RBG-48019, 2019 Annual Radioactive Effluent Release Report

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2019 Annual Radioactive Effluent Release Report
ML20121A286
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/30/2020
From: Schenk T
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-48019
Download: ML20121A286 (72)
v • d • e


Text

Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61N St. Francisville, LA 70775 Tel 225-381-4177 Tim Schenk Manager-Regulatory Assurance RBG-48019 April 30, 2020 Attn: Document Control Desk U. S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738

Subject:

2019 Annual Radioactive Effluent Release Report River Bend Station - Unit 1 License No. NPF-47 Docket No. 50-458 Enclosed is the River Bend Station (RBS) Annual Radioactive Effluent Release Report for the period of January 1, 2019 through December 31, 2019. This report is submitted in accordance with the RBS Technical Specifications, Section 5.6.3.

Should you have any questions regarding the enclosed, please contact Tim Schenk, at (225) 381-4177.

Sincerely, Tim Schenk TAS/tf

Enclosure:

2019 Annual Radioactive Effluent Release Report cc:

NRC Region IV Regional Administrator, w/o Enclosure NRC Senior Resident Inspector - River Bend Station, Unit 1 Ji Young Wiley, Department of Environmental Quality, Office of Environmental Compliance, Radiological Emergency Planning and Response Section Public Utility Commission of Texas, Attn: PUC Filing Clerk NRC Project Manager Tim Schenk Digitally signed by Tim Schenk Date: 2020.04.30 13:35:19

-05'00'

Enclosure 2019 Annual Radioactive Effluent Release Report

Plant: River Bend Nuclear Station Page 1 of 70 YEAR: 2019 Document Number: RBG-48013 Annual Radioactive Effluent Release Report

Plant: River Bend Nuclear Station Year: 2019 Page 2 of 70 Annual Radioactive Effluent Release Report TABLE OF CONTENTS

1.0 INTRODUCTION

......................................................................................................................... 3 2.0 SUPPLEMENTAL INFORMATION.............................................................................................. 3 3.0 GASEOUS EFFLUENTS........................................................................................................... 13 4.0 LIQUID EFFLUENTS................................................................................................................ 17 5.0 SOLID WASTE

SUMMARY

...................................................................................................... 22 6.0 RADIOLOGICAL IMPACT TO MAN.......................................................................................... 24 7.0 METEORLOGICAL DATA......................................................................................................... 27 ATTACHMENTS - Groundwater Monitoring Well Sampling Results........................................................... 44

Plant: River Bend Nuclear Station Year: 2019 Page 3 of 70 Annual Radioactive Effluent Release Report

1.0 INTRODUCTION

This is the Annual Radioactive Effluent Release Report for the period of January 1, 2019, through December 31, 2019. This report is submitted in accordance with Technical Specification 5.6.3 of Appendix A to River Bend Station (RBS) License Number NPF-47.

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.1.1 10CFR50, Appendix I Limits

1.

Fission and activation gases:

a.

In accordance with Technical Requirement (TR) 3.11.2.2, the air dose due to noble gases released in gaseous effluent to areas at and beyond the SITE BOUNDARY shall be limited to:

1)

Quarterly Less than or equal to 5 mrads gamma Less than or equal to 10 mrads beta

2)

Yearly Less than or equal to 10 mrads gamma Less than or equal to 20 mrads beta

2.

Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days.

a.

In accordance with Technical Requirement 3.11.2.3, the dose to a MEMBER OF THE PUBLIC from radioiodines (I-131 and I-133), tritium (H-3) and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluent releases to areas at and beyond the SITE BOUNDARY shall be limited to:

1)

Quarterly Less than or equal to 7.5 mrem to any organ

2)

Yearly Less than or equal to 15 mrem to any organ

Plant: River Bend Nuclear Station Year: 2019 Page 4 of 70 Annual Radioactive Effluent Release Report

3.

Liquid Effluents Dose

a.

In accordance with Technical Requirement 3.11.1.2, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluent released to UNRESTRICTED AREAS shall be limited to:

1)

Quarterly Less than or equal to 1.5 mrem total body Less than or equal to 5 mrem critical organ

2)

Yearly Less than or equal to 3 mrem total body Less than or equal to 10 mrem critical organ

4.

Total Dose (40CFR190)

a.

In accordance with Technical Requirement 3.11.4, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to:

Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.

Less than or equal to 75 mrem, Thyroid 2.1.2 Miscellaneous Limits

1.

Technical Requirement 3.11.2.1 - Fission and Activation Gases

a.

In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be:

Less than or equal to 500 mrem/year to the total body Less than or equal to 3000 mrem/year to the skin

2.

Technical Requirement 3.11.2.1 - Radioiodine (I-131 & I-133) and Particulate

a.

In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioiodines, tritium, and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to:

Less than or equal to 1500 mrem/yr to any organ

Plant: River Bend Nuclear Station Year: 2019 Page 5 of 70 Annual Radioactive Effluent Release Report

3.

Technical Requirement 3.11.1.1 - Liquid Effluent

a.

In accordance with Technical Requirement 3.11.1.1, the concentration of radioactive material released in liquid effluent to UNRESTRICTED AREAS shall be limited to ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/milliliter total concentration.

4.

Technical Requirement 3.11.2.5 - Ventilation Exhaust Treatment

a.

In accordance with Technical Requirement 3.11.2.5, the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31-day period.

5.

Technical Requirement 3.11.1.3 - Liquid Radwaste Treatment System

a.

In accordance with Technical Requirement 3.11.1.3, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.

2.2 Effluent Concentration Limits

1.

Gaseous Releases

a.

The concentrations of radioactive gaseous releases are based on the dose rate restrictions in RBS Technical Requirements, rather than the Effluent Concentration Limits (ECL) listed in 10CFR20 Appendix B, Table 2, Column 1.

2.

Liquid Releases

a.

The Effluent Concentration Limits of radioactive materials in liquid effluents are limited to ten times 10CFR20, Appendix B, Table 2, Column

2.

2.3 Measurements & Approximations of Total Radioactivity

1.

Gaseous Efflluent

a.

Fission & activation gases Periodic grab samples are obtained from the Main Plant Exhaust Duct, Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent. These samples are analyzed using high purity germanium detectors coupled to computerized pulse height analyzers. The sampling and analysis frequencies are described in Table 4.

Plant: River Bend Nuclear Station Year: 2019 Page 6 of 70 Annual Radioactive Effluent Release Report Sampling and analysis of these effluent streams provide noble gas radionuclide relative abundance that can then be applied to the noble gas gross activity and gross activity release rate to obtain nuclide specific activities and release rates. The noble gas gross activity released within a specific time period is determined by integrating the stack monitor release rate over the considered time period. If no activity was detected between the stack grab sample and a significant increase in hourly averages was recorded, the nuclide relative abundance of the last sample (or the last similar event), which indicated the presence of activity, was used to obtain nuclide specific activities. Correction factors for the monitors are derived and applied for each sampling period whenever noble gas radionuclides are detected in the effluent stream.

b.

Particulate and Radioiodine (I-131 & I-133)

Particulates, Iodine-131 and Iodine-133 are continuously sampled from the three release points using a particulate filter and charcoal cartridge in line with a sample pump (stack monitor pump). These filters and charcoal cartridges are removed and analyzed in accordance with the frequencies specified in Table 4. Analysis is performed to identify and quantify radionuclides using high purity germanium detectors coupled to computerized pulse height analyzers. Given the nuclide specific activity concentrations, process flow rate, and duration of the sample, the nuclide specific activity released to the environment can be obtained. Due to the continuous sampling process, it is assumed that the radioactive material is released to the environment at a constant rate within the sampling period. Strontium-89 and Strontium-90 (Sr-89 and Sr-90) are quantitatively analyzed by counting by gas flow proportional counting.

Gross alpha analysis is performed using a zinc sulfide scintillation counter.

c.

Tritium Tritium grab samples are obtained from the three gaseous release points at the specified frequencies listed in Table 4 using an ice bath condensation collection method. The collected sample is then analyzed using a liquid scintillation counter. Given the tritium concentration, process flow rate, and time period for which the sample is obtained, the tritium activity released to the environment can be determined. Due to the frequency of sampling, it is assumed that the tritium is released to the environment at a constant rate within the time period for which the sample is obtained.

Plant: River Bend Nuclear Station Year: 2019 Page 7 of 70 Annual Radioactive Effluent Release Report

d.

Carbon-14 The bounding annual dose from C-14 was calculated using guidance from Regulatory Guide 1.21, Revision 2, NUREG-0016, and the methodology in Regulatory Guide 1.109. The results of this calculation are listed in Table 13. The C-14 source term of 11 curies was taken from the site calculation PR(C)-359-3A, Gaseous Releases per NUREG-0016 Revision

1. Carbon-14 does not have dose factors associated with standing on contaminated ground; therefore, no ground plane dose was calculated.

There is no milk pathway within five miles of River Bend Station so this pathway is not evaluated. RBS does not take credit for decay in the X/Q.

This calculation assumes the inhalation, meat and vegetation pathways are at the site boundary in the sector with the highest X/Q. The dose from liquid effluents is not calculated as the dose contribution from C-14 is considered to be insignificant as indicated in Regulatory Guide 1.21, Revision 2. According to EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, 95% of the carbon released is in the form of carbon dioxide and this contributes the highest dose to man.

The ingestion pathway, specifically vegetation, is the most likely route of intake for man. An assumption has been made for gaseous releases that plants obtain all of their C-14 from carbon dioxide.

e.

Nickel-63 No Nickel-63 was quantified in 2019.

f.

Gaseous Effluent Summary Information Gaseous effluent summary information is located in Table 1, Table 2, and Table 3. It should be noted that an entry of 0.00E+00 Curie (Ci) or microcurie/second (uCi/sec) in this section indicates that the concentration of the particular radionuclide was below the Lower Limit of Detection (LLD) as listed in Table 4. Also, any nuclide not appearing in the tables was < LLD for all four quarters.

2.

Liquid Effluents

a.

Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 8. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed using a high purity germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined using a liquid scintillation counter. Strontium-89 and Strontium-90 are quantitatively analyzed by scintillation techniques (Cherenkov counting). Iron-55 is counted with a liquid scintillation counter after digestion of the iron. Gross alpha analysis is performed using a zinc sulfide scintillation counter. The activity of each nuclide released to the environment is determined from the nuclide specific concentration and total tank volume released.

Plant: River Bend Nuclear Station Year: 2019 Page 8 of 70 Annual Radioactive Effluent Release Report

b.

Liquid effluent summation information is located in Table 5 and Table 6.

It should be noted that an entry of 0.00E+00 Ci or uCi/ml in this section indicates that the concentration of the particular radionuclide was below the Lower Limit of Detection (LLD) as listed in Table 8. Also, any nuclide not appearing in the tables was < LLD for all four quarters.

3.

Estimate of Total Error

a.

Liquid The maximum error associated with sample collection, laboratory analysis, and discharge volume is collectively estimated to be:

Fission and Activation Products

+ 14.2%

Tritium

+ 14.2%

Dissolved and Entrained Noble Gases

+ 14.2%

Gross Alpha Radioactivity

+ 14.2%

b.

Gaseous The maximum error (not including sample line loss) associated with sample flow, process flow, sample collection, monitor accuracy and laboratory analysis are collectively estimated to be:

Noble Gases

+ 37.0%

Iodines

+ 18.6%

Particulate

+ 18.6%

Tritium

+ 18.2%

c.

Determination of Total Error The total error (i.e., collective error due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.) is calculated using the following equation:

= [(1)2 + (2)2+... ()2]

Where:

ET = total error E1... En = individual errors due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.

Plant: River Bend Nuclear Station Year: 2019 Page 9 of 70 Annual Radioactive Effluent Release Report 2.4 Batch Releases:

2.4.1 Liquid Batch releases and receiving stream flow from River Bend Station during the reporting period of January 1, 2019, through December 31, 2019 are shown in Table 7.

The Mississippi River stream flow is obtained by averaging data from the U. S. Army Corp of Engineers website using flow gauge data at Tarbert Landing.

2.4.2 Gaseous There were no routine batch releases of gaseous effluents from River Bend Station during the reporting period of January 1, 2019, through December 31, 2019.

2.5 Abnormal Releases There were no abnormal releases in 2019.

2.6 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems Engineering performed a review of the Asset Suite database to evaluate non-administrative design changes completed or partially completed during 2019 involving the subject systems (i.e. changes classified as evaluations or nuclear changes).

These design changes were then reviewed to determine if there have been any major changes to the subject systems. The review was based on a major change being defined as a modification which affected the method of processing or the effluent from the system. Also, to be a major change the change must have affected the Updated Safety Analysis Report (USAR).

The Engineering Changes (ECs) to liquid, solid or gaseous radwaste systems implemented during this time period were:

EC-53367 - Liquid Radwaste Piping Replacement River Bend Station (RBS) Condition Report CR-RBS-2000-2033 identified leakage on 2 diameter Liquid Waste System (LWS) discharge line LWS-002-615-4, leading to elevated levels of radioactive material in the soil adjacent to the buried portion of piping. This line functions in parallel with a 3 diameter Service Water Piping (SWP) line, SWP-003-1043-4. Line SWP-003-1043-4 was dedicated to the LWS by M86-0156 in order to increase the discharge capacity to the Circulating Water System (CWS).

Plant: River Bend Nuclear Station Year: 2019 Page 10 of 70 Annual Radioactive Effluent Release Report This EC removes a portion of discharge line LWS-002-615-4, and all of lines LWS-003-1000-4 and LWS-002-640-4 from 2 valve LWS-AOV257 to the CWS blowdown pit. The segment of line SWP-003-1043-4 routed inside the plant is also removed by this modification. Line LWS-002-640-4 and the buried segment of SWP-003-1043-4 are retired-in-place by filling the lines with a flowable grout and installing blind flanges on the ends. The existing lines are replaced by approximately 100 feet of 2 diameter piping and approximately 1000 feet of 4 diameter piping. The new LWS piping utilizes the existing LWS/SWP pipe routing and existing pipe supports, where possible, for the portion of piping inside the piping tunnels.

A new engineered trench configuration is installed for the exterior portion of piping in the site yard, from the Turbine Building (TB) to the CWS blowdown pit. Stainless steel pipe is used for the in-plant piping and heat fusion joined High Density Polyethylene (HDPE) pipe is used for the exterior piping that is routed inside the concrete trench. Flanges are installed at the stainless steel/HDPE piping interface. Inside the CWS blowdown pit, the new 4 diameter LWS line connects to line CWS-020-35-4 via new 4 diameter CWS valve and line. The new 4 diameter CWS valve and line is installed by performing a hot tap on line CWS-020-35-4.

Two (2) new, 6 diameter wall penetrations are installed to route the 4 diameter HDPE piping. The first new penetration is installed at El. 93 on the south wall of the Turbine Building, near existing penetrations for lines LWS-002-615-4 and SWP-003-1043-4. The second penetration is installed at El. 90.67 on the west wall of the CWS Blowdown Pit, approximately 27-9 from the south edge.

There is no impact to the method of liquid waste processing or system effluent as a result of this change.

EC-79510 -REPLACEMENT OF RECORDER WTW-FR117 WITH YOKOGAWA DX364 Administrative engineering change EC 79150 has been created to incorporate configuration management document updates for the replacement of recorder WTW-FR117. This replacement was evaluated under EC 6225 and Engineering Standard EN-IC-S-004-R Revision 7 which addressed the differences between the upgraded Yokogawa DX364 digital recorder and the previous Bailey 771 series recorders located in the River Bend Station (RBS) Auxiliary Control Room. The affected configuration management documents are listed in section 2.0 of this engineering change, which includes updates to Asset Suite for the equipment/component database information.

As stated in the evaluation for EC 6225, the power consumption and heat produced will be less for some recorders but higher for others when the individual recorders are replaced. The overall changes to the power consumption and heat loads in the Auxiliary Control Room show a net decrease after all recorders are replaced.

There is no impact to the method of liquid waste processing or system effluent as a result of this change.

Plant: River Bend Nuclear Station Year: 2019 Page 11 of 70 Annual Radioactive Effluent Release Report No EC was identified as being completed during this time period that modified any radioactive waste system major component such that the processing method or effluent was changed. Also no changes were identified affecting the method of processing solid, liquid or gaseous waste or the isotopic composition or the quantity of liquid, solid, or gaseous waste as described in the USAR.

In conclusion, no design changes were completed during the specified time period that constituted a major change to either the liquid, solid or gaseous radwaste treatment systems.

2.7 Land Use Census Changes A Land Use Census was not conducted in 2019. The Land Use Census is performed every two years in accordance with procedure EN-CY-127, as required by the Technical Requirements Manual (TRM) (TR 3.12.2). The results of the Land Use Census are included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

2.8 Effluent Monitor Instrument Inoperability 2.8.1 Radioactive Liquid Effluent Monitoring Instrumentation Operability The minimum number of channels required to be OPERABLE as described in Table 3.3.11.2-1 of Technical Requirement 3.3.11.2 were, if inoperable at any time in the period January 1, 2019, through December 31, 2019, restored to operable status within the required time.

2.8.2 Radioactive Gaseous Effluent Monitoring Instrumentation Operability The minimum number of channels required to be OPERABLE as described in Table 3.3.11.3-1 of Technical Requirement 3.3.11.3 were, if inoperable at any time in the period January 1, 2019, through December 31, 2019, restored to operable status within the required time.

Plant: River Bend Nuclear Station Year: 2019 Page 12 of 70 Annual Radioactive Effluent Release Report 2.9 Offsite Dose Calculation Manual Changes There were no changes to the Offsite Dose Calculation Manual in 2019.

2.10 Radiological Environmental Monitoring Program Changes There were no changes to the Radiological Environmental Monitoring Program during the reporting period January 1, 2019, through December 31, 2019. Process Control Program (PCP) Changes There were no changes to the Process Control Program (PCP) in 2019.NON-REMP Groundwater Monitoring Results (NEI 07-07)

Ground water samples were taken in support of the Groundwater Protection Initiative (GPI). These samples are not part of the Radiological Environmental Monitoring Program. The sample results for 2019 are located in Table 17, Table 18, and Table 19.

River Bend Station made no NEI 07-07 voluntary notifications in 2019.

2.11 Outside Tanks The maximum quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any unprotected outdoor tank during the period of January 1, 2019, through December 31, 2019 was less than or equal to the 10 curie limit as required by Technical Specification 5.5.8.b.

Plant: River Bend Nuclear Station Year: 2019 Page 13 of 70 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS 3.1 Gas Effluent and Waste Disposal Report Table 1, Gaseous Effluents-Summation of All Releases A.

Fission & Activation Gases Unit Quarter 1

Quarter 2

Quarter 3

Quarter 4

Annual

1.

Total Release Ci 1.28E+02 6.40E+01 1.83E+01 4.94E+01 2.60E+02

2.

Average release rate for the period Ci/sec 1.65E+01 8.14E+00 2.30E+00 6.21E+00 8.25E+00 B.

Iodine

1.

Total Iodine - 131 Ci 6.80E-02 1.13E-02 3.65E-02 4.47E-02 1.61E-01

2.

Average release rate for the period Ci/sec 8.74E-03 1.44E-03 4.60E-03 5.62E-03 5.09E-03 C.

Particulates

1.

Particulates with half-lives > 8 days Ci 1.11E-03 2.11E-04 2.80E-04 6.29E-04 2.23E-03

2.

Average release rate for the period Ci/sec 1.43E-04 2.69E-05 3.52E-05 7.91E-05 7.08E-05 D.

Tritium

1.

Total Release Ci 7.57E+00 5.77E+00 4.42E+00 4.36E+00 2.21E+01

2.

Average release rate for the period Ci/sec 9.74E-01 7.34E-01 5.56E-01 5.48E-01 7.01E-01 E.

Gross Alpha

1.

Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2.

Average release rate for the period Ci/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F.

Carbon-14

1.

Total Release Ci 2.71E+00 2.74E+00 2.77E+00 2.77E+00 1.1E+01

2.

Average release rate for the period Ci/sec 3.49E-01 3.48E-01 3.48E-01 3.48E-01 3.49E-01

% of limit is located in the Radiological Impact to Man Table

Plant: River Bend Nuclear Station Year: 2019 Page 14 of 70 Annual Radioactive Effluent Release Report Table 2, Gaseous Effluents - Ground Level Release - Continuous Mode Radionuclide Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Xe-131m Ci 2.14E+00 0.00E+00 0.00E+00 0.00E+00 2.14E+00 Xe-133m Ci 0.00E+00 3.67E-01 0.00E+00 0.00E+00 3.67E-01 Xe-133 Ci 0.00E+00 1.99E+01 0.00E+00 0.00E+00 1.99E+01 Xe-135m Ci 1.91E+01 1.25E+00 4.42E+00 4.60E+00 2.94E+01 Xe-135 Ci 1.81E+01 7.160E-01 3.13E+00 2.63E+00 2.45E+01 Total For Period Ci 3.93E+01 2.22E+01 7.55E+00 7.23E+00 7.63E+01 lodines I-131 Ci 4.97E-04 1.18E-04 7.04E-05 7.97E-05 7.65E-04 I-133 Ci 7.11E-04 3.60E-05 1.15E-04 8.57E-05 9.48E-04 Total for Period Ci 1.21E-03 1.54E-04 1.85E-04 1.65E-04 1.71E-03 Particulates Co-60 Ci 1.64E-06 6.32E-06 4.61E-06 2.69E-06 1.53E-05 Total for Period Ci 1.64E-06 6.32E-06 4.61E-06 2.69E-06 1.53E-05 Tritium H-3 Ci 3.13E+00 4.20E+00 3.18E+00 1.54E+00 1.20E+01

Plant: River Bend Nuclear Station Year: 2019 Page 15 of 70 Annual Radioactive Effluent Release Report Table 3, Gaseous Effluents - Mixed Mode Release - Continuous Mode Radionuclide Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Kr-85m Ci 9.24E-01 6.28E-01 5.63E-02 4.41E-01 2.05E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 1.49E-02 1.49E-02 Kr-87 Ci 0.00E+00 1.68E+00 0.00E+00 0.00E+00 1.68E+00 Kr-88 Ci 0.00E+00 1.81E+00 0.00E+00 4.90E-02 1.85E+00 Xe-131m Ci 0.00E+00 0.00E+00 5.12E+00 0.00E+00 5.12E+00 Xe-133 Ci 1.65E+01 1.99E+00 1.33E-01 7.59E+00 2.62E+01 Xe-135m Ci 2.04E+01 5.97E+00 2.92E+00 1.66E+01 4.59E+01 Xe-135 Ci 4.90E+01 7.78E+00 2.50E+00 1.48E+01 7.41E+01 Xe-137 Ci 0.00E+00 2.37E+00 0.00E+00 0.00E+00 2.37E+00 Xe-138 Ci 2.32E+00 1.96E+01 1.59E-02 2.66E+00 2.45E+01 Total for Period Ci 8.91E+01 4.18E+01 1.08E+01 4.22E+01 1.84E+02 lodines I-131 Ci 8.78E-03 2.14E-03 3.27E-03 4.16E-03 1.84E-02 I-133 Ci 5.80E-02 9.04E-03 3.31E-02 4.03E-02 1.41E-01 Total for Period Ci 6.68E-02 1.12E-02 3.64E-02 4.45E-02 1.59E-01 Particulates Fe-59 Ci 4.25E-06 0.00E+00 0.00E+00 0.00E+00 4.25E-06 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 1.26E-05 1.26E-05 Co-60 Ci 0.00E+00 1.05E-05 0.00E+00 5.11E-05 6.16E-05 Ni-63 Ci 1.24E-04 0.00E+00 0.00E+00 0.00E+00 1.24E-04 Zn-65 Ci 0.00E+00 0.00E+00 0.00E+00 6.79E-06 6.79E-06 Sr-89 Ci 5.50E-04 8.63E-05 9.72E-05 2.21E-04 9.54E-04 Sr-90 Ci 1.48E-06 0.00E+00 0.00E+00 0.00E+00 1.48E-06 Nb-95 Ci 0.00E+00 1.39E-06 0.00E+00 1.18E-06 2.57E-06 Ag-110m Ci 1.40E-05 1.52E-05 6.84E-06 4.96E-06 4.10E-05 Cs-136 Ci 0.00E+00 0.00E+00 0.00E+00 1.08E-05 1.08E-05 Ba-140 Ci 4.13E-04 9.15E-05 1.68E-04 3.12E-04 9.84E-04 Ce-141 Ci 6.18E-06 0.00E+00 2.83E-06 6.36E-06 1.54E-05 Total for Period Ci 1.11E-03 2.05E-04 2.75E-04 6.26E-04 2.22E-03 Tritium H-3 Ci 4.44E+00 1.57E+00 1.24E+00 2.82E+00 1.01E+01

Plant: River Bend Nuclear Station Year: 2019 Page 16 of 70 Annual Radioactive Effluent Release Report Table 4, Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Type Sampling Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit of Detection (LLD) uC/ml Main Plant Exhaust Duct M

Grab Sample M

Principle Gamma Emitters 1.00E-04 H-3 1.00E-06 Fuel Building Ventilation Exhaust Duct M

Grab Sample M

Principle Gamma Emitters 1.00E-04 H-3 1.00E-06 Radwaste Building Ventilation Exhaust Duct M

Grab Sample M

Principle Gamma Emitters 1.00E-04 H-3 1.00E-06 All Release Types as listed above Continuous W

Charcoal Sample I-131 1.00E-12 I-133 1.00E-10 Continuous W

Particulate Sample Principle Gamma Emitters (I-131, Others) 1.00E-11 Continuous M

Composite Particulate Sample Gross Alpha 1.00E-11 Continuous Q

Composite Particulate Sample Sr-89, Sr-90 1.00E-11 Continuous Noble Gas Monitor Noble Gases Gross Beta or Gamma 1.00E-6 W = At least once per 7 days M = At least once per 31 days Q = At least once per 92 days

Plant: River Bend Nuclear Station Year: 2019 Page 17 of 70 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS 4.1 Liquid Effluent and Waste Disposal Report Table 5, Liquid Effluents-Summation of All Releases A.

Fission & Activation Products Unit Quarter 1

Quarter 2

Quarter 3

Quarter 4

Annual

1.

Total Release (not including tritium, gases or alpha)

Ci 3.75E-03 6.96E-03 2.52E-03 1.90E-03 1.51E-02 2

Average diluted concentration during period Ci/mL 1.73E-06 1.41E-06 4.97E-07 5.78E-07 9.79E-07 B.

Tritium

1.

Total Release Ci 1.11E+01 1.73E+01 1.57E+01 1.26E+01 5.67E+01

2.

Average diluted concentration during period.

Ci/mL 5.13E-03 3.51E-03 3.09E-03 3.84E-03 3.67E-03 C.

Dissolved & Entrained Gases

1.

Total Release Ci 1.02E-01 2.28E-02 8.74E-02 5.68E-02 2.69E-01

2.

Average diluted concentration during period Ci/mL 4.72E-05 4.62E-06 1.73E-05 1.72E-05 1.74E-05 D.

Gross Alpha Activity

1.

Total Release Ci 0.0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E.

Volume Of Waste Released (prior to dilution)

Liters 2.17E+06 4.94E+06 5.06E+06 3.29E+06 1.55E+07 F.

Volume Of Dilution Water Used During Period Liters 1.36E+09 1.13E+09 1.36E+09 1.38E+09 5.23E+09

% of limit is located in the Radiological Impact to Man Table

Plant: River Bend Nuclear Station Year: 2019 Page 18 of 70 Annual Radioactive Effluent Release Report Table 6, Liquid Effluents - Batch Release Radionuclide Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission and Activation Products Cr-51 Ci 0.00E+00 1.30E-05 7.52E-06 0.00E+00 2.05E-05 Mn-54 Ci 5.57E-05 2.24E-04 8.41E-05 4.47E-05 4.09E-04 Co-58 Ci 2.15E-06 2.12E-05 0.00E+00 3.93E-06 2.73E-05 Co-60 Ci 2.88E-03 6.20E-03 2.09E-03 1.47E-03 1.27E-02 Ni-65 Ci 0.00E+00 5.70E-06 0.00E+00 0.00E+00 5.70E-06 Zn-65 Ci 8.05E-05 9.03E-05 7.11E-06 0.00E+00 1.78E-04 Y-92 Ci 1.37E-05 0.00E+00 0.00E+00 0.00E+00 1.37E-05 Zr-95 Ci 1.88E-06 1.02E-05 0.00E+00 0.00E+00 1.21E-05 Nb-95 Ci 2.54E-06 1.92E-05 2.11E-06 0.00E+00 2.39E-05 Nb-97 Ci 0.00E+00 3.14E-06 0.00E+00 0.00E+00 3.14E-06 Mo-99 Ci 0.00E+00 1.62E-05 0.00E+00 0.00E+00 1.62E-05 Tc-99m Ci 0.00E+00 0.00E+00 0.00E+00 6.76E-06 6.76E-06 Ru-103 Ci 0.00E+00 2.80E-06 0.00E+00 6.83E-07 3.48E-06 Ru-105 Ci 0.00E+00 4.42E-06 0.00E+00 0.00E+00 4.42E-06 Ag-110m Ci 0.00E+00 4.20E-06 0.00E+00 0.00E+00 4.20E-06 Rh-105 Ci 0.00E+00 6.79E-06 0.00E+00 0.00E+00 6.79E-06 Sb-124 Ci 0.00E+00 1.76E-05 0.00E+00 0.00E+00 1.76E-05 Sb-125 Ci 0.00E+00 7.73E-06 0.00E+00 0.00E+00 7.73E-06 Sb-126 Ci 0.00E+00 2.08E-06 0.00E+00 1.26E-06 3.34E-06 I-131 Ci 3.66E-05 1.81E-06 4.93E-06 0.00E+00 4.34E-05 I-133 Ci 2.26E-06 1.21E-06 0.00E+00 0.00E+00 3.47E-06 Cs-134 Ci 4.82E-05 7.99E-05 1.37E-05 6.35E-06 1.48E-04 Cs-137 Ci 3.97E-05 5.40E-05 1.12E-05 2.82E-06 1.08E-04 Ba-142 Ci 4.08E-04 0.00E+00 2.07E-04 3.50E-04 9.65E-04 La-140 Ci 1.08E-04 1.55E-05 7.30E-05 1.49E-05 2.11E-04 Ce-141 Ci 1.15E-05 7.12E-05 0.00E+00 0.00E+00 8.28E-05 Ce-144 Ci 5.75E-05 8.82E-05 0.00E+00 0.00E+00 1.46E-04 W-187 Ci 0.00E+00 0.00E+00 5.03E-06 0.00E+00 5.03E-06 Np-239 Ci 0.00E+00 0.00E+00 9.07E-06 0.00E+00 9.07E-06 Total for Period Ci 3.75E-03 6.96E-03 2.52E-03 1.90E-03 1.51E-02 Tritium H-3 Ci 1.11E+01 1.73E+01 1.57E+01 1.26E+01 5.67E+01 Total for Period Ci 1.11E+01 1.73E+01 1.57E+01 1.26E+01 5.67E+01

Plant: River Bend Nuclear Station Year: 2019 Page 19 of 70 Annual Radioactive Effluent Release Report Table 6, Liquid Effluents - Batch Release Radionuclide Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Dissolved and Entrained Gases Kr-88 Ci 1.46E-05 0.00E+00 9.00E-05 5.72E-05 1.62E-04 Xe-131m Ci 1.01E-03 5.17E-04 0.00E+00 0.00E+00 1.52E-03 Xe-133m Ci 2.62E-03 2.45E-04 1.13E-03 5.36E-04 4.53E-03 Xe-133 Ci 5.62E-02 1.45E-02 3.73E-02 2.13E-02 1.29E-01 Xe-135 Ci 4.24E-02 7.49E-03 4.90E-02 3.49E-02 1.34E-01 Total for Period Ci 1.02E-01 2.28E-02 8.74E-02 5.68E-02 2.69E-01

Plant: River Bend Nuclear Station Year: 2019 Page 20 of 70 Annual Radioactive Effluent Release Report Table 7, Supplemental Information for Liquid Effluents - Batch Mode Report for 2019 Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Number of releases 28 66 81 53 228 Total Release Time minutes 1.09E+04 2.49E+04 2.63E+04 1.72E+04 7.93E+04 Maximum Release Time minutes 1.42E+03 1.44E+03 7.41E+02 7.03E+02 1.44E+03 Average Release Time minutes 3.89E+02 3.77E+02 3.25E+02 3.25E+02 3.48E+02 Minimum Release Time minutes 2.00E+02 1.10E+02 2.61E+02 2.53E+02 1.10E+02 Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Average Mississippi River stream flow during periods of release into a flowing stream ft3/sec 1,171,102 1,216,977 716,761 573,554

Plant: River Bend Nuclear Station Year: 2019 Page 21 of 70 Annual Radioactive Effluent Release Report Table 8, Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Type Sampling Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit of Detection (LLD) uC/ml Batch Waste Release (Liquid Radwaste Recovery Sample Tanks)

P Each Batch P

Each Batch Principle Gamma Emitters; except Ce-144 5.00E-07 5.00E-06 I-131 1.00E-06 P

Each Batch / M M

Dissolved and Entrained Gases (Gamma Emitters) 1.00E-05 P

Each Batch M

Composite H-3 1.00E-05 Gross Alpha 1.00E-07 P

Each Batch Q

Composite Sr-89, Sr-90 5.00E-8 Fe-55 1.00E-06 P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days

Plant: River Bend Nuclear Station Year: 2019 Page 22 of 70 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE

SUMMARY

5.1 Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel) 5.1.1 Types of Waste Table 9, Types of Solid Waste Summary Types of Waste Total Quantity (m3 )

Total Activity (Ci)

Est. Total Error (%)

a. Spent resins, filter sludges, evaporator bottoms, etc.

9.11E+01 7.87E+01 25

b. Dry compressible waste, contaminated equip, etc.

1.82E+03 1.04E+01 25

c. Irradiated components, control rods, etc.

0.00E+00 0.00E+00 25

d. Other (Water, EHC, Waste Oil, etc.)

6.51E+01 4.00E-02 25 5.1.2 Estimate of major nuclide composition (by waste type) only >1% [Note 1] are reported.

Table 10, Major Nuclides Major Nuclide Composition Isotope Curies

a. Resins, filters, evaporator bottoms, etc.

C-14 8.69 6.84E+00 Mn-54 2.19 1.72E+00 Fe-55 20.24 1.59E+01 Co-60 46.11 3.63E+01 Ni-63 2.13 1.67E+00 Zn-65 3.04 2.39E+00 Sr-90 1.15 9.07E-01 Cs-134 6.54 5.15E+00 Cs-137 7.78 6.12E+00

b. Dry compressible waste, contaminated equip, etc.

Mn-54 1.65 1.72E-01 Fe-55 42.8 4.47E+00 Co-60 52.22 5.45E+00 Ni-63 1.91 2.00E-01

c. Irradiated components, control rods, etc.

N/A N/A N/A

Plant: River Bend Nuclear Station Year: 2019 Page 23 of 70 Annual Radioactive Effluent Release Report Table 10, Major Nuclides Major Nuclide Composition Isotope Curies

d. Other (Water, EHC, Waste Oil, Etc.)

Mn-54 1.88 7.51E-04 Fe-55 43.22 1.73E-02 Co-60 51.91 2.05E-02 Ni-63 1.82 7.27E-04

[Note 1] - Major" radionuclide is equivalent to a principle radionuclide, i.e. greater than 1 percent of total activity.

5.1.3 Solid Waste Disposition Table 11, Solid Waste Disposition (Specify Site or Unit)

Number of Shipments Mode of Transportation Destination 8

Truck Energy Solutions, LLC (Gallaher) - Oak Ridge, TN 3

Truck Energy Solutions (Memphis) - Memphis, TN 51 Truck Energy Solutions (Bear Creek) - Oak Ridge, TN 2

Truck Energy Solutions (Erwin ResinSolution) - Erwin, TN Table 12, Irradiated Fuel Shipments Disposition No Irradiated Fuel Shipments for 2019 Number of Shipments Mode of Transportation Destination N/A N/A N/A

Plant: River Bend Nuclear Station Year: 2019 Page 24 of 70 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN 6.1 10CFR Part50, Appendix I Evaluation Table 13, Dose Assessment Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, Total Body 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem Total Body Dose 6.02E-05 2.71E-04 5.73E-05 1.89E-05 3.69E-04

% of Limit 4.01E-03 1.81E-02 3.82E-03 1.26E-03 1.23E-02 Liquid Effluent Dose Limit, Any Organ 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Maximum Organ Dose 9.45E-05 7.45E-04 2.23E-04 7.79E-05 9.63E-04

% of Limit 1.89E-03 1.49E-02 4.47E-03 1.56E-03 9.63E-03 Gaseous Effluent Dose Limit, Gamma Air 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Gamma Air Dose 1.53E-01 4.40E-02 2.95E-02 3.92E-02 2.65E-01

% of Limit 3.05E+00 8.80E-01 5.90E-01 7.80E-01 2.65E+00 Gaseous Effluent Dose Limit, Beta Air 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Beta Air Dose 9.87E-02 5.03E-02 1.62E-02 2.06E-02 1.86E-01

% of Limit 9.90E-01 5.00E-01 1.60E-01 2.10E-01 9.30E-01 Gaseous Effluent Organ Dose Limit (Iodine, Tritium, Particulates with >

8 day half-life) 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Gaseous Effluent Organ Dose (Iodine, Tritium, Particulates with > 8 day half-life) 4.06E-01 1.11e-01 1.58e-01 1.87e-01 8.62e-01

% of Limit 5.41E+00 1.48E+00 2.11E+00 2.49E+00 5.74E+00

Plant: River Bend Nuclear Station Year: 2019 Page 25 of 70 Annual Radioactive Effluent Release Report Table 13, Dose Assessment (continued)

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gaseous Effluent Organ Dose Limit (Carbon Bounding Calculation) 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Gaseous Effluent Organ Dose (Carbon Bounding Calculation) 1.16E+00 1.17E+00 1.18E+00 1.18E+00 4.70E+00

% of Limit 1.55E+01 1.56E+01 1.58E+01 1.58E+01 3.13E+01 6.2 Dose to Members of the Public Inside the Site Boundary The maximally exposed member of the pubic was calculated to be member of the West Feliciana Parish Sheriff's Office (WFPSO) that opened a substation in a facility within the site boundary beginning in 2019. The office is estimated to be occupied during normal work hours for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year. It should be noted that the liquid effluent pathway dose was not considered since the individual would not engage in activities that would allow exposure to this pathway.

Location Annual Critical Organ Dose (mrem)

Annual Total Body Dose (mrem)

Annual Skin Dose (mrem)

Annual Duration Factor Alligator Bayou 6.18E-05 1.08E-04 1.86E-04 4.57E-03 Deer Hunters 2.72E-03 4.04E-03 6.97E-03 2.92E-02 Onsite RV Park 5.66E-03 8.40E-03 1.45E-02 6.08E-02 WFPSO Building 2.12E-02 3.15E-02 5.45E-02 2.28E-01

Plant: River Bend Nuclear Station Year: 2019 Page 26 of 70 Annual Radioactive Effluent Release Report 6.3 40CFR Part 190 Evaluation for an Individual in the Unrestricted Area An assessment (see Table 14) was made of radiation doses to the likely most-exposed member of the public from River Bend and other nearby uranium fuel cycle sources (none within five miles). The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

Table 14, EPA 40 CFR PART 190 Evaluation Total Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Dose 9.44E-01 1.74E+00 5.23E+00

% of Limit 3.77E+00 2.32E+00 2.09E+01 Liquid dose, gaseous dose including a bounding calculation of C-14 dose, direct shine, ISFSI and any other nuclear power related facility within 5 miles of the station are considered when calculating dose compliance with 40 CFR 190.

Plant: River Bend Nuclear Station Year: 2019 Page 27 of 70 Annual Radioactive Effluent Release Report 7.0 METEORLOGICAL DATA Cumulative joint frequency distributions and annual average data for continuous releases are listed below. The meteorological recovery for 2019 was 97.91%.

7.1 Joint Frequency Distributions All Stability Classes Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

117 66 106 117 99 179 100 0

0 0

784 NNE 108 52 77 141 119 99 22 0

0 0

618 NE 86 55 78 148 146 100 12 0

0 0

625 ENE 97 82 64 107 67 72 6

0 0

0 495 E

73 79 78 74 46 10 0

0 0

0 360 ESE 25 52 93 117 76 37 3

0 0

0 403 SE 25 65 112 260 188 163 34 3

0 0

850 SSE 12 38 71 182 203 343 163 12 0

0 1024 S

9 22 40 111 131 229 78 0

0 0

620 SSW 13 23 26 46 67 85 44 0

0 0

304 SW 14 25 24 35 51 41 8

0 0

0 198 WSW 13 33 27 58 63 51 4

0 0

0 249 W

39 67 26 55 66 100 14 0

0 0

367 WNW 68 97 47 56 76 64 34 0

0 0

442 NW 126 103 44 58 52 101 52 4

0 0

540 NNW 131 57 60 96 72 85 82 0

0 0

583 Total 956 916 973 1661 1522 1759 656 19 0

0 8462 Number of Calms: 115 Number of Invalid Hours: 183 Number of Valid Hours: 8577 Total Hours for the Period: 8760

Plant: River Bend Nuclear Station Year: 2019 Page 28 of 70 Annual Radioactive Effluent Release Report Stability Class A Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

1 0

1 6

16 42 24 0

0 0

90 NNE 0

1 1

4 26 25 10 0

0 0

67 NE 0

0 1

8 29 32 6

0 0

0 76 ENE 0

0 0

7 19 17 1

0 0

0 44 E

0 1

1 12 21 5

0 0

0 0

40 ESE 0

0 1

10 17 15 0

0 0

0 43 SE 0

0 0

5 34 53 4

0 0

0 96 SSE 0

0 1

6 15 51 33 1

0 0

107 S

0 0

0 2

16 73 30 0

0 0

121 SSW 0

0 0

5 18 27 6

0 0

0 56 SW 0

0 0

6 21 17 3

0 0

0 47 WSW 0

0 0

11 34 35 2

0 0

0 82 W

0 0

2 9

36 72 11 0

0 0

130 WNW 0

1 0

6 34 29 12 0

0 0

82 NW 0

0 0

7 20 38 12 0

0 0

77 NNW 1

0 0

9 20 25 30 0

0 0

85 Total 2

3 8

113 376 556 184 1

0 0

1243 Number of Calms: 0 Number of Invalid Hours: 0 Number of Valid Hours: 1243 Total Hours for the Period: 1243

Plant: River Bend Nuclear Station Year: 2019 Page 29 of 70 Annual Radioactive Effluent Release Report Stability Class B Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

0 0

1 2

1 9

8 0

0 0

21 NNE 0

0 0

1 5

4 0

0 0

0 10 NE 0

0 0

4 9

7 0

0 0

0 20 ENE 0

0 0

4 3

5 0

0 0

0 12 E

0 0

0 3

0 0

0 0

0 0

3 ESE 0

0 0

6 6

1 0

0 0

0 13 SE 0

0 0

3 9

9 0

0 0

0 21 SSE 0

0 0

7 10 17 18 0

0 0

52 S

0 0

0 1

2 21 11 0

0 0

35 SSW 0

0 0

3 2

7 6

0 0

0 18 SW 0

0 0

1 6

4 0

0 0

0 11 WSW 0

0 0

3 4

1 0

0 0

0 8

W 0

0 1

1 4

10 0

0 0

0 16 WNW 0

0 0

2 7

4 1

0 0

0 14 NW 0

0 1

1 6

4 0

0 0

0 12 NNW 0

0 0

0 4

9 2

0 0

0 15 Total 0

0 3

42 78 112 46 0

0 0

281 NUMBER OF CALMS: 1 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 282 TOTAL HOURS FOR THE PERIOD: 282

Plant: River Bend Nuclear Station Year: 2019 Page 30 of 70 Annual Radioactive Effluent Release Report Stability Class C Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

0 0

0 1

8 18 10 0

0 0

37 NNE 0

0 0

5 8

14 2

0 0

0 29 NE 0

0 2

7 14 15 1

0 0

0 39 ENE 0

0 1

11 5

11 1

0 0

0 29 E

0 0

3 7

2 1

0 0

0 0

13 ESE 0

0 2

11 4

1 0

0 0

0 18 SE 1

0 2

11 18 16 4

0 0

0 52 SSE 0

0 2

8 12 44 31 2

0 0

99 S

0 0

0 7

21 40 4

0 0

0 72 SSW 0

0 0

2 7

15 5

0 0

0 29 SW 0

0 0

2 8

4 1

0 0

0 15 WSW 0

0 0

7 7

6 1

0 0

0 21 W

0 0

1 11 16 8

1 0

0 0

37 WNW 0

0 1

7 4

7 5

0 0

0 24 NW 0

0 0

9 7

9 3

0 0

0 28 NNW 0

0 2

6 10 11 6

0 0

0 35 Total 1

0 16 112 151 220 75 2

0 0

577 NUMBER OF CALMS: 0 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 577 TOTAL HOURS FOR THE PERIOD: 577

Plant: River Bend Nuclear Station Year: 2019 Page 31 of 70 Annual Radioactive Effluent Release Report Stability Class D Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

1 1

14 36 43 91 55 0

0 0

241 NNE 0

0 7

46 45 50 10 0

0 0

158 NE 0

4 11 44 43 33 4

0 0

0 139 ENE 0

5 17 34 15 21 2

0 0

0 94 E

1 4

13 25 12 3

0 0

0 0

58 ESE 1

4 22 40 22 10 3

0 0

0 102 SE 0

2 11 56 47 47 20 3

0 0

186 SSE 1

0 5

22 55 144 59 7

0 0

293 S

0 2

1 16 35 75 21 0

0 0

150 SSW 0

0 6

20 29 27 17 0

0 0

99 SW 0

1 5

11 11 12 4

0 0

0 44 WSW 0

1 7

17 16 6

1 0

0 0

48 W

0 3

4 19 7

9 1

0 0

0 43 WNW 1

0 3

13 17 17 15 0

0 0

66 NW 1

1 4

11 9

32 32 4

0 0

94 NNW 1

2 5

14 26 35 39 0

0 0

122 Total 7

30 135 424 432 612 283 14 0

0 1937 NUMBER OF CALMS: 2 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 1939 TOTAL HOURS FOR THE PERIOD: 1939

Plant: River Bend Nuclear Station Year: 2019 Page 32 of 70 Annual Radioactive Effluent Release Report Stability Class E Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

5 10 36 46 31 18 3

0 0

0 149 NNE 6

14 24 65 30 6

0 0

0 0

145 NE 4

22 37 63 47 13 1

0 0

0 187 ENE 4

21 26 36 23 18 2

0 0

0 130 E

6 23 40 24 10 1

0 0

0 0

104 ESE 5

19 47 46 26 9

0 0

0 0

152 SE 8

30 63 167 78 38 5

0 0

0 389 SSE 1

15 33 108 99 86 21 2

0 0

365 S

1 4

15 66 54 20 12 0

0 0

172 SSW 3

9 12 12 11 9

10 0

0 0

66 SW 4

13 12 14 5

4 0

0 0

0 52 WSW 1

9 11 18 2

2 0

0 0

0 43 W

5 10 10 12 3

1 1

0 0

0 42 WNW 7

20 18 23 12 5

1 0

0 0

86 NW 3

7 16 25 9

18 5

0 0

0 83 NNW 6

11 19 53 10 4

4 0

0 0

107 Total 69 237 419 778 450 252 65 2

0 0

2272 NUMBER OF CALMS: 3 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 2275 TOTAL HOURS FOR THE PERIOD: 2275

Plant: River Bend Nuclear Station Year: 2019 Page 33 of 70 Annual Radioactive Effluent Release Report Stability Class F Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

19 28 35 17 0

1 0

0 0

0 100 NNE 23 20 38 16 5

0 0

0 0

0 102 NE 17 10 20 19 4

0 0

0 0

0 70 ENE 21 22 18 15 2

0 0

0 0

0 78 E

20 27 16 2

1 0

0 0

0 0

66 ESE 12 20 18 4

1 1

0 0

0 0

56 SE 8

25 31 17 2

0 1

0 0

0 84 SSE 6

15 29 30 12 1

1 0

0 0

94 S

5 11 20 17 3

0 0

0 0

0 56 SSW 5

11 8

3 0

0 0

0 0

0 27 SW 3

9 6

0 0

0 0

0 0

0 18 WSW 8

20 7

1 0

0 0

0 0

0 36 W

18 28 3

1 0

0 0

0 0

0 50 WNW 17 38 19 4

2 1

0 0

0 0

81 NW 29 25 19 5

1 0

0 0

0 0

79 NNW 20 15 12 11 2

1 1

0 0

0 62 Total 231 324 299 162 35 5

3 0

0 0

1059 NUMBER OF CALMS: 18 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 1077 TOTAL HOURS FOR THE PERIOD: 1077

Plant: River Bend Nuclear Station Year: 2019 Page 34 of 70 Annual Radioactive Effluent Release Report Stability Class G Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

91 27 19 9

0 0

0 0

0 0

146 NNE 79 17 7

4 0

0 0

0 0

0 107 NE 65 19 7

3 0

0 0

0 0

0 94 ENE 72 34 2

0 0

0 0

0 0

0 108 E

46 24 5

1 0

0 0

0 0

0 76 ESE 7

9 3

0 0

0 0

0 0

0 19 SE 8

8 5

1 0

0 0

0 0

0 22 SSE 4

8 1

1 0

0 0

0 0

0 14 S

3 5

4 2

0 0

0 0

0 0

14 SSW 5

3 0

1 0

0 0

0 0

0 9

SW 7

2 1

1 0

0 0

0 0

0 11 WSW 4

3 2

1 0

1 0

0 0

0 11 W

16 26 5

2 0

0 0

0 0

0 49 WNW 43 38 6

1 0

1 0

0 0

0 89 NW 93 70 4

0 0

0 0

0 0

0 167 NNW 103 29 22 3

0 0

0 0

0 0

157 Total 646 322 93 30 0

2 0

0 0

0 1093 NUMBER OF CALMS: 91 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 1184 TOTAL HOURS FOR THE PERIOD: 1184

Plant: River Bend Nuclear Station Year: 2019 Page 35 of 70 Annual Radioactive Effluent Release Report All Stability Classes Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

2 5

10 31 39 219 260 32 0

0 598 NNE 3

3 9

36 76 264 246 20 0

0 657 NE 1

4 11 40 72 202 304 19 1

0 654 ENE 1

3 13 48 77 161 213 39 9

0 564 E

1 3

8 52 94 193 93 9

6 0

459 ESE 1

2 7

30 61 314 479 62 11 2

969 SE 3

1 14 32 46 221 308 39 7

0 671 SSE 0

4 4

40 60 209 346 77 12 0

752 S

0 2

2 44 66 265 301 30 0

0 710 SSW 0

2 5

27 63 165 121 40 0

0 423 SW 1

5 6

27 52 113 45 3

0 0

252 WSW 0

4 6

22 88 148 36 3

0 0

307 W

1 2

8 45 88 200 94 20 2

0 460 WNW 0

3 12 20 61 123 84 18 6

0 327 NW 0

2 4

31 49 123 121 35 2

0 367 NNW 0

2 7

20 51 128 145 52 0

0 405 Total 14 47 126 545 1043 3048 3196 498 56 2

8575 NUMBER OF CALMS: 2 NUMBER OF INVALID HOURS: 183 NUMBER OF VALID HOURS: 8577 TOTAL HOURS FOR THE PERIOD: 8760

Plant: River Bend Nuclear Station Year: 2019 Page 36 of 70 Annual Radioactive Effluent Release Report Stability Class A Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

0 0

1 1

5 19 46 4

0 0

76 NNE 0

0 1

2 9

28 27 8

0 0

75 NE 0

0 0

2 9

31 26 3

0 0

71 ENE 0

0 0

3 5

15 36 7

0 0

66 E

0 0

1 1

10 28 13 3

0 0

56 ESE 0

0 1

2 5

29 44 8

0 0

89 SE 0

0 0

3 4

26 30 2

1 0

66 SSE 0

0 0

2 1

18 41 18 1

0 81 S

0 0

0 3

11 35 62 4

0 0

115 SSW 0

0 0

2 9

17 20 1

0 0

49 SW 0

1 0

4 9

15 14 0

0 0

43 WSW 0

0 0

1 19 53 15 0

0 0

88 W

0 0

1 6

17 79 48 6

0 0

157 WNW 0

0 0

4 6

30 19 8

0 0

67 NW 0

1 0

5 11 20 30 5

0 0

72 NNW 0

0 0

0 10 19 33 10 0

0 72 Total 0

2 5

41 140 462 504 87 2

0 1243 NUMBER OF CALMS: 0 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 1243 TOTAL HOURS FOR THE PERIOD: 1243

Plant: River Bend Nuclear Station Year: 2019 Page 37 of 70 Annual Radioactive Effluent Release Report Stability Class B Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

0 0

0 0

0 6

10 2

0 0

18 NNE 0

0 0

2 1

2 6

0 0

0 11 NE 0

0 0

2 2

9 8

1 0

0 22 ENE 0

0 0

0 2

4 7

0 0

0 13 E

0 0

0 1

1 5

2 0

0 0

9 ESE 0

0 0

0 3

7 13 1

0 0

24 SE 0

0 0

2 3

3 7

1 0

0 16 SSE 0

0 0

2 2

6 14 12 0

0 36 S

0 0

0 2

2 7

23 4

0 0

38 SSW 0

0 0

1 3

4 9

5 0

0 22 SW 0

0 0

1 1

5 2

0 0

0 9

WSW 0

0 0

1 2

4 2

0 0

0 9

W 0

0 0

4 1

9 4

0 0

0 18 WNW 0

0 0

0 3

6 2

0 1

0 12 NW 0

0 0

0 0

5 3

0 0

0 8

NNW 0

0 1

0 3

5 6

2 0

0 17 Total 0

0 1

18 29 87 118 28 1

0 282 NUMBER OF CALMS: 0 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 282 TOTAL HOURS FOR THE PERIOD: 282

Plant: River Bend Nuclear Station Year: 2019 Page 38 of 70 Annual Radioactive Effluent Release Report Stability Class C Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

0 0

0 4

2 11 16 1

0 0

34 NNE 0

0 0

1 2

9 16 1

0 0

29 NE 0

0 1

1 9

14 16 3

0 0

44 ENE 0

0 0

3 5

5 18 4

1 0

36 E

0 1

0 3

3 9

2 0

0 0

18 ESE 0

0 1

3 5

19 17 4

0 0

49 SE 0

0 1

1 4

15 18 8

0 0

47 SSE 0

0 0

1 4

18 34 12 2

0 71 S

0 0

0 1

5 25 34 0

0 0

65 SSW 0

0 0

0 3

9 13 4

0 0

29 SW 0

0 0

0 3

6 3

1 0

0 13 WSW 0

0 0

1 8

12 1

0 0

0 22 W

0 0

0 6

7 21 8

3 1

0 46 WNW 0

1 0

1 8

6 6

1 0

0 23 NW 0

0 0

2 6

5 8

0 0

0 21 NNW 0

0 1

3 5

6 12 3

0 0

30 Total 0

2 4

31 79 190 222 45 4

0 577 NUMBER OF CALMS: 0 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 577 TOTAL HOURS FOR THE PERIOD: 577

Plant: River Bend Nuclear Station Year: 2019 Page 39 of 70 Annual Radioactive Effluent Release Report Stability Class D Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

0 1

2 4

10 63 97 23 0

0 200 NNE 0

0 1

10 26 67 95 10 0

0 209 NE 0

1 2

11 16 41 55 8

1 0

135 ENE 0

0 4

10 18 29 36 10 3

0 110 E

0 1

0 8

6 33 29 2

5 0

84 ESE 0

1 0

5 4

54 72 18 10 2

166 SE 0

0 3

8 9

42 67 20 3

0 152 SSE 0

0 1

6 9

33 127 19 6

0 201 S

0 0

0 4

11 44 87 16 0

0 162 SSW 0

1 0

5 9

35 41 18 0

0 109 SW 0

0 1

6 4

16 14 2

0 0

43 WSW 0

2 0

8 9

10 12 2

0 0

43 W

0 0

2 6

15 15 17 9

1 0

65 WNW 0

0 2

5 6

14 19 6

5 0

57 NW 0

0 1

2 4

17 39 27 2

0 92 NNW 0

1 0

2 6

21 47 33 0

0 110 Total 0

8 19 100 162 534 854 223 36 2

1938 NUMBER OF CALMS: 1 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 1939 TOTAL HOURS FOR THE PERIOD: 1939

Plant: River Bend Nuclear Station Year: 2019 Page 40 of 70 Annual Radioactive Effluent Release Report Stability Class E Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

1 1

5 11 9

54 51 2

0 0

134 NNE 2

0 1

12 14 80 63 1

0 0

173 NE 1

2 4

12 16 59 66 3

0 0

163 ENE 0

3 5

11 22 38 72 13 5

0 169 E

0 1

5 18 40 65 29 3

0 0

161 ESE 0

0 2

12 20 110 217 29 1

0 391 SE 1

0 3

7 8

75 115 7

2 0

218 SSE 0

1 0

9 15 57 111 16 3

0 212 S

0 0

1 12 14 84 85 6

0 0

202 SSW 0

1 0

6 8

33 31 12 0

0 91 SW 0

0 2

2 8

29 11 0

0 0

52 WSW 0

0 3

6 11 16 4

1 0

0 41 W

0 0

2 10 19 20 6

2 0

0 59 WNW 0

1 5

2 11 13 21 3

0 0

56 NW 0

1 2

8 7

29 26 3

0 0

76 NNW 0

1 2

5 9

32 23 4

0 0

76 Total 5

12 42 143 231 794 931 105 11 0

2274 NUMBER OF CALMS: 1 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 2275 TOTAL HOURS FOR THE PERIOD: 2275

Plant: River Bend Nuclear Station Year: 2019 Page 41 of 70 Annual Radioactive Effluent Release Report Stability Class F Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

0 2

1 5

3 27 20 0

0 0

58 NNE 0

1 4

5 13 43 31 0

0 0

97 NE 0

0 2

2 10 21 68 1

0 0

104 ENE 0

0 1

13 15 31 24 5

0 0

89 E

0 0

1 15 18 21 10 1

1 0

67 ESE 0

0 1

2 11 58 86 2

0 0

160 SE 1

0 3

7 7

28 47 1

1 0

95 SSE 0

2 2

11 11 27 8

0 0

0 61 S

0 1

0 11 9

29 9

0 0

0 59 SSW 0

0 0

9 10 27 5

0 0

0 51 SW 1

1 0

5 16 16 0

0 0

0 39 WSW 0

1 2

1 12 17 0

0 0

0 33 W

1 1

2 2

10 25 5

0 0

0 46 WNW 0

0 2

1 10 15 9

0 0

0 37 NW 0

0 1

6 6

13 7

0 0

0 33 NNW 0

0 1

5 7

25 10 0

0 0

48 Total 3

9 23 100 168 423 339 10 2

0 1077 NUMBER OF CALMS: 0 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 1077 TOTAL HOURS FOR THE PERIOD: 1077

Plant: River Bend Nuclear Station Year: 2019 Page 42 of 70 Annual Radioactive Effluent Release Report Stability Class G Period of Record: 01/01/2019 - 12/31/2019 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)

Wind Direction 0.22-0.50 0.51-0.75 0.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0

>10.0 Total N

1 1

1 6

10 39 20 0

0 0

78 NNE 1

2 2

4 11 35 8

0 0

0 63 NE 0

1 2

10 10 27 65 0

0 0

115 ENE 1

0 3

8 10 39 20 0

0 0

81 E

1 0

1 6

16 32 8

0 0

0 64 ESE 1

1 2

6 13 37 30 0

0 0

90 SE 1

1 4

4 11 32 24 0

0 0

77 SSE 0

1 1

9 18 50 11 0

0 0

90 S

0 1

1 11 14 41 1

0 0

0 69 SSW 0

0 5

4 21 40 2

0 0

0 72 SW 0

3 3

9 11 26 1

0 0

0 53 WSW 0

1 1

4 27 36 2

0 0

0 71 W

0 1

1 11 19 31 6

0 0

0 69 WNW 0

1 3

7 17 39 8

0 0

0 75 NW 0

0 0

8 15 34 8

0 0

0 65 NNW 0

0 2

5 11 20 14 0

0 0

52 Total 6

14 32 112 234 558 228 0

0 0

1184 NUMBER OF CALMS: 0 NUMBER OF INVALID HOURS: 0 NUMBER OF VALID HOURS: 1184 TOTAL HOURS FOR THE PERIOD: 1184

Plant: River Bend Nuclear Station Year: 2019 Page 43 of 70 Annual Radioactive Effluent Release Report 7.2 Stability Class Table 15, Classification of Atmospheric Stability Stability Condition Pasquill Categories Hours (Percentage)

Extremely Unstable A

14 Moderately Stable B

3 Slightly Unstable C

7 Neutral D

23 Slightly Stable E

27 Moderately Stable F

13 Extremely Stable G

14 Table 16, Atmospheric Dispersion and Deposition Rates for the Maximum Individual Dose Calculations Analysis Location (meters)

Ground Level Releases Mixed Mode Releases Gamma air dose (3) and Beta Air Dose 994 m WNW (Containment)

CHI/Q - 421.0 CHI/Q - 33.1 Maximum Receptor (4) 994 m WNW CHI/Q - 421.0 CHI/Q - 33.1 Resident D/Q - 50.3 D/Q - 18.0 Garden Meat animal Immersion Milk animal (5) 7,000 m WNW CHI/Q - 3.58 D/Q - 0.38 CHI/Q -.870 D/Q -.223 Other on-site Receptors 115 m ENE CHI/Q - 5977.0 D/Q - 529.7 CHI/Q - 407.5 D/Q - 46.9 275 m N CHI/Q - 1644.0 D/Q - 345.6 CHI/Q - 169.1 D/Q - 68.4 2500 SW CHI/Q - 34.45 D/Q - 3.35 CHI/Q - 4.65 D/Q - 1.40 Notes:

(1) All CHI/Q = 10-7 sec/m3 (2) All D/Q = 10-9 m-2 (3) Maximum offsite location (property boundary) with highest CHI/Q (unoccupied).

(4) Maximum hypothetical occupied offsite location with highest CHI/Q and D/Q.

(5) No milk animal within 5 miles radius, hypothetical location in worst sector.

(6) Other onsite receptors (7) Revisions to X/Q and D/Q can be performed using NUREG/CR-2919, XOQDOQ, Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations

RBG-48013 Rev. 2019 Page 44 of 70 Annual Radioactive Effluent Release Report Page 1 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-100 2/19/2019 pCi/L

< 4.0E+00

< 5.7E+00

< 1.0E+01

< 6.0E+00

< 9.6E+00

< 7.2E+00

< 1.2E+01

< 1.4E+01

< 7.8E+00

< 5.9E+00

< 4.1E+01

< 1.2E+01 MW-124 2/19/2019 pCi/L

< 3.5E+00

< 3.9E+00

< 9.0E+00

< 4.4E+00

< 8.3E+00

< 5.2E+00

< 8.0E+00

< 1.3E+01

< 4.8E+00

< 4.5E+00

< 3.0E+01

< 1.0E+01 MW-125 2/19/2019 pCi/L

< 4.9E+00

< 5.0E+00

< 9.3E+00

< 5.1E+00

< 8.9E+00

< 5.4E+00

< 8.3E+00

< 1.4E+01

< 5.6E+00

< 5.7E+00

< 3.3E+01

< 9.3E+00 MW-142 2/19/2019 pCi/L

< 2.8E+00

< 3.0E+00

< 6.6E+00

< 3.2E+00

< 5.7E+00

< 3.2E+00

< 5.2E+00

< 1.1E+01

< 3.1E+00

< 3.0E+00

< 2.1E+01

< 5.7E+00 MW-144 2/19/2019 pCi/L

< 3.5E+00

< 4.7E+00

< 1.2E+01

< 5.7E+00

< 8.7E+00

< 4.8E+00

< 7.8E+00

< 1.5E+01

< 5.1E+00

< 5.1E+00

< 3.2E+01

< 1.4E+01 MW-146 2/19/2019 pCi/L

< 4.3E+00

< 5.6E+00

< 1.0E+01

< 4.3E+00

< 9.0E+00

< 5.3E+00

< 9.2E+00

< 1.5E+01

< 5.2E+00

< 5.0E+00

< 3.5E+01

< 1.2E+01 MW-147 2/19/2019 pCi/L

< 4.6E+00

< 6.2E+00

< 1.2E+01

< 6.0E+00

< 9.1E+00

< 6.4E+00

< 9.1E+00

< 1.5E+01

< 5.0E+00

< 5.4E+00

< 2.9E+01

< 9.6E+00 MW-148 2/19/2019 pCi/L

< 5.1E+00

< 4.7E+00

< 1.1E+01

< 4.5E+00

< 1.0E+01

< 5.0E+00

< 8.1E+00

< 1.3E+01

< 5.3E+00

< 4.9E+00

< 3.3E+01

< 1.0E+01 MW-148 2/19/2019 pCi/L

< 5.0E+00

< 5.5E+00

< 1.3E+01

< 6.1E+00

< 1.0E+01

< 5.4E+00

< 9.8E+00

< 1.4E+01

< 7.4E+00

< 5.2E+00

< 4.0E+01

< 1.1E+01 MW-155 2/19/2019 pCi/L

< 3.1E+00

< 3.3E+00

< 6.5E+00

< 2.8E+00

< 6.5E+00

< 3.5E+00

< 5.7E+00

< 1.1E+01

< 3.2E+00

< 3.1E+00

< 2.3E+01

< 6.4E+00 MW-156 2/19/2019 pCi/L

< 3.6E+00

< 4.0E+00

< 1.2E+01

< 4.3E+00

< 8.3E+00

< 5.1E+00

< 9.5E+00

< 1.5E+01

< 4.2E+00

< 4.6E+00

< 3.4E+01

< 1.2E+01 MW-157 2/19/2019 pCi/L

< 4.8E+00

< 4.0E+00

< 9.2E+00

< 4.8E+00

< 8.5E+00

< 4.7E+00

< 8.7E+00

< 1.5E+01

< 5.2E+00

< 4.2E+00

< 2.8E+01

< 8.8E+00 MW-158 2/19/2019 pCi/L

< 5.6E+00

< 4.1E+00

< 1.3E+01

< 5.7E+00

< 8.9E+00

< 3.9E+00

< 9.4E+00

< 1.3E+01

< 5.6E+00

< 5.1E+00

< 3.2E+01

< 1.1E+01 MW-159 2/19/2019 pCi/L

< 5.2E+00

< 4.9E+00

< 8.5E+00

< 5.3E+00

< 9.0E+00

< 5.4E+00

< 9.0E+00

< 1.5E+01

< 5.3E+00

< 3.6E+00

< 3.5E+01

< 1.1E+01 MW-159 2/19/2019 pCi/L

< 5.9E+00

< 7.4E+00

< 1.1E+01

< 6.6E+00

< 1.1E+01

< 6.4E+00

< 1.2E+01

< 1.3E+01

< 5.5E+00

< 6.3E+00

< 4.7E+01

< 1.4E+01 MW-162 2/19/2019 pCi/L

< 2.8E+00

< 3.0E+00

< 7.1E+00

< 2.6E+00

< 5.9E+00

< 2.9E+00

< 5.1E+00

< 8.7E+00

< 3.0E+00

< 2.9E+00

< 1.9E+01

< 6.8E+00 MW-188 2/19/2019 pCi/L

< 2.3E+00

< 2.7E+00

< 5.7E+00

< 2.8E+00

< 4.9E+00

< 2.5E+00

< 4.5E+00

< 8.9E+00

< 2.6E+00

< 2.7E+00

< 1.8E+01

< 5.6E+00

RBG-48013 Rev. 2019 Page 45 of 70 Annual Radioactive Effluent Release Report Page 2 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-205 2/19/2019 pCi/L

< 3.0E+00

< 3.3E+00

< 6.6E+00

< 3.0E+00

< 6.5E+00

< 2.5E+00

< 5.8E+00

< 9.8E+00

< 3.2E+00

< 2.8E+00

< 1.9E+01

< 7.9E+00 MW-207 2/19/2019 pCi/L

< 2.6E+00

< 2.7E+00

< 6.1E+00

< 2.9E+00

< 5.6E+00

< 2.8E+00

< 5.2E+00

< 7.3E+00

< 2.8E+00

< 2.8E+00

< 1.8E+01

< 6.0E+00 MW-211 2/19/2019 pCi/L

< 5.1E+00

< 4.0E+00

< 1.1E+01

< 5.8E+00

< 1.0E+01

< 4.8E+00

< 8.8E+00

< 9.5E+00

< 5.8E+00

< 4.3E+00

< 2.4E+01

< 9.6E+00 MW-211 2/19/2019 pCi/L

< 5.3E+00

< 4.6E+00

< 1.3E+01

< 5.6E+00

< 1.0E+01

< 5.8E+00

< 9.6E+00

< 1.2E+01

< 4.8E+00

< 5.6E+00

< 3.1E+01

< 1.1E+01 MW-213 2/19/2019 pCi/L

< 2.1E+00

< 2.1E+00

< 5.8E+00

< 2.6E+00

< 4.5E+00

< 2.5E+00

< 4.4E+00

< 8.5E+00

< 2.6E+00

< 2.4E+00

< 1.6E+01

< 5.1E+00 MW-213 2/19/2019 pCi/L

< 4.6E+00

< 6.1E+00

< 1.1E+01

< 4.9E+00

< 8.5E+00

< 5.7E+00

< 8.7E+00

< 1.1E+01

< 6.0E+00

< 5.1E+00

< 2.8E+01

< 1.0E+01 MW-215 2/19/2019 pCi/L

< 6.2E+00

< 5.6E+00

< 1.1E+01

< 6.9E+00

< 1.3E+01

< 5.5E+00

< 1.1E+01

< 1.2E+01

< 6.8E+00

< 5.5E+00

< 2.4E+01

< 1.2E+01 MW-217 2/19/2019 pCi/L

< 6.5E+00

< 6.2E+00

< 1.3E+01

< 7.5E+00

< 1.4E+01

< 7.9E+00

< 1.3E+01

< 1.4E+01

< 7.1E+00

< 6.9E+00

< 4.0E+01

< 1.2E+01 MW-227 2/19/2019 pCi/L

< 2.8E+00

< 2.5E+00

< 6.6E+00

< 3.3E+00

< 6.0E+00

< 3.1E+00

< 5.0E+00

< 8.2E+00

< 3.0E+00

< 2.8E+00

< 2.1E+01

< 6.2E+00 MW-229 2/19/2019 pCi/L

< 2.8E+00

< 3.1E+00

< 7.2E+00

< 3.0E+00

< 5.5E+00

< 3.0E+00

< 5.3E+00

< 9.6E+00

< 3.2E+00

< 3.0E+00

< 2.1E+01

< 6.4E+00 MW-110 2/20/2019 pCi/L

< 4.9E+00

< 5.6E+00

< 1.2E+01

< 5.2E+00

< 1.2E+01

< 6.3E+00

< 1.1E+01

< 1.5E+01

< 6.2E+00

< 5.3E+00

< 3.2E+01

< 1.1E+01 MW-112 2/20/2019 pCi/L

< 5.5E+00

< 5.4E+00

< 1.6E+01

< 7.2E+00

< 9.0E+00

< 5.5E+00

< 1.1E+01

< 1.4E+01

< 7.1E+00

< 6.9E+00

< 4.2E+01

< 1.1E+01 MW-114 2/20/2019 pCi/L

< 4.7E+00

< 5.0E+00

< 9.0E+00

< 5.8E+00

< 8.8E+00

< 4.3E+00

< 9.4E+00

< 1.3E+01

< 5.3E+00

< 4.6E+00

< 2.4E+01

< 9.1E+00 MW-116 2/20/2019 pCi/L

< 4.9E+00

< 5.5E+00

< 1.2E+01

< 6.1E+00

< 9.9E+00

< 5.1E+00

< 9.4E+00

< 1.4E+01

< 3.0E+00

< 4.8E+00

< 3.9E+01

< 1.3E+01 MW-118 2/20/2019 pCi/L

< 4.3E+00

< 4.4E+00

< 1.0E+01

< 4.8E+00

< 7.8E+00

< 5.0E+00

< 7.4E+00

< 1.4E+01

< 4.6E+00

< 3.7E+00

< 2.9E+01

< 1.1E+01 MW-137 2/20/2019 pCi/L

< 4.0E+00

< 4.7E+00

< 1.0E+01

< 4.5E+00

< 9.8E+00

< 4.5E+00

< 6.7E+00

< 1.4E+01

< 4.6E+00

< 4.8E+00

< 3.1E+01

< 9.2E+00 MW-139 2/20/2019 pCi/L

< 3.2E+00

< 4.0E+00

< 9.2E+00

< 4.6E+00

< 7.8E+00

< 4.3E+00

< 7.5E+00

< 1.3E+01

< 4.4E+00

< 5.1E+00

< 2.7E+01

< 1.1E+01

RBG-48013 Rev. 2019 Page 46 of 70 Annual Radioactive Effluent Release Report Page 3 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-141 2/20/2019 pCi/L

< 4.8E+00

< 4.7E+00

< 1.0E+01

< 4.3E+00

< 8.1E+00

< 5.3E+00

< 9.1E+00

< 1.4E+01

< 4.3E+00

< 4.9E+00

< 3.1E+01

< 9.6E+00 MW-151 2/20/2019 pCi/L

< 5.1E+00

< 4.6E+00

< 1.3E+01

< 4.8E+00

< 9.7E+00

< 4.1E+00

< 8.7E+00

< 1.4E+01

< 4.4E+00

< 4.4E+00

< 3.0E+01

< 9.5E+00 MW-153 2/20/2019 pCi/L

< 4.5E+00

< 5.0E+00

< 1.0E+01

< 6.2E+00

< 1.3E+01

< 4.9E+00

< 8.3E+00

< 1.5E+01

< 4.8E+00

< 4.7E+00

< 3.1E+01

< 7.4E+00 MW-161 2/20/2019 pCi/L

< 4.6E+00

< 5.5E+00

< 1.1E+01

< 4.1E+00

< 9.7E+00

< 4.9E+00

< 8.9E+00

< 1.4E+01

< 4.5E+00

< 4.3E+00

< 2.9E+01

< 1.1E+01 MW-164 2/20/2019 pCi/L

< 4.2E+00

< 4.2E+00

< 9.3E+00

< 5.0E+00

< 7.1E+00

< 4.4E+00

< 8.0E+00

< 1.4E+01

< 4.8E+00

< 4.5E+00

< 3.0E+01

< 1.1E+01 MW-165 2/20/2019 pCi/L

< 5.6E+00

< 6.0E+00

< 1.3E+01

< 6.2E+00

< 1.3E+01

< 5.8E+00

< 1.1E+01

< 1.3E+01

< 7.3E+00

< 5.2E+00

< 2.9E+01

< 1.2E+01 MW-165 2/20/2019 pCi/L

< 4.2E+00

< 4.9E+00

< 1.1E+01

< 6.0E+00

< 1.1E+01

< 4.3E+00

< 7.4E+00

< 8.6E+00

< 5.5E+00

< 5.6E+00

< 2.7E+01

< 9.5E+00 MW-170 2/20/2019 pCi/L

< 4.4E+00

< 6.2E+00

< 1.2E+01

< 4.9E+00

< 1.0E+01

< 5.3E+00

< 9.7E+00

< 1.2E+01

< 5.0E+00

< 4.9E+00

< 2.5E+01

< 7.2E+00 MW-178 2/20/2019 pCi/L

< 4.3E+00

< 4.8E+00

< 1.0E+01

< 4.4E+00

< 1.0E+01

< 5.1E+00

< 9.9E+00

< 1.4E+01

< 5.0E+00

< 5.1E+00

< 3.0E+01

< 9.8E+00 MW-179 2/20/2019 pCi/L

< 4.4E+00

< 4.1E+00

< 1.2E+01

< 5.5E+00

< 1.1E+01

< 5.7E+00

< 8.5E+00

< 1.4E+01

< 5.1E+00

< 4.8E+00

< 2.8E+01

< 1.0E+01 MW-182 2/20/2019 pCi/L

< 5.7E+00

< 7.7E+00

< 1.6E+01

< 7.5E+00

< 1.3E+01

< 8.2E+00

< 1.5E+01

< 1.5E+01

< 6.0E+00

< 7.1E+00

< 3.8E+01

< 9.9E+00 MW-186 2/20/2019 pCi/L

< 2.3E+00

< 2.7E+00

< 6.0E+00

< 2.7E+00

< 5.4E+00

< 2.9E+00

< 4.4E+00

< 1.0E+01

< 2.6E+00

< 2.6E+00

< 2.0E+01

< 6.4E+00 MW-187 2/20/2019 pCi/L

< 2.7E+00

< 3.0E+00

< 6.3E+00

< 2.7E+00

< 5.8E+00

< 3.2E+00

< 5.5E+00

< 1.1E+01

< 2.9E+00

< 3.0E+00

< 2.3E+01

< 6.3E+00 MW-201 2/20/2019 pCi/L

< 4.1E+00

< 3.8E+00

< 9.3E+00

< 3.8E+00

< 8.8E+00

< 4.8E+00

< 7.1E+00

< 1.3E+01

< 4.4E+00

< 4.1E+00

< 2.8E+01

< 8.0E+00 MW-203 2/20/2019 pCi/L

< 3.9E+00

< 4.2E+00

< 8.0E+00

< 4.0E+00

< 7.3E+00

< 4.6E+00

< 6.8E+00

< 1.5E+01

< 4.9E+00

< 4.3E+00

< 2.8E+01

< 9.1E+00 MW-209 2/20/2019 pCi/L

< 6.0E+00

< 5.1E+00

< 1.2E+01

< 6.5E+00

< 9.8E+00

< 5.5E+00

< 8.3E+00

< 1.0E+01

< 6.4E+00

< 5.7E+00

< 2.8E+01

< 7.5E+00 MW-219 2/20/2019 pCi/L

< 6.1E+00

< 5.2E+00

< 1.3E+01

< 5.4E+00

< 1.3E+01

< 6.2E+00

< 1.0E+01

< 1.3E+01

< 5.9E+00

< 5.7E+00

< 2.9E+01

< 7.3E+00

RBG-48013 Rev. 2019 Page 47 of 70 Annual Radioactive Effluent Release Report Page 4 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-221 2/20/2019 pCi/L

< 3.9E+00

< 3.7E+00

< 8.4E+00

< 3.5E+00

< 8.5E+00

< 4.5E+00

< 6.8E+00

< 1.4E+01

< 4.3E+00

< 3.9E+00

< 2.8E+01

< 1.1E+01 MW-223 2/20/2019 pCi/L

< 3.3E+00

< 3.8E+00

< 8.0E+00

< 3.6E+00

< 7.7E+00

< 4.5E+00

< 6.3E+00

< 1.2E+01

< 3.9E+00

< 3.3E+00

< 2.6E+01

< 7.5E+00 MW-225 2/20/2019 pCi/L

< 3.5E+00

< 4.1E+00

< 7.7E+00

< 3.4E+00

< 9.1E+00

< 4.2E+00

< 7.4E+00

< 8.6E+00

< 4.1E+00

< 4.2E+00

< 2.1E+01

< 6.1E+00 MW-231 2/20/2019 pCi/L

< 5.6E+00

< 7.2E+00

< 1.5E+01

< 7.9E+00

< 1.1E+01

< 6.1E+00

< 1.3E+01

< 1.0E+01

< 6.9E+00

< 5.8E+00

< 2.9E+01

< 1.4E+01 MW-233 2/20/2019 pCi/L

< 5.3E+00

< 5.7E+00

< 1.1E+01

< 6.9E+00

< 1.3E+01

< 4.9E+00

< 9.3E+00

< 9.6E+00

< 5.9E+00

< 4.9E+00

< 2.5E+01

< 1.1E+01 MW-235 2/20/2019 pCi/L

< 5.1E+00

< 4.9E+00

< 1.2E+01

< 5.2E+00

< 9.3E+00

< 6.1E+00

< 9.7E+00

< 1.2E+01

< 6.5E+00

< 5.2E+00

< 2.7E+01

< 6.5E+00 PZ-01 2/20/2019 pCi/L

< 4.8E+00

< 5.5E+00

< 1.1E+01

< 5.0E+00

< 1.0E+01

< 5.6E+00

< 8.0E+00

< 1.4E+01

< 5.7E+00

< 5.5E+00

< 4.0E+01

< 1.2E+01 SW-101 2/21/2019 pCi/L

< 4.0E+00

< 4.5E+00

< 1.0E+01

< 3.5E+00

< 7.6E+00

< 4.5E+00

< 6.9E+00

< 1.4E+01

< 4.8E+00

< 4.8E+00

< 3.1E+01

< 1.1E+01 SW-102 2/21/2019 pCi/L

< 3.7E+00

< 4.5E+00

< 1.0E+01

< 4.5E+00

< 7.7E+00

< 4.7E+00

< 9.3E+00

< 1.4E+01

< 4.0E+00

< 4.1E+00

< 3.3E+01

< 1.1E+01 SW-103 2/21/2019 pCi/L

< 3.1E+00

< 3.4E+00

< 7.3E+00

< 3.0E+00

< 6.5E+00

< 3.6E+00

< 6.3E+00

< 1.3E+01

< 3.5E+00

< 3.3E+00

< 2.5E+01

< 7.6E+00 SW-104 2/21/2019 pCi/L

< 4.6E+00

< 5.1E+00

< 1.1E+01

< 5.5E+00

< 8.3E+00

< 5.2E+00

< 9.6E+00

< 1.5E+01

< 5.4E+00

< 5.3E+00

< 2.8E+01

< 1.5E+01 MW-158 4/17/2019 pCi/L

< 3.6E+00

< 4.2E+00

< 8.8E+00

< 3.8E+00

< 8.8E+00

< 5.2E+00

< 7.7E+00

< 1.3E+01

< 4.1E+00

< 4.2E+00

< 2.8E+01

< 1.2E+01 MW-124 5/14/2019 pCi/L

< 2.9E+00

< 3.3E+00

< 6.3E+00

< 3.6E+00

< 6.5E+00

< 3.5E+00

< 5.9E+00

< 7.2E+00

< 3.5E+00

< 3.3E+00

< 1.9E+01

< 5.5E+00 MW-124 5/14/2019 pCi/L

< 4.5E+00

< 4.6E+00

< 9.7E+00

< 4.4E+00

< 9.7E+00

< 5.2E+00

< 8.4E+00

< 1.5E+01

< 5.3E+00

< 4.7E+00

< 3.0E+01

< 1.0E+01 MW-125 5/14/2019 pCi/L

< 4.1E+00

< 5.1E+00

< 1.2E+01

< 5.3E+00

< 8.5E+00

< 5.7E+00

< 8.9E+00

< 1.4E+01

< 6.3E+00

< 4.4E+00

< 3.4E+01

< 1.1E+01 MW-142 5/14/2019 pCi/L

< 2.7E+00

< 3.1E+00

< 6.8E+00

< 2.3E+00

< 5.3E+00

< 3.0E+00

< 5.1E+00

< 1.0E+01

< 3.1E+00

< 2.9E+00

< 2.0E+01

< 8.0E+00 MW-144 5/14/2019 pCi/L

< 3.2E+00

< 3.2E+00

< 6.4E+00

< 3.1E+00

< 6.4E+00

< 3.5E+00

< 5.9E+00

< 8.2E+00

< 3.5E+00

< 3.1E+00

< 1.9E+01

< 7.0E+00

RBG-48013 Rev. 2019 Page 48 of 70 Annual Radioactive Effluent Release Report Page 5 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-146 5/14/2019 pCi/L

< 3.4E+00

< 3.6E+00

< 7.9E+00

< 3.9E+00

< 7.1E+00

< 3.9E+00

< 6.5E+00

< 9.0E+00

< 4.2E+00

< 3.8E+00

< 2.1E+01

< 8.0E+00 MW-147 5/14/2019 pCi/L

< 3.2E+00

< 3.0E+00

< 9.1E+00

< 3.8E+00

< 6.6E+00

< 3.6E+00

< 6.9E+00

< 8.5E+00

< 3.6E+00

< 3.6E+00

< 2.0E+01

< 7.2E+00 MW-148 5/14/2019 pCi/L

< 3.3E+00

< 3.5E+00

< 7.4E+00

< 4.4E+00

< 5.1E+00

< 3.8E+00

< 5.4E+00

< 7.6E+00

< 3.4E+00

< 3.6E+00

< 1.9E+01

< 6.5E+00 MW-156 5/14/2019 pCi/L

< 3.9E+00

< 3.8E+00

< 9.3E+00

< 4.2E+00

< 8.3E+00

< 4.7E+00

< 8.2E+00

< 1.4E+01

< 4.9E+00

< 4.5E+00

< 3.1E+01

< 8.3E+00 MW-157 5/14/2019 pCi/L

< 3.5E+00

< 3.6E+00

< 7.1E+00

< 3.2E+00

< 6.5E+00

< 3.5E+00

< 5.8E+00

< 7.7E+00

< 3.8E+00

< 3.0E+00

< 1.9E+01

< 6.5E+00 MW-157 5/14/2019 pCi/L

< 3.0E+00

< 3.6E+00

< 7.1E+00

< 3.9E+00

< 6.7E+00

< 3.8E+00

< 6.3E+00

< 8.0E+00

< 3.7E+00

< 3.5E+00

< 2.1E+01

< 7.9E+00 MW-158 5/14/2019 pCi/L

< 3.8E+00

< 4.4E+00

< 9.3E+00

< 3.9E+00

< 7.3E+00

< 4.4E+00

< 7.6E+00

< 1.4E+01

< 4.0E+00

< 3.5E+00

< 2.6E+01

< 7.2E+00 MW-159 5/14/2019 pCi/L

< 4.1E+00

< 4.1E+00

< 9.1E+00

< 4.0E+00

< 8.6E+00

< 3.9E+00

< 6.1E+00

< 1.0E+01

< 4.5E+00

< 3.7E+00

< 2.3E+01

< 7.6E+00 MW-162 5/14/2019 pCi/L

< 3.6E+00

< 4.0E+00

< 8.1E+00

< 4.2E+00

< 8.8E+00

< 4.3E+00

< 7.7E+00

< 1.4E+01

< 3.7E+00

< 4.1E+00

< 2.8E+01

< 9.3E+00 MW-100 5/15/2019 pCi/L

< 4.4E+00

< 4.7E+00

< 1.1E+01

< 4.3E+00

< 9.1E+00

< 4.2E+00

< 7.1E+00

< 1.3E+01

< 6.2E+00

< 4.0E+00

< 2.7E+01

< 1.2E+01 MW-110 5/15/2019 pCi/L

< 3.7E+00

< 4.2E+00

< 8.8E+00

< 3.9E+00

< 8.4E+00

< 4.1E+00

< 8.2E+00

< 1.1E+01

< 4.1E+00

< 4.0E+00

< 2.9E+01

< 8.2E+00 MW-112 5/15/2019 pCi/L

< 5.2E+00

< 5.1E+00

< 1.3E+01

< 4.9E+00

< 1.1E+01

< 6.0E+00

< 1.1E+01

< 1.3E+01

< 6.0E+00

< 3.8E+00

< 3.5E+01

< 1.3E+01 MW-114 5/15/2019 pCi/L

< 3.7E+00

< 4.2E+00

< 8.6E+00

< 4.6E+00

< 6.9E+00

< 4.3E+00

< 8.3E+00

< 1.2E+01

< 4.3E+00

< 3.3E+00

< 2.8E+01

< 1.1E+01 MW-116 5/15/2019 pCi/L

< 4.9E+00

< 5.0E+00

< 1.1E+01

< 5.2E+00

< 8.3E+00

< 5.3E+00

< 8.7E+00

< 1.4E+01

< 5.2E+00

< 4.4E+00

< 3.3E+01

< 1.3E+01 MW-118 5/15/2019 pCi/L

< 3.5E+00

< 4.2E+00

< 8.6E+00

< 4.3E+00

< 9.8E+00

< 4.1E+00

< 6.3E+00

< 1.2E+01

< 4.6E+00

< 4.1E+00

< 2.5E+01

< 9.8E+00 MW-131 5/15/2019 pCi/L

< 4.1E+00

< 4.5E+00

< 1.0E+01

< 3.7E+00

< 7.5E+00

< 4.0E+00

< 7.8E+00

< 1.2E+01

< 4.4E+00

< 4.4E+00

< 2.9E+01

< 8.8E+00 MW-132 5/15/2019 pCi/L

< 3.9E+00

< 3.8E+00

< 8.4E+00

< 3.7E+00

< 8.2E+00

< 3.7E+00

< 7.3E+00

< 1.3E+01

< 4.5E+00

< 4.0E+00

< 2.7E+01

< 8.1E+00

RBG-48013 Rev. 2019 Page 49 of 70 Annual Radioactive Effluent Release Report Page 6 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-137 5/15/2019 pCi/L

< 4.1E+00

< 5.4E+00

< 9.8E+00

< 4.8E+00

< 8.6E+00

< 5.5E+00

< 1.0E+01

< 1.4E+01

< 5.4E+00

< 5.4E+00

< 3.3E+01

< 1.2E+01 MW-139 5/15/2019 pCi/L

< 4.0E+00

< 5.2E+00

< 8.6E+00

< 4.2E+00

< 8.6E+00

< 4.9E+00

< 9.7E+00

< 1.2E+01

< 4.2E+00

< 3.9E+00

< 2.9E+01

< 1.0E+01 MW-141 5/15/2019 pCi/L

< 6.1E+00

< 5.8E+00

< 1.0E+01

< 5.1E+00

< 1.0E+01

< 4.9E+00

< 8.0E+00

< 1.4E+01

< 6.4E+00

< 4.5E+00

< 3.5E+01

< 1.1E+01 MW-151 5/15/2019 pCi/L

< 2.2E+00

< 2.3E+00

< 5.2E+00

< 2.3E+00

< 4.2E+00

< 2.4E+00

< 4.5E+00

< 1.3E+01

< 2.3E+00

< 2.2E+00

< 2.1E+01

< 6.1E+00 MW-153 5/15/2019 pCi/L

< 4.6E+00

< 6.2E+00

< 1.0E+01

< 5.7E+00

< 1.0E+01

< 5.8E+00

< 1.0E+01

< 1.5E+01

< 5.5E+00

< 5.0E+00

< 3.6E+01

< 1.0E+01 MW-155 5/15/2019 pCi/L

< 4.3E+00

< 5.1E+00

< 1.1E+01

< 5.1E+00

< 8.5E+00

< 4.7E+00

< 8.5E+00

< 1.5E+01

< 4.4E+00

< 4.3E+00

< 2.8E+01

< 1.0E+01 MW-161 5/15/2019 pCi/L

< 4.8E+00

< 5.8E+00

< 1.3E+01

< 5.8E+00

< 1.1E+01

< 4.5E+00

< 9.4E+00

< 1.5E+01

< 5.3E+00

< 4.9E+00

< 3.5E+01

< 9.9E+00 MW-161 5/15/2019 pCi/L

< 4.0E+00

< 4.8E+00

< 1.1E+01

< 6.6E+00

< 7.6E+00

< 5.1E+00

< 8.8E+00

< 1.4E+01

< 5.0E+00

< 4.3E+00

< 3.0E+01

< 7.4E+00 MW-164 5/15/2019 pCi/L

< 1.7E+00

< 1.8E+00

< 4.2E+00

< 1.8E+00

< 3.3E+00

< 2.0E+00

< 3.5E+00

< 9.5E+00

< 1.8E+00

< 1.7E+00

< 1.7E+01

< 5.2E+00 MW-165 5/15/2019 pCi/L

< 1.6E+00

< 1.8E+00

< 3.9E+00

< 1.7E+00

< 3.3E+00

< 2.0E+00

< 3.3E+00

< 9.8E+00

< 1.8E+00

< 1.6E+00

< 1.7E+01

< 5.1E+00 MW-167 5/15/2019 pCi/L

< 3.2E+00

< 3.9E+00

< 8.5E+00

< 3.4E+00

< 6.2E+00

< 3.8E+00

< 6.0E+00

< 1.3E+01

< 4.0E+00

< 3.5E+00

< 2.4E+01

< 7.9E+00 MW-172 5/15/2019 pCi/L

< 1.4E+00

< 1.5E+00

< 3.6E+00

< 1.5E+00

< 3.0E+00

< 1.8E+00

< 2.8E+00

< 8.8E+00

< 1.6E+00

< 1.6E+00

< 1.5E+01

< 5.0E+00 MW-174 5/15/2019 pCi/L

< 1.8E+00

< 2.0E+00

< 4.2E+00

< 1.8E+00

< 3.7E+00

< 1.9E+00

< 3.7E+00

< 1.1E+01

< 2.0E+00

< 1.8E+00

< 1.9E+01

< 6.3E+00 MW-178 5/15/2019 pCi/L

< 3.7E+00

< 3.7E+00

< 7.4E+00

< 4.2E+00

< 7.2E+00

< 4.0E+00

< 7.6E+00

< 1.1E+01

< 4.1E+00

< 3.5E+00

< 2.4E+01

< 8.1E+00 MW-179 5/15/2019 pCi/L

< 5.6E+00

< 4.9E+00

< 1.1E+01

< 5.7E+00

< 1.1E+01

< 5.3E+00

< 8.3E+00

< 1.3E+01

< 5.0E+00

< 5.0E+00

< 3.1E+01

< 1.1E+01 MW-185 5/15/2019 pCi/L

< 4.3E+00

< 4.0E+00

< 9.9E+00

< 4.0E+00

< 7.9E+00

< 4.8E+00

< 7.6E+00

< 1.5E+01

< 4.4E+00

< 5.2E+00

< 3.2E+01

< 8.4E+00 MW-185 5/15/2019 pCi/L

< 4.2E+00

< 4.4E+00

< 1.1E+01

< 4.6E+00

< 9.2E+00

< 4.4E+00

< 7.2E+00

< 1.5E+01

< 4.5E+00

< 4.7E+00

< 3.3E+01

< 9.4E+00

RBG-48013 Rev. 2019 Page 50 of 70 Annual Radioactive Effluent Release Report Page 7 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-186 5/15/2019 pCi/L

< 1.6E+00

< 1.9E+00

< 4.3E+00

< 1.9E+00

< 3.6E+00

< 1.9E+00

< 3.4E+00

< 1.1E+01

< 1.9E+00

< 1.7E+00

< 1.8E+01

< 6.4E+00 MW-187 5/15/2019 pCi/L

< 1.5E+00

< 1.8E+00

< 4.3E+00

< 1.7E+00

< 3.1E+00

< 2.0E+00

< 3.5E+00

< 1.2E+01

< 1.8E+00

< 1.8E+00

< 1.9E+01

< 6.4E+00 MW-201 5/15/2019 pCi/L

< 1.7E+00

< 1.8E+00

< 4.4E+00

< 1.7E+00

< 3.8E+00

< 2.0E+00

< 3.4E+00

< 1.1E+01

< 1.9E+00

< 1.8E+00

< 1.8E+01

< 6.5E+00 MW-203 5/15/2019 pCi/L

< 2.0E+00

< 2.2E+00

< 4.9E+00

< 2.3E+00

< 4.0E+00

< 2.3E+00

< 4.1E+00

< 1.3E+01

< 2.2E+00

< 2.0E+00

< 2.2E+01

< 6.4E+00 MW-211 5/15/2019 pCi/L

< 4.6E+00

< 4.6E+00

< 9.3E+00

< 4.4E+00

< 9.0E+00

< 5.0E+00

< 6.9E+00

< 1.4E+01

< 4.5E+00

< 4.4E+00

< 2.8E+01

< 1.1E+01 MW-213 5/15/2019 pCi/L

< 4.4E+00

< 5.0E+00

< 9.6E+00

< 4.0E+00

< 9.6E+00

< 5.7E+00

< 8.6E+00

< 1.3E+01

< 4.6E+00

< 5.0E+00

< 2.7E+01

< 1.0E+01 PZ-01 5/15/2019 pCi/L

< 3.9E+00

< 5.0E+00

< 9.7E+00

< 5.1E+00

< 7.4E+00

< 4.8E+00

< 7.7E+00

< 1.2E+01

< 4.2E+00

< 4.1E+00

< 2.8E+01

< 1.1E+01 PZ-03 5/15/2019 pCi/L

< 3.8E+00

< 4.5E+00

< 8.8E+00

< 4.3E+00

< 8.0E+00

< 4.6E+00

< 6.6E+00

< 1.5E+01

< 4.7E+00

< 4.1E+00

< 3.2E+01

< 1.1E+01 MW-106 5/16/2019 pCi/L

< 4.1E+00

< 4.0E+00

< 9.0E+00

< 3.8E+00

< 8.6E+00

< 4.5E+00

< 7.1E+00

< 1.2E+01

< 3.8E+00

< 3.4E+00

< 2.7E+01

< 9.6E+00 MW-120 5/16/2019 pCi/L

< 4.2E+00

< 5.0E+00

< 1.2E+01

< 4.4E+00

< 9.0E+00

< 5.1E+00

< 7.4E+00

< 1.3E+01

< 5.2E+00

< 4.3E+00

< 3.3E+01

< 9.9E+00 MW-122 5/16/2019 pCi/L

< 2.0E+00

< 2.3E+00

< 5.4E+00

< 2.4E+00

< 4.2E+00

< 2.4E+00

< 4.3E+00

< 1.3E+01

< 2.2E+00

< 2.2E+00

< 2.3E+01

< 6.9E+00 MW-126 5/16/2019 pCi/L

< 1.5E+00

< 1.7E+00

< 3.8E+00

< 1.5E+00

< 3.1E+00

< 1.8E+00

< 3.0E+00

< 9.7E+00

< 1.6E+00

< 1.5E+00

< 1.6E+01

< 5.1E+00 MW-126 5/16/2019 pCi/L

< 1.6E+00

< 1.7E+00

< 4.0E+00

< 1.6E+00

< 3.2E+00

< 1.8E+00

< 3.1E+00

< 1.1E+01

< 1.6E+00

< 1.6E+00

< 1.7E+01

< 6.1E+00 MW-128 5/16/2019 pCi/L

< 1.5E+00

< 1.7E+00

< 3.9E+00

< 1.5E+00

< 3.0E+00

< 1.7E+00

< 3.0E+00

< 1.1E+01

< 1.6E+00

< 1.5E+00

< 1.7E+01

< 6.2E+00 MW-130 5/16/2019 pCi/L

< 1.4E+00

< 1.5E+00

< 3.5E+00

< 1.3E+00

< 3.0E+00

< 1.5E+00

< 2.7E+00

< 8.7E+00

< 1.5E+00

< 1.4E+00

< 1.5E+01

< 4.7E+00 MW-134 5/16/2019 pCi/L

< 4.5E+00

< 4.4E+00

< 1.1E+01

< 4.0E+00

< 9.6E+00

< 4.8E+00

< 9.1E+00

< 1.3E+01

< 4.9E+00

< 4.6E+00

< 2.8E+01

< 8.2E+00 MW-169 5/16/2019 pCi/L

< 3.5E+00

< 3.8E+00

< 8.7E+00

< 4.5E+00

< 9.4E+00

< 5.2E+00

< 6.5E+00

< 1.4E+01

< 4.0E+00

< 4.7E+00

< 2.7E+01

< 1.1E+01

RBG-48013 Rev. 2019 Page 51 of 70 Annual Radioactive Effluent Release Report Page 8 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-170 5/16/2019 pCi/L

< 4.0E+00

< 4.4E+00

< 7.7E+00

< 4.2E+00

< 9.9E+00

< 5.4E+00

< 8.1E+00

< 1.5E+01

< 5.5E+00

< 4.6E+00

< 2.9E+01

< 1.0E+01 MW-180 5/16/2019 pCi/L

< 3.8E+00

< 3.9E+00

< 9.3E+00

< 4.8E+00

< 8.3E+00

< 4.3E+00

< 7.0E+00

< 1.3E+01

< 4.2E+00

< 4.0E+00

< 2.8E+01

< 7.9E+00 MW-182 5/16/2019 pCi/L

< 4.8E+00

< 4.5E+00

< 1.2E+01

< 4.9E+00

< 1.0E+01

< 4.8E+00

< 8.7E+00

< 1.4E+01

< 5.1E+00

< 4.7E+00

< 2.9E+01

< 1.1E+01 MW-188 5/16/2019 pCi/L

< 1.6E+00

< 1.9E+00

< 4.5E+00

< 1.7E+00

< 3.5E+00

< 2.0E+00

< 3.3E+00

< 1.0E+01

< 1.9E+00

< 1.7E+00

< 1.8E+01

< 5.4E+00 MW-205 5/16/2019 pCi/L

< 1.9E+00

< 2.1E+00

< 5.1E+00

< 1.9E+00

< 3.8E+00

< 2.2E+00

< 3.8E+00

< 1.2E+01

< 2.0E+00

< 1.8E+00

< 1.9E+01

< 6.9E+00 MW-207 5/16/2019 pCi/L

< 4.9E+00

< 4.4E+00

< 8.6E+00

< 4.2E+00

< 9.4E+00

< 5.0E+00

< 8.8E+00

< 1.2E+01

< 5.9E+00

< 4.9E+00

< 3.1E+01

< 1.2E+01 MW-209 5/16/2019 pCi/L

< 4.5E+00

< 4.0E+00

< 1.0E+01

< 4.3E+00

< 8.5E+00

< 4.2E+00

< 8.1E+00

< 1.3E+01

< 4.4E+00

< 4.2E+00

< 3.0E+01

< 1.2E+01 MW-209 5/16/2019 pCi/L

< 4.1E+00

< 4.9E+00

< 8.6E+00

< 4.4E+00

< 8.3E+00

< 4.8E+00

< 7.6E+00

< 1.4E+01

< 4.7E+00

< 4.2E+00

< 2.8E+01

< 1.0E+01 MW-215 5/16/2019 pCi/L

< 4.4E+00

< 5.5E+00

< 9.9E+00

< 4.7E+00

< 1.0E+01

< 5.5E+00

< 7.4E+00

< 1.5E+01

< 4.3E+00

< 4.1E+00

< 3.0E+01

< 1.3E+01 MW-217 5/16/2019 pCi/L

< 5.0E+00

< 5.4E+00

< 1.3E+01

< 5.5E+00

< 5.0E+00

< 5.4E+00

< 9.4E+00

< 1.5E+01

< 5.4E+00

< 4.4E+00

< 3.3E+01

< 1.1E+01 MW-219 5/16/2019 pCi/L

< 3.4E+00

< 4.3E+00

< 7.2E+00

< 4.4E+00

< 7.5E+00

< 4.3E+00

< 7.4E+00

< 1.2E+01

< 4.5E+00

< 3.8E+00

< 2.5E+01

< 8.4E+00 MW-221 5/16/2019 pCi/L

< 1.6E+00

< 1.9E+00

< 4.1E+00

< 1.6E+00

< 3.4E+00

< 2.0E+00

< 3.3E+00

< 1.1E+01

< 1.6E+00

< 1.7E+00

< 1.8E+01

< 6.1E+00 MW-223 5/16/2019 pCi/L

< 1.6E+00

< 2.0E+00

< 4.7E+00

< 1.9E+00

< 3.3E+00

< 2.0E+00

< 3.6E+00

< 1.1E+01

< 2.0E+00

< 1.7E+00

< 1.8E+01

< 6.3E+00 MW-225 5/16/2019 pCi/L

< 4.4E+00

< 4.9E+00

< 1.2E+01

< 5.0E+00

< 9.6E+00

< 4.0E+00

< 1.0E+01

< 1.4E+01

< 5.2E+00

< 5.2E+00

< 3.5E+01

< 9.4E+00 MW-227 5/16/2019 pCi/L

< 1.8E+00

< 2.0E+00

< 4.5E+00

< 1.9E+00

< 3.8E+00

< 2.3E+00

< 3.6E+00

< 1.4E+01

< 2.0E+00

< 1.8E+00

< 2.0E+01

< 6.3E+00 MW-229 5/16/2019 pCi/L

< 4.3E+00

< 3.9E+00

< 9.2E+00

< 4.0E+00

< 8.7E+00

< 4.2E+00

< 6.3E+00

< 1.1E+01

< 4.4E+00

< 4.4E+00

< 2.7E+01

< 9.2E+00 MW-231 5/16/2019 pCi/L

< 5.2E+00

< 4.8E+00

< 1.3E+01

< 6.0E+00

< 1.1E+01

< 5.4E+00

< 1.0E+01

< 1.3E+01

< 5.1E+00

< 4.3E+00

< 2.9E+01

< 1.1E+01

RBG-48013 Rev. 2019 Page 52 of 70 Annual Radioactive Effluent Release Report Page 9 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-231 5/16/2019 pCi/L

< 5.0E+00

< 4.4E+00

< 1.2E+01

< 7.0E+00

< 9.8E+00

< 5.5E+00

< 8.4E+00

< 1.5E+01

< 4.6E+00

< 4.8E+00

< 3.1E+01

< 1.1E+01 MW-233 5/16/2019 pCi/L

< 1.7E+00

< 1.9E+00

< 4.4E+00

< 1.6E+00

< 3.4E+00

< 1.9E+00

< 3.4E+00

< 1.1E+01

< 1.8E+00

< 1.7E+00

< 1.8E+01

< 6.5E+00 MW-235 5/16/2019 pCi/L

< 1.6E+00

< 1.8E+00

< 4.4E+00

< 2.0E+00

< 3.5E+00

< 2.0E+00

< 3.1E+00

< 1.1E+01

< 1.7E+00

< 1.7E+00

< 1.7E+01

< 6.0E+00 SW-101 5/16/2019 pCi/L

< 1.5E+00

< 1.8E+00

< 4.3E+00

< 1.6E+00

< 3.2E+00

< 1.8E+00

< 3.0E+00

< 1.0E+01

< 1.6E+00

< 1.5E+00

< 1.6E+01

< 5.6E+00 SW-102 5/16/2019 pCi/L

< 4.2E+00

< 4.3E+00

< 8.7E+00

< 5.5E+00

< 9.4E+00

< 4.6E+00

< 8.6E+00

< 1.3E+01

< 5.1E+00

< 4.3E+00

< 3.0E+01

< 9.3E+00 SW-103 5/16/2019 pCi/L

< 3.8E+00

< 4.7E+00

< 1.0E+01

< 4.9E+00

< 1.1E+01

< 4.4E+00

< 7.8E+00

< 1.3E+01

< 5.4E+00

< 4.4E+00

< 2.7E+01

< 1.0E+01 SW-104 5/16/2019 pCi/L

< 3.9E+00

< 3.9E+00

< 7.8E+00

< 5.1E+00

< 8.1E+00

< 4.7E+00

< 8.2E+00

< 1.3E+01

< 4.6E+00

< 4.0E+00

< 2.9E+01

< 9.1E+00 MW-100 8/13/2019 pCi/L

< 2.3E+00

< 2.5E+00

< 6.0E+00

< 2.6E+00

< 4.6E+00

< 2.6E+00

< 4.5E+00

< 8.2E+00

< 2.5E+00

< 2.6E+00

< 1.8E+01

< 6.0E+00 MW-124 8/13/2019 pCi/L

< 2.7E+00

< 2.8E+00

< 6.4E+00

< 3.5E+00

< 6.0E+00

< 3.2E+00

< 5.3E+00

< 7.6E+00

< 2.9E+00

< 2.8E+00

< 2.0E+01

< 7.4E+00 MW-125 8/13/2019 pCi/L

< 5.1E+00

< 5.5E+00

< 9.5E+00

< 5.1E+00

< 9.9E+00

< 6.1E+00

< 9.7E+00

< 1.4E+01

< 5.0E+00

< 5.2E+00

< 3.0E+01

< 1.0E+01 MW-142 8/13/2019 pCi/L

< 3.0E+00

< 3.6E+00

< 9.4E+00

< 3.4E+00

< 6.5E+00

< 3.9E+00

< 6.6E+00

< 1.4E+01

< 3.9E+00

< 3.0E+00

< 3.4E+01

< 9.1E+00 MW-144 8/13/2019 pCi/L

< 3.3E+00

< 3.4E+00

< 7.3E+00

< 3.7E+00

< 5.6E+00

< 3.5E+00

< 6.0E+00

< 9.3E+00

< 3.4E+00

< 3.4E+00

< 2.1E+01

< 7.2E+00 MW-146 8/13/2019 pCi/L

< 5.2E+00

< 5.4E+00

< 1.1E+01

< 5.3E+00

< 1.1E+01

< 6.2E+00

< 1.1E+01

< 1.4E+01

< 5.2E+00

< 5.1E+00

< 4.2E+01

< 1.1E+01 MW-147 8/13/2019 pCi/L

< 4.0E+00

< 4.4E+00

< 1.0E+01

< 3.8E+00

< 8.9E+00

< 5.3E+00

< 8.1E+00

< 1.3E+01

< 4.7E+00

< 3.7E+00

< 2.9E+01

< 1.2E+01 MW-148 8/13/2019 pCi/L

< 3.7E+00

< 3.5E+00

< 9.1E+00

< 3.2E+00

< 6.0E+00

< 4.5E+00

< 6.6E+00

< 1.4E+01

< 4.0E+00

< 3.7E+00

< 3.0E+01

< 1.1E+01 MW-155 8/13/2019 pCi/L

< 3.0E+00

< 3.4E+00

< 6.2E+00

< 3.1E+00

< 7.0E+00

< 3.2E+00

< 5.5E+00

< 9.1E+00

< 3.3E+00

< 3.2E+00

< 2.0E+01

< 5.7E+00 MW-156 8/13/2019 pCi/L

< 2.6E+00

< 3.2E+00

< 7.3E+00

< 3.0E+00

< 6.1E+00

< 3.1E+00

< 5.1E+00

< 8.1E+00

< 3.1E+00

< 3.1E+00

< 2.0E+01

< 6.9E+00

RBG-48013 Rev. 2019 Page 53 of 70 Annual Radioactive Effluent Release Report Page 10 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-156 8/13/2019 pCi/L

< 3.0E+00

< 3.0E+00

< 6.1E+00

< 3.1E+00

< 6.1E+00

< 2.9E+00

< 4.9E+00

< 7.9E+00

< 2.8E+00

< 3.0E+00

< 1.8E+01

< 5.4E+00 MW-157 8/13/2019 pCi/L

< 3.0E+00

< 3.3E+00

< 7.0E+00

< 3.3E+00

< 6.8E+00

< 3.3E+00

< 5.9E+00

< 8.4E+00

< 3.5E+00

< 3.1E+00

< 2.0E+01

< 6.7E+00 MW-157 8/13/2019 pCi/L

< 3.0E+00

< 3.3E+00

< 6.9E+00

< 3.3E+00

< 6.9E+00

< 3.6E+00

< 5.9E+00

< 8.9E+00

< 3.3E+00

< 3.1E+00

< 2.1E+01

< 6.6E+00 MW-158 8/13/2019 pCi/L

< 3.7E+00

< 4.2E+00

< 8.5E+00

< 3.7E+00

< 7.5E+00

< 4.4E+00

< 8.6E+00

< 1.4E+01

< 4.1E+00

< 4.4E+00

< 2.9E+01

< 9.5E+00 MW-159 8/13/2019 pCi/L

< 2.8E+00

< 2.9E+00

< 6.9E+00

< 3.3E+00

< 4.9E+00

< 2.8E+00

< 5.0E+00

< 6.7E+00

< 3.3E+00

< 2.7E+00

< 1.7E+01

< 5.4E+00 MW-162 8/13/2019 pCi/L

< 2.5E+00

< 3.4E+00

< 6.8E+00

< 3.3E+00

< 5.6E+00

< 3.5E+00

< 5.6E+00

< 1.2E+01

< 3.2E+00

< 2.3E+00

< 2.3E+01

< 8.3E+00 MW-205 8/13/2019 pCi/L

< 3.3E+00

< 3.7E+00

< 6.2E+00

< 3.2E+00

< 6.1E+00

< 3.4E+00

< 4.9E+00

< 1.4E+01

< 3.2E+00

< 3.3E+00

< 2.6E+01

< 8.4E+00 MW-207 8/13/2019 pCi/L

< 2.9E+00

< 2.8E+00

< 5.8E+00

< 2.7E+00

< 5.2E+00

< 2.9E+00

< 5.2E+00

< 8.3E+00

< 3.1E+00

< 2.8E+00

< 1.8E+01

< 6.2E+00 MW-211 8/13/2019 pCi/L

< 4.1E+00

< 3.9E+00

< 1.1E+01

< 4.5E+00

< 6.4E+00

< 4.5E+00

< 8.4E+00

< 1.3E+01

< 4.9E+00

< 4.2E+00

< 3.3E+01

< 1.0E+01 MW-213 8/13/2019 pCi/L

< 3.9E+00

< 4.1E+00

< 9.7E+00

< 3.9E+00

< 8.0E+00

< 4.8E+00

< 9.0E+00

< 1.4E+01

< 4.4E+00

< 4.4E+00

< 2.7E+01

< 9.1E+00 MW-215 8/13/2019 pCi/L

< 2.7E+00

< 2.8E+00

< 6.6E+00

< 2.8E+00

< 6.2E+00

< 3.2E+00

< 5.6E+00

< 8.6E+00

< 3.1E+00

< 2.8E+00

< 2.0E+01

< 7.0E+00 MW-217 8/13/2019 pCi/L

< 4.2E+00

< 5.6E+00

< 9.5E+00

< 4.4E+00

< 7.8E+00

< 5.3E+00

< 8.7E+00

< 1.4E+01

< 4.7E+00

< 4.5E+00

< 3.4E+01

< 1.1E+01 MW-227 8/13/2019 pCi/L

< 3.3E+00

< 3.9E+00

< 9.6E+00

< 4.5E+00

< 7.3E+00

< 3.9E+00

< 6.9E+00

< 1.3E+01

< 3.9E+00

< 3.4E+00

< 3.5E+01

< 1.3E+01 MW-229 8/13/2019 pCi/L

< 2.8E+00

< 3.5E+00

< 7.2E+00

< 3.2E+00

< 6.1E+00

< 3.8E+00

< 7.5E+00

< 1.3E+01

< 3.3E+00

< 2.6E+00

< 2.4E+01

< 9.0E+00 MW-110 8/14/2019 pCi/L

< 4.3E+00

< 5.4E+00

< 1.1E+01

< 5.4E+00

< 9.8E+00

< 6.1E+00

< 8.4E+00

< 1.4E+01

< 5.7E+00

< 5.3E+00

< 3.2E+01

< 1.1E+01 MW-112 8/14/2019 pCi/L

< 4.7E+00

< 5.2E+00

< 1.0E+01

< 4.8E+00

< 1.2E+01

< 5.5E+00

< 9.3E+00

< 1.4E+01

< 6.1E+00

< 4.9E+00

< 3.6E+01

< 1.0E+01 MW-114 8/14/2019 pCi/L

< 4.6E+00

< 4.3E+00

< 9.6E+00

< 4.7E+00

< 8.9E+00

< 4.8E+00

< 8.6E+00

< 1.2E+01

< 5.1E+00

< 4.8E+00

< 2.7E+01

< 1.0E+01

RBG-48013 Rev. 2019 Page 54 of 70 Annual Radioactive Effluent Release Report Page 11 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-116 8/14/2019 pCi/L

< 5.0E+00

< 5.0E+00

< 1.1E+01

< 5.3E+00

< 1.0E+01

< 5.8E+00

< 9.9E+00

< 1.5E+01

< 5.8E+00

< 5.6E+00

< 3.6E+01

< 1.1E+01 MW-118 8/14/2019 pCi/L

< 5.0E+00

< 5.1E+00

< 1.3E+01

< 6.4E+00

< 1.0E+01

< 4.8E+00

< 9.7E+00

< 1.3E+01

< 5.7E+00

< 5.5E+00

< 3.4E+01

< 1.1E+01 MW-137 8/14/2019 pCi/L

< 2.9E+00

< 3.0E+00

< 7.4E+00

< 2.6E+00

< 6.3E+00

< 3.3E+00

< 5.6E+00

< 8.1E+00

< 2.7E+00

< 3.2E+00

< 1.9E+01

< 5.5E+00 MW-139 8/14/2019 pCi/L

< 4.9E+00

< 5.0E+00

< 1.0E+01

< 4.3E+00

< 1.0E+01

< 4.4E+00

< 8.4E+00

< 1.2E+01

< 5.4E+00

< 4.8E+00

< 3.0E+01

< 1.0E+01 MW-141 8/14/2019 pCi/L

< 3.9E+00

< 5.2E+00

< 1.1E+01

< 4.5E+00

< 8.7E+00

< 5.0E+00

< 8.6E+00

< 1.3E+01

< 4.2E+00

< 4.1E+00

< 2.5E+01

< 1.0E+01 MW-151 8/14/2019 pCi/L

< 4.3E+00

< 4.5E+00

< 1.1E+01

< 5.1E+00

< 9.2E+00

< 4.9E+00

< 8.6E+00

< 1.4E+01

< 5.0E+00

< 4.1E+00

< 3.0E+01

< 8.7E+00 MW-153 8/14/2019 pCi/L

< 3.2E+00

< 3.3E+00

< 7.5E+00

< 2.5E+00

< 6.6E+00

< 3.3E+00

< 5.7E+00

< 8.3E+00

< 3.4E+00

< 3.1E+00

< 2.1E+01

< 7.0E+00 MW-161 8/14/2019 pCi/L

< 4.7E+00

< 5.7E+00

< 1.3E+01

< 5.2E+00

< 1.1E+01

< 5.8E+00

< 1.0E+01

< 1.5E+01

< 6.0E+00

< 5.5E+00

< 3.6E+01

< 1.2E+01 MW-164 8/14/2019 pCi/L

< 5.3E+00

< 5.2E+00

< 1.2E+01

< 4.6E+00

< 1.1E+01

< 5.5E+00

< 8.2E+00

< 1.3E+01

< 4.6E+00

< 4.9E+00

< 3.2E+01

< 1.1E+01 MW-165 8/14/2019 pCi/L

< 1.9E+00

< 2.2E+00

< 4.7E+00

< 2.3E+00

< 4.8E+00

< 2.2E+00

< 4.2E+00

< 7.6E+00

< 2.0E+00

< 2.3E+00

< 1.5E+01

< 5.2E+00 MW-165 8/14/2019 pCi/L

< 4.9E+00

< 4.8E+00

< 9.8E+00

< 4.7E+00

< 9.4E+00

< 5.6E+00

< 8.2E+00

< 1.4E+01

< 4.6E+00

< 4.7E+00

< 3.3E+01

< 9.8E+00 MW-170 8/14/2019 pCi/L

< 4.4E+00

< 4.4E+00

< 1.1E+01

< 3.7E+00

< 8.9E+00

< 4.1E+00

< 6.8E+00

< 1.3E+01

< 5.0E+00

< 3.3E+00

< 3.0E+01

< 1.4E+01 MW-178 8/14/2019 pCi/L

< 3.8E+00

< 3.7E+00

< 9.6E+00

< 3.3E+00

< 8.6E+00

< 4.6E+00

< 7.9E+00

< 1.1E+01

< 3.6E+00

< 4.1E+00

< 2.7E+01

< 8.4E+00 MW-179 8/14/2019 pCi/L

< 4.3E+00

< 4.1E+00

< 8.0E+00

< 3.5E+00

< 8.4E+00

< 3.7E+00

< 7.0E+00

< 9.3E+00

< 4.0E+00

< 4.0E+00

< 2.2E+01

< 6.4E+00 MW-182 8/14/2019 pCi/L

< 4.7E+00

< 5.5E+00

< 1.2E+01

< 3.8E+00

< 8.8E+00

< 5.8E+00

< 9.4E+00

< 1.4E+01

< 4.4E+00

< 4.5E+00

< 3.3E+01

< 9.3E+00 MW-186 8/14/2019 pCi/L

< 3.5E+00

< 3.5E+00

< 8.8E+00

< 3.2E+00

< 8.3E+00

< 3.9E+00

< 6.4E+00

< 1.3E+01

< 3.8E+00

< 3.8E+00

< 2.7E+01

< 1.1E+01 MW-187 8/14/2019 pCi/L

< 2.4E+00

< 3.7E+00

< 8.4E+00

< 4.3E+00

< 7.9E+00

< 4.0E+00

< 6.0E+00

< 1.1E+01

< 4.2E+00

< 3.0E+00

< 2.0E+01

< 9.5E+00

RBG-48013 Rev. 2019 Page 55 of 70 Annual Radioactive Effluent Release Report Page 12 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-188 8/14/2019 pCi/L

< 4.1E+00

< 4.2E+00

< 8.2E+00

< 4.9E+00

< 6.6E+00

< 4.2E+00

< 7.5E+00

< 1.3E+01

< 4.0E+00

< 3.8E+00

< 3.1E+01

< 9.7E+00 MW-201 8/14/2019 pCi/L

< 1.9E+00

< 2.3E+00

< 4.8E+00

< 2.0E+00

< 4.1E+00

< 2.4E+00

< 4.0E+00

< 1.1E+01

< 2.3E+00

< 2.0E+00

< 1.9E+01

< 6.8E+00 MW-203 8/14/2019 pCi/L

< 1.8E+00

< 2.2E+00

< 4.4E+00

< 2.0E+00

< 3.9E+00

< 1.9E+00

< 3.4E+00

< 9.9E+00

< 2.0E+00

< 1.8E+00

< 1.9E+01

< 5.5E+00 MW-209 8/14/2019 pCi/L

< 3.6E+00

< 3.5E+00

< 9.1E+00

< 3.8E+00

< 8.4E+00

< 4.3E+00

< 6.5E+00

< 1.4E+01

< 4.3E+00

< 3.7E+00

< 2.8E+01

< 7.3E+00 MW-219 8/14/2019 pCi/L

< 3.4E+00

< 4.6E+00

< 7.4E+00

< 4.2E+00

< 8.4E+00

< 3.7E+00

< 6.9E+00

< 1.4E+01

< 3.9E+00

< 3.5E+00

< 2.8E+01

< 1.1E+01 MW-221 8/14/2019 pCi/L

< 4.0E+00

< 4.0E+00

< 7.8E+00

< 4.4E+00

< 6.0E+00

< 4.2E+00

< 8.2E+00

< 1.4E+01

< 4.1E+00

< 4.1E+00

< 2.9E+01

< 9.1E+00 MW-221 8/14/2019 pCi/L

< 3.8E+00

< 4.4E+00

< 7.7E+00

< 3.7E+00

< 6.9E+00

< 3.8E+00

< 6.5E+00

< 1.4E+01

< 4.2E+00

< 3.5E+00

< 2.8E+01

< 1.0E+01 MW-223 8/14/2019 pCi/L

< 3.7E+00

< 3.9E+00

< 1.0E+01

< 4.2E+00

< 8.9E+00

< 5.0E+00

< 7.1E+00

< 1.4E+01

< 4.0E+00

< 4.1E+00

< 3.0E+01

< 9.0E+00 MW-223 8/14/2019 pCi/L

< 3.1E+00

< 3.5E+00

< 7.7E+00

< 4.6E+00

< 7.1E+00

< 4.4E+00

< 7.1E+00

< 1.4E+01

< 3.6E+00

< 3.6E+00

< 2.6E+01

< 9.5E+00 MW-225 8/14/2019 pCi/L

< 3.0E+00

< 3.9E+00

< 9.0E+00

< 4.4E+00

< 7.5E+00

< 3.6E+00

< 7.3E+00

< 1.4E+01

< 4.2E+00

< 4.0E+00

< 3.0E+01

< 1.0E+01 MW-231 8/14/2019 pCi/L

< 4.3E+00

< 4.4E+00

< 9.3E+00

< 4.1E+00

< 8.5E+00

< 5.3E+00

< 8.1E+00

< 1.4E+01

< 4.6E+00

< 4.2E+00

< 3.1E+01

< 1.1E+01 MW-233 8/14/2019 pCi/L

< 3.8E+00

< 3.9E+00

< 9.2E+00

< 4.7E+00

< 7.7E+00

< 5.0E+00

< 7.2E+00

< 1.4E+01

< 3.4E+00

< 3.9E+00

< 3.0E+01

< 7.3E+00 MW-235 8/14/2019 pCi/L

< 2.6E+00

< 2.6E+00

< 6.1E+00

< 2.7E+00

< 4.9E+00

< 2.7E+00

< 4.8E+00

< 8.2E+00

< 2.8E+00

< 2.7E+00

< 1.8E+01

< 6.1E+00 PZ-01 8/14/2019 pCi/L

< 5.3E+00

< 6.1E+00

< 1.0E+01

< 5.6E+00

< 9.4E+00

< 4.9E+00

< 7.5E+00

< 1.4E+01

< 4.7E+00

< 5.0E+00

< 3.2E+01

< 1.0E+01 SW-101 8/15/2019 pCi/L

< 4.0E+00

< 4.6E+00

< 9.9E+00

< 5.1E+00

< 9.3E+00

< 5.1E+00

< 8.3E+00

< 1.4E+01

< 4.5E+00

< 4.7E+00

< 3.2E+01

< 8.3E+00 SW-103 8/15/2019 pCi/L

< 3.9E+00

< 4.1E+00

< 8.2E+00

< 5.1E+00

< 8.4E+00

< 4.2E+00

< 8.5E+00

< 1.4E+01

< 4.4E+00

< 4.2E+00

< 3.3E+01

< 8.7E+00 SW-104 8/15/2019 pCi/L

< 4.1E+00

< 3.6E+00

< 8.2E+00

< 4.1E+00

< 7.5E+00

< 4.5E+00

< 6.1E+00

< 1.2E+01

< 4.7E+00

< 4.3E+00

< 2.3E+01

< 5.4E+00

RBG-48013 Rev. 2019 Page 56 of 70 Annual Radioactive Effluent Release Report Page 13 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-111 11/5/2019 pCi/L

< 8.0E+00

< 7.8E+00

< 1.8E+01

< 4.5E+00

< 1.7E+01

< 9.6E+00

< 1.4E+01

< 6.8E+01

< 5.2E+00

< 7.4E+00

< 9.3E+01

< 2.2E+01 MW-112 11/5/2019 pCi/L

< 6.0E+00

< 8.0E+00

< 1.3E+01

< 8.3E+00

< 1.3E+01

< 8.2E+00

< 1.2E+01

< 8.2E+01

< 7.2E+00

< 6.9E+00

< 1.0E+02

< 4.3E+01 MW-116 11/5/2019 pCi/L

< 3.6E+00

< 8.8E+00

< 2.3E+01

< 6.6E+00

< 1.5E+01

< 9.6E+00

< 1.4E+01

< 8.4E+01

< 8.3E+00

< 7.1E+00

< 1.1E+02

< 3.4E+01 MW-118 11/5/2019 pCi/L

< 8.5E+00

< 1.0E+01

< 2.2E+01

< 4.8E+00

< 1.2E+01

< 9.6E+00

< 1.3E+01

< 8.9E+01

< 7.6E+00

< 8.1E+00

< 1.2E+02

< 3.6E+01 MW-124 11/5/2019 pCi/L

< 5.1E+00

< 7.8E+00

< 1.7E+01

< 5.9E+00

< 1.1E+01

< 9.4E+00

< 1.5E+01

< 8.0E+01

< 6.7E+00

< 6.0E+00

< 9.9E+01

< 3.4E+01 MW-125 11/5/2019 pCi/L

< 6.7E+00

< 1.0E+01

< 1.6E+01

< 1.1E+01

< 2.1E+01

< 1.0E+01

< 1.7E+01

< 9.5E+01

< 9.2E+00

< 8.5E+00

< 1.3E+02

< 3.9E+01 MW-125 11/5/2019 pCi/L

< 6.8E+00

< 9.6E+00

< 2.0E+01

< 7.0E+00

< 1.4E+01

< 1.0E+01

< 1.8E+01

< 8.7E+01

< 8.9E+00

< 7.6E+00

< 1.2E+02

< 4.1E+01 MW-137 11/5/2019 pCi/L

< 6.6E+00

< 8.4E+00

< 2.0E+01

< 7.1E+00

< 1.2E+01

< 9.6E+00

< 1.5E+01

< 7.4E+01

< 6.2E+00

< 5.5E+00

< 8.5E+01

< 3.9E+01 MW-137 11/5/2019 pCi/L

< 4.9E+00

< 8.5E+00

< 1.7E+01

< 5.8E+00

< 2.1E+01

< 1.1E+01

< 1.9E+01

< 9.2E+01

< 6.7E+00

< 7.9E+00

< 1.2E+02

< 3.0E+01 MW-139 11/5/2019 pCi/L

< 6.3E+00

< 7.3E+00

< 1.7E+01

< 6.1E+00

< 1.2E+01

< 8.9E+00

< 1.5E+01

< 8.6E+01

< 7.7E+00

< 7.4E+00

< 1.1E+02

< 3.2E+01 MW-141 11/5/2019 pCi/L

< 8.2E+00

< 9.9E+00

< 2.1E+01

< 8.3E+00

< 9.8E+00

< 8.0E+00

< 1.3E+01

< 7.4E+01

< 7.5E+00

< 4.9E+00

< 1.2E+02

< 3.2E+01 MW-142 11/5/2019 pCi/L

< 6.9E+00

< 8.1E+00

< 2.0E+01

< 6.0E+00

< 1.5E+01

< 9.4E+00

< 1.8E+01

< 8.8E+01

< 8.7E+00

< 6.6E+00

< 1.1E+02

< 3.7E+01 MW-144 11/5/2019 pCi/L

< 5.5E+00

< 9.8E+00

< 1.6E+01

< 8.0E+00

< 1.7E+01

< 8.9E+00

< 1.4E+01

< 8.4E+01

< 7.8E+00

< 6.8E+00

< 1.1E+02

< 3.1E+01 MW-146 11/5/2019 pCi/L

< 5.8E+00

< 5.6E+00

< 2.4E+01

< 7.0E+00

< 1.9E+01

< 7.9E+00

< 1.5E+01

< 8.9E+01

< 6.0E+00

< 6.4E+00

< 1.0E+02

< 4.7E+01 MW-147 11/5/2019 pCi/L

< 7.2E+00

< 9.6E+00

< 2.4E+01

< 5.4E+00

< 1.5E+01

< 8.9E+00

< 1.7E+01

< 9.7E+01

< 7.6E+00

< 7.8E+00

< 1.3E+02

< 4.5E+01 MW-148 11/5/2019 pCi/L

< 7.0E+00

< 1.1E+01

< 2.5E+01

< 7.9E+00

< 1.7E+01

< 9.8E+00

< 2.1E+01

< 9.3E+01

< 8.0E+00

< 9.1E+00

< 1.2E+02

< 5.0E+01 MW-153 11/5/2019 pCi/L

< 5.9E+00

< 7.3E+00

< 1.9E+01

< 6.8E+00

< 1.5E+01

< 8.5E+00

< 1.3E+01

< 9.6E+01

< 7.5E+00

< 6.6E+00

< 9.9E+01

< 4.1E+01

RBG-48013 Rev. 2019 Page 57 of 70 Annual Radioactive Effluent Release Report Page 14 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-155 11/5/2019 pCi/L

< 8.1E+00

< 9.6E+00

< 2.5E+01

< 8.7E+00

< 1.5E+01

< 1.1E+01

< 1.8E+01

< 1.1E+02

< 8.5E+00

< 8.4E+00

< 1.2E+02

< 5.4E+01 MW-158 11/5/2019 pCi/L

< 5.4E+00

< 1.0E+01

< 2.0E+01

< 5.8E+00

< 9.6E+00

< 1.2E+01

< 1.6E+01

< 9.4E+01

< 7.5E+00

< 7.5E+00

< 1.1E+02

< 4.4E+01 MW-159 11/5/2019 pCi/L

< 8.1E+00

< 9.9E+00

< 2.2E+01

< 8.5E+00

< 1.8E+01

< 9.6E+00

< 1.8E+01

< 8.5E+01

< 8.3E+00

< 8.4E+00

< 1.2E+02

< 4.2E+01 MW-162 11/5/2019 pCi/L

< 7.2E+00

< 7.4E+00

< 2.4E+01

< 7.5E+00

< 1.8E+01

< 7.7E+00

< 1.5E+01

< 6.4E+01

< 8.3E+00

< 5.9E+00

< 8.7E+01

< 3.2E+01 MW-172 11/5/2019 pCi/L

< 7.2E+00

< 8.3E+00

< 1.8E+01

< 4.1E+00

< 1.6E+01

< 9.6E+00

< 1.2E+01

< 8.4E+01

< 5.7E+00

< 8.1E+00

< 9.9E+01

< 3.8E+01 MW-174 11/5/2019 pCi/L

< 5.3E+00

< 1.1E+01

< 1.7E+01

< 6.9E+00

< 1.5E+01

< 8.3E+00

< 1.6E+01

< 6.7E+01

< 8.0E+00

< 8.2E+00

< 1.0E+02

< 5.2E+01 MW-188 11/5/2019 pCi/L

< 6.3E+00

< 8.3E+00

< 1.6E+01

< 8.2E+00

< 1.7E+01

< 8.0E+00

< 1.5E+01

< 7.4E+01

< 8.9E+00

< 7.4E+00

< 1.0E+02

< 5.1E+01 MW-227 11/5/2019 pCi/L

< 7.5E+00

< 7.0E+00

< 1.9E+01

< 5.6E+00

< 1.6E+01

< 8.0E+00

< 1.2E+01

< 7.3E+01

< 7.1E+00

< 7.1E+00

< 9.5E+01

< 4.0E+01 MW-04 11/6/2019 pCi/L

< 6.0E+00

< 6.0E+00

< 1.4E+01

< 8.0E+00

< 1.4E+01

< 8.6E+00

< 1.2E+01

< 6.1E+01

< 4.5E+00

< 7.1E+00

< 8.5E+01

< 3.2E+01 MW-100 11/6/2019 pCi/L

< 6.4E+00

< 4.2E+00

< 2.0E+01

< 8.2E+00

< 1.2E+01

< 8.7E+00

< 1.5E+01

< 5.1E+01

< 7.7E+00

< 7.8E+00

< 9.7E+01

< 2.9E+01 MW-103 11/6/2019 pCi/L

< 7.4E+00

< 7.0E+00

< 2.5E+01

< 9.8E+00

< 1.3E+01

< 6.4E+00

< 1.6E+01

< 5.7E+01

< 6.8E+00

< 5.7E+00

< 9.9E+01

< 3.6E+01 MW-104 11/6/2019 pCi/L

< 6.1E+00

< 6.8E+00

< 1.7E+01

< 5.9E+00

< 8.3E+00

< 6.5E+00

< 1.1E+01

< 5.4E+01

< 6.4E+00

< 5.4E+00

< 7.0E+01

< 2.5E+01 MW-104 11/6/2019 pCi/L

< 7.2E+00

< 1.2E+01

< 2.3E+01

< 7.7E+00

< 2.3E+01

< 9.1E+00

< 1.7E+01

< 7.1E+01

< 7.9E+00

< 7.0E+00

< 1.1E+02

< 3.1E+01 MW-106 11/6/2019 pCi/L

< 4.6E+00

< 8.3E+00

< 1.3E+01

< 6.4E+00

< 1.4E+01

< 9.0E+00

< 1.4E+01

< 6.3E+01

< 6.5E+00

< 5.5E+00

< 9.9E+01

< 3.3E+01 MW-110 11/6/2019 pCi/L

< 6.3E+00

< 6.9E+00

< 1.8E+01

< 6.0E+00

< 1.2E+01

< 7.3E+00

< 1.2E+01

< 7.0E+01

< 7.0E+00

< 6.0E+00

< 8.7E+01

< 3.3E+01 MW-114 11/6/2019 pCi/L

< 7.9E+00

< 8.0E+00

< 1.8E+01

< 6.4E+00

< 1.7E+01

< 7.5E+00

< 1.5E+01

< 8.3E+01

< 7.9E+00

< 6.3E+00

< 1.0E+02

< 2.8E+01 MW-126 11/6/2019 pCi/L

< 8.1E+00

< 8.3E+00

< 2.8E+01

< 7.9E+00

< 1.8E+01

< 8.6E+00

< 1.6E+01

< 7.4E+01

< 7.6E+00

< 7.7E+00

< 9.9E+01

< 4.0E+01

RBG-48013 Rev. 2019 Page 58 of 70 Annual Radioactive Effluent Release Report Page 15 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-126 11/6/2019 pCi/L

< 6.8E+00

< 6.7E+00

< 1.9E+01

< 7.3E+00

< 1.4E+01

< 8.6E+00

< 1.4E+01

< 6.3E+01

< 7.4E+00

< 6.3E+00

< 1.1E+02

< 3.7E+01 MW-128 11/6/2019 pCi/L

< 7.6E+00

< 9.0E+00

< 2.1E+01

< 9.2E+00

< 1.3E+01

< 1.0E+01

< 1.3E+01

< 6.5E+01

< 9.3E+00

< 7.5E+00

< 7.8E+01

< 3.6E+01 MW-130 11/6/2019 pCi/L

< 6.6E+00

< 7.7E+00

< 2.0E+01

< 6.8E+00

< 1.9E+01

< 9.2E+00

< 1.3E+01

< 6.7E+01

< 5.8E+00

< 7.3E+00

< 1.1E+02

< 3.5E+01 MW-14 11/6/2019 pCi/L

< 8.3E+00

< 9.5E+00

< 2.2E+01

< 7.2E+00

< 1.6E+01

< 8.8E+00

< 2.0E+01

< 6.8E+01

< 9.8E+00

< 7.5E+00

< 1.1E+02

< 3.5E+01 MW-151 11/6/2019 pCi/L

< 3.6E+00

< 9.2E+00

< 2.4E+01

< 5.1E+00

< 1.1E+01

< 9.5E+00

< 1.4E+01

< 7.2E+01

< 8.3E+00

< 7.4E+00

< 1.1E+02

< 4.1E+01 MW-156 11/6/2019 pCi/L

< 7.7E+00

< 8.2E+00

< 2.2E+01

< 8.3E+00

< 1.5E+01

< 1.1E+01

< 1.6E+01

< 9.3E+01

< 7.7E+00

< 5.4E+00

< 1.0E+02

< 4.5E+01 MW-157 11/6/2019 pCi/L

< 5.2E+00

< 6.1E+00

< 1.7E+01

< 5.5E+00

< 1.1E+01

< 6.5E+00

< 1.2E+01

< 6.3E+01

< 5.6E+00

< 4.4E+00

< 8.1E+01

< 3.6E+01 MW-161 11/6/2019 pCi/L

< 7.1E+00

< 7.2E+00

< 1.7E+01

< 7.0E+00

< 1.7E+01

< 8.2E+00

< 1.2E+01

< 6.8E+01

< 8.3E+00

< 7.3E+00

< 9.0E+01

< 3.4E+01 MW-164 11/6/2019 pCi/L

< 8.4E+00

< 7.6E+00

< 2.6E+01

< 6.8E+00

< 1.5E+01

< 7.5E+00

< 1.4E+01

< 7.8E+01

< 9.6E+00

< 5.9E+00

< 1.0E+02

< 2.7E+01 MW-165 11/6/2019 pCi/L

< 6.2E+00

< 8.0E+00

< 1.9E+01

< 6.2E+00

< 1.7E+01

< 8.0E+00

< 1.6E+01

< 6.8E+01

< 7.9E+00

< 7.6E+00

< 1.0E+02

< 3.3E+01 MW-178 11/6/2019 pCi/L

< 5.8E+00

< 6.8E+00

< 1.7E+01

< 6.9E+00

< 1.2E+01

< 8.5E+00

< 1.3E+01

< 7.4E+01

< 8.7E+00

< 6.0E+00

< 9.6E+01

< 3.4E+01 MW-179 11/6/2019 pCi/L

< 8.0E+00

< 9.9E+00

< 2.2E+01

< 7.4E+00

< 1.6E+01

< 1.1E+01

< 1.7E+01

< 8.1E+01

< 9.9E+00

< 8.3E+00

< 1.1E+02

< 4.7E+01 MW-18 11/6/2019 pCi/L

< 8.8E+00

< 9.5E+00

< 2.3E+01

< 1.1E+01

< 1.8E+01

< 8.3E+00

< 1.6E+01

< 7.2E+01

< 5.6E+00

< 6.2E+00

< 7.3E+01

< 2.7E+01 MW-185 11/6/2019 pCi/L

< 6.9E+00

< 1.0E+01

< 2.3E+01

< 8.2E+00

< 1.5E+01

< 7.5E+00

< 1.2E+01

< 8.6E+01

< 9.4E+00

< 7.4E+00

< 1.1E+02

< 4.4E+01 MW-186 11/6/2019 pCi/L

< 6.1E+00

< 8.0E+00

< 1.8E+01

< 8.5E+00

< 1.8E+01

< 9.5E+00

< 1.4E+01

< 7.7E+01

< 9.7E+00

< 7.3E+00

< 1.0E+02

< 2.3E+01 MW-187 11/6/2019 pCi/L

< 9.0E+00

< 1.1E+01

< 1.8E+01

< 8.2E+00

< 2.0E+01

< 1.3E+01

< 1.8E+01

< 9.1E+01

< 8.3E+00

< 8.6E+00

< 1.2E+02

< 3.3E+01 MW-201 11/6/2019 pCi/L

< 5.7E+00

< 9.5E+00

< 1.6E+01

< 9.8E+00

< 1.9E+01

< 7.1E+00

< 1.5E+01

< 5.9E+01

< 7.7E+00

< 6.8E+00

< 9.2E+01

< 4.0E+01

RBG-48013 Rev. 2019 Page 59 of 70 Annual Radioactive Effluent Release Report Page 16 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-203 11/6/2019 pCi/L

< 5.0E+00

< 8.3E+00

< 2.1E+01

< 8.2E+00

< 8.7E+00

< 9.8E+00

< 1.3E+01

< 5.2E+01

< 6.8E+00

< 6.5E+00

< 8.1E+01

< 2.7E+01 MW-205 11/6/2019 pCi/L

< 6.8E+00

< 6.1E+00

< 2.3E+01

< 5.6E+00

< 1.5E+01

< 1.1E+01

< 1.2E+01

< 6.5E+01

< 6.9E+00

< 4.6E+00

< 1.0E+02

< 3.4E+01 MW-205 11/6/2019 pCi/L

< 5.5E+00

< 5.4E+00

< 1.8E+01

< 5.9E+00

< 9.8E+00

< 6.5E+00

< 1.2E+01

< 5.8E+01

< 7.0E+00

< 4.5E+00

< 9.1E+01

< 2.3E+01 MW-209 11/6/2019 pCi/L

< 6.9E+00

< 4.7E+00

< 2.1E+01

< 7.8E+00

< 1.6E+01

< 7.6E+00

< 1.5E+01

< 6.5E+01

< 4.2E+00

< 6.2E+00

< 8.2E+01

< 2.7E+01 MW-209 11/6/2019 pCi/L

< 9.1E+00

< 1.0E+01

< 2.5E+01

< 7.1E+00

< 1.7E+01

< 9.2E+00

< 1.9E+01

< 7.0E+01

< 6.9E+00

< 9.8E+00

< 1.4E+02

< 2.5E+01 MW-8 11/6/2019 pCi/L

< 8.6E+00

< 9.1E+00

< 1.9E+01

< 8.7E+00

< 1.6E+01

< 1.2E+01

< 1.5E+01

< 7.2E+01

< 8.5E+00

< 7.7E+00

< 1.0E+02

< 2.8E+01 PZ-01 11/6/2019 pCi/L

< 7.7E+00

< 9.6E+00

< 1.7E+01

< 9.8E+00

< 1.6E+01

< 1.2E+01

< 1.7E+01

< 8.1E+01

< 7.7E+00

< 8.0E+00

< 1.1E+02

< 3.6E+01 PZ-03 11/6/2019 pCi/L

< 6.6E+00

< 6.8E+00

< 1.9E+01

< 9.4E+00

< 1.4E+01

< 7.4E+00

< 1.4E+01

< 6.4E+01

< 6.7E+00

< 6.6E+00

< 1.0E+02

< 2.6E+01 T-14 11/6/2019 pCi/L

< 6.4E+00

< 5.8E+00

< 2.4E+01

< 6.9E+00

< 1.8E+01

< 8.6E+00

< 2.0E+01

< 7.4E+01

< 7.2E+00

< 7.9E+00

< 8.3E+01

< 5.1E+01 MW-05 11/7/2019 pCi/L

< 8.2E+00

< 9.6E+00

< 2.3E+01

< 6.8E+00

< 1.6E+01

< 9.2E+00

< 2.0E+01

< 6.6E+01

< 8.1E+00

< 8.0E+00

< 1.2E+02

< 3.5E+01 MW-107 11/7/2019 pCi/L

< 7.6E+00

< 7.9E+00

< 2.0E+01

< 4.2E+00

< 1.3E+01

< 7.8E+00

< 1.2E+01

< 6.2E+01

< 6.2E+00

< 4.9E+00

< 7.2E+01

< 1.5E+01 MW-108 11/7/2019 pCi/L

< 4.9E+00

< 6.4E+00

< 1.6E+01

< 5.5E+00

< 1.5E+01

< 9.8E+00

< 1.7E+01

< 5.9E+01

< 6.6E+00

< 7.0E+00

< 8.4E+01

< 3.7E+01 MW-120 11/7/2019 pCi/L

< 7.1E+00

< 8.7E+00

< 1.8E+01

< 9.5E+00

< 1.8E+01

< 9.9E+00

< 1.2E+01

< 7.7E+01

< 4.2E+00

< 6.8E+00

< 7.9E+01

< 3.0E+01 MW-127 11/7/2019 pCi/L

< 6.8E+00

< 9.9E+00

< 2.0E+01

< 7.5E+00

< 4.7E+00

< 9.8E+00

< 1.5E+01

< 7.5E+01

< 7.2E+00

< 8.7E+00

< 1.3E+02

< 4.4E+01 MW-131 11/7/2019 pCi/L

< 6.6E+00

< 9.0E+00

< 2.0E+01

< 7.8E+00

< 1.1E+01

< 9.0E+00

< 1.7E+01

< 6.6E+01

< 6.9E+00

< 5.1E+00

< 8.5E+01

< 3.4E+01 MW-132 11/7/2019 pCi/L

< 6.5E+00

< 6.8E+00

< 2.1E+01

< 8.6E+00

< 1.9E+01

< 8.0E+00

< 1.7E+01

< 6.5E+01

< 5.1E+00

< 7.5E+00

< 1.0E+02

< 3.1E+01 MW-134 11/7/2019 pCi/L

< 6.4E+00

< 8.0E+00

< 1.5E+01

< 6.2E+00

< 1.1E+01

< 8.6E+00

< 1.3E+01

< 5.4E+01

< 7.5E+00

< 6.5E+00

< 7.6E+01

< 3.7E+01

RBG-48013 Rev. 2019 Page 60 of 70 Annual Radioactive Effluent Release Report Page 17 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-167 11/7/2019 pCi/L

< 6.0E+00

< 9.2E+00

< 1.7E+01

< 7.3E+00

< 9.6E+00

< 7.3E+00

< 1.5E+01

< 6.7E+01

< 7.0E+00

< 8.5E+00

< 1.2E+02

< 4.3E+01 MW-169 11/7/2019 pCi/L

< 8.2E+00

< 1.1E+01

< 2.0E+01

< 6.9E+00

< 1.6E+01

< 9.7E+00

< 1.4E+01

< 7.5E+01

< 7.2E+00

< 8.0E+00

< 1.0E+02

< 3.7E+01 MW-170 11/7/2019 pCi/L

< 7.9E+00

< 9.6E+00

< 2.8E+01

< 7.8E+00

< 1.5E+01

< 1.0E+01

< 1.5E+01

< 6.2E+01

< 8.8E+00

< 7.2E+00

< 1.1E+02

< 4.0E+01 MW-180 11/7/2019 pCi/L

< 7.9E+00

< 9.4E+00

< 2.3E+01

< 9.1E+00

< 1.4E+01

< 9.8E+00

< 1.2E+01

< 7.0E+01

< 8.8E+00

< 6.1E+00

< 9.0E+01

< 3.7E+01 MW-182 11/7/2019 pCi/L

< 7.5E+00

< 8.6E+00

< 2.0E+01

< 6.2E+00

< 1.3E+01

< 8.7E+00

< 1.4E+01

< 6.9E+01

< 6.9E+00

< 6.4E+00

< 1.0E+02

< 3.4E+01 MW-207 11/7/2019 pCi/L

< 8.7E+00

< 8.5E+00

< 2.1E+01

< 9.5E+00

< 1.7E+01

< 8.0E+00

< 1.8E+01

< 7.6E+01

< 8.4E+00

< 7.7E+00

< 9.3E+01

< 5.2E+01 MW-211 11/7/2019 pCi/L

< 6.9E+00

< 6.7E+00

< 1.7E+01

< 7.2E+00

< 1.3E+01

< 7.9E+00

< 1.5E+01

< 5.7E+01

< 6.6E+00

< 6.6E+00

< 8.0E+01

< 3.0E+01 MW-213 11/7/2019 pCi/L

< 7.1E+00

< 7.5E+00

< 1.9E+01

< 7.1E+00

< 1.6E+01

< 9.8E+00

< 1.6E+01

< 6.6E+01

< 7.6E+00

< 8.0E+00

< 9.9E+01

< 1.9E+01 MW-215 11/7/2019 pCi/L

< 8.8E+00

< 9.1E+00

< 1.9E+01

< 6.5E+00

< 1.6E+01

< 9.9E+00

< 1.6E+01

< 8.1E+01

< 9.1E+00

< 7.4E+00

< 1.2E+02

< 3.6E+01 MW-217 11/7/2019 pCi/L

< 8.9E+00

< 9.0E+00

< 1.5E+01

< 7.1E+00

< 1.8E+01

< 1.0E+01

< 1.8E+01

< 6.9E+01

< 8.0E+00

< 8.0E+00

< 1.0E+02

< 3.1E+01 MW-219 11/7/2019 pCi/L

< 5.8E+00

< 6.6E+00

< 1.7E+01

< 5.9E+00

< 1.0E+01

< 6.9E+00

< 1.2E+01

< 4.8E+01

< 6.3E+00

< 5.8E+00

< 7.6E+01

< 2.6E+01 MW-221 11/7/2019 pCi/L

< 7.5E+00

< 9.4E+00

< 2.4E+01

< 8.0E+00

< 1.2E+01

< 7.8E+00

< 1.3E+01

< 5.9E+01

< 6.2E+00

< 8.0E+00

< 8.6E+01

< 3.2E+01 MW-223 11/7/2019 pCi/L

< 6.6E+00

< 7.2E+00

< 1.8E+01

< 6.9E+00

< 1.6E+01

< 8.8E+00

< 1.3E+01

< 6.3E+01

< 6.1E+00

< 6.1E+00

< 8.5E+01

< 3.3E+01 MW-225 11/7/2019 pCi/L

< 5.2E+00

< 9.0E+00

< 2.2E+01

< 8.1E+00

< 1.2E+01

< 1.2E+01

< 1.8E+01

< 6.0E+01

< 7.9E+00

< 6.4E+00

< 1.3E+02

< 3.4E+01 MW-229 11/7/2019 pCi/L

< 6.7E+00

< 8.4E+00

< 1.9E+01

< 7.3E+00

< 1.6E+01

< 9.7E+00

< 1.4E+01

< 7.5E+01

< 5.7E+00

< 6.5E+00

< 8.8E+01

< 3.8E+01 MW-229 11/7/2019 pCi/L

< 6.5E+00

< 6.1E+00

< 1.4E+01

< 6.4E+00

< 1.4E+01

< 6.4E+00

< 9.8E+00

< 4.7E+01

< 4.1E+00

< 5.7E+00

< 7.4E+01

< 2.3E+01 MW-231 11/7/2019 pCi/L

< 5.6E+00

< 8.6E+00

< 1.9E+01

< 7.8E+00

< 1.5E+01

< 6.5E+00

< 1.5E+01

< 5.9E+01

< 7.1E+00

< 7.4E+00

< 7.6E+01

< 3.6E+01

RBG-48013 Rev. 2019 Page 61 of 70 Annual Radioactive Effluent Release Report Page 18 of 27 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 MW-233 11/7/2019 pCi/L

< 7.3E+00

< 9.1E+00

< 2.0E+01

< 9.6E+00

< 1.9E+01

< 1.3E+01

< 2.1E+01

< 8.1E+01

< 8.8E+00

< 9.2E+00

< 1.2E+02

< 3.5E+01 MW-235 11/7/2019 pCi/L

< 4.0E+00

< 6.0E+00

< 1.3E+01

< 5.2E+00

< 1.2E+01

< 5.0E+00

< 1.1E+01

< 4.6E+01

< 6.2E+00

< 5.8E+00

< 7.8E+01

< 2.9E+01 SW-103 11/7/2019 pCi/L

< 7.8E+00

< 5.6E+00

< 1.8E+01

< 6.6E+00

< 1.4E+01

< 8.9E+00

< 1.5E+01

< 6.1E+01

< 6.2E+00

< 8.0E+00

< 1.1E+02

< 2.9E+01 SW-104 11/7/2019 pCi/L

< 7.0E+00

< 7.3E+00

< 1.8E+01

< 7.0E+00

< 1.2E+01

< 9.0E+00

< 1.3E+01

< 4.8E+01

< 6.7E+00

< 5.9E+00

< 8.3E+01

< 2.8E+01 Table 18, Hard to Detect Nuclides Station ID Sample Date Units FE-55 NI-63 SR-89 SR-90 CM-242 CM-243/244 PU-238 MW-158 02/19/2019 1102 pCi/L

< 2.5E+01

< 1.9E+01

< 1.1E+01

< 8.9E-01

< 1.3E-02

< 6.1E-02

< 2.3E-02

RBG-48013 Rev. 2019 Page 62 of 70 Annual Radioactive Effluent Release Report Page 19 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-100 2/19/2019 pCi/L

< 4.7E+02 MW-205 2/19/2019 pCi/L

< 4.8E+02 MW-124 2/19/2019 pCi/L 4.60E+04 MW-207 2/19/2019 pCi/L

< 4.8E+02 MW-125 2/19/2019 pCi/L 5.70E+05 MW-211 2/19/2019 pCi/L 6.40E+02 MW-142 2/19/2019 pCi/L

< 5.0E+02 MW-211 2/19/2019 pCi/L

< 4.6E+02 MW-144 2/19/2019 pCi/L

< 4.7E+02 MW-213 2/19/2019 pCi/L

< 4.8E+02 MW-146 2/19/2019 pCi/L 1.60E+05 MW-213 2/19/2019 pCi/L

< 4.7E+02 MW-147 2/19/2019 pCi/L 6.80E+04 MW-215 2/19/2019 pCi/L

< 5.2E+02 MW-148 2/19/2019 pCi/L

< 4.8E+02 MW-217 2/19/2019 pCi/L

< 4.7E+02 MW-148 2/19/2019 pCi/L

< 4.7E+02 MW-227 2/19/2019 pCi/L

< 4.8E+02 MW-155 2/19/2019 pCi/L 1.10E+05 MW-229 2/19/2019 pCi/L

< 4.7E+02 MW-156 2/19/2019 pCi/L 4.20E+03 MW-110 2/20/2019 pCi/L 2.90E+04 MW-157 2/19/2019 pCi/L 2.00E+05 MW-112 2/20/2019 pCi/L 5.70E+03 MW-158 2/19/2019 pCi/L 6.00E+05 MW-114 2/20/2019 pCi/L 2.00E+03 MW-159 2/19/2019 pCi/L 6.60E+03 MW-116 2/20/2019 pCi/L 6.00E+03 MW-159 2/19/2019 pCi/L 7.80E+03 MW-118 2/20/2019 pCi/L 3.60E+03 MW-162 2/19/2019 pCi/L

< 4.7E+02 MW-137 2/20/2019 pCi/L 1.20E+04 MW-188 2/19/2019 pCi/L

< 4.7E+02 MW-139 2/20/2019 pCi/L 6.80E+02

RBG-48013 Rev. 2019 Page 63 of 70 Annual Radioactive Effluent Release Report Page 20 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-141 2/20/2019 pCi/L 3.40E+03 MW-221 2/20/2019 pCi/L

< 5.1E+02 MW-151 2/20/2019 pCi/L

< 4.7E+02 MW-223 2/20/2019 pCi/L

< 4.8E+02 MW-153 2/20/2019 pCi/L 1.30E+03 MW-225 2/20/2019 pCi/L

< 4.7E+02 MW-161 2/20/2019 pCi/L 1.30E+03 MW-231 2/20/2019 pCi/L

< 4.7E+02 MW-164 2/20/2019 pCi/L

< 4.7E+02 MW-233 2/20/2019 pCi/L

< 4.7E+02 MW-165 2/20/2019 pCi/L

< 4.7E+02 MW-235 2/20/2019 pCi/L

< 4.7E+02 MW-165 2/20/2019 pCi/L

< 4.6E+02 PZ-01 2/20/2019 pCi/L 7.40E+04 MW-170 2/20/2019 pCi/L

< 4.7E+02 SW-101 2/21/2019 pCi/L

< 4.6E+02 MW-178 2/20/2019 pCi/L 4.90E+03 SW-102 2/21/2019 pCi/L

< 4.7E+02 MW-179 2/20/2019 pCi/L 2.60E+05 SW-103 2/21/2019 pCi/L

< 4.6E+02 MW-182 2/20/2019 pCi/L

< 4.8E+02 SW-104 2/21/2019 pCi/L

< 4.7E+02 MW-186 2/20/2019 pCi/L

< 4.7E+02 MW-158 4/17/2019 pCi/L 6.30E+05 MW-187 2/20/2019 pCi/L

< 4.8E+02 MW-124 5/14/2019 pCi/L 3.90E+04 MW-201 2/20/2019 pCi/L

< 4.6E+02 MW-124 5/14/2019 pCi/L 5.10E+04 MW-203 2/20/2019 pCi/L

< 4.8E+02 MW-125 5/14/2019 pCi/L 4.50E+05 MW-209 2/20/2019 pCi/L

< 4.7E+02 MW-142 5/14/2019 pCi/L

< 5.3E+02 MW-219 2/20/2019 pCi/L

< 4.7E+02 MW-144 5/14/2019 pCi/L

< 5.3E+02

RBG-48013 Rev. 2019 Page 64 of 70 Annual Radioactive Effluent Release Report Page 21 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-146 5/14/2019 pCi/L 9.30E+04 MW-137 5/15/2019 pCi/L 1.20E+04 MW-147 5/14/2019 pCi/L 7.60E+04 MW-139 5/15/2019 pCi/L 6.30E+02 MW-148 5/14/2019 pCi/L

< 5.2E+02 MW-141 5/15/2019 pCi/L 2.50E+03 MW-156 5/14/2019 pCi/L 6.30E+03 MW-151 5/15/2019 pCi/L

< 5.2E+02 MW-157 5/14/2019 pCi/L 2.10E+05 MW-153 5/15/2019 pCi/L 9.80E+02 MW-157 5/14/2019 pCi/L 2.10E+05 MW-155 5/15/2019 pCi/L 1.50E+05 MW-158 5/14/2019 pCi/L 4.90E+05 MW-161 5/15/2019 pCi/L 7.40E+02 MW-159 5/14/2019 pCi/L 1.50E+04 MW-161 5/15/2019 pCi/L

< 5.1E+02 MW-162 5/14/2019 pCi/L

< 6.4E+02 MW-164 5/15/2019 pCi/L

< 5.7E+02 MW-100 5/15/2019 pCi/L

< 6.3E+02 MW-165 5/15/2019 pCi/L

< 5.5E+02 MW-110 5/15/2019 pCi/L 1.90E+04 MW-167 5/15/2019 pCi/L

< 6.2E+02 MW-112 5/15/2019 pCi/L 3.80E+03 MW-172 5/15/2019 pCi/L

< 5.7E+02 MW-114 5/15/2019 pCi/L 1.50E+03 MW-174 5/15/2019 pCi/L

< 5.6E+02 MW-116 5/15/2019 pCi/L 2.30E+03 MW-178 5/15/2019 pCi/L 4.40E+03 MW-118 5/15/2019 pCi/L 3.70E+03 MW-179 5/15/2019 pCi/L 2.30E+05 MW-131 5/15/2019 pCi/L

< 6.1E+02 MW-185 5/15/2019 pCi/L

< 6.3E+02 MW-132 5/15/2019 pCi/L

< 6.2E+02 MW-185 5/15/2019 pCi/L

< 6.2E+02

RBG-48013 Rev. 2019 Page 65 of 70 Annual Radioactive Effluent Release Report Page 22 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-186 5/15/2019 pCi/L

< 5.7E+02 MW-170 5/16/2019 pCi/L

< 6.3E+02 MW-187 5/15/2019 pCi/L

< 5.7E+02 MW-180 5/16/2019 pCi/L

< 6.2E+02 MW-201 5/15/2019 pCi/L

< 5.6E+02 MW-182 5/16/2019 pCi/L

< 6.2E+02 MW-203 5/15/2019 pCi/L

< 5.7E+02 MW-188 5/16/2019 pCi/L

< 5.7E+02 MW-211 5/15/2019 pCi/L

< 5.3E+02 MW-205 5/16/2019 pCi/L

< 5.6E+02 MW-213 5/15/2019 pCi/L

< 6.3E+02 MW-207 5/16/2019 pCi/L

< 6.3E+02 PZ-01 5/15/2019 pCi/L 6.30E+04 MW-209 5/16/2019 pCi/L

< 6.3E+02 PZ-03 5/15/2019 pCi/L

< 6.3E+02 MW-209 5/16/2019 pCi/L

< 6.2E+02 MW-106 5/16/2019 pCi/L

< 6.2E+02 MW-215 5/16/2019 pCi/L

< 6.2E+02 MW-120 5/16/2019 pCi/L

< 6.2E+02 MW-217 5/16/2019 pCi/L

< 6.1E+02 MW-122 5/16/2019 pCi/L

< 5.8E+02 MW-219 5/16/2019 pCi/L

< 6.2E+02 MW-126 5/16/2019 pCi/L

< 5.6E+02 MW-221 5/16/2019 pCi/L

< 5.8E+02 MW-126 5/16/2019 pCi/L

< 5.8E+02 MW-223 5/16/2019 pCi/L

< 5.7E+02 MW-128 5/16/2019 pCi/L

< 5.7E+02 MW-225 5/16/2019 pCi/L

< 6.2E+02 MW-130 5/16/2019 pCi/L

< 5.7E+02 MW-227 5/16/2019 pCi/L

< 5.7E+02 MW-134 5/16/2019 pCi/L

< 6.2E+02 MW-229 5/16/2019 pCi/L

< 6.2E+02 MW-169 5/16/2019 pCi/L

< 6.2E+02 MW-231 5/16/2019 pCi/L

< 6.3E+02

RBG-48013 Rev. 2019 Page 66 of 70 Annual Radioactive Effluent Release Report Page 23 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-231 5/16/2019 pCi/L

< 6.3E+02 MW-156 8/13/2019 pCi/L 3.70E+03 MW-233 5/16/2019 pCi/L

< 5.7E+02 MW-157 8/13/2019 pCi/L 1.90E+05 MW-235 5/16/2019 pCi/L

< 5.8E+02 MW-157 8/13/2019 pCi/L 2.10E+05 SW-101 5/16/2019 pCi/L

< 5.8E+02 MW-158 8/13/2019 pCi/L 4.70E+05 SW-102 5/16/2019 pCi/L

< 6.2E+02 MW-159 8/13/2019 pCi/L 2.10E+04 SW-103 5/16/2019 pCi/L

< 6.2E+02 MW-162 8/13/2019 pCi/L

< 6.0E+02 SW-104 5/16/2019 pCi/L

< 6.2E+02 MW-205 8/13/2019 pCi/L

< 6.4E+02 MW-100 8/13/2019 pCi/L

< 5.4E+02 MW-207 8/13/2019 pCi/L

< 5.5E+02 MW-124 8/13/2019 pCi/L 1.00E+05 MW-211 8/13/2019 pCi/L

< 5.4E+02 MW-125 8/13/2019 pCi/L 6.30E+05 MW-213 8/13/2019 pCi/L

< 5.4E+02 MW-142 8/13/2019 pCi/L

< 6.1E+02 MW-215 8/13/2019 pCi/L

< 5.4E+02 MW-144 8/13/2019 pCi/L 6.30E+02 MW-217 8/13/2019 pCi/L

< 5.5E+02 MW-146 8/13/2019 pCi/L 3.10E+04 MW-227 8/13/2019 pCi/L

< 6.4E+02 MW-147 8/13/2019 pCi/L 4.70E+03 MW-229 8/13/2019 pCi/L

< 6.0E+02 MW-148 8/13/2019 pCi/L 4.50E+03 MW-110 8/14/2019 pCi/L 1.50E+04 MW-155 8/13/2019 pCi/L 1.60E+05 MW-112 8/14/2019 pCi/L 3.40E+03 MW-156 8/13/2019 pCi/L 3.80E+03 MW-114 8/14/2019 pCi/L 1.20E+03

RBG-48013 Rev. 2019 Page 67 of 70 Annual Radioactive Effluent Release Report Page 24 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-116 8/14/2019 pCi/L 1.10E+03 MW-188 8/14/2019 pCi/L

< 6.6E+02 MW-118 8/14/2019 pCi/L 4.20E+03 MW-201 8/14/2019 pCi/L

< 5.9E+02 MW-137 8/14/2019 pCi/L 1.00E+04 MW-203 8/14/2019 pCi/L

< 6.0E+02 MW-139 8/14/2019 pCi/L

< 5.7E+02 MW-209 8/14/2019 pCi/L

< 6.2E+02 MW-141 8/14/2019 pCi/L 3.20E+03 MW-219 8/14/2019 pCi/L

< 6.1E+02 MW-151 8/14/2019 pCi/L

< 5.3E+02 MW-221 8/14/2019 pCi/L

< 6.0E+02 MW-153 8/14/2019 pCi/L 1.20E+03 MW-221 8/14/2019 pCi/L

< 6.0E+02 MW-161 8/14/2019 pCi/L 1.50E+03 MW-223 8/14/2019 pCi/L

< 6.6E+02 MW-164 8/14/2019 pCi/L

< 5.3E+02 MW-223 8/14/2019 pCi/L

< 6.5E+02 MW-165 8/14/2019 pCi/L

< 5.5E+02 MW-225 8/14/2019 pCi/L

< 6.1E+02 MW-165 8/14/2019 pCi/L

< 5.3E+02 MW-231 8/14/2019 pCi/L

< 5.9E+02 MW-170 8/14/2019 pCi/L

< 6.0E+02 MW-233 8/14/2019 pCi/L

< 6.2E+02 MW-178 8/14/2019 pCi/L 2.80E+03 MW-235 8/14/2019 pCi/L

< 5.4E+02 MW-179 8/14/2019 pCi/L 2.00E+05 PZ-01 8/14/2019 pCi/L 4.20E+04 MW-182 8/14/2019 pCi/L

< 5.4E+02 SW-101 8/15/2019 pCi/L

< 6.1E+02 MW-186 8/14/2019 pCi/L

< 6.6E+02 SW-103 8/15/2019 pCi/L

< 6.5E+02 MW-187 8/14/2019 pCi/L

< 6.7E+02 SW-104 8/15/2019 pCi/L

< 6.5E+02

RBG-48013 Rev. 2019 Page 68 of 70 Annual Radioactive Effluent Release Report Page 25 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-111 11/5/2019 pCi/L

< 5.9E+02 MW-155 11/5/2019 pCi/L 1.60E+05 MW-112 11/5/2019 pCi/L 3.70E+03 MW-158 11/5/2019 pCi/L 4.30E+05 MW-116 11/5/2019 pCi/L 3.40E+03 MW-159 11/5/2019 pCi/L 2.30E+04 MW-118 11/5/2019 pCi/L 6.00E+03 MW-162 11/5/2019 pCi/L

< 5.9E+02 MW-124 11/5/2019 pCi/L 1.70E+05 MW-172 11/5/2019 pCi/L

< 5.8E+02 MW-125 11/5/2019 pCi/L 6.10E+05 MW-174 11/5/2019 pCi/L

< 5.9E+02 MW-125 11/5/2019 pCi/L 6.00E+05 MW-188 11/5/2019 pCi/L

< 5.9E+02 MW-137 11/5/2019 pCi/L 2.80E+04 MW-227 11/5/2019 pCi/L

< 5.8E+02 MW-137 11/5/2019 pCi/L 2.50E+04 MW-04 11/6/2019 pCi/L

< 6.0E+02 MW-139 11/5/2019 pCi/L 6.10E+02 MW-100 11/6/2019 pCi/L

< 5.8E+02 MW-141 11/5/2019 pCi/L 3.10E+03 MW-103 11/6/2019 pCi/L

< 5.8E+02 MW-142 11/5/2019 pCi/L

< 5.9E+02 MW-104 11/6/2019 pCi/L

< 5.7E+02 MW-144 11/5/2019 pCi/L 6.40E+02 MW-104 11/6/2019 pCi/L

< 5.8E+02 MW-146 11/5/2019 pCi/L 1.60E+05 MW-106 11/6/2019 pCi/L

< 5.4E+02 MW-147 11/5/2019 pCi/L 6.90E+04 MW-110 11/6/2019 pCi/L 2.20E+04 MW-148 11/5/2019 pCi/L

< 5.0E+02 MW-114 11/6/2019 pCi/L 2.00E+03 MW-153 11/5/2019 pCi/L 1.20E+03 MW-126 11/6/2019 pCi/L 1.00E+03

RBG-48013 Rev. 2019 Page 69 of 70 Annual Radioactive Effluent Release Report Page 26 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-126 11/6/2019 pCi/L 1.30E+03 MW-203 11/6/2019 pCi/L

< 5.8E+02 MW-128 11/6/2019 pCi/L

< 5.8E+02 MW-205 11/6/2019 pCi/L

< 5.3E+02 MW-130 11/6/2019 pCi/L

< 5.3E+02 MW-205 11/6/2019 pCi/L

< 5.9E+02 MW-14 11/6/2019 pCi/L

< 5.8E+02 MW-209 11/6/2019 pCi/L 8.60E+02 MW-151 11/6/2019 pCi/L

< 5.4E+02 MW-209 11/6/2019 pCi/L

< 5.9E+02 MW-156 11/6/2019 pCi/L 2.90E+03 MW-8 11/6/2019 pCi/L

< 5.8E+02 MW-157 11/6/2019 pCi/L 2.20E+05 PZ-01 11/6/2019 pCi/L 4.30E+04 MW-161 11/6/2019 pCi/L 3.00E+03 PZ-03 11/6/2019 pCi/L

< 5.4E+02 MW-164 11/6/2019 pCi/L

< 5.8E+02 T-14 11/6/2019 pCi/L

< 5.9E+02 MW-165 11/6/2019 pCi/L

< 5.8E+02 MW-05 11/7/2019 pCi/L

< 5.9E+02 MW-178 11/6/2019 pCi/L 2.70E+03 MW-107 11/7/2019 pCi/L

< 5.8E+02 MW-179 11/6/2019 pCi/L 1.60E+05 MW-108 11/7/2019 pCi/L

< 5.8E+02 MW-18 11/6/2019 pCi/L

< 5.8E+02 MW-120 11/7/2019 pCi/L

< 5.8E+02 MW-185 11/6/2019 pCi/L

< 5.4E+02 MW-127 11/7/2019 pCi/L

< 5.4E+02 MW-186 11/6/2019 pCi/L

< 5.5E+02 MW-131 11/7/2019 pCi/L

< 5.5E+02 MW-187 11/6/2019 pCi/L

< 5.3E+02 MW-132 11/7/2019 pCi/L

< 5.3E+02 MW-201 11/6/2019 pCi/L

< 5.8E+02 MW-134 11/7/2019 pCi/L

< 5.8E+02

RBG-48013 Rev. 2019 Page 70 of 70 Annual Radioactive Effluent Release Report Page 27 of 27 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-167 11/7/2019 pCi/L

< 5.4E+02 MW-221 11/7/2019 pCi/L 7.00E+02 MW-169 11/7/2019 pCi/L

< 5.4E+02 MW-223 11/7/2019 pCi/L

< 5.8E+02 MW-170 11/7/2019 pCi/L

< 5.8E+02 MW-225 11/7/2019 pCi/L

< 5.8E+02 MW-180 11/7/2019 pCi/L

< 5.8E+02 MW-229 11/7/2019 pCi/L

< 5.8E+02 MW-182 11/7/2019 pCi/L

< 5.4E+02 MW-229 11/7/2019 pCi/L

< 5.8E+02 MW-207 11/7/2019 pCi/L

< 5.8E+02 MW-231 11/7/2019 pCi/L

< 5.8E+02 MW-211 11/7/2019 pCi/L

< 5.4E+02 MW-233 11/7/2019 pCi/L

< 5.7E+02 MW-213 11/7/2019 pCi/L

< 5.4E+02 MW-235 11/7/2019 pCi/L

< 5.8E+02 MW-215 11/7/2019 pCi/L

< 5.8E+02 SW-102 11/7/2019 pCi/L

< 5.5E+02 MW-217 11/7/2019 pCi/L

< 5.8E+02 SW-103 11/7/2019 pCi/L

< 5.4E+02 MW-219 11/7/2019 pCi/L

< 5.9E+02 SW-104 11/7/2019 pCi/L

< 5.8E+02

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