ML13121A078

Annual Radiological Environmental Operating Report, 1 January Through 31 December 2012

ML13121A078
Person / Time
Site:	Three Mile Island
Issue date:	04/30/2013
From:	Teledyne Brown Engineering Environmental Services
To:	Office of Nuclear Reactor Regulation, Exelon Generation Co
References
TMI-13-065
Download: ML13121A078 (119)

Text

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 2012 Prepared By Teledyne Brown Engineering Environmental Services SExelonGeneration, Three Mile Island Nuclear Station Middletown, PA 17057 April 2013 Table Of Contents I. Sum m ary and Conclusions

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1 I1. Introduction

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

3 B. Im plem entation of the O bjectives

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4 I1l. Program Description

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4 A. Sam ple Collection

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

6 C. Data Interpretation

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7 D. Program Exceptions

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

11 IV. Results and Discussion

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11 A. Aquatic Environm ent .....................................................................................

11 1. Surface W ater .....................................................................................

11 2. Drinking W ater ...................................................................................

12 3. Effl uent W ater .....................................................................................

13 4. Storm W ater .......................................................................................

14 5. G round W ater .....................................................................................

14 6. Fish .....................................................................................................

14 7. Sedim ent ............................................................................................

15 B. Atm ospheric Environm ent ...........................................................................

15 1. Airborne Particulates

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15 a. Air Particulates

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

16 2. Terrestrial

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16 a. M ilk ..........................................................................................

16 b. Food Products .........................................................................

17 C. Am bient Gam m a Radiation

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17 D. Land Use Survey ..........................................................................................

18 E. Radiological Im pact of TM INS O perations

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19 F. Summary of Results -Inter-laboratory Comparison Program ......................

26 V. References

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28 i Appendices Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Table B-3 Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2012 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, 2012 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2012 Fi-gures Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2012 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2012 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2012 Data Tables and Figures -Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.ii Table C-11.1 Table C-11.2 Table C-11.3 Table C-11.4 Table C-II1.1 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, 2012.Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.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, 2012.Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Strontium in Predator and Bottom Feeder (Fish)Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.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, 2012.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.iii Table C-X.1 Table C-X.2 Table C-X.3 Fi-gures 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-I.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-II.1 Quarterly OSLD Results for Three Mile Island Nuclear Station, 2012.Mean Quarterly OSLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2012.Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2012.Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2012.Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974- 2012.Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2012.Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2012.Mean Cesium-1 37 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984- 2012.Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2012.Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 -2012.Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2012.Data Tables and Figures -Comparison Laboratory Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2012.Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Iodine-1 31 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.iv Table D-Ill.1 Table D-IV.1 Table D-V.1 Table D-V.2 Table D-VI.1 Fi-gures 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, 2012.Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2012.Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2012.Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2012.Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2012 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2012 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Teledyne Brown Engineering, 2012 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2012 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Environmental, Inc., 2012 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 2012 through 31 December 2012. During that time period, 1,734 analyses were performed on 1,320 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 F. No Sr-89 and Sr-90 activities were detected.Iodine-1 31 and gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in twelve 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 detected in six sediment samples. Occasionally Cs-1 37 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. No 1-131 or Sr-89 activities were detected.Concentrations of naturally occurring K-40 were consistent with those detected in previous years. Strontium-90 activities detected were consistent with those detected in previous years and were attributed to fallout from nuclear weapons testing. No other fission or activation products were found.Food Product samples were analyzed for concentrations of gamma emitting nuclides (including 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.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).

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 2012 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 2012 did not have any adverse effects on the health of the public or on the environment.

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

2.5 miles

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

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

At the end of 1993 TMI-2 was placed in a condition called Post-Defueling Monitored Storage. TMI-2 is maintained by Exelon under contract with GPU Nuclear.A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Landauer and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2012 through 31 December 2012.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 exposure pathways.2. Establishing baseline radiological data of media within those pathways.3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

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 2012. 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 three surface water locations (A3-2, J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9-1), and one effluent water location (K1-1). 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 sampleswere collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection.

Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND) location.

Location IND could be affected by TMINS' effluent releases.

Sediment samples composed of recently deposited substrate were collected semiannually at three locations (A1-3, J2-1 and K1-3). In addition, one sediment sample was collected annually at the EDCB. Location A1-3 was the control.

Atmospheric Environment The atmospheric environment was evaluated by 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, F1-3, G2-1, H3-1, M2-1 and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached.

The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product. Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K1 5-3 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 H1-2). B10-2 was the control location for both annual and monthly sampling.

Six different kinds of vegetation samples and eight 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.An indicator ring consisting of 60 locations (A3-1, A5-1, A9-3, B13-1, B2-1, B5-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, El-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1 and R9-1) extending to approximately 10 miles from the site designed to measure possible exposures to close-in population.

The balance of 11 locations (D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1) represent control areas.The specific dosimeter locations were determined by the following criteria: 1. The presence of relatively dense population;

2. Site meteorological data taking into account distance and elevation for each of the sixteen-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 2012. 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 Reportingq 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-1 34 and Cs-1 37 were reported.For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-1 34 and Cs-1 37 were reported.For air particulate eight nuclides, Be-7, Mn-54, Co-58, Co-60, Nb-95, Zn-95, Cs-1 34 and Cs-1 37 were reported.For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-1 40 and La-140 were reported.For food products five nuclides, Be-7, K-40, 1-131, Cs-1 34 and Cs-1 37 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 2012 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 E1-2, E1-2Q 1. For the sampling period 02/15/12 -02/22/12, samplers were temporarily turned off due to problems at the visitor's center. The power supply was repaired and the air samplers were returned to service. The samples were valid and sent to the lab for analysis.(IR 1327164 and IR 1327256)

F1-3 2. For the sampling period 06/13/12 -06/20/12, the pump was not operating at the time of sampling.

The timer was still operating making the sample invalid per procedure, therefore the sample was not sent to the lab. The pump was replaced on 06/22/12 returning the sampling station to service. (IR 1384487)G2-1, E1-2, E1-2Q, M2-1 3. For the sampling period 07125/12 -08/18/12, power outages due to severe storms caused lower than expected volumes. All samples were valid and sent to the lab for analysis (IR 488572).M2-1 4. For the sampling period 08/01/12 -08/08/12, lower than expected run times and sample volumes were noted, probably due to substation maintenance power interruption.

All samples were valid and sent to the lab for analysis (IR 488572).A3-1 5. For the sampling period 09/19/12 -09/26/12, lower than expected run times and sample volumes were noted, probably due to substation maintenance power interruption.

All samples were valid and sent to the lab for analysis (IR 488572).WATER J11-2 1. Hourly composite samples were missed when the sample line into the Susquehanna became submerged/lifted or disconnected from its anchoring cinderblocks due to river conditions.

Heat trace and insulation were also knocked off. In all cases the line was either repositioned/reconnected and/or the heat trace/insulation was reattached.

The sampler was verified operating during sample collection.

At all times enough sample was collected for the weekly composite sample so grab sampling was not required.

The impacted sampling periods were (IR 1376592): 01/03/12 -01/10/12 -sufficient volume, no grab sample required 01/17/12 -01/24/12 -sufficient volume, no grab sample required 02/28/12 -03/06/12 -sufficient volume, no grab sample required Q9-1 2. Surface water -source water to ISCO sampler was unavailable due to plant upgrades.

Grab sampling was performed for the following sampling periods (IR 1326498): 01/31/12 -02/07/12 02/07/12 -02/14/12 02/14/12 -02/21/12 02/21/12 -02/28/12 J1-2 3. For the sampling period 05/15/12 -05/22/12, sixty-three hourly samples were missed. The intake tubing was out of the water lying on the shoreline.

The intake line was repositioned into the water and the line was reattached to the anchor and buoy. Sufficient sample for the week was collected and a grab samples was not required (IR 488572).J1-2 4. For the following sampling periods, hourly samples were missed due to partially submerged line: 08/28/12 -09/04/12 -thirty-five samples were missed. Sufficient sample for the week was collected and a grab sample was not required.09/04/12 -09/11/12-43 samples were missed. Sufficient volume for the week was collected and a grab sample was not required. (IR 1446309)The line was repositioned on 09/07/12.J1-2 5. For the sampling period 09/18/12 -09/25/12, the composite sample was not available due to the sample line being detached from the sampler. A grab sample was taken for the week. The sample line was reattached to the sampler. (IR 1446309)J1-2 6. For the sampling period 10/02/12 -10/09/12, fifty-three samples were missed due to a no liquid detected error. Sufficient sample volume was collected and a grab sample was not required.

During sampler troubleshooting and return to service, the controller continued to receive a no sample detected error even though full volume was delivered.

On 10/10/12 the sampler was replaced with a new sampler.(IR 1446309)

TLD K1 5-1 1. During the first quarter collection, station K1 5-1 was found missing/stolen.

New mounting hardware and second quarter dosimeters were installed. (IR 1353661)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 2012.IV. Results and Discussion A. Aquatic Environment

1. Surface Water Samples were taken weekly from a continuous sampler at three locations (A3-2, J1-2 and Q9-1) and 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 five of 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 278 to 10,000 pCi/I. 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.

lodine-131 from medical discharges was detected in one sample, at a concentration of 1.5 pCi/I.Gamma Spectrometry 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-11.1, Appendix C). Gross beta activity was detected in 24 of 36 samples. The concentrations ranged from 1.7 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). Iodine-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 detected in one of 36 samples at concentrations just above the LLD. The concentration was 254 pCi/L (Figures C-4, Appendix C). The hypothetical dose to the maximum exposed individual from consuming this water from two locations was calculated as <0.004 mrem. (IR 1459647)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 2.7 to 6.9 pCi/l. Concentrations detected were consistent with those detected in previous years.Iodine-131 Monthly samples from location K1-1 were analyzed for concentrations of 1-131 (Tables C-111.1, Appendix C). Iodine-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 seven of 12 samples. The concentrations ranged from 475 to 63,300 pCi/l. 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.

Strontium Semiannual composite samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-111.1, Appendix C). No strontium activity was detected.

The highest MDC was calculated at <3.4 pCi/I for Sr-89 and at <1.0 pCi/I for Sr-90.Gamma Spectrometry Samples from location K1-1 were analyzed for gamma emitting nuclides (Table C-111.2, 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 <4.1 pCi/kg wet for Sr-90.Gamma Spectrometry 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 2,756 to 4,637 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 (Al -3, J2-1 and K1-3) semiannually.

Of these locations two (J2-1 and K1-3) could be affected by TMINS' effluent releases.

The following analysis was performed:

Gamma Spectrometry Sediment samples from all locations were analyzed for gamma emitting nuclides (Table C-V.1, Appendix C). Potassium-40 was found in all sediment samples and ranged from 8,405 to 19,760 pCi/kg dry. Cesium-137 was detected in six sediment samples.The concentrations ranged from 74 to 248 pCi/L. Cesium-1 37 is occasionally found in sediment at very low levels (just above LLD)and is not distinguishable from background levels. No other fission or activation products were detected (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 6 to 33 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.The results from the intermediate offsite locations (Group II)ranged from 7 to 32 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.The results from the Control location (Group III) ranged from 9 to 31 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3.Comparison of the 2012 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 2012 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 25 samples. These concentrations ranged from 52 to 134 E-3 pCi/m3. All other nuclides were less than the MDC.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 (K15-3, E2-2, F4-1 G2-1 and P4-1) biweekly March through November and monthly December through February.

The following analyses were performed:

Iodine-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VIII.1, Appendix C). All 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 activity was detected.

Strontium-90 activity was detected in two of 20 samples. The concentrations were 0.7 and 1.1 pCi/I. The activity detected was 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 623 to 1,659 pCi/l. All other nuclides were less than the MDC.b. Food Products Samples were collected from two locations (B10-2 and H11-2)on a monthly basis in lieu of milk sampling.

Samples from the four food product groups were collected annually from three locations (B10-2, E1-2 and H1-2) this year due to unavailability of sweet corn and a root vegetable at E1-2.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 10 of 26 samples. The concentrations ranged from 4 to 7 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 23 of 32 samples. These concentrations ranged from 179 to 5,459 pCi/I. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 1,894 to 8,952 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 12.1 to 35.0 mR/standard month. 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, G1 0-1, GI 5-1, 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, August, September, and October 2012 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 1/2 degree sectors around the site. The results of this survey 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 1.6 2.1 2.1 2 NNE 0.7 0.9 -2.4 3 NE 0.5 1.5 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 1.9 1.4 1.4 8 SSE 0.7 0.8 -9 S 2.3 2.7 3.3 10 SSW 0.6 2.5 4.9,14.4 -11 SW 0.5 1.0 12 WSW 0.5 1.3 13 W 0.7 1.3 -14 WNW 0.4 2.2 3.7 2.4 15 NW 0.4 1.2 --16 NNW 0.7 2.4 E. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2012 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation.

The 2012 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 0.16 mrem. This dose is equivalent to 0.05% 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 an advanced "class A" dispersion model.This model incorporates the guidelines and methodology set forth by the USNRC in Regulatory Guide 1.109. 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.

Once released, the dispersion of radionuclides in the environment is readily determined by computer modeling.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 and shoreline exposure.

The exposure pathways considered for the discharge of TMINS airborne effluents are plume exposure, inhalation, cow milk consumption, fruit and vegetable consumption, meat consumption and land deposition.

Numerous data files are used in the calculations that describe the area around TMI in terms of receptors.

Data files include such information as the distance from the plant stack to the site boundary in each sector, the population groupings, milk cows, milk goats, gardens of more than 500 square feet, meat animals, downstream drinking water users and crop yields.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).Doses are calculated for what is termed the "maximum hypothetical individual".

This individual is assumed to be affected by the combined maximum environmental concentrations wherever they occur.For liquid releases, the maximum hypothetical individual would consume 193 gallons of Susquehanna River water per year from the first downstream drinking water supplier, eat 46 pounds of fish each year that reside in the plant discharge area and stand 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year on the shoreline influenced by the plant discharge.

For airborne releases, the maximum hypothetical individual would live at the location of highest radionuclide concentration for inhalation and direct plume exposure.

Additionally, each year the hypothetical individual would consume 106 gallons of cow milk, 141 pounds of leafy vegetables, 1389 pounds of non-leafy vegetables and fruits and 243 pounds of meat produced at the locations with the highest predicted radionuclide concentrations.

The exposure pathway through goat milk does not currently exist. Therefore, goat milk is not included.2. Result of Dose Calculations The maximum hypothetical doses due to 2012 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 2012 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 2012 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.16 mrem. This dose is equivalent to 0.05% 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 2012 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).In conclusion, radioactive materials related to 2012 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 2012 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 2012 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 2012 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hoothetical 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 (lodines, Tritium and Particulates) 3 total body, or 10 any organ 5 total body, or 15 skin 15 any organ Calculated Dose (mrem/yr)TMI-l TMI-2 1.77E-2 2.02E-4 1.85E-2 3.22 E-4 8.93E-5 0*1.54E-4 0*1.36E-1 1.46E-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 0.74 0.84 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 2012 TMINS operations was 0.60 nirem. This dose was based on a maximum net fence-line exposure rate of 8.7 mR/std month 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 (0.16 mrem) and the dose from direct radiation (0.60 mrem) yielded a maximum hypothetical dose of 0.76 mrem.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2012 TMI-I and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)TMI- I TMI-2 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-2.1 .77E-2 2.02E-4 8.93E-5 0*1.36E-1 1.46E-5 Individual Whole Body Dose Due to TMI-I and TMI-2 Onerations:

0.16 mrem/yr 311 mrem/vr Individual Whole Body Dose Due to Natural Backyround Radiation (1)(1) NCRP 160- (2009)

Figure I Exposure Pathways For Radionuclides Routinely Released From TMINS PREDOMINANT RADIONUCLIDES, NOBLE GASES (Xe,Kr)Plume exposure RADIOIODINES (1-131, 1-133)Inhalation and consumption of milk, water, fruits, and vegetables RADIOSTRONTIUMS (Sr-19. 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, fru its, and vegetables TRITIUM (H-3)Inhalation and consumption of water, milk, fruits, and vegetables F. 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.

For the TBE laboratory, 12 out of 18 analytes met the specified acceptance criteria.

Six analytes (Co-60, Gross Alpha, Gross Beta, Sr-89, Sr-90 and Zn-65) did not meet the specified acceptance criteria for the following reason:

Teledyne Brown Engineering's MAPEP March 2012 Co-60 in soil result of 7.61 Bq/kg was higher than the known value of 1.56 Bq/kg, resulting in a found to known ratio of 4.88 on a sensitivity evaluation.

NCR 12-08 was initiated to investigate this failure. No cause could be found for the failure. TBE is monitoring the Co-60 in soil analyses on a case-to-case basis.2. Teledyne Brown Engineering's MAPEP March 2012 Zn-65 in AP result of 4.19 Bq/sample was higher than the known value of 2.99 Bq/sample, exceeding the upper control limit of 3.89 Bq/sample.

NCR 12-08 was initiated to investigate this failure. No cause could be found for the failure and is considered an anomaly specific to the MAPEP sample. The first and second quarter 2012 Analytics AP Zn-65 analyses were acceptable.

3. Teledyne Brown Engineering's MAPEP September 2012 Sr-90 in water result of 19.6 pCi/L was higher than the known value of 12.2 pCi/L, exceeding the upper control limit of 15.9 pCi/L. NCR 12-11 was initiated to investigate this failure. An incorrect aliquot was entered into LIMS. Using the correct aliquot, the result would have fallen within the acceptance range.4. Teledyne Brown Engineering's ERA May 2012 Gross Alpha in water result of 82.4 pCi/L was higher than the known value of 62.9 pCi/L, which exceeded the upper control limit of 78.0 pCi/L. NCR 12-05 was initiated to investigate this failure. The G-1 detector is slightly biased high for Th-230 based measurements.

The G-1 detector is used only for ERA samples. The detector was recalibrated.

5. Teledyne Brown Engineering's ERA November 2012 Gross Beta in water result of 59.3 pCi/L was higher than the known value of 39.2 pCi/L, which exceeded the upper control limit of 46.7 pCi/L. NCR 12-13 was initiated to investigate this failure. The rerun result of 44.8 fell within the control limits. It appears an incorrect aliquot was entered into LIMS.6. Teledyne Brown Engineering's ERA November 2012 Sr-89 in water result of 46.5 pCi/L was higher than the known value of 39.1 pCi/L, which exceeded the upper control limit of 46.1 pCi/L. NCR 12-13 was initiated to investigate this failure. The found to known ratio was 1.19, which TBE considers acceptable with warning.For the EIML laboratory, 12 out of 14 analytes met the specified acceptance criteria.

Two analytes (Gross Beta and Co-57) did not meet the specified acceptance criteria for the following reason:

1. Environmental Inc., Midwest Laboratory's ERA April 2012 Gross Beta in water result of 76.2 pCi/L was higher than the known value of 44.2 pCi/L, exceeding the upper control limit of 51.5 pCi/L. The rerun result of 38.3 fell within the control limits. A sample dilution problem is suspected.

2. Environmental Inc., Midwest Laboratory's MAPEP August 2012 Co-57 in vegetation result of 7.44 pCi/L was higher than the known value of 5.66 pCi/L, exceeding the upper control limit of 7.36 pCi/L.The recount result of 6.74 fell within the control limits. The sample was recounted using a geometry more closely matched to the MAPEP sample size.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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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 3046 (5/12)(278/10000)

GAMMA MN-54 CO-58 I NA 15 <LLD 15 <LLD 30 '<LLD 15 <LLD 30 <LLD<LLD 1.5 (0/12)<LLD<LLD<LLD<LLD<LLD 3046 (5/12)(278/10000)

J 1-2 INDICATOR WEST SHORE; TMI 0.5 MILES S OF SITE A3-2 CONTROL SWATARA CREEK 2.5 MILES N OF SITE 1.5 (1/12)0 0 FE-59 CO-60 ZN-65 NB-95 0 0 0 0 0 0 15 <LLD <LLD TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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 PAT1WAY 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)

ZR-95 CS- 134 CS-137 BA- 140 LA- 140 30 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD 4 2.8 (18/24)(1.9/4.2)1 <LLD 2000 254 (1/24)<LLD<LLD<LLD<LLD<LLD 2.1 (6/12)(1.7/3.0)0 0 0 0 0 0 DRINKING WATER (PCI/LITER)

GR-B 1-131 H-3 36 36 36 2.9 (12/12)(1.9/4.2)G15-2 INDICATOR WRIGHTS WATER SUPPLY 13.3 MILES SE OF SITE<LLD<LLD 0 0 254 (1/12)TM-DW-G15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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)

GAMMA MN-54 36 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 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 CS-134 15 <LLD <LLD 0 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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)

CS-137 BA-140 LA- 140 18 <LLD 60 <LLD 15 <LLD<LLD<LLD<LLD 0 0 0 EFFLUENT WATER (PCV/LITER)

GR-B 1-131 12 4.7 (12/12)(2.7/6.9)12 12<LLD NA NA NA NA 47 (12/12)(2.7/6.9)KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE H-3 2000 15589 (7/12)(475/63300) 5 <LLD 15589 (7/12)(475/63300)

KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 0 0 0 0 0 SR-89 SR-90 2 2 <LLD NA TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBEROF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION f 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)

LI GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 15 <LLD Is <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD NA NA NA NA 0 0 12 0 NA 0 0 0 NA NA 15 <LLD NA 0 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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)

CS-137 BA-140 LA- 140 SR-90 GAMMA K-40 18 <LLD 60 <LLD 15 <LLD 10 <LLD NA NA NA 0 0 0 0 BOTTOM FEEDER (PCI/KG WET)4<LLD 4 NA 2974 (2/2)(2756/3192) 4138 (2/2)(3964/4311) 4138 (2/2)(3964/4311

)BKGB CONTROL CITY ISLAND UPSTREAM OF DISCHARGE MN-54 CO-58 FE-59 130 <LLD 0 0 0 130 <LLD<LLD 260 <LLD <LLD 0 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION 4 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)CO-60 ZN-65 CS-134 CS-137 SR-90 GAMMA K-40 130 <LLD 260 <LLD 130 <LLD]so <LLD 10 <LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 PREDATOR (PCI/KG WET)4 4 NA 4110 (2/2)(3739/4480) 130 <LLD 4048 (2/2)(3459/4637) 4110 (2/2)(3739/4480)

INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE 0 MN-54 CO-58<LLD 130 <LLD <LLD TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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 (PCIKG WET)00 FE-59 CO-60 ZN-65 CS- 134 CS-137 GAMMA K-40 260 <LLD 130 <LLD 260 <LLD 130 <LLD 150 <LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 SEDIMENT (PCIKG DRY)7 NA 14195 (5/5)13545 (2/2)17110 (I/I)EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE 0 (8405/19760)

(11090/16000)

MN-54 CO-58 NA <LLD<LLD NA <LLD <LLD 0 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION f 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-60 CS-134 CS-137 GR-B AIR PARTICULATE (E-3 PCI/CU.METER) 370 NA <LLD 150 <LLD 180 169 (4/5)(74/248)10 18 (312/317)(6/33)NA 71.7 (21/24)(51.8/134)

NA <LLD NA <LLD<LLD<LLD<LLD 19 (52/53)(9/31)248 (I/I)19 (52/53)(9/31)0 0 0 0 EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE Q15-I CONTROL WEST FAIRVIEW 13.5 MILES NW OF SITE A3-1 INDICATOR M IDDLETOWN 2.6 MILES N OF SITE GAMMA BE-7 28 73.7 (4/4)(54.1/96.7) 79.5 (3/4)(57.7/93.3)

MN-54 CO-58 CO-60<LLD 0 0 0 0<LLD NA <LLD <LLD TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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 NA <LLD NA <LLD 50 <LLD 60 <LLD<LLD<LLD<LLD<LLD 0 0 0 0 0 CS-137 AIR IODINE -(E-3 PCI/CU.METER)

GAMMA 1-131 370 70 <LLD I <LLD MILK (PCI/LITER) 1-131 SR-89 SR-90 115 20 20<LLD<LLD<LLD 1./(1/4)0 0 0 0<LLD 2 0.7 (1/16)1.1 (1/4)K15-3 CONTROL MEYER'S FARM 14.5 MILES SSW OF SITE TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBEROF 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-137 115 NA 1274 (92/92)(623/1659) 1299 (23/23)(1021/1597) 1415 (23/23)(1119/1659)

P4-I INDICATOR 0 0 15 <LLD 18 <LLD 60 <LLD 15 <LLD<LLD<LLD<LLD<LLD 0 BA- 140 LA- 140 0I 0 VEGETATION (PCI/KG WET)SR-90.26 10 5.8 (5/13)(4.5/7.1)5.5 (4/13)(3.9/7.2)5.8 (5/12)(4.5/7.1)H 1-2 INDICATOR RED HILL MARKET 1.0 MILES SSE OF SITE B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE 0 ALONG ROUTE 441 GAMMA BE-7 32 NA 920 (12/16)(208/2644) 1748 (11/16)(179/5459) 1748 (11/16)(179/5459) 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2012 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2012 Location of Facility:

MIDDLETOWN, PA REPORTING PERIOD: 2012 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)K-40 1-131 NA 4549 (16/16)(2590/7721) 5280 (16/16)(1894/8952) 5280 (16/16)(1894/8952)

B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE CS- 134 CS- 137 60 <LLD 60 <LLD 80 <LLD<LLD<LLD<LLD 0 0 0 0 DIRECT RADIATION OSLD-QUARTER 356 (MILLI-ROENTGEN/QUARTER)

NA 19.7 (316/316)(12.1/35.0) 21.7 (40/40)(17.0/33.4) 29.8 (4/4)(27.7/35.0)

H8-1 INDICATOR SAGINAW ROAD 7.4 MILES.SSE OF SITE 0 STARVIEW APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION

& ANALYTICAL METHODS 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, 2012 Sample Medium Station Map Distance Code Number (miles) Azimuth Description AQS ID APAID 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 A1-3 A1-4 A3-1 A3-2 A5-1 A9-3 B1-1 B1-2 B2-1 B5-1 B10-1 B10-2 C1-1 C1-2 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 2 2 2 3 2 2 3 2 2 3 10 0.7 0.3 1.5 4.7 7.1 0.5 0.3 2.7 2.7 4.4 8.0 0.6 0.4 1.9 4.9 1 0.2 1 0.5 3 9.2 ID ID ID 2 3 3 2 2 2 3 2 2 2 3 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 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 20 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 31' 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 44' 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 760 ENE of Reactor Building on top of dike, TMI 670 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 0 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 1430 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 1310 SE of site at intersection of Bainbridge and Risser Roads 128' 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 AP, Al ID ID M ID ID ID ID ID ID ID Al, AP, M ID ID ID ID DW DW 3 22 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, 2012 Sample Medium ID FP AP, Al, ID ID ID ID AQF ID SW ID AQS ID ID ID ID EW AQS Station Map Code Number H1-1 1 HI-2 1 H3-1 2 H5-1 2 H8-1 3 H15-1 3 Indicator

-J1-1 1 J1-2 1 J1-3 1 J2-1 2 J3-1 2 J5-1 2 J7-1 3 J15-1 3 K1-1 1 K1-3 1 K1-4 1 K2-1 2 K3-1 2 K5-1 2 K8-1 3 K15-1 3 Distance (miles)ID ID ID ID ID ID M ID ID ID ID ID ID ID Azimuth Description 0.5 167' SSE of site, TMI 1.0 1510 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 1630 SSE of site along Saginaw Road, Starview 13.2 1570 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 0.3 189' 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 1810 S of site along Canal Road, Conewago Heights 6.5 1760 S of site off of Maple Street, Manchester 12.6 1830 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 1960 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 0.1 250° WSW of Reactor Building on SE corner 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 Lewvsberny 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 Lisbum Road and Main Street, Lisbum 0.4 303 0 WNW of site on Shelley Island ID AP, Al, ID K1 5-3 L1-1-LU-2 L2-1 L5-1 L8-1 L15-1 M1-1 M1-2 M2-1 M5-1 M9-1 N1-1 N1-3 N2-1 N5-1 N8-1 N15-2 1 2 2 3 3 ID ID ID ID ID ID ID ID ID 3 1 2 2 3 2 2 3 3 1 P1-1 B-3 TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2012 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 01-2 Q2-1 Q5-1 Q9-1 Q15-1 R1-1 R1-2 R3-1 R5-1 R9-1 R15-1 2 2 2 3 2 2 3 3 3 1 2 2 2.0 3.7 5.0 8.0 0.5 0.2 1.9 5.0 8.5 13.4 0.2 0.7 2.6 4.9 1 0.1 2920 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 283' WNW of site along Route 262 295' WNW of site at farm on Valley Road 2840 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 3210 NW of Reactor Building on fence W of Warehouse 1, TMI 3100 NW of site along access road along river 3170 NW of site along Lumber Street, Highspire 3100 NW of site at the Steelton Water Company 309' NW of site behind West Fairview Fire Dept. Social Hall (abandoned) 3350 NNW of Reactor Building along W fence, TMI 3340 NNW of site on central Henry Island 3410 NNW of site at Crawford Station, Middletown 3390 NNW of site at intersection of Spring Garden Drive and Route 441 3410 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights 3320 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park ID ID ID ID ID ID 3 8.0 3 11.2 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, 2012 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 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 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 I_ _ IIIexchange 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 inn exchanoe 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, 2012 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, 2012 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 andlor 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 I _ I gamma spectroscopy TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2012 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 A120 3:c Landauer Station)Dosimetry Incorporated elements.w Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2012 B-9 Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2012 B-1O Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2012 B-1I Intentionally left blank APPENDIX C DATA TABLES AND FIGURES -PRIMARY LABORATORY TABLE C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 01/03/12 -01/31/01/31/12 -02/28/02/28/12 -04/03/04/03/12 -05/01/05/01/12 -05/29/05/29/12 -07/03/07/03/12 -07/31/07/31/12 -08/28 08/28/12 -10/02/10/02/12 -10/30 10/30/12 -11/27 11/27/12-12/31 J,1-2 Q9-1 12/12 12 12 12 12 12 12'12/12/12/12 (1)(1)(1)(1)(1)(1)278 +/- 118 174<< 184< 183< 186 354 +/- 129< 169< 161 446 +/- 139 4150 +/- 463 10000 +/- 1040< 184< 167< 174< 181< 184< 182< 184< 168< 160< 195< 183< 167< 183 MEAN*3046 +/- 8441 -TABLE C-1.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 01/10/12 -01/31/12 02/07/12 -02/28/12 03/06/12 -04/03/12 04/10/12 -05/01/12 05/08/12 -05/29/12 06/05/12 -07/03/12 07/10/12 -07/31/12 08/07/12 -08/28/12 09/04/12 -10/02/12 10/09/12 -10/30/12 11/06/12 -11/27/12 12/05/12 -12/31/12 A3-2< 0.6< 0.6< 0.4< 0.5< 0.6< 0.8 1.5 +/- 0.5< 0.7< 0.6< 0.6< 0.7< 0.7 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-I TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION Mn-54 PERIOD Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 J1-2 01103112 -01/31112 (1) < 5 01/31112 -02/28/12 < 6 02/28/12 -04/03/12 (1) < 4 04/03/12 -05/01/12 < 6 05/01/12 -05/29/12 (1) < 5 05/29/12 -07/03/12 < 4 07103/12 -07/31/12 < 6 07/31/12 -08/28/12 < 5 08/28/12 -10/02/12 (1) < 4 10/02/12 -10/30/12 < 5 10/30/12 -11/27/12 < 6 11/27112 -12131/12 < 5 MEAN 09-1 01/03/12 -01/31/12 < 4 01/31/12 -02/28/12 (1) < 6 02/28/12 -04/03/12 < 4 04/03/12 -05/01/12 < 9 05/01/12 -05/29/12 < 4 05/29/12 -07/03/12 < 4 07/03/12 -07/31/12 < 5 07/31/12 -08/28/12 < 6 08/28/12 -10/02/12 < 4 10/02/12 -10/30/12 < 5 10/30/12 -11/27/12 < 6 11/27/12 -12/31/12 < 5 MEAN<8<4<7<5<4<5<6<3<5<6<6<4<6<4<9<5<4<6<6<4.<5<6<6< 1U* 16<9*13*13<8<9< 14<9* 12*13<11<8<13* 12*19<8<9< 10<11<9* 12<13<15< 6<8<4<7<7<4<6<6<3<7<5<5<3<7<4<9<4<4<6<6<3<4<5<5< 12* 14<9* 12< 10<7< 12< 14<7< 11< 10< 11<8< 14<9< 19< 10<8< 12< 10<7< 11< 12* 12< 5<7<5<6<6<4<6<6<4<6<6<6<4<6<5< 10<5<4<6<7<4<4<6<6< 9< 16<8< 11<9<6<9< 11<8<9*12< 10<6< 11<8< 16< 10<8<9<9<7<9< 11<9< 5<6<4<6<5<4<5<4<4<5<6<5<3<6<4<9<4<4<5<6<3<4<6<5< 5< 10<5<7<6<4<6<6<4<6<7<5<4<7<6<9<6<4<6<6<4<5<6<6* 261< 35* 20< 30* 20< 19* 28< 31* 28* 28< 36* 29< 16< 31* 23< 45< 25< 17* 25< 30* 29* 21< 30< 29< 9< 10<6< 10<7<6<6< 11<8<7<4<7<5< 11<5< 14<6<7<11< 13<9<9< 11< 13 (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, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 01/03/12 -01/31/12 01/31/12 -02/28/12 02/28/12 -04/03/12 04/03112 -05/01/12 05/01/12 -05/29/12 05/29/12 -07/03/12 07/03/12 -07/31/12 07/31/12 -08/28/12 08/28/12 -10/02/12 10/02/12 -10/30/12 10/30/12 -11/27/12 11/27/12 -12/31/12 G15-2 G15-3 Q9-1 2.7 +/- 1.0 < 1.4 < 1.4 3.0 +/- 1.4 3.0 +/- 1.3 < 1.9 3.3 +/- 2.0 < 2.8 < 2.6 1.9 +/- 1.2 < 1.8 < 1.7 2.9 +/- 1.9 < 2.7 < 2.6 2.3 +/- 1.0 < 1.5 2.2.2 +/- 1.0 2.5 +/- 1.1 1.2.8 +/- 1.2 2.4 +/- 1.2 1.3.4 +/- 1.1 3.1 +/- 1.2 3.3.2 +/- 1.1 2.5 +/- 1.1 1.4.2 +/- 1.2 2.5 +/- 1.1 2.3.1 +/- 1.4 < 2.0 < 2.0 0 +/- 1.0 7 +/- 1.0 8 +/-1.1 0 1.1 8 +/-1.0 5 + 1.0 MEAN*2.9 +/- 1.2 2.6 +/- 0.6 2.1 +/- 1.0 TABLE C-11.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PF R 1I"1" G15-2 G15-3 Q9-1 PERIOD UliU31iz -Ui/JlI[e 01/31/12 -02/28/12 02/28/12 -04/03/12 04/03/12 -05/01/12 05/01/12 -05/29/12 05/29/12 -07/03/12 07/03/12 -07/31/12 07/31/12 -08/28/12 08/28/12 -10/02/12 10/02/12 -10/30/12 10/30/12 -11/27/12 11/27/12 -12/31/12* 0.3< 0.5< 0.4* 0.4< 0.8< 0.6< 0.6< 0.6< 0.7* 0.6< 0.6< U.3< 0.3* 0.4< 0.3< 0.3< 0.9< 0.5* 0.7< 0.5< 0.7< 0.6< 0.7< U.0< 0.3< 0.4< 0.3< 0.4< 0.9< 0.6< 0.6< 0.6< 0.7< 0.6< 0.7 MEAN TABLE C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 01/03/12 -01/31/12 01/31/12 -02/28/12 02/28/12 -04/03/12 04/03/12 -05/01/12 05/01/12 -05/29/12 05/29/12 -07/03/12 07/03/12 -07/31/12 07/31/12 -08/28/12 08/28/12 -10/02/12 10/02/12 -10/30/12 10/30/12 -11/27/12 11/27/12 -12/31/12 G15-2 G15-3 Q9-1< 166< 174< 189< 179< 169< 186< 167< 162< 192< 184< 164< 186< 166* 175< 184< 164* 157< 181< 165* 163< 194< 173 254 +/- 139< 176< 167< 173< 182< 166< 199< 182< 172< 163< 193< 182< 165< 187 MEAN** THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-3 TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 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 G15-2 01/03/12 -01/31/12 < 4 01/31/12 -02/28/12 < 8 02/28/12 -04/03/12 < 4 04/03/12 -05/01/12 < 6 05/01/12 -05/29112 < 4 05/29/12 -07/03/12 < 3 07/03/12 -07/31/12 < 6 07131/12 -08/28/12 < 5 08/28/12 -10/02/12 < 4 10/02/12 -10/30/12 < 5 10/30/12 -11/27/12 < 8 11/27/12 -12/31/12 < 5 MEAN<3 <5<:8 <17< 4 <9<6 <11< 5 <8<3 <6<5 <9<4 <7<3 <9<*5 <10<*6 <12<*5 <13<4 <9<6 < 14<*6 <13<*7 <14<*6 <16<*5 <10<5 <11< 5 <12<4 <9<4 <.9<:6 <14<6 <13<2<7<5<6<4<3<6<5<3<5<6<6<6< 16<9<11<10<6<9<7<7<9< 16<11<9<10<11<15* 14<9* 13* 10<7* 10* 14<9<4<7<5<6<5<3<6<5<5<5<8<6<5<6<5<8<6<5<8<8<4<5<7<7<5<15<8<9<7<5<9<8<7<10* 14<11<8<11<10* 12<11<8<10<10<7<7*13<12< 3<8<4<6<4<3<6<4<4<5<8<:4<3<8<5<5<4<3<5<5<4<5<7<5<5<7<6<8<:8<5<7<7<4<5<7<7<14 <5<31 < 11<21 <7<27 <8<19 <7<14 <4<24 < 11<24 <9<26 <9<25 <6< 37 < 13<34 <13<21 <8<23 <8<27 <8< 37 < 13<35 <9<22 <6<33 < 11<32 < 9<26 < 8<22 < 7<26 < 11<28 <9 G15-3 01/03/12 -01/31/12 < 6 01/31/12 -02/28112 < 6 02/28/12 -04/03/12 < 5 04/03/12 -05/01/12 < 7 05/01/12 -05/29/12 < 5 05/29/12 -07/03/12 < 4 07/03/12 -07/31/12 < 5 07/31/12 -08/28/12 < 6 08/28/12 -10/02/12 < 4 10/02/12 -10/30/12 < 4 10130/12 -11/27/12 < 6 11/27/12 -12/31/12 < 6<5<7<5<7<7<5<6<8<3<4<7<5<4<6<5<8< 6<4<5<6<3<:4<5<5 MEAN TABLE C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 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 Q9-1 01/03/12 01/31/12 02/28/12 04/03/12 05/01/12 05/29/12 07/03/12 07/31/12 08/28/12 10/02/12 10/30/12-01/31/12-02/28/12-04/03/12-05/01/12-05/29/12-07/03/12-07/31/12-08/28/12-10/02/12-10/30/12-11/27/12<4<5<4<7<8<5<5<5<4<:4<6<5<4<6<4<9<8<4<5<4<5<5<6<8< 11<7< 16< 14<8<9<11<11< 10<11<4<6<4<8< 10<4<5<4<5<4<6<8< 12<8< 19< 14<9<9< 10<11< 10< 15<4<6<4<9<8<4<4<6<5<4<6<8-13<7< 15< 14<7<8<8<8<7<13<3<7<4<9<8<4<4<4<4<4<7<4<6<5<8<8<4<4<5<4<4<6< 18< 31< 21< 43< 39* 20* 19< 25< 27* 20< 29<6<9<7< 14<11<7<6<9<9<7< 11 11127/12 -12/31112<5 <11 <6 <9 <5 <12 <4 <5 <30 <10 MEAN 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, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION PERIOD GR-B 1-131 H-3 SR-89 SR-90 K1-1 01/03/12 01/03/12 01/31/12 02/28/12 04/03/12 05/01/12 05/29/12 07/03/12 07/03/12 07/31/12 08/28/12 10/02/12 10/30/12 11/27/12 MEAN*01131/12 07/03/12 02/28/12 04/03/12 05/01/12 05/29/12 07/03/12 07/31/12 12/31/12 08/28/12 10/02/12 10/30/12 11/27/12 12131/12 2.8 +/- 1.1 < 0.6 475 +/- 127 3.8 4.2 4.0 4.3 2.7 6.9+/- 1.4+/- 2.1+/- 1.5+/- 2.0+/- 1.2+/- 1.5< 0.3< 0.4< 0.3< 0.5< 0.8< 0.6< 0.8< 0.6< 0.6< 0.8< 0.6 172 182 182 178 5530 +/- 605 1820 +/- 234< 1.9 < 1.0< 3.4 < 0.7 4.5 +/-5.4 +/-6.9 +/-5.0 +/-6.4 +/-1.4 1.4 1.4 1.3 1.7 2110 +/-4690 +/-31200 +/-63300 +/-< 184 253 526 3150 6340 4.7 +/- 2.9 15589 +/- 47186 -* 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, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE K1-1 COLLECTION PERIOD 01/03/12 -01/31/12 01/31/12 -02/28/12 02/28/12 -04/03/12 04/03/12 -05/01/12 05/01/12 -05/29/12 05/29/12 -07/03/12 07/03/12 -07/31/12 07/31/12 -08/28/12 08/28/12 -10/02/12 10/02/12 -. 10/30/12 10/30/12 -11/27/12 11/27/12 -12/31/12 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-1 37 Ba-140 La-140<4<6<3<7<4<4<5<6<3<5<8<5<4<4<2<7<4<4<4<6<4<5<8<6<6< 13<7* 12< 15<8<9< 14<7< 11< 13< 10<4<5<3<6<4<4<4<7<3<6<7<5<8< 11<7<18< 11<7<8< 11<7<9< 13< 13<4<5<3<7<6<4<6<6<3<5<6<7<7< 10<4< 12< 10<7<8< 12<6<9< 11< 13<3<4<2<9<5<4<5<6<3<5<6<5<4<7<3<7<5<5<6<6<3< 6<7<6< 16< 30* 16< 30< 22< 20< 26< 33< 24< 23< 35< 26<6<7<5< 10<9<6<9< 12<7<9< 11<8 MEAN TABLE C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH)SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD INDP PREDATOR 06/04/12 09/25/12 Sr-90< 4.1< 3.9 MEAN INDB BOTTOM FEEDER 06/04/12 10/04/12 MEAN BKGP PREDATOR 06/14/12 10/11/12< 3.5< 3.3< 3.1< 2.5 MEAN BKGB BOTTOM FEEDER 06/14/12 10/11/12< 3.5< 3.0 MEAN 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, 2012 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 SITE COLLECTION PERIOD BKGB BOTTOM FEEDER 06/14/12 10/11/12 MEAN BKGP PREDATOR 06/14/12 10/11/12 4311 +/- 1166 < 72 3964 +/- 773 < 59< 84 < 156 < 81 < 122 < 62< 58 < 103 < 57 < 119 < 55< 75< 61 4138 +/- 491 3459 +/- 863 < 46 4637 +/- 920 < 41 4048 +/- 1666 -< 58 < 155 < 58 < 110 < 43< 44 < 109 < 47 < 87 < 47< 57< 44 MEAN cm INDB BOTTOM FEEDER 06/04112 10/04/12 MEAN INDP PREDATOR 06/04/12 09/25/12 3192 +/- 847 < 50 < 59 < 121 < 73 < 105 < 57 2756 +/- 854 < 43 < 53 < 122 < 45 < 116 < 48 2974 +/- 617 -----4480 +/- 897 < 51 < 70 < 128 < 66 < 133 < 53 3739 +/- 821 < 44 < 48 < 92 < 57 < 81 < 47< 47< 50< 55< 53 MEAN 4110 +/- 1048 TABLE C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA SITE COLLECTION PERIOD A1-3 06/18/12 10/24/12 MEAN EDCB 10/24/12 MEAN*J2-1 06/18/12 10/24/12 MEAN*K1-3 06/18/12 10/24/12 MEAN K-40 16000 +/- 1275 11090 +/- 1396 13545 +/- 6944 17110 +/- 1896 19760 +/- 1892 10700 +/- 1393 15230 +/- 12813 15000 +/- 1502 8405 +/- 1090 11703 +/- 9327 Mn-54 Co-58 Co-60 Cs-134 U< 59< 74< 83< 85< 69< 79< 57 Cs-137< 54 < 58 < 48 < 66< 56 < 85 < 57 < 81< 80 < 90 < 69< 89 < 90 < 72< 57 < 68 < 54< 86 < 83 < 70< 49 < 68 < 46 248 +/- 117 124 +/- 71< 70 229 +/- 83 74 +/- 38 152 +/- 220* THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-IO TABLE C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION. 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD GROUP I GROUP 11 El-2 12/28/11 01/04/12 01/11/12 01/18/12 01/25/12 02/01/12 02/08/12 02/15/12 02/22/12 02/29/12 03/07/12 03/14/12 03/21/12 03/28/12 04/04/12 04/11/12 04/18/12 04/25/12 05/02/12 05/09/12 05/16/12 05/22/12 05/30/12 06/06/12 06/13/12 06/20/12 06/27/12 07/04/12 07/11/12 07/18/12 07/25/12 08/01/12 08/08/12 08/15/12 08/22/12 08/29/12 09/05/12 09/12/12 09/19/12 09/26/12 10/03/12 10/10/12 10/17/12 10/24/12 10/31/12 11/07/12 11/14/12 11/20/ 12 11/28/12 12/06/12 12/12/12 12/19/12 12/27/12-01/04/12-01/11/12-01/18/12-01/25/12-02/01/12-02/08/12-02/15/12-02/22/12-02/29/12-03/07/12-03/14/12-03/21/12-03/28/12-04/04/12-04/11/12-04/18/12-04/25/12-05/02/12-05/09/12-05/16/12-05/22/12-05/30/12-06/06/12-06/13/12-06/20/12-06/27/12-07/04/12-07/11/12-07/18/12-07/25/12-08/01/12-08/08/12-08/15/12-08/22/12-08/29/12-09/05/12-09/12/12-09/19/12-09/26/12-10/03/12-10/10/12-10/17/12-10/24/12-10/31/12-11/07/12-11/14/12-11/20/12-11/28/12-12/06/12-12/12/12-12/19/12-12/27/12-01/02/13 10 1 5 16 +/- 6 16 1 5 22 +/- 6 18 +/- 5 15 +/- 5 18 +/- 5 (1) 15 1 6 13 +/- 5 10 +/- 5 15 +/- 5 21 +/- 5 16 +/- 5< 7 15 +/- 5 15 +/- 5 9+/-5 18 +/-5 11 +/- 5< 7 17 +/- 6< 6 6 13 9 13 19 18 11 (1) 13 9 (1) 28 20 20 26 28 19 23 (1) 18 17 24 12 21 20 6 22 27 21 23 18 27 14 17 Fl-3 17 +/-5 18 +/-6 14 +/-5 20 +/-6 18 +/-5 16 +/-5 22 +/- 5 16 +/- 5 17 +/- 6 11 +/-5 19 +/-5 13 +/-5 15 +/-5 9+/-5 18 +/-5 19 +/-5 16 +/-5 24 +/-6 11 +/-5 10 +/-5 11 +/-5 15 +/-5 12 +/-5 16 +/- 5 (1)19 +/- 7 23 +/- 6 16 +/- 5 18 +/- 5 12 +/- 5 13 +/- 5 26 +/- 6 15 +/- 5 26 +/- 6 27 +/- 6 33 +/- 6 12 +/- 5 20 +/- 5 12 +/- 5 21 +/- 6 23 +/- 6 11 +/-5 28 +/-5 23 +/-5 7+/-2 29 +/-6 23 +/-6 21 +/-5 25 +/- 5 17 +/- 6 27 +/- 6 19 +/- 5 16 +/- 6 A3-1 13 +/- 5 23 +/- 6 16 +/- 5 15 +/- 5 15 +/- 5 18 +/- 5 16 +/- 5 15 +/- 5 21 +/- 6 13 +/- 5 15 +/- 5 20 +/- 5 16 +/- 5 12 +/- 5 17 +/- 5 17 +/- 5 15 +/- 5 25 +/- 6 9+/-5 12 +/-5 10 +/-5 17 +/-5 10 +/-5 19 +/- 5 10 +/- 5 22 +/- 5 25 +/- 6 17 +/- 5 14 +/- 5 14 +/- 5 11 +/-5 23 +/-6 14 +/-5 26 +/-6 25 +/-6 29 +/-6 13 +/-5 18 5 14 +/-6 18 +/- 6 23 +/- 6 9+/-5 24 +/-5 20 +/-5 8+/-3 24 +/-5 26 +/-6 27 +/-6 25 +/- 5 18 +/- 6 22 +/-6 17 +/-5 16 +/-6 G2-1 14+/- 5 16 +/-6 16 +/-5 17 +/-5 17 +/-5 15 +/-5 17 +/-5 15 +/-5 14 +/-5 10 +/- 5 19 +/- 5 21 +/- 5 13 +/- 5<7 10 16 12 22< 6+/-4+/-5+/-5+/-5 H3-1 11 +/-5 17 +/-6 13 +/-5 19 +/-6 19 +/-5 17 +/-5 25 +/- 5 21 +/- 5 25 +/- 6 14 +/- 5 18 +/- 5 17 +/- 5 12 +/- 5 12 +/- 5 14 +/- 5 16 +/- 5 14 +/- 5 24 +/- 6 10 +/- 5 14 +/-5 11 +/-5 15 +/-5 15 +/-5 14 +/-5 12 +/-5 24 +/-6 23 +/-6 17 +/-5 19 +/-6 15 +/-5 14 +/-6 29 +/-6 19 +/-6 23 +/-6 21 +/-6 26 +/-6 14 +/-5 20 +/-5 18 +/- 6 23 +/- 6 21 +/- 6 15 +/- 5 26 +/- 5 18 +/- 5 8+/-3 22 +/-5 23 +/-6 26 +/-6 30 +/-6 15 +/-6 29 +/-6 15 +/-5 18 +/-6 M2-1 20 +/- 5 18 +/- 6 15 +/- 5 24 +/- 6 16 +/- 5 19 +/- 5 22 +/-5 20 +/-5 18 +/-6 13 +/- 5 15 +/- 5 20 +/- 5 16 +/- 5 10 +/- 5 15 +/- 5 19 +/- 5 17 +/- 5 22 +/- 6 8 +/-4 12 +/- 5 14 +/- 5 10 +/- 4 13 +/- 5 17 +/- 5 10 +/- 4 15 +/- 5 27 +/- 6 13 +/- 5 20 +/- 5 16 +/- 5 17 +/- 6 24 +/- 6 20 +/- 6 21 +/- 6 24 +/- 6 30 +/- 6 14 +/- 5 19 +/- 5 18 +/- 6 23 +/- 6 22 +/- 6 14 +/- 5 23 +/- 5 21 +/- 5 9+/-3 25 +/-5 26 +/-6 26 +/-6 26 +/-5 16 +/-6 27 +/-6 13 +/-4 32 +/-7 GROUP III 18 5-18 +/- 6 16 +/- 5 19 +/-6 16 +/-5 15 +/-5 27 +/-6 22 +/-5 19 +/-6 12 +/- 5 17 +/- 5 21 +/- 5 19 +/- 5 9+/-5 14 +/-5 19 +/-5 19 +/-5 25 +/-6<6 12 +/- 5 15 +/- 6 15 +/- 5 12 +/- 5 17 +/- 5 15 +/- 5 25 +/- 5 28 +/- 6 17 +/- 5 21 +/- 5 13 +/- 5 15 +/- 6 24 +/- 6 16 +/- 5 24 +/- 6 19 +/- 5 31 +/- 6 17 +/- 5 17 +/- 5 16 +/- 5 26 +/- 6 20 +/- 6 16 +/- 5 28 +/- 5 20 +/- 5 9+/-3 29 +/-6 28 +/-6 24 +/-5 31 +/-6 17 +/- 6 23 +/- 6 16 +/- 5 19 +/- 6 I MEAN* 17 +/- 11 18 +/- 12 18 +/- 11 18 +/- 11 18 +/- 11 18 +/- 11 19 +/- 11 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION 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, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I -CLOSEST TO THE SITE BOUNDARY GROUP II -INTERMEDIATE OFFSITE GROUP III -CONTROL LOCATIONS COLLECTION PERIOD 12/28/11 -02/01/12 02/01/12 -02/29/12 02/29/12 -03/28/12 03/28/12 -05/02/12 05/02/12 -05/30/12 05/30/12 -06/27/12 06/27/12 -08/01/12 08/01/12 -08/29/12 08/29/12 -10/03/12 10/03/12 -10/31/12 10/31112 -11/20/12-11/20/12 01/02/13 MIN 10 13 10 9 10 6 9 15 12 11 6 14 MAX 22 22 21 24 17 19 23 28 33 28 29 27 MEAN +/-2SD 17 +/- 7 16 +/- 5 15 +/- 7 16 +/- 10 13 +/- 6 13 +/- 8 15 +/- 8 24 +/- 9 20 +/- 13 20 +/- 12 19 +/- 20 20 +/- 9 COLLECTION PERIOD 12/28/11 02/01/12 02/29/12 03/28/12 05/02/12 05/30/12 06/27/12 08/01/12 08/29/12 10/03/12 10/31/12 11/20/12-02/01/12-02/29/12-03/28/12-05/02/12-05/30/12-06/27/12-08/01/12-08/29/12-10/03/12-10/31/12-11/20/12-01/02/13 MIN 11 14 10 10 8 10 11 14 13 9 7 13 MAX 24 25 21 25 17 24 27 29 32 28 28 32 MEAN +/-2SD 17 +/- 6 19 +/- 7 16 +/- 6 16 +/- 9 12 +/- 5 15 +/- 9 18 +/- 9 22 +/- 8 20 +/- 11 20 +/- 10 20 +/- 17 21 +/- 12 COLLECTION PERIOD 12/28/11 02/01/12 02/29112 03/28/12 05/09/12 05/30/12 06/27/12 08/01/12 08/29/12 10/03/12 10/31/12 11/20/12 02/01/12 02/29/12 03/28/12 05/02/12 05/30/12 06/27/12 08/01/12 08129/12 10/03/12 10131112 11/20/12 01/02/13 MIN 16 15 12 9 12 12 13 16 16 16 9 16 MAX 19 27 21 25 15 25 28 24 31 28 29 31 MEAN +/-2SD 18 +/- 3 21 +/- 10 17 +/- 8 17 +/- 12 14 +/- 3 17 +/- 11 19 + 12 21 +/-8 21 + 14 21 +/- 10 22 +/- 23 22 +/- 11 12/28/11 -01/02/13 6 33 18 +/- 11 12/28/11 -01/02/13 7 32 18 +/- 11 12/28/11 -01/02/13 9 31 19 +/- 11* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES TABLE C-VI.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE A3-1 COLLECTION PERIOD 12/28/11 -03/28/12 03/28/12 -06/27/12 10/03/12 -01102/13 06/27/12 -10/03/12 MEAN*Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs- 137 93 1 28 88 +/- 25 58 +/- 21<91 E1-2 12/28/11 03/28/12 10/03/12 06/27/12 MEAN Fl-3 12/28/11 03/28/12 10/03/12 06/27/12 MEAN 03/28/12 06/27/12 01/02/13 10/03/12 03/28/12 06/27/12 01/02/13 10/03/12 03/28/12 06/27/12 01/02/13 10/03/12 03/28/12 06/27/12 01/02/13 10/03/12 80 +/- 38 70 +/- 31 63 +/- 37 52 +/- 20 81 +/- 39 67 +/- 24 58 +/- 28 78 +/- 24 53 +/- 21 78 + 57 67 +/- 27 52 +/- 17 63 +/- 39 52 +/- 27 134 +/- 92 75 +/- 79<3<2<3<4<3<3<3<3<3<3<2<2<2<4<4<3<4<3<3<3 G2-1 12/28/11 -03/28/12 -10/03/12 -06/27/12 -<3<3<2<8<3<4<3<6<3<4<3<5<3<4<4<7<3<5<3<6<4<5<3<9<4<4<4<6<3<2<2<3<3<4<3<3<3<3<3<4<3<4<4<3<2<4<2<4<3<3<3<4<4<5<3<3<3<3<3<9<3<5<5<9<3<4<3<6<3<4<5<9<4<5<2<7<6 <3<5 <3<5 <2<12 <4<7<7<7< 15<4<7<6<12<6<9<8< 14<2<3<3<4<3<3<3<3<2<4<4<3<2<2<3<4<3<3<3<3<2<3<2<3<2<3<4<2<2<3<2<2<4<3<3<4<3<4<3<2 MEAN H3-1 12/28/11 03/28/12 10/03/12 06/27/12 54 +/- 26 96 +/- 35 71 +/- 35< 77<7 <3<8 <3<3 <2<14 <3 MEAN*74 +/- 42 -M2-1 12/28/11 03/28/12 10/03/12 06/27/12 MEAN*-03/28/12-06/27/12-01/02/13-10/03/12-03/28/12-06127/12-01/02/13-10/03/12 69 +/- 36 81 +/- 32 63 +/- 26< 93<4<3<3<4 71 +/- 18 -<4 <9 <4<4 <6 <3<4 <7 <3<10 <16 <5<4 <8 <3<5 <10 <4<4 <6 <3<7 <9 <3 Q15-1 12/28/11 03/28/12 10/03/12 06/27/12 97 +/- 35 72 +/- 28 54 +/- 27 72 +/- 33 74 +/- 35<3<4<3<3 MEAN* THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-13 TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I IGROUP 11 GROUP III PERIOD E11-2 F11-3 A3-1 G2-11 H3-1 M2-11 Q15-1 12/28/11 -01/04/12

< 56 < 57 < 60 < 55 < 57 < 58 < 61 01/04/12 -01/11/12

< 29 < 30 < 31 < 18 < 30 < 30 < 31 01/11/12 -01/18/12

< 31 < 31 < 41 < 30 < 31 < 40 < 42 01/18/12 -01/25/12

< 46 < 47 < 62 < 45 < 26 < 60 < 62 01/25/12 -02/01/12

< 35 < 36 < 26 < 35 < 36 < 25 < 26 02/01/12 -02/08/12

< 39 < 40 < 25 < 38 < 25 < 15 < 25 02/08/12 -02/15/12

< 55 < 56 < 52 < 53 < 56 < 49 < 52 02/15/12 -02/22/12 (1) < 48 < 35 < 49 < 34 < 49 < 47 < 19 02/22/12-02/29/12

< 37 < 38 < 35 < 37 < 38 < 33 < 35 02/29/12 -03/07/12

< 48 < 49 < 24 < 47 < 62 < <60 < 63 03/07/12-03/14/12

< 38 < 38 < 34 < 36 < 38 < 33 < 34 03/14/12 -03/21/12

< 32 < 32 < 41 < 31 < 32 < 40 < 42 03/21/12 -03/28/12

< 49 < 50 < 46 < 48 < 49 < 44 < 46 03/28/12 -04/04/12

< 12 < 32 < 45 < 31 < 32 < 43 < 45 04/04/12 -04/11/12

< 29 < 30 < 21 < 28 < 30 < 20 < 21 04/11/12 -04/18/12

< 56 < 57 < 40 < 21 < 57 < 38 < 40 04/18/12 -04/25/12

< 54 < 56 < 47 < 53 < 55 < 45 < 47 04/25/12 -05/02/12

< 43 < 44 < 38 < 42 < 17 < 37 < 39 05/02/12 -05/09/12

< 47 < 48 < 43 < 46 < 47 < 41 < 42 05/09/12 -05/16/12

< 60 < 61 < 43 < 58 < 41 < 22 < 42 05/16/12 -05/22/12

< 61 < 62 < 52 < 59 < 62 < 49 < 51 05/22/12 -05/30/12

< 61 < 62 < 64 < 60 < 66 < 61 < 27 05/30/12 -06/06/12

< 53 < 55 < 54 < 52 < 54 < 52 < 54 06/06/12 -06/13/12

< 37 < 37 < 20 < 36 < 51 < 48 < 51 06/13/12 -06/20/12

< 57 (1) < 49 < 56 < 58 < 47 < 49 06/20/12 -06/27/12

< <31 < 60 < 66 < 59 < 61 <.66 < 65 06/27/12 -07/04/12

< 38 < 37 < 43 < 38 < 39 < 44 < 43 07/04/12 -07/11/12

< 67 < 65 < 68 < 29 < 68 < 68 < 67 07/11/12 -07/18/12

< 40 < 39 < 33 < 39 < 40 < 34 < 33 07/18/12 -07/25/12 (1) < 48 < 47 < 47 < 48 < 20 < 47 < 45 07/25/12 -08/01/12

< 51 < 49 < 55 < 54 < 51 < 58 < 55 08/01/12 -08/08/12 (1) < 36 < 35 < 38 < 37 < 40 < <40 < 16.08/08/12 -08/15/12

< 47 < 45 < 29 < 46 < 47 < 29 < 29 08/15/12 -08/22/12

< 34 < 33 < 21 < 33 < 56 < 54 < 53 08/22/12 -08/29/12

< 39 < 38 < 24 < 38 < 39 < 25 < 24 08/29/12 -09/05/12

< 44 < 17 < 30 < 43 < 45 < 30 < 30 09/05/12 -09/12/12

< 29 < 28 < 24 < 28 < 29 < 23 < 23 09/12/12 -09/19/12

< 22 < 37 < 58 < 37 < 38 < 58 < 57 09/19/12 -09/26/12 (1) < 57 < 56 < 45 < 56 < 58 < 44 < 42 09/26/12 -10/03/12

< 35 < 34 < 30 < 18 < 35 < 30 < 30 10/03/12 -10/10/12

< 60 < 59 < 64 < 59 < 61 < 65 < 63 10/10/12 -10/17/12

< 37 < 36 < 27 < 37 < 16 < 26 < 26 10/17/12 -10/24/12

< 11 < 10 < 15 < 10 < 11 < 15 < 15 10/24/12 -10/31/12

< 38 < 37 < 36 < 38 < 37 < 13 < 36 10/31/12 -11/07/12

< 29 < 28 < 25 < 29 < 29 < 25 < 25 11/07/12 -11/14/12

< 29 < 28 < 34 < 28 < 35 < 34 < 14 11/14/12 -11/20/12

< 65 < 64 < 69 < 64 < 65 < 66 < 68 11/20/12 -11/28/12

< 46 < 45 < 8 < 50 < 46 < 22 < 21 11/28/12-12/06/12

< 33 < 32 < 36 < 32 < 33 < 36 < 36 12/06/12 -12/12/12

< 61 < 23 < 65 < 60 < 62 < 65 < 64 12/12/12 -12/19/12

< 13 < 37 < 27 < 37 < 38 < 27 < 27 12/19/12 -12/27/12

< 47 < 44 < 53 < 45 < 46 < 53 < 52 12/27/12 -01/02/13

< 66 < 65 < 60 < 65 < 66 < 60 < 59 MEAN -------(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-i14 TABLE C-VIII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA CONTROL FARM K15-3 INDICATOR FARM COLLECTION PERIOD 01/04/12 02/01/12 03/07/12 03/21/12 04/04/12 04/18/12 05/02/12 05/16/12 05/30/12 06/13/12 06/27/12 07/11/12 07/25/12 08/08/12 08/22/12 09/05/12 09/19/12 10/03/12 10/17/12 10/31/12 11/14/12 11/28/12 12/12/12 E2-2 F4-1 G2-1 P4-1< 0.6< 0.6< 0.4< 0.4< 0.4< 0.4< 0.5< 0.5< 0.5< 0.6< 0.7< 0.6< 0.7< 0.5< 0.7< 0.6< 0.6< 0.8< 0.7< 0.9< 0.7< 0.7< 0.7< 0.6< 0.5< 0.5< 0.5< 0.3< 0.3< 0.5< 0.5< 0.6< 0.7< 0.8< 0.5< 0.6< 0.6< 0.7< 0.5< 0.6< 0.7< 0.8< 0.8< 0.9< 0.7< 0.8< 0.5< 0.5< 0.3< 0.3< 0.4< 0.3< 0.3< 0.4< 0.5< 0.6< 0.7< 0.5< 0.6< 0.5< 0.6< 0.6< 0.6< 0.8< 0.7< 0.8< 0.7< 0.8< 0.7< 0.6< 0.5< 0.4< 0.5< 0.3< 0.4< 0.5< 0.5< 0.6< 0.7< 0.7< 0.5< 0.7< 0.6< 0.7< 0.6< 0.6< 0.7< 0.8< 0.9< 0.8< 0.8< 0.7< 0.7< 0.5< 0.3< 0.5< 0.4< 0.4< 0.5< 0.4< 0.6< 0.6< 0.7< 0.5< 0.7< 0.5< 0.7< 0.6< 0.7< 0.7< 0.7< 0.7< 0.8< 0.8< 0.6 MEAN C-15 TABLE C-VIII.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA CONTROLFARM INDICATOR FARMS COLLECTION PERIOD K1 5-3 P4-1 E2-2 I F4-1 G2-1 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 01/04/12 -03/21/12 < 3.1 04104/12 -06/27/12 < 1.7< 0.6< 2.6 07/11/12 -09/19/12 10/03/12 -12/12/12< 1.6< 2.6< 0.7 < 1.8 1.1 +/- 0.2 < 1.5< 0.8 < 3.9< 0.6< 0.6< 0.9< 0.8< 3.1< 1.8< 1.7< 2.5< 0.6< 0.6< 0.9< 0.8< 3.0< 1.4< 1.6< 2.3< 1.0< 0.4< 2.6< 1.7< 0.6< 0.4< 0.8< 0.7 0.7 +/- 0.2 < 1.3< 0.8 < 2.4 MEAN i~

TABLE C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE E2-2 COLLECTION PERIOD 01/04/12 02/01/12 03/07/12 03/21/12 04/04/12 04/18/12 05/02/12 05/16/12 05/30/12 06/13/12 06/27/12 07/11/12 07/25/12 08/08/12 08/22/12 09/05/12 09/19/12 10/03/12 10/17/12 10/31/12 11/14/12 11/28/12 12/12/12 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1376 +/- 117 1287 +/- 121 1353 +/- 114 1210 +/- 123 1329 +/- 157 1186 +/- 152 1354 +/- 160 1230 +/- 151 1218 +/- 168 1449 +/- 146 1206 +/- 132 1319 +/- 199 1353 +/- 158 1263 +/- 142 1332 +/- 180 1237 +/- 111 1218 +/- 133 1444 +/- 183 1356 +/- 153 1287 +/- 171 1369 +/- 140 1150 +/- 184 1212 +/- 125 1293 +/- 165 1333 +/- 130 1302 +/- 144 1457 +/- 136 1375 +/- 125 1347 +/- 154 1498 +/- 161 1349 +/- 134 1401 +/- 161 1547 +/- 218 1389 +/- 151 1357 +/- 130 1451 +/- 166 1364 +/- 192 1379 +/- 129 1299 +/- 164 1345 +/- 89 1439 +/- 146 1450 +/- 199 1464 +/- 127 1435 +/- 165 1453 +/- 174 1403 +/- 159 1413 +/- 159 1402 +/- 125<4<5<4<5<6<6<7<6<5<5<4<6<5<5<6<4<5<6<4<7<5<6<3<6<6<5<3<4<6<5<7<6<6<5<5<5<5<8<4<4<6<4<5<6<6<6<5<5<5<6<6<7<6<7<7<6<5<6<8<6<9<5<5<6<5<7<5<7<4<6<6<6<4<5<-7<6<9<7<6<6<6<5<6< 10<4<5<8<5<6<7<6<6< 25< 20< 21< 25< 32< 38< 29< 30< 25< 27< 41< 32< 30< 29< 44< 20< 27< 33< 21< 39< 22< 40< 16< 29< 26< 28< 16< 20< 46< 28< 36.< 40< 28< 56< 28< 23< 26< 40< 20< 21< 38< 22< 29< 28< 33< 28<8<7<7<7<9< 10<9<8<8<7< 14< 13< 11<8<8<5<9< 14<7<8<8<8<3<7<6<7<5-<7< 13<7< 10<9< 10< 12<8<9<6<8<6<8< 12<7<8<6<9<8 F4-1 01/04/12 02/01/12 03/07/12 03/21/12 04/04/12 04/18/12 05/02/12 05/16/12 05/30/12 06/13/12 06/27/12 07/11/12 07/25/12 08/08/12 08/22/12 09/05/12 09/19/12 10/03/12 10/17/12 10/31/12 11/14/12 11/28/12 12/12/12 MEAN C-17 TABLE C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE G2-1 COLLECTION PERIOD 01/04/12 02/01/12 03/07/12 03/21/12 04/04/12 04/18/12 05/02/12 05/16/12 05/30/12 06/13/12 06/27/12 07/11/12 07/25/12 08/08/12 08/22/12 09/05/12 09/19/12 10/03/12 10/17/12 10/31/12 11/14/12 11/28/12 12/12/12 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1187 +/-1193 +/-983 +/-1165 +/-855 +/-863 +/-841 +/-1318 +/-1259 +/-1342 +/-841 +/-699 +/-1058 +/-1267 +/-623 +/-986 +/-841 +/-967 +/-1261 +/-631 +/-890 +/-868 +/-752 +/-152 104 154 124 144 101 116 168 144 128 111 107 127 155 141 89 94 150 127 144 136 113 141 987 +/- 447<6<5<4<5<7<3<6<8<7<5<5<4<5<5<6<4<4<8<5<7<5<7<6<5<5<5<4<6<6< 10<8<6<5<3<5<5<4<6<5<4<8<7<8<4<9<5<6<5<5<6<8<3<6<6<6<6<5<5<7<7<8<4<5<9<6<7<6<6<6<7<6<6<4<6<6<9< 10<6<6<4<5<5<5<7<6<5<8<8<8<5< 10<6< 33< 22< 23< 25< 38< 21< 28< 32< 27< 24< 47< 24< 27< 33< 32< 23< 21< 41< 25< 32< 28< 39< 30< 31< 25< 26< 21< 31< 39< 33< 40< 27< 29< 38< 25< 28< 26< 30< 22< 24< 39< 38< 35< 23< 50< 26<8"<7<9<7< 13<6<9<9<8<7< 14<7<9< 10< 10<7<8< 13<7< 11< 11< 11<9< 10<8<8<7<9< 10<8< 14<6<7< 14<7<5<7<6<8<6< 13< 12<7<6<9<8 K15-3 01/04/12 02/01/12 03/07/12 03/21/12 04/04/12 04/18/12 05/02/12 05/16/12 05/30/12 06/13/12 06/27/12 07/11/12 07/25/12 08/08/12 08/22/12 09/05/12 09/19/12 10/03/12 10/17/12 10/31/12 11/14/12 11/28/12 12/12/12 1308 +/-1296 +/-1385 +/-1324 +/-1316 +/-1438 +/-1330 +/-1597 +/-1377 +/-1355 +/-1269 +/-1447 +/-1259 +/-1241 +/-1021 +/-1239 +/-1263 +/-1186 +/-1254 +/-1255 +/-1148 +/-1304 +/-1268 +/-134 145 143 104 140 170 131 183 159 141 153 132 138 148 173 118 105 163 138 158 118 172 125 MEAN 1299 +/- 224 C-18 TABLE C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER t 2 SIGMA SITE COLLECTION PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 P4-1 01/04/12 02/01/12 03/07/12 03/21/12 04/04/12 04/18/12 05/02/12 05/16/12 05/30/12 06/13/12 06/27/12 07/11/12 07/25/12 08/08/12 08/22/12 09/05/12 09/19/12 10/03/12 10/17/12 10/31/12 11/14/12 11/28/12 12/12/12 1482 +/- 150 1443 +/- 125 1549 +/- 155 1654 +/- 130 1426 +/- 152 1414 +/- 171 1550 +/- 165 1516 +/- 150 1328 +/- 144 1298 +/- 156 1575+/- 119 1379 +/- 137 1231 +/- 162 1574 +/- 143 1659 +/- 205 1567 +/- 122 1216 +/- 149 1254 +/- 207 1438 +/- 115 1119 +/- 218 1255 +/- 102 1313 +/- 149 1296 +/- 148 1415 +/- 302<5<4<5<5< 5.5< 4.8< 8.9<6<5<4< 4.6<5<8<5<7<4<6<5<5<6<4<6<5<6<5<6<5<7<6<9<7<6<5<5<5<8<6<9<4<6<9<5<6<4<8<7< 26< 20< 34< 22< 28< 30< 41< 30< 24< 24< 35< 29< 34< 25< 31< 19< 31< 42< 24< 31< 19< 40< 28<8<5< 11<6< 6.7< 9.3< 13<9<3<5< 14<6< 11<7< 10<8< 10< 11<6< 11<4<8<8 MEAN 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, 2012 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA COLLECTION PERIOD B10-2 06/26/12 06/26/12 06/26/12 07/17/12 07/17/12 07/31/12 07/31/12 07/31/12 07/31/12 07/31/12 08/28/12 08/28/12 08/28/12 09/26/12 09/26/12 09/26/12 TYPE Sr-90 Be-7 K-40 1-131 Cs-134 Cs-137 Broccoli Leaves Green Cabbage Sunflower Leaves Cabbage Red Beets Green Cabbage Red Beet Leaves Sunflower Leaves Sweet Corn Tomatoes Pumpkin Leaves Red Beet Leaves Sunflower Leaves Pumpkin Leaves Squash Leaves Sunflower Leaves< 4 179 +/- 63<3 <75< 2 598 +/- 95< 2 <48< 33< 4 284 +/- 150 7 +/- 4 907 +/- 253 5 +/- 4 874 +/- 209< 181< 145 4 +/- 2 3729 +/- 282 5 +/- 2 1148 +/- 189< 2 1016 +/- 115< 3 2657 +/- 331< 3 5459 +/- 184< 3 2380 +/- 262 5380 3273 8952 2616 3215 2966 7013 5534 1894 2101 7248 8333 6833 4867 6750 7510+/- 169+/- 172+/- 276+/- 132+/- 142+/- 443+/- 683+/- 596+/- 378+/- 341+/- 420+/- 496+/- 320+/- 551+/- 254+/- 522* 31* 32* 27* 12<7* 25< 46< 33* 32* 23* 31< 39* 24<56< 42< 60<7<7<6<5<4< 18< 28< 20< 25< 16< 14<19< 11< 15< 12< 17<7<7<7<5<4< 21< 32< 20< 22< 19< 15< 20< 13< 18< 12< 18 MEAN*5 +/- 3 1748 +/- 3300 5280 +/- 4670 E1-2 07/17/12 07/17/12 07/31/12 07/31/12 Cabbage Red Beets Sweet Corn Tomatoes< 3 75 89 151 137 2903 4823 2628 2590+/- 179+/- 257+/- 350+/- 434 18 18 27 31<8<9< 16< 17<9< 10< 17< 24 MEAN 3236 +/- 2134 H1-2 06/26/12 06/26/12 06/26/12 07/31/12 07/31/12 07/31/12 08/28/12 08/28/12 08/28/12 09/26/12 09/26/12 09/26/12 Eggplant Leaves < 2 Yellow Squash Leaves Zucchini Leaves < 3 Eggplant Leaves Squash Leaves Zucchini Leaves Eggplant Leaves < 3 Pumpkin Leaves Squash Leaves < 3 Squash Leaves < 3 Turnip Greens < 3 Zucchini Leaves < 3 6+/-2 4+/-2 5+/-3 6+/-4 7+/-2 528 495 427 1595 848 587 2644 1620 867 813 208 402+/- 73+/- 76+/- 62+/- 296+/- 283+/- 258+/- 336+/- 158+/- 123+/- 227+/- 117+/- 147 7721 5103 5403 5901 5185 3975 3353 5152 4784 4422 4822 4011+/- 207+/- 170+/- 155+/- 626+/- 573+/- 541+/- 481+/- 319+/- 340+/- 481+/- 401+/- 380< 32< 27< 26< 35< 39< 37< 48< 27< 28< 55< 44< 56<6<5<6< 22< 22< 26< 20< 12< 14< 17< 13< 16<7<6<6< 27< 27< 28< 21< 14< 15< 18< 13< 21 MEAN* 6 +/- 2 920 +/- 1401 4986 +/- 2224 -* 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, 2012 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER STATION MEAN JAN -MAR APR -JUN JUL -SEP OCT -DEC CODE +/- 2 S.D.A1-4 17.3 +/- 4.0 16.2 +/- 0.0 20.2 +/- 0.3 17.0 +/- 0.8 15.7 +/- 0.3 A3-1 17.2 +/- 4.4 15.0 +/- 0.0 20.1 +/- 1.9 17.5 +/- 1.0 16.1 +/- 1.5 A5-1 20.6 +/- 4.0 19.3 +/- 0.0 23.4 +/- 1.1 20.6 +/- 2.8 19.1 +/- 0.3 A9-3 17.7 +/- 5.2 15.0 +/- 0.0 21.0 +/- 0.1 18.5 +/- 0.2 16.4 +/- 0.0 61-1 17.4 +/- 4.9 15.6 +/- 0.0 20.8 +/- 0.4 17.6 +/- 0.7 15.6 +/- 1.3 B1-2 18.6 +/- 4.6 16.3 +/- 0.0 21.1 +/- 2.1 20.0 +/- 0.7 17.1 +/- 0.1 62-1 17.7 +/- 3.9 16.5 +/- 0.0 20.3 +/- 1.3 18.0 +/- 1.1 16.0 +/- 0.4 65-1 19.6 +/- 5.2 18.7 1.4 22.7 +/- 1.2 20.3 +/- 1.5 16.6 +/- 2.1 Cl-i 19.8 +/- 4.1 18.9 +/- 1.4 22.7 +/- 1.1 19.7 +/- 0.1 17.9 +/- 1.4 C1-2 17.2 +/- 5.1 16.2 +/- 0.0 20.8 +/- 0.9 17.0 +/- 0.5 14.9 +/- 0.2 C2-1 19.0 +/- 3.4 18.4 +/- 0.0 21.4 +/- 1.5 18.9 +/- 0.2 17.4 +/- 0.3 C5-1 19.6 +/- 5.6 16.8 +/- 7.1 23.0 +/- 7.2 20.6 +/- 2.1 17.8 +/- 3.8 C8-1 21.1 +/- 6.1 18.7 +/- 1.4 25.5 +/- 1.9 20.4 +/- 0.7 19.6 +/- 0.7 D1-1 18.8 +/- 5.0 17.0 +/- 7.1 22.4 +/- 2.2 18.7 +/- 1.4 17.2 +/- 0.3 D1-2 18.5 +/- 5.0 17.6 +/- 7.1 21.8 +/- 1.7 18.8 +/- 1.8 15.8 +/- 3.0 D2-2 22.9 +/- 6.7 20.4 +/- 1.4 27.7 +/- 2.1 22.7 +/- 2.4 20.8 +/- 1.3 D6-1 22.6 +/- 5.3 20.7 +/- 0.0 26.3 +/- 0.3 22.6 +/- 2.3 20.6 +/- 1.3 E1-2 18.3 +/- 4.9 17.0 +/- 0.0 21.9 +/- 0.8 17.9 +/- 0.4 16.5 +/- 0.6 E1-4 23.2 +/- 7.5 24.3 +/- 0.0 27.7 +/- 0.1 21.6 +/- 0.5 19.0 +/- 3.7 E2-3 20.7 +/- 8.2 17.9 +/- 0.0 26.3 +/- 1.8 21.1 +/- 0.3 17.3 +/- 1.5 E5-1 20.4 +/- 4.3 18.8 +/- 1.4 23.3 +/- 0.1 20.6 +/- 1.2 18.7 +/- 0.6 E7-1 20.7 +/- 6.0 18.7 +/- 9.9 25.0 +/- 0.4 20.4 +/- 0.5 18.6 +/- 0.6 F1-1 22.6 +/- 7.1 17.7 +/- 0.0 23.7 +/- 1.4 26.1 +/- 2.9 22.9 +/- 4.5 F1-2 27.0 +/- 11 28.2 +/- 2.8 34.5 +/- 0.5 23.5 +/- 0.1 21.8 +/- 3.5 F1-4 25.7 +/- 9.6 25.0 +/- 8.5 32.6 +/- 3.2 22.9 +/- 1.4 22.1 +/- 0.5 F2-1 22.0 +/- 6.3 19.4 +/- 1.4 26.6 +/- 0.2 21.5 +/- 2.7 20.6 +/- 1.3 F5-1 23.0 +/- 6.0 20.7 +/- 1.4 27.3 +/- 0.4 22.6 +/- 1.7 21.3 +/- 0.0 G1-2 20.7 +/- 4.6 18.3 +/- 0.0 23.4 +/- 2.9 21.6 +/- 0.2 19.4 +/- 5.1 Gi-3 21.6 +/- 11 24.3 +/- 1.4 28.3 +/- 2.3 18.2 +/- 0.4 15.7 +/- 0.5 G1-5 19.2 +/- 3.9 17.0 +/- 0.0 21.4 +/- 2.4 20.1 +/- 1.3 18.2 +/- 0.0 G1-6 23.0 +/- 3.9 20.2 +/- 4.2 23.4 +/- 0.0 24.2 +/- 1.4 24.3 +/- 2.1 G2-4 24.1 +/- 8.0 21.6 +/- 1.4 29.9 +/- 5.6 23.7 +/- 0.5 21.2 +/- 1.4 G5-1 20.2 +/- 6.9 18.2 +/- 0.0 25.3 +/- 0.8 19.5 +/- 0.4 17.9 +/- 1.2 H1-1 20.1 +/- 7.7 17.8 +/- 7.1 25.7 +/- 0.1 19.5 +/- 1.8 17.4 +/- 0.3 H3-1 16.5 +/- 4.7 14.9 +/- 0.0 19.7 +/- 0.8 16.6 +/- 0.3 14.6 +/- 0.6 H5-1 15.4 +/- 3.0 14.7 +/- 0.0 17.2 +/- 0.2 15.9 +/- 0.3 13.7 +/- 0.3 H8-1 29.8 +/- 7.0 27.7 +/- 1.4 35.0 +/- 3.3 28.5 +/- 1.9 28.0 +/- 0.7 J1-1 17.7 +/- 4.6 16.4 +/- 0.0 20.8 +/- 1.9 17.9 +/- 0.6 15.5 +/- 1.2 J1-3 15.2 +/- 5.1 14.4 +/- 0.0 18.0 +/- 2.7 16.3 +/- 1.0 12.1 +/- 0.8 J3-1 19.4 +/- 5.1 17.6 +/- 7.1 22.7 +/- 1.3 19.9 +/- 0.4 17.2 +/- 0.8 J5-1 21.5 +/- 6.3 19.6 +/- 1.4 25.5 +/- 1.8 22.3 +/- 0.4 18.4 +/- 3.0 J7-1 21.4 +/- 6.2 18.9 +/- 2.8 25.9 +/- 2.2 20.1 +/- 3.1 20.6 +/- 0.3 K1-4 18.1 +/- 4.2 17.1 +/- 7.1 20.9 +/- 0.2 18.4 +/- 0.7 16.1 +/- 1.0 K2-1 21.9 +/- 6.0 19.5 +/- 1.4 26.2 +/- 1.3 21.6 +/- 1.1 20.3 +/- 0.8 K3-1 17.9 +/- 6.1 15.9 +/- 0.0 22.3 +/- 2.5 17.8 +/- 1.4 15.7 +/- 0.0 K5-1 21.6 +/- 6.5 19.4 +/- 0.0 26.3 +/- 3.6 21.2 +/- 1.9 19.4 +/- 0.0 K8-1 20.1 +/- 3.6 19.2 +/- 1.4 22.5 +/- 4.5 20.3 +/- 1.7 18.4 +/- 0.5 C-21 TABLE C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER STATION CODE LI-1 L1-2 L2-1 L5-1 L8-1 Mi-i Mi1-2 M2-1 M5-1 M9-1 Ni-i N11-3 N2-1 N5-1 N8-1 P1-i P1-2 P2-1 P5-1 P8-1 Q1-1 Q1-2 Q2-1 Q5-1 09-1 Ri-i R1i-2 R3-1 R5-1 R9-1 B10-1 D15-1 F10-1 F25-1 G10-1 G15-1 H15-1 J15-1 L15-1 N15-2 Q15-1 R15-1 MEAN+/- 2 S.D.18.8 +/- 5.1 18.4 +/- 4.8 19.6 +/- 4.3 18.4 +/- 4.7 19.4 +/- 7.2 16.1 +/- 3.5 19.1 +/- 4.4 17.3 +/- 4.7 19.2 +/- 4.4 24.1 +/- 6.9 18.8 +/- 5.3 17.5 +/- 2.6 20.1 +/- 4.8 16.5 +/- 5.0 20.5 +/- 5.3 18.7 +/- 5.2 18.7 +/- 4.6 22.2 +/- 5.5 19.9 +/- 5.0 16.6 +/- 4.6 18.7 +/- 5.6 15.6 +/- 4.5 16.8 +/- 3.0 18.2 +/- 4.6 18.8 +/- 4.9 16.3 +/- 5.0 17.6 +/- 4.7 22.4 +/- 6.4 21.4 +/- 6.2 20.7 +/- 6.5 18.5 +/- 6.8 20.1 +/- 4.7 21.5 +/- 9.8 21.3 +/- 5.7 24.2 +/- 13 26.5 +/- 5.9 21.0 +/- 5.8 22.7 +/- 5.7 19.5 +/- 6.2 21.5 +/- 5.2 21.2 +/- 4.6 19.2 +/- 4.7 JAN-MAR APR-JUN JUL-SEP OCT-DEC 17.1 +/- 0.0 17.1 +/- 0.0 18.1 +/- 0.0 17.4 +/- 0.0 17.1 +/- 7.1 14.9 +/- 0.0 17.3 +/- 7.1 16.3 +/- 0.0 18.4 +/- 0.0 22.1 +/- 0.0 17.0 +/- 7.1 15.9 +/- 0.0 19.5 +/- 1.4 15.1 +/- 0.0 18.6 +/- 1.4 16.8 +/- 0.0 16.2 +/- 0.0 20.8 +/- 2.8 18.7 +/- 1.4 15.2 +/- 0.0 16.4 +/- 0.0 14.1 +/- 0.0 15.8 +/- 0.0 16.8 +/- 0.0 17.4 +/- 7.1 15.4 +/- 0.0 16.6 +/- 7.1 20.1 +/- 0.0 19.1 +/- 0.0 18.5 +/- 1.4 17.5 +/- 8.5 18.5 +/- 1.4 20.2 +/- 2.8 18.7 +/- 1.4 24.2 +/- 2.8 22.6 +/- 1.4 19.2 +/- 0.0 21.1 +/- 0.0 17.0 +/- 7.1 19.7 +/- 1.4 19.8 +/- 2.8 18.2 +/- 1.4 22.3 +/- 3.5 21.9 +/- 0.2 22.5 +/- 0.2 21.7 +/- 3.1 24.4 +/- 2.7 18.4 +/- 2.1 21.7 +/- 3.5 20.5 +/- 1.4 22.4 +/- 0.7 29.1 +/- 1.6 22.5 +/- 2.3 19.0 +/- 4.4 23.3 +/- 0.8 19.9 +/- 1.1 24.3 +/- 1.9 22.4 +/- 2.1 21.2 +/- 3.7 25.9 +/- 2.1 23.4 +/- 1.7 19.6 + 2.9 22.3 +/- 0.2 18.8 +/- 0.8 17.8 +/- 3.4 21.2 +/- 1.5 22.3 +/- 0.2 19.3 +/- 0.1 20.8 +/- 0.7 27.0 +/- 2.7 25.9 +/- 2.8 25.2 +/- 0.8 23.4 +/- 0.2 23.5 +/- 0.0 28.6 +/- 0.7 25.2 +/- 3.1 33.4 +/- 0.7 29.8 +/- 0.9 25.3 +/- 1.4 26.9 +/- 0.4 23.9 +/- 0.8 25.2 +/- 1.0 24.5 +/- 1.6 22.6 +/- 0.3 18.9 +/- 0.3 18.2 +/- 1.9 20.0 +/- 1.9 18.4 +/- 0.6 19.6 +/- 1.8 16.4 +/- 0.1 20.1 +/- 1.8 17.2 +/- 2.0 18.8 +/- 0.3 23.5 +/- 1.4 19.0 +/- 0.7 17.2 +/- 0.4 19.9 +/- 1.2 16.9 +/- 1.4 20.4 +/- 0.1 18.5 +/- 0.4 17.4 +/- 1.2 22.6 +/- 0.9 19.8 +/- 1.9 17.1 +/- 1.5 19.6 +/- 0.9 15.7 +/- 0.3 18.3 +/- 1.8 18.7 +/- 0.0 18.3 +/- 0.1 16.9 +/- 0.7 17.6 +/- 1.0 21.9 +/- 1.4 20.8 +/- 0.8 20.8 +/- 0.5 17.7 +/- 0.3 19.7 +/- 1.0 19.4 +/- 1.0 21.5 +/- 1.3 21.0 +/- 0.6 26.9 +/- 0.1 20.3 +/- 0.2 21.8 +/- 0.3 19.1 +/- 0.7 21.2 +/- 0.2 20.8 +/- 2.1 18.5 +/- 0.9 16.7 +/- 0.6 16.5 +/- 1.0 17.8 + 1.0 16.2 +/- 0.3 16.5 +/- 3.3 14.6 +/- 0.5 17.3 +/- 1.7 15.0 +/- 1.0 17.3 +/- 1.8 21.5 +/- 1.4 16.7 +/- 0.4 17.9 +/- 0.1 17.5 +/- 0.7 14.2 +/- 2.7 18.7 +/- 1.2 17.0 +/- 0.1 20.0 +/- 0.2 19.5 +/- 4.1 17.7 +/- 0.2 14.5 +/- 2.8 16.6 +/- 0.7 13.9 +/- 3.0 15.2 +/- 0.5 16.0 +/- 0.3 17.0 +/- 0.3 13.4 +/- 0.5 15.3 +/- 0.2 20.4 +/- 0.6 19.8 +/- 0.6 18.2 +/- 3.3 15.5 +/- 0.5 18.7 +/- 0.5 17.6 +/- 1.4 19.8 +/- 0.7 18.2 +/- 1.5 26.5 +/- 0.7 19.2 +/- 0.0 20.8 +/- 1.0 17.8 +/- 0.4 19.8 +/- 0.8 19.6 +/- 1.2 17.4 +/- 0.2 C-22 TABLE C-X.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER COLLECTION PERIOD SITE BOUNDARY+/- 2 S.D.INDICATOR CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 18.3 +/- 8.2 22.9 +/- 9.5 18.9 +/- 5.1 17.3 +/- 6.3 18.1 +/- 4.3 23.6 +/- 6.2 19.9 +/- 4.5 17.9 +/- 4.9 19.9 +/- 4.3 26.0 +/- 6.5 21.1 +/- 4.6 19.8 +/- 5.2 TABLE C-X.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER SAMPLES PERIOD PERIOD ANALYZED MINIMUM MAXIMUM PERIOD MEAN+/- 2 S.D.LOCATION SITE BOUNDARY INDICATOR CONTROL 76 12.1 240 13.7 40 17.0 34.5 35.0 33.4 19.4 +/- 8.5 19.9 +/- 6.8 21.7 +/- 7.2 SITE BOUNDARY STATIONS-A1-4, B1-2, Cl-2, D1-1, E1-4, Fl-2, F14, GI-3, G1-5, G1-6, H1-1, J1-3, K1-4, Li-1, Mi1-1, N1-3, P1-2, Q1-2, RI-i INDICATOR STATIONS -A3-1, A5-1, A9-3, B1-1, B10-1, B2-1, B5-1, Ci-1, C2-1, C5-1, C8-1, Di-2, D2-2, D6-1, E1-2, 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, J1-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, MI1-2, 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, L15-1, N15-2, Q15-1, R15-1 C-23 FIGURE C-I Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2012 oi Station J1-2 (Downstream of Discharge) u Station Q9-1 (Control)1 0 0 0 0 00 -.- .--------------------------------------------------------------------------------------------------------------------'q 10000 -------------

---

---

---

---

---

---

---

.-.-

---

.-

I n.1000 .... ... ... .0 ... .....d- u -F-- :.. 2...*10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month FIGURE C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2012 Indicator Samples--- Control Samples n)a-U, 0 0.U-12000 11000 10000 9000 8000 7000 6000 5000 4000 3000 2000 1000 0-1000 IT U) 0 Fl- w M 0- C\J("'M LO Cr- w O0 0- N M aC LO MDr- W M0. C; NM I ~U') 0 -M M ~ 0 ;: C2 M)0 0~ M) M) M M 0) 0) M 0) M M 0M 0M 0M 0M 0) M 0M 0) M) M M M) M) 0D 0 0 0D 0 0 0 0) 0D 0a-~ ~ ~ ~ ~ ~ ~~~~~~~~~" .-, -, -, -, -rr.~.r-r,.,r N( N( N N (N (N (N (N " 0 N (N Year FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2012 EJ Indicator Samples I Control Samples 0)-J a, 0~cn 0)=C., 0 C., a-10 9 8 7 6 5 4 3 2 1 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2012 NOTE: The mean values are calculated using both the MDCs and 51 Indicator Samples m Control Samples the positive values.500 500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L 5 400-o~300-0 100-0 ..........0 -Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month E Station K1-1 (TMINS Liquid Discharge) 1000000 100000 10000 --- -----U)1000 --- --0 100 C.)10" Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2012 Indicator Samples --- Control Samples 900 Significant Event Chemobyl April 19861 800-..,700 E 600 -.o 0 500 -L-Cn 400 -_----- -0) U300 2 0 0 -----...-----------. .-- -----.-- --------.-.- ---100 -- --,,- --__, .°.,_= -, --.. -_. / ------0 UO (0 r- CO M 0 0 -" M T , M 0 r -0 M 0 -CN M') ' LO ( D P- (O 0) 0 .- N (')oo OD 0o w w M ;3 c 0) 0 M M 0 0 M 0 0 0) 0)C 0 0 0 CD C 0) 0) 0') 0) 0) 0 ) 0 ) 0) 0) 0) 0 0) 0) 0 0 0 0 0 0 0 0 0 0 0 0 0'- -,- ,- --.- ,- -'N4 " N " N N , 04 4 N N Year FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2012--Indicator--- Control 0.4 0.35 t Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chernobyl April 1986 December 1978 October 1980 0.3-t 0.2 a_0.25-0.2 0.15-0.1 0.05 0 T-------------------------------------------------------------

-- --------------------------------------------------------

I Illlllllllllllllllllllll N C~) ~t U) CO t- CO N- N- N- N- N- N- N-0) 0) 0) 0) 0) 0) 0)(3)0C.-;N CV) 01 U) (D r--C000)0Crý;N CI) aCONC -000) 0 -NC Sf) (N- 000) CD;: S1 t- 00 00 00~ mo Co Co Mo wo ) 00)0) 0)0) 0) 0) 0)0 00 0 0()C0 0C)00- F 0) 0) 0) 07) 0) 0) 0) 03) 0) 03) 0) 0) 0) 0) 0) 0) 0) 0)M0) 0) 0 0 0 0 0 0 0 0 0 0 0 0: 0 0.Year FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 -2012 0.100*Indicator

-.- Control 0.090 0.080 0.070 0 0 .0 6 0 -- ------------------------------------0 o 0.050..000.040 -- ------------ -------------o T 0.000 0. 1 ------ ------- --- -------o oý 0 0) 0 0ý 0 0 0) 0 0= 03 0 C)C S( D60C )0 0 0 oR '- 0 0: 0n 0D 0 0 0 0 0 0 0D 0 0D I 0 0 0) 0 0 04 o 0 r-- -o o -0 Q (! (z Q Q o -Q 0,--" (O ) 0 0 U)O r- -- CN 0N " CO ,- I (0 -'- (M Go 0 (N LO f- -(N Month I Day / Year I ne high value on I I/24/2UU9 was caused by an airborne release on I 1/21/20U9 FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2012 Indicator Samples -.- Control Samples Significant Events Major Atm. Nuclear Weapon Tests TM1-2 Accident March 1979 December 1978 October 1980 TMI-2 RB Purge June 1980 Chernobyl April 1986 7 8----------------------------------------------------------------------------

.4--.. 6 I-.a)C--- ----0 -- -...... ...-- --- --- ---- --- --- --- ------- -----------------------------

2 -----* -t ---M~ 0 '- (N M' I f En rl- W O 0 ;; "N M) a L) (W t-. ( am) 0 M N ) ~ L) ( -( ) 0 ' (I 0 r-- oo 00 00 (W W W W W 0 0 )0 o ) 00))0 0 00 0C0 0 0 0 0 CD -o -o-)0) 0) 0) 0) 0) 0) 0) 0 0 00 0 0 0 0 0 Year Intentionally left blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY 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.D-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, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD Q9-1Q U I IU3I Iz 01/31/12 02/28/12 04/03/12 05/01/12 05/29/12 07/03/12 07/31/12 08/12/12 10/02/12 10/30/12 11/27/12 UI i13 iII 02/28/12 04/03/12 05/01/02 05/29/12 07/03/12 07/31/12 08/28/12 10/02/12 10/30/12 11/27/12 12/31/12 MEAN*< 0.b< 1.3< 0.8< 0.9< 0.8 1.5 +/- 0.7 1.6 +/- 0.9 2.1 +/- 1.0 2.0 +/- 0.9 1.0 +/- 0.3 2.4 +/- 1.0< 1.7 1.8 +/- 1.0 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD Q9-1Q UllIU3I2 01/31/12 02/28/12 04/03/12 05/01/12 05/29/12 07/03/12 07/31/12 08/28/12 10/02/12 10/30/12 11/27/12 U0,.11312 02/28/12 04/03/12 05/01/12 05/29/12 07/03/12 07/31/12 08/28/12 10/02/12 10/30/12 11/27/12 12/31/12 MEAN< 140< 141< 152* 157< 152< 141< 151< 150< 151< 152< 144< 144 TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD Q9-1Q 01/31/12 02/28/12 04/03/12 05/01/12 05/29/12 07/03/12 07/31/12 08/12/12 10/02/12 10/30/12 11/27/12-U01/31/1-02/28/12-04/03/12-05/01/12-05/29/12-07/03/12-07/31/12-08/28/12-10/02/12-10/30/12-11/27/12-12/31/12* U.b< 0.2< 0.5< 0.4< 0.3< 0.2< 0.3< 0.3< 0.3< 0.4< 0.2< 0.4 MEAN* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-3 TABLE D-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/LITER 12 SIGMA SITE COLLECTION PERIOD Q9-1Q 01/03/12 -01/31112 01/31/12 -02/28/12 02/28/12 -04/03/12 04/03/12 -05/01/12 05101/12 -05/29/12 05/29/12 -07/03/12 07/03/12 -07/31/12 07/31/12 -08/28/12 08/28/12 -10/02/12 10/02/12 -10/30/12 10/30/12 -11/27/12 11/27/12 -12/31/12 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<2<3<2< 1<2<3< 2<2<2<5<4<7<4<6<5<8<7<6<8<6<5<2<2<2<2<2<3<2<3<1<3<2<3<2<2<1<2<2<4<2<2<2<2<2<2<4<4<4<5<3<5<2<4<2<3<5<4<3<3<3<6<4<5<4<3<5<5<5<3<2<3<3<3<2<4<2<3<3<2<3<3<1<3<5<3<3<3<2<2<1<1<3<3<2<3<3<2<3<2<2<3<2<2<3<2*15<13<16* 22<11* 16<19<13* 22* 19* 12* 20<2<3<3<5<2<2<6<4<4<2<4<3 MEAN TABLE D-1I.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 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 10/04/12 < 18 < 7 3330 +/- 400 < 8 < 10 < 17 < 18 < 17 < 12 < 14 TABLE D-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2012 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD J2-1 10/24/12 K-40 Cs-134 Cs-137 7510 +/- 540 < 26 < 21 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, 2012 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD H1-2Q 08/28/12 B10-2Q 07/17/12 MEAN K-40 1-131 Cs-134 Cs-137 Sr-89 Sr-90 5050 +/- 370 2630 +/- 240 3840 +/- 3422< 16 < 10 < 13< 13 < 10 < 7< 13<3 9+/-4 2+/-1 6 +/-10 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, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD El-2Q GROSS BETA E1-2Q 1-131 01/04/12 01/11/12 01/18/12 01/25/12 02/01/12 02/08/12 02/16/12 02/22/12 02/29/12 03/07/12 03/14/12 03/21/12 03/28/12 04/04/12 04/11/12 04/18/12 04/25/12 05/02/12 05/09/12 05/16/12 05/22/12 05/30/12 06/06/12 06/13/12 06/20/12 06/27/12 07/04/12 07/11/12 07/18/12 07/25/12 08/01/12 08/08/12 08/15/12 08122/12 08/29/12 09/05/12 09/12/12 09/19/12 09/26/12 10/03/12 10/10/12 10/17/12 10/24/12 10/31/12 11/07/12 11/14/12 11/20/12 11/28/12 12/06/12 12/12/12 12/19/12 12/27/12-01/11/12-01/18/12-01/25/12-02/01/12-02/08/12-02/15/12-02/22/12-02/29/12-03/07/12-03/14/12-03/21/12-03/28/12-04/04/12-04/11/12-04/18/12-04/25/12-05/02/12-05/09/12-05/16/12-05/22/12-05/30/12-06/06/12-06/13/12-06/20/12-06/27/12-07/04/12-07/11/12-07/18/12-07/25/12-08/01/12-08/08/12-08/15/12-08/22/12-08/29/12.-09/05/12-09/12/12-09/19/12-09/26/12-10/03/12-10/10/12-10/17/12-10/24/12-10/31/12-11/07/12-11/14/12-11/20/12-11/28/12-12/06/12-12/12/12-12/19/12-12/27/12-01/02/13< lb< 18< 18< 19<9< 25< 27< 10< 13< 12< 12< 22< 23< 10< 17< 21< 11< 15< 14< 16< 20< 13< 10< 24< 17< 14< 11< 20< 16< 10< 14< 14< 13< 21< 24< 12< 28< 22< 16< 21< 21< 21< 17< 19< 25< 19< 26< 12< 13< 17<9< 18< 17 MEAN 26 +/- 18* THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (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, 2012 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD E1-2Q 12/28/11 -03/28/12 03/28/12 -06/27/12 06/27/12 -10/03/12 10/03/12 -01/02/13 Be-7 Cs-134 Cs- 137 73 113 97 59+ 14+ 22+ 18+/- 16* 0.8* 1.0* 0.5* 0.7< 0.5< 1.0< 0.1< 0.4 MEAN 86 +/- 48 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, 2012 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE COLLECTION DATE 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 G2-1Q 01/04/12 02/01/12 03/07/12 03/21/12 03/23/12 04/04/12 04/18/12 05/02/12 05/16/12 05/30/12 06/13/12 06/27/12 07/11/12 07/25/12 08/08/12 08/22/12 09/05/12 09/19/12 10/03/12 10/17/12 10/31/12 11/14/12 11/28/12 12/12/12* 0.3* 0.3* 0.3* 0.4* 0.5* 0.2* 0.3< 0.4* 0.2* 0.3* 0.2* 0.4* 0.2* 0.3* 0.2* 0.4< 0.3< 0.3* 0.4* 0.5* 0.3< 0.1* 0.3 1255 +/- 101 1529 +/- 95 1034 +/- 103 1011 +/- 88 1153 +/- 105 1038 +/- 101 877 +/- 94 1288 +/- 115 1255 +/- 109 914 +/- 94 740 +/- 74 686 +/- 74 1385 +/- 106 1269 +/- 85 882 +/- 85 952 +/- 90 946 +/- 83 970 +/- 59 1336 +/- 101 836 +/- 75 1070 +/- 114 989 +/- 159 887 +/- 183 1057 +/- 433<5<2<4<4<3<4<4<3<3<5<4<3<4<3<4<4<3<2<2<3<4<7<8<4<3<3<4<4<4<4<4<2<4<2<3<4<3<3<3<2<2<4<3<6<9<7* 14* 16* 17* 16* 17* 26*19* 29* 20* 19* 19< 35* 28* 31* 18* 18* 27* 25* 40* 19* 40* 32< 34<3<4<7<3<6<2<4<4<3<3<5<6<4<4<4<3<6<4<7<7<9< 10<6< 0.8 < 0.6< 1.0 < 0.5< 0.7 0.6 +/- 0.3< 0.5 0.5 +/- 0.3 MEAN*0.5 +/- 0.2* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-1O FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2012 6--QC-LAB.------ ---- ------------

---

---- PRIM A RY -LA B 4 a-C-, 3 2 1 0 Jan Feb Mar Apr May Jun Jul Aug Sep MONTH Oct Nov Dec FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2012 60 QC -LAB 50 ---- PRIMARY -LAR E.2 C.)0.40 30 20 10 0 1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2012 (PAGE 1 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)March 2012 E10066 E10067 E10069 E10068 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 101 94.8 pCi/L 11.7 13.5 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 87.5 247 435 133 156 127 190 179 327 274 167 310 107 109 87.6 133 113 226 185 92.5 260 436 149 159 132 195 168 333 279 164 276 94.5 101 83.5 123 106 210 176 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 2012 E10070 E10198 E10199 E10201 E10200 pCi 92.8 94.2 pCi/L 1800 1570 pCi/L 86.1 99.8 pCi/L 9.2 12.7 1.07 0.87 0.95 0.95 1.00 0.89 0.98 0.96 0.97 1.07 0.98 0.98 1.02 1.12 1.13 1.08 1.05 1.08 1.07 1.08 1.05 0.99 1.15 0.86 0.72 0.89 0.89 0.98 0.91 0.97 0.97 0.98 1.01 0.97 0.96 0.97 1.00 1.04 1.06 1.01 0.98 1.07 0.99 1.04 1.05 A A A A A A A A A A A A A A A A A A A A A A A A W A A A A A A A A A A A A A A A A A A A Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 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 88.9 72.8 394 159 206 89.5 129 129 193 342 73.2 367 165 205 84.7 118 125 181 338 99.7 82.2 402 174 212 92.3 132 128 199 355 75.1 366 159 193 84.2 121 117 182 324 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 101 96.6 A E-I TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2012 (PAGE 2 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)June 2012 E10202 Water Fe-55 pCi/L 1890 1580 pCi/L 106 99.6 pCi/L 13.6 16.0 September2012 E10296 E10297 E10299 E10298 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 89.8 160 230 101 174 97.2 188 159 195 155 145 219 94.1 140 88.3 173 136 165 133 99.6 164 248 108 174 100 196 152 192 152 135 205 89.4 144 83.0 162 125 159 125 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 E10300 pCi 95.5 97.2 pCi/L 1630 1900 pCi/L 101 96.6 pCi/L 11.3 13.8 1.20 1.06 0.85 0.90 0.98 0.93 0.94 1.00 0.97 0.96 1.05 1.02 1.02 1.07 1.07 1.05 0.97 1.06 1.07 1.09 1.04 1.06 0.98 0.86 1.05 0.82 1.03 1.03 1.07 0.95 0.97 0.96 1.00 1.07 1.02 1.01 1.04 1.10 1.02 0.99 1.01 1.05 0.94 0.92 1.08 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A December2012 E10334 E10335 E10337A 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 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 93.1 52.5 373 157 113 94.1 116 124 190 172 51.8 372 165 113 96.5 118 105 166 179 90.0 51.0 348 165 117 98.5 116 116 186 170 49.6 338 161 114 95.8 112 112 181 165 AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E-2 TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2012 (PAGE 3 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)December 2012 E10336 E10333 Charcoal 1-131 Water Fe-55 pCi 73.1 72.7 pCi/L 1550 1750 1.01 0.89 A A (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, 2012 (PAGE 1 OF 1)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)May 2012 RAD-89 MRAD-16 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Filter Gr-A Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Filter Gr-A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 63.4 33.5 89.2 66.5 152 73.3 109 82.4 43.6 25.9 15433 58.5 37.4 82.3 74.2 155 72.9 105 62.9 44.2 27.1 15800 46.9-66.3 27.4 -43.1 69.1 -90.5 60.6-81.6 140- 172 65.6 -82.6 94.5- 125 33.0 -78.0 29.6 -51.5 22.5- 31.9 13800 -17400 pCi/filter 39.5 77.8 26.1 -121 A A A A A A A N (1)A A A A N (2)A A A A A A A N (2)A A November, 2012 RAD-91 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 46.5 16.6 85.2 76.9 177 77.4 209 50.6 59.3 22.9 5020 39.1 20.1 84.8 76.6 183 78.3 204 58.6 39.2 24.8 4890 29.7-46.1 14.4 -23.8 71.3- 93.3 62.6- 84.3 165-203 70.5-88.5 184-240 30.6 -72.9 26.0-46.7 20.6 -29.4 4190-5380 MRAD-17 pCi/filter 59.6 87.5 29.3 -136 A (1) Detector G1 is slightly biased high for Th-230 based measurements used only for ERA Gross Alpha samples. NCR 12-05 (2) The Sr-89 found to known ratio was 1. 19, which TBE considers acceptable.

It appears the aliquot was entered incorrectly for the Gross Beta NCR 12-13 (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, 2012 (PAGE 1 OF 2)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)March 2012 12-MaW26 12-GrW26 12-MaS26 12-RdF26 12-GrF26 12-RdV26 September 2012 12-MaW27 12-GrW27 Water Cs-1 34 Cs-137 Co-57 Co-60 H-3 Mn-54 K-40.Sr-90 Zn-65 Water Gr-A Gr-B Soil Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/L -0.0045 (1)Bq/L 37.5 39.9 27.9- 51.9 Bq/L 30.8 32.9 23.0-42.8 Bq/L 22.4 23.72 16.60 -30.84 Bq/L 456 437 306 -568 Bq/L 31.0 31.8 22.3-41.3 Bq/L 144 142 99-185 Bq/L -0.0084 (1)Bq/L -0.369 (1)Bq/L 2.06 2.14 0.64-3.64 Bq/L 7.48 6.36 3.18-9.54 Bq/kg 831 828 580-1076 Bq/kg 0.145 (1)Bq/kg 1270 1179 825-1533 Bq/kg 7.61 1.56 (2)Bq/kg 634 558 391 -725 Bq/kg 1690 1491 1044-1938 Bq/kg 328 392 274 -540 Bq/kg 753 642 449 -835 Bq/sample 2.31 2.38 1.67 -3.09 Bq/sample 2.15 1.79 1:25 -2.33 Bq/sample

-0.0701 (1)Bq/sample 2.62 2.182 1.527 -2.837 Bq/sample 4.13 3.24 2.27-4.21 Bq/sample 0.0185 (1)Bq/sample 4.19 2.99 2.09-3.89 A A A A A A A A A A A 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 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B Bq/sample 0.365 1.2 Bq/sample 2.31 2.4 Bq/sample 8.72 8.43 Bq/sample 0.0424 Bq/sample 15.5 .12.0 Bq/sample 6.80 6.05 Bq/sample 0.0057 Bq/sample 2.24 2.11 Bq/sample 10.5 8.90 Bq/L 21.4 23.2 Bq/L 17.0 16.7 Bq/L 28.7 29.3 Bq/L 0.179 Bq/L 387 334 Bq/L 18.1 17.8 Bq/L 139 134 Bq/L 19.6 12.2 Bq/L 27.2 25.9 Bq/L 0.966 1.79 Bq/L 10.0 9.1 0.4 -2.0 1.2-3.6 5.90- 10.96 (1)8.4- 15.6 4.24 -7.87 (1)1.48-2.74 6.23-11.57 16.2-30.2 11.7-21.7 20.5-38.1 (1)234 -434 12.5-23.1 94 -174 8.5- 15.9 18.1 -33.7 0.54 -3.04 4.6- 13.7 A A A N (3)A A A A A W A W W A N (3)A A A A W A A A A A A A A A A A N (4)A A A E-5 TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING, 2012 (PAGE 2 OF 2)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)September 2012 12-MaS27 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 12-RdF27 12-GrF27 12-RdV27 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg 880 939 Bq/kg 1220 1150 Bq/kg 1330 1316 Bq/kg 552 531 Bq/kg 1000 920 Bq/kg 674 632 Bq/kg 528 508 Bqlkg 665 606 Bq/sample 2.760 2.74 Bq/sample 0.0415 Bq/sample 2.00 191.00 Bq/sample 1.78 1.728 Bq/sample 2.40 2.36 Bq/sample 0.931 1.03 Bq/sample

-0.688 Bq/sample 0.434 0.97 Bq/sample 1.927 1.92 Bq/sample 6.28 6.51 Bq/sample 4.62 4.38 Bq/sample 6.51 5.66 Bq/sample 5.32 5.12 Bq/sample 3.59 3.27 Bq/sample 0.0012 Bq/sample

-0.046 657- 1221 805- 1495 921 -1711 372 -690 644-1196 442 -822 356 -660 424 -788 1.92-3.56 (1)1.34-2.48 1.210 -2.246 1.65-3.07 0.72-1.34 (1)0.29-1.65 0.96 -2.88 4.56 -8.46 3.07 -5.69 3.96 -7.36 3.58-6.66 2.29 -4.25 (1)(1)A A A A A A A A A A A A A A A A A A A A A A A A (1) False positive test.(2) Sensitivity evaluation (3) No cause was found for the failed high soil Co-60 sensitivity test or the high Zn-65 in AP, which TBE considers an anomaly. NCR 12-08 (4) Sr-90 in water high due to incorrect aliquot entered in LIMS. 12-11 (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) DOEIMAPEP evaluation:

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

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

SUMMARY

PROFICIENCY TESTING PROGRAM'ENVIRONMENTAL, INC., 2012 (Page 1 of 1)Concentration (pCi/L)Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1783 04/09/12 Sr-89 ERW-1783 04/09/12 Sr-90 ERW-1786 ERW-1 786 ERW-1 786 ERW-1786 ERW-1786 04/09/12 04/09/12 04/09/12 04/09/12 04/09/12 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 ERW-1789 04/09/12 ERW-1789 d 04/09/12 Gr. Alpha Gr. Beta ERW-1798 04/09/12 H-3 ERW-6283 10/05/12 Sr-89 ERW-6283 10/05/12 Sr-90 62.2 +/- 6.0 33.7 +/- 2.1 75.7 +/- 4.1 71.9 +/- 4.0 70.0 +/- 4.3 151.5 +/-6.1 108.3 +/- 89.0 55.0 +/- 2.4 76.2 +/- 1.8 16023 +/- 355 41.5 +/- 4.1 19.7 +/- 1.6 82.7 +/- 4.4 77.2 +/- 3.7 74.4 +/- 1.5 183.0 +/- 6.2.211.0 +/- 9.9 47.0 +/- 2.3 33.4 +/- 1.2 23.3 +/- 1.0 58.5 46.9- 66.3 37.4 27.4-43.1 82.3 72.9 74.2 155.0 105.0 62.9 33.0 -78.0 44.2 29.6 -51.5 15800 13800 -17400 69.1 -90.5 65.6 -82.6 60.6 -81.6 140.0 -172.0 94.5 -125.0 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 39.1 20.1 ERW-6286 ERW-6286 ERW-6286 ERW-6286 ERW-6286 10/05/12 10/05/12 10/05/12 10/05/12 10/05/12 Ba-1 33 Co-60 Cs-134 Cs-137 Zn-65 84.8 78.3 76.6 183.0 204.0 29.7 -46.1 14.4 -23.8 71.3 -93.3 70.5 -88.5 62.6 -84.3 165.0 -203.0 184.0 -240.0 ERW-6288 10/05/12 Gr. Alpha ERW-6288 10/05/12 Gr. Beta ERW-6290 10/05/12 1-131 58.6 30.6 -72.9 39.2 26.0 -46.7 24.8 20.6 -29.4 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.d Result of reanalysis:

38.3 +/- 1.3 pCi/L. Sample dilution problem suspected.

A new dilution was prepared.E-7 TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)ENVIRONMENTAL, INC., 2012 (Page 1 of 2)Concentration a Known Control Lab Code D Date Analysis oratory result Activity Limits ' Acceptance STSO-1 766 STSO-1 766 STSO-1766 STSO-1766 STSO-1 766 STSO-1766 STSO-1766 STSO-1766 STAP-1772 STAP-1 772 STAP-1772 STAP-1 772 STAP-1 772 STAP-1 772 STAP-1 772 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 1352.10 +/- 4.00 1.70 +/- 0.70 842.20 +/- 4.30 0.40 +/- 0.90 1729.60 +/- 22.20 647.60 +/- 4.20 383.20 +/- 15.30 766.70 +/- 6.70 0.010 +/- 0.01 2.40 +/- 0.08 2.33 +/- 0.13 2.07 +/- 0.10 3.77 +/- 0.14-0.010 +/- 0.060 3.67 +/- 0.20 1179.00 1.56 828.00 0.00 1491.00 558.00 392.00 642.00 0.00 2.18 2.38 1.79 3.24 0.000 2.99 825.00 -1533.00 1.00 -2.00 580.00 -1076.00 0.00-1.00 1044.00 -1938.00 391.00 -725.00 274.00 -510.00 449.00 -835.00 0.000-1.00 1.53 -2.84 1.67 -3.09 1.25 -2.33 2.27 -4.21-0.10 -0.13 2.09 -3.89 STAP-1773 02/01/12 Gr. Alpha STAP-1773 02/01/12 Gr. Beta 0.51 +/- 0.05 2.75 +/- 0.10 1.20 2.40 0.40 -2.00 1.20 -3.60 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass.Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STVE-1776 STVE-1776 STVE-1 776 STVE-1776 STVE-1776 STVE-1776 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 STW-1960 02/01/12 Gr. Alpha STW-1960 02/01/12 Gr. Beta 14.57 +/- 0.28 6.45 +/- 0.23 8.39 +/- 0.29 0.01 +/- 0.09 0.03 +/- 0.08 10.31 +/- 0.67 1.68 +/- 0.09 6.33 +/- 0.10 33.30 +/- 0.40 23.20 +/- 0.40 0.30 +/- 3.00 40.10 +/- 0.60 460.00 +/- 12.10 153.00 +/- 4.20 32.70 +/- 0.60 0.10 +/- 0.20 0.01 +/- 0.20 12.00 6.05 8.43 0.00 0.00 8.90 2.14 6.36 32.90 23.72 0.00 39.90 437.00 142.00 31.80 0.00 0.00 8.40-15.60 4.24 -7.87 5.90 -10.96 0.00 -0.10 0.00 -0.10 6.23-11.57 0.64 -3.64 3.18 -9.54 23.00 -42.80 16.60 -30.84 0.00 -1.00 27.90 -51.90 306.00 -568.00 99.00 -185.00 22.30 -41.30 0.00 -1.00 0.00-1.00 STW-1964 STW-1 964 STW-1 964 STW-1 964 STW-1 964 STW-1964 STW-1 964 STW-1964 STW-1 964 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-1 34 Cs-1 37 H-3 K-40 Mn-54 Sr-90 Zn-65 E-8 TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)ENVIRONMENTAL, INC., 2012 (Page 2 of 2)Concentration a Known Control Lab Code D Date Analysis -oratory result Activity Limits c Acceptance STSO-5392 08/01/12 Sr-90 483.52 +/- 16.47 508.00 356.00 -660.00 Pass STSO-5394 08/01/12 Co-57 1528.00 +/- 4.10 1316.00 921.00 -1711.00 Pass STSO-5394 08/01/12 Co-60 592.00 +/- 3.20 531.00 372.00 -690.00 Pass STSO-5394 08/01/12 Cs-1 34 933.60 +/- 5.82 939.00 657.00 -1221.00 Pass STSO-5394 08/01/12 Cs-137 1319.80 +/- 5.50 1150.00 805.00 -1495.00 Pass STSO-5394 08/01/12 K-40 737.30 +/- 17.70 632.00 442.00 -822.00 Pass STSO-5394 08/01/12 Mn-54 1083.20 +/- 5.20 920.00 644.00 -1196.00 Pass STSO-5394 08/01/12 Zn-65 696.10 +/- 7.00 606.00 424.00 -788.00 Pass STVE-5395 a 08/01/12 Co-57 7.44 +/- 0.17 5.66 3.96 -7.36 Fail STVE-5395 08/01/12 Co-60 5.90 +/- 0.15 5.12 3.58 -6.66 Pass STVE-5395 08/01/12 Cs-1 34 7.40 +/- 0.31 6.51 4.56 -8.46 Pass STVE-5395 08/01/12 Cs-1 37 5.45 +/- 0.18 4.38 3.07 -5.69 Pass STVE-5395 08/01/12 Mn-54 4.06 +/- 0.21 3.27 2.29 -4.25 Pass STAP-5398 08/01/12 Gr. Alpha 0.41 +/- 0.05 0.97 0.29 -1.65 Pass STAP-5398 08/01/12 Gr. Beta 2.11 +/- 0.09 1.92 0.96 -2.88 Pass STAP-5403 08/01/12 Co-57 1.96 +/- 0.05 1.91 1.34 -2.48 Pass STAP-5403 08/01/12 Co-60 1.76 +/- 0.07 1.73 1.21 -2.25 Pass STAP-5403 08/01/12 Cs-1 34 2.74 +/- 0.18 2.74 1.92 -3.56 Pass STAP-5403 08/01/12 Cs-1 37 0.00 +/- 0.03 0.00 -0.01 -0.01 Pass STAP-5403 08/01/12 Mn-54 2.52 +/- 0.10 2.36 1.65 -3.07 Pass STAP-5403 08/01/12 Zn-65 0.01 +/- 0.06 0.00 -0.010 -0.010 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (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.d Result of reanalysis:

6.74 +/- 0.15 Bq/sample.

Gamma emitters for the vegetation matrix exhibited a high bias, only Co-57 exceeded acceptance limits. Recounted using a geometry more closely matched to the MAPEP sample size.E-9 Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)