Text

2023 Annual Radiological Environmental Operating Report
	ML24135A204
Person / Time
Site:	Duane Arnold
Issue date:	05/08/2024
From:	Both J; NextEra Energy Duane Arnold
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NG-24-0004
	Download: ML24135A204 (1)
	v • d • e

May 8, 2024 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 NEXTeraM EN~~~~

NG-24-0004 DQAP

Subject:

2023 Annual Radiological Environmental Operating Report Please find as Enclosure 1 to this letter, a copy of NextEra Energy Duane Arnold, LLC's 2023 Annual Radiological Environmental Operating Report for the Duane Arnold Energy Center, pursuant to the requirements of DODAM Section 8.2.2 and DQAP Appendix F.

This letter contains no new commitments and does not revise any existing commitments.

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

Justin Both Decommissioning Director NextEra Energy Duane Arnold, LLC Enclosure cc:

Regional Administrator, USNRC, Region Ill Inspector, USNRC, Duane Arnold Energy Center Project Manager, USNRC, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

Duane Arnold Energy Center 2023 Annual Radiological Environmental Operating Report 78 pages follow Enclosure to NG-24-0004

NEXTeraM EN ER~G~7~~*

DUANE ARNOLD 2023 Annual Radiological Environmental Operating Report Duane Arnold Energy Center Cedar Rapids, Iowa Docket No. 50-331 January 1, 2023 through December 31, 2023 Prepared By:_::::::;~~~~-Le:~;.....__---

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._:)- / ~/ Q.. y Michael Casey, Radiation Protectio and Environmental Manager Reviewed By: cf i4L Date: s [7 {_z '1 Lonnie Helms, Radiatio tectio Project Manager '

Approved By:~~k"~~~~~

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Decommissioning Director 7

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700 Landwehr Road

Northbrook, IL 60062-2310 phone (847) 564-0700

fax (847) 564-4517 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, 2023 Prepared by Microbac Laboratories - Northbrook Project No. 8001

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a-N.J Approved: -

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Ashok Banavali, Ph.D.

Laboratory Director

PREFACE Staff members of the Microbac Laboratories - Northbrook 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 Microbac Laboratories - Northbrook.

ii

TABLE OF CONTENTS PARTI 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............................................................4 3.3 Program Execution............................................................................................... 5 3.4 Laboratory Procedures..................................................................................... 5 3.5 Program Modifications.......................................................................................... 6 4.0 RE SUL TS AND DISCUSSION...................................................................................... 7 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............................................................................................. 10

6.0 REFERENCES

CITED................................................................................................ 25 APPENDICES A

lnterlaboratory Comparison 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 iii

TABLE OF CONTENTS (continued)

PARTII Data Tabulations and Analyses...................................................................................... i iv

LIST OF TABLES No.

Page 5.1 Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic Analyses.................................................................................................................... 11 5.2 Sample Collection and Analysis Program..................................................................... 12 5.3 Sampling Locations, DAEC.......................................................................................... 14 5.4 Type and Frequency of Collections.............................................................................. 16 5.5 Sample Codes for Tables 5.4 and 5.6.......................................................................... 17 5.6 Program Deviations.......................................................................................................... 18

5. 7 Radiological Environmental Monitoring Program Summary......................................... 19 In addition, the following tables are included in the Appendices:

Appendix A A-0 Attachment A.................................................................................................................. A-2 A-1 Environmental Resource Associates (RAD).................................................................. A-3 A-2 lnterlaboratory Comparison Program Results, Thermoluminescent Dosimeters(TLDs).......................................................................... A-4 A-3 In-house "Spiked" Samples............................................................................................ A-6 A-4 In-house "Blank" Samples............................................................................................ A-8 A-5 In-house "Duplicate" Samples.................................................................................... A-10 A-6 Department of Energy MAPEP comparison results.................................................... A-14 A-7 Environmental Resource Associates (MRAD).................................................... A-16 AppendixC C-1 Maximum permissible concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas....................................................... C-2 V

LIST OF FIGURES 5.1 Environmental Monitoring Programs Sampling near the Duane Arnold Energy Center small area........................................................ 23 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles from DAEC Large Area................................................................... 24 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 2023. 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, 197 4. The reactor reached 100% power on August 12, 197 4. Commercial operation began on February 1, 1975.

The DAEC permanently shut down on August 10, 2020. NextEra Energy Duane Arnold (NEDA) informed the NRC by letter dated August 27, 2020 (Accession No. ML20240A067); certifying the permanent cessation of power operations at the DAEC.

In October 2020 NEDA certified by letter (ML20286A317) the permanent defueling of the reactor at DAEC. Therefore, as specified in 10 CFR 50.82(a)(2), the 10 CFR Part 50 license for DAEC no longer authorizes operations of the reactor or emplacement or retention of fuel into the reactor vessel.

In April 2022 all the nuclear fuel had been removed from the fuel pool and placed in dry cask storage at the site Independent Spent Fuel Storage Installation (ISFSI). There are no effluents from the ISFSI based on the design of the casks.

By December 2022 the plant was in SAFSTOR (a long-term storage condition for a permanently shutdown nuclear power plant). During SAFSTOR, radioactive contamination decreases substantially, making subsequent decontamination and demolition easier and reducing the amount of low level radioactive waste requiring disposal. All radioactive and service water systems were drained or placed in a stable condition. Plant systems are monitored, and adverse conditions are documented and addressed as needed.

The contribution of dose to a member of the public is most likely to be exposed from liquid and gaseous effluent releases. Calculation methods in the Defueled Offsite Dose Assessment Manual (DODAM) 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".

2.0

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 2023 are summarized and discussed. Information regarding DAEC effluents and the Defueled Offsite Dose Assessment Manual (DO DAM) can be found in the 2023 DAEC 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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3.1 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 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 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. Alternatively, 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 DAEC's Monitoring Program 3

3.2 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.

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 at the remaining locations are indicators: D-15 and D-16. Filters are changed and counted bi-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.

Ambient gamma radiation is monitored at a total of 22 locations. A TLD is placed at each location and exchanged and analyzed quarterly.

Surface water is collected monthly from two total locations: D-49 and D-61. The monthly samples are analyzed for tritium and gamma-emitting isotopes.

The aquatic environment is also monitored at D-49 and D-61 with semiannual fish collection.

Cedar River bottom sediment is collected semiannually at the D-49 and D-51. The samples are analyzed for gamma-emitting isotopes.

Drinking water is collected monthly from D-52 and D-53. 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.

Milk sampling was discontinued in November of 2020.

Additional monitoring of the terrestrial environment, grain, forage and broadleaf vegetation samples are collected annually, as available, from two indicators locations D-015 and D-016.

Grain, forage 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.

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.

3.2.2 Groundwater Protection Program The Duane Arnold Energy Center has committed to the Nuclear Energy lnstitute's Industry Groundwater Protection Initiative - NEI 07-07. The Groundwater Protection Plan (GWPP) is a component of the Duane Arnold Energy Center's Radiplogical Environmental Monitoring Program (REMP). As such, REMP and GWPP sampling and analysis except for sewage effluent results can be found in the Duane Arnold Energy Center 2023 Annual Radiological Environmental Operating Report.

In 2016, a tritium plume was discovered as part of the GWPP inside the owner controlled area/

directly adjacent to the turbine building. A professional engineering firm was hired to model the soil type, groundwater flow and location of groundwater extraction wells. Three extraction wells and twenty additional monitoring wells were installed in the SSE direction / within the site conceptual flow toward the Cedar River (to the Southeast of the turbine building). Samples of 4

3.3 3.4 thirty-one monitoring wells in and around the area of the plume are sent to Microbac Laboratories, Inc. in Northbrook, IL for additional confirmatory analysis. In 2023, all thirty-one sample results were <1000 pCi/L.

The sampling and collection schedule can be found in DODAM Table 6.3-2, and the sampling locations are shown in Figure 5-1 and Figure 5-2.

Sewage effluent Samples were collected during operation of the sewage treatment plant bi-weekly; there were no plant by-products identified in the samples. The maximum value for the lower limit of detection (LLD) for environmental sample analysis are noted in the DO DAM Table 6.3-3 Maximum Values of the Lower Limit of Detection for Environmental Sample Analysis.

The sewage treatment facility has been shut down; the Iowa Department of Natural Resources in Manchester, Iowa was informed in May of 2023. The influent pipes from the plant sources outside the security building was cut and plugged, the influent pumps were shut off, the discharge pipe was plugged, and the system was emptied.

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

The second quarter TLD for location D-31 was missing in the field.

Laboratory Procedures Levels of iodine-131 in vegetation and concentrations of airborne iodine-131 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.

Microbac Laboratories - Northbrook (previously 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 (Microbac Laboratories Inc -

Northbrook, 2023). The QA Program includes participation in lnterlaboratory Comparison (crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

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3.5 Program Modifications A new well was added to the program in the second quarter of 2023. (See table 5 location D-55). This location ultimately did replace the well at location D-52.

Eight temporary TLD sampling locations were added to the program for the third and fourth quarter of 2023.

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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 2023 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 4.2 There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2023. The Fukushima Daiichi nuclear accident occurred March 11, 2011.

There were no reported atmospheric nuclear tests in 2023. The last reported test was conducted on October 16, 1980 by the People's Republic of China.

Program Findings Results obtained show background levels of radioactivity in the environmental samples collected outside of the Owner Controlled Area in 2023.

Airborne Particulates The average annual gross beta concentrations in airborne particulates were 0.030 pCi/m3 at the indicator locations. Sampling has been discontinued at the control location. The results are consistent with levels observed from 2000 through 2022. The historical results are tabulated below.

Year Indicators Controls Year Indicators Controls Concentration {pCi/m3)

Concentration (pCi/m3) 2000 0.026 0.027 2012 0.030 0.029 2001 0.026 0.026 2013 0.028 0.025 2002 0.027 0.027 2014 0.026 0.025 2003 0.029 0.029 2015 0.027 0.024 2004 0.028 0.028 2016 0.027 0.023 2005 0.031 0.031 2017 0.028 0.025 2006 0.029 0.027 2018 0.028 0.026 2007 0.031 0.031 2019 0.026 0.025 2008 0.029 0.029 2020 0.026 0.026 2009 0.031 0.030 2021 0.031 0.028 2010 0.028 0.028 2022 0.030 0.053 2011 0.030 0.029 2023 0.030 NA Average annual gross beta concentrations in airborne particulates.

NA-Not analyzed. Sampling has been discontinued at the control location.

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4.2 Program Findings. Airborne Particulates (continued)

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded Beryllium-?

results for the indicator locations similar to last year"s results. Sampling has been discontinued at the control location. Beryllium-7.produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955), is typically detected in quarterly air samples. No reactor by-product radionuclides were identified in any of the air samples analyzed. All samples met required lower limits of detection as specified in the ODAM.

Airborne Iodine All iodine sampling has been discontinued.

Ambient Radiation (TLDs) 103 TLDs were collected and analyzed in 2023. At the control location. D-4. thermoluminescent dosimeter (TLD) readings averaged 16.8 mR/quarter. At locations within a half mile. one mile and three mile radius of the stack. the measurements averaged 16.9. 18.6 and 15.3 mR/quarter, respectively. The on-site location D-15 averaged 14.5 mR/quarter. 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 62.4 mR/quarter. Eight temporary TLD locations were added for the third and fourth quarter of 2023. These TLD"s averaged 42.7 mR/quarter.

Calculations performed using thermoluminescent dosimeters (TLDs) data has determined that radiation within 300 feet of the ISFSI is statistically higher than background. There is direct radiation for members of the public that are on site and close (within 300 feet) of the ISFSI. For members of the public who traverse the road adjacent to the ISFSI the residency time is considered negligible and hence the dose is "0".

Groundwater (drinking water-potable)

The location designation D-55 was used to document the analysis of a new drinking water well for the site Security Building. Once the permitting was complete the new drinking water well was submitted with the D-52 Plant Potable water.

28 drinking water samples from three locations were collected in 2023. Tritium concentrations in ground water samples were less than the MDC of 172 pCi/L in all samples analyzed. 1-131 and other 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 4.3 Program Findings (continued)

Vegetation Six vegetation samples from two locations were collected in 2023 consisting of green leafy vegetation, forage and grain samples. lodine-131 concentrations in vegetation samples were less than the LLD level of 0.043 pCi/g wet weight in the two green leafy vegetation samples and less 0.054 pCi/g wet in the four grain and forage samples analyzed.

Naturally occurring potassium-40 was the only other gamma-emitting isotope observed in all vegetation samples, all other gamma-emitting isotopes were below detection limits. All samples met required lower limits of detection as specified in the ODAM.

Surface Water 24 surface water samples were collected from two locations in 2023. No tritium was detected above an LLD of 172 pCi/L. No gamma emitting isotopes were measured above their respective LLD's in any of the samples tested.

Fish Seven fish samples from three sport fish species were collected in April and November, 2023, 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 (3.92 and 3.96 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 Four river sediment samples from two locations were collected in 2023 during the months of April and November, and analyzed for gamma-emitting isotopes. Potassium-40 activity ranged from 7.73 to 10.18 pCi/g dry weight at the indicator locations and between 7.21 and 9.97 pCi/g dry weight at the control location.

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

Ground Water Protection Program Findings Microbac Laboratories - Northbrook provides laboratory services for the Duane Arnold Energy Center Ground Water Protection Program except for sewage effluent results.

Groundwater 31 groundwater samples (non-potable water) were collected from 31 permitted monitoring wells 2023. Tritium was the only plant by-product identified. Concentrations of tritium ranged from less than 157 pCi/L to 964 pCi/L at D-132A, monitoring well MW-12A. 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, no tritium was detected above an MDC of 167 pCi/L.

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5.0 TABLES AND FIGURES IO

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 53.2 d with atmosphere B. Terrestrial Primordial K-40 1.26 X 109 y II. Fission Products b Nuclear accidents and detonations constitute the major environmental source.

A. Short-lived 1-131 8.04d 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 30.174y 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 5.26 y Zn-65 245 d Half-lives are taken from Appendix E of Environmental Quarterly, 1 January 1978, EML-334 (U. S. Department of b

Energy, 1978).

Includes fission-product daughters.

11

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 15 On-site North Continuous operation of Analyze for gross beta activity Particulates 16 On-site South 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 collection at least once change. Perform gamma monthly or as required isotopic analysis on each by dust loading sample having gross beta activity greater than ten times the yearly mean of the control samples.

Composite weekly samples to form a quarterly composite (by location). Analyze quarterly composite for gamma isotopic.

Ambient 4

(Controls)

One dosimeter continuously Read gamma radiation dose Radiation at each location.

quarterly.

(Indicators) 15,17,18, Within 0.5 mile of Dosimeters are changed at 20,22,29, Stack least quarterly.

31, 83,85 Within 3.0 miles of 33,35,37, Stack 39,42 Within 1.0 mile of 43,46,48 Stack 161-164 ISFSI Fence line Surface Water 49 Lewis Access (C)

Once per month.

Gamma isotopic and tritium 61 Plant Discharge analysis for each sample (by

~1/2mi. downstream location).

from Plant Discharge 12

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 and tritium on quarterly samples.

If reactor by-product gamma emitters are identified, or if tritium 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 51 Plant Discharge Vegetation 15, 16 Farms raising food Annually at harvest Gamma isotopic analysis, of crops time. Two samples of each sample.

each: grain, green leafy, and forage.

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).

61 Downstream of DAEC in influence of effluent a (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.

c Sample collection discontinued after 01-08-22 collection period 13

Table 5.3 Sampling locations, Duane Arnold Energy Center.

Sampling Location Code Location Description Distance and Direction from Site Stack D-4 Pleasant Creek SRA 4,960 meters NW D-15 On-site, North0Northwest 1,050 meters NNW D-16 On-site, SSE 520 meters SSE D-17 On-site, N 1,050 meters N D-18 On-site, NNE 630 meters NNE D-20 On-site, ENE 550 meters ENE D-22 On-site, ESE 535 meters ESE D-29 On-site,W 630 meters W D-31 On-site, NW 1,020 meters NW D-33 3 mile rino 4,340 meters N D-35 3 mile rino 2,800 meters NE D-37 3 mile rino 2,960 meters E D-39 3 mile rino 2,510 meters SE D-42 3 mile ring 4,380 meters SSE D-43 1 mile ring 1,590 meters SSW D-46 1 mile rino 1,580 meters WNW D-48 1 mile rino 1,680 meters NNW 14

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-51 Plant Discharqe 600 meters SE D-52 Plant potable water On-site D-53 Treated Municipal Water 13,900 meters SE D-61 Downstream of plant discharqe 670 meters SSE D-83 On-site, SSE 620 meters SSE D-85 On-site, SSW 660 meters SSW 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 15

Table 5.4 Type and Frequency of collections.

Location Monthly Quarterly Semiannually Annually D-4 TLD D-15 AP TLD G

D-16 AP G

D-17 TLD D-18 TLD D-20 TLD D-22 TLD D-29 TLD D-31 TLD D-33 TLD D-35 TLD D-37 TLD D-39 TLD D-42 TLD.

D-43 TLD D-46 TLD D-48 TLD D-49 SW BS, F D-51 BS D-52 WW D-53 WW D-61 SW F

D-83, D-85 TLD D-161 to D-164 TLD 16

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 WW Well Water G

Vegetation ME Meat SW Surface Water F

Fish BS River Sediment so Soil 17

Table 5.6. Program Deviations, Duane Arnold Energy Center.

Sample Type TLD Analysis Direct Radiation Location(s)

D-31 Collection Date or Period 2nd Qtr '23 18 Comments TLD missing in field

Table 5.7 Radiological Environmental Monitoring Program Summary.

Name of Facility Location ofFacility Sample Type and Number of Type Analyses' (Units)

Airborne Particulates GB 101 (pCi/m3)

GS 7

Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 TLDs (mR/quarter)

Gamma 4

Control Locations Within 0.5 mi. of Stack Gamma 35 Within 1. 0 mi. of Gamma 12 Stack Within 3.0 mi.of Gamma 20 Stack ISFSI border Gamma 32 Duane Arnold Energy Center Linn, Iowa Docket No.

Reporting Period Indicator Locationwith Highest Annual Mean Locations LLD b Mean (F)

Mean (F)

Range*

Location d Range*

Airborne Pathway 0.003 0.030 (101/101)

D-16 0.032(1/50)

(0.013-0.073)

(0.017-0.070) 0.146 0.060(8/8)

D-16 0.063 (4/4)

(0.050-0.070)

(0.050-0.070) 0.0011

< LLD 0.0035

< LLD 0.0012

< LLD 0.0018

< LLD 0.0021

< LLD 0.0016

< LLD 0.0019

< LLD 0.0015

< LLD

< LLD 0.0094 0.0014

< LLD 0.0013

< LLD 0.0028

<LLD 0.0058

< LLD Direct Radiation 1.0 None D-4 16.8 (4/4)

(16.1-17.7) 1.0

15. 1 (35/35)

D-29 / D-31 16.9 (4/4)/(4/4)

(11.7-19.5)

(15.1-17.6)/

1.0 D-42 (16.0-18.1) 16.7 (12/12)

(12.7-20.6) 18 6 (4/4)

(17.7-19.6) 1.0 13.9 (20/20)

D-42 15.3(4/4)

(10.4-17.6)

(14.4-17.6) 1.0 52.5 (32/32)

D-161 to D-164 90.5(4/4)

(18.3-96.1)

(84.8-96.1) 19 50-331 January-December, 2023 Control Number Locations Non-Mean (F) c Routine Range c Results*

0

< LLD 0

16.8 (4/4) 0 (16.1-17.7)

None 0

Table 5.7 Radiological Environmental Monitoring Program Summary.

Name of Facility Location of Facility Sample Type and Type Number of (Units)

Analyses*

Surface Water H-3 24 (pCi/L)

GS 24 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Sediments GS 4

Ci/gdry)

K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 Duane Arnold Energy Center Linn, Iowa Indicator Locations LLD b Mean (F)'

Range' Docket No.

Reporting Period Location with Highest Annual Mean Mean (F)'

Location d Range' Waterborne Pathway 172

<LLD D-49 8.1

<LLD 20.0

< LLD 8.3

< LLD 8.9

<LLD 14.3

< LLD 9.5

< LLD 14.0

< LLD 12.1

<LLD 9.7

< LLD 8.5

< LLD 39.7

< LLD 10.8

< LLD 8.75 (2/2)

D-51 8.75 (2/2) 1.0 (7.33-10.18)

(7.73-10.18) 0.0381

< LLD 0.112

< LLD 0.045

< LLD 0.029

< LLD 0.062

< LLD 0.079

< LLD 0.083

< LLD 0.052

< LLD 0.180

< LLD 0.022

< LLD 0.016 0.07 (1/2)

D-49 0.08 (1/2) 0.113

< LLD 0.212

< LLD 20 50-331 January-December, 2023 Control Number Locations Non-Mean (F) c Routine Range c Results*

< LLD 0

8.59 (2/2) 0 (7.21-9.97)

< LLD 0

< LLD o

< LLD 0

< LLD o

< LLD 0

< LLD o

< LLD 0

0.08 (1/2) o

< LLD o

Table 5.7 Radiological Environmental Monitoring Program Summary.

Name of Facility Location of Facility Sample Type and Type Number of (Units)

Analyses*

Ground Water, potable (pCi/L)

H-3 GS Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 28 28 Broadleaf GS 2

Vegetation K-40 (pCi/gwet)

Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ce-141 Ce-144 Duane Arnold Energy Center Linn, Iowa Indicator Locations LLD b Mean (F) c Range c Waterborne 172

< LLD 7.4

< LLD 13.4

< LLD 8.9

< LLD 9.1

< LLD 7.8

< LLD 8.1

< LLD 15.0

< LLD 14.6

<LLD 8.5

< LLD 8.3

< LLD 38.3

<LLD 13.7

<LLD Docket No.

Reporting Period Location with Highest Annual Mean Location d Mean (F) c Range c Pathway Ingestion Pathway 0.05 4.63.(2/2)

D-16 8.86 (1/1)

(3.40-5.86) 0.026

< LLD 0.056

< LLD 0.028

< LLD 0.062

< LLD 0.052

< LLD 0.027

< LLD 0.041

< LLD 0.032

< LLD 0.188

< LLD 0.043

< LLD 0.032

< LLD 0.050

< LLD 0.056

< LLD 0.258

<LLD 21 50-331 January-December, 2023 Control Number Locations Non-Mean (F) c Routine Range c Results*

< LLD 0

None 0

0 0

Table 5.7 Radiological Environmental Monitoring Program Summary.

Duane Arnold Energy Center 50-331 Name of Facility Location of Facility Linn, Iowa Docket No.

Reporting Period January-December, 2023 (County, State)

Type and Indicator Location with Highest Annual Mean Control Sample Locations Locations Type Number of LLD b Mean (F) 0 Mean (F) 0 Mean (F) 0 (Units)

Analyses a Range 0

Location d Range 0

Range 0

Ingestion Pathway (cont.)

GS 4

Vegetation (Grain and Forage)

K-40 0.05 3.92 (4/4)

D-16 3.96 (2/2)

None (pCi/gwet)

(2.30-5.46)

(3.56-4.37)

Mn-54 0.025

< LLD Fe-59 0.064

< LLD Co-58 0.023

< LLD

,Co-60 0.049

< LLD Zn-65 0.056

< LLD Nb-95 0.032

< LLD Zr-95 0.051

< LLD Ru-103 0.024

< LLD Ru-106 0.274

< LLD 1-131 0.054

< LLD Cs-134 0.029

< LLD Cs-137 0.041

< LLD Ce-141 0.065

< LLD Ce-144 0.172

< LLD Fish GS 7

(pCi/gwet)

K-40 1.0 3.92 (4/4)

D-61 3.92 (4/4) 3.54(3/3)

(3.61-4.30)

(3.44-3.65)

Mn-54 0.019

<LLD

<LLD Fe-59 0.053

<LLD

< LLD Co-58 0.023

< LLD

< LLD Co-60 0.026

<LLD

< LLD Zn-65 0.065

<LLD

< LLD Nb-95 0.045

<LLD

<LLD Zr-95 0.049

<LLD

< LLD Ru-103 0.035

< LLD

< LLD Ru-106 0.175

<LLD

< LLD Cs-134 0.023

< LLD

< LLD Cs-137 0.025

< LLD

< LLD Ce-141 0.055

<LLD

< LLD Ce-144 0.151

<LLD

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

0 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.

22 Number Non-Routine Results*

0 0

Figure 5-1 Environmental Monitoring Programs Sampling Near the Duane Arnold Energy Center Small Area See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

23

Figure 5-2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles from DAEC Large Area See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

24

6.0 REFERENCES

CITED Arnold, J. R. and H. A. AI-Salih. 1955. Beryllium-? Produced by Cosmic Rays. Science 121: 451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275-276.

Environmental, Inc., Midwest Laboratory.

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

____ 2001 through 2022. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 2001 - 2019.

____ 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 Tabul_ations 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.

____.2022.

Quality Manual, Rev. 8, 17 October 2022.

____.2012.

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

____ 2022.

Quality Control Procedures Manual, Rev. 5, 9 May 2022.

____ 2009.

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

Microbac Laboratories-Northbrook (Before June 1, 2023 Environmental Inc.)

____.2023.

Quality Manual, Rev. 9, 25 August 2023.

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 1 0CFR 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.

25

(§) MICROBAC "

700 Landwehr Road

Northbrook, IL 60062-2310 phone (847) 564-0700

fax (847) 564-4517 NOTE:

APPENDIX A INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RESULTS Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.

January, 2023 through December, 2023

Appendix A lnterlaboratory/ lntralaboratory Comparison Program Results Microbac Laboratories - Northbrook (previously Environmental Inc.) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality program in December 1971.

These programs are operated by agencies and/or companies which supply environmental sample types containing concentrations of radionuclides known to the issuing entity 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.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.

Table A-3 lists results of the analyses on intralaboratory "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on intralaboratory "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 lists analytical results from the intralaboratory "duplicate" program for the past twelve months. Acceptance is based on each result being within 25% of the mean of the two results or the two sigma uncertainties of each result overlap.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-7 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental 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-1

Analysis Gamma Emitters Strontium-89, Strontium-90 Potassium-40 Gross alpha Gross beta Tritium Radium-226, Radium-228 Plutonium lodine-129, lodine-131 Nickel-63, Technetium-99, Uranium-238 lron-55 Other Analyses Attachment A ACCEPTANCE CRITERIA FOR INTRALABORATORY "SPIKED" SAMPLES Ratio of lab result to known value.

0.8 to 1.2 0.8 to 1.2 0.8 to 1.2 0.5to1.5 0.8 to 1.2 0.8 to 1.2 0.7 to 1.3 0.8 to 1.2 0.8 to 1.2 0.7 to 1.3 0.8 to 1.2 0.8 to 1.2 A-2

TABLE A-1. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) 8 RAD study Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Acceptance Result Value Limits Acceptance RAD-132 Study ERDW-162 2/23/2023 Ba-133 33.0 +/- 3.5 30.5 24.2 - 34.6 Pass ERDW-162 2/23/2023 Cs-134 30.7 +/- 3.0 28.2 21.9 -31.1 Pass ERDW-162 2/23/2023 Cs-137 191 +/- 7 190 171 - 211 Pass ERDW-162 2/23/2023 Co-60 110 +/- 4 110 99.0 -123 Pass ERDW-162 2/23/2023 Zn-65 109 +/- 8 105 94.5 -125 Pass ERDW-162 2/23/2023 Gr. Alpha 25.3 +/- 0.2 30.0 15.3 - 39.2 Pass ERDW-162 2/23/2023 G. Beta 15.0 +/- 0.1 16.5 9.25 - 24.8 Pass ERDW-162 2/23/2023 Ra-226 7.58 +/- 0.52 8.26 6.21 - 9.71 Pass ERDW-162 2/23/2023 Ra-228 7.44 +/- 1.53 7.17 4.51 - 9.20 Pass ERDW-162 2/23/2023 H-3 22,600 +/-467 21,600 18,900 - 23,800 Pass RAD-134 Study ERDW-1956 7/10/2023 Ba-133 64.1 +/-4.7 66.5 55.4 - 73.2 Pass ERDW-1956 7/10/2023 Cs-134 97.0 +/-4.8 90.8 74.5 - 99.9 Pass ERDW-1956 7/10/2023 Cs-137 179 +/- 8 163 147 -181 Pass ERDW-1956 7/10/2023 Co-60 26.6 +/-2.9 20.7 17.5 -25.6 Fail b ERDW-1956 7/10/2023 Zn-65 318 +/-12 290 261 - 339 Pass ERDW-50167 7/10/2023 Gr. Alpha 34.3 +/- 1.9 47.9 24.9 - 60.3 Pass ERDW-50167 7/10/2023 G. Beta 27.4 +/- 1.2 28.6 18.2 -36.4 Pass ERDW-50171 7/10/2023 Ra-226 19.3 +/- 0.9 17.4 12.9 -19.9 Pass ERDW-50171 7/10/2023 Ra-228 7.11 +/- 1.59 7.16 4.50 -9.18 Pass ERDW-50173 7/10/2023 H-3 10,500 +/- 326 9,860 8,570 - 10,800 Pass ERDW-50169 7/10/2023 1-131 23.9 +/- 1.2 24.4 20.2 - 28.9 Pass a Results obtained by Microbac Laboratories Inc. - Northbrook as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resource Associates (ERA).

b The Cobalt-60 result did not meet ERA acceptance criteria. The sample was reanalyzed and passed for all analytes.

(Co-60 reanalysis result was 21.2 +/- 3.0 pCi/L). No cause for the earlier failure could be determined.

A-3

TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).

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

Environmental, Inc.

Group 1 2022-23-3 11/29/2023 Spike 1 93.0 90.0

-0.03 2022-23-3 11/29/2023 Spike 2 93.0 88.5

-0.05 2022-23-3 11/29/2023 Spike 3 93.0 89.0

-0.04 2022-23-3 11/29/2023 Spike 4 93.0 89.5

-0.04 2022-23-3 11/29/2023 Spike 5 93.0 88.1

-0.05 2022-23-3 11/29/2023 Spike 6 93.0 95.1 0.02 2022-23-3 11/29/2023 Spike 7 93.0 90.8

-0.02 2022-23-3 11/29/2023 Spike 8 93.0 90.8

-0.02 2022-23-3 11/29/2023 Spike 9 93.0 92.3

-0.01 2022-23-3 11/29/2023 Spike 10 93.0 89.0

-0.04 2022-23-3 11/29/2023 Spike 11 93.0 84.9

-0.09 2022-23-3 11/29/2023 Spike 12 93.0 90.8

-0.02 2022-23-3 11/29/2023 Spike 13 93.0 92.0

-0.01 2022-23-3 11/29/2023 Spike 14 93.0 87.7

-0.06 2022-23-3 11/29/2023 Spike 15 93.0 88.8

-0.05 2022-23-3 11/29/2023 Spike 16 93.0 88.6

-0.05 2022-23-3 11/29/2023 Spike 17 93.0 84.2

-0.09 2022-23-3 11/29/2023 Spike 18 93.0 88.6

-0.05 2022-23-3 11/29/2023 Spike 19 93.0 86.4

-0.07 2022-23-3 11/29/2023 Spike 20 93.0 88.3

-0.05 Mean (Spike 1-20) 89.2

-0.04 Passd Standard Deviation (Spike 1-20) 2.5 0.03 Passd a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air*kerma rate. TLD's were read and the results were submitted by Microbac Laboratories - Northbrook to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.

b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(1 0)K. = 1.20. mrem/cGy = 1000.

c Performance Quotient (P) is calculated as ((reported dose - conventionally true value) + conventionally true value) where the conventionally 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-4

TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards). 8 mrem Lab Code Irradiation Delivered Reportedb Performance 0

Date Description Dose Dose Quotient (P)

Environmental, Inc.

Group 2 2022-23-4 11/29/2023 Spike 21 176.0 170.1

-0.03 2022-23-4 11/29/2023 Spike 22 176.0 166.8

-0.05 2022-23-4 11/29/2023 Spike 23 176.0 156.3

-0.11 2022-23-4 11/29/2023 Spike 24 176.0 163.1

-0.07 2022-23-4 11/29/2023 Spike 25 176.0 166.8

-0.05 2022-23-4 11/29/2023 Spike 26 176.0 168.0

-0.05 2022-23-4 11/29/2023 Spike 27 176.0 159.8

-0.09 2022-23-4 11/29/2023 Spike 28 176.0 160.4

-0.09 2022-23-4 11/29/2023 Spike 29 176.0 165.4

-0.06 2022-23-4 11/29/2023 Spike 30 176.0 166.2

-0.06 2022-23-4 11/29/2023 Spike 31 176.0 159.9

-0.09 2022-23-4 11/29/2023 Spike 32 176.0 161.4

-0.08 2022-23-4 11/29/2023 Spike 33 176.0 165.8

-0.06 2022-23-4 11/29/2023 Spike 34 176.0 163.9

-0.07 2022-23-4 11/29/2023 Spike 35 176.0 167.9

-0.05 2022-23-4 11/29/2023 Spike 36 176.0 157.4

-0.11 2022-23-4 11/29/2023 Spike 37 176.0 165.6

-0.06 2022-23-4 11/29/2023 Spike 38 176.0 161.3

-0.08 2022-23-4 11/29/2023 Spike 39 176.0 165.9

-0.06 2022-23-4 11/29/2023 Spike 40 176.0 159.4

-0.09 Mean (Spike 21-40) 163.6

-0.07 Passd Standard Deviation (Spike 21-40) 3.9 0.02 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 Microbac Laboratories - Northbrook 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)K.= 1.20. mrem/cGy = 1000.

c Performance Quotient (P) is calculated as ((reported dose - conventionally true value) + conventionally true value) where the conventionally 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-5

TABLE A-3. lntralaboratory "Spiked" Samples Concentration*

Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1° Activity Limitsd Acceptance Lab/Known SPDW-26 1/5/2023 Ra-228 11.8 +/- 1.9 13.4 9.4-17.4 Pass 0.88 SPDW-50002 1/11/2023 H-3 21,747 +/- 452 22,100 17,680 - 26,520 Pass 0.98 SPDW-50004 1/20/2023 H-3 21,861 +/- 458 22,100 17,680 - 26,520 Pass 0.99 SPDW-50006 1/5/2023 Ra-226 11.3 +/- 0.3 12.3 8.6 -16.0 Pass 0.92 SPDW-50034 1/27/2023 Ra-226 12.6 +/- 0.4 12.3 8.6 -16.0 Pass 1.02 LCS-SO-012723 8/1/2020 Cs-134 17.1 +/- 0.2 19.2 15.4 - 23.0 Pass 0.89 LCS-SO-012723 8/1/2020 Zn-65 13.8+/-1.7 14.1 11.3 - 16.9 Pass 0.98 LCS-SO-012723 8/1/2020 Co-60 26.4 +/- 0.2 27.0 21.6 - 32.4 Pass 0.98 LCS-SO-012723 8/1/2020 Co-57 30.7+/-0.1 30.9 24.7 -37.1 Pass 0.99 LCS-SO-012723 8/1/2020 Mn-54 17.7 +/- 0.8 16.5 13.2 -19.8 Pass 1.07 LCS-SO-012723 8/1/2020 K-40 18.4 +/- 0.7 16.8 13.4 - 20.2 Pass 1.10 SPDW-50010 1/31/2023 Ra-228 9.7 +/- 1.3 13.4 9.4-17.4 Pass 0.72 SPDW-50008 2/3/2023 H-3 21,961 +/- 459 22,100 17,680 - 26,520 Pass 0.99 SPDW-50016 2/10/2023 H-3 22,137 +/- 462 22,100 17,680 - 26,520 Pass 1.00 SPDW-50012 2/24/2023 Sr-90 18.6 +/- 1.2 17.1 13.7 -20.5 Pass 1.09 SPDW-50032 2/16/2023 Ra-228 13.1+/-1.9 13.4 9.4-17.4 Pass 0.98 SPDW-50018 2/16/2023 Gr. Alpha 19.1 +/-1.3 23.5 11.8 - 28.2 Pass 0.81 SPDW-50018 2/16/2023 Gr. Beta 133 +/- 2 141 112 -169 Pass 0.94 SPDW-50021 2/17/2023 H-3 21,843 +/- 459 22,100 17,680 - 26,520 Pass 0.99 SPDW-50047 2/24/2023 Ra-226 12.8 +/- 0.4 12.3 8.6 -16.0 Pass 1.04 SPDW-50049 3/17/2023 H-3 22,120 +/- 465 22,100 17,680 - 26,520 Pass 1.00 SPDW-50056 3/24/2023 H-3 21,911 +/- 463 22,100 17,680 - 26,520 Pass 0.99 SPDW-50060 3/16/2023 Ra-226 12.9 +/- 0.4 12.3 8.6 -16.0 Pass 1.05 SPDW-50097 4/13/2023 Ra-226 11.7+/-0.5 12.3 8.6 -16.0 Pass 0.95 SPDW-50068 4/14/2023 H-3 22,656 +/- 482 22,100 17,680 - 26,520 Pass 1.03 SPDW-50081 4/25/2023 H-3 21,594 +/- 461 22,100 17,680 - 26,520 Pass 0.98 SPDW-50131 5/3/2023 Ra-226 11.4 +/- 0.3 12.3 8.6 -16.0 Pass 0.93 SPDW-50104 5/12/2023 H-3 21,513 462 22,100 17,680 - 26,520 Pass 0.97 SPDW-50117 5/26/2023 H-3 22,069 468 22,100 17,680 - 26,520 Pass 1.00 SPDW-50182 6/8/2023 Ra-226 10.4 +/- 0.3 12.3 8.6 -16.0 Pass 0.85 SPDW-50137 6/12/2023 H-3 21,898 +/- 456 22,100 17,680 - 26,520 Pass 0.99 SPDW-50138 6/12/2023 H-3 21,898 +/- 456 22,100 17,680 - 26,520 Pass 0.99 SPDW-50153 6/26/2023 H-3 21,672 +/- 456 22,100 17,680 - 26,520 Pass 0.98 SPDW-50153 6/26/2023 H-3 21,672 +/- 456 22,100 17,680 - 26,520 Pass 0.98 SPDW-50259 7/19/2023 Ra-226 10.5 +/- 0.3 12.3 8.6 -16.0 Pass 0.85 SPDW-50219 8/15/2023 Sr-90 17.5 +/- 1.1 17.1 13.7 - 20.5 Pass 1.02 SPDW-50291 8/28/2023 Ra-226 11.0 +/- 0.3 12.3 8.6 -16.0 Pass 0.89 SPDW-50249 8/22/2023 Gr.Alpha 16.7+/-1.4 23.5 11.8 - 28.2 Pass 0.71 SPDW-50249 8/22/2023 Gr. Beta 128 +/- 2 141 112 -169 Pass 0.91 SPDW-50252 8/18/2023 H-3 21,628 +/- 459 22,100 17,680 - 26,520 Pass 0.98 SPDW-50257 8/25/2023 H-3 22,152 +/- 469 22,100 17,680 - 26,520 Pass 1.00

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 Acceptance criteria are listed in Attachment A of this report.

A-6

TABLE A-3. lntralaboratory "Spiked" Samples Concentration" Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1° Activity Limitsd Acceptance Lab/Known LCS-09/12/23 8/1/2020 Cs-134 17,533 +/- 346 19,170 15,336 - 23,004 Pass 0.91 LCS-09/12/23 8/1/2020 Co-60 27,480 +/- 347 26,055 20,844 - 31,266 Pass 1.05 LCS-09/12/23 8/1/2020 K-40 20,183 1268 18,468 14,774 - 22,162 Pass 1.09 SPDW-50270 9/6/2023 H-3 22,287 +/- 469 22,100 17,680 - 26,520 Pass 1.01 SPDW-50283 9/25/2023 H-3 21,062 +/- 444 22,100 17,680 - 26,520 Pass 0.95 SPDW-50291 8/28/2023 Ra-226 11.0 +/- 0 12.3 8.6 -16.0 Pass 0.89 SPDW-50316 10/3/2023 H-3 21,406 +/- 454 22,100 17,680 - 26,520 Pass 0.97 SPW-50330 11/17/2023 H-3 21,143 +/- 543 22,100 17,680 - 26,520 Pass 0.96 LCS-S0-112823 8/1/2020 Cs-134 17.2 +/- 0.2 19.2 15.4 - 23.0 Pass 0.90 LCS-S0-112823 8/1/2020 Zn-65 14.9+/-3.1 14.1 11.3 - 16.9 Pass 1.06 LCS-S0-112823 8/1/2020 Co-60 26.0 +/- 0.3 27.0 21.6 - 32.4 Pass 0.96 LCS-S0-112823 8/1/2020 Co-57 29.3 +/- 0.9 30.9 24.7 -37.1 Pass 0.95 LCS-S0-112823 8/1/2020 Mn-54 17.5+/-1.3 16.5 13.2 -19.8 Pass 1.06 LCS-S0-112823 8/1/2020 K-40 18.0 +/- 0.7 16.8 13.4 - 20.2 Pass 1.07 SPW-3908 12/18/2023 Nl-63 2,032 +/- 27 1,788 1,430 - 2,146 Pass 1.14 SPW-3910 12/18/2023 Fe-55 269 +/- 24 232 186 - 278 Pass 1.16 SPDW-50378 12/19/2023 H-3 21,102 +/- 452 22,100 17,680 - 26,520 Pass 0.95 SPDW-50388 12/28/2023 H-3 20,540 +/- 445 22,100 17,680 - 26,520 Pass 0.93 SPDW-50393 12/19/2023 Ra-226 11.6 +/- 0.3 12.3 8.6 -16.0 Pass 0.94

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 Acceptance criteria are listed in Attachment A of this report.

A-7

TABLE A-4. lntralaboratory "Blank" Samples Concentration*

Lab Codeb Sample Date Analysis 0

Laboratory results (4.66a)

Acceptance Type LLD Activity Criteria (4.66 a)

SPW-25 Water 1/5/2023 Ra-228 0.98 0.74 +/- 0.54 2

SPDW-50000 Water 1/6/2023 1-131 0.36

-0.10 +/- 0.16 1

SPDW-50001 Water 1/11/2023 H-3 157 13 +/- 74 200 SPDW-50003 Water 1/20/2023 H-3 161 98 +/- 85 200 SPDW-50005 Water 1/5/2023 Ra-226 0.02 0.00 +/- 0.03 2

SPDW-50033 Water 1/27/2023 Ra-226 0.03

-0.01 +/- 0.03 2

SPDW-50009 Water 1/31/2023 Ra-228 1.40 0.69 +/- 0.75 2

SPDW-50007 Water 2/3/2023 H-3 160 17 +/- 80 200 SPDW-50015 Water 2/10/2023 H-3 159 91 +/- 84 200 SPDW-50011 Water 2/9/2023 Sr-89 0.62 0.24 +/- 0.49 5

SPDW-50011 Water 2/9/2023 Sr-90 0.66

-0.02 +/- 0.30 1

SPDW-50018 Water 2/16/2023 Gr. Alpha 0.62 0.01 +/- 0.44 2

SPDW-50018 Water 2/16/2023 Gr. Beta 0.78

-0.10 +/- 0.54 4

SPDW-50020 Water 2/17/2023 H-3 154 122 +/- 80 200 SPDW-50031 Water 2/16/2023 Ra-228 0.82 0.42 +/- 0.43 2

SPDW-50046 Water 2/24/2023 Ra-226 0.03 0.05 +/- 0.04 2

SPDW-50044 Water 3/13/2023 1-131 0.15

-0.06 +/- 0.08 SPDW-50048 Water 3/17/2023 H-3 163 80 +/- 80 200 SPDW-50055 Water 3/24/2023 H-3 169 63 +/- 82 200 SPDW-50059 Water 3/16/2023 Ra-226 0.04

-0.02 +/- 0.03 2

SPDW-50063 Water 3/28/2023 Ra-226 0.06

-0.01 +/- 0.05 2

SPDW-50067 Water 4/14/2023 H-3 173 92 +/- 87 200 SPDW-50069 Water 4/17/2023 1-131 0.11

-0.05 +/- 0.08 1

SPDW-50102 Water 5/15/2023 1-131 0.15

-0.01 +/- 0.08 SPDW-50103 Water 5/12/2023 H-3 161 67 +/- 80 200 SPDW-50116 Water 5/26/2023 H-3 161 122 +/- 87 200 SPDW-50137 Water 6/12/2023 H-3 157 125 +/- 80 200 SPDW-50154 Water 6/26/2023 H-3 157 105 +/- 80 200 SPDW-50181 Water 6/8/2023 Ra-226 0.04

-0.07 +/- 0.03 2

SPDW-50218 Water 8/15/2023 Sr-89 0.66

-0.07 +/- 0.48 5

SPDW-50218 Water 8/15/2023 Sr-90 0.55 0.02 +/- 0.26 SPDW-50248 Water 8/22/2024 Gr. Alpha 0.57

-0.03 +/- 0.40 2

SPDW-50248 Water 8/22/2024 Gr. Beta 0.70 0.28 +/- 0.50 4

SPDW-50256 Water 8/25/2023 H-3 161 75 +/- 84 200 SPDW-50258 Water 7/19/2023 Ra-226 0.06

-0.25 +/- 0.04 2

SPDW-50270 Water 9/6/2023 H-3 160 90 +/- 81 200 SPDW-50282 Water 9/25/2023 H-3 163 53 +/- 79 200 SPDW-50290 Water 8/28/2023 Ra-226 0.05 0.00 +/- 0.04 2

Liquid sample results are reported in pCi/Liter, air filters ( pCi!m\\ 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).

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

d Activity reported is a net activity result.

A-8

TABLEA-4. lntralaboratory "Blank" Samples Concentration*

Lab Codeb Sample Date Analysis 0

Laboratory results (4.66cr)

Acceptance Type LLD Activity Criteria (4.66 cr)

SPDW-50311 Water 10/16/2023 1-131 0.25 0.06 +/- 0.14 SPDW-50312 Water 10/3/2023 Ra-226 0.04 0.06 +/- 0.09 2

SPDW-50315 Water 10/27/2023 H-3 169 5 +/- 79 200 SPDW-50329 Water 11/17/2023 H-3 170 51 +/- 82 200 SPDW-50379 Water 11/17/2023 Ra-226 0.05 0.09 +/- 0.04 2

SPDW-50346 Water 12/5/2023 H-3 0.10

-0.12 +/- 0.07 SPDW-50347 Water 12/5/2023 Ra-228 1.27

-0.07 +/- 0.62 2

SPW-3907 Water 12/18/2023 Ni-63 149 0 +/- 91 200 SPW-3909 Water 12/18/2023 Fe-55 435 7 +/- 265 2000 SPDW-50377 Water 12/19/2023 H-3 173

-42 +/- 78 200 SPDW-50387 Water 12/28/2023 H-3 171

-21 +/- 79 200

Liquid sample results are reported in pCi/Liter, air filters ( pCitm\\ 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-9

TABLE A-5. lntralaboratory "Duplicate" Samples Concentration*

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance W\\/1/-65,66 1/10/2023 Gr. Beta 15.4 +/- 2.0 17.2 +/- 2.1 16.3 +/- 1.5 Pass WW-107,108 1/18/2023 H-3 153 +/- 88 132 +/- 87 143 +/- 62 Pass SG-187,188 1/30/2023 Gr. Alpha 28.1 +/- 3.9 22.0 +/- 3.5 25.1 +/- 2.6 Pass SG-187,188 1/30/2023 Gr. Beta 22.3 +/- 1.8 22.2 +/- 1.8 22.3 +/- 1.3 Pass SG-187,188 1/30/2023 Pb-214 4.08 +/- 0.16 3.38 +/- 0.09 3.73 +/- 0.09 Pass SG-187,188 1/30/2023 Ac-228 3.88 +/- 0.28 3.98 +/- 0.14 3.93 +/- 0.16 Pass SWU-201,202 1/31/2023 H03 171 +/- 89 234 +/- 92 203 +/- 64 Pass SW-243,244 2/7/2023 H-3 358 +/- 98 262 +/- 93 310 +/- 68 Pass PW-266,267 2/6/2023 Ra-226 0.61 +/- 0.18 0.37 +/- 0.20 0.49 +/- 0.13 Pass DW-50028.50029 2/27/2023 Ra-226 0.68 +/- 0.13 0.76 +/- 0.13 0.72 +/- 0.09 Pass DW-50028.50029 2/27/2023 Ra-228 2.26 +/- 0.65 1.20 +/- 0.65 1.73 +/- 0.46 Pass DW-50052,50053 2/27/2023 Ra-228 0.48 +/- 0.57 1.19+/-0.65 0.84 +/- 0.43 Pass DW-50035,50036 2/28/2023 Gr. Alpha 3.68 +/- 1.42 4.00 +/- 1.29 3.84 +/- 0.96 Pass DW-50035,50036 2/28/2023 Gr. Beta 2.50 +/- 0.64 1.99 +/- 0.64 2.25 +/- 0.45 Pass LW-518,519 3/8/2023 Gr. Beta 1.71 +/- 0.64 1.38 +/- 0.64 1.55 +/- 0.45 Pass SG-571,572 3/8/2023 Pb-214 7.80 +/- 0.46 8.20 +/- 0.35 8.00 +/- 0.29 Pass SG-571,572 3/8/2023 Ac-228 11.9+/-0.8 11.4 +/- 0.6 11.7+/-0.5 Pass SG-571.572 3/8/2023 Gr. Alpha 86.5 +/- 10.6 89.6+/-11.0 88.1 +/- 7.6 Pass DW-50052,50053 3/17/2023 Gr. Alpha 9.16 +/- 1.02 14.7 +/- 1.2 11.9+/-0.8 Pass DW-50052,50053 3/17/2023 Gr. Beta 6.03 +/- 0.71 7.58 +/- 0.75 6.81 +/- 0.52 Pass CF-700,701 3/22/2023 K-40 2.91 +/- 0.32 3.30 +/- 0.36 3.11 +/- 0.24 Pass SW-679,680 3/27/2023 H-3 14,480 +/- 389 14,487 +/- 389 14,484 +/- 275 Pass SG-974,975 4/4/2023 Gr. Alpha 12.0 +/-2.1 12.1+/-2.1 12.1 +/- 1.5 Pass DW-5007 4,50075 4/21/2023 Ra-226 1.63 +/- 0.22 1.56 +/- 0.28 1.60 +/- 0.18 Pass DW-5007 4,50075 4/21/2023 Ra-228 3.41 +/- 0.98 2.14 +/- 0.80 2.78 +/- 0.63 Pass U-1038, 1039 4/20/2023 Gr. Beta 6.14+/-1.71 6.46 +/-2.19 6.30 +/- 1.39 Pass W\\/1/-1101, 1102 4/25/2023 H-3 358 +/- 96 334 +/- 95 346 +/- 68 Pass DW-50092,50093 5/1/2023 Ra-226 1.00 +/- 0.22 1.46+/-0.19 1.23 +/- 0.15 Pass DW-50092,50093 5/1/2023 Ra-228 1.11 +/- 0.73 1.57 +/- 0.82 1.34 +/- 0.55 Pass W\\/1/-1122, 1123 5/2/2023 H-3 307 +/- 93 229 +/- 89 268 +/- 64 Pass W\\/1/-1269, 1270 5/17/2023 H-3 366 +/- 100 214 +/- 92 290 +/- 68 Pass DW-50110,50111 5/29/2023 Ra-226 6.27 +/-0.40 4.77 +/- 0.26 5.52 +/- 0.24 Pass DW-50110,50111 5/29/2023 Ra-228 2.81 +/- 0.97 3.53 +/- 0.98 3.17 +/- 0.69 Pass SW-1356, 1357 5/30/2023 H-3 380 +/- 94 257 +/- 88 319 +/- 64 Pass W\\/1/-1398, 1399 5/24/2023 H-3 571 +/- 103 613 +/- 105 592 +/- 74 Pass SG-1377,1378 5/30/2023 Pb-214 1.07+/-0.14 1.19+/-0.15 1.13 +/- 0.10 Pass SG-1377, 1378 5/30/2023 Ac-228 1.23 +/- 0.28 1.11 +/- 0.23 1.17 +/- 0.18 Pass A-10

TABLE A-5. lntralaboratory "Duplicate" Samples Concentration*

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance DW-50124,50125 6/5/2023 Ra-226 0.25 +/- 0.08 0.24 +/- 0.09 0.25 +/- 0.06 Pass AP-060523NB 6/5/2023 Gr. Beta 0.023 +/- 0.003 0.0236 +/- 0.003 0.023 +/- 0.002 Pass DW-50126,50127 6/5/2023 Gr. Alpha 2.50+/-1.17 3.87 +/- 1.39 3.19 +/- 0.91 Pass WW-1441, 1442 6/6/2023 Gr. Beta 2.55 +/- 0.64 1.91 +/- 0.67 2.23 +/- 0.46 Pass SW-1483, 1484 6/8/2023 H-3 281 +/- 90 281 +/- 90 281 +/- 64 Pass CF-1546,1547 6/12/2023 K-40 7.77 +/- 0.34 7.48 +/- 0.48 7.63 +/- 0.29 Pass AP-061223NB 6/12/2023 Gr. Beta 0.031 +/- 0.005 0.030 +/- 0.005 0.031 +/- 0.004 Pass S-1567,1568 6/14/2023 K-40 9.75 +/- 0.71 9.80 +/- 0.77 9.78 +/- 0.52 Pass WW-1630, 1631 6/6/2023 H-3 319 +/- 93 236 +/- 89 278 +/- 64 Pass F-1945, 1946 6/26/2023 K-40 3.81 +/- 0.34 3.22 +/- 0.54 3.52 +/- 0.32 Pass DW-50157,50158 6/26/2023 Gr. Beta 0.93 +/- 0.59 1.09 +/- 0.06 1.01 +/- 0.30 Pass AP-062823NB 6/28/2023 Gr. Beta 0.026 +/- 0.004 0.021 +/- 0.003 0.024 +/- 0.003 Pass AP-070323NB 7/3/2023 Gr. Beta 0.028 +/- 0.003 0.026 +/- 0.003 0.027 +/- 0.002 Pass DW-50160,50161 7/5/2023 Ra-226 2.63 +/- 0.32 2.77 +/- 0.27 2.70 +/- 0.21 Pass DW-50160,50161 7/5/2023 Ra-228 2.46 +/- 0.78 2.51 +/- 0.81 2.49 +/- 0.56 Pass AP-071123NB 7/11/2023 Gr. Beta 0.025 +/- 0.003 0.027 +/- 0.003 0.026 +/- 0.002 Pass DW-50188,50189 7/21/2023 Ra-226 3.07 +/- 0.30 2.63 +/- 0.20 2.85 +/- 0.18 Pass DW-50188,50189 7/21/2023 Ra-228 5.28 +/- 0.92 5.08 +/- 0.90 5.18 +/- 0.64 Pass DW-50197,50198 7/24/2023 Gr. Alpha 5.82 +/- 1.50 5.78 +/- 1.30 5.80 +/- 0.99 Pass DW-50200,50201 7/24/2023 Ra-226 2.51 +/- 0.24 4.07 +/- 0.29 3.29 +/- 0.19 Pass DW-50200,50201 7/24/2023 Ra-228 7.04 +/- 1.13 6.55 +/- 1.09 6.80 +/- 0.79 Pass SG-2199,2200 7/25/2023 Pb-214 1.18 +/-0.22 1.03+/-0.19 1.11 +/- 0.15 Pass SG-2199,2200 7/25/2023 Ac-228 1.74 +/- 0.32 1.86 +/- 0.42 1.80 +/- 0.26 Pass AP-072623NB 7/26/2023 Gr. Beta 0.021 +/- 0.003 0.021 +/- 0.003 0.021 +/- 0.002 Pass AP-080223NB 8/2/2023 Gr. Beta 0.015 +/- 0.003 0.016 +/- 0.003 0.016 +/- 0.002 Pass SG-2315,2316 8/3/2023 Gr. Alpha 59.5 +/- 6.7 48.2 +/-6.1 53.9 +/- 4.5 Pass SG-2315,2316 8/3/2023 Gr. Beta 39.8 +/- 2.9 34.4 +/- 2.6 37.1 +/- 1.9 Pass AP-080723NB 8/7/2024 Gr. Beta 0.025 +/- 0.005 0.025 +/- 0.005 0.025 +/- 0.004 Pass DW-50200,50201 8/9/2023 Ra-228 1.88 +/- 0.71 1.29 +/- 0.70 1.59 +/- 0.50 Pass AP-081423NB 8/14/2023 Gr. Beta 0.030 +/- 0.003 0.028 +/- 0.003 0.029 +/- 0.002 Pass AP-082123NB 8/21/2023 Gr. Beta 0.020 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.002 Pass DW-50262,50263 8/24/2023 Ra-228 2.62 +/- 0.87 1.46 +/- 0.52 2.04 +/- 0.51 Pass DW-50262,50263 8/24/2023 Ra-228 2.62 +/- 0.87 2.80 +/- 0.67 2.71 +/- 0.55 Pass AP-082823NB 8/28/2023 Gr. Beta 0.023 +/- 0.003 0.028 +/- 0.003 0.026 +/- 0.002 Pass DW-50268,50269 8/29/2023 Gr. Alpha 0.87 +/- 0.69 0.97 +/- 0.81 0.92 +/- 0.53 Pass SG-2660,2661 9/4/2023 Gr. Alpha 68.5 +/- 7.1 51.0 +/- 6.3 59.8 +/- 4.7 Pass SG-2660,2661 9/4/2023 Pb-214 13.7 +/- 0.5 14.2 +/- 0.5 14.0 +/- 0.4 Pass SG-2660,2661 9/4/2023 Ac-228 14.4 +/- 0.8 14.3 +/- 0.9 14.4 +/- 0.6 Pass AP-090523NB 9/5/2023 Gr. Beta 0.023 +/- 0.003 0.023 +/- 0.003 0.023 +/- 0.002 Pass AP-091223NB 9/12/2023 Gr. Beta 0.024 +/- 0.002 0.025 +/- 0.002 0.025 +/- 0.001 Pass A-11

TABLE A-5. lntralaboratory "Duplicate" Samples Concentration" Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance W-2776,2777 9/18/2023 Gr. Alpha 1.86 +/- 1.73 0.99 +/- 1.64 1.43 +/- 1.19 Pass W-2776,2777 9/18/2023 Ra-226 0.43 +/- 0.10 0.55 +/- 0.27 0.49 +/- 0.14 Pass W-2776,2777 9/18/2023 Ra-228 1.71 +/- 1.07 3.33+/-1.12 2.52 +/- 0.77 Pass AP-092023AfB 9/20/2023 Gr. Beta 0.039 +/- 0.004 0.042 +/- 0.004 0.041 +/- 0.003 Pass DW-50296,50297 9/27/2023 Ra-226 0.51 +/- 0.09 0.54 +/- 0.20 0.53 +/- 0.11 Pass AP-092823AfB 9/28/2023 Gr. Beta 0.030 +/- 0.004 0.034 +/- 0.004 0.032 +/- 0.003 Pass S-3136,3137 10/11/2023 Pb-214 1.93 +/- 0.06 1.84 +/- 0.08 1.89 +/- 0.05 Pass S-3135,3136 10/11/2023 Ac-228 4.06 +/- 0.17 3.84 +/- 0.19 3.95 +/- 0.13 Pass SG-3511,3512 10/10/2023 Gr. Alpha 59.0 +/- 6.2 68.5 +/- 6.6 63.8 +/- 4.5 Pass SG-3511,3512 10/10/2023 Gr. Beta 52.1 +/- 2.9 54.6 +/- 3.0 53.4 +/- 2.1 Pass SG-3511,3512 10/10/2023 Pb-214 9.67 +/- 0.25 9.57 +/- 0.29 9.62 +/- 0.19 Pass SG-3511,3512 10/10/2023 Ac-228 8.99 +/- 0.43 8.79 +/- 0.53 8.89 +/- 0.34 Pass SG-3521,3522 11/8/2023 Gr. Alpha 57.3 +/- 7.3 70.9 +/- 7.6 64.1 +/- 5.3 Pass SG-3521,3522 11/8/2023 Pb-214 11.2 +/- 0.2 11.7 +/- 0.2 11.5 +/- 0.1 Pass SG-3521,3522 11/8/2023 Ac-228 13.0 +/- 0.4 13.4+/-0.5 13.2 +/- 0.3 Pass DW-50335,50336 11/17/2023 Gr. Alpha 3.70 +/- 1.00 3.46 +/- 0.90 3.58 +/- 0.67 Pass DW-50335,50336 11/17/2023 Gr. Beta 1.73 +/- 0.63 2.07 +/- 0.06 1.90 +/- 0.32 Pass W-3647,3648 11/20/2023 H-3 2,815 +/- 181 2,829 +/- 182 2,822 +/- 128 Pass DW-50358,50359 12/4/2023 Gr. Beta 2.53 +/- 0.61 1.66 +/- 0.62 2.10 +/- 0.43 Pass DW-50349,50350 12/4/2023 Ra-226 0.04 +/- 0.11 0.32 +/- 0.10 0.18 +/- 0.07 Pass DW-50349,50350 12/4/2023 Ra-228 1.37 +/- 0.48 1.57 +/- 0.47 1.47 +/- 0.34 Pass DW-50365,50366 12/11/2023 Gr. Alpha 1.4 +/- 0.79 1.95 +/- 0.91 1.675 +/- 0.60 Pass DW-50365,50366 12/11/2023 Gr. Beta 3.18 +/- 0.62 3.18 +/- 0.66 3.18 +/- 0.45 Pass DW-50374,50375 12/13/2023 Gr. Alpha 0.89 +/- 0.60 0.54 +/- 0.67 0.715 +/- 0.45 Pass W-4035.4036 12/31/2023 H-3 157,638 +/- 1,218 159,848 +/- 1,227 158,743 +/- 864 Pass W-4035.4036 12/31/2023 Ni-63 2,410 +/- 78 2,337 +/- 78 2,373 +/- 55 Pass W-4035.4036 12/31/2023 Sr-90 49.8 +/- 5.2 42.7 +/- 4.8 46.3 +/- 3.5 Pass A-12

TABLEA-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentrationa Reference Known Acceptance Lab Code b Date Analysis Laboratory result Activity Range c Acceptance MAAP-544 2/1/2023 Gross Alpha 1.23 +/- 0.10 0.97 0.29 -1.65 Pass MAAP-544 2/1/2023 Gross Beta 1.67 +/- 0.06 1.49 0.75 - 2.24 Pass MADW-543 2/1/2023 Gross Alpha 0.843 +/- 0.074 1.19 0.36 - 2.02 Pass MADW-543 2/1/2023 Gross Beta 0.578 +/- 0.093 5.94 2.97 - 8.91 Fail d MASO-540 2/1/2023 Cs-134 2.33 +/-2.77 0

NA C Pass MASO-540 2/1/2023 Cs-137 1.22 +/- 2.41 0

NA C Pass MASO-540 2/1/2023 Co-57 585 +/-4 698 489 - 907 Pass MASO-540 2/1/2023 Co-60 727 +/- 8 795 557 - 1034 Pass MASO-540 2/1/2023 Mn-54 1180 +/- 10 1230 861 - 1599 Pass MASO-540 2/1/2023 Zn-65 846 +/- 11 990 693 - 1287 Pass MASO-540 2/1/2023 K-40 526 +/- 23 574 402 - 746 Pass MADW-545 2/1/2023 Cs-134 9.17 +/- 0.17 9.6 6.7 - 12.5 Pass MADW-545 2/1/2023 Cs-137 9.38 +/- 0.29 8.7 6.1 -11.3 Pass MADW-545 2/1/2023 Co-57

-0.01 +/- 0.08 0.0 NA C Pass MADW-545 2/1/2023 Co-60 7.47 +/-0.18 7.24 5.07 - 9.41 Pass MADW-545 2/1/2023 Mn-54 12.3 +/- 0.3 11.3 7.9 - 14.7 Pass MADW-545 2/1/2023 Zn-65 15.7 +/- 0.5 15.3 10.7 -19.9 Pass MADW-545 2/1/2023 K-40 1.23 +/- 1.52 0

NA C Pass MADW-545 2/1/2023 Sr-90

-0.0035 +/- 0.0172 0

NA C Pass MAAP-538 2/1/2023 Cs-134 1.12 +/- 0.04 1.52 1.06 -1.98 Pass MAAP-538 2/1/2023 Cs-137 0.56 +/- 0.07 0.630 0.441 - 0.819 Pass MAAP-538 2/1/2023 Co-57 0.62 +/- 0.30 0.661 0.463 - 0.859 Pass MAAP-538 2/1/2023 Co-60 0.89 +/- 0.07 1.05 0.74 - 1.37 Pass MAAP-538 2/1/2023 Mn-54 2.02 +/- 0.09 2.14 1.50 - 2.78 Pass MAAP-538 2/1/2023 Zn-65 2.13 +/- 0.14 2.25 1.58 - 2.93 Pass MAAP-538 2/1/2023 Sr-90 0.004 +/- 0.061 0

NA C Pass MASO-540 2/1/2023 Cs-134 2.33 +/- 2.77 0

NA C Pass MASO-540 2/1/2023 Cs-137 1.22 +/- 2.41 0

NA C Pass MASO-540 2/1/2023 Co-57 585 +/-4 698 489 - 907 Pass MASO-540 2/1/2023 Co-60 727 +/- 8 795 557 -1034 Pass MASO-540 2/1/2023 Mn-54 1180 +/- 10 1230 861 -1599 Pass MASO-540 2/1/2023 Zn-65 846 +/- 11 990 693 - 1287 Pass MASO-540 2/1/2023 K-40 526 +/- 23 574 402 - 746 Pass A-13

TABLEA-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentrationa Reference Known Acceptance Lab Code b Date Analysis Laboratory result Activity Range c Acceptance MADW-545 2/1/2023 Cs-134 9.17 +/- 0.17 9.6 6.7 -12.5 Pass MADW-545 2/1/2023 Cs-137 9.38 +/- 0.29 8.7 6.1 - 11.3 Pass MADW-545 2/1/2023 Co-57

-0.01 +/- 0.08 0.0 NA C Pass MADW~545 2/1/2023 Co-60 7.47 +/-0.18 7.24 5.07 - 9.41 Pass MADW-545 2/1/2023 Mn-54 12.3 +/- 0.3 11.3 7.9 - 14.7 Pass MADW-545 2/1/2023 Zn-65 15.7 +/- 0.5 15.3 10.7 - 19.9 Pass MADW-545 2/1/2023 K-40 1.23 +/- 1.52 0

NA C Pass MADW-545 2/1/2023 Sr-90

-0.0035 +/- 0.0172 0

NA C Pass MAAP-538 2/1/2023 Cs-134 1.12 +/-0.04 1.52 1.06 -1.98 Pass MAAP-538 2/1/2023 Cs-137 0.56 +/- 0.07 0.630 0.441 - 0.819 Pass MAAP-538 2/1/2023 Co-57 0.62 +/- 0.30 0.661 0.463 - 0.859 Pass MAAP-538 2/1/2023 Co-60 0.89 +/- 0.07 1.05 0.74 -1.37 Pass MAAP-538 2/1/2023 Mn-54 2.02 +/- 0.09 2.14 1.50 -2.78 Pass MAAP-538 2/1/2023 Zn-65 2.13 +/-0.14 2.25 1.58 -2.93 Pass MAAP-538 2/1/2023 Sr-90 0.004 +/- 0.061 0

NA 0

Pass MAVE-545 2/1/2023 Cs-134 7.45 +/- 0.39 7.60 5.32 - 9.88 Pass MAVE-545 2/1/2023 Cs-137 0.010 +/- 0.084 0

NA 0

Pass MAVE-545 2/1/2023 Co-57 6.83 +/-0.17 6.93 4.85 - 9.01 Pass MAVE-545 2/1/2023 Co-60 6.89 +/-0.17 6.51 4.56 - 8.46 Pass MAVE-545 2/1/2023 Mn-54 9.08 +/- 0.28 8.03 5.62 - 10.44 Pass MAVE-545 2/1/2023 Zn-65 7.83 +/- 0.39 7.43 5.20 - 9.66 Pass MAAP-2761 8/1/2023 Gross Alpha 0.16 +/-0.04 0.255 0.077 -0.434 Pass MAAP-2761 8/1/2023 Gross Beta 1.16 +/- 0.07 0.927 0.464 - 1.391 Pass MADW-2753 8/1/2023 Gross Alpha 1.20 +/- 0.06 1.59 0.48 -2.70 Pass MADW-2753 8/1/2023 Gross Beta 14.7 +/-0.1 16.27 8.14 -24.41 Pass MASO-2757 8/1/2023 Cs-134 612 +/- 8 693 485 - 901 Pass MASO-2757 8/1/2023 Cs-137 1900 +/- 20 1810 1267 -2353 Pass MASO-2757 8/1/2023 Co-57 1020 +/- 20 1060 742-1378 Pass MASO-2757 8/1/2023 Co-60 901 +/- 10 898 629 -1167 Pass MASO-2757 8/1/2023 Mn-54 6.53 +/- 3.22 0

NA C Pass MASO-2757 8/1/2023 Zn-65 1270 +/- 30 1160 812 -1508 Pass MASO-2757 8/1/2023 K-40 702 +/- 54 574 402 - 746 Pass A-14

TABLEA-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration 8

Reference Known Acceptance Lab Code b Date Analysis Laboratory result Activity Range c Acceptance MADW-2751 8/1/2023 Cs-134 8.88 +/- 0.18 11.3 7.9 - 14.7 MADW-2751 8/1/2023 Cs-137 7.95 +/- 0.30 8.7 6.1 - 11.3 MADW-2751 8/1/2023 Co-57 16.5 +/- 0.3 19.3 13.5 -25.1 MADW-2751 8/1/2023 Co-60 0.09 +/- 0.06 0

NAC MADW-2751 8/1/2023 Mn-54 11.6 +/- 0.3 12.7 8.9 - 16.5 MADW-2751 8/1/2023 Zn-65 17.9 +/- 0.6 19.1 13.4 - 24.8 MADW-2751 8/1/2023 K-40 1.56 +/- 1.60 0

NA C MAAP-2755 8/1/2023 Cs-134 1.30 +/- 0.10 1.60 1.12 -2.08 MAAP-2755 8/1/2023 Cs-137 0.04 +/- 0.03 0

NAC MAAP-2755 8/1/2023 Co-57 1.47 +/- 0.05 1.63 1.14 -2.12 MAAP-2755 8/1/2023 Co-60 0.04 +/- 0.09 0

NA C MAAP-2755 8/1/2023 Mn-54 1.59 +/- 0.09 1.57 1.10 -2.04 MAAP-2755 8/1/2023 Zn-65 1.71 +/-0.14 1.89 1.32 - 2.46 MAAP-2755 8/1/2023 Sr-90 0.533 +/- 0.040 0.614 0.430 - 0.796 MAVE-2759 8/1/2023 Cs-134 4.25 +/- 0.14 4.96 3.49 - 6.47 MAVE-2759 8/1/2023 Cs-137 0.025 +/- 0.050 0

NA C MAVE-2759 8/1/2023 Co-57 4.28 +/- 0.13 4.24 2.97 - 5.51 MAVE-2759 8/1/2023 Co-60 2.49 +/- 0.11 2.79 1.95 - 3.63 MAVE-2759 8/1/2023 Mn-54 2.45 +/- 0.16 2.6 1.8 - 3.3 MAVE-2759 8/1/2023 Zn-65 0.058 -0.107 0

NAC 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), MADW (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 an acceptance range.

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass d A decimal point was misplaced in a unit conversion. If the conversion was was done properly the result: 5.78 +/- 0.93 Bq/L woud have been within MAPEP's acceptance range.

A-15

TABLEA-7. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)*.

MRAD-38 Study Concentration

Lab Code b Date Analysis Laboratory ERA Acceptance Result Value 0

Limits d Acceptance ERAP-599 3/20/2023 Cs-134 139 153 99 - 188 Pass ERAP-599 3/20/2023 Cs-137 970 892 733 - 1170 Pass ERAP-599 3/20/2023 Co-60 474 467 397 - 593 Pass ERAP-599 3/20/2023 Mn-54

< 3.3

< 35.0 0.00 -35.0 Pass ERAP-599 3/20/2023 Zn-65 1280 1110 910 - 1700 Pass ERAP-599 3/20/2023 Sr-90 143 137 87 -187 Pass ERAP-598 3/20/2023 Gross Alpha 72.7 76.8 40.1 -127 Pass ERAP-598 3/20/2023 Gross Beta 35.0 32.8 19.9 -49.6 Pass

Results obtained by Microbac Laboratories - Northbrook 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).

0 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.

A-16

©) MICROBAC'*

700 Landwehr Road

Northbrook, IL60062-2310 phone (847) 564-0700

lax (847) 564-4517 Appendix B Data Reporting Conventions

APPENDIX B.

DATA REPORTING CONVENTIONS Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows:

x +/- s where:

x = value of the measurement; s = 2cr counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66cr uncertainty for a background sample.

3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. :

3.1 Individual results: For two analysis results; x1 +/- s1 and x2 +/- s2 Reported result:

x +/- s; where x = (1/2) (x1 + x2) ands= (1/2).J s; + Si 3.2.

3.3.

Individual results:

< L1, < L2 Individual results:

x +/- s, < L Reported result: < L, where L = lower of L1 and L2 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 e~ample, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers x1, x2... xn are defined as follows:

1

- ~

x=nZ:x 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.

B-1

©) MICROBAC "

700 Landwehr Road

Northbrook, IL 60062-2310 phone (847) 564-0700

fax (847) 564-4517 Appendix C Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas

APPENDIX C Table C-1.

Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas 8

Air (pCi/m 3

)

Water (pCi/L)

Gross alpha 1 X 1 ff 3

Strontium-89 8,000 Gross beta 1

Strontium-90 500 lodine-131b 2.8x1ff 1

Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 Potassium-40 c 4,000 Gross alpha 2

Gross beta 10 Tritium 1 X 10 6

a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

Concentrations may be averaged over a period not greater than one year.

b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

c A natural radionuclide.

C-1

@ MICROBAC "

700 Landwehr Road

Northbrook, ll 60062-2310 phone (847) 564-0700

fax (847) 564-4S17 Reviewed and Approved 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, 2023 Prepared by Microbac Laboratories Inc. - Northbrook Project No. 8001 Ashok Banavali, Ph.D.

Laboratory Director

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

1.0 INTRODUCTION

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

LIST OF TABLES Title 1

Airborne particulates, Location D-15, analyses for gross beta...................................................... 1-1 2

Airborne particulates, Location D-16, analyses for gross beta...................................................... 2-1 3

Airborne Particulate samples, quarterly composites of weekly samples, analyses for gamma-emitting isotopes.............................................................................. 3-1 4

Ambient gamma radiation by thermoluminescent dosimeters (TLD), quarterly exposure.............4-1 5

Groundwater samples, analysis for iodine-131, tritium and gamma-emitting isotopes............... 5-1 6

Vegetation samples, analysis for iodine-131 and gamma-emitting isotopes.............................................................................................. 6-1 7

Surface water samples, analysis for iodine-131, tritium and gamma-emitting isotopes.............. 7-1 8

Fish samples, analysis for gamma-emitting isotopes................................................................. 8-1 9

River sediment samples, analysis for gamma-emitting isotopes........................................... 9-1 10 Groundwater Protection Program................................................................................. 10-1 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 2023. 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 Defueled Offsite Dose Assessment Manual (DODAM). 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

Sample Type Analysis TLD Gamma 2.0 PROGRAM DEVIATIONS Location(s)

D-31 Collection Date or Period 2nd Qtr '23 V

Comments TLD missing in field.

3.0 DATA TABLES vi

Table 1. Airborne particulates, analyses for gross beta.

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

Units: pCi/m3 Collection: Monthly requirement.

Date Volume Date Volume Collected (m")

Gross Beta Collected (m")

Gross Beta Required LLD 0.010 Required LLD 0.010 01-06-23 286 0.046 +/- 0.005 07-06-23 291 0.030 +/- 0.004 01-13-23 291 0.066 +/- 0.005 07-13-23 288 0.017 +/- 0.003 01-20-23 288 0.036 +/- 0.004 07-20-23 285 0.019 +/- 0.003 01-27-23 288 0.033 +/- 0.004 07-27-23 289 0.029 +/- 0.004 02-03-23 288 0.040 +/- 0.004 08-03-23 277 0.029 +/- 0.004 02-10-23 286 0.027 +/- 0.004 08-10-23 285 0.029 +/- 0.004 02-17-23 291 0.021 +/- 0.004 08-17-23 300 0.020 +/- 0.003 02-24-23 286 0.021 +/- 0.004 08-24-23 285 0.042 +/- 0.005 03-03-23 288 0.027 +/- 0.004 08-31-23 293 0.029 +/- 0.004 03-10-23 291 0.020 +/- 0.004 09-07-23 282 0.029 +/- 0.004 03-17-23 284 0.022 +/- 0.004 09-14-23 286 0.016 +/- 0.004 03-24-23 291 0.031 +/- 0.004 09-21-23 293 0.029 +/- 0.004 03-31-23 285 0.044 +/- 0.005 09-28-23 283 0.030 +/- 0.004 1st Quarter Mean +/- s.d.

0.033 +/- 0.013 3rd Quarter Mean +/- s.d.

0.027 +/- 0.007 04-06-23 250 0.023 +/- 0.004 10-05-23 290 0.043 +/- 0.005 04-14-23 328 0.027 +/- 0.004 10-12-23 287 0.018 +/- 0.003 04-21-23 287 0.016 +/- 0.003 10-19-23 288 0.024 +/- 0.004 04-28-23 288 0.013 +/- 0.003 10-26-23 290 0.028 +/- 0.004 11-02-23 286 0.024 +/- 0.004 05-05-23 288 0.013 +/- 0.003 05-12-23 No*

11-09-23 290 0.038 +/- 0.004 05-19-23 327 0.023 +/- 0.004 11-16-23 291 0.027 +/- 0.004 05-26-23 286 0.018 +/- 0.003 11-22-23 247 0.023 +/- 0.004 06-02-23 296 0.028 +/- 0.004 11-30-23 NSb 06-08-23 240 0.023 +/- 0.004 12-07-23 287 0.073 +/- 0.006 06-15-23 285 0.018 +/- 0.003 12-14-23 325 0.025 +/- 0.004 06-22-23 288 0.026 +/- 0.004 12-21-23 325 0.032 +/- 0.004 06-29-23 289 0.024 +/- 0.004 12-29-23 374 0.032 +/- 0.004 2nd Quarter Mean +/- s.d.

0.021 +/- 0.005 4th Quarter Mean +/- s.d.

0.032 +/- 0.015 Cumulative Average 0.028

"ND" = No data; sample lost in transit.

b "NS' = No sample. Sample holder found detached. Filter appeared blank.

1-1

Table 2. Airborne particulates, analyses for gross beta.

Location: D-16 (On-site)

Units: pCi/m3 Collection: Monthly requirement.

Date Volume Collected (m")

Gross Beta Required LLD 0.010 01-06-23 272 0.051 +/- 0.005 01-13-23 277 0.070 +/- 0.006 01-20-23 273 0.034 +/- 0.004 01-27-23 274 0.036 +/- 0.005 02-03-23 274 0.035 +/- 0.004 02-10-23 272 0.039 +/- 0.004 02-17-23 276 0.021 +/- 0.004 02-24-23 272 0.028 +/- 0.004 03-03-23 274 0.033 +/- 0.004 03-10-23 276 0.026 +/- 0.004 03-17-23 270 0.023 +/- 0.004 03-24-23 276 0.027 +/- 0.004 03-31-23 269 0.044 +/- 0.005 1st Quarter Mean+/- s.d.

0.036 +/- 0.013 04-06-23 237 0.023 +/- 0.005 04-14-23 312 0.031 +/- 0.004 04-21-23 273 0.017 +/- 0.003 04-28-23 273 0.020 +/- 0.004 05-05-23 274 0.017 +/- 0.003 05-12-23 NSa 05-19-23 311 0.025 +/- 0.004 05-26-23 272 0.020 +/- 0.004 06-02-23 282 0.031 +/- 0.004 06-08-23 228 0.028 +/- 0.004 06-15-23 271 0.020 +/- 0.004 06-22-23 274 0.026 +/- 0.004 06-29-23 275 0.029 +/- 0.004 2nd Quarter Mean+/- s.d.

0.024 +/- 0.005

"ND"= No data; sample lost in transit.

b Lower volume due to power outage.

Date Volume Collected (m")

Gross Beta Required LLD 0.010 07-06-23 276 0.031 +/- 0.004 07-13-23 272 0.021 +/- 0.004 07-20-23 273 0.021 +/- 0.004 07-27-23 274 0.034 +/- 0.004 08-03-23 290 0.025 +/- 0.004 08-10-23 183 0.034 +/- 0.006 08-17-23 277 0.027 +/- 0.004 08-24-23 266 0.044 +/- 0.005 08-31-23 279 0.037 +/- 0.004 09-07-23 272 0.032 +/- 0.004 09-14-23 272 0.027 +/- 0.004 09-21-23 279 0.038 +/- 0.004 09-28-23 270 0.041 +/- 0.005 3rd Quarter Mean +/- s.d.

0.032 +/- 0.007 10-05-23 276 0.047 +/- 0.005 10-12-23 273 0.023 +/- 0.004 10-19-23 274 0.025 +/- 0.004 10-26-23 275 0.033 +/- 0.004 11-02-23 272 0.026 +/- 0.004 11-09-23 276 0.047 +/- 0.005 11-16-23 276 0.033 +/- 0.004 11-22-23 234 0.029 +/- 0.005 11-30-23 314 0.035 +/- 0.004 12-07-23 273 0.041 +/- 0.005 12-14-23 351 0.030 +/- 0.004 12-21-23 351 0.039 +/- 0.004 12-29-23 404 0.037 +/- 0.004 4th Quarter Mean+/- s.d.

0.034 +/- 0.008 Cumulative Average 0.032 2-1

Table 3.

Airborne particulates, analyses for gamma-emitting isotopes.

Collection: Quarterly Composite Units: pCi/m" Location D-15 Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Lab Code DAP-818 DAP-2040 DAP-3177 DAP-4084 Volume (m')

3742 3452 3737 3580 Be-7 0.059 +/- 0.011 0.065 +/- 0.015 0.054 +/- 0.015 0.050 +/- 0.012 Mn-54

< 0.0007

< 0.0008

< 0.0007 Fe-59

< 0.0009

< 0.0029

< 0.0023

< 0.0016 Co-58

< 0.0009

< 0.0007

< 0.0006 Co-60

< 0.0015

< 0.0008

< 0.0011

< 0.0014 Zn-65

< 0.0015

< 0.0009

< 0.0017

< 0.0013 Nb-95

< 0.0013

< 0.0016

< 0.0010

< 0.0007 Zr-95

< 0.0014

< 0.0017

< 0.0014

< 0.0007 Ru-103

< 0.0008

< 0.0015

< 0.0012

< 0.0007 Ru-106

< 0.0055

< 0.0082

< 0.0081

< 0.0042 Cs-134

< 0.0007

< 0.0010

< 0.0008 Cs-137

< 0.0012

< 0.0008

< 0.0006

< 0.0010 Ce-141

< 0.0014

< 0.0018

< 0.0014

< 0.0011 Ce-144

< 0.0026

< 0.0040

< 0.0039

< 0.0050 Location D-16 Quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Lab Code DAP-819 DAP-2041 DAP-3179 DAP-4085 Volume (m')

3556 3283 3483 3849 Be-7 0.067 +/- 0.017 0.070 +/- 0.016 0.065 +/- 0.016 0.049 +/- 0.012 Mn-54

< 0.0011

< 0.0008

< 0.0006 Fe-59

< 0.0023

< 0.0035

< 0.0023

< 0.0006 Co-58

< 0.0011

< 0.0012

< 0.0003

< 0.0005 Co-60

< 0.0010

< 0.0006

< 0.0018 Zn-65

< 0.0021

< 0.0009

< 0.0012

< 0.0016 Nb-95

< 0.0012

< 0.0015

< 0.0009

< 0.0010 Zr-95

< 0.0012

< 0.0019

< 0.0010

< 0.0011 Ru-103

< 0.0012,

< 0.0014

< 0.0013

< 0.0010 Ru-106

< 0.0071

< 0.0094

< 0.0064 Cs-134

< 0.0009

< 0.0007

< 0.0014

< 0.0008 Cs-137

< 0.0009

< 0.0005

< 0.0013 Ce-141

< 0.0028

< 0.0017

< 0.0014

< 0.0016 Ce-144

< 0.0058

< 0.0036

< 0.0048 3-1

Table 4. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD).

Quarterly collection.

Units: mR/91 days Control Location 1st Qtr.

3rd Qtr.

4th Qtr.

D-4 16.6 +/- 1.2 16.1 +/- 1.8 17.7+/-1.5 16.7 +/-1.9 Within 0.5 mi. of Stack D-15 15.1 +/- 0.7 12.9 +/-1.4 15.9 +/- 0.9 14.0 +/- 1.3 D-17 17.3 +/- 1.0 13.9 +/- 1.1 19.5 +/- 0.9 14.9 +/- 1.1 D-18 14.2 +/- 0.9 15.2+/-1.2 15.2 +/- 0.9 16.0 +/- 1.2 D-20 13.8 +/- 0.8 11.7 +/- 1.1 15.1 +/- 0.9 12.7 +/- 1.1 D-22 12.7 +/- 0.7 13.6 +/- 1.2 13.6 +/- 0.7 15.3 +/- 1.2 D-29 15.1 +/- 1.3 17.4+/-1.8 17.6+/-1.0 17.6 +/-1.3 D-31 16.6 +/- 1.1 NDa 16.0+/-1.3 18.1 +/- 1.1 D-83 13.0 +/- 0.9 14.0 +/-1.3 14.1 +/- 1.1 14.8 +/- 1.1 D-85 15.7 +/- 0.5 15.0 +/- 1.5 16.8 +/- 0.5 15.8 +/- 1.4 Mean +/-s.d.

14.8 +/- 1.6 14.2 +/- 1.7 16.0 +/- 1.8 15.5 +/- 1.7 a "ND" = No data; see Table 2.0, Program Deviations.

4-1

Table 4. 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 13.3 +/- 1.1 12.7+/-1.2 15.5 +/- 0.9 13.6 +/- 1.1 D-46 17.7+/-1.0 18.5 +/- 2.2 19.6 +/- 1.0 18.6 +/- 2.2 D-48 17.7 +/- 1.3 15.7 +/- 1.3 20.6 +/- 1.3 16.4 +/- 1.5 Mean+/- s.d.

16.3 +/- 2.5 15.6 +/- 2.9 18.5 +/- 2.7 16.2 +/- 2.5 Within 3.0 mi. of Stack D-33 12.3 +/- 0.7 12.0 +/- 1.1 13.4 +/- 0.7 12.6+/-1.0 D-35 13.0 +/- 0.8 10.4 +/- 1.1 13.9 +/- 0.8 11.4 +/- 1.1 D-37 12.6 +/- 1.2 13.6 +/- 1.2 16.8 +/- 0.7 14.1 +/- 1.3 D-39 15.4 +/- 1.1 13.8 +/- 1.2 16.6 +/- 1.0 14.7 +/- 1.2 D-42 14.4+/-1.0 14.4 +/- 1.1 17.6 +/- 1.2 14.7 +/- 1.1 Mean+/- s.d.

13.5 +/- 1.3 12.8+/-1.6 15.7 +/- 1.9 13.5 +/- 1.5 ISFSI Fenceline D-161 85.4 +/- 3.3 77.4 +/- 4.5 74.4 +/- 5.5 77.7 +/-2.2 D-162 24.5 +/- 1.2 24.3 +/- 1.7 24.9 +/- 1.7 23.6 +/- 1.6 D-163 76.0 +/- 3.4 78.4 +/-2.1 70.9 +/- 1.0 73.5 +/- 3.3 D-164 85.3 +/- 3.7 70.2 +/- 5.8 71.4 +/-4.1 60.1 +/- 3.7 D-ISFSI-1 28.1 +/- 1.6 23.8 +/- 1.1 D-ISFSl-2 96.1 +/- 6.4 84.8 +/-6.6 D-ISFSl-3 77.6 +/- 4.8 63.0 +/-4.0 D-ISFSl-4 26.8 +/- 1.3 22.0 +/- 1.0 D-ISFSl-5 34.7 +/-2.2 33.9 +/- 1.7 D-ISFSl-6 46.5 +/- 2.1 43.0 +/- 2.8 D-ISFSl-7 34.8 +/- 0.8 30.3 +/- 2.1 D-ISFSl-8 19.2 +/- 0.9 18.3 +/- 1.2 Mean+/- s.d.

67.8 +/- 29.2 62.6 +/- 25.8 50.5 +/-26.0 58.7 +/- 24.6 4-2

Table 5. Well water samples, analyses for gamma emitting isotopes and tritium.

Location Lab Code Collection: Monthly Units: pCi/L DWW-73 Date Collected 01-13-23 H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Lab Code Date Collected H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

< 161

< 1.3

< 6.3

< 2.3

< 1.7

< 4.4

< 1.8

< 3.9

< 2.8

< 2.4

< 10.4

< 1.7 DWW-1218 05-15-23

< 161

< 1.3

< 3.4

< 1.3

< 1.7

< 2.5

< 2.9

< 4.6

< 4.8

< 2.1.

< 2.6

< 16.4

< 2.6 D-52 Drinking Water DWW-340 02-15-23

< 154

< 1.9

< 3.1

< 1.2

< 1.5

< 2.7

< 1.0

< 3.2

< 1.8

< 1.6

< 1.5

< 6.2

< 2.5 DWW-1551 06-12-23

< 157

< 4.4

< 12.2

< 5.0

< 3.9

< 4.2

< 4.8

< 7.6

< 11.9

< 5.1

< 4.1

< 37.2

< 12.4 5-1 DWW-575 03-15-23

< 164

< 1.3

< 1.7

< 0.8

< 2.9

< 2.7

< 1.5

< 1.0

< 2.1

< 1.4

< 2.4

< 7.0

< 1.5 DWW-2022 07-17-23

< 162

< 3.3

< 2.9

< 2.2

< 5.7

< 5.5

< 3.9

< 5.1

< 3.7

< 3.2

< 5.5

< 11.2

< 3.4 DWW-892 04-13-23

< 161

< 1.6

< 1.9

< 1.1

< 4.1

< 3.5

< 2.1

< 3.3

< 3.0

< 2.0

< 3.3

< 11.5

< 2.9 DWW-2498 08-16-23

< 158

< 6.8

< 4.2

< 5.2

< 4.4

< 4.8

< 8.5

< 7.0

< 6.7

< 5.1

< 24.4

< 5.2

Table 5. Well water samples, analyses for gamma emitting isotopes and tritium.

Location Lab Code Collection: Monthly Units: pCi/L DWW-2684 Date Collected 09-11-23 H-3

< 163 Mn-54

< 3.7 Fe-59

< 5.3 Co-58

< 3.4 Co-60

< 9.1 Zn-65

< 7.5 Nb-95

< 3.0 Zr-95

< 7.0 1-131

< 11.2 Cs-134

< 5.7 Cs-137

< 7.5 Ba-140

< 23.1 La-140

< 4.0 D-52 Drinking Water DWW-3189 10-16-23

< 169

< 4.7

< 2.9

< 5.6

< 7.3

< 6.3

< 4.4

< 7.2

< 6.8

< 4.7

< 8.3

< 17.7

< 2.9 5-2 DWW-3573 DWW-3777 11-15-23 12-04-23

< 172

< 171

< 1.8

< 2.4

< 5.2

< 7.6

< 2.8

< 2.9

< 2.4

< 6.2

< 6.3

< 6.0

< 4.1

< 4.3

< 6.4

< 4.2

< 7.9

< 4.1

< 3.0

< 4.7

< 3.5

< 6.4

< 21.5

< 14.1

< 3.5

< 2.0

Table 5. Well water samples, analyses for gamma emitting isotopes and tritium.

Location Lab Code Collection: Monthly Units: pCi/L DWW-74 Date Collected 01-13-23 H-3

< 161 Mn-54

< 1.9 Fe-59

< 2.7 Co-58

< 2.3 Co-60

< 6.1 Zn-65

< 4.3 Nb-95

< 2.6 Zr-95

< 5.3 1-131

< 5.0 Cs-134

< 3.3 Cs-137

< 4.9 Ba-140

< 9.8 La-140

< 2.0 Lab Code DWW-1216 Date Collected 05-15-23 H-3

< 161 Mn-54

< 2.4 Fe-59

< 3.0 Co-58

< 1.7 Co-60

< 6.3 Zn-65

< 3.1 Nb-95

< 4.5 Zr-95

< 5.8 1-131

< 14.2 Cs-134

< 3.1 Cs-137

< 5.5 Ba-140

< 14.3 La-140

< 6.1 D-53 Treated Municipal Water, Drinking Water DWW-341 DWW-576 02-15-23 03-15-23

< 154

< 164

< 1.5

< 2.8

< 3.6

< 2.0

< 2.4

< 1.9

< 2.1

< 3.6

< 4.3

< 2.3

< 1.7

< 2.1

< 3.7

< 2.4

< 2.0

< 2.2

< 2.3

< 1.7

< 10.3

< 8.9

< 1.5

< 1.8 DWW-1552 DWW-2021 06-12-23 07-17-23

< 157

< 162

< 3.5

< 2.0

< 13.4

< 3.9

< 4.5

< 2.9

< 5.4

< 6.6

< 3.4

< 2.6

< 5.7

< 2.4

< 8.7

< 4.8

< 14.6

< 5.0

< 6.4

< 3.3

< 4.4

< 5.2

< 38.3

< 13.0

< 13.7

< 3.7 5-3 DWW-893 04-13-23

< 161

< 3.5

< 2.3

< 2.2

< 6.1

< 4.3

< 2.5

< 5.1

< 6.1

< 3.2

< 5.1

< 13.7

< 2.7 DWW-2497 08-16-23

< 158

< 3.2

< 3.7

< 3.6

< 7.1

< 5.2

< 2.5

< 4.7

< 5.3

< 3.7

< 7.0

< 19.3

< 2.0

Table 5. Well water samples, analyses for gamma emitting isotopes and tritium.

Location Lab Code Collection: Monthly Units: pCi/L Date Collected DWW-2685 09-11-23 H-3

< 163 Mn-54

< 7.4 Fe-59

< 9.1 Co-58

< 8.9 Co-60

< 5.3 Zn-65

< 7.7 Nb-95

< 8.1 Zr-95

< 15.0 1-131

< 10.5 Cs-134

< 8.5 Cs-137

< 6.0 Ba-140

< 24.5 La-140

< 7.8 D-53 Treated Municipal Water, Drinking Water DWW-3190 DWW-3574 10-16-23

< 169

< 6.3

< 9.8

< 4.7

< 4.9

< 7.8

< 6.9

< 9.8

< 5.1

< 8.3

< 7.7

< 23.3

< 4.8 5-4 11-15-23

< 172

< 2.5

< 5.4

< 2.9

< 3.3

< 4.1

< 4.0

< 2.8

< 6.0

< 3.1

< 2.9

< 16.3

< 5.3 DWW-3778 12-04-23

< 171

< 1.7

< 5.2

< 3.1

< 1.8

< 6.5

< 3.4

< 5.0

< 5.3

< 4.1

< 3.5

< 15.8

< 3.5

Table 5. Well water samples, analyses for gamma emitting isotopes and tritium.

Location Lab Code Collection: Monthly Units: pCi/L D-55 First Interface (New Well)

DWW-890 DWW-1217 Date Collected 04-12-23 05-15-23 H-3

< 161

< 161 Mn-54

< 1.2

< 2.2 Fe-59

< 6.4

< 4.5 Co-58

< 1.5

< 1.9 Co-60

< 1.8

< 2.1 Zn-65

< 3.2

< 2.2 Nb-95

< 2.0

< 2.6 Zr-95

< 4.5

< 4.3 1-131

< 3.1

< 2.6 Cs-134

< 2.5

< 2.3 Cs-137

< 2.9

< 2.2 Ba-140

< 9.8

< 8.1 La-140

< 2.6

< 4.2 5-5 DWW-1553 DWW-2023 06-12-23 07-17-23

< 157

< 162

< 4.6

< 4.1

< 12.0

< 5.3

< 5.0

< 6.2

< 4.7

< 4.4

< 8.7

< 10.0

< 6.1

< 3.4

< 9.5

< 8.8

< 13.8

< 6.5

< 5.9

< 5.1

< 3.4

< 38.0

< 24.7

< 9.0

< 5.1

Table 6. Vegetation, analyses for iodine-131 and other gamma-emitting isotopes.

Collection: Annually Units: pCi/g wet Location D-015 Lab Code DVE-2708 Date Collected 09-12-23 Sample Type Green Leaves K-40 3.40 +/- 0.64 Mn-54

< 0.022 Fe-59

< 0.051 Co-58

< 0.011 Co-60

< 0.062 Zn-65

< 0.044 Nb-95

< 0.019 Zr-95

< 0.026 Ru-103

< 0.032 Ru-106

< 0.188 1-131

< 0.040 Cs-134

< 0.032 Cs-137

< 0.050 Ce-141

< 0.056 Ce-144

< 0.258 Location D-016 Lab Code DVE-2711 Date Collected 09-12-23 Sample Type Green Leaves K-40 5.86 +/- 0.60 Mn-54

< 0.026 Fe-59

< 0.056 Co-58

< 0.028 Co-60

< 0.029 Zn-65

< 0.052 Nb-95

< 0.027 Zr-95

< 0.041 Ru-103

< 0.030 Ru-106

< 0.187 1-131

< 0.043 Cs-134

< 0.027 Cs-137

< 0.032 Ce-141

< 0.055 Ce-144

< 0.214 D-015 DVE-2709 09-12-23 Forage 5.46 +/- 0.54

< 0.021

< 0.040

< 0.023

< 0.049

< 0.056

< 0.024

< 0.046

< 0.024

< 0.189

< 0.054

< 0.026

< 0.041

< 0.044

< 0.135 D-016 DVE-2712 09-12-23 Forage 4.37 +/- 0.53

< 0.025

< 0.064

< 0.021

< 0.024

< 0.053

< 0.032

< 0.051

< 0.023

< 0.274

< 0.048

< 0.029

< 0.034

< 0.065

< 0.172 6-1 D-015 DVE-2710 09-12-23 Corn 2.30 +/- 0.19

< 0.006

< 0.028

< 0.009

< 0.010

< 0.021

< 0.018

< 0.021

< 0.012

< 0.102

< 0.012

< 0.013

< 0.011

< 0.015

< 0.064 D-016 DVE-2713 09-12-23 Corn 3.56 +/- 0.23

< 0.006

< 0.018

< 0.004

< 0.005

< 0.016

< 0.007

< 0.011

< 0.007

< 0.063

< 0.006

< 0.008

< 0.006

< 0.010

< 0.045

Table 7. Surface water samples, analyses for iodine-131, tritium and gamma-emitting isotopes.

Collection:

Monthly Units:

Location:

Lab Code Date Collected H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Lab Code Date Collected H-3 Mn-54 Fe-59 Co-56 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 pCi/L D-49 DSW-103 01-18-23

< 160

< 4.4

< 5.9

< 2.1

< 3.1

< 6.1

< 2.1

< 4.1

< 4.0

< 3.6

< 3.4

< 10.9

< 4.1 DSW-2052 07-16-23

< 162

< 4.6

< 9.1

< 3.4

< 4.2

< 10.1

< 4.3

< 7.9

< 6.6

< 5.6

< 4.2

< 21.4

< 4.7 DSW-365 02-20-23

< 154

< 2.0

< 4.5

< 2.5

< 6.5

< 2.2

< 4.0

< 2.6

< 2.7

< 3.3

< 9.4

< 1.9 DSW-2495 06-16-23

< 161

< 4.0

< 7.1

< 1.7

< 6.9

< 5.1

< 4.6

< 7.3

< 6.6

< 4.9

< 7.2

< 16.6

< 3.1 DSW-596 03-20-23

< 164

< 3.7

< 5.2

< 2.0

< 7.0

< 5.4

< 3.0

< 6.5

< 5.2

< 3.6

< 6.2

< 12.4

< 2.6 DSW-2771 09-18-23

< 163

< 6.1

< 20.0

< 6.3

< 7.0

< 14.3

< 7.2

< 13.6

< 7.2

< 6.6

< 7.7

< 14.0

< 9.3 7-1 DSW-951 04-18-23

< 161

< 3.8

< 3.7

< 3.8

< 2.4

< 3.6

< 4.1

< 6.3

< 3.3

< 3.6

< 2.3

< 6.1

< 3.0 DSW-3227 10-17-23

< 169

< 3.4

< 4.5

< 2.3

< 8.0

< 4.3

< 4.9

< 3.6

< 3.9

< 8.5

< 20.9

< 4.6 DSW-1290 05-18-23

< 161

< 2.7

< 4.2

< 2.9

< 3.4

< 4.2

< 2.3

< 4.5

< 4.6

< 2.4

< 2.5

< 12.3

< 2.2 DSW-3546 11-14-23

< 172

< 1.6

< 3.1

< 1.2

< 3.4

< 3.3

< 2.7

< 3.4

< 2.4

< 1.9

< 3.3

< 6.6

< 1.9 DSW-1643 06-19-23

< 162

< 2,5

< 13.4

< 4.3

< 2.6

< 11.3

< 6.7

< 10.2

< 12.0

< 7.6

< 6.2

< 30.2

< 5.4 DSW-3929 12-16-23

< 171

< 2.0

< 5.0

< 1.8

< 0.6

< 4.6

< 2.6

< 3.1

< 2.2

< 2.7

< 2.5

< 9.4

< 3.3

Table 7. Surface water samples, analyses for iodine-131, tritium and gamma-emitting isotopes.

Collection:

Monthly Units:

pCi/L Location:

D-61 Lab Code Date Collected DSW-104 01-18-23 H-3

< 160 Mn-54

< 2.9 Fe-59

< 5.0 Co-58

< 1.9 Co-60

< 2.7 Zn-65

< 2.9 Nb-95

< 1.9 Zr-95

< 3.9 1-131

< 2.3 Cs-134

< 3.3 Cs-137

< 3.3 Ba-140

< 12.0 La-140

< 3.4 Lab Code DSW-2051 Date Collected 07-18-23 H-3

< 162 Mn-54

< 2.7 Fe-59

< 5.1 Co-58

< 2.3 Co-60

< 6.3 Zn-65

< 4.8 Nb-95

< 2.4 Zr-95

< 6.6 1-131

< 5.2 Cs-134

< 3.3 Cs-137

< 5.7 Ba-140

< 14.5 La-140

< 3.1 DSW-366 02-20-23

< 154

< 2.0

< 5.0

< 2.6

< 6.6

< 5.4

< 2.0

< 4.7

< 4.6

< 3.1

< 5.6

< 8.7

< 1.8 DSW-2496 08-16-23

< 158

< 5.4

< 4.4

< 6.7

< 4.8

< 8.6

< 4.5

< 11.7

< 4.2

< 7.3

< 7.4

< 13.6

< 3.6 DSW-597 03-20-23

< 164

< 2.8

< 4.2

< 3.8

< 1.6

< 8.1

< 2.6

< 6.1

< 3.2

< 3.8

< 5.0

< 16.4

< 3.8 DSW-2772 09-18-23

< 163

< 7.5

< 6.5

< 5.0

< 5.1

< 7.0

< 7.5

< 14.0

< 7.9

< 9.7

< 4.9

< 39.7

< 5.3 7-2 DSW-952 04-18-23

< 161

< 1.1

< 2.6

< 1.4

< 2.8

< 2.1

< 1.6

< 2.3

< 1.9

< 1.4

< 2.3

< 5.0

< 1.7 DSW-3228 10-17-23

< 169

< 7.7

< 12.3

< 8.3

< 7.2

< 7.6

< 9.5

< 11.1

< 5.4

< 9.3

< 6.5

< 19.5

< 5.7 DSW-1292 05-18-23

< 161

< 1.9

< 2.8

< 1.3

< 1.5

< 2.7

< 1.7

< 1.9

< 2.7

< 1.5

< 1.6

< 8.6

< 2.4 DSW-3547 11-14-23

< 172

< 1.7

< 4.1

< 3.3

< 5.4

< 3.5

< 2.4

< 4.1

< 11.8

< 3.3

< 5.5

< 18.6

< 4.8 DSW-1644 06-19-23

< 158

< 4.9

< 14.4

< 4.3

< 3.4

< 10.1

< 6.9

< 9.5

< 12.1

< 7.1

< 4.9

< 36.1

< 10.8 DSW-3931 12-18-23

< 171

< 2.4

< 4.0

< 3.1

< 3.0

< 7.7

< 3.3

< 2.4'

< 2.7

< 2.9

< 2.8

< 11.6

< 2.8

Table 8. Fish, analyses of edible portion for gamma-emitting isotopes.

Collection: Semiannually Units: pCi/g wet Location Lab Code DF-1021 Date Collected 04-27-23 Sample Type Channel Catfish K-40 3.44 +/- 0.37 Mn-54

< 0.014 Fe-59

< 0.051 Co-58

< 0.017 Co-60

< 0.014 Zn-65

< 0.029 Nb-95

< 0.035 Zr-95

< 0.024 Ru-103

< 0.016 Ru-106

< 0.129 Cs-134

< 0.018 Cs-137

< 0.017 Ce-141

< 0.043 Ce-144

< 0.105 Location Lab Code DF-1023 Date Collected 04-27-23 Sample Type Channel Catfish K-40 3.61 +/- 0.35 Mn-54

< 0.010 Fe-59

< 0.025 Co-58

< 0.015 Co-60

< 0.026 Zn-65

< 0.034 Nb-95

< 0.017 Zr-95

< 0.021 Ru-103

< 0.032 Ru-106

< 0.117 Cs-134

< 0.015 Cs-137

< 0.022 Ce-141

< 0.047 Ce-144

< 0.098 Upstream, D-49 DF-1022 04-27-23 Walleye 3.53 +/- 0.34

< 0.011

< 0.025

< 0.012

< 0.013

< 0.022

< 0.017

< 0.027

< 0.020

< 0.088

< 0.012

< 0.010

< 0.035

< 0.052 Downstream, D-61 DF-1024 04-27-23 Largemouth Bass 3.66 +/- 0.35

< 0.011

< 0.043

< 0.013

< 0.024

< 0.031

< 0.033

< 0.023

< 0.123

< 0.013

< 0.017

< 0.045

< 0.080 8-1 DF-3499 11-07-23 Walleye 3.65 +/- 0.57

< 0.014

< 0.033

< 0.023

< 0.011

< 0.039

< 0.025

< 0.035

< 0.164

< 0.023

< 0.020

< 0.055

< 0.117 DF-3500 DF-3502 11-07-23 11-07-23 Walleye Channel Catfish 4.30 +/- 0.60 4.10 +/- 0.60

< 0.019

< 0.047

< 0.053

< 0.015

< 0.018

< 0.017

< 0.024

< 0.065

< 0.060

< 0.045

< 0.035

< 0.038

< 0.049

< 0.029

< 0.023

< 0.175

< 0.130

< 0.023

< 0.022

< 0.025

< 0.028

< 0.041

< 0.108

< 0.151

Table 9. River sediment, analysis for gamma-emitting isotopes.

Location Lab Code Collection: Semiannually Units: pCi/g _dry Date Collected K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 Location Lab Code Date Collected K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 DBS-1016 04-27-23 9.97 +/- 0.69

< 0.031

< 0.085

< 0.027

< 0.022

< 0.062

< 0.041

< 0.050

< 0.035

< 0.180

< 0.019 0.08 +/- 0.025

< 0.085

< 0.116 DBS-1017 04-27-23 10.18 +/- 0.76

< 0.038

< 0.112

< 0.045

< 0.029

< 0.052

< 0.079

< 0.083

< 0.052

< 0.135

< 0.022 0.07 +/- 0.037

< 0.113

< 0.212 9-1 D-49 (Control)

DBS-3413 11-02-23 7.21 +/- 0.41

< 0.016

< 0.028

< 0.019

< 0.009

< 0.024

< 0.020

< 0.021

< 0.022

< 0.135

< 0.011

< 0.012

< 0.052

< 0.075 D-51 (Discharge)

DBS-3414 11-02-23 7.33 +/- 0.50

< 0.018

< 0.057

< 0.022

< 0.014

< 0.041

< 0.037

< 0.035

< 0.020

< 0.127

< 0.011

< 0.016

< 0.061

< 0.112

Table 10 Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium *.

Lab Code Date H-3 (pCVL)

D-129A (09A)

DWW-1455 06101123

< 157 D-129B (09B)

DWW-1478 05/31123 253 +/-89 D-131A (11A)

DWW-1469 06/01123

< 157 D-131B (11B)

DWW-1470 06101/23

< 157 D-132A (12A)

DWW-1471 06/01/23 864+/-117 D-132B (12B)

DWW-1473 06/01123 237 +/-88 D-134A (14A)

DWW-1459 05131123 467 +/-99 D-134B (14B)

DWW-1554 06106123 211 +/-86 D-62 (18A)

DWW-1460 05131/23 512 +/- 101 D-64 (20A)

DWW-1479 05/31123 223 +/-87 a Analyses for gamma, gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1 K pCi/L.

10-1

Table 18 Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium *.

Lab Code Date H-3 (pCi/L)

D-65 DWW-1461 05/31/23

< 157 D-66 DWW-1458 05/31/23 291 +/- 91 D-67 DWW-1456 05/31/23 486 +/- 100 D-165 DWW-1464 06/01/23

< 157 D-167 DWW-1472 06/01/23 192 +/- 85 D-168A DWW-1465 06/01/23

< 157 D-168B DWW-1466 06/01/23

< 157 D-169A DWW-1474 06/01/23

< 157 D-169B DWW-1451 06/01/23

< 157

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

10-2 (21A)

(22A)

(23A)

(24A)

(26A)

(27A)

(27B)

(28A)

(28B)

Table 18 Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium *.

Lab Code Date H-3 (pCVL)

D-170A DWW-1468 06/01123 183 +/- 85 D-170B DWW-1450 06101/23

< 157 D-171A DWW-1452 06/01/23

< 157 D-171B DWW-1462 06/01/23

< 157 D-173A DWW-1467 06/01123

< 157 D-173B DWW-1475 06101123 169 +/- 84 D-79 DWW-1453 06/01123

< 157 D-80 DWW-1454 06/01/23 232 +/- 87 D-81 DWW-1476 06/01123

< 157

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

10-3 (29A)

(29B)

(30A)

(30B)

(32A)

(32B)

MW-33A MW-34A MW-35A

Table 18 Groundwater Protection Program Summary.

Ground water, Monitoring wells, analyses for tritium *.

Lab Code Date H-3 (pCi/L)

EW-01 DWW-1457 05/31/23 730 +/- 111 EW-02 DWW-1480 05/31/23 798 +/- 114 EW-03 DWW-1477 05/31/23 699 +/- 110

Analyses for gamma, gross alpha, Sr-69, Sr-90, Fe-55 and Ni-63 will be performed if tritium activity> 1K pCi/L.

10-4

NG-24-0004, 2023 Annual Radiological Environmental Operating Report

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6.0 REFERENCES

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NG-24-0004, 2023 Annual Radiological Environmental Operating Report

Text

Subject:

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

1.0 INTRODUCTION

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