,21 1/2/2019 Be-7 0.27 +/- 0.09 0.29 +/- 0.08 0.28 +/- 0.06 Pass CF-20,21 1/2/2019 K-40 6.69 +/- 0.34 6.83 +/- 0.34 6.76 +/- 0.24 Pass SG-211,212 1/21/2019 Ra-226 7.94 +/- 0.26 8.50 +/- 0.29 8.22 +/- 0.19 Pass SG-211,212 1/21/2019 Ac-228 4.46 +/- 0.37 4.63 +/- 0.43 4.55 +/- 0.28 Pass WW-324,325 2/4/2019 Gr. Alpha 0.68 +/- 0.44 0.49 +/- 0.46 0.59 +/- 0.32 Pass WW-324,325 2/4/2019 Gr. Beta 1.80 +/- 0.55 2.95 +/- 0.63 2.37 +/- 0.42 Pass W-345,346 2/4/2019 H-3 245 +/- 84 277 +/- 85 261 +/- 60 Pass WW-797,798 3/5/2019 H-3 165 +/- 80 222 +/- 83 193 +/- 58 Pass WW-648,649 3/8/2019 H-3 587 +/- 101 630 +/- 102 608 +/- 72 Pass SW-713,714 3/14/2019 H-3 326 +/- 90 254 +/- 86 290 +/- 62 Pass AP-1241, 1242 4/2/2019 Be-7 0.097 +/- 0.018 0.108 +/- 0.020 0.103 +/- 0.013 Pass AP-1285,1286 4/3/2019 Be-7 0.080 +/- 0.014 0.078 +/- 0.012 0.079 +/- 0.009 Pass AP-1306, 1307 4/3/2019 Be-7 0.085 +/- 0.009 0.096 +/- 0.011 0.090 +/- 0.007 Pass AP-1327,1328 4/3/2019 Be-7 0.078 +/- 0.010 0.079 +/- 0.011 0.078 +/- 0.007 Pass AP-1327,1328 4/3/2019 K-40 0.012 +/- 0.007 0.021 +/- 0.010 0.017 +/- 0.006 Pass AP-2119,2120 4/3/2019 Be-7 0.276 +/- 0.098 0.265 +/- 0.116 0.270 +/- 0.076 Pass AP-2225,2226 4/3/2019 Be-7 0.231 +/- 0.128 0.208 +/- 0.123 0.220 +/- 0.089 Pass CF-820,821 4/3/2019 K-40 6.39 +/- 0.30 6.63 +/- 0.37 6.51 +/- 0.24 Pass WW-648,649 4/5/2019 H-3 587 +/- 101 630 +/- 102 608 +/- 72 Pass WW-1043,1044 4/5/2019 H-3 666 +/- 121 662 +/- 121 664 +/- 86 Pass SW-1087,1088 4/8/2019 H-3 9,997 +/- 300 10,330 +/- 305 10, 164 +/- 214 Pass WW-1198,1199 4/9/2019 H-3 562 +/- 99 640 +/- 102 601 +/- 71 Pass LW-1503,1504 4/25/2019 Gr. Beta 1.09 +/- 0.55 1.46 +/- 0.57 1.27 +/- 0.39 Pass WW-1789, 1790 517/2019 H-3 366 +/- 90 400 +/- 92 383 +/- 64 Pass SG-2269,2270 517/2019 Pb-214 39.1 +/- 0.5 40.3 +/- 0.5 39.7 +/- 0.4 Pass SG-2269,2270 517/2019 Ac-228 53.2+/-1.0 57.1+/-1.0 55.2 +/- 0.7 Pass DW-10049,10050 5/7/2019 Ra-226 1.31 +/- 0.13 1.66 +/- 0.15 1.49+/-0.10 Pass DW-10049,10050 5/7/2019 Ra-228 1.24 +/- 0.52 1.33 +/- 0.53 1.29 +/- 0.37 Pass WW-1690A,B 5/8/2019 H-3 325 +/- 89 303 +/- 93 314 +/- 64 Pass S-1812,1813 5/16/2019 K-40 22.0 +/- 0.9 23.3 +/- 1.0 22.6 +/- 0.7 Pass S-1812, 1813 5/16/2019 Cs-137 0.05 +/- 0.03 0.07 +/- 0.04 0.06 +/- 0.02 Pass DW-10053, 10054 5/22/2019 Gr. Alpha 0.93 +/- 0.63 1.14 +/- 0.72 1.04 +/- 0.48 Pass DW-10053, 10054 5/22/2019 Gr. Beta 1.43 +/- 0.62 1.13 +/- 0.59 1.28 +/- 0.43 Pass W-2053,2054 5/29/2019 H-3 1572+/-135 1470 +/- 131 1521 +/- 94 Pass A-13

TABLE A-6. In-House "Duplicate" Samples Concentration*

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance G-1989,1990 6/3/2019 Be-7 0.80 +/- 0.18 0.72 +/-0.15 0.76 +/- 0.12 Pass G-1989,1990 6/3/2019 K-40 6.15 +/-0.51 5.98 +/- 0.46 6.07 +/- 0.34 Pass G-1989,1990 6/3/2019 Gr. Beta 7.24 +/- 0.19 7.00 +/- 0.19 7.12 +/- 0.13 Pass WW-2204,2205 6/6/2019 H-3 3861 +/- 194 3722 +/- 191 3792 +/- 136 Pass S-2031,2032 6/10/2019 Pb-214 5.16 +/- 0.19 4.75 +/- 0.22 4.96 +/-0.15 Pass S-2031,2032 6/10/2019 Ac-228 3.81 +/- 0.31 3.63 +/- 0.33 3.72 +/- 0.23 Pass S-2010,2011 6/10/2019 Pb-214 1.48 +/- 0.10 1.05 +/- 0.11 1.27 +/- 0.07 Pass F-2140,2141 6/12/2019 K-40 1.01 +/- 0.28 1.39 +/- 0.32 1.20 +/- 0.21 Pass S-2162,2163 6/12/2019 Pb-214 0.65 +/- 0.06 0.54 +/- 0.05 0.60 +/- 0.04 Pass S-2162,2163 6/12/2019 Ac-228 0.46 +/- 0.10 0.44 +/- 0.08 0.45 +/- 0.07 Pass S-2162,2163 6/12/2019 K-40 4.22 +/- 0.49 3.81 +/- 0.41 4.02 +/- 0.32 Pass S-2162,2163 6/12/2019 Tl-208 0.09 +/- 0.02 0.10 +/- 0.02 0.09 +/- 0.01 Pass S-2162,2163 6/12/2019 Pb-212 0.34 +/- 0.03 0.26 +/- 0.03 0.30 +/- 0.02 Pass SWT-2355,2356 6/25/2019 Gr. Beta 1.12 +/-0.57 1.24 +/- 0.56 1.18 +/- 0.40 Pass AP-2689,2690 6/28/2019 Be-7 0.089 +/- 0.020 0.075 +/- 0.018 0.082 +/- 0.013 Pass AP-2710,2711 7/1/2019 Be-7 0.091 +/- 0.010 0.097 +/- 0.010 0.094 +/- 0.007 Pass AP-2731,2732 7/2/2019 Be-7 0.073 +/- 0.013 0.072 +/- 0.011 0.072 +/- 0.009 Pass DW-10062, 10063 7/5/2019 Ra-226 4.10 +/- 0.30 4.03 +/- 0.30 4.07 +/- 0.21 Pass DW-10062, 10063 7/5/2019 Ra-228 1.95 +/- 0.60 2.31 +/- 0.62 2.13 +/- 0.43 Pass AP-70818,70819 7/8/2019 Gr. Beta 0.021 +/- 0.004 0.023 +/- 0.004 0.022 +/- 0.003 Pass XW-2459,2460 7/10/2019 H-3 304 +/- 92 234 +/- 89 269 +/- 64 Pass VE-2516,2517 7/10/2019 Be-7 0.63 +/-0.16 0.52 +/- 0.19 0.58 +/- 0.12 Pass VE-2516,2517 7/10/2019 K-40 6.50 +/- 0.47 6.81 +/- 0.54 6.66 +/- 0.36 Pass AP-71518A,B 7/15/2019 Gr. Beta 0.022 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.003 Pass VE-2668,2669 7/16/2019 K-40 3.84 +/- 0.27 3.74 +/- 0.26 3.79 +/-0.19 Pass DW-10076, 10077 7/16/2019 Gr. Alpha 3.01 +/- 0.92 4.13 +/- 0.91 3.57 +/- 0.65 Pass DW-10073, 10074 7/16/2019 Ra-226 1.57 +/-0.18 1.51 +/- 0.21 1.54 +/- 0.14 Pass DW-10073, 10074 7/16/2019 Ra-228 1.29 +/- 0.56 1.48 +/- 0.57 1.385 +/- 0.40 Pass AP-72218A,B 7/22/2019 Gr. Beta 0.013 +/- 0.004 0.016 +/- 0.004 0.015 +/- 0.003 Pass G-2752,2753 7/23/2019 K-40 4.53 +/- 0.42 4.47 +/- 0.46 4.50 +/- 0.31 Pass G-2752,2753 7/23/2019 Be-7 1.98 +/- 0.29 1.96 +/- 0.29 1.97 +/- 0.20 Pass AP-2800,2801 7/25/2019 Be-7 0.208 +/- 0.090 0.321 +/- 0.147 0.264 +/- 0.086 Pass AP-72918A,B 7/29/2019 Gr. Beta 0.026 +/- 0.005 0.025 +/- 0.005 0.025 +/- 0.003 Pass VE-2840,2841 7/31/2019 K-40 3.94 +/- 0.38 3.99 +/- 0.47 3.96 +/- 0.30 Pass AP-2903,2904 8/1/2019 Be-7 0.198 +/- 0.102 0.228 +/- 0.102 0.213 +/- 0.072 Pass P-2882,2983 8/1/2019 H-3 265 +/- 85 327 +/- 88 296 +/- 61 Pass SG-2926,2927 8/5/2019 Pb-214 9.07 +/- 0.39 8.82 +/- 0.39 8.95 +/- 0.28 Pass SG-2926,2927 8/5/2019 Ac-228 9.00 +/- 0.76 8.58 +/- 0.72 8.79 +/- 0.52 Pass AV-2993,2994 8/9/2019 Gr. Beta 1.22 +/- 0.19 1.28 +/- 0.21 1.25 +/- 0.14 Pass AV-2993,2994 8/9/2019 K-40 3.12 +/- 0.36 3.14 +/- 0.35 3.13 +/- 0.25 Pass A-14

TABLE A-6. In-House "Duplicate" Samples Concentration*

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance DW-10088, 10089 8/9/2019 Ra-228 0.60 +/- 0.50 1.20 +/- 0.50 0.90 +/- 0.35 Pass DW-10088, 10089 8/9/2019 Ra-226 1.40 +/- 0.20 0.94 +/- 0.20 1.17 +/-0.14 Pass VE-3016,3017 8/12/2019 Be-7 0.39 +/- 0.12 0.47 0.28 0.43 0.15 Pass VE-3016,3017 8/12/2019 K-40 6.13+/-0.41 6.24 0.64 6.18 0.38 Pass G-3600,3601 8/12/2019 Be-7 4.42 +/- 0.33 4.35 0.27 4.39 0.21 Pass WW-3100,3101 8/14/2019 H-3 480 +/- 96 401 +/- 92 441 +/- 66 Pass Ml-3211,3212 8/27/2019 K-40 1862 +/- 131 1923 +/- 136 1893 +/- 94 Pass Ml-3211,3212 8/27/2019 Sr-90 0.90 +/- 0.33 0.56 +/- 0.29 0.73 +/- 0.22 Pass LW-3512,3513 8/30/2019 Gr. Beta 0.79 +/- 0.50 1.39 +/- 0.58 1.09 +/- 0.38 Pass DW-10100,10101 9/5/2019 Ra-226 0.50 +/- 0.11 0.57 0.12 0.54 +/- 0.08 Pass DW-10100,10101 9/5/2019 Ra-228 3.38 +/- 0.82 2.54 1.03 2.96 +/- 0.66 Pass DW-10111,10112 9/23/2019 Gr. Alpha 1.72 +/- 0.73 1.41 0.68 1.57 +/- 0.50 Pass DW-10115, 10116 9/25/2019 Ra-228 3.65 +/- 0.80 2.76 0.68 3.21 +/- 0.52 Pass DW-10115,10116 9/25/2019 Ra-226 2.99 +/- 0.23 2.74 0.25 2.87 +/- 0.17 Pass WW-3793,3794 10/8/2019 Gr. Beta 3.75+/-1.18 4.34 1.20 4.05 +/- 0.84 Pass BS-3879,3880 10/9/2019 Pb-214 0.60 +/- 0.03 0.65 +/- 0.05 0.63 +/- 0.03 Pass BS-3879,3880 10/9/2019 Ra-226 1.27 +/- 0.14 1.15 +/- 0.14 1.21 +/- 0.10 Pass BS-3879,3880 10/9/2019 K-40 11.05 +/- 0.29 10.69 +/- 0.30 10.87 +/- 0.21 Pass BS-3879,3880 10/9/2019 Pb-212 0.58 +/- 0.02 0.55 +/- 0.02 0.56 +/- 0.01 Pass BS-3879,3880 10/9/2019 Tl-208 0.21 +/- 0.02 0.21 +/- 0.01 0.21 +/- 0.01 Pass BS-3879,3880 10/9/2019 Bi-212 0.75 +/- 0.17 0.62 +/- 0.17 0.68 +/-0.12 Pass BS-3879,3880 10/9/2019 Bi-214 0.57 +/- 0.02 0.52 +/- 0.06 0.54 +/- 0.03 Pass BS-4161,4162 10/29/2019 K-40 15.3 +/- 0.6 15.3 +/- 0.7 15.3 +/- 0.5 Pass BS-4161,4162 10/29/2019 Ra-226 2.16 +/- 0.35 2.27 +/- 0.78 2.22 +/- 0.43 Pass DW-10126, 10127 10/22/2019 Ra-228 0.85 +/- 0.58 1.19 +/-0.62 1.02 +/- 0.42 Pass DW-10129,10130 10/22/2019 Gr. Alpha 1.44 +/- 0.96 3.06 +/- 0.95 2.25 +/- 0.68 Pass SG-4071 10/22/2019 Ac-228 2.10 +/- 0.16 2.16 +/-0.20 2.13 +/- 0.13 Pass SPSG-4071,4072 10/22/2019 Pb-214 1.61+/-0.10 1.29 +/- 0.08 1.45 +/- 0.06 Pass SS-3900,3901 10/15/2019 Bi-212 0.29 +/-0.14 0.19 +/- 0.12 0.24 +/- 0.09 Pass WW-4291,4292 11/5/2019 H-3 481 +/- 97 528 +/- 97 505 +/- 68 Pass DW-10139,10140 11/6/2019 Ra-228 2.61 +/- 0.62 2.26 +/- 0.63 2.44 +/- 0.44 Pass DW-10139,10140 11/6/2019 Ra-226 1.49+/-0.17 1.32 +/- 0.19 1.41 +/- 0.13 Pass WW-4270,4271 11/6/2019 H-3 112 +/- 78 165 +/- 81 139 +/- 56 Pass S-4312,4313 11/7/2019 K-40 20.2 +/- 0.8 23.0 +/- 0.9 21.6 +/- 0.6 Pass AP-4379,4380 11/12/2019 Be-7 0.133 +/- 0.075 0.134 +/- 0.073 0.134 +/- 0.052 Pass S-4422,4223 11/13/2019 Pb-214 1.22 +/- 0.09 1.28 +/-0.10 1.25 +/- 0.07 Pass S-4422,4423 11/13/2019 Ac-228 1.14 +/- 0.15 1.21 +/- 0.17 1.18 +/- 0.11 Pass WW-4556,4557 11/13/2019 H-3 438 +/- 96 482 +/- 98 460 +/- 69 Pass S0-5024,5025 11/14/2019 K-40 6.60 +/- 0.54 6.26 +/- 0.58 6.43 +/- 0.40 Pass Ml-4443,4444 11/18/2019 K-40 1304+/-114 1340 +/- 109 1322 +/- 79 Pass A-15

TABLE A-6. In-House "Duplicate" Samples Concentration*

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance SW-4492,4493 11/19/2019 H-3 188 +/- 87 264 +/- 97 226 +/- 65 Pass WW-4577,4578 11/21/2019 H-3 212 +/- 83 232 +/- 84 222 +/- 59 Pass AP-4514,4515 11/21/2019 Be-7 0.130 +/- 0.055 0.193 +/- 0.112 0.162 +/- 0.062 Pass SWT-4598,4599 11/26/2019 Gr. Beta 1.43 +/- 0.57 1.14+/-0.54 1.28 +/- 0.39 Pass AP-120218A,B 12/2/2019 Gr. Beta 0.009 +/- 0.004 0.013 +/- 0.004 0.011 +/- 0.003 Pass S-4644,4645 12/4/2019 Pb-214 1.01 +/- 0.09 0.91 +/- 0.09 0.96 +/- 0.06 Pass S-4644,4645 12/4/2019 Ac-228 0.85 +/- 0.15 0.96 +/- 0.16 0.91 +/- 0.11 Pass AP-121618A,B 12/16/2019 Gr. Beta 0.028 +/- 0.005 0.030 +/- 0.005 0.029 +/- 0.003 Pass S-4735,4736 12/16/2019 Pb-214 9.33 +/- 0.38 9.45 +/- 0.27 9.39 +/- 0.23 Pass S-4735,4736 12/16/2019 Ac-228 13.4 +/- 0.7 14.9 +/- 0.7 14.1 +/- 0.5 Pass AP-122318A,B 12/23/2019 Gr. Beta 0.034 +/- 0.005 0.035 +/- 0.005 0.035 +/- 0.003 Pass AP-123018A,B 12/30/2019 Gr. Beta 0.037 +/- 0.005 0.037 +/- 0.005 0.037 +/- 0.004 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).

b CH (Charcoal Canister), OW (Drinking Water), E (Egg), F (Fish), G (Grass), LW (Lake Water), P (Precipitation),

PM (Powdered Milk), S, (Solid), SG (Sludge), SO (Soil), SS (Shoreline Sediment), SW (Surface Water),

SWT (Surface Water Treated), SWU (Surface Water Untreated), VE (Vegetation), W Water (Water), WW (Well Water).

A-16

TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration*

Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-609 2/1/2019 Gross Alpha 0.16+/-0.03 0.528 0.158 - 0.898 Pass MAAP-609 2/1 /2019 Gross Beta 1.09 +/- 0.07 0.948 0.474 - 1.422 Pass MAW-550 2/1/2019 Gross Alpha 0.73 +/- 0.06 0.84 0.25 - 1.43 Pass MAW-550 2/1 /2019 Gross Beta 2.26 +/- 0.06 2.33 1.17 -3.50 Pass MAS0-605 2/1 /2019 Am-241 38.89 +/- 5.92 49.9 34.9 +/- 64.9 Pass MAS0-605 2/1/2019 Cs-134 0.45 +/- 2.52 0.0 NA c Pass MAS0-605 2/1/2019 Cs-137 1273.1+/-13.0 1164 815-1513 Pass MAS0-605 2/1/2019 Co-57 0.46+/-1.1 0.0 NA c Pass MAS0-605 2/1/2019 Co-60 857.96 +/- 8.52 855.0 599 - 1112 Pass MAS0-605 2/1 /2019 Mn-54 1,138.0+/-13.5 1027 719 - 1335 Pass MAS0-605 2/1 /2019 Zn-65 730.92 +/- 16.48 668 468 - 868 Pass MAS0-605 2/1 /2019 K-40 676 +/- 47 585 410 - 761 Pass MAS0-605 2/1/2019 Sr-90 0.0007 +/- 0.0007 0.000 NAC Pass MAS0-605 2/1/2019 Pu-238 78.15 +/- 6.11 71.0 49.7 - 92.3 Pass MAS0-605 2/1/2019 Pu-239/240 65.00 +/- 5.4 59.8 41.9 -77.7 Pass MAS0-605 2/1/2019 U-234 65 +/- 13 56 39 - 73 Pass MAS0-605 2/1/2019 U-238 237 +/- 23 205 144 - 267 Pass MAW-613 2/1/2019 Am-241 0.46 +/- 0.03 0.582 0.407 - 0.757 Pass MAW-613 2/1/2019 Cs-134 5.49+/-0.18 5.99 4.19 - 7.79 Pass MAW-613 2/1/2019 Cs-137 0.089 +/- 0.080 0 NA c Pass MAW-613 2/1/2019 Co-57 10.87 +/- 0.24 10.00 7.0 -13.0 Pass MAW-613 2/1/2019 Co-60 6.78 +/- 0.19 6.7 4.7 - 8.7 Pass MAW-613 2/1/2019 Mn-54 8.98 +/- 0.17 8.4 5.9 - 10.9 Pass MAW-613 2/1/2019 Zn-65 0.096 +/- 0.141 0 NA c Pass MAW-613 2/1/2019 Fe-55 0.004 +/- 4.00 0 NA c Pass MAW-613 2/1 /2019 Ni-63 5.54 +/- 1.52 5.8 4.1 -7.5 Pass MAW-613 2/1/2019 Sr-90 6.02 +/- 0.53 6.35 4.45 - 8.26 Pass MAW-613 2/1/2019 Pu-238 0.315 +/- 0.088 0.451 0.316 - 0.586 Fail*

MAW-613 2/1/2019 Pu-239/240 0.07 +/- 0.07 0.005 NA ct Pass MAW-613 2/1/2019 . U-234 0.96 +/- 0.07 0.800 0.56 +/- 1.04 Pass MAW-613 2/1/2019 U-238 0.94 +/- 0.07 0.810 0.57 +/- 1.05 Pass MAAP-611 2/1/2019 Cs-134 0.185 +/- 0.025 0.216 0.151 - 0.281 Pass MAAP-611 2/1/2019 Cs-137 0.288 +/- 0.045 0.290 0.203 - 0.377 Pass MAAP-611 2/1/2019 Co-57 0.369 +/- 0.033 0.411 0.288 - 0.534 Pass MAAP-611 2/1 /2019 Co-60 0.333 +/- 0.045 0.340 0.238 - 0.442 Pass MAAP-611 2/1/2019 Mn-54 0.546 +/- 0.058 0.547 0.383 - 0.711 Pass MAAP-611 2/1/2019 Zn-65 0.025 +/- 0.0348 0 NAC Pass MAAP-611 2/1/2019 Sr-90 1.34 +/-0.13 0.662 0.463 - 0.861 Fail1 MAAP-611 2/1/2019 U-234 4.14 +/-0.97 0.106 0.074 -0.138 Fail 1 1

MAAP-611 2/1/2019 U-238 3.89 +/- 0.94 0.110 0.077 -0.143 Fail MAW-601 2/1/2019 1-129 0.56 +/- 0.08 0.616 0.431 - 0.801 Pass A-17

TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration*

Reference Known Control 0

Lab Code b Date Analysis Laboratory result Activity Limits Acceptance MAVE-607 2/1/2019 Cs-134 2.33 +/- 0.10 2.44 1.71-3.17 Pass MAVE-607 2/1/2019 Cs-137 2.62 +/- 0.13 2.30 1.61 - 2.99 Pass MAVE-607 2/1/2019 Co-57 2.39 +/- 0.11 2.07 1.45 - 2.69 Pass MAVE-607 2/1/2019 Co-60 0.046 +/- 0.04 0 NA c Pass MAVE-607 2/1/2019 Mn-54 0.031 +/- 0.04 0 NA c Pass MAVE-607 2/1/2019 Sr-90 0.013 +/- 0.022 0 NA c Pass MAAP-3299 8/1/2019 Gross Alpha 0.13 +/- 0.03 0.528 0.158 - 0.898 Fail 9 MAAP-3299 8/1/2019 Gross Beta 1.06 +/- 0.07 0.937 0 .469 - 1.406 Pass MAW-3252 8/1/2019 Gross Alpha 0.93 +/- 0.06 1.06 0.32 - 1.80 Pass MAW-3252 8/1/2019 Gross Beta 3.03 +/- 0.07 3.32 1.66 - 4.98 Pass MAS0-3297 8/19/2019 Cs-134 881.98 +/- 9.03 1020 714 - 1326 Pass MAS0-3297 8/19/2019 Cs-137 871.50+/-10.83 789 552 - 1026 Pass MAS0-3297 8/19/2019 Co-57 -1.72 +/- 3.01 0 NA c Pass MAS0-3297 8/19/2019 Co-60 783.69 +/- 8.21 760 532 - 988 Pass MAS0-3297 8/19/2019 Mn-54 834.48 +/- 11.29 745 522 - 969 Pass MAS0-3297 8/19/2019 Zn-65 -3.01 +/- 5.27 0 NA c Pass MAS0-3297 8/19/2019 K-40 662.91 +/- 42.65 555 389 - 722 Pass 0

MAW-3240 8/1/2019 Cs-134 -0.08 +/- 0.06 0 NA Pass MAW-3240 8/1/2019 Cs-137 18.48 +/- 0.90 18.4 12.9 - 23.9 Pass MAW-3240 8/1/2019 Co-57 14.68 +/- 0.52 15.6 10.9 - 20.3 Pass MAW-3240 8/1/2019 Co-60 8.67 +/- 0.39 8.8 6.2 - 11.4 Pass MAW-3240 8/1/2019 Mn-54 20.72 +/- 0.93 20.6 14.4 - 26.8 Pass MAW-3240 8/1/2019 Zn-65 20.52 +/- 1.05 20.3 14.200 - 26.400 Pass 0

MAW-3240 8/1/2019 K-40 5.11 +/- 0.68 0 NA Fail MAW-3240 8/1/2019 H-3 179.52 +/- 3.32 175 123 - 228 Pass MAW-3240 8/1/2019 U-234 1.11 +/- 0.04 1.07 0.75 - 1.39 Pass MAW-3240 8/1/2019 U-238 1.08 +/- 0.04 1.05 0.74 - 1.37 Pass MAVE-3295 8/1/2019 Cs-134 0.02 +/- 0.02 0 NA c Pass MAVE-3295 8/1/2019 Cs-137 3.38 +/- 0.32 3.28 2.30 - 4.26 Pass MAVE-3295 8/1/2019 Co-57 4.99 +/- 0.51 4.57 3.20 - 5.94 Pass MAVE-3295 8/1/2019 Co-60 5.29 +/- 0.39 5.30 3.71 - 6.89 Pass MAVE-3295 8/1/2019 Mn-54 4.73 +/- 0.45 4.49 3.14 - 5.84 Pass MAVE-3295 8/1/2019 Zn-65 3.10 +/- 0.31 2.85 2.00 - 3.71 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) and MAVE (vegetation).

0 MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

d Provided in the series for "sensitivity evaluation". MA PEP does not provide control limits.

• Past results have been acceptable so will watch to see if a trend develops.

1 An erroneous volume conversion caused some incorrect values to be submitted. If the conversion had been performed properly the results in Bq/sample would have been (Sr-90: 0.671 +/- 0.066) and (U-234: 0.153 +/- 0.036) and (U-238: 0.144 +/- 0.035).

This result had been included in the Uranium investigation. See footnote "C" on Table A-1.

9 The lab will adopt a MAPEP specific gross alpha/beta filter calibration as discussed in the MAPEP test instructions ..

Utilizing a MAPEP specific calibration, the result in Bq/sample yields a result of ( 0.39 +/- 0.09 Bq/total).

A-18

8 TABLEA-8. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) .

MRAD-30 Study Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Value c Limits d Acceptance ERAP-846 3/18/2019 Am-241 19.1 18.7 13.3 - 24.9 Pass ERAP-846 3/18/2019 Cs-134 612 721 468 - 884 Pass ERAP-846 3/18/2019 Cs-137 679 634 521 - 832 Pass ERAP-846 3/18/2019 Co-60 93.7 93.8 79.7-119 Pass ERAP-846 3/18/2019 Fe-55 612 718 262 - 1150 Pass ERAP-846 3/18/2019 Mn-54 < 0.5 < 50.0 0.00 - 50.0 Pass ERAP-846 3/18/2019 Zn-65 1500 1380 1130-2110 Pass ERAP-846 3/18/2019 Pu-238 34.0 33.8 25.5 - 41.5 Pass ERAP-846 3/18/2019 Pu-239 64.9 67.0 50.1 - 80.8 Pass ERAP-846 3/18/2019 Sr-90 199 181 114 - 246 Pass ERAP-846 3/18/2019 U-234° 29.0 18.2 13.5 - 21.3 Fail ERAP-846 3/18/2019 U-238° 28.6 18.1 13.7-21.6 Fail ERAP-848 3/18/2019 Gross Alphi: 48.4 50.3 26.3 - 82.9 Pass ERAP-848 3/18/2019 Gross Beta 95.5 78.6 47.7-119 Pass

• Results obtained by Environmental, Inc .. Midwest Laboratory (EIML) as a participant in the crosscheck program for proficiency testing administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory code ERAP (air filter). Results are reported in units of (pCi/Filter).

c The ERA Assigned values for the air filter standards are equal to 100% of the parameter present in the standard as determined by the gravimetric and/or volumetric measurements made during standard preparation as applicable.

d The acceptance limits are established per the guidelines contained in the Department of Energy (DOE) report EML-564, Analysis of Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP)

Data Determination of Operational Criteria and Control Limits for Performance Evaluation Purposes or ERA's SOP for the generation of Performance Acceptance Limits.

• Failure traced to an over-estimated U-232 tracer value. Tracer has been re-standardized. (See footnote "c" on Table A-1).

A-19

~*L All Es:pvironmental, Inc.

,..~/"\I Midwest Laboratory 700 Landwehr Road* Northbrook. IL 60062-2310 phone (847) 564-0700 *fax (847) 564-4517 Appendix B Data Reporting Conventions B-1

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 +/- s1 and x2 +/- s2 Reported result: x +/- s; where x = (1/2) (x 1 + x2 ) ands = (1/2) ~ s~ + si 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 examp~, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers x 1 , x2 . . . xn are defined as follows:

x =r; 1

Ix s-

-~~ \j~

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.

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~*L. All EIJVironmental, Inc.

,..~/'"\I Midwest Laboratory 700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 5$4-0700 *fax (847) 5$4--4517 Appendix C Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas C-1

APPENDIX C Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural 8

background in unrestricted areas .

3 Air (pCi/m ) Water (pCi/L)

Gross alpha 1 x 10-3 Strontium-89 8,000 Gross beta Strontium-90 500 1

lodine-131b 2.8x10- Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 Potassium-40 c 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1x10 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.

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APPENDIX D

SUMMARY

OF THE LAND USE CENSUS AND REMP-GWPP DATA D-1

Appendix D Summary of the 2019 Land Use Census and REMP-GWPP Data The Duane Arnold Energy Center Land Use Census was completed during September 2019 . All residences, milk animals, cattle, and gardens greater than 500 square feet were identified within three miles for each of the 16 meteorological sectors. If none were identified within three-mile range, additional surveys were performed out to a distance of five miles. The 16 meteorological sectors were identified using Google Earth and digital compass rose overlay for accuracy and precision.

The 2019 Land Use Census identified 81 gardens , which is 37 fewer gardens than in 2018 and 40 fewer gardens than in 2017. Six farmers/residents provided vegetation samples including two adjacent neighbors to DAEC, D-58 and D-57. Vegetation providers are found in ODAM, Table 5-1 . Gardens were identified using Google Earth ,

Linn County GIS data, field observation, and interviewing local residents.

There are no nearest resident changes. In addition, the Pleasant Creek State Recreation Area has a large transient population of 50-300 people camping in RV's and tents from April to October. An analysis of 2016 data indicated an air sampler should be installed near this population . Therefore, an air sampler and TLD were installed in 2018 and the location is identified as D-4, Pleasant Creek SRA.

There are six nearest livestock change attributed to field observation verification .

Farmers in the NW and ENE sectors were observed to have goats. If the farmer provides goat milk, the farm will be included as a sample location in the ODAM, Table 5-1. The Iowa Department of Agriculture and Land Stewardship provided a list of permitted commercial dairy farms located with Benton and Linn Counties. Large commercial dairies were included in the survey, but none were located within five miles of the DAEC facility. DAEC continues to collect milk samples from two permitted dairy D-2

farms located in WSW and SW sectors. No goat milk samples were collected in 2019 from D-76, ODAM table 5-1.

The Cedar River was surveyed by University of Iowa Hygienic Laboratory boat on June 13, 2019, and August 23, 2019, for water use downstream of the DAEC to Cedar Rapids. Both surveys identified no new usages of river water when compared to previous surveys. Recreational fishing is the only identified food pathway use of Cedar River water between the DAEC and the City of Cedar Rapids eight miles down-river.

The State of Iowa Hygienic Laboratory performed fish sampling on June 11, 2019, and August 16, 2019. Fish filets from smallmouth bass, northern pike, white crappie, channel catfish, and largemouth bass were processed for off-site laboratory analysis and results indicate no impact to human consumable fish.

Cedar River bed sediment samples were collected on April 1, 2019, and October 18, 2019. A background sample from D-49 identified Cesium 137 (Cs-137), Similarly, on-site sediment samples collected from D-15a and D16 on June 20, 2019, also identified Cs-137. An investigation with the State of Iowa Hygienic Laboratory determined the source of Cs-137 is not from DAEC operations, but rather historical atmospheric deposition from nuclear weapon testing.

Benton County Public Health Department and Linn County Public Health Department provided ground water well permit data. In 2019, no new drinking wells were installed within three miles of the facility and none of these wells are impacted by plant activities.

As a result of the 2019 Land Use Census, adjustments were made to the Meteorological Information and Dose Assessment System (MIDAS-NU) projection software model for changes in receptor distances. No significant annual dose corrections were necessary. The 2019 annual radiation dose assessment can be found in Appendix E.

In accordance with the DAEC's Environmental Sampling Procedure ESP 4.4, "Land Use Census", no changes in land use were identified that would adversely affect the safe operation of the DAEC, or that would warrant an update of the DAEC Updated Final Safety Analysis Report (UFSAR). Examples of land use that would warrant an UFSAR update include new hazards near the DAEC such as new gas pipelines or new installations utilizing toxic gases.

NextEra Energy Resources, Duane Arnold has committed to compliance with NEI 07-07, "Nuclear Energy lnstitute's Industry Ground Water Protection Initiative".

Per NEI 07-07, the following information is presented:

• Radioactive reactor-by-product material was identified in multiple groundwater samples collected by the DAEC's Ground Water Protection Program (GWPP).

The following was included to the DAEC Offsite Dose Assessment Manual (ODAM):

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"In February 2016, the GWPP routine sampling identified a contaminate plume in the shallow aquifer (less than 25 feet deep). Release standards are set forth in Section 6.0, Radiological Liquid Effluent Release 0.6.1.2, Table 7.1-2. In accordance with GWPP Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water standards for tritium, 20,000 pCi/L, groundwater batch and continuous releases are expected less than (<) 20,000 pCi/L. Groundwater samples are analyzed on-site and validated by off-site secondary laboratory. Off-site laboratory results are published Annual Radiological Environmental Operating Report."

• There are 56 monitoring wells on-site. Tritium concentrations from on-site monitoring wells range from non-detectable at less than (<) 150 pCi/L to 95,396 pCi/L, from monitoring well MW-22A (D-66). Gross alpha values in several samples are believed to be influenced by naturally occurring radioactive materials in the environment, i.e. radon. No on-site or neighboring drinking water wells are installed in this shallow aquifer. No plant by-products were identified in any drinking water samples or samples from the Cedar River at the intake, D-50, and the discharge point, D-51. Tritiated groundwater remains within the owner controlled area and the shallow aquifer is undergoing mitigation in accordance with ACP 1411.35.

From January 1 to December 31, 2019, three extraction wells were in operation and are designed to remove tritiated groundwater continuously from the shallow aquifer. In addition, temporary mitigation of monitoring wells was performed at MW-08A (D-128A),

MW-22A (D-66), and MW-23A (D-67). For specific liquid effluent release data, see the 2019 Duane Arnold Annual Radioactive Material Release Report.

• The United States Nuclear Regulatory Commission, NRC, provides an informative resource for tritium. The information can be found at:

https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/tritium-radiation-fs.html Updates to REMP and GWPP sampling include:

1. D-6 Center Point and D-7 Shellsburg air samplers will be continued until 2021.

2. D-58 sample location includes groundwater, vegetables, and meat (chicken)

3. D-97 sample location was corrected to account for surface water samples.

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APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT E-1

Appendix E Annual Radiation Dose Assessment The annual offsite radiation dose to a member of the public was determined by assessment of environmental dosimetry results and by calculations based on monitored effluent releases.

Section A. Dose Contribution from Direct Radiation Direct radiation dose from the operation of the DAEC was reported by TLDs placed at locations in the surrounding environment as described in the Offsite Dose Assessment Manual (ODAM).

1. Pre-operational and 2019 TLD results were evaluated with a paired difference statistical test.

The evaluation concluded that there were no significant differences in the TLD populations for the 0.5 mile and 1 mile TLD populations as per Environmental Sampling Procedure, ESP 4.5.

2. As stated in Part 1 of this report, no plant effect was indicated by the TLDs when dose results were compared to the estimated average natural background for the central United States.

Section B. Estimated Offsite Dose from Effluent Releases

1. The contribution of dose to a member of the public most likely to be exposed from liquid and gaseous effluent releases was calculated using the Meteorological Information and Dose Assessment System (MIDAS) computer program in accordance with the ODAM. The calculation methods follow those prescribed by Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I".

2. Following calculation of offsite doses, the appropriateness of REMP sampling station types and locations was reviewed. The current sampling scheme was determined to be adequate for the identified receptors.

Results of the MIDAS dose calculations are displayed below.

1.) There were 82 batch and continuous releases of radioactive material (tritium) to liquid effluents (groundwater mitigation) in 2019. The maximum dose from tritiated groundwater release to a child total body and liver was 0.114 mrem.

2.) The maximum dose to air at the site boundary from noble gases released was 0.00724 mrad from gamma radiation at 481 meters towards the South-Southeast.

3.) The maximum dose to air at the site boundary from noble gases released was 0.0000847 mrad beta radiation at 4,022 meters towards the West-Northwest.

4.) The whole body dose equivalent to the hypothetical maximally exposed individual from noble gases was 0.00270 mrem, at 805 meters towards the West.

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5.) The skin dose equivalent to the hypothetical maximally exposed individual (child) from noble gases was 0.00270 mrem, at 805 meters towards the West.

6.) The hypothetical maximally exposed organ due to airborne iodines and particulates with half-lives greater than eight days (excluding carbon-14) was the lungs of a child at 805 meters towards the West, with an estimated dose equivalent of 0.00557 mrem.

7.) The hypothetical maximally exposed organ due to airborne carbon-14 was the bone of a child located 3,510 meters to the West-Northwest of the site. The dose was 0.385 mrem.

Conclusion No measurable dose due to the operation of the DAEC or the DAEC ISFSI was detected by environmental TLDs in 2019. The calculated doses are below the regulatory limits stated in Appendix I to 10CFR50, 40CFR 190, and 10 CFR 72.104.

Estimated Maximum Offsite Individual Doses for 2019 Type Age Distance Direction Dose or Dose Equivalent Annual 10 CFR 50, Group (meters) (mrem) Appendix I "Limit" Direct Radiation None *

(as measured by TLDs)

Liquid Releases Whole Body Dose Child D* SE 0.114 mrem 3 mrem Organ Dose Child - D* SE 0.114 mrem 10 mrem Liver Noble Gas Gamma Air Dose 481 SSE 0.000724 mrad 10 mrad Beta Air Dose 4.022 WNW 0.0000847 mrad 20 mrad Whole Body All 805 w 0.00270 mrem 5 mrem Skin Child 805 w 0.00270 mrem 15 mrem Particulates & Iodines Organ Dose Child- 805 w 0.00557 mrem 15 mrem Lungs Carbon 14 Organ Dose Child- 3,015 WNW 0.385 mrem 15 mrem Bone

• There is no Appendix I limit for direct radiation. Compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid is demonstrated in the Duane Arnold Energy Center 2018 Annual Radiological Environmental Operating Report, subsections "Ambient Radiation (TLDs)" and "ISFSI Facility Operations Monitoring".

D* Receptor location is aquatic pathway at Cedar River, See Offsite Dose Assessment Manual, ODAM, figure 3-2.

E-3

The following graphs are TLD trends based on distance to the facility over time.

DAEC ANNUAL ENVIRONMENTAL TLD RESULTS 95 T"---~

'. ~I~--.-~1_M_i_le~~-o-~H_a_lf_M_i_le~~.....~3_M_i_le_s~~......~c_o~n_tr_o_IT_L_D_s~~

YEAR OBSERVED DAEC ANNUAL ENVIRONMENTAL TLD RESULTS 95.00 85.00 Ig 75.00 LU 8

3M~es E-4

Appendix E Errata Correction and Amendments

1. The 2018 Annual Radiological Environmental Operating Report was provided to the NRC on May 14, 2019, ADAMS Accession No. ML19134A051. That report contained a typographical error such that the table heading on page E-3 cited 2017 when it should have cited 2018. NextEra Energy Duane Arnold, LLC has determined the error to be small in accordance with Regulatory Guide 1.21, Revision 2, Section 7.1. The affected page has been submitted to the NRC by letter dated May 7, 2020.

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