ML23108A082

Annual Radiological Environmental Operating Report

ML23108A082
Person / Time
Site:	Three Mile Island
Issue date:	04/18/2023
From:	Orth T Constellation Energy Generation
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
TMl-23-008
Download: ML23108A082 (1)

Text

Constellation. Three Mile Island Nuclear Station 2625 River RD Middletown, PA 17057 TMl-23-008 April 18, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility 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:

2022 Annual Radiological Environmental Operating Report In accordance with TMl-1 Decommissioning Quality Assurance Program Section E.7.2 and TMl-2 Technical Specification 6.8.1.2, enclosed is the Annual Radiological Environmental Operating Report covering the time period for January 1 through December 31, 2022, 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.

Trevor L. Orth Site Decommissioning Director Three Mile Island Nuclear Station, Unit 1

Attachment:

Three Mile Island 2022 Annual Radiological Environmental Operating Report cc: w/ Attachment Regional Administrator - NRC Region I NRC Project Manager, NMSS - Three Mile Island, Unit 1 and Unit 2 David Saracco - Commonwealth of Pennsylvania - Bureau of Radiation Protection T.R. Devik - TMl-2 Solutions, LLC

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 2022 Prepared By Teledyne Brown Engineering Environmental Services Three Mile Island Nuclear Station Middletown, PA 17057 April 2023

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 ...................................................................................................... 4 A. Sample Collection................................................................................................ 4 B. Sample Analysis .................................................................................................. 6 C. Data Interpretation............................................................................................... 6 D. Program Exceptions ............................................................................................ 7 E. Program Changes ............................................................................................... 8 IV. Results and Discussion ................................................................................................. 9 A. Aquatic Environment ........................................................................................... 9

1. Surface Water ........................................................................................... 9

2. Drinking Water .......................................................................................... 9

3. Effluent Water ......................................................................................... 10

4. Storm Water............................................................................................ 11

5. Ground Water ......................................................................................... 11

6. Fish ......................................................................................................... 11

7. Sediment................................................................................................. 11 B. Atmospheric Environment ................................................................................. 11

1. Airborne Particulates .............................................................................. 11

a. Air Particulates............................................................................. 11

b. Airborne Iodine ............................................................................ 12

2. Terrestrial ................................................................................................ 12

a. Milk .............................................................................................. 12

b. Food Products ............................................................................. 13 C. Ambient Gamma Radiation ............................................................................... 13 D. Land Use Survey............................................................................................... 14 E. Radiological Impact of TMINS Operations ........................................................ 15 F. Errata Data ........................................................................................................ 21 G. Summary of Results - Inter-laboratory Comparison Program .......................... 21 V. References ................................................................................................................... 24 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, 2022 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, 2022 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2022 Figures Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2022 Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2022 Figure B-3 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2022 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, 2022 Table C-I.2 Concentrations of I-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-I.3 Concentrations of Gamma-Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 ii

Table C-II.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-II.2 Concentrations of I-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-II.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-II.4 Concentrations of Gamma-Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 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, 2022 Table C-III.2 Concentrations of Gamma-Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-IV.1 Concentrations of Strontium in Predator and Bottom Feeder (Fish)

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 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, 2022 Table C-V.1 Concentrations of Gamma-Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 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, 2022 Table C-VI.3 Concentrations of Gamma-Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-VII.1 Concentrations of I-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-VIII.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-VIII.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-VIII.3 Concentrations of Gamma-Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table C-IX.1 Concentrations of Strontium and Gamma-Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 iii

Table C-X.1 Quarterly OSLD Results for Three Mile Island Nuclear Station, 2022 Table C-X.2 Mean Quarterly OSLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2022 Table C-X.3 Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2022 Figures Figure C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2022 Figure C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2022 Figure C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2022 Figure C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2022 Figure C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2022 Figure C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2022 Figure C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2022 Figure C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2022 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, 2022 Table D-I.2 Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table D-I.3 Concentrations of Iodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table D-I.4 Concentrations of Gamma-Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table D-II.1 Concentrations of Strontium and Gamma-Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table D-III.1 Concentrations of Gamma-Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 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, 2022 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, 2022 Table D-V.2 Concentrations of Gamma-Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 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, 2022 Figures Figure D-1 Monthly Gross Beta Concentrations in Drinking Water Samples Collected from TMINS Location Q9-1Q, 2022 Figure D-2 Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2022 Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2022 Table E-2 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2022 Table E-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2022 Table E-4 Analytics Environmental Radioactivity Cross Check Program Constellation Energy Group, 2022 Table E-5 ERA Environmental Radioactivity Cross Check Program Constellation Energy Group, 2022 Table E-6 DOEs Mixed Analyte Performance Evaluation Program (MAPEP)

GEL Laboratories, Inc., 2022 Table E-7 ERA Environmental Radioactivity Cross Check Program GEL Laboratories, Inc., 2022 Table E-8 Analytics Environmental Radioactivity Cross Check Program GEL Laboratories, Inc., 2022 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 Constellation covers the period 1 January 2022 through 31 December 2022. During that time period, 1,645 analyses were performed on 1,311 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 surface water and effluent water sample 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 or 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, Sr-89 or Sr-90 activities were detected. Occasionally Sr-90 activity may be detected and 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. 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, Constellation (formerly Exelon) changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and ThermoLumin-escent Dosimetry (TLD) were discontinued. This change resulted in a slight 1

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 2022 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 2022 did not have any adverse effects on the health of the public or on the environment.

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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 Constellation Energy Company (formerly Exelon) and became operational in 1974.

TMI-2 is operated and owned by TMI-2 Solutions, LLC. 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 Energy Solutions under contract with TMI-2 Solutions. LLC.

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 Constellation Energy Group (CEG)/GEL Laboratories on samples collected during the period 1 January 2022 through 31 December 2022.

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.

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III. Program Description A. Sample Collection Samples for the TMINS REMP were collected for Constellation by Constellation Energy Group (CEG) 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 2022. 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 four locations (F4-1, G2-1, J18-1 and P4-1) from March through November, and monthly from December through February. A single sample was collected in January from control location K15-3. This control location 4

was replaced with J18-1 in March. 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 September 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. Three different kinds of vegetation samples and nine 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, Constellation 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 22 locations (A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, H1-3, J1-4, J1-3, K1-4, K1-5, 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, H1-3, H3-1, H5-1, H8-1, J1-1, J1-4, J3-1, J5-1, J7-1, K1-5, 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);

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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 CEG/GEL to analyze the environmental samples for radioactivity for the TMINS REMP in 2022. 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.

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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. In order to meet MDC requirements, I-131 is prepped and analyzed by a different methodology than gamma spectroscopy.

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 2022, the TMINS REMP had a sample recovery rate of >99%. Issue Reports (IR) were initiated to document significant exceptions and missing samples. All exceptions are listed below:

Water Q9-1 (Surface Water and Drinking Water)

For the sampling periods 01/01/22 - 04/02/22 and 04/02/22 - 04/23/22, composite samplers were not set back up for collection due to no access to plant for visitors because of COVID. Weekly grab samples were collected by a plant worker at both locations and used to make a monthly composite.

Composite samplers were set up on 04/23/22 and routine compositing continued from that date. (IRs 4499010 and 4517062) 7

Milk (P4-1)

On 08/03/22, TMI REMP biweekly collection efforts for the P4-1 milk farm did not have samples available due to farmer selling his herd. No samplers were available at the location for the collection. The samples will not be available for the near future (period 09/03/22 - 12/31/22).

(IR 4514765)

Dosimetry (E1-2)

During the routine TMI air sampling tour for 09/01/22, the CGS the field technician arrived at the TMI E1-2 sample station for air collection and found the two main dosimeters of legal record plus the QA dosimeter for the REMP program were missing. The field tech did a complete sweep of the area, but nothing was found. The previous AR for lost samples at the site are 04394059 and 04466619. The missing dosimeter numbers are EX000601061, EX00082424R and EX00081796B. The dosimeters were replaced. (IR 4520477)

Air Samplers

1. G2-1 (Sample period 06/11/22 - 06/16/22)

Upon arrival at the G2-1 air sampler station on 06/16/22 for TMI air sample collection in support of the REMP program, the field tech found that the pump for G2-1 was not functioning as expected. Although running, vacuum was much higher than normal. The field tech diagnosed the issue to an Internal issue with the air pump. Suspected sample loss due to the issue. (IR 4506053)

2. M2-1 (Sample period 10/01/22 - 10/06/22)

Upon arrival at the M2-1 air sampler station on 10/06/22 for TMI air sample collection in support of the REMP program, the field tech found that the AP filter for M2-1 had developed a hole in the sample.

Suspected sample loss due to the weather. (IR 4527418)

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 indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

E. Program Changes OSLD K1-5 was added at the site boundary and OSLDs H1-3 and J1-4 were added as closest to the ISFSI pad.

There were no other changes to the program in 2022.

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IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken weekly from a continuous sampler at one location (J1-2) and weekly grab samples from two locations (Q9-1 and 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 4 of 12 samples at location J1-2, which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 741 to 1,070 pCi/L, well below any regulatory limits. 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.

(Figures C-1 and C-2, Appendix C)

Iodine Monthly samples were taken from location A3-2 and analyzed for I-131. 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. I-131 activity was not detected in any sample. (Table C-I.2, Appendix C).

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 13 of 36 samples. The concentrations ranged from 1.8 to 4.4 pCi/L. Concentrations detected were consistent with those detected in previous years. (Figure C-3, Appendix C) 9

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

(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 not detected in any sample.

(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 7 of 12 samples. The concentrations ranged from 2.1 to 3.8 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 4 of 12 samples. The concentrations ranged from 2,700 to 3,610 pCi/L. Concentrations detected were consistent with those detected in previous years.

(Table C-III.1 & 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 <4.7 pCi/L for Sr-89 and at <0.9 pCi/L for Sr-90. (Table C-III.1, Appendix C)

Gamma Spectrometry Samples were analyzed for gamma-emitting nuclides. All nuclides were less than the MDC. (Table C-III.2, Appendix C) 10

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 <4.6 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 2,267 to 3,658 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 804 to 13,070 pCi/kg dry. No fission or activation products were detected. (Figure C-5 & 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.

11

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 6 to 29E-3 pCi/m3 with a mean of 16E-3 pCi/m3. The results from the intermediate offsite locations (Group II) ranged from 7 to 36E-3 pCi/m3 with a mean of 16E-3 pCi/m3. The results from the Control location (Group III) ranged from 8 to 32E-3 pCi/m3 with a mean of 17E-3 pCi/m3. Comparison of the 2022 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 2022 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 41 to 86E-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 three locations (J18-1, F4-1 and G2-1) biweekly March through November and monthly December through February. Samples were collected from one location (P4-1) monthly January-February and biweekly March through July. 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) 12

Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90. No Sr-89 or Sr-90 activity was detected. (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 806 to 1,493 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 Six food product samples were analyzed for concentrations of Sr-90. No Sr-90 activity was detected in any sample.

(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 25 of 48 samples with concentrations ranging from 313 to 4,583 pCi/kg. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 1,867 to 6,698 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 Dosimeters (OSLD). Ninety-three OSLD locations were established around the site. Results of OSLD measurements are listed in Tables C-X.1 to C-X.3, Appendix C.

The nearest resident to the Independent Spent Fuel Storage Installation (ISFSI) saw no detectable gamma radiation levels above background due to ISFSI. Therefore, ISFSI operations did not have an impact to members of the public in 2022.

All of the OSLD measurements were below 37 mR/quarter, with a range of 12.5 to 36.6 mR/standard quarter. A comparison of the Site Boundary and 13

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. Independent Spent Fuel Storage Instillation (ISFSI)

ISFSI operations began in October 2021. Forty-two casks and 1 GTCC container were added to the GCE ISFSI pad in 2022 utilizing the NAC MAGNASTOR System. Site boundary Environmental OSLD's, which measure gamma radiation closest to ISFSI are C1-2, D1-1, E1-4, F1-2, G1-3, K1-3, K1-5, L1-1, M1-1 and N1-3. OSLD K1-5 was added at the site boundary and OSLD's H1-3 and J1-4 were added as closest to the ISFSI pad. There was no radiation detected above background. Therefore, there was no direct radiation attributed to TMI from ISFSI operations to any resident.

E. Land Use Survey A Land Use Survey conducted in the 2022 fall growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Constellation Energy Group (CEG) for compliance with TMI-2 Tech Spec 6.7.2.b and Section 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 Sector Milk Farm 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 0.5 3.2 G SE 0.7 0.6 1.4 H SSE 0.7 0.8 -

J S 2.2 2.5 -

K SSW 0.6 1.6 4.9 L SW 0.5 1.7 -

M WSW 1.2 1.3 -

N W 1.2 1.3 -

P WNW 1.1 1.5 3.7 Q NW 1.1 1.2 -

R NNW 1.1 2.4 -

14

F. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2022 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2022 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 0.009 mrem. This dose is equivalent to 0.003% 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 15

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 2022 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 2022 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 2022 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.009 mrem.

This dose is equivalent to 0.003% percent of the dose that an individual living in the TMI area receives each year from natural background radiation (311 mrem).

16

The low doses calculated for 2022 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).

In conclusion, radioactive materials related to 2022 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 2022 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 2022 did not have any adverse effects on the health of the public or on the environment.

17

TABLE 1 Calculated Maximum Hypothetical Doses to an Individual from 2022 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 5.66E-03 3.86E-04 in Liquid Releases 10 any organ 6.81E-03 6.14E-04 From Radionuclides in 5 total body, or 0* 0*

Airborne Releases (Noble Gases) 15 skin 0* 0*

From Radionuclides in Airborne 15 any organ 2.57E-03 1.03E-04 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 0.006 25 total body 0.010 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 2022 TMINS operations was 0.629 mrem/yr based on calculations from ANSI/HI Standard N13.37.

18

TABLE 2 Calculated Whole Body Doses to the Maximum Individual from 2022 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 5.66E-03 3.86E-04 From Radionuclides in Airborne Releases 0* 0*

(Noble Gases)

From Radionuclides In Airborne 2.57E-03 1.03E-04 Releases (Iodines, Tritium and Particulates)

• No noble gases were released from TMI-1 or TMI-2.

Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations: 0.009 mrem/yr Individual Whole Body Dose Due to Natural Background Radiation (1) 311 mrem/yr (1) NCRP 160 - (2009) 19

Figure 1 20

G. Errata Data There was no errata data for 2022.

H. 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 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)

• 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, 142 out of 150 analyses performed met the specified acceptance criteria. Eight analyses did not meet the specified acceptance criteria and were addressed through the TBE Corrective Action Program. A summary is found below:

21

NOTE: Two analyses (soil for Tc-99 and U-238) that did not meet acceptance criteria was performed for TBE information and is not on the list of required ICP analyses.

1. The Analytics March 2022 AP Ce-141 result was evaluated as Not Acceptable. The reported value for Ce-141 was 60.9 pCi and the known result was 42.0 pCi/L (1.45 ratio of reported result vs. known; TBEs internal acceptance range is 0.70 - 1.30). This sample was used as the workgroup duplicate with a result of 45.7 (109% of known) and was also counted on a different detector with a result of 50.9 (121% of known).

This was TBEs first failure for AP Ce-141. (NCR 22-04)

2. The MAPEP February 2022 Urine U-234 & U-238 results were evaluated as Not Acceptable. TBEs reported values of 0.142 and 0.0254 were above the known upper ranges of 0.0096 and 0.0134 respectively for U-234 and U-238. These spiked values were below TBEs typical MDC for urine client samples. The samples were re-prepped using a larger sample aliquot and counted for 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> as opposed to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The recount results were 0.00732 for U-234 and 0.0119 for U-238 (both within acceptable range). MAPEP urine samples will be flagged to use a larger sample aliquot and counting time than typical client samples.

MAPEP did not include any urine cross-check samples in August. (NCR 22-05)

3. The ERA MRAD September 2022 AP Pu-238 was evaluated as Not Acceptable. The reported value was 38.8 pCi and the known result was 29.9 (acceptance range 22.6 - 36.7). The AP filter was cut in half prior to digestion (shared with Fe-55) but should have been complete digested together and aliquotted afterwards like typical client samples. This is the first failure for AP Pu-238. (NCR 22-19)

4. The ERA October 2022 water Uranium result was evaluated as Not Acceptable. The reported value was 10.54 pCi/L and the known was 8.53 (acceptance range 6.60 - 9.88) or 124% of the known (acceptable for TBE QC). The 2-sigma error was 3.2, placing the reported result well within the acceptable range. This sample was used as the workgroup duplicate with a result of 8.2 +/- 2.9 pCi/L (also within the acceptable range). All other QA was reviewed with no anomalies. (NCR 22-20)

5. The Analytics AP Co-60 result was evaluated as Not Acceptable. The reported value was 207 pCi and the known was 147 (141% of the known). TBEs internal QC acceptance is 70 - 130%. All QA was reviewed with no anomalies. This sample was used as the workgroup duplicate and counted on a different detector with a result of 167 pCi (114% of the known). This is the first failure for AP Co average result ratio compared to the known is 109%. (NCR 22-21) 22

6. The MAPEP August 2022 water Tc-99 result was evaluated as Not Acceptable. The reported value was 1.86 +/- 0.414 Bq/L for this false positive test. The evaluation of the submitted result to the 3 times the uncertainty indicated a slight positive. This sample was used as the workgroup duplicate with a result of 0.88 +/- 0.374 Bq/L. All QC was reviewed, and no anomalies found. This is the first unacceptable since the resumption of reporting water Tc-99 for the 3rd quarter of 2020. TBE to known ratios have ranged from 94-109% during this time.

(NCR 22-22)

For the secondary QC samples, the CGS laboratory analyzed gross beta, gramma, and I-131 for TMINS. For the CGS Laboratory, 91 out of 92 analyses performed met the specified NRC Resolution Test Criteria (NRC Inspection Manual, Inspection Procedure 84750, March 15, 1994).

Laboratory results are reported with 2-sigma uncertainty. When evaluating with the NRC Resolution Test, a 1-sigma uncertainty is used to determine Pass or Fail. Any failures are addressed through the Corrective Action Program. A summary of these failures are described below:

1. The ERA 2nd quarter 2022 water reported result of 35.8 pCi/L for gross beta passed on the low end of the vendor acceptance criteria but failed NRC Resolution Test Criteria. Low recovery of activity was likely due to an ineffective residue correction factor that undercompensates for the significant residue weight present in the study. This low value and a low uncertainty in turn resulted in the failure. A set of 3rd party NIST-traceable standards has been procured to build a residue correction curve for more accurate results going forward.

For the secondary QC samples, GEL laboratory only analyzed H-3 and Sr-89/90 nuclides for the TMINS REMP. Gross alpha & gamma nuclides were also analyzed for the TMINS RGPP. For these nuclides, 81 out of 82 cross-check samples met the specified acceptance criteria. Failures were addressed through GELs Corrective Action Program. A summary of these failures are described below:

1. The MAPEP 4th quarter vegetation reported result of 1.12 Bq/kg for Sr-90 was evaluated as Not Acceptable. The data for the Sr-90 analysis was reviewed and no anomalies were noted. The QC in the analysis batch met acceptance criteria. The lab evaluated both the prep and instrument processes for possible areas of contamination that contributed to the positive bias. A definitive source was not determined.

2. The ERA 4th quarter MRAD water reported result of 283 pCi/L for Sr-90 was evaluated as Not Acceptable. For this same study, the vegetation result of 4,560 pCi/kg was evaluated as Not Acceptable. The known result for the water was 224 pCi/L with an acceptance range of 161 -

277 pCi/L. The known result for the vegetation was 2,960 pCi/kg with an acceptance range of 1,670 - 3,860 pCi/kg. An investigation 23

determined that the lab met all quality control criteria specified in each method and all internal procedures and policies were performed as required. The lab will continue to monitor the recoveries of these parameters to ensure that there are no continued issues. During the same reporting period, the lab successfully passed Sr-90 water samples for MAPEP. Samples for both studies were prepared and analyzed by the same processes and procedures.

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. Constellation. 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 24

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank 25

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2022 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2022 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) 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 864 <LLD 864 J1-2 INDICATOR 0 (PCI/LITER) (4/12) (4/12) DOWNSTREAM OF TMINS LIQUID DISCHARGE OUTFALL 741 - 1070 741 - 1070 0.5 MILES S OF SITE I-131 12 1 <LLD <LLD <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 ZN-65 30 <LLD <LLD - 0 NB-95 15 <LLD <LLD - 0 ZR-95 30 <LLD <LLD - 0 CS-134 15 <LLD <LLD - 0 A-1 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 2.0 3.4 G15-2 INDICATOR 0 (PCI/LITER) (10/24) (3/12) (7/12) WRIGHTSVILLE WATER PLANT 1.8 - 4.4 1.8 - 2.1 2.1 - 4.4 13.3 MILES SE OF SITE I-131 36 1 <LLD <LLD - 0 H-3 36 2000 <LLD <LLD - 0 GAMMA 36 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 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, 2022 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2022 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) 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 GR-B 12 4 3.1 NA 3.1 K1-1 INDICATOR 0 (PCI/LITER) (7/12) (7/12) RML-7 MAIN STATION DISCHARGE BLDG 2.1 - 3.8 2.1 - 3.8 0.2 MILES ONSITE I-131 (LOW LVL) 12 1 <LLD NA - 0 H-3 12 2000 3205 NA 3205 K1-1 INDICATOR 0 (4/12) (4/12) RML-7 MAIN STATION DISCHARGE BLDG 2700 - 3610 2700 - 3610 0.2 MILES ONSITE SR-89 2 5 <LLD NA - 0 SR-90 2 2 <LLD NA - 0 GAMMA 12 MN-54 15 <LLD NA - 0 A-2 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 LA-140 15 <LLD NA - 0 BOTTOM FEEDER SR-90 4 10 <LLD <LLD - 0 (PCI/KGWET)

GAMMA 4 K-40 NA 3842 3245 4148 INDB INDICATOR 0 (2/2) (2/2) (1/1) YORK HAVEN DAM 3535 - 4148 2832 - 3658 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 (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, 2022 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2022 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) 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 SR-90 4 10 <LLD <LLD - 0 (PCI/KGWET) GAMMA 4 K-40 NA 2762 3151.5 3151.5 BKGP CONTROL 0 (2/2) (2/2) (2/2) CITY ISLAND 2267 - 3257 3026 - 3277 3026 - 3277 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 SEDIMENT GAMMA 6 (PCI/KG DRY) K-40 NA 10806 8809 12630 J2-1 INDICATOR 0 A-3 (4/4) (2/2) (2/2) YORK HAVEN DAM 8847 - 13070 8043 - 9575 12190 - 13070 1.5 MILES S 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 364 10 16 17 17 Q15-1 CONTROL 0 (E-3 PCI/CU.METER) (310/312) (52/52) (52/52) WEST FAIRVIEW FIRE DEPT SOCIAL HALL 6 - 36 8 - 32 8 - 32 13.4 MILES NW OF SITE GAMMA 28 BE-7 NA 67 68 72 H3-1 INDICATOR 0 (24/24) (4/4) (4/4) FALMOUTH-COLLINS SUBSTATION 41 - 86 55 - 81 66 - 86 2.2 MILES SSE 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 (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, 2022 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2022 INDICATOR CONTROL MEDIUM OR REQUIRED LOCATIONS LOCATION LOCATION WITH HIGHEST ANNUAL MEAN (M) 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 IODINE GAMMA 364 (E-3 PCI/CU.METER) I-131 70 <LLD <LLD - 0 MILK I-131 78 1 <LLD <LLD - 0 (PCI/LITER)

SR-89 15 5 <LLD <LLD - 0 SR-90 15 2 <LLD <LLD - 0 GAMMA 78 K-40 NA 1251 1213 1291 P4-1 INDICATOR 0 (56/56) (22/22) (12/12) FISHER FARM 806 - 1493 828 - 1483 1095 - 1432 3.6 MILES WNW OF SITE CS-134 15 <LLD <LLD - 0 CS-137 18 <LLD <LLD - 0 A-4 BA-140 60 <LLD <LLD - 0 LA-140 15 <LLD <LLD - 0 VEGETATION SR-90 6 10 <LLD <LLD - 0 (PCI/KG WET)

GAMMA 48 BE-7 NA 1239 912 1639 H1-2 INDICATOR 0 (16/30) (9/18) (10/12) RED HILL MARKET 313 - 4583 383 - 1318 464 - 4583 1.0 MILES SSE OF SITE K-40 NA 3738 4017 4450 H1-2 INDICATOR 0 (30/30) (18/18) (12/12) RED HILL MARKET 1867 - 6017 2245 - 6698 3017 - 6017 1.0 MILES SSE OF SITE I-131 60 <LLD <LLD - 0 CS-134 60 <LLD <LLD - 0 CS-137 80 <LLD <LLD - 0 DIRECT RADIATION OSLD - QUARTERLY 371 NA 18.3 18.9 31.9 J1-4 INDICATOR 0 (MILLIREM/STD.MO.) (327/327) (44/44) (4/4) TMI 12.5 - 36.6 15.2 - 29.9 23.3 - 35.2 0.1 MILES S 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 X/YY/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, 2022 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 1.2 33° NNE of site at 2389 Sunset Drive, Middletown 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 & 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 N. Market Street (Route 230) and Zeager Road ID E7-1 3 6.7 88° E of site along Hummelstown Street, Elizabethtown ID F1-2 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 ESE of site along 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 G1-2 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 B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2022 Sample Station Map Distance Medium Code Number (miles) Azimuth Description 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 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 ID H1-3 1 0.1 82° SSE of site, TMI 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 Rds, 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 ID J1-4 1 0.1 307° S of site, 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 M J18-1 3 17.6 188° S of site at Stump Dairy on Arnold Road, York 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 K1-5 1 0.1 277° SSW of site, TNI 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 Rd and Route 295, Zions View ID K15-1 3 12.8 203° SSW of site behind McDonalds & 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 B-3

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2022 Sample Station Map Distance Medium Code Number (miles) Azimuth Description 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 Bldg 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 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 Rd (Route 262) and Beinhower Rd 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 1.7 334° 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, 2022 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Monthly composite CY-ES-240 CGS Collection of Surface-Surface Gamma from a continuous Drinking-Effluent Water Samples for 2 gallon TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Water Spectroscopy water compositor Radiological Analysis (TMI)

Monthly composite CY-ES-240 CGS Collection of Surface-Surface TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Various Gross Beta from a continuous Drinking-Effluent Water Samples for 2 gallon Water Matrices water compositor Radiological Analysis (TMI)

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

Monthly composite CY-ES-240 CGS Collection of Surface- TBE, TBE-2012 Radioiodine in Various Matrices Surface B-5 Iodine-131 from a continuous Drinking-Effluent Water Samples for 2 gallon Water CGS, CY-ES-205 Operation of HPGE Gamma Detectors water compositor Radiological Analysis (TMI)

TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Various Monthly composite CY-ES-240 CGS Collection of Surface- Matrices Drinking Gross Beta from a continuous Drinking-Effluent Water Samples for 2 gallon Water CGS, CY-ES-206 Operation of the Tennelec S5E Proportional water compositor Radiological Analysis (TMI)

Counter Monthly composite CY-ES-240 CGS Collection of Surface- TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Drinking Gamma from a continuous Drinking-Effluent Water Samples for 2 gallon Water Spectroscopy EIS, CY-ES-205 Operation of HPGE Gamma Detectors water compositor Radiological Analysis (TMI)

TBE, TBE-2012 Radioiodine in Various Matrices Monthly composite CY-ES-240 CGS Collection of Surface-Drinking Iodine-131 from a continuous Drinking-Effluent Water Samples for 2 gallon CGS, CY-ES-204 Sample Preparation for Gamma Analysis Water water compositor Radiological Analysis (TMI)

CGS, CY-ES-205 Operation of HPGE Gamma Detectors Monthly composite CY-ES-240 CGS Collection of Surface- TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Drinking Scintillation Tritium from a continuous Drinking-Effluent Water Samples for 2 gallon Water water compositor Radiological Analysis (TMI) GEL, EPA 906.0 Mod, for Tritium analysis by Liquid scintillation Monthly composite CY-ES-240 CGS Collection of Surface-Effluent 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)

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2022 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Monthly composite CY-ES-240 CGS Collection of Surface-Effluent Gamma TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis from a continuous Drinking-Effluent Water Samples for 2 gallon Water Spectroscopy water compositor Radiological Analysis (TMI)

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

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

B-6 CY-ES-240 CGS Collection of Surface-Quarterly composite of TBE, TBE-2011 Tritium Analysis in Drinking Water by Liquid Storm Water Tritium Drinking-Effluent Water Samples for 1 gallon monthly grab samples Scintillation Radiological Analysis (TMI)

Semi-annual samples Gamma collected via ER-TMI-13 Collection of fish samples for 1000 grams TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Fish Spectroscopy electroshocking or radiological analysis (TMINS) (wet) CGS, CY-ES-205 Operation of HPGE Gamma Detectors other techniques Semi-annual samples collected via ER-TMI-13 Collection of fish samples for 1000 grams TBE, TBE-2018 Radiostrontium Analysis by Chemical Separation Fish Strontium-90 electroshocking or radiological analysis (TMINS) (wet) GEL, EPA 905.0 Mod/DOE RP501 Rev. 1 Mod other techniques Gamma Semi-annual grab ER-TMI-03 Collection of sediment 500 grams TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Sediment Spectroscopy samples samples for radiological analysis (TMINS) (dry) CGS, CY-ES-205 Operation of HGPE Gamma Detectors TBE, TBE-2023 Compositing of Samples 13 filters TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Air Gamma Quarterly composite of CY-ES-204 Sample Preparation for (approx. 3600 Particulates Spectroscopy each station CGS, CY-ES-205 Operation of HPGE Gamma Detectors Gamma and Beta Counting cubic meters)

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2022 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium One-week composite 1 filter TBE, TBE-2008 Gross Alpha and/or Gross Beta Activity in Various Air of continuous air CY-ES-237 Collection of Air Iodine & Air (approx. 280 Matrices Gross Beta Particulates sampling through glass Particulate for Radiological Analysis (TMI) cubic meters CGS,CY-ES-206 Operation of the Tennelec S5E Proportional fiber filter paper weekly) Counter One-week composite 1 filter Gamma of continuous air CY-ES-237 Collection of Air Iodine & Air (approx. 280 TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Air Iodine Spectroscopy sampling through Particulate for Radiological Analysis (TMI) cubic meters CGS, CY-ES-205 Operation of HGPE Gamma Detectors charcoal filter weekly)

Bi-weekly grab sample when cows CY-ES-238 Sample Collection for TBE, TBE-2012 Radioiodine in Various Matrices Milk I-131 2 gallon are on pasture. Radiological Analysis - Milk (TMI) CGS, CY-ES-205 Operation of HGPE Gamma Detectors Monthly all other times B-7 Quarterly composite of TBE, TBE-2023 Compositing of Samples TBE, TBE-2019 Radiostrontium Analysis by Ion Exchange Milk Sr-89/90 bi-weekly and monthly CY-ES-238 Sample Collection for 2 gallon GEL, EPA 905.0 Mod/DOE RP501 Rev. 1 Mod grab samples Radiological Analysis - Milk (TMI)

Bi-weekly grab Gamma sample when cows CY-ES-238 Sample Collection for TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Milk 2 gallon Spectroscopy are on pasture. Radiological Analysis - Milk (TMI) CGS, CY-ES-205 Operation of HGPE Gamma Detectors Monthly all other times Gamma Monthly and annual CY-ES-241 Sample Collection for Gamma TBE, TBE-2007 Gamma-Emitting Radioisotope Analysis Vegetation 1000 grams Spectroscopy grab sample Counting - Vegetation (TMI) CGS, CY-ES-205 Operation of HGPE Gamma Detectors Strontium- Monthly and annual CY-ES-241 Sample Collection for Gamma TBE, TBE-2018 Radiostrontium Analysis by Chemical Separation Vegetation 1000 grams 89/90 grab sample Counting - Vegetation (TMI) GEL, EPA 905.0 Mod/DOE RP501 Rev. 1 Mod Optically Quarterly OSLDs Stimulated comprised of two CY-ES-239 Collection of OSLD samples 2 badges with OSLD Landauer Incorporated Luminescence Al2O3:C Landauer for radiological analysis (TMINS) 3 dosimeters Dosimetry Incorporated elements.

Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2022 B-8

Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2022 B-9

Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2022 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, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD J1-2 Q9-1 12/29/21 - 02/03/22 < 195 < 199 02/03/22 - 03/03/22 < 186 < 195 03/03/22 - 03/30/22 < 194 < 194 03/30/22 - 04/27/22 < 163 < 163 04/27/22 - 06/02/22 < 192 < 191 06/02/22 - 06/30/22 < 192 < 194 06/30/22 - 07/27/22 894 +/- 164 < 189 07/27/22 - 09/01/22 741 +/- 154 < 179 09/01/22 - 09/29/22 < 172 < 192 09/29/22 - 11/03/22 752 +/- 152 < 168 11/03/22 - 11/30/22 < 189 < 190 11/30/22 - 12/29/22 1070 +/- 180 < 189 MEAN +/- 2 STD DEV 864 +/- 308 -

Table C-I.2 CONCENTRATIONS OF I-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD A3-2 12/29/21 - 02/03/22 < 0.8 02/03/22 - 03/03/22 < 0.6 03/03/22 - 03/30/22 < 0.9 03/30/22 - 04/27/22 < 0.8 04/27/22 - 06/02/22 < 1.0 06/02/22 - 06/30/22 < 0.9 06/30/22 - 07/27/22 < 0.8 07/27/22 - 09/01/22 < 0.9 09/01/22 - 09/29/22 < 0.8 09/29/22 - 11/03/22 < 0.9 11/03/22 - 11/30/22 < 0.7 11/30/22 - 12/29/22 < 0.7 MEAN +/- 2 STD DEV -

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, 2022 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 12/29/21 - 02/03/22 < 6 < 7 < 12 < 7 < 12 < 7 < 11 < 7 < 6 < 26 < 10 02/03/22 - 03/03/22 < 8 < 9 < 14 < 8 < 15 < 6 < 10 < 8 < 8 < 28 < 8 03/03/22 - 03/30/22 < 8 < 6 < 10 < 8 < 16 < 5 < 11 < 6 < 6 < 27 < 10 03/30/22 - 04/27/22 < 6 < 5 < 11 < 6 < 11 < 5 < 9 < 6 < 5 < 23 < 8 04/27/22 - 06/02/22 < 5 < 6 < 13 < 8 < 11 < 5 < 11 < 5 < 5 < 24 < 5 06/02/22 - 06/30/22 < 6 < 7 < 16 < 6 < 14 < 6 < 10 < 5 < 7 < 38 < 12 06/30/22 - 07/27/22 < 6 < 5 < 13 < 7 < 13 < 6 < 10 < 7 < 7 < 24 < 8 07/27/22 - 09/01/22 < 6 < 5 < 14 < 6 < 11 < 6 < 10 < 6 < 7 < 29 < 9 09/01/22 - 09/29/22 < 7 < 7 < 16 < 5 < 16 < 8 < 13 < 5 < 7 < 27 < 8 09/29/22 - 11/03/22 < 6 < 5 < 13 < 8 < 11 < 7 < 9 < 7 < 6 < 27 < 7 11/03/22 - 11/30/22 < 6 < 5 < 13 < 6 < 17 < 7 < 10 < 7 < 7 < 28 < 9 11/30/22 - 12/29/22 < 7 < 7 < 11 < 5 < 13 < 7 < 13 < 6 < 8 < 33 < 9 C-2 MEAN - - - - - - - - - - -

Q9-1 12/29/21 - 02/03/22 < 7 < 6 < 16 < 6 < 11 < 7 < 10 < 9 < 8 < 35 < 9 02/03/22 - 03/03/22 < 6 < 6 < 13 < 7 < 11 < 4 < 11 < 8 < 7 < 23 < 7 03/03/22 - 03/30/22 < 5 < 6 < 11 < 6 < 12 < 7 < 10 < 7 < 6 < 26 < 9 03/30/22 - 04/27/22 < 6 < 6 < 11 < 6 < 12 < 6 < 10 < 5 < 6 < 28 < 6 04/27/22 - 06/02/22 < 5 < 5 < 7 < 8 < 14 < 7 < 12 < 8 < 6 < 22 < 9 06/02/22 - 06/30/22 < 6 < 7 < 13 < 7 < 14 < 7 < 10 < 6 < 6 < 28 < 9 06/30/22 - 07/27/22 < 6 < 5 < 12 < 6 < 14 < 6 < 13 < 7 < 7 < 32 < 9 07/27/22 - 09/01/22 < 5 < 7 < 11 < 6 < 10 < 5 < 9 < 6 < 6 < 30 < 12 09/01/22 - 09/29/22 < 7 < 8 < 14 < 10 < 13 < 8 < 12 < 6 < 8 < 29 < 14 09/29/22 - 11/03/22 < 7 < 8 < 13 < 4 < 16 < 7 < 10 < 10 < 10 < 26 < 7 11/03/22 - 11/30/22 < 7 < 6 < 13 < 9 < 12 < 7 < 13 < 7 < 7 < 27 < 11 11/30/22 - 12/29/22 < 8 < 7 < 14 < 6 < 14 < 6 < 9 < 7 < 6 < 35 < 13 MEAN - - - - - - - - - - -

Table C-II.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 12/29/21 - 02/03/22 < 2.1 < 2.0 < 1.9 02/03/22 - 03/03/22 < 2.6 < 2.4 < 2.3 03/03/22 - 03/30/22 4.2 +/- 1.5 2.3 +/- 1.3 < 1.8 03/30/22 - 04/27/22 < 2.3 < 2.1 < 2.1 04/27/22 - 06/02/22 2.1 +/- 1.4 < 2.0 < 1.9 06/02/22 - 06/30/22 < 2.4 < 2.3 < 2.3 06/30/22 - 07/27/22 3.9 +/- 1.6 < 2.1 2.1 +/- 1.4 07/27/22 - 09/01/22 4.4 +/- 2.1 < 2.8 < 2.7 09/01/22 - 09/29/22 < 2.8 < 2.6 < 2.4 09/29/22 - 11/03/22 2.8 +/- 1.7 < 2.3 < 2.3 11/03/22 - 11/30/22 3.9 +/- 1.5 3.9 +/- 1.4 1.8 +/- 1.2 11/30/22 - 12/29/22 2.8 +/- 1.4 1.8 +/- 1.2 2.1 +/- 1.2 MEAN +/- 2 STD DEV 3.4 +/- 1.7 2.6 +/- 2.2 2.0 +/- 0.4 Table C-II.2 CONCENTRATIONS OF I-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 12/29/21 - 02/03/22 < 0.8 < 0.7 < 0.8 02/03/22 - 03/03/22 < 0.8 < 0.7 < 0.9 03/03/22 - 03/30/22 < 0.7 < 0.9 < 0.9 03/30/22 - 04/27/22 < 0.9 < 0.8 < 0.9 04/27/22 - 06/02/22 < 0.9 < 1.0 < 0.9 06/02/22 - 06/30/22 < 0.8 < 0.8 < 0.9 06/30/22 - 07/27/22 < 0.9 < 0.9 < 0.9 07/27/22 - 09/01/22 < 0.9 < 0.7 < 0.8 09/01/22 - 09/29/22 < 0.7 < 0.9 < 0.7 09/29/22 - 11/03/22 < 0.9 < 0.8 < 0.9 11/03/22 - 11/30/22 < 0.8 < 0.8 < 0.7 11/30/22 - 12/29/22 < 0.9 < 0.8 < 0.9 MEAN - - -

Table C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 12/29/21 - 02/03/22 < 199 < 199 < 200 02/03/22 - 03/03/22 < 192 < 195 < 194 03/03/22 - 03/30/22 < 186 < 196 < 197 03/30/22 - 04/27/22 < 177 < 198 < 155 04/27/22 - 06/02/22 < 178 < 186 < 188 06/02/22 - 06/30/22 < 177 < 183 < 179 06/30/22 - 07/27/22 < 189 < 189 < 197 07/27/22 - 09/01/22 < 185 < 181 < 176 09/01/22 - 09/29/22 < 187 < 196 < 185 09/29/22 - 11/03/22 < 178 < 176 < 189 11/03/22 - 11/30/22 < 180 < 174 < 199 11/30/22 - 12/29/22 < 171 < 170 < 173 MEAN - - -

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, 2022 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 12/29/21 - 02/03/22 < 7 < 7 < 10 < 8 < 12 < 7 < 11 < 7 < 6 < 29 < 11 02/03/22 - 03/03/22 < 7 < 7 < 13 < 5 < 11 < 6 < 11 < 7 < 8 < 26 < 8 03/03/22 - 03/30/22 < 6 < 6 < 13 < 6 < 12 < 8 < 10 < 7 < 8 < 28 < 11 03/30/22 - 04/27/22 < 4 < 4 < 10 < 4 < 12 < 5 < 9 < 5 < 5 < 25 < 8 04/27/22 - 06/02/22 < 6 < 6 < 12 < 7 < 11 < 7 < 10 < 7 < 6 < 31 < 9 06/02/22 - 06/30/22 < 5 < 7 < 11 < 6 < 11 < 7 < 11 < 7 < 6 < 29 < 9 06/30/22 - 07/27/22 < 5 < 7 < 13 < 9 < 16 < 6 < 13 < 8 < 9 < 27 < 10 07/27/22 - 09/01/22 < 6 < 4 < 15 < 6 < 12 < 5 < 12 < 6 < 5 < 34 < 11 09/01/22 - 09/29/22 < 7 < 6 < 14 < 6 < 12 < 6 < 10 < 9 < 6 < 25 < 12 09/29/22 - 11/03/22 < 7 < 7 < 16 < 7 < 11 < 6 < 11 < 8 < 7 < 28 < 11 11/03/22 - 11/30/22 < 5 < 5 < 11 < 6 < 13 < 6 < 9 < 5 < 6 < 24 < 13 11/30/22 - 12/29/22 < 7 < 6 < 14 < 7 < 16 < 8 < 11 < 8 < 8 < 31 < 10 MEAN - - - - - - - - - - -

G15-3 12/29/21 - 02/03/22 < 8 < 6 < 11 < 6 < 12 < 6 < 9 < 6 < 6 < 24 < 10 02/03/22 - 03/03/22 < 7 < 6 < 12 < 7 < 12 < 7 < 11 < 7 < 6 < 24 < 6 03/03/22 - 03/30/22 < 7 < 6 < 11 < 6 < 13 < 8 < 11 < 7 < 8 < 32 < 10 C-4 03/30/22 - 04/27/22 < 5 < 5 < 8 < 5 < 11 < 6 < 10 < 6 < 5 < 17 < 9 04/27/22 - 06/02/22 < 5 < 8 < 15 < 6 < 15 < 5 < 14 < 7 < 6 < 29 < 9 06/02/22 - 06/30/22 < 5 < 4 < 12 < 5 < 9 < 8 < 10 < 5 < 6 < 32 < 11 06/30/22 - 07/27/22 < 6 < 6 < 16 < 6 < 13 < 6 < 9 < 6 < 7 < 26 < 10 07/27/22 - 09/01/22 < 6 < 5 < 15 < 7 < 13 < 6 < 10 < 7 < 6 < 32 < 11 09/01/22 - 09/29/22 < 7 < 6 < 18 < 6 < 13 < 8 < 14 < 6 < 7 < 30 < 13 09/29/22 - 11/03/22 < 6 < 7 < 15 < 4 < 14 < 8 < 13 < 6 < 8 < 28 < 11 11/03/22 - 11/30/22 < 7 < 7 < 13 < 7 < 13 < 5 < 10 < 8 < 6 < 29 < 8 11/30/22 - 12/29/22 < 6 < 7 < 9 < 6 < 11 < 6 < 12 < 7 < 9 < 29 < 7 MEAN - - - - - - - - - - -

Q9-1 12/29/21 - 02/03/22 < 7 < 7 < 11 < 8 < 12 < 8 < 13 < 8 < 7 < 39 < 12 02/03/22 - 03/03/22 < 7 < 6 < 12 < 8 < 14 < 8 < 10 < 7 < 7 < 30 < 8 03/03/22 - 03/30/22 < 4 < 5 < 9 < 6 < 9 < 6 < 10 < 5 < 5 < 24 < 8 03/30/22 - 04/27/22 < 6 < 5 < 10 < 5 < 7 < 7 < 10 < 5 < 6 < 28 < 8 04/27/22 - 06/02/22 < 7 < 8 < 15 < 7 < 16 < 6 < 13 < 7 < 7 < 27 < 7 06/02/22 - 06/30/22 < 6 < 7 < 12 < 7 < 9 < 6 < 12 < 6 < 6 < 33 < 13 06/30/22 - 07/27/22 < 5 < 6 < 13 < 5 < 11 < 2 < 9 < 5 < 6 < 29 < 14 07/27/22 - 09/01/22 < 6 < 6 < 11 < 6 < 9 < 7 < 8 < 5 < 6 < 35 < 12 09/01/22 - 09/29/22 < 6 < 7 < 11 < 5 < 16 < 8 < 11 < 7 < 6 < 33 < 9 09/29/22 - 11/03/22 < 5 < 6 < 16 < 7 < 15 < 7 < 12 < 7 < 7 < 25 < 9 11/03/22 - 11/30/22 < 3 < 5 < 8 < 4 < 7 < 4 < 6 < 5 < 4 < 20 < 7 11/30/22 - 12/29/22 < 6 < 8 < 15 < 8 < 13 < 7 < 12 < 5 < 7 < 34 < 11 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, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD GR-B I-131 H-3 SR-89 SR-90 K1-1 12/29/21 - 02/03/22 < 2.0 < 0.8 < 199 02/03/22 - 03/03/22 < 2.4 < 0.8 < 190 03/03/22 - 03/30/22 2.4 +/- 1.3 < 0.9 < 197 03/30/22 - 04/27/22 < 2.1 < 0.9 < 162 04/27/22 - 06/02/22 < 2.0 < 0.9 < 191 06/02/22 - 06/30/22 < 2.3 < 0.9 < 182 06/30/22 - 07/27/22 3.7 +/- 1.6 < 0.8 3200 +/- 376 07/27/22 - 09/01/22 3.8 +/- 2.1 < 0.9 3310 +/- 394 12/29/21 - 06/30/22 < 4.1 < 0.7 09/01/22 - 09/29/22 2.9 +/- 1.9 < 0.7 < 188 09/29/22 - 11/03/22 3.4 +/- 1.7 < 1.0 3610 +/- 421 11/03/22 - 11/30/22 3.5 +/- 1.3 < 0.8 < 198 11/30/22 - 12/29/22 2.1 +/- 1.3 < 0.9 2700 +/- 335 06/30/22 - 12/29/22 < 4.7 < 0.9 MEAN +/- 2 STD DEV 3.1 +/- 1.3 - 3205 +/- 757 - -

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, 2022 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 12/29/21 - 02/03/22 < 7 < 8 < 12 < 8 < 12 < 7 < 10 < 8 < 8 < 31 < 12 02/03/22 - 03/03/22 < 6 < 6 < 21 < 8 < 17 < 7 < 14 < 9 < 7 < 33 < 13 03/03/22 - 03/30/22 < 5 < 5 < 13 < 6 < 10 < 5 < 8 < 7 < 7 < 23 < 9 03/30/22 - 04/27/22 < 3 < 3 < 6 < 3 < 8 < 4 < 5 < 4 < 4 < 15 < 5 04/27/22 - 06/02/22 < 7 < 7 < 13 < 7 < 14 < 7 < 13 < 8 < 10 < 30 < 12 06/02/22 - 06/30/22 < 7 < 6 < 11 < 7 < 17 < 8 < 12 < 7 < 7 < 36 < 12 06/30/22 - 07/27/22 < 8 < 7 < 17 < 5 < 13 < 6 < 10 < 9 < 8 < 28 < 7 07/27/22 - 09/01/22 < 4 < 4 < 12 < 6 < 11 < 7 < 13 < 6 < 5 < 30 < 10 09/01/22 - 09/29/22 < 7 < 7 < 16 < 9 < 18 < 11 < 14 < 11 < 10 < 39 < 13 09/29/22 - 11/03/22 < 6 < 6 < 13 < 8 < 15 < 7 < 8 < 5 < 7 < 32 < 11 11/03/22 - 11/30/22 < 6 < 6 < 16 < 7 < 11 < 7 < 9 < 9 < 6 < 24 < 7 C-6 11/30/22 - 12/29/22 < 7 < 5 < 9 < 7 < 13 < 7 < 10 < 5 < 7 < 38 < 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, 2022 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION SITE PERIOD Sr-90 BKGB BOTTOM FEEDER 06/16/22 < 4.3 10/12/22 < 4.6 MEAN -

BKGP PREDATOR 06/16/22 < 4.3 10/12/22 < 4.2 MEAN -

INDB BOTTOM FEEDER 06/14/22 < 4.1 09/29/22 < 4.2 MEAN -

INDP PREDATOR 06/14/22 < 3.8 09/29/22 < 4.4 MEAN -

C-7

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, 2022 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 06/16/22 3658 +/- 911 < 53 < 56 < 92 < 56 < 136 < 41 < 56 10/12/22 2832 +/- 733 < 39 < 45 < 110 < 43 < 101 < 54 < 59 MEAN +/- 2 STD DEV 3245 +/- 1168 - - - - - - -

BKGP PREDATOR 06/16/22 3277 +/- 919 < 47 < 55 < 110 < 58 < 129 < 66 < 59 10/12/22 3026 +/- 993 < 73 < 63 < 138 < 69 < 130 < 70 < 84 MEAN +/- 2 STD DEV 3152 +/- 355 - - - - - - -

INDB BOTTOM FEEDER 06/14/22 3535 +/- 1089 < 74 < 58 < 135 < 79 < 170 < 82 < 84 09/29/22 4148 +/- 1166 < 90 < 65 < 161 < 88 < 138 < 89 < 72 MEAN +/- 2 STD DEV 3842 +/- 867 - - - - - - -

INDP PREDATOR 06/14/22 2267 +/- 885 < 47 < 46 < 83 < 46 < 82 < 64 < 57 09/29/22 3257 +/- 914 < 72 < 55 < 153 < 51 < 145 < 70 < 54 MEAN +/- 2 STD DEV 2762 +/- 1400 - - - - - - -

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, 2022 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 06/14/22 8043 +/- 1563 < 77 < 63 < 66 < 97 < 77 11/21/22 9575 +/- 881 < 47 < 40 < 43 < 54 < 50 MEAN +/- 2 STD DEV 8809 +/- 2167 - - - - -

J2-1 06/14/22 12190 +/- 1621 < 72 < 79 < 132 < 92 < 95 11/21/22 13070 +/- 1107 < 48 < 46 < 52 < 66 < 64 MEAN +/- 2 STD DEV 12630 +/- 1245 - - - - -

K1-3 06/14/22 8847 +/- 1377 < 67 < 55 < 69 < 82 < 74 11/21/22 9115 +/- 1629 < 79 < 68 < 123 < 98 < 98 MEAN +/- 2 STD DEV 8981 +/- 379 - - - - -

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, 2022 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 12/29/21 - 01/05/22 16 +/- 4 15 +/- 4 14 +/- 4 17 +/- 5 16 +/- 4 15 +/- 4 17 +/- 5 01/05/22 - 01/12/22 26 +/- 5 28 +/- 5 29 +/- 5 24 +/- 5 27 +/- 5 28 +/- 5 26 +/- 5 01/12/22 - 01/19/22 23 +/- 5 21 +/- 5 25 +/- 5 23 +/- 5 19 +/- 5 24 +/- 5 24 +/- 5 01/19/22 - 01/27/22 23 +/- 5 21 +/- 4 21 +/- 4 21 +/- 4 21 +/- 4 22 +/- 5 21 +/- 4 01/27/22 - 02/03/22 20 +/- 5 16 +/- 4 15 +/- 5 16 +/- 4 13 +/- 4 17 +/- 5 18 +/- 5 02/03/22 - 02/10/22 15 +/- 4 19 +/- 5 13 +/- 4 11 +/- 4 18 +/- 5 17 +/- 5 17 +/- 5 02/10/22 - 02/16/22 16 +/- 4 15 +/- 4 19 +/- 5 18 +/- 4 17 +/- 4 19 +/- 5 16 +/- 4 02/16/22 - 02/24/22 15 +/- 4 16 +/- 4 17 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 15 +/- 4 02/24/22 - 03/03/22 14 +/- 4 13 +/- 4 21 +/- 5 18 +/- 4 18 +/- 4 19 +/- 4 19 +/- 4 03/03/22 - 03/11/22 16 +/- 4 14 +/- 4 16 +/- 4 11 +/- 3 12 +/- 3 12 +/- 3 16 +/- 4 03/11/22 - 03/16/22 20 +/- 6 14 +/- 5 20 +/- 6 18 +/- 6 15 +/- 5 14 +/- 5 18 +/- 6 03/16/22 - 03/24/22 11 +/- 3 10 +/- 3 15 +/- 4 12 +/- 4 15 +/- 4 13 +/- 4 15 +/- 4 03/24/22 - 03/30/22 8 +/- 4 9 +/- 4 7 +/- 4 8 +/- 4 < 6 9 +/- 4 9 +/- 4 03/30/22 - 04/06/22 7 +/- 4 12 +/- 4 12 +/- 4 7 +/- 4 9 +/- 4 9 +/- 4 9 +/- 4 04/06/22 - 04/13/22 7 +/- 3 6 +/- 3 7 +/- 3 8 +/- 4 8 +/- 4 7 +/- 3 8 +/- 4 04/13/22 - 04/20/22 9 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 13 +/- 4 13 +/- 4 11 +/- 4 04/20/22 - 04/27/22 16 +/- 4 12 +/- 4 20 +/- 5 18 +/- 4 12 +/- 4 19 +/- 5 20 +/- 5 04/27/22 - 05/06/22 14 +/- 4 13 +/- 3 15 +/- 4 14 +/- 4 13 +/- 4 14 +/- 4 16 +/- 4 05/06/22 - 05/12/22 16 +/- 5 14 +/- 5 13 +/- 5 14 +/- 5 15 +/- 5 15 +/- 5 17 +/- 5 05/12/22 - 05/19/22 10 +/- 4 7 +/- 3 16 +/- 7 7 +/- 3 10 +/- 4 9 +/- 4 8 +/- 4 05/19/22 - 05/26/22 12 +/- 4 13 +/- 4 13 +/- 4 15 +/- 4 15 +/- 4 12 +/- 4 15 +/- 5 05/26/22 - 06/02/22 12 +/- 4 14 +/- 5 13 +/- 4 12 +/- 4 16 +/- 5 15 +/- 5 16 +/- 5 06/02/22 - 06/08/22 15 +/- 5 20 +/- 5 18 +/- 5 15 +/- 5 16 +/- 5 18 +/- 5 17 +/- 5 06/08/22 - 06/16/22 13 +/- 4 13 +/- 4 13 +/- 4 < 4 15 +/- 4 15 +/- 4 11 +/- 4 06/16/22 - 06/23/22 15 +/- 4 12 +/- 4 13 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 12 +/- 4 06/23/22 - 06/30/22 10 +/- 4 8 +/- 4 8 +/- 4 7 +/- 4 9 +/- 4 9 +/- 4 8 +/- 4 06/30/22 - 07/07/22 10 +/- 4 10 +/- 4 9 +/- 4 14 +/- 4 11 +/- 4 7 +/- 4 8 +/- 4 07/07/22 - 07/15/22 16 +/- 4 16 +/- 4 12 +/- 4 18 +/- 4 16 +/- 4 16 +/- 4 22 +/- 4 07/15/22 - 07/21/22 20 +/- 5 20 +/- 5 16 +/- 5 20 +/- 5 21 +/- 5 20 +/- 5 19 +/- 5 07/21/22 - 07/27/22 20 +/- 6 20 +/- 6 16 +/- 6 23 +/- 6 20 +/- 6 22 +/- 6 18 +/- 6 07/27/22 - 08/04/22 17 +/- 4 17 +/- 4 16 +/- 4 21 +/- 4 19 +/- 4 17 +/- 4 16 +/- 4 08/04/22 - 08/11/22 14 +/- 4 14 +/- 4 10 +/- 3 12 +/- 4 13 +/- 4 13 +/- 4 16 +/- 4 08/11/22 - 08/19/22 15 +/- 4 20 +/- 4 16 +/- 4 20 +/- 4 18 +/- 4 18 +/- 4 18 +/- 4 08/19/22 - 08/25/22 16 +/- 5 22 +/- 5 18 +/- 5 23 +/- 5 24 +/- 5 21 +/- 5 28 +/- 5 08/25/22 - 09/01/22 22 +/- 5 28 +/- 5 28 +/- 5 28 +/- 5 25 +/- 5 25 +/- 5 24 +/- 5 09/01/22 - 09/07/22 12 +/- 5 15 +/- 5 17 +/- 5 12 +/- 4 12 +/- 4 10 +/- 4 13 +/- 5 09/07/22 - 09/15/22 16 +/- 4 15 +/- 4 13 +/- 3 12 +/- 3 14 +/- 4 16 +/- 4 16 +/- 4 09/15/22 - 09/22/22 28 +/- 5 29 +/- 5 36 +/- 5 26 +/- 6 27 +/- 5 26 +/- 5 32 +/- 5 09/22/22 - 09/29/22 12 +/- 4 12 +/- 4 11 +/- 4 10 +/- 4 9 +/- 4 12 +/- 4 14 +/- 4 09/29/22 - 10/06/22 14 +/- 4 15 +/- 4 15 +/- 4 10 +/- 4 15 +/- 4 14 +/- 4 10 +/- 4 10/06/22 - 10/12/22 19 +/- 5 18 +/- 5 20 +/- 5 24 +/- 5 21 +/- 5 26 +/- 5 23 +/- 5 10/12/22 - 10/21/22 21 +/- 4 22 +/- 4 17 +/- 3 22 +/- 4 20 +/- 4 24 +/- 4 22 +/- 4 10/21/22 - 10/27/22 13 +/- 5 15 +/- 5 17 +/- 5 17 +/- 5 19 +/- 5 17 +/- 5 18 +/- 5 10/27/22 - 11/03/22 18 +/- 5 16 +/- 4 22 +/- 5 18 +/- 4 16 +/- 4 20 +/- 5 18 +/- 5 11/03/22 - 11/10/22 13 +/- 4 17 +/- 4 20 +/- 5 18 +/- 4 20 +/- 4 18 +/- 4 19 +/- 4 11/10/22 - 11/17/22 11 +/- 4 10 +/- 4 11 +/- 4 10 +/- 4 12 +/- 4 13 +/- 4 10 +/- 4 11/17/22 - 11/23/22 21 +/- 5 25 +/- 5 21 +/- 5 22 +/- 5 23 +/- 5 24 +/- 5 23 +/- 5 11/23/22 - 11/30/22 23 +/- 5 22 +/- 5 23 +/- 5 21 +/- 4 30 +/- 5 26 +/- 5 25 +/- 5 11/30/22 - 12/07/22 24 +/- 5 21 +/- 5 23 +/- 5 23 +/- 5 20 +/- 5 21 +/- 5 24 +/- 5 12/07/22 - 12/15/22 17 +/- 4 17 +/- 4 17 +/- 4 14 +/- 4 16 +/- 4 14 +/- 4 20 +/- 4 12/15/22 - 12/21/22 13 +/- 4 13 +/- 4 18 +/- 5 16 +/- 5 13 +/- 4 15 +/- 4 16 +/- 5 12/21/22 - 12/29/22 14 +/- 5 17 +/- 4 22 +/- 4 22 +/- 4 23 +/- 4 22 +/- 4 22 +/- 4 MEAN +/- 2 STD DEV 16 +/- 9 16 +/- 10 17 +/- 11 16 +/- 11 16 +/- 10 17 +/- 10 17 +/- 11 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, 2022 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 12/29/21 - 02/03/22 15 28 21 +/- 9 12/29/21 - 02/03/22 13 29 20 +/- 10 12/29/21 - 02/03/22 17 26 21 +/- 7 02/03/22 - 03/03/22 13 19 15 +/- 4 02/03/22 - 03/03/22 11 21 17 +/- 5 02/03/22 - 03/03/22 15 19 17 +/- 3 03/03/22 - 03/30/22 8 20 13 +/- 8 03/03/22 - 03/30/22 7 20 13 +/- 7 03/03/22 - 03/30/22 9 18 15 +/- 7 03/30/22 - 04/27/22 6 16 10 +/- 7 03/30/22 - 04/27/22 7 20 12 +/- 9 03/30/22 - 04/27/22 8 20 12 +/- 12 04/27/22 - 06/02/22 7 16 12 +/- 5 04/27/22 - 06/02/22 7 16 13 +/- 5 04/27/22 - 06/02/22 8 17 14 +/- 7 06/02/22 - 06/30/22 8 20 13 +/- 8 06/02/22 - 06/30/22 7 18 13 +/- 7 06/02/22 - 06/30/22 8 17 12 +/- 8 06/30/22 - 08/04/22 10 20 17 +/- 8 06/30/22 - 08/04/22 7 23 17 +/- 9 06/30/22 - 08/04/22 8 22 17 +/- 10 08/04/22 - 09/01/22 14 28 19 +/- 10 08/04/22 - 09/01/22 10 28 19 +/- 11 08/04/22 - 09/01/22 16 28 22 +/- 11 09/01/22 - 09/29/22 12 29 17 +/- 14 09/01/22 - 09/29/22 9 36 16 +/- 16 09/01/22 - 09/29/22 13 32 19 +/- 18 09/29/22 - 11/03/22 13 22 17 +/- 6 09/29/22 - 11/03/22 10 26 19 +/- 8 09/29/22 - 11/03/22 10 23 18 +/- 10 C-11 11/03/22 - 11/30/22 10 25 18 +/- 11 11/03/22 - 11/30/22 10 30 19 +/- 11 11/03/22 - 11/30/22 10 25 19 +/- 13 11/30/22 - 12/29/22 13 24 17 +/- 8 11/30/22 - 12/29/22 13 23 19 +/- 7 11/30/22 - 12/29/22 16 24 20 +/- 7 12/29/21 - 12/29/22 6 29 16 +/- 10 12/29/21 - 12/29/22 7 36 16 +/- 11 12/29/21 - 12/29/22 8 32 17 +/- 11

Table C-VI.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 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 12/29/21 - 03/30/22 84 +/- 18 < 2 < 2 < 3 < 2 < 4 < 3 < 2 03/30/22 - 06/30/22 74 +/- 19 < 1 < 1 < 2 < 1 < 3 < 1 < 2 06/30/22 - 09/29/22 68 +/- 24 < 4 < 3 < 3 < 3 < 7 < 3 < 3 09/29/22 - 12/29/22 46 +/- 14 < 2 < 2 < 3 < 2 < 4 < 2 < 2 MEAN +/- 2 STD DEV 68 +/- 32 - - - - - - -

E1-2 12/29/21 - 03/30/22 83 +/- 22 < 3 < 3 < 3 < 3 < 6 < 2 < 3 03/30/22 - 06/30/22 66 +/- 17 < 1 < 2 < 3 < 2 < 2 < 1 < 1 06/30/22 - 09/29/22 59 +/- 21 < 3 < 2 < 3 < 2 < 3 < 2 < 2 09/29/22 - 12/29/22 62 +/- 21 < 2 < 2 < 3 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 67 +/- 22 - - - - - - -

F1-3 12/29/21 - 03/30/22 64 +/- 18 < 2 < 2 < 2 < 2 < 3 < 2 < 2 03/30/22 - 06/30/22 73 +/- 17 < 2 < 1 < 1 < 1 < 2 < 2 < 1 06/30/22 - 09/29/22 61 +/- 32 < 4 < 4 < 3 < 4 < 5 < 3 < 3 09/29/22 - 12/29/22 41 +/- 16 < 2 < 2 < 2 < 2 < 3 < 2 < 2 MEAN +/- 2 STD DEV 60 +/- 27 - - - - - - -

G2-1 12/29/21 - 03/30/22 60 +/- 18 < 2 < 2 < 1 < 2 < 4 < 2 < 2 03/30/22 - 06/30/22 77 +/- 30 < 3 < 3 < 3 < 3 < 4 < 3 < 3 06/30/22 - 09/29/22 76 +/- 21 < 3 < 2 < 3 < 3 < 5 < 3 < 2 09/29/22 - 12/29/22 66 +/- 24 < 3 < 3 < 3 < 3 < 5 < 3 < 2 MEAN +/- 2 STD DEV 70 +/- 16 - - - - - - -

H3-1 12/29/21 - 03/30/22 86 +/- 20 < 3 < 3 < 3 < 3 < 6 < 2 < 2 03/30/22 - 06/30/22 72 +/- 19 < 2 < 2 < 3 < 1 < 3 < 2 < 2 06/30/22 - 09/29/22 66 +/- 22 < 3 < 3 < 3 < 3 < 5 < 2 < 2 09/29/22 - 12/29/22 66 +/- 17 < 2 < 2 < 3 < 2 < 5 < 2 < 2 MEAN +/- 2 STD DEV 72 +/- 19 - - - - - - -

M2-1 12/29/21 - 03/30/22 59 +/- 20 < 2 < 3 < 3 < 3 < 4 < 2 < 2 03/30/22 - 06/30/22 77 +/- 23 < 2 < 2 < 2 < 2 < 5 < 2 < 3 06/30/22 - 09/29/22 65 +/- 19 < 2 < 2 < 2 < 3 < 4 < 2 < 2 09/29/22 - 12/29/22 62 +/- 16 < 3 < 4 < 4 < 3 < 5 < 3 < 2 MEAN +/- 2 STD DEV 66 +/- 15 - - - - - - -

Q15-1 12/29/21 - 03/30/22 65 +/- 17 < 2 < 3 < 2 < 2 < 3 < 2 < 2 03/30/22 - 06/30/22 81 +/- 18 < 3 < 2 < 2 < 2 < 5 < 2 < 2 06/30/22 - 09/29/22 73 +/- 23 < 2 < 3 < 2 < 3 < 4 < 2 < 1 09/29/22 - 12/29/22 55 +/- 20 < 2 < 2 < 3 < 2 < 4 < 2 < 2 MEAN +/- 2 STD DEV 68 +/- 22 - - - - - - -

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, 2022 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 12/29/21 - 01/05/22 < 39 < 32 < 40 < 39 < 39 < 39 < 24 01/05/22 - 01/12/22 < 37 < 37 < 30 < 35 < 35 < 35 < 35 01/12/22 - 01/19/22 < 32 < 32 < 16 < 36 < 36 < 37 < 37 01/19/22 - 01/27/22 < 47 < 19 < 34 < 46 < 47 < 47 < 34 01/27/22 - 02/03/22 < 45 < 44 < 37 < 36 < 30 < 37 < 37 02/03/22 - 02/10/22 < 30 < 30 < 37 < 20 < 30 < 38 < 37 02/10/22 - 02/16/22 < 39 < 38 < 23 < 53 < 53 < 54 < 54 02/16/22 - 02/24/22 < 27 < 26 < 36 < 26 < 18 < 26 < 36 02/24/22 - 03/03/22 < 34 < 33 < 35 < 14 < 34 < 36 < 35 03/03/22 - 03/11/22 < 35 < 34 < 27 < 26 < 26 < 22 < 27 03/11/22 - 03/16/22 < 22 < 22 < 27 < 64 < 64 < 62 < 63 03/16/22 - 03/24/22 < 20 < 20 < 27 < 20 < 20 < 11 < 27 03/24/22 - 03/30/22 < 30 < 29 < 22 < 51 < 51 < 52 < 52 03/30/22 - 04/06/22 < 42 < 41 < 57 < 34 < 41 < 42 < 57 04/06/22 - 04/13/22 < 42 < 17 < 22 < 41 < 41 < 42 < 33 04/13/22 - 04/20/22 < 16 < 36 < 45 < 37 < 38 < 36 < 43 04/20/22 - 04/27/22 < 17 < 20 < 27 < 26 < 26 < 23 < 27 04/27/22 - 05/06/22 < 26 < 25 < 22 < 25 < 25 < 26 < 26 05/06/22 - 05/12/22 < 28 < 65 < 54 < 65 < 65 < 65 < 55 05/12/22 - 05/19/22 < 19 < 19 < 29 < 37 < 37 < 37 < 38 05/19/22 - 05/26/22 < 18 < 34 < 26 < 34 < 34 < 34 < 27 05/26/22 - 06/02/22 < 43 < 42 < 59 < 59 < 60 < 60 < 25 06/02/22 - 06/08/22 < 24 < 57 < 48 < 56 < 56 < 57 < 49 06/08/22 - 06/16/22 < 17 < 35 < 14 < 34 < 35 < 35 < 24 06/16/22 - 06/23/22 < 46 < 46 < 14 < 35 < 34 < 34 < 35 06/23/22 - 06/30/22 < 21 < 50 < 29 < 50 < 50 < 50 < 29 06/30/22 - 07/07/22 < 15 < 36 < 39 < 35 < 36 < 36 < 17 07/07/22 - 07/15/22 < 51 < 50 < 15 < 37 < 37 < 37 < 37 07/15/22 - 07/21/22 < 51 < 21 < 14 < 50 < 50 < 50 < 14 07/21/22 - 07/27/22 < 41 < 41 < 57 < 24 < 57 < 57 < 58 07/27/22 - 08/04/22 < 26 < 46 < 18 < 42 < 42 < 42 < 43 08/04/22 - 08/11/22 < 45 < 44 < 16 < 31 < 31 < 31 < 32 08/11/22 - 08/19/22 < 13 < 27 < 23 < 27 < 27 < 27 < 24 08/19/22 - 08/25/22 < 28 < 54 < 52 < 53 < 54 < 54 < 51 08/25/22 - 09/01/22 < 63 < 62 < 25 < 59 < 60 < 60 < 62 09/01/22 - 09/07/22 < 28 < 65 < 40 < 64 < 64 < 65 < 35 09/07/22 - 09/15/22 < 15 < 33 < 50 < 33 < 33 < 34 < 51 09/15/22 - 09/22/22 < 23 < 22 < 24 < 13 < 23 < 23 < 25 09/22/22 - 09/29/22 < 48 < 48 < 12 < 48 < 48 < 19 < 12 09/29/22 - 10/06/22 < 53 < 52 < 28 < 21 < 51 < 53 < 29 10/06/22 - 10/12/22 < 48 < 47 < 35 < 48 < 48 < 19 < 35 10/12/22 - 10/21/22 < 12 < 29 < 42 < 29 < 29 < 29 < 43 10/21/22 - 10/27/22 < 49 < 48 < 30 < 36 < 36 < 35 < 35 10/27/22 - 11/03/22 < 37 < 36 < 29 < 36 < 36 < 19 < 30 11/03/22 - 11/10/22 < 35 < 34 < 46 < 34 < 35 < 33 < 16 11/10/22 - 11/17/22 < 28 < 65 < 58 < 58 < 58 < 60 < 27 11/17/22 - 11/23/22 < 19 < 37 < 40 < 37 < 37 < 35 < 20 11/23/22 - 11/30/22 < 67 < 66 < 44 < 65 < 65 < 28 < 46 11/30/22 - 12/07/22 < 23 < 53 < 15 < 53 < 53 < 53 < 16 12/07/22 - 12/15/22 < 14 < 32 < 42 < 32 < 32 < 32 < 43 12/15/22 - 12/21/22 < 19 < 40 < 42 < 39 < 40 < 40 < 43 12/21/22 - 12/29/22 < 46 < 47 < 34 < 44 < 44 < 44 < 26 MEAN - - - - - - -

C-13

TABLE C-VIII.1 CONCENTRATIONS OF I-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION CONTROL FARM INDICATOR FARMS PERIOD J18-1 F4-1 G2-1 P4-1 01/19/22 < 0.8 < 0.7 < 0.9 < 0.7 02/16/22 < 0.7 < 0.8 < 0.7 < 0.6 03/16/22 < 0.8 < 0.9 < 0.9 < 0.8 03/30/22 < 0.7 < 0.7 < 0.7 < 0.8 04/13/22 < 0.9 < 0.9 < 0.9 < 0.8 04/27/22 < 0.8 < 0.8 < 0.9 < 0.9 05/11/22 < 0.6 < 0.5 < 0.5 < 0.6 05/26/22 < 0.8 < 0.7 < 0.7 < 0.9 06/08/22 < 1.0 < 0.8 < 1.0 < 1.0 06/22/22 < 0.8 < 0.8 < 0.9 < 0.8 07/07/22 < 0.8 < 0.8 < 0.8 < 0.9 07/20/22 < 0.8 < 0.6 < 0.7 < 0.7 08/03/22 < 0.9 < 0.9 < 0.9 (1) 08/17/22 < 0.9 < 0.8 < 0.8 (1) 08/31/22 < 0.9 < 0.9 < 0.8 (1) 09/15/22 < 0.8 < 0.8 < 0.8 (1) 09/29/22 < 0.5 < 0.8 < 0.8 (1) 10/12/22 < 0.8 < 0.8 < 0.7 (1) 10/27/22 < 0.8 < 0.8 < 0.9 (1) 11/10/22 < 0.9 < 0.9 < 0.9 (1) 11/23/22 < 0.8 < 0.6 < 0.6 (1) 12/07/22 < 0.8 < 0.6 < 0.4 (1)

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, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDICATOR FARMS COLLECTION J18-1 F4-1 G2-1 P4-1 PERIOD Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 01/19/22 - 03/30/22 < 3.8 < 0.9 < 4.7 < 0.9 < 4.4 < 0.9 < 4.6 < 1.0 04/13/22 - 06/22/22 < 4.4 < 0.9 < 4.2 < 0.8 < 4.1 < 0.8 < 4.2 < 0.8 07/07/22 - 09/29/22 < 3.6 < 0.9 < 3.3 < 0.9 < 3.5 < 0.8 < 4.9 < 0.8 10/12/22 - 12/07/22 < 4.7 < 0.9 < 4.4 < 0.9 < 4.8 < 0.8 (1)

MEAN - - - - - - - -

C-15 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 F4-1 01/19/22 1247 +/- 176 < 10 < 8 < 32 < 9 02/16/22 1404 +/- 222 < 9 < 7 < 25 < 8 03/16/22 1289 +/- 211 < 8 < 8 < 29 < 7 03/30/22 1121 +/- 179 < 10 < 7 < 31 < 11 04/13/22 1207 +/- 188 < 9 < 9 < 42 < 7 04/27/22 1301 +/- 188 < 10 < 9 < 31 < 11 05/11/22 1230 +/- 177 < 7 < 7 < 27 < 14 05/26/22 1334 +/- 165 < 9 < 7 < 26 < 10 06/08/22 1449 +/- 193 < 8 < 8 < 34 < 9 06/22/22 1385 +/- 160 < 7 < 7 < 29 < 7 07/07/22 980 +/- 196 < 10 < 10 < 39 < 8 07/20/22 1464 +/- 147 < 6 < 7 < 28 < 8 08/03/22 1399 +/- 143 < 6 < 6 < 30 < 10 08/17/22 1271 +/- 151 < 7 < 7 < 26 < 10 08/31/22 1360 +/- 173 < 8 < 8 < 31 < 11 09/15/22 1283 +/- 192 < 10 < 9 < 36 < 9 09/29/22 1144 +/- 189 < 7 < 8 < 36 < 12 10/12/22 1177 +/- 181 < 9 < 8 < 26 < 10 10/27/22 1372 +/- 150 < 7 < 7 < 29 < 7 11/10/22 1318 +/- 194 < 10 < 9 < 37 < 6 11/23/22 1279 +/- 166 < 7 < 7 < 28 < 8 12/07/22 1368 +/- 148 < 6 < 6 < 23 < 9 MEAN +/- 2 STD DEV 1290 +/- 232 - - - -

G2-1 01/19/22 1216 +/- 125 < 6 < 6 < 21 < 8 02/16/22 997 +/- 142 < 7 < 7 < 21 < 9 03/16/22 1343 +/- 192 < 9 < 9 < 39 < 8 03/30/22 1265 +/- 183 < 9 < 9 < 37 < 11 04/13/22 1192 +/- 186 < 10 < 8 < 47 < 9 04/27/22 1222 +/- 162 < 8 < 9 < 35 < 7 05/11/22 1289 +/- 131 < 6 < 6 < 25 < 7 05/26/22 1094 +/- 184 < 6 < 10 < 34 < 10 06/08/22 1129 +/- 177 < 8 < 7 < 34 < 9 06/22/22 936 +/- 151 < 8 < 7 < 37 < 10 07/07/22 1382 +/- 156 < 8 < 6 < 24 < 8 07/20/22 1447 +/- 181 < 8 < 6 < 31 < 10 08/03/22 1095 +/- 163 < 6 < 8 < 29 < 9 08/17/22 1493 +/- 135 < 7 < 7 < 18 < 7 08/31/22 806 +/- 156 < 6 < 6 < 29 < 10 09/15/22 920 +/- 185 < 9 < 9 < 39 < 15 09/29/22 1365 +/- 174 < 8 < 8 < 25 < 7 10/12/22 1250 +/- 169 < 10 < 8 < 29 < 7 10/27/22 1230 +/- 175 < 8 < 8 < 33 < 7 11/10/22 1242 +/- 154 < 9 < 10 < 35 < 13 11/23/22 1185 +/- 173 < 8 < 9 < 36 < 11 12/07/22 1078 +/- 176 < 11 < 10 < 38 < 12 MEAN +/- 2 STD DEV 1190 +/- 347 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-16

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 J18-1 01/19/22 1329 +/- 149 < 7 < 6 < 25 < 7 02/16/22 1260 +/- 177 < 7 < 7 < 26 < 7 03/16/22 1136 +/- 188 < 9 < 10 < 39 < 9 03/30/22 1153 +/- 152 < 9 < 8 < 26 < 8 04/13/22 1159 +/- 173 < 8 < 9 < 33 < 13 04/27/22 1259 +/- 176 < 8 < 8 < 37 < 10 05/11/22 1329 +/- 164 < 7 < 7 < 36 < 9 05/26/22 1112 +/- 180 < 8 < 8 < 34 < 10 06/08/22 1206 +/- 174 < 7 < 4 < 36 < 14 06/22/22 1322 +/- 183 < 9 < 8 < 28 < 9 07/07/22 1483 +/- 174 < 8 < 7 < 21 < 5 07/20/22 828 +/- 121 < 7 < 9 < 38 < 12 08/03/22 1197 +/- 143 < 6 < 7 < 29 < 8 08/17/22 1160 +/- 179 < 7 < 7 < 25 < 9 08/31/22 1250 +/- 192 < 8 < 9 < 32 < 10 09/15/22 1293 +/- 186 < 5 < 7 < 32 < 12 09/29/22 1220 +/- 185 < 10 < 9 < 36 < 13 10/12/22 1131 +/- 200 < 9 < 8 < 27 < 9 10/27/22 1175 +/- 147 < 7 < 5 < 24 < 9 11/10/22 1376 +/- 184 < 9 < 9 < 33 < 12 11/23/22 1166 +/- 161 < 7 < 6 < 28 < 10 12/07/22 1131 +/- 186 < 9 < 7 < 29 < 5 MEAN +/- 2 STD DEV 1213 +/- 255 - - - -

P4-1 01/19/22 1174 +/- 150 < 8 < 8 < 26 < 7 02/16/22 1317 +/- 169 < 8 < 7 < 30 < 3 03/16/22 1432 +/- 192 < 9 < 11 < 33 < 13 03/30/22 1296 +/- 209 < 8 < 9 < 30 < 15 04/13/22 1370 +/- 222 < 8 < 10 < 37 < 13 04/27/22 1358 +/- 216 < 9 < 9 < 32 < 7 05/11/22 1384 +/- 150 < 7 < 7 < 27 < 8 05/26/22 1290 +/- 204 < 7 < 8 < 31 < 10 06/08/22 1293 +/- 196 < 11 < 7 < 38 < 12 06/22/22 1130 +/- 170 < 9 < 10 < 35 < 7 07/07/22 1358 +/- 177 < 7 < 8 < 26 < 8 07/20/22 1095 +/- 155 < 7 < 7 < 19 < 6 08/03/22 (1) 08/17/22 (1) 08/31/22 (1) 09/15/22 (1) 09/29/22 (1) 10/12/22 (1) 10/27/22 (1) 11/10/22 (1) 11/23/22 (1) 12/07/22 (1)

MEAN +/- 2 STD DEV 1291 +/- 211 - - - -

THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION 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, 2022 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 Cabbage 06/22/22 < 287 4262 +/- 675 < 30 < 40 < 37 Kale 06/22/22 < 367 4361 +/- 827 < 34 < 31 < 28 Broccoli 06/22/22 < 344 5422 +/- 856 < 31 < 32 < 36 Kale 07/20/22 990 +/- 507 5018 +/- 895 < 53 < 58 < 47 Cabbage 07/20/22 575 +/- 279 3304 +/- 595 < 42 < 27 < 30 Broccoli 07/20/22 1061 +/- 340 4456 +/- 655 < 48 < 36 < 39 Corn 08/17/22 < 4.1 < 126 2752 +/- 427 < 21 < 20 < 16 Tomato 08/17/22 < 4.1 < 185 2296 +/- 501 < 27 < 29 < 26 Potato 08/17/22 < 4.5 < 173 2245 +/- 461 < 23 < 21 < 24 Kale 08/17/22 383 +/- 234 4677 +/- 503 < 29 < 30 < 28 Cabbage 08/17/22 1049 +/- 382 5355 +/- 729 < 34 < 34 < 35 Lettuce 08/17/22 652 +/- 206 5352 +/- 574 < 27 < 30 < 26 Kale 09/20/22 1153 +/- 452 6698 +/- 1156 < 51 < 53 < 53 Cabbage 09/20/22 1318 +/- 356 5143 +/- 675 < 31 < 35 < 35 Collard Greens 09/20/22 1024 +/- 314 3667 +/- 740 < 30 < 33 < 34 MEAN +/- 2 STD DEV - 912 +/- 610 4017 +/- 2737 - - -

E1-2 Broccoli 06/22/22 < 382 3275 +/- 614 < 44 < 40 < 37 Cabbage 06/22/22 < 249 2881 +/- 539 < 29 < 30 < 35 Cauliflower 06/22/22 410 +/- 201 3079 +/- 499 < 23 < 26 < 19 Cabbage 07/20/22 937 +/- 293 2913 +/- 593 < 42 < 23 < 28 Broccoli 07/20/22 467 +/- 306 3063 +/- 537 < 56 < 45 < 37 Cauliflower 07/20/22 < 295 4334 +/- 618 < 41 < 23 < 31 Corn 08/17/22 < 4.4 < 108 2022 +/- 372 < 15 < 13 < 15 Tomato 08/17/22 < 4.3 < 105 1867 +/- 300 < 17 < 16 < 13 Potato 08/17/22 < 4.3 < 197 5495 +/- 672 < 28 < 34 < 29 Cauliflower 08/17/22 603 +/- 308 4303 +/- 620 < 29 < 33 < 26 Kale 08/17/22 707 +/- 265 3606 +/- 687 < 48 < 44 < 46 Cabbage 08/17/22 313 +/- 167 4237 +/- 372 < 20 < 21 < 20 Kale 09/20/22 < 367 2815 +/- 553 < 42 < 40 < 33 Collard Greens 09/20/22 < 456 2506 +/- 627 < 42 < 43 < 42 Cabbage 09/20/22 < 358 2970 +/- 623 < 34 < 37 < 29 MEAN +/- 2 STD DEV - 573 +/- 453 3264 +/- 2246 - - -

H1-2 Zucchini 06/22/22 < 366 4391 +/- 834 < 33 < 31 < 36 Yellow Squash Leaves 06/22/22 464 +/- 165 3750 +/- 504 < 24 < 24 < 21 Cucumber 06/22/22 583 +/- 233 3842 +/- 582 < 30 < 35 < 27 Pumpkin 07/20/22 476 +/- 245 5775 +/- 719 < 51 < 34 < 36 Cucumber 07/20/22 828 +/- 296 3693 +/- 674 < 36 < 36 < 34 Yellow Squash 07/20/22 < 421 6017 +/- 828 < 47 < 38 < 37 Yellow Squash 08/17/22 771 +/- 231 3017 +/- 401 < 25 < 25 < 22 Zucchini 08/17/22 1110 +/- 245 3653 +/- 526 < 28 < 27 < 25 Pumpkin 08/17/22 750 +/- 383 4067 +/- 699 < 35 < 39 < 28 Pumpkin 09/20/22 4583 +/- 651 5416 +/- 814 < 43 < 46 < 40 Butternut Squash 09/20/22 3388 +/- 514 5112 +/- 923 < 36 < 46 < 35 Eggplant 09/20/22 3435 +/- 800 4668 +/- 1134 < 57 < 59 < 44 MEAN +/- 2 STD DEV 1639 +/- 3076 4450 +/- 1898 - - -

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, 2022 RESULTS IN UNITS OF MILLIREM/QUARTER - MISSING STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC A1-4 14.6 +/- 1.7 14.8 14.6 13.5 15.5 A3-1 14.5 +/- 3.4 12.5 15.3 16.4 13.8 A5-1 19.6 +/- 2.8 17.8 19.7 19.7 21.2 A9-3 15.9 +/- 2.4 14.8 14.9 17.1 16.8 B1-1 15.3 +/- 4.3 15.2 15.2 12.8 18.0 B1-2 14.9 +/- 1.7 14.8 15.8 13.7 15.1 B2-1 14.7 +/- 1.7 14.4 14.3 16.0 14.2 B5-1 18.7 +/- 2.3 18.3 17.3 19.8 19.4 B10-1 17.6 +/- 3.0 17.2 17.7 19.5 15.9 C1-1 17.4 +/- 4.3 16.6 14.9 20.0 17.9 C1-2 14.6 +/- 2.1 13.7 14.7 13.8 16.0 C2-1 16.7 +/- 3.6 16.8 14.6 19.0 16.5 C5-1 18.2 +/- 2.1 17.3 17.5 18.2 19.6 C8-1 19.1 +/- 3.5 17.4 17.7 20.6 20.5 D1-1 15.7 +/- 1.4 15.2 15.8 15.0 16.6 D1-2 16.8 +/- 3.4 16.5 15.0 19.1 16.6 D15-1 18.1 +/- 3.3 16.8 17.1 20.4 18.1 D2-2 19.6 +/- 2.8 19.3 17.9 21.3 19.7 D6-1 20.3 +/- 3.7 18.7 19.0 21.0 22.6 E1-2 14.8 +/- 2.4 14.4 13.8 (1) 16.1 E1-4 17.0 +/- 4.1 16.7 16.1 15.2 19.9 E2-3 19.7 +/- 2.0 18.9 19.5 21.2 19.3 E5-1 20.4 +/- 2.0 20.0 19.1 21.0 21.3 E7-1 18.3 +/- 3.0 17.0 19.1 20.0 17.0 F1-1 16.8 +/- 1.7 15.9 16.2 17.8 17.1 F1-2 16.5 +/- 1.2 16.0 16.1 16.4 17.3 F1-4 16.4 +/- 3.7 14.5 17.0 15.3 18.6 F2-1 20.2 +/- 3.4 18.4 19.0 21.9 21.3 F5-1 19.6 +/- 3.6 18.2 19.6 22.1 18.4 F10-1 21.2 +/- 3.0 20.3 19.9 23.2 21.5 F25-1 18.1 +/- 2.4 17.1 17.0 18.9 19.3 G1-2 18.2 +/- 4.0 16.3 16.8 19.1 20.6 G1-3 15.0 +/- 2.9 14.4 15.8 13.2 16.5 G1-5 17.4 +/- 3.1 15.7 18.5 16.4 18.9 G1-6 18.3 +/- 4.3 16.2 17.7 18.0 21.3 G2-4 21.1 +/- 4.1 20.5 19.4 24.1 20.5 G5-1 17.8 +/- 3.1 15.7 17.5 19.1 18.7 G10-1 25.8 +/- 6.0 25.5 22.7 29.9 25.1 G15-1 16.5 +/- 1.5 16.4 15.9 17.5 16.0 H1-1 24.4 +/- 7.5 18.8 25.8 26.8 26.1 H1-3 30.9 +/- 16.9 18.6 32.4 36.1 36.6 H3-1 13.9 +/- 1.6 13.3 13.2 14.9 14.3 H5-1 14.1 +/- 2.7 13.7 12.9 13.8 16.0 H8-1 29.1 +/- 5.0 27.3 26.9 32.2 30.0 H15-1 17.9 +/- 1.8 17.2 17.9 17.3 19.2 J1-1 15.4 +/- 3.6 14.1 15.0 14.3 18.0 J1-3 30.3 +/- 13.3 20.9 34.0 30.2 35.9 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-19

Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF MILLIREM/QUARTER - MISSING STATION MEAN CODE +/- 2 S.D. JAN - MAR APR - JUN JUL - SEP OCT - DEC J1-4 31.9 +/- 11.5 23.3 35.2 33.9 35.0 J3-1 18.0 +/- 2.2 17.5 16.7 18.9 18.9 J5-1 20.4 +/- 4.2 18.4 18.8 21.9 22.5 J7-1 21.7 +/- 2.5 20.2 21.1 22.6 22.8 J15-1 20.5 +/- 2.4 22.0 19.8 20.8 19.3 K1-4 15.9 +/- 4.4 15.6 14.5 14.4 19.1 K1-5 22.6 +/- 9.7 15.7 25.0 23.0 26.8 K2-1 19.4 +/- 2.0 18.2 19.3 19.3 20.7 K3-1 16.1 +/- 3.0 14.6 15.5 16.1 18.1 K5-1 19.3 +/- 1.4 18.5 19.1 20.2 19.5 K8-1 18.6 +/- 1.9 19.1 17.4 18.3 19.6 K15-1 16.8 +/- 1.1 16.5 16.2 16.9 17.5 L1-1 16.9 +/- 2.5 16.9 17.2 15.2 18.2 L1-2 15.2 +/- 1.3 14.9 14.9 14.8 16.2 L2-1 17.4 +/- 2.0 16.0 17.2 17.9 18.3 L5-1 16.5 +/- 1.0 15.9 16.6 16.5 17.1 L8-1 17.3 +/- 2.6 16.3 16.0 18.5 18.3 L15-1 18.3 +/- 3.2 17.0 16.9 19.1 20.2 M1-1 16.2 +/- 3.9 15.2 17.5 14.0 18.1 M1-2 17.3 +/- 3.1 15.9 16.1 18.5 18.8 M2-1 16.3 +/- 1.0 16.5 16.1 15.7 16.9 M5-1 17.1 +/- 1.5 16.7 16.4 17.3 18.1 M9-1 21.8 +/- 2.9 20.1 21.0 23.1 22.8 N1-1 16.4 +/- 1.0 16.2 16.7 16.8 15.7 N1-3 18.3 +/- 2.2 17.4 18.6 17.5 19.8 N2-1 18.8 +/- 4.2 17.3 17.4 18.7 21.8 N5-1 15.3 +/- 2.3 14.3 14.6 15.6 16.8 N8-1 18.9 +/- 2.8 17.7 17.9 19.5 20.6 N15-2 20.0 +/- 2.5 19.3 18.8 20.4 21.6 P1-1 15.9 +/- 1.7 16.1 15.0 15.6 17.0 P1-2 21.5 +/- 1.1 22.2 21.7 20.9 21.3 P2-1 21.8 +/- 2.6 20.8 21.5 21.1 23.7 P5-1 18.2 +/- 2.6 16.9 18.2 17.7 20.0 P8-1 15.4 +/- 2.8 15.0 14.4 14.7 17.5 Q1-1 16.9 +/- 3.5 16.5 16.2 19.4 15.3 Q1-2 16.2 +/- 3.7 16.3 15.6 14.3 18.7 Q2-1 15.7 +/- 2.9 14.2 14.9 16.0 17.5 Q5-1 16.4 +/- 2.4 15.5 15.3 17.1 17.8 Q9-1 16.8 +/- 1.2 16.0 17.1 17.3 16.6 Q15-1 19.5 +/- 2.0 19.3 18.7 20.9 19.0 R1-1 16.1 +/- 2.9 15.7 16.5 14.3 17.8 R1-2 15.0 +/- 0.9 15.2 14.4 14.9 15.5 R3-1 20.3 +/- 4.2 17.2 20.7 21.3 21.8 R5-1 18.6 +/- 2.0 19.0 18.5 19.5 17.2 R9-1 18.1 +/- 2.5 16.5 18.3 19.5 18.2 R15-1 16.2 +/- 1.8 16.3 15.9 17.3 15.2 C-20

TABLE C-X.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF MILLIREM/QUARTER

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY PERIOD +/- 2 STD DEV INDICATOR CONTROL JAN-MAR 16.8 +/- 5.1 17.0 +/- 4.7 18.5 +/- 5.8 APR-JUN 19.8 +/- 12.9 17.2 +/- 4.9 17.9 +/- 4.1 JUL-SEP 18.7 +/- 13.8 18.8 +/- 6.2 19.9 +/- 7.3 OCT-DEC 21.3 +/- 13.2 18.7 +/- 5.5 19.1 +/- 5.4 TABLE C-X.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2021 RESULTS IN UNITS OF MILLIREMQUARTER SAMPLES PERIOD PERIOD PERIOD MEAN LOCATION ANALYZED MINIMUM MAXIMUM +/- 2 STD DEV SITE BOUNDARY 88 13.2 36.6 19.1 +/- 12.1 INDICATOR 239 12.5 32.2 17.9 +/- 5.6 CONTROL 44 15.2 29.9 18.9 +/- 5.8 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, H1-3, J1-3, J1-4, K1-4, K1-5, 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, P8-1, 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, 2022 Station J1-2 (Downstream of Discharge) Station Q9-1 (Control) 100000 10000 1000 100 Picocuries per Liter 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 - 2022 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 Major Atm. Nuclear Weapon Tests 8000 June 1974 September 1974 September 1976 November 1976 7000 September 1977 March 1978 C-23 December 1978 October 1980 6000 5000 4000 Picocuries per Liter 3000 2000 1000 0

-1000 1974 1980 1986 1992 1998 2004 2010 2016 2022 Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2022 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, 2022 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 Month

FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2022 Indicator Samples Control Samples 900 Significant Event

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

1984 1993 2002 2012 2022 Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2022 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 Picocuries per Cubic Meter 0.15 0.1 0.05 0

1972 1977 1982 1987 1992 1997 2002 2007 2012 2017 2022 Year

FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2022 0.100 0.090 Indicator Control 0.080 0.070 0.060 0.050 C-28 0.040 Picocuries per Cubic Meter 0.030 0.020 0.010 0.000 01/01/07 09/01/09 05/02/12 01/01/15 09/01/17 05/02/20 01/01/23 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 - 2022 Indicator Samples Control Samples 10 Significant Events Major Atm. Nuclear Weapon Tests TMI-2 Accident March 1979 December 1978 October 1980 9

TMI-2 RB Purge June 1980 Chernobyl April 1986 8

7 6

C-29 5

Picocuries per Liter 4 3

2 1

0 1979 1990 2001 2012 2023 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, Constellation Energy Group (CEG) 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, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB PERIOD Q9-1Q CGS 12/29/21 - 02/03/22 17.7 +/- 1.5 02/03/22 - 03/03/22 2.0 +/- 0.8 03/03/22 - 03/30/22 2.1 +/- 0.8 03/30/22 - 04/27/22 < 1.2 04/27/22 - 06/02/22 1.1 +/- 0.7 06/02/22 - 06/30/22 1.5 +/- 0.8 06/30/22 - 07/27/22 1.4 +/- 0.8 07/27/22 - 09/01/22 3.5 +/- 0.3 09/01/22 - 09/29/22 2.1 +/- 0.8 `

09/29/22 - 11/03/22 2.8 +/- 0.8 11/03/22 - 11/30/22 2.1 +/- 0.7 11/30/22 - 12/29/22 2.8 +/- 0.8 MEAN +/- 2 STD DEV 3.3 +/- 9.1 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB PERIOD Q9-1Q GEL 12/29/21 - 03/30/22 < 146 03/30/22 - 06/30/22 < 143 06/30/22 - 09/29/22 < 139 09/29/22 - 12/29/22 < 188 MEAN -

TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB PERIOD Q9-1Q CGS 12/29/21 - 02/03/22 < 0.4 02/03/22 - 03/03/22 < 0.9 03/03/22 - 03/30/22 < 0.6 03/30/22 - 04/27/22 < 0.4 04/27/22 - 06/02/22 < 0.4 06/02/22 - 06/30/22 < 0.4 06/30/22 - 07/27/22 < 0.3 07/27/22 - 09/01/22 < 0.3 09/01/22 - 09/29/22 < 0.5 09/29/22 - 11/03/22 < 0.4 11/03/22 - 11/30/22 < 0.4 11/30/22 - 12/29/22 < 0.5 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, 2022 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 CGS Q9-1Q 12/29/21 - 02/03/22 < 6 < 6 < 12 < 7 < 15 < 6 < 10 < 7 < 7 < 23 < 8 02/03/22 - 03/03/22 < 6 < 7 < 13 < 7 < 14 < 7 < 11 < 7 < 7 < 33 < 11 03/03/22 - 03/30/22 < 6 < 6 < 12 < 6 < 13 < 6 < 11 < 6 < 6 < 40 < 14 03/30/22 - 04/27/22 < 4 < 3 < 10 < 4 < 8 < 5 < 7 < 5 < 5 < 17 < 5 04/27/22 - 06/02/22 < 4 < 6 < 10 < 4 < 10 < 5 < 7 < 3 < 5 < 23 < 8 06/02/22 - 06/30/22 < 4 < 4 < 6 < 4 < 9 < 5 < 5 < 4 < 5 < 26 < 10 06/30/22 - 07/27/22 < 3 < 3 < 6 < 3 < 5 < 4 < 5 < 3 < 4 < 16 < 7 07/27/22 - 09/01/22 < 3 < 3 < 6 < 3 < 5 < 4 < 1 < 3 < 4 < 17 < 6 09/01/22 - 09/29/22 < 5 < 3 < 6 < 3 < 8 < 4 < 6 < 4 < 3 < 13 < 7 09/29/22 - 11/03/22 < 3 < 2 < 5 < 1 < 7 < 4 < 5 < 3 < 4 < 12 < 4 11/03/22 - 11/30/22 < 3 < 2 < 8 < 4 < 7 < 4 < 5 < 2 < 4 < 14 < 7 11/30/22 - 12/29/22 < 3 < 2 < 7 < 4 < 8 < 4 < 5 < 3 < 2 < 13 < 6 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, 2022 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 CGS INDP 10/06/22 2950 +/- 246 < 8 < 8 < 33 < 9 < 22 < 6 < 7 GEL INDP 10/06/22 < 43 < 25 D-3

TABLE D-III.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 COLLECTION LAB SITE PERIOD K-40 Cs-134 Cs-137 CGS J2-1 11/21/22 12100 +/- 2140 < 91 < 127 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, 2022 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 GEL B10-2 Cabbage 08/17/22 56.3 +/- 18.4 56.9 +/- 8.9 CGS H1-2Q Cabbage 08/17/22 634 +/- 95 3700 +/- 227 < 25 < 18 < 21 CGS H1-2Q Pumpkin 07/20/22 534 +/- 88 5330 +/- 289 < 20 < 21 < 26 CGS H1-2Q Zucchini 08/17/22 1330 +/- 157 3440 +/- 272 < 31 < 20 < 22 CGS H1-2Q Pumpkin 09/20/22 3050 +/- 314 4540 +/- 575 < 20 < 18 < 26 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, 2022 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION E1-2Q E1-2Q LAB PERIOD GROSS BETA I-131 CGS 12/29/21 - 01/05/22 24 +/- 2 < 14 01/05/22 - 01/12/22 32 +/- 2 < 18 01/12/22 - 01/19/22 33 +/- 2 < 15 01/19/22 - 01/27/22 25 +/- 2 < 18 01/27/22 - 02/03/22 23 +/- 2 < 12 02/03/22 - 02/10/22 25 +/- 2 < 13 02/10/22 - 02/16/22 18 +/- 2 < 17 02/16/22 - 02/24/22 23 +/- 2 < 14 02/24/22 - 03/03/22 25 +/- 2 < 14 03/03/22 - 03/11/22 16 +/- 2 < 16 03/11/22 - 03/16/22 23 +/- 3 < 49 03/16/22 - 03/24/22 19 +/- 2 < 17 03/24/22 - 03/30/22 11 +/- 2 < 32 03/30/22 - 04/06/22 16 +/- 2 < 26 04/06/22 - 04/13/22 9 +/- 2 < 10 04/13/22 - 04/20/22 15 +/- 2 < 13 04/20/22 - 04/27/22 23 +/- 2 < 22 04/27/22 - 05/06/22 19 +/- 2 < 9 05/06/22 - 05/12/22 16 +/- 2 < 26 05/12/22 - 05/19/22 10 +/- 2 < 21 05/19/22 - 05/26/22 20 +/- 2 < 16 05/26/22 - 06/02/22 20 +/- 2 < 17 06/02/22 - 06/08/22 15 +/- 3 < 14 06/08/22 - 06/16/22 18 +/- 2 < 7 06/16/22 - 06/23/22 21 +/- 2 < 18 06/23/22 - 06/30/22 16 +/- 3 < 20 06/30/22 - 07/07/22 26 +/- 1 < 21 07/07/22 - 07/15/22 21 +/- 3 < 10 07/15/22 - 07/21/22 26 +/- 2 < 11 07/21/22 - 07/27/22 32 +/- 2 < 18 07/27/22 - 08/04/22 24 +/- 3 < 11 08/04/22 - 08/11/22 28 +/- 4 < 21 08/11/22 - 08/19/22 15 +/- 1 < 18 08/19/22 - 08/25/22 24 +/- 2 < 12 08/25/22 - 09/01/22 21 +/- 2 < 19 09/01/22 - 09/07/22 21 +/- 2 < 12 09/07/22 - 09/15/22 20 +/- 2 < 8 09/15/22 - 09/22/22 45 +/- 3 < 15 09/22/22 - 09/29/22 20 +/- 2 < 10 09/29/22 - 10/06/22 15 +/- 2 < 11 10/06/22 - 10/12/22 36 +/- 3 < 15 10/12/22 - 10/21/22 25 +/- 2 < 12 10/21/22 - 10/27/22 24 +/- 2 < 27 10/27/22 - 11/03/22 26 +/- 2 < 13 11/03/22 - 11/10/22 21 +/- 2 < 13 11/10/22 - 11/17/22 17 +/- 2 < 10 11/17/22 - 11/23/22 29 +/- 3 < 16 11/23/22 - 11/30/22 41 +/- 3 < 17 11/30/22 - 12/07/22 34 +/- 3 < 14 12/07/22 - 12/15/22 22 +/- 2 < 6 12/15/22 - 12/21/22 23 +/- 3 < 17 12/21/22 - 12/29/22 28 +/- 3 < 23 MEAN +/- 2 STD DEV 23 +/- 14 -

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, 2022 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION LAB SITE PERIOD Be-7 Mn-54 Co-58 Co-60 CGS E1-2Q 12/29/21 - 03/30/22 72 +/- 18 < 2 < 2 < 3 03/30/22 - 06/30/22 82 +/- 6 < 1 < 1 < 1 06/30/22 - 09/29/22 68 +/- 13 < 1 < 1 < 1 09/29/22 - 12/29/22 49 +/- 14 < 1 < 1 < 1 MEAN +/- 2 STD DEV 68 +/- 28 - - -

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, 2022 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 CGS G2-1Q 01/19/22 < 0.4 1290 +/- 135 < 7 < 7 < 28 < 9 CGS 02/16/22 < 0.5 967 +/- 123 < 6 < 7 < 33 < 9 CGS 03/16/22 < 0.8 1450 +/- 143 < 6 < 7 < 3 < 10 CGS 03/30/22 < 0.8 1280 +/- 143 < 9 < 9 < 41 < 15 GEL 01/19/22 - 03/30/22 < 5.1 < 1.8 CGS 04/13/22 < 0.2 1180 +/- 137 < 6 < 7 < 23 < 7 CGS 04/27/22 < 0.5 1490 +/- 145 < 3 < 4 < 24 < 7 CGS 05/11/22 < 0.4 1230 +/- 131 < 3 < 4 < 16 < 5 CGS 05/26/22 < 0.4 1380 +/- 139 < 3 < 4 < 18 < 5 CGS 06/08/22 < 0.3 1410 +/- 77 < 5 < 6 < 26 < 8 CGS 06/22/22 < 0.4 961 +/- 62 < 5 < 5 < 16 < 6 GEL 04/13/22 - 06/22/22 < 4.2 < 1.4 CGS 07/07/22 < 0.4 1460 +/- 95 < 4 < 5 < 22 < 10 D-8 CGS 07/20/22 < 0.3 792 +/- 56 < 5 < 5 < 27 < 7 CGS 08/03/22 < 0.4 1180 +/- 64 < 4 < 3 < 19 < 8 CGS 08/17/22 < 0.3 1390 +/- 71 < 4 < 3 < 21 < 6 CGS 08/31/22 < 0.4 1090 +/- 62 < 3 < 4 < 12 < 1 CGS 09/15/22 < 0.4 1100 +/- 122 < 5 < 5 < 17 < 8 CGS 09/29/22 < 0.3 1490 +/- 144 < 3 < 4 < 19 < 4 GEL 07/07/22 - 09/29/22 < 3.7 < 2.0 CGS 10/12/22 < 0.3 1340 +/- 140 < 4 < 4 < 19 < 8 CGS 10/27/22 < 0.3 1480 +/- 144 < 3 < 4 < 16 < 5 CGS 11/10/22 < 0.4 1330 +/- 137 < 4 < 4 < 25 < 7 CGS 11/23/22 < 0.5 1510 +/- 143 < 4 < 4 < 20 < 6 CGS 12/07/22 < 0.4 1290 +/- 134 < 4 < 5 < 22 < 7 GEL 10/12/22 - 12/07/22 < 2.7 < 1.2 MEAN +/- 2 STD DEV 1277 +/- 394 - - - - - -

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, 2022 17.7 7.0 QC-LAB 6.0 PRIMARY - LAB 5.0 4.0 D-9 pCi/liter 3.0 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, 2022 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 2022 E13706 Milk Sr-89 pCi/L 80.3 96.8 0.83 A Sr-90 pCi/L 12.7 12.6 1.01 A E13707 Milk Ce-141 pCi/L 62.3 65 0.96 A Co-58 pCi/L 158 164 0.96 A Co-60 pCi/L 286 302 0.95 A Cr-51 pCi/L 314 339 0.93 A Cs-134 pCi/L 155 182 0.85 A Cs-137 pCi/L 210 223 0.94 A Fe-59 pCi/L 211 185 1.14 A I-131 pCi/L 88.0 96.7 0.91 A Mn-54 pCi/L 169 164 1.03 A Zn-65 pCi/L 238 246 0.97 A E13708 Charcoal I-131 pCi 79.9 87.1 0.92 A E13709 AP Ce-141 pCi 60.9 42.0 1.45 N(1)

Co-58 pCi 118 107 1.11 A Co-60 pCi 218 196 1.11 A Cr-51 pCi 251 221 1.14 A Cs-134 pCi 129 118 1.09 A Cs-137 pCi 156 145.0 1.07 A Fe-59 pCi 124 120.0 1.03 A Mn-54 pCi 120 107 1.12 A Zn-65 pCi 162 160 1.01 A E13710 Soil Ce-141 pCi/g 0.123 0.103 1.19 A Co-58 pCi/g 0.254 0.263 0.97 A Co-60 pCi/g 0.493 0.483 1.02 A Cr-51 pCi/g 0.603 0.543 1.11 A Cs-134 pCi/g 0.268 0.292 0.92 A Cs-137 pCi/g 0.399 0.431 0.93 A Fe-59 pCi/g 0.320 0.296 1.08 A Mn-54 pCi/g 0.263 0.263 1.00 A Zn-65 pCi/g 0.407 0.395 1.03 A E13711 AP Sr-89 pCi 83.2 97.4 0.85 A Sr-90 pCi 12.7 12.7 1.00 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 22-04 (Page 1 of 2)

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 2022 E13712 Milk Sr-89 pCi/L 71.1 89.1 0.80 A Sr-90 pCi/L 12.0 13.6 0.88 A E13713 Milk Ce-141 pCi/L 148 161 0.92 A Co-58 pCi/L 178 189 0.94 A Co-60 pCi/L 229 260 0.88 A Cr-51 pCi/L 486 456 1.07 A Cs-134 pCi/L 220 252 0.87 A Cs-137 pCi/L 203 222 0.92 A Fe-59 pCi/L 174 173 1.01 A I-131 pCi/L 75.9 94.2 0.81 A Mn-54 pCi/L 269 282 0.95 A Zn-65 pCi/L 364 373 0.97 A E13714 Charcoal I-131 pCi 81.4 83.6 0.97 A E13715 AP Ce-141 pCi 102 91 1.12 A Co-58 pCi 118 107 1.11 A Co-60 pCi 207 147 1.41 N(2)

Cr-51 pCi 310 257 1.21 W Cs-134 pCi 148 142 1.04 A Cs-137 pCi 137 125 1.10 A Fe-59 pCi 115 98 1.18 A Mn-54 pCi 168 159 1.05 A Zn-65 pCi 240 211 1.14 A E13716 Soil Ce-141 pCi/g 0.288 0.284 1.01 A Co-58 pCi/g 0.320 0.334 0.96 A Co-60 pCi/g 0.445 0.459 0.97 A Cr-51 pCi/g 0.883 0.805 1.10 A Cs-134 pCi/g 0.410 0.446 0.92 A Cs-137 pCi/g 0.447 0.465 0.96 A Fe-59 pCi/g 0.314 0.305 1.03 A Mn-54 pCi/g 0.489 0.499 0.98 A Zn-65 pCi/g 0.666 0.660 1.01 A E13717 AP Sr-89 pCi 87.5 98.3 0.89 A Sr-90 pCi 12.6 15.0 0.84 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 (2) See NCR 22-21 (Page 2 of 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 2022 22-GrF46 AP Gross Alpha Bq/sample 0.402 1.20 0.36 - 2.04 A Gross Beta Bq/sample 0.669 0.68 0.341 - 1.022 A 22-MaS46 Soil Ni-63 Bq/kg 645 780 546 - 1014 A Tc-99 Bq/kg 526 778 545 - 1011 N(3) 22-MaSU46 Urine Cs-134 Bq/L 1.67 1.77 1.24 - 2.30 A Cs-137 Bq/L 1.50 1.56 1.09 - 2.03 A Co-57 Bq/L 4.93 5.39 3.77 - 7.01 A Co-60 Bq/L 2.13 2.06 1.44 - 2.68 A Mn-54 Bq/L 4.83 5.08 3.56 - 6.60 A U-234 Bq/L 0.142 0.0074 0.0052 - 0.0096 N(4)

U-238 Bq/L 0.0254 0.0103 0.0072 - 0.0134 N(4)

Zn-65 Bq/L 4.71 4.48 3.14 - 5.82 A 22-MaW46 Water Ni-63 Bq/L 28.6 34.0 23.8 - 44.2 A Tc-99 Bq/L 8.59 7.90 5.5 - 10.3 A 22-RdV46 Vegetation Cs-134 Bq/sample 6.61 7.61 5.33 - 9.89 A Cs-137 Bq/sample 1.50 1.52 1.06 - 1.98 A Co-57 Bq/sample 5.11 5.09 3.56 - 6.62 A Co-60 Bq/sample 0.0162 (1) A Mn-54 Bq/sample 2.42 2.59 1.81 - 3.37 A Sr-90 Bq/sample 0.684 0.789 0.552 - 1.026 A Zn-65 Bq/sample 1.44 1.47 1.03 - 1.91 A August 2022 22-MaS47 Soil Ni-63 Bq/kg 14.6 (1) A Tc-99 Bq/kg 994 1000 700 - 1300 A 22-MaW47 Water Ni-63 Bq/L 24.4 32.9 23.0 - 42.8 A Tc-99 Bq/L 1.9 (1) N(5) 25-RdV47 Vegetation Cs-134 Bq/sample 0.032 (1) A Cs-137 Bq/sample 0.891 1.08 0.758 - 1.408 A Co-57 Bq/sample 0.006 (1) A Co-60 Bq/sample 4.04 4.62 3.23 - 6.01 A Mn-54 Bq/sample 2.01 2.43 1.70 - 3.16 A Sr-90 Bq/sample 1.25 1.60 1.12 - 2.08 W Zn-65 Bq/sample 6.16 7.49 5.24 - 9.74 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) Tc-99 soil cross-checks done for TBE information only - not required (4) See NCR 22-05 (5) See NCR 22-22 (Page 1 of 1)

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

Number Value Value (a) Limits March 2022 MRAD-36 Water Am-241 pCi/L 68.3 74.6 51.2 - 95.4 A Fe-55 pCi/L 797 1140 670 - 1660 A Pu-238 pCi/L 146 147 88.4 - 190 A Pu-239 pCi/L 69.9 71.9 44.5 - 88.6 A Soil Sr-90 pCi/kg 8050 6720 2090 - 10500 A AP Fe-55 pCi/filter 148 127 46.4 - 203 A Pu-238 pCi/filter 29.9 29.6 22.3 - 36.4 A Pu-239 pCi/filter 51.6 49.7 37.2 - 60.0 A U-234 pCi/filter 59.9 67.3 49.9 - 78.9 A U-238 pCi/filter 59.0 66.7 50.4 - 79.6 A GR-A pCi/filter 95.6 94.2 49.2 - 155 A GR-B pCi/filter 71.2 66.8 40.5 - 101 A April 2022 RAD-129 Water Ba-133 pCi/L 61.7 62.9 52.3 - 69.2 A Cs-134 pCi/L 80.9 81.6 68.8 - 89.8 A Cs-137 pCi/L 37.4 36.6 32.1 - 43.3 A Co-60 pCi/L 103 97.4 87.7 - 109 A Zn-65 pCi/L 318 302 272 - 353 A GR-A pCi/L 26.9 20.8 10.4 - 28.3 A GR-B pCi/L 49.7 51.0 34.7 - 58.1 A U-Nat pCi/L 56.3 68.9 56.3 - 75.8 A H-3 pCi/L 17,000 18,100 15,800 - 19,000 A Sr-89 pCi/L 65.3 67.9 55.3 - 76.1 A Sr-90 pCi/L 42.1 42.7 31.5 - 49.0 A I-131 pCi/L 25.7 26.2 21.8 - 30.9 A September 2022 MRAD-37 Water Am-241 pCi/L 111 96.2 66.0 - 123 A Fe-55 pCi/L 850 926 544 - 1350 A Pu-238 pCi/L 62.1 52.6 31.6 - 68.2 A Pu-239 pCi/L 139.5 117 72.5 - 144 A Soil Sr-90 pCi/kg 3350 6270 1950 - 9770 A U-234 pCi/kg 1684 3350 1570 - 4390 A (2)

U-238 pCi/kg 1658 3320 1820 - 4460 N AP Fe-55 pCi/filter 71.9 122 44.5 - 195 A Pu-238 pCi/filter 38.8 29.9 22.6 - 36.7 N(1)

Pu-239 pCi/filter 14.5 13.0 9.73 - 15.7 A U-234 pCi/filter 78.0 71.5 53.0 - 83.8 A U-238 pCi/filter 79.7 70.9 53.5 - 84.6 A GR-A pCi/filter 62.8 55.5 29.0 - 91.4 A GR-B pCi/filter 70.9 64.8 39.3 - 97.9 A October 2022 RAD-131 Water Ba-133 pCi/L 76.2 79.4 66.6 - 87.3 A Cs-134 pCi/L 28.0 30.5 23.9 - 33.6 A Cs-137 pCi/L 202 212 191 - 235 A Co-60 pCi/L 52.4 51.4 46.3 - 59.1 A Zn-65 pCi/L 216 216 194 - 253 A GR-A pCi/L 19.7 16.9 8.28 - 23.7 A GR-B pCi/L 49.8 53.0 36.1 - 60.0 A U-Nat pCi/L 10.54 8.53 6.60 - 9.88 N(3)

H-3 pCi/L 13,900 15,100 13,200 - 16,600 A Sr-89 pCi/L 59.7 64.5 52.3 - 72.5 A Sr-90 pCi/L 32.9 37.3 27.4 - 43.0 A I-131 pCi/L 26.9 24.4 20.2 - 28.9 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 22-19 (2) U soil cross-checks done for TBE information only - not required (3) See NCR 22-20 (Page 1 of 1)

TABLE E.4 Analytics Environmental Radioactivity Cross Check Program Constellation Generation Solutions (2022)

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

Number Value (a) to EIS Result Value March 2022 E13643 Milk I-131 pCi/L 98.9 96.7 102 Pass Detector 4 Ce-141 pCi/L 58.6 64.6 90.7 Pass Co-58 pCi/L 160 164 97.6 Pass Co-60 pCi/L 313 302 104 Pass Cr-51 pCi/L 390 339 115 Pass Cs-134 pCi/L 168 182 92.3 Pass Cs-137 pCi/L 222 223 100 Pass Fe-59 pCi/L 185 185 100 Pass Mn-54 pCi/L 157 164 95.7 Pass Zn-65 pCi/L 231 246 93.9 Pass E13643 Milk I-131 pCi/L 96.2 96.7 99.5 Pass Detector 5 Ce-141 pCi/L 71.6 64.6 111 Pass Co-58 pCi/L 164 164 100 Pass Co-60 pCi/L 302 302 100 Pass Cr-51 pCi/L 398 339 117 Pass Cs-134 pCi/L 168 182 92.3 Pass Cs-137 pCi/L 212 223 95.1 Pass Fe-59 pCi/L 207 185 112 Pass Mn-54 pCi/L 166 164 101 Pass Zn-65 pCi/L 230 246 93.5 Pass E13644 (S5E) Water Gr-B pCi/L 224 222 101 Pass E13645 (D2) Charcoal I-131 pCi 81.9 88.2 92.9 Pass Detector 3 84.7 88.2 96.0 Pass Detector 4 82.0 88.2 93.0 Pass June 2022 E13647 Water I-131 pCi/L 112 91.2 123 Pass Detector 3 Ce-141 pCi/L 141 139 101 Pass Co-58 pCi/L 126 128 98.4 Pass Co-60 pCi/L 244 242 101 Pass Cr-51 pCi/L 314 344 91.3 Pass Cs-134 pCi/L 163 172 94.8 Pass Cs-137 pCi/L 213 204 104 Pass Fe-59 pCi/L 170 157 108 Pass Mn-54 pCi/L 243 229 106 Pass Zn-65 pCi/L 302 296 102 Pass E13647 Water I-131 pCi/L 86.2 91.2 94.5 Pass Detector 4 Ce-141 pCi/L 126 139 90.6 Pass Co-58 pCi/L 124 128 96.9 Pass Co-60 pCi/L 248 242 102 Pass Cr-51 pCi/L 358 344 104 Pass Cs-134 pCi/L 163 172 94.8 Pass Cs-137 pCi/L 217 204 106 Pass Fe-59 pCi/L 180 157 115 Pass Mn-54 pCi/L 253 229 110 Pass Zn-65 pCi/L 253 296 85.5 Pass E13649 AP Gr-B pCi 276 242 114 Pass S5E Gr-B pCi 276 242 114 Pass Gr-B pCi 275 242 114 Pass E13648 AP Ce-141 pCi 96.7 96.6 100 Pass Detector 4 Co-58 pCi 89.2 89.3 100 Pass Co-60 pCi 171 168 102 Pass Cr-51 pCi 265 239 111 Pass Cs-134 pCi 104 119 87.4 Pass Cs-137 pCi 147 142 104 Pass Fe-59 pCi 136 109 125 Pass Mn-54 pCi 170 159 107 Pass Zn-65 pCi 198 206 96.1 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

TABLE E.4 Analytics Environmental Radioactivity Cross Check Program Constellation Generation Solutions (2022)

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

Number Value (a) to EIS Result Value June 2022 E13648 AP Ce-141 pCi 101 96.6 105 Pass Detector 5 Co-58 pCi 89.3 89.3 100 Pass Co-60 pCi 169 168 101 Pass Cr-51 pCi 252 239 105 Pass Cs-134 pCi 100 119 84.0 Pass Cs-137 pCi 142 142 100 Pass Fe-59 pCi 129 109 118 Pass Mn-54 pCi 168 159 106 Pass Zn-65 pCi 211 206 102 Pass September 2022 E13650A AP Gr-B pCi 242 224 108 Pass December 2022 E13651 AP Ce-141 pCi 144 140 103 Pass Detector 4 Co-58 pCi 143 144 99.3 Pass Co-60 pCi 174 181 96.1 Pass Cr-51 pCi 287 290 99.0 Pass Cs-134 pCi 93.0 120 77.5 Pass Cs-137 pCi 134 137 97.8 Pass Fe-59 pCi 142 124 115 Pass Mn-54 pCi 162 158 103 Pass Zn-65 pCi 192 191 101 Pass E13651 AP Ce-141 pCi 146 140 104 Pass Detector 5 Co-58 pCi 140 144 97.2 Pass Co-60 pCi 180 181 99.4 Pass Cr-51 pCi 286 290 98.6 Pass Cs-134 pCi 94.5 120 78.8 Pass Cs-137 pCi 125 137 91.2 Pass Fe-59 pCi 148 124 119 Pass Mn-54 pCi 172 158 109 Pass Zn-65 pCi 199 191 104 Pass E13652 (S5E) Water Gr-B pCi/L 308 283 109 Pass E13653 (D2) Charcoal I-131 pCi 88.7 91.6 96.8 Pass Detector 3 88.5 91.6 96.6 Pass Detector 4 93.5 91.6 102.1 Pass Detector 5 89.8 91.6 98.0 Pass E13654 Milk I-131 pCi/L 104 95.1 109 Pass Detector 4 Ce-141 pCi/L 223 225 99.1 Pass Co-58 pCi/L 222 230 96.5 Pass Co-60 pCi/L 281 290 96.9 Pass Cr-51 pCi/L 433 464 93.3 Pass Cs-134 pCi/L 182 191 95.3 Pass Cs-137 pCi/L 214 219 97.7 Pass Fe-59 pCi/L 220 198 111 Pass Mn-54 pCi/L 252 252 100 Pass Zn-65 pCi/L 274 305 89.8 Pass E13654 Milk I-131 pCi/L 102 95.1 107 Pass Detector 5 Ce-141 pCi/L 228 225 101 Pass Co-58 pCi/L 226 230 98.3 Pass Co-60 pCi/L 285 290 98.3 Pass Cr-51 pCi/L 494 464 106 Pass Cs-134 pCi/L 179 191 93.7 Pass Cs-137 pCi/L 231 219 105 Pass Fe-59 pCi/L 214 198 108 Pass Mn-54 pCi/L 252 252 100 Pass Zn-65 pCi/L 282 305 92.5 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

TABLE E.5 ERA Environmental Radioactivity Cross Check Program Constellation Generation Solutions (2022)

EIS Acceptance Known (b)

Month/Year ID Number Matrix Nuclide Units Reported Ratio of ERA Evaluation Value (a)

Value to EIS Result April 2022 RAD-129 Water Ba-133 pCi/L 56.6 62.9 90.0 Pass Detector 4 Cs-134 pCi/L 81.0 81.6 99.3 Pass Cs-137 pCi/L 37.8 36.6 103 Pass Co-60 pCi/L 97.6 97.4 100 Pass Zn-65 pCi/L 293 302 97.0 Pass I-131 pCi/L 27.1 26.2 103 Pass S5E Water GR-B pCi/L 35.8 51.0 70.2 Fail(1)

September 2022 MRAD-37 AP Cs-134 pCi 270 325 83.1 Pass Detector 4 Cs-137 pCi 706 795 88.8 Pass Co-60 pCi 198 191 104 Pass Zn-65 pCi 125 120 104 Pass October 2022 RAD-131 Water Ba-133 pCi/L 75.0 79.4 94.5 Pass Detector 4 Cs-134 pCi/L 29.0 30.5 95.1 Pass Cs-137 pCi/L 212 212 100 Pass Co-60 pCi/L 50.4 51.4 98.1 Pass Zn-65 pCi/L 212 216 98.1 Pass I-131 pCi/L 25.4 24.4 104 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 (1) Passed vendor acceptance criteria, but failed NRC Resolution Test criteria

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

GEL Laboratories (H-3 & Sr-90)

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

Number Value Value (a) 2nd/2022 22-MaW46 Water Gr-A Bq/L 0.782 0.87 0.26 - 1.48 A Co-57 Bq/L 37 36.0 25.2 - 46.8 A Co-60 Bq/L 9.64 9.3 6.5 - 12.1 A Cs-134 Bq/L -0.0355 False Positive Test A Cs-137 Bq/L 7.9 7.64 5.35 - 9.93 A Mn-54 Bq/L 19.8 18.9 13.2 - 24.6 A Zn-65 Bq/L 29.3 26.2 18.3 - 34.1 A H-3 Bq/L 303 300 210 - 390 A Sr-90 Bq/L 14.9 12.9 5.5 - 10.3 A 22-RdV46 Veg Sr-90 Bq/kg 1.12 0.789 0.552 - 1.026 N(1) 4th/2022 22-MaW47 Water Gr-A Bq/L 0.978 0.871 0.261 - 1.481 A Co-57 Bq/L 30.4 30.0 21.0 - 39.0 A Co-60 Bq/L 17.8 17.0 11.9 - 22.1 A Cs-134 Bq/L 15.9 17 12.0 - 22.2 A Cs-137 Bq/L 17.8 16.80 11.8 - 21.8 A Mn-54 Bq/L -0.0317 False Positive Test A Zn-65 Bq/L 12.6 11.3 7.9 - 14.7 A H-3 Bq/L 350 395 277 - 514 A Sr-90 Bq/L 7.49 7.73 5.41 - 10.05 A 22-RdV47 Veg Sr-90 Bq/kg 1.78 1.600 1.12 - 2.08 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) Correactive Action information in IV Results & Discussion, Section G

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

Identification Reported Known Acceptance (b)

Quarter/Year Matrix Nuclide Units Evaluation Number Value Value (a) Limits 2nd/2022 MRAD-36 Water Co-60 pCi/L 2,880 2,710 2,340 - 3,110 A Cs-134 pCi/L 1,620 1,720 1,300 - 1,890 A Cs-137 pCi/L 1,130 1,120 959 - 1,270 A Mn-54 pCi/L <8.37 <71.0 <71.0 A Zn-65 pCi/L 1,320 1,220 1,090 - 1,540 A H-3 pCi/L 28,000 28,200 21,300 - 34,300 A Sr-90 pCi/L 639 628 452 - 776 A Gr-A pCi/L 74.5 79.4 29.0 - 109 A Veg Sr-90 pCi/kg 5,170 4,340 2450 - 5660 A RAD-129 Water Sr-89 pCi/L 67.6 67.9 55.3 - 76.1 A 3rd/2022 RAD-130 Water Co-60 pCi/L 79.0 72.4 65.2 - 82.1 A Cs-134 pCi/L 84.7 88.6 72.7 - 97.5 A Cs-137 pCi/L 177 170 153 - 189 A Zn-65 pCi/L 363 326 293 - 380 A H-3 pCi/L 20,200 22,100 19,400 - 24,300 A Sr-89 pCi/L 48.4 49.6 39.0 - 57.0 A Sr-89 pCi/L 47.4 49.6 39.0 - 57.0 A Sr-90 pCi/L 12.8 11.2 7.62 - 13.8 A Sr-90 pCi/L 11.9 11.2 7.62 - 13.8 A Gr-A pCi/L 54.3 60.2 31.5 - 74.8 A Gr-A pCi/L 58.8 60.2 31.5 - 74.8 A 4th/2022 MRAD-37 Water Co-60 pCi/L 1,500 1,420 1,220 - 1,630 A Cs-134 pCi/L 452 483 365 - 531 A Cs-137 pCi/L 1,220 1,250 1,070 - 1,420 A Mn-54 pCi/L <5.46 <71.0 <71.0 A Zn-65 pCi/L 145 122 109 - 154 A H-3 pCi/L 16,900 18,800 14,200 - 22,900 A Sr-90 pCi/L 283 224 161 - 277 N (1)

Gr-A pCi/L 46.6 42.7 15.6 - 58.9 A Veg Sr-90 pCi/kg 4,560 2,960 1670 - 3860 N (1)

(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) Correactive Action information in IV Results & Discussion, Section G

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

Identification Reported Known Acceptance (b)

Quarter/Year Matrix Nuclide Units Evaluation Number Value Value (a) Limits 1st/2022 E13656 Milk Sr-89 pCi/L 93.0 96.8 1.03 A Sr-90 pCi/L 8.4 12.6 0.67 A E13658 Water Co-58 pCi/L 205 193 1.06 A Co-60 pCi/L 379 355 1.07 A Cs-134 pCi/L 200 214 0.93 A Cs-137 pCi/L 265 263 1.01 A Fe-59 pCi/L 239 218 1.10 A Mn-54 pCi/L 207 193 1.07 A Zn-65 pCi/L 325 290 1.12 A 2nd/2022 E13660 Milk Sr-89 pCi/L 67.6 87.2 0.78 A Sr-90 pCi/L 10.7 14.5 0.74 A E13662 Water Co-58 pCi/L 138 128 1.07 A Co-60 pCi/L 258 242 1.07 A Cs-134 pCi/L 168 172 0.98 A Cs-137 pCi/L 212 204 1.04 A Fe-59 pCi/L 171 157 1.09 A Mn-54 pCi/L 257 229 1.12 A Zn-65 pCi/L 309 296 1.04 A 3rd/2022 E13664 Milk Sr-89 pCi/L 95.4 89.1 1.07 A Sr-90 pCi/L 8.87 13.6 0.65 A E13666 Water Co-58 pCi/L 149 148 1.01 A Co-60 pCi/L 217 204 1.07 A Cs-134 pCi/L 184 198 0.93 A Cs-137 pCi/L 179 174 1.03 A Fe-59 pCi/L 157 136 1.16 A Mn-54 pCi/L 230 221 1.04 A Zn-65 pCi/L 342 293 1.17 A 4th/2022 E13668 Milk Sr-89 pCi/L 99.3 90.4 1.10 A Sr-90 pCi/L 12.8 15.0 0.86 A E13670 Water Co-58 pCi/L 254 229 1.07 A Co-60 pCi/L 297 2,898 1.03 A Cs-134 pCi/L 171 191 0.90 A Cs-137 pCi/L 217 218 1.00 A Fe-59 pCi/L 232 197 1.18 A Mn-54 pCi/L 272 251 1.08 A Zn-65 pCi/L 336 304 1.11 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

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 2022 Prepared By Teledyne Brown Engineering Environmental Services Three Mile Island Nuclear Station Middletown, PA 17057 April 2023

Intentionally left blank Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction...................................................................................................................... 2 A. Objectives of the RGPP ....................................................................................... 3 B. Implementation of the Objectives ........................................................................ 3 C. Program Description ............................................................................................ 4 D. Characteristics of Tritium (H-3)............................................................................ 4 III. Program Description....................................................................................................... 6 A. Sample Analysis .................................................................................................. 6 B. Data Interpretation ............................................................................................... 6 IV. Results and Discussion ................................................................................................. 8 A. Groundwater Results ........................................................................................... 8 B. Surface Water Results ......................................................................................... 9 C. Storm Water Results ........................................................................................... 9 D. Precipitation Water Results ................................................................................. 9 E. Leaks, Spills, and Releases............................................................................... 10 F. Actions Taken .................................................................................................... 10 G. Missed Samples ................................................................................................ 10 i

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Three Mile Island Nuclear Station, 2022 Figures Figure A-1 Sampling Locations at the Three Mile Island Nuclear Station, 2022 Appendix B Data Tables Tables Table B-I.1 Concentrations of Tritium and Strontium in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2022 Table B-I.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 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, 2022 Table B-II.1 Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2022 Table B-II.2 Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2022 Table B-III.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2022 Appendix C Data Tables - Comparison Tables Table C-I.1 Concentrations of Tritium, Strontium in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2022 ii

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, 2022 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, 2022 Table C-II.1 Concentrations of Tritium in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2022 iii

I. Summary and Conclusions In 2006, Constellation (formerly 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 2022. During that time period 341 analyses were performed on 165 samples from 58 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 storm water samples. In the case of tritium, Constellation 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, 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 19 of 49 groundwater monitoring locations. The groundwater tritium concentrations ranged from 181 +/-

116 pCi/L to 1,670 +/- 245 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. One stormwater tritium sample was detected just above the LLD at a concentration 212 +/- 135 pCi/L. Tritium was detected in 2 of 8 precipitation water locations. The concentrations ranged from 195 +/- 115 to 575 +/- 146 pCi/L.

Hard-To-Detect analyses, including Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, U-238, Fe-55 and Ni-63 were analyzed in 2022.

Action levels trigger monitoring requirements for these analyses. Uranium-234 and U-238 were detected in one sample at concentrations of 1.44 +/- 0.51 pCi/L and 0.73 +/- 0.37 pCi/L respectively. No other nuclides were detected.

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

Conestoga Rovers & Associates (CRA) performed the initial assessment. CRA prepared a Hydrogeologic Investigation Report (HIR) for Constellation 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 a Constellation website 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 Constellation Energy Group (CEG)/GEL Laboratories on well water, surface water, storm water, and precipitation water samples collected in 2022. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides.

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 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.

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 Area of Further Evaluation (AFE)

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Gel Laboratories (subcontracted from Constellation) on samples collected in 2022.

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

Groundwater, Storm Water, and Precipitation Samples of water are collected, managed, transported and analyzed in accordance with approved procedures. Groundwater, 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 CES/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 Constellation (CES)/GEL Laboratories to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2022.

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

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

2. Concentrations of strontium in groundwater

3. Concentrations of tritium in groundwater, 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 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. Constellation 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 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 radioanalytical 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 49 locations were analyzed for tritium activity. Tritium values ranged from the detection limit to 1,670 pCi/L. (Table B-I.1, Appendix B)

Tritium Split Samples Samples from 9 locations were analyzed for tritium activity. Tritium values ranged from the detection limit to 216 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 detected above their required detection limits of 10 and 1.0 pCi/L, respectively. (Table C-I.1, Appendix C)

Gamma Emitters Samples from 49 locations were analyzed for gamma-emitting nuclides. No gamma-emitting nuclides were detected above the detection limits.

(Table B-I.2, Appendix B)

Gamma Emitters Split Samples Samples from 5 locations were analyzed for gamma-emitting nuclides. No gamma-emitting nuclides were detected above the detection limits.

(Table C-I.2, Appendix C)

Hard-To-Detect One sample was analyzed for Hard-To-Detect analyses, which included Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. Uranium-234 and U-238 were detected at 1.44 pCi/L and 0.73 pCi/L respectively. Seven locations were analyzed for Fe-55 and Ni-63. Neither Fe-55 nor Ni-63 were detected in any sample. (Table B-I.3, Appendix B)

Hard-To-Detect Split Samples Hard to detects were not analyzed on any split samples in 2022.

(Table C-I.3, Appendix C)

B. Surface Water Results No samples were collected from surface water locations in 2022.

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 Four samples from one location analyzed for tritium. Tritium activity was detected just above the detection limit in 1 of the 4 samples at a concentration of 212 pCi/L. (Table B-II.1, Appendix B)

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

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

D. Precipitation Water Results Samples were collected at 8 locations. The following analyses were performed:

Tritium Samples from 8 locations were analyzed for tritium activity. Tritium activity was detected at 2 of 8 locations. The concentrations ranged from 195 to 575 pCi/L. (Table B-III.1, Appendix B)

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

E. Leaks, Spills, and Releases There were no leaks, spills or releases in 2022.

F. Actions Taken There were no compensatory/corrective actions taken in 2022.

G. Missed Samples There were no missed samples in 2022.

APPENDIX A LOCATION DESIGNATION & DISTANCE

Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Three Mile Island Nuclear Station, 2022 Site Site Type 48S Production Potable Well EDCB Storm Water MS-1 Monitoring Well MS-2 Monitoring Well MS-3 Monitoring Well MS-4 Monitoring Well MS-5 Monitoring Well MS-7 Monitoring Well MS-8 Monitoring Well MS-20 Monitoring Well MS-21 Monitoring Well MS-22 Monitoring Well MW-1 Monitoring Well MW-2 Monitoring Well MW-TMI-1D Monitoring Well MW-TMI-2D Monitoring Well MW-TMI-3I Monitoring Well MW-TMI-4I Monitoring Well MW-TMI-4S 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 MW-TMI-9S Monitoring Well MW-TMI-10D Monitoring Well MW-TMI-10I Monitoring Well MW-TMI-10S Monitoring Well MW-TMI-12S Monitoring Well MW-TMI-13I Monitoring Well MW-TMI-14D Monitoring Well MW-TMI-14I Monitoring Well MW-TMI-16D Monitoring Well MW-TMI-18D Monitoring Well MW-TMI-19I Monitoring Well MW-TMI-20I Monitoring Well MW-TMI-21D Monitoring Well MW-TMI-21I Monitoring Well MW-TMI-21S Monitoring Well MW-TMI-22D Monitoring Well MW-TMI-22I Monitoring Well MW-TMI-22S Monitoring Well NW-A Production Well NW-B Production Well NW-C Production Well OS-14 Monitoring Well OS-16 Monitoring Well OS-18 Monitoring Well OSF Production Potable Well RW-1 Monitoring Well TM-PR-EDCB Precipitation Water TM-PR-ESE Precipitation Water TM-PR-MS-1 Precipitation Water TM-PR-MS-2 Precipitation Water TM-PR-MS-4 Precipitation Water TM-PR-MS-8 Precipitation Water TM-PR-MW-22S Precipitation Water TM-PR-RW-1 Precipitation Water A-1

Figure A - 1 Sampling Locations at the Three Mile Island Nuclear Station, 2022 A-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICALGROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A SITE DATE H-3 Sr-89 Sr-90 (Dis) (Sus) 48S 02/24/22 < 180 48S 06/01/22 < 182 48S 08/31/22 < 193 < 8.6 < 0.9 < 2.0 < 0.8 48S 11/10/22 < 185 MS-1 05/17/22 < 192 MS-2 02/23/22 < 192 MS-2 05/18/22 < 179 < 8.6 < 0.8 < 0.5 < 0.6 MS-2 08/24/22 < 182 MS-2 11/01/22 < 190 MS-3 02/23/22 < 180 MS-3 05/18/22 < 178 < 6.4 < 0.7 < 0.6 < 0.6 MS-3 08/24/22 236 +/- 125 MS-3 11/01/22 < 193 MS-4 05/20/22 < 185 MS-4 11/01/22 215 +/- 126 MS-5 02/23/22 < 174 MS-5 05/18/22 < 192 < 5.4 < 0.7 < 0.9 < 0.6 MS-5 08/24/22 < 175 MS-5 11/01/22 < 189 MS-7 02/22/22 212 +/- 119 MS-7 05/18/22 < 191 < 6.3 < 0.8 < 0.7 < 0.8 MS-7 05/18/22 DUP < 181 < 7.3 < 0.7 < 0.7 < 0.8 MS-7 08/24/22 < 195 MS-7 11/01/22 < 189 MS-7 11/01/22 DUP 249 +/- 133 MS-8 02/23/22 363 +/- 131 MS-8 05/20/22 < 184 < 5.1 < 0.6 < 0.4 1.6 +/- 0.8 MS-8 08/24/22 273 +/- 124 MS-8 11/01/22 277 +/- 131 MS-20 02/23/22 238 +/- 123 MS-20 05/20/22 < 182 < 6.3 < 0.9 < 0.7 3.3 +/- 1.2 MS-20 08/23/22 340 +/- 130 < 1.0 < 0.8 MS-20 11/01/22 424 +/- 139 MS-21 02/23/22 < 175 MS-21 05/20/22 < 182 < 7.7 < 0.6 < 8.7 < 4.6 MS-21 08/23/22 203 +/- 132 < 0.5 < 1.7 MS-21 11/01/22 < 192 MS-22 02/23/22 871 +/- 165 MS-22 05/24/22 451 +/- 129 < 9.9 < 0.9 < 0.9 < 1.2 MS-22 08/23/22 426 +/- 133 MS-22 11/02/22 334 +/- 129 MW-1 05/17/22 < 187 MW-2 05/24/22 < 189 MW-TMI-1D 05/24/22 < 194 MW-TMI-2D 05/17/22 < 189 MW-TMI-2D 05/17/22 DUP < 187 MW-TMI-3I 02/22/22 < 188 MW-TMI-3I 05/24/22 < 187 < 5.0 < 0.6 < 0.9 < 1.3 MW-TMI-3I 05/24/22 DUP < 189 < 5.8 < 0.6 < 0.9 < 1.2 MW-TMI-3I 08/24/22 205 +/- 124 BOLD Values = Unable to meet detection limis due to high solids content B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICALGROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A SITE DATE H-3 Sr-89 Sr-90 (Dis) (Sus)

MW-TMI-3I 11/01/22 < 197 MW-TMI-4I 05/17/22 < 187 MW-TMI-4S 05/17/22 < 192 MW-TMI-6D 02/22/22 < 168 MW-TMI-6D 05/18/22 < 192 < 6.1 < 0.7 < 0.9 < 1.3 MW-TMI-6D 08/24/22 < 192 MW-TMI-6D 11/01/22 323 +/- 131 MW-TMI-6I 02/22/22 233 +/- 124 MW-TMI-6I 05/18/22 221 +/- 130 < 6.5 < 0.8 < 0.5 < 0.8 MW-TMI-6I 08/24/22 < 191 MW-TMI-6I 11/01/22 339 +/- 134 MW-TMI-7S 05/20/22 < 172 MW-TMI-8S 05/17/22 < 189 MW-TMI-9I 05/17/22 < 187 MW-TMI-9S 05/17/22 < 191 MW-TMI-10D 05/18/22 < 181 MW-TMI-10I 05/18/22 415 +/- 129 MW-TMI-10I 11/01/22 436 +/- 131 MW-TMI-10S 05/18/22 < 180 MW-TMI-10S 05/18/22 DUP 193 +/- 122 MW-TMI-10S 11/01/22 276 +/- 131 MW-TMI-12S 02/23/22 < 176 MW-TMI-12S 05/20/22 < 183 < 5.9 < 0.8 < 0.4 < 1.0 MW-TMI-12S 08/24/22 < 186 MW-TMI-12S 11/01/22 < 187 MW-TMI-13I 05/17/22 < 195 MW-TMI-13I 11/01/22 445 +/- 140 MW-TMI-14D 05/17/22 205 +/- 124 MW-TMI-14D 11/01/22 323 +/- 135 MW-TMI-14D 11/01/22 DUP 306 +/- 133 MW-TMI-14I 05/17/22 < 191 MW-TMI-14I 11/01/22 < 200 MW-TMI-16D 05/17/22 361 +/- 126 MW-TMI-18D 05/17/22 204 +/- 130 MW-TMI-19I 05/24/22 < 185 MW-TMI-19I 05/24/22 DUP < 185 MW-TMI-20I 05/18/22 < 186 MW-TMI-21D 05/24/22 1310 +/- 198 MW-TMI-21D 11/02/22 1660 +/- 242 MW-TMI-21I 05/24/22 285 +/- 129 MW-TMI-21I 11/02/22 302 +/- 140 MW-TMI-21S 02/23/22 342 +/- 125 MW-TMI-21S 05/24/22 341 +/- 129 < 9.5 < 0.9 < 1.2 < 1.1 MW-TMI-21S 08/23/22 205 +/- 130 MW-TMI-21S 11/02/22 363 +/- 134 MW-TMI-22D 05/24/22 1300 +/- 216 MW-TMI-22D 11/02/22 1670 +/- 245 MW-TMI-22I 05/24/22 505 +/- 141 MW-TMI-22I 11/02/22 329 +/- 132 MW-TMI-22S 02/23/22 395 +/- 127 BOLD Values = Unable to meet detection limis due to high solids content B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICALGROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gr-A Gr-A SITE DATE H-3 Sr-89 Sr-90 (Dis) (Sus)

MW-TMI-22S 05/24/22 395 +/- 133 < 9.5 < 0.9 6.8 +/- 1.5 < 1.1 MW-TMI-22S 08/23/22 251 +/- 114 < 1.4 < 0.6 MW-TMI-22S 11/02/22 297 +/- 125 NW-A 06/01/22 < 171 NW-A 11/16/22 312 +/- 125 NW-B 03/01/22 < 184 NW-B 08/31/22 256 +/- 125 < 9.7 < 0.9 < 1.3 < 0.8 NW-B 11/16/22 < 171 NW-C 06/01/22 476 +/- 133 NW-C 11/16/22 436 +/- 128 OS-14 02/23/22 181 +/- 116 OS-14 05/20/22 < 182 < 2.7 < 0.8 < 0.7 < 1.0 OS-14 08/24/22 < 169 OS-14 08/24/22 DUP < 183 OS-14 11/01/22 189 +/- 123 OS-16 02/23/22 260 +/- 125 OS-16 05/18/22 < 174 < 5.4 < 0.6 < 0.4 < 1.0 OS-16 08/24/22 < 175 OS-16 11/01/22 248 +/- 131 OS-18 05/24/22 < 179 OSF 02/24/22 202 +/- 126 OSF 06/01/22 < 193 < 7.7 < 1.0 < 1.9 < 0.7 OSF 08/31/22 < 175 OSF 11/10/22 < 174 RW-1 02/23/22 < 173 RW-1 05/18/22 < 196 < 6.4 < 0.7 < 0.7 < 0.6 RW-1 08/23/22 < 181 RW-1 08/23/22 DUP < 190 RW-1 11/01/22 < 188 BOLD Values = Unable to meet detection limis due to high solids content B-3

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 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 06/01/22 < 16 < 29 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 MS-1 05/17/22 < 17 < 35 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 2 < 2 < 11 < 4 MS-2 05/18/22 < 15 < 19 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 8 < 3 MS-3 05/18/22 < 18 < 23 < 2 < 2 < 5 < 3 < 5 < 2 < 4 < 2 < 2 < 10 < 4 MS-4 05/20/22 < 16 < 38 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 9 < 3 MS-5 05/18/22 < 16 < 37 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 9 < 3 MS-7 05/18/22 < 15 < 16 < 2 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 MS-7 DUP 05/18/22 < 18 < 43 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 2 < 2 < 9 < 3 MS-8 05/20/22 < 11 27 +/- 18 < 1 < 1 < 3 < 1 < 3 < 1 < 2 < 1 < 1 < 8 < 2 MS-20 05/20/22 < 16 < 15 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 11 < 3 MS-21 05/20/22 < 17 < 34 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 11 < 4 MS-22 05/24/22 < 16 < 16 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 12 < 4 MW-1 05/17/22 < 17 < 33 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 2 < 2 < 11 < 4 MW-2 05/24/22 < 18 < 33 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 10 < 4 MW-TMI-1D 05/24/22 < 16 < 17 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 10 < 4 B-4 MW-TMI-2D 05/17/22 < 14 < 32 < 2 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 MW-TMI-2D DUP 05/17/22 < 14 < 15 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 MW-TMI-3I 05/24/22 < 11 < 19 < 1 < 1 < 2 < 1 < 2 < 1 < 2 < 1 < 1 < 7 < 2 MW-TMI-3I DUP 05/24/22 < 16 < 16 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 10 < 3 MW-TMI-4I 05/17/22 < 14 < 17 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 MW-TMI-4S 05/17/22 < 15 < 31 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 MW-TMI-6D 05/18/22 < 25 < 49 < 3 < 4 < 6 < 3 < 6 < 3 < 6 < 3 < 3 < 15 < 5 MW-TMI-6I 05/18/22 < 16 < 32 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 9 < 3 MW-TMI-7S 05/20/22 < 16 < 37 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 11 < 4 MW-TMI-8S 05/17/22 < 16 < 37 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 10 < 4 MW-TMI-9I 05/17/22 < 18 < 31 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 11 < 4 MW-TMI-9S 05/17/22 < 14 < 15 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 MW-TMI-10D 05/18/22 < 14 < 16 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 MW-TMI-10I 05/18/22 < 26 < 29 < 3 < 3 < 5 < 3 < 6 < 4 < 5 < 3 < 3 < 14 < 5 MW-TMI-10S 05/18/22 < 16 < 16 < 2 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 2 MW-TMI-10S DUP 05/18/22 < 16 < 18 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 8 < 3 MW-TMI-12S 05/20/22 < 16 < 19 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 10 < 3 MW-TMI-13I 05/17/22 < 17 < 29 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 10 < 4 MW-TMI-14D 05/17/22 < 11 < 20 < 1 < 1 < 2 < 1 < 2 < 1 < 2 < 1 < 1 < 7 < 3 MW-TMI-14I 05/17/22 < 11 < 17 < 1 < 1 < 2 < 1 < 2 < 1 < 2 < 1 < 1 < 6 < 2 MW-TMI-16D 05/17/22 < 14 < 14 < 2 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 MW-TMI-18D 05/17/22 < 14 < 24 < 2 < 1 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 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-19I 05/24/22 < 15 < 17 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 MW-TMI-19I DUP 05/24/22 < 16 < 16 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 10 < 3 MW-TMI-20I 05/18/22 < 14 < 28 < 1 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 MW-TMI-21D 05/24/22 < 15 < 15 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 13 < 4 MW-TMI-21I 05/24/22 < 17 < 35 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 13 < 5 MW-TMI-21S 05/24/22 < 12 < 11 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 10 < 3 MW-TMI-22D 05/24/22 < 17 < 21 < 2 < 2 < 5 < 2 < 4 < 2 < 4 < 2 < 2 < 14 < 5 MW-TMI-22I 05/24/22 < 17 < 30 < 2 < 2 < 5 < 2 < 3 < 2 < 3 < 2 < 2 < 13 < 5 MW-TMI-22S 05/24/22 < 15 < 16 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 12 < 5 MW-TMI-22S 08/23/22 < 13 < 26 < 1 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 NW-A 06/01/22 < 16 < 33 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 9 < 4 NW-B 08/31/22 < 17 < 17 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 2 < 2 < 13 < 4 NW-C 06/01/22 < 13 < 27 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 OS-14 05/20/22 < 14 < 15 < 2 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 OS-16 05/18/22 < 13 < 13 < 1 < 1 < 3 < 1 < 3 < 2 < 3 < 2 < 1 < 10 < 3 B-5 OS-18 05/24/22 < 14 < 16 < 2 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 9 < 3 OSF 06/01/22 < 16 < 38 < 2 < 2 < 4 < 2 < 4 < 2 < 3 < 2 < 2 < 9 < 3 RW-1 05/18/22 < 12 < 15 < 1 < 1 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 7 < 2

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, 2022 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 48S 02/24/22 < 0.19 < 0.04 < 0.13 < 0.19 < 0.05 1.44 +/- 0.51 < 0.16 0.73 +/- 0.37 MS-3 05/18/22 < 163 < 4.1 MS-5 05/18/22 < 87 < 4.1 MS-8 05/20/22 < 182 < 4.5 MW-TMI-6D 05/18/22 < 196 < 3.5 MW-TMI-6I 05/18/22 < 129 < 4.2 OS-14 05/20/22 < 80 < 4.2 OS-16 05/18/22 < 196 < 4.3 B-6

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATES H-3 EDCB 02/03/22 - 03/30/22 212 +/- 135 EDCB 04/27/22 - 06/30/22 < 183 EDCB 07/27/22 - 09/29/22 < 171 EDCB 11/03/22 - 12/29/22 < 169 B-7

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2022 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 02/03/22 - 03/30/22 < 27 < 52 < 3 < 3 < 8 < 4 < 8 < 3 < 5 < 4 < 4 < 13 < 5 EDCB 04/27/22 - 06/30/22 < 14 < 15 < 2 < 2 < 3 < 2 < 3 < 2 < 3 < 2 < 2 < 8 < 3 EDCB 07/27/22 - 09/29/22 < 18 < 33 < 2 < 2 < 4 < 2 < 5 < 2 < 4 < 2 < 2 < 9 < 3 EDCB 11/03/22 - 12/29/22 < 18 < 38 < 2 < 2 < 4 < 2 < 4 < 2 < 4 < 2 < 2 < 9 < 3 B-8

TABLE B-III.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2022 COLLECTION SITE DATE H-3 TM-PR-EDCB 03/11/22 < 194 TM-PR-EDCB 06/29/22 < 174 TM-PR-EDCB 09/22/22 < 189 TM-PR-EDCB 12/21/22 < 169 TM-PR-ESE 02/22/22 < 187 TM-PR-ESE 05/17/22 < 190 TM-PR-ESE 08/23/22 < 193 TM-PR-ESE 11/01/22 < 164 TM-PR-MS-1 02/22/22 < 187 TM-PR-MS-1 05/17/22 < 184 TM-PR-MS-1 08/23/22 < 199 TM-PR-MS-1 11/01/22 < 169 TM-PR-MS-2 02/22/22 < 187 TM-PR-MS-2 05/17/22 < 187 TM-PR-MS-2 08/23/22 < 196 TM-PR-MS-2 11/01/22 < 159 TM-PR-MS-4 02/22/22 < 193 TM-PR-MS-4 05/17/22 < 181 TM-PR-MS-4 08/23/22 < 192 TM-PR-MS-4 11/01/22 < 165 TM-PR-MS-8 02/22/22 < 195 TM-PR-MS-8 05/17/22 195 +/- 115 TM-PR-MS-8 08/23/22 < 194 TM-PR-MS-8 11/01/22 < 180 TM-PR-MW-22S 02/22/22 575 +/- 146 TM-PR-MW-22S 05/17/22 346 +/- 122 TM-PR-MW-22S 08/23/22 264 +/- 123 TM-PR-MW-22S 11/01/22 289 +/- 118 TM-PR-RW-1 02/22/22 < 187 TM-PR-RW-1 05/17/22 < 180 TM-PR-RW-1 08/23/22 < 184 TM-PR-RW-1 11/01/22 < 169 B-9

Intentionally left blank APPENDIX C DATA TABLES COMPARISON LAB

Intentionally left blank TABLE C-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE DATE H-3 Sr-89 Sr-90 Gr-A GEL MS-7 02/22/22 < 126 MS-7 05/18/22 < 149 < 0.8 < 0.6 < 3.1 MS-7 11/01/22 < 139 MW-TMI-2D 05/17/22 < 158 MW-TMI-3I 05/24/22 184 +/- 102 < 1.1 < 0.7 < 3.3 MW-TMI-6I 02/22/22 216 +/- 96 MW-TMI-10S 05/18/22 198 +/- 113 MW-TMI-14D 11/01/22 < 137 MW-TMI-19I 05/24/22 < 142 OS-14 08/24/22 < 126 RW-1 08/23/22 < 137 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, 2022 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 MS-7 05/18/22 < 5 < 18 < 7 < 8 < 12 < 16 < 8 < 7 < 6 < 11 < 28 MW-TMI-2D 05/17/22 < 10 < 22 < 10 < 8 < 15 < 20 < 10 < 8 < 8 < 11 < 35 MW-TMI-3I 05/24/22 < 6 < 19 < 6 < 8 < 14 < 12 < 7 < 7 < 7 < 65 < 23 MW-TMI-10S 05/18/22 < 7 < 25 < 7 < 9 < 17 < 12 < 10 < 7 < 8 < 11 < 35 MW-TMI-19I 05/24/22 < 6 < 11 < 5 < 6 < 12 < 8 < 6 < 5 < 5 < 63 < 19 C-2

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 NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA No samples collected or analyzed for hard to detects in 2022 C-3

TABLE C-II.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2022 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LAB SITE DATE H-3 GEL TM-PR-MS-2Q 03/11/22 < 113 06/29/22 < 172 09/22/22 < 148 12/21/22 < 169 C-4