ML15125A023

Three Mile Island, Units 1 and 2 - 2014 Annual Radiological Environmental Operating Report

ML15125A023
Person / Time
Site:	Three Mile Island
Issue date:	04/30/2015
From:	Haaf T P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
TM1-15-053
Download: ML15125A023 (177)

Text

A Exelon Generation, Three Mile Island Unit 1 Route 441 South P.O. Box 480 Middletown, PA 17057 717-948-8000 Office www.exeloncorp.com April 30, 2015 TM1-15-053 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION UNIT 1 AND UNIT 2 RENEWED OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR 73 DOCKET NOS. 50-289 AND 50-320

SUBJECT:

2014 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT In accordance with TMI Technical Specification 6.9.3.1, TMI-2 Technical Specifications 6.8.1.1, enclosed is the Annual Radiological Environmental Operating Report covering the time period of January 1 through December 31, 2014, for the Three Mile Island Nuclear Station.Please contact Laura Weber of TMI-Chemistry at (717) 948-8947 if you have questions regarding this submittal.

Sincerely, Plant Manager TPH/LKW/dam Attachments/Enclosures cc: Region 1 Administrator TMI Senior Resident Inspector TMI-1 Senior Project Manager TMI-2 Project Manager GPU Nuclear Cognizant Officer Department of Environmental Protection, Bureau of Radiation Protection A~Q 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 2014 Prepared By Teledyne Brown Engineering Environmental Services A" Exeton Generation, Three Mile Island Nuclear Station Middletown, PA 17057 April 2015 I Intentionally left blank Table Of Contents I. Sum m ary and Conclusions

..............................................................................................

1 I1. Introduction

.....................................

3........A. Objectives of the REM P .................................................................................

3 B. Im plem entation of the Objectives

....................................................................

4 Ill. Program Description

..................................................................................................

4 A. Sam ple Collection

..........................................................................................

4 B. Sam ple Analysis .............................................................................................

6 C. Data Interpretation

..........................................................................................

7 D. Program Exceptions

........................................................................................

8 E. Program Changes ........................................................................................

12 IV. Results and Discussion

..........................................................................................

12 A. Aquatic Environm ent ...................................................................................

12 1. Surface W ater ....................................................................................

12 2. Drinking W ater ....................................................................................

13 3. Effluent W ater ....................................................................................

14 4. Storm W ater .....................................................................................

15 5. Ground W ater ....................................................................................

15 6. Fish ...................................................................................................

15 7. Sedim ent .............................................................................................

16 B. Atm ospheric Environm ent .............................................................................

16 1. Airborne Particulates

..........................................................................

16 a. Air Particulates

.........................................................................

16 b. Airborne Iodine ........................................................................

17 2. Terrestrial

..........................................................................................

17 a. M ilk ...........................................................................................

17 b. Food Products ........................................................................

18 C. Am bient Gam m a Radiation

...........................................................................

19 D. Land Use Survey ...........................................................................................

19 E. Radiological Im pact of TM INS Operations

....................................................

20 F. Errata Data ...................................................................................................

27 G. Summary of Results -Inter-laboratory Comparison Program ....................

27 V. References

...................................................................................................................

30 i Appendices Appendix A Tables 'Table A-1 Appendix B Tables Table B-1 Table B-2 Table B-3 Figures Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Radiological Environmental Monitoring Report Summary I Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2014 Location Designation, Distance & Direction And Sample Collection

&Analytical Methods Location Designation and Identification System for the Three Mile Island Nuclear Station Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2014 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2014 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2014 Data Tables and Figures -Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.ii Table C-I1.1 Table C-11.2 Table C-11.3 Table C-11.4 Table C-111.1 Table C-111.2 Table C-IV. 1 Table C-IV.2 Table C-V.1 Table C-VI.1 Table C-VI.2 Table C-VI.3 Table C-VII.1 Table C-VIII.1 Table C-VIII.2 Table C-VIII.3 Table C-IX. 1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concpntrations of Tritium in Drinking Water Samples Cqllected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gross Beta, 1-131, Tritium, and Strontium in Effluent Water Samples for Station K1-1 Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Strontium in Predator and Bottom Feeder (Fish)Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.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, 2014.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.iii Table C-X.1 Table C-X.2 Table C-X.3 Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Figure C-7 Figure C-8 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-11.1 Quarterly OSLD Results for Three Mile Island Nuclear Station, 2014.Mean Quarterly OSLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2014.Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2014.Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2014.Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2014.Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2014.Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2014.Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2014.Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2014.Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 -2014.Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2014.Data Tables and Figures -Comparison Laboratory Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2014.Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Iodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.I iv Table D-Ill.1 Table D-IV.1 Table D-V. 1 Table D-V.2 Table D-VI.1 Figures Figure D-1 Figure D-2 Appendix E Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2014.Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2014.Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Teledyne Brown Engineering, 2014 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2014 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Environmental, Inc., 2014 Annual Radiological Groundwater Protection Program Report (ARGPPR)v Intentionally Left Blank vi I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Three Mile Island Nuclear Station (TMINS) by Exelon covers the period 1 January 2014 through 31 December 2014. During that time period, 1,931 analyses were performed on 1,325 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 1-131. Drinking and effluent water samples were also analyzed for concentrations of gross beta. Effluent water samples were also analyzed for concentrations of Sr-89 and Sr-90. All groundwater, precipitation water and storm water results are now being reported in the ARGPPR, Appendix G. No Sr-89 and Sr-90 activities were detected.lodine-131 and gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in four surface water samples and monthly effluent water samples was due to TMINS activities or releases.

No other fission or activation products potentially attributed to TMI liquid releases were detected.Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides.

Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected.

No fission or activation products were detected in fish samples. Cesium-1 37 was not detected in any sediment samples. Occasionally Cs-137 is detected at very low levels (just above LLD) and is not distinguishable from background levels.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 Be-7 was detected at levels consistent with those detected in previous years. No other activation products were detected.High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity for 1-131.Cow milk samples were analyzed for concentrations of 1-131, gamma emitting nuclides, Sr-89 and Sr-90. One milk sample was initially positive for 1-131.Upon further investigation, recounting the sample twice showed an increase in activity, which is not congruent with 1-131 decay. Additionally, a gamma spectroscopy analysis was performed on the 1-131 sample, which determined that K-40 was the interfering isotope. No Sr-89, Sr-90 activities were detected.Concentrations of naturally occurring K-40 were consistent with those detected in previous years. Occasionally Sr-90 activities are detected and are consistent with those detected in previous years and were attributed to fallout from nuclear weapons testing. No other fission or activation products were found. No Sr-90 was detected in milk samples for this year.

Food Product samples were analyzed for concentrations of gamma emitting nuclides (including 1-131) and Sr-90. Strontium-90 activity was detected in both the indicator and control samples. This was a result of plant uptake of Sr-90 in soil as a result of past nuclear weapons testing. Concentrations of naturally occurring Be-7 and K-40 were consistent with those detected in previous years.No other fission or activation products were detected.

I Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued.

This change resulted in a slight change in process and reporting of quarterly results. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

In conclusion, radioactive materials related to TMINS operations were detected in environmental samples, but the measured concentrations were low and consistent with measured effluents.

The environmental sample results verified that the doses received by the public from TMINS effluents in 2014 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 2014 did not have any adverse effects on the health of the public or on the environment.

II. Introduction The Three Mile Island Nuclear Station (TMINS), consisting of two pressurized water reactors (PWR), is located on the northern end of Three Mile Island in the Susquehanna River approximately

2.5 miles

south of Middletown in Lpndonderry Township, Dauphin County, Pennsylvania.

TMI-1 is owned and operated by Exelon and became operational in 1974. TMI-2 is operated by GPU Nuclear, Inc. and owned by Metropolitan Edison (50%), Pennsylvania Electric (25%) and Jersey Central Power & Light (25%). TMI-2 became operational in 1978 and was shut down following the 1979 accident.

At the end of 1993 TMI-2 was placed in a condition called Post-Defueling Monitored Storage. TMI-2 is maintained by Exelon under contract with GPU Nuclear.A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Landauer and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2014 through 31 December 2014.A. Objective 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 inplant 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 exposutre 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.

Ill. Program Description A. Sample Collection Samples for the TMINS REMP were collected for Exelon by Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used by RMC to obtain environmental samples for the TMINS REMP in 2014. 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 RMC 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 (KM-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 now being 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 KM-3). In addition, one sediment sample was collected annually at the EDCB. Location A1-3 was the control.Atmospheric Environment The atmospheric environment was evaluated Ihy performing radiological analyses on samples of air particulates, airborne iodine, milk and food product. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (A3-1, E1-2, FI-3, G2-1, H3-1, M2-1 and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached.

The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product. Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K15-3 and P4-1)from March through November, and monthly from December through February.

The control location was K1 5-3. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory.

Food products were collected monthly at three locations (B10-2, E1-2 and H 1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2 and H 1-2). B10-2 was the control location for both annual and monthly sampling.

Five different kinds of vegetation samples and ten different kinds of vegetation leaves were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued.

This change may result in a step change in readings, up or down, depending on site characteristics.

The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

The OSLDs were placed at locations on and around the TMINS site as follows: A site boundary ring consisting of 19 locations (A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, 1-1I, 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.I I An indicator rinq consisting of 60 locations (A3-1, A5-1, A9-3, B1-1, 12-1, 85-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, LI-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, Lb5-1, N15-2, Q15-1 and R1 5-1) 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-22 1/2 degree sectors around the site, where estimated annual dose from TMINS, if any, would be most significant;

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

4. And near the closest dwelling to the vents in the prevailing downwind direction.

Each station has two A120 3:C Optically Stimulated Luminescence Dosimeters enclosed in plastic placed at each location in a frame located approximately three to six 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 Midwest Labs to analyze the environmental samples for radioactivity for the TMINS REMP in 2014. 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 1-131 in surface, drinking and effluent water, air, milk and food products.5. Concentrations of strontium in effluent water, fish, milk and food products.6. Ambient gamma radiation levels at various site environs.C. Data Interpretation Data were compared to previous years' operational data for consistency and trending.

In addition, comparison to pre-operational data is sometimes made. For the purpose of this report, TMINS was considered operational at initial criticality.

Several factors were important in the interpretation of the data: 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity.

All analyses were designed to achieve the required TMINS detection capabilities for environmental sample analysis.The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity.

Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity~was not detected.Gamma spectroscopy results for each type of sample were grouped as follows: For surface, drinking, and effluent water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.For fish eight nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134 and Cs-137 were reported.For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were reported.For air particulate eight nuclides, Be-7, Mn-54, Co-58, Co-60, Nb-95, Zn-95, Cs-134 and Cs-137 were reported.For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-140 and La-140 were reported.For food products five nuclides, Be-7, K-40, 1-131, Cs-134 and Cs-137 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 2014 the TMINS REMP had a sample recovery rate in excess of 99%.Issue Reports (IR) were initiated to document significant exceptions and missing samples. All exceptions are listed below: AIR E2-1, E2-1Q 1. During the sampling period 2/7/14 to 2/14/14, the E1-2 pump malfunctioned but the timer continued to operate. Per procedure, the sample was invalid. The QC sample was sent to the primary lab for analysis.

Station E1-2 pump was replaced on 2/14/14. (IR 1662133)

M2-1 2. During the sampling period 3/6/14 to 3/12/14, the pump malfunctioned but the timer continued to operate. Per procedure, the sample was invalid. The pump was repaired and installed on 3/13/14. (IR 1662133)H3-1 3. For the sampling period 5/7/14 to 5/15/14, the sampler had a low run time and air volume due to power interruptions from a breaker trip.Per procedure, sample was still valid and sent to the lab for analysis.Offsite lab still achieved required LLD for iodine sampling and particulate results were normal. (IR 488572)A3-1 4. For the sampling period 6/5/14 to 6/11/14, the timer was found reset for unknown reason. Per procedure, the sample was not valid and was not sent for analysis.

The timer is currently functioning and the sampler was returned to service. (IR 1670228)For the sampling period 6/11/14 to 6/19/14, the sample volume was lower than expected probably due to power interruptions from thunderstorms.

Per procedure the sample was still valid and was sent for analysis. (IR 1670228)F1-3 5. For the sampling period 6/25/14-7/3/14, the sampler was found not operating with the breaker tripped. The pump and timer were not operating.

The sample volume was insufficient.

The samples were not valid and were not sent for analysis.

The pump was replaced on 7/4/14 and the sampler was returned to service. (IR 2115414)For the sampling period 7/3/14-7/10/14, there was a lower volume due to pump replacement on 7/4/14. Samples were valid and sent for analysis.(IR 2115414)E1-2Q 6. For the sampling period 7/17/14-7/24/14, the sampler was found with the air intake coupler sheared off due to a fallen tree limb. Per procedure, the sample volume was insufficient, and the samples were not valid. They were not sent for analysis.

The sample station was repaired and the sampler was returned to service.(IR 2423641)A3-1 7. For the sampling periods 8/21/14-8/28/14 and 8/29/14-9/4/14, the air samples had low volumes due to a breaker tripped due to a pump malfunction.

Per procedure, samples were valid and sent to lab for analysis.

The pump was replaced on 8/29/14 and returned to service.(IR 2423641)

M2-1 8. The sampler was found not running and did not operate due to a faulty breaker which required repair. This impacted two sampling periods.For 11/20/14 to 11/26/14, the sample volume collected was sufficient per procedure, and the samples weye valid and sent for analysis.

For 11/26/14 to 12/4/14, the sample volume was insufficient, and the samples were not valid per procedure.

They were not sent to the laboratory for analysis.

The sampler was repaired and returned to service on 12/4/14. (IR 2458509)WATER 1. J1-2 Numerous hourly samples missed due to ice in the sampling tubing and river ice dislodging/submerging sample tubing anchor and buoy.(IR 1617591/1662133) 12/31/13-1/7/14, 38 samples missed, sufficient volume, no grab required 1/7/14-1/14/14, 44 samples missed, sufficient volume, no grab required 1/14/14-1121/14, 22 samples missed, sufficient volume, no grab required 1/21/14-1/28/14, all but 1 sample missed, insufficient sample, grab sample required 1/28/14-2/4/14, 3L of sample collected, no grab sample taken due to hazardous conditions 2/4/14-2/11/14, all but 29 samples missed, insufficient sample, grab sample required 2/11/14-2/18/14, 77 samples missed, sufficient volume, no grab required 2/18/14-2/25/14, 21 samples missed, sufficient volume, no grab required 2/25/14-3/5/14, 117 samples missed, sufficient volume, no grab required 3/5/14-3/11/14, 17 samples missed, sufficient volume, no grab required 3/11/14-3/18/14, 30 samples missed, sufficient volume, no grab required 3/18/14-3/25/14, 20 samples missed, sufficient volume, no grab required 3/25/14-4/1/14, 27 samples missed, sufficient volume, no grab required

2. G15-2 During sampling period 2/25/14 to 3/5/14, sampler had an error, per data logger FLOAT/WEIGHT TRIPPED, 119 samples were collected.

Sufficient sample volume was collected and no grab sample required.During sampling period 3/5/14 to 3/11/14, sampler was found with no LCD on ISCO and unable to retrieve data from data logger. The cause for the malfunction is not known. The electronics were replaced and the unit was calibrated on 3/11/14. Sufficient sample volume was collected and no grab sample required. (IR 1662133)3. A3-2 Due to Swatara Creek being frozen over could not break ice and collect grab sample for 1/21/14-1/28/14 sampling period. January composite will consist of 3 rather than 4 samples. (IR 1617591)4. Q9-1 Drinking Water For the sampling period 6/24/14-7/1/14, No weekly sample was available and a grab sample was collected.

The suction strainer was found not submerged in the source bucket. Suspect strainer did not reseat in source water bucket after sample collection on 6/24/14.During previous weekly sample collection the regular TMI REMP sampler was on vacation.

Backup sampler was coached to self check and ensure first sample after collection operates correctly.

A supplier FMS observation was submitted to document inadequate human performance. (IR 2115414)5. G15-2 For the sampling periods 7/22/14-7/29/14 and 7/29/14-8/5/14, there were low collection volumes in the compositor.

Sufficient sample was collected for analyses and no grab samples were required.

The lost volume was due to ISCO hose problems and the hose was replaced on 7/30/14. (IR 2423641)Milk 1. K15-3 Control The 7/23/14 sample initially showed activity for 1-131. The sample was recounted two days later and again the next day. Both recounts showed an increase in activity.

These results are not congruent with normal 1-131 decay. A gamma scan was then performed and K-40 was detected.

The non-decaying activity was attributed to this naturally occurring isotope. No 1-131 analysis result is available for this sample.

Dosimeter 1. A5-1 New pole recently installed.

Old pole still standing but third quarter dosimeters not attached/found.

The dosimeters were presumably removed and discarded by utility personnel during new pole installation.

Fourth quarter dosimeters mounted on newly installed pole. (IR 2384588)2. E5-1 New pole recently installed.

Per personnel (who were present) old pole will be removed. Fourth quarter dosimeters mounted on newly installed pole instead. (IR 2384588)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 No program changes for 2014.IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken weekly from a continuous sampler at two locations (J1-2 and Q9-1) and weekly grab samples from one location (A3-2). Weekly samples were composited on a monthly schedule.

Of these locations only J1-2 located downstream could be affected by TMINS' effluent releases.

The following analyses were performed:

Tritium Monthly samples from J1-2 and Q9-1 were analyzed for tritium activity (Table C-1.1, Appendix C). Positive tritium activity was detected in four of 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 291 to 2,280 pCi/l. The increased tritium concentrations detected were a result of TMINS releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations.

The indicator surface water sample is taken just downstream of the liquid discharge outfall where mixing of liquid effluents with the river water is incomplete.

More complete mixing is not achieved until liquid effluents pass over the York Haven Dam. This water is normally not consumed by humans. The concentrations detected were well below any regulatory limits (Figures C-1 and C-2, Appendix C).Iodine Monthly samples from location A3-2 were analyzed for 1-131 activity (Table C-1.2, Appendix C). 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.Gamma Spectrometrv Locations J1-2 and Q9-1 were analyzed for gamma emitting nuclides (Table C-1.3, 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-I1.1, Appendix C). Gross beta activity was detected in 22 of 36 samples. The concentrations ranged from 1.9 to 4.2 pCi/l. Concentrations detected were consistent with those detected in previous years (Figure C-3, Appendix C).Iodine Monthly samples from all locations were analyzed for concentrations of 1-131 (Table C-11.2, Appendix C). lodine-131 activity was not detected in any samples.Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was not detected in any samples (Figures C-4, Appendix C).Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.4, Appendix C). All nuclides were less than the MDC.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 (Tables C-111.1, Appendix C). Gross beta was detected in all 12 samples. The concentrations ranged from 2.8 to 7.0 pCi/l. Concentrations detected were consistent with those detected in previous years.Iodine-1 31 Monthly samples from location K1-1 were analyzed for concentrations of 1-131 (Tables C-111.1, Appendix C). lodine-131 was not detected in any of the samples.Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-111.1, Appendix C). Tritium activity was detected in 4 of 12 samples. The concentrations ranged from 2,300 to 27,000 pCi/I. The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations.

These results were from the liquid discharge mixing basin. The concentrations detected agree with those obtained from the TMINS Effluent Monitoring Program.The concentrations were well below any regulatory limits. (Figure C-4, Appendix C)Strontium Semiannual composite samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-I11.1, Appendix C). No strontium activity was detected.

The highest MDC was calculated at <4.6 pCi/I for Sr-89 and at <0.9 pCi/I for Sr-90.Gamma Spectrometry Samples from location K1-1 were analyzed for gamma emitting nuclides (Table C-I11.2, Appendix C). All nuclides were less than the MDC.4. Storm Water Storm water results are now included in the Annual Radiological Groundwater Protection Program (ARGPPR), Appendix F.5. Ground Water Groundwater results are now 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 (Table C-IV.1, Appendix C). No strontium activity was detected.

The highest MDC was calculated at <3.7 pCi/kg wet for Sr-90.

Gamma Spectrometrv The edible portions of fish samples from both locations were analyzed for gamma emitting nuclides (Table C-IV.2, Appendix C).Naturally occurring K-40 was found in all fish samples and ranged from 2,411 to 3,869 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were detected.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 KI-3) could be affected by TMINS' effluent releases.

The following analysis was performed:

Gamma Spectrometrv Sediment samples from all locations were analyzed for gamma emitting nuclides (Table C-V.1, Appendix C). Potassium-40 was found in all sediment samples and ranged from 8,369 to 17,610 pCi/kg dry. No other fission or activation products were detected.Cesium-1 37 is occasionally found in sediment at very low levels (just above LLD) and is not distinguishable from background levels (Figure C-5, Appendix C).B. Atmospheric Environment 1 .Airborne Particulates

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

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-VI.1 and C-VI.2, Appendix C).

Detectable gross beta activity was observed at all locations.

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 8 to 32 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3.The results from the intermediate offsite locations (Group II)ranged from 6 to 38 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3.The results from the Control location (Group Ill)ranged from 9 to 31 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3.Comparison of the 2014 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 2014 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 (Table C-VI.3, Appendix C).Naturally occurring Be-7 due to cosmic ray activity was detected in 26 samples. These concentrations ranged from 37 to 102 E-3 pCi/m3. All other nuclides were less than the MDC.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 1-131 (Table C-VII.1, Appendix C). All results were less than the MDC for 1-131.2. Terrestrial

a. Milk Samples were collected from five locations (K1 5-3, E2-2, F4-1 G2-1 and P4-1) biweekly March through November and monthly December through February.

The following analyses were performed:

Iodine-1 31 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VIII.1, Appendix C). The K15-3 sample collected on 07/23/14 initially showed activity for 1-131. The sample was recounted two days later and again the next day. Both recounts showed an increase in activity.

These results are not congruent with normal 1-131 decay. A gamma scan was then performed and K-40 was detected.

The non-decaying activity was attributed to this naturally occurring isotope. No 1-131 analysis result is available for this sample. All other results were less than the MDC.Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-VIII.2, Appendix C). No Sr-89 or Sr-90 activity was detected.

Occasionally Sr-90 is detected and is 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 (Table C-VIII.3, Appendix C).Naturally occurring K-40 activity was found in all samples.The concentrations ranged from 636 to 1,517 pCi/l. All other nuclides were less than the MDC.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, E1-2 and H1-2). B10-2 was the control location for both annual and monthly sampling.

The following analyses were performed:

Strontium Twenty-six of 32 food product samples were analyzed for concentrations of Sr-90 (Table C-IX.1, Appendix C).Strontium-90 activity was detected in 11 of 26 samples. The concentrations ranged from 2 to 18 pCi/kg wet.

Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C).Naturally occurring Be-7 due to cosmic ray activity was detected in 14 of 32 samples. These concentrations ranged from 353 to 2,515 pCi/I. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 1,672 to 8,693 pCi/I. All other nuclides were less than the MDC.C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Optically Stimulated Luminescence Dosimeter (OSLD). Ninety OSLD locations were established around the site. Results of OSLD measurements are listed in Tables C-X.1 to C-X.3, Appendix C All of the OSLD measurements were below 40 mR/quarter, with a range of 16.2 to 37.4 mR/standard quarter. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 averaged higher than indicator stations.

Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 have a historical high bias, but tracked with the data from all three groups this bias is most likely due to radon and other naturally occurring nuclides, e.g. K-40, emanating from the ground.D. Land Use Survey A Land Use Survey conducted in the July through November 2014 growing season around the Three Mile Island Nuclear Station (TMINS)was performed by Normandeau Associates, RMC Environmental Services Division for Exelon to comply with Sections 8.2 of the Plant's Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident, milk-producing animal and garden of greater than 500 ft2 in each of the sixteen 22 /2 degree sectors around the site. For 2014, a meat census was also performed.

The results of these surveys are summarized below.

Distance in Miles from the TMINS Reactor Buildings Sector Residence Garden Milk Farm Meat Animal Miles Miles Miles Miles 1 N 1.1 1.9 2.1 2.1 2 NNE 0.7 1.2 -2.4 3 NE 0.5 0.7 4.2 2.4 4 ENE 0.5 0.5 4.5 1.1 5 E 0.4 0.5 1.1 1.1 6 ESE 1.1 1.2 3.2 1.1 7 SE 0.7 1.6 1.4 1.4 8 SSE 0.7 0.8 -1.8 9 S 2.3 2.7 3.3 10 SSW 0.6 2.5 4.9, 14.4 4.9 11 SW 0.5 1.0 -12 WSW 0.5 1.3 13 W 0.7 1.4 --14 WNW 0.4 1.7 3.7 2.4 15 NW 0.4 1.2 --16 NNW 1.1 2.4 -E. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2014 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation.

The 2014 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 0.12 mrem. This dose is equivalent to 0.04% of the dose that an individual living in the TMI area receives each year from natural background radiation.

1. Determination of Radiation Doses to the Public Dose assessments can be performed by using either effluent data and an environmental transport model or environmental sample data. To the extent possible, doses to the public are based on the direct measurement of dose rates from external sources and the measurement of radionuclide concentrations in environmental media which may contribute to an internal dose of radiation.

Optically Stimulated Luminescent Dosimetry (OSLDs) positioned in the environment around TMINS provide measurements to determine external radiation doses to humans. Samples of air, water and food products are used to determine internal doses.The quantity of radioactive materials released during normal operations are typically too small to be measured once distributed in the offsite environment.

Therefore, the potential offsite doses are more effectively calculated for TMINS operations using a computerized model that predicts concentrations of radioactive materials in the environment and subsequent radiation doses based on measured effluents.

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

Therefore, the model predicts doses that are higher than actual doses received by people. The type and amount of radioactivity released from TMINS is calculated using measurements from effluent sample analyses.Airborne releases are diluted and carried away from the site by atmospheric diffusion, which continuously acts to disperse radioactivity.

Variables that affect atmospheric dispersion include wind speed, temperature at different elevations, terrain, and shift in wind direction.

A weather station on the north end of TMI is linked to a data logger that records the meteorological data.Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Susquehanna River.Actual monthly Susquehanna River flows are obtained from the USGS Stream gauging station 01570500 located at Harrisburg, PA.The human exposure pathways also are included in the model and are depicted in Figure 1. The exposure pathways that are considered for the discharge of TMINS liquid effluents are consumption of drinking water and fish. The exposure pathways considered for the discharge of TMINS airborne effluents are plume exposure, inhalation, cow milk consumption, fruit and vegetable consumption, and meat consumption.

When determining the dose to humans, it is necessary to consider all applicable pathways and all exposed tissues, summing the dose from each to provide the total dose for each organ as well as the whole body from a given radionuclide.

Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted and half-life.

The dose assessment model also contains dose conversion factors for the radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone and GI tract).2. Result of Dose Calculations The maximum hypothetical doses due to 2014 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 2014 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 2014 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.12 mrem. This dose is equivalent to 0.04% percent of the dose that an individual living in the TMI area receives each year from natural background radiation (311 mrem).The low doses calculated for 2014 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).

In conclusion, radioactive materials related to 2014 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 2014 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 2014 did not have any adverse effects on the health of the public or on the environment.

TABLE 1 Calculated Maximum Hypothetical Doses to an Individual from 2014 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual USNRC 10 CFR 50 APP. I Guidelines (mrem/yr)From Radionuclides In Liquid Releases From Radionuclides In Airborne Releases (Noble Gases)From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates) 3 total body, or 10 any organ 5 total body, or 15 skin 15 any organ Calculated Dose (mrem/yr)TMI-1 TMI-2 4.57E-3 3.87E-4 4.63E-3 6.15E-4 1.85E-4 0*2.72E-4 0*I.IOE-1 5.63E-5*No noble gases were released from TMI-2.USEPA 40 CFR 190 Limits (mrem/yr)Calculated Dose (mrem/yr)TMI-1 and TMI-2 Combined**

Total from Site 75 thyroid 0.69 0.77 25 total body 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 2014 TMINS operations was 0.65 mrem. This dose was based on a maximum net fence-line exposure rate and a shoreline/fence-line occupancy factor of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> (Regulatory Guide 1.109). The combination of the maximum organ dose from TMI-I and TMI-2 effluents (0.12 mrem) and the dose from direct radiation (0.65 mrem) yielded a maximum hypothetical dose of 0.77 mrem.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2014 TMI-1 and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)I From Radionuclides In Liquid Releases From Radionuclides in Airborne Releases (Noble Gases)From Radionuclides In Airborne Releases (lodines, Tritium and Particulates)

• No noble gases were released from TMI-2.TMI-I TMI-2 4.57E-3 3.87E-4 1.85E-4 0*3.03E-2 5.63E-5 Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations:

Individual Whole Body Dose Due to Natural Background Radiation (1)0.12 mrem/yr 311 mrem/yr (1) NCRP 160-(2009)

Figure 1 Exposure Pathways For Radlonuclides Routinely Released From TMINS I I I PREDOMINANT RADIONUCLIDES!

NOBLE GASES (Xe,Kr)Plume exposure RADIOIODINES (1-131, 1-133)Inhalation and consumption of milk, water, fruits, and vegetables RADIOSTRONTIUMS (Sr-89, Sr-90)Consumption of milk, meat.fruits, and vegetables ACTIVATION PRODUCTS.(Co-60, Mn.54)Shoreline exposure RADIOCESIUMS (Cs-134, Cs-137)Shoreline exposure and consumption of milk, meat, fish, water, fruits, and vegetables TR(TIUM (H-3)Inhalation and consumption of water, milk, fruits, and vegetables F. Errata Data There is no errata data for 2014.G. Summary of Results -Inter-Laboratory Comparison Program The primary and 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 DOE's MAPEP, were evaluated against the following pre-set acceptance criteria: 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's 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 MAPEP's evaluation report provides an acceptance range with associated flag values.The MAPEP defines three levels of performance:

Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

In reviewing our environmental inter-laboratory crosscheck programs, we identified

1) duplication of efforts on some matrices and isotopes and 2) that we are performing crosscheck samples on some matrices and isotopes that we do not perform for clients.Since the DOE MAPEP is designed to evaluate the ability of analytical facilities to cprrectly analyze for radiological constituents representative of those at DOE sites, the needed changes were made to the MAPEP program. Therefore, the following isotopes were removed from the MAPEP program: Soil -gamma -will be provided by Analytics twice per year, starting in 2015. For 2014, one soil gamma is provided by MAPEP, the 2 nasoil gamma is provided by Analytics.

AP -gamma -is currently provided by Analytics.

Water -gamma, H-3, Sr-90, uranium, gross alpha and gross beta currently provided by ERA.MAPEP evaluates non-reported (NR) analyses as failed if they were reported in the previous series.For the TBE laboratory, 163 out of 169 analyses performed met the specified acceptance criteria.

Six analyses (Ni-63, K-40 and 1-131 in water, and two Sr-90s and one Gross Alpha in AP samples) did not meet the specified acceptance criteria for the following reasons: 1. Teledyne Brown Engineering's MAPEP March 2014 Ni-63 in water result of 32.7 +/- 1.69 Bq/L was overlooked when reporting the data but would have passed the acceptance range of 23.9 -44.2 Bq/L. NCR 14-04 2. Teledyne Brown Engineering's MAPEP March 2014 K-40 in water result of 1.63 +/- 2.49 Bq/L was overlooked when reporting the data but would have passed the false positive test. NCR 14-04 3. Teledyne Brown Engineering's ERA November 2014 1-131 in water result of 15.8 pCi/L was lower than the known value of 20.3 pCi/L, failing below the lower acceptance limit of 16.8.The result was evaluated as failed with a found to known ratio of 0.778. No cause could be found for the slightly low result. All ERA 1-131 evaluations since 2004 have been acceptable.

NCR 14-08 4. Teledyne Brown Engineering's MAPEP March 2014 Sr-90 in AP result of 0.822 Bq/sample was lower than the known value of 1.18 Bq/sample, failing below the lower acceptance limit of 0.83 Bq/sample.

The rerun result was still low, but fell within the lower acceptance range of 0.836. The rerun result was statistically the same number as the original result. No cause could be found for the slightly low results.NCR 14-04 5. Teledyne Brown Engineering's MAPEP September 2014 Sr-90 in AP result of 0.310 Bq/sample was lower than the known value of 0.703 Bq/shmple.

The gravimetric yield of 117% was very high (we normally see yields of 60% to 70%) and could account for the low activity.

NCR 14-09 6. Teledyne Brown Engineering's MAPEP September 2014 Gr-Alpha in AP result of 0.153 Bq/sample was lower than the known value of 0.53 Bq/sample.

The AP sample was counted on the wrong side. The AP was flipped over and recounted with acceptable results. NCR 14-09 For the EIML laboratory, 85 of 90 analyses met the specified acceptance criteria.

Five analyses (Water -Pu-238, Pu-239, Fe-55; AP -Co-57; Soil, Cs134) did not meet the specified acceptance criteria for the following reasons: 1. Environmental Inc., Midwest Laboratory's MAPEP February 2014 water Pu-238 result of 1.28 Bq/L was higher than the known value of 0.83 Bq/L, exceeding the upper control limit of 1.08 Bq/L. The high bias on the plutonium was traced to contamination from a newly purchased standard.

The result of the reanalysis with the new tracer was 0.68, which fell within the acceptance criteria.2. Environmental Inc., Midwest Laboratory's MAPEP February 2014 water Pu-239/240 result of 0.91 Bq/L was higher than the known value of 0.68 Bq/L, exceeding the upper control limit of 0.88 Bq/L. The high bias on the plutonium was traced to contamination from a newly purchased standard.The result of reanalysis with the new tracer was 0.66 Bq/L, which fell within the acceptance criteria.3. Environmental Inc., Midwest Laboratory's MAPEP February 2014 AP Co-57 result of 1.60 +/- 0.05 Bq/total sample failed the false positive test. Interference from the Eu-1 52 resulted in the misidentification of Co-57.4. Environmental Inc., Midwest Laboratory's MAPEP February 2014 soil Cs-134 result of 6.10 +/- 1.80 Bq/kg failed the false positive test. Long sample counting time lead to interference from naturally occurring Bi-214 in the sample matrix with a close spectral energy.

5. Environmental Inc., Midwest Laboratory's MAPEP August 2014 water Fe-55 result of 55.10 +/- 14.80 Bq/L was higher than the known value of 31.50 Bq/L, exceeding the upper control limit of 41.00 Bq/L. The result of the reanalysis of tFe-55 was 32.63 +/- 16.30 Bq/L, which fell within thp acceptance criteria.The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.V. References

1. Three Mile Island Nuclear Station, Unit 1, Technical Specifications, DPR 50.2. Three Mile Island Nuclear Station, Unit 2, PDMS Technical Specifications, DPR 73.3. Radiation Management Corporation. "Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1974 -June 5, 1974." RMC-TR-75-17, January 1975.4. Exelon. "Three Mile Island Nuclear Station Offsite Dose Calculation Manual (ODCM)." 5. National Council of Radiation Protection and Measurements Report No.160. "Ionizing Radiation Exposure of the Population of the United States." 2009.

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER (PCI/LITER)

H-3 1-131 24 12 24 2000 935 (4/12)(291/2280)

I NA<LLD<LLD 935 (4/12)(291/2280)

J 1-2 INDICATOR WEST SHORE; TMI 0.5 MILES S OF SITE 0 0 GAMMA MN-54 CO-58 FE-59 CO-60 15 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 ZN-65 NB-95 ZR-95 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER (PCI/LITER)

CS-134 CS-137 BA-140 LA-140 15 <LLD 18 <LLD 60 <LLD 15 <LLD<LLD<LLD<LLD<LLD>)0 DRINKING WATER (PCI/LITER)

GR-B 1-131 36 36 36 36 3.1 (16/24)(2.3/4.2)2.1 (6/12)(1.9/2.3)3.1 (11/12)(2.3/4.2)G 15-2 INDICATOR WRIGHTS WATER SUPPLY 13.3 MILES SE OF SITE 0 H-3 I <LLD 2000 <LLD 15 <LLD 15 <LLD<LLD<LLD 0 GAMMA MN-54 CO-58<LLD<LLD 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER (PCI/LITER)

FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA- 140 LA-140 30 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER (PCI/LITER)

GR-B 1-131 12 12 12 4 5.3 (12/12)(2.8/7.0)I <LLD H-3 SR-89 SR-90 2000 11593 (4/12)(2300/27000) 5 <LLD 2 <LLD 15 <LLD 2 NA NA NA NA NA NA NA NA NA 5.3 (12/12)(2.8/7.0)11593 (4/12)(2300/27000)

KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 0 KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 0 0 GAMMA MN-54 12 0 CO-58 FE-59 CO-60 15 <LLD 30 <LLD 15 <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER (PCI/LITER)

ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA- 140 SR-90 GAMMA K-40 30 <LLD 15 <LLD 30 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD 10 <LLD NA NA NA NA NA NA NA 0 0 0 0 0 0 0 0 BOTTOM FEEDER (PCVKG WET)<LLD 4 NA 3451 (2/2)(3032/3869) 3188 (2/2)(2512/3864) 3451 (2/2)(3032/3869)

INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER (PCI/KG WET)MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 SR-90 GAMMA K-40 130 <LLD 130 <LLD 260 <LLD 130 <LLD 260 <LLD 130 <LLD 150 <LLD 10 <LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 PREDATOR (PCI/KG WET)0 4 NA 3119 (2/2)(2434/3804 2809 (2/2)(2411/3206) 3119 INDP INDICATOR (2/2) YORK HAVEN DAM (2434/3804)

DOWNSTREAM OF DISCHARGE 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014.NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS PREDATOR (PCI/KG WET)MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 130 <LLD 130 <LLD 260 <LLD 130 <LLD 260 <LLD 130 <LLD 150 <LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 0 0 SEDIMENT (PCI/KG DRY)GAMMA 7 K-40 NA 12573 (5/5)13155 (2/2)17610 (1/1)EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE (8369/17610)

(11700/14610) 0 0 MN-54 NA <LLD<LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT (PCI/KG DRY)CO-58 CO-60 CS-134 CS-137 00 AIR PARTICULATE (E-3 PCI/CU.METER)

GR-B 360 NA <LLD NA <LLD 150 <LLD 180 <LLD 10 17 (305/308)(6/38)NA 68 (22/24)(37/102)NA <LLD NA <LLD NA <LLD<LLD<LLD<LLD<LLD 17 (50/52)(9/31 )63 (4/4)(49/95)0 0 0 0 0 18 (51/51)(8/35)82 (4/4)(68/95)A3-1 INDICATOR MIDDLETOWN

2.6 MILES

N OF SITE A3-1 INDICATOR MIDDLETOWN

2.6 MILES

N OF SITE GAMMA BE-7 28 0 0 MN-54 CO-58 CO-60<LLD<LLD<LLD 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE (E-3 PCI/CU.METER)

NB-95 ZR-95 CS-134 CS-137 GAMMA 1-131 NA <LLD NA <LLD 50 <LLD 60 <LLD 70 <LLD I <LLD 5 <LLD 2 <LLD<LLD<LLD<LLD<LLD 0 0 0 AIR IODINE (PCI/CU.M)

MILK (PCI/LITER) 360 1-131I SR-89 SR-90 114 20 20<LLD<LLD<LLD<LLD 0 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK (PCI/LITER)

GAMMA K-40 CS-134 CS-137 BA-140 LA-140 115 NA 1265 (92/92)(636/1517) 1251 (23/23)(1028/1448) 1371 (23/23)(1049/1517)

F4-1 INDICATOR TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE ,0 15 <LLD 18 <LLD 60 <LLD 15 <LLD<LLD<LLD<LLD<LLD 0 0 0 0 VEGETATION (PCI/KG WET)SR-90 26 32 GAMMA BE-7 K-40 10 7 (8/13)(2/13)NA 859 (8/16)(353/1944)

NA 4244 (16/16)(2680/6885) 12 (3/13)(4/18)1431 (6/16)(795/2515) 4257 (16/16)(1672/8693) 12 (3/13)(4/18)1431 (6/16)(795/2515) 4531 (12/12)(2738/6885)

B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE B 10-2 CONTROL MILTON HERSHEY SCHOOL 10. 1 MILES NNE OF SITE HI-2 INDICATOR RED HILL MARKET, ALONG ROUTE 441 1.0 MILES SSE OF SITE 0 1-131 60 <LLD<LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION (PCI/KG WET)CS-134 CS-137 60 <LLD 80 <LLD<LLD<LLD 0 0 DIRECT RADIATION (MILLI-ROENTGEN/STD.MO.)

OSLD-QUARTERLY 359 NA 22.1 (315/315)(16.2/37.4) 23.6 (44/44)(19.1/31.8) 35.6 (4/4)(32.8/37.4)

F1-2 INDICATOR 0 REACTOR BUILDING ON TOP OF DYKE MIDWAY 0.5 MILES ESE OF SITE C,.THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

Intentionally left blank APPENDIX B LOCATION DESIGNATION, AND SAMPLE COLLECTION DISTANCE & DIRECTION,& ANALYTICAL METHODS Intentionally left blank TABLE B-i: Location Designation and Identification System for the Three Mile Island Nuclear Station XYY-Z- General code for identification of locations, where: X -Angular Sector of Sampling Location.

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

YY -Radial Zone of Sampling Location in miles.Z -Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.B-i TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Sample Medium Station Map Distance Code Number (miles)AQS ID APAIID SW ID ID ID ID ID ID ID FP ID ID ID ID ID AQF ID ID ID ID ID AP, Al, ID, FP ID M ID ID Al -3 A1-4 A3-1 A3-2 A5-1 A9-3 Bi-1 B1-2 B2-1 B5-1 B10-1 B10-2 C1-1 Cl-2 C2-1 C5-1 C8-1 Control D1-1 D1-2 D2-2 D6-1 D15-1 E1-2 E1-4 E2-2 E2-3 E5-1 E7-1 F1-1 F1-2 F1-3 F1-4 F2-1 F4-1 F5-1 F10-1 F25-1 G1-2 G1 -3 G1-5 G1-6 G2-1 G2-4 G5-1 G10-1 G15-1 G15-2 G15-3 0.5 0.3 2.7 2.7 4.4 8.0 0.6 0.4 1.9 4.9 9.2 10 0.7 0.3 1.5 4.7 7.1 0.2 0.5 1.6 5.2 10.8 0.4 0.2 1.1 2.0 4.7 6.7 0.5 0.2 0.6 0.2 1.3 3.2 4.7 9.4 Azimuth Description 3590 N of site off north tip of TMI in Susquehanna River 60 N of Reactor Building on W fence adjacent to North Weather Station, TMI 3570 N of site at Mill Street Substation 3560 N of site at Swatara Creek, Middletown 30 N of site on Vine Street Exit off Route 283 2o N of site at Duke Street Pumping Station, Hummelstown 250 NNE of site on light pole in middle of North Bridge, TMI 230 NNE of Reactor Building on top of dike, TMI 170 NNE of site on Sunset Dr. (off Hillsdale Rd.)190 NNE of site at intersection of School House and Miller Roads 210 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey 310 NNE of site at Milton Hershey School, Hershey 370 NE of site along Route 441 N 50' NE of Reactor Building on top of dike, TMI 440 NE of site at Middletown Junction 430 NE of site on Kennedy Lane 480 NE of site at Schenk's Church on School House Road-All locations where finfish are collected above Dock St.Dam, Harrisburg 76' ENE of Reactor Building on top of dike, TMI 67' ENE of site off Route 441 along lane between garden center and residence 740 ENE of site along Hillsdale Rd. (S of Zion Rd.)660 ENE of site off Beagle Road 640 ENE of site along Route 241, Lawn 970 E of site at TMI Visitor's Center 970 E of Reactor Building on top of dike, TMI 960 E of site at farm on Pecks Road 970 E of site along Hillsdale Rd. (N of Creek Rd.)820 E of site at intersection of North Market Street (Route 230) and Zeager Road 880 E of site along Hummelstown Street, Elizabethtown 1170 ESE of site near entrance to 500 kV Substation 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI 1120 ESE of site in 500 kV Substation 1220 ESE of Reactor Building on top of dike, TMI 1190 ESE of site along Engle Road 104 0 ESE of site at farm on Turnpike Road 109° ESE of site along Amosite Road 1120 ESE of site along Donegal Springs Road, Donegal Springs 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster 1450 SE of site along Route 441 S 1300 SE of Reactor Building on top of dike, TMI 143' SE of Reactor Building on top of dike, TMI 1390 SE of Reactor Building on top of dike, TMI 1260 SE of site at farm on Becker Road 1380 SE of site on Becker Road 131 0 SE of site at intersection of Bainbridge and Risser Roads 1280 SE of site at farm along Engles Tollgate Road, Marietta 1260 SE of site at Columbia Water Treatment Plant 1290 SE of site at Wrightsville Water Treatment Plant 1240 SE of site at Lancaster Water Treatment Plant ID ID ID AP, Al ID ID M ID ID ID 3 22 ID ID ID ID Al, AP, M ID ID ID ID DW DW 1 1 2 2 2 3 3 3 3 0.7 0.2 0.3 0.3 1.4 1.7 4.8 9.7 14.4 13.3 15.7 B-2 TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Sample Medium ID FP AP, Al, ID ID ID ID Station Map Code Number H1-1 H1-2 H3-1 H5-1 H8-1 H15-1 AQF ID SW ID AQS ID ID ID ID EW AQS ID ID ID ID ID ID M ID ID ID ID ID ID ID Indicator J1-1 J1-2 J1-3 J2-1 J3-1 J5-1 J7-1 J15-1 K1-1 K1 -3 K1-4 K2-1 K3-1 K5-1 K8-1 K15-1 K15-3 1-1i L1-2 L2-1 L5-1 L8-1 L15-1 M1-1 2 2 3 3 2 2 2 3 3 2 2 2 3 3 3 2 2 3 3 2 2 3 2 2 3 3 1 Distance (miles) Azimuth Description 0.5 167 0 SSE of site, TMI 1.0 151

• SSE of site along Route 441, Red Hill Market 2.2 1600 SSE of site in Falmouth-Collins Substation 4.1 1580 SSE of site by Guard Shack at Brunner Island Steam Electric Station 7.4 163 0 SSE of site along Saginaw Road, Starview 13.2 157* SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills--All locations where finfish are collected downstream of the TMINS liquid discharge outfall 0.8 176° S of site, TMI 0.5 1880 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River 0.3 1890 S of Reactor Building just S of SOB, TMI 1.4 1790 S of site in Susquehanna River just upstream of the York Haven Dam 2.7 1790 S of site at York Haven/Cly 4.9 181 ° S of site along Canal Road, Conewago Heights 6.5 176° S of site off of Maple Street, Manchester 12.6 183 0 S of site in Met-Ed York Load Dispatch Station 0.2 2100 On site at RML-7 Main Station Discharge Building 0.2 2120 SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River 0.2 2090 SSW of Reactor Building on top of dike behind Warehouse 2, TMI 1.2 2000 SSW of site on S Shelley Island 2.0 2060 SSW of site along Rt. 262, N of Cly 4.9 2020 SSW of site along Conewago Creek Road, Strinestown 7.5 196' SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View 12.8 2030 SSW of site behind McDonald's and next to child care center, Weiglestown 14.4 2050 SSW of site at farm along S Salem Church Rd, Dover 0.1 2360 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI 0.5 221 SW of site on Beech Island 1.8 2240 SW of site along Route 262 4.1 2280 SW of site at intersection of Stevens and Wilson Roads 8.0 2250 SW of site along Rohlers Church Rd., Andersontown 11.8 2260 SW of site on W side of Route 74, rear of church, Mt.Royal 0.1 2500 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI 0.4 2520 WSW of site on E side of Shelley Island, Lot #157 1.3 2560 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro 4.3 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown 8.7 2430 WSW of site along Alpine Road, Maytown 0.7 2740 W of site on W side of Shelley Island, between lots #13 and #14 0.1 2740 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI 1.2 261 W of site at Goldsboro Marina 5.0 2680 W of site off of Old York Road along Robin Hood Drive 7.7 2620 W of site along Route 382, 1/2 mile north of Lewisberry 10.4 2750 W of site at intersection of Lisburn Road and Main Street, Lisburn 0.4 303 0 WNW of site on Shelley Island ID AP, Al, ID ID ID ID ID ID ID ID ID ID M1-2 M2-1 M5-1 M9-1 N1-1 N1-3 N2-1 N5-1 N8-1 N15-2 P1-1 B-3 TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Sample Medium Station Map Distance Code Number (miles)Azimuth Description ID ID M ID ID ID ID ID ID SW, DW, ID AP, Al, ID P1-2 P2-1 P4-1 P5-1 P8-1 Q1-1 Q1-2 Q2-1 Q5-1 Q9-1 Q15-1 R1-1 R1-2 R3-1 R5-1 R9-1 R15-1 0.1 2.0 3.7 5.0 8.0 0.5 0.2 1.9 5.0 8.5 13.4 2920 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 2830 WNW of site along Route 262 295° WNW of site at farm on Valley Road 284U WNW of site at intersection of Valley Road (Route 262)and Beinhower Road 2920 WNW of site along Evergreen Road, Reesers Summit 3170 NW of site on E side of Shelley Island 321' NW of Reactor Building on fence W of Warehouse 1, TMI ID ID ID ID ID ID 0.2 0.7 2.6 4.9 8.0 3100 3170 3100 309*3350 3340 3410 3390 3410 NW of site along access road along river NW of site along Lumber Street, Highspire NW of site at the Steelton Water Company NW of site behind West Fairview Fire Dept. Social Hall (abandoned)

NNW of Reactor Building along W fence, TMI NNW of site on central Henry Island NNW of site at Crawford Station, Middletown NNW of site at intersection of Spring Garden Drive and Route 441 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights NNW of site at intersection of Route 22 and Colonial Road, Colonial Park 11.2 3320 IDENTIFICATION KEY ID = Immersion Dose (OSLD)SW = Surface Water Al =Air Iodine AP = Air Particulate FP = Food Products (Green Leafy Vegetation, Fruits, Vegetables)

EW DW M AQF AQS= Effluent Water= Drinking Water= Milk (Cow)= Finfish= Aquatic Sediment B-4 TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor.

Nuclear Station)Env. Inc., T-02 Determination of tritium in water (direct method)Surface lodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchange Drinking Gross Beta Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in Water from a continuous radiological analysis (Three Mile Island various matrices water compositor.

Nuclear Station)Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)Drinking Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor.

Nuclear Station)Env. Inc., T-02 Determination of tritium in water (direct method)Drinking Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by an ion exchange Effluent Water Iodine-131 Monthly composite from a continuous water compositor.

ER-TMI-06 Collection of water samples for radiological analysis (Three Mile Island Nuclear Station)2 gallon TBE, TBE-2012 Radioiodine in various matrices Env. Inc., 1-131-01 Determination of 1-131 in milk by an ion exchanae Effluent Gross Beta Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in Water from a continuous radiological analysis (Three Mile Island various matrices water compositor.

Nuclear Station)Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)

TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Effluent Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor.

Nuclear Station)Env. Inc., T-02 Determination of tritium in water (direct method)Effluent Strontium-Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange Water 89/90 composite from monthly samples.Storm Gamma Quarterly composite ER-TMI-06 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy of monthly grab radiological analysis (Three Mile Island samples Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Storm Tritium Quarterly composite ER-TMI-06 Collection of water samples for 1 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water of monthly grab radiological analysis (Three Mile Island scintillation samples Nuclear Station)Env. Inc., T-02 Determination of tritium in water (direct method)Fish Gamma Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by other techniques gamma spectroscopy Fish Strontium-90 Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet) TBE, TBE-2019 Radiostrontium analysis by ion exchange collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in other techniques Ashed Samples TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Sediment Gamma Semi-annual grab ER-TMI-03 Collection of sediment samples for 500 grams (dry) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Gross Beta One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2008 Gross alpha and/or gross beta activity in Particulates composite of iodine samples for radiological analysis (Three (approximately various matrices continuous air Mile Island Nuclear Station) 280 cubic sampling through meters weekly) Env. Inc., AP-02 Determination of gross alpha and/or gross glass fiber filter beta in air particulate filters paper Air Gamma Quarterly composite TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy of each station (approximately Env. Inc., AP-03 Procedure for compositing air 3600 cubic Env. Inc., GS-01 Determination of gamma emitters by particulate filters for gamma spectroscopic meters) gamma spectroscopy analysis Air Iodine Gamma One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy composite of iodine samples for radiological analysis (Three (approximately continuous air Mile Island Nuclear Station) 280 cubic Env. Inc., 1-131-02 Determination of 1-131 in charcoal sampling through meters weekly) canisters by gamma spectroscopy (batch method)charcoal filter Milk 1-131 Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various" matrices sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion Monthly all other exchange times Milk Strontium-Quarterly composite ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 of Bi-weekly and radiological analysis (Three Mile Island Nuclear monthly grab Station) Enc. Inc., SR-07, Determination of Sr-89 and Sr-90 in Milk samples (Ion Exchange Batch Method)TBE, TBE-2023 Compositing of samples Milk Gamma Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., GS-01 Determination of gamma emitters by Monthly all other gamma spectroscopy times Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Vegetation Strontium-Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in Ashed Samples OSLD Optically Quarterly OSLDs ER-TMI-02 Collection of OSLD samples for 2 badges with 3 Landauer Incorporated Stimulated comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Luminescence A1 2 0 3:C Landauer Station)Dosimetry Incorporated elements.

& t"i b s*mP a**3g..j &aih, 94402, amg Figure B-I Environmental sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2014 B-9 3 2 0.5 1-igure B-2 "plinU Locat. ionS St Oat n 2 we Envir Sonmetheal O M ile island Nu la t to ,2 1 Miles 01tne Thre B-1O 2I LaIauw -on Oft w H 4 "& EWeWfIn MSIb.MM SOU NAD7, bd Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2014 B-1I I Intentionally left blank APPENDIX C DATA TABLES AND FIGURES -PRIMARY LABORATORY Intentionally left blank Table C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA COLLECTION J1-2 Q9-1 PERIOD 12/31/13 -01/28/14 (1) < 193 < 188 01/28/14 -02/25/14 (1) < 160 < 161 02/25/14 -04/01/14 (1) < 166 < 167 04/01/14 -04/29/14 291 +/- 133 < 185 04/29/14 -06/03/14 700 +/- 157 < 190 06/03/14 -07/01/14 467 +/- 131 < 171 07/01/14 -07/29/14 2280 +/- 277 < 164 07/29/14 -09/02/14 < 188 < 192 09/02/14 -09/30/14 < 180 < 184 09/30/14 -10/28/14 < 166 < 167 10/28/14 -12/02/14 < 184 < 189 12/02/14 -12/30/14 < 168 < 170 MEAN 935 +/- 1825 -Table C-I.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA COLLECTION A3-2 PERIOD 01/06/14 -01/21/14 (1) < 0.6 02/04/14 -02/25/14 < 0.8 03/05/14 -04/01/14 < 0.7 04/08/14 -04/29/14 < 0.6 05/06/14 -06/03/14 < 0.7 06/10/14 -07/01/14 < 0.7 07/08/14 -07/29/14 < 0.7 08/05/14 -09/02/14 < 0.7 09/09/14 -09/30/14 < 0.7 10/07/14 -10/28/14 < 0.6 11/04/14 -12/02/14 < 0.6 12/09/14 -12/30/14 < 0.4 MEAN -THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+ 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 SITE COLLECTION PERIOD J1-2 12/31/13 -01/28/14 01/28/14 -02/25/14 02/25/14 -04/01/14 04/01/14 -04/29/14 04/29/14 -06/03/14 06/03/14 -07/01/14 07/01/14 -07/29/14 07/29/14 -09/02/14 09/02/14 -09/30/14 09/30/14 -10/28/14 10/28114 -12/02/14 12/02/14 -12/30/14 (1)(1)(1)<5<5<4<2<6<5<3<5<4<5<3<6<6<5<4<2<6<4<3<5<4<4<4<6< 12< 10<9<4< 12< 10<6< 15<9<8<7< 14 MEAN<5<5<4<2<5<4<3<6<4<6<4<5<5<5<4<2<7<4<4<4<6<4<4<5< 12< 10<9<3<9< 11<6< 11<9< 11<7< 10< 12< 10<8<3<13<8<6<8< 11< 10<6<14<6<5<4<2<6<5<3<7<4<5<4<6<6<6<5<2<6<4<4<6<7<5<3<7< 10< 10<7<3< 12<9<5<9<6<9<6< 10<9<10<8<3<9<7<6<9< 11<8<7< 12<6<5<3<2<6<5<3<5<4<4<3<6<5<6<5<2<6<4<6<5<5<5<3<6<6<6<4<2<6<6<3<7<5<5<3<6<7<6<5<2<7<4<6<5<5<5<3<8< 32< 28< 27< 12< 29< 25< 16< 33< 26< 25< 19< 30< 30< 27< 30< 12< 27< 23< 30< 26< 35< 21< 18< 36<9<9<7<3< 10<9<5<6<9<8<6< 11<11<8< 8<4< 12<6<3<7< 11<8<7<7 Q9-1 12/31/13 -01/28/14 01/28/14 -02/25/14 02/25/14 -04/01/14 04/01/14 -04/29/14 04/29/14 -06/03/14 06/03/14 -07/01/14 07/01/14 -07/29/14 07/29/14 -09/02/14 09/02/14 -09/30/14 09/30/14 -10/28/14 10/28/14 -12/02/14 12/02/14 -12/30/14<6<5<5<2<5<4<4<5<5<5<3<6<6<6<4<2<6<4<4<4<6<5<4<7< 10< 11<9<4< 16<7<8<8< 11< 12<7< 14 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION Table C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/31/13 -01/28/14 (1) 3.9 +/- 1.6 2.4 +/- 1.4 2.0 +/- 1.3 01/28/14 -02/25/14 2.3 +/- 1.4 3.8 +/- 1.6 < 1.9 02/25/14 -04/01/14 2.7 +/- 1.5 < 2.1 2.0 +/- 1.4 04/01/14 -04/29/14 2.6 +/- 1.4 < 1.8 1.9 + 1.2 04/29114 -06/03114 2.9 +/- 1.5 < 2.0 < 1.9 06/03/14 -07/01/14 2.8 +/- 1.5 < 2.2 < 2.1 (1)07/01/14 -07/29/14 (1) < 2.2 < 2.2 < 2.1 07/29/14 -09/02/14 (1) 2.9 +/- 1.5 3.3 +/- 1.5 < 1.9 09/02/14 -09/30/14 3.5 +/- 1.5 3.1 +/- 1.6 2.3 + 1.6 09/30/14 -10/28/14 2.9 +/- 1.6 < 2.3 < 2.2 10/28/14 -12/02/14 3.4 +/- 1.6 < 2.2 2.3 +/- 1.5 12/02/14 -12/30/14 4.2 +/- 1.5 2.4 +/- 1.3 2.1 + 1.3 MEAN 3.1 +/- 1.2 3.0 +/- 1.2 2.1 + 0.3 Table C-II.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 1 Z/31/1 -U1/Zd/14 (1) < U.8 < u.8 < 0.8 01/28/14 -02/25/14 < 0.7 < 0.8 < 0.9 02/25/14 -04/01/14 < 0.8 < 1.0 < 0.8 04/01/14 -04/29/14 < 0.5 < 0.7 < 0.6 04/29/14 -06/03/14 < 0.7 < 0.7 < 0.6 06/03/14 -07/01/14 < 0.7 < 0.8 < 0.7 (1)07/01114 -07/29/14 (1) < 0.6 < 0.5 < 0.6 07/29/14 -09/02/14 (1) < 0.8 < 0.8 < 0.8 09/02/14 -09/30/14 < 0.6 < 0.6 < 0.6 09/30/14 -10/28/14 < 0.5 < 0.7 < 0.6 10128/14 -12/02/14 < 0.8 < 0.5 < 0.6 12/02/14 -12/30/14 < 0.4 < 0.6 < 0.5 MEAN --Table C-11.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/31/13 -01/28/14 (1) < 193 < 179 < 19u 01128/14 -02/25/14 < 166 < 162 < 164 02/25/14 -04/01/14 < 170 < 175 < 169 04/01/14 -04/29/14 < 186 < 191 < 186 04/29/14 -06/03/14 < 191 < 190 < 189 06103/14 -07/01/14 < 173 < 169 < 173 (1)07101/14 -07/29/14 (1) < 171 < 168 < 164 07/29/14 -09/02/14 (1) < 191 < 192 < 193 09102/14 -09/30/14 < 182 < 183 < 185 09/30/14 -10/28/14 < 165 < 165 < 171 10/28/14 -12/02/14 < 188 < 186 < 185 12/02/14 -12/30/14 < 168 < 165 < 166 MEAN --THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3 Table C-Ih.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD G15-2 12/31/13 -01/28/14 01/28/14 -02/25/14 02/25/14 -04/01/14 04101114 -04/29/14 04/29/14 -06103/14 06/03/14 -07/01/14 07/01/14 -07/29/14 07/29/14 -09/02/14 09/02/14 -09/30/14 09130t14 -10/28114 10/28/14 -12/02/14 12/02/14 -12/30/14 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 (1) < 5<5<4<2<4<4 (1) < 4 (1) < 4<5<6<6<5 MEAN<7<7<3<2<3<5<3<4<6<6<7<5<8<5<4<2<6<5<5<6<6<7<7<4< 13< 11<9<5<8< 11<8<7<9< 13< 12< 13< 16< 12<6<4< 12< 13<9< 12< 11< 14< 15< 10<6<6<4<2<5<5<4<4<4<6<7<3<9<7<4<2<6<5<4<5<7<8<8<5< 11< 12<7<4<8<9<6<9< 11< 12< 11< 11< 15< 14<6<4< 16< 10< 10< 13< 10< 18< 14<9<5<7<4<2<4<5<4<4<5<7<6<6<7<6<3<2<7<5<5<5<6<7<7<5< 10< 10<6<4<9<9<6<7<6< 10< 11<8< 15< 12<6<3< 12<9<8< 10< 10< 11< 12<8<6<6<3<2<4<5<4<4<4<5<6<6<6<6<3<2<5<6<4<6<5<6<6<4<6<6<4<2<4<4<4<4<5<6<6<6<7<6<3<2<6<7<5<6<6<7<6<5< 35< 26< 26< 15< 21< 27< 17< 17< 25< 28< 34< 27< 38< 31< 25< 13< 31< 31< 19< 21< 35< 29< 34< 24< 11<9<7<4<6<9<5<6<6< 10< 11<6<8< 12<8<4<9< 14<7<8<9< 10< 14<8 G15-3 12/31/13 01/28/14 02/25/14 04/01/14 04/29/14 06/03/14 07/01/14 07/29/14 09/02114 09130/14 10/28/14 12/02/14-01/28/14-02/25/14-04101114-04/29/14-06103/14-07/01/14-07/29/14-09/02/14-09/30/14-10128/14-12/02/14-12/30/14<7<5<3<2<6<6<5<5<6<7<7<4 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD Q9-1 12/31/13 -01/28/14 01/28/14 -02/25/14 02/25/14 -04/01/14 04/01/14 -04/29/14 04/29/14 -06/03/14 06/03/14 -07/01/14 07/01/14 -07/29/14 07/29/14 -09/02/14 09/02/14 -09/30/14 09/30/14 -10/28/14 10/28/14 -12/02/14 12/02/14 -12/30/14 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140<5<5<4<2<6 (1) < 6<5<6<5<6<5<8<5<5<4<2<5<6<5<6<5<4<4<8< 10<11< 10<5<9< 12<9< 13< 15< 12< 11< 15<7<4<5<2<6<6<5<7<6<6<5<9< 10< 10<7<5< 10<9<10< 13< 10< 12< 10< 21<5<5<4<2<5<5<6<7<7<6<5<9< 11< 10<9<4< 10< 10<9< 12< 12< 11<8< 12<5<5<4<2<6<6<5<7<6<6<5<7<6<6<4<2<6<7<5<7<7<7<5<7< 34< 23< 29< 15< 28< 34< 27< 34< 34< 33< 31< 41<9<5<9<6<5<9<6< 10< 14<9<7<5 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION Table C-III.1 CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION KI-1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD K1-1 12/31/13 -01/28 12/31/13 -07/01 01/28/14 -02/25 02/25114 -04101 04/01/14 -04/29 04/29/14 -06/03 06/03/14 -07/01 07/01/14 -07/29 07/01/14 -12/30 07/29/14 -09/02 09/02/14 -09/30 09/30/14 -10/28 10/28/14 -12/02 12/02/14 -12/30 GR-B 1-131 H-3 SR-89 SR-90/14/14/14/14/14/14/14/14/14/14/14/14/14/14 5.7 +/- 1.6 < 0.8< 187 6.5 +/- 1.8 3.6 +/- 1.5 2.8 +/- 1.4 3.4 +/- 1.6 4.6 +/- 1.9 7.0 +/- 2.1 5.9 +/- 2.0 6.4 +/-2.1 6.2 +2.1 6.3 +/- 2.1 5.6 +/- 1.6< 0.8< 0.8< 0.6< 0.7< 0.7< 0.5< 0.7< 0.5< 0.5< 0.6< 0.5< 160< 167 2300 +/- 282 9780 +/- 1020 7290 +/- 775 27000 +/- 2740< 197< 182< 167< 186< 188< 4.4 < 0.9< 4.6 < 0.7 MEAN 5.3 +/- 2.8 -11593 +/- 21464 -THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-6 Table C-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION 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 12/31/13 01/28/14 02/25/14 04/01/14 04/29/14 06/03/14 07/01/14 07/29/14 09/02/14 09/30/14 10/28/14 12/02/14 MEAN 01/28/14 02/25/14 04/01/14 04/29/14 06/03/14 07/01/14 07/29/14 09/02/14 09/30/14 10/28/14 12/02/14 12/30/14<5<4<4<2<5<3<3<4<5<5<5<6<5<5<4<2<5<3<3<4<6<6<5<7< 13<9< 10<4< 15<7<7<9< 10< 11< 10< 13<6<4<4<2<8<3<3<4<3<5<4<6< 12<8<8<3< 11<6<6<9< 11< 12<9< 10<5<5<4<2<6<3<3<7<5<6<5<7 9 7 7 3 10 5 5 9 9 8 10 11<5<6<4<2<5<3<3<6<4<6<4<6<8<5<4<2<5<3<3<6<5<6<6<7< 24< 24< 31< 13< 33< 18< 15< 22< 29< 28< 32< 32<10<8<7<3<8<7<5<9<8<6<9<1 Table C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH)SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD INDP PREDATOR 06/13/14 09124/14 MEAN INDB BOTTOM FEEDER 06/13/14 09/24/14 MEAN BKGP PREDATOR 06/19/14 09/30/14 Sr-90< 2.1< 2.3< 2.5< 1.4< 1.7< 2.3 MEAN BKGB BOTTOM FEEDER 06/19/14 09/30/14 MEAN< 1.9< 3.7 C-8 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, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD BKGB BOTTOM FEEDER 06/19/14 09/30/14 MEAN BKGP PREDATOR 06/19/14 09/30/14 MEAN INDB BOTTOM FEEDER 06/13/14 09/24/14 MEAN INDP PREDATOR 06/13/14 09/24/14 MEAN K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 2512 +/- 875 < 51 < 78 < 133 < 60 < 101 < 62 3864 +/- 997 < 61 < 61 < 140 < 67 < 130 < 55< 78< 67 3188 +/- 1912 -2411 +/- 758 < 65 3206 +/- 1103 < 77< 67 < 140 < 60 < 123 < 72< 88 < 174 < 97 < 143 < 75< 75< 76 2809 +/- 1124 3032 +/- 763 < 49 < 48 < 120 < 69 < 129 < 48 3869 +/- 954 < 68 < 60 < 168 < 57 < 148 < 59 3451 +/- 1184 ------< 59< 69 3804 +/- 1259 < 81 2434 +/- 1075 < 68< 80 < 152 < 75 < 202 < 86< 91 < 196 < 67 < 152 < 84* 98< 79 3119 +/- 1937 C-9 Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-1 37 PERIOD A1-3 06/13/14 14610 +/- 1576 < 83 < 78 < 85 < 83 < 103 10/31/14 11700 +/- 1544 < 87 < 99 < 93 < 94 < 98 MEAN 13155 +/- 4115 -----EDCB 10/31/14 17610 +/- 1344 < 43 < 45 < 40 < 42 < 69 MEAN J2-1 06/13/14 10/31/14 MEAN K1-3 06/13/14 10/31/14 MEAN 16770 +/- 1773 11150 +/- 1510 13960 +/- 7948 8369 +/- 1161 8965 +/- 1349 8667 +/- 843< 102< 93< 77< 86< 98 < 79< 97 < 81< 81 < 110< 113 < 111< 67 < 72 < 73 < 81< 92 < 71 < 75 < 88 C-I0 Table C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION. 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I IGROUP 11 GROUP III PERIOD E1-2 F1-3 A3-1 G2-1 1-3-1 M2-1 Q15-1 01/02/14 -01/09/14 17 +/- 5 16 +/-5 16 +/-5 16 +/- 5 14 +/-5 16+/-:t5 15 +/-5 01/09/14 -01/15/14 18 +/-6 20 +/-6 27 +/-6 20 +/-6 19 +/-6 26+/-i6 23 +/-6 01/15/14 -01/23/14 18 +/-5 22 +/-5 20 +/-5 19 +/-5 21 +/-5 21+/-i5 23 +/-5 01/23/14-01/30/14 10 +/-5 12 +/-5 15 +/-5 14 +/-5 14 +/-5 9 +/-5 12 +/-5 01/30/14 -02/06/14 12 +/- 5 22 +/-5 23 +/-5 17 +/- 5 22 +/-6 22 +/- 5 14+/-5 02/06/14-02/12/14 32 +/-7 (1) 31 +/-7 30 +/-7 37 +/-7 38 +/-7 23+/-i6 31+/-7 02/12/14 -02/20/14 26 +/- 6 20 +/-5 26 +/-5 22 +/- 5 25 +/-5 27 +/- 5 19+/-5 02/20/14 -02/27/14 13 +/- 6 14 +/-5 15 +/-5 16 +/- 5 17 +/-5 16 +/- 5 16+/-5 02/27/14-03/06/14 32 +/-6 23 +/-6 35 +/-6 29 +/-6 29 +/-6 27 +/-6 27+/-6 03/06/14-03/12/14 25 +/-6 19 +/-6 22 +/-6 19 +/-6 25 +/-6 (1) 24+/- 6 03/12/14 -03/20/14 12 +/- 4 11 +/- 4 10 +/- 4 12 +/- 4 14 +/- 5 12 +/- 5 10 +/- 4 03/20/14 -03/27/14 20 +/- 5 16 +/-5 18 +/-5 19 +/- 5 16 +/-5 16+/-i5 22+/- 5 03/27/14 -04/03/14 13 +/- 5 11 +/- 5 17 +/- 5 15 +/- 5 11 +/- 5 8 +/- 5 9 +/- 5 04/03/14 -04/10/14 18 +/-4 14 +/-5 21 +/-4 19 +/-4 17 +/-4 17 +/-4 21+/- 4 04/10/14 -04/17/14 14 +/- 5 15 +/-5 17 +/-5 14 +/- 5 15 +/-5 18 t 5 15 +/-5 04/17/14 -04/23/14 19 +/- 6 16 +/-6 15 +/-6 13 +/- 6 12 +/-6 15 +/- 6 17+/- 6 04/23/14-05/01/14 10 +/-4 9 +/-4 12 +/-4 9 +/-4 13 +/-5 6+/-:t4 13+/- 4 05/01/14 -05/07/14 11 +/- 6 8 +/- 6 10 +/- 6 < 8 9 +/-6 < 8 < 8 05/07/14 -05/15/14 16 +/- 5 10 +/-4 13 +/-5 17 +/- 5 16+/-5 (1) 15 +/-5 15+/- 5 05/15/14 -05/22/14 17 +/- 5 17 +/-5 17 +/-5 20 +/- 5 21+/-5 18 +/-5 20+/- 5 05/22/14 -05/29/14 11 +/- 5 8 +/- 4 14 +/- 5 12 +/- 5 12 +/-5 13 +/- 5 13 +/- 5 05/29/14-06/05/14 8 +/-5 8 +/-5 8 +/-5 9 +/-5 11+/-5 < 7 < 7 06/05/14 -06/11/14 12 +/- 5 10 +/- 5 (1) 13 +/- 6 11 +/-5 9 +/- 5 10 +/- 5 06/11/14 -06/19/14 20 +/- 5 14 +/- 4 18 +/- 5 16 +/- 4 16 +/- 4 13 +/- 4 15 +/- 4 06/19/14 -06/25/14 17 +/- 6 12 +/-5 17 +/-5 13 +/- 5 19 +/-6 17 +/-6 20+/- 6 06/25/14 -07/03/14 9 +/- 4 (1) 14 +/-5 18 +/- 5 14 +/-5 14 +/- 5 16+/- 5 07/03/14 -07/10/14 10 +/- 5 22 +/- 6 (1) 17 +/- 5 18 +/- 5 11 +/- 5 20 +/- 5 20 +/- 5 07/10/14 -07/17/14 16 +/- 5 11 +/- 5 20 +/- 5 15 +/- 5 14 +/- 5 18 +/- 5 15 +/- 5 07/17/14 -07/24/14 17 +/- 5 18 +/-5 19 +/-5 17 +/- 5 16 +/-5 15 +/-5 14+/- 5 07/24/14 -07/31/14 9 +/- 5 12 +/- 5 12 +/- 5 14 +/- 5 10 +/- 5 12 +/- 5 11 +/- 5 07/31/14 -08/07/14 17 +/- 5 15 +/-5 19 +/-5 17 +/- 5 19 +/-5 19 +/- 5 16 +/-5 08/07/14 -08/14/14 17 +/- 5 12 +/-5 17 +/-5 15 +/- 5 17 +/-5 19 +/-5 15+/- 5 08/14/14 -08/21/14 16 +/- 5 13 +/-5 13 +/-5 17 +/- 5 16 +/-5 16 +/-5 18+/- 5 08/21/14 -08/28/14 17 +/- 5 21 +/-5 21 +/-7 (1) 14 +/- 5 18 +/-5 18 +/-5 16+/- 5 08/28/14-09/04/14 9 +/-5 20 +/-6 20 +/-6 12 +/-5 15 +/-5 14 +/-5 15+/- 5 09/04/14 -09/10/14 17 +/- 6 19 +/-6 23 +/-6 17 +/- 6 16 +/-6 15 +/- 6 16+/- 6 09/10/14 -09/18/14 10 +/- 4 12 +/-4 17 +/-5 15 +/- 5 15 +/-5 15 +/- 5 17+/- 5 09/18/14 -09/25/14 17 +/- 5 24 +/-5 20 +/-5 20 +/- 5 23 +/-5 24 +/-6 20+/- 5 09/25/14-10/02/14 24 +/-6 20 +/-5 24 +/-6 26 +/-6 19 +/-5 20 +/-5 24+/- 6 10/02/14 -10/09/14 18 +/- 5 13 +/-5 19 +/-5 19 +/- 5 18 +/-5 16 +/- 5 17+/- 5 10/09/14 -10/16/14 21 +/- 5 21 +/-5 19 +/-5 20 +/- 5 20 +/-5 20 +/-5 18 +/-5 10/16/14 -10/23/14 12 +/- 5 10 +/- 5 14 +/- 5 13 +/- 5 15 +/- 5 11 +/- 5 14 +/- 5 10/23/14 -10/30/14 16 +/- 5 16 +/-5 19 +/-6 17 +/- 5 20 +/-6 19 +/-6 20+/- 6 10/30/14 -11/06/14 15 +/- 5 16 +/- 5 13 +/- 5 15 +/- 5 13 +/- 5 16 +/- 5 14 +/- 5 11/06/14 -11/13/14 19 +/- 5 17 +/- 5 18 +/- 5 18 +/- 5 17 +/- 5 20 +/- 5 20 +/- 5 11/13/14 -11/20/14 17 +/- 5 19 +/- 5 15 +/- 5 19 +/- 5 18 +/- 5 16 +/- 5 16 +/- 5 11/20/14 -11/26/14 26 +/- 6 22 +/- 6 22 +/- 6 28 +/- 7 26 +/- 6 25 +/- 9 (1) 21 +/- 6 11/26/14 -12/04/14 18 +/- 5 16 +/- 4 17 +/- 5 18 +/- 5 21 +/- 5 (1) 21 +/- 5 12/04/14 -12/11/14 19 +/- 6 14 +/- 5 14 +/- 5 15 +/- 5 14 +/- 5 17 +/- 5 13 +/- 5 12/11/14 -12/17/14 25 +/- 6 19 +/- 6 21 +/- 6 19 +/- 6 20 +/- 6 17 +/- 6 21 +/- 6 12/17/14 -12/24/14 8 +/- 4 11 +/- 4 14 +/- 5 14 +/- 5 12 +/- 5 16 +/- 5 17 +/- 5 12/24/14 -01/01/15 19 +/- 5 16 +/-4 20 +/-5 17 +/- 5 17 +/-5 14 +/-4 19+/- 5 MEAN 16 +/- 11 16 +/- 10 18 +/- 10 17 +/- 10 17 +/- 11 17 +/- 9 17 +/- 9 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1Il 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, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I -CLOSEST TO THE SITE BOUNDARY COLLECTION MIN MAX MEAN +PERIOD 2SD GROUP II -INTERMEDIATE OFFSITE GROUP III -CONTROL LOCATIONS COLLECTION PERIOD MIN MAX MEAN+/-2SD COLLECTION PERIOD MIN MAX MEAN+/-2SD 011/0114 01/30/14 02127/14 04/03/14 05101/14 05/29/14 07/03/14 07/31/14 09/04/14 10/02/14 10/30/14 12/04/14 U1/1U/14 02/27/14 04/03/14 05/01/14 05129t14 07/03/14 07/31/14 09/04/14 10/02/14 10/30/14 12/04/14 01/01/15 1U 12 11 9 8 8 9 9 10 10 15 8 32 32 32 19 17 20 22 21 24 21 26 25 11 +7 21 +/- 16 18 +/- 14 14 +/- 7 12 +/- 8 12 +/- 8 14 +/- 9 16 +/- 8 18 +/- 10 16 +/- 8 18 +/- 7 16 +/- 11 U1/U0I14 -U1/30/14 01/30114 02/27/14 04(03/14 05/01/14 05/29/14 07/03/14 07/31/14 09/04/14 10/02/14 10/30/14 12/04/14 02/27/14 04/03/14 05(01(14 05129/14 07/03/14 07/31/14 09104114 10/02/14 10/30/14 12/04/14 01/01115 15 8 6 9 8 10 12 15 11 13 12 27 38 35 21 21 19 20 21 26 20 28 21 18 +/-1 24 +/- 14 19 +/- 15 15 +/- 7 15-+/- 7 14 7 15 6 17 5 19 7 17 +/-5 19 +/- 9 16 +/- 6 01102/14 01130/14 02/27/14 04(03/14 05107/14 06/05/14 07/03/14 07/31/14 09/04/14 10/02/14 10/30/14 12104/14 01/30/14 02/27/14 04/03/14 05/01(14 05t29114 07/03/14 07/31/14 09/04/14 10/02/14 10/30/14 12/04/14 01/01/15 12 14 9 13 13 10 11 15 16 14 14 13 23 31 27 21 20 20 20 18 24 20 21 21 20 18 16 16 15 15 16 19 17 18 18+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-11 15 17 7 8 9 8 2 8 5 6 7 I',J 01/02/14 -01/0'1115 8 32 16 +/- 10 01/02/14 -01101/15 6 38 17 +/- 10 01102/14 -01/01/15 9 31 17 +/- 9 Table C-VI.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD A3-1 01/02/14 -04/03/14 04/03/14 -07/03/14 07/03/14 -10/02/14 10/02/14 -01/01/15 MEAN E1-2 01/02/14 -04/03/14 04/03/14 -07/03/14 07/03/14 -10/02/14 10/02/14 -01/01/15 MEAN F1-3 01/02/14 -04/03/14 04/03/14 -07/03/14 07/04/14 -10/02/14 10/02/14 -01/01/15 MEAN G2-1 01/02/14 -04/03/14 04/03/14 -07/03/14 07/03/14 -10/02/14 10/02/14 -01/01/15 MEAN H3-1 01/02/14 -04/03/14 04/03/14 -07/03/14 07/03/14 -10/02/14 10/02/14 -01/01/15 MEAN M2-1 01/02/14 -04/03/14 04/03/14 -07/03/14 07/03/14 -10/02/14 10/02/14 -01/01/15 MEAN Q15-1 01/02/14 -04/03/14 04/03/14 -07/03/14 07/03/14 -10/02/14 10/02/14 -01/01/15 MEAN Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 68+/-38 <4 <4 <4 87+/-31 <4 <5 <4 79+/-27 <3 <4 <3 95 +/- 23 < 3 < 3 < 3 82 +/- 23 57 +/- 20 < 3 < 3 < 3 73 +/- 26 < 3 < 3 < 2 50+/-33 <3 <4 <4<46 <4 <6 <5 60 +/- 24 ---69 +/- 30 < 3 < 4 < 2 50+/-17 <2 <3 <3 60+/-39 <4 <6 <4 46+/-16 <1 <3 <2 56 +/- 21 -99+/-37 <7 <9 <5 62+/-21 <2 <3 <2<61 <4 <6 <4 44+/-21 <2 <3 <3<4<6<4<3<3<3<5<5<4<3<6<2<8<3<7<3<3<4<3<4<5<3<3<4<5<4<4<5<5<6<8<8 68 +/- 56<8 <4 <4<10 <4 <4<8 <3 <3<6 <3 <4<3 <3<3 <2<2 <3<4 <3 69+/-20 <3 <4 <2 69+/-25 <3 <4 <2 94+/-29 <3 <4 <3 37+/-20 <2 <3 <2<9 <4 <4<5 <2 <2<10 <4 <4<4 <2 <2<16 <6 <8<5 <2 <3<12 <5 <3<5 <2 <2<6 <2 <3<6 <2 <2<5 <2 <2<6 <2 <3<8 <3 <3<6 <3 <2<6 <2 <2<7 <3 <3<10 <4 <4<6 <2 <3<6 <2 <3<7 <4 <3 67 +/- 47 63+/-22 <3 <5 <3 54+/-23 <2 <3 <2 70+/-22 <2 <3 <1 102+/-22 <3 <4 <3 72 +/- 42 55+/-26 <4 <4 <5 95+/-29 <3 <3 <3 49+/-28 <4 <5 <2 53+/-29 <4 <5 <4 63 +/- 43 C-13 Table C-VII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 01/02114 -01109/14 01/09/14 -01/15/14 01/15114 -01/23/14 01/23/14 -01/30/14 01130/14 -02/06/14 02/06/14 -02/12/14 02/12/14 -02/20/14 02/20/14 -02/27/14 02/27/14 -03/06/14 03/06/14 -03/12/14 03/12/14 -03/20/14 03/20/14 -03/27/14 03/27/14 -04/03/14 04/03/14 -04/10/14 04/10/14 -04/17/14 04/17/14 -04/23/14 04/23/14 -05/01/14 05101/14 -05/07/14 05/07/14 -05/15/14 05/15/14 -05/22/14 05/22/14 -05/29/14 05/29/14 -06/05/14 06/05/14 -06/11/14 06/11/14 -06/19/14 06/19/14 -06/25/14 06/25/14 -07/03/14 07/03/14 -07/10/14 07/10/14 -07/17/14 07/17/14 -07/24/14 07/24/14 -07/31/14 07/31/14 -08/07/14 08/07/14 -08/14/14 08/14/14 -08/21/14 08/21/14 -08/28/14 08/28/14 -09/04/14 09/04/14 -09/10/14 09/10/14 -09/18/14 09/18/14 -09/25/14 09/25/14 -10/02/14 10/02/14 -10/09/14 10/09/14 -10/16/14 10/16/14 -10/23/14 10/23/14 -10/30/14 10/30/14 -11/06/14 11/06/14 -11/13/14 11/13/14 -11/20/14 11/20/14 -11/26/14 11/26/14 -12/04/14 12/04/14 -12/11/14 12/11/14 -12/17/14 12/17/14 -12/24/14 12/24/14 -01/01/15 GROUP I El -2< 55< 65< 60* 53* 61* 62 (1)* 61* 56* 65* 57< 43* 61* 68< 54* 57* 53* 25*<67* 60* 68* 23* 28< 41* 33* 69* 23* 51* 41* 27* 19* 25* 30* 57* 60* 59* 53< 64* 67* 66* 59* 38* 30* 40* 69* 25< 68* 67* 67* 57* 66* 67* 31 Fl -3< 53<64<58< 51<59<60< 44<c49* 64* 55*<43* 58* 66* 22<55* 52* 63* 66* 58* 66* 22* 27< 40* 33* 68 (1)* 56 (1)* 41* 27* 54* 25* 29* 56* 59* 58* 52* 63* 66* 65* 58* 37* 12* 39* 68* 25< 67* 65* 68* 56* 65* 66* 31 I A3-1* 51* 56* 53* 69* 56* 58* 62* 48< 48< 41< 46* 16* 64* 55* 57* 51* 61< 66* 56* 61* 23* 26 (1)* 48* 61* 23< 48* 39* 27* 62* 25* 29* 56* 63 (1)* 67* 53* 67* 59* 60* 58* 38* 30< 41< 64* 28* 19< 43* 67< 43* 68* 61* 38 G2-1* 54< 64* 59* 52* 60* 26* 45* 51* 65* 56< 43* 59* 67< 54* 56* 52< 64* 66* 37* 67* 23* 29* 42., 34< 70<- 24< 52< 43< 28< 56< 26< 12< 59< 61< 61< 54< 66< 68< 68< 60< 39< 31< 41< 65< 26< 38< 68< 69< 59< 68< 69< 32 GROUP 11 1-3-1* 56* 67< 56< 54* 62* 63< 46* 18* 67* 43* 49< 46* 69* 55* 58* 54* 66* 69* 50 (1)* 29* 23* 27* 42< 34* 68< 24* 49< 42* 28* 55* 26* 30* 58* 23* 60* 53* 65* 67* 66* 59* 38* 31< 40* 70* 26< 69* 67* 70* 58* 67* 68* 39 M2-1* 52* 56< 54* 69* 57* 58* 63* 49* 48 (1)* 53< 44* 65<53<57* 51* 62* 67* 56* 61< 24< 11* 41* 38* 61< 24* 48* 39* 28* 63< 26* 29* 57* 39* 61* 53* 28* 61* 60* 55* 39* 30< 42< 65* 28* 19* 68 (1)(1)* 42* 69* 63* 15 IGROUP III Q15-1< 53< 57< 54< 69< 58< 59< 63< 49< 50< 42< 20< 45< 65< 54< 57< 52< 62< 67< 57< 62< 24< 26< 41< 37< 59< 24< 48< 39< 27< 62< 25< 29< 57< 39< 60< 53< 67< 60< 60< 54< 38< 30< 41< 64< 28< 19< 43< 67< 43< 69< 61< 38 U MEAN--(1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C- 14 Table C-VIII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA CONTROL FARM TM-M-K15-3 I TM-M-E2-2 INDICATOR FARM TM-M-F4-1 TM-M-G2-1 TM-M-P4-1 COLLECTION PERIOD 01/08/14 02/05/14 03/05/14 03/19/14 04/02/14 04/16/14 04/30/14 05/14/14 05/28/14 06/11/14 06/25/14 07/09/14 07/23/14 08/06/14 08/20/14 09/03/14 09/17/14 10/01/14 10/15/14 10/29/14 11/12/14 11/25/14 12/10/14< 0.8< 0.8< 0.8< 0.8< 0.6< 0.7< 0.7< 0.6< 0.6< 0.6< 0.6< 0.6 (1)< 0.6< 0.7< 0.9< 0.5< 0.5< 0.8< 0.8< 0.3< 0.6< 0.7< 0.6< 0.7< 0.9< 0.8< 0.8< 0.6< 0.7< 0.9< 0.7< 0.6< 0.6< 0.6< 0.4< 0.6< 0.9< 0.7< 0.6< 0.6< 0.5< 0.7< 0.8< 0.7< 0.8< 0.6< 0.8< 0.7< 0.5< 0.6< 0.6< 0.8< 0.6< 0.7< 0.7< 0.5< 0.6< 0.5< 0.6< 0.7< 0.6< 0.5< 0.5< 0.6< 0.8< 0.9< 0.7< 0.6< 0.7< 0.7< 0.9< 0.7< 0.9< 0.8< 0.9< 0.7< 0.9< 0.7< 0.6< 0.7< 0.4< 0.6< 0.9< 0.7< 0.5< 0.7< 0.7< 0.7< 0.4< 0.6< 0.6< 0.8< 0.6< 0.7< 0.8< 0.9< 0.6< 0.7< 0.7< 0.8< 0.6< 0.6< 0.6< 0.5< 0.7< 0.8< 0.7< 0.6< 0.5< 0.7< 0.6< 0.6< 0.7<'0.8 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-15 Table C-VIII.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+ 2 SIGMA CONTROL FARM I INDICATOR FARM COLLECTION PERIOD K15-3 SR-90 I P4-1 I E2-2 I F4-1 I G2-1 SR-89 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 01/08/14 -03/19/14 04/02/14 -06/25/14 07/09/14 -09/17/14 10/01/14 -12/10/14< 3.6< 3.8< 3.2< 2.8< 0.6< 0.6< 0.9< 0.9< 4.7< 4.6< 3.5< 2.6< 0.7< 0.3< 1.0< 0.7< 3.8<4.3< 1.7< 3.5< 0.6< 0.4< 0.5< 1.0< 3.9< 4.0< 3.2< 2.8< 0.8< 0.6< 0.8< 1.0< 4.9< 3.4< 2.4< 2.9< 0.8< 0.6< 0.6* 0.9 MEAN 0~~

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE L--COLLECTION PERIOD 01/08/14 02/05/14 03/05/14 03/19/14 04/02/14 04/16/14 04/30/14 05/14/14 05/28/14 06/11/14 06/25/14 07/09/14 07/23/14 08/06/14 08/20/14 09/03/14 09/17/14 10/01/14 10/15/14 10/29/14 11/12/14 11/25/14 12/10/14 MEAN 01/08/14 02/05/14 03/05/14 03/19/14 04/02/14 04/16/14 04/30/14 05/14/14 05/28/14 06/11/14 06/25/14 07/09/14 07/23/14 08/06/14 08/20/14 09/03/14 09/17/14 10/01/14 10/15/14 10/29/14 11/12/14 11/25/14 12/10/14 MEAN K-40 Cs-134 Cs-1 37 Ba-140 La-140 11b +/- lbl 1294 +/- 160 1442 +/- 170 1171 +/- 106 1409 +/- 166 1309 +/- 145 1260 +/- 131 1347 +/- 168 1302 +/- 147 1473 +/- 151 1258 +/- 134 1511 +/- 203 1347 +/- 126 1343 +/- 183 1292 +/- 128 1300 +/- 163 1156 +/- 153 1388 +/- 125 1191 +/- 111 1411 +/- 169 1292 +/- 182 1340 +/- 173 1325 +/- 113 1319 +/- 189 1049 +/- 157 1348 +/- 139 1443 +/- 178 1335 +/- 93 1500 +/- 172 1333 +/- 135 1306 +/- 141 1322 +/- 132 1382 +/- 175 1343 +/- 128 1224 +/- 159 1478 +/- 174 1259 +/- 118 1341 +/- 169 1456 +/- 148 1318 +/- 156 1468 +/- 156 1507 +/- 208 1473 +/- 130 1517 +/- 138 1263 +/- 158 1483 +/- 176 1396 +/- 114 1371 +/- 225<6<6< 6<5<7<6<5<7<7<6<6<7<5<6<5<8<5<4<4<7<6<6<5<8<5<5<4<5<6<6<5<8<7<5<7<4<7<4<6<4<8<5<8<7<6<4<7<6<7<5<8<6<6<8<8<7<7< 10<6<8<5<8<6<6<4<7<7<9<5<9<6<7<4<5<6<6<6<8<7<7<8<4<7<6<8<6<7<5<8<7<8<5< 37t< 44< 38< 21< 37< 34< 36< 24< 32< 34< 26< 43< 24< 38< 22< 59< 28< 27< 45< 42< 38< 43< 24< 42< 33< 36< 20< 26< 28< 41< 23< 43< 37< 31< 31* 23< 36< 22< 49< 25< 43< 46< 46< 33< 40< 22< 10< 12<8<6< 12< 10< 13<5< 10<7<8< 11<6<6<8< 10<8<8< 12< 13< 10< 14<7< 13< 12< 11<6<5<7< 12<6< 12<9<6< 10<6<9<7< 11<3< 11< 14< 11<8< 10<6 F4-1 C-17 Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PFRIflfl K-40 Cs-134 Cs-137 Ba-140 La-1 40 PERIOD G2-1 01/08/14 02/05/14 03/05/14 03/19/14 04/02/14 04/16/14 04/30/14 05/14/14 05/28/14 06/11/14 06/25/14 07/09/14 07/23/14 08/06/14 08/20/14 09/03/14 09/17/14 10/01/14 10/15/14 10/29/14 11/12/14 11/25/14 12/10/14 1090 1195 985 1218 1127 971 915 770 1240 963 802 1296 957 636 1072 1289 851 907 1126 756 824 973 1133+/- 158+/- 118+/- 105+/- 115+/- 149+/- 135+/- 130+/- 139+/- 150+/- 103+/- 131+/- 215+/- 133+/- 161+/- 184+/- 169+/- 143+/- 171+/- 110+/- 120+/- 150+/- 133+/- 142<5<6<5<4<7<6<6<8<7<5<8<7<5<8<7<6<7<9<4<5< 12<5<7 MEAN 1004 +/- 366<7<7<6<5<7<8<6<8<8<6<9<8<6<7<8<8<8<9<6<5< 10<7<7<8<6<7<5<8<6<5<8<8<6<7<6<4<7<6<6<7< 10<5<6<9<6<4< 38< 43* 30< 24< 43< 39< 42< 40< 37< 28< 35< 37< 32< 42< 29< 51< 33< 44< 44< 43< 51< 33< 35< 42< 39< 43< 22< 37< 31< 34< 30< 34< 26< 31< 34< 19< 28< 26< 42< 29< 48< 44< 41< 42< 35< 22< 12< 11<7<6< 14< 11< 15< 12< 12< 10<9< 14<9< 14< 12< 15<9< 13< 15< 12< 12<8<11< 14<9< 10<8<11<7< 11<5<9<8<7<9<5<12<8< 15<8* 13< 14<11<11< 10<6 K15-3 01/08/14 02/05/14 3/5/2014 03/19/14 4/2/2014 04/16/14 04/30/14 05/14/14 05/28/14 06/11/14 06125/14 07/09/14 07/23/14 08/06/14 08/20/14 09/03/14 09/17/14 10/01/14 10/15/14 10/29/14 11/12/14 11/25/14 12/10/14 1293 +/-1332 +/-1101 +/-1028 +/-1392 +/-1448 +/-1295 +/-1292 +/-1384 +/-1254 +/-1060 +/-1222 +/-1244 +/-1282 +/-1275 +/-1333 +/-1231 +/-1068 +/-1369 +/-1174 +/-1335 +/-1077 +/-1275 +/-164 122 166 105 188 130 136 172 182 129 139 171 118 156 151 148 140 183 116 132 194 157 108<6<5<7<4<7<6<4<5<7<5<6<6<4<6<5<5<6<8<4<6<7<6<4 MEAN 1251 +/- 233 C-18 Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE P4-1 COLLECTION PERIOD 01/08/14 02/05/14 03/05/14 03/19/14 04/02/14 04/16/14 04/30/14 05/14/14 05/28/14 06/11/14 06/25/14 07/09/14 07/23/14 08/06/14 08/20/14 09/03/14 09/17/14 10/01/14 10/15/14 10/29/14 11/12/14 11/25/14 12/10/14 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1318 +/- 123 1339 +/- 171 1290 +/- 133 1465 +/- 107 1487 +/- 124 1390 +/- 105 1378 +/- 140 1430 +/- 124 1482 +/- 155 1388 +/- 116 1363 +/- 181 1219 +/- 183 1467 +/- 128 1438 +/- 184 1398 +/- 182 1350 +/- 136 1206 +/- 118 1117 +/- 184 1188 +/- 121 1366 +/- 162 1450 +/- 177 1492 +/- 168 1411 +/- 167 1367 +/- 206<5<6<5<4<5<4<5<5<5<4<7<8<4<7<7<5<4<7<5<6< 11<7<3<6<6<6<5<5<4<5<5<6<4<7<9<5<8<7<4<5<6<5<7<9<8<2< 30<41< 26< 19< 23< 19< 38< 20< 26< 18< 27< 36< 23< 35< 27< 34* 16< 34< 47< 42< 50< 38< 16< 10< 12<7<6<7<5<13<6<8<6< 10<8<6< 12<5<7<6< 10< 15< 15< 14< 15<4 C-19 Table C-IX.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION SR-90 PERIOD Be-7 K-40 1-131 Cs-134 Cs-137 B10-2 Broccoli Leaves Cabbage & Leaves Cauliflower Leaves Cabbage Cabbage Sunflower Leaves Sweet Corn Leaves Sweet Corn Tomatoes Cabbage Neck Pumpkin Leaves Sunflower Leaves Cabbage Neck Pumpkin Leaves Sunflower Leaves Sweet Potatoes E1-2 Cabbage Sweet Corn Tomatoes Sweet Potatoes H1i-2 Eggplant Leaves Squash Leaves Zucchini Leaves Eggplant Leaves Squash Leaves Zucchini Leaves Cucumber Leaves Squash Leaves Zucchini Leaves Broccoli Leaves Cauliflower Leaves Turnip Greens 06/30/14 06/30/14 06/30/14 07/23114 07/30/14 07/30/14 07/30/14 08/04/14 08/04/14 08/27/14 08/27/14 08/27/14 09/24/14 09/24/14 09/24/14 10/08/14<3<3<4<2<4 14 + 3<3 18 + 3<2<3<2<2 4+/-3< 244< 185< 282< 186< 218 1595 +/- 268 1096 +/- 229< 133< 95< 162 2515 +/- 224 1088 +/- 190< 108 1497 +/- 90 795 +/- 84< 176 3697 4292 5720 2865 2559 6073 3642 2449 1672 2450 5745 8693 2744 5150 6838 3518+/- 616+/- 458+/- 608+/- 409+/- 529+/- 550+/- 398+/- 376+/- 258+/- 335+/- 416+/- 438+/- 217+/- 174+/- 214+/- 460< 55< 44< 58< 36< 49<41< 39< 18< 16< 59< 52< 58< 51< 44< 30< 37< 26< 19< 23< 20* 22< 19< 20< 15< 10< 14< 12< 14< 10<7<5< 21< 29< 24< 29< 20* 21< 22< 22<16<11< 19< 16* 16< 11<8<6< 21 MEAN 12 +/- 14 1431 +/- 1214 4257 +/- 3877 -07/23/14 08/04/14 08/04/14 10/08/14<1 122 179 148 171 2680 2976 3008 4872+/- 279+/- 368+/- 363+/- 546* 22< 30< 24< 32< 12< 22< 18< 19< 14< 23< 18< 21 MEAN 3384 +/- 2006 -06/30/14 06/30/14 06/30/14 07/30/14 07/30/14 07/30/14 08/27/14 08/27/14 08/27/14 09/24/14 09/24/14 09/24/14< 4 403 +/- 201 8 +/-2 353 +/- 196 4 +/-2 < 278< 3 940 +/- 230 8 +/-2 1944 +/- 270 10 +/-2 1055 +/- 178< 2 1129 +/- 207 13 +/- 3 488 +/- 131 10 +/- 2 563 +/- 139 4 +/-1 < 108< 2 < 110 2 +/-1 < 82 6885 +/- 497 4753 +/- 579 5055 +/- 591 4196 +/- 533 5062 +/- 504 4452 +/- 379 2970 +/- 322 2900 +/- 270 4499 +/- 375 3979 +/- 241 2738 +/- 205 6877 +/- 240< 37< 51* 46< 50< 51< 29< 58< 47< 59< 52< 50< 43< 19< 23< 20< 22< 20< 15< 14< 11< 14< 10< 10<8< 19< 22* 24* 27< 24* 14* 15* 12* 14< 10< 10<9 MEAN 7 +/-7 859 +/- 1065 4531 +/- 2723 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-20 Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREM/QUARTER STATION CODE MEAN+/- 2 S.D.JAN -MAR APR -JUN JUL -SEP OCT -DEC A1-4 A3-1 A5-1 A9-3 B1-1 B1-2 B2-1 B5-1 Cl-i C1-2 C2-1 C5-1 C8-1 D1-1 D1-2 02-2 D6-1 E1-2 E1-4 E2-3 E5-1 E7-1 F1-1 F1-2 F1-4 F2-1 F5-1 G1-2 G1-3 G1-5 G1-6 G2-4 G5-1 H1-1 H3-1 H5-1 H8-1 J1-1 J1-3 J3-1 J5-1 J7-1 K1 -4 K2-1 K3-1 K5-1 K8-1 L1-1 18.7 +/- 3.4 18.6 +/- 2.6 23.3 +/- 5.2 19.8 +/- 3.6 19.7 +/- 2.8 19.2 +/- 3.0 19.0 +/- 2.6 22.4 +/- 4.0 22.1 +/- 3.2 19.8 +/- 2.9 20.9 +/- 3.8 23.0 +/- 3.4 22.5 +/- 3.9 21.8 +/- 2.8 20.8 +/- 3.6 25.2 +/- 5.1 24.1 +/- 5.7 20.5 +/- 3.0 27.9 +/- 1.4 23.7 +/- 4.2 22.9 +/- 4.3 22.6 +/- 3.6 21.8 +/- 3.1 35.6 +/- 4.2 35.3 +/- 4.6 23.9 +/- 4.1 25.3 +/- 5.2 22.3 +/- 3.1 28.0 +/- 3.1 21.7 +/- 3.2 23.6 +/- 2.7 25.9 +/- 5.2 21.7 +/- 3.3 21.5 +/- 2.9 18.2 +/- 1.8 18.0 +/- 2.6 32.6 +/- 7.8 19.5 +/- 3.6 18.0 +/- 2.1 21.5 +/- 4.4 23.5 +/- 6.1 25.5 +/- 5.0 19.7 +/- 2.9 23.6 +/- 4.3 19.6 +/- 3.9 23.2 +/- 4.7 23.0 +/- 3.8 20.4 +/- 3.0 16.2 16.8 20.9 17.6 18.0 17.1 17.5 19.6 19.9 18.4 18.9 20.7 19.7 20.3 18.4 21.8 20.6 18.8 27.1 20.9 19.9 20.2 19.9 37.0 37.1 21.2 21.6 20.1 28.4 20.1 23.2 22.6 19.8 19.6 17.0 16.5 27.7 17.2 16.9 18.7 20.0 22.4 18.3 20.7 17.6 20.2 20.5 18.4 18.8 18.7 23.0 19.6 19.2 19.3 18.5 22.4 21.9 18.7 20.2 22.8 22.7 21.3 20.7 24.8 23.1 20.1 27.6 23.4 22.7 22.2 21.2 35.3 35.4 24.0 25.6 22.2 27.6 20.9 21.8 25.4 20.9 21.2 18.2 17.6 31.7 18.9 17.4 21.0 22.1 24.6 18.7 23.2 18.4 23.0 22.6 20.3 19.9 19.7 (1)20.3 20.7 20.5 20.6 24.1 23.3 21.3 23.4 24.5 23.7 23.6 22.5 26.9 26.9 22.3 28.5 25.6 24.2 24.2 22.9 37.4 36.6 26.1 27.5 23.4 29.9 23.8 24.7 28.6 23.7 22.4 18.5 19.5 36.8 20.8 19.1 22.8 25.9 27.2 21.2 25.1 21.9 23.8 24.7 21.7 19.8 19.4 26.1 21.9 20.9 20.1 19.3 23.5 23.2 20.8 21.3 24.2 24.0 21.9 21.8 27.3 26.0 21.0 28.4 25.0 24.7 23.8 23.1 32.8 32.0 24.3 26.5 23.5 26.2 22.1 24.5 27.1 22.3 22.8 19.1 18.5 34.4 21.0 18.7 23.7 26.2 27.8 20.7 25.4 20.4 25.8 24.3 21.2 (1)(1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-21 Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREM/QUARTER STATION MEAN JAN -MAR APR -JUN JUL -SEP OCT -DEC CODE +/- 2 S.D.L1-2 19.9 +/- 2.5 18.4 19.4 21.1 20.7 L2-1 21.8 +/- 2.8 19.9 21.5 22.8 22.9 L5-1 20.4 +/- 2.4 18.9 20.0 21.4 21.3 L8-1 22.0 +/- 4.7 18.8 21.7 24.1 23.4 MI-i 18.1 +/- 2.3 16.5 18.1 19.2 18.5 M1-2 21.3 +/- 4.9 18.5 20.2 23.7 23.0 M2-1 19.3 +/- 3.2 17.5 18.7 21.3 19.6 M5-1 21.3 +/- 3.5 19.0 21.0 22.8 22.6 M9-1 26.0 +/- 4.8 23.1 25.1 28.6 27.2 N1-1 20.8 +/- 4.2 18.3 19.9 22.9 22.1 N1-3 20.5 +/- 3.0 19.0 19.8 22.4 21.0 N2-1 22.3 +/- 4.4 19.7 21.3 23.5 24.7 N5-1 18.7 +/- 3.6 16.5 18.3 20.8 19.1 N8-1 22.7 +/- 3.0 20.8 22.5 24.1 23.7 P1-i 20.5 +/- 3.2 18.3 20.6 21.7 21.7 P1-2 19.0 +/- 2.4 17.7 18.5 20.4 19.6 P2-1 25.2 +/- 5.0 21.9 25.0 26.3 27.7 P5-1 22.4 +/- 4.4 19.6 21.9 24.8 23.3 P8-1 19.1 +/- 3.7 16.8 18.7 21.0 20.1 Q1-1 20.9 +/- 3.6 18.8 20.1 22.3 22.4 Q1-2 17.7 +/- 2.4 16.2 17.3 18.5 18.8 Q2-1 19.4 +/- 4.0 16.8 19.0 21.4 20.5 Q5-1 20.2 +/- 2.8 18.6 19.6 21.4 21.3 Q9-1 20.9 +/- 4.3 17.9 20.8 22.3 22.7 R1-1 18.5 +/- 2.4 16.9 18.4 19.9 18.8 R1-2 19.2 +/- 2.7 17.6 18.7 20.6 20.0 R3-1 24.3 +/- 4.2 21.3 24.3 25.8 25.7 R5-1 22.9 +/- 4.5 19.6 23.2 24.4 24.3 R9-1 23.2 +/- 2.6 21.5 23.3 24.5 23.6 B10-1 21.3 +/- 2.8 19.2 21.8 22.2 22.2 D15-1 21.8 +/- 3.9 19.5 21.1 24.0 22.7 F10-1 25.4 +/- 5.0 22.4 24.5 27.8 27.1 F25-1 23.1 +/- 3.2 20.9 23.2 23.6 24.7 G10-1 29.5 +/- 5.9 25.2 30.2 30.8 31.8 G15-1 26.1 +/- 2.0 24.7 27.0 26.7 26.0 H15-1 22.4 +/- 4.0 19.7 22.5 24.4 23.3 J15-1 24.8 +/- 4.3 22.4 23.7 26.9 26.4 K15-1 21.0 +/- 2.9 19.7 19.9 22.7 21.9 L15-1 21.7 +/- 4.2 19.1 21.3 24.1 22.4 N15-2 23.7 +/- 4.2 21.1 23.1 25.7 25.1 Q15-1 23.8 +/- 4.6 21.0 23.0 25.5 25.9 R15-1 21.3 +/- 2.1 19.9 21.1 22.4 21.6 C-22 TABLE C-X.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREM/QUARTER

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA I I COLLECTION PERIOD SITE BOUNDARY+/-2 S.D.INDICATOR CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 21.3 +/- 13.0 21.9 +/- 11.1 23.7 +/- 11.1 22.5 +/- 8.7 19.5 +/- 4.0 21.6 +/- 5.0 23.6 +/- 5.8 23.3 +/- 5.7 21.2 +/- 4.2 23.3 +/- 5.9 25.2 +/- 4.8 24.7 +/- 5.8 TABLE C-X.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREMQUARTER LOCATION SAMPLES PERIOD PERIOD ANALYZED MINIMUM MAXIMUM PERIOD MEAN+/- 2 S.D.SITE BOUNDARY INDICATOR CONTROL 76 239 44 16.2 16.5 19.1 37.4 36.8 31.8 22.4 +/- 11.0 22.0 + 6.1 23.6 +/- 5.9 SITE BOUNDARY STATIONS -AI-4, B1-2, Cl-2, Di-1, E1-4, F1-2, FI-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, LI-1, Mi-1, N1-3, P1-2, Q1-2, Ri-i INDICATOR STATIONS -A3-1, A5-1, A9-3, Bi-1, B10-1, B2-1, B5-1, Cl-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, Ei-2, E2-3, E5-1, E7-1, Fi-1, F10-1, F2-1, F5-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, Ji-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, Li-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, Ni-i, N2-1, N5-1, N8-1, Pi-1, P2-1, P5-1, P8-1, Qi-i, 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, N15-2, Q15-1, R15-1 C-23 FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2014 10000 -1_10000-_ 1000-100-10 0 Station J1-2 (Downstream of Discharge)

U Station Q9-1 (Control)...........................................

i......................

o...... .. o.............

.................................................

.. ..................... .....h. .... ..................... ........... .........Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec n'.Month 1000000100000-10000-* -1000-o 100-a. 10 E Station K1-1 (TMINS Liquid Discharge)

.................................................................................................................................................

...............................

......... ......................................................

..... .......................Jan Feb Mar Apr May Jun Jul Aug Sep Month Oct Nov Dec FIGURE C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2014-Indicator Samples-Control Samples t'j LAh 0.cn 0)U 0 C-)0~12000 11000 10000 9000 8000 7000 6000 5000 4000 3000 2000 1000 0-1000 II LO (0C 1- w a N 0 '( f- w MCD y- " 0 Loco 1-CD m cD N m L~* DO I- wO MD 0 NC* I r-f-r- r'- -I-C D D D wO wO wO wOC MOOCC w CO g M M MMMCD C" CD D D 0 a O~ 00- -----)CD~~~~~ ~~ SDC DC DC D DC DC DC CD C' C' CD aD a CD aD aD a a CD 0a---- ---- ---- --- ---- ---- ---NDN CND N(N N~N N N N N " N(N (N Year FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2014 El Indicator Samples E] Control Samples 10 9 8 7 -----

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2014 NOTE: The mean values are calculated using both the MDCs and the positive values.EJ Indicator Samples M Control Samples 500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L400 .. ........a 300 -0):D 200 -----C.) 300 -- -; -t ----- --o 200 -- -:: ---s~ ---.::: -~E~. --... ... ......(L 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec-.1 Month N Station K1-1 (TM IINS Liquid Discharge) a)I...a)a-0)a)0 0 U*15: 1000000 100000-10000-1000-100-10-I--/- 1---Jan Feb Mar Apr May Jun Jul Month Aug Sep Oct Nov Dec FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2014 Indicator Samples -,,- Control Samples 900 -]" Significant Event 800 Chemobyl ------ April 1986 ..........700 -... ..... ..... -----E A-0 300 -----.. ..- ----. .---------42 a.\200 .. ....100 -_ !0 Year FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2014 Indicator-Control 0.4 TMI-1 Critical 0.35 TMI-2 Critical TMI-2 Accident TMI-2 RB Purge June 1974 March 1972 March 1978 June 1974 March 1979 September 1976 June 1980 September 1977 June 1973 September 1 November 1 March 1978 e k)0.3 (D 0.25 U C.,~30.0~0.2 4.8 0.15 Q.6 0.1 0.05 0 M ~ ~ ~ ~ ~ C 9 O0r-W 0 0ý If LO W r- W M~. CD ;N M VU' oI-M DZ M a f CO Wf 1- -. 1- r- -f, N- -CO CO CO CO w ~ w) w) w) M) (n M M M M 0 0 0 CD 0 CD 0 0CDC 0 0ý0)0 )0 )0 )0 )0 )0 ) )0 )0 )0 )0 )0 )0 0) 0) ) 0 D n 0 0 3 0 D 0 0 0 a 0 0' 0 0 0 0 0D Year-FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates-Three Mile Island Nuclear Station, 2007 -2014 0.100--Indicator

-- Control 0 .0 9 0 ........ .......................................0.080$ 0.070.2 0.060 , 16 0 .0 5 0 --.. ---.- -.-- ---.- -..-. -----.-.- --...-----.-. ----.- ----8 oo 0.020 0.010 --0.0001 0 0 ;a a il a i:4 0 ~ 0 ;z -4 0 Nz N N i / ay / Year Month IDay / Year Ihe high value on I 1/24/2U09 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 -2014-Indicator Samples-Control Samples in 9-8-Significant Events Maior Atm. Nuclear Weapon Tests_ TMI-2 Accident March 1979 December 1978 October 1980 TMI-2 RB Purge June 1980 Chemobyl April 1986 L..0.0 0 F,)7-6-5 4 3 2 A-~ --A AA*r\1+0 i11111 Iit i I 1111 t I t ll ti ii 1 k:1 I- GoN M4 CD'M U-) 001 0) iM t% 'a) 0 ) 0) C) D C.) C. CD 8- 8) 0) 0Z; ~ ~ U-! T -R R 11 NR R 8 N N N N N N N N N N Year I Intentionally left blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY Intentionally left blank The following section presents the results of data analysis performed by the QC laboratory, Environmental Inc. Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and the QC laboratory.

Comparison of the results for most media were within expected ranges. Q D-1 I Intentionally left blank D-2 TABLE D-I.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/31/13 -01/28/01/28/14 -02/25/02/25/14 -04/01/04/01/14 -04/29/04/29/14 -06/03/06/03/14 -07/01/07/01/14 -07/29/07/29/14 -09/02/09/02/14 -09/30/09/30/14 -10/28/10/28/14 -12/02/12/02/14 -12/30/Q9-1Q 14 14 14 14 14 14 14 14 14 14 14 14< 1.2 1.6 +/- 0.7< 1.3< 1.8< 0.8< 1.3< 0.9 1.8 +/- 0.9 2.2 +/- 0.8 1.3 +/- 0.6 3.5 +/- 1.1 1.5 +/- 0.7 2.0 +/- 1.6 MEAN TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD Q9-1Q 12/31/13 01/28/14 02/25/14 04/01/14 04/29/14 06/03/14 07/01/14 07/29/14 09/02/14 09/30/14 10/28/14 12/02/14 01/28/14 02/25/14 04/01/14 04/29/14 06/03/14 07/01/14 07/29/14 09/02/14 09/30/14 10/28/14 12/02/14 12/30/14 147 146 148 145 142 134 131 177 149 169 169 175 MEAN TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD Q9-10 1213113 01/28/14 02/25/14 04/01/14 04/29/14 06/03/14 07/01/14 07/29/14 09/02/14 09/30/14 10/28/14 12/02/14-0112814-02/25/14-04/01/14-04/29/14-06/03/14-07/01/14-07/29/14-09/02/14-09/30/14-10/28/14-12/02/14-12/30/14< 0.2< 0.3< 0.3< 0.3< 0.2< 0.4< 0.3< 0.2< 0.3< 0.3* 0.3< 0.2 MEAN THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-3 TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD Q9-1Q 12/31/13 -01/28/14 01/28/14 -02/25/14 02/25/14 -04/01/14 04101/14 -04/29/14 04/29/14 -06/03/14 06/03/14 -07/01/14 07/01/14 -07/29/14 07/29/14 -09/02/14 09/02/14 -09/30/14 09/30/14 -10/28/14 10/28/14 -12/02/14 12/02/14 -12/30/14 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140< 3<2<2<3<4<3<3<2<3<2<3<3<4<5<2<3<4<7<6<4<6<2<6<3< 3<2<3<3<3<3<4<2<5<2<3<3< 3<2<1<2<2<4<2<2<3<3<2<3<4<5<3<3<5<4<5<2<6<3<3<3< 3<4<3<5<4<7<5<5<6<5<5<4<4<2<3<3<5<4<2<3<4<3<4<2<2<2<3<2<4<3<2<2<3<2<4<2<2<3<2<3<3<4<4<2<3<2<4<3<8* 15< 16< 13<15<17< 27< 23< 14< 20< 12< 15<2<3<3<3<2<5<7<5<2<5<4<2 TABLE D-1I.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDP 09/24/14 < 10 < 7 3210 +/- 380 < 13 < 14 < 22 < 17 < 18 < 10 < 14 TABLE D-III.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD J2-1 10/31/14 A1-3 10/31/14 K-40 Cs-134 Cs-137 9443 +/- 631 < 18 < 26 9891 +/- 652 <21 < 24 MEAN 9667 +/- 634 D-6 TABLE D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD K-40 1-131 Cs-134 Cs-1 37 Sr-89 Sr-90 PERIOD H1-2Q 07/30/14 B10-2Q 07/23/14 4580 +/- 340 2720 +/- 320 3650 +/- 2630< 22 < 10< 12 < 11<9 <15<10 <3 8+/-5 2+/-1 MEAN D-7 TABLE D-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 01/09/14 01/09114 01/15/14 01/23/14 01/30/14 02/06/14 02/12/14 02/20/14 02127/14 03/06/14 03/12/14 03/20/14 03/27/14 04/03/14 04/10/14 04/17/14 04/23/14 05/01/14 05/07114 05/15/14 05/22/14 05/29/14 06/05/14 06/11/14 06/19/14 06/25/14 07/03/14 07/10/14 07/17/14 07/24/14 07131/14 08/07/14 08/14/14 08/21/14 08/28/14 09104/14 09/10/14 09/18/14 09/25/14 10/02/14 10/09/14 10/16/14 10/23/14 10/30/14 11/06/14 11/13/14 11/20/14 11126114 12/04/14 12/11/14 12/17/14 12/24/14 O1/U9/14 01/15/14 01/23/14 01/30/14 02/06/14 02/12/14 02120/14 02/27/14 03/06/14 03/12/14 03/20/14 03/27/14 04/03/14 04/10/14 04/17/14 04/23/14 05/01/14 05/07/14 05/15/14 05/22/14 05/29/14 06/05/14 06/11/14 06/19/14 06/25/14 07/03/14 07/10/14 07/17/14 07/24/14 07/31/14 08/07/14 08/14/14 08/21/14 08/28/14 09/04/14 09/10/14 09/18/14 09/25/14 10/02/14 10/09/14 10/16/14 10/23/14 10/30/14 11/06/14 11/13/14 11/20/14 11/26/14 12/04/14 12/11/14 12/17/14 12/24/14 01/01/15 El-2Q GROSS BETA 25 -+/--5 30 +/- 5 29 +/- 4 24 +/- 4 26 +/- 4 (1)27 +4 20 +5 37 +5 28 +5 20 +4 24 +5 17+/- 4 17 +/-4 21 +4 26 +/-5 14+/- 3 17 5 21 +/- 4 25 +/- 4 24 +/- 4 15 +/- 4 16 +/- 5 17 +/- 4 16 +/- 5 21 +/- 4 24 +/- 5 25 +/- 4 (1)19 +/- 5 24 +/- 5 21 +/- 5 25 +/- 5 26 +/- 4 25 +/- 4 23 +/- 5 21 +/- 4 30 +/- 5 31 +/- 5 23 +/- 4 24 +/- 4 11+/- 4 28 +/-4 20 +4 22 +/-4 24 +/-4 33 +/-6 22 +4 25 +/-4 27 +/-5 15+/- 4 21 +4 23 +/- 10 El -20 1-13 1< 1I* 13* 14* 19< 17 (1)< 17* 21* 25< 18< 25< 25* 15< 19* 16* 21< 10< 11* 20* 20* 24< 26< 17< 14< 19* 27* 23< 25 (1)* 21* 28< 25< 25< 33< 18< 18< 25< 33< 14< 23* 24< 14< 12< 19< 24< 30* 31* 19< 14< 18< 27< 18 E1-2Q 1-131 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION D-8 TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD Be-7 Cs-1 34 Cs-1 37 E1-2Q 01/02/14 -04/03/14 04/03/14 -07/03/14 07/03/14 -10/02/14 10/02/14 -01/01/15 MEAN 80 +/- 16 93 +/- 18 87 +/- 19 62 +/- 16 81 +/- 27< 0.9< 0.5* 1.3< 1.0< 0.7< 0.6< 1.1< 0.9 D-9 TABLE D-VI.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION, GAMMA EMITTERS, AND STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION DATE 1-131 K-40 Cs-1 34 Cs-1 37 Ba-140 La-140 Sr-89 Sr-90 G2-1Q 01/08/14 02/05114 03/05/14 03/19/14 04/02/14 04/16/14 04/30/14 05/14/14 05/28/14 06111/14 06125/14 07/09/14 07/23/14 08/06/14 08/20/14 09/03/14 09/17/14 10/01/14 10/15/14 10/29/14 11/12/14 11/25/14 12/10/14< 0.3< 0.3< 0.4< 0.5< 0.3< 0.3< 0.3< 0.5< 0.3< 0.4< 0.4< 0.2< 0.3< 0.2< 0.3< 0.4< 0.3< 0.4< 0.4< 0.3< 0.4< 0.2< 0.3 1403 976 863 1042 978 757 1032 1082 997 899 1023 1468 1013 763 1267 1314 1001 1230 1191 759 799 910 988+/- 103+/- 103+/- 94+/- 96+/- 95+/- 147+/- 96+/- 102+/- 115+/- 80+/- 88+/- 106+/- 88+/- 79+/- 107+/- 125+/- 143+/- 123+/- 76+/- 87+/- 64+/- 94+/- 91<3<6<5<4<4< 11<4<3<6<3<3<3<4<3<3<2<6<5<2<3<3<3<3<3<4<2<4<4<4<3<3<6<2<3<3<3<3<3<3<4<5<2<3<4<4<5< 22< 21< 19< 18< 21< 17< 19< 26< 17< 14* 20< 26< 34<41* 31< 16< 25< 23< 25< 22< 24< 27< 23<5<5<4<5<4<9<3<4<3<4<5<3<3<7<3<2<6<2<6<4<7<2<3< 0.5 0.5 +/- 0.3< 1.0 < 0.5< 0.7 < 0.6< 0.8 < 0.5 MEAN 1033 +/- 408 D-10 FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2014 6 i 0 c________.

________ l_QC-LAB S....................................................................................--a-PRIM A RY -LA B 4 4..3 2 1 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, 2014 60 50 I"J*(D40 E 30 C.)C.)LW20 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 TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)March 2014 E10854 E10855 E10857 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 95.1 91.7 pCi/L 10.9 15.1 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 96.6 112 449 186 250 248 292 230 312 321 53.0 232 100 122 122 135 111 140 187 74.1 98.5 119 491 210 253 268 297 219 323 337 53.9 223 95.3 115 121 135 99.3 147 153 76.4 AP Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 June 2014 E10856 E10858 E10913 E10914 E10916 E10915 E10917 pCi/L 2090 1760 pCi/L 85.9 91.3 pCi/L 13.8 14.5 pCi 1.04 0.72 0.98 0.94 0.91 0.89 0.99 0.93 0.98 1.05 0.97 0.95 0.98 1.04 1.05 1.06 1.01 1.00 1.12 0.95 1.22 0.97 1.19 0.94 0.95 0.95 0.90 1.01 0.91 1.03 0.94 0.99 1.04 1.00 0.97 1.03 1.13 1.00 1.06 1.05 0.99 0.95 1.02 1.07 1.00 0.93 A W A A A A A A A A A A A A A A A A A A W A A Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 86.5 111 255 147 123 105 155 106 251 218 95.1 215 122 95.1 88.7 115 72.6 193 179 90.9 124 253 162 120 112 156 102 252 224 92.6 190 122 89.8 84.1 116 76.7 189 168 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi 85.6 85.2 pCi/L 1680 1810 A E-1 TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)September2014 E10946 E10947 E10949 E10948 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 90.7 96.9 pCi/L 14.0 16.4 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 92.0 117 281 141 186 137 138 162 75.2 286 97.8 212 106 131 85.7 92.8 113 53.2 202 97.6 126 288 158 193 143 142 158 73.0 297 82.1 188 103 126 93.0 92.3 103 47.5 193 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi 83.9 89.8 pCi/L 2010 1720 0.94 0.85 0.94 0.93 0.98 0.89 0.96 0.96 0.97 1.03 1.03 0.96 1.19 1.13 1.03 1.04 0.92 1.01 1.10 1.12 1.05 0.93 1.17 1.12 0.94 0.93 1.09 0.93 1.16 1.02 1.08 1.02 0.90 0.83 0.90 0.94 0.99 0.95 0.98 0.94 0.98 1.05 0.97 0.95 E10950 E 10951 Soil December 2014 El1078 El1079 Milk Milk Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g 0.208 0.398 0.216 0.398 0.197 0.242 0.238 0.117 0.447 0.186 0.425 0.233 0.365 0.211 0.209 0.233 0.108 0.438 pCi/L 85.7 95.7 pCi/L 12.9 15.6 A A A A A A A A A A A A A A A A A A A A A A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 85.9 205 402 156 194 122 220 183 287 224 95.1 219 406 164 198 130 225 175 297 235 E-2 TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 3 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)December 2014 El1081 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 pCi pCi pCi pCi pCi pCi pCi pCi pCi 96.4 171 73.1 99.0 57.5 107 74.2 144 114 102 190 76.9 92.6 60.8 105 81.6 139 110 0.95 0.90 0.95 1.07 0.95 1.02 0.91 1.04 1.04 0.95 0.89 A A A A A A A A A A A El1080 E11082 pCi 93.5 98.2 pCi/L 1760 1970 (a) Teledyne Brown Engineering reported result.(b) 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.(c) Ratio of Teledyne Brown Engineering to Analytics results.(d) 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.E-3 TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 1)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)May 2014 RAD-97 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 MRAD-20 November 2014 RAD-99 Filter Gr-A pCi/L 38.25 pCi/L 24.65 pCi/L 89.1 pCi/L 45.55 pCi/L 91.15 pCi/L 65.10 pCi/L 244 pCi/L 45.65 pCi/L 27.95 pCi/L 23.75 pCi/L 9.61 pCi/L 8435 pCi/filter 28.0 pCiIL 30.4 pCi/L 18.6 pCi/L 46.8 pCi/L 88.0 pCi/L 99.0 pCi/L 92.5 pCi/L 325 pCi/L 29.9 pCi/L 27.5 pCi/L 15.8 pCi/L 5.74 pCi/L 6255 pCi/filter 27.3 36.7 26.5 87.9 44.3 89.1 64.2 235 61.0 33.0 25.7 10.2 8770 46.0 31.4 21.8 49.1 89.8 98.8 92.1 310 37.6 27.4 20.3 5.80 6880 27.5 -43.6 19.2 -30.9 74.0 -96.7 35.5 -48.7 80.2- 101 57.8 -73.1 212-275 31.9 -75.8 21.4-40.7 21.3-30.3 7.95-11.8 7610-9650 15.4-71.4 22.8 -38.1 15.6-25.7 40.3 -54.5 73.7- 98.8 88.9-111 82.9- 104 279 -362 19.4-48.1 17.3-35.3 16.8-24.4 4.34 -6.96 5940 -7570 A A A A A A A A A A A A Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A A A A A A A A A A A N (1)A A MRAD-21 36.9 12.4 -57.3 A (1) The Iodine-131 was evaluated as failed with a ratio of 0. 778. No cause could be found for the slighly low activity.

TBE would evaluate this as acceptablle with warning. A rerun was not possible due to 1-131 decay. All ERA /odine-131 evaluations since 2004 have been acceptable.

NCR 14-08 (a) Teledyne Brown Engineering reported result.(b) 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.(c) ERA evaluation:

A=acceptable.

Reported result falls within the Warning Limits. NA=not acceptable.

Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.E-4 TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 2)Identification Reported Known Acceptance MonthNear Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c)March 2014 14-MaW30 Water Am-241 Cs-134 Cs-137 Co-57 Co-60 H-3**Mn-54 Ni-63 Pu-238 Pu-239/240 K-40 Sr-90**U-234/233**

U-238**Zn-65 14-MaS30 14-RdF30 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 0.764 20.7 28.0 26.5 15.6 NR 13.5 NR 0.911 0.751 NR NR NR NR-0.201 2.02 1300 1069 1.32 1510 669 4.14 763 NR NR NR NR NR 0.8220 NR 0.720 23.1 28.9 27.5 16.0 321 13.9 34.0 0.828 0.676 8.51 0.225 1.45 1238 966 1.22 1430 622 695 0.504 -0.936 16.2-300 20.2 -37.6 19.3 -35.8 11.2-20.8 225 -417 9.7- 18.1 23.8 -44.2 0.580 -1.076 0.473 -0.879 (1)5.96- 11.06 0.158 -0.293 1.02-1.89 (1)(1)867 -1609 676- 1256 (2)1001 -1859 435 -809 (1)487 -904 A A A A A N (3)A N (3)N (3)N (3)N (3)N (3)A A A A A A A A A N (3)N (3)N (3)N (3)N (3)N (3)N (3)14-GrF30 14-RdV30 AP Cs-134**Cs-137**Co-57**Co-60**Mn-54**Sr-90 Zn-65**AP Gr-A Gr-B Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 1.91 1.34-2.48 1.76 1.23-2.29 (1)1.39 0.97 -1.81 (1)1.18 0.83-1.53 (1)1.77 0.53-3.01 0.77 0.39- 1.16 Bq/sample 0.606 Bq/sample 0.7507 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 5.96 5.06 11.8 7.34 8.95 1.23 8.91 6.04 4.74 10.1 6.93 8.62 1.46 7.86 4.23 -7.85 3.32-6.16 7.1 -13.1 4.85 -9.01 6.03- 11.21 1.02-1.90 5.50- 10.22 A A A A A A A A A E-5 TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 2)Identification Reported Known Acceptance Month/Year Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c)September 2014 14-MaW31 14-MaS31 Water Am-241 Cs-134***Cs-137***Co-57***Co-60***Mn-54***Ni-63 Pu-238 Pu-2391240 K-40***Zn-65***Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 0.705 NR NR NR NR NR 24.07 0.591 0.0153 NR NR NR NR NR NR NR NR 694 NR 0.88 0.62- 1.14 (1)18.4 12.9(- 23.9 24.7 17.3-32.1 12.4 8.7-16.1 14.0 9.8 -18.2 24.6 17.2-32.0 0.618 0.433 -0.803 0.0048 (2)161 113-209 10.9 7.6- 14.2 Soil Cs-i 34*~*Cs-i 37***Co-57***Co-60~**Mn-54***K-40***Sr-90 Zn-65***622 1116 779 1009 824 858 541 435-809 (1)781-1451 545-1013 706-1312 577-1071 601-1115 379-703 A N (4)N (4)N (4)N (4)N (4)A A A N (4)N (4)N (4)N (4)N (4)N (4)N (4)N (4)A N (4)N (4)N (4)A 14-RdF31 14-GrF31 September 2014 14-RdV31 AP Sr-90 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample 0.310 0.703 0.492 -0.914 Bq/sample 0.153 0.53 0.16-0.90 Bq/sample 0.977 1.06 0.53- 1.59 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 7.31 8.93 10.8 6.31 7.76 0.738 7.16 7.38 8.14 9.2 6.11 7.10 0.85 6.42 5.17-9.59 5.70 -10.58 6.4- 12.0 4.28 -7.94 4.97 -9.23 0.60-1.11 4.49 -8.35 A A A A A A A* The MAPEP cross check isotope list has been reduced due to duplication of effort or analysis not being performed for clients.These nuclides are no longer part of the TBE cross check program due to duplication of effort or analysis not being performed for clients. MAPEP evaluates non-reported analyses as failed if they were reported in the previous series.All future gamma cross check samples for these isotopes will be provided by Analytics.(I) False positive test.(2) Sensitivity evaluation.

(3) Water, Ni-63 overlooked when reporting, but the result of 32. 7 +- 1.69 would have passed the acceptance criteria.

NCR 14-04 Water, the non-detected K-40 was overlooked when reporting, but would have passed the false positive test. NCR 14-04 AP, Sr-S0 rerun was within the low range of the acceptqance criteria.

The original and rerun results were statistically the same. No cause could be identified for the slightly low Sr-90 activity.

NCR 14-04 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-04 (4) AP, Sr-90 gravimetric yield was very high at 117%. Could indicate larger than normal amounts of calcium in the AP. A second fuming HNO 3 separation would be required to remove the excess calcium. NCR 14-09 AP, Gr-Alpha was counted on the wrong side. When flipped over and recounted the results were acceptable.

NCR 14-09 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-09 (a) Teledyne Brown Engineering reported result.(b) 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.(c) DO__MAPEP evaluation:

A=acceptable, W=acceptable with warning, N=not acceptable.

E-6 TABLE E-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2014 (Page 1 of 1)Concentration (pCi/L)Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1384 ERW-1 384 ERW-1385 ERW-1385 ERW-1385 ERW-1385 ERW-1385 ERW-1388 ERW-1388 ERW-1391 ERW-1394 ERW-1397 ERW-5382 ERW-5382 ERW-5385 ERW-5385 ERW-5385 ERW-5385 ERW-5385 ERW-5388 ERW-5388 ERW-5392 ERW-5394 ERW-5397 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 04/07/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 10/06/14 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Uranium H-3 Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr. Alpha G. Beta 1-131 Uranium H-3 40.29 +/-24.08 +/-78.23 +/-62.75 +/-44.97 +/-88.54 +/-249.1 +/-56.70 +/-32.10 +/-25.52 +/-10.76 +/-8982 +/-29.40 +/-19.19 +/-43.54 +/-81.95 +/-95.76 +/-90.25 +/-327.4 +/-30.88 +/-20.47 +/-19.58 +/-5.51 +/-6876 +/-5.76 2.35 3.93 3.53 3.99 4.93 10.44 2.47 1.20 1.12 0.74 279 5.32 1.85 4.54 7.49 5.50 2.77 23.3 8.05 4.75 2.35 0.37 383 36.70 26.50 87.90 64.20 44.30 89.10 235.0 61.00 33.00 25.70 10.20 8770 31.40 21.80 49.10 89.80 98.80 92.10 310.00 37.60 27.40 20.30 5.80 6880 27.50 19.20 74.00 57.80 35.50 80.20 212.0 31.90 21.40 21.30 7.95 7610 22.80 15.60 40.30 73.70 88.90 82.90 279.0 19.40 17.30 16.80 4.34 5940-43.60-30.90-96.70-73.10-48.70-101.00-275.0-75.80-40.70-30.30-11.80-9650-38.10-25.70-54.50-98.80-111.00-104.00-362.0-46.10-35.30-24.40-6.96-7570 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.E-7 TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)ENVIRONMENTAL, INC., 2014 (Page 1 of 2)Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-1 140 MAW-1 140 MAW-i 184 MAW-1184 MAW-1184 MAW-i 184 MAW-i 184 MAW-i 184 MAW-1184 MAW-1184 MAW-i 184 MAW-1184 MAW-i 184 MAW-i 184 MAW-i 184 MAW-1184 MAW-1 184 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAAP-1 151 MAAP-1 151 MAAP-1 151 MAAP-1151 MAAP-1151 MAAP- 1151 MAAP-1151 MAAP-1 154 MAAP-1 154 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 02/01/14 Gr. Alpha 02/01/14 Gr. Beta 0.77 +/- 0.06 4.31 +/- 0.08 0.85 4.19 0.26 -1.44 2.10 -6.29 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01114 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 02/01/14 Fe-55 H-3 Ni-63 Pu-238 Pu-239/240 Sr-90 U-233/234 U-238 Co-57 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Sr-90 0.40 +/- 3.20 345.10 +/- 10.60 32.40 +/- 3.20 1.28 +/- 0.12 0.91 +/- 0.10 7.00 +/- 0.70 0.20 +/- 0.07 1.25 +/- 0.18 27.86 +/- 0.38 15.99 +/- 0.27 21.85 +/- 0.54 28.74 +/- 0.49 1.80 +/- 2.00 14.06 +/- 0.40 0.00 +/- 0.19 11.63 +/- 0.19 7.28 +/- 0.18 0.00 321.00 34.00 0.83 0.68 8.51 0.23 1.45 27.50 16.00 23.10 28.90 0.00 13.90 0.00 10.10 6.93 6.04 4.74 8.62 7.86-0.01 225.00 23.80 0.58 0.47 5.96 0.16 1.02 19.30 11.20 16.20 20.20 0.00 9.70-0.01-2.00-417.00-44.20-1.08-0.88-11.06-0.29-1.89-35.80-20.80-30.00-37.60-10.00-18.10-0.00-13.10-9.01-7.85-6.16-11.21-10.22 6.29 +/-5.18 +/-9.22 +/-8.59 +/-1.60 +/-1.38 +/-1.75 +/-1.81 +/-0.01 +/--0.24 +/-1.11 +/-0.29 0.20 0.26 0.40 0.05 0.08 0.11 0.10 0.03 0.09 0.14 7.10 4.85 4.23 3.32 6.03 5.50 Pass Pass Pass Pass Pass Fail (1)Fail (1)Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail (2)Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail (4)Pass Pass Pass Pass Pass 0.00 1.39 1.91 1.76 0.00 0.00 1.18 1.77 0.77 NA 0.97 -1.81 1.34 -2.48 1.23 -2.29 NA-0.50 -1.00 0.83 -1.53 0.53 -3.01 0.39 -1.16 Gr. Alpha Gr. Beta Ni-63 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Zn-65 Sr-90 0.56 +/- 0.06 0.98 +/- 0.06 4.80 1064.50 1.70 6.10 1364.30 728.90 1588.00 763.50 1.23+/- 15.30+/- 3.60+/- 0.50+/- 1.80+/- 5.30+/- 15.90+/- 6.00+/- 6.80+/- 1.37 0.00 966.00 1.22 0.00 1238.00 622.00 1430.00 695.00 0.00 NA 676.00 -1256.00 (3)NA 867.00 -1609.00 435.00 -809.00 1001.00 -1859.00 487.00 -904.00 NA E-8 TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)ENVIRONMENTAL, INC., 2014 (Page 2 of 2)Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 Ni-63 Sr-90 Cs-1 34 Co-57 Co-60 Mn-54 Zn-65 Am-241 Cs-1 37 Co-57 Co-60 H-3 Fe-55 Mn-54 Zn-65 771.62 +/- 23.29 778.34 +/- 17.82 520.60 +/- 7.09 1135.00 +/- 7.40 768.20 +/- 7.70 1050.70 +/- 12.60 407.89 +/- 15.03 0.79 +/- 0.08 18.62 +/- 0.54 24.85 +/- 0.42 12.27 +/- 0.38 207.20 +/- 10.60 55.10 +/- 14.80 14.36 +/- 0.53 11.46 +/- 0.78 980.00 858.00 622.00 1116.00 779.00 1009.00 541.00 0.88 18.40 24.70 12.40 208.00 31.50 14.00 10.90 686.00 601.00 435.00 781.00 545.00 706.00 379.00 0.62 12.90 17.30 8.70 146.00 22.10 9.80 7.60-1274.00-1115.00-809.00-1451.00-1013.00-1312.00-703.00-1.14-23.90-32.10-16.10-270.00-41.00-18.20-14.20 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail (5)Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass MAW-4493 08/01/14 Gr. Alpha MAW-4493 08/01/14 Gr. Beta MAAP-4433 MAAP-4444 MAAP-4444 MAVE-4436 MAVE-4436 MAVE-4436 MAVE-4436 MAVE-4436 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 08/01/14 Sr-90 Sr-89 Sr-90 Cs-1 34 Co-57 Co-60 Mn-54 Zn-65 0.93 +/- 0.07 6.31 +/- 1.35 0.74 +/- 0.10 7.82 +/- 0.52 0.76 +/- 0.10 7.49 +/- 0.18 11.20 +/- 0.19 6.84 +/- 0.17 8.11 +/- 0.26 7.76 +/- 0.43 1.40 6.50 0.70 9.40 0.76 7.38 9.20 6.11 7.11 6.42 0.42 -2.38 3.25 -9.75 0.49 -0.91 6.60 -12.20 0.53 -0.99 5.17 6.40 4.28 4.97 4.49-9.59-12.00-7.94-9.23-8.35 a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive".

MAPEP does not provide control limits.(1) The high bias on the plutonium crosscheck samples was traced to contamination from a newly purchased standard.The results of reanalysis with replacement tracer purchased from NIST: MAW-1184 Pu-238 0.68 +/- 0.10 Bq / L MAW-1 184 Pu-239/240 0.66 +/- 0.10 Bq / L (2) Interference from Eu-1 52 resulted in misidentification of Co-57.(3) Provided in the series for "sensitivity evaluation".

MAPEP does not provide control limits.(4) False positive test. Long sample counting time lead to interference from naturally occuring Bi-214 in sample matrix with a close spectral energy.(5) Result of reanalysis Fe-55 32.63 +/- 16.30 Bq/L E-9 Intentionally left blank 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 2014 Prepared By Teledyne Brown Engineering Environmental Services om-r ExelonGeneration, Three Mile Island Nuclear Station Middletown, PA 17057 April 2015 Intentionally left blank Table Of Contents I. Sum m ary and Conclusions

..............................................................................................

1 11. Introduction

.. 9 --** 3 II.Inroucio

....................

...... ***.............

.......3 A. O bjectives of the RGPP .................................................................................

3 B. Im plem entation of the Objectives

....................................................................

4 C. Program Description

.....................................................................................

4 D. Characteristics of Tritium (H-3) ......................................................................

5 Ill. Program Description

.................................................................................................

6 A. Sam ple Analysis .............................................................................................

6 B. Data Interpretation

..........................................................................................

7 IV. Results and Discussion

............................................................................................

8 A. Groundwater Results ......................................................................................

8 B. Surface W ater Results ...................................................................................

9 C. Storm W ater Results ....................................................................................

10 D. Precipitation W ater Results ...........................................................................

11 E. Leaks, Spills, and Releases ..........................................................................

11 F. Actions Taken ...............................................................................................

12 Appendices I Appendix A Tables Table A-1 Figures Figure A-1 Appendix B Tables Table B-1.1 Location Designation I Radiological Groundwater Protection Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Sampling Locations at the Three Mile Island Nuclear Station, 2014 Data Tables Table B-1.2 Table B-1.3 Table B-11.1 Table B-11.2 Table B-111.1 Table B-Ill.2 Table B-IV.1 Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.Concentrations of Gamma E'mitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2014.Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.ii Appendix C Data Tables Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-I1.1 Table C-11.2 Table C-I11.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.Concentrations of Hard-To-Detects in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2014.Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.Concentrations of Gamma Emitters in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.Concentrations of Tritium in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.iii I. Summary and Conclusions In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Three Mile Island Nuclear Station. At Three Mile Island Nuclear, 31 new permarent groundwater monitoring wells were installed in 2006. The results for all TMI wells are included in this report. This report covers groundwater, surface water, storm water and precipitation samples collected from the environment, both on and off station property in 2014. During that time period 694 analyses were performed on 258 samples from 68 locations.

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

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater, surface water, storm water and precipitation samples. In the case of tritium, Exelon specified that its laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

Strontium-89 and strontium-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 groundwater, surface water, storm water or precipitation water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 30 of 60 groundwater monitoring locations.

The groundwater tritium concentrations ranged from 184 +/- 115 pCi/L to 17,700 + 1,810 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of a potential leak, historical releases, the recapture of gaseous tritium releases via rainwater and/or background from external sources greater than 200 pCi/L. Tritium was detected in three of four precipitation water locations.

The concentration ranged from 246+/- 83 to 2,470 + 299 pCi/L. Tritium was not detected at any surface water location.

Tritium was detected in two storm water samples. The concentrations ranged from 289 +/- 118 to 312 +/- 114 pCi/L.Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2014. Gross Alpha (dissolved) was not detected at any of the groundwater locations.

Gross Alpha (suspended) was detected at four of 39 groundwater locations.

The concentrations ranged from 3.2 to 4.3 pCi/L. Gross Beta (dissolved) was detected at 38 of 39 groundwater locations.

The concentrations ranged from 1.2 to 13.7 pCi/L. Gross Beta (suspended) was detected at six of 39 groundwater locations.

The concentrations ranged from 1.9 and 8.2 pCi/L.Hard-To-Detect analyses were performed on a select group of groundwater locations.

The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

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

Conestoga Rovers & Associates (CRA) performed the initial assessment.

CRA prepared a Hydrogeologic Investigation Report (HIR) for Exelon to determine whether groundwater at and near TMINS has been adversely impacted by any releases of radionuclides.

The CRA report documents the results of the May 2006 Hydrogeologic Investigation Work Plan. CRA assessed groundwater quality at the Station and identified locations designated as Areas for Further Evaluation.

The results and conclusions of this Phase 1 study were made available to state and federal regulators, as well as the public on an Exelon web site for station specific reports.As a result of the Phase 1 study, the Radiological Groundwater Protection Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on well water, surface water, precipitation water and storm water samples collected in 2014. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides.This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2014.A. Objective of the RGPP The long-term objectives of the Radiological Groundwater Protection Program (RGPP) are as follows: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

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

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

5. Regularly assess analytical results to identify adverse trends.6. Take necessary corrective actions to protect groundwater resources.

B. Implementation of the Objectives The objectives identified have been implemented at Three Mile Island Nuclear Station as discussed below: 1. Three Mile Island Nuclear Station continues to sample and monitor the groundwater at the station in accordance with station procedures.

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

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

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

4. Three Mile Island Nuclear Station has implemented procedures to identify and report leaks, spills, or other detections with potential radiological significance in a timely manner.5. Three Mile Island Nuclear Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.C. Program Description

1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1 and A-2, Appendix A.Groundwater, Surface Water, Storm Water, and Precipitation Samples of water are collected, managed, transported and analyzed in accordance with approved procedures.

Groundwater, surface water, storm water and precipitation are collected.

Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures.

Contractor and/or station personnel are trained in the collection, preservation management and shipment of samples, as well as in documentation of sampling events. For split samples, collectors will periodically collect samples that are sent to Midwest Labs 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.Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2014.In order to achieve the stated objectives, the current program includes the following analyses: 1. Concentrations of gamma emitters in groundwater, surface water and storm water.2. Concentrations of strontium in groundwater.

3. Concentrations of tritium in groundwater, surface water, precipitation water and storm water.4. Concentrations of Am-241 in groundwater.

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

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

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

8. Concentrations of Fe-55 in groundwater.

9. Concentrations of Ni-63 in groundwater.

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

B. Data Interpretation

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

2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence.

The convention is to report results with a 95% level of confidence.

The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error).Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.Gamma spectroscopy results for each type of sample were grouped as follows: For groundwater, surface water, and storm water 13 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.The radio-analytical laboratory is counting 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 60 locations were analyzed for tritium activity.

Tritium values ranged from the detection limit to 17,700 pCi/L (Table B-I.1, Appendix B).Tritium Split Samples Tritium values ranged from 186 to 8,916 pCi/L (Table C-1.1, Appendix C).Strontium Strontium-89 and strontium-90 were not detected above their required detection limit of 10 and 1.0 pCi/L, respectively (Table B-1.1, Appendix B).Strontium Split Samples Strontium-89 and Strontium-90 were not detected above the required detection limit (Table C-1.1, Appendix C).Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2014. Gross Alpha (dissolved) was not detected at any of the 39 groundwater locations.

Gross Alpha (suspended) was detected at four of 39 groundwater locations.

The concentrations ranged from 3.2 to 4.3 pCi/L. Gross Beta (dissolved) was detected at 38 of 39 groundwater locations.

The concentrations ranged from 1.2 to 13.7 pCi/L. Gross Beta (suspended) was detected at six of 39 groundwater locations.

The concentrations were 1.9 and 8.2 pCi/L (Table B-1.1, Appendix B).

Gross Alpha and Gross Beta Split Samples Two split samples were analyzed for Gross Alpha and Gross Beta in 2014. Gross Alpha was not detected at either groundwater location.

Gross beta was detected in both samples analyzed.

The concentrations ranged from 2.7 to 3.5 pCi/L (Table C-1.1, Appendix C).Gamma Emitters Potassium-40 was detected in four of 78 samples with concentrations ranging from 53 pCi/L to 119 pCi/L. No other gamma-emitting nuclides were detected (Table B-1.2, Appendix B).Gamma Emitters Split Samples Five locations were analyzed for gamma-emitting nuclides in 2014.No gamma-emitting nuclides were detected in any split samples (Table C-1.2, Appendix C).Hard-To-Detect Hard-To-Detect analyses were performed on a select group of groundwater locations.

The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs (Table B-1.3, Appendix B).Hard-To-Detect Split Samples Hard to detects were not analyzed on any split samples in 2014 (Table C-1.3, Appendix C).B. Surface Water Results Samples were collected from surface water locations in accordance with the station radiological groundwater protection program.Analytical results and anomalies are discussed below.Tritium Three locations were analyzed for tritium in 2014. Tritium was not detected above the required detection limit of 200 pCi/L in any of the 13 samples analyzed (Table B-11.1, Appendix B).Tritium Split Samples One location was analyzed for tritium in 2014. Tritium was not detected above the required detection limit (Table C-I1.1, Appendix C).Strontium Surface water samples were not analyzed for Sr-90 in 2014 (Table B-II.1, Appendix B).Gamma Emitters Three locations were analyzed for gamma-emitting nuclides in 2014. None of the four samples detected gamma-emitting nuclides (Table B-1I.2, Appendix B).Gamma Emitters Split Samples One location was analyzed for gamma-emitting nuclides in 2014.No gamma emitting nuclides were detected (Table C-11.2, Appendix C).C. Storm Water Results Samples were collected from storm water locations in accordance with the station radiological groundwater protection program.Analytical results and anomalies are discussed below.Tritium One location was analyzed for tritium. Tritium was detected in two of samples above the required detection limit of 200 pCi/L. The concentration ranged from 289 to 312 pCi/L (Table B-Ill.1, Appendix B).Gamma Emitters Samples from one location were analyzed for gamma-emitting nuclides.

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

D. Precipitation Water Results Samples were collected at four locations.

The following analyses were performed:

Tritium Samples from five locations were analyzed for tritium activity.

Tritium activity was detected at three of four locations.

The concentrations ranged from 246 to 2,470 pCi/L (Table B-IV.1, Appendix B).Tritium Split Samples Samples from one location were analyzed for tritium activity.

Tritium activity was detected in three of four samples. The concentrations ranged from 246 to 2,350 pCi/L (Table C-111.1, Appendix C).Gamma Emitters Precipitation water was not analyzed for Gamma Emitters in 2014.Gamma Emitters Split Samples No gamma-emitting nuclides were analyzed in 2014.E. Leaks, Spills, and Releases A potential leak was identified at TMI in 2012 due to elevated MS-22 tritium concentration readings.

TMI continues to monitor MS-22 and surrounding wells, in addition to tritium plumes from previous years, and reports the activity and dose to the public in the ARERR. The elevated MS-22 well tritium concentrations were voluntarily reported under the reporting requirements for the NEI Groundwater Protection Initiative (GPI)as implemented in Exelon's Reportability procedure LS-AA-1 120, RAD 1.34 ( IR 1385497/1515261)

As reported previously a number of potential sources were mitigated in 2013. The Borated Water Storage Tank (BWST) tunnel sump was cleaned and repaired.

An active input to the BWST tunnel sump (packing leak-off of a BWST isolation valve) was corrected.

A tank leak on CST B and a leaking buried pipe flange were repaired, and BS-T-1 & 2 and ancillary piping were drained and emptied.In June 2014 an inspection of the BWST external connections revealed that a 24 inch flange was found coated in boron deposits indicating leakage. The flange was cleaned and the boron deposits removed. The repair of the flange is scheduled during TMI's refueling outage in the Fall of 2015. In December 2014, a follow-up inspection showed additional boron deposits.

In January 2015, an enclosure with a catch containment was installed to help in preventing the small amounts of leakage from migrating to the environment.

F. Actions Taken 1. Compensatory Actions In 2013, TMI installed eight new wells to help isolate and investigate the area of the leak. TMI has an extensive groundwater monitoring program with over 50 monitoring wells. No monitoring wells outside the investigation area have seen elevated tritium concentrations.

TMI continues to monitor the BWST area wells closely. The leakage has been mitigated by preventing rain/snow from entering the area of concern and by placement of a catch containment for any moisture that might accumulate.

The containment is inspected regularly, and the permanent flange repair is scheduled during TMI's next refueling outage in Fall 2015.

Intentionally left blank APPENDIX A LOCATION DESIGNATION

& DISTANCE Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program -Sampling Locations and Distance, Three Mile Island Nuclear Station, 2014 Site Site Type#3 48N 48S E1-2 EDCB GP-12 GP-6 GP-8 GP-9 MS-1 MS-19 MS-2 MS-20 MS-21 MS-22 MS-3 MS-4 MS-5 MS-6 MS-7 MS-8 MW-1 MW-2 MW-3 MW-4 N2-1 NW-A NW-B NW-C NW-CW OS-13B OS-14 OS-16 OS-17 OS-18 OSF RW-1 RW-2 SW-E-1 SW-E-2 SW-E-3 MW-TMI-9S*

MW-TMI-1 0D MW-TMI-101 MW-TMI-10S MW-TM- 11 S*MW-TMI-12S MW-TMI-131 MW-TMI-13S MW-TMI-14D MW-TMI-141 MW-TMI-14S MW-TMI-16D MW-TMI-161 MW-TMI-17D MW-TMI-171 MW-TMI-18D MW-TMI-19D MW-TM -191 MW-TMI-1D MW-TMI-20D**

Monitoring Well Monitoring Well Production Potable Well Monitoring Well, Offsite Storm Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well, Offsite Production Well Production Well Production Well Clearwell Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Production Potable Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well A-I TABLE A-I: Radiological Groundwater Protection Program -Sampling Locations and Distance, Three Mile Island Nuclear Station, 2014 Site Site Type MW-TMI-201**

MW-TMI-21 D**MW-TMI-21 I**MW-TMI-21S**

MW-TMI-22D**

MW-TMI-221**

MW-TMI-22S**

MW-TMI-2D MW-TMI-31 MW-TMI-41 MW-TMI-4S MW-TMI-5D MW-TMI-6D MW-TMI-61 MW-TMI-7S MW-TMI-8S MW-TMI-91 MW-TMI-9S TRAINING CENTER TM-PR-ESE TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-20 TM-PR-MS-22 TM-PR-MS-4 TM-PR-NW-B Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Offsite Monitoring Well Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water* NO WATER PRESENT TO SAMPLE** NEW WELLS INSTALLED 2014 A-2 Figure A -1 Sampling Locations at the Three Mile Island Nuclear Station, 2014 A-3 I Intentionally left blank APPENDIX B DATA TABLES Intentionally left blank TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014£1 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus)COLLECTION DATE SITE Gr-B (Dis) Gr-B3 (Sus)3 3 3 3 48S 48S 48S 48S 48S 48S MS-i MS-1 MS-1 MS-1 MS-19 MS-19 MS-19 MS-19 MS-2 MS-2 MS-2 MS-2 MS-2 MS-2 MS-2 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-21 MS-21 MS-21 MS-21 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-3 MS-3 MS-3 MS-3 MS-3 MS-4 U1/ZU/14 04/23/14 07/10/14 10/28/14 10/28/14 01/20/14 04/24/14 Original 04/24/14 Recount 07/10/14 07/10/14 10/28/14 01/21/14 04/22/14 07/09/14 10/28/14 01/21/14 04/22/14 07/09/14 10/28/14 01/21/14 04/23/14 Original 04/23/14 Recount 04/23/14 Original 04/23/14 Recount 07/10/14 10/29/14 01/20/14 01/20/14 04/21/14 07/09/14 10/27/14.

Original 10/27/14 Recount 10/27/14 Reanaly, 12/16/14 01/20/14 04/23/14 07/09/14 10/27/14 01/20/14 02/10/14 03/07/14 04/23/14 04/23/14 05/19/14 06/17/14 Original 06/17/14 Recount 06/17/14 Reanalys 07/09/14 10/27/14 Original 10/27/14 Recount 10/27/14 Reanalys 12/16/14 01/21/14 04/23/14 Original 04/23/14 Recount 07/10/14 10/29/14 04/23/14< 16V< 167 200 +/- 114 195 +/- 114 196 +/- 114< 181 192 +/- 116 196 +/- 122* 184< 184< 166< 184< 159< 183< 173< 181< 169< 183< 174 312 +/- 116 718 +/- 141 808 +/- 163 798 +/- 153 659 +/- 150 513 +/- 129 522 +/- 125 491 +/- 141 418 +/- 138 630 +/- 133 630 +/- 137 2650 +/- 319 2670 +/- 312 sis 2500 +/- 296 298 +/- 120< 163 240 +/- 115< 165< 168 2460 +/- 292 1930 +/- 244 1990 +/- 249 4790 +/- 524< 4.8< 4.4< 5.2* 5.8< 6.9< 4.9< 4.1< 0.7 < 1.3< 0.6 < 5.1< 0.7 < 0.9< 0.8 < 0.8< 0.5 < 0.9< 0.7 < 1.2< 0.8 < 0.4< 4.7 < 0.6 < 0.5< 0.9< 0.7< 0.6 3.9 +/- 1.5 3.4 +/- 0.9 6.2 +/- 1.5 1.6 +/- 0.8 < 1.6 3.9 +/- 1.1 < 1.4 6.7 +/- 1.6 < 1.3< 0.9< 0.7< 0.6< 0.9< 0.7< 0.6< 0.9 4.0 + 1.1 < 1.6 5.2 +/- 1.1 < 1.4 6.4 +/- 1.2 < 1.3 1.7 + 0.7 < 1.6 7.7 + 1.1 < 1.4 9.2 +/- 1.9 < 2.8 5.5 +/- 1.1 < 1.6 S< 6.9 < 0.6 < 0.8< 4.9 < 0.5 < 2.7 S S 3180 5380 5040 sis 5140 9850 12900 14300 sis 13400 2700< 184 437 360 376 251 251+/- 364+/- 578+/- 553+/- 558+/- 1030+/- 1330+/- 1470+/- 1380+/- 320+/-+/-:1+/-1+129 < 8.5 140 124 118 117< 0.6 < 0.8 B-1 TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus)COLLECTION DATE SITE MS-5 MS-5 MS-5 MS-5 MS-5 MS-5 MS-7 MS-7 MS-7 MS-7 MS-7 MS-8 MS-8 MS-8 MS-8 MS-8 MS-8 MW-1 MW-2 MW-TMI -10D MW-TMI-10D MW-TMI-10D MW-TMI-10D MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-1 01 MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TM I-10S MW-TMI-12S MW-TMI-12S MW-TMI-1 2S MW-TMI-12S MW-TMI-131 MW-TMI-131 MW-TMI-1 31 MW-TMI-131 MW-TMI-131 MW-TMI-13S MW-TMI-13S MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-14S MW-TMI-14S MW-TMI-16D MW-TMI-16D MW-TMI-160 MW-TMI-161 MW-TMI-161 Gr-B (Dis) Gr-B (Sus)01/21/14 04/23/14 07/10/14 07/10/14 07/10/14 10/29/14 01/21/14 04/22/14 07109114 07109/14 10/29/14 01/21/14 01/21/14 04/23/14 07/10/14 10/29/14 10/29/14 04/24/14 04/24/14 01120114 04/22/14 04/22/14 10128/14 01/20/14 04/22/14 07/09/14 10/28/14 01120/14 01/20/14 04/22/14 07/09/14 07/09/14 10/28/14 01/21/14 04/23/14 07/10/14 10/28/14 01/20/14 04/22/14 07/09/14 10/28/14 10/28/14 01/20/14 04/22/14 01/22114 04/22/14 07/09/14 10/28/14 01/21/14 01/21/14 04/22/14 01/21/14 04/22/14 01/21114 04/22114 10/29/14 01/21/14 04/22/14< 183* 167 Original 336 +/- 133 Recount 190 +/- 107 Reanalysis 244 +/- 111< 167< 190< 160< 184< 192< 175< 183< 190 276 +/- 120 281 +/- 117< 171< 172< 191< 191 197 +/- 111 218 +/- 113 226 +/- 114< 171 903 +/- 146 741 +/- 138 733 +/- 155 705 +/- 138 741 +/- 140 643 +/- 148 741 +/- 142 1710 +/- 225 1630 +/- 216 1570 +/- 214< 189< 170< 161< 169 348 +/- 135 382 +/- 121 212 +/- 123* 170< 171 223 +/- 128< 150 293 +/- 128 226 +/- 111 274 +/- 131 184 +/- 115* 180* 190 207 +/- 113* 179* 161 905 +/- 165 620 +/- 121 634 +/- 136* 180 Original 224 +/- 108< 3.3 < 0.7 < 0.6< 3.1 < 0.6 <0.9< 0.9 5.0 +/- 1.1 < 1.6 4.0 +/- 1.7 3.4 +/- 1.4 5.2 +/- 1.9< 3.8* 4.8* 4.1< 0.5 <0.7< 0.6 <1.2< 0.7 <0.7< 0.9< 0.6* 0.9* 0.9< 0.6< 0.6 4.3+/- 0.9 < 1.6 5.2 +/-1.1 < 1.3 4.5 +/-1.1 < 1.6 9.4 +/-1.4 < 1.6 3.4 +/-0.8 < 1.3 1.2 +/-0.7 1.9 +/- 1.0< 3.5 < 0.5 <0.9< 5.5< 5.4< 0.7 <0.8< 0.8 <0.7 B-2 TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus)COLLECTION DATE SITE Gr-B (Dis) Gr-B (Sus)MW-TMI-161 MW-TMI-171 MW-TMI-18D MW-TMI-18D MW-TMI-191 MW-TMI-1 D MW-TMI-20D MW-TMI-20D MW-TMI-201 MW-TMI-201 MW-TMI-21D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 I MW-TMI-21 I MW-TMI-211 MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21 S MW-TMI-21 S MW-TMI-21 S MW-TMI-21 S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-221 MW-TMI-221 MW-TMI-221 04/22/14 Recount 04/24/14 04/24/14 04/24/14 04/22/14 04/24/14 01/20/14 04/22/14 01/20/14 04/22/14 01/20/14 02/10/14 03/07/14 04/21/14 05/19/14 06/17/14 07/09/14 10/27/14 12/16/14 01/20/14 Original 01/20/14 Recount 02/10/14 03/07/14 04/21/14 Original 04/21/14 Recount 04/21/14 Reanalys 05/19/14 06/17/14 07/09/14 07/09/14 10/27/14 Original 10/27/14 Recount 10/27/14 Reanalys 12/16/14 01/20/14 Original 01/20/14 Recount 02/10/14 03/07/14 04/21/14 05/19/14 06/17/14 07/09/14 10/27/14 Original 10/27/14 Recount 10/27/14 Reanalys 12/16114 01/20/14 02/10/14 03/11/14 04/21/14 05/19/14 06/17/14 07/09/14 10/27/14 12/16/14 01/20/14 02/10/14 03/11/14 S 211 +/- 124< 179 273 +/- 128 331 +/- 133< 167 190 +/- 114 287 +/- 118 303 +/- 119 407 +/- 124 611 +/- 124 3120 +/- 359 2760 +/- 323 2810 +/- 331 3450 +/- 395 4010 +/- 447 3740 +/- 412 3660 +/- 403 3960 +/- 440 3480 +/- 397 3480 +/- 396 3930 +/- 439 2980 +/- 344 2090 +/- 259 5250 +/- 574 5130 +/- 563 is 4630 +/- 510 5660 +/- 607 3250 +/- 368 3510 +/- 389 3130 +/- 350 10400 +/- 1080 11300 +/- 1170'is 10500 +/- 1090 5720 +/- 618 454 +/- 130 546 +/- 147 359 +/- 115 502 +/- 136 594 +/- 155 326 +/- 134 489 +/- 147 502 +/- 132 4020 +/- 444 4900 +/- 534'is 4650 +/- 511 923 +/- 154 4690 +/- 515 4470 +/- 492 4430 +/- 490 5280 +/- 576 6630 +/- 705 5410 +/- 581 5680 +/- 602 4100 +/- 453 4130 +/- 461 7890 +/- 834 7490 +/- 789 8430 +/- 887< 5.3< 6.0< 5.1< 3.8< 3.8< 4.0< 0.6 < 2.3< 0.7 < 7.6< 0.5 < 0.9< 0.5 < 2.5< 0.5 < 2.6< 0.4 < 2.4< 0.6< 1.2< 0.6< 1.1< 1.1< 1.1 5.9 +/- 1.3 < 1.3 34.0 +/- 3.4 < 2.3 1.5 +/- 0.9 < 2.8 4.1 +/- 1.4 < 2.5 7.3 +/- 1.6 <2.5 2.3 +/- 1.3 < 2.5 S$B-3 TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-2D MW-TMI-2D MW-TMI-2D MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-41 MW-TMI-41 MW-TMI-4S MW-TMI-6D MW-TMI-6D MW-TMI-61 MW-TMI-61 MW-TMI-7S MW-TMI-8S MW-TMI-8S MW-TMI-91 MW-TMI-91 MW-TMI-9S N2-1 NW-A NW-A NW-A NW-A NW-B NW-B NW-B NW-B NW-C NW-C NW-C NW-C NW-CW NW-CW NW-CW NW-CW COLLECTION DATE 04/21/14 05/19/14 06/17/14 07/09/14 10/27/14 12/16/14 01/20/14 02/10/14 Original 02/10/14 Recount 03/11/14 Original 03/11/14 Reanalys 04/21/14 04/21/14 05/19/14 06/17/14 Original 06/17/14 Recount 06/17/14 Reanalys 07/09/14 10/27/14 12/16/14 01/22/14 04/24/14 04/24/14 Original 01/22/14 Recount 04/24/14 07/10/14 10/29/14 10/29/14 04/22/14 04/22/14 04/22/14 01/21/14 04/22/14 01/21/14 04/22/14 04/24/14 04/24/14 Original 04/24/14 Recount 04/24/14 Original 04/24/14 Recount 04/24/14 04/25/14 02/20/14 04/25/14 07/08/14 10/28/14 02/20/14 04/25/14 07/08/14 10/28/14 02/20/14 04/25/14 07/08/14 10/28/14 01/24/14 04/24/14 Original 04/24/14 Recount 07/08/14 H-3 9230 +/-9430 +/-8400 +/-8590 +/-7540 +/-8890 +/-3210 +/-5100 +/-5860 +/-7740 +/-is 7030 +/-8660 +/-8380 +/-7440 +/-17200 +/-17200 +/-is 17700 +/-12900 +/-12300 +/-3780 +/-< 161 412 +/-319 +/-309 +/-290 +/-272 +/-193 +/-241 +/-< 165< 180< 158* 189< 165< 187< 165< 186 281 +/-224 +/-248 +/-241 +/-< 186< 175 588 +/-723 +/-663 +/-850 +/-261 +/-337 +/-< 185 185 +/-897 +/-1020 +/-1260 +/-820 +/-403 +/-579 +/-474 +/-494 +/-Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus)Gr-B (Dis) Gr-B (Sus)968 985 878 893 794 932 369 553 631 819 755 904 883 787 1760 1760 1810 1320 1270 427 137 134 132 126 127 113 117< 5.4< 8.2< 3.6< 5.0< 6.2< 0.5 < 1.6< 0.9 < 0.6< 0.4 < 2.4< 0.7 < 0.4< 0.9 < 1.8< 1.1< 0.7< 1.1< 0.8 4.4 +/- 1.1 < 2.5 7.2 +/- 0.9 < 1.4 8.2 +/- 1.5 <2.5 13.7 +/- 1.0 2.2 +/- 1.1 4.3 +/- 1.4 6.0 +/- 1.3 8.2 +/- 1.6< 5.0 < 0.6 < 1.0< 3.6 < 0.7 < 0.5< 0.6 1 3.2 +/- 1.6 < 1.6.9 +/- 0.9 < 1.3 4.4 +/- 1.8 131 129 130 133 133 145 152 149 121 136 109 154 166 183 146 132 139 140 143< 6.5< 5.9< 4.6< 2.8< 0.7 < 0.8< 0.5 < 0.7< 0.5 < 0.7< 0.5 < 0.7< 0.7* 0.7< 0.7< 0.7 2.2 +/- 0.9 < 1.4 2.6 +/- 0.9 < 1.4 1.5 +/- 0.8 < 1.4 2.5 +/- 0.9 < 1.4 B-4 TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus)COLLECTION SITE DATE Gr-B (Dis) Gr-B (Sus)NW-CW 10/28/14 OS-14 01/21/14 OS-14 04/23/14 OS-14 07/10/14 OS-14 10/29/14 OS-16 01/21/14 OS-16 04/23/14 OS-16 07/10/14 OS-16 10/29/14 OS-18 01/21/14 OS-18 04122/14 Original OS-18 04/22/14 Recount OSF 01/20/14 OSF 04/24/14 OSF 07/10/14 OSF 10/28/14 RW-1 01/20/14 RW-1 04/24/14 RW-1 07/10/14 RW-1 10/28/14 RW-2 01/21/14 RW-2 01/21/14 RW-2 04/23/14 TRAINING CENTEF 04/23/14 447 +/- 128< 180< 170< 167< 170< 8.3 < 0.5 < 1.0 443 651 445 463< 186 347 327 494 258 294 220< 163< 181< 163< 170< 186< 162< 168< 168+/- 125+/- 139+/- 125+/- 124+/- 113+/- 129+/- 141+/- 108+/- 131+/- 116< 4.5< 6.2< 6.6< 0.7 < 0.6< 0.7 < 1.4< 0.5 < 1.8< 0.9< 0.9* 0.6< 0.7* 0.7< 0.9 9.3 +/- 1.3 < 1.6 5.9 +/- 0.9 < 1.6 6.6 +/- 1.2 < 1.3 6.1 +/- 1.3 < 1.4 8.5 +/- 1.3 < 1.4 11.5 +/- 1.4 < 1.6< 3.4 < 0.6 < 1.1< 4.4 < 0.6 < 0.8 B-5 TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION 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 3 48S MS-1 MS-19 MS-2 MS-2 MS-20 MS-21 MS-22 MS-22 MS-3 MS-3 MS-3 MS-3 MS-4 MS-5 MS-5 MS-5 MS-5 MS-7 MS-8 MS-8 MS-8 MS-8 MS-8 MS-8 MW-i MW-2 MW-TMI-10D MW-TMI-101 MW-TMI-10S MW-TMI-12S MW-TMI-1 3S MW-TMI-14S MW-TMI-16D MW-TMI-171 MW-TMI-1 8D MW-TMI -18D MW-TMI-191 MW-TMI-1D MW-TMI-20D MW-TMI-201 DATE 04/23/14 04/24/14 04/22/14 04/22/14 04/23/14 04/23/14 04121/14 04/23/14 04/23/14 05/19/14 01/21/14 04/23/14 07/10/14 10/29/14 04/23/14 01/21/14 04/23/14 07/10/14 10/29/14 04/22/14 01/21/14 01/21/14 04/23114 07110114 10/29/14 10/29/14 04/24/14 04/24/14 10/28/14 04/22/14 04/22/14 04/23/14 04/22/14 04/22/14 10/29/14 04/24/14 04/24/14 04/24/14 04/22/14 04/24/14 04/22114 04/22/14< 41< 37< 44< 35< 42< 35< 32< 32< 39< 20< 32< 39< 45< 58<41< 46< 45< 39< 50< 41< 35< 37< 42< 37< 56< 56< 41< 40< 43< 39< 43< 43< 43< 43< 70< 44< 38< 44< 32< 40< 40<41< 72< 72< 43< 74 107< 32< 34< 65< 83< 33< 27< 36< 47< 135< 44< 86< 80< 69< 112< 83< 71< 32 119< 82< 102< 97< 85< 34< 55< 80< 42< 35< 45< 46< 70< 93< 37< 39< 24< 93< 77< 74<4<3<5<4+/- 49 < 5<3<3<4<4<2<4<4<4<6<4<4<5<4<5<4<4<4+/- 51 <4<4<8<6<4<4<5<4<4<5<5<4<8<4<4<4<4<4<4<4<4<4<5<3<5<4<4<4<4<2<4<4<5<7<4<5<4<5<6<5<4<4<5<4<5<5<5<4<5<4<4<5<5<5<7<5<5<3<4<4<5<5< 10<8< 10<5< 11<8<7<8<9<5<8<8< 10< 11<9< 11<9<8< 13<9<8<9<9<9< 17< 14< 10<8< 10< 10< 12< 10< 10< 10< 15< 13<B<8<5< 10<9<9<5<4<5<4<4<3<3<4<4<2<3<4<4<6<4<5<5<4<5<5<3<4<4<4<9<6<4<3<3<4<5<4<5<5<5<4<3<3<6<5<5<8<8<8<6<9<6<6<7<8<4<6<8<9< 15<8<9<7<8< 11<9<8<7< 10<8< 15< 15<8<6< 10<8<9<8< 10<7< 17< 10<8<8<8<9<9<7<-5<4<5<4<5<4<4<5<5<2<4<5<5<7<4<5<5<5<6<5<4<4<5<4<8<7<5<4<5<5<4<5<5<4<7<5<4<4<4<5<4<5<9<6<9<6<9<6<6<8<8<4<6<7<8< 16<8< 10<9<9< 10<8<7<8<8<8< 11< 12<7<7<8<8<9<9<8<9< 12< 11<8<7<6<8<8<8<4<4<5<4<5<3<3<4<4<2<3<4<4<6<4<4<4<4<6<4<4<4<5<4<5<6<4<4<5<4<4<5<4<4<8<4<4<4<3<4<4<4< 5<3<5<3<5<4<4<4<4<2<4<5<5<8<4<5<4<5<6<4< 3<4<5<4<8<7<5<4<4<4<4<5<5<4<8<5<4<4<4<4<4<4< 3i< 24< 32< 27< 27< 29< 26< 24< 32< 21< 27< 30< 27< 31< 27< 34< 30< 25< 27< 29< 27< 26< 31< 22< 29< 31< 31< 26< 27< 29< 30< 30< 32< 33< 41< 31< 28< 25< 22< 28< 28< 29< lU<8< 10<5< 12<8<7<8<8<8<6<7<8< 10<9< 12< 12<9<9<9<8< 10<9<7< 14< 11<9<6<7< 10<9<9< 11<9< 10< 11<9< 10<5<8< 11< 10 TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION 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 ,4 MW-TMI-21 D MW-TMI-21 I MW-TMI-21 S MW-TMI-22D MW-TMI-221 MW-TMI-22S MW-TMI-22S MW-TMI-2D MW-TMI-31 MW-TMI-41 MW-TMI-41 MW-TMI-4S MW-TMI-6D MW-TMI-61 MW-TMI-7S MW-TMI-8S MW-TMI-91 MW-TMI-9S N2-1 NW-A NW-B NW-C NW-CW OS-14 OS-14 OS-14 OS-14 OS-16 OS-16 OS-16 OS-16 OS-18 OSF RW-1 RW-2 DATE 05/19/14 05/19/14 05/19/14 05/19/14 05/19/14 04/21/14 05/19/14 04/24/14 04/24/14 04/22/14 04/22/14 04/22/14 04/22/14 04/22/14 04/24/14 04/24/14 04/24/14 04/24/14 04/25/14 04/25/14 04/25/14 04/25/14 04/24/14 01/21/14 04/23/14 07/10/14 10/29/14 01/21/14 04/23/14 07/10/14 10/29/14 04/22/14 04/24/14 04/24/14 04/23/14< 23< 18< 21* 21< 21< 30<18< 44< 41< 44< 39< 45< 42< 40< 49< 39< 42< 45< 16< 42< 43< 49< 45< 35< 41< 34< 80< 39< 37< 48< 58< 45< 44< 39< 43< 44<17 <2<14 <2<22 <2<45 <2<17 <2< 39 <4<32 <2< 112 < 4< 89 <4 96 55 < 5<63 <4< 35 <4< 36 <4<25 <5<36 <4<48 <4<86 <4<91 <4<32 < 2<92 <5< 76 <4<49 < 5<50 <5<60 < 3<41 <4<51 <3< 165 < 7<42 <4<46 <4<56 < 5<65 <6<110 <4<46 <4 53 + 35 < 4< 34 <4< 86 <4<2<2<2<2<2<3<2<5<4<5<4<4<4<4<4<5<6<5<2<5<5<5<5<4<5<3<8<4<5<6<7<5<4<4<5<5<5<4<6<5<5<8<5<7<8< 10<9<9< 10<8< 11< 10<9< 10<4< 10< 11< 10< 12<7< 10<5< 18<9<9< 13< 15<9<11<9<7< 11<2<2<2<2<2<4<2<4<4<5<3<4<5<4<5<5<4<5<2<4<4<4<5<4<5<3<9<4<4<6<6<4<4<4<4<5<4<4<5<4<4<7<4<9<8<10<7<9<8<9<7<9< 11< 10<3< 10<11<9< 10<7<9<5< 15<9<8< 10< 10<8<9<8<7<9<2<2<3<2<2<4<2<5<4<6<4<4<5<5<4<5<5<5<2<5<5<5<5<4<5<4<8<5<4<6<7<5<5<4<4<6<4<4<4<4<4<6<4<9<8<9<7<8<7<8<9<7<7<9<3<9<8<8<9<6< 10<5< 15<8<8< 10< 13<7<9<8<7<9<2<2<2<2<2<3<2<4<4<5<3<4<4<4<5<4<4<4<1<5<4<4<5<3<4<3<6<4<4<5<6<4<4<4<4<5<2<2<2<2<2<3<2<5<4<5<4<4<4<6<5<4<5<4<2<5<4<5<5<4<5<3<8<4<4<5<6<5<5<4<4<5< 22< 19< 21< 22< 22< 26<19* 30< 29< 32< 31< 30< 32* 30< 35< 27< 28< 32< 13< 33< 28< 36< 32< 27< 33< 19< 41< 31< 28< 32< 29< 32< 29< 26< 28< 31 TRAINING CENTER 04/23/14 TABLE B-I.3 SITE COLLECTION DATE MW-TMI-101 04/22114 MW-TMI-10S 04/22/14 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238< 0.04 < 0.04 < 0.05 < 0.03 < 0.02 < 0.04 < 0.02 < 0.04< 0.10 < 0.02 < 0.03 < 0.02 < 0.03 < 0.08 < 0.14 < 0.18 Fe-55< 140< 94 Ni-63* 4.8* 4.8 80 TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE SW-E-1 SW-E-1 SW-E-1 SW-E-1 SW-E-2 SW-E-2 SW-E-2 SW-E-2 SW-E-3 SW-E-3 SW-E-3 SW-E-3 SW-E-3 COLLECTION DATE 01/20/14 04/24/14 07/10/14 10/28/14 01/22/14 04/23/14 07/10/14 10/28/14 01/22/14 04/23/14 04/23/14 07/10/14 10/28/14 U H-3< 181< 179< 176< 170< 181< 165< 181< 172< 182< 156< 170< 182< 170 B-9 TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 SW-E-1 SW-E-2 SW-E-3 SW-E-3 04/24114 04/23/14 04/23/14 04/23/14< 41 < 46< 36 < 32< 51 < 95.< 40 < 102<4 <5 <12 <4<3 <3 <8 <4<5 <6 <12 <4<4 <4 <10 <4<9 <5<8 <4<10 <6<7 <4<7<7<8<7<3 <4<4 <3<5 <5<4 <4<28 <8<27 <7<38 <10<31 <7 L586 L586 L586 L586 0 TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION SITE DATE H-3 EUDB EDCB EDCB EDCB 02/04/14 04/29/14 07/29/14 10/28/14 289 +/- 118* 176< 157 312 +/- 114 B-Il TABLE B-I11.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION Be-7 DATE EDCB 02/04/14 < 19 EDCB 04/29/14 < 48 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140< 45< 108<2 <2<6 <5<4 <2 <4< 10 < 6 < 12<2 <4 <2 <2 <14 <5<6 <10 <5 <5 <29 <9 EDCB 07/29/14 EDCB 10/28/14<41 <40<43 <69<5 <5 <8 <4 <8 <5 <9 <4 <5 <26 <6<4 <5 <9 <6 <9 <5 <7 <4 <5 <23 <8 ,=J TABLE B-IV.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION SITE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 U DATE 03/10/14 03/10/14 03/10/14 05/10/14 08108/14 10/08/14 10/08/14 10/08/14 03/10/14 05/10/14 08/08/14 10/08/14 03/10/14 03/10/14 03/10/14 05/10/14 08/08/14 10/08/14 10/08/14 10/08/14 03/10/14 03/10/14 03/10/14 05/10/14 08/08/14 10/08/14 10/08/14 10/08/14 H-3 Original Recount Reanalysis Original Recount Reanalysis Original Recount Reanalysis Original Recount Reanalysis Original Recount Reanalysis Original Recount Reanalysis 2140 2180 2470 182 194 741 721 502 191 188 194 177 2210 2200 2070 191 196 459 357 300 1060 1010 838 187 194 318 324 353+/- 256+/- 273+/- 299+/-+/-+/-153 152 145+/- 272+/- 275+/- 260:1+/-+++/-+135 131 132 173 175 163+/- 128+/- 131+/- 144 B-13 Intentionally left blank APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY Intentionally left blank TABLE C-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A Gr-B 3 48S MS-2 MS-20 MS-7 MS-8 MW-TM I-10)D MW-TMI-1OS MW-TMI-10S MW-TMI-1 31 MW-TMI-141 MW-TMI-18D MW-TMI-21 I MW-TMI-22S MW-TMI-31 MW-TMI-41 RW-2 10/28/14 07/10/14 04/23/14 01/20/14 07/09/14 01/21/14 04/22/14 01/20/14 07/09/14 10/28/14 01/20/14 04/24114 07/09/14 04/21/14 10/29/14 04/22/14 01/21/14 431 +/- 110* 136 860 568 186 295 293 795 1695 284< 144 305 3540 8916 404 186< 144+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-+/-110 < 0.5 101 76 90 87 110 133 102 88 182 278 < 0.7 109 82< 0.4 < 1.4< 0.6 < 0.9 2.7 +/- 0.7 3.5 +/- 0.7 C-I 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, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE MS-2 MS-8 MW-TMI-18D MW-TMI-22S MW-TMI-41 COLLECTION Be-7 PERIOD 04/23/14 < 32 01/21/14 < 43 04/24/14 < 30 04/21/14 < 34 04/22/14 < 28< 73< ##< 35< 53< 63 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140<4<4<2<2<2<5<4<3<4<6<2<2<2<1<3<2<3<3<2<2<5<8<7<3<5<4<7<4<3<5<3<6<2<4<3<2<3<4<3<3<4<3<3<3<2< 16< 16< 16< 15< 13<5<2<3<4<3 n-TABLE C-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 PERIOD Cm-243/244 Pu-238 Pu-239/240 U-233/234 U-235 U-238 Fe-55 Ni-63 NONE FOR 2014 TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION DATE SITE H-3 SW-E-3 04/23/14< 146 C-4 TABLE C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION Be-7 PERIOD K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 SW-E-3 04/23/14< 32 < 65<3 <4 <2 <3 <3 <4 <2 <3 <2 <17 <3 TABLE C-II1.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE TM-PR-MS-2Q TM-PR-MS-2Q TM-PR-MS-2Q TM-PR-MS-2Q COLLECTION DATE 03/31/14 06/06/14 08/29/14 11/07/14 H-3 2350 +/- 158 246 +/- 83< 177 599 +/- 111 C-6