Text

2019 Annual Radiological Environmental Operating Report
	ML20121A007
Person / Time
Site:	Three Mile Island
Issue date:	04/30/2020
From:	Orth T; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	TMI-20-016
	Download: ML20121A007 (165)
	v • d • e

Three Mile Island Nuclear Station, Unit 1 441 S. P.O. Box 480 Middletown, PA 17057 TMI-20-016 April 30, 2020 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket Nos. 50-289 Three Mile Island Nuclear Station, Unit 2 Possession Only License No. DPR-73 NRC Docket No. 50-320

Subject:

2019 Annual Radiological Environmental Operating Report In accordance with TMI-1 Technical Specification 6.9.2.1 and TMI-2 Technical Specifications 6.8.1.1, enclosed is the Annual Radiological Environmental Operating Report covering the time period of January 1 through December 31, 2019, for the Three Mile Island Nuclear Station.

There are no commitments in this letter.

Should you have any questions concerning this letter, please contact Mr. Daniel Jordan, Chemistry/Environmental Specialist, at (717) 948-8470.

Respectfully, Trevor L. Orth Decommissioning Plant Manager Three Mile Island Nuclear Station, Unit 1

Attachment:

Three Mile Island 2019 Annual Radiological Environmental Operating Report

TMI-20-016 April 30, 2020 U. S. Nuclear Regulatory Commission Page 2 cc: w/Attachments Regional Administrator - NRC Region I

ATTACHMENT Three Mile Island Annual Radiological Environmental Operating Report

Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 Annual Radiological Environmental Operating Report 1 January through 31 December 2019 Prepared By Teledyne Brown Engineering Environmental Services Three Mile Island Nuclear Station Middletown, PA 17057 April 2020

Intentionally left blank Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 3 A. Objectives of the REMP ...................................................................................... 3 B. Implementation of the Objectives ........................................................................ 3 III. Program Description ...................................................................................................... 5 A. Sample Collection ............................................................................................... 5 B. Sample Analysis .................................................................................................. 7 C. Data Interpretation .............................................................................................. 8 D. Program Exceptions ............................................................................................ 9 E. Program Changes ............................................................................................. 10 IV. Results and Discussion ............................................................................................... 11 A. Aquatic Environment ......................................................................................... 11

1. Surface Water......................................................................................... 11

2. Drinking Water ........................................................................................ 11

3. Effluent Water ......................................................................................... 12

4. Storm Water ........................................................................................... 13

5. Ground Water ......................................................................................... 13

6. Fish ......................................................................................................... 13

7. Sediment................................................................................................. 14 B. Atmospheric Environment ................................................................................. 14

1. Airborne Particulates .............................................................................. 14

a. Air Particulates............................................................................. 14

b. Airborne Iodine ............................................................................ 15

2. Terrestrial ................................................................................................ 15

a. Milk............................................................................................... 15

b. Food Products ............................................................................. 16 C. Ambient Gamma Radiation ............................................................................... 16 D. Land Use Survey............................................................................................... 17 E. Radiological Impact of TMINS Operations ........................................................ 17 F. Errata Data ........................................................................................................ 24 G. Summary of Results - Inter-Laboratory Comparison Program ........................ 24 V. References ................................................................................................................... 28 i

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2019 Appendix B Location Designation, Distance & Direction And Sample Collection &

Analytical Methods Tables Table B-1 Location Designation and Identification System for the Three Mile Island Nuclear Station Table B-2 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2019 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2019 Figures Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2019 Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2019 Figure B-3 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2019 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-I.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-I.2 Concentrations of I-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-I.3 Concentrations of Gamma-Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 ii

Table C-II.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-II.2 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-II.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-II.4 Concentrations of Gamma-Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-III.1 Concentrations of Gross Beta, I-131, Tritium, and Strontium in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-III.2 Concentrations of Gamma-Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-IV.1 Concentrations of Strontium in Predator and Bottom Feeder (Fish)

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-IV.2 Concentrations of Gamma-Emitters in Predator and Bottom Feeder (Fish)

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-V.1 Concentrations of Gamma-Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-VI.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-VI.3 Concentrations of Gamma-Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-VII.1 Concentrations of I-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-VIII.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-VIII.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-VIII.3 Concentrations of Gamma-Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table C-IX.1 Concentrations of Strontium and Gamma-Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 iii

Table C-X.1 Quarterly OSLD Results for Three Mile Island Nuclear Station, 2019 Table C-X.2 Mean Quarterly OSLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2019 Table C-X.3 Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2019 Figures Figure C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2019 Figure C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2019 Figure C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2019 Figure C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2019 Figure C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2019 Figure C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2019 Figure C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2019 Figure C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2019 Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-I.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2019 Table D-I.2 Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table D-I.3 Concentrations of Iodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table D-I.4 Concentrations of Gamma-Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table D-II.1 Concentrations of Strontium and Gamma-Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table D-III.1 Concentrations of Gamma-Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 iv

Table D-IV.1 Concentrations of Gamma-Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table D-V.1 Concentrations of Gross Beta in Air Particulate and I-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table D-V.2 Concentrations of Gamma-Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table D-VI.1 Concentrations of I-131 by Chemical Separation, Gamma-Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Figures Figure D-1 Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2019 Figure D-2 Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2019 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2019 Table E-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2019 Table E-4 Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services, 2019 Table E-5 ERA Environmental Radioactivity Cross Check Program Exelon Industrial Services, 2019 Table E-6 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

GEL Laboratories, Inc., 2019 Table E-7 ERA Environmental Radioactivity Cross Check Program GEL Laboratories, Inc., 2019 Table E-8 Analytics Environmental Radioactivity Cross Check Program GEL Laboratories, Inc., 2019 Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) v

Intentionally Left Blank I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Three Mile Island Nuclear Station (TMINS) by Exelon covers the period 1 January 2019 through 31 December 2019. During that time period, 1,701 analyses were performed on 1,315 samples. In assessing all the data gathered for this report and comparing these results with preoperational data and operational REMP data, it was concluded that the operation of TMINS had no adverse radiological impact on the environment.

Surface, drinking and effluent water samples were analyzed for concentrations of tritium and gamma-emitting nuclides. Surface, drinking and effluent water samples were also analyzed for concentrations of Iodine-131 (I-131). Drinking and effluent water samples were also analyzed for concentrations of gross beta.

Effluent water samples were analyzed for concentrations of Strontium-89 (Sr-89) and Strontium-90 (Sr-90). All groundwater, precipitation water, and stormwater results are reported in the ARGPPR, Appendix F. No I-131, Sr-89 or Sr-90 activities were detected. Gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in 5 surface water samples and 8 monthly effluent water samples was due to TMINS activities or releases. No other fission or activation products potentially attributed to TMI liquid releases were detected.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma-emitting nuclides. Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected. No fission or activation products were detected in fish. Occasionally, Cs-137 is detected at very low levels (just above LLD) and is not distinguishable from background levels. Cs-137 was found in one sediment sample. No other fission or activation products were detected in sediment samples.

Air particulate samples were analyzed for concentrations of gross beta and gamma-emitting nuclides. Gross beta activity is consistent with data from previous years. Cosmogenic Beryllium-7 (Be-7) was detected at levels consistent with those detected in previous years. No other activation products were detected.

High-sensitivity I-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity for I-131.

Cow milk samples were analyzed for concentrations of I-131, gamma-emitting nuclides, Sr-89, and Sr-90. Concentrations of naturally-occurring Potassium-40 (K-40) were consistent with those detected in previous years. No I-131 or Sr-89 activities were detected. Sr-90 activity was detected in one indicator sample slightly above the MDC. Occasionally Sr-90 activities are detected and are consistent with those detected in previous years and were attributed to fallout from nuclear weapons testing. No other fission or activation products were found.

Food Product samples were analyzed for concentrations of gamma-emitting nuclides including I-131 and Sr-90. Strontium-90 activity was detected in both indicator and control samples. This was a result of plant uptake of Sr-90 in soil as a result of past nuclear weapons testing. Concentrations of naturally-occurring Be-7 and K-40 were consistent with those detected in previous years. No other fission or activation products were detected.

Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued. This change resulted in a slight change in process and reporting of quarterly results. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

In conclusion, radioactive materials related to TMINS operations were detected in environmental samples, but the measured concentrations were low and consistent with measured effluents. The environmental sample results verified that the doses received by the public from TMINS effluents in 2019 were well below applicable dose limits and only a small fraction of the doses received from natural background radiation. Additionally, the results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.

Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2019 did not have any adverse effects on the health of the public or on the environment.

II. Introduction The Three Mile Island Nuclear Station (TMINS), consisting of two pressurized water reactors (PWR), is located on the northern end of Three Mile Island in the Susquehanna River approximately 2.5 miles south of Middletown in Londonderry Township, Dauphin County, Pennsylvania. TMI-1 is owned and operated by Exelon and became operational in 1974. TMI-2 is operated by GPU Nuclear, Inc.

and owned by Metropolitan Edison (50%), Pennsylvania Electric (25%) and Jersey Central Power & Light (25%). TMI-2 became operational in 1978 and was shut down following the 1979 accident. At the end of 1993 TMI-2 was placed in a condition called Post-Defueling Monitored Storage. TMI-2 is maintained by Exelon under contract with GPU Nuclear.

A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Landauer and Exelon Industrial Services (EIS)/GEL Laboratories on samples collected during the period 1 January 2019 through 31 December 2019.

A. Objectives of the REMP The objectives of the REMP are to:

1. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

2. Provide data on measurable levels of radiation and radioactive materials in the site environs.

3. To verify in-plant controls for the containment of radioactive materials.

4. To determine buildup of long-lived radionuclides in the environment and changes in background radiation levels.

5. To provide reassurance to the public that the program is capable of adequately assessing impacts and identifying noteworthy changes in the radiological status of the environment.

6. To fulfill the requirements of the TMI-1 and TMI-2 Technical Specifications.

B. Implementation of the Objectives The implementation of the objectives is accomplished by:

1. Identifying significant exposure pathways.

2. Establishing baseline radiological data of media within those pathways.

3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

III. Program Description A. Sample Collection Samples for the TMINS REMP were collected for Exelon by Exelon Industrial Services, LLC (EIS) and Normandeau Associates, Inc. (NAI).

This section describes the general collection methods used by EIS & NAI to obtain environmental samples for the TMINS REMP in 2019. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by EIS &

NAI are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, fish and sediment. Two gallon water samples were collected monthly from continuous samplers located at two surface water locations (J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9-1), and one effluent water location (K1-1). A composite of weekly grab samples at one surface water location (A3-2) were collected. The control locations were A3-2 and Q9-1. All groundwater and storm water results are reported in the ARGPPR, Appendix F.

All water samples were collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream indicator (IND) location. Location IND could be affected by TMINS effluent releases. Sediment samples composed of recently deposited substrate were collected semiannually at three locations (A1-3, J2-1 and K1-3).

Location A1-3 was the control.

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulates and airborne iodine. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1 and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product. Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K15-3 and P4-1) from March through November, and monthly from December through February. The control location was K15-3. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory.

Food products were collected from June through October at three locations (B10-2, E1-2 and H1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2 and H1-2). B10-2 was the control location for both annual and monthly sampling. Three different kinds of vegetation samples and eleven different kinds of vegetation leaves were collected, placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics.

The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation). The OSLDs were placed at locations on and around the TMINS site as follows:

A site boundary ring consisting of 19 locations (A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, L1-1, M1-1, N1-3, P1-2, Q1-2 and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release.

An indicator ring consisting of 60 locations (A3-1, A5-1, A9-3, B1-1, B2-1, B5-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1 and R9-1) extending to approximately 10 miles from the site, designed to measure possible exposures to close-in population.

The balance of 11 locations (D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1) represent control areas.

The specific dosimeter locations were determined by the following criteria:

1. The presence of relatively dense population

2. Site meteorological data taking into account distance and elevation for each of the sixteen 221/2 degree sectors around the site, where estimated annual dose from TMINS, if any, would be most significant

3. On hills free from local obstructions and within sight of the vents (where practical)

4. And near the closest dwelling to the vents in the prevailing downwind direction Each station has two Al2O3:C Optically Stimulated Luminescence Dosimeters enclosed in plastic placed at each location in a frame located approximately 3-6 feet above ground level. Since each OSLD responds to radiation independently, this provides two independent detectors at each station.

B. Sample Analysis This section describes the general analytical methods used by TBE and EIS to analyze the environmental samples for radioactivity for the TMINS REMP in 2019. The analytical procedures used by the laboratories are listed in Table B-3.

In order to achieve the stated objectives the current program includes the following analyses:

1. Concentrations of beta-emitters in drinking and effluent water and air particulates

2. Concentrations of gamma-emitters in surface, drinking, and effluent water, air particulates, milk, fish, sediment and food products

3. Concentrations of tritium in surface, drinking and effluent water

4. Concentrations of I-131 in surface, drinking and effluent water, air, milk and food products

5. Concentrations of strontium in effluent water, fish, milk and food products

6. Ambient gamma radiation levels at various site environs C. Data Interpretation Data were compared to previous years' operational data for consistency and trending. In addition, comparison to pre-operational data is sometimes made. For the purpose of this report, TMINS was considered operational at initial criticality. Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5%

probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required TMINS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.

Gamma spectroscopy results for each type of sample were grouped as follows:

For surface, drinking, and effluent water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 MDCs were reported.

For fish eight nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134 and Cs-137 MDCs were reported.

For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-134 and Cs-137 MDCs were reported.

For air particulate eight nuclides, Be-7, Mn-54, Co-58, Co-60, Nb-95, Zn-95, Cs-134 and Cs-137 MDCs were reported.

For milk five nuclides, K-40, Cs-134, Cs-137, Ba-140 and La-140 MDCs were reported.

For food products five nuclides, Be-7, K-40, I-131, Cs-134 and Cs-137 MDCs were reported.

Means and standard deviations of the results were calculated. The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.

D. Program Exceptions For 2019, the TMINS REMP had a sample recovery rate of 99.5%. Issue Reports (IR) were initiated to document significant exceptions and missing samples. All exceptions are listed below:

Water

1. J1-2 (Surface Water)

For the sampling periods 1/30/19 - 3/27/19, 3/27/19 - 6/17/19 and 6/27/19 - 8/10/19, compensatory grab samples were required due to the sample line being pulled into the river and disconnected. There was not an immediate ability to replace the sample tube because of adverse seasonal conditions. (IRs 04240350 and 04266250)

Dosimetry

1. N1-1 For the sampling periods 3/20/19 - 6/21/19 and 6/21/19 - 9/22/19, the dosimeters for this subgroup were found to be missing at the time of change out, likely due to vandalism. (IRs 04291991 and 04258998)

2. R15-1 On 12/20/19, the dosimeters were missing for the period 09-09-19 20-19 and not found. (IR 04306154)

Air

1. E1-2 For the 5/30/19 - 6/7/19 sampling period, sample was missed due to a tripped GFCI outlet and the timer reading 24.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (not enough for a valid sample). (IR 04255157)

2. E1-2 For the sampling period 7/20/19 - 7/27/19, the sampler was found out of operation. The sampler was repaired, but the weekly sample was invalid. (IR 04291955)

Milk

1. E2-2 For the sampling periods of 1/1/19 - 3/31/19, 4/3/19 - 6/26/19 and 06/27/19 - 09/2819, no samples were able to be obtained due to owner not cooperating. Vegetation will be sampled in this sector instead. The minimum number of milk samples was still met.

(IR 04240530) (IR 04291955) (IR 04266250)

Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.

The overall sample recovery rate (>99%) indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes There were no changes to the program in 2019.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken weekly from a continuous sampler at two locations (J1-2 and Q9-1) and weekly grab samples from one location (A3-2). Weekly samples were composited on a monthly schedule. Of these locations only J1-2 located downstream could be affected by TMINS effluent releases. The following analyses were performed:

Tritium Monthly samples from J1-2 and Q9-1 were analyzed for tritium activity (Table C-I.1, Appendix C). Positive tritium activity was detected in 5 of 12 samples at location J1-2, which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 661 to 12,700 pCi/L. The increased tritium concentrations detected were a result of TMINS releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. The indicator surface water sample is taken just downstream of the liquid discharge outfall where mixing of liquid effluents with the river water is incomplete. More complete mixing is not achieved until liquid effluents pass over the York Haven Dam. This water is normally not consumed by humans. The concentrations detected were well below any regulatory limits. (Figures C-1 and C-2, Appendix C)

Iodine Monthly samples were taken from location A3-2. This is a control or background station sampled because known medical discharges of radiopharmaceuticals occur into the surface water upstream of TMI from a nearby hospital. Monthly samples were taken from A3-2 and analyzed for I-131. (Table C-I.2, Appendix C). I-131 activity was not detected in any samples.

Gamma Spectrometry Locations J1-2 and Q9-1 were analyzed for gamma-emitting nuclides (Table C-I.3, Appendix C). All nuclides were less than the MDC.

2. Drinking Water Monthly samples were collected from continuous water samplers at three locations (G15-2, G15-3 and Q9-1). Two locations (G15-2 and G15-3) could be affected by TMINS effluent releases. The following analyses were performed:

Gross Beta Monthly samples from all locations were analyzed for concentrations of gross beta (Tables C-II.1, Appendix C). Gross beta activity was detected in 17 of 36 samples. The concentrations ranged from 2.1 to 5.6 pCi/L. Concentrations detected were consistent with those detected in previous years. (Figure C-3, Appendix C)

Iodine Monthly samples from all locations were analyzed for concentrations of I-131. I-131 activity was not detected in any samples.

(Table C-II.2, Appendix C)

Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-II.3, Appendix C). Tritium was detected in 1 of 36 samples at a concentration of 203 pCi/L. (Figures C-4, Appendix C)

Gamma Spectrometry Samples from all locations were analyzed for gamma-emitting nuclides.

All nuclides were less than the MDC. (Table C-II.4, Appendix C)

3. Effluent Water Monthly samples were collected from a continuous water sampler at one location (K1-1). The following analyses were performed:

Gross Beta Monthly samples from location K1-1 were analyzed for concentrations of gross beta. Gross beta was detected in 10 of 12 samples. The concentrations ranged from 2.3 to 7.1 pCi/L. Concentrations detected were consistent with those detected in previous years.

(Tables C-III.1, Appendix C)

Iodine-131 Monthly samples from location K1-1 were analyzed for concentrations of I-131. I-131 was not detected in any of the samples.

(Tables C-III.1, Appendix C)

Tritium Monthly samples from location K1-1 were analyzed for tritium activity.

Tritium activity was detected in 8 of 12 samples. The concentrations ranged from 220 to 91,300 pCi/L. (Table C-III.1, Appendix C)

The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. These results were from the liquid discharge mixing basin. The concentrations detected agree with those obtained from the TMINS Effluent Monitoring Program. (Figure C-4, Appendix C)

Strontium Semiannual composite samples from location K1-1 were analyzed for Sr-89 and Sr-90. No strontium activity was detected. The highest MDC was calculated at <4.3 pCi/L for Sr-89 and at <0.7 pCi/L for Sr-90. (Table C-III.1, Appendix C)

Gamma Spectrometry Samples from location K1-1 were analyzed for gamma-emitting nuclides. All nuclides were less than the MDC.

(Table C-III.2, Appendix C)

4. Storm Water Storm water results are included in the Annual Radiological Groundwater Protection Program (ARGPPR), Appendix F.

5. Ground Water Groundwater results are included in the Annual Radiological Groundwater Protection Program (ARGPPR), Appendix F.

6. Fish Fish samples comprised of bottom feeders and predators were collected at two locations (IND and BKG) semiannually. Location IND could be affected by TMINS effluent releases. The following analyses were performed:

Strontium The edible portions of fish samples from both locations were analyzed for Sr-90. No strontium activity was detected. The highest MDC was calculated at <4.8 pCi/kg wet for Sr-90. (Table C-IV.1, Appendix C)

Gamma Spectrometry The edible portions of fish samples from both locations were analyzed for gamma-emitting nuclides. Naturally-occurring K-40 was found in all fish samples. Concentrations ranged from 2,875 to 3,790 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were detected. (Table C-IV.2, Appendix C)

7. Sediment Aquatic sediment samples were collected at three locations (A1-3, J2-1 and K1-3) semiannually. Of these locations two (J2-1 and K1-3) could be affected by TMINS effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from all locations were analyzed for gamma-emitting nuclides. Potassium-40 was found in all sediment samples and ranged from 6,261 to 14,690 pCi/kg dry. Cs-137 is occasionally found in sediment at very low levels (just above LLD) and is not distinguishable from background levels. Cs-137 was found in one sample at 112 pCi/kg dry. (Figure C-5, Appendix C) No other fission or activation products were detected. (Table C-V.1, Appendix C)

B. Atmospheric Environment

1. Airborne Particulates

a. Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. Six locations (A3-1, E1-2, F1-3, G2-1, H3-1 and M2-1) were indicator stations located in the highest D/Q sectors and the nearest communities to TMI. One sample (Q15-1) represents the control location at a remote distance from TMINS.

The following analyses were performed:

Gross Beta Weekly samples were analyzed for concentrations of beta emitters.

Detectable gross beta activity was observed at all locations.

(Table C-VI.1 and C-VI.2, Appendix C)

Comparison of results aid in determining the effects, if any, resulting from the operation of TMINS. The results from the closest to the site boundary locations (Group I) ranged from 7 to 33E-3 pCi/m3 with a mean of 14E-3 pCi/m3. The results from the intermediate offsite locations (Group II) ranged from 5 to 32E-3 pCi/m3 with a mean of 14E-3 pCi/m3. The results from the Control location (Group III) ranged from 5 to 32E-3 pCi/m3 with a mean of 15E-3 pCi/m3. Comparison of the 2019 air particulate data with previous years data indicate no effects from the operation of TMINS (Figure C-6, Appendix C). In addition, a comparison of the weekly mean values for 2019 indicate no notable differences between indicator and control stations. (Figure C-7, Appendix C)

Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma-emitting nuclides. Naturally-occurring Be-7 due to cosmic ray activity was detected in all 28 samples. These concentrations ranged from 52 to 88E-3 pCi/m3. All other nuclides were less than MDC. (Table C-VI.3, Appendix C)

b. Airborne Iodine Continuous air samples were collected from seven (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1 and Q15-1) locations and analyzed weekly for I-131. All results were less than the MDC for I-131.

(Table C-VII.1, Appendix C)

2. Terrestrial

a. Milk Samples were collected from four locations (K15-3, F4-1, G2-1 and P4-1) biweekly March through November and monthly December through February. The following analyses were performed:

Iodine-131 Milk samples from all locations were analyzed for concentrations of I-131. All results were less than the MDC.

(Table C-VIII.1, Appendix C)

Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90. No Sr-89 activity was detected.

Sr-90 activity was detected in 1 sample at a concentration of 0.9 pCi/L. (Table C-VIII.2, Appendix C) The results are consistent with those detected in the pre-operational years.

(Figure C-8, Appendix C)

Gamma Spectrometry Milk samples from all locations were analyzed for concentrations of gamma-emitting nuclides. Naturally-occurring K-40 activity was found in all samples. The concentrations ranged from 974 to 2,206 pCi/L. All other nuclides were less than the MDC.

(Table C-VIII.3, Appendix C).

b. Food Products Food products were collected monthly at three locations (B10-2, E1-2 and H1-2), in lieu of milk sampling, and annually from the four food product groups at two locations (B10-2 and E1-2). B10-2 was the control location for both annual and monthly sampling. The following analyses were performed:

Strontium Forty-two food product samples were analyzed for concentrations of Sr-90. Sr-90 activity was detected in 24 of the 42 samples. The concentrations ranged from 5.6 to 39.7 pCi/kg wet.

(Table C-IX.1, Appendix C)

Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma-emitting nuclides. Naturally-occurring Be-7 due to cosmic ray activity was detected in 26 of 42 samples with concentrations ranging from 195 to 1,514 pCi/kg. Naturally-occurring K-40 activity was found in all samples. The concentrations ranged from 1,721 to 8,256 pCi/kg. All other nuclides were less than the MDC.

(Table C-IX.1, Appendix C)

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Optically Stimulated Luminescence Dosimeter (OSLD). Ninety OSLD locations were established around the site. Results of OSLD measurements are listed in Tables C-X.1 to C-X.3, Appendix C.

All of the OSLD measurements were below 40 mR/quarter, with a range of 9.1 to 39.1 mR/standard quarter. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 averaged higher than indicator stations. Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 have a historical high bias, and this bias is most likely due to radon and other naturally-occurring nuclides, e.g. K-40, emanating from the ground.

D. Land Use Survey A Land Use Survey conducted in the 2019 fall growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Exelon Industrial Services (EIS) for Exelon to comply with Sections 8.2 of the Plant's Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident, milk-producing animal and garden of greater than 500 ft2 in each of the sixteen 221/2 degree sectors around the site. The results of these surveys are summarized below:

Distance in Miles from the TMINS Reactor Buildings Residence Garden Milk Farm Sector Miles Miles Miles A N 1.0 1.9 2.1 B NNE 0.8 1.2 -

C NE 0.5 1.1 4.2 D ENE 0.5 0.5 4.5 E E 0.4 0.5 1.1 F ESE 1.1 1.2 3.2 G SE 0.7 1.6 1.4 H SSE 0.7 0.8 -

J S 2.2 2.5 -

K SSW 0.6 1.6 4.9, 14.4 L SW 0.5 1.7 -

M WSW 0.5 1.3 -

N W 0.7 1.3 -

P WNW 0.4 1.7 3.7 Q NW 0.4 1.2 -

R NNW 1.1 2.4 -

E. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2019 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2019 whole body dose potentially received by an assumed maximum exposed individual from TMI-1 and TMI-2 liquid and airborne effluents was conservatively calculated to be 0.13 mrem. This dose is equivalent to 0.04% of the dose that an individual living in the TMI area receives each year from natural background radiation.

1. Determination of Radiation Doses to the Public Dose assessments can be performed by using either effluent data and an environmental transport model or environmental sample data. To the extent possible, doses to the public are based on the direct measurement of dose rates from external sources and the measurement of radionuclide concentrations in environmental media which may contribute to an internal dose of radiation. Optically Stimulated Luminescent Dosimetry (OSLDs) positioned in the environment around TMINS provide measurements to determine external radiation doses to humans. Samples of air, water and food products are used to determine internal doses.

The quantity of radioactive materials released during normal operations are typically too small to be measured once distributed in the offsite environment. Therefore, the potential offsite doses are more effectively calculated for TMINS operations using a computerized model that predicts concentrations of radioactive materials in the environment and subsequent radiation doses based on measured effluents.

Doses are calculated using a model that incorporates the guidelines and methodology set forth by the USNRC in Regulatory Guide 1.109 and NUREG 0133. Due to the conservative assumptions that are used in the model, the calculated doses are generally higher than the doses based on actual environmental sample concentrations.

Therefore, the model predicts doses that are higher than actual doses received by people. The type and amount of radioactivity released from TMINS is calculated using measurements from effluent sample analyses.

Airborne releases are diluted and carried away from the site by atmospheric diffusion, which continuously acts to disperse radioactivity.

Variables that affect atmospheric dispersion include wind speed, temperature at different elevations, terrain, and shift in wind direction. A weather station on the north end of TMI is linked to a data logger that records the meteorological data.

Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Susquehanna River. Actual monthly Susquehanna River flows are obtained from the USGS Stream gauging station 01570500 located at Harrisburg, PA.

The human exposure pathways also are included in the model and are depicted in Figure 1. The exposure pathways that are considered for the discharge of TMINS liquid effluents are consumption of drinking water and fish. The exposure pathways considered for the discharge of TMINS airborne effluents are plume exposure, inhalation, cow milk consumption, fruit and vegetable consumption, and meat consumption.

When determining the dose to humans, it is necessary to consider all applicable pathways and all exposed tissues, summing the dose from each to provide the total dose for each organ as well as the whole body from a given radionuclide. Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted and half-life. The dose assessment model also contains dose conversion factors for the radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone and GI tract).

2. Result of Dose Calculations The maximum hypothetical doses due to 2019 TMI-1 and TMI-2 liquid and airborne effluents are summarized in Tables 1 and 2. Table 1 compares the calculated maximum hypothetical individual doses to the USNRC 10 CFR 50 App. I guidelines. This table also compares the calculated doses (to an individual of the public) from effluents and direct radiation to USEPA 40 CFR 190 dose limits. Table 2 presents the maximum hypothetical whole body doses to an individual. As shown in Table 1, the doses calculated for 2019 operations at TMINS were well below the Federal dose limits (USEPA 40 CFR 190) and the guidelines of USNRC 10 CFR 50 App. I. This conclusion was supported by radionuclide concentrations detected in actual environmental samples.

Doses from natural background radiation provide a baseline for assessing the potential public health significance of radioactive effluents.

Natural background radiation from cosmic, terrestrial and natural radionuclides in the human body (not including radon), averages about 81 mrem/yr (Ref. 5). Additionally, the average individual living in the United States receives an annual dose of about 2,760 mrem to the lung from natural radon gas. This lung dose is considered to be equivalent to a whole (or total) body dose of 230 mrem (Ref. 5). Therefore, the average person in the United States receives a whole body dose of about 311 mrem/yr from natural background radiation sources.

As shown on Table 2, the maximum hypothetical whole body dose received by an individual from 2019 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.13 mrem. This dose is equivalent to 0.04% percent of the dose that an individual living in the TMI area receives each year from natural background radiation (311 mrem).

The low doses calculated for 2019 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).

In conclusion, radioactive materials related to 2019 TMINS operations were detected in environmental samples, but the measured concentrations were low and consistent with measured effluents. The environmental sample results verified that the doses received by the public from TMINS effluents in 2019 were well below applicable dose limits and only a small fraction of the doses received from natural background radiation. Additionally, the results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.

Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2019 did not have any adverse effects on the health of the public or on the environment.

TABLE 1 Calculated Maximum Hypothetical Doses to an Individual from 2019 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual USNRC 10 CFR 50 APP. I Calculated Dose Guidelines (mrem/yr)

(mrem/yr) TMI-1 TMI-2 From Radionuclides 3 total body, or 2.25E-02 3.24E-04 In Liquid Releases 10 any organ 2.43E-02 5.15E-04 From Radionuclides In 5 total body, or 2.75E-04 0*

Airborne Releases (Noble Gases) 15 skin 4.03E-04 0*

From Radionuclides In Airborne 15 any organ 1.05E-01 1.45E-05 Releases (Iodines, Tritium and Particulates)

No noble gases were released from TMI-2.

USEPA Calculated Dose 40 CFR 190 (mrem/yr)

Limits TMI-1 and TMI-2 (mrem/yr) Combined**

Total from Site 75 thyroid 0.48 25 total body 0.79 or other organs

*This sums together TMI-1 and TMI-2 maximum doses regardless of age group for different pathways.

The combined doses include those due to radioactive effluents and direct radiation from TMINS. The direct radiation dose is calculated from environmental dosimeter data. For this calculation, exposure is assumed to be equal to dose.

The direct radiation dose from 2019 TMINS operations was 0.363 mrem/yr based on calculations from ANSI/HI Standard N13.37.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual from 2019 TMI-1 and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)

TMI-1 TMI-2 From Radionuclides In Liquid Releases 2.25E-02 3.24E-04 From Radionuclides in Airborne Releases 2.75E-04 0*

(Noble Gases)

From Radionuclides In Airborne 1.05E-01 1.45E-05 Releases (Iodines, Tritium and Particulates)

No noble gases were released from TMI-2.

Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations: 0.13 mrem/yr Individual Whole Body Dose Due to Natural Background Radiation (1) 311 mrem/yr (1) NCRP 160 - (2009)

Figure 1 F. Errata Data There is no errata data for 2019.

G. Summary of Results - Inter-Laboratory Comparison Program The primary and other secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOEs MAPEP, were evaluated against the following pre-set acceptance criteria:

1. Analytics Evaluation Criteria Analytics evaluation report provides a ratio of TBEs result and Analytics known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.

2. ERA Evaluation Criteria ERAs evaluation report provides an acceptance range for control and warning limits with associated flag values. ERAs acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERAs SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

3. DOE Evaluation Criteria MAPEPs evaluation report provides an acceptance range with associated flag values.

The MAPEP defines three levels of performance: Acceptable (flag =

A), Acceptable with Warning (flag = W), and Not Acceptable (flag =

N). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from

+/-20% to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities.

For the TBE laboratory, 119 out of 129 analyses performed met the specified acceptance criteria. Ten analyses did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program:

1. The ERA April 2019 water Cs-134 result was evaluated as Not Acceptable. The reported value was 15.2 pCi/L (error 2.82 pCi/L) and the known result was 12.1 pCi/L (acceptance range of 8.39 - 14.4 pCi/L). With the error, the reported result overlaps the acceptable range. This sample was run as the workgroup duplicate on a different detector with a result of 10.7 pCi/L (within acceptable range).

(NCR 19-10)

2. The ERA April 2019 water Sr-89 result was evaluated as Not Acceptable. The reported value was 44.9 pCi/L and the known result was 33.3 pCi/L (acceptance range of 24.5 - 40.1 pCi/L). The sample was only counted for 15 minutes instead of 200 minutes. The sample was re-prepped in duplicate and counted for 200 minutes with results of 30.7 +/- 5.37 pCi/L and 33.0 +/- 8.71 pCi/L. This was the 1st high failure for Sr-89 in 5 years. (NCR 19-11)

3. The MAPEP February 2019 soil Sr-90 result was not submitted and therefore evaluated as Not Acceptable. The sample was run in duplicate, with results of -1.32 +/- 4.09 Bq/kg (<6.87) and -1.030 +/- 3.55 Bq/kg (<5.97). The known result was a false positive test (no significant activity). TBE did not submit a result because it appeared that the results may not be accurate. TBE analyzed a substitute soil Sr-90 sample from another vendor, with a result within the acceptable range. (NCR 19-12)

4. The MAPEP February 2019 water Am-241 result was evaluated as Not Acceptable. The reported value was 0.764 +/- 0.00725 Bq/L with a known result of 0.582 Bq/L (acceptable range 0.407 - 0.757 Bq/L).

TBEs result falls within the upper acceptable range with the error. It appeared that a non-radiological interference was added and lead to an increased mass and higher result. (NCR 19-13)

5. The MAPEP February 2019 vegetation Sr-90 result was evaluated as Not Acceptable. The reported result was -0.1060 +/- 0.0328 Bq/kg and the known result was a false positive test (no significant activity).

TBEs result was correct in that there was no activity. MAPEPs evaluation was a statistical failure at 3 standard deviations.

(NCR 19-14)

6. The ERA October 2019 water Gross Alpha result was evaluated as Not Acceptable. TBEs reported result was 40.5 +/- 10.3 pCi/L and the known result was 27.6 pCi/L (ratio of TBE to known result at 135%).

With the associated error, the result falls within the acceptable range (14.0 - 36.3 pCi/L). The sample was run as the workgroup duplicate on a different detector with a result of 30.8 +/- 9.17 pCi/L (within the acceptable range). This was the first failure for drinking water Gr-A since 2012. (NCR 19-23)

7. The ERA October 2019 water Sr-90 result was evaluated as Not Acceptable. TBEs reported result was 32.5 +/- 2.12 pCi/L and the known result was 26.5 pCi/L (ratio of TBE to known result at 123%).

With the associated error, the result falls within the acceptable range (19.2 - 30.9 pCi/L). The sample was run as the workgroup duplicate on a different detector with a result of 20.0 +/- 1.91 pCi/L (within the acceptable range). Both TBE results are within internal QC limits. A substitute quick response sample was analyzed with an acceptable result of 18.6 pCi/L (known range of 13.2 - 22.1 pCi/L). (NCR 19-24)

8. The MAPEP August 2019 soil Ni-63 result of 436 +/- 22.8 Bq/kg was evaluated as Not Acceptable. The known result was 629 Bq/kg (acceptable range 440 - 818 Bq/sample). With the associated error, the TBE result falls within the lower acceptance range. All associated QC was acceptable. No reason for failure could be found. This is the first failure for soil Ni-63 since 2012. (NCR 19-25).

9. The MAPEP August 2019 water Am-241 result was not reported and therefore evaluated as Not Acceptable. Initial review of the results showed a large peak where Am-241 should be (same as the February, 2019 sample results). It is believed that Th-228 was intentionally added as an interference. The sample was re-prepped and analyzed using a smaller sample aliquot. The unusual large peak (Th-228) was seen again and also this time a smaller peak (Am-241). The result was 436 +/- 22.8 Bq/L (acceptable range 0.365 +/- 0.679 Bq/L). Th-228 is not a typical nuclide requested by clients, so there is no analytical purpose to take samples through an additional separation step. TBE will pursue using another vendor for Am-241 water cross-checks that more closely reflects actual customer samples. (NCR 19-26)

10. The Analytics September 2019 soil Cr-51 sample was evaluated as Not Acceptable. TBEs reported result of 0.765 +/- 0.135 pCi/g exceeded the upper acceptance range (140% of the known result of 0.547 pCi/g).

The TBE result was within the acceptable range (0.63 - 0.90 pCi/g) with the associated error. The Cr-51 result is very close to TBEs normal detection limit. In order to get a reportable result, the sample must be counted for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months (10x longer than client samples). There is no client or regulatory requirement for this nuclide and TBE will remove Cr-51 from the reported gamma nuclides going forward. (NCR 19-27)

For the secondary QC samples, EIS laboratory, analyzed gross beta, gramma, and I-131 for TMINS. For EIS, 114 of 114 analyses met the specified acceptance criteria.

For the secondary QC samples, GEL laboratory analyzed only H-3 and Sr-89/90 for TMINS REMP. GEL analyzed H-3 and gamma nuclides for RGPP. For these analyses, 96 of 100 cross-check samples met the specified acceptance criteria. All failures were addressed through GELs Corrective Action Program and the pertinent failures are described below:

1. Two ERA 1st quarter 2019 water Sr-89 results were evaluated as Not Acceptable. The reported values were 78.5 pCi/L and 76.5 pCi/L. The known result was 66.9 pCi/L, with an acceptance range of 54.4 - 75.0 pCi/L. A review of the data as well as of the preparation processes did not reveal any errors or possible contributors to the high bias. The Laboratory has concluded that this positive bias was an isolated occurrence and that the overall process is within control. In addition, the reported value is 117% of the reference value, which is within the labs standard acceptance criteria of +/- 25% for Laboratory Control Samples. No permanent corrective or preventative actions or improvements made at the time. The laboratory will continue to monitor the recoveries to ensure that there are no continued issues in the process. (CARR190225-1192)

2. The ERA 2nd quarter 2019 vegetation Sr-90 result was evaluated as Not Acceptable. The reported value was 4670 pCi/kg and the known result was 3530 pCi/kg (acceptance range of 1990 - 4600 pCi/L). The reanalysis was performed using the same processes as the original reported analysis. The reanalysis result met the acceptance range with 96% recovery. No permanent corrective or preventative actions or improvements made at the time. The laboratory will continue to monitor the recoveries to ensure that there are no continued issues in the process. (CARR190530-1211)

3. One of the two ERA 3rd quarter 2019 water Sr-89 results was evaluated as Not Acceptable. The reported value was 69.4 pCi/L and the known result was 58.7 (acceptance range of 47.1 - 66.5 pCi/L). A review of the data as well as of the preparation processes did not reveal any errors or possible contributors to the high bias. The Laboratory has concluded that this positive bias was an isolated occurrence and that the overall process is within control. In addition, the reported value is 118% of the reference value, which is within the labs standard acceptance criteria of +/- 25% for Laboratory Control Samples. In addition, a duplicate sample was run using separation resin and that result was within the acceptance range. The results from the two methods compared with a relative percent difference (RPD) of 11.1%,

which meets the labs duplicate acceptance criteria. No permanent corrective or preventative actions or improvements made at the time.

The laboratory will continue to monitor the recoveries to ensure that there are no continued issues in the process. (CARR190826-1250)

The Inter-Laboratory Comparison Program provides evidence of in control counting systems and methods, and that the laboratories are producing accurate and reliable data. Interlaboratory Comparison results may be found in Appendix E.

V. References

1. Three Mile Island Nuclear Station, Unit 1, Technical Specifications, DPR 50.

2. Three Mile Island Nuclear Station, Unit 2, PDMS Technical Specifications, DPR 73.

3. Radiation Management Corporation. Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1974 - June 5, 1974. RMC-TR-75-17, January 1975.

4. Exelon. Three Mile Island Nuclear Station Offsite Dose Calculation Manual (ODCM).

5. National Council of Radiation Protection and Measurements Report No. 160.

Ionizing Radiation Exposure of the Population of the United States. 2009.

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2019 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS SURFACE WATER H-3 24 2000 3440 <LLD 3440 J1-2 INDICATOR 0 (PCI/LITER) (5/12) (5/12) WEST SHORE; TMI 661 - 12700 661 - 12700 0.5 MILES S OF SITE I-131 12 1 NA <LLD - 0 GAMMA 24 MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 A-1 ZN-65 30 <LLD <LLD - 0 NB-95 15 <LLD <LLD - 0 ZR-95 30 <LLD <LLD - 0 CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 BA-140 60 <LLD <LLD - 0 LA-140 15 <LLD <LLD - 0 DRINKING WATER GR-B 36 4 3.2 2.7 3.3 G15-2 INDICATOR 0 (PCI/LITER) (14/24) (3/12) (9/12) WRIGHTSVILLE WATER TREATMENT PLANT 2.2 - 5.6 2.1 - 3.5 2.2 - 5.6 13.3 MILES SE OF SITE I-131 36 1 <LLD <LLD - 0 H-3 36 2000 203 <LLD 203 G15-3 INDICATOR 0 (1/24) (1/12) LANCASTER WATER TREATMENT PLANT 15.7 MILES SE OF SITE (M) The Mean Values are calculated using the positive values. (F ) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2019 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS DRINKING WATER GAMMA 36 (PCI/LITER) MN-54 15 <LLD <LLD - 0 CO-58 15 <LLD <LLD - 0 FE-59 30 <LLD <LLD - 0 CO-60 15 <LLD <LLD - 0 ZN-65 30 <LLD <LLD - 0 NB-95 15 <LLD <LLD - 0 ZR-95 30 <LLD <LLD - 0 CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 BA-140 60 <LLD <LLD - 0 A-2 LA-140 15 <LLD <LLD - 0 EFFLUENT WATER GR-B 12 4 4.2 NA 4.2 K1-1 INDICATOR 0 (PCI/LITER) (10/12) (10/12) MAIN STATION LIQ. DISCHARGE 2.3 - 7.1 2.3 - 7.1 ONSITE I-131 (LOW LVL) 12 1 <LLD NA - 0 H-3 12 2000 35603 NA 35603 K1-1 INDICATOR 0 (8/12) (8/12) MAIN STATION LIQ. DISCHARGE 220 - 91300 220 - 91300 ONSITE SR-89 2 5 <LLD NA - 0 SR-90 2 2 <LLD NA - 0 (M) The Mean Values are calculated using the positive values. (F ) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2019 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS EFFLUENT WATER GAMMA 12 (PCI/LITER) MN-54 15 <LLD NA - 0 CO-58 15 <LLD NA - 0 FE-59 30 <LLD NA - 0 CO-60 15 <LLD NA - 0 ZN-65 30 <LLD NA - 0 NB-95 15 <LLD NA - 0 ZR-95 30 <LLD NA - 0 CS-134 15 <LLD NA - 0 CS-137 18 <LLD NA - 0 BA-140 60 <LLD NA - 0 A-3 LA-140 15 <LLD NA - 0 BOTTOM FEEDER SR-90 4 10 <LLD <LLD - 0 (PCI/KGWET)

GAMMA 4 K-40 NA 3494 3277 3494 INDB INDICATOR 0 (2/2) (2/2) (2/2) YORK HAVEN DAM 3197 - 3790 3194 - 3360 3197 - 3790 DOWNSTREAM OF DISCHARGE MN-54 130 <LLD <LLD - 0 CO-58 130 <LLD <LLD - 0 FE-59 260 <LLD <LLD - 0 CO-60 130 <LLD <LLD - 0 ZN-65 260 <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 PREDATOR SR-90 4 10 <LLD <LLD - 0 (PCI/KGWET)

(M) The Mean Values are calculated using the positive values. (F ) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2019 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS PREDATOR GAMMA 4 (PCI/KGWET) K-40 NA 3134 3524 3524 BKGP CONTROL 0 (2/2) (2/2) (2/2) CITY ISLAND 2875 - 3393 3365 - 3683 3365 - 3683 UPSTREAM OF DISCHARGE MN-54 130 <LLD <LLD - 0 CO-58 130 <LLD <LLD - 0 FE-59 260 <LLD <LLD - 0 CO-60 130 <LLD <LLD - 0 ZN-65 260 <LLD <LLD - 0 CS-134 130 <LLD <LLD - 0 CS-137 150 <LLD <LLD - 0 A-4 SEDIMENT GAMMA 6 (PCI/KG DRY) K-40 NA 12093 9456 12360 K1-3 INDICATOR 0 (4/4) (2/2) (2/2) DOWNSTREAM OF TMINS LIQUID DISCHARGE OUTFALL 8961 - 14690 6261 - 12650 11310 - 13410 0.2 MILES SSW OF SITE MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 CS-134 150 <LLD <LLD - 0 CS-137 180 <LLD <LLD - 0 AIR PARTICULATE GR-B 369 10 14 15 15 Q15-1 CONTROL 0 (E-3 PCI/CU.METER) (305/316) (52/53) (52/53) WEST FAIRVIEW FIRE DEPT SOCIAL HALL 5 - 33 5 - 32 5 - 32 13.4 MILES NW OF SITE (M) The Mean Values are calculated using the positive values. (F ) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2019 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS AIR PARTICULATE GAMMA 28 (E-3 PCI/CU.METER) BE-7 NA 69 80 80 Q15-1 CONTROL 0 (24/24) (4/4) (4/4) WEST FAIRVIEW FIRE DEPT SOCIAL HALL 52 - 85 68 - 88 68 - 88 13.4 MILES NW OF SITE MN-54 NA <LLD <LLD - 0 CO-58 NA <LLD <LLD - 0 CO-60 NA <LLD <LLD - 0 NB-95 NA <LLD <LLD - 0 ZR-95 NA <LLD <LLD - 0 CS-134 50 <LLD <LLD - 0 CS-137 60 <LLD <LLD - 0 A-5 AIR IODINE GAMMA 369 (E-3 PCI/CU.METER) I-131 70 <LLD <LLD - 0 MILK I-131 92 1 <LLD <LLD - 0 (PCI/LITER)

SR-89 16 5 <LLD <LLD - 0 SR-90 16 2 <LLD 0.9 0.9 K15-3 CONTROL 0 (1/4) (1/4) MEYER'S FARM 0.9 0.9 14.5 MILES SSW OF SITE GAMMA 92 K-40 NA 1299 1248 1326 P4-1 INDICATOR 0 (69/69) (23/23) (23/23) FARM ON VALLEY ROAD 1041 - 1582 974 - 2206 1066 - 1582 3.6 MILES WNW OF SITE CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 BA-140 60 <LLD <LLD - 0 LA-140 15 <LLD <LLD - 0 (M) The Mean Values are calculated using the positive values. (F ) Fraction of detectable measurement are indicated in parentheses.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2019 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2019 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

MEDIUM OR REQUIRED LOCATIONS LOCATION NUMBER OF PATHWAY SAMPLED TYPES OF NUMBER OF LOWER LIMIT MEAN (M) MEAN (M) MEAN (M) STATION # NONROUTINE (UNIT OF ANALYSIS ANALYSIS OF DETECTION (F) (F) (F) NAME REPORTED MEASUREMENT) PERFORMED PERFORMED (LLD) RANGE RANGE RANGE DISTANCE AND DIRECTION MEASUREMENTS VEGETATION SR-90 42 10 16.3 13.4 20.4 H1-2 INDICATOR 0 (PCI/KG WET) (18/27) (6/15) (11/12) RED HILL MARKET ALONG ROUTE 441 6.7 - 32.1 5.6 - 39.7 14.1 - 32.1 1.0 MILES SSE OF SITE GAMMA 42 BE-7 NA 885 958 1083 H1-2 INDICATOR 0 (17/27) (9/15) (10/12) RED HILL MARKET 260 - 1514 195 - 1469 572 - 1514 1.0 MILES SSE OF SITE K-40 NA 4021 4627 4627 B10-2 CONTROL 0 (27/27) (15/15) (15/15) MILTON HERSHEY SCHOOL, MILTON 1760 - 8256 1721 - 7265 1721 - 7265 10 MILES NNE OF SITE A-6 I-131 60 <LLD <LLD - 0 CS-134 60 <LLD <LLD - 0 CS-137 80 <LLD <LLD - 0 DIRECT RADIATION OSLD - QUARTERLY 357 NA 15.7 18.2 26.5 H8-1 INDICATOR 0 (MILLIREM/STD.MO.) (314/314) (43/43) (4/4) SAGINAW ROAD, STARVIEW 8.8 - 39.1 12.6 - 28.8 22.5 - 29.4 7.4 MILES SSE OF SITE (M) The Mean Values are calculated using the positive values. (F ) Fraction of detectable measurement are indicated in parentheses.

APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS

Intentionally left blank TABLE B-1: Location Designation and Identification System for the Three Mile Island Nuclear Station XYY-Z - General code for identification of locations, where:

X - Angular Sector of Sampling Location. The compass is divided into 16 sectors of 22 1/2 degrees each with center at Three Mile Island's Units 1 and 2 off-gas vents. Sector A is centered due North, and others are alphabetical in a clockwise direction.

YY - Radial Zone of Sampling Location in miles.

Z - Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.

B-1

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2019 Sample Station Map Distance Medium Code Number (miles) Azimuth Description AQS A1-3 1 0.6 359° N of site off north tip of TMI in Susquehanna River ID A1-4 1 0.3 6° N of Reactor Building on W fence adjacent to North Weather Station, TMI AP, AI, ID A3-1 2 2.7 357° N of site at Mill Street Substation SW A3-2 2 2.7 356° N of site at Swatara Creek, Middletown ID A5-1 2 4.4 3° N of site on Vine Street Exit off Route 283 ID A9-3 3 8.0 2° N of site at Duke Street Pumping Station, Hummelstown ID B1-1 1 0.6 25° NNE of site on light pole in middle of North Bridge, TMI ID B1-2 1 0.4 24° NNE of Reactor Building on top of dike, TMI ID B2-1 2 1.9 17° NNE of site on Sunset Dr. (off Hillsdale Rd.)

ID B5-1 2 4.9 19° NNE of site at intersection of School House and Miller Roads ID B10-1 3 9.2 21° NNE of site at intersection of West Areba Avenue and Mill Street, Hershey FP B10-2 3 10 31° NNE of site at Milton Hershey School, Hershey ID C1-1 1 0.7 37° NE of site along Route 441 N ID C1-2 1 0.3 50° NE of Reactor Building on top of dike, TMI ID C2-1 2 1.5 44° NE of site at Middletown Junction ID C5-1 2 4.7 43° NE of site on Kennedy Lane ID C8-1 3 7.1 48° NE of site at Schenk's Church on School House Road AQF Control - - - All locations where finfish are collected above Dock St.

Dam, Harrisburg ID D1-1 1 0.2 76° ENE of Reactor Building on top of dike, TMI ID D1-2 1 0.5 67° ENE of site off Route 441 along lane between garden center and residence ID D2-2 2 1.6 74° ENE of site along Hillsdale Rd. (S of Zion Rd.)

ID D6-1 3 5.2 66° ENE of site off Beagle Road ID D15-1 3 10.8 64° ENE of site along Route 241, Lawn AP, AI, ID, FP E1-2 1 0.4 97° E of site at TMI Visitor's Center ID E1-4 1 0.2 97° E of Reactor Building on top of dike, TMI M E2-2 2 1.1 96° E of site at farm on Pecks Road ID E2-3 2 2.0 97° E of site along Hillsdale Rd. (N of Creek Rd.)

ID E5-1 2 4.7 82° E of site at intersection of North Market Street (Route 230) and Zeager Road ID E7-1 3 6.7 88° E of site along Hummelstown Street, Elizabethtown ID F1-1 1 0.5 117° ESE of site near entrance to 500 kV Substation ID F1-2 1 0.2 112° ESE of Reactor Building on top of dike midway within ISWSF, TMI AP, AI F1-3 1 0.6 112° ESE of site in 500 kV Substation ID F1-4 1 0.2 122° ESE of Reactor Building on top of dike, TMI ID F2-1 2 1.3 119° ESE of site along Engle Road M F4-1 2 3.2 104° ESE of site at farm on Turnpike Road ID F5-1 2 4.7 109° ESE of site along Amosite Road ID F10-1 3 9.4 112° ESE of site along Donegal Springs Road, Donegal Springs ID F25-1 3 22 106° ESE of site at intersection of Steel Way and Loop Roads, Lancaster ID G1-2 1 0.7 145° SE of site along Route 441 S ID G1-3 1 0.2 130° SE of Reactor Building on top of dike, TMI ID G1-5 1 0.3 143° SE of Reactor Building on top of dike, TMI ID G1-6 1 0.3 139° SE of Reactor Building on top of dike, TMI AI, AP, M G2-1 2 1.4 126° SE of site at farm on Becker Road ID G2-4 2 1.7 138° SE of site on Becker Road ID G5-1 2 4.8 131° SE of site at intersection of Bainbridge and Risser Roads ID G10-1 3 9.7 128° SE of site at farm along Engles Tollgate Road, Marietta ID G15-1 3 14.4 126° SE of site at Columbia Water Treatment Plant DW G15-2 3 13.3 129° SE of site at Wrightsville Water Treatment Plant DW G15-3 3 15.7 124° SE of site at Lancaster Water Treatment Plant B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2019 Sample Station Map Distance Medium Code Number (miles) Azimuth Description ID H1-1 1 0.5 167° SSE of site, TMI FP H1-2 1 1.0 151° SSE of site along Route 441, Red Hill Market AP, AI, ID H3-1 2 2.2 160° SSE of site in Falmouth-Collins Substation ID H5-1 2 4.1 158° SSE of site by Guard Shack at Brunner Island Steam Electric Station ID H8-1 3 7.4 163° SSE of site along Saginaw Road, Starview ID H15-1 3 13.2 157° SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills AQF Indicator - - - All locations where finfish are collected downstream of the TMINS liquid discharge outfall ID J1-1 1 0.8 176° S of site, TMI SW J1-2 1 0.5 188° S of site downstream of the TMINS liquid discharge outfall in Susquehanna River ID J1-3 1 0.3 189° S of Reactor Building just S of SOB, TMI AQS J2-1 2 1.4 179° S of site in Susquehanna River just upstream of the York Haven Dam ID J3-1 2 2.7 179° S of site at York Haven/Cly ID J5-1 2 4.9 181° S of site along Canal Road, Conewago Heights ID J7-1 3 6.5 176° S of site off of Maple Street, Manchester ID J15-1 3 12.6 183° S of site in Met-Ed York Load Dispatch Station EW K1-1 1 0.2 211° On site at RML-7 Main Station Discharge Building AQS K1-3 1 0.2 213° SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River ID K1-4 1 0.2 209° SSW of Reactor Building on top of dike behind Warehouse 2, TMI ID K2-1 2 1.2 200° SSW of site on S Shelley Island ID K3-1 2 2.0 206° SSW of site along Rt. 262, N of Cly ID K5-1 2 4.9 202° SSW of site along Conewago Creek Road, Strinestown ID K8-1 3 7.5 196° SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View ID K15-1 3 12.8 203° SSW of site behind McDonalds and next to child care center, Weiglestown M K15-3 3 14.4 205° SSW of site at farm along S Salem Church Rd, Dover ID L1-1 1 0.1 236° SW of site on top of dike W of Mech. Draft Cooling Tower, TMI ID L1-2 1 0.5 221° SW of site on Beech Island ID L2-1 2 1.8 224° SW of site along Route 262 ID L5-1 2 4.1 228° SW of site at intersection of Stevens and Wilson Roads ID L8-1 3 8.0 225° SW of site along Rohlers Church Rd., Andersontown ID L15-1 3 11.8 226° SW of site on W side of Route 74, rear of church, Mt.

Royal ID M1-1 1 0.1 249° WSW of Reactor Building on SE corner of U-2 Screenhouse fence, TMI ID M1-2 1 0.4 252° WSW of site on E side of Shelley Island, Lot #157 AP, AI, ID M2-1 2 1.3 256° WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro ID M5-1 2 4.3 249° WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown ID M9-1 3 8.7 243° WSW of site along Alpine Road, Maytown ID N1-1 1 0.7 274° W of site on W side of Shelley Island, between lots #13 and #14 ID N1-3 1 0.1 274° W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI ID N2-1 2 1.2 261° W of site at Goldsboro Marina ID N5-1 2 4.9 268° W of site off of Old York Road along Robin Hood Drive ID N8-1 3 7.7 262° W of site along Route 382, 1/2 mile north of Lewisberry ID N15-2 3 10.4 275° W of site at intersection of Lisburn Road and Main Street, Lisburn ID P1-1 1 0.4 303° WNW of site on Shelley Island B-3

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2019 Sample Station Map Distance Medium Code Number (miles) Azimuth Description ID P1-2 1 0.1 292° WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI ID P2-1 2 1.9 283° WNW of site along Route 262 M P4-1 2 3.6 295° WNW of site at farm on Valley Road ID P5-1 2 5.0 284° WNW of site at intersection of Valley Road (Route 262) and Beinhower Road ID P8-1 3 7.9 292° WNW of site along Evergreen Road, Reesers Summit ID Q1-1 1 0.5 317° NW of site on E side of Shelley Island ID Q1-2 1 0.2 321° NW of Reactor Building on fence W of Warehouse 1, TMI ID Q2-1 2 1.9 310° NW of site along access road along river ID Q5-1 2 5.0 317° NW of site along Lumber Street, Highspire SW, DW, ID Q9-1 3 8.5 310° NW of site at the Steelton Water Company AP, AI, ID Q15-1 3 13.4 309° NW of site behind West Fairview Fire Dept. Social Hall (abandoned)

ID R1-1 1 0.2 335° NNW of Reactor Building along W fence, TMI ID R1-2 1 0.7 334° NNW of site on central Henry Island ID R3-1 2 2.6 341° NNW of site at Crawford Station, Middletown ID R5-1 2 4.9 339° NNW of site at intersection of Spring Garden Drive and Route 441 ID R9-1 3 8.0 341° NNW of site at intersection of Derry and 66th Streets, Rutherford Heights ID R15-1 3 11.2 332° NNW of site at intersection of Route 22 and Colonial Road, Colonial Park IDENTIFICATION KEY ID = Immersion Dose (OSLD) EW = Effluent Water SW = Surface Water DW = Drinking Water AI = Air Iodine M = Milk (Cow)

AP = Air Particulate AQF = Finfish FP = Food Products (Green Leafy AQS = Aquatic Sediment Vegetation, Fruits, Vegetables)

B-4

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2019 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Monthly composite CY-ES-240 EIS Collection of Surface- TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Surface Gamma from a continuous Drinking-Effluent Water Samples for 2 gallon Water Spectroscopy EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the water compositor Radiological Analysis (TMI) Genie PC Counting System Monthly composite CY-ES-240 EIS Collection of Surface- TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Various Surface Gross Beta from a continuous Drinking-Effluent Water Samples for 2 gallon Matrices Water water compositor Radiological Analysis (TMI) EIS, CY-ES-206 Operation of the Tennelec S5E Proportional Counter Monthly composite CY-ES-240 EIS Collection of Surface- TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Surface Tritium from a continuous Drinking-Effluent Water Samples for 2 gallon Scintillation Water water compositor Radiological Analysis (TMI) GEL, EPA 906.0 Mod, for Tritium analysis by Liquid scintillation Monthly composite CY-ES-240 EIS Collection of Surface- TBE, TBE-2012 Radioiodine in Various Matrices Surface Iodine-131 from a continuous Drinking-Effluent Water Samples for 2 gallon B-5 Water EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the water compositor Radiological Analysis (TMI) Genie PC Counting System Drinking Monthly composite CY-ES-240 EIS Collection of Surface-Gross Beta 2 gallon TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Various Water from a continuous Drinking-Effluent Water Samples for Matrices water compositor Radiological Analysis (TMI)

Drinking Gamma Monthly composite CY-ES-240 EIS Collection of Surface-from a continuous Drinking-Effluent Water Samples for 2 gallon TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Water Spectroscopy water compositor Radiological Analysis (TMI)

Drinking Monthly composite CY-ES-240 EIS Collection of Surface-Iodine-131 from a continuous Drinking-Effluent Water Samples for 2 gallon TBE, TBE-2012 Radioiodine in Various Matrices Water water compositor Radiological Analysis (TMI)

Drinking Monthly composite CY-ES-240 EIS Collection of Surface-Tritium 2 gallon TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Water from a continuous Drinking-Effluent Water Samples for Scintillation water compositor Radiological Analysis (TMI)

Effluent Monthly composite CY-ES-240 EIS Collection of Surface-Iodine-131 from a continuous Drinking-Effluent Water Samples for 2 gallon TBE, TBE-2012 Radioiodine in Various Matrices Water water compositor Radiological Analysis (TMI)

Effluent Gamma Monthly composite CY-ES-240 EIS Collection of Surface-2 gallon TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Water Spectroscopy from a continuous Drinking-Effluent Water Samples for water compositor Radiological Analysis (TMI)

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2019 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Monthly composite CY-ES-240 EIS Collection of Surface-Tritium 2 gallon TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Water from a continuous Drinking-Effluent Water Samples for Scintillation water compositor Radiological Analysis (TMI)

Effluent Strontium- Semi-annual TBE, TBE-2023 Compositing of 2 gallon Water 89/90 composite from TBE, TBE-2018 Radiostrontium Analysis by Chemical Separation Samples monthly samples Gamma CY-ES-240 EIS Collection of Surface-Storm Water Quarterly composite of 1 gallon Spectroscopy Drinking-Effluent Water Samples for TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis monthly grab samples Radiological Analysis (TMI)

CY-ES-240 EIS Collection of Surface-Storm Water Tritium Quarterly composite of 1 gallon TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Drinking-Effluent Water Samples for monthly grab samples Scintillation Radiological Analysis (TMI)

B-6 Semi-annual samples TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Gamma collected via ER-TMI-13 Collection of fish samples 1000 grams Fish Spectroscopy electroshocking or for radiological analysis (TMINS) (wet) EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the other techniques Genie PC Counting System Semi-annual samples 1000 grams TBE, TBE-2018 Radiostrontium Analysis by Chemical Separation Fish Strontium-90 collected via ER-TMI-13 Collection of fish samples electroshocking or for radiological analysis (TMINS) (wet)

GEL, EPA 905.0 Mod/DOE RP501 Rev. 1 Mod other techniques TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Gamma ER-TMI-03 Collection of sediment 500 grams Sediment Semi-annual grab Spectroscopy samples for radiological analysis (dry) EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the samples (TMINS) Genie PC Counting System TBE, TBE-2023 Compositing of TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis 13 filters Air Gamma Quarterly composite of Samples (approx.. 3600 Particulates Spectroscopy each station EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the CY-ES-204 Sample Preparation for cubic meters)

Gamma and Beta Counting Genie PC Counting System One-week composite 1 filter TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Various Air CY-ES-237 Collection of Air Iodine & (approx.. 280 Gross Beta of continuous air Matrices Particulates Air Particulate for Radiological Analysis cubic meters sampling through glass (TMI) weekly) fiber filter paper CY-ES-206 Operation of the Tennelec S5E Proportional Counter

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2019 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium One-week composite 1 filter TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Gamma CY-ES-237 Collection of Air Iodine &

Air Iodine of continuous air (approx. 280 Spectroscopy Air Particulate for Radiological Analysis sampling through cubic meters EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the (TMI) charcoal filter weekly) Genie PC Counting System Bi-weekly grab TBE, TBE-2012 Radioiodine in Various Matrices Milk I-131 sample when cows CY-ES-238 Sample Collection for 2 gallon are on pasture. Radiological Analysis - Milk (TMI) EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the Monthly all other times Genie PC Counting System TBE, TBE-2023 Compositing of Quarterly composite of Samples TBE, TBE-2019 Radiostrontium Analysis by Ion Exchange Milk Sr-89/90 bi-weekly and monthly 2 gallon CY-ES-238 Sample Collection for grab samples GEL, EPA 905.0 Mod/DOE RP501 Rev. 1 Mod Radiological Analysis - Milk (TMI)

B-7 Bi-weekly grab TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Gamma sample when cows CY-ES-238 Sample Collection for Milk 2 gallon Spectroscopy are on pasture. Radiological Analysis - Milk (TMI) EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the Monthly all other times Genie PC Counting System TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Gamma Monthly and annual CY-ES-241 Sample Collection for Vegetation 1000 grams Spectroscopy grab sample Gamma Counting - Vegetation (TMI) EIS, CY-ES-205 Gamma Counting Using the HPGe Detector with the Genie PC Counting System Strontium- TBE, TBE-2018 Radiostrontium Analysis by Chemical Separation Vegetation Monthly and annual CY-ES-241 Sample Collection for 1000 grams 89/90 grab sample Gamma Counting - Vegetation (TMI)

GEL, EPA 905.0 Mod/DOE RP501 Rev. 1 Mod Optically Quarterly OSLDs comprised of two CY-ES-239 Collection of OSLD OSLD Stimulated 2 badges with Al2O3:C Landauer samples for radiological analysis Landauer Incorporated Luminescence 3 dosimeters Incorporated elements. (TMINS)

Dosimetry

Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2019 B-8

Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2019 B-9

Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2019 B-10

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank Table C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD J1-2 Q9-1 01/03/19 - 01/30/19 2380 +/- 302 < 192 01/30/19 - 02/27/19 < 195 < 195 02/27/19 - 03/27/19 < 183 < 198 03/27/19 - 05/01/19 < 189 < 192 05/01/19 - 05/30/19 < 190 < 192 05/30/19 - 06/27/19 12700 +/- 1310 < 196 06/27/19 - 08/01/19 661 +/- 151 < 196 08/01/19 - 08/29/19 748 +/- 147 < 184 08/29/19 - 10/03/19 711 +/- 154 < 192 10/03/19 - 10/31/19 < 191 < 193 10/31/19 - 12/04/19 < 193 < 188 12/04/19 - 01/02/20 < 186 < 183 MEAN +/- 2 STD DEV 3440 +/- 10454 -

Table C-I.2 CONCENTRATIONS OF I-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD A3-2 01/03/19 - 01/30/19 < 0.5 01/30/19 - 02/27/19 < 0.5 02/27/19 - 03/27/19 < 0.5 03/27/19 - 05/01/19 < 0.7 05/01/19 - 05/30/19 < 0.8 05/30/19 - 06/27/19 < 0.8 06/27/19 - 08/01/19 < 0.6 08/01/19 - 08/29/19 < 1.0 08/29/19 - 10/03/19 < 0.6 10/03/19 - 10/31/19 < 0.8 10/31/19 - 12/04/19 < 0.7 12/04/19 - 01/02/20 < 0.8 MEAN -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1

Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 J1-2 01/03/19 - 01/30/19 < 7 < 5 < 17 < 8 < 16 < 7 < 12 < 8 < 7 < 24 < 10 01/30/19 - 02/27/19 < 6 < 6 < 13 < 8 < 12 < 8 < 12 < 5 < 6 < 27 < 11 02/27/19 - 03/27/19 < 7 < 6 < 13 < 7 < 15 < 7 < 12 < 6 < 7 < 36 < 11 03/27/19 - 05/01/19 < 8 < 8 < 16 < 8 < 17 < 8 < 14 < 9 < 8 < 38 < 11 05/01/19 - 05/30/19 < 6 < 8 < 12 < 7 < 17 < 6 < 14 < 8 < 9 < 30 < 9 05/30/19 - 06/27/19 < 5 < 6 < 13 < 8 < 16 < 7 < 10 < 7 < 6 < 28 < 10 06/27/19 - 08/01/19 < 5 < 6 < 11 < 7 < 11 < 5 < 10 < 6 < 8 < 27 < 8 08/01/19 - 08/29/19 < 7 < 6 < 14 < 8 < 16 < 6 < 14 < 6 < 7 < 33 < 11 08/29/19 - 10/03/19 < 8 < 7 < 15 < 9 < 17 < 6 < 9 < 7 < 6 < 37 < 9 10/03/19 - 10/31/19 < 8 < 9 < 15 < 8 < 20 < 8 < 11 < 9 < 6 < 38 < 10 10/31/19 - 12/04/19 < 6 < 7 < 13 < 7 < 15 < 7 < 12 < 7 < 7 < 34 < 9 12/04/19 - 01/02/20 < 5 < 5 < 11 < 6 < 14 < 6 < 11 < 7 < 7 < 28 < 7 C-2 MEAN - - - - - - - - - - -

Q9-1 01/03/19 - 01/30/19 < 4 < 6 < 16 < 7 < 14 < 7 < 9 < 8 < 9 < 34 < 13 01/30/19 - 02/27/19 < 6 < 6 < 14 < 7 < 13 < 6 < 11 < 7 < 6 < 36 < 9 02/27/19 - 03/27/19 < 7 < 6 < 16 < 7 < 15 < 8 < 11 < 8 < 7 < 31 < 10 03/27/19 - 05/01/19 < 6 < 8 < 12 < 8 < 15 < 7 < 13 < 8 < 9 < 33 < 11 05/01/19 - 05/30/19 < 7 < 6 < 12 < 7 < 14 < 6 < 9 < 9 < 5 < 25 < 8 05/30/19 - 06/27/19 < 6 < 5 < 13 < 6 < 11 < 6 < 12 < 6 < 7 < 25 < 8 06/27/19 - 08/01/19 < 6 < 5 < 10 < 4 < 11 < 6 < 10 < 6 < 4 < 22 < 7 08/01/19 - 08/29/19 < 7 < 7 < 13 < 6 < 18 < 7 < 12 < 9 < 9 < 30 < 8 08/29/19 - 10/03/19 < 8 < 8 < 15 < 9 < 19 < 9 < 15 < 8 < 10 < 40 < 14 10/03/19 - 10/31/19 < 6 < 6 < 15 < 7 < 13 < 8 < 12 < 8 < 6 < 31 < 12 10/31/19 - 12/04/19 < 8 < 7 < 16 < 7 < 18 < 8 < 14 < 8 < 7 < 33 < 10 12/04/19 - 01/02/20 < 7 < 7 < 12 < 6 < 12 < 6 < 11 < 8 < 5 < 28 < 10 MEAN - - - - - - - - - - -

Table C-II.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 01/03/19 - 01/30/19 2.2 +/- 1.4 < 2.0 < 1.9 01/30/19 - 02/27/19 < 2.1 2.2 +/- 1.4 < 2.0 02/27/19 - 03/27/19 2.6 +/- 1.4 < 1.9 < 1.8 03/27/19 - 05/01/19 < 2.1 < 2.0 < 1.9 05/01/19 - 05/30/19 < 2.2 < 2.0 < 1.9 05/30/19 - 06/27/19 3.2 +/- 1.6 < 2.0 2.1 +/- 1.4 06/27/19 - 08/01/19 3.8 +/- 1.7 < 2.2 < 2.1 08/01/19 - 08/29/19 2.8 +/- 1.6 < 2.2 < 2.1 08/29/19 - 10/03/19 4.4 +/- 1.5 3.4 +/- 1.5 3.5 +/- 1.4 10/03/19 - 10/31/19 2.4 +/- 1.5 3.8 +/- 1.6 < 2.1 10/31/19 - 12/04/19 2.3 +/- 1.4 3.3 +/- 1.5 2.5 +/- 1.4 12/04/19 - 01/02/20 5.6 +/- 1.7 2.9 +/- 1.4 < 1.9 MEAN +/- 2 STD DEV 3.3 +/- 2.3 3.1 +/- 1.2 2.7 +/- 1.5 Table C-II.2 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 01/03/19 - 01/30/19 < 0.7 < 0.6 < 0.6 01/30/19 - 02/27/19 < 0.5 < 0.8 < 0.5 02/27/19 - 03/27/19 < 0.7 < 0.8 < 0.7 03/27/19 - 05/01/19 < 0.6 < 0.6 < 0.6 05/01/19 - 05/30/19 < 0.7 < 0.9 < 0.9 05/30/19 - 06/27/19 < 0.9 < 0.8 < 0.8 06/27/19 - 08/01/19 < 0.6 < 0.7 < 0.9 08/01/19 - 08/29/19 < 0.8 < 0.9 < 0.6 08/29/19 - 10/03/19 < 0.5 < 0.8 < 0.5 10/03/19 - 10/31/19 < 0.9 < 0.9 < 0.8 10/31/19 - 12/04/19 < 0.9 < 0.8 < 0.7 12/04/19 - 01/02/20 < 0.5 < 0.5 < 0.4 MEAN - - -

Table C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 01/03/19 - 01/30/19 < 194 < 192 < 189 01/30/19 - 02/27/19 < 196 < 195 < 198 02/27/19 - 03/27/19 < 198 < 182 < 175 03/27/19 - 05/01/19 < 170 < 190 < 183 05/01/19 - 05/30/19 < 196 < 191 < 196 05/30/19 - 06/27/19 < 195 < 193 < 196 06/27/19 - 08/01/19 < 196 < 192 < 194 08/01/19 - 08/29/19 < 180 < 180 < 179 08/29/19 - 10/03/19 < 193 203 +/- 128 < 195 10/03/19 - 10/31/19 < 192 < 190 < 192 10/31/19 - 12/04/19 < 188 < 187 < 187 12/04/19 - 01/02/20 < 188 < 189 < 187 MEAN +/- 2 STD DEV - 203 +/- 0 -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-3

Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 G15-2 01/03/19 - 01/30/19 < 6 < 5 < 11 < 7 < 9 < 6 < 10 < 7 < 5 < 28 < 10 01/30/19 - 02/27/19 < 4 < 5 < 11 < 5 < 9 < 5 < 8 < 5 < 5 < 26 < 7 02/27/19 - 03/27/19 < 9 < 7 < 18 < 9 < 12 < 8 < 15 < 8 < 7 < 38 < 10 03/27/19 - 05/01/19 < 6 < 7 < 15 < 8 < 14 < 6 < 11 < 8 < 9 < 27 < 11 05/01/19 - 05/30/19 < 6 < 6 < 10 < 6 < 11 < 6 < 10 < 8 < 7 < 27 < 10 05/30/19 - 06/27/19 < 7 < 8 < 12 < 10 < 13 < 7 < 13 < 8 < 8 < 32 < 11 06/27/19 - 08/01/19 < 5 < 7 < 12 < 7 < 16 < 7 < 11 < 7 < 6 < 27 < 12 08/01/19 - 08/29/19 < 7 < 7 < 12 < 8 < 11 < 6 < 10 < 6 < 7 < 32 < 12 08/29/19 - 10/03/19 < 7 < 5 < 17 < 6 < 13 < 6 < 11 < 6 < 8 < 35 < 8 10/03/19 - 10/31/19 < 7 < 7 < 15 < 13 < 15 < 8 < 11 < 8 < 10 < 36 < 11 10/31/19 - 12/04/19 < 8 < 6 < 14 < 6 < 11 < 8 < 11 < 8 < 7 < 32 < 12 12/04/19 - 01/02/20 < 5 < 6 < 11 < 6 < 12 < 6 < 10 < 6 < 5 < 23 < 8 MEAN - - - - - - - - - - -

G15-3 01/03/19 - 01/30/19 < 7 < 7 < 14 < 5 < 13 < 6 < 12 < 8 < 7 < 30 < 8 01/30/19 - 02/27/19 < 6 < 6 < 13 < 8 < 13 < 6 < 11 < 7 < 6 < 30 < 11 02/27/19 - 03/27/19 < 7 < 7 < 12 < 6 < 13 < 6 < 11 < 7 < 7 < 35 < 9 C-4 03/27/19 - 05/01/19 < 5 < 6 < 18 < 13 < 14 < 6 < 10 < 8 < 6 < 29 < 9 05/01/19 - 05/30/19 < 5 < 6 < 14 < 8 < 13 < 6 < 12 < 5 < 6 < 24 < 11 05/30/19 - 06/27/19 < 6 < 7 < 18 < 8 < 10 < 7 < 12 < 7 < 8 < 35 < 13 06/27/19 - 08/01/19 < 6 < 7 < 14 < 8 < 16 < 7 < 10 < 9 < 7 < 34 < 11 08/01/19 - 08/29/19 < 7 < 6 < 19 < 10 < 16 < 9 < 17 < 8 < 8 < 35 < 13 08/29/19 - 10/03/19 < 8 < 7 < 14 < 7 < 14 < 6 < 11 < 8 < 7 < 30 < 9 10/03/19 - 10/31/19 < 10 < 11 < 18 < 10 < 28 < 12 < 16 < 11 < 10 < 44 < 11 10/31/19 - 12/04/19 < 8 < 6 < 14 < 8 < 13 < 8 < 13 < 7 < 6 < 36 < 9 12/04/19 - 01/02/20 < 5 < 4 < 11 < 6 < 13 < 7 < 10 < 6 < 5 < 29 < 8 MEAN - - - - - - - - - - -

Q9-1 01/03/19 - 01/30/19 < 5 < 5 < 13 < 7 < 13 < 6 < 9 < 6 < 6 < 25 < 8 01/30/19 - 02/27/19 < 7 < 7 < 15 < 8 < 9 < 6 < 11 < 5 < 6 < 38 < 14 02/27/19 - 03/27/19 < 5 < 6 < 16 < 5 < 13 < 7 < 11 < 7 < 6 < 28 < 8 03/27/19 - 05/01/19 < 6 < 6 < 14 < 7 < 13 < 8 < 13 < 8 < 6 < 31 < 9 05/01/19 - 05/30/19 < 5 < 5 < 9 < 9 < 14 < 7 < 7 < 5 < 5 < 23 < 8 05/30/19 - 06/27/19 < 6 < 4 < 11 < 5 < 9 < 7 < 9 < 5 < 6 < 28 < 10 06/27/19 - 08/01/19 < 7 < 7 < 14 < 6 < 13 < 7 < 12 < 7 < 7 < 33 < 8 08/01/19 - 08/29/19 < 6 < 5 < 10 < 5 < 13 < 5 < 10 < 6 < 5 < 27 < 9 08/29/19 - 10/03/19 < 8 < 7 < 17 < 7 < 15 < 7 < 10 < 9 < 7 < 21 < 9 10/03/19 - 10/31/19 < 7 < 6 < 15 < 8 < 12 < 8 < 11 < 8 < 9 < 32 < 12 10/31/19 - 12/04/19 < 6 < 8 < 10 < 8 < 10 < 5 < 14 < 9 < 7 < 25 < 12 12/04/19 - 01/02/20 < 7 < 5 < 12 < 7 < 14 < 7 < 12 < 8 < 7 < 28 < 10 MEAN - - - - - - - - - - -

Table C-III.1 CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD GR-B I-131 H-3 SR-89 SR-90 K1-1 01/03/19 - 01/30/19 3.4 +/- 1.6 < 0.5 29100 +/- 2950 01/30/19 - 02/27/19 < 2.1 < 0.8 91300 +/- 9170 02/27/19 - 03/27/19 2.8 +/- 1.5 < 0.8 220 +/- 129 03/27/19 - 05/01/19 2.3 +/- 1.5 < 0.7 44000 +/- 4460 05/01/19 - 05/30/19 2.9 +/- 1.5 < 1.0 < 191 05/30/19 - 06/27/19 5.0 +/- 1.8 < 0.8 75800 +/- 7590 01/03/19 - 06/27/19 < 4.3 < 0.7 06/27/19 - 08/01/19 4.7 +/- 1.9 < 0.8 20300 +/- 2090 08/01/19 - 08/29/19 7.1 +/- 2.2 < 0.7 11400 +/- 1200 08/29/19 - 10/03/19 6.1 +/- 1.9 < 0.8 12700 +/- 1330 10/03/19 - 10/31/19 5.3 +/- 1.7 < 0.9 < 191 10/31/19 - 12/04/19 2.6 +/- 1.4 < 0.8 < 189 12/04/19 - 01/02/20 < 1.8 < 0.8 < 195 06/27/19 - 01/02/20 < 3.1 < 0.6 MEAN +/- 2 STD DEV 4.2 +/- 3.4 - 35603 +/- 65147 - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-5

Table C-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 K1-1 01/03/19 - 01/30/19 < 8 < 8 < 15 < 8 < 17 < 9 < 14 < 9 < 8 < 38 < 12 01/30/19 - 02/27/19 < 6 < 5 < 13 < 6 < 12 < 8 < 9 < 6 < 7 < 28 < 7 02/27/19 - 03/27/19 < 6 < 8 < 15 < 6 < 15 < 7 < 10 < 8 < 7 < 24 < 12 03/27/19 - 05/01/19 < 7 < 5 < 15 < 7 < 14 < 6 < 12 < 8 < 7 < 32 < 11 05/01/19 - 05/30/19 < 6 < 8 < 12 < 6 < 13 < 6 < 10 < 7 < 7 < 27 < 10 05/30/19 - 06/27/19 < 6 < 7 < 11 < 7 < 10 < 7 < 14 < 7 < 6 < 23 < 10 06/27/19 - 08/01/19 < 5 < 5 < 12 < 5 < 13 < 6 < 11 < 7 < 6 < 24 < 6 08/01/19 - 08/29/19 < 5 < 5 < 12 < 6 < 8 < 4 < 10 < 7 < 6 < 25 < 11 08/29/19 - 10/03/19 < 5 < 7 < 12 < 8 < 14 < 7 < 9 < 8 < 5 < 32 < 14 10/03/19 - 10/31/19 < 7 < 7 < 17 < 8 < 16 < 7 < 13 < 7 < 5 < 25 < 10 10/31/19 - 12/04/19 < 5 < 5 < 12 < 5 < 11 < 6 < 11 < 5 < 6 < 28 < 10 C-6 12/04/19 - 01/02/20 < 6 < 6 < 15 < 8 < 6 < 6 < 11 < 8 < 7 < 26 < 8 MEAN - - - - - - - - - - -

Table C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH) SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE Sr-90 BKGB BOTTOM FEEDER 06/12/19 < 4.1 09/27/19 < 4.8 MEAN -

BKGP PREDATOR 06/12/19 < 3.0 09/27/19 < 2.5 MEAN -

INDB BOTTOM FEEDER 06/06/19 < 4.4 09/26/19 < 4.5 MEAN -

INDP PREDATOR 06/06/19 < 3.6 09/26/19 < 2.6 MEAN -

C-7

Table C-IV.2 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINTY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 BKGB BOTTOM FEEDER 06/12/19 3194 +/- 844 < 46 < 38 < 89 < 50 < 86 < 39 < 52 09/27/19 3360 +/- 1046 < 52 < 53 < 71 < 72 < 134 < 66 < 65 MEAN +/- 2 STD DEV 3277 +/- 235 - - - - - - -

BKGP PREDATOR 06/12/19 3683 +/- 772 < 42 < 42 < 94 < 47 < 107 < 51 < 49 09/27/19 3365 +/- 827 < 49 < 31 < 83 < 44 < 99 < 54 < 47 MEAN +/- 2 STD DEV 3524 +/- 450 - - - - - - -

INDB BOTTOM FEEDER 06/06/19 3790 +/- 820 < 52 < 46 < 121 < 43 < 109 < 60 < 49 09/26/19 3197 +/- 1060 < 82 < 81 < 164 < 75 < 186 < 95 < 95 MEAN +/- 2 STD DEV 3494 +/- 839 - - - - - - -

INDP PREDATOR 06/06/19 3393 +/- 566 < 33 < 32 < 70 < 39 < 77 < 37 < 30 09/26/19 2875 +/- 828 < 60 < 75 < 129 < 74 < 153 < 76 < 58 MEAN +/- 2 STD DEV 3134 +/- 733 - - - - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-8

Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 A1-3 06/18/19 12650 +/- 1616 < 94 < 92 < 104 < 117 112 +/- 79 10/30/19 6261 +/- 875 < 50 < 45 < 54 < 63 < 54 MEAN +/- 2 STD DEV 9456 + 9035 - - - - 112 + 0 J2-1 06/18/19 14690 +/- 1688 < 110 < 112 < 102 < 137 < 140 10/30/19 8961 +/- 1508 < 60 < 57 < 65 < 102 < 91 MEAN +/- 2 STD DEV 11826 + 8102 - - - - -

K1-3 06/18/19 11310 +/- 1610 < 62 < 63 < 82 < 79 < 79 10/30/19 13410 +/- 2108 < 118 < 85 < 100 < 145 < 141 MEAN +/- 2 STD DEV 12360 + 2970 - - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-9

Table C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD E1-2 F1-3 A3-1 G2-1 H3-1 M2-1 Q15-1 12/27/18 - 01/03/19 11 +/- 4 10 +/- 4 10 +/- 3 14 +/- 4 12 +/- 4 11 +/- 4 13 +/- 4 01/03/19 - 01/10/19 15 +/- 4 15 +/- 4 12 +/- 3 16 +/- 4 14 +/- 4 16 +/- 4 15 +/- 4 01/10/19 - 01/16/19 15 +/- 5 14 +/- 5 11 +/- 4 13 +/- 5 17 +/- 5 13 +/- 5 15 +/- 5 01/16/19 - 01/23/19 15 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 13 +/- 4 13 +/- 4 13 +/- 4 01/23/19 - 01/30/19 17 +/- 4 22 +/- 4 16 +/- 4 17 +/- 4 16 +/- 4 18 +/- 4 21 +/- 4 01/30/19 - 02/07/19 17 +/- 4 16 +/- 4 17 +/- 4 19 +/- 4 16 +/- 4 19 +/- 4 20 +/- 4 02/07/19 - 02/14/19 15 +/- 4 15 +/- 4 11 +/- 4 15 +/- 4 13 +/- 4 10 +/- 4 12 +/- 4 02/14/19 - 02/21/19 15 +/- 4 15 +/- 4 16 +/- 4 15 +/- 4 18 +/- 4 14 +/- 4 16 +/- 4 02/21/19 - 02/27/19 23 +/- 5 23 +/- 5 26 +/- 5 25 +/- 5 22 +/- 5 26 +/- 5 22 +/- 5 02/27/19 - 03/07/19 12 +/- 4 9 +/- 3 11 +/- 3 12 +/- 4 11 +/- 4 14 +/- 4 13 +/- 4 03/07/19 - 03/14/19 21 +/- 5 16 +/- 4 19 +/- 4 20 +/- 4 22 +/- 5 18 +/- 4 18 +/- 4 03/14/19 - 03/21/19 13 +/- 4 13 +/- 4 11 +/- 3 15 +/- 4 17 +/- 4 14 +/- 4 13 +/- 4 03/21/19 - 03/27/19 < 6 9 +/- 4 < 5 7 +/- 4 < 6 < 6 10 +/- 5 03/27/19 - 04/04/19 10 +/- 3 8 +/- 3 12 +/- 3 16 +/- 4 11 +/- 4 14 +/- 4 12 +/- 4 04/04/19 - 04/11/19 9 +/- 4 11 +/- 4 8 +/- 3 11 +/- 4 8 +/- 4 10 +/- 4 10 +/- 4 04/11/19 - 04/18/19 9 +/- 4 11 +/- 4 10 +/- 4 11 +/- 4 13 +/- 4 13 +/- 4 12 +/- 4 04/18/19 - 04/25/19 < 5 7 +/- 4 5 +/- 3 6 +/- 4 7 +/- 4 5 +/- 3 5 +/- 4 04/25/19 - 05/01/19 10 +/- 4 7 +/- 4 8 +/- 4 9 +/- 4 9 +/- 4 6 +/- 4 11 +/- 4 05/01/19 - 05/09/19 10 +/- 4 9 +/- 3 11 +/- 3 8 +/- 3 8 +/- 3 12 +/- 4 12 +/- 4 05/09/19 - 05/15/19 < 6 < 6 < 6 < 6 < 6 7 +/- 4 < 6 05/15/19 - 05/22/19 20 +/- 4 19 +/- 4 18 +/- 4 21 +/- 4 14 +/- 4 19 +/- 4 19 +/- 4 05/22/19 - 05/30/19 10 +/- 3 10 +/- 3 9 +/- 3 7 +/- 3 8 +/- 3 10 +/- 3 12 +/- 4 05/30/19 - 06/07/19 (1) 16 +/- 4 16 +/- 4 12 +/- 4 17 +/- 4 10 +/- 3 15 +/- 4 06/07/19 - 06/13/19 12 +/- 5 9 +/- 4 12 +/- 4 16 +/- 5 9 +/- 4 10 +/- 4 11 +/- 5 06/13/19 - 06/19/19 12 +/- 4 12 +/- 4 12 +/- 4 8 +/- 4 9 +/- 4 9 +/- 4 8 +/- 4 06/19/19 - 06/27/19 13 +/- 3 14 +/- 3 17 +/- 4 19 +/- 4 13 +/- 3 13 +/- 3 17 +/- 4 06/27/19 - 07/03/19 17 +/- 5 20 +/- 5 21 +/- 5 18 +/- 5 15 +/- 5 17 +/- 5 18 +/- 5 07/03/19 - 07/11/19 11 +/- 3 12 +/- 3 13 +/- 3 11 +/- 3 14 +/- 4 10 +/- 3 12 +/- 3 07/11/19 - 07/18/19 14 +/- 4 14 +/- 4 11 +/- 4 12 +/- 4 9 +/- 4 13 +/- 4 15 +/- 4 07/18/19 - 07/25/19 (1) 10 +/- 4 10 +/- 4 6 +/- 3 9 +/- 4 9 +/- 4 9 +/- 4 07/25/19 - 08/01/19 16 +/- 4 17 +/- 4 19 +/- 4 20 +/- 5 18 +/- 4 16 +/- 4 19 +/- 4 08/01/19 - 08/07/19 19 +/- 5 17 +/- 5 21 +/- 5 16 +/- 5 17 +/- 5 13 +/- 5 12 +/- 5 08/07/19 - 08/15/19 15 +/- 4 18 +/- 4 17 +/- 4 17 +/- 4 21 +/- 4 16 +/- 4 17 +/- 4 08/15/19 - 08/21/19 20 +/- 5 24 +/- 6 24 +/- 5 25 +/- 6 26 +/- 6 18 +/- 5 24 +/- 5 08/21/19 - 08/29/19 10 +/- 3 11 +/- 4 15 +/- 4 12 +/- 4 11 +/- 3 11 +/- 3 12 +/- 4 08/29/19 - 09/05/19 13 +/- 4 16 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 18 +/- 4 17 +/- 4 09/05/19 - 09/12/19 17 +/- 4 19 +/- 4 17 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 19 +/- 4 09/12/19 - 09/18/19 12 +/- 5 15 +/- 5 18 +/- 5 17 +/- 5 18 +/- 5 16 +/- 5 13 +/- 5 09/18/19 - 09/26/19 15 +/- 4 19 +/- 4 19 +/- 4 15 +/- 4 19 +/- 4 18 +/- 4 17 +/- 4 09/26/19 - 10/03/19 19 +/- 4 21 +/- 4 23 +/- 4 21 +/- 5 25 +/- 5 20 +/- 4 22 +/- 5 10/03/19 - 10/10/19 11 +/- 4 10 +/- 4 12 +/- 4 11 +/- 4 12 +/- 4 12 +/- 4 13 +/- 4 10/10/19 - 10/17/19 12 +/- 4 16 +/- 4 15 +/- 4 14 +/- 4 17 +/- 4 13 +/- 4 17 +/- 4 10/17/19 - 10/24/19 11 +/- 4 10 +/- 4 11 +/- 4 10 +/- 4 9 +/- 4 8 +/- 3 12 +/- 4 10/24/19 - 10/31/19 14 +/- 4 14 +/- 4 10 +/- 4 12 +/- 4 15 +/- 4 12 +/- 4 12 +/- 4 10/31/19 - 11/07/19 11 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 15 +/- 4 15 +/- 4 19 +/- 5 11/07/19 - 11/14/19 14 +/- 4 10 +/- 4 14 +/- 4 16 +/- 4 13 +/- 4 14 +/- 4 13 +/- 4 11/14/19 - 11/21/19 16 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 17 +/- 4 17 +/- 4 11/21/19 - 11/27/19 16 +/- 4 14 +/- 4 14 +/- 4 14 +/- 4 15 +/- 4 16 +/- 4 13 +/- 4 11/27/19 - 12/04/19 8 +/- 4 8 +/- 4 7 +/- 3 8 +/- 4 7 +/- 4 9 +/- 4 9 +/- 4 12/04/19 - 12/12/19 10 +/- 4 13 +/- 4 15 +/- 4 11 +/- 4 11 +/- 4 14 +/- 4 16 +/- 4 12/12/19 - 12/19/19 17 +/- 4 16 +/- 4 15 +/- 4 16 +/- 4 18 +/- 4 14 +/- 4 18 +/- 4 12/19/19 - 12/26/19 33 +/- 5 29 +/- 5 32 +/- 5 32 +/- 5 25 +/- 5 25 +/- 5 32 +/- 5 12/26/19 - 01/02/20 14 +/- 4 19 +/- 4 19 +/- 4 16 +/- 4 17 +/- 4 15 +/- 4 17 +/- 4 MEAN +/- 2 STD DEV 14 +/- 9 14 +/- 9 15 +/- 10 15 +/- 10 14 +/- 9 14 +/- 8 15 +/- 9 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-10

Table C-VI.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - CLOSEST TO THE SITE BOUNDARY GROUP II - INTERMEDIATE OFFSITE GROUP III - CONTROL LOCATIONS COLLECTION MEAN COLLECTION MEAN COLLECTION MEAN PERIOD MIN MAX +/- 2SD PERIOD MIN MAX +/- 2SD PERIOD MIN MAX +/- 2SD 12/27/18 - 01/30/19 10 22 15 +/- 6 12/27/18 - 01/30/19 10 18 14 +/- 5 12/27/18 - 01/30/19 13 21 16 +/- 6 01/30/19 - 02/27/19 15 23 17 +/- 7 01/30/19 - 02/27/19 10 26 17 +/- 10 01/30/19 - 02/27/19 12 22 17 +/- 9 02/27/19 - 03/27/19 9 21 13 +/- 8 02/27/19 - 03/27/19 7 22 15 +/- 9 02/27/19 - 03/27/19 10 18 13 +/- 6 03/27/19 - 05/01/19 7 11 9 +/- 3 03/27/19 - 05/01/19 5 16 10 +/- 6 03/27/19 - 05/01/19 5 12 10 +/- 5 05/01/19 - 05/30/19 9 20 13 +/- 10 05/01/19 - 05/30/19 7 21 11 +/- 10 05/01/19 - 05/30/19 12 19 14 +/- 7 05/30/19 - 06/27/19 9 16 12 +/- 4 05/30/19 - 06/27/19 8 19 13 +/- 7 05/30/19 - 06/27/19 8 17 13 +/- 8 06/27/19 - 08/01/19 10 20 15 +/- 6 06/27/19 - 08/01/19 6 21 14 +/- 8 06/27/19 - 08/01/19 9 19 15 +/- 8 08/01/19 - 08/29/19 10 24 17 +/- 9 08/01/19 - 08/29/19 11 26 17 +/- 10 08/01/19 - 08/29/19 12 24 16 +/- 11 08/29/19 - 10/03/19 12 21 17 +/- 6 08/29/19 - 10/03/19 14 25 18 +/- 6 08/29/19 - 10/03/19 13 22 17 +/- 6 10/03/19 - 10/31/19 10 16 12 +/- 4 10/03/19 - 10/31/19 8 17 12 +/- 5 10/03/19 - 10/31/19 12 17 14 +/- 4 C-11 10/31/19 - 12/04/19 8 16 13 +/- 7 10/31/19 - 12/04/19 7 17 13 +/- 6 10/31/19 - 12/04/19 9 19 14 +/- 8 12/04/19 - 01/02/20 10 33 19 +/- 16 12/04/19 - 01/02/20 11 32 18 +/- 13 12/04/19 - 01/02/20 16 32 21 +/- 16 12/27/18 - 01/02/20 7 33 14 +/- 9 12/27/18 - 01/02/20 5 32 14 +/- 9 12/27/18 - 01/02/20 5 32 15 +/- 9

Table C-VI.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION SITE PERIOD Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 A3-1 12/27/18 - 03/27/19 76 +/- 18 < 3 < 3 < 3 < 3 < 6 < 3 < 3 03/27/19 - 06/27/19 80 +/- 22 < 3 < 3 < 3 < 3 < 6 < 3 < 2 06/27/19 - 10/03/19 72 +/- 18 < 2 < 2 < 2 < 2 < 3 < 2 < 2 10/03/19 - 01/02/20 65 +/- 15 < 1 < 2 < 2 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 73 +/- 13 - - - - - - -

E1-2 12/27/18 - 03/27/19 64 +/- 22 < 2 < 3 < 3 < 3 < 4 < 2 < 2 03/27/19 - 06/27/19 70 +/- 22 < 2 < 2 < 3 < 3 < 6 < 3 < 3 06/27/19 - 10/03/19 75 +/- 19 < 3 < 3 < 4 < 3 < 5 < 2 < 3 10/03/19 - 01/02/20 55 +/- 16 < 2 < 2 < 2 < 2 < 2 < 2 < 2 MEAN +/- 2 STD DEV 66 +/- 17 - - - - - - -

F1-3 12/27/18 - 03/27/19 84 +/- 19 < 2 < 2 < 2 < 2 < 4 < 2 < 2 03/27/19 - 06/27/19 67 +/- 20 < 2 < 2 < 2 < 3 < 5 < 2 < 2 06/27/19 - 10/03/19 65 +/- 23 < 3 < 3 < 3 < 3 < 4 < 3 < 2 10/03/19 - 01/02/20 61 +/- 16 < 2 < 2 < 3 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 69 +/- 20 - - - - - - -

G2-1 12/27/18 - 03/27/19 74 +/- 26 < 3 < 3 < 3 < 3 < 4 < 2 < 2 03/27/19 - 06/27/19 85 +/- 34 < 4 < 4 < 4 < 4 < 6 < 4 < 3 06/27/19 - 10/03/19 62 +/- 17 < 2 < 2 < 3 < 2 < 4 < 2 < 2 10/03/19 - 01/02/20 52 +/- 16 < 2 < 2 < 3 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 68 +/- 28 - - - - - - -

H3-1 12/27/18 - 03/27/19 83 +/- 28 < 3 < 4 < 4 < 3 < 6 < 3 < 3 03/27/19 - 06/27/19 75 +/- 22 < 2 < 3 < 3 < 3 < 5 < 2 < 2 06/27/19 - 10/03/19 71 +/- 20 < 2 < 3 < 3 < 2 < 4 < 2 < 2 10/03/19 - 01/02/20 52 +/- 20 < 1 < 1 < 2 < 2 < 4 < 2 < 2 MEAN +/- 2 STD DEV 70 +/- 26 - - - - - - -

M2-1 12/27/18 - 03/27/19 77 +/- 21 < 2 < 2 < 3 < 2 < 5 < 3 < 2 03/27/19 - 06/27/19 72 +/- 18 < 2 < 2 < 2 < 2 < 4 < 2 < 1 06/27/19 - 10/03/19 76 +/- 20 < 3 < 2 < 3 < 3 < 4 < 3 < 2 10/03/19 - 01/02/20 52 +/- 13 < 1 < 2 < 2 < 1 < 3 < 1 < 2 MEAN +/- 2 STD DEV 69 +/- 23 - - - - - - -

Q15-1 12/27/18 - 03/27/19 87 +/- 22 < 2 < 3 < 2 < 3 < 3 < 2 < 2 03/27/19 - 06/27/19 77 +/- 19 < 2 < 2 < 2 < 2 < 4 < 3 < 2 06/27/19 - 10/03/19 88 +/- 17 < 2 < 3 < 4 < 3 < 4 < 3 < 2 10/03/19 - 01/02/20 68 +/- 14 < 2 < 2 < 2 < 2 < 2 < 1 < 2 MEAN +/- 2 STD DEV 80 +/- 19 - - - - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-12

Table C-VII.1 CONCENTRATIONS OF I-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PERIOD E1-2 F1-3 A3-1 G2-1 H3-1 M2-1 Q15-1 12/27/18 - 01/03/19 < 59 < 57 < 47 < 59 < 58 < 52 < 53 01/03/19 - 01/10/19 < 59 < 57 < 46 < 60 < 59 < 51 < 52 01/10/19 - 01/16/19 < 37 < 36 < 47 < 38 < 37 < 52 < 53 01/16/19 - 01/23/19 < 36 < 34 < 17 < 36 < 35 < 43 < 44 01/23/19 - 01/30/19 < 45 < 43 < 45 < 45 < 44 < 50 < 51 01/30/19 - 02/07/19 < 44 < 43 < 20 < 45 < 44 < 40 < 41 02/07/19 - 02/14/19 < 59 < 57 < 21 < 59 < 58 < 65 < 66 02/14/19 - 02/21/19 < 34 < 33 < 18 < 34 < 34 < 47 < 47 02/21/19 - 02/27/19 < 60 < 57 < 56 < 59 < 59 < 62 < 63 02/27/19 - 03/07/19 < 17 < 17 < 14 < 17 < 17 < 37 < 38 03/07/19 - 03/14/19 < 57 < 55 < 29 < 57 < 57 < 32 < 32 03/14/19 - 03/21/19 < 38 < 37 < 21 < 38 < 38 < 42 < 43 03/21/19 - 03/27/19 < 43 < 23 < 59 < 43 < 43 < 65 < 66 03/27/19 - 04/04/19 < 45 < 43 < 28 < 45 < 44 < 31 < 31 04/04/19 - 04/11/19 < 38 < 37 < 28 < 39 < 38 < 37 < 38 04/11/19 - 04/18/19 < 43 < 41 < 18 < 43 < 43 < 48 < 49 04/18/19 - 04/25/19 < 25 < 24 < 20 < 25 < 24 < 40 < 41 04/25/19 - 05/01/19 < 49 < 47 < 19 < 50 < 49 < 25 < 26 05/01/19 - 05/09/19 < 35 < 34 < 20 < 35 < 35 < 22 < 22 05/09/19 - 05/15/19 < 19 < 20 < 54 < 20 < 20 < 55 < 57 05/15/19 - 05/22/19 < 45 < 46 < 20 < 46 < 46 < 18 < 26 05/22/19 - 05/30/19 < 36 < 36 < 40 < 35 < 36 < 42 < 43 05/30/19 - 06/07/19 (1) < 43 < 21 < 43 < 43 < 42 < 18 06/07/19 - 06/13/19 < 41 < 51 < 25 < 33 < 33 < 32 < 33 06/13/19 - 06/19/19 < 11 < 11 < 13 < 11 < 11 < 10 < 15 06/19/19 - 06/27/19 < 47 < 49 < 22 < 48 < 48 < 23 < 24 06/27/19 - 07/03/19 < 42 < 43 < 42 < 43 < 42 < 18 < 45 07/03/19 - 07/11/19 < 32 < 18 < 19 < 49 < 49 < 49 < 51 07/11/19 - 07/18/19 < 30 < 31 < 17 < 32 < 32 < 32 < 33 07/18/19 - 07/25/19 (1) < 34 < 51 < 34 < 33 < 33 < 56 07/25/19 - 08/01/19 < 24 < 25 < 39 < 42 < 42 < 41 < 23 08/01/19 - 08/07/19 < 37 < 37 < 18 < 51 < 50 < 46 < 48 08/07/19 - 08/15/19 < 21 < 22 < 38 < 21 < 21 < 18 < 42 08/15/19 - 08/21/19 < 33 < 28 < 43 < 33 < 33 < 30 < 15 08/21/19 - 08/29/19 < 21 < 22 < 35 < 24 < 21 < 37 < 38 08/29/19 - 09/05/19 < 33 < 34 < 21 < 27 < 26 < 27 < 28 09/05/19 - 09/12/19 < 32 < 32 < 28 < 31 < 30 < 29 < 16 09/12/19 - 09/18/19 < 53 < 55 < 33 < 55 < 41 < 40 < 43 09/18/19 - 09/26/19 < 37 < 38 < 37 < 37 < 37 < 40 < 41 09/26/19 - 10/03/19 < 30 < 30 < 13 < 30 < 30 < 25 < 15 10/03/19 - 10/10/19 < 36 < 15 < 23 < 30 < 30 < 30 < 31 10/10/19 - 10/17/19 < 32 < 33 < 9 < 32 < 32 < 8 < 10 10/17/19 - 10/24/19 < 46 < 46 < 19 < 25 < 24 < 24 < 25 10/24/19 - 10/31/19 < 28 < 26 < 38 < 41 < 40 < 40 < 35 10/31/19 - 11/07/19 < 33 < 18 < 26 < 27 < 27 < 27 < 14 11/07/19 - 11/14/19 < 19 < 20 < 29 < 20 < 20 < 30 < 31 11/14/19 - 11/21/19 < 19 < 17 < 16 < 37 < 36 < 36 < 38 11/21/19 - 11/27/19 < 39 < 47 < 26 < 33 < 33 < 33 < 34 11/27/19 - 12/04/19 < 28 < 24 < 14 < 38 < 38 < 36 < 37 12/04/19 - 12/12/19 < 23 < 23 < 26 < 23 < 23 < 10 < 29 12/12/19 - 12/19/19 < 39 < 33 < 15 < 16 < 16 < 16 < 14 12/19/19 - 12/26/19 < 36 < 31 < 22 < 37 < 37 < 35 < 56 12/26/19 - 01/02/20 < 27 < 14 < 34 < 27 < 27 < 26 < 36 MEAN - - - - - - -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-13

TABLE C-VIII.1 CONCENTRATIONS OF I-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROL FARM INDICATOR FARMS PERIOD K15-3 E2-2 F4-1 G2-1 P4-1 01/09/19 < 0.5 (1) < 0.5 < 0.8 < 0.6 02/13/19 < 0.8 (1) < 0.9 < 1.0 < 1.0 03/06/19 < 0.6 (1) < 0.5 < 0.6 < 0.6 03/20/19 < 0.4 (1) < 0.7 < 0.8 < 0.7 04/03/19 < 0.5 (1) < 0.5 < 0.9 < 0.9 04/17/19 < 0.8 (1) < 0.6 < 0.7 < 0.7 05/01/19 < 0.5 (1) < 0.9 < 0.6 < 0.8 05/15/19 < 0.7 (1) < 0.6 < 0.9 < 0.7 05/29/19 < 0.6 (1) < 0.6 < 0.5 < 0.7 06/12/19 < 0.8 (1) < 0.8 < 0.8 < 1.0 06/26/19 < 0.8 (1) < 0.9 < 0.8 < 0.8 07/10/19 < 0.4 (1) < 0.6 < 0.6 < 0.6 07/24/19 < 0.8 (1) < 0.6 < 0.6 < 0.8 08/07/19 < 0.8 (1) < 0.7 < 0.7 < 0.7 08/21/19 < 0.3 (1) < 0.7 < 0.5 < 0.4 09/04/19 < 0.8 (1) < 1.0 < 0.9 < 0.6 09/18/19 < 0.8 (1) < 0.7 < 0.9 < 1.0 10/02/19 < 0.9 (1) < 0.9 < 0.8 < 0.9 10/16/19 < 0.8 (1) < 0.9 < 0.7 < 0.9 10/30/19 < 0.9 (1) < 0.9 < 0.8 < 0.8 11/13/19 < 0.5 (1) < 0.6 < 0.5 < 0.6 11/26/19 < 0.8 (1) < 0.6 < 0.9 < 0.8 12/11/19 < 0.9 (1) < 0.9 < 0.9 < 1.0 MEAN - - - - -

(1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-14

Table C-VIII.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDICATOR FARMS COLLECTION K15-3 E2-2 F4-1 G2-1 P4-1 PERIOD Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 01/09/19 - 03/20/19 < 2.8 < 0.6 (1) (1) < 4.2 < 0.8 < 2.9 < 0.7 < 3.4 < 0.6 04/03/19 - 06/26/19 < 4.6 < 0.9 (1) (1) < 3.7 < 0.9 < 3.6 < 0.8 < 4.4 < 0.9 07/10/19 - 09/18/19 < 4.2 < 0.9 (1) (1) < 4.2 < 0.9 < 4.1 < 0.9 < 3.9 < 0.9 10/02/19 - 12/11/19 < 4.1 0.9 +/- 0.5 (1) (1) < 4.2 < 1.0 < 3.8 < 0.8 < 3.8 < 0.8 MEAN +/- 2 STD DEV - 0.9 + 0 - - - - - -

C-15 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 (1)

E2-2 F4-1 01/09/19 1171 +/- 82 < 5 < 5 < 22 < 5 02/13/19 1327 +/- 152 < 12 < 9 < 45 < 10 03/06/19 1229 +/- 195 < 9 < 7 < 38 < 5 03/20/19 1333 +/- 189 < 9 < 7 < 24 < 9 04/03/19 1177 +/- 138 < 11 < 8 < 28 < 7 04/17/19 1253 +/- 194 < 8 < 7 < 33 < 13 05/01/19 1422 +/- 194 < 9 < 8 < 31 < 9 05/15/19 1324 +/- 163 < 7 < 7 < 30 < 8 05/29/19 1386 +/- 202 < 8 < 8 < 32 < 11 06/12/19 1297 +/- 199 < 10 < 9 < 25 < 5 06/26/19 1044 +/- 190 < 7 < 8 < 35 < 13 07/10/19 1345 +/- 186 < 10 < 10 < 32 < 10 07/24/19 1273 +/- 191 < 10 < 8 < 26 < 9 08/07/19 1482 +/- 183 < 9 < 8 < 35 < 9 08/21/19 1329 +/- 156 < 8 < 7 < 32 < 9 09/04/19 1392 +/- 194 < 9 < 9 < 42 < 10 09/18/19 1536 +/- 183 < 7 < 8 < 31 < 12 10/02/19 1321 +/- 211 < 10 < 7 < 33 < 12 10/16/19 1191 +/- 175 < 9 < 7 < 38 < 6 10/30/19 1233 +/- 168 < 9 < 9 < 36 < 11 11/13/19 1467 +/- 170 < 8 < 7 < 28 < 8 11/26/19 1321 +/- 210 < 10 < 10 < 42 < 13 12/11/19 1422 +/- 195 < 9 < 9 < 30 < 9 MEAN +/- 2 STD DEV 1316 +/- 227 - - - -

G2-1 1/9/2019 1434 +/- 172 < 7 < 6 < 22 < 7 02/13/19 1103 +/- 178 < 7 < 7 < 34 < 11 03/06/19 1115 +/- 175 < 10 < 9 < 43 < 10 03/20/19 1236 +/- 149 < 9 < 9 < 30 < 8 04/03/19 1316 +/- 174 < 7 < 7 < 23 < 7 04/17/19 1308 +/- 194 < 7 < 7 < 28 < 10 05/01/19 1316 +/- 199 < 9 < 8 < 33 < 14 05/15/19 1467 +/- 177 < 8 < 7 < 33 < 6 05/29/19 1126 +/- 163 < 9 < 7 < 34 < 14 06/11/19 1043 +/- 184 < 9 < 11 < 37 < 12 06/26/19 1222 +/- 207 < 8 < 9 < 32 < 8 07/10/19 1194 +/- 160 < 8 < 8 < 25 < 8 07/24/19 1114 +/- 194 < 9 < 11 < 41 < 11 08/07/19 1565 +/- 173 < 8 < 9 < 33 < 10 08/21/19 1401 +/- 166 < 8 < 7 < 31 < 5 09/04/19 1244 +/- 191 < 9 < 7 < 34 < 9 09/18/19 1485 +/- 176 < 9 < 8 < 36 < 11 10/02/19 1150 +/- 173 < 10 < 9 < 41 < 13 10/16/19 1041 +/- 180 < 8 < 7 < 38 < 12 10/30/19 1074 +/- 183 < 9 < 10 < 48 < 13 11/13/19 1392 +/- 157 < 7 < 6 < 20 < 6 11/26/19 1183 +/- 149 < 8 < 8 < 25 < 8 12/11/19 1361 +/- 192 < 11 < 10 < 33 < 14 MEAN +/- 2 STD DEV 1256 +/- 305 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-16

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 K15-3 01/09/19 1210 +/- 105 < 4 < 4 < 18 < 5 02/13/19 1085 +/- 187 < 6 < 8 < 31 < 11 3/6/2019 1308 +/- 195 < 9 < 7 < 41 < 10 03/20/19 1083 +/- 187 < 6 < 9 < 24 < 9 04/03/19 1208 +/- 178 < 10 < 8 < 25 < 7 04/17/19 1475 +/- 205 < 8 < 8 < 39 < 11 05/01/19 1051 +/- 138 < 9 < 9 < 43 < 10 05/15/19 1340 +/- 184 < 7 < 5 < 25 < 6 05/29/19 1128 +/- 137 < 7 < 8 < 32 < 9 06/12/19 974 +/- 177 < 8 < 7 < 23 < 10 06/26/19 1271 +/- 177 < 7 < 7 < 34 < 11 07/10/19 1211 +/- 168 < 7 < 6 < 24 < 7 07/24/19 2206 +/- 244 < 10 < 8 < 33 < 9 08/07/19 1121 +/- 184 < 8 < 7 < 30 < 8 08/21/19 1202 +/- 174 < 9 < 7 < 32 < 9 09/04/19 1379 +/- 189 < 10 < 8 < 32 < 10 09/18/19 1222 +/- 189 < 5 < 6 < 27 < 7 10/02/19 1168 +/- 200 < 11 < 9 < 47 < 12 10/16/19 1224 +/- 144 < 6 < 6 < 35 < 14 10/30/19 1255 +/- 171 < 11 < 11 < 51 < 13 11/13/19 1325 +/- 174 < 9 < 7 < 24 < 10 11/26/19 1121 +/- 172 < 8 < 8 < 33 < 11 12/11/19 1128 +/- 177 < 8 < 8 < 43 < 12 MEAN +/- 2 STD DEV 1248 +/- 476 - - - -

P4-1 01/09/19 1240 +/- 199 < 7 < 6 < 29 < 8 02/13/19 1379 +/- 138 < 9 < 9 < 40 < 10 03/06/19 1458 +/- 174 < 7 < 8 < 33 < 11 03/20/19 1210 +/- 197 < 10 < 8 < 29 < 8 04/03/19 1465 +/- 154 < 7 < 7 < 23 < 7 04/17/19 1582 +/- 201 < 7 < 7 < 32 < 12 05/01/19 1068 +/- 179 < 8 < 7 < 31 < 8 05/15/19 1568 +/- 176 < 7 < 6 < 24 < 9 05/29/19 1263 +/- 191 < 9 < 9 < 43 < 10 06/12/19 1332 +/- 159 < 9 < 8 < 27 < 7 06/26/19 1342 +/- 123 < 7 < 7 < 27 < 8 07/10/19 1253 +/- 198 < 9 < 6 < 24 < 7 07/24/19 1227 +/- 174 < 9 < 8 < 33 < 8 08/07/19 1232 +/- 196 < 9 < 8 < 35 < 8 08/21/19 1066 +/- 210 < 9 < 9 < 40 < 6 09/04/19 1499 +/- 177 < 7 < 5 < 24 < 8 09/18/19 1473 +/- 149 < 6 < 7 < 29 < 9 10/02/19 1386 +/- 210 < 9 < 9 < 36 < 12 10/16/19 1280 +/- 157 < 6 < 8 < 29 < 10 10/30/19 1276 +/- 208 < 7 < 10 < 33 < 12 11/13/19 1117 +/- 157 < 8 < 8 < 21 < 8 11/26/19 1362 +/- 157 < 10 < 8 < 42 < 12 12/11/19 1418 +/- 209 < 9 < 7 < 36 < 12 MEAN +/- 2 STD DEV 1326 +/- 289 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-17

Table C-IX.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Sr-90 Be-7 K-40 I-131 Cs-134 Cs-137 B10-2 Sunflower Leaves 06/26/19 < 3.2 1414 +/- 322 7265 +/- 726 < 33 < 26 < 26 Collard Leaves 06/26/19 5.6 +/- 2.6 < 254 5361 +/- 542 < 49 < 32 < 33 Cabbage Leaves 06/26/19 < 3.9 < 214 7067 +/- 586 < 44 < 25 < 25 Sunflower Leaves 07/17/19 6.0 +/- 2.6 1094 +/- 287 6951 +/- 767 < 24 < 31 < 27 Collard Leaves 07/17/19 < 4.1 195 +/- 192 3665 +/- 420 < 25 < 26 < 24 Kale Leaves 07/17/19 < 4.6 369 +/- 153 3112 +/- 430 < 25 < 23 < 22 Kale Leaves 08/22/19 13.9 +/- 2.6 1342 +/- 335 5536 +/- 735 < 46 < 39 < 26 Sunflower Leaves 08/22/19 < 3.8 1469 +/- 300 6543 +/- 792 < 45 < 31 < 27 Squash Leaves 08/22/19 9.1 +/- 3.3 998 +/- 323 4614 +/- 739 < 45 < 35 < 30 Tomatoes 08/22/19 < 3.7 < 259 1721 +/- 518 < 28 < 42 < 34 Corn 09/26/19 < 4.3 < 178 2263 +/- 515 < 27 < 22 < 21 Pumpkin Leaves 09/26/19 39.7 +/- 4.9 770 +/- 361 3923 +/- 654 < 51 < 35 < 40 Kale Leaves 09/26/19 6.2 +/- 2.1 < 335 3261 +/- 664 < 54 < 40 < 37 Squash Leaves 09/26/19 < 3.3 969 +/- 295 4099 +/- 854 < 46 < 27 < 34 Potatoes 10/24/19 < 4.3 < 271 4025 +/- 612 < 41 < 33 < 34 MEAN +/- 2 STD DEV 13.4 +/- 26.5 958 +/- 895 4627 +/- 3530 - - -

E1-2 Kale Leaves 06/26/19 6.7 +/- 2.6 612 +/- 256 5000 +/- 743 < 40 < 29 < 22 Collard Leaves 06/26/19 11.1 +/- 2.3 < 395 3885 +/- 624 < 55 < 39 < 34 Cabbage Leaves 06/26/19 9.7 +/- 2.5 260 +/- 119 3288 +/- 322 < 33 < 18 < 17 Tomato 06/26/19 < 4.3 < 179 1760 +/- 389 < 33 < 24 < 19 Kale Leaves 07/17/19 8.3 +/- 3.2 794 +/- 229 2785 +/- 527 < 23 < 27 < 24 Collard Leaves 07/17/19 10.3 +/- 2.6 618 +/- 196 4677 +/- 598 < 30 < 28 < 26 Cabbage Leaves 07/17/19 14.7 +/- 2.8 674 +/- 281 3623 +/- 547 < 30 < 27 < 25 Collard Leaves 08/22/19 < 3.2 776 +/- 358 4721 +/- 781 < 30 < 47 < 50 Kale Leaves 08/22/19 < 3.6 472 +/- 334 3120 +/- 731 < 49 < 41 < 29 Cabbage Leaves 08/22/19 < 4.2 < 271 2335 +/- 589 < 44 < 32 < 32 Corn 09/26/19 < 4.9 < 180 3634 +/- 640 < 31 < 30 < 23 Collard Leaves 09/26/19 9.2 +/- 2.6 < 325 4933 +/- 647 < 37 < 36 < 38 Kale Leaves 09/26/19 < 2.8 < 232 3469 +/- 660 < 38 < 28 < 24 Swiss Chard Leaves 09/26/19 < 3.8 < 342 8256 +/- 814 < 41 < 38 < 28 Potatoes 10/24/19 < 3.4 < 254 4123 +/- 726 < 35 < 31 < 35 MEAN +/- 2 STD DEV 10.0 +/- 5.0 601 +/- 371 3974 +/- 3028 - - -

H1-2 Zuchinni Leaves 06/26/19 23.0 +/- 4.0 1263 +/- 321 5577 +/- 662 < 50 < 38 < 34 Eggplant Leaves 06/26/19 18.2 +/- 3.7 1170 +/- 354 7310 +/- 955 < 47 < 42 < 34 Yellow Squash Leaves 06/26/19 32.1 +/- 3.4 599 +/- 265 2991 +/- 502 < 38 < 30 < 27 Cucumber Leaves 07/17/19 15.2 +/- 3.6 1103 +/- 218 2608 +/- 327 < 20 < 21 < 20 Eggplant Leaves 07/17/19 29.6 +/- 3.0 955 +/- 288 6587 +/- 703 < 27 < 25 < 28 Yellow Squash Leaves 07/17/19 15.4 +/- 2.7 1482 +/- 401 2645 +/- 673 < 39 < 35 < 26 Zuchinni Leaves 08/22/19 14.1 +/- 2.8 1125 +/- 257 3075 +/- 538 < 32 < 27 < 18 Squash Leaves 08/22/19 22.8 +/- 3.5 572 +/- 185 4918 +/- 609 < 35 < 27 < 26 Sunflower Leaves 08/22/19 < 3.7 1514 +/- 373 4680 +/- 647 < 46 < 31 < 30 Collard Leaves 09/26/19 16.3 +/- 4.0 < 390 2927 +/- 669 < 54 < 36 < 35 Squash Leaves 09/26/19 15.3 +/- 3.4 < 431 2982 +/- 671 < 51 < 40 < 43 Sunflower Leaves 09/26/19 21.9 +/- 3.2 1049 +/- 378 2657 +/- 604 < 46 < 40 < 41 MEAN +/- 2 STD DEV 20.4 +/- 12.3 1083 +/- 633 4080 +/- 3358 - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-18

Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF MILLIREM/QUARTER STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC A1-4 13.8 +/- 5.1 11.6 16.4 11.5 15.5 A3-1 12.8 +/- 5.7 9.4 15.3 11.5 15.0 A5-1 16.7 +/- 6.1 13.3 19.4 14.8 19.1 A9-3 14.7 +/- 4.9 12.4 17.2 12.7 16.3 B1-1 13.8 +/- 5.6 10.9 15.5 11.9 16.7 B1-2 14.0 +/- 5.1 11.9 16.1 11.7 16.3 B2-1 14.3 +/- 5.6 11.0 16.1 12.9 17.0 B5-1 16.1 +/- 5.8 13.5 19.1 13.8 18.1 C1-1 16.2 +/- 6.0 12.9 19.2 14.5 18.3 C1-2 12.9 +/- 4.6 10.8 14.3 11.1 15.4 C2-1 16.0 +/- 5.7 12.7 18.4 14.6 18.4 C5-1 17.5 +/- 5.4 14.4 20.8 16.4 18.2 C8-1 17.9 +/- 5.7 14.7 20.6 16.3 20.0 D1-1 13.8 +/- 6.1 11.1 15.5 11.3 17.2 D1-2 14.8 +/- 4.8 12.8 17.8 12.9 15.7 D2-2 18.8 +/- 5.5 16.2 21.6 16.7 20.7 D6-1 18.7 +/- 6.1 14.5 21.5 18.4 20.3 E1-2 14.2 +/- 4.5 12.4 16.4 12.2 15.9 E1-4 13.7 +/- 5.6 11.6 15.9 10.9 16.3 E2-3 18.0 +/- 5.1 15.4 19.9 16.1 20.4 E5-1 19.6 +/- 5.8 16.6 22.8 17.8 21.2 E7-1 17.5 +/- 4.7 14.5 20.0 17.0 18.5 F1-1 16.1 +/- 5.2 13.9 19.1 14.0 17.4 F1-2 14.6 +/- 5.0 12.9 15.7 12.3 17.6 F1-4 13.6 +/- 5.2 11.0 16.2 11.7 15.3 F2-1 18.5 +/- 5.7 15.0 19.8 17.4 21.6 F5-1 18.7 +/- 5.8 15.8 20.8 16.6 21.5 G1-2 16.6 +/- 5.7 13.3 19.6 15.3 18.2 G1-3 13.3 +/- 6.2 10.9 15.4 10.3 16.4 G1-5 13.2 +/- 4.5 11.2 13.6 11.7 16.2 G1-6 13.8 +/- 5.2 11.0 16.1 12.2 16.0 G2-4 19.3 +/- 5.3 16.1 21.1 18.1 21.8 G5-1 16.5 +/- 5.0 13.7 19.0 15.2 18.2 H1-1 16.0 +/- 5.6 12.6 17.8 14.9 18.8 H3-1 12.6 +/- 5.0 10.2 14.7 10.7 14.8 H5-1 11.5 +/- 5.8 8.8 14.0 9.1 13.9 H8-1 26.5 +/- 6.4 22.5 28.7 25.2 29.4 J1-1 14.2 +/- 6.4 11.3 16.1 11.7 17.7 J1-3 12.0 +/- 6.5 9.2 14.8 9.1 14.7 J3-1 15.2 +/- 5.9 11.7 17.7 13.8 17.5 J5-1 17.6 +/- 6.8 14.5 21.0 14.9 20.1 J7-1 19.2 +/- 6.2 15.4 21.4 18.0 22.0 K1-4 13.2 +/- 5.9 10.6 15.2 10.8 16.3 K2-1 17.5 +/- 5.0 15.4 18.4 15.6 20.6 K3-1 13.5 +/- 6.8 10.6 16.5 10.6 16.4 K5-1 17.9 +/- 7.6 14.3 21.6 15.0 20.7 K8-1 16.5 +/- 6.8 13.3 19.5 13.7 19.3 C-19

Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF MILLIREM/QUARTER STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC L1-1 14.9 +/- 5.4 12.4 16.3 12.8 17.9 L1-2 13.9 +/- 6.5 10.9 16.6 11.2 16.7 L2-1 14.4 +/- 6.0 11.4 17.5 12.3 16.5 L5-1 14.0 +/- 6.7 10.6 17.4 11.7 16.3 L8-1 15.5 +/- 6.9 12.0 18.6 13.1 18.3 M1-1 13.3 +/- 4.4 11.4 14.8 11.3 15.5 M1-2 15.8 +/- 6.5 12.6 16.2 14.1 20.1 M2-1 12.9 +/- 5.6 10.1 15.6 10.9 15.0 M5-1 15.3 +/- 5.9 12.5 18.2 13.0 17.4 M9-1 19.9 +/- 6.3 16.5 22.9 18.0 22.3 N1-1 14.8 +/- 8.3 11.8 (1) (1) 17.7 N1-3 13.9 +/- 5.6 11.6 15.3 11.5 17.1 N2-1 21.4 +/- 24.0 13.4 39.1 14.6 18.6 N5-1 13.6 +/- 5.4 10.6 15.4 12.0 16.3 N8-1 17.2 +/- 6.4 14.6 20.2 14.3 19.8 P1-1 14.3 +/- 6.1 12.2 15.6 11.5 18.0 P1-2 13.4 +/- 5.2 11.6 14.7 10.9 16.4 P2-1 18.9 +/- 6.3 15.5 22.2 17.0 20.9 P5-1 15.8 +/- 5.7 13.1 18.1 13.5 18.3 P8-1 13.5 +/- 5.9 10.2 16.1 11.8 15.9 Q1-1 15.2 +/- 6.9 11.6 16.6 13.2 19.3 Q1-2 12.5 +/- 6.4 9.3 14.7 10.1 15.7 Q2-1 12.5 +/- 6.0 9.4 14.2 10.6 15.8 Q5-1 16.4 +/- 13.7 11.4 25.7 11.1 17.4 Q9-1 15.3 +/- 5.5 12.6 18.1 13.3 17.2 R1-1 17.7 +/- 21.2 10.7 33.2 11.0 16.0 R1-2 13.1 +/- 6.1 10.8 15.0 10.3 16.4 R3-1 19.3 +/- 5.9 15.7 22.2 18.2 21.2 R5-1 17.3 +/- 6.6 13.1 20.8 16.6 18.8 R9-1 17.5 +/- 8.0 13.8 20.9 14.3 21.0 B10-1 16.1 +/- 6.3 12.6 17.9 14.3 19.4 D15-1 16.2 +/- 6.0 13.8 19.0 13.5 18.6 F10-1 21.0 +/- 6.9 17.4 24.4 18.8 23.5 F25-1 17.2 +/- 4.8 14.7 18.7 15.7 19.7 G10-1 23.4 +/- 7.1 19.3 25.4 21.8 27.2 G15-1 22.5 +/- 6.8 19.1 25.6 20.0 25.2 H15-1 15.9 +/- 6.9 12.8 18.2 13.0 19.4 J15-1 19.6 +/- 7.2 15.3 22.7 17.8 22.4 K15-1 15.8 +/- 6.1 12.6 18.8 13.9 18.0 L15-1 16.0 +/- 5.0 13.2 17.8 14.5 18.3 N15-2 20.2 +/- 12.9 14.7 28.8 15.8 21.4 Q15-1 17.1 +/- 5.4 15.1 19.7 14.5 19.1 R15-1 15.3 +/- 6.2 12.8 18.8 14.3 (1)

(1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-20

TABLE C-X.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, INDICATOR CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF MILLIREM/QUARTER

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY PERIOD +/- 2 STD DEV INDICATOR CONTROL JAN-MAR 11.2 +/- 1.9 13.2 +/- 4.8 14.9 +/- 4.7 APR-JUN 16.4 +/- 8.3 19.3 +/- 7.8 21.2 +/- 7.5 JUL-SEP 11.4 +/- 2.4 14.3 +/- 5.7 15.9 +/- 5.7 OCT-DEC 16.3 +/- 2.0 18.7 +/- 5.1 20.9 +/- 6.3 TABLE C-X.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF MILLIREMQUARTER SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM +/- 2 STD DEV SITE BOUNDARY 76 9.1 33.2 13.9 +/- 6.8 INDICATOR 238 8.8 39.1 16.3 +/- 8.0 CONTROL 43 12.6 28.8 18.2 +/- 8.3 SITE BOUNDARY STATIONS - A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, L1-1, M1-1, N1-3, P1-2, Q1-2, R1-1 INDICATOR STATIONS - A3-1, A5-1, A9-3, B1-1, B10-1, B2-1, B5-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, F1-1, F10-1, F2-1, F5-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, R9-1 CONTROL STATIONS - D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-1, Q15-1, R15-1 C-21

FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2019 Station J1-2 (Downstream of Discharge) Station Q9-1 (Control) 100000 10000 1000 Picocuries per Liter 100 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec C-22 Month Station K1-1 (TMINS Liquid Discharge) 1000000 100000 10000 1000 Picocuries per Liter 100 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month

FIGURE C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2019 Indicator Samples Control Samples 12000 Significant Events 11000 TMI-1 Critical June 1974 TMI-2 Critical March 1978 10000 TMI-2 Accident March 1979 TMI-2 RB Purge June 1980 9000 Chernobyl April 1986 8000 Major Atm. Nuclear Weapon Tests June 1974 September 1974 September 1976 November 1976 7000 September 1977 March 1978 C-23 December 1978 October 1980 6000 5000 Picocuries per Liter 4000 3000 2000 1000 0

-1000 1974 1983 1992 2001 2010 2019 Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2019 Indicator Samples Control Samples 10.0 9.0 8.0 7.0 6.0 C-24 5.0 4.0 Picocuries per Liter 3.0 2.0 1.0 0.0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2019 NOTE: The mean values are calculated using both the MDCs and Indicator Samples Control Samples the positive values.

500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L 400 300 200 Picocuries per Liter 100 0

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month C-25 Station K1-1 (TMINS Liquid Discharge) 1000000 100000 10000 1000 Picocuries per Liter 100 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month

FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2019 Indicator Samples Control Samples 900 Significant Event

.Chernobyl April 1986 800 700 600 C-26 500 400 300 Picocuries per kilogram (dry) 200 100 0

1984 1991 1997 2004 2012 2019 Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2019 Indicator Control 0.4 Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 0.35 TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chernobyl April 1986 December 1978 October 1980 0.3 0.25 C-27 0.2 0.15 Picocuries per Cubic Meter 0.1 0.05 0

1972 1978 1984 1990 1996 2002 2008 2014 2020 Year

FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2019 0.100 0.090 Indicator Control 0.080 0.070 0.060 0.050 C-28 Picocuries per Cubic Meter 0.040 0.030 0.020 0.010 0.000 01/01/07 11/10/08 09/20/10 07/30/12 06/09/14 04/18/16 02/26/18 01/06/20 Month / Day / Year The high value on 11/24/2009 was caused by an airborne release on 11/21/2009

FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2019 Indicator Samples Control Samples 10 Significant Events Major Atm. Nuclear Weapon Tests 9 TMI-2 Accident March 1979 December 1978 October 1980 TMI-2 RB Purge June 1980 Chernobyl April 1986 8

7 6

C-29 5

4 Picocuries per Liter 3

2 1

0 1979 1984 1989 1994 1999 2004 2009 2014 2019 Year

Intentionally left blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORIES

Intentionally left blank The following section presents the results of data analysis performed by the QC laboratories, Exelon Industrial Services (EIS) and GEL Laboratories (GEL). Duplicate samples were obtained from several locations and media and were split with the primary laboratory, Teledyne Brown Engineering (TBE). Comparison of the results for most media were within expected ranges.

Intentionally left blank TABLE D-I.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB PERIOD Q9-1Q EIS 01/03/19 - 01/30/19 0.9 +/- 0.6 01/30/19 - 02/27/19 1.7 +/- 0.6 02/27/19 - 03/27/19 1.6 +/- 0.7 03/27/19 - 05/01/19 1.0 +/- 0.6 05/01/19 - 05/30/19 1.2 +/- 0.6 05/30/19 - 06/27/19 1.4 +/- 0.6 06/27/19 - 08/01/19 1.6 +/- 0.6 08/01/19 - 08/29/19 1.6 +/- 0.6 08/29/19 - 10/03/19 2.5 +/- 0.7 10/03/19 - 10/31/19 1.1 +/- 0.6 10/31/19 - 12/04/19 1.9 +/- 0.7 12/04/19 - 01/02/20 1.6 +/- 0.6 MEAN +/- 2 STD DEV 1.5 +/- 0.9 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB PERIOD Q9-1Q GEL 01/03/19 - 03/21/19 < 121 03/27/19 - 06/27/19 < 122 06/27/19 - 10/03/19 < 139 10/03/19 - 01/02/20 < 137 MEAN -

TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB PERIOD Q9-1Q EIS 01/03/19 - 01/30/19 < 0.6 01/30/19 - 02/27/19 < 0.6 02/27/19 - 03/27/19 < 0.9 03/27/19 - 05/01/19 < 0.6 05/01/19 - 05/30/19 < 0.7 05/30/19 - 06/27/19 < 0.9 06/27/19 - 08/01/19 < 0.9 08/01/19 - 08/29/19 < 0.8 08/29/19 - 10/03/19 < 0.7 10/03/19 - 10/31/19 < 0.5 10/31/19 - 12/04/19 < 0.8 12/04/19 - 01/02/20 < 0.7 MEAN -

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-1

TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 EIS Q9-1Q 01/03/19 - 01/30/19 < 3 < 3 < 8 < 3 < 6 < 4 < 5 < 3 < 3 < 15 < 6 01/30/19 - 02/27/19 < 3 < 4 < 9 < 4 < 8 < 4 < 7 < 4 < 5 < 22 < 9 02/27/19 - 03/27/19 < 4 < 4 < 7 < 4 < 8 < 4 < 6 < 4 < 4 < 17 < 6 03/27/19 - 05/01/19 < 0 < 4 < 9 < 4 < 8 < 4 < 7 < 4 < 4 < 28 < 10 05/01/19 - 05/30/19 < 3 < 3 < 7 < 3 < 8 < 4 < 5 < 3 < 3 < 22 < 8 05/30/19 - 06/27/19 < 3 < 3 < 8 < 3 < 7 < 4 < 6 < 3 < 3 < 29 < 9 06/27/19 - 08/01/19 < 3 < 4 < 9 < 4 < 9 < 5 < 7 < 4 < 4 < 25 < 10 08/01/19 - 08/29/19 < 3 < 3 < 7 < 3 < 6 < 3 < 5 < 3 < 3 < 12 < 4 08/29/19 - 10/03/19 < 4 < 4 < 7 < 3 < 8 < 4 < 6 < 4 < 4 < 12 < 4 10/03/19 - 10/31/19 < 3 < 4 < 6 < 3 < 6 < 3 < 5 < 3 < 3 < 14 < 4 10/31/19 - 12/04/19 < 4 < 4 < 10 < 5 < 10 < 5 < 8 < 4 < 4 < 24 < 10 12/04/19 - 01/02/20 < 3 < 3 < 6 < 3 < 7 < 3 < 6 < 3 < 3 < 13 < 5 D-2 MEAN - - - - - - - - - - -

TABLE D-II.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION LAB SITE PERIOD Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 EIS INDP 10/24/19 3070 +/- 381 < 18 < 22 < 61 < 22 < 57 < 15 < 20 D-3

TABLE D-III.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 COLLECTION LAB SITE PERIOD K-40 Cs-134 Cs-137 EIS J2-1 10/30/19 8300 +/- 906 < 70 < 69 D-4

TABLE D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION LAB SITE TYPE PERIOD Be-7 K-40 I-131 Cs-134 Cs-137 Sr-89 Sr-90 EIS B10-2Q Sunflower 06/26/19 2220 +/- 199 6800 +/- 416 < 58 < 17 < 17 GEL B10-2Q Sunflower 06/26/19 < 1.8 < 0.8 EIS H1-2Q Zucchini Leaves 06/26/19 842 +/- 91 4210 +/- 267 < 39 < 13 < 13 GEL H1-2Q Zucchini Leaves 06/26/19 EIS H1-2Q Eggplant 07/17/19 1130 +/- 143 5620 +/- 401 < 30 < 19 < 19 GEL H1-2Q Eggplant 07/17/19 < 1.7 < 0.9 EIS H1-2Q Zucchini Leaves 08/22/19 876 +/- 151 2680 +/- 348 < 31 < 21 < 25 GEL H1-2Q Zucchini Leaves 08/22/19 < 1.8 < 0.9 EIS H1-2Q Collards 09/26/19 62 +/- 56 3100 +/- 273 < 40 < 14 < 16 GEL H1-2Q Collards 09/26/19 < 1.1 < 0.9 D-5

TABLE D-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND I-131 IN AIR IODINE SAMPLES COLLECED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION E1-2Q E1-2Q LAB PERIOD GROSS BETA I-131 EIS 12/27/18 - 01/03/19 23 +/- 2 < 10 01/03/19 - 01/10/19 22 +/- 2 < 13 01/10/19 - 01/16/19 19 +/- 1 < 21 01/16/19 - 01/23/19 22 +/- 1 < 18 01/23/19 - 01/30/19 29 +/- 1 < 16 01/30/19 - 02/07/19 28 +/- 2 < 9.1 02/07/19 - 02/14/19 17 +/- 2 < 16 02/14/19 - 02/21/19 21 +/- 2 < 15 02/21/19 - 02/27/19 33 +/- 3 < 23 02/27/19 - 03/07/19 19 +/- 3 < 17 03/07/19 - 03/14/19 34 +/- 3 < 10 03/14/19 - 03/21/19 20 +/- 2 < 16 03/21/19 - 03/27/19 14 +/- 2 < 13 03/27/19 - 04/04/19 17 +/- 2 < 13 04/04/19 - 04/11/19 20 +/- 2 < 11 04/11/19 - 04/18/19 14 +/- 2 < 13 04/18/19 - 04/25/19 12 +/- 2 < 18 04/25/19 - 05/01/19 14 +/- 2 < 15 05/01/19 - 05/09/19 15 +/- 2 < 15 05/09/19 - 05/15/19 8 +/- 2 < 20 05/15/19 - 05/22/19 23 +/- 2 < 18 05/22/19 - 05/30/19 14 +/- 2 < 8 05/30/19 - 06/07/19 19 +/- 2 < 15 06/07/19 - 06/13/19 13 +/- 2 < 20 06/13/19 - 06/19/19 16 +/- 2 < 16 06/19/19 - 06/27/19 17 +/- 2 < 13 06/27/19 - 07/03/19 25 +/- 3 < 14 07/03/19 - 07/11/19 21 +/- 2 < 13 07/11/19 - 07/18/19 20 +/- 2 < 9 07/18/19 - 07/25/19 21 +/- 2 < 13 07/25/19 - 08/01/19 32 +/- 3 < 12 08/01/19 - 08/07/19 28 +/- 3 < 20 08/07/19 - 08/15/19 31 +/- 2 < 13 08/15/19 - 08/21/19 33 +/- 3 < 15 08/21/19 - 08/29/19 19 +/- 2 < 13 08/29/19 - 09/05/19 26 +/- 2 < 13 09/05/19 - 09/12/19 33 +/- 3 < 16 09/12/19 - 09/18/19 27 +/- 3 < 13 09/18/19 - 09/26/19 36 +/- 2 < 9 09/26/19 - 10/03/19 31 +/- 2 < 15 10/03/19 - 10/10/19 15 +/- 2 < 12 10/10/19 - 10/17/19 30 +/- 2 < 10 10/17/19 - 10/24/19 14 +/- 2 < 13 10/24/19 - 10/31/19 22 +/- 2 < 8 10/31/19 - 11/07/19 23 +/- 2 < 13 11/07/19 - 11/14/19 25 +/- 2 < 8 11/14/19 - 11/21/19 24 +/- 2 < 10 11/21/19 - 11/28/19 27 +/- 3 < 15 11/27/19 - 12/04/19 9 +/- 2 < 11 12/04/19 - 12/12/19 22 +/- 2 < 9 12/12/19 - 12/19/19 20 +/- 2 < 10 12/19/19 - 12/26/19 46 +/- 3 < 18 12/26/19 - 01/02/20 31 +/- 2 < 12 MEAN +/- 2 STD DEV 23 +/- 15 -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES D-6

TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION LAB SITE PERIOD Be-7 Cs-134 Cs-137 EIS E1-2Q 12/27/18 - 03/27/19 74 +/- 10 < 0.9 < 1.0 03/29/18 - 06/28/18 68 +/- 10 < 0.8 < 0.7 06/27/19 - 10/03/19 74 +/- 9 < 0.8 < 0.7 10/03/19 - 01/02/20 60 +/- 8 < 0.8 < 0.8 MEAN +/- 2 STD DEV 69 +/- 14 - -

D-7

TABLE D-VI.1 CONCENTRATIONS OF I-131 BY CHEMICAL SEPARATION, GAMMA EMITTERS, AND STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE DATE I-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 EIS G2-1Q 01/09/19 < 0.6 1490 +/- 90 < 4 < 4 < 26 < 7 EIS 02/13/19 < 0.6 1410 +/- 118 < 6 < 5 < 23 < 10 EIS 03/06/19 < 0.8 1040 +/- 74 < 4 < 4 < 18 < 7 EIS 03/20/19 < 0.7 1270 +/- 83 < 4 < 4 < 24 < 7 GEL 01/09/19 - 03/20/19 < 5.5 < 1.7 EIS 04/03/19 < 0.9 1300 +/- 109 < 5 < 6 < 36 < 11 EIS 04/17/19 < 0.7 1400 +/- 86 < 3 < 4 < 26 < 8 EIS 05/01/19 < 0.9 1230 +/- 81 < 4 < 4 < 25 < 10 EIS 05/15/19 < 0.8 1510 +/- 95 < 4 < 6 < 21 < 8 EIS 05/29/19 < 0.8 1510 +/- 97 < 5 < 6 < 22 < 7 EIS 06/11/19 < 1.0 1230 +/- 82 < 4 < 4 < 24 < 7 EIS 06/26/19 < 0.9 1310 +/- 83 < 3 < 4 < 24 < 7 GEL 04/03/19 - 06/26/19 < 3.6 < 1.6 D-8 EIS 07/10/19 < 0.8 1180 +/- 80 < 3 < 4 < 19 < 6 EIS 07/24/19 < 0.7 1310 +/- 110 < 6 < 5 < 34 < 12 EIS 08/07/19 < 0.7 1350 +/- 114 < 5 < 6 < 28 < 8 EIS 08/21/19 < 0.7 1340 +/- 111 < 5 < 6 < 23 < 9 EIS 09/04/19 < 0.9 1520 +/- 95 < 5 < 5 < 19 < 7 EIS 09/18/19 < 0.8 1420 +/- 86 < 4 < 4 < 22 < 6 GEL 07/10/19 - 09/19/19 < 3.7 < 1.9 EIS 10/02/19 < 0.7 1270 +/- 90 < 5 < 6 < 21 < 8 EIS 10/16/19 < 0.6 1310 +/- 89 < 4 < 5 < 22 < 6 EIS 10/30/19 < 0.6 1020 +/- 102 < 7 < 7 < 31 < 10 EIS 11/13/19 < 0.8 1250 +/- 109 < 5 < 6 < 23 < 10 EIS 11/26/19 < 0.6 1250 +/- 82 < 4 < 4 < 18 < 6 EIS 12/11/19 < 0.8 1470 +/- 89 < 3 < 4 < 17 < 5 GEL 10/02/19 - 12/11/19 < 3.8 < 1.7 MEAN +/- 2 STD DEV 1321 +/- 273 - - - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2019 6.0 QC-LAB 5.0 PRIMARY - LAB 4.0 D-9 3.0 pCi/liter 2.0 1.0 0.0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH

FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2019 60 QC - LAB 50 PRIMARY - LAB 40 D-10 30 E-3 pCi/cubic meter 20 10 0

1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank Analytics Environmental Radioactivity Cross Check Program Table E.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value March 2019 E12468A Milk Sr-89 pCi/L 87.1 96 0.91 A Sr-90 pCi/L 12.6 12.6 1.00 A E12469A Milk Ce-141 pCi/L 113 117 0.97 A Co-58 pCi/L 153 143 1.07 A Co-60 pCi/L 289 299 0.97 A Cr-51 pCi/L 233 293 0.80 A Cs-134 pCi/L 147 160 0.92 A Cs-137 pCi/L 193 196 0.98 A Fe-59 pCi/L 153 159 0.96 A I-131 pCi/L 91.5 89.5 1.02 A Mn-54 pCi/L 149 143 1.04 A Zn-65 pCi/L 209 220 0.95 A E12470 Charcoal I-131 pCi 77.5 75.2 1.03 A E12471 AP Ce-141 pCi 60.7 70.2 0.87 A Co-58 pCi 87.9 85.8 1.02 A Co-60 pCi 175 179 0.98 A Cr-51 pCi 165 176 0.94 A Cs-134 pCi 91.2 95.9 0.95 A Cs-137 pCi 120 118 1.02 A Fe-59 pCi 108 95.3 1.13 A Mn-54 pCi 94.2 85.7 1.10 A Zn-65 pCi 102 132 0.77 W E12472 Water Fe-55 pCi/L 2230 1920 1.16 A E12473 Soil Ce-141 pCi/g 0.189 0.183 1.03 A Co-58 pCi/g 0.209 0.224 0.93 A Co-60 pCi/g 0.481 0.466 1.03 A Cr-51 pCi/g 0.522 0.457 1.14 A Cs-134 pCi/g 0.218 0.250 0.87 A Cs-137 pCi/g 0.370 0.381 0.97 A Fe-59 pCi/g 0.263 0.248 1.06 A Mn-54 pCi/g 0.248 0.223 1.11 A Zn-65 pCi/g 0.371 0.344 1.08 A E12474 AP Sr-89 pCi 88.3 95.2 0.93 A Sr-90 pCi 11.7 12.5 0.94 A August 2019 E12562 Soil Sr-90 pCi/g 4.710 6.710 0.70 W (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (Page 1 of 2)

E-1

Analytics Environmental Radioactivity Cross Check Program Table E.1 Teledyne Brown Engineering Environmental Services TBE Identification Known Ratio of TBE to Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Analytics Result Value September 2019 E12475 Milk Sr-89 pCi/L 70.0 93.9 0.75 W Sr-90 pCi/L 12.0 12.9 0.93 A E12476 Milk Ce-141 pCi/L 150 167 0.90 A Co-58 pCi/L 170 175 0.97 A Co-60 pCi/L 211 211 1.00 A Cr-51 pCi/L 323 331 0.98 A Cs-134 pCi/L 180 207 0.87 A Cs-137 pCi/L 147 151 0.97 A Fe-59 pCi/L 156 148 1.05 A I-131 pCi/L 81.1 92.1 0.88 A Mn-54 pCi/L 160 154 1.04 A Zn-65 pCi/L 303 293 1.03 A E12477 Charcoal I-131 pCi 95.9 95.1 1.01 A E12478 AP Ce-141 pCi 129 138 0.93 A Co-58 pCi 128 145 0.88 A Co-60 pCi 181 174 1.04 A Cr-51 pCi 292 274 1.07 A Cs-134 pCi 166 171 0.97 A Cs-137 pCi 115 125 0.92 A Fe-59 pCi 119 123 0.97 A Mn-54 pCi 129 128 1.01 A Zn-65 pCi 230 242 0.95 A E12479 Water Fe-55 pCi/L 1810 1850 0.98 A E12480 Soil Ce-141 pCi/g 0.305 0.276 1.10 A Co-58 pCi/g 0.270 0.289 0.93 A Co-60 pCi/g 0.358 0.348 1.03 A Cr-51 pCi/g 0.765 0.547 1.40 N(1)

Cs-134 pCi/g 0.327 0.343 0.95 A Cs-137 pCi/g 0.308 0.321 0.96 A Fe-59 pCi/g 0.257 0.245 1.05 A Mn-54 pCi/g 0.274 0.255 1.07 A Zn-65 pCi/g 0.536 0.485 1.11 A E12481 AP Sr-89 pCi 95.9 91.9 1.04 A Sr-90 pCi 12.3 12.6 0.97 A E12563 Soil Sr-90 pCi/g 0.392 0.360 1.09 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on TBE internal QC limits:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) See NCR 19-27 (Page 2 of 2)

E-2

DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Table E.2 Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Range Value February 2019 19-GrF40 AP Gross Alpha Bq/sample 0.184 0.528 0.158 - 0.898 A Gross Beta Bq/sample 0.785 0.948 0.474 - 1.422 A 19-MaS40 Soil Ni-63 Bq/kg 420 519.0 363 - 675 A Sr-90 Bq/kg (1) NR(3) 19-MaW40 Water Am-241 Bq/L 0.764 0.582 0.407 - 0.757 N(4)

Ni-63 Bq/L 4.72 5.8 4.1 - 7.5 A Pu-238 Bq/L 0.443 0.451 0.316 - 0.586 A Pu-239/240 Bq/L -0.00161 0.0045 (2) A 19-RdF40 AP U-234/233 Bq/sample 0.1138 0.106 0.074 - 0.138 A U-238 Bq/sample 0.107 0.110 0.077 - 0.143 A 19-RdV40 Vegetation Cs-134 Bq/sample 2.14 2.44 1.71 - 3.17 A Cs-137 Bq/sample 2.22 2.30 1.61 - 2.99 A Co-57 Bq/sample 2.16 2.07 1.45 - 2.69 A Co-60 Bq/sample 0.02382 (1) A Mn-54 Bq/sample -0.03607 (1) A Sr-90 Bq/sample -0.1060 (1) N(5)

Zn-65 Bq/sample 1.35 1.71 1.20 - 2.22 W August 2019 19-GrF41 AP Gross Alpha Bq/sample 0.192 0.528 0.158 - 0.898 W Gross Beta Bq/sample 0.722 0.937 0.469 - 1.406 A 19-MaS41 Soil Ni-63 Bq/kg 436 629 440 - 818 N(6)

Sr-90 Bq/kg 444 572 400 - 744 W 19-MaW41 Water Am-241 Bq/L NR(7)

Ni-63 Bq/L 7.28 9.7 6.8 - 12.6 W Pu-238 Bq/L 0.0207 0.0063 (2) A Pu-239/240 Bq/L 0.741 0.727 0.509 - 0.945 A 19-RdF41 AP U-234/233 Bq/sample 0.0966 0.093 0.065 - 0.121 A U-238 Bq/sample 0.0852 0.096 0.067-0.125 A 19-RdV41 Vegetation Cs-134 Bq/sample 0.0197 (1) A Cs-137 Bq/sample 3.21 3.28 2.30 - 4.26 A Co-57 Bq/sample 4.62 4.57 3.20 - 5.94 A Co-60 Bq/sample 4.88 5.30 3.71 - 6.89 A Mn-54 Bq/sample 4.54 4.49 3.14 - 5.84 A Sr-90 Bq/sample 0.889 1.00 0.70 - 1.30 A Zn-65 Bq/sample 2.78 2.85 2.00 - 3.71 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOE/MAPEP evaluation:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 (1) False positive test (2) Sensitivity evaluation (3) See NCR 19-12 (4) See NCR 19-13 (5) See NCR 19-14 (6) See NCR 19-25 (Page 1 of 1)

(7) See NCR 19-26 E-3

ERA Environmental Radioactivity Cross Check Program Table E.3 Teledyne Brown Engineering Environmental Services TBE Identification Known Acceptance Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) Limits Value April 2019 Rad-117 Water Ba-133 pCi/L 26.3 24.1 18.6 - 27.8 A Cs-134 pCi/L 15.2 12.1 8.39 - 14.4 N(1)

Cs-137 pCi/L 33.6 33.1 28.8 - 39.4 A Co-60 pCi/L 11.9 11.5 8.67 - 15.5 A Zn-65 pCi/L 87.1 89.2 80.3 - 107 A GR-A pCi/L 19 19.3 9.56 - 26.5 A GR-B pCi/L 20.2 29.9 19.1 - 37.7 A U-Nat pCi/L 55.5 55.9 45.6 - 61.5 A H-3 pCi/L 21500 21400 18700 - 23500 A (2)

Sr-89 pCi/L 44.9 33.3 24.5 - 40.1 N Sr-90 pCi/L 24.5 26.3 19.0 - 30.7 A I-131 pCi/L 28.9 28.4 23.6 - 33.3 A October 2019 Rad-119 Water Ba-133 pCi/L 42.7 43.8 35.7 - 48.8 A Cs-134 pCi/L 53.5 55.9 45.2 - 61.5 A Cs-137 pCi/L 77.7 78.7 70.8 - 89.2 A Co-60 pCi/L 51.5 53.4 48.1 - 61.3 A Zn-65 pCi/L 36.6 34.0 28.5 - 43.1 A GR-A pCi/L 40.5 27.6 14.0 - 36.3 N(3)

GR-B pCi/L 36.3 39.8 26.4 - 47.3 A U-Nat pCi/L 27.66 28.0 22.6 - 31.1 A H-3 pCi/L 22800 23400 20500 - 25700 A Sr-89 pCi/L 47.1 45.5 35.4 - 52.7 A Sr-90 pCi/L 32.5 26.5 19.2 - 30.9 N(4)

I-131 pCi/L 26.0 23.9 19.8 - 28.4 A December 2019 QR 120419D Water Sr-90 pCi/L 20.1 18.6 13.2 - 22.1 A (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(b) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) See NCR 19-10 (2) See NCR 19-11 (3) See NCR 19-23 (4) See NCR 19-24 (Page 1 of 1)

E-4

TABLE E.4 Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services (2019)

EIS Identification Known Ratio of Analytics Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) to EIS Result Value March 2019 E 12379 Water Gr-B pCi/L 264 288 92 Pass E 12380 Charcoal I-131 pCi 73.0 75.6 97 Pass E 12378A Milk I-131 pCi/L 92 89.5 103 Pass Ce-141 pCi/L 101 117 86 Pass Cr-51 pCi/L 227 293 77 Pass Cs-134 pCi/L 138 160 86 Pass Cs-137 pCi/L 184 196 94 Pass Co-58 pCi/L 128 143 90 Pass Mn-54 pCi/L 141 143 99 Pass Fe-59 pCi/L 149 159 94 Pass Zn-65 pCi/L 177 220 80 Pass Co-60 pCi/L 262 299 88 Pass June 2019 E12383 AP Ce-141 pCi/Filter 97.7 88 111 Pass Cr-51 pCi/Filter 222 223 100 Pass Cs-134 pCi/Filter 80.9 93 87 Pass Cs-137 pCi/Filter 119 111 107 Pass Co-58 pCi/Filter 77.7 74 105 Pass Mn-54 pCi/Filter 142 126 113 Pass Fe-59 pCi/Filter 121 93.5 129 Pass Zn-65 pCi/Filter 185 164 113 Pass Co-60 pCi/Filter 139 131 106 Pass E12382 Water I-131 pCi/L 115 89.1 129 Pass Ce-141 pCi/L 142 145 98 Pass Cr-51 pCi/L 327 368 89 Pass Cs-134 pCi/L 139 153 91 Pass Cs-137 pCi/L 186 184 101 Pass Co-58 pCi/L 115 122 94 Pass Mn-54 pCi/L 214 207 103 Pass Fe-59 pCi/L 154 154 100 Pass Zn-65 pCi/L 257 270 95 Pass Co-60 pCi/L 216 216 100 Pass E12381 Water Gr-B pCi/L 199 199 100 Pass September 2019 E12384 AP Gr-B pCi 270.7 221 122 Pass December 2019 E12386 Water Gr-B pCi/L 260 269 97 Pass E12387 Cartridge I-131 pCi 79.0 88.2 90 Pass Detector 2 E12387 Cartridge I-131 pCi 79.1 88.2 90 Pass Detector 3 E12387 Cartridge I-131 pCi 79.2 88.2 90 Pass Detector 4 December 2019 E12385 AP Ce-141 pCi/Filter 98.5 99.1 99 Pass Detector 2 Cr-51 pCi/Filter 246 288 85 Pass Cs-134 pCi/Filter 123 135.0 91 Pass Cs-137 pCi/Filter 128 121.0 106 Pass Co-58 pCi/Filter 117 107.0 109 Pass Mn-54 pCi/Filter 170 155.0 110 Pass Fe-59 pCi/Filter 124 104.0 119 Pass (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on EIS internal QC limits in accordance with the NRC Resolution Test criteria E-5

TABLE E.4 Analytics Environmental Radioactivity Cross Check Program Exelon Industrial Services (2019)

EIS Identification Known Ratio of Analytics Month/Year Matrix Nuclide Units Reported Evaluation (b)

Number Value (a) to EIS Result Value December 2019 E12385 AP Zn-65 pCi/Filter 194 190 102 Pass Detector 2 Co-60 pCi/Filter 139 138 101 Pass E12385 AP Ce-141 pCi/Filter 95.7 99.1 97 Pass Detector 3 Cr-51 pCi/Filter 257.1 288 89 Pass Cs-134 pCi/Filter 128 135.0 95 Pass Cs-137 pCi/Filter 128 121.0 105 Pass Co-58 pCi/Filter 111 107.0 104 Pass Mn-54 pCi/Filter 173 155.0 112 Pass Fe-59 pCi/Filter 121.7 104.0 117 Pass Zn-65 pCi/Filter 203 190 107 Pass Co-60 pCi/Filter 147.5 138 107 Pass E12385 AP Ce-141 pCi/Filter 102 99.1 103 Pass Detector 4 Cr-51 pCi/Filter 299 288 104 Pass Cs-134 pCi/Filter 122 135.0 90 Pass Cs-137 pCi/Filter 122 121.0 101 Pass Co-58 pCi/Filter 102 107.0 95 Pass Mn-54 pCi/Filter 167 155.0 108 Pass Fe-59 pCi/Filter 132 104.0 127 Pass Zn-65 pCi/Filter 195 190 103 Pass Co-60 pCi/Filter 146 138 106 Pass E12388 Milk I-131 pCi/L 100 94.5 106 Pass Detector 2 Ce-141 pCi/L 82.4 83.0 99 Pass Cr-51 pCi/L 271 241 112 Pass Cs-134 pCi/L 112 113 99 Pass Cs-137 pCi/L 123 102 121 Pass Co-58 pCi/L 84.9 89.9 94 Pass Mn-54 pCi/L 128 130 98 Pass Fe-59 pCi/L 95.5 87 110 Pass Zn-65 pCi/L 148 159 93 Pass Co-60 pCi/L 119 115 103 Pass E12388 Milk I-131 pCi/L 99.3 94.5 105 Pass Detector 3 Ce-141 pCi/L 80.7 83.0 97 Pass Cr-51 pCi/L 227.9 241 95 Pass Cs-134 pCi/L 103.4 113 92 Pass Cs-137 pCi/L 109.2 102 107 Pass Co-58 pCi/L 101.9 89.9 113 Pass Mn-54 pCi/L 140.8 130 108 Pass Fe-59 pCi/L 102.1 87 117 Pass Zn-65 pCi/L 166.2 159 105 Pass Co-60 pCi/L 111 115 97 Pass E12388 Milk I-131 pCi/L 104 94.5 110 Pass Detector 4 Ce-141 pCi/L 78.3 83.0 94 Pass Cr-51 pCi/L 235.4 241 98 Pass Cs-134 pCi/L 114 113 101 Pass Cs-137 pCi/L 105 102 103 Pass Co-58 pCi/L 92 89.9 102 Pass Mn-54 pCi/L 143 130 110 Pass Fe-59 pCi/L 104 87 119 Pass Zn-65 pCi/L 164 159 103 Pass Co-60 pCi/L 123 115 107 Pass (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) Analytics evaluation based on EIS internal QC limits in accordance with the NRC Resolution Test criteria E-6

TABLE E.5 ERA Environmental Radioactivity Cross Check Program Exelon Industrial Services (2019)

EIS Acceptance Known Month/Year ID Number Matrix Nuclide Units Reported Ratio of ERA Evaluation (b)

Value (a)

Value to EIS Result April 2019 RAD-117 Water Ba-133 pCi/L 23.0 24.1 95 Pass Cs-134 pCi/L 10.8 12.1 89 Pass Cs-137 pCi/L 34 33.1 104 Pass Co-60 pCi/L 11.3 11.5 98 Pass Zn-65 pCi/L 88.0 89.2 99 Pass I-131 pCi/L 25.3 28.4 89 Pass GR-B pCi/L 28.8 29.9 96 Pass H-3 pCi/L 20,766 21,400 97 Pass July 2019 RAD-118 H-3 pCi/L 17,684 16,700 106 Pass September 2019 MRAD-31 AP Am-241 pCi/Filter 28.4 32 89 Pass Cs-134 pCi/Filter 60.7 59 103 Pass Cs-137 pCi/Filter 440 437 101 Pass Co-60 pCi/Filter 57.5 58.4 98 Pass Zn-65 pCi/Filter 381 364 105 Pass October 2019 RAD-119 Water Ba-133 pCi/L 37.2 43.8 85 Pass Cs-134 pCi/L 52.2 55.9 93 Pass Cs-137 pCi/L 80.3 78.7 102 Pass Co-60 pCi/L 54.8 53.4 103 Pass Zn-65 pCi/L 39.3 34 116 Pass I-131 pCi/L 25.4 23.9 106 Pass (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(b) ERA evaluation based on EIS internal QC limits in accordance with the NRC Resolution Test criteria E-7

TABLE E.6 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

GEL Laboratories (Gamma, H-3 & Sr-90)

Identification Reported Known Quarter/Year Matrix Nuclide Units Acceptance Range Evaluation (b)

Number Value Value (a) 2nd/2019 19-MaS40 Soil Sr-90 Bq/Kg 3.44 False Positive Test A 19-MaW40 Water H-3 Bq/L 389 421 295 - 547 A Sr-90 Bq/L 5.86 6.35 4.45 - 8.26 A Cs-134 Bq/L 5.32 5.99 4.19 - 7.79 A Cs-137 Bq/L 0 False Positive Test A Co-60 Bq/L 6.7 6.7 4.7 - 8.7 A Fe-55 Bq/L 0.0173 False Positive Test A Mn-54 Bq/L 8.8 8.4 5.9 - 10.9 A Zn-65 Bq/L -0.0318 False Positive Test A 19-RdF40 AP Sr-90 Bq/sample 0.616 0.662 0.463 - 0.861 A 19-RdV40 Veg Sr-90 Bq/sample 0.00951 False Positive Test A 4th/2019 19-MaS41 Soil S-90 Bq/Kg 609 572 400 - 744 A 19-MaW41 Water H-3 Bq/L 166 175 123 - 228 A Sr-90 Bq/L 9.34 10.6 7.4 - 13.8 A Cs-134 Bq/L 0.0266 False Positive Test A Cs-137 Bq/L 19.7 18.4 12.9 - 23.9 A Co-60 Bq/L 9.01 8.8 6.2 - 11.4 A Fe-55 Bq/L 13.8 15.70 11.0 - 20.4 A Mn-54 Bq/L 22.6 20.6 14.4 - 26.8 A Zn-65 Bq/L 23.1 20.3 5.27 - 9.79 A 19-RdF41 AP Sr-90 Bq/sample 0.442 0.498 0.349 - 0.647 A 19-RdV41 Veg Sr-90 Bq/sample 0.847 1.00 0.70 - 1.30 A (a) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation (b) DOE/MAPEP evaluation:

A = Acceptable - reported result falls within ratio limits of 0.80-1.20 W = Acceptable with warning - reported result falls within 0.70-0.80 or 1.20-1.30 N = Not Acceptable - reported result falls outside the ratio limits of < 0.70 and > 1.30 E-8

TABLE E.7 ERA Environmental Radioactivity Cross Check Program GEL Laboratories (Gamma, H-3 & Sr-89/90)

Identification Reported Known Acceptance Quarter/Year Matrix Nuclide Units Evaluation (b)

Number Value Value (a) Limits 1st/2019 RAD-116 Water Cs-134 pCi/L 48.2 49.1 39.5 - 54.0 A Cs-137 pCi/L 128 125 112 - 140 A Co-60 pCi/L 104 96.4 86.8 - 108 A Zn-65 pCi/L 88.1 77.4 69.5 - 93.2 A H-3 pCi/L 2,160 2,110 1,740 - 2,340 A H-3 pCi/L 1,920 2,110 1,740 - 2,340 A (1)

Sr-89 pCi/L 78.5 66.9 54.4 - 75.0 N (1)

Sr-89 pCi/L 76.5 66.9 54.4 - 75.0 N Sr-90 pCi/L 40.1 41.0 30.2 - 47.1 A Sr-90 pCi/L 42.2 41.0 30.2 - 47.1 A 2nd/2019 MRAD-30 Soil Sr-90 pCi/kg 1,220 1,350 420 - 2,100 A Veg Sr-90 pCi/kg 4,670 3,530 1,900 - 4,600 N(2)

AP Sr-90 pCi 169 181 114 - 246 A Water Sr-90 pCi/L 365 315 227 - 389 A H-3 pCi/L 22,200 23,700 17,900 - 28,800 A Cs-134 pCi/L 116 123 92.9 - 135 A Cs-137 pCi/L 126 125 107 - 142 A Co-60 pCi/L 1,200.0 1,100 949 - 1,260 A Fe-55 pCi/L 1,310 1,320 776 - 1,920 A Mn-54 pCi/L <5.6 <100 <100 A Zn-65 pCi/L 1,990 1,780 1,580 - 2,250 A RAD-116 Water Sr-89 pCi/L 35.9 33.3 24.5 - 40.2 A Sr-89 pCi/L 34.4 33.3 24.5 - 40.2 A 3rd/2019 RAD-118 Water Cs-134 pCi/L 30.4 32.0 25.1 - 35.2 A Cs-137 pCi/L 23 21 17.6 - 26.7 A Co-60 pCi/L 102 95.1 85.6 - 107 A Zn-65 pCi/L 49.2 41.2 35.3 - 51.4 A H-3 pCi/L 14,700 16,700 14,600 - 18,400 A H-3 pCi/L 14,700 16,700 14,600 - 18,400 A H-3 pCi/L 15,000 16,700 14,600 - 18,400 A (3)

Sr-89 pCi/L 69.4 58.7 47.1 - 66.5 N Sr-89 pCi/L 62.1 58.7 47.1 - 66.5 A Sr-90 pCi/L 34.3 38.5 28.3 - 44.3 A Sr-90 pCi/L 33.4 38.5 28.3 - 44.3 A 4th/2019 MRAD-31 Soil Sr-90 pCi/kg 1,660 1,910 594 - 2,980 A Veg Sr-90 pCi/kg 4,010 3,940 2,220 - 5,130 A AP Sr-90 pCi 34.8 34.5 21.8 - 47.0 A Water Sr-90 pCi/L 508 481 346 - 595 A H-3 pCi/L 20,900 22,300 16,800 - 27,100 A Cs-134 pCi/L 1,820 1,960 1,480 - 2,160 A Cs-137 pCi/L 1,820 1,840 1,580 - 2,090 A Co-60 pCi/L 1,970 1,870 1,610 - 2,150 A Fe-55 pCi/L 1,410 1,460 858 - 2,120 A Mn-54 pCi/L <7.24 <100 <100 A Zn-65 pCi/L 1,490 1,370 1,220 - 1,730 A (a) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(b) ERA evaluation:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits (1) CARR190225-1192 )

(2) CARR190530-1211 (3) CARR190826-1250 E-9

TABLE E.8 Analytics Environmental Radioactivity Cross Check Program GEL Laboratories (Gamma and Sr-89/90 only)

Identification Reported Known Acceptance Quarter/Year Matrix Nuclide Units Evaluation (b)

Number Value Value (a) Limits 1st/2019 E12367 Water Cs-134 pCi/L 143 155 0.92 A Cs-137 pCi/L 209 191 1.10 A Co-58 pCi/L 143 139 1.03 A Co-60 pCi/L 318 290 1.10 A Fe-59 pCi/L 176 154 1.14 A M:n-54 pCi/L 155 139 1.12 A Zn-65 pCi/L 244 214 1.14 A 2nd/2019 E12361 Milk Sr-89 pCi/L 101 82.9 1.22 A Sr-90 pCi/L 12.1 13.5 0.90 A E12363 Water Cs-134 pCi/L 137 153 0.89 A Cs-137 pCi/L 190 184 1.03 A Co-58 pCi/L 122 122 1.00 A Co-60 pCi/L 222 216 1.03 A Fe-59 pCi/L 173 154 1.12 A Mn-54 pCi/L 227 270 1.10 A Zn-65 pCi/L 301 270 1.11 A 3rd/2019 E12369 Milk Sr-89 pCi/L 87.1 93.9 0.93 A Sr-90 pCi/L 7.02 12.9 0.54 A E12371 Water Cs-134 pCi/L 150 157 0.96 A Cs-137 pCi/L 122 114 1.07 A Co-58 pCi/L 136 133 1.03 A Co-60 pCi/L 168 160 1.04 A Fe-59 pCi/L 127 112 1.13 A Mn-54 pCi/L 134 117 1.15 A Zn-65 pCi/L 257 222 1.16 A 4th/2019 E12373 Milk Sr-89 pCi/L 66.0 80.6 0.82 A Sr-90 pCi/L 11.1 11.0 1.00 A E12375 Water Cs-134 pCi/L 106 114 0.93 A Cs-137 pCi/L 109 103 1.06 A Co-58 pCi/L 95.4 91.1 1.05 A Co-60 pCi/L 122 117 1.05 A Fe-59 pCi/L 93.2 88.2 1.06 A Mn-54 pCi/L 144 131 1.10 A Zn-65 pCi/L 191 161 1.19 A (a) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(b) Analytics evaluation based on laboratory's internal acceptance criteria of 75% - 125%:

A = Acceptable - Reported value falls within the Acceptance Limits N = Not Acceptable - Reported value falls outside of the Acceptance Limits E-10

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January through 31 December 2019 Prepared By Teledyne Brown Engineering Environmental Services Three Mile Island Nuclear Station Middletown, PA 17057 April 2020

Intentionally left blank Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction...................................................................................................................... 3 A. Objectives of the RGPP ....................................................................................... 4 B. Implementation of the Objectives ........................................................................ 4 C. Program Description ............................................................................................ 5 D. Characteristics of Tritium (H-3)............................................................................ 5 III. Program Description....................................................................................................... 7 A. Sample Analysis .................................................................................................. 7 B. Data Interpretation ............................................................................................... 7 IV. Results and Discussion ................................................................................................. 9 A. Groundwater Results ........................................................................................... 9 B. Surface Water Results ....................................................................................... 10 C. Storm Water Results ......................................................................................... 11 D. Precipitation Water Results ............................................................................... 11 E. Leaks, Spills, and Releases............................................................................... 12 F. Actions Taken .................................................................................................... 12 i

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2019 Figures Figure A-1 Sampling Locations at the Three Mile Island Nuclear Station, 2019 Appendix B Data Tables Tables Table B-I.1 Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 Table B-I.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table B-I.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2019 Table B-II.1 Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 Table B-II.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table B-III.1 Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 Table B-III.2 Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2019 Table B-IV.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 ii

Appendix C Data Tables - Comparison Tables Table C-I.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 Table C-I.2 Concentrations of Gamma Emitters in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 Table C-I.3 Concentrations of Hard-To-Detects in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2019 Table C-II.1 Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 Table C-II.2 Concentrations of Gamma Emitters in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 Table C-III.1 Concentrations of Tritium in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2019 iii

I. Summary and Conclusions In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Three Mile Island Nuclear Station. This report covers groundwater, surface water, storm water, and precipitation samples collected from the environment, both on and off station property in 2019. During that time period 462 analyses were performed on 243 samples from 60 locations.

In assessing all the data gathered for this report, it was concluded that the operation of Three Mile Island Nuclear Station had no adverse radiological impact on the environment.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater, surface water, storm water, and precipitation samples.

In the case of tritium, Exelon specified that its laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

Strontium-89 (Sr-89) and Strontium-90 (Sr-90) were not detected at a concentration greater than their respective LLD of 10 and 1 picocurie per liter (pCi/L) in the groundwater samples tested.

Tritium was not detected in any ground water, surface water, storm water or precipitation water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 27 of 52 groundwater monitoring locations. The groundwater tritium concentrations ranged from 188 +/- 123 pCi/L to 3,840 +/- 445 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of previous tank leakage, historical releases, the recapture of gaseous tritium releases via rainwater, and/or background from external sources greater than 200 pCi/L. Tritium was not detected at any surface water location. Tritium was detected in 3 storm water samples. The concentrations ranged from 219 +/- 127 to 381 +/- 131 pCi/L. Tritium was detected in 3 of 4 precipitation water locations. The concentrations ranged from 237 +/- 124 to 802 +/- 152 pCi/L.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on 25 groundwater samples during the second quarter sampling in 2019. Neither Gross Alpha (dissolved) nor Gross Alpha (suspended) was detected at any of the 25 groundwater locations. Gross Beta (dissolved) was detected at all 25 groundwater locations. The concentrations ranged from 1.4 to 12.6 pCi/L. Gross Beta (suspended) was detected at 3 of the 25 groundwater locations. The concentrations ranged from 3.3 to 5.7 pCi/L.

Hard-To-Detect analyses, which include Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238, were not analyzed in 2019.

II. Introduction The Three Mile Island Nuclear Station (TMINS) established a revised and more comprehensive groundwater monitoring program in 2006 as part of an Exelon Nuclear fleetwide assessment.

Conestoga Rovers & Associates (CRA) performed the initial assessment. CRA prepared a Hydrogeologic Investigation Report (HIR) for Exelon to determine whether groundwater at and near TMINS has been adversely impacted by any releases of radionuclides. The CRA report documents the results of the May 2006 Hydrogeologic Investigation Work Plan. CRA assessed groundwater quality at the Station and identified locations designated as Areas for Further Evaluation. The results and conclusions of this Phase 1 study were made available to state and federal regulators, as well as the public on an Exelon web site for station specific reports.

As a result of the Phase 1 study, the Radiological Groundwater Protection Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Exelon Industrial Services (EIS)/GEL Laboratories on well water, surface water, storm water, and precipitation water samples collected in 2019. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides.

In December 2019, GHD completed an additional five-year update hydrogeologic investigation report for the Station (NEI 07-07, Hydrogeologic Investigation Report). The referenced report summarized station activities since the 2015 hydrogeologic investigation report, including changes at the Station as well as RGPP sampling activities and groundwater flow. Relevant conclusions from the report are:

AFE-TMI-6-BWST, 1 BWST is retained as an AFE In September 2015, GHD completed an additional five-year update hydrogeologic investigation report for the Station (NEI 07-07, Hydrogeologic Investigation Report). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including changes at the Station as well as RGPP sampling activities and groundwater flow. Relevant conclusions from the report are:

None of the Areas of Further Evaluation (AFEs) identified in 2006 indicate current impacts to groundwater and are no longer considered AFEs.

One new AFE, AFE-TMI-6-BWST, was identified based on laboratory analytical data.

In July 2012, elevated tritium concentrations were noted for a sample collected from an electric vault west of MS-22. The source of this elevated tritium concentration was believed to be the BWST.

Tritium is not migrating off of the Station property at concentrations greater than the USEPA Drinking Water Standard of 20,000 pCi/L.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective LLDs.

Strontium 89 or 90 were not detected at concentrations greater than their respective LLDs.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Gel Laboratories (subcontracted from Exelon Industrial Services) on samples collected in 2019.

A. Objectives of the RGPP The long-term objectives of the Radiological Groundwater Protection Program (RGPP) are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.

2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

3. Perform routine water sampling and radiological analysis of water from selected locations.

4. Notify stakeholders in a timely manner for new leaks, spills, or other detections with potential radiological significance.

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives The objectives identified have been implemented at Three Mile Island Nuclear Station as discussed below:

1. Three Mile Island Nuclear Station continues to sample and monitor the groundwater at the station in accordance with station procedures.

Sample frequencies and locations are adjusted based on monitoring results and investigations.

2. The Three Mile Island Nuclear Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.

3. Three Mile Island Nuclear Station will continue to perform routine sampling and radiological analysis of water from selected locations.

4. Three Mile Island Nuclear Station has implemented procedures to identify and report leaks, spills, or other detections with potential radiological significance in a timely manner.

5. Three Mile Island Nuclear Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.

C. Program Description

1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1 and A-2, Appendix A.

Groundwater, Surface Water, Storm Water, and Precipitation Samples of water are collected, managed, transported and analyzed in accordance with approved procedures. Groundwater, surface water, storm water and precipitation are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures.

Contractor and/or station personnel are trained in the collection, preservation management and shipment of samples, as well as in documentation of sampling events. For split samples, collectors will periodically collect samples that are sent to Exelon Industrial Services/GEL Laboratories to confirm that TBE is producing comparable data. Analytical laboratories are subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables as data are received.

Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.

D. Characteristics of Tritium (H-3)

Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

Tritium is created in the environment from naturally-occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. This cosmogenic tritium combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, lithogenic tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

The chemical properties of tritium are essentially those of ordinary hydrogen. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, all tritium is essentially cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium has a radiological half-life of approximately 12.3 years. It decays spontaneously to Helium-3 (He-3). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides, because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

III. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE and Exelon Industrial Services (EIS)/GEL Laboratories to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2019.

In order to achieve the stated objectives, the current program includes the following analyses, as applicable:

1. Concentrations of gamma-emitters in groundwater, surface water, and storm water

2. Concentrations of strontium in groundwater

3. Concentrations of tritium in groundwater, surface water, precipitation water and storm water

4. Concentrations of Am-241 in groundwater

5. Concentrations of Cm-242 and Cm-243/244 in groundwater

6. Concentrations of Pu-238 and PU-239/240 in groundwater

7. Concentrations of U-234, U-235 and U-238 in groundwater

8. Concentrations of Fe-55 in groundwater

9. Concentrations of Ni-63 in groundwater

10. Concentrations of Gross Alpha and Gross Beta (Dissolved and Suspended) in groundwater B. Data Interpretation

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.

2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error).

Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.

Gamma spectroscopy results for each type of sample were grouped as follows:

For groundwater, surface water, and storm water 13 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.

The radio-analytical laboratory counts tritium results to an LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 - 240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration.

IV. Results and Discussion A. Groundwater Results Samples were collected from on and off-site wells in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Samples from 52 locations were analyzed for tritium activity. Tritium values ranged from the detection limit to 3,840 pCi/L.

(Table B-I.1, Appendix B)

Tritium Split Samples Tritium values ranged from the detection limit to 418 pCi/L.

(Table C-I.1, Appendix C)

Strontium Sr-89 and Sr-90 were not detected above their required detection limits of 10 and 1.0 pCi/L, respectively. (Table B-I.1, Appendix B)

Strontium Split Samples Sr-89 and Sr-90 were not analyzed on any split samples in 2019.

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on 25 groundwater samples during the second quarter sampling in 2019.

Gross Alpha (dissolved) was not detected at any of the groundwater locations. Gross Alpha (suspended) was also not detected at any of the groundwater locations.

Gross Beta (dissolved) was detected at all 25 groundwater locations. The concentrations ranged from 1.4 to 12.6 pCi/L. Gross Beta (suspended) was detected in 3 of the 25 groundwater locations. The concentrations ranged from 3.3 to 5.7 pCi/L. (Table B-I.1, Appendix B)

Gross Alpha and Gross Beta (dissolved and suspended) Split Samples Gross Alpha and Gross Beta were not analyzed on any split samples in 2019. (Table C-I.1, Appendix C)

Gamma Emitters Sixty-one locations were analyzed for gamma-emitting nuclides in 2019.

Naturally-occurring K-40 was detected in 1 sample at a concentration of 102 +/- 61 pCi/L. No other gamma-emitting nuclides were detected.

(Table B-I.2, Appendix B)

Gamma Emitters Split Samples One location analyzed a sample for gamma-emitting nuclides in 2019. No gamma-emitting nuclides were detected in this sample.

(Table C-I.2, Appendix C)

Hard-To-Detect Hard-To-Detect analyses, which include Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238, were not analyzed in 2019. (Table B-I.3, Appendix B)

Hard-To-Detect Split Samples Hard to detects were not analyzed on any split samples in 2019.

(Table C-I.3, Appendix C)

B. Surface Water Results Samples were collected from surface water locations in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Three locations analyzed for tritium in 2019. Tritium was not detected above the required detection limit of 200 pCi/L in any of the 15 samples analyzed. (Table B-II.1, Appendix B)

Tritium Split Samples Two locations analyzed for tritium in 2019. Tritium was not detected above the required detection limit of 200 pCi/L in either sample analyzed.

(Table C-II.1, Appendix C)

Gamma Emitters Three locations analyzed for gamma-emitting nuclides in 2019. No gamma-emitting nuclides were detected. (Table B-II.2, Appendix B)

Gamma Emitters Split Samples One surface water sample was analyzed for gamma-emitting nuclides in 2019. No gamma-emitting nuclides were detected.

(Table C-II.2, Appendix C).

C. Storm Water Results Samples were collected from storm water locations in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium One location analyzed for tritium. Tritium was detected in 3 of 4 samples at a concentration range of 219 to 381 pCi/L. (Table B-III.1, Appendix B)

Gamma Emitters Four samples from one location were analyzed for gamma-emitting nuclides.

No gamma-emitting nuclides were detected. (Table B-III.2, Appendix B)

D. Precipitation Water Results Samples were collected a 4 locations. The following analyses were performed:

Tritium Samples from 4 locations were analyzed for tritium activity. Tritium activity was detected at 3 of 4 locations. The concentrations ranged from 237 to 731 pCi/L. (Table B-IV.1, Appendix B)

Tritium Split Samples Samples from one location were analyzed for tritium activity. Tritium was not detected in any of the 4 samples. (Table C-III.1, Appendix C).

Gamma Emitters Precipitation water was not analyzed for Gamma Emitters in 2019.

Gamma Emitters Split Samples No gamma-emitting nuclides were analyzed in 2019.

E. Leaks, Spills, and Releases There were no leaks, spills or releases in 2019. A potential leak was identified at TMI in 2012 due to elevated MS-22 tritium concentration readings. TMI continues to monitor MS-22 and surrounding wells, in addition to tritium plumes from previous years, and reports the activity and dose to the public in the ARERR. The elevated MS-22 well tritium concentrations were voluntarily reported under the reporting requirements for the NEI Groundwater Protection Initiative (GPI) as implemented in Exelon's Reportability procedure LS-AA-1120, RAD 1.34 ( IR 1385497/1515261).

In May and June 2015, it was determined that multiple Borated Water Storage Tank (BWST) connections (10 of 13 bolted flange connections) had evidence of leakage in the form of boron deposits in addition to the main 24-inch flange (IR 1670674/2427517/2508405/2509685).

F. Actions Taken There were no compensatory/corrective actions taken in 2019.

Fully encapsulating enclosures were installed around all BWST connections including the 24-inch main outlet flange. Each enclosure was fitted with a Tygon tubing discharge point, connected to a water collection bottle to prevent tritiated water from reaching the ground surface. The outlet flange and leaking connections were repaired during the TMI refueling outage in November 2015.

TMI has an extensive groundwater monitoring program with over 50 monitoring wells. No monitoring wells outside the BWST investigation area have seen elevated tritium concentrations. TMI continues to monitor the BWST area wells closely. The leakage has been mitigated by repairing the leaking flanges, and groundwater tritium concentrations have decreased during 2019.

Intentionally left blank APPENDIX A LOCATION DESIGNATION & DISTANCE

Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Three Mile Island Nuclear Station, 2019 Site Site Type

3 Monitoring Well 48N Monitoring Well 48S Production Potable Well E1-2 Monitoring Well, Offsite EDCB Storm Water MS-1 Monitoring Well MS-19 Monitoring Well MS-2 Monitoring Well MS-20 Monitoring Well MS-21 Monitoring Well MS-22 Monitoring Well MS-3 Monitoring Well MS-4 Monitoring Well MS-5 Monitoring Well MS-6 Monitoring Well MS-7 Monitoring Well MS-8 Monitoring Well MW-1 Monitoring Well MW-2 Monitoring Well MW-3 Monitoring Well MW-4 Monitoring Well N2-1 Monitoring Well, Offsite NW-A Production Well NW-B Production Well NW-C Production Well NW-CW Clearwell OS-13B Monitoring Well OS-14 Monitoring Well OS-16 Monitoring Well OS-17 Monitoring Well OS-18 Monitoring Well OSF Production Potable Well RW-1 Monitoring Well RW-2 Monitoring Well SW-E-1 Surface Water SW-E-2 Surface Water SW-E-3 Surface Water MW-TMI-9S* Monitoring Well MW-TMI-10D Monitoring Well MW-TMI-10I Monitoring Well MW-TMI-10S Monitoring Well MW-TMI-11S* Monitoring Well MW-TMI-12S Monitoring Well MW-TMI-13I Monitoring Well MW-TMI-13S Monitoring Well MW-TMI-14D Monitoring Well MW-TMI-14I Monitoring Well MW-TMI-14S Monitoring Well MW-TMI-16D Monitoring Well MW-TMI-16I Monitoring Well MW-TMI-17D Monitoring Well MW-TMI-17I Monitoring Well MW-TMI-18D Monitoring Well MW-TMI-19D Monitoring Well MW-TMI-19I Monitoring Well MW-TMI-1D Monitoring Well MW-TMI-20D Monitoring Well MW-TMI-20I Monitoring Well MW-TMI-21D Monitoring Well MW-TMI-21I Monitoring Well A-1

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Three Mile Island Nuclear Station, 2019 Site Site Type MW-TMI-21S Monitoring Well MW-TMI-22D Monitoring Well MW-TMI-22I Monitoring Well MW-TMI-22S Monitoring Well MW-TMI-2D Monitoring Well MW-TMI-3I Monitoring Well MW-TMI-4I Monitoring Well MW-TMI-4S Monitoring Well MW-TMI-5D Monitoring Well MW-TMI-6D Monitoring Well MW-TMI-6I Monitoring Well MW-TMI-7S Monitoring Well MW-TMI-8S Monitoring Well MW-TMI-9I Monitoring Well TRAINING CENTER Offsite Monitoring Well TM-PR-ESE Precipitation Water TM-PR-MS-1 Precipitation Water TM-PR-MS-2 Precipitation Water TM-PR-MS-20 Precipitation Water TM-PR-MS-22 Precipitation Water TM-PR-MS-4 Precipitation Water TM-PR-NW-B Precipitation Water TM-PR-MW-TMI-22S Precipitation Water

NO WATER PRESENT TO SAMPLE A-2

Figure A - 1 Sampling Locations at the Three Mile Island Nuclear Station, 2019 A-3

Intentionally left blank APPENDIX B DATA TABLES

Intentionally left blank TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A Gr-B Gr-B SITE DATE H-3 Sr-89 Sr-90 (Dis) (Sus) (Dis) (Sus) 48S 02/19/19 < 190 48S 05/21/19 < 181 < 2.5 < 0.4 < 5.3 < 0.6 2.5 +/- 1.4 < 1.5 48S 08/27/19 < 193 48S 11/19/19 < 198 MS-1 02/18/19 < 191 MS-1 02/18/19 NP < 197 MS-1 05/21/19 NP < 191 MS-1 05/21/19 < 183 < 4.8 < 0.8 < 8.2 < 0.8 6.4 +/- 3.0 < 1.6 MS-1 08/27/19 < 191 MS-1 08/27/19 NP < 181 MS-1 11/18/19 265 +/- 133 MS-1 11/18/19 DUP 246 +/- 124 MS-1 11/18/19 NP 474 +/- 135 MS-2 02/22/19 200 +/- 126 MS-2 05/21/19 < 181 < 5.9 < 1.0 < 1.2 < 0.4 2.8 +/- 0.9 < 1.6 MS-2 08/28/19 < 194 MS-2 11/20/19 201 +/- 126 MS-3 02/22/19 200 +/- 129 MS-3 05/21/19 < 198 < 4.3 < 0.7 < 1.3 < 0.4 5.3 +/- 1.1 < 1.6 MS-3 08/28/19 226 +/- 126 MS-3 11/20/19 262 +/- 128 MS-4 05/21/19 < 185 MS-5 02/22/19 < 193 MS-5 05/21/19 < 197 < 6.3 < 0.6 < 1.4 < 0.7 3.7 +/- 0.9 < 1.3 MS-5 08/28/19 < 192 MS-5 11/20/19 < 197 MS-7 02/19/19 < 195 MS-7 05/23/19 < 196 < 6.1 < 0.9 < 0.9 < 0.7 1.6 +/- 0.6 < 1.3 MS-7 08/28/19 < 180 MS-7 11/21/19 < 196 MS-7 11/21/19 DUP < 185 MS-8 02/22/19 267 +/- 131 MS-8 05/21/19 < 197 < 7.0 < 0.9 < 1.3 < 0.7 4.6 +/- 0.9 < 1.3 MS-8 08/28/19 < 193 MS-8 11/20/19 196 +/- 128 MS-20 02/19/19 310 +/- 132 MS-20 05/21/19 294 +/- 124 < 5.7 < 0.9 < 1.2 < 0.4 5.8 +/- 1.1 < 1.6 MS-20 08/27/19 361 +/- 134 MS-20 08/27/19 DUP 313 +/- 126 MS-20 11/20/19 430 +/- 137 MS-21 02/19/19 < 189 MS-21 05/21/19 < 198 < 6.5 < 0.9 < 1.1 < 0.7 2.3 +/- 0.7 < 1.3 MS-21 08/27/19 < 195 MS-21 08/27/19 DUP < 182 MS-21 11/20/19 < 191 MS-22 02/19/19 901 +/- 166 MS-22 02/19/19 NP 929 +/- 167 MS-22 05/21/19 NP 963 +/- 170 MS-22 05/21/19 820 +/- 158 < 6.6 < 0.9 < 1.4 < 0.4 11.8 +/- 1.4 5.7 +/- 0.7 MS-22 05/21/19 889 +/- 164 MS-22 08/27/19 NP 649 +/- 137 MS-22 08/27/19 518 +/- 140 Bolded values indicate LLD was not met due to high solid content in the sample NP = Non-purge study samples B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A Gr-B Gr-B SITE DATE H-3 Sr-89 Sr-90 (Dis) (Sus) (Dis) (Sus)

MS-22 11/20/19 893 +/- 166 MS-22 11/20/19 NP 844 +/- 163 MW-1 05/22/19 < 183 MW-1 05/22/19 DUP < 198 MW-2 05/22/19 < 184 MW-TMI-1D 05/22/19 < 197 MW-TMI-2D 05/22/19 234 +/- 123 MW-TMI-3I 02/19/19 310 +/- 132 MW-TMI-3I 05/23/19 < 197 < 5.0 < 0.7 < 5.3 < 0.6 8.8 +/- 2.6 < 2.6 MW-TMI-3I 08/27/19 389 +/- 134 MW-TMI-3I 11/18/19 244 +/- 133 MW-TMI-3I 11/18/19 DUP 202 +/- 119 MW-TMI-4I 05/23/19 < 196 MW-TMI-4S 05/23/19 < 182 MW-TMI-6D 02/19/19 < 190 MW-TMI-6D 02/19/19 DUP < 192 MW-TMI-6D 05/23/19 < 188 < 4.2 < 0.8 < 1.7 < 0.4 2.9 +/- 1.0 < 1.6 MW-TMI-6D 08/28/19 328 +/- 126 MW-TMI-6D 11/21/19 211 +/- 114 MW-TMI-6I 02/19/19 263 +/- 130 MW-TMI-6I 05/23/19 < 187 < 6.5 < 0.8 < 1.2 < 0.4 2.4 +/- 0.9 < 1.6 MW-TMI-6I 08/28/19 261 +/- 124 MW-TMI-6I 11/21/19 225 +/- 114 MW-TMI-7S 05/22/19 < 184 MW-TMI-8S 05/22/19 < 185 MW-TMI-9I 05/22/19 < 181 MW-TMI-9S 05/22/19 < 185 MW-TMI-10D 05/23/19 < 184 MW-TMI-10I 02/18/19 396 +/- 137 MW-TMI-10I 02/18/19 DUP 356 +/- 136 MW-TMI-10I 02/18/19 NP 404 +/- 138 MW-TMI-10I 05/23/19 NP 465 +/- 138 MW-TMI-10I 05/23/19 308 +/- 128 MW-TMI-10I 05/23/19 DUP 447 +/- 132 MW-TMI-10I 08/27/19 390 +/- 136 MW-TMI-10I 08/27/19 NP 407 +/- 129 MW-TMI-10I 11/21/19 293 +/- 134 MW-TMI-10I 11/21/19 NP 356 +/- 128 MW-TMI-10S 02/18/19 215 +/- 126 MW-TMI-10S 02/18/19 NP 258 +/- 128 MW-TMI-10S 05/23/19 NP 386 +/- 133 MW-TMI-10S 05/23/19 456 +/- 133 < 5.1 < 0.8 < 1.7 < 0.4 5.7 +/- 1.4 < 1.6 MW-TMI-10S 08/27/19 729 +/- 158 MW-TMI-10S 08/27/19 NP 720 +/- 145 MW-TMI-10S 11/21/19 413 +/- 139 MW-TMI-10S 11/21/19 NP 352 +/- 130 MW-TMI-12S 02/19/19 < 194 MW-TMI-12S 05/21/19 < 186 < 5.3 < 0.8 < 1.1 < 0.4 6.1 +/- 1.0 < 1.6 MW-TMI-12S 08/28/19 < 192 MW-TMI-12S 11/20/19 < 192 MW-TMI-13I 02/19/19 199 +/- 127 MW-TMI-13I 05/22/19 < 183 Bolded values indicate LLD was not met due to high solid content in the sample NP = Non-purge study samples B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A Gr-B Gr-B SITE DATE H-3 Sr-89 Sr-90 (Dis) (Sus) (Dis) (Sus)

MW-TMI-13I 05/22/19 DUP < 182 MW-TMI-13I 08/28/19 < 181 MW-TMI-13I 08/28/19 DUP < 180 MW-TMI-13I 11/21/19 < 171 MW-TMI-14D 02/19/19 307 +/- 133 MW-TMI-14D 05/22/19 268 +/- 127 MW-TMI-14D 05/22/19 DUP 260 +/- 125 MW-TMI-14D 08/28/19 < 196 MW-TMI-14D 11/21/19 222 +/- 128 MW-TMI-14I 02/19/19 < 190 MW-TMI-14I 02/19/19 DUP < 190 MW-TMI-14I 05/22/19 < 177 MW-TMI-14I 08/28/19 < 184 MW-TMI-14I 11/21/19 < 196 MW-TMI-16D 05/22/19 557 +/- 136 MW-TMI-17I 05/23/19 < 188 MW-TMI-18D 05/23/19 < 177 MW-TMI-19I 05/23/19 < 187 MW-TMI-20I 05/23/19 369 +/- 130 MW-TMI-21D 02/19/19 3840 +/- 445 MW-TMI-21D 02/19/19 NP 3730 +/- 431 MW-TMI-21D 05/21/19 3110 +/- 374 MW-TMI-21D 05/21/19 NP 3400 +/- 402 MW-TMI-21D 08/27/19 NP 3450 +/- 403 MW-TMI-21D 08/27/19 3230 +/- 388 MW-TMI-21D 11/20/19 NP 2810 +/- 345 MW-TMI-21D 11/20/19 2750 +/- 340 MW-TMI-21I 02/19/19 696 +/- 150 MW-TMI-21I 02/19/19 NP 1020 +/- 175 MW-TMI-21I 05/21/19 NP 621 +/- 146 MW-TMI-21I 05/21/19 532 +/- 138 MW-TMI-21I 08/27/19 NP 948 +/- 162 MW-TMI-21I 08/27/19 948 +/- 166 MW-TMI-21I 11/20/19 791 +/- 156 MW-TMI-21I 11/20/19 NP 760 +/- 156 MW-TMI-21S 02/19/19 289 +/- 135 MW-TMI-21S 02/19/19 NP 407 +/- 138 MW-TMI-21S 05/21/19 NP 369 +/- 137 MW-TMI-21S 05/21/19 380 +/- 130 < 6.6 < 0.9 < 1.9 < 0.6 6.7 +/- 1.3 3.3 +/- 0.6 MW-TMI-21S 05/21/19 454 +/- 135 MW-TMI-21S 08/27/19 NP 265 +/- 124 MW-TMI-21S 08/27/19 284 +/- 121 MW-TMI-21S 11/20/19 1090 +/- 183 MW-TMI-21S 11/20/19 NP 1080 +/- 184 MW-TMI-22D 02/19/19 3080 +/- 370 MW-TMI-22D 02/19/19 NP 2760 +/- 218 MW-TMI-22D 05/21/19 NP 3200 +/- 384 MW-TMI-22D 05/21/19 2570 +/- 321 MW-TMI-22D 08/27/19 NP 2560 +/- 316 MW-TMI-22D 08/27/19 1910 +/- 253 MW-TMI-22D 11/20/19 1930 +/- 261 MW-TMI-22D 11/20/19 NP 1800 +/- 251 MW-TMI-22I 02/19/19 1490 +/- 218 MW-TMI-22I 02/19/19 NP 1360 +/- 174 NP = Non-purge study samples B-3

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A Gr-B Gr-B SITE DATE H-3 Sr-89 Sr-90 (Dis) (Sus) (Dis) (Sus)

MW-TMI-22I 05/21/19 NP 909 +/- 167 MW-TMI-22I 05/21/19 806 +/- 158 MW-TMI-22I 05/21/19 Recount 697 +/- 155 MW-TMI-22I 05/21/19 Reanalysis 765 +/- 152 MW-TMI-22I 08/27/19 NP 967 +/- 167 MW-TMI-22I 08/27/19 1150 +/- 180 MW-TMI-22I 11/20/19 1310 +/- 202 MW-TMI-22I 11/20/19 NP 1200 +/- 195 MW-TMI-22S 02/19/19 594 +/- 146 MW-TMI-22S 02/19/19 NP 580 +/- 144 MW-TMI-22S 05/21/19 NP 701 +/- 150 MW-TMI-22S 05/21/19 578 +/- 143 < 9.1 < 0.7 < 1.6 < 0.8 7.1 +/- 1.1 4.5 +/- 0.7 MW-TMI-22S 05/21/19 583 +/- 143 MW-TMI-22S 08/27/19 NP 506 +/- 132 MW-TMI-22S 08/27/19 436 +/- 130 MW-TMI-22S 11/20/19 466 +/- 139 MW-TMI-22S 11/20/19 NP 290 +/- 131 N2-1 05/30/19 < 188 NW-A 02/19/19 306 +/- 128 NW-A 05/21/19 307 +/- 128 < 6.8 < 0.8 < 1.7 < 0.6 3.0 +/- 1.0 < 1.5 NW-A 08/27/19 < 187 NW-A 11/20/19 258 +/- 132 NW-B 02/19/19 372 +/- 135 NW-B 05/21/19 301 +/- 131 < 3.8 < 0.7 < 1.6 < 0.6 2.5 +/- 1.0 < 1.5 NW-B 08/27/19 < 189 NW-B 11/20/19 256 +/- 130 NW-C 02/19/19 610 +/- 144 NW-C 05/21/19 476 +/- 137 < 3.2 < 0.6 < 1.6 < 0.6 1.4 +/- 0.9 < 1.5 NW-C 08/27/19 458 +/- 137 NW-C 11/20/19 355 +/- 134 NW-CW 02/19/19 432 +/- 138 NW-CW 05/21/19 351 +/- 132 < 4.1 < 0.7 < 1.6 < 0.6 1.9 +/- 0.9 < 1.5 NW-CW 08/27/19 < 187 NW-CW 11/19/19 358 +/- 137 OS-14 02/22/19 213 +/- 128 OS-14 05/21/19 < 194 < 4.7 < 0.9 < 3.2 < 0.7 12.6 +/- 1.7 < 1.3 OS-14 08/28/19 234 +/- 127 OS-14 11/20/19 188 +/- 123 OS-16 02/22/19 287 +/- 130 OS-16 05/21/19 < 190 < 3.5 < 0.7 < 1.2 < 0.6 4.6 +/- 0.8 < 1.5 OS-16 08/28/19 194 +/- 125 OS-16 11/20/19 < 193 OS-18 05/23/19 < 184 OSF 02/19/19 363 +/- 132 OSF 05/21/19 235 +/- 127 < 3.9 < 0.7 < 4.0 < 0.6 5.1 +/- 1.4 < 1.5 OSF 08/27/19 255 +/- 123 OSF 11/20/19 515 +/- 143 RW-1 02/19/19 < 190 RW-1 05/21/19 < 192 < 3.2 < 0.6 < 1.7 < 0.6 5.5 +/- 1.2 < 1.5 RW-1 08/28/19 < 192 RW-1 11/20/19 < 193 TRAINING CENTER 05/22/19 < 184 Bolded values indicate LLD was not met due to high solid content in the sample NP = Non-purge study samples B-4

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 48S 05/21/19 < 60 < 84 < 7 < 7 < 15 < 6 < 14 < 6 < 9 < 9 < 7 < 35 < 9 MS-1 05/21/19 < 59 < 121 < 6 < 7 < 12 < 8 < 10 < 7 < 11 < 8 < 6 < 21 < 12 MS-2 05/21/19 < 59 < 77 < 4 < 5 < 15 < 8 < 14 < 6 < 12 < 6 < 5 < 35 < 13 MS-3 02/22/19 < 36 < 71 < 4 < 4 < 10 < 5 < 8 < 5 < 7 < 5 < 4 < 20 < 7 MS-3 05/21/19 < 47 102 +/- 61 < 5 < 6 < 12 < 5 < 10 < 6 < 10 < 7 < 6 < 26 < 11 MS-3 08/28/19 < 55 < 75 < 6 < 6 < 11 < 5 < 12 < 7 < 10 < 8 < 7 < 32 < 12 MS-3 11/20/19 < 55 < 124 < 5 < 7 < 11 < 8 < 14 < 7 < 10 < 8 < 7 < 26 < 5 MS-4 05/21/19 < 28 < 29 < 3 < 3 < 7 < 4 < 7 < 4 < 6 < 4 < 3 < 17 < 6 MS-5 02/22/19 < 35 < 75 < 4 < 4 < 8 < 5 < 7 < 4 < 7 < 4 < 3 < 18 < 5 MS-5 05/21/19 < 60 < 121 < 6 < 7 < 16 < 8 < 15 < 9 < 12 < 8 < 7 < 31 < 9 MS-5 08/28/19 < 67 < 76 < 8 < 9 < 16 < 8 < 20 < 9 < 15 < 9 < 9 < 37 < 12 MS-5 11/20/19 < 29 < 65 < 4 < 4 < 7 < 3 < 8 < 4 < 6 < 4 < 3 < 17 < 6 MS-7 05/23/19 < 45 < 102 < 5 < 5 < 9 < 4 < 9 < 6 < 10 < 6 < 5 < 29 < 8 B-5 MS-8 02/22/19 < 38 < 77 < 4 < 5 < 9 < 5 < 8 < 4 < 7 < 5 < 4 < 18 < 7 MS-8 05/21/19 < 70 < 59 < 8 < 8 < 13 < 10 < 12 < 7 < 15 < 8 < 8 < 41 < 12 MS-8 08/28/19 < 65 < 153 < 8 < 7 < 14 < 8 < 16 < 8 < 13 < 7 < 8 < 34 < 11 MS-8 11/20/19 < 54 < 116 < 6 < 6 < 14 < 8 < 17 < 8 < 10 < 6 < 6 < 30 < 11 MS-20 05/21/19 < 42 < 56 < 5 < 6 < 10 < 6 < 11 < 5 < 10 < 6 < 6 < 26 < 10 MS-21 05/21/19 < 55 < 105 < 6 < 6 < 12 < 6 < 16 < 7 < 8 < 7 < 8 < 37 < 12 MS-22 05/21/19 < 38 < 39 < 4 < 4 < 9 < 3 < 8 < 5 < 8 < 4 < 4 < 28 < 11 MW-1 05/22/19 < 44 < 58 < 3 < 5 < 10 < 4 < 10 < 5 < 9 < 5 < 5 < 20 < 11 MW-1 DUP 05/22/19 < 55 < 120 < 7 < 7 < 12 < 7 < 13 < 6 < 10 < 6 < 7 < 34 < 11 MW-2 05/22/19 < 63 < 77 < 6 < 7 < 15 < 7 < 14 < 7 < 10 < 7 < 8 < 35 < 10 MW-TMI-10D 05/23/19 < 37 < 65 < 5 < 4 < 9 < 5 < 8 < 4 < 8 < 4 < 4 < 20 < 9 MW-TMI-10S 05/23/19 < 42 < 87 < 4 < 4 < 10 < 4 < 8 < 5 < 7 < 4 < 5 < 18 < 8 MW-TMI-12S 05/21/19 < 65 < 99 < 8 < 7 < 13 < 8 < 15 < 9 < 11 < 7 < 7 < 37 < 11 MW-TMI-16D 05/22/19 < 52 < 59 < 5 < 8 < 10 < 7 < 12 < 6 < 11 < 7 < 6 < 29 < 10 MW-TMI-17I 05/23/19 < 58 < 106 < 6 < 8 < 13 < 7 < 14 < 6 < 11 < 6 < 8 < 34 < 10 MW-TMI-18D 05/23/19 < 53 < 98 < 6 < 8 < 11 < 5 < 14 < 6 < 10 < 8 < 6 < 33 < 7 MW-TMI-19I 05/23/19 < 38 < 81 < 4 < 5 < 9 < 5 < 9 < 5 < 8 < 5 < 4 < 21 < 7 MW-TMI-1D 05/22/19 < 56 < 57 < 6 < 6 < 13 < 6 < 9 < 7 < 12 < 7 < 6 < 29 < 10 MW-TMI-20I 05/23/19 < 39 < 55 < 5 < 4 < 11 < 5 < 8 < 4 < 8 < 6 < 5 < 24 < 11 MW-TMI-21S 05/21/19 < 37 < 74 < 4 < 4 < 8 < 4 < 8 < 4 < 8 < 4 < 4 < 29 < 9 MW-TMI-22S 05/21/19 < 38 < 76 < 4 < 4 < 9 < 4 < 8 < 5 < 8 < 4 < 4 < 32 < 10

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 MW-TMI-2D 05/22/19 < 47 < 151 < 7 < 8 < 15 < 8 < 14 < 6 < 12 < 8 < 6 < 36 < 13 MW-TMI-3I 05/23/19 < 55 < 62 < 6 < 6 < 11 < 7 < 13 < 7 < 11 < 6 < 6 < 32 < 11 MW-TMI-4I 05/23/19 < 44 < 47 < 5 < 5 < 11 < 5 < 11 < 6 < 9 < 6 < 6 < 26 < 10 MW-TMI-4S 05/23/19 < 48 < 75 < 5 < 5 < 11 < 6 < 10 < 4 < 8 < 5 < 5 < 28 < 7 MW-TMI-6D 05/23/19 < 32 < 65 < 4 < 3 < 9 < 4 < 7 < 3 < 6 < 5 < 4 < 21 < 8 MW-TMI-6I 05/23/19 < 38 < 86 < 5 < 4 < 9 < 4 < 8 < 4 < 8 < 5 < 5 < 25 < 8 MW-TMI-7S 05/22/19 < 51 < 136 < 7 < 8 < 17 < 8 < 13 < 8 < 11 < 6 < 7 < 36 < 11 MW-TMI-8S 05/22/19 < 44 < 116 < 6 < 7 < 17 < 9 < 13 < 8 < 12 < 7 < 7 < 24 < 9 MW-TMI-9I 05/22/19 < 52 < 140 < 6 < 6 < 15 < 6 < 14 < 7 < 11 < 8 < 7 < 29 < 10 MW-TMI-9S 05/22/19 < 59 < 76 < 7 < 6 < 11 < 7 < 14 < 7 < 11 < 8 < 4 < 30 < 13 N2-1 05/30/19 < 49 < 42 < 5 < 5 < 11 < 5 < 12 < 6 < 10 < 4 < 6 < 34 < 9 NW-A 05/21/19 < 59 < 55 < 7 < 7 < 15 < 9 < 17 < 9 < 11 < 9 < 8 < 38 < 15 NW-B 05/21/19 < 56 < 54 < 7 < 7 < 12 < 8 < 11 < 6 < 12 < 7 < 5 < 33 < 11 B-6 NW-C 05/21/19 < 35 < 80 < 4 < 4 < 8 < 5 < 9 < 4 < 7 < 5 < 4 < 21 < 6 NW-CW 05/21/19 < 53 < 100 < 7 < 7 < 16 < 7 < 17 < 7 < 13 < 8 < 7 < 36 < 10 OS-14 02/22/19 < 35 < 57 < 4 < 4 < 9 < 5 < 9 < 4 < 6 < 5 < 4 < 19 < 7 OS-14 05/21/19 < 66 < 71 < 6 < 6 < 14 < 7 < 18 < 6 < 13 < 8 < 7 < 37 < 11 OS-14 08/28/19 < 48 < 120 < 6 < 6 < 14 < 4 < 9 < 8 < 11 < 8 < 8 < 30 < 13 OS-14 11/20/19 < 58 < 57 < 7 < 7 < 15 < 6 < 15 < 9 < 13 < 8 < 8 < 30 < 13 OS-16 02/22/19 < 38 < 42 < 4 < 4 < 8 < 4 < 8 < 5 < 7 < 5 < 5 < 19 < 6 OS-16 05/21/19 < 57 < 55 < 5 < 6 < 12 < 6 < 10 < 6 < 11 < 6 < 6 < 30 < 11 OS-16 08/28/19 < 61 < 66 < 7 < 7 < 13 < 8 < 17 < 8 < 11 < 8 < 8 < 33 < 11 OS-16 11/20/19 < 45 < 109 < 5 < 5 < 11 < 6 < 11 < 6 < 9 < 6 < 6 < 24 < 6 OS-18 05/23/19 < 44 < 76 < 4 < 5 < 11 < 5 < 8 < 5 < 7 < 5 < 4 < 25 < 10 OSF 05/21/19 < 58 < 119 < 6 < 6 < 15 < 7 < 12 < 7 < 9 < 7 < 7 < 35 < 10 RW-1 05/21/19 < 64 < 78 < 7 < 7 < 17 < 9 < 14 < 7 < 11 < 8 < 7 < 38 < 8 TRAINING CENTER 05/22/19 < 59 < 84 < 6 < 6 < 14 < 7 < 12 < 7 < 10 < 7 < 7 < 27 < 12

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 There were no hard to detect analyses for 2019 B-7

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-1 02/19/19 < 192 SW-E-1 05/22/19 < 191 SW-E-1 08/28/19 < 190 SW-E-1 11/20/19 < 192 SW-E-2 02/19/19 < 192 SW-E-2 05/22/19 < 181 SW-E-2 08/28/19 < 193 SW-E-2 DUP 08/28/19 < 180 SW-E-2 11/20/19 < 189 SW-E-3 02/19/19 < 194 SW-E-3 05/22/19 < 179 SW-E-3 DUP 05/22/19 < 183 SW-E-3 08/28/19 < 192 SW-E-3 11/20/19 < 194 SW-E-3 DUP 11/20/19 < 171 B-8

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 SW-E-1 05/22/19 < 52 < 99 < 5 < 6 < 14 < 6 < 15 < 5 < 8 < 8 < 5 < 30 < 11 SW-E-2 05/22/19 < 41 < 39 < 4 < 5 < 10 < 4 < 10 < 5 < 8 < 5 < 5 < 23 < 8 SW-E-3 05/22/19 < 43 < 124 < 5 < 5 < 10 < 5 < 12 < 6 < 11 < 7 < 6 < 29 < 8 SW-E-3 05/22/19 < 53 < 138 < 6 < 4 < 14 < 7 < 15 < 6 < 12 < 6 < 6 < 34 < 9 B-9

TABLE B-III.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM - THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATES H-3 EDCB 01/03/19 - 03/27/19 219 +/- 127 EDCB 05/01/19 - 06/27/19 < 195 EDCB 08/01/19 - 10/03/19 234 +/- 122 EDCB 10/31/19 - 01/02/20 381 +/- 131 B-10

TABLE B-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATES Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 EDCB 01/03/19 - 03/27/19 < 50 < 115 < 5 < 6 < 10 < 4 < 11 < 7 < 8 < 7 < 5 < 32 < 9 EDCB 05/01/19 - 06/27/19 < 72 < 140 < 8 < 6 < 13 < 9 < 15 < 7 < 10 < 9 < 8 < 29 < 10 EDCB 08/01/19 - 10/03/19 < 57 < 134 < 6 < 7 < 18 < 7 < 14 < 6 < 14 < 9 < 7 < 33 < 11 EDCB 10/31/19 - 01/02/20 < 62 < 86 < 6 < 6 < 12 < 8 < 9 < 5 < 11 < 6 < 8 < 26 < 5 B-11

TABLE B-IV.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 TM-PR-ESE 02/18/19 < 195 TM-PR-ESE 04/18/19 < 194 TM-PR-ESE 07/27/19 237 +/- 124 TM-PR-ESE 11/18/19 802 +/- 152 TM-PR-MS-1 02/18/19 < 191 TM-PR-MS-1 04/18/19 < 197 TM-PR-MS-1 07/27/19 < 187 TM-PR-MS-1 11/18/19 < 181 TM-PR-MS-2 02/18/19 < 200 TM-PR-MS-2 04/18/19 < 195 TM-PR-MS-2 07/27/19 < 184 TM-PR-MS-2 11/18/19 731 +/- 148 TM-PR-MS-4 02/18/19 < 198 TM-PR-MS-4 04/18/19 < 193 TM-PR-MS-4 07/27/19 < 188 TM-PR-MS-4 11/18/19 443 +/- 128 B-12

APPENDIX C DATA TABLES COMPARISON LAB

Intentionally left blank TABLE C-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE DATE H-3 GEL MS-1 11/18/19 < 118 MS-7 11/21/19 < 117 MS-20 08/27/19 418 +/- 103 MS-21 08/27/19 < 128 MW-1 05/22/19 < 172 MW-TMI-3I 11/18/19 < 119 MW-TMI-6D 02/19/19 < 135 MW-TMI-10I 02/18/19 403 +/- 93 MW-TMI-10I 05/23/19 385 +/- 136 MW-TMI-13I 08/28/19 < 130 MW-TMI-13I 05/22/19 < 173 MW-TMI-14D 05/22/19 214 +/- 92 MW-TMI-14I 02/19/19 < 132 C-1

TABLE C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE PERIOD Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 GEL MW-1 05/22/19 < 2 < 3 < 2 < 2 < 3 < 3 < 2 < 2 < 2 < 11 < 4 C-2

TABLE C-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-233/234 U-235 U-238 Fe-55 Ni-63 There were no hard to detect analyses for 2019 C-3

TABLE C-II.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE DATE H-3 GEL SW-E-2 08/28/19 < 122 SW-E-3 05/22/19 < 170 C-4

TABLE C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE PERIOD Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 GEL SW-E-3 05/22/19 < 1 < 2 < 1 < 1 < 2 < 2 < 2 < 1 < 2 < 8 < 3 C-5

TABLE C-III.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE DATES H-3 GEL TM-PR-MS-2Q 02/18/19 - 02/17/19 < 112 04/18/19 - 05/24/19 < 168 07/27/19 - 08/27/19 < 125 11/18/19 - 12/18/19 < 133 C-6

TMI-20-016, 2019 Annual Radiological Environmental Operating Report

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