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Annual Radiological Environmental Operating Report for the Year 2015
	ML16125A193
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Site:	Three Mile Island
Issue date:	04/30/2016
From:	; Teledyne Brown Engineering Environmental Services
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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ML16125A190	List: ML16125A193; TMI-16-017, Submittal of 2015 Radiological Environmental Monitoring Program Report;
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Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1and2 Annual Radiological Environmental Operating Report

1 January Through 31 December 2015 Prepared By Teledyne Brown Engineering Environmental Services Three Mile Island Nuclear Station Middletown, PA 17057 April 2016 Intentionally left blank Table Of Contents I. Summary and Conclusions

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1 II. Introduction

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3 A. Objectives of the REMP .....................................

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3 B. Implementation of the Objectives

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4 Ill. Program Description

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4 A. Sample Collection

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4 B. Sample Analysis ..................................................................................................

6 C. Data Interpretation

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7 D. Program Exceptions

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

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11 IV. Results and Discussion

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1*1 A. Aquatic Environment

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

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

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

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

14 5. Ground Water .........................................................................................

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

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14 7. Sediment.

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15 B. Atmospheric Environment

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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. Milk ...............................................................................................

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

17 C. Ambient Gamma Radiation

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18 D. Land Use Survey ...............................................................................................

18 E. Radiological Impact ofTMINS Operations

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19 F. Errata Data .........................................................................................................

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

26 V. References

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30 Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table 8-2 Table B-3 Figures Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Appendices Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2015 Location Designation, Distance & Direction An.d 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, 2015 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Environmental Sampling*

Locations Within One Mile of the Three Mile Island Nuclear Station, 2015 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2015 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2015 Data Tables and Figures -Primary Laboratory . Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. ii Table C-11.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the,Vicinity of Three Mile Island Nuclear Station, 2015. Table C-11.2 Concentrations of 1-131 in Drinking Water Samples Collected in the ViGinity of Three Mile Island t;Juclear Station, 2015. Table C-11.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-111.1 Concentrations of Gross Beta, 1-131, Tritium, and Strontium in E,ffluent Water Samples for Station K1-1 Collected in the Vicinity of Three Mile Island NuGlear Station, 2015. Table C-111.2 Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-IV:1 Concentrations of Strontium in .Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. --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, 2015.

Table C-V.1 Concentrations of Gamma Emitters in Sediment .Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-Vl.1 C.oncentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 201.5. Table C-Vl.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) In Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-Vl.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the. Vicinity of Three Mile Island Nuclear Station, 2015. Table C-Vll.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015.

Table C-Vlll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear 2015. *

Table C-Vlll.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Statio.n, 2015.

Table C-Vlll.3 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-IX.1 Cqncentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. iii Table C-X.1 Quarterly OSLO Results for Three Mile Island Nuclear Station, 2015. Table C-X.2 Mean Quarterly OSLO Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2015. Table C-X.3 Summary of the Ambient Dosimetry Program for Three Mile Island Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 1 Figure C-7 Figure C-8 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-11.1 . Nuclear Station, 2015. Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2015. Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2015. * . Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2015. Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2015. Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2015. Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2015. Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 -2015. Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2015. Data Tables and Figures -Comparison Laboratory Concentrations of Gross Beta in Drinking Wat,er Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2015. Concentration of Tritium in Drinking Water Samples Collecteq in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of lodine-131 ir:i Drinking Water Sample.s Collected in the Vicinity of Three Mile Nuclear Station, 2015. Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. iv*

Table D-111.1 Table D-IV.1 Table D-V.1 Table D-V.2 Table D-Vl.1 Figures Figure D-1 Figure D-2 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1 Q, 2015. Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2015. Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Teledyne Brown Engineering, 2015 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Environmental, Inc., 2015 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 2015 through 31 December 2015. During that time_ period, 1,694 analyses were performed on 1,305 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 1-131, Sr-89 and Sr-90 activities were detected.

Gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in 11 surface water samples, two drinking water samples and 11 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-137 was detected in one sediment sample. Occasionally Cs-137 is detected at very low levels Gust 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, Sr-89 or Sr-90 activities were detected.

Concentrations of naturally occurring K-40 were consistent with those detected in previous years. Occasionally Sr-90 activities are detected and are consistent with those detected in previous years and were attributed to fallout from nuclear weapons testing. No other fission or activation products were found. 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 nat1,Jrally 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 (OSLO) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued.

This change resulted in a slight change in process and reporting of quarterly results. The relative comparison to control locations remains valid. OSLO 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 2015 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 environment afld no increase in b.ackground radiation levels.

Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2015 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.

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

At the end of 1993 TMl-2 was placed in a condition called Post-Defueling Monitored -Storage.

TMl-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 2015 through 31 December 2015. 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 TMl-1 and TMl-2 Technical Specifications.

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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 2015. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3. Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, fish and sediment.

Two gallon water samples were collected monthly from continuous samplers located at two surface water locations (J1-2 and Q9-1 ), three drinking water locations (G15-2, G15-3 and Q9-1 ), and one effluent water location (K1-1 ). A composite of weekly grab samples at one surface water location (A3-2) were collected.

The control locations were A3-2 and Q9-1. All groundwater and storm water results are now being reported in the ARGPPR, Appendix F. All water samples were collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection.

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

Location IND could be affected by TMINS' effluent releases.

Sediment samples composed of recently deposited substrate were collected semiannually at three locations (A 1-3, J2-1 and K1-3). In addition, one sediment sample was collected annually at the East Dike Catch Basin (EDCB)'. Location A 1-3 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 p'articulate samples were collected and analyzed weekly at seven locations (A3-1, E1-2, F1-3,*G2-1, H3-1, M2-1 and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using' a vacuum pump with charcoal and glass fiber filters *attached.

The pumps were run , continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly-and sent to the laboratory for analysis.

Terrestrial Environment

_The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product.*

Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K15-3 and P4-1) from March through November, and monthly. from December through February.

The control location was K15-3. All samples were collected in new unused. two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory.

Food products were collected monthly at three locations (810-2, E1-2 and H1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2*and H1-2). 810-2 was the control loca.tion for both annual and monthly sampling.

Three different kinds of vegetation.

samples and seven 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 cha*nged the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLO) were *deployed and 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. OSLO 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 (A 1-4, 81-2, C1-2, 01-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, L1-1, M1-1, N1-3, P1-2, Q1-2 and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release. An indicator ring consisting of 60 locations (A3-1, A5-1, A9-3; 81-1, 82-1, 85-1, 810-1, C1-1., C2-1, C5-1, CB-1, 01-2, 02-2, 06-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, FS-1, F10-1, G1-2, G2-4, .G5-1, H3-1, H5-1, HB-1, J1-1, J3-1, J5-1, J?-1 K2-1, K3-1, K5-1, KB-1, L 1-2, L2-1, L5-1, LB-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1,'N5-1, NB-1, P1-1, P2-1, P5'-1, PB-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, .R5-1 and R9-1) extending to apprqximately 10 miles from the site, designed to measure possible exposures to close-in population.

The balance of 11 locations (015-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L 15-1, 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);

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

Each station has two Al20 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 OSLO responds to radiation independently, this provides two independent detectors .at each. station. 8. Sample Analysis This section describes the general analytical methods used by T8E and . Midwest Labs to analyze the environmental samples for radioactivity for the TMINS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-3.

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.

1 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 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 a*nalysis.

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

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity.

Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.

Gamma spectroscopy results for each type of *sample were grouped as follows: For surface, drinking, and effluent water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.

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

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

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

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

For food products five nuclides, Be-7, K-40, 1-131, Cs-134 and Cs-13 7 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 2015 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 015-1 1. For the sampling period 02/05/15 to 02/12/15, the vacuum pump malfunctioned.

Pump and timer were operating but not pulling any vacuum. Per procedures, samples were invalid and not sent to the lab for analyses.

Pump was replaced on 02/14/15, and sampler was returned to service. For sampling period 02/12/15 -02/19/15, the total volume was impacted, but per procedures, the samples were valid and sent to the lab for analysis. (IR 2500642) G2-:I 2. For the sampling period 04/02/15 to 04/09/15 and 04/09/15 to 04/16/15, there were lower than expected run times and air volumes due to power interruptions.

Maintenance work was in-progress at the farm which is now completed.

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

Offsite lab still achieved required LLD for iodine sampling and particulate results were normal. (IR 2500733) H3-1 3. For the sampling period 05/14/15 to 05/21/15 and 05/21/15 to 05/28/15, breaker was found tripped. The breaker was reset and sampler. was returned to service. Sample volumes were lower than normal but still valid per procedure and sent to the lab for analyses. (IR 2553457) . H3-1 4. For the sampling period 06/18/15 to 06/25/15, the sample pump malfunctioned and was found not operating.

The sample volume was insufficient.

Per procedure, the samples were not valid and were not *sent for analysis.

The pump was replaced on 06/26/15 and the sampler was returned to service. (IR 2553457) H3-1 5. For the sampling period 08/19/15 to 08/27 /15, a potentially invalid sample was collected.

During the previous weeks collection, the vacuum switch tubing was not seated properly when connected, and as a result the run timer did not operate. The pump was operational and the sample appeared normal. The sample on and off time were used to calculate run hours as an alternate volume estimation.

The samples were not valid per procedure, but were sent for analyses to the lab with the approximated volume. (IR 2553457) E1-2 6. For the sampling period 12/03/15 to 12/10/15, the breaker was found tripped. The breaker was reset and sampler was returned to service. Sample volumes were lower than normal but still valid per procedure and sent to the lab for analysis. (IR 2631797)

WATER 1. A3-2 Due to Swatara Creek being frozen,over could not break ice and collect grab sample for 02/17/15 to 02/24/15 sampling period. February composite will consist of three rather than four samples. (IR 2500642) 09-1 2. For the sampling period 04/14/15 to 04/21/15, the drinking water sampler was found with the GFI tripped. One hundred and twenty three (123) samples were missed, and insufficient sample volume was* collected.

Grab samples were taken to.supplement the volume of water collected for the week. The GFI was reset and the sampler was returned to service. (IR 2500733) Q9-1 -3. For drinking water weekly sample from 10/27/15 to 11/03/15, 105 hourly samples were missed due to a power interruption probably related to plant maintenance at the water treatment facility.

Insufficient sample volume was collected to meet all QA and backup samples, and grab samples were taken to supplement the volume of water collected for the week. (IR 2631797) Q9-1 4. For surface water weekly sample from 12/01/15 to 12/08/15, sampler was found with GFI tripped and 97 hourly samples were missed. Sufficient sample volume was collected.

The GFI was reset and the sampler was returned to service. (IR 2631797) Dosimeter L2-1 1. Telephone mounting pole replaced and first quarter dosimeters could not be located. New mounting hardware was installed on the new pole for second quarter dosimeter installation., (IR 2500642) R3-1 2. First quarter dosimeters found under snow on the ground. Dosimeters were sent for analyses.

Dosimeter analysis results were not impacted. (IR 2500642)

Vegetation H1-2 1. Indicator vegetation plants were not mature enough to harvest for June. (IR 488572) 2. 810'-2 Due to growing season ending, only one of three monthly samples were available from the control garden for August and September. (IR 488572) Each program exception was reviewed to understand the causes of the program exception.

Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence.

Occasional equipment breakdowns and power outages were unavoidable.

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

E. Program Changes There were no changes to the program in 2015. IV. Results and Discussion A. Aquatic Environment

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

Of these locations only J 1-2 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 11 of 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 454 to 6,250 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 were taken from location A3-2. This is a control or background station sampled because known medical discharges of radiopharmaceuticals occur into the surface. water upstream of TMI from a nearby hospital.

Monthly samples were taken from A3-2 and analyzed for 1-131. (Table C-1.2, Appendix C). lodine-131 activity was not detected in any samples. Gamma Spectrometry Locations J1-2 and 09-1 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 G15-3 and 09-1). 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 21 of 36 samples. The concentrations ranged from 2.0 to 5.5 pCi/I. Concentrations detected were .consistent with those detected in previous years (Figure C-3, . Appendix C).

Iodine Monthly samples from all locations were analyzed for concentrations of 1-131 (Table C-11.2, Appendix C). lodine-131 activity was not detected in any samples. Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was detected in two of 36. The concentrations ranged from 288 to 621 pCi/L. The hypothetical dose to the maximum exposed individual from consuming this water during both time periods was calculated as <0.009 mrem (IR 2469947/2531179 (Figures C-4, Appendix C). Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.4, Appendix C). All nuclides were less than the MDC. 3. Effluent Water Monthly samples were collected from. a continuous water sampler at one location (K1-1). The following analyses were performed:

Gross Beta Monthly samples from location K1-1 were analyzed for concentrations of gross beta (Tables C-111.1, Appendix C). Gross beta was detected in all 12 samples. The concentrations ranged from 2.1 to 8.3 pCi/I. Concentrations detected were consistent with those detected in previous years. lodine-131 Monthly samples from location K1-1 were analyzed for concentrations of 1-131 (Tables C-111.1, Appendix C). lodine-131 was not detected in any of the samples .. Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-111.1, Appendix C). Tritium activity was detected in 11 of 12 samples. The concentrations ranged from 5,440 to 106,000 pCi/I. The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations.

These results were from the liquid discharge mixing basin .. The concentrations detected agree with those obtained from the TMINS Effluent Monitoring Program. The concentrations were well below any regulatory limits. (Figure C-4, Appendix C} Strontium . .

Semiannual composite samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-111.1, Appendix C). No strontium activity was detected. highest MDC was calculated at <4.0 pCi/I for Sr-89 and at <0.9 pCi/I for Sr-90. Gamma Spectrometry . Samples from location K1-1 were analyzed for gamma emitting nuclides (Table C-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 (ARGPRR), 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 <4.2 pCi/kg wet for Sr-90.

Gamma Spectrometry The edible portions of fish samples from *bath 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 1 ,439 to 4,283 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 (A 1-3, 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 5,753 to 14,700 pCi/kg dry. Cs-137 was found in one sample at a concentration of , 211 pCi/kg d!)'. No other fission or activation products were detected.

Cesium-137 is occasionally found in sediment at very low levels Oust above LLD) and is not distinguishable from background levels (Figure C-5, Appendix C). B. Atmospheric Environment 1.. Airborne Particulates

a. Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. Six locations (A3-1, E1-2, F1-3, G2-1, H3-1 and M2,..1) were indicator stations located in the highest D/Q sectors and the nearest communities to TMI. One sample (015-1) 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-Vl.1 and C-Vl.2, Appendix C). -1,5 -

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 31 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3. The results from the intermediate offsite locations (Group II) ranged from 6 to 41 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. The results from the Control location (Group Ill) ranged from 7 .to 36 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. Comparison of the 2015 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 2015 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-Vl.3, Appendix C). Naturally occurring Be-7 due to cosmic ray activity was detected in 26 samples. These concentrations ranged from 39 to 112 E-3 pCi/m3. All other nuclides were less than the MDC. b. Airborne Iodine Continuous air samples were collected from seven (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1 and 015-1) locations and analyzed weekly for 1-131 (Table C-Vll.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:

lodine-131 Milk samples from all locations were analyzed for concentrations of 1-1,31 (Table G-Vlll.1, Appendix C). All results were less than the MDC.

Strontium Milk samples from all locations were composited quarterly and analyze6 for,Sr-89 and Sr-90 (Table C-Vlll.2, Appendix C). No Sr-89' or Sr-90 activity was detected .. Occasionally Sr-90 is detected and is consistent with those detected in the years (Figure C-8, Appendix C). ' ' Gamma Spectrometry Milk samples from all locations were analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.3, Appendix C). Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 703 to 1,657 pCi/L. All other nuclides were less than the MDC. b. Food Products Food products were collected monthly at three locations (810-2, E1-2 and H1-2), in lieu of milk sampling., and annually from the four food product groups at two locations (810-2, E1 "2 and H1:-2). 810-2 was the control location for both annual and monthly sampling.

The following analyses were performed:

Strontium Nineteen of 25 food product samples were analyzed for concentrations of Sr-90 (Table C-IX.1, Appendix C). Strontium-90 activity was detected in eight of 19 samples. The concentrations ranged from 3 to 11 pCi/kg wet. Gamma Spectrometry Each food sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). Naturally occurring 8e-7 due to cosmic ray activity was detected in 14 of' 25 samples. These concentrations ranged from 153 to 1,965 pGi/kg. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from -1.7 -

1,996 to 7,653:pCi/kg.

All *other nuclides were less than the MDC. C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Optically Stimulated Luminescence Dosimeter (OSLO). Ninety OSLO locations were established around the site. Results of OSLO measurements are listed in Tables C-X.1 to C-X.3, Appendix C All of the OSLO measurements were below 40 mR/quarter, with a range of 17.2 to 37.8 mR/standard quarter. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations 015-1, F25-1, G10-1, G15-1, H15-1, J15-1,. K15-1, L15-1, N15-2, 015-1 and R15-1 averaged higher than indicator stations.

Locations 015-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, 015-1 and R15-1 have a historical

high bias, and this *bias is most likely due to radon and other naturally . occurring nuclides, e.g. K-40, emanating from the ground.

D. Land Use Survey A Land Use Survey conducted in the July through November 2015 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 ft 2 in each of the sixteen 22 % degree sectors around the site. For 2015, a meat census was also performed.

The results of these surveys are summarized below.

E. 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 1.2 2.4 3 NE 0.5 1.1 4.2 2.4 4 ENE 0.5 0.5 4.5 1.1 5 E 0.4 0.5 1.1 1.1 6 ESE 1.1 1.2 3.2 1.1 7 SE 0.7 ' ' 1.6 1.4 1.4 8 SSE 0.7-0.8 1.8 9 s 2.3 2.5 3.3 10 SSW 0.6 1.6 4.9, 14.4 4.9 11-SW 0.5 1.0 12 WSW 0.5 . 1.3 13 w 0:1 1.4 14 WNW 0.4 1.7 3.7 2.4 15 NW 0.4 1.2 16 NNW 1.1 2.4 Radiological Im-pact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the pubiic fror:n 2015 operations at TMINS were well below all applicable regulato*r)f limits and were significantly less than doses received from natural sources of radiation.

The 2015 whole body dose potentially received by an assumed maximum exposed individual from TMl-1 and TMl-2 liquid and airbo_rne effluents was conservatively calculated to be 0.12 mrem. This dose is equivalent to 0.04% of the dose that an individual living in the TMI area receives each year from natural background radiation.

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

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

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

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

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

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

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

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

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

The dose assessment model also contains dose conversion factors for the radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, .skin, kidney, lung, bone and GI tract). 2. Result of Dose Calculations The maximum hypothetical doses due to 2015 TMl-1 and TMl-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 ofthe 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 2015 operations at TMINS were well below the Federal dose limits (US EPA 40 CFR 190) and the guidelines of USN RC 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 2015 TMl-1 and TMl-2 liquid and airborne effluents combined was conservatively calculated to be 0.12 mrem. This dose is equivalent to 0.04% percent of the dose that an individual living in the TMI area receives each year from . natural background radiation (311 mrem). The low doses calculated for 2015 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).

In conclusion, radioactive materials related to 2015 TMINS , operations were detected in environmental samples, but the concentrations were low and consistent with measured effluents.

The environmental sample results verified that the doses received by the public from TMINS effluents in 2015 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 n'o 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 2015 did not have any adverse effects on the health of the public or on the environment.

TABLEl Calculated Maximum Hypothetical Doses to an Individual from 2015 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual From Radionuclides In Liquid Releases From Radionuclides In Airborne Releases (Noble Gases) From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates)

No noble gases were released from TMI-2. Total from Site USNRC . 10 CFR 50 APP. I Guidelines (mrem/yr) 3 total body, or 10 any organ 5 total body, or 15 skin 15 any organ USEPA 40CFR190 Limits (mrem/yr) 75 thyroid 25 total body or other organs Calculated Dose (mrem/yr) TMI-1 TMI-2 2.52E-2 4.l 7E-4 2.62E-2 6.60E-4 4.07E-4 5.99E-4 O* O* 3.88E-1 2.86E-5 Calculated Dose (mrem/yr)

TMI-1 and TMI-2 Combined**

0.62 0.92 **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 2015 TMINS operations was 0.50 mrem. This dose was based on a maximum net fence-line exposure rate and a shoreline/fence-line occupancy factor of 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months (Regulatory Guide 1.109). The combination of the maximum organ dose from TMI-1 and TMI-2 effluents (0.42 mrem) and the dose from direct radiation (0.50 mrem) yielded a maximum hypothetical dose of0.92 mrem.

TABLE2 .Calculated Whole Body Doses to the Maximum Individual From 2015 TMI-1 and TMI-2 Liquid and Airborne Effluents From Radionuclides In Liquid Releases From Radionuclides in Airborne Releases ** (Noble Gases)

From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates)

No noble gases were released from TMl-2. Calculated Maximum Individual Whole Body Dose (mrem/yr)

TMI-1 TMI-2 2.52E-2 4.17E-4 4.07E-4 O* 9.83E-2 2.86E-5 Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations:

0 .12 mrem/yr Individual Whole Body Dose Due to Natural Background Radiation (1) 311 mrem/vr (1) NCRP 160 -(2009)

Figure 1 Exposure Pathways For Radioifuclides Routinely Released From TMINS PEOPLE t IPREDOl\UNANT RADIONUCLIDES

! . .,.,J NOBLE GASES Plume exposure RADIOIODINES (H31, I-133) rnhalation and c-0nsumption of milk, water. fruits, and vegetables R.AOIOSTRONTIUM$

Sr-90) Consumption of rn ilk. meat, fruits, and vegetsiblcs ACTIVATION PRODUCTS Mn-54) Shoreline expos11re RADIOCESWMS (Cs* l34, Cs*l37) Sh<>reHne e:xp.;1sure and coniiumpHon of milk, meat, fish, water, f.ru its, and vegetables TRtTIUM (H*3) Inhalation a11d t:onsumption of water, milk, fruits, and vegetables F. Errata Data There is no errata data for 2015. G. Summary of Results -Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:

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

2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC,. state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable.

The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the *appropriate regulatory document.

3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. The MAPEP defines three levels of performance:

Acceptable (flag = "A"), Aq;eptable 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 wtien 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, 129 out of 139 analyses performed met the specified acceptance criteria.

Ten analyses (AP -Cr-51, U-234/233, Gr A, Sr-9o;*soil Sr-90; Water -Ni-63,* Sr-89/90, U natural; Vegetation Sr-90 samples) did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program: Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities . . 1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Gr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio .of 1.30 (acceptable with warning) was exceeded.

The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the shortest half-life (27.7 days) and the lowest gamma energy (320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations).

This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable.

NCR 15-18 . . 2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr-90 result of 286 Total Bq/kg. was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested sample utilized for analysis.

The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was.evaluated as acceptable with a result of .694 and an acceptance range of 601 -1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a* result of 429 and an acceptance range of 298'-553 Bq/kg. This issue is specific to the March 2015 MAPEP sample. NCR 15-13 . 3. Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233.result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper c;icceptance range of 0.0202 Sq/sample.

Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would . overlap with the known value, which* is statistically considered acceptable.

MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of*0.96) than the normal U-234/233.

Due to the extremely low activity, *it was difficult to quantify the U-234/233.

NCR 15-13 4. Teledyne Brown Engineering's MAPEP Marth 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the lower acceptance range of 0.53 Sq/sample.

The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard.

The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency.

When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and

cannot escape to be*counted.

When the sample media absorbs the alpha particles this is known as self-absorption or attenuation.

The calibration must include a similar configuration/media to correct for the attenuation.

In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters. The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24 -1.53 Sq/sample.

Unlike the MAPEP samples *. air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed.

NCR 15-13* 5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 .+/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" .or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot' of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21 6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53

Sq/sample.:

In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TSE suspects that this may be the *cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.

TSE will no longer analyze the air particulate Sr-90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-:-90 in the air particulate matrix. NCR 15-21 7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the *lower acceptance range of 0.91 Sq/sample.

In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TSE suspects that this maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, .can cause interferences to indicate lower activity or higher activity.

Results from previous performance.

evaluations were reviewed and shown to be acceptable.

NCR 15-21 8. & 9.Teledyne Brown Engineering's ERA May* water Sr-89/90 results of 45.? and 28.0 pCi/l, were lower than the known values of 63.2 and 41.9 pCi/l, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/l, respectively.

The yields were on the high side of the TSE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09 10. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/l was higher than the known value of 56.2 pCi/l, exceeding the upper acceptance limit of 62.4 pCi/L. The.technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57.16 agreed with the assigned value of 56.2. NCR 15-19 For the El Ml laboratory, 90 of 94 analyses met the specified acceptance criteria.

Four analyses (Water-Co-57, Fe-55; AP -Co-57; Soil -sr .. 90) did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Sq/L was lower than the known value of 29.9 Sq/L, exceeding the lower control limit of 20.9 Sq/L. The reported value should have been 27.84, which would have been evaluated as acceptable.

A data entry error resulted in a acceptable result. 2. Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value 6f 1.51 Sq/ sample, exceeding the lower control limit of 1.06 Sq/sample.

The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable.

A data entry error resulted in a hon-acceptable result. 3. Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Sq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Sq/kg. The .

separation of calcium from strontium caused a failed low result The reanalysis result of 352 Sq/kg fell within acceptance criteria .. 4. Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe"'-55 res*ult of 4.2 Sq/L was lower than the known value of 13.1 Sq/l, exceeding the lower control limit of 9.2 Sq/L. The known activity was below the routine laboratory detection limits for available aliquot fraction.

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 Nudear Station, Unit 1, Technical Specifications, DPR 50. 2. Three Mile Island Nuclear Station, Unit 2, PDMS Teclinical Specifications, DPR 73. . 3. Radiation Management Corporation. "Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1.974-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.

Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

> I ....... NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

SURFACE WATER (PCI/LITER)

TYPES OF ANALYSIS PERFORMED H-3 I-131 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 24 12 24 REQUIRED LOWER LIMIT OF DETECTION (LLD) 2000 15* 15 30 15 30 15 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION MEAN(M) MEAN(M) MEAN(M) STATION# (F) (F) (F) NAME RANGE RANGE RANGE DISTANCE AND DIRECTION 2307 <LLD 2307 TM-SW-Jl-2 INDICATOR (11/12) (11/12) WEST SHORE; TMI (454/6250)

(454/6250) 0.5 MILES S OF SITE NA <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

SURFACE WATER (PCI/LITER)

DRINKING WATER (PCI/LITER)

TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) ZR-95 30 CS-134 15 CS-137 18 BA-140 60 LA-140 15 GR-B 36 4 I-131 36 H-3 36 2000 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD 3.1 (17/24) (2.3/5.5) . <LLD 455 (2/24) (288/621)

CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD 2.7 (4/12) (2.0/3.7)

<LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 3.2 (10/12) (2.3/5.5) . 455 (2/12) (288/621)

STATION# NAME DISTANCE AND DIRECTION 1M-DW-G15-2 INDICATOR WRIGHTS WATER SUPPLY 13.3 MILES SE OF SITE 1M-DW-G15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0

> I w NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAl\1PLED (UNITOF MEASUREMENT)

DRINKING WATER (PCI/LITER)

TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) GAMMA 36 MN-54 15 C0-58 15 J'.E-59 30 C0-60 15 ZN-65 30 NB-95 15 ZR-95 30 CS-134 15 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULAWD USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0

> I -!>-NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PA1HW A Y SAMPLED (UNITOF MEASUREMENT)

DRINKING WATER (PCT/LITER)

EFFLUENT WATER (PCT/LITER)

TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) CS-137 18 BA-140 60 LA-140 15 GR-B 12 4 I-131 12 H-3 12 2000 SR-89 2 5 SR-90 2 2 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD 4.6 (12/12) (2.1/8.3)

<LLD 31188 (11/12) (54401106000)

<LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD NA NA NA NA NA LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 4.6 (12/12) (2.1/8.3) 31188 (11112) (5440/106000)

STATION# NAME DISTANCE AND DIRECTION TM-EW-Kl-1 INDICATOR MAIN STATION LIQ. DISCHARGE ON SITE TM-EW-Kl-1 INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

EFFLUENT WATER (PCI/LITER)

TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) GAMMA 12 MN-54 15 C0-58 15 FE-59 30 C0-60 15 ZN-65 30 NB-95 15 ZR-95 30 CS-134 15 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE NA NA NA NA NA NA NA NA LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0

> I 0\ NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320. 2015 l\.1EDIUM OR PATHWAY SAMPLED (UNITOF l\.1EASUREl\.1ENT)

EFFLUENT WATER (PCI/LITER)

BOTTOM FEEDER (PCI/KG WET) TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORl\.1ED PERFORl\.1ED OF DETECTION (LLD) CS-137 18 BA-140 60 LA-140 15 SR-90 4 IO GAMMA 4 K-40 NA MN-54 130 C0-58 130 FE-59 260 INDICATOR CONTROL LOCATIONS LOCATION l\.1EAN (M) l\.1EAN (M) (F) (F) RANGE RANGE <LLD NA <LLD NA <LLD NA <LLD <LLD 2861 2945 (2/2) (2/2) (1439/4283)

(2863/3026)

<LLD <LLD <LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) l\.1EAN (M) (F) RANGE 2945 (2/2) (2863/3026)

STATION# NAl\.1E DISTANCE AND DIRECTION BKGB CONTROL CITY ISLAND UPSTREAM OF DISCHARGE THE l\.1EAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE l\.1EASUREl\.1ENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED l\.1EASUREl\.1ENTS 0 0 0 0 0 0 0 0

> I -..J NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

BOTTOM FEEDER (PCI/KG WET) PREDATOR (PCI/KG WET) TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFOR!vIBD PERFOR!vIBD OF DETECTION (LLD) C0-60 130 ZN-65 260 CS-134 130 CS-137 150 SR-90 4 10 GAMMA 4 K-40 NA MN-54 130 C0-58 130_ INDICATOR CONTROL LOCATIONS LOCATION MEAN(M) MEAN (M) (F) (F) RANGE RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 3170 3327 (2/2) (2/2) (2493/3846)

(2869/3785)

<LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 3327 (2/2) -(2869/3785)

STATION# NA!vIB DISTANCE AND DIRECTION BKGP CONTROL CITY ISLAND UPSTREAM OF DISCHARGE THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0

> I 00 NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

PREDATOR (PCI/KG WET) SEDIMENT (PCI/KG DRY) TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) FE-59 260 C0-60 130 ZN-65 260 CS-134 130 CS-137 150 GAMMA 7 K-40 NA MN-54 NA C0-58 NA INDICATOR CONTROL LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD. <LLD 11041 12635 (515) (2/2) (5753/14700)

(11580/13690)

<LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 14700 (!/!) STATION# NAME DISTANCE AND DIRECTION EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0

>-I \0 NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

SEDIMENT (PC!/KG DRY) AIR PARTICULATE (E-3 PCI/CU.METER)

INDICATOR LOCATIONS TYPES OF NUMBER OF REQUIRED MEAN(M) ANALYSIS ANALYSIS LOWER LIMIT (F) PERFORMED PERFORMED OF DETECTION RANGE (LLD) C0-60 NA <LLD CS-134 150 <LLD CS-137 180 211 (1/5) GR-B 362 10 17 (307/311)

(6/41) GAMMA 28 BE-7 NA 66 (22/24) (39/112) MN-54 NA <LLD C0-58 NA <LLD C0-60 NA <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD 18 (51/51) (7/36) 62 (4/4) (42/78) <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 211 (Ill) 18 (51/51) (7/36) 74 (4/4) (44/103) STATION# NAME DISTANCE AND DIRECTION EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE TM-AP-Ql5-l CONTROL WEST FAIRVIEW 13.5 MILES NW OF SITE TM-AP-M2-l INDICATOR FISHING CREEK; GOLDSBORO 1.3 MILES WSW OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0

> I -0 NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

AIR PARTICULATE (E-3 PCI/CU.METER)

A!RIODINE (PCI/CU.M)

MILK (PCIILITER)

TYPES OF ANALYSIS PERFORMED NB-95 ZR-95 CS-134 CS-137 GAMMA 1-131 I-131 SR-89 SR-90 NUMBER OF ANALYSIS PERFORMED 362 110 20 20 REQUIRED LOWER LIMIT OF DETECTION (LLD) NA NA 50 60 70 5 2 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0

> I --NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

MILK (PCT/LITER)

VEGETATION (PCI/KG WET) INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION# ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION (LLD) GAMMA 110 K-40 NA 1281 1267 1418 TM-M-F4-1 INDICATOR (88/88) (22/22) (22/22) TURNPIKE ROAD FARM (703/1657) (1120/1477) (1242/1657) 3.0 MILES ESE OF SITE CS-134 15 <LLD <LLD CS-137 18 <LLD <LLD BA-140 60 <LLD <LLD LA-140 15 <LLD <LLD SR-90 19 10 7 7 7 Hl-2 INDICATOR (4/10) (4/9) (4/9) RED HILL MARKET (3/11) (4/8) (3/11) 1.0 MILES SSE OF SITE GAMMA 25 BE-7 NA 891 737 981 Hl-2 INDICATOR (8/13) (6/12) (7/9) RED HILL MARKET (263/1654)-

(153/1965)

(499/1654)

!. 0 MILES SSE OF SITE K-40 NA 3872.2 3912.8 4163.3 El-2 INDICATOR (13/13) (12/12) (4/4) TMI VISITOR'S CENTER (2079/7428) (1996/7653) (2339/7428) 0.4 MILES E OF SITE THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0

> I ...... N NAME OF FACILITY:

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:

MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)

VEGETATION (PCI/KG WET) DIRECT RADIATION (MILL!REM/STD.MO.)

INDICATOR LOCATIONS TYPES OF NUMBER OF REQUIRED MEAN(M) ANALYSIS ANALYSIS LOWER LIMIT (F) *PERFORMED PERFORMED OF DETECTION RANGE (LLD) I-131 60 <LLD CS-134 60 <LLD CS-137 80 <LLD OSLD-QUARTERL Y 359 NA 22.4 (3151315)

(12.1/37.8)

CONTROL I,OCATION MEAN(M) (F) RANGE <LLD <LLD <LLD 24.5 (44/44) (19.8/33.9)

LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 33.1 (4/4) (30.1/37.8)

STATION# NAME DISTANCE AND DIRECTION HS-I INDICATOR SAGINAW ROAD 7.4 MILES SSE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION

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

Radial Zone of Sampling Location in miles. Station's Numerical Designation within sector and zone, using 1, 2, 3 ... in each sector and zone. B-1 TABLE 13-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Sample Station Map Distance Medium Code (miles) Azimuth Description AQS A1-3 0.6 359° N of site off north tip of TMI in Susquehanna River ID A1-4 0.3 50 N of Reactor Building on W fence adjacent to North Weather Station, TMI AP,Al,ID A3-1 2 2.7 357° N of site at Mill Street Substation SW A3-2 2 2.7 356° N of site at Swatara Creek, Middletown ID A5-1 2 4.4 30 N of site on Vine Street Exit off Route 283 ID A9-3 3 8.0 20 N of site at Duke Street Pumping Station, Hummelstown ID B1-1 1 0.6 25° NNE of site on light pole in middle of North Bridge, TMI ID B1-2 1 0.4 24° NNE of Reactor Building on top of dike, TMI ID B2-1 2 1.9 17° NNE of site on Sunset Dr. (off Hillsdale Rd.) ID B5-1 2 4.9 19° NNE of site at intersection of School House and Miller Roads ID B10-1 3 9.2 21° NNE of site at intersection of West Areba Avenue and Mill Street, Hershey FP Bto-2 3 10 31° NNE of site at Milton Hershey School, Hershey ID CH 1 0.7 37° NE of site along Route 441 N ID C1-2 1 0.3 50° NE of Reactor Building on top of dike, TMI ID C2-1 2 1.5 44° NE of site at Middletown Junction ID C5-1 2 4.7 43° NE of site on Kennedy Lane ID C8-1 3 7.1 48° NE of site at Schenk's Church on School House Road AQF Control All locations where finfish are collected above Dock St. Dam, Harrisburg ID 01-1 0.2 76° ENE of Reactor Building on top of.dike, TMI ID 01-2 0.5 67° ENE of site off Route 441 along lane between garden center and residence ID 02-2 2 1.6 74° ENE of site along Hillsdale Rd. (S of Zion Rd.) ID 06-1 3 5.2 66° ENE of site off Beagle Road JD 015-1 3 10.8 64° ENE of site along. Route 241, Lawn AP, Al, ID, FP E1-2 1 0.4 97° E of site at TMI Visitor's Center JD E1-4 1 0.2 97° E o_f Reactor Building on top of dike, TMI M E2-2 2 1.1 96° E of site at farm on Pecks Road ID E2-3 2 2.0 97° E of site along Hillsdale Rd. (N of Creek Rd.) ID E5-1 2 4.7 82° E of site at intersection of North Market Street (Route 230) and Zeager Road ID E7-1 3 6.7 88° E of site along Hummelstown Street, Elizabethtown ID F1-1 1 0.5 117° ESE of site near entrance to 500 kV Substation ID F1-2 1 0.2 112° ESE of Reactor Building on top of dike midway within ISWSF, TMI AP,AI F1-3 0.6 112° ESE of site in 500 kV Substation ID F1-4 0.2 122° ESE of Reactor Building on top of dike, TMI ID F2-1 2 1.3 119° ESE of site along Engle Road M F4-1 2 3.2 104° ESE of site at farm on Turnpike Road ID F5-1 2 4.7 109° ESE of site along Amosite Road ID F10-1 3 9.4 112° ESE of site along Donegal Springs Road, Donegal Springs ID F25-1 3 22 106° ESE of site at intersection of Steel Way and Loop Roads, Lancaster ID G1-2 1 0.7 145° SE of site along Route 441 S ID G1-3 1 0.2 130° SE of Reactor Building on top of dike, TMI ID G1-5 1 0.3 143° SE of Reactor Building on top of dike, TMI ID G1-6 1 0.3 139° SE of Reactor Building on top of dike, TMI AJ,AP,M G2-1 2 1.4 126° SE of site at farm on Becker Road ID G2-4 2 1.7 138° SE of site on Becker Road ID G5-1 2 4.8 131° SE of site at intersection of Bainbridge and Risser Roads ID G10-1 3 9.7 128° SE of site at farm along Engles Tollgate Road, Marietta ID G15-1 3 14.4 126° SE of site at Columbia Water Treatment Plant OW G15-2 3 13.3 129° SE of site at Wrightsville Water Treatment Plant OW G15-3 3 15.7 124° SE of site at Lancaster Water Treatment Plant B-2 TABLE B-2: Sample Medium ID FP AP,AI, ID ID ID ID AQF ID SW ID AQS ID ID ID ID EW AQS ID ID ID ID ID ID M ID ID ID ID ID ID ID ID AP,AI, ID ID ID ID ID ID ID ID ID ID Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Station Map Code Number H1-1 1 H1-2 1 H3-1 2 H5-1 2 H8-1 3 H15-1 3 Indicator J1-1 1 J1-2 .1 J1-3 J2-1 2 J3-1 2 J5-1

2 J7-1 3 J15-1 3 K1-1 1 K1-3 1 K1-4 K2-1 2 K3-1 2 K5-1 2 K8-1 3 K15-1 3 K15-3 3 L 1-1 1 L1-2 1 L2-1 2 L5-1 2 L8-1 3 L 15-1 3 M1-1 M1-2 1 M2-1 2 M5-1 2 M9-1 3 N1-1 1 N1-3 N2-1 2 N5-1 2 N8-1 3 N15-2 3 P1-1 Distance !miles) 0.5 1.0 2.2 4.1 7.4 13.2 0.8 0.5 0.3 1.4 2.7 4.9 6.5 12.6 0.2 0.2 0.2 1.2 2.0 4.9 7.5 12.8 14.4 0.1 0.5 1.8 4.1 8.0 11.8 0.1 0.4 1.3 4.3 8.7 0.7 0.1 1.2 4.9 7.7 10.4 0.4 167° 151° 160° 158° 163° 157° 176° 188° 189° 179° 179° 181° 176° 183° 211° 213° 209° 200° 206° 202° 196° 203° 205° 236° 221° 224° 228° 225° 226° 249° 252° 256° 249° 243° 274° 274° 261° 268° 262° 275° 303° B-3 Description SSE of site, TMI SSE of site along Route 441, Red Hill Market SSE of site in Falmouth-Collins Substation SSE of site by Guard Shack at Brunner Island Steam Electric Station SSE of site along Saginaw Road, Starview 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 S of site, TMI S of site downstream of the TMINS liquid discharge outfall in. Susquehanna River S of Reactor Building just S of SOB, TMI S of site in Susquehanna River just upstream of the York Haven Dam S of site at York Haven/Cly S of site along Canal Road, Conewago Heights S of site off of Maple Street, Manchester S of site in Met-Ed York Load Dispatch Station On site at RML-7 Main Station Discharge Building SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River SSW of Reactor Building on top of dike behind Warehouse 2, TMI SSW of site on S Shelley Island SSW of site along Rt. 262, N of Cly SSW of site along Conewago Creek Road, Strinestown SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View SSW of site behind McDonald's and next to child care center, Weiglestown SSW of site at farm along S Salem Church Rd, Dover SW of site on top of dike W of Mech. Draft Cooling Tower, TMI SW of site on Beech Island SW of site along Route 262 SW of site at intersection of Stevens and Wilson Roads SW of site along Rohlers Church Rd., Andersontown SW of site on W side of Route 74, rear of church, Mt. Royal WSW of Reactor Building on SE corner of U-2 Screenhouse fence, TMI WSW of site on E side of Shelley Island, Lot #157 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown WSW of site .along Alpine Road, Maytown W of site on W side of Shelley Island, between lots #13 and #14 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI W of site at Goldsboro Marina W of site off of Old York Road along Robin Hood Drive W of site along Route 382, 1/2 mile north of Lewisberry W of site at intersection of Lisburn Road and Main Street, Lisburn WNW of site on Shelley Island TABLE 8-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Sample Station Map Medium 'Number ID P1-2 ID P2-1 M P4-1 ID P5-1 ID P8-1 ID 01-1 ID 01-2 ID 02-1 ID 05-1 SW,DW,ID 09-1 AP,AI, ID 015-1 ID R1-1 ID R1-2 ID R3-1 ID R5-1 ID R9-1 ID R15-1 ID = Immersion Dose (OSLO) SW = Surface Water Al = Air Iodine AP =Air Particulate 2 2 2 3 1 1 2 2 3 3 1 1 2 2 3 3 FP = Food Products (Green Leafy Vegetation, Fruits, Vegetables)

EW DW M AOF AOS Distance (miles) Azimuth Descrii;ition 0.1 292° WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 1.9 283° WNW of site along Route 262 3.6 295° WNW of site at farm on Valley Road 5.0 284° WNW of site at intersection of Valley Road (Route 262) and Beinhower Road 7.9 292° WNW of site along Evergreen Road, Reesers Summit 0.5 317° NW of site on E side of Shelley Island 0.2 321° NW of Reactor Building on fence W of Warehouse 1, TMI 1.9 310° NW of site along access road along river 5.0 317° NW of site along Lumber Street, Highspire 8.5 310° NW of site at the Steelton Water Company 13.4 309° NW of site behind West Fairview Fire Dept. Social Hall " (abandoned) 0.2 335° NNW of Reactor Building along W fence, TMI 0.7 334° NNW of site on central Henry Island 2.6 341° NNW of site at Crawford Station, Middletown 4.9 339° NNW of,site at intersection of Spring Garden Drive and Route441 8.0 341° NNW of site at intersection of Derry and 66th Streets, Rutherford Heights 11.2 332° NNW of site at intersection of Route 22 and Colonial Road, Colonial Park IDENTIFICATION KEY = Effluent Water = Drinking Water =Milk (Cow) = Finfish = Aquatic Sediment B-4 TABLE 8-3: Sample Medium Surface Water Surface Water Surface Water Drinking Water Drinking Water Drinking Water Drinking Water Effluent Water Effluent Water Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Gamma Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous.

radiological analysis (Three Mile Island water compositor.

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

Nuclear Station) Env. Inc., T-02 Determination of.tritium in water (direct method) lodine-131 Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices 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 exchanqe Gross Beta Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in 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 cross beta in water (dissolved solids or total residue) Gamma Monthly composite ER-TMl-06 Collection of water samples for 2 gallon

TBE, TBE-2007 Gamma emittinQ radioisotope analysis Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station) Env. Inc., GS-01 Determination of g;:imma emitters by ,_ qamma spectroscopy Tritium Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid from a continuous radiological analysis (Three Mile Island scintillation water compositor.

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

Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by an ion exchange lodine-131 Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radibiodine in various matrices 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 exchanqe Gross Beta Monthly composite ER-TMl-06 Collection of water samples for 2.gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in 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: Sample Medium Effluent Water Effluent Water Effluent Water Storm Water Storm Water Fish Fish Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Gamma Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

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

water compositor.

Nuclear Station) Env. Inc., T-02 Determination of tritium in water (direct method) Strontium-Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 composite from monthly samples. Gamma Quarterly composite ER-TMl-06 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy of monthly grab radiological analysis (Three Mile Island samples Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Tritium Quarterly composite ER-TMl-06 Collection of water samples for 1 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid of monthly grab radiological analysis (Three Mile Island scintillation samples Nuclear Station) Env. Inc., T-02 Determination of tritium in water (direct method) Gamma Semi-annual samples ER-TMl-13 Collection offish 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 Strontium-90 Semi-annual samples ER-TMl-13 Collection offish 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 Samoles TABLE B-3: Sample Medium Sediment Air Particulates Air Particulates Air Iodine Milk Milk Milk Vegetation Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Method Gamma Semi-annual grab ER-TMl-03 Collection of sediment"samples for 500 grams (dry) TSE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by aamma spectroscopv Gross Beta One-week ER-TMl-14 Collection of air particulate and air 1 filter TSE, TBE-2008 Gross alpha and/or gross beta activity in composite of iodine samples for radiological analysis (Three (approximately various matrices continuous air Mile Island Nuclear Station) 280 cubic sampling through meters weekly) Env. Inc., AP-02 Determination of gross alpha and/or gross glass fiber filter beta in air particulate filters paper Gamma Quarterly composite TSE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis 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 Gamma One-week ER-TMl-14 Collection of air particulate and air 1 filter TSE, 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 1-131 Bi-weekly grab ER-TMl-01 Collection of milk samples for 2 gallon TSE, 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 Strontium-Quarterly composite ER-TMl-01 Collection of milk samples for 2 gallon TSE, 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 Compositina of samples Gamma Bi-weekly grab ER-TMl-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 Gamma Monthly and annual ER-TMl-04 Collection of vegetatipn 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 aamma spectroscopv l::ti I 00 TABLE Sample Medium Vegetation OSLO* Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Method Strontium-Monthly*and annual ER-TMl-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 Optically Quarterly OSLDs ER-TMl-02 Collection of OSLO samples for 2 badges with 3 Landauer Incorporated Stimulated comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Luminescence Al203:C Landauer Station) Dosimetry Incorporated elements.

H I Sorvice l..ave r Ciadil>: Soun:H: E sri. o.Lonne. NAVTEQ. TomTom. l nt ermap , increment P Corp., GEBCO , U SGS , FAO , NPS , NRCAN. GooBa5e , IGN , KadasterNL. Ord n a n ce Su""'Y. Es ri Japan. MET l., Es ri Ch in a (Hong Kong). swisstopo. and Ille GlS User Com munity Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2015 B-9 Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island ,Nuclear Station, 2015 B-10

.....

,,.,,; < -, ,'( ;,; w p !Af111t 3 h&l f-A p _, .,,. ., .. "'>.., Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station , 2015 B-11 Oc l Intentionally left blank APPENDIX C DATA TABLES AND FIGURES -PRIMARY LABORATORY Intentionally left blank Table C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/1,5 MEAN J1-2 4630 +/- 501 5050 +/- 547 876 +/- 165 517 +/- 148 6250 +/- 668 2080 +/- 261 679 +/- 153, 3130 +/- 365 1170 +/- 180 544 +/- 142 < 194 454 +/- 144 2307 +/- 4239 09-1 < 172 < 177 < 196 < 193 < 185 < 187 < 189 < 183 < 184 < 189 < 194 < 193 Table C-1.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA COLLECTION A3-2 PERIOD 01/06/15 -02/03/15 < 0.4 02/10/15 -03/03/15 < 0.7 03/10/15 -03/31/15 < 0.4 04/07/15 -04/28/15 < 0.4 05/05/15 -06/02/15 < 0.3 06/09/15 -06/30/15 < 0. 7 07/07/15 -07/28/15 < 0.8 08/04/15 -09/01/15 < 0.6 09/07/15 -09/29/15 < 0.6 10/06/15 -11/03/15 < 0.4 11/10/15 -12/01/15 < 0.5 12/08/15 -12/29/15 < 0. 7 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1 n I N Table C-1.3 SITE COLLECTION PERIOD J1-2 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31 /15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07 /28/15 -09/01 /15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN 09-1 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 " 07 /28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -.12/29/15 MEAN CONCENTRATIONS OF.GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+ 2 SIGMA Mn-54 <4 <4 < 5 < 9 < 5 < 5 < 5 < 7 <7 < 3 <4 < 5 <2 < 6 < 6 < 5 <4 < 5 < 7 <4 <7 < 3 <4 < 5 Co-58 <4 <4 < 5 < 8 <4 < 6 <7 < 7 < 7 < 3 < 3 < 5 < 3 <7 < 6 < 5 <4 < 5 <4 < 5 <7 < 3 < 6 <4 Fe-59 < 9 < 8 < 11 < 14 < 10 < 12 < 12 < 16 < 15 < 7 < 6 < 10 < 7 < 17 < 15 < 9 < 9 < 12 < 17 < 15 < 14 < 5 < 12 < 11 Co-60 < 5 <4 < 5 < 8 <4 < 6 < 5 < 8 <8 < 4 <4 <4 < 3 <7 < 6 <4 < 3 < 6 < 8 <4 < 7 < 3 < 6 <5 Zn-65 < 10 < 9 < 11 < 15 < 8 < 12 < 15 < 16 < 14 < 7 < 8 < 7 < 6 < 15 < 11 < 10 <7 < 10 < 12 < 15 < 10 < 5 < 11 < 9

< 5 < 5 < 6 < 7 <4 < 6 <6 . < 9 <7 . < 3 <4 < 5 < 3 <7 < 6 <7 <4 . < 5 < 5 < 7 <6 < 3 <6 < 6 Zr-95 < 8 < 7* < 11 < 11 < 8 < 7 < 11 < 15 < 12 < 6 -< 6 < 6 < 6 < 12 < 10 < 10 < 6 < 8 < 11 < 12 < 10 < 5 < 11 < 10 Cs-134 Cs-137

< 5 < 5 <4 <5 *< 5 < 6 <7 <4 < 5 < 6 < 8 < 9 < 3 < 3 < 4 < 3 <7 < 5 <6 <4 < 5 < 5 < 6 <5 < 2 <5 < 5 < 8 < 5 <7 < 5 <7 < 7 < 3. <4 <5 <3 < 8 <6 < 6 <4 <6 < 8 < 5 < 6 <3 < 6 < 5 Ba-140 < 21 < 28 < 28 < 35 < 24 < 34 < 32 < 30 < 33 < 17 < 19 < 29 < 24 < 31 < 33 < 25 < 20 < 29 < 29 < 32 < 27 < 14 < 35 < 33 La-140 < 6 < 8 < 11 < 10 < 8 < 10 <7 < 11 < 13 < 6 < 7 < 5 < 7 < 13 < 11 < 7 < 7 < 10 < 12 < 8 < 10 < 5 < 10 < 10 Table C-11.1 COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31 /15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01 /15 -09/29/15 09/29/15 -11 /03/15 11103/15 -12101115 12/01/15 -12/29/15 MEAN Table C-11.2 COLLECTION PERIOD 12/36114 -62/63/1 g 02/03/15 -03/03115 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01 /15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN Table C-11.3 COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01 /15 -09/29/15 . 09/29/15 -11103/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA G15-2 G15-3 Q9-1 3.1 +/- 1.5 2.7 +/- 1.4 < 1.9 2.8 +/- 1.5 < 2.1 < 2.0 < 2.2 < 2.1 < 2.0 < 2.2 < 2.0 < 2.0 3.2 +/- 1.4 2.7 +/- 1.4. 2.1 +/- 1.3 2.5 +/- 1.5 2.5 +/- 1.4 2.0 +/- 1.4 2.7 +/- 1.4 < 1.9 < 1.9 3.6 +/- 1.6 2.7 +/- 1.6 < 2.1 3.7 +/- 1.5 4.0 +/- 1.6 3.7 +/- 1.6 5.5 +/- 1.9 3.2 +/- 1.7 < 2.0 2.3 +/- 1.3 2.4 +/- 1.3 2.9 +/- 1.2 2.9 +/- 1.5 < 1.9 < 1.8 3.2 +/- 1.8 2:9 +/- 1.1 2.7 +/- 1.6 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA G15-2 G15-3 Q9-1 < 6.5 < 6.5 < 6.4 < 0.8 < 0.7 < 0.7 < 0.4 < 0.4 < 0.3 < 0.5 < 0.6 < 0.6 < 0.4 < 0.3 < 0.3 < 0.7 < 0.7 < 0.7 < 0.9 < 0.7 < 0.8 < 0.5 < 0.5 < 0.6 < 0.7 < 0.6 < 0.7 < 0.4 < 0.4 < 0.4 < 0.8 < 0.5 < 0.5 < 0.6 < 0.6 < 0.6 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA G15-2 G15-3 Q9-1 < 168 288 +/- 122 < 169 < 178 < 178 < 175 < 196 < 198 < 198 < 192. < 195 < 191 < 185 . 621 +/- 152 "< 184 < 189 <*183 < 190 < 186 < 186 < 188 < 180 < 191 < 182 < t84 <:184 < 184 < 191 < 191 < 187 < 195 < 194 < 194 < 192 < 1.93 < 195 455 +/- 471 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-3

(') I .;:.. Table C-11.4 SITE COLLECTION PERIOD G15-2 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN G15-3 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31 /15 03/31 /15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA Mn-54 < 6 < 7 < 5 < 5 < 5 < 8 < 8 < 8 < 9 < 3 < 6 < 4 < 6 < 5 <4 < 7 <4 < 6 < 6 < 6 < 6 < 3 < 9 < 5 Co-58 <7 < 8 <5. < 6 < 5 < 8 < 6 <7 < 7 < 3 < 7 < 5 < 5 < 5 < 3 < 7 < 5 < 6 <_7 < 7 < 6 < 3 <7 < 5 Fe-59 < 12 < 15 < 10 < 11 < 11 < 14 < 15 < 16 < 17 < 7 < 17 < 11 < 12 < 11 < 8 < 14 < 10-< 14 < 13 < 14 < 11 < 6 < 17 < 9 Co-60 < 6 <4 <4 < 6 < 5 < 6 < 8 < 8 < 9 < 3 < 5 < 5 < 5 < 6 < 5 <4 < 4* "<6 < 8 < 5 .<7 < 3 < 8 < 5 Zn-65 < 13 < 13 < 9 < 9 < 10 < 15 < 14 < 15 < 16 < 6 < 11 < 9 < 13 < 13 < 9 < 13 < 8 < 14 < 14 < 17 < 13 <6 < 13 < 9 Nb-95 < 7 < 6 < 5 < 6 < 6 < 7 < 8 <6 < 7 < 3 < 7 < 5 < 6 < 5 < 4 < 6 <5 < 6 < 8 < 9 < 7 < 3. <8 < 5 Zr-95 < 12 < 12 < 10 < 10 <8 < 13 < 15 < 10 < 14 < 6-_ < 12 < 7 <9 < 9 <8 < 12 <6 < 11 < 13 < 14 < 10 <5 < 13 <9 Cs-134 Cs-137 Ba-140 La-140 <6 <8 <35 <8 < 6 < 5 <

31 < 12 < 4 < 6 <

26 < 9 < 5 < 6 <

30 < 7 < 5 < 5 <

29 < 9 < 7 < 6 <

42 < 12 < 6 < 7 <

32 < 12 < 7 <7 < 3 <7 <4 < 5 < 5 <4 < 6 <4 < 6 <6 < 6 < 6 < 3 <7 <4 <7 < 6 < 3 <7 < 5 < 6 < 6 <4 < 6 <4 < 7 < 7 < 8 < 6 < 3 <7 < 5 < 34 < 25 < 17 < 31 < 21 < 28 < 26 < 24 < 31 < 20 < 41 < 32 < 36 < 23 < 15 < 42 < 27 < 10 < 8 < 5 < 11 < 7 < 9 < 10 < 8 < 9 <6 < 11 < 15 < 11 < 6 <4 < 12 < 10 Table C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCilLITER

+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q9-1 12/30/14 -

02/03/15 < 7 < 7 <

14 < 4 < 15 < 7 < 12 <6 < 8 < 34 < 11 02/03/15 -03/03/15 < 5 < 7 < 12 < 4 < 10 < 6 < 12 <5 < 7 < 33 < 10 03/03/15 -03/31/15 < 5 <4 < 12 < 5 < 9 <4 < 8 <4 < 5 < 26 < 10 03/31/15 -04/28/15 < 6 <5 < 10 < 7 < 12 < 8 < 12 < 6 < 6 <

26 < 8 04/28/15 -06/02/15 < 3 < 3 < 6 <4 <7 < 3 <6 < 3 < 3 <

18 < 6 06/02/15 -06/30/15 < 6 < 6 <

15 < 6 < 14 < 6 < 11 < 6 < 7 <

36 < 13 06/30/15 -07 /28/15 < 7 < 6 <

18 < 8 < 15 <7 < 12 < 6 < 6 <

35 < 10 07/28/15 -09/01/15 < 6 < 5 <

17 < 7 < 18 <7 < 11 < 6 < 6 <

31 < 10 09/01/15 -09/29/15 < 10 < 8 < 19 < 5 < 16 < 9 < 13 < 7 < 7 <

30 < 8 09/29/15 -11/03/15 < 3 < 3 < 5 < 2 < 6 < 3

<5 < 3 < 3 < 15 < 5 11/03/15 -12/01 /15 < 8 < 8 < 20 < 7 < 17 < 8 < 15 < 7 < 8 <

39 < 13 12/01/15 -12/29/15 < 5 < 5 <

12 < 5 < 11 < 6 < 10 < 5 < 6 <

32 < 8 n MEAN I lll Table C-111.1 SITE COLLECTION PERIOD K1-1 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION K1-1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA GR-8 1-131 H-3 SR-89 SR-90 2.5 +/- 1.4 < 0.3 69900 +/- 7000 < 4.0 < 0.7 4.3 +/- 1.7 < 0.8 38800 +/- 3900 3.2 +/- 1.6 < 0.5 9350 +/- 983 2.6 +/- 1.5 < 0.9 11600 +/- 1210 4.7 +/- 1.7 < 0.3 106000 +/- 7590 4.3 +/- 1.7 < 0.7 29700 +/- 3010 2.1 +/- 1.4 < 0.8 6860 +/- 739 < 3.1 < 0.9 6.7 +/- 2.1 < 0.8 45800 +/- 4620 6.7 +/- 2.0 < 0.6 13900 +/- 1440 8.3 +/- 2.3 < 0.3 5720 +/- 625 3.0 +/- 1.3 < 0.5 < 198 6.2 +/- 1.8 < 0.9 5440 +/- 600 4.6 +/- 4.0 36685 +/- 65243 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-6 Table C-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD K1-1 12/30/14 -02/03/15 <6 <6 < 14 <6 < 14 <7 < 11 <6 <7 < 32 < 9 02/03/15 -03/03/15 < 5 < 5 < 9 < 5 <

10 <7 < 13 <5 < 6 < 34 < 12 03/03/15 -03/31/15 < 5 <4 < 9 <4 <9 . < 5 <8 <3 < 5 < 25 < 9 03/31/15 -04/28/15 <6 < 8 < 15 < 11 < 19 < 9 < 14 <7 < 9 < 41 < 15 04/28/15 -06/02/15 <5 <6 < 14 <6 < 10 <6 <9 <5 < 5 < 27 < 9 06/02/15 -06/30/15 <5 <4 < 11 < 5 <9 <6 <9 <4 < 5 < 31 <6 06/30/15 -07/28/15 <6 <7 < 18 <7 < 14 <6 < 13 <6 < 8 < 32 < 11 07/28/15 -09/01/15 <6 <6 < 12 < 5 < 10 <6 <9 <5 < 6 < 28 <6 09/01/15 -09/29/15 <7 <6 < 10 <7 < 15 <6 < 13 <6 < 7 < 29 < 13 09/29/15 -11/03/15 <9 <7 < 9 <7 < 13 <6 < 11 < 5 < 7 <

33 < 13 11/03/15 -12/01/15 <4 <6 < 9 <5 < 13 <5 <8 < 5 < 6 < 34 < 9 12/01/15 -12/29/15 <7 <7 < 14 <7 < 12 <7 < 13 < 6 <6 < 39 < 12 MEAN (") I ....;i Table C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH) SAMPLES COLLECTED IN THE VICINITY*OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Sr-90 PERIOD INDP PREDATOR 06/10/15 < 3.2 09/23/15 < 4.2 MEAN INDB BOTTOM FEEDER 06/10/15 < 3.3 09/23/15 < 3.9 MEAN BKGP PREDATOR 06/11/15 < 3.9 10/06/15 < 2.4 MEAN BKGB BOTTOM FEEDER 06/11/15 < 2.1 10/06/15 < 3.5 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, 2015 RESULTS IN UNITS OF PCl/KG WET +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58

Fe-59 . Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDP PREDATOR 06/11/15 2493 +/- 818 < 45 < 44 < 114 < 42 < .1.03 < 44 < 48 10/06/15 3846 +/- 787 < 44 < 42 < 96 < 38 < 87 < 42 < 49 MEAN 3170 +/- 1913 INDB BOTTOM FEEDER 06/11/15 4283 +/- 1253 < 105 < 114 < 232 < 82 < 237 < 88 < 97 10/06/15 1439 +/- 1004 < 74 < 85 < 168 < 66 < 127 < 66 < 70 MEAN 2861 +/- 4022 BKGP PREDATOR 06/11/15 3785 +/- 756 < 59 < 67 < 141 < 60 < 132 < 54 < 69 10/06/15 2869 +/- 1097 < 74 < 58 < 155 < 58 < 178 < 73 < 72 MEAN 3327 +/- 1295 BKGB BOTTOM FEEDER 06/11/15 2863 +/- 1027 < 62 < 76 < 162 < 74 < 130 < 77 < 68 10/06/15 3026 +/- 326 < 27 < 60 < 209 < 20 < 59 < 22 < 22 2945 +/- 231 C-9 Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG DRY+/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD A1-3 06/12/15 13690 +/- 1842 < 97 < 85 < 93 < 83 < 106 10/29/15 11580 +/- 1417 < 75 < 53 < 73 < 69 < 86 *MEAN 12635 +/- 2984 EDCB 10/29/15 14700 +/- 1708 < 84 < 70 < 88 < 76 211 +/- 84 MEAN 14700 +/- 0 211 +/- 0 J2-1 06/12/15 13980 +/- 2067 < 113 < 113 < 103 < 98 < 137 10/29/15 14640 +/- 1705 < 81 < 71 < 81 < 68 < 93 MEAN 14310 +/- 933 K1-3 06/12/15 6131 +/- 765 < 41 < 52 < 42 < 38 < 46 10/29/15 5753 +/- 1033 < 68 < 67 < 77 < 69 < 86 MEAN 5942 +/- 535 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-10 Table C-Vl.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION PERIOD 01/01/15 -01/08/15 01/08/15 -01/15/15 01/15/15 -01/22115 01/22115 -01/29/15 01/29/15 -02/05/15 02/05/15 -02/12/15 02/12115 -02119/15 02119/15 -02/26/15 02/26/15 -03/05/15 03/05/15 -03/12115 03/12/15 -03/18/15 03/18/15 -03/26/15 03/26/15 -04/02/15 04/02/15 -04/09/15 04/09/15 -04/16/15 04/16/15 -04/23/15 04/23/15 -04/30/15 04/30/15 -05/07 /15 05/07/15 -05/14/15 05/14/15 -05121/15 05/21/15 -05/28/15 05/28/15 -06/04/15 06/04/15 -06/10/15 06/10/15 -06/18/15 06/18/15 -06/25/15 06/25/15 -07/02115 07 /02115 -07 /09/15 07 /09/15 -07 /16/15 07/16/15 -07/23/15 07/23/15 -07/30/15 07 /30/15 -08/06/15 08/06/15 -08/13/15 08/13/15 -08/19/15 08/19/15 -08/27 /15 08/27/15 -09/03/15 09/03/15 -09/10/15 09/10/15 -09/16/15 09/16/15 -09/24/15 09/24/15 -10/01/15 10/01/15 -10/08/15 10/08/15 -10/15/15 10/15/15 -10/22/15 10/22115 -10/29/15 10/29/15 -11/05/15 11/05/15 -11/12/15 11/12/15 -11/19/15 11/19/15 -11/25/15 11/25/15 -12103/15 12/03/15 -12110/15 12110/15 -12/17/15 12/17/15 -12123/15 12/23/15 -12/31/15 MEAN GROUP I E1-2 F1-3 17 +/- 5 20 +/- 5 23 +/- 5 19 +/- 5 21 +/- 6 17 +/- 5 13 +/- 5 13 +/- 5 17 +/- 5 23 +/- 5 25 +/- 5 20 +/- 5 16 +/- 5 17 +/- 6 17 +/- 5 15 +/- 5 16 +/- 5 14 +/- 5 8 +/- 5 11 +/- 4 12 +/- 5 16 +/- 5 13 +/- 5 18 +/- 5 <7 11 +/- 5 12 +/- 4 15 +/- 5 9 +/- 5 19 +/- 5 13 +/- 5 16 +/- 5 7 +/- 5 9 +/- 5 10 +/- 4 24 +/- 6 15 +/- 4 31 +/- 5 27 +/- 6 16 +/- 6 21 +/- 4 15 +/- 5 14 +/- 5 17 +/- 5 17 +/- 5 14 +/- 5 22 +/- 5 14 +/- 5 14 +/- 5 12 +/- 5 15 +/- 4 29 +/- 9 31 +/- 6 23 +/- 6 8 +/- 4 17 +/- 11 17 +/- 5 11 +/- 5 21 +/- 5 21 +/- 5 26 +/- 5 18 +/- 5 17 +/- 5 11 +/- 5 13 +/- 4 10 +/- 5 12 +/- 5 16 +/- 5 12 +/- 5 11 +/- 4 14 +/- 5 15 +/- 5 13 +/- 5 18 +/- 5 8 +/-_5 <7 13 +/- 4 11 +/- 5 8 +/- 5 18 +/- 5 16 +/- 5 15 +/- 5 16 +/- 5 12 +/- 5 9 +/- 4 16 +/- 6 16 +/- 4 27 +/- 5 25 +/- 6 18 +/- 6 17 +/- 4 16 +/- 5 11 +/- 4 16 +/- 5 16 +/- 5 13 +/- 5 20 +/- 5 14 +/- 5 16 +/- 5 10 +/- 5 12 +/- 4 27 +/- 6 26 +/- 6 15 +/- 6 6 +/- 4 16 +/- 10 A3-1 23 +/- 6 15 +/- 5 19 +/- 5 15 +/- 5 12 +/- 5 16 +/- 5 18 +/- 5 23 +/- 5 24 +/- 6 15 +/- 5 13 +/- 5 18 +/- 5 12 +/- 5 13 +/- 5 12 +/- 4 8 +/- 5 9 +/- 4 15 +/- 5 ' 14 +/- 5 10 +/- 4 15 +/- 5 10_ +/- 5 13 +/- 5 9 +/- 4 12 +/- 5 9 +/- 5 19 +/- 5 16 +/- 5 14 +/- 4 15 +/- 5 16 +/- 5 14 +/- 4 23 +/- 6 15 +/- 4 32 +/- 5 28 +/- 6 15 +/- 6 23 +/- 4 19 +/- 5 11 +/- 4 19 +/- 5 18 +/- 5 18 +/- 5 18 +/- 5 18 +/- 5 19 +/- 5 18 +/- 5 12 +/- 4 39 +/- 6 28 +/- 6 23 +/- 6 10 +/- 4 17 +/- 12 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION GROUP II G2-1 H3-1 18 +/- 5 20 +/- 6 16 +/- 5 17 +/- 5 22 +/- 6 19 +/- 5 16 +/- 5 14 +/- 5 18 +/- 5 22 +/- 5 25 +/- 5 25 +/- 6 18 +/- 5 12 +/- 5 15 +/- 5 12 +/- 5 14 +/- 5 13 +/- 5 8 +/- 5 13 +/- 5 12 +/- 5 17 +/- 5 14 +/- 5 18 +/- 5 9 +/- 5 14 +/- 5 12 +/- 4 10 +/- 4 7 +/- 4 15 +/- 5 16 +/- 5 12 +/- 4 15 +/- 6 16 +/- 5 11 +/- 4 23 +/- 6 18 +/- 4 36 +/- 6 28 +/- 6 18 +/- 6 22 +/- 4 17 +/- 5 11 +/- 4 19 +/- 5 18 +/- 5 14 +/- 5 22 +/- 5 10 +/- 4 18 +/- 5 13 +/- 5 17 +/- 4 41 +/- 6 25 +/- 5 20 +/- 6 9 +/- 4 17 +/- 13 -14 +/- 5 13 +/- 5 21 +/- 6 24 +/- 5 23 +/- 5 23 +/- 6 18 +/- 5 16 +/- 6 14 +/- 4 14 +/- 5 13 +/- 5 13 +/- 5 < 7 12 +/- 4 12 +/- 4 15 +/- 5 10 +/- 6 13 +/- 7 8 +/- 5 9 +/- 5 10 +/- 4 (1) < 8 21 +/- 5 15 +/- 5 18 +/- 5 11 +/- 5 17 +/- 5 17 +/- 5 28 +/- 6 -16 +/- 4 32 +/-.6 28 +/- 6 14 +/- 6 20 +/- 4 16 +/- 5 12 +/- 5 15 +/- 5 17 +/- 5 12 +/- 5 21 +/- 5 14 +/- 5 17 +/- 5 16 +/- 5 14 +/- 4 39 +/- 6 29 +/- 6 21 +/- 6 8 +/- 4 17 +/- 13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-11 M2-1 20 +/- 6 14 +/- 5 22 +/- 6 16 +/- 5 11 +/- 5 21 +/- 6 24 +/- 5 27 +/- 6 20 +/- 5 19 +/- 5 15 +/- 6 18 +/- 5 12 +/- 5 14 +/- 5 12 +/- 5 10 +/- 5 12 +/- 4 12 +/- 5 14 +/- 5 12 +/- 5 21 +/- 5 10 +/- 5 15 +/- 6 14 +/- 4 12 +/- 5 13 +/- 5 17 +/- 5 16 +/- 5 17 +/- 5 16 +/- 5 14 +/- 5 16 +/- 5 21 +/- 6 18 +/- 4 34 +/- 6 29 +/- 6 25 +/- 6 22 +/- 4 20 +/- 5 10 +/- 4 14 +/- 5 14 +/- 5 14 +/- 5 17 +/- 5 18 +/- 5 19 +/- 5 14 +/- 5 15 +/- 4 41 +/- 6 26 +/- 6 22 +/- 6 6 +/- 4 17 +/- 13 GROUP Ill Q15-1 23 +/- 6 21 +/- 5 23 +/- 6 15 +/- 5 14 +/- 5 (1) 25 +/- 7 28 +/- 6 22 +/- 5 18 +/- 5 14 +/- 5 14 +/- 4 15 +/- 5 14 +/- 5 13 +/- 5 10 +/- 5 11 +/- 4 16 +/- 5 17 +/- 5 11 +/- 5 19 +/- 5 10 +/- 5 13 +/- 6 13 +/- 4 11 +/- 5 9 +/- 5 22 +/- 5 16 +/- 5 17 +/- 5 12 +/- 5 9 +/- 5 14 +/- 5 25 +/- 6 16 +/- 4 32 +/- 5 30 +/- 6 21 +/- 6 22 +/- 4 14 +/- 5 11 +/- 4 23 +/- 5 20 +/- 5 13 +/- 5 23 +/- 5 -13 +/- 5 19 +/- 5 19 +/- 5 13 +/- 4 36 +/- 6 34 +/- 6 18 +/- 6 7 +/- 4 18 +/- 13 Table C-Vl.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/Cl.J METER+/- 2 SIGMA GROUP I -CLOSEST TO THE SITE BOUNDARY GROUP II -INTERMEDIATE OFFSITE GROUP Ill -CONTROL LOCATIONS COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- PERIOD 2SD PERIOD 2SD PERIOD 2SD 01/01/15 -01/29/15 13 23 18 +/- 6 01/01/15 -01/29/15 14 23 18 +/- 6 01/01/15 -01/29/15 15 23 20 +/- 8 01/29/15 -02/26/15 11 26 20 +/- 11 01/29/15 -02/26/15 11 27 19 +/- 10 01/29/15 -02/26/15 14 28 23 +/- 15 02/26/15 -04/02/15 10 20 15 +/- 6 02i26/15 -04/02/15 12 25 17 +/- 8 02/26/15 --04/02/15 14 22 17 +/- 7 04/02/15 -04/30/15 8 16 12 +/- 5 04/02/15 -04/30/15 8 14 12 +/- 4 04/02/15 -04/30/15 10 14 12 +/- 3 04/30/15 -05/28/15 12 18 15 +/- 5 04/30/15 -05/28/15 10 21 14 +/- 6 04/30/15 -05/28/15 11 19 16 +/- 7 05/28/15 -07/02/15 8 15 11 +/- 5 05/28/15 -07/02/15 7 15 11 +/- 5 05/28/15 -07/02/15 9 13 11 +/- 4 07 /02/15 -07 /30/15 7 19 15 +/- 7 07/02/1.5

-07/30/15 11 21 16 +/- 5 07/02/15 -07/30/15 12 22 17 +/- 9 07 /30/15 -09/03/15 9 31 17 +/- 16 07130/15 -09/03/15 ' 11 36 21 +/- 15 07/30/15 -09/03/15 9 32 19 £ 18 09/03/15 -10/01/15 15 27 20 +/- 9 09/03/15 -10/01/15 14 29 21 +/- 10 09/03/15 -10/01/15 14 30 22 +/- 13 10/01/15 -10/29/15 11 17 15 +/- 4 10/01/15 -10/29/15 10 19 15 +/- 6 10/01/15 -10/29/15 11 23 17 +/- 11 ("') 10/29/15 -12/03/15 *10 22 15 +/- 7 10/29/15 -12/03/15 10 22 16 +/- 6 10/29/15 -12/03/15 13 23 17 +/- 8 I 12/03/15 -12/31/15 6 31 21 +/- 19 12/03/15 -12/31/15 6 41 24 +/- 24 12/03/15 -12/31/15 7 36 24 +/- 28 ...... N 01/01/15 -12131/15 6 31 16 +/- 11 01/01/15 -12/31/15 6 41 17 +/- 12 01/01/15 -12/31/15 7 36 18 +/- 13 Table C-Vl.3 SITE COLLECTION PERIOD A3-1 01/01/15 -04/02/15 04/02115 -07/02115 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN E1-2 01/01/15 -04/02115 04/02/15 -07 /02/15 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN F1-3 01/01/15 -04/02115 04/02/15 -07 /02/15 07/02/15 -10/01/15 10/01/15 -12/31/15 MEAN G2-1 01/01/15 -04/02,115 04/02/15 -07 /02/15 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN H3-1' 01/01/15 -04/02/15 04/02/15 -07 /02/15 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN* M2-1 01/01/15 -04/02/15 04/02/15 ° 07 /02115 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN 015-1 01/01/15 -04/02115 04/02115 -07 /02115 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA Be-7 Mn-54 Co-58 81 +/-'46 <6 76+/-28 <3 53 +/- 39 < 3 41 +/- 20 < 2 63 +/- 38 68 +/- 37 < 4 62+/-32 <3 80 +/- 28 < 3 42 +/- 21 < 3 63 +/- 32 < 69 < 6 67+/-32 <5 68 +/- 36 < 3 63 +/- 21 < 2 66 +/- 5 64+/-38 <3 74 +/- 28 < 2 63 +/- 37 < 3 49+/-28 <4 62 +/- 20 < 94 < 5 112+/-52 <5 54+/-26 <2 39 +/- 24 < 2 68 +/- 77 85 +/- 37 < 4 65 +/- 30 < 4 103 +/- 28 < 2 44+/-22 <2 74 +/- 51 78 +/- 34 < 3 53+/-28 <3 75 +/- 30 < 3 42 +/- 28 < 4 62 +/- 35 <7 <4 <3 <2 < 5 <4

<3 <4 < 9 <4 <4 < 3 < 5 <3 <4 < 3 <9 <9 <3 <3 <4 <4 <4 <3 <5 <2 <4 <4 Co-60 < 3 <_4 .< 2 < .. 3 <4 < 3 <2 <2 <7 <4 <4

<4 < 3 <4 < 3 <6 <5

<2 < 2 <3 <2 < 3 <2

<2 <4 < 3 <4 < 3 Nb-95 <6 <4 <4 <3 <6 <5 <4 < 3 <7 <5 <5 <4 <4 <4 < 5 < 5 <9 <7 <3 <3 <4 <6 < 4. < 3. <5 < 1 <4 <4 Zr-95 <9 <6 < 6 <4 <8 <6 < 5 <6 < 13 < 10 < 9 < 5 < 9 <6 < 7 < 8 < 14 < 13 <5 <7 < 10 < 9 < 8 < 5 < 9 <6 < 8 < 9 Cs-134 Cs-137 < 5 < 3 < 3 <2 <3 <3 < 3 <-3 <4 <5 <4

<2 <_4 < 3 < 3 <4 <5 < 5 < 3 <2 <2 <4 <2 <3 <4 <4 <3 <4 <4 <3 <3 <2 <3 <2 <2 <3 <4 <5

<3 < 3 <3 < 3 <2 <3 <6 <6 <2 < 3 <2 <3 <2 <3 <4 <3 <3

<3 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-13 Table C-Vll.1 COLLECTION PERIOD 01/01/15 -01/08/15 01/08/15 -01/15/15 01 /15/15 -01 /22/15 01/22/15 -01/29/15 01/29/15 -02/05/15 02/05/15 -02/12/15 02/12/15 -02/19/15 02/19/15 -02/26/15 02/26/15 -03/05/15 03/05/15 -03/12/15 03/12/15 -03/18/15 03/18/15 -03/26/15 03/26/15 -04/02/15 04/02/15 -04/09/15 04/09/15 -04/16/15 04/16/15 -.04/23/15 04/23/15 -04/30/15 04/30/15 -05/07 /15 05/07 /15 -05/14/15 05/14/15 -05/21/15 05/21/15 -05/28/15 05/28/15 -06/04/15 06/04/15 -06/10/15 06/10/15 -06118/15 06/18/15 -06/25/15 06/25/15 -07/02/15 07 /02/15 -07 /09/15 07/09/15 -07/16/15 07116/15 -07/23/15 07/23/15 -07/30/15 07 /30/15 -08/06/15 08/06/15 -08/13/15 08/13/15 -08/19/15 08/19/15 -08/27/15 08/27 /15 -09/03/15 09/03/15 -09/10/15 09/10/15 -09/16/15 09/16/15 -09/24115 09/24/15 -10/01/15 10/01/15 -10/08/15 10/08/15 -10/15/15 10/15/15 -10/22/15 10/22/15 -10/29/15 10/29/15 -11 /05/15 11/05/15 -11/12/15 11/12/15 -11/19/15 11/19/15 -11/25/15 11/25/15 -12/03/15 12/03/15 -12/1 0/15 12/10/15 -12117/15 12117/15 -12/23/15 12/23/15 -12/31/15 MEAN CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I E1-2 F1-3 < 29 < 29 < 43 < 42 < 47 < 18 < 26 < 57 < 63 < 61 < 64 < 52 < 62 < 26 < 69 < 44 < 46 < 64 < 29 < 64 < 67 < 45 < 55 < 43 < 58 < 41 < 59 < 59 < 47 < 48 < 43 < 35 < 54 < 42 < 41 < 49 < 51 < 43 < 43 < 43 < 41 < 27 < 38 < 68 < 47 < 17 < 55 < 33 < 37 < 62 < 69 < 69 < 54 < 61 < 61 < 29 < 45 < 63 < 52 < 61 < 26 < 68 < 43 < 45 < 24 < 10 < 63 < 66 < 44 < 53 < 42 < 57 < 41 < 59 < 59 < 47 < 48 < 43 < 35 < 55 < 42 \. < 41 < 49 < 52 < 43 < 44 < 43 < 41 < 65 < 38 < 68 < 47 < 17 < 55 < 33 < 37 < 62 < 69 < 69 < 54 < 38 < 62 < 29 < 45 A3-1 < 29 < 26 < 43 < 52 < 67 < 69 < 60 < 48 < 23 < 54 < 60 < 38 < 67 < 26 < 64 < 55 < 42 < 43 < 66 < 62 < 38 < 58 < 33 < 13 < 45 < 60 < 15 < 40 < 39 < 43 < 64 < 55 < 51 < 28 < 22 < *57 < 68 < 27 < 58 < 55 < 15 < 43 < 42 < 29 < 61 < 60 < 51 < 47 < 54 < 55 < 36 < 24 GROUP II G2-1 H3-1 < 30 < 30 < 43 < 48 < 48 < 47 < 60 < 59 < 23 < 63 < 66 < 54 < 64 < 27 < 70 < 45 < 47 < 68 < 30 < 64 < 69 < 46 < 22 < 44 < 60 < 43 < 66 < 58 < 46 < 48 < 42 < 35 < 56 < 41 < 47 <*48 < 51 < 44 < 43 < 42 < 16 < 28 < 37 < 67 < 46 < 17 < 23 < 33 < 36 < 24 < 68 < 68 < 53 < 37 < 23 < 11 < 44 < 25 < 53 < 49 < 27 < 70 < 61 < 46 < 64 < 30 < 64 < 68 < 45 < 55 < 43 < 56 < 62 < 68 < 59 < 36 < 51 < 36 < 55 < 41 < 45 < 49 < 52 < 42 < 44 < 43 < 42 < 66 < 67 < 69 < 47 < 17 < 55 < 34 < 37 < 63 < 62 < 54 < 54 < 38 < 62 < 29 < 49 (1) M2-1 < 30 < 48 < 44 < 53 < 69 < 70 < 61 < 20 < 23 < 23 < 24 < 39 < 63 < 26 < 65 < 56 <43 < 54 < 67 < 63 < 38 < 66 < 33 < 35 < 45 < 60 < 35 < 40 < 40 < 44 < 65 < 55 < 50 < 67 < 53 < 57 < 68 < 65 < 59 < 55 < 15 < 43 < 43 < 29 < 61 < 60 < 52 < 47 < 54 < 55 < 37 < 47 I GROUP Ill Q15-1 < 29 < 47 < 42 < 53 < 68 < 42 < 48 < 23 < 54* < 60 < 38 < 67 < 26 < 64 < 55 < 42 < 43 < 66 < 62 < 38 < 58 < 33 < 35 < 45 < 61 < 36 < 40 < 40 < 44 < 65 55 < 50 < 68 < 53 < 58 < 68 < 66 < 59 < 56 < 15 < 44 < 46 < 29 < 61 < 61 < 52 < 47 < 55 < 56 < 37 < 48 (1) (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-14 Table C-Vlll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA CONTROL FARM INDICATOR FARM COLLECTION TM-M-K15-3 I TM-M-E2-2 TM-M-F4-1 TM-M-G2-1 TM-M-P4-1 PERIOD 01/07/15 < 0.6 < 0.4 < 0.5 < 0.5 < 0.5 02/11/15 < 0.4 < 0.5 < 0.5 < 0.8 < 0.5 03/11/15 < 0.4 < 0.6 < 0.4 < 0.5 < 0.5 03/25/15 < 0.3 < 0.4 < 0.2 < 0.4 < 0.3 04/08/15 < 0.6 < 0.6 < 0.7 < 0.6 < 0.6 04/22/15 < 0.3 < 0.5 < 0.7 < 0.4 < 0.4 05/06/15 < 0.5 < 0.9 < 0.5 < 0.8 < 0.9 05/20/15 < 0.6 < 0.7 < 0.7 < 0.7 < 0.6 06/03/15 < 0.7 < 0.9 < 0.6 < 0.7 < 0.5 06/17/15 < 0.4 < 0.7 < 0.6 < 0.6 < 0.7 07/01/15 < 0.5 < 0.7 < 0.5 < 0.7 < 0.6 07/15/15 < 0.9 < 0.8 < 0.8 < 0.8 < 0.7 07/29/15 < 0.7 < 0.8 < 0.9 < 0.9 < 0.9 08/12/15 < 0.6 < 0.6 < 0.6 < 0.5 < 0.5 08/26/15 < 0.5 < 0.7 < 0.5 < 0.7 . < 0.7 09/09/15 < 0.3 < 0.5 < 0.4 < 0.6 < 0.6 09/23/15 < 0.6 < 0.5 < 0.5 < 0.5 < 0.4 10/07/15 < 0.4 < 0.5 < 0.6 < 0.5 < 0.7 10/21/15 < 0.6 < 0.4 < 0.6 < 0.5 : < 0.4. 11/04/15 < 0.4 < 0.6 < 0.6 < 0.7 < 0.6 11/18/15 < 0.8 < 0.8 < 0.9 < 0.6 < 0.9 12/02/15 < 0.9 < 1.0 < 0.6 < 0.8 < 1.0 MEAN C-15 Table C-Vlll.2 COLLECTION PERIOD 01/07/15 -03/25/15 04/08/15 -06/17/15 07/01/15 -09/23/15 10/07/15 -12/02/15 MEAN (") I -O"I CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+ 2 SIGMA CONTROL FARM INDICATOR FARM K15-3 P4-1 E2-2 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 < 4.0 < 0.4 < 2.1 < 0.4 < 2.0 < 0.4 < 3.6 < 3.9 < 0.6 < 3.5 < 0.7 < 4.3 < 0.7 < 4.2 < 3.5 < 0.3 < 3.6 < 0.7 < 3.6 < 0.3 < 3.5 < 3.9 < 0.7 < 4.2 < 0.4 < 2.6 < 0.5 < 3.0 F4-1 G2-1 SR-90 SR-89 SR-90 < 0.4 < 4.6 < 0.4 < 0.6 < 4.9 < 0.7 < 0.4 < 3.7 < 0.4 < 0.7 < 3.9 < 0.6 Table C-Vlll.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA SITE COLLECTION K-40

Cs-137 Ba-140

La-140 PERIOD E2-2 *01/07/15 1343 +/- 148 < 6 < 8 < 34 <7 02/11/15 1355 +/- 187 < 7 < 6 < 48 < 15 03/11/15 1362 +/- 191 < 8 < 9 < 49* < 14 03/25/15 1276 +/- 134 < 5 < 6 < 55 < 13 04/08/15 1172 +/- 155 < 6 < 7 < 42 < 13 04/22/15 1309 +/- 98 <4 <4 < 41 < 13 05/06/15 1197 +/- 213 < 7 < 11 < 38 < 14 05/20/15 1045 +/- 172 < 6 < 7 < 40' < 10 06/03/15 1409 +/- 185 <7 <7 < 35 < 7 06/17/15 1505 +/- 174 < 8 < 7 < 42 < 12 07/01/15 1200 +/- 206 < 10 < 10 < 48 < 13 07/15/15 1343 +/- 173 < 5 < 6 < 43 < 10 07/29/15 1447 +/- 161 <7 <7 < 35 < 12 08/12/15 1369 +/- 278 <7 < 11 < 58 < 14 08/26/15 1310 +/- 197 < 8 < 12 < 40 < 13 09/09/15 1408 +/- 165 < 7 < 9 < 37 < 9 09/23/15 1422 +/- 194 < 7 < 7 < 27 < 12 10/07/15 1296 +/- 184 < 9 < 12 < 35 < 10 10/21/15 1340 +/- 214 <8 < 12 < 29 < 9 11/04/15 1063 +/- 216 < 9 < 10 < 47 < 15 11/18/15 1321 +/- 161 < 7 <6 < 27 < 7 12/02/15 -1260 +/- 140 < 7 < 6 < 36 < 13 MEAN 1307 +/- 231 F4-1 01/07/15 1396 +/- 160 <7 <7 < 29 < 12 02/11/15 1522 +/- 175 <6 < 7 < 45 < 15 03/11/15 1360 +/- 187 < 8 < 8 < 34 < 11 03/25/15 1431 +/- 101 <4 < 5 < 42 < 12 04/08/15 1657 +/- 175 < 6 < 7 < 42 < 9 04/22/15 1367 +/- 89 < 3 <4 < 37 < 10 05/06/15 1395 +/- 198 < 5 < 7 < 35 < 11 05/20/15 1390 +/- 98 < 6 < 5 < 28 < 8 06/03/15 1464 +/- 162 < 8 < 8 < 39 < 11 06/17/15 1433 +/- 177 < 5 < 9 < 32. < 11 07/01/15 1404 +/- 217 < 7 < 7 < 46 < 13 07/15/15 1266 +/- 135 < 5 < 6 < 36 <7 07/29/15 '1330 +/- 149 <6 < 7 < 30 < 9 08/12/15 1479 +/- 243 < 10 < 8 < 46 < 12 08/26/15 1242 +/- 199 < 7 < 10 < 46 <7 09/09/15 1381 +/- 156 < 6 <7 < 24 < 8 09/23/15 1346 +/- 199 < 10 < 11 < 37 < 14 10/07/15 1487 +/- 184 <*7 < 7 < 26 < 9 10/21/15 1617 +/- 251 < 10 < 9 < 32 < 12 11/04/15 1395 +/- 216 "< 9 < 9 < 40 < 9 11/18/15 1477 +/- 146 < 10 < 10 < 35 < 10 12/02/15 1347 +/- 165 <7 < 6 < 38 < 11 MEAN 1418 +/- 197 C-17 Table C-Vlll.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD G2-1 01/07/15 1146 +/- 157 < 7 < 7 < 34 < 9 02/11/15 975 +/- 153, < 7 < 8 < 36 < 9 03/11/15 1151 +/- 181 <6 < 9 < 42 < 14 03/25/15 1065 +/- 112 < 5 < 6 < 49 < 13 04/08/15 773 +/- 123 < 6 < 7 < 47 < 15 04/22/15 859 +/- 88 <4 < 5 < 46 < 15 05/06/15 703 +/- 141 < 9 < 10 < 49 < 12 05/20/15 1387 +/- 169 < 7 < 8 < 43 < 9 06/03/15 1089 +/- 147 < 6 < 7 < 36 < 13 06/17/15 831 +/- 121 < 7 <7 < 35 < 14 07/01/15 829 +/- 155 < 10 < 10 < 47 < 14 07/15/15 1115 +/- 151 < 7 < 6 < 42 < 15 07/29/15 1074 +/- 124 < 7 < 7 < 36 < 11 08/12/15 895 +/- 159 < 8 < 9 < 47 < 15 08/26/15 1012 +/- 148 < 8 < 9 < 40 < 10 09/09/15 1077 +/- 147 < 7 < 8 < 31 < 7 09/23/15 827 +/- 164 < 9 < 9 < 37 < 13 10/07/15 1021 +/- 155 < 6 < 6 < 19 < 8 10/21/15 777 +/- 134 < 8 < 8 < 37 < 13 11/04/15 934 +/- 165 < 9 < 9 < 41 < 10 11/18/15 1239 +/- 130 < 6 < 6 < 20 < 6 12/02/15 885 +/- 175 ' < 7 < 9 < 40 < 8 MEAN 985 +/- 341 K15-3 01/07/15 1204 +/- 133 < 5 < 5 < 27 <6 02/11/15 1319 +/- 166 <7 < 7 < 45 < 11 03/11/15 1202 +/- 160 < 7 ' < 8 < 36 < 10 03/25/15 1330 +/- 126 <5 < 5 < 54 < 13 04/08/15 1247 +/- 141 <"5 < 6 < 35 < 10 04/22/15 1477 +/- 161 < 5 < 5 < 52 < 13 05/06/15 1216 +/- 175 < 7 < 7 < 46 < 12 05/20/15 1214 +/- 128 <4 < 6 < 26 < 9 06/03/15 1267 +/- 125 < 5 < 5 < 23 < 9 06/17/15 '1334 +/- 150 < 6 <6 < 31 < 8 07/01/15 1157 +/- 173 < 7 < 8 < 43 < 14 07/15/15 1120 +/- 121 < 5 < 6 < 37 < 8 07/29/15 1360 +/- 147 < 5 < 5 < 24 <"9 08/12/15 "1366 +/- 233 < 8 < 9 < 51 < 11 08/26/15 1368 +/- 149 < 7 < 6 < 26 < 9 09/09/15 1335 +/- 177 <6 < 6 < 26 < 9 09/23/15 1248 +/- 140 "< 7 <7 < 28 < 5 10/07/15 1222 +/- 126 < 5 < 5 < 18 < 6 10/21/15 1234 +/- 239 < 7 < 13 < 40 <: 8 11/04/15 1220 +/- 188 < 7 < 10 < 46 < 13 11/18/15 1147 +/- 143 <4 < 6 < 19 < 2 12/02/15 1282 +/- 193 < 12 < 10 < 56 < 12 MEAN 1267 +/- 173 C-18 Table C-Vlll.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD P4-1 01/07/15 1389 +/- 163 < 6 < 7. < 29 < 9 02/11/15 1478 +/- 187 < 7 < 7 < 45 < 14 03/11/15 1526 +/- 160 < 9 < 10 < 48 < 12 03/25/15 1271 +/- 120 <4 < 5 < 34 < 13 04/08/15 1375 +/- 143 < 5 <6' < 37 < 8 04/22/15 1487 +/- 101 <4 <4 < '38 < 12 05/06/15 1491 +/- 200 < 8 < 8 < 44 < 12 05/20/15 1485 +/- 195 < 11 < 12 < 56 < 14 06/03/15 1367 +/- 205 < 7 < 8 < 41 < 9 06/17/15 1396 +/- 139 < 5 < 7 < 27 < 7 07/01/15 1315 +/- 150 < 5 < 6 < 27 < 9 07/15/15 1421 +/- 164 < 6 <7 < 47 < 14 07/29/15 1346 +/- 134 <4 < 5 < 24 < 6 08/12/15 1332 +/- 241 < 9 < 11 < 54 < 10 08/26/15 1508 +/- 201 < 8 < 10 < 35 < 10 09/09/15 1501 +/- 195 < 9 < 8 < 34 < 11 09/23/15 1493 +/- 140 < 6 < 6 < 23 < 6 10/07/15 1475 +/- 166 < 5 < 8 < 24 < 6 10/21/15 1484 +/- 193 <7 .< 8 < 27 < 8. 11/04/15 1193 +/- 221 <4 <. 7 < 27 < 14 11/18/15 1382 +/- 128 < 5 < 5 < 18 <4 12/02/15 1382 +/- 200 < 7 < 9 < 42 < 11 MEAN 1414 +/- 175 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, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION SR-90 Be-7 K-40 1-131 *Cs-134 Cs-137 PERIOD 810-2 Brocolli Leaves 06/29/15 8 +/-0 2 395 +/- 227 4272 +/- 544 < 58 < 25 < 29 Cabbage (& Leaves) 06/29/15 < 1 160 +/- 77 3661 +/- 193 < 17 < 8 < 9 Sunflow¢r Leaves 06/29/15 8 +/- 2 1965 +/- 326 6947' +/- 690. < 53 < 19 < 27 Cabbage (& Leaves) 07/20/15 <4 153 +/- 128 2261 +/- 333 < 44 < 15 < 19 Brocolli Leaves 07/27/15 7 +/- 2 296 +/- 58 4532 +/- 166 < 38. < 6 <6 Cabbage (& Leaves) 07/27/15 < 2 < 86 3123 +/- 174 < 50 < 8 < 8 Sunflower .Leaves 07/27/15 < 3 1452 +/- 114 7653 +/- 234 < 52 < 8 < 9 Sweet Corn 08/03/15 < 122 2175 +/- 271 < 50 < 9 < 13 Tomatoes 08/03/15 < 117 1999 +/- 252 < 53 < 10 < 12 Cabbage (& Leaves) 08/31/15 4 +/- 2 < 389 3164 +/- 901 < 51 < 50 < 55 Cabbage (& Leaves) 09/28/15 < 3 < 202 3640 +/- 557 < 46 < 24 < 29 Sweet Potatoes 10/05/15 < 137 3530 +/- 482 < 22 < 18 < 21 MEAN 7 +/- 3 737 +/- 1550 3913 +/- 3547 E1-2 Cabbage (&Leaves) 07/20/15 < 3 263 +/- 25.4 7428 +/- 576 < 47 << 18 < 19 Sweet Corn 08/03/15 < 124 2339 +/- 318 < 56 < 13 < 14 Tomatoes 08/03/15 < 103 3406 +/- 243 < 51 < 10 < 10 Sweet Potatoes 10/05/15 < 100 3480 +/- 369 < 17 < 12 < 14 MEAN 263 +/- 0 4163 +/- 4476 H1-2 Eggplant Leaves 07/27/15 <3 996 +/- 106 6136 +/- 210 < 49 <7 < 8 Squash Leaves 07/27/15 3 +/- 2 1019 +/- 101 4172 +/- 167 < 40 < 6 <6 Zuchinni Leaves 07/27/15 < 3 \ 860 +/- 85 3662 +/- 180 < 47 < 7 < 8 Eggplant Leaves 08/31/15 10 +/- 5 1212 +/- 499 4681 +/- 1382 < 47 < 30 < 38 Squash Leaves 08/31/15 < 5 627 +/- 265 3355 +/- 892 < 57 < 39 < 49 Zuchinni Leaves 08/31/15 11 +/- 4 < 475 3026 +/- 914 < 52 < 46 < 54 Squash Leaves 09/28/15 < 3 1654 +/- 271 2715 +/- 474 < 43 < 22 < 26 Turnip Greens 09/28/15 6 +/- 3 < 306 3860 +/- 558" < 54 < 25 < 27 Zuchinni Leaves 09/28/15 <4 499 +/- 215 2079 +/- 408 < 40 < 18 < 24 MEAN 7 +/- 8 981 +/- 766 3743 +/- 2377 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE* POSITIVE VALUES C-20 Table C-X.1 QUARTERLY OSLO RES UL TS FOR THREE MILE ISLAND NUCLEAR STATION, 2015 . RESULTS IN UNITS OF MILLI REM/QUARTER

STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +/-2 S.D. A1-4 19.9 +/- 2.9 18.1 19.3 21.5 20.5 A3-1 19.7 +/- 2.6 18.6 18.8 21.4 20.1 A5-1 23;6 +/- 3.0 23.0 22.2 25.7 23.5 A9-3 20.5 +/- 3.1 18.7 19.7 22.1 *21.4 81-1 20.4 +/- 3.5 19.0 18.8 21.6 22.2 81-2 20:6 +/- 2.2 19.4 20.0 22.0 20.8 82-1 . .Z0.3 +/- 3.3 18.9 18.9 22.3 20.9 85-1 23.1 +/- 3.2 21.9 21.6 24.6 24.4 C1-1 23.2 +/- 2.5 21.6 23.3 24.6 23.3 C1-2 19.7 +/- 1.3 19.1 19.2 20.4 20.1 C2-1 22.6 +/- 4.2 21.5 20.7 25.5 22.5 C5-1 23.9 +/- 4.0 22.0 22.4 26.2 24.8 C8-1 24.3 +/- 5.0 21.3 23.1 26.5 26.2 01-1 20.3 +/- 2.6 19.7 18.8 21.6 21.1 01-2 21.3 +/- 3.1 19.8 20.1 22.6 22.6 02-2 26.1 +/- 4.1 24.3 25.4 29.0 25.5 06-1 26.0 +/- 4.6 22.8 26.0 28.3 26.7 E1-2 20.7 +/- 2.3 20.0 19.7 22.2 21.0 E1-4 20.0 +/- 3.7 18.3 18.4 21.2 21.9 E2-3 24.4 +/- 3.4 22.3 23.8 26.2 25.2 E5-1 25.9 +/- 2.8 24.3 26.2 27.6 25.4 E7-1 23.7 +/- 4.8 21.3 22.6 26.9 23.9 F1-1 .. 22.3 +/- 1.9 21.3 21.9 23.5 22.6 F1-2 21.0 +/- 3.1 19.il 19.5 22.6 21.9 F1-4 20.3 +/- 3.7 19.3 18.2 21.3 22.3 F2-1 25.1 +/- 3.5 23.8 24.1 27.6 25.0 F5-1 25.6 +/- 4.6 23.3 24.6 28.7 25.9 G1-2 23.3 +/- 4.1 21.1 22.3 25.8 24.1 G1-3 19.6 +/- 2.0 18.6 19.0 20.8 20.0 G1-5 20.0 +/- 2.0 18.6 19.9 20.7 20.7 G1-6 20.5 +/- 2.4 19.0 20.1 21.5 21.4 G2-4 27.0 +/- 3.9 24.6 26.8 29.4 27.0 G5-1 23.0 +/- 3.8 20.7 22.1 24.7 24.3 H1-1 22.3 +/- 2.1 21.1 21.6 23.0 23.3 H3-1 19.6 +/- 2.1 19.1 18.5 20.0 20.9 H5-1 19.1 +/- 2.6 17.8 18.4 20.8 19.3 H8-1 33.1 +/- 6.9 30.1 31.0 37.8 33.3 J1-1 20.4 +/- 2.1 19.4 19.8 21.7 20.8 J1-3 18.1 +/- 1.8 17.6 17.2 19.1 18.6 J3-1 22.6 +/- 4.2 21.0 20.6 24.4 24.5 J5-1 25.2 +/- 4.4 22.6 24.3 27.6 26.2 J7-1 26.1 +/- 4.9 24.0 24.6 29.5 26.2 K1-4 20.3 +/- 2.4 18.9 19.9 21.7 20.8 K2-1 24.5 +/- 3.6 22.5 24.4 26.9 24.3 K3-1 20.4 +/- 2.8 19.0 19.4 21.7 21.5 K5-1 23.9 +/- 2.3 22.5 23.4 24.3 25.2 K8-1 23.5 +/- 3.3 23.1 21.4 24.5 25.1 C-21 Table 9-X.1 QUARTERLY OSLO RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF MILLIREM/QUARTER STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +/-2S.D. L 1-1 21.2 +/- 4.7 19.3 19.8 24.5 21.3 L 1-2 21.0 +/- 2.5 19.8 20.2 22.4 21.7 L2-1 22.9 +/- 2.9 21.2 -24.0 23.4 L5-1 20.4 +/- 2.7 20.0 18.7 21.7 21.2 L8-1 22.8 +/- 3.8 20.4 22.1 24.5 24.1 M1-1 20.0 +/- 3.8 17.7 19.2 21.9 21.2 M1-2 22.2 +/- 2.6 21.2 21.4 24.1 22.2 M2-1 20.5 +/- 2.4 19.3 19.6 21.2 21.8 M5-1 22.2 +/- 2.9 21.0 20.9 23.1 23.8 M9-1 26.7 +/- 5.2 23.1 26.3 28.8 28.4 N1-1 21.6 +/- 3.3 20.3 20.4 23.8 21.7 N1-3 22.2 +/- 5.0 19.7 21.4 25.6 22.1 N2-1 22.9 +/- 2.6 21.4 22.2 24.2 23.7 N5-1 20.1 +/- 3.9 18.2 19.0 20.4 22.6 N8-1 23.2 +/- 2.9 21.7 22.7 25.2 23.3 P1-1 21.2 +/- 4.2 19.1 19.9 23.7 22.2 P1-2 24.7 +/- 13.0 18.0 23.5 33.6 23.8 P2-1 25.6 +/- 3.3 23.9 24.5 27.2 26.8 P5-1 22.6 +/- 3.2 20.7 21.7 23.8 24.0 P8-1 20.3 +/- 2.3 19.8 19.0 21.7 20.6 Q1-1 21.8 +/- 4.4 19.5 20.5 24.4 22.7 Q1-2 19.6 +/- 4.6 17.2 18.7 22.6 19.9 Q2-1 20.0 +/- 1.8 18.8 19.7 20.9 20.4 Q5-1 21.4 +/- 2.5 21.1 20.0 23.0 21.4 Q9-1 21.8 +/- 2.2 21.2 20.5 22.7 22.7 R1-1 20.6 +/- 4.6 17.7 20.0 23.1 21.4 R1-2 20.2 +/- 2.3 19.0 19.5 20.9 21.4 R3-1 25.0 +/- 4.0 22.7 24.0 26.9 26.5 R5-1 24.4 +/- 3.1 22.9 23.3 25.9 25.6 R9-1 24.1 +/- 2.7 22.6 23.3 25.0 25.5 810-1 23.2 +/- 3.0 22.8 21.7 25.3 22.8 015-1 23.3 +/- 2.9 21.8 22.4 24.8 24.2 F10-1 26.9 +/- 4.7 24.1 25.8 29.0 .28.6 F25-1 24.0 +/- 1.9 23.5 23.2 25.3 24.1 G10-1 31.0 +/-4.2 28.8 30.7 33.9 30.7 G15-1 26.3 +/- 4.0 24.4 25.9 29.1 25.6 H15-1 22.6 +/- 3.5 20.9 21.3 24.4 23.7 J15-1 27.2 +/- 4.9 24.5 25.9 29.9 28.5 K15-1 21.7 +/- 3.4 19.8 20.8 23.1 23.2 L 15-1 22.9 +/- 3.0 20.9 22.9 24.5 23.2 N15-2 24.4 +/- 2.1 22.9 24.2 25.3 25.0 015-1 24.6 +/- 3.4 22.4 24.5 26.5 25.1 R15-1 22.1 +/- 2.9 20.5 21.4 23.8 22.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-22 TABLEC-X.2 COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC TABLE C-X.3 LOCATION SITE BOUNDARY INDICATOR CONTROL MEAN QUARTERLY OSLO RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF MILLIREM/OUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA SITE BOUNDARY INDICATOR CONTROL +/-2 S.D. 18.8 +/- 1.9 21.4 +/-4.3 22.8 +/- 5.1 19.7 +/- 2.8 22.0 +/- 5.1 23.9 +/- 5.7 22.6 +/- 6.1 24.8 +/- 6.1 26.4 +/- 6.5 21.2 +/- 2.4 23.7 +/- 5.0 25.1 +/- 4.9

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF NJILLIREMOUARTER SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/-2S.D. 76 17.2 33.6 20.6 +/- 4.6 239 17.8 37.8 23.0 +/- 5.8 44 19.8 33.9 24.5 +/- 6.0 SITE BOUNDARY STATIONS -A1-4, 81-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, L1-1, M1-1, N1-3, P1-2, 01-2, R1-1 INDICATOR STATIONS -A3-1, AS-1, A9-3, 81-1, 810-1, 82-1, 85-1, C1-1, C2-1, C5-1, C8-1, D1-2, 02-2, 06-1, E1-2, E2-3, ES-1, E7-1, F1-1, F10-1, F2-1, F5-1, G1-2, G2-4, GS-1, H3-1, H5-1, HB-1, J1-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, KB-1, L1-2, L2-1, L5-1, LB-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, NB-1, P1-1, P2-1, P5-1, PB-1, 01-1, 02-1, 05-1, 09-1, R1-2, R3-1, R5-1, R9-.1 CONTROL STATIONS -D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L 15-1, N15-2, 015-1, C-23 n I N ..j::. FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2015 o Station*J1-2

(Downstream of

,_ -.. -* *rullill Station* (Goritr61) 100000 .._ Q) :!::::! _J 10000 .._ Q) 0.. Cf) 1000 Q) *;:: :J 100 () 0 () 0:: 10 Jan 1000000 .._ Q) 100000 +" :.:::i .._ Q) 0. 10000 --(/) Q) 1000 --*c:: :J (.) 0 100 --(.) a. 10 Jan Feb Mar Apr _ May Jun Jul Month Aug Sep Oct Nov *Station K1-1 (TMINS Liquid Discharge)

Feb Mar Apr -May Jun Jul Aug Sep Oct Nov Dec Month Dec

..... Q) n -I ::i N ..... Vl Q) c.. I/) Q) *c:: :::::i t) 0 t) a: FIGURE C-2' -Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2015 -Indicator Samples -----Control Samples Significant Events Major Atm. Nuclear Weapon Tests 11000 TMI-1 Critical June 1974 June 1974 September 197 -----------------

TMI-2 Critical March 1978 September 1976 November 197 10000 TMI-2 Accident March 1979 September 1977 March 1978 TMI-2 RB Purge June 1980 December 1978 October 1980 8000 7000 6000 5000 ------------------------------------------------------

4000 ---------------------------------

3000 ---------------------------------

2000 1000 0 -1000 "<I" LO co r-co Ol 0 ...... N (') "<I" Lb co r-co Ol 0 ...... N (') "<I" LO co r-co Ol 0 ...... N (') "<I" LO co r-co Ol 0 N r-r-r-r-r-r-co co co co co co co co . co co Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 .0 0 0 0 0 0 ...... ...... ...... Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 0 0 0 0 0 0 ...... ...... ...... ...... ...... ...... ...... N N N N N N N N N N N N N Year (') "<I" LO co ...... ...... ...... ...... 0 0 0 0 N N N N

..... Q) ("') -I ::::i N ..... 0\ Q) a. II) Q) *c:: :::::i (.) 0 0.. FIGURE C-3 .Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2015 D Indicator Samples IT! Control Samples 9 _,_ -------------------------------------------------------------------------------8 -----------------------------------------------------------

-* ---------------------7 _ ... --------------------------------------------------------------------------------

6 _,_ --------------------------------------------------------------------------------

5 _,_ --------------------------------------------------------------------------------

4 _._ ------------------------------------------------------

-,.::_------3 _,_ --------------------------------------------

2 1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month n I N -..J FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Mile Island Nuclear Station, 2015 ,_ (]) +-' :..:::i ,_ (]) 0.. "' (]) *c:: ::l 0 0 0 a: ,_ (]) +-' :..:::i ,_ (]) 0.. "' (]) *c:: ::l 0 0

0 0.... NOTE: The mean values are calculated using both the MDCs and the positive values. D Indicator Samples 500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L 400 300 liilll Control Samples 200 ------------------------

100 0 11111 :l!l!l!l! --iiiiliil --_.:* ... -**'1 __ ... *****'1 ___ ..... -'1_. __ ... *****'i_ ... ******'i_

...... -**'1 __ ... -****'1 __ ... ***=::!1---.. ********'i_

... ******'i_

.... *****'i_ ... *******'i_

... ******'i_

... ******'1 __ ... *****'i ;iiiiiili iiiilili Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month *Station K1-1 (TMINS Liquid Discharge) 1000000 100000 10000 1000 100 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month n I N 00 800 700 -"'O --E aoo C> 0 500 :S2 L... Q) a. 400 en Q) *c ::J g '300 (.) a.. .200 100 0 FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984-2015 -Indicator Samples --Control Samples Significant Event -GhemobyJ -----Apr-il-1986. --------.. --------------------------------------------------

"'" LO co I"-CX) O'l 0 .,.... N C') "'" LO co I"-CX) O'l 0 .,.... N C') "'" LO co I"-CX) O'l 0 .,.... N C') "'" LO CX) CX) CX) CX) CX) CX) O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l 0 0 0 0 0 0 0 0 0 0 0 .,.... .,.... .,.... .,.... .,.... O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... N N N N N N N N N N N N N N N N Year

.... Q) -Q) 2 n CJ I :..c N \0 ::J (.) .... Q) a. (/) Q) *c:: ::J CJ 0 CJ c:: FIGURE C-6 Mean 'Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2015 -Indicator

-"---+---Control

---=S1>.:'gn=1='fi=c=an=t-=E...,.v""'en::.:t,,_s

__ Ma'or Atm. Nuclear Wea on Test TMI-1 Critical June 1974 March 1972 June 1973 0.35 1MI-2 Critical March 1978 June 1974 September 19 1MI-2 Accident March 1979 September 1976 November 197 1MI-2 RB Purge

JUne 1980 September 1977 , March 1978 0.3 Chemob 1 A ril 1986 December 1978 October 1980 .......

_____________________________________

_ 0.25 0.2 .0.15 0.1 0.05. 0 N C') "<!' in co I' co mo ..... N C') "<!' in co I' co mo ..... N C'> "<!' in co I' co m 0 ..-N C') "<!' in co I' co m 0 ..-N C') "<!' in co I' I' I' I' I' I' I' I' co co co co co co co co co co .m m mm m mm m mm 0 00 0 0 0 0 0 00 ..... ..... ..... ..... ..... ..... ..... m mm m mm m mm m m mm m mm m mm m mm m mm m mm 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 0 ..........

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

..... ..... N NN N N NN N NN N NN N NN N Year (1 I I w 0 FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007-: 2015 0.100 * -Indicator

--+---Control 0.090 0.080 .... 0.070 Q) -Q) 2 u 0.060 :.a :::J () (D 0.050 a. en Q) '§ 0.040 u 0 u a: 0,030 0.020 0.010 0.000 I"-r--r--r--tO tO tO O'l O'l O'l O'l 0 0 0 ...... ...... ...... ...... N C\I N (") (") (") (") '<I' '<I' '<I' lO lO 0 Q Q 0 Q 0 .Q 0 Q 0 ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ..---.. -.. -.. -.. -.. <<; -.. -.. -.. ;:::: -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. ;:::: 0 lO tO 0 lO tO ..--N 0 (") O'l r--0 0 (") r--N lO r--C\I lO O'l C\I ..--Q Q ...... Q ...... ...... ...... Q ...... Q ...... 0 Q ...... ...... ...... 0 -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. ...... '<I' tO ...... (") co 0 ..--'<I' tO ...... (") co 0 ...... lO tO ..--(") co 0 ...... tO ...... (") co 0 ..--0 0 0 ...... 0 0 ..--0 0 0 ...... 0 0 ...... 0 0 0 ...... 0 0 ..--0 0 0 ..--0 0 0 0 Month I Day I Year lO lO ..--...... -.. -.. O'l (") ...... 0 -.. -.. tO C\I 0 I.... Q) +-' ::::i (j I.... I Q) w _. a. CJ) Q) *c::: ::J (.) 0 (.) a..: FIGURE C-8. Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2015 -Indicator Samples ----+-Control Samples Significant Events Major Atm. Nuclear Weapon Tests 9 TMI-2 Accident March 1979December 1978 October 1980 TMI-2 RB Purge June 1980 Chernobyl April 1986 8 7 6 5 4 3 2 1 0 Ol 0 ..--N C') '<t LO (!) I"-c:o Ol 0 ..--N C') '<t LO (!) I"-c:o Ol 0 ..--N C') '<t LO (!) I"-c:o Ol 0 N C') I"-c:o c:o c:o c:o c:o c:o c:o c:o c:o c:o Ol Q) Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 0 0 0 ..--..--..--..--Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ..--..--..--N N N N N N N N N N N N N N Year '<t LO (!) ..--..--..--0 0 0 N N N Intentionally left blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY Intentionally left blank The following section presents the results of data analysis performed by the QC laborator}', Environmental Inc. Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TSE) and the QC laboratory.

Comparison of the results for most media were within expected ranges. D-1 Intentionally left blank D-2

--TABLE D-1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31 /15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07 /28/15 -09/01 /15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN TABLE D-1.2 COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN TABLE D-1.3 IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA Q9-1Q 1.4'+/-0.7 1.2 +/- 0.5 < 1.8 < 1.7 1.8 +/- 0.7 < 0.9 1.0 +/- 0.5 < 0.9 1.6 +/- 0.6 2.1 +/- 1.0 < 0.9 2.4 +/- 1 1.6 +/- 1.0 CONCENTRATIONS OF TRITIUM IN DRINKING WAT.ER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA Q9-1Q < 189 < 151 < 149 < 147 < 155 < 149 < 146 < 149 < 149 < 148 < 144 < 144 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA COLLECTION Q9-1Q PERIOD 12/30/14 -02/03/15 < 0.4 02/03/15 -03/03/15 < 0.4 03/03/15 -03/31/15 < 0.4 03/31/15 -04/28/15 < 0.2 04/28/15 -06/02/15 < 0.4 06/02/15 -06/30/15 < 0.3 06/30/15 -07/28/15 < 0.3 07/28/15 -09/01/15 < 0.4 09/01/15 -09/29/15 < 0.3 09/29/15 -11/03/15 < 0.5 11/03/15 -12/01/15 < 0.4 12/01/15 -12/29/15 < 0.3 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, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA SITE COLLECTION Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q9-1Q 12/30/14 -

02/03/15 < 1 < 3 < 1 < 1 < 2 < 2 < 1 < 1 < 1 < 8 < 3 02/03/15 -03/03/15 < 4 < 7 < 3 < 3 < 6 <4 <4 < 2 <5 < 11 < 3 03/03/15 -03/31/15 < 2 <4 < 1 < 2 < 2 < 3 < 1 < 1 < 1 < 12 < 6 03/31 /15 -04/28/15 < 1 < 5 <2 < 2 <4 <3 <4 < 2 <2 < 25 <2 04/28/15 -06/02/15 < 5 < 10 <5 <4 < 6 < 8 <4 <4 <6 < 31 < 8 06/02/15 -06/30/15 < 3 < 4* < 2 < 1 < 3 < 5 < 3 < 3 < 3 < 20 <2 06/30/15 -07 /28/15 < 4 <.6 < 5 < 5 < 9 < 6 <3 <4 < 3 < 17 < 8 07/28/15 -09/01/15 < 2 <3 < 2 < 2 < 4 < 5 < 3 < 2 < 1 <

20 <4 09/01/15 -09/29/15 < 1 < 6 <2 < 2 <4 <4 < 3 < 3 < 4 < 19 < 3 u 09/29/15 -11/03/15 < 1

<2 < 1 < 1 <2 <2 < 1 < 1 < 1 <

11 < 3 I 11/03/15 -12/01/15 < 4

., <4 < 5 <4 <3 < 8 < 3 < 3 < 6 < 24 < 6 ..j:>. 12/01/15 -12/29/15 < 3 <

10 < 5 <4 < 11 < 9 <4 <4 < 6 < 26 <6 ti I VI ,f ** : .** *' TABLE D-11.1 SITE COLLECTION PERIOD INDP 10/08/15 ,_.,;**';::_-;

CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA Sr-89 SHJO K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 < 12 <5 3350 +/- 410 < 10 < 19 < 40 < 10 < 29 < 20 < 15 TABLE D-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA I SITE COLLECTION KJ40 Cs-134 Cs-137 PERIOD J2-1 10/29/15 13750 +/- 736 < 19 56 +/- 20 MEAN 13750 +/- 0 ' .-(' D-6 TABLE D-IV.1 SITE COLLECTION PERIOD H1-2Q 07/27/15 B10-2Q 07/20/15 MEAN CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA K-40 4010 +/- 370 2330 +/- 290 3170 +/- 2376 1-131 < 13 < 15 D-7 Cs-134 < 9 < 9 Cs-137

Sr-89 < 16 < 11 < 9 <4 Sr-90 35 +/- 5 2 +/- 1 19 +/- 47 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, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION E1-2Q E1-2Q PERIOD GROSS BETA 1-131 61/61115 -61/68115 36 +/- 5 < .19

-01/15/15 28 +/- 4 < 16 01/15/15 -01/22/15 27 +/- 5 <. 11 01/22/15 -01/29/15 19 +/- 4 < 13 01 /29/15 -02/05/15 19 +/- 4 < 16 02/05/15 -02/12/15 24 +/- 4 < 17 02/15/15 -02/19/15 31 +/- 4 < 27 02/19/15 -02/26/15 42 +/- 6 < 21 02/26/15 -03/05/15 29 +/- 5 < 11 03/05/15 -03/12/15 23 +/- 5 < 27 03/12/15 -03/18/15 17 +/- 5 < 17 03/18/15 -03/26/15 26 +/- 4 < 18 03/26/15 -04/02/15 21 +/- 5 < 21 04/02/15 -04/09/15 23 +/- 5 < 12 04/09/15 -04/16/15 18 +/- 4 < 25 04/16/15 -04/23/15 16 +/- 4 < 20 04/23/15 -04/30/15 13 +/- 4 < 16 04/30/15 -05/07 /15 23 +/- 5 < 14 05/07/15 -05/14/15 22 +/- 4 < 20 05/14/15 -05/21/15 21 +/- 4 < 28 05/21/15 -05/28/15 26 +/- 5 < 24 05/15/15 -06/04/15 16 +/- 4 < 18 06/04/15 -06/10/15 20 +/- 5 < 33 06/10/15 -06/18/15 18 +/- 4 < 26 06/18/15 -06/25/15 25 +/- 5 < 15 06/25/15 -07/02/15 18 +/- 5 < 16 07/02/15 -07/09/15 23 +/- 5 < 18 07/09/15 -07/16/15 23 +/- 5 < 17 07/16/15 -07/23/15 24 +/- 5 < 26 07/23/15 -07/30/15 34 +/- 5 < 24 07 /30/15 -08/06/15 29 +/- 5 < 21 08/06/15 -08/13/15 23 +/- 5 < 52 08/13/15 -08/19/15 40 +/- 6 < 25 08/19/15 -08/27/15 28 +/- 4 < 22 08/27 /15 -09/03/15 56 +/- 6 < 25 09/03/15 -09/10/15 47 +/- 6 < 20 09/10/15 -09/16/15 32 +/- 6 < 12 09/16/15 -09/24/15 36 +/- 5 < 20 09/24/15 -10/01/15 21 +/- 5 < 14 10/01 /15 -10/08/15 15 +/- 5 < 26 10/08/15 -10/15/15 26 +/- 5 < 16 10/15/15 -10/22/15 28 +/- 5 < 19 10/22/15 -10/29/15 23 +/- 5 < 23 10/29/15 -11 /05/15 32 +/- 5 < 18 11/05/15 -11/12/15 24 +/- 5 < 22 11/12/15 -11/19/15 31 +/- 5 < 22 11/19/15 -11/25/15 20 +/- 5 < 35 11/25/15 -12/03/15 29 +/- 4 < 11 12/03/15 -12/10/15 69 +/- 6 < 20 12/10/15 -12/17/15 50 +/- 6 < 21 12/17/15 -12/23/15 32 +/- 6 < 24 12123/15 -12/31/15 16 +/- 4 < 20 MEAN 27 +/- 21 D-8 TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Be-7 Cs-134 Cs-137 PERIOD E1-2Q 01/01/15 -04/02/15 79 +/- 13 < 0.8 < 0.7 04/02/15 -07 /02/15 88 +/- 16 < 0.7 < 0.8 07/02/15 -10/01/15 98 +/- 19 < 0.8 < 1.0 10/01/15 -12/31/15 62 +/- 16 < 0.5 < 0.5 MEAN 82 +/- 31 D-9 TABLE DNl.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, 2015 RESULTS IN UNITS OF PCl/LITER

+/- 2 SIGMA SITE COLLECTION 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 DATE G2-1Q 01/07/15 < 0.2 1106 +/- 94 <2 <4 < 31 < 5 02/11/15 < 0.4 1026 +/- 90 <2 < 3 < 31 < 6 03/11/15 < 0.5 1059 +/- 86 <2 <3 < 22 < 3 03/25/15 < 0.2 1136 +/- 88 < 3 < 3 < 23 < 5 < 0.6 < 0.6 04/08/15 < 0.4 966 +/- 77 <2 < 3 < 26 <4 04/22/15 < 0.4 837 +/- 75 < 2 < 3 < 25 < 6 05/06/15 < 0.2 863 +/- 66 < 2 < 2 < 30 < 5 05/20/15 < 0.4 1389 +/- 101 < 2 < 3 < 16 < 4 06/03/15 < 0.3 740 +/- 80 <3 < 2 < 38 < 8 06/17/15 < 0.4 1009 +/- 106 <4 <4 < 18 < 5 < 0.5 < 0.6 07/01/15 < 0.5 1065 +/- 118 < 6 < 7 < 19 < 8 07/15/15 < 0.4 1108 +/- 100 <3 < 3 < 27 <4 07/29/15 < 0.3 1308 +/- 150 < 6 < 6 < 24 < 6 08/12/15 < 0.2 1084 +/- 85 <2 <4 < 49 < 12 08/26/15 < 0.4 1130 +/- 109 <3 < 3 < 35 < 9 09/09/15 < 0.4 1122 +/- 78 < 2 < 2 <

39 < 5 09/23/15 < 0.4 777 +/- 75 < 3 < 3 < 27 < 7 < 0.6 < 0.5 10/07/15 < 0.5 998 +/- 85 < 3 < 3 <

28 < 14 10/21/15 < 0.3 927 +/- 86 < 3 < 3 < 43 < 6 11/04/15 < 0.2 895 +/- 36 < 1 < 2 < 11 < 5 11/18/15 < 0.4 1473 +/- 98 < 3 <4 < 31 <4 12/02/15 < 0.4 1328 +/- 137 <5 < 5 < 27 < 5 < 0.5 < 0.4 MEAN 1061 +/- 382 D-10 I --FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2015 ---QC-LAB s ---------------------------*---------------------------------------

__.___PRIMARY

-LAB --4 -----------------------------------------------------------------------------*----------------------------------:

... s 3 0 c. 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTl:I I -N FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2015 ------QC -LAB 50 *-* --'*--PRIMARY

-LAB 40 -G) E .c :I 30 0 c. C? . w 20 10 1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM Intentionally left blank TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 {PAGE 1OF3) Identification Reported Known Ratio (c) MonthNear Number Matrix Nuclide Units Value (a) Value (b)

Evaluation (d) March 2015 .E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 w E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A E11184 AP Ce-141 pCi 107 85.0 1.26 w Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 *77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 *Water Fe-55 pCi/L 1950 ' 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 w Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143 125 1. 14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 w Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1) Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 .A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi . 198 210 0.94 . A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A E-1 TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE2 OF3) Identification Reported Known Ratio (c) Month/Year Number Matrix .Nuclide Units Value(a) Value (b) TSE/Analytics Evaluation (d) June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A Zn-65 pCi/L 392 353 1.11 A Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 .Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A .. Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg '311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 pCi/L 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L .265 281 0.94 A Cs-134. pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A E-2 TABLE E-1 ANAL Y.TICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (bl TSE/Analytics Evaluation (d) December 2015 E11357 AP Ce-141 pCi 89.9 84.0 1.07 Cr-51 pCi 215 184 1.17 Cs-134 pCi 103 105 0.98 Cs-137 *pCi 76.6 74.8 1.02 Co-58 pCi 76.2 71.9 1.06 Mn-54 pCi 91.4 94.4 0.97 Fe-59 pCi 78.6 70.3 1.12 Zn-65 pCi 173 162 1.07 Co-60 pCi 138 139 0.99 . E11422 AP Sr-89 pCi 98.0 96.9 1.01 Sr-90 pCi 10.0 14.0 0.71 E11356 Charcoal:

1-131 pCi 74.9 75.2 1.00 E11358 Water Fe-55 pCi/L 2160 1710 1.26 E11353 Soil Ce-141 pCi/kg 252 222 1.14

Cr-51 pCi/kg 485 485 1.00 Cs-134 pCi/kg 319 277 1.15 Cs-137 pCi/kg 292 276 1.06 Co-58 pCi/kg 193 190 1.02 Mn-54 pCi/kg 258 250 1.03 Fe-59 pCi/kg 218 186 1.17 Zn-65 pCi/kg 457 429 1.07 Co-60 pCi/kg 381 368 1.04 (1) AP Cr-51 -Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable.

NCR 15-18 (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 o'f W-Acceptable with warning, reported result falls within o. 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 A A A A A A A A A A w A w A A A A A A A A A TABLE E-2 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance

Month/Year Number Media Nuclide* Units Value (a) Value (b) Range *Evaluation (c) Mcirch 2015 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 -*0.850 A Ni-63 Sq/L 2.5 (1) A Pu-238 Sq/L 0.0204 0.0089 (2) A Pu-239/240 Sq/L 0.9 0.8 0.582 -1.082 A 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314 -582 A Sr-90 Sq/kg 286 653 487 -849 N (3) 15-RdF32 AP Sr-90 Sq/sample

-0.0991 (1) A U-234/233 Sq/sample 0.0211 0.0155 0.0109 -0.0202 N (3) U-238 Sq/sample 0.095 0.099 0.069 -0.129 A 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53-3.01 N (3) Gr-S Sq/sample 0.7580 0.75 0.38 -1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample . 8.08 7.32 5.12 -9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 -11.93 w Co-57 Sq/sample

-0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 -7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample

0.999 1.08 0.76-1.40 A Zn-65. Sq/sample (1) A September 2015 15-MaW33 Water

Am-241 Sq/L 1.012 1.055 0.739-1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4) Pu-238 Sq/L 0.727 0.681 0.477 -0.885 A Pu-239/240 Sq/L 0.830 0.900 0.630 -1.170 A 15-MaS33 Soil Ni-63 Sq/kg 635 682 477 -887 A Sr-90 Sq/kg 429 425 298 -553 A 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53-2.83 N (4) U-234/233 Sq/sample 0.143 0.143 0.100-0.186 A U-238 Sq/sample 0.149 0.148 0.104-0.192 A 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 A Gr-S Sq/sample 1.34 1.56 0.78 -2.34 A 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06 -7.54 A Cs-137 Sq/sample 0.0002 (1) A Co-57 Sq/sample 8.01 6.62 4.63 -8.61 w Co-60 Sq/sample 4.97 4.56 3.19 -5.93 A Mn-54 Sq/sample 8.33 7.68 5.38 -9.98 A Sr-90 Sq/sample 0.386 1.30 0.91-1.69 N (4) .(1) False positive test. Zn-65 Sq/sample 6.07 5.46 3.82-7.10 A (2) Sensitivity evaluation.

(3) Soil Sr-90 -incomplete digestion of the sample resulted in low results; AP U-2341233

-extremely low activity was difficult to quantify AP Gr-A -the MAPEP filter has the activity embedded in the fitter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult tci quantify; AP & Vegetation Sr-90 was lost during separation,.

possible from substance added by MAPEP NCR 15-21. (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) DOE/MAPEP evaluation:

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

E-4 TABLE E-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 -71.2 Sr-90 pCi/L 28.0 41.9 30.8 -48.1 Ba-133 pCi/L 80.6 82.5 63.9 -90.8 Cs-134 pCi/L 71.7 75.7 61.8 -83.3 Cs-137 pCi/L 187 189 170 -210 Co-60 pCi/L 85.7 84.5 76.0-95.3 Zn-65 pCi/L 197 203 183 -238 Gr-A pCi/L 26.1 42.6 22.1 -54.0 Gr-B pCi/L 28.8 32.9 21.3 -40.6 1-131 'pCi/L 23.5 23.8 19.7 -28.3 U-Nat pCi/L 6.19 6.59 4.99-7.83 H-3 pCi/L 3145 3280 2770-3620 November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 -42.5 Sr-90 pCi/L 29.3 31.1 22.7 36.1 Ba-133 pCi/L 31.5 32.5 25.9 -36.7 Cs-134 pCi/L 59.65 62.3 50.6 -68.5 Cs-137

pCi/L 156 157 141 -175 Co-60 pCi/L 70.6 71.1 64.0-80.7 Zn-65 pCi/L 145 126 113-149 Gr-A pCi/L 38.2 51.6 26.9-64.7 Gr-8 pCi/L 42.0 36.6 24.1 -44.2 1-131 pCi/L 24.8 26.3 21.9-31.0 U-Nat pCi/L 146.90 56.2 45:7 -62.4 H-3 pCi/L 21100 21300 18700 -23400 (1) Yield on the high side of our acceptance range indicates possibility of calcium interference.

NCR 15-09 (2) Technician failed to dilute original sample. If dilulted, the result would have been 57. 1, which fell within the acceptance limits. NCR 15-19 (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-5 Evaluation (c) N (1) N (1) A A A A A A A A A A A A A A A A A A A A N(2) A TABLE E-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM 8 ENVIRONMENTAL, INC., 2015 (Page 1 of 1) Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 -48.10 ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 -90.80 ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 -83.30 ERW-1448 04/06/15 Cs-137 -191.92 +/-5.9 189 -170.00 -210.0 ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 -95.30 ERW-1448 04/06/15 Zn-65 -195.97 +/- 12.0 203 -183.00 -238.0 ERW-1450 04/06/15 Gr. Alpha 34.05 +/- .1.90 42.60 22.10 -54.00 ERW-1450 04/06/15 G. Beta 26.93 +/- 1.12 32.90 21.30 -40.60 ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 -3620 ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 -36.70 ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 -175.0 ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 -80. 70 ERW-5531 10/05/15 Zn-65 . -138.94 +/- 5.7 126 -113.00 -149.0 ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 -44.20 ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 -31.00 ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45. 70 -62.40 ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 -23400.0

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crossche.ck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA). b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. E-6 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass TABLE E-5

DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 1of2) Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 02/01/15 Nic63 341 +/- 18 448 314 -582 Pass MAS0-975 02/01/15 sr-90 523 +/- 12 653 457 -849 Pass MAS0-975 02/01/15 Cs-134 533 +/- 6 678 475 -881 Pass MAS0-975 02/01/15 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 02/01/15 Co-57 0.5 +/- 1 0.0 NA c Pass MAS0-975 02/01/15 Co-60 741 +/- 8 817 572 -1062* Pass MAS0-975 02/01/15 Mn-54 1,153 +/- 9 1,198 839 -1557 Pass MAS0-975 02/01/15 Zn-65 892 +/- 18 1064 745 -1383 Pass MAW-969 02/01/15 Am-241 0.650 +/- 0.078 0.654 0.458 -0.850 Pass MAW-969 02/01/15 Cs-134 21.09 +/- 0.25 23.5 16.5 -30.6 Pass MAW-969 02/01/15 Cs-137 19.63 +/- 0.34 19.1 13.4 -24.8 Pass MAW-969 d 02/01/15 Co-57 10.2 +/- 0.4 29.9 20.9' -38.9 Fail MAW-969 02/01/15 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 02/01/15 H-3 *569+/-13 563 394 -732 Pass MAW-969 02/01/15 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 02/01/15.

Mn-54 0.02 +/- 0.07 0.00 NAC Pass MAW-969 02/01/15 Ni-63 2.9 +/- 3 0.00 NAC Pass MAW-969 02/01/15 Zn-65 16.54 +/-. 0.85 18.3 . 1*2.8 -23.8 Pass MAW-969 02/01/15 Pu-238 0.02 +/- 0.03 0.01 NA 0 Pass MAW-969 02/01/15 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 02/01/15 Sr-90 9.40 +/- 1.30 9.48 6.64 -12.32 Pass MAW-950 02/01/15 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 02/01/15 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAAP-978 02/01/15 Cs-134 1.00 +/- 0.04 1.15 0.81 -1.50 Pass MAAP-978 02/01/15 Cs-137 0.004 +/- 0.023 o,oo NA c Pass MAAP-978 e 02/01/15 Co-57 0.04 +/- 0.04 1.51 1.06 -1.96 Fail MAAP"978 02/01/15 Co-60 0.01 +/- 0.02 0.00 NAC Pass MAAP-978 02/01/15 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978 02/01/15 Zn-65 0.83 +/- 0.10 0.83 0.58 -1.08 Pass MAAP-981 02/01/15 Sr-89 38.12 +/- 1.01 47.5 33.3 -61.8 Pass MAAP-981 02/01/15 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 02/01/15 Gr. Alpha 0.59 +/- 0.06 *1.77 0.53 -3.01 Pass MAAP-984 02/01/15 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 02/01/15 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 02/01/15 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 02/01/15 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 02/01/15 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 02/01/15 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 02/01/15 Zn-65 0.09 +/- 0.12 0.00 . NA c Pass E-7 TABLE E-5 DOE'S MIXEDANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 2 of 2) Concentration a Known Lab Code b Date Analysis Laboratory result Activity MAS0-4903 08/01/15 Ni-63 556 +/- 18 682 MAS0-4903 f 08/01/15 Sr-90 . 231 +/- 7 425 MAS0-4903

f. 08/01/15 Sr-90 352 +/- 10 425 MAS0-4903 08/01/15 Cs-134 833 +/- 10 1,010 MAS0-4903 08/01/15 *Cs-137 ' 808 +/- 11 809.00 MAS0-4903 08/01115 Co-57 1,052 +/- 10 1, 180 MAS0-4903 08/01/15' Co-60 2 +/- 2 1.3 MAS0-4903 08/01/15 Mn-54 1.,331 +/- 13 1,340 MAS0-4903 08/01/15 Zn-65 686 +/- 15 662 MAW-5007 08/01/15 Cs-134 16.7 +/- 0.4 23.1 MAW-5007 08/01/15 Cs-137 -0.36 +/- 0.13 0 MAW-5007 08/01/15 Co-57 21.8 +/- 0.4 20.8 MAW-5007 08/01/15 Co-60 17.3 +/- 0.3 17.1 MAW-5007 08/01/15 H-3 227.5 +/- 8.9 216 MAW-5007 g 08/01/15 Fe-55 4.2 +/- 14.1 13.1 MAW-5007 08/01/15 Mn-54 16.6 +/- 0.5 15.6 MAW-5007 08/01/15 Ni-63 '9.1 +/- 2.6 8.55 MAW-5007 08/01/15 Zn-65 15.5 +/- 0.9 13.9 MAW-5007 08/01/15 Sr-90 4.80 +/- 0.50 4.80 MAW-5007 08/01/15 Gr. Alpha 0.41 +/- 0.04 0.43 MAW-5007 08/01/15 Gr. Beta 3.45 +/- 0.07 3.52 MAAP-4911 08/01/15 Sr-89 3.55 +/- 0.67 3.98 MAAP-4911 08/01/15 Sr-90 0.94 +/- 0.16 1.05 MAAP-4907 08/01/15 Gr. Alpha 0.30 +/- 0.04 0.90 MAAP-4907 08/01/15 Gr. Beta 1.85 +/- 0.09 1.56 MAVE-4901 . 08/01/15 Cs-134 5.56 +/- 0.16 5.80 MAVE-4901 08/01/15 Cs-137

+/- 0.06 0.00 MAVE-4901 08/01/15 Co'-57 7.74+/-0.18 6.62 MAVE-4901 08/01/15 Co-60 4.84 +/- 0.15 4.56 MAVE-4901 08/01/15 Mn-54 *8.25 +/- 0.25 7.68 MAVE-4901 08/01/15 Zn-65 5.78 +/- 0.29 5.46

Results are reported in units of Bq/kg (soil), Bq/L (water).,or Sq/total sample (filters, vegetation).

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

Control Limits c 477 -887 298 -553 298 -553 707 -1313 566 -1052 826 -1534 NA 0 938 -1742 463 -861 16.2 -30 NA c 14.6 -27 12 -22.2 151 -281 92 -17 10.9 -20.3 5.99 -11.12 9.7 -18.1 3.36 -6.24 0.13 -0.73 1.76 -5.28 , 2.79 -5.17 0.74 -1.37 0.27 -1.53 0.78 -2.34 4.06 -7.54 NA c 4.63 -8.61 3.19 -5.93 5.38 -9.98 3.82 -7.10 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 Lab result was 27.84. Data entry error resulted in a non-acceptable result.

Lab result was 1.58. Data entry error resulted in a non-acceptable result. f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

g The known activity was below the routine laboratory detection limits for the available aliquot fraction.

E-8 Acceptance Pass Fail Pass Pass Pass Pass, Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1and2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January Through 31 December 2015 Prepared By Teledyne Brown Engineering Environmental Services E*:. ***. *. xe Three Mile Island Nuclear Station Middletown, PA 17057 April 2016 Intentionally left blank Table Of Contents I. Summary and Conclusions

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1 II. Introduction

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..... 3 A. Objectives of the RGPP ......................................................................................

4 B. Implementation of the Objectives

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4 C. Program Description

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

5 Ill. Program Description

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6 A. Sample Analysis ..................................................................................................

6 B. Data Interpretation

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.' .. 7 IV. Results and Discussion

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

8 B. Surface Water Results ..............................

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10 C. Storm Water Results .... : ...................................................... ......*......................

10 D. Precipitation Water Results ........................................................................ ...... 11 E. Leaks, Spills, and Releases ................

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

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12 Appendix A Tables Table A-1 Figures Figure A-1 Appendix B Tables Table 8-1.1 Table 8-1.2 Table 8-1.3 Table B-11 .1 Table B-11.2 Table B-111.1 Table B-111.2 Table 8-IV.1 Appendices Location Designation Radiological Groundwater Protection Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Sampling Locations at the Three Mile Island Nuclear Station, 2015 Data Tables Concentrations of Tritium, Strontium, Gross Alpha, and Gross. Beta in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. ' Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2015. Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuc.lear Station, 2015. Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. ii Appendix C Data Tables -Comparison Tables Table C-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. Table C-1.2 Concentrations of Gamma Emitters in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection ,Program, Three Mile Island Nuclear Station, 2015. Table C-1.3 Concentrations of Hard-To-Detects in Groundwater Split Samples Collected Part of the Radiological Groundwater Protection

Program, Mile Island Generating Station, 2015. Table C-11.1 Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile

Island Nuclear Station, 2015.

Ta,ble C-11.2 Concentrations of Gamma Emitters in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Statio.n, 2015. Table C-111.1 Concentrations of Tritium in Predpitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, : Three Mile Island Nuclear Station, 2015. iii I. Summary and Conclusions In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Three Mile Island Nuclear Station. At Three Mile Island Nuclear, 31 new p*ermanent groundwater monitoring wells were installed in 2006. The results for all TMI wells are included in this report. This report covers groundwater, surface water, storm water and precipitation samples collected from the environment, both on and off .station property in 2015. During that time period 617 analyses were performed on 377 samples from 68 locations.

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

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

Strontium-89 and strontium-90 were not detected at a concentration greater than their respective LLD of 10 and 1 picoCurie .per liter (pCi/L) in the groundwater samples tested. Tritium was not detected in any surface water, storm water or precipitation water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Tritium was detected in groundwater samples above the 20,000 pCi/L limit at 2 locations ranging from 6, 150 to 37 ,200 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 33 of 58 groundwater monitoring locations.

The groundwater tritium concentrations ranged from 203 +/- 128 pCi/L to 37,200 +/- 3,740 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of a tank leakage, historical releases, the recapture of gaseous tritium releases via rainwater and/or background from external sources greater than 200 pCi/L. Tritium was not detected at any surface water location.

Tritium was detected in two of four storm water samples at concentrations of 316 +/- 135 pCi/L to 424 +/- 146 pCi/L. Tritium was detected in five of six precipitation water locations.

The concentration ranged from 192 +/- 125 to 8, 170 +/- 870 pCi/L.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2015. Gross Alpha (dissolved) was not detected at any of the groundwater locations

.. Gross Alpha (suspended) was detected at two of 25 groundwater locations

.. The concentrations ranged from 1.9 to 6.9 pCi/L. Gross Beta (dissolved) was detected at 25 of 25 groundwater locations.

The concentrations ranged from 1.5 to 11.0 pCi/L.

Gross Beta (suspended) was not detected in any of the 25 groundwater locations.

*Hard-To-Detect analyses, which include Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238, were not analyzed i.n 2015.

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

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

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

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

The results and conclusions of this Phase 1 study were made available to state and federal regulators, as well as the public on an Exelon web site for station specific reports. As a result of the Phase 1 study, the Radiological Groundwater Protection

Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on well water, surface water, precipitation water and storm water samples collected in 2015. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides. In September 2015, GHD completed an additional five-year update hydrogeologic investigation report for the Station (NE/ 07-07, Hydrogeo/ogic Investigation Report). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including changes at the Station as well as RGPP sampling activities and groundwater flow. Relevant conclusions from the report are:

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

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

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

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

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

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

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2015. A. Objective of the RGPP The long-term objectives of the Radiological Groundwater Protection Program (RGPP) are as follows: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources. 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

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

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

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

R Implementation of the Objectives The objectives*

identified have been implemented at Three Mile Island Nuclear Station as discussed below:

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

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

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

measurements.

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

4. Three Mile Island Nuclear Station has implemented procedures to identify and report leaks, spills, or other detections with potential

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radiological significance in a timely manner.. 5. Three Mile Island Nuclear Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends. C. Program Description

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

Surface Water. Storm Water. and Precipitation Samples of water are collected, managed, transported and analyzed.in accordance with approved procedures.

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

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

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

Analytical data results are reviewed.

by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.

D. Characteristics of Tritium (H-3) Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen.

The most common form of tritium is tritium oxide, which is also called "tritiated water." Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the .same velocity as the average groundwater velocity.*

Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., made) sources. Tritium is produ.ced naturally in the upper atmosphere when cosmic rays strike air molecules.

This "cosmogenic' 1 tritium combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere.

The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritium can be taken into the-body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, all tritium is essentially cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period. Tritium has a radiological half-life of approximately 12.3 years. It decays spontaneously to helium-3 (He-3). This radioactive decay releases a beta particle (low-energy electron).

The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides, because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue. Ill. Program Description A. Sample Analysis *. This section describes the general analytical methodologies used by TSE

and Midwest Labs to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2015. In order to achieve the stated objectives, the current program includes the following analyses, as applicable:

1. Concentrations of gamma emitters in groundwater, surface water and storm water. 2. Concentrations of strontium in groundwater.

3: Concentrations of tritium in groundwater, surface water,

precipitation water and storm water. 4. Concentrations of Am-241 in groundwater.

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

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

7. . Concentrations

of U-234, U-235 and U-238' in groundwater.

8. Concentrations of Fe-55 in groundwater.

9. .Concentrations of Ni-63 in groundwater.

10.. *Concentrations.

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

8: Data Interpretation

1.

Lower Limit of Detection and Minimum Detectable Concentration

The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.

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

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

The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of-a measurement created by statistical process (counting error). Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR. Gamma spectroscopy results for each type of sample were grouped as follows: For groundwater, surface water, and storm water 13 nuclides, 8e-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, 8a-140 and La-140 were reported.

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

.. IV. Results and Discussion A. Groundwater Results Samples were collected from on and off-site wells in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below. Tritium Samples from 58 locations were analyzed for tritium activity.

Tritium values ranged from the detection limit to 37,200 pCi/L (Table 8-1.1, Appendix 8). *

Tritium Split Samples Tritium values ranged from *143 to 952 pCi/L (Table C-1.1, Appendix C). Strontium Strontium-89 and strontium-90 were not detected above their required detection limit of 10 and 1.0 pCi/L, respectively (Table

B-1.1, Appendix B). Strontium Split Samples Strontium-89 and Strontium-90 were not detected above the required detection limit (Table C-1.1, Appendix C). Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and:Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during th_e quarter sampling in 2015. Gross Alpha (dissolved) was not detected at any of the groundwater locations.

Gross Alpha* (suspe'nded) was detected at two of 25 groundwater locations.

The concentrations ranged from 1.9 to 6.9 pCi/L. Gross Beta (dissolved) was dete.cted at 25 of 25 groundwater locations.

The concentrations ranged from 1.5 to 11.0 pCi/L. Gross Beta (suspended) was not detected in any of the 25 groundwater locations. (Table B-1.1, Appendix B). Gross Alpha and Gross Beta Split Samp.les Two split samples were analyzed for Gross Alpha and Gross Beta iri 2015. Gross Alpha was .not detected at either groundwater location.

Gross beta was detected in one sample analyzed.

The concentration was 2.5 pCi/L (Table C-1.3, Appendix C). Gamma Emitters Potassium-40 was detected in three of 63 samples with concentrations ranging from 74 pCi/L to 139 pCi/L. No other gamma-emitting nuclides were detected (Table B-1.2, Appendix B). Gamma Emitters Split Samples Five locations were analyzed for gamma-emitting nuclides in 2015. Potassium-40 was detected in one of five samples with a concentration of 94 pCi/L. No other gamma-emitting nuclides were . detected in any split samples C-1.2, Appendix C).

Hard-To-Detect Hard-To-Detect analyses, .which include Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238, were not analyzed in 2015 {Table B-1.3, Appendix B). Hard-To-Detect Split Samples Hard to detects were not analyzed on any split samples in 2015 (Table C-1.3, Appendix C). B. Surface Water Results Samples were collected from surface water locations in accordance

with the station radiologica*I groundwater protection program. Analytical results and anomalies are discussed below. Tritium Three locations were analyzed for tritium in 2015. Tritium was not . detected above the* required detection limit of 200 pCi/L in any of . the 13 samples analyzed (Table B-11.1, Appendix B). Tritium Split Samples One location was analyzed for tritium iii 2015. Tritium was not detected above the required detection limit of 200 pCi/L in the. *sample analyzed (Table C-IL 1, Appendix C). Gamma Emitters Three locations were analyzed for gamma-emitting nuclides in 2015. None of the three samples detected gamma-emitting nuclides {Table B-11.2, Appendix B).-* Gamma Emitters Split Samples Surface water samples were not analyzed for gamma-emitting*

nuclides in 2015 {Table C-11.2, Appendix C). ' . C. Storm WaterHesults Samples were collected from *storm water locations in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium One location was analyzed for tritium. Tritium was detected in two . *of four samples above the required detection limit of 200 pCi/L at concentrations of 316 and 424 pCi/L (Table B-111.1, Appendix B). Gamma Emitters Samples from one location were analyzed for gamma-emitting nuclides.

No gamma emitting nuclide? were detected (Table* B-111.2, Appendix B). D. Precipitation Water Results Samples were collected at six locations.

The following analyses were* performed:

Tritium .Samples from six locations were analyzed for tritium activity .. Tritium .activity was detected five of six locations, The concentrations ranged.from

.192 to 8, 170 pCi/L (Table B-IV.1, Appendix B). Tritium Split Samples Samples fron:i one location were analyzed for tritium activity.

Tritium . activity was detected in :two of four samples. The concentrations ranged from235 to 1.,073 pCi/L (Table C-111.1, Appendix C). Gamma Emitters Precipitation water was not analyzed for Gamma Emitters in 2015. Gamma Emitters Split Samples No gamma-emitting nuclides were analyzed in 2015. E. Leaks, Spills, and Releases ' ' A potential leak was identified at TMI in 2012 due to elevated MS-22 tritium concentration readings.

TMI continues to monitor MS-22 and surrounding wells, .in addition to tritium plumes from previous years, and reports the activity and dose to the public in the ARERR. The elevated MS-22 well tritium concentrations were voluntarily repo.rted under the reporti.ng requirements for the NEI Groundwater Protection Initiative (GPI) as implemented in Exelon's Reportability procedure LS-AA-1120, RAD 1.34 ( IR 1385497/1515261

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

F. Actions Taken 1. Compensatory/Corrective Actions Fully encapsulating enclosures were installed around all BWST connections including the 24-inch main outlet flange. Each enclosure was fitted with a tygon tubing discharge point, connected to a water collection bottle to prevent tritiated water from reaching the ground surface. The outlet flange and leaking connections were repaired during the TMI refueling outage in November 2015. TMI has an extensive groundwater monitoring program with over 50 monitoring wells. No monitoring wells outside the BWST investigation area have seen elevated tritium concentrations.

TMI continues to monitor the BWST area wells closely. The leakage has been mitigated by repairing the leaking flanges.

Intentionally left blank APPENDIX A LOCATION DESIGNATION

& DISTANCE Intentionally left blank TABLEA-1:

Site #3 48N 48S E1-2 EOC8 GP-12 GP-6 GP-8 GP-9 MS-1 MS-19 MS-2 MS-20 MS-21 MS-22 MS-3 MS-4 MS-5 MS-6 MS-7 MS-8 MW-1 MW-2 MW-3 MW-4 N2-1 NW-A NW-8 NW-C NW-CW OS-138 OS-14 OS-16 OS-17 OS-18 OSF RW-1 RW-2 SW-E-1 SW-E-2 SW-E-3 MW-TMl-9S*

MW-TMl-100 MW-TMl-101

MW-TMl-10S MW-TMl-11S*

MW-TMl-128 MW-TMl-131 MW-TMl-13S MW-TMl-140 MW-TMl-141 MW-TMl-14S MW-TMl-160 MW-TMl-161 MW-TMl-170 MW-TMl-171 MW-TMl-180 MW-TMl-190 MW-TMl-191 MW-TMl-10 MW-TMl-200**

Radiological Groundwater"Protection Program -Sampling Locations and Distance, Three MileJsland Nuclear Station, 2015 Site Type Monitoring Well Monitoring Well Production Potable Well Monitoring Well, Offsite Storm Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring.

Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well, Offsite Production Well Production Well Production Well Clearwell Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Production Potable Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well A-1 TABLE A-1: Site MW-TMl-20I**

MW-TMl-210**

MW-TMl-211**

MW-TMl-21S**

MW-TMl-220**

MW-TMl-221**

MW-TMl-22S**

MW-TMl-20 MW-TMl-31 MW-TMl-41 MW-TMl-4S MW-TMl-50 MW-TMl-60 MW-TMl-61 MW-TMl-7S MW-TM I-BS MW-TMl-91 MW-TMl-9S TRAINING CENTER TM-PR-ESE TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-20 TM-PR-MS-22 TM-PR-MS-4 TM-PR-NW-B Radiological Groundwater Protection Program -Sampling Locations and Distance, Three Mile Island Nuclear Station, 2015 Site Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Offsite Monitoring Well Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water

NO WATER PRESENT TO SAMPLE **NEW WELLS INSTALLED 2014 A-2 Q p L N t R J ...... ..........

'**'ooF H* B H

Ol.Tt' 0 2/03/15 .,.._, Figure A-1 *-0::: co c:: c:: co a: RGPP Groundwater Sampling Locations at Three Mile Island Nuclear Station Sampling Locations at the Three Mile Island Nuclear Station, 2015 A-3 Intentionally left blank APPENDIX B DATA TABLES Intentionally left blank TABLE B-1.1 . CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015

RESULTS.IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr"A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) < 48S 04/17/15 < 194 < 7.7 < 0.7 < 6.4 < 0.5 4.1 +/- 1.5 < 1.5 48S 07/28/15 < 187 48S 10/06/15 Original 397 +/- 140 48S 10/06/15 Recount 387 +/- 135 48S 10/06/15 Reanalysis 311 +/- 137 MS-1 01/29/15 < 187 MS-1 04/23/15 < 197 < 6.9 < 0.6 < 4.6 < 0.5 4.8 +/- 2.8 < 1.5 MS-1 07/28/15 < 190 MS-1 10/06/15 Original 326 +/- 136 MS-1 10/06/15 Recount 276 +/-. 132 MS-1 10/06/15 Reanalysis 311 +/- 131 MS-2 01/28/15 < 186 MS-2 04/22/15 328 +/- 141 < 6.4 < 0.6 < 1.1 < 0.7* 2.8 +/- 0.8 < 1.6 MS-2 07/28/15 280 +/- 133 MS-2 10/06/15 203 +/- 128 MS-20 01/27/15 495 +/- 142 MS-20 02/26/15 456 +/- 140 MS-20 04/21/15 57.8 +/- 152 < 5.8 < 0.7 < 1.9 < 0.7 6.6 +/- 1.2 < 2.2. MS-20 07/27/15 384 +/- 141 MS-20 07/27/15 453 +/- 148 MS-20 10/06/15 425 +/- 139 MS-21 01/27/15 < 153 MS-21 01/27/15 < 187 MS-21 04/21/15 < 189 < 5.5 < 0.6 < 0.8 < 0.5 2.0 +/- 0.7 < 1.5 MS-21 07/27/15 < 199 MS-21 10/07/15 < 195 MS-21 10/07/15 < 196 MS-22 01/27/15 1330 +/- 189 MS-22 02/03/15 6060 +/- 645 MS-22 02/12/15 10200 +/- 1060 MS-22 02/18/15 11100 +/- 1150 MS-22 03/10/15 2370 +/- 289 MS-22 03/25/15 9110 +/- 957 MS-22 04/09/15 16900 +/- 1720 MS-22 04/21/15 15600 +/- 1610 < 7.0 < 0.9 < 0.6 < 0.5 6.0 +/- 1'.0 < 1.6 MS-22 05/07/15 17800 +/- 1830 MS-22 05/21/15 14700 +/- 1510 MS-22 06/02/15 14500 +/- 1490 MS-22 06/16/15 Original 6990 +/- 753 06/16/15 Recount 7370 +/- 786 MS-22 06/16/15 Reanalysis 7250 +/- 764 MS-22 06/30/15 2250 +/- 274 MS-22 07/16/15 5230 +/- 556 MS-22 07/27/15 7980 +/- 850 MS-22 08/11/15 Original 8560 +/- 887 MS-22 08/11/15 Recount 8330 +/- 885 MS-22 08/11/15 Reanalysis 7650 +/- 815 MS-22 08/25/15 Original 2940 +/- 346 MS-22 08/25/15 Recount 2580 +/- 318 08/25/15 Reanalysis 2420 +/- 302 MS-22 09/09/15 Original 6960 +/- 750 MS-22 09/09/15 Recount 6850 +/- 730 MS-22 09/21/15 2830 +/- 338 MS-22 10/05/15 Original 720 +/- 149 MS-22 10/05/15 Recount 710 +/- 156 B-1 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus) MS-22 10/05/15 Reanalysis 609 +/- 147 MS-22 10/20/15 Original 3300 +/- 387 MS-22 10/20/15 Recount 3700 +/- 428 MS-22 11/17/15 2500 +/- 307 MS-22 12/04/15 4270 +/- 480 MS-22 12/21/15 3850 +/- 443 MS-3 01/28/15 306 +/- 114 MS-3 04/22/15 347 +/- 143 < 6.1 < 0.5 < 1.5 < 0.7 10.1 +/- 1.3 < 1.6 MS-3 07/28/15 279 +/- 131 MS-3 10/06/15 225 +/- 131 MS-4 04/22/15 261 +/- 137 MS-5 01/28/15 < 185 MS-5 04/22/15 < 200 < 8.5 < 1.0 < 1.4 < 0.5 7.0 +/- 1.2 < 1.5 MS-5
< 193 MS-5 10/06/15 < 192 MS-7 01/29/15 < 188 MS-7 04/22/15 < 196 < 5.5 < 0.6 < 1.1 < 0.5 4.6 +/- 1.0 < 1.5 MS-7 07/28/15 < 187 MS-7 10/06/15 < 194 MS-7 10/06/15 Original 206 +/- 131 MS-7 10/06/15 Recount 205 +/- 125 MS-7 10/06/15 Reanalysis 204 +/- 131 MS-8 01/27/15 < 188 MS-8 04/22/15 260 +/- 131 < 5.5 < 0.5 < 1.1 6.9 +/- 1.6 4.0 +/- 0.8 < 4.1 MS-8 07/28/15 < 185 MS-8 10/06/15 < 189 MW-1 04/21/15 < 194 MW-2 04/21/15 < 194 MW-TMl-10D 04/22/15 336 +/- 139 MW-TMl-101 01/29/15 779 +/- 158 MW-TMl-101 04/22/15 903 +/- 170 MW-TMl-101 04/22/15 1000 +/- 175 MW-TMl-101 07/28/15 793 +/- 158 MW-TMl-101 10/07/15 691 +/- 151 MW-TMl-101 10/07/15 576 +/- 148 MW-TMl-10S 01/29/15 1470 +/- 202 MW-TMl-10S 04/22/15 1260 +/- 189 < 6.0 < 0.6 < 1.4 < 0.5 6.8 +/- 1.3 < 1.5 MW-TMl-10S 07/29/15 1540 +/- 216 MW-TMl-10S 10/07/15 1410 +/- 209 MW-TMl-12S 01/28/15 < 162 MW-TMl-12S 04/22/15 < 195 < 6.2 < 0.6 < 0.9 < 0.5 5.6 +/- 0.9 < 1.5 MW-TMl-12S 07/28/15 < 192 MW-TMl-12S 10/07/15 < 193 MW-TMl-131 01/29/15 < 188 MW-TMl-131 04/21/15 < 194 MW-TMl-131 07/28/15 < 189 MW-TMl-131 10/06/15 < 196 MW-TMl-14D 01/29/15 251 +/- 129 MW-TMl-14D 01/29/15 262 +/- 131 MW-TMl-14D 04/21/15 253 +/- 136 MW-TMl-14D 07/28/15 333 +/- 135 MW-TMl-14D 10/07/15 367 +/- 138 MW-TMl-14D 10/07/15 329 +/- 134 MW-TMl-141 01/29/15 < 178 MW-TMl-141 04/21/15 286 +/- 137 MW-TMl.-141 07/28/15 209 +/- 126 B-2
TABLE SITE MW-TMl-141 MW-TMl-141 MW-TMl-160 MW-TMl-171 MW-TMl-180 MW-TMl-191 MW-TMl-10 MW-TMl-201
MW-TMl-201 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl"21D MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211
MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211
MW-TMl-211 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND* NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) 07/28/15 231 +/- 131 10/07/15 287 +/- 134 04/23/15 595 +/- 154 04/23/15 < 191 04/21/15 286 +/- 135 04/22/15 < 197 04/21/15 247 +/- 136 04/22/15 445 +/- 148 04/22/15 415 +/- 144 01/27/15 3890 +/- 431 02/03/15 4440 +/- 483 02/12/15 3410 +/- 382 02/18/15 4210 +/- 466 02/26/15 4240 +/- 470 03/10/15 4210 +/- 469 03/25/15 4260 +/- 474 04/09/15 4670 +/- 514 04/21/15 4540 +/- 503 05/07/15 3980 +/- 441 05/21/15 5210 +/- 559 06/02/15 4840 +/- 535 06/16/15 4440 +/- 499 06/30/15 5240 +/- 567 07/16/15 4690 +/- 503 07/27/15 4740 +/- 527 08/11/15 5660 +/- 599 08/25/15 5620 +/- 611 09/09/15 5440 +/- 597 09/21/15 4930 +/- 545 10/05/15 5040 +/- 550 10/20/15 5130 +/- 568 11/17/15 6240 +/- 675 12/04115 5750 +/- 628 12/21/15 5260 +/- 583 01/27/15 8500 +/- 891 02/03/15 7800 +/- 815 02/12/15 5930 +/- 631 02/18/15 5190 +/- 564 02/26/15 8820 +/- 926 03/10/15 10700 +/- 1120 03/25/15 8540 +/- 900 04/09/15 8200 +/- 864 04/21/15 10200 +/- 1060 05/07/15 6720 +/- 713 05/21/15 5270 +/- 569 06/02/15 5140 +/- 566 06/16/15 3900 +/- 446 06/30/15 4600 +/- 499 07/:16/15 6700 +/- 702 07/27/15 6040 +/- 656 08/11/15 6230 +/- 656 08/25/15 5780 +/- 626 09/09/15 5770 +/- 630 09/21/15.
5750 +/- 629 10/05/15 4680 +/- 513 10/20/15 4750 +/- 529 B-3 Gr-B (Sus)
TABLE B-1.1 SITE MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S
MW-TMl-21S MW-TMl-218 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMJ-220 MW-TMJ-220 MW-TMJ-220
MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMJ-220
MW-TMl-220 MW-TMlc22D MW-TMl-220 MW-TMl-220
MW-TMJ-220 MW-TMl-220 MW-TMJ-220 MW-TMl-220 MW-TMJ-220 MW-TMl-220 MW-TMl-221 MW-TMl-221 MW-TMJ-221 CONCENTRATIONS OF*TRITIUM, STRONTIUM, GROSS ALPHA'AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION DATE
H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) 11/17/15 5120 +/- 564 12/Q4/15 5520 +/- 604 12/21/15 4430 +/- 500 01/27/15 692 +/- 151 02/03/15 648 +/- 147 02/12/15 544 +/- 132 02/18/15 489 +/- 144 02/26/15 6580 +/- 702 03/10/15 527 +/- 142 03/25/15 521 +/- 142 04/09/15 658 +/- 152 04/21/15 753 +/- 158 < 8.0 < 0.8 < 0.8 < 0.5 11.0 +/- 1.5 05/07/15 647 +/- 142 05/21/15 678 +/- 148 06/02/15 310 +/- 139 06/16/15 500 +/- 147 06/30/15 491 +/- 141 07/16/15 677 +/- 135 07/27/15 476 +/- 144 08/11/15 624 +/- 127 08/25/15 580 +/- 140 09/09/15 675 +/- 151 09/21/15 451 +/- 144 10/05/15 431 +/- 133 10/20/15 614 +/- 147 11/17/15 728 +/- 154 12/04/15 548 +/- 143 12/21/15 937 +/- 164 01/27/15 4990 +/- 543 02/03/15 5900 +/- 627 02/12/15 4070 +/- 446 02/18/15 5760 +/- 621 02/26/15 5590 +/- 602 03/10/15 5070 +/- 553 03/25/15 4780 +/- 526 04/09/15 7390 +/- 784 04/21/15 6050 +/- 650 05/07/15 5320 +/- 574 05/21/15 5160 +/- 556 06/02/15 8600 +/- 909 06/16/15 6870 +/- 740 06/30/15 6920 +/- 747 07/16/15 7130 +/- 745 07/27/15 7260 +/- 777 08/11/15 7060 +/- 738 08/25/15 7210 +/- 769 09/09/15 8300 +/- 882 09/21/15 7340 +/- 782 10/05/15 6540 +/- 696 10/20/15 7340 +/- 787 11/17/15 5630 +/- 615 12/04/15 6070 +/- 659 12/21/15 4380 +/- 496 01/27/15 8420 +/- 883 02/03/15 8990 +/- 937 02/12/15 8080 +/- 844 B-4 Gr-8 (Sus) < 1.6 TABLE. B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) MW-TMl-221 02/18/15 9470 +/- 991 MW-TMl-221 02/26/15 11300 +/- 1170 MW-TMl-221 03/10/15 9290 +/- 973 MW-TMl-221 03/25/15 8680 +/- 914 MW-TMl-221 04/09/15 11400 +/- 1190 MW-TMl-221 04/21/15 Original 19500 +/- 1990 MW-TMl-221 . 04/21/15 Reanalysis 16200 +/- 1660 MW-TMl-221 05/07/15 24500 +/- 2480 MW-TMl-221 05/21/15 27400 +/- 2770 MW-TMl-221 06/02/15 26000 +/- 2640 MW-TMl-221 06/16/15 23400 +/- 2380 MW-TMl-221 06/30/15 21900 +/- 2240 MW-TMl-221 07/16/15 21200 +/- 2150 MW-TMl-221 07/27/15 22900 +/- 2340 MW-TMl-221 08/11/15 23400 +/- 2370 MW-TMl-221 08/25/15 21700 +/- 2190 MW-TMl-221 09/09/15 23100 +/- 2360 MW-TMl-221 09/21/15 19000 +/- 1950 MW-TMl-221 10/05/15 17000 +/- 1730 MW-TMl-221 10/20/15 17700 +/- 1820 MW-TMl-221 10/20/15 18500 +/- 1900 MW-TMl-221 11/17/15 21200 +/- 2160 MW-TMl-221 12/04/15 18500 +/- 1890 MW-TMl-221 12/21/15 17000 +/- 1750 MW-TMl-22S 01/27/15 16600 +/- 1690 MW-TMl-22S 01/29/15 28200 +/- 2850 MW-TMl-22S 02/03/15 23100 +/- 2350 MW-TMl-22S 02/12/15 24700 +/- 2500 MW-TMl-22S 02/18/15 25500 +/- 2580 MW-TMl-22S 02/26/15 8560 +/- 897 MW-TMl-22S 03/10/15 11000 +/- 1140 MW-TMl-22S 03/25/15 6150 +/- 659 . MW"TMl-22S 04/09/15 27000 +/- 2740 MW-TMl-22S 04/21/15 Original 37200 +/- 3740 < 6.5 < 0.6 < 1.5 < 0.5 8.0 +/- 1.4 < 1.6 MW-TMl-22S 04/21/15 Reanalysis 36900 +/- 3710 MW-TMl-22S 05/07/15 30300 +/- 3070 MW-TMl-22S 05/21/15 5580 +/- 599 MW-TMl-22S 06/02/15 8010 +/- 852 MW-TMl-22S 06/16/15 7610 +/- 812 MW-TMl-22S 06/30/15 Original 15400 +/- 1590 MW-TMl-22S 06/30/15 Recount 14600 +/- 1510 MW-TMl-22S 06/30/15 Reanalysis 14900 +/- 1530 MW-TMl-22S 07/16/15 7560 +/- 788 MW-TMl-22S 07/27/15 13500 +/- 1400 MW-TMlc22S 08/11/15 14000 +/- 1430 MW-TMl-22S 08/25/15 12600 +/- 1290 MW-TMl-22S 09/09/15 14500 +/- 1500 MW-TMl-22S 09/21/15 10900 +/- 1130 MW-TMl-22S 10/05/15 8780 +/- 921 MW-TMl-22S 10/20/15 7720 +/- 824 MW-TMl-22S 11/17/15 6380 +/- 689 MW-TMl-22S 12/04/15 6170 +/- 668 MW-TMl-22S 12/21/15 5470 +/- 602 B-5 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus) MW-TMl-2D 04/21115 206 +/- 134 MW-TMl-2D 04/21/15 274 +/- 135 MW-TMl-31 01/29/15 < 186 MW-TMl-31 04/23/15 < 199 < 6.6 < 0.6 < 2.1 < 0.7 6.8 +/- 1.6 < 1.6 MW-TMl-31 04/23/15 < 194 < 7.0 < 0.6 < 2.0 < 0.7 6.8 +/- 1.6 < 1.6 MW-TMl-31 07/29/15 < 191 MW-TMl-31 10/07/15 Original 251 +/- 131 MW-TMl-31 10/07/15 Recount 220 +/- 128 MW-TMl-31 10/07/15 Reanalysis 279 +/- 139 MW-TMl-41 04/23/15 < 198 MW-TMl-4S 04/22/15 < 199 MW-TMl-6D 01/29/15 < 189 MW-TMl-6D 04/22/15 < 186 < 4.2 < o.5 < 1.6 < 0.5 2.9 +/- 0.9 < 1.5 MW-TMl-6D 07/28/15 < 190 MW-TMl-6D 10/06/15 < 188 MW-TMl-61 01/29/15 < 184 MW-TMl-61 01/29/15 < 185 MW-TMl-61 04/22/15 < 189 < 7.1 < 0.6 < 1.3 1.9 +/- 1.0 3.6 +/- 1.1 < 2.0 MW-TMl-61 07/28/15 < 190 MW-TMl-61 10/06/15 < 194 MW-TMl-7S 04/22/15 < 199 MW-TMl-8S 04/21/15 < 191 MW-TMl-91 04/21/15 < 196 MW-TMl-91 04/21/15 217 +/- 131 N2-1 04/20/15 < 195 NW-A 01/29/15 870 +/- 159 NW-A 04/23/15 1290 +/- 186 < 4.3 < 0.6 < 0.8 < 0.6 3.8 +/- 0.9 < 1.5 NW-A 07/28/15 1000 +/- 169 NW-A 10/06/15 791 +/- 157 NW-B 01/29/15 233 +/- 129 NW-B 04/23/15 319 +/- 133 < 4.3 < 0.6 < 1.0 < 0.6 1.5 +/- 1.0 < 1.5 NW-B 07/28/15 259 +/- 135 NW-B 10/06/15 240 +/- 132 NW-C 01/29/15 911 +/- 164 NW-C 04/23/15 1250 +/- 179 < 5.1 < 0.7 < 0.8 < 0.6 2.4 +/- 0.8 < 1.5 NW-C 07/28/15 1050 +/- 172 NW-C 10/14/15 1110 +/- 177 NW-CW 01/29/15 388 +/- 138 NW-CW 04/17/15 611 +/- 155 < 7.2 < 0.6 < 1.7 < 0.5 1.9 +/- 0.9 < 1.5 NW-CW 07/28/15 671 +/- 154 NW-CW 07/28/15 820 +/- 160 NW-CW 10/06/15 663 +/- 160 OS-14 01/27/15 < 188 OS-14 04/22/15 < 197 < 5.5 < 0.6 < 2.1 < 0.7 10.8 +/- 1.6 < 1.6 B-6 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATE.R SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) OS-14 07/28/15 < 197 OS-14 10/06/15 < 188 OS-16 01/28/15 246 +/- 130 OS-16 04/22/15 382 +/- 143 < 7.8 < 0.6 < 0.9 < 0.7 5.4 +/- 0.8 OS-16 07/28/15 326 +/- 133 OS-16 10/07/15 305 +/- 132 OS-18 04/22/15 258 +/- 134 OSF 01/29/15 332 +/- 134 OSF 04/17/15 376 +/- 146 < 6.5 < 0.7 < 4:8 < 0.5 8.1 +/- 1.8 OSF 07/28/15 269 +/- 131 OSF 10/06/15 282 +/- 133 RW-1 01/28/15 < 178 RW-1 01/28/15 < 164 RW-1 04/21/15 < 193 < 8.5 < 0.7 < 0.8 < 0.7 10.5 +/- 1.5 RW-1 07/28/15 < 191 RW-1 10/07/15 < 193 TRAINING CENTEF104/20/15
< 190 _; ' B-7 Gr-B (Sus) < 1.6 < 1.5 < 1.6 to I °" TABLE B-1.2 SITE 488 MS-1 MS-2 MS-20 MS-21 MS-22 MS-3 MS-3 MS-3 MS-3 MS-4 MS-5 MS-5 MS-5 MS-5 MS-7 MS-8 MS-8 MS-8 MS-8 MW-1 MW-2 MW-TMl-100 MW-Tlllil-108 MW-TMl-128 MW-TMl-160 MW-TMl-171 MW-TMl-180 MW-TMl-191 MW-TMl-10 MW-TMl-201 MW-TMl-20I MW-TMl-218 MW-TMl-228 MW-TMl-20 MW-TMl-20 MW-TMl-31 MW-TMl-31 MW-TMl-41 MW-TMl-48 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTIOI\
Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 .,Ba-140 La-140 04/17/15 04/23/15 04/22/15 04/21/15 04/21/15 04/21/15 01/28/15 04/22/15 07/28/15 10/06/15 04/22/15 01/28/15 04/22/15 07/28/15 10/06/15 04/22/15 01/27/15 04/22/15 07/28/15 10/06/15 04/21/15 04/21/15 04/22/15 04/22/15 04/22/15 04/23/15 04/23/15 04/21/15 04/22/15 04/21/15 04/22/15 04/22/15 Q4/21/15 04/21/15 04/21/15 04/21/15 04/23/15 04/23/15 04/23/15 04/22/15 < 18 < 43 < 35 < 31 < 35 < 22 < 59 < 40 < 36 < 51 < 45 < 63 < 31 < 29 < 58 < 37 < 44 < 40 < 34 < 44 < 36 < 35 < 33 < 33 < 33 < 53 < 27 < 35 < 39 < 31 < 44 < 43 < 24 < 25 < 31 < 27 < 38 < 41 < 48 < 40 < 17 < 2 < 103 < 5 < 29 < 4 < 51 < 3 < 47 < 3 < 17 < 2 < 138 < 6 < 94 < 4 < 74 < 4 < 35 < 6 < 89 < 5 117 +/- 62 < 7 < 25 < 3 < 28 < 3 < 105 < 7 < 35 < 4 < 52 < 5 < 41 < 4 < 29 < 4 < 81 < 4 < 34 < 4 < 36 < 4 < 42 < 4 < 38 < 4 < 72 < 3 < 48 < 6 < 27 < 3 < 54 < 3 < 73 < 4 < 50 < 3 < 42 < 4 139 +/- 90 < 5 74 +/- 33 < 2 < 48 < 2 < 28 < 3 < 25 < 3 < 37 < 4 < 95 < 4 < 41 < 5 < 71 < 4 <2 < 5 <4 <4 <4 < 3 < 7 <4 <4 < 5 < 5 < 7 <4
<4 < 7 <4 <4 <4 <4 < 3 <4 < 3 <3 <4 < 3 <6 < 3 <4 < 5 < 3 < 5 < 5 < 2 < 3 < 3 < 3 < 5 <4 < 5 <4 < 4 < 9 < 8 < 9 < 8 < 5 < 14 < 9 <7 < 8 < 11 < 13 < 6 < 8 < 15 < 9 < 11 < 10 < 7 < 8 < 9 < 7 < 8 < 9 < 7 < 13 < 7 < 8 < 10 < 6 < 10 < 10 < 5 < 7 <7 < 6 < 10 < 8 < 12 < 9 < 2 <4 <4 < 3 < 3 <2 <6 <4 < 4 <7 < 5 < 6 < 3 <3 < 13 < 4 <3 <4 <4 <4 <4 <4 < 5 <4 <4 < 6 <2
<4
<4 <3 < 5 < 5 <2 < 2 < 3 < 3 <4 <4 < 5 . < 5 < 3 < 8 < 8 < 7 < 7 <4 < 11 < 8 < 9 < 10 < 11 < 14 < 5 <7 < 14 < 7 < 10 < 9 < 7 < 5 <7 < 7 < 8 < 8 < 6 < 11 <6 < 7 < 9 <6 < 9 < 10 <5 < 5 < 6 <5 < 10 < 7 < 11 < 9 < 2 < 5 <4 <4 <4 <2 < 6 <4 <4 < 6 < 5 <7 < 3 < 3 < 8 <4 < 5 '5 5 <4 < 5 < 5 <4 <4 <4 < 3 < 6 < 3 <4 < 5 < 3 < 6 < 5 <2 < 3 <4 < 3 < 5 < 5 < 6 < 5 < 3 < 8 < 7 < 7 < 7 <4 < 11 < 8 <7 <7 < 8 < 12 < 5 < 6 < 14 <7 < 8 < 8 <6 < 9 < 8 <6 < 8 < 7 <6 < 11 < 5 <7 < 8 < 5 < 9* < 9 <4 < 5 < 6 < 6 < 8 < 8 < 10 < 7 < 2 <4 < 3 <3 < 3 < 2 <6 <4 <4 < 6 <4 < 8 < 3 <3 <7 < 3 <4 <4 <4 <4 <4 <4 <4 <3 < 3 < 6 <3 < 3 <4 <3 <4 < 5 < 2 < 2 < 3 <3 <4 <4 <5 <4 . < 2 < 5 <4 <4 < 3 <2 < 7 <4 <4 < 5 < 6 < 7 < 3 < 3 < 7 <4 < 5 < 5 < 3 < 6 <4 <4 <4 <4 <4 <6 <4
<4 <4 < 3 < 5 <4 < 2 < 3 < 3 < 3 <4 <4 <6 <4 < 16 < 27 < 23 < 25 < 26 <<21 < 33 < 31 -< 22 < 31 < 31 < 38 _< 21 < 19 < 32 < 27 < 26 < 33 < 21 < 20 < 30 < 27 < 28 < 24 < 24 < 34 < 23 < 29 < 28 < 23 < 32 < 32 < 23 < 26 < 22 < 23 < 32 < 30 < 36 < 28 < 5 < 11 < 9 < 8 < 7 < 8 < 12 < 9 < 7 < 8 < 11 <* 11 <_6 < 6 < 14 <7 < 8 < 9 < 6 < 8 < 9 < 6 < 8 < 7 <7 < 11 < 6 < 11 < 10 < 8 < 12 < 12 < 7 < 9 <7 < 7 < 11 < 9 < 11 < 11 TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTIOI\
Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 MW-TMl-60 04/22/15 MW-TMl-61 04/22/15 MW-TMl-78 04/22/15 MW-TMl-88 04/21/15 MW-TMl-91 04/21/15 MW-TMl-91 04/21/15 N2-1 04/20/15 NW-A 04/23/15 NW-B 04/23/15 NW-C 04/23/15 NW-CW 04/17/15 OS-14 01/27/15 OS-14 04/22/15 OS-14 07/28/15 OS-14 10/06/15 OS-16 01/28/15 OS-16 04/22/15 OS-16 07/28/15 OS-16 10/07/15 OS-18 04/22/15 OSF 04/17/15 RW-1 04/21/15 TRAINING CENTER 04/20/15 < 39 < 33 < 33 < 26 < 27 < 30 < 37 < 9 < 11 < 7 < 20 < 49 < 39 < 41 < 51 < 45 < 33 < 28 < 54 < 39 < 18 < 32 < 32 < 74 < 68 < 27 < 43 < 21 < 65 < 38 < 19 < 8 < 5 < 19 < 59 < 44 < 50 < 107 < 47 < 34 < 34 < 131 < 66 < 17 < 31 < 26 < 5 < 3 < 3 < 3 < 2 < 3 <4 < 1 < 1 < 1 <2 < 6 < 3 < 5 < 5 < 6 < 3 < 3 <6 <4 <2 < 3 < 3 <4 <4 < 3 < 3 < 2 < 3 <4 < 1 < 1 < 1 < 2 < 6 <4 < 5 < 6 < 5 <4 < 3 < 7 <4 <2 <4 < 3 < 9 < 9 <7 < 6 < 7 < 7 < 7 <2 <2 <2 < 5 < 13 < 9 < 11 < 12 < 9 < 8 < 6 < 14 <.9 <5 < 8 < 8 <'4 < 3 < 3 < 2 < 2 < 3 <4 < 1 < 1 < 1 < 2 < 5 <4 < 5 < 5 <-5 <4 <3 <7 < 5 < 2 <4 < 3 < 8 <7 < 6 <4 < 5 < 6 < 9 < 1 <2 < 1 <4 < 12 < 8 < 12 < 8 < 8 < 8 < 6 < 13 < 7 <4 < 7 < 6 <4 <4 <4 < 3 < 2 < 3 < 5 < 1 < 1 < 1 < 2 < 7 < 5 < 5 < 6 < 5 <4 < 3 < 6 < 5 < 2 <4 < 3 <7 <7 < 6 <4 <4 <6 < 8 <2 <2 < 1 <4 < 10 < 8 < 9 < 7 < 8 <7 <6 < 11 < 8 <4 < 7 < 6 <4 <4 < 3 < 3 <2 <3 <4 < 1 < 1 < 1 < 2 < 6 <4
<4 < 5 < 5 < 3 < 3 < 6 <4 <2 < 3 < 3 <4 <4 <4 <2 < 3 < 3 <4 < 1 < 1 < 1 < 2 < 6 <4 < 5 < 5 < 5 <4 < 3 < 6 <4 <2 <4 < 3 < 27 < 24 < 29 < 21 < 23 < 25 < 29 < 14 < 18 < 14 < 18 < 30 < 31 < 26 < 23 < 26 < 27 < 19 < 28 < 28 < 16 < 31 < 22 < 9 < 7 < 8 < 7 <6 < 8 < 9 <5 <4 <4 < 6 < 9 < 8 < 9 < 7 <6 < 9 <6 < 9 < 8 < 5 < 10 < 8 ttl I ...... 0 TABLE B-1.3 CONCENTRATiONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 SITE RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 There were no hard to detect analyses analyzed in 2015 U-235 U-238 Fe-55 Ni-63 TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-1 01/28/15 < 184 SW-E-1 04/21/15 < 192 SW-E-1 07/29/15 < 195 SW-E-1 10/07/15 < 192 SW-E-2 01/28/15 < 184 SW-E-2 04/21/15 < 192 SW-E-2 07/29/15 < 193 SW-E-2 07/29/15 < 190 SW-E-2 10/07/15 < 196 SW-E-3 01/28/15 < 184 SW-E-3 04/21/15 < 194 SW-E-3 07/29/15 < 191 SW-E-3 10/07/15 < 195 B-11 TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE SW-E-1 04/21/15 < 34 < 33 <3 < 3 < 9 <4 < 8 <4 < 7 < 3 < 3 <
25 < 9 SW-E-2 04/21/15 < 37 < 24 < 3 <4 < 7 < 3 <6 <4 < 7 <4 <4 < 28 < 6 SW-E-3 04/21/15 < 43 < 35 <4 <4 < 8 <4 < 9 < 5 < 7
<4 < 5 < 31 < 9 t:t:I I -N TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 EDCB 02/06/15 424 +/- 146 EDCB 04/28/15 < 189 EDCB 07/28/15 < 186 EDCB 11/03/15 316 +/- 135 B-13 TABLE B-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE EDCB 02/06/15 < 32 < 59 <4 < 3 < 7 <4 < 6 <4 < 6 <4 <4 < 28 < 9 EDCB 04/28/15 < 31 < 90 < 5 < 5 <
11 < 4 < 8 . < 6 < 10 <4 < 5 < 33 < 5 EDCB 07/28/15 < 97 < 221 < 9 < 9 <
19 < 10 < 18 < 9 < 14 < 11 < 9 < 35 < 12 EDCB 11/03/15 < 45 < 87 < 6 < 6 <
12 < 6 < 14 < 5 < 9 < 5
<6 < 29 < 9 TABLE B-IV.1 SITE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE; TM-PR-ESE TM-PR-ESE TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-22 TM-PR-MS-22 TM-PR-MS-22 TM-PR-MS-4 TM-PR-MS-4
TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MW"22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S
TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION DATE H-3 03/09/15 380 +/- 135 05/11/15 266 +/- 130 07/20/15 < 181 10/09/15 Original 1290 +/- 193 10/09/15 Recount 1310 +/- 203 10/09/15 Rerun 1220 +/- 186 03/09/15 < 183 05/11/15 < 183 07/20/15 < 179 10/09/15 < 187 03/09/15 401 +/- 134 05/11/15 < 186 07/20/15 < 178 10/09/15 Original 1220 +/- 186 10/09/15 Recount 988 +/- 172 10/09/15 Rerun 908 +/- 162 05/07/15 Original 3110 +/- 355 05/07/15 Rerun 3260 +/- 370 05/07/15 Rerun/recount 2770 +/- 321 03/09/15 373 +/- 133 05/11/15 .192 +/- 125 07/20/15 < 178 10/09/15 Original 544 +/- 142 10/09/15 Recount 466 +/- 144 10/09/15 Rerun 637 +/- 154 05/21/15 560 +/- 146 06/02/15 461 +/- 144 06/16/15 < 175 06/30/15 1270,+/- 182 07/16/15 Original 2640 +/- 322 07/16/15 Recount 3140 +/- 367 07/16/15 Rerun/recount 3110 +/- 369 07/27/15 5940 +/- 644 08/11/15 Original < 185 08/11/15 Recount < 190 08/11/15 Rerun < 197 08/25/15 823 +/- 161 09/21/15 665 +/- 155 10/05/15 650 +/- 153 10/20/15 256 +/- 131 11/17/15 Original 7680 +/- 819 11/17/15 Recount 8020 +/- 854 11/17/15 Rerun 8170 +/- 870 12/04/15 2970 +/- 354 12/21/15 4110 +/-474 B-15 Intentionally left blank APPENDIX C DATA TABLES-COMPARISON TABLE C-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A Gr-B MS-20 07/27/15 484 +/- 101 MS-21 01/27/15 222 +/- 104 MS-21 10/07/15 186 +/- 81 MS-7 10/06/15 < 149 MW-TMl-10l 04/22/15 952 +/- 120 MW-TMl-10l 10/07/15 580 +/- 99 MW-TMl-140 01/29/15 262 +/- 106 MW-TMl-140 10/07/15 184 +/- 81 MW-TMl-141 07/28/15 143 +/- 86 MW-TMl-201 04/22/15 382 +/- 98 MW-TMl-20 04/21/15 162 +/- 88 MW-TMl-31 04/23/15 243 +/- 92 < 0.5 < 0.4 < 2.4 < 1.6 MW-TMl-61 01/29/15 < 180 MW-TMl-91 04/21/1.5 162 +/- 88 NW-CW 07/28/15 721 +/- 110 OSF 04/17/15 296 +/- 95 < 0.5 < 0.5 < 2.9 2.5 +/- 1.4 RW-1 01/28/15 < 180 C-1 TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER+/-
2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD MW-TMl-201 04/22/15 < 26 94 +/- 50 <4 <4 < 3 < 2 < 5 < 5 < 3 < 2
<2 < 22 < 3 MW-TMl-20 04/21/15 < 35 70 < 3 < 3 <2 < 2 < 7 < 6 < 2 < 2 < 3 < 25 <4 MW-TMl-31 04/23/15 < 30 61 < 2 < 3 <2 < 2 < 3 < 3 < 3 < 2 < 1 <
13 < 4 MW-TMl-91 04/21/15 < 26 43 < 3 < 3 <2 <2 < 4 <4 < 2 <2 < 3 < 20 < 3 OSF 04/17/15 < 29 40 < 2 < 5 < 3 < 1 < 4 < 5 <2 < 2 <2 < 16 <4 n I N
(") I w TABLE C-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-233/234 U-235 U-238 Fe-55 Ni-63 PERIOD NONE FOR 2015 TABLE C-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-2 07/29/15 < 150 C-4 n I Vi TABLE C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD NONE FOR 2015 TABLE C-111.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 SITE TM-PR-MS-20 TM-PR-MS-20 TM-PR-MS-20 TM-PR-MS-20 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION DATE 03/30/15 06/24/15 09/02/15 11/16/15 H-3 < 149 235 +/- 83 < 147 1073 +/- 122 C-6 Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1and2 Annual Radiological Environmental Operating Report
1 January Through 31 December 2015 Prepared By Teledyne Brown Engineering Environmental Services Three Mile Island Nuclear Station Middletown, PA 17057 April 2016 Intentionally left blank Table Of Contents I. Summary and Conclusions
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1 II. Introduction
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3 A. Objectives of the REMP .....................................
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3 B. Implementation of the Objectives
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4 Ill. Program Description

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4 A. Sample Collection
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4 B. Sample Analysis ..................................................................................................
6 C. Data Interpretation
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7 D. Program Exceptions
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8 E. Program Changes ................................
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11 IV. Results and Discussion
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1*1 A. Aquatic Environment
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11 1. Surface Water .........................................................
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11 2. Drinking Water .........................................................................................
12 3. Effluent Water ......................
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13 4. Storm Water ...........................................................................................
14 5. Ground Water .........................................................................................
14 6. Fish .................................................................................................
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14 7. Sediment.
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15 B. Atmospheric Environment
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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. Milk ...............................................................................................
16 b. Food Products .............................................................................
17 C. Ambient Gamma Radiation
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18 D. Land Use Survey ...............................................................................................
18 E. Radiological Impact ofTMINS Operations
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19 F. Errata Data .........................................................................................................
26
G. Summary of Results -Inter-laboratory Comparison Program .........................
26 V. References
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30 Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table 8-2 Table B-3 Figures Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Appendices Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2015 Location Designation, Distance & Direction An.d 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, 2015 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Environmental Sampling*
Locations Within One Mile of the Three Mile Island Nuclear Station, 2015 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2015 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2015 Data Tables and Figures -Primary Laboratory . Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015.
Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. ii Table C-11.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the,Vicinity of Three Mile Island Nuclear Station, 2015. Table C-11.2 Concentrations of 1-131 in Drinking Water Samples Collected in the ViGinity of Three Mile Island t;Juclear Station, 2015. Table C-11.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-111.1 Concentrations of Gross Beta, 1-131, Tritium, and Strontium in E,ffluent Water Samples for Station K1-1 Collected in the Vicinity of Three Mile Island NuGlear Station, 2015. Table C-111.2 Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-IV:1 Concentrations of Strontium in .Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. --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, 2015.
Table C-V.1 Concentrations of Gamma Emitters in Sediment .Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-Vl.1 C.oncentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 201.5. Table C-Vl.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) In Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-Vl.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the. Vicinity of Three Mile Island Nuclear Station, 2015. Table C-Vll.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015.
Table C-Vlll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear 2015. *
Table C-Vlll.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Statio.n, 2015.
Table C-Vlll.3 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Table C-IX.1 Cqncentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. iii Table C-X.1 Quarterly OSLO Results for Three Mile Island Nuclear Station, 2015. Table C-X.2 Mean Quarterly OSLO Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2015. Table C-X.3 Summary of the Ambient Dosimetry Program for Three Mile Island Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 1 Figure C-7 Figure C-8 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-11.1 . Nuclear Station, 2015. Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2015. Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2015. * . Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2015. Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2015. Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2015. Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2015. Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 -2015. Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2015. Data Tables and Figures -Comparison Laboratory Concentrations of Gross Beta in Drinking Wat,er Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2015. Concentration of Tritium in Drinking Water Samples Collecteq in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of lodine-131 ir:i Drinking Water Sample.s Collected in the Vicinity of Three Mile Nuclear Station, 2015. Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. iv*
Table D-111.1 Table D-IV.1 Table D-V.1 Table D-V.2 Table D-Vl.1 Figures Figure D-1 Figure D-2 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1 Q, 2015. Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2015. Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Teledyne Brown Engineering, 2015 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Environmental, Inc., 2015 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 2015 through 31 December 2015. During that time_ period, 1,694 analyses were performed on 1,305 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 1-131, Sr-89 and Sr-90 activities were detected.
Gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in 11 surface water samples, two drinking water samples and 11 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-137 was detected in one sediment sample. Occasionally Cs-137 is detected at very low levels Gust 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, Sr-89 or Sr-90 activities were detected.
Concentrations of naturally occurring K-40 were consistent with those detected in previous years. Occasionally Sr-90 activities are detected and are consistent with those detected in previous years and were attributed to fallout from nuclear weapons testing. No other fission or activation products were found. 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 nat1,Jrally 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 (OSLO) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued.
This change resulted in a slight change in process and reporting of quarterly results. The relative comparison to control locations remains valid. OSLO 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 2015 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 environment afld no increase in b.ackground radiation levels.
Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2015 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.
TMl-1 is owned and operated by Exelon and beca*me operational in 1974. TMl-2 is operated by GPU Nuclear, Inc. and owned by Metropolitan Edison (50%), Pennsylvania Electric (25%) and Jersey Central Power & Light (25%). TMl-2 became operational in 1978 and was shut down following the 1979 accident.
At the end of 1993 TMl-2 was placed in a condition called Post-Defueling Monitored -Storage.
TMl-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 2015 through 31 December 2015. 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 TMl-1 and TMl-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 2015. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3. Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, fish and sediment.
Two gallon water samples were collected monthly from continuous samplers located at two surface water locations (J1-2 and Q9-1 ), three drinking water locations (G15-2, G15-3 and Q9-1 ), and one effluent water location (K1-1 ). A composite of weekly grab samples at one surface water location (A3-2) were collected.
The control locations were A3-2 and Q9-1. All groundwater and storm water results are now being reported in the ARGPPR, Appendix F. All water samples were collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection.
Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND) location.
Location IND could be affected by TMINS' effluent releases.
Sediment samples composed of recently deposited substrate were collected semiannually at three locations (A 1-3, J2-1 and K1-3). In addition, one sediment sample was collected annually at the East Dike Catch Basin (EDCB)'. Location A 1-3 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 p'articulate samples were collected and analyzed weekly at seven locations (A3-1, E1-2, F1-3,*G2-1, H3-1, M2-1 and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using' a vacuum pump with charcoal and glass fiber filters *attached.
The pumps were run , continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly-and sent to the laboratory for analysis.
Terrestrial Environment
_The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product.*
Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K15-3 and P4-1) from March through November, and monthly. from December through February.
The control location was K15-3. All samples were collected in new unused. two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory.
Food products were collected monthly at three locations (810-2, E1-2 and H1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2*and H1-2). 810-2 was the control loca.tion for both annual and monthly sampling.
Three different kinds of vegetation.
samples and seven 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 cha*nged the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLO) were *deployed and 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. OSLO 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 (A 1-4, 81-2, C1-2, 01-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, L1-1, M1-1, N1-3, P1-2, Q1-2 and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release. An indicator ring consisting of 60 locations (A3-1, A5-1, A9-3; 81-1, 82-1, 85-1, 810-1, C1-1., C2-1, C5-1, CB-1, 01-2, 02-2, 06-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, FS-1, F10-1, G1-2, G2-4, .G5-1, H3-1, H5-1, HB-1, J1-1, J3-1, J5-1, J?-1 K2-1, K3-1, K5-1, KB-1, L 1-2, L2-1, L5-1, LB-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1,'N5-1, NB-1, P1-1, P2-1, P5'-1, PB-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, .R5-1 and R9-1) extending to apprqximately 10 miles from the site, designed to measure possible exposures to close-in population.
The balance of 11 locations (015-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L 15-1, 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 Al20 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 OSLO responds to radiation independently, this provides two independent detectors .at each. station. 8. Sample Analysis This section describes the general analytical methods used by T8E and . Midwest Labs to analyze the environmental samples for radioactivity for the TMINS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-3.
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.
1 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 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 a*nalysis.
The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity.
Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.
Gamma spectroscopy results for each type of *sample were grouped as follows: For surface, drinking, and effluent water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.
For fish eight nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134 and Cs-137 were reported.
For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were reported.
For air particulate eight nuclides, Be-7, Mn-54, Co-58, Co-60, Nb-95, Zn-95, Cs-134 and Cs-137 were reported.
For milk five nuclides, K-40, Cs-134, Cs-137, Ba-140 and La-140 were reported.
For food products five nuclides, Be-7, K-40, 1-131, Cs-134 and Cs-13 7 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 2015 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 015-1 1. For the sampling period 02/05/15 to 02/12/15, the vacuum pump malfunctioned.
Pump and timer were operating but not pulling any vacuum. Per procedures, samples were invalid and not sent to the lab for analyses.
Pump was replaced on 02/14/15, and sampler was returned to service. For sampling period 02/12/15 -02/19/15, the total volume was impacted, but per procedures, the samples were valid and sent to the lab for analysis. (IR 2500642) G2-:I 2. For the sampling period 04/02/15 to 04/09/15 and 04/09/15 to 04/16/15, there were lower than expected run times and air volumes due to power interruptions.
Maintenance work was in-progress at the farm which is now completed.
Per procedure, the samples were still valid and sent to the lab for analysis.
Offsite lab still achieved required LLD for iodine sampling and particulate results were normal. (IR 2500733) H3-1 3. For the sampling period 05/14/15 to 05/21/15 and 05/21/15 to 05/28/15, breaker was found tripped. The breaker was reset and sampler. was returned to service. Sample volumes were lower than normal but still valid per procedure and sent to the lab for analyses. (IR 2553457) . H3-1 4. For the sampling period 06/18/15 to 06/25/15, the sample pump malfunctioned and was found not operating.
The sample volume was insufficient.
Per procedure, the samples were not valid and were not *sent for analysis.
The pump was replaced on 06/26/15 and the sampler was returned to service. (IR 2553457) H3-1 5. For the sampling period 08/19/15 to 08/27 /15, a potentially invalid sample was collected.
During the previous weeks collection, the vacuum switch tubing was not seated properly when connected, and as a result the run timer did not operate. The pump was operational and the sample appeared normal. The sample on and off time were used to calculate run hours as an alternate volume estimation.
The samples were not valid per procedure, but were sent for analyses to the lab with the approximated volume. (IR 2553457) E1-2 6. For the sampling period 12/03/15 to 12/10/15, the breaker was found tripped. The breaker was reset and sampler was returned to service. Sample volumes were lower than normal but still valid per procedure and sent to the lab for analysis. (IR 2631797)
WATER 1. A3-2 Due to Swatara Creek being frozen,over could not break ice and collect grab sample for 02/17/15 to 02/24/15 sampling period. February composite will consist of three rather than four samples. (IR 2500642) 09-1 2. For the sampling period 04/14/15 to 04/21/15, the drinking water sampler was found with the GFI tripped. One hundred and twenty three (123) samples were missed, and insufficient sample volume was* collected.
Grab samples were taken to.supplement the volume of water collected for the week. The GFI was reset and the sampler was returned to service. (IR 2500733) Q9-1 -3. For drinking water weekly sample from 10/27/15 to 11/03/15, 105 hourly samples were missed due to a power interruption probably related to plant maintenance at the water treatment facility.
Insufficient sample volume was collected to meet all QA and backup samples, and grab samples were taken to supplement the volume of water collected for the week. (IR 2631797) Q9-1 4. For surface water weekly sample from 12/01/15 to 12/08/15, sampler was found with GFI tripped and 97 hourly samples were missed. Sufficient sample volume was collected.
The GFI was reset and the sampler was returned to service. (IR 2631797) Dosimeter L2-1 1. Telephone mounting pole replaced and first quarter dosimeters could not be located. New mounting hardware was installed on the new pole for second quarter dosimeter installation., (IR 2500642) R3-1 2. First quarter dosimeters found under snow on the ground. Dosimeters were sent for analyses.
Dosimeter analysis results were not impacted. (IR 2500642)
Vegetation H1-2 1. Indicator vegetation plants were not mature enough to harvest for June. (IR 488572) 2. 810'-2 Due to growing season ending, only one of three monthly samples were available from the control garden for August and September. (IR 488572) Each program exception was reviewed to understand the causes of the program exception.
Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence.
Occasional equipment breakdowns and power outages were unavoidable.
The overall sample recovery rate (>99%) indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
E. Program Changes There were no changes to the program in 2015. IV. Results and Discussion A. Aquatic Environment
1. Surface Water Samples were taken weekly from a continuous sampler at two locations (J1-2 and Q9-1) and weekly grab samples from one location (A3-2). Weekly samples were composited on a monthly schedule.
Of these locations only J 1-2 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 11 of 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 454 to 6,250 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 were taken from location A3-2. This is a control or background station sampled because known medical discharges of radiopharmaceuticals occur into the surface. water upstream of TMI from a nearby hospital.
Monthly samples were taken from A3-2 and analyzed for 1-131. (Table C-1.2, Appendix C). lodine-131 activity was not detected in any samples. Gamma Spectrometry Locations J1-2 and 09-1 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 G15-3 and 09-1). 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 21 of 36 samples. The concentrations ranged from 2.0 to 5.5 pCi/I. Concentrations detected were .consistent with those detected in previous years (Figure C-3, . Appendix C).
Iodine Monthly samples from all locations were analyzed for concentrations of 1-131 (Table C-11.2, Appendix C). lodine-131 activity was not detected in any samples. Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was detected in two of 36. The concentrations ranged from 288 to 621 pCi/L. The hypothetical dose to the maximum exposed individual from consuming this water during both time periods was calculated as <0.009 mrem (IR 2469947/2531179 (Figures C-4, Appendix C). Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.4, Appendix C). All nuclides were less than the MDC. 3. Effluent Water Monthly samples were collected from. a continuous water sampler at one location (K1-1). The following analyses were performed:
Gross Beta Monthly samples from location K1-1 were analyzed for concentrations of gross beta (Tables C-111.1, Appendix C). Gross beta was detected in all 12 samples. The concentrations ranged from 2.1 to 8.3 pCi/I. Concentrations detected were consistent with those detected in previous years. lodine-131 Monthly samples from location K1-1 were analyzed for concentrations of 1-131 (Tables C-111.1, Appendix C). lodine-131 was not detected in any of the samples .. Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-111.1, Appendix C). Tritium activity was detected in 11 of 12 samples. The concentrations ranged from 5,440 to 106,000 pCi/I. The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations.
These results were from the liquid discharge mixing basin .. The concentrations detected agree with those obtained from the TMINS Effluent Monitoring Program. The concentrations were well below any regulatory limits. (Figure C-4, Appendix C} Strontium . .
Semiannual composite samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-111.1, Appendix C). No strontium activity was detected. highest MDC was calculated at <4.0 pCi/I for Sr-89 and at <0.9 pCi/I for Sr-90. Gamma Spectrometry . Samples from location K1-1 were analyzed for gamma emitting nuclides (Table C-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 (ARGPRR), 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 <4.2 pCi/kg wet for Sr-90.
Gamma Spectrometry The edible portions of fish samples from *bath 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 1 ,439 to 4,283 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 (A 1-3, 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 5,753 to 14,700 pCi/kg dry. Cs-137 was found in one sample at a concentration of , 211 pCi/kg d!)'. No other fission or activation products were detected.
Cesium-137 is occasionally found in sediment at very low levels Oust above LLD) and is not distinguishable from background levels (Figure C-5, Appendix C). B. Atmospheric Environment 1.. Airborne Particulates
a. Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. Six locations (A3-1, E1-2, F1-3, G2-1, H3-1 and M2,..1) were indicator stations located in the highest D/Q sectors and the nearest communities to TMI. One sample (015-1) 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-Vl.1 and C-Vl.2, Appendix C). -1,5 -
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 31 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3. The results from the intermediate offsite locations (Group II) ranged from 6 to 41 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. The results from the Control location (Group Ill) ranged from 7 .to 36 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. Comparison of the 2015 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 2015 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-Vl.3, Appendix C). Naturally occurring Be-7 due to cosmic ray activity was detected in 26 samples. These concentrations ranged from 39 to 112 E-3 pCi/m3. All other nuclides were less than the MDC. b. Airborne Iodine Continuous air samples were collected from seven (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1 and 015-1) locations and analyzed weekly for 1-131 (Table C-Vll.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:
lodine-131 Milk samples from all locations were analyzed for concentrations of 1-1,31 (Table G-Vlll.1, Appendix C). All results were less than the MDC.
Strontium Milk samples from all locations were composited quarterly and analyze6 for,Sr-89 and Sr-90 (Table C-Vlll.2, Appendix C). No Sr-89' or Sr-90 activity was detected .. Occasionally Sr-90 is detected and is consistent with those detected in the years (Figure C-8, Appendix C). ' ' Gamma Spectrometry Milk samples from all locations were analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.3, Appendix C). Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 703 to 1,657 pCi/L. All other nuclides were less than the MDC. b. Food Products Food products were collected monthly at three locations (810-2, E1-2 and H1-2), in lieu of milk sampling., and annually from the four food product groups at two locations (810-2, E1 "2 and H1:-2). 810-2 was the control location for both annual and monthly sampling.
The following analyses were performed:
Strontium Nineteen of 25 food product samples were analyzed for concentrations of Sr-90 (Table C-IX.1, Appendix C). Strontium-90 activity was detected in eight of 19 samples. The concentrations ranged from 3 to 11 pCi/kg wet. Gamma Spectrometry Each food sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). Naturally occurring 8e-7 due to cosmic ray activity was detected in 14 of' 25 samples. These concentrations ranged from 153 to 1,965 pGi/kg. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from -1.7 -
1,996 to 7,653:pCi/kg.
All *other nuclides were less than the MDC. C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Optically Stimulated Luminescence Dosimeter (OSLO). Ninety OSLO locations were established around the site. Results of OSLO measurements are listed in Tables C-X.1 to C-X.3, Appendix C All of the OSLO measurements were below 40 mR/quarter, with a range of 17.2 to 37.8 mR/standard quarter. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations 015-1, F25-1, G10-1, G15-1, H15-1, J15-1,. K15-1, L15-1, N15-2, 015-1 and R15-1 averaged higher than indicator stations.
Locations 015-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, 015-1 and R15-1 have a historical
high bias, and this *bias is most likely due to radon and other naturally . occurring nuclides, e.g. K-40, emanating from the ground.
D. Land Use Survey A Land Use Survey conducted in the July through November 2015 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 ft 2 in each of the sixteen 22 % degree sectors around the site. For 2015, a meat census was also performed.
The results of these surveys are summarized below.
E. 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 1.2 2.4 3 NE 0.5 1.1 4.2 2.4 4 ENE 0.5 0.5 4.5 1.1 5 E 0.4 0.5 1.1 1.1 6 ESE 1.1 1.2 3.2 1.1 7 SE 0.7 ' ' 1.6 1.4 1.4 8 SSE 0.7-0.8 1.8 9 s 2.3 2.5 3.3 10 SSW 0.6 1.6 4.9, 14.4 4.9 11-SW 0.5 1.0 12 WSW 0.5 . 1.3 13 w 0:1 1.4 14 WNW 0.4 1.7 3.7 2.4 15 NW 0.4 1.2 16 NNW 1.1 2.4 Radiological Im-pact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the pubiic fror:n 2015 operations at TMINS were well below all applicable regulato*r)f limits and were significantly less than doses received from natural sources of radiation.
The 2015 whole body dose potentially received by an assumed maximum exposed individual from TMl-1 and TMl-2 liquid and airbo_rne effluents was conservatively calculated to be 0.12 mrem. This dose is equivalent to 0.04% of the dose that an individual living in the TMI area receives each year from natural background radiation.
1. Determination of Radiation Doses to the Public Dose assessments can be performed by using either effluent data and an environmental transport model or environmental sample data. To the extent possible, doses to _the public are based on the direct measurement of dose rates from external sources and the measurement of radionuclide concentrations in environmental media which may contribute to an internal dose of radiation.
Optically Stimulated Luminescent Dosimetry (OSLDs) positioned in the environment around TMINS provide measureme.nts to determine external radiation doses to humans. Samples of air, water and food products are used to determine internal doses. The quantity of radioactive materials released during normal operations are typically too small to be measured once distributed in the offsite environment.
Therefore, the potential offsite doses are more effectively calculated for TMINS operations using a computerized model that predicts concentrations of radioactive materials in the environment and subsequent radiation doses based on measured effluents.
Doses are calculated using a model that incorporates the guidelines and methodology set forth by the USN RC in Regulatory Guide 1.109 and NUREG 0133. Due to the conservative assumptions that are used in the model, the calculated doses are generally higher than the doses based on actual environmental sample concentrations.
Therefore, the model predicts doses that are higher than actual doses received by people. The type and amount of radioactivity released from TMINS is calculated using measurements from effluent sample analyses. " Airborne releases are diluted and carried away from the site by atmospheric diffusion, which continuously acts to disperse radioactivity.
Variables that affect atmospheric dispersion include wind speed, temperature at different elevations, terrain, and shift in wind direction.
A weather station on the north end of TMI is linked to a data logger that records the meteorological data. Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Susquehanna River. Actual' monthly Susquehanna River flows are obtained from the USGS Stream gauging station 01570500 located at Harrisburg, PA. The human exposure pathways also are included in the model and are depicted in Figure 1. The exposure pathways that are considered for the discharge of TMINS liquid effluents are consumption of drinking water and fish. The exposure pathways considered for the discharge of TMINS ai_rborne effluents are plume exposure, inhalation, cow milk consumption, fruit and vegetable consumption, and meat consumption.
When determining the dose to humans, it is necessary to consider all applicable pathways and all exposed tissues, summing the dose from each to provide the to,tal dose for each organ as well as the whole body from a given radionuclide.
Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted *and half-life.
The dose assessment model also contains dose conversion factors for the radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, .skin, kidney, lung, bone and GI tract). 2. Result of Dose Calculations The maximum hypothetical doses due to 2015 TMl-1 and TMl-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 ofthe 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 2015 operations at TMINS were well below the Federal dose limits (US EPA 40 CFR 190) and the guidelines of USN RC 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 2015 TMl-1 and TMl-2 liquid and airborne effluents combined was conservatively calculated to be 0.12 mrem. This dose is equivalent to 0.04% percent of the dose that an individual living in the TMI area receives each year from . natural background radiation (311 mrem). The low doses calculated for 2015 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).
In conclusion, radioactive materials related to 2015 TMINS , operations were detected in environmental samples, but the concentrations were low and consistent with measured effluents.
The environmental sample results verified that the doses received by the public from TMINS effluents in 2015 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 n'o 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 2015 did not have any adverse effects on the health of the public or on the environment.
TABLEl Calculated Maximum Hypothetical Doses to an Individual from 2015 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual From Radionuclides In Liquid Releases From Radionuclides In Airborne Releases (Noble Gases) From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates)
No noble gases were released from TMI-2. Total from Site USNRC . 10 CFR 50 APP. I Guidelines (mrem/yr) 3 total body, or 10 any organ 5 total body, or 15 skin 15 any organ USEPA 40CFR190 Limits (mrem/yr) 75 thyroid 25 total body or other organs Calculated Dose (mrem/yr) TMI-1 TMI-2 2.52E-2 4.l 7E-4 2.62E-2 6.60E-4 4.07E-4 5.99E-4 O* O* 3.88E-1 2.86E-5 Calculated Dose (mrem/yr)
TMI-1 and TMI-2 Combined**
0.62 0.92 **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 2015 TMINS operations was 0.50 mrem. This dose was based on a maximum net fence-line exposure rate and a shoreline/fence-line occupancy factor of 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months (Regulatory Guide 1.109). The combination of the maximum organ dose from TMI-1 and TMI-2 effluents (0.42 mrem) and the dose from direct radiation (0.50 mrem) yielded a maximum hypothetical dose of0.92 mrem.
TABLE2 .Calculated Whole Body Doses to the Maximum Individual From 2015 TMI-1 and TMI-2 Liquid and Airborne Effluents From Radionuclides In Liquid Releases From Radionuclides in Airborne Releases ** (Noble Gases)
From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates)
No noble gases were released from TMl-2. Calculated Maximum Individual Whole Body Dose (mrem/yr)
TMI-1 TMI-2 2.52E-2 4.17E-4 4.07E-4 O* 9.83E-2 2.86E-5 Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations:
0 .12 mrem/yr Individual Whole Body Dose Due to Natural Background Radiation (1) 311 mrem/vr (1) NCRP 160 -(2009)
Figure 1 Exposure Pathways For Radioifuclides Routinely Released From TMINS PEOPLE t IPREDOl\UNANT RADIONUCLIDES
! . .,.,J NOBLE GASES Plume exposure RADIOIODINES (H31, I-133) rnhalation and c-0nsumption of milk, water. fruits, and vegetables R.AOIOSTRONTIUM$
Sr-90) Consumption of rn ilk. meat, fruits, and vegetsiblcs ACTIVATION PRODUCTS Mn-54) Shoreline expos11re RADIOCESWMS (Cs* l34, Cs*l37) Sh<>reHne e:xp.;1sure and coniiumpHon of milk, meat, fish, water, f.ru its, and vegetables TRtTIUM (H*3) Inhalation a11d t:onsumption of water, milk, fruits, and vegetables F. Errata Data There is no errata data for 2015. G. Summary of Results -Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:
1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC,. state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable.
The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the *appropriate regulatory document.
3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. The MAPEP defines three levels of performance:
Acceptable (flag = "A"), Aq;eptable 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 wtien 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, 129 out of 139 analyses performed met the specified acceptance criteria.
Ten analyses (AP -Cr-51, U-234/233, Gr A, Sr-9o;*soil Sr-90; Water -Ni-63,* Sr-89/90, U natural; Vegetation Sr-90 samples) did not meet the specified acceptance criteria for the following reasons and were addressed through the TBE Corrective Action Program: Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained at commercial nuclear power facilities . . 1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Gr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio .of 1.30 (acceptable with warning) was exceeded.
The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the shortest half-life (27.7 days) and the lowest gamma energy (320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations).
This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable.
NCR 15-18 . . 2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr-90 result of 286 Total Bq/kg. was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested sample utilized for analysis.
The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was.evaluated as acceptable with a result of .694 and an acceptance range of 601 -1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a* result of 429 and an acceptance range of 298'-553 Bq/kg. This issue is specific to the March 2015 MAPEP sample. NCR 15-13 . 3. Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233.result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper c;icceptance range of 0.0202 Sq/sample.
Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would . overlap with the known value, which* is statistically considered acceptable.
MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of*0.96) than the normal U-234/233.
Due to the extremely low activity, *it was difficult to quantify the U-234/233.
NCR 15-13 4. Teledyne Brown Engineering's MAPEP Marth 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the lower acceptance range of 0.53 Sq/sample.
The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard.
The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency.
When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and
cannot escape to be*counted.
When the sample media absorbs the alpha particles this is known as self-absorption or attenuation.
The calibration must include a similar configuration/media to correct for the attenuation.
In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters. The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24 -1.53 Sq/sample.
Unlike the MAPEP samples *. air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed.
NCR 15-13* 5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 .+/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" .or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot' of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21 6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53
Sq/sample.:
In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TSE suspects that this may be the *cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.
TSE will no longer analyze the air particulate Sr-90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-:-90 in the air particulate matrix. NCR 15-21 7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the *lower acceptance range of 0.91 Sq/sample.
In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for the laboratories analyzing the cross checks. TSE suspects that this maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, .can cause interferences to indicate lower activity or higher activity.
Results from previous performance.
evaluations were reviewed and shown to be acceptable.
NCR 15-21 8. & 9.Teledyne Brown Engineering's ERA May* water Sr-89/90 results of 45.? and 28.0 pCi/l, were lower than the known values of 63.2 and 41.9 pCi/l, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/l, respectively.
The yields were on the high side of the TSE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09 10. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/l was higher than the known value of 56.2 pCi/l, exceeding the upper acceptance limit of 62.4 pCi/L. The.technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57.16 agreed with the assigned value of 56.2. NCR 15-19 For the El Ml laboratory, 90 of 94 analyses met the specified acceptance criteria.
Four analyses (Water-Co-57, Fe-55; AP -Co-57; Soil -sr .. 90) did not meet the specified acceptance criteria for the following reasons:
1. Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Sq/L was lower than the known value of 29.9 Sq/L, exceeding the lower control limit of 20.9 Sq/L. The reported value should have been 27.84, which would have been evaluated as acceptable.
A data entry error resulted in a acceptable result. 2. Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value 6f 1.51 Sq/ sample, exceeding the lower control limit of 1.06 Sq/sample.
The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable.
A data entry error resulted in a hon-acceptable result. 3. Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Sq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Sq/kg. The .
separation of calcium from strontium caused a failed low result The reanalysis result of 352 Sq/kg fell within acceptance criteria .. 4. Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe"'-55 res*ult of 4.2 Sq/L was lower than the known value of 13.1 Sq/l, exceeding the lower control limit of 9.2 Sq/L. The known activity was below the routine laboratory detection limits for available aliquot fraction.
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 Nudear Station, Unit 1, Technical Specifications, DPR 50. 2. Three Mile Island Nuclear Station, Unit 2, PDMS Teclinical Specifications, DPR 73. . 3. Radiation Management Corporation. "Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1.974-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.
Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
Intentionally left blank
> I ....... NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
SURFACE WATER (PCI/LITER)
TYPES OF ANALYSIS PERFORMED H-3 I-131 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 24 12 24 REQUIRED LOWER LIMIT OF DETECTION (LLD) 2000 15* 15 30 15 30 15 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION MEAN(M) MEAN(M) MEAN(M) STATION# (F) (F) (F) NAME RANGE RANGE RANGE DISTANCE AND DIRECTION 2307 <LLD 2307 TM-SW-Jl-2 INDICATOR (11/12) (11/12) WEST SHORE; TMI (454/6250)
(454/6250) 0.5 MILES S OF SITE NA <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
SURFACE WATER (PCI/LITER)
DRINKING WATER (PCI/LITER)
TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) ZR-95 30 CS-134 15 CS-137 18 BA-140 60 LA-140 15 GR-B 36 4 I-131 36 H-3 36 2000 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD 3.1 (17/24) (2.3/5.5) . <LLD 455 (2/24) (288/621)
CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD 2.7 (4/12) (2.0/3.7)
<LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 3.2 (10/12) (2.3/5.5) . 455 (2/12) (288/621)
STATION# NAME DISTANCE AND DIRECTION 1M-DW-G15-2 INDICATOR WRIGHTS WATER SUPPLY 13.3 MILES SE OF SITE 1M-DW-G15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0
> I w NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAl\1PLED (UNITOF MEASUREMENT)
DRINKING WATER (PCI/LITER)
TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) GAMMA 36 MN-54 15 C0-58 15 J'.E-59 30 C0-60 15 ZN-65 30 NB-95 15 ZR-95 30 CS-134 15 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULAWD USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0
> I -!>-NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PA1HW A Y SAMPLED (UNITOF MEASUREMENT)
DRINKING WATER (PCT/LITER)
EFFLUENT WATER (PCT/LITER)
TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) CS-137 18 BA-140 60 LA-140 15 GR-B 12 4 I-131 12 H-3 12 2000 SR-89 2 5 SR-90 2 2 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD 4.6 (12/12) (2.1/8.3)
<LLD 31188 (11/12) (54401106000)
<LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD NA NA NA NA NA LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 4.6 (12/12) (2.1/8.3) 31188 (11112) (5440/106000)
STATION# NAME DISTANCE AND DIRECTION TM-EW-Kl-1 INDICATOR MAIN STATION LIQ. DISCHARGE ON SITE TM-EW-Kl-1 INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
EFFLUENT WATER (PCI/LITER)
TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) GAMMA 12 MN-54 15 C0-58 15 FE-59 30 C0-60 15 ZN-65 30 NB-95 15 ZR-95 30 CS-134 15 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE NA NA NA NA NA NA NA NA LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0
> I 0\ NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320. 2015 l\.1EDIUM OR PATHWAY SAMPLED (UNITOF l\.1EASUREl\.1ENT)
EFFLUENT WATER (PCI/LITER)
BOTTOM FEEDER (PCI/KG WET) TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORl\.1ED PERFORl\.1ED OF DETECTION (LLD) CS-137 18 BA-140 60 LA-140 15 SR-90 4 IO GAMMA 4 K-40 NA MN-54 130 C0-58 130 FE-59 260 INDICATOR CONTROL LOCATIONS LOCATION l\.1EAN (M) l\.1EAN (M) (F) (F) RANGE RANGE <LLD NA <LLD NA <LLD NA <LLD <LLD 2861 2945 (2/2) (2/2) (1439/4283)
(2863/3026)
<LLD <LLD <LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) l\.1EAN (M) (F) RANGE 2945 (2/2) (2863/3026)
STATION# NAl\.1E DISTANCE AND DIRECTION BKGB CONTROL CITY ISLAND UPSTREAM OF DISCHARGE THE l\.1EAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE l\.1EASUREl\.1ENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED l\.1EASUREl\.1ENTS 0 0 0 0 0 0 0 0
> I -..J NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
BOTTOM FEEDER (PCI/KG WET) PREDATOR (PCI/KG WET) TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFOR!vIBD PERFOR!vIBD OF DETECTION (LLD) C0-60 130 ZN-65 260 CS-134 130 CS-137 150 SR-90 4 10 GAMMA 4 K-40 NA MN-54 130 C0-58 130_ INDICATOR CONTROL LOCATIONS LOCATION MEAN(M) MEAN (M) (F) (F) RANGE RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 3170 3327 (2/2) (2/2) (2493/3846)
(2869/3785)
<LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 3327 (2/2) -(2869/3785)
STATION# NA!vIB DISTANCE AND DIRECTION BKGP CONTROL CITY ISLAND UPSTREAM OF DISCHARGE THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0
> I 00 NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
PREDATOR (PCI/KG WET) SEDIMENT (PCI/KG DRY) TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) FE-59 260 C0-60 130 ZN-65 260 CS-134 130 CS-137 150 GAMMA 7 K-40 NA MN-54 NA C0-58 NA INDICATOR CONTROL LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD. <LLD 11041 12635 (515) (2/2) (5753/14700)
(11580/13690)
<LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 14700 (!/!) STATION# NAME DISTANCE AND DIRECTION EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0
>-I \0 NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
SEDIMENT (PC!/KG DRY) AIR PARTICULATE (E-3 PCI/CU.METER)
INDICATOR LOCATIONS TYPES OF NUMBER OF REQUIRED MEAN(M) ANALYSIS ANALYSIS LOWER LIMIT (F) PERFORMED PERFORMED OF DETECTION RANGE (LLD) C0-60 NA <LLD CS-134 150 <LLD CS-137 180 211 (1/5) GR-B 362 10 17 (307/311)
(6/41) GAMMA 28 BE-7 NA 66 (22/24) (39/112) MN-54 NA <LLD C0-58 NA <LLD C0-60 NA <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD 18 (51/51) (7/36) 62 (4/4) (42/78) <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 211 (Ill) 18 (51/51) (7/36) 74 (4/4) (44/103) STATION# NAME DISTANCE AND DIRECTION EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE TM-AP-Ql5-l CONTROL WEST FAIRVIEW 13.5 MILES NW OF SITE TM-AP-M2-l INDICATOR FISHING CREEK; GOLDSBORO 1.3 MILES WSW OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0
> I -0 NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
AIR PARTICULATE (E-3 PCI/CU.METER)
A!RIODINE (PCI/CU.M)
MILK (PCIILITER)
TYPES OF ANALYSIS PERFORMED NB-95 ZR-95 CS-134 CS-137 GAMMA 1-131 I-131 SR-89 SR-90 NUMBER OF ANALYSIS PERFORMED 362 110 20 20 REQUIRED LOWER LIMIT OF DETECTION (LLD) NA NA 50 60 70 5 2 INDICATOR LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0
> I --NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
MILK (PCT/LITER)
VEGETATION (PCI/KG WET) INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION# ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION (LLD) GAMMA 110 K-40 NA 1281 1267 1418 TM-M-F4-1 INDICATOR (88/88) (22/22) (22/22) TURNPIKE ROAD FARM (703/1657) (1120/1477) (1242/1657) 3.0 MILES ESE OF SITE CS-134 15 <LLD <LLD CS-137 18 <LLD <LLD BA-140 60 <LLD <LLD LA-140 15 <LLD <LLD SR-90 19 10 7 7 7 Hl-2 INDICATOR (4/10) (4/9) (4/9) RED HILL MARKET (3/11) (4/8) (3/11) 1.0 MILES SSE OF SITE GAMMA 25 BE-7 NA 891 737 981 Hl-2 INDICATOR (8/13) (6/12) (7/9) RED HILL MARKET (263/1654)-
(153/1965)
(499/1654)
!. 0 MILES SSE OF SITE K-40 NA 3872.2 3912.8 4163.3 El-2 INDICATOR (13/13) (12/12) (4/4) TMI VISITOR'S CENTER (2079/7428) (1996/7653) (2339/7428) 0.4 MILES E OF SITE THE MEAN AND 2 STANDARD DEVIATION VALVES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0
> I ...... N NAME OF FACILITY:
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2015 THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: LOCATION OF FACILITY:
MIDDLETOWN COUNTY PA REPORTING PERIOD: 50-289 & 50-320 2015 MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
VEGETATION (PCI/KG WET) DIRECT RADIATION (MILL!REM/STD.MO.)
INDICATOR LOCATIONS TYPES OF NUMBER OF REQUIRED MEAN(M) ANALYSIS ANALYSIS LOWER LIMIT (F) *PERFORMED PERFORMED OF DETECTION RANGE (LLD) I-131 60 <LLD CS-134 60 <LLD CS-137 80 <LLD OSLD-QUARTERL Y 359 NA 22.4 (3151315)
(12.1/37.8)
CONTROL I,OCATION MEAN(M) (F) RANGE <LLD <LLD <LLD 24.5 (44/44) (19.8/33.9)
LOCATION WITH HIGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 33.1 (4/4) (30.1/37.8)
STATION# NAME DISTANCE AND DIRECTION HS-I INDICATOR SAGINAW ROAD 7.4 MILES SSE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION
& ANALYTICAL METHODS Intentionally left blank TABLE B-1: Location Designation and Identification System for the Three Mile Island Nuclear Station XYY-Z-General code for identification of locations, where: 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.
Radial Zone of Sampling Location in miles. Station's Numerical Designation within sector and zone, using 1, 2, 3 ... in each sector and zone. B-1 TABLE 13-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Sample Station Map Distance Medium Code (miles) Azimuth Description AQS A1-3 0.6 359° N of site off north tip of TMI in Susquehanna River ID A1-4 0.3 50 N of Reactor Building on W fence adjacent to North Weather Station, TMI AP,Al,ID A3-1 2 2.7 357° N of site at Mill Street Substation SW A3-2 2 2.7 356° N of site at Swatara Creek, Middletown ID A5-1 2 4.4 30 N of site on Vine Street Exit off Route 283 ID A9-3 3 8.0 20 N of site at Duke Street Pumping Station, Hummelstown ID B1-1 1 0.6 25° NNE of site on light pole in middle of North Bridge, TMI ID B1-2 1 0.4 24° NNE of Reactor Building on top of dike, TMI ID B2-1 2 1.9 17° NNE of site on Sunset Dr. (off Hillsdale Rd.) ID B5-1 2 4.9 19° NNE of site at intersection of School House and Miller Roads ID B10-1 3 9.2 21° NNE of site at intersection of West Areba Avenue and Mill Street, Hershey FP Bto-2 3 10 31° NNE of site at Milton Hershey School, Hershey ID CH 1 0.7 37° NE of site along Route 441 N ID C1-2 1 0.3 50° NE of Reactor Building on top of dike, TMI ID C2-1 2 1.5 44° NE of site at Middletown Junction ID C5-1 2 4.7 43° NE of site on Kennedy Lane ID C8-1 3 7.1 48° NE of site at Schenk's Church on School House Road AQF Control All locations where finfish are collected above Dock St. Dam, Harrisburg ID 01-1 0.2 76° ENE of Reactor Building on top of.dike, TMI ID 01-2 0.5 67° ENE of site off Route 441 along lane between garden center and residence ID 02-2 2 1.6 74° ENE of site along Hillsdale Rd. (S of Zion Rd.) ID 06-1 3 5.2 66° ENE of site off Beagle Road JD 015-1 3 10.8 64° ENE of site along. Route 241, Lawn AP, Al, ID, FP E1-2 1 0.4 97° E of site at TMI Visitor's Center JD E1-4 1 0.2 97° E o_f Reactor Building on top of dike, TMI M E2-2 2 1.1 96° E of site at farm on Pecks Road ID E2-3 2 2.0 97° E of site along Hillsdale Rd. (N of Creek Rd.) ID E5-1 2 4.7 82° E of site at intersection of North Market Street (Route 230) and Zeager Road ID E7-1 3 6.7 88° E of site along Hummelstown Street, Elizabethtown ID F1-1 1 0.5 117° ESE of site near entrance to 500 kV Substation ID F1-2 1 0.2 112° ESE of Reactor Building on top of dike midway within ISWSF, TMI AP,AI F1-3 0.6 112° ESE of site in 500 kV Substation ID F1-4 0.2 122° ESE of Reactor Building on top of dike, TMI ID F2-1 2 1.3 119° ESE of site along Engle Road M F4-1 2 3.2 104° ESE of site at farm on Turnpike Road ID F5-1 2 4.7 109° ESE of site along Amosite Road ID F10-1 3 9.4 112° ESE of site along Donegal Springs Road, Donegal Springs ID F25-1 3 22 106° ESE of site at intersection of Steel Way and Loop Roads, Lancaster ID G1-2 1 0.7 145° SE of site along Route 441 S ID G1-3 1 0.2 130° SE of Reactor Building on top of dike, TMI ID G1-5 1 0.3 143° SE of Reactor Building on top of dike, TMI ID G1-6 1 0.3 139° SE of Reactor Building on top of dike, TMI AJ,AP,M G2-1 2 1.4 126° SE of site at farm on Becker Road ID G2-4 2 1.7 138° SE of site on Becker Road ID G5-1 2 4.8 131° SE of site at intersection of Bainbridge and Risser Roads ID G10-1 3 9.7 128° SE of site at farm along Engles Tollgate Road, Marietta ID G15-1 3 14.4 126° SE of site at Columbia Water Treatment Plant OW G15-2 3 13.3 129° SE of site at Wrightsville Water Treatment Plant OW G15-3 3 15.7 124° SE of site at Lancaster Water Treatment Plant B-2 TABLE B-2: Sample Medium ID FP AP,AI, ID ID ID ID AQF ID SW ID AQS ID ID ID ID EW AQS ID ID ID ID ID ID M ID ID ID ID ID ID ID ID AP,AI, ID ID ID ID ID ID ID ID ID ID Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Station Map Code Number H1-1 1 H1-2 1 H3-1 2 H5-1 2 H8-1 3 H15-1 3 Indicator J1-1 1 J1-2 .1 J1-3 J2-1 2 J3-1 2 J5-1
2 J7-1 3 J15-1 3 K1-1 1 K1-3 1 K1-4 K2-1 2 K3-1 2 K5-1 2 K8-1 3 K15-1 3 K15-3 3 L 1-1 1 L1-2 1 L2-1 2 L5-1 2 L8-1 3 L 15-1 3 M1-1 M1-2 1 M2-1 2 M5-1 2 M9-1 3 N1-1 1 N1-3 N2-1 2 N5-1 2 N8-1 3 N15-2 3 P1-1 Distance !miles) 0.5 1.0 2.2 4.1 7.4 13.2 0.8 0.5 0.3 1.4 2.7 4.9 6.5 12.6 0.2 0.2 0.2 1.2 2.0 4.9 7.5 12.8 14.4 0.1 0.5 1.8 4.1 8.0 11.8 0.1 0.4 1.3 4.3 8.7 0.7 0.1 1.2 4.9 7.7 10.4 0.4 167° 151° 160° 158° 163° 157° 176° 188° 189° 179° 179° 181° 176° 183° 211° 213° 209° 200° 206° 202° 196° 203° 205° 236° 221° 224° 228° 225° 226° 249° 252° 256° 249° 243° 274° 274° 261° 268° 262° 275° 303° B-3 Description SSE of site, TMI SSE of site along Route 441, Red Hill Market SSE of site in Falmouth-Collins Substation SSE of site by Guard Shack at Brunner Island Steam Electric Station SSE of site along Saginaw Road, Starview 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 S of site, TMI S of site downstream of the TMINS liquid discharge outfall in. Susquehanna River S of Reactor Building just S of SOB, TMI S of site in Susquehanna River just upstream of the York Haven Dam S of site at York Haven/Cly S of site along Canal Road, Conewago Heights S of site off of Maple Street, Manchester S of site in Met-Ed York Load Dispatch Station On site at RML-7 Main Station Discharge Building SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River SSW of Reactor Building on top of dike behind Warehouse 2, TMI SSW of site on S Shelley Island SSW of site along Rt. 262, N of Cly SSW of site along Conewago Creek Road, Strinestown SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View SSW of site behind McDonald's and next to child care center, Weiglestown SSW of site at farm along S Salem Church Rd, Dover SW of site on top of dike W of Mech. Draft Cooling Tower, TMI SW of site on Beech Island SW of site along Route 262 SW of site at intersection of Stevens and Wilson Roads SW of site along Rohlers Church Rd., Andersontown SW of site on W side of Route 74, rear of church, Mt. Royal WSW of Reactor Building on SE corner of U-2 Screenhouse fence, TMI WSW of site on E side of Shelley Island, Lot #157 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown WSW of site .along Alpine Road, Maytown W of site on W side of Shelley Island, between lots #13 and #14 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI W of site at Goldsboro Marina W of site off of Old York Road along Robin Hood Drive W of site along Route 382, 1/2 mile north of Lewisberry W of site at intersection of Lisburn Road and Main Street, Lisburn WNW of site on Shelley Island TABLE 8-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Sample Station Map Medium 'Number ID P1-2 ID P2-1 M P4-1 ID P5-1 ID P8-1 ID 01-1 ID 01-2 ID 02-1 ID 05-1 SW,DW,ID 09-1 AP,AI, ID 015-1 ID R1-1 ID R1-2 ID R3-1 ID R5-1 ID R9-1 ID R15-1 ID = Immersion Dose (OSLO) SW = Surface Water Al = Air Iodine AP =Air Particulate 2 2 2 3 1 1 2 2 3 3 1 1 2 2 3 3 FP = Food Products (Green Leafy Vegetation, Fruits, Vegetables)
EW DW M AOF AOS Distance (miles) Azimuth Descrii;ition 0.1 292° WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 1.9 283° WNW of site along Route 262 3.6 295° WNW of site at farm on Valley Road 5.0 284° WNW of site at intersection of Valley Road (Route 262) and Beinhower Road 7.9 292° WNW of site along Evergreen Road, Reesers Summit 0.5 317° NW of site on E side of Shelley Island 0.2 321° NW of Reactor Building on fence W of Warehouse 1, TMI 1.9 310° NW of site along access road along river 5.0 317° NW of site along Lumber Street, Highspire 8.5 310° NW of site at the Steelton Water Company 13.4 309° NW of site behind West Fairview Fire Dept. Social Hall " (abandoned) 0.2 335° NNW of Reactor Building along W fence, TMI 0.7 334° NNW of site on central Henry Island 2.6 341° NNW of site at Crawford Station, Middletown 4.9 339° NNW of,site at intersection of Spring Garden Drive and Route441 8.0 341° NNW of site at intersection of Derry and 66th Streets, Rutherford Heights 11.2 332° NNW of site at intersection of Route 22 and Colonial Road, Colonial Park IDENTIFICATION KEY = Effluent Water = Drinking Water =Milk (Cow) = Finfish = Aquatic Sediment B-4 TABLE 8-3: Sample Medium Surface Water Surface Water Surface Water Drinking Water Drinking Water Drinking Water Drinking Water Effluent Water Effluent Water Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Gamma Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous.
radiological analysis (Three Mile Island water compositor.
Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Tritium Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE"2010 Tritium and carbon-14 analysis by liquid from a continuous radiological analysis (Three Mile Island scintillation water compositor.
Nuclear Station) Env. Inc., T-02 Determination of.tritium in water (direct method) lodine-131 Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices 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 exchanqe Gross Beta Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in 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 cross beta in water (dissolved solids or total residue) Gamma Monthly composite ER-TMl-06 Collection of water samples for 2 gallon
TBE, TBE-2007 Gamma emittinQ radioisotope analysis Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.
Nuclear Station) Env. Inc., GS-01 Determination of g;:imma emitters by ,_ qamma spectroscopy Tritium Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid from a continuous radiological analysis (Three Mile Island scintillation water compositor.
Nuclear Station) Env. Inc., T-02 Determination of tritium in water (direct method) lodine-131 Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices from a continuous radiological analysis (Three Mile Island water compositor.
Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by an ion exchange lodine-131 Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radibiodine in various matrices 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 exchanqe Gross Beta Monthly composite ER-TMl-06 Collection of water samples for 2.gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in 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: Sample Medium Effluent Water Effluent Water Effluent Water Storm Water Storm Water Fish Fish Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Gamma Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.
Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma soectroscopy Tritium Monthly composite ER-TMl-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid from a continuous radiological analysis (Three Mile Island scintillation.
water compositor.
Nuclear Station) Env. Inc., T-02 Determination of tritium in water (direct method) Strontium-Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 composite from monthly samples. Gamma Quarterly composite ER-TMl-06 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy of monthly grab radiological analysis (Three Mile Island samples Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Tritium Quarterly composite ER-TMl-06 Collection of water samples for 1 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid of monthly grab radiological analysis (Three Mile Island scintillation samples Nuclear Station) Env. Inc., T-02 Determination of tritium in water (direct method) Gamma Semi-annual samples ER-TMl-13 Collection offish 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 Strontium-90 Semi-annual samples ER-TMl-13 Collection offish 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 Samoles TABLE B-3: Sample Medium Sediment Air Particulates Air Particulates Air Iodine Milk Milk Milk Vegetation Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Method Gamma Semi-annual grab ER-TMl-03 Collection of sediment"samples for 500 grams (dry) TSE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by aamma spectroscopv Gross Beta One-week ER-TMl-14 Collection of air particulate and air 1 filter TSE, TBE-2008 Gross alpha and/or gross beta activity in composite of iodine samples for radiological analysis (Three (approximately various matrices continuous air Mile Island Nuclear Station) 280 cubic sampling through meters weekly) Env. Inc., AP-02 Determination of gross alpha and/or gross glass fiber filter beta in air particulate filters paper Gamma Quarterly composite TSE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis 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 Gamma One-week ER-TMl-14 Collection of air particulate and air 1 filter TSE, 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 1-131 Bi-weekly grab ER-TMl-01 Collection of milk samples for 2 gallon TSE, 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 Strontium-Quarterly composite ER-TMl-01 Collection of milk samples for 2 gallon TSE, 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 Compositina of samples Gamma Bi-weekly grab ER-TMl-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 Gamma Monthly and annual ER-TMl-04 Collection of vegetatipn 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 aamma spectroscopv l::ti I 00 TABLE Sample Medium Vegetation OSLO* Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2015 Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Method Strontium-Monthly*and annual ER-TMl-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 Optically Quarterly OSLDs ER-TMl-02 Collection of OSLO samples for 2 badges with 3 Landauer Incorporated Stimulated comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Luminescence Al203:C Landauer Station) Dosimetry Incorporated elements.
H I Sorvice l..ave r Ciadil>: Soun:H: E sri. o.Lonne. NAVTEQ. TomTom. l nt ermap , increment P Corp., GEBCO , U SGS , FAO , NPS , NRCAN. GooBa5e , IGN , KadasterNL. Ord n a n ce Su""'Y. Es ri Japan. MET l., Es ri Ch in a (Hong Kong). swisstopo. and Ille GlS User Com munity Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2015 B-9 Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island ,Nuclear Station, 2015 B-10
.....
,,.,,; < -, ,'( ;,; w p !Af111t 3 h&l f-A p _, .,,. ., .. "'>.., Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station , 2015 B-11 Oc l Intentionally left blank APPENDIX C DATA TABLES AND FIGURES -PRIMARY LABORATORY Intentionally left blank Table C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/1,5 MEAN J1-2 4630 +/- 501 5050 +/- 547 876 +/- 165 517 +/- 148 6250 +/- 668 2080 +/- 261 679 +/- 153, 3130 +/- 365 1170 +/- 180 544 +/- 142 < 194 454 +/- 144 2307 +/- 4239 09-1 < 172 < 177 < 196 < 193 < 185 < 187 < 189 < 183 < 184 < 189 < 194 < 193 Table C-1.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION A3-2 PERIOD 01/06/15 -02/03/15 < 0.4 02/10/15 -03/03/15 < 0.7 03/10/15 -03/31/15 < 0.4 04/07/15 -04/28/15 < 0.4 05/05/15 -06/02/15 < 0.3 06/09/15 -06/30/15 < 0. 7 07/07/15 -07/28/15 < 0.8 08/04/15 -09/01/15 < 0.6 09/07/15 -09/29/15 < 0.6 10/06/15 -11/03/15 < 0.4 11/10/15 -12/01/15 < 0.5 12/08/15 -12/29/15 < 0. 7 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1 n I N Table C-1.3 SITE COLLECTION PERIOD J1-2 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31 /15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07 /28/15 -09/01 /15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN 09-1 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 " 07 /28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -.12/29/15 MEAN CONCENTRATIONS OF.GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+ 2 SIGMA Mn-54 <4 <4 < 5 < 9 < 5 < 5 < 5 < 7 <7 < 3 <4 < 5 <2 < 6 < 6 < 5 <4 < 5 < 7 <4 <7 < 3 <4 < 5 Co-58 <4 <4 < 5 < 8 <4 < 6 <7 < 7 < 7 < 3 < 3 < 5 < 3 <7 < 6 < 5 <4 < 5 <4 < 5 <7 < 3 < 6 <4 Fe-59 < 9 < 8 < 11 < 14 < 10 < 12 < 12 < 16 < 15 < 7 < 6 < 10 < 7 < 17 < 15 < 9 < 9 < 12 < 17 < 15 < 14 < 5 < 12 < 11 Co-60 < 5 <4 < 5 < 8 <4 < 6 < 5 < 8 <8 < 4 <4 <4 < 3 <7 < 6 <4 < 3 < 6 < 8 <4 < 7 < 3 < 6 <5 Zn-65 < 10 < 9 < 11 < 15 < 8 < 12 < 15 < 16 < 14 < 7 < 8 < 7 < 6 < 15 < 11 < 10 <7 < 10 < 12 < 15 < 10 < 5 < 11 < 9
< 5 < 5 < 6 < 7 <4 < 6 <6 . < 9 <7 . < 3 <4 < 5 < 3 <7 < 6 <7 <4 . < 5 < 5 < 7 <6 < 3 <6 < 6 Zr-95 < 8 < 7* < 11 < 11 < 8 < 7 < 11 < 15 < 12 < 6 -< 6 < 6 < 6 < 12 < 10 < 10 < 6 < 8 < 11 < 12 < 10 < 5 < 11 < 10 Cs-134 Cs-137
< 5 < 5 <4 <5 *< 5 < 6 <7 <4 < 5 < 6 < 8 < 9 < 3 < 3 < 4 < 3 <7 < 5 <6 <4 < 5 < 5 < 6 <5 < 2 <5 < 5 < 8 < 5 <7 < 5 <7 < 7 < 3. <4 <5 <3 < 8 <6 < 6 <4 <6 < 8 < 5 < 6 <3 < 6 < 5 Ba-140 < 21 < 28 < 28 < 35 < 24 < 34 < 32 < 30 < 33 < 17 < 19 < 29 < 24 < 31 < 33 < 25 < 20 < 29 < 29 < 32 < 27 < 14 < 35 < 33 La-140 < 6 < 8 < 11 < 10 < 8 < 10 <7 < 11 < 13 < 6 < 7 < 5 < 7 < 13 < 11 < 7 < 7 < 10 < 12 < 8 < 10 < 5 < 10 < 10 Table C-11.1 COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31 /15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01 /15 -09/29/15 09/29/15 -11 /03/15 11103/15 -12101115 12/01/15 -12/29/15 MEAN Table C-11.2 COLLECTION PERIOD 12/36114 -62/63/1 g 02/03/15 -03/03115 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01 /15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN Table C-11.3 COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01 /15 -09/29/15 . 09/29/15 -11103/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA G15-2 G15-3 Q9-1 3.1 +/- 1.5 2.7 +/- 1.4 < 1.9 2.8 +/- 1.5 < 2.1 < 2.0 < 2.2 < 2.1 < 2.0 < 2.2 < 2.0 < 2.0 3.2 +/- 1.4 2.7 +/- 1.4. 2.1 +/- 1.3 2.5 +/- 1.5 2.5 +/- 1.4 2.0 +/- 1.4 2.7 +/- 1.4 < 1.9 < 1.9 3.6 +/- 1.6 2.7 +/- 1.6 < 2.1 3.7 +/- 1.5 4.0 +/- 1.6 3.7 +/- 1.6 5.5 +/- 1.9 3.2 +/- 1.7 < 2.0 2.3 +/- 1.3 2.4 +/- 1.3 2.9 +/- 1.2 2.9 +/- 1.5 < 1.9 < 1.8 3.2 +/- 1.8 2:9 +/- 1.1 2.7 +/- 1.6 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA G15-2 G15-3 Q9-1 < 6.5 < 6.5 < 6.4 < 0.8 < 0.7 < 0.7 < 0.4 < 0.4 < 0.3 < 0.5 < 0.6 < 0.6 < 0.4 < 0.3 < 0.3 < 0.7 < 0.7 < 0.7 < 0.9 < 0.7 < 0.8 < 0.5 < 0.5 < 0.6 < 0.7 < 0.6 < 0.7 < 0.4 < 0.4 < 0.4 < 0.8 < 0.5 < 0.5 < 0.6 < 0.6 < 0.6 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA G15-2 G15-3 Q9-1 < 168 288 +/- 122 < 169 < 178 < 178 < 175 < 196 < 198 < 198 < 192. < 195 < 191 < 185 . 621 +/- 152 "< 184 < 189 <*183 < 190 < 186 < 186 < 188 < 180 < 191 < 182 < t84 <:184 < 184 < 191 < 191 < 187 < 195 < 194 < 194 < 192 < 1.93 < 195 455 +/- 471 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-3
(') I .;:.. Table C-11.4 SITE COLLECTION PERIOD G15-2 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN G15-3 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31 /15 03/31 /15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA Mn-54 < 6 < 7 < 5 < 5 < 5 < 8 < 8 < 8 < 9 < 3 < 6 < 4 < 6 < 5 <4 < 7 <4 < 6 < 6 < 6 < 6 < 3 < 9 < 5 Co-58 <7 < 8 <5. < 6 < 5 < 8 < 6 <7 < 7 < 3 < 7 < 5 < 5 < 5 < 3 < 7 < 5 < 6 <_7 < 7 < 6 < 3 <7 < 5 Fe-59 < 12 < 15 < 10 < 11 < 11 < 14 < 15 < 16 < 17 < 7 < 17 < 11 < 12 < 11 < 8 < 14 < 10-< 14 < 13 < 14 < 11 < 6 < 17 < 9 Co-60 < 6 <4 <4 < 6 < 5 < 6 < 8 < 8 < 9 < 3 < 5 < 5 < 5 < 6 < 5 <4 < 4* "<6 < 8 < 5 .<7 < 3 < 8 < 5 Zn-65 < 13 < 13 < 9 < 9 < 10 < 15 < 14 < 15 < 16 < 6 < 11 < 9 < 13 < 13 < 9 < 13 < 8 < 14 < 14 < 17 < 13 <6 < 13 < 9 Nb-95 < 7 < 6 < 5 < 6 < 6 < 7 < 8 <6 < 7 < 3 < 7 < 5 < 6 < 5 < 4 < 6 <5 < 6 < 8 < 9 < 7 < 3. <8 < 5 Zr-95 < 12 < 12 < 10 < 10 <8 < 13 < 15 < 10 < 14 < 6-_ < 12 < 7 <9 < 9 <8 < 12 <6 < 11 < 13 < 14 < 10 <5 < 13 <9 Cs-134 Cs-137 Ba-140 La-140 <6 <8 <35 <8 < 6 < 5 <
31 < 12 < 4 < 6 <
26 < 9 < 5 < 6 <
30 < 7 < 5 < 5 <
29 < 9 < 7 < 6 <
42 < 12 < 6 < 7 <
32 < 12 < 7 <7 < 3 <7 <4 < 5 < 5 <4 < 6 <4 < 6 <6 < 6 < 6 < 3 <7 <4 <7 < 6 < 3 <7 < 5 < 6 < 6 <4 < 6 <4 < 7 < 7 < 8 < 6 < 3 <7 < 5 < 34 < 25 < 17 < 31 < 21 < 28 < 26 < 24 < 31 < 20 < 41 < 32 < 36 < 23 < 15 < 42 < 27 < 10 < 8 < 5 < 11 < 7 < 9 < 10 < 8 < 9 <6 < 11 < 15 < 11 < 6 <4 < 12 < 10 Table C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCilLITER
+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q9-1 12/30/14 -
02/03/15 < 7 < 7 <
14 < 4 < 15 < 7 < 12 <6 < 8 < 34 < 11 02/03/15 -03/03/15 < 5 < 7 < 12 < 4 < 10 < 6 < 12 <5 < 7 < 33 < 10 03/03/15 -03/31/15 < 5 <4 < 12 < 5 < 9 <4 < 8 <4 < 5 < 26 < 10 03/31/15 -04/28/15 < 6 <5 < 10 < 7 < 12 < 8 < 12 < 6 < 6 <
26 < 8 04/28/15 -06/02/15 < 3 < 3 < 6 <4 <7 < 3 <6 < 3 < 3 <
18 < 6 06/02/15 -06/30/15 < 6 < 6 <
15 < 6 < 14 < 6 < 11 < 6 < 7 <
36 < 13 06/30/15 -07 /28/15 < 7 < 6 <
18 < 8 < 15 <7 < 12 < 6 < 6 <
35 < 10 07/28/15 -09/01/15 < 6 < 5 <
17 < 7 < 18 <7 < 11 < 6 < 6 <
31 < 10 09/01/15 -09/29/15 < 10 < 8 < 19 < 5 < 16 < 9 < 13 < 7 < 7 <
30 < 8 09/29/15 -11/03/15 < 3 < 3 < 5 < 2 < 6 < 3
<5 < 3 < 3 < 15 < 5 11/03/15 -12/01 /15 < 8 < 8 < 20 < 7 < 17 < 8 < 15 < 7 < 8 <
39 < 13 12/01/15 -12/29/15 < 5 < 5 <
12 < 5 < 11 < 6 < 10 < 5 < 6 <
32 < 8 n MEAN I lll Table C-111.1 SITE COLLECTION PERIOD K1-1 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION K1-1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA GR-8 1-131 H-3 SR-89 SR-90 2.5 +/- 1.4 < 0.3 69900 +/- 7000 < 4.0 < 0.7 4.3 +/- 1.7 < 0.8 38800 +/- 3900 3.2 +/- 1.6 < 0.5 9350 +/- 983 2.6 +/- 1.5 < 0.9 11600 +/- 1210 4.7 +/- 1.7 < 0.3 106000 +/- 7590 4.3 +/- 1.7 < 0.7 29700 +/- 3010 2.1 +/- 1.4 < 0.8 6860 +/- 739 < 3.1 < 0.9 6.7 +/- 2.1 < 0.8 45800 +/- 4620 6.7 +/- 2.0 < 0.6 13900 +/- 1440 8.3 +/- 2.3 < 0.3 5720 +/- 625 3.0 +/- 1.3 < 0.5 < 198 6.2 +/- 1.8 < 0.9 5440 +/- 600 4.6 +/- 4.0 36685 +/- 65243 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-6 Table C-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD K1-1 12/30/14 -02/03/15 <6 <6 < 14 <6 < 14 <7 < 11 <6 <7 < 32 < 9 02/03/15 -03/03/15 < 5 < 5 < 9 < 5 <
10 <7 < 13 <5 < 6 < 34 < 12 03/03/15 -03/31/15 < 5 <4 < 9 <4 <9 . < 5 <8 <3 < 5 < 25 < 9 03/31/15 -04/28/15 <6 < 8 < 15 < 11 < 19 < 9 < 14 <7 < 9 < 41 < 15 04/28/15 -06/02/15 <5 <6 < 14 <6 < 10 <6 <9 <5 < 5 < 27 < 9 06/02/15 -06/30/15 <5 <4 < 11 < 5 <9 <6 <9 <4 < 5 < 31 <6 06/30/15 -07/28/15 <6 <7 < 18 <7 < 14 <6 < 13 <6 < 8 < 32 < 11 07/28/15 -09/01/15 <6 <6 < 12 < 5 < 10 <6 <9 <5 < 6 < 28 <6 09/01/15 -09/29/15 <7 <6 < 10 <7 < 15 <6 < 13 <6 < 7 < 29 < 13 09/29/15 -11/03/15 <9 <7 < 9 <7 < 13 <6 < 11 < 5 < 7 <
33 < 13 11/03/15 -12/01/15 <4 <6 < 9 <5 < 13 <5 <8 < 5 < 6 < 34 < 9 12/01/15 -12/29/15 <7 <7 < 14 <7 < 12 <7 < 13 < 6 <6 < 39 < 12 MEAN (") I ....;i Table C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH) SAMPLES COLLECTED IN THE VICINITY*OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Sr-90 PERIOD INDP PREDATOR 06/10/15 < 3.2 09/23/15 < 4.2 MEAN INDB BOTTOM FEEDER 06/10/15 < 3.3 09/23/15 < 3.9 MEAN BKGP PREDATOR 06/11/15 < 3.9 10/06/15 < 2.4 MEAN BKGB BOTTOM FEEDER 06/11/15 < 2.1 10/06/15 < 3.5 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, 2015 RESULTS IN UNITS OF PCl/KG WET +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58
Fe-59 . Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDP PREDATOR 06/11/15 2493 +/- 818 < 45 < 44 < 114 < 42 < .1.03 < 44 < 48 10/06/15 3846 +/- 787 < 44 < 42 < 96 < 38 < 87 < 42 < 49 MEAN 3170 +/- 1913 INDB BOTTOM FEEDER 06/11/15 4283 +/- 1253 < 105 < 114 < 232 < 82 < 237 < 88 < 97 10/06/15 1439 +/- 1004 < 74 < 85 < 168 < 66 < 127 < 66 < 70 MEAN 2861 +/- 4022 BKGP PREDATOR 06/11/15 3785 +/- 756 < 59 < 67 < 141 < 60 < 132 < 54 < 69 10/06/15 2869 +/- 1097 < 74 < 58 < 155 < 58 < 178 < 73 < 72 MEAN 3327 +/- 1295 BKGB BOTTOM FEEDER 06/11/15 2863 +/- 1027 < 62 < 76 < 162 < 74 < 130 < 77 < 68 10/06/15 3026 +/- 326 < 27 < 60 < 209 < 20 < 59 < 22 < 22 2945 +/- 231 C-9 Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG DRY+/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD A1-3 06/12/15 13690 +/- 1842 < 97 < 85 < 93 < 83 < 106 10/29/15 11580 +/- 1417 < 75 < 53 < 73 < 69 < 86 *MEAN 12635 +/- 2984 EDCB 10/29/15 14700 +/- 1708 < 84 < 70 < 88 < 76 211 +/- 84 MEAN 14700 +/- 0 211 +/- 0 J2-1 06/12/15 13980 +/- 2067 < 113 < 113 < 103 < 98 < 137 10/29/15 14640 +/- 1705 < 81 < 71 < 81 < 68 < 93 MEAN 14310 +/- 933 K1-3 06/12/15 6131 +/- 765 < 41 < 52 < 42 < 38 < 46 10/29/15 5753 +/- 1033 < 68 < 67 < 77 < 69 < 86 MEAN 5942 +/- 535 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-10 Table C-Vl.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION PERIOD 01/01/15 -01/08/15 01/08/15 -01/15/15 01/15/15 -01/22115 01/22115 -01/29/15 01/29/15 -02/05/15 02/05/15 -02/12/15 02/12115 -02119/15 02119/15 -02/26/15 02/26/15 -03/05/15 03/05/15 -03/12115 03/12/15 -03/18/15 03/18/15 -03/26/15 03/26/15 -04/02/15 04/02/15 -04/09/15 04/09/15 -04/16/15 04/16/15 -04/23/15 04/23/15 -04/30/15 04/30/15 -05/07 /15 05/07/15 -05/14/15 05/14/15 -05121/15 05/21/15 -05/28/15 05/28/15 -06/04/15 06/04/15 -06/10/15 06/10/15 -06/18/15 06/18/15 -06/25/15 06/25/15 -07/02115 07 /02115 -07 /09/15 07 /09/15 -07 /16/15 07/16/15 -07/23/15 07/23/15 -07/30/15 07 /30/15 -08/06/15 08/06/15 -08/13/15 08/13/15 -08/19/15 08/19/15 -08/27 /15 08/27/15 -09/03/15 09/03/15 -09/10/15 09/10/15 -09/16/15 09/16/15 -09/24/15 09/24/15 -10/01/15 10/01/15 -10/08/15 10/08/15 -10/15/15 10/15/15 -10/22/15 10/22115 -10/29/15 10/29/15 -11/05/15 11/05/15 -11/12/15 11/12/15 -11/19/15 11/19/15 -11/25/15 11/25/15 -12103/15 12/03/15 -12110/15 12110/15 -12/17/15 12/17/15 -12123/15 12/23/15 -12/31/15 MEAN GROUP I E1-2 F1-3 17 +/- 5 20 +/- 5 23 +/- 5 19 +/- 5 21 +/- 6 17 +/- 5 13 +/- 5 13 +/- 5 17 +/- 5 23 +/- 5 25 +/- 5 20 +/- 5 16 +/- 5 17 +/- 6 17 +/- 5 15 +/- 5 16 +/- 5 14 +/- 5 8 +/- 5 11 +/- 4 12 +/- 5 16 +/- 5 13 +/- 5 18 +/- 5 <7 11 +/- 5 12 +/- 4 15 +/- 5 9 +/- 5 19 +/- 5 13 +/- 5 16 +/- 5 7 +/- 5 9 +/- 5 10 +/- 4 24 +/- 6 15 +/- 4 31 +/- 5 27 +/- 6 16 +/- 6 21 +/- 4 15 +/- 5 14 +/- 5 17 +/- 5 17 +/- 5 14 +/- 5 22 +/- 5 14 +/- 5 14 +/- 5 12 +/- 5 15 +/- 4 29 +/- 9 31 +/- 6 23 +/- 6 8 +/- 4 17 +/- 11 17 +/- 5 11 +/- 5 21 +/- 5 21 +/- 5 26 +/- 5 18 +/- 5 17 +/- 5 11 +/- 5 13 +/- 4 10 +/- 5 12 +/- 5 16 +/- 5 12 +/- 5 11 +/- 4 14 +/- 5 15 +/- 5 13 +/- 5 18 +/- 5 8 +/-_5 <7 13 +/- 4 11 +/- 5 8 +/- 5 18 +/- 5 16 +/- 5 15 +/- 5 16 +/- 5 12 +/- 5 9 +/- 4 16 +/- 6 16 +/- 4 27 +/- 5 25 +/- 6 18 +/- 6 17 +/- 4 16 +/- 5 11 +/- 4 16 +/- 5 16 +/- 5 13 +/- 5 20 +/- 5 14 +/- 5 16 +/- 5 10 +/- 5 12 +/- 4 27 +/- 6 26 +/- 6 15 +/- 6 6 +/- 4 16 +/- 10 A3-1 23 +/- 6 15 +/- 5 19 +/- 5 15 +/- 5 12 +/- 5 16 +/- 5 18 +/- 5 23 +/- 5 24 +/- 6 15 +/- 5 13 +/- 5 18 +/- 5 12 +/- 5 13 +/- 5 12 +/- 4 8 +/- 5 9 +/- 4 15 +/- 5 ' 14 +/- 5 10 +/- 4 15 +/- 5 10_ +/- 5 13 +/- 5 9 +/- 4 12 +/- 5 9 +/- 5 19 +/- 5 16 +/- 5 14 +/- 4 15 +/- 5 16 +/- 5 14 +/- 4 23 +/- 6 15 +/- 4 32 +/- 5 28 +/- 6 15 +/- 6 23 +/- 4 19 +/- 5 11 +/- 4 19 +/- 5 18 +/- 5 18 +/- 5 18 +/- 5 18 +/- 5 19 +/- 5 18 +/- 5 12 +/- 4 39 +/- 6 28 +/- 6 23 +/- 6 10 +/- 4 17 +/- 12 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION GROUP II G2-1 H3-1 18 +/- 5 20 +/- 6 16 +/- 5 17 +/- 5 22 +/- 6 19 +/- 5 16 +/- 5 14 +/- 5 18 +/- 5 22 +/- 5 25 +/- 5 25 +/- 6 18 +/- 5 12 +/- 5 15 +/- 5 12 +/- 5 14 +/- 5 13 +/- 5 8 +/- 5 13 +/- 5 12 +/- 5 17 +/- 5 14 +/- 5 18 +/- 5 9 +/- 5 14 +/- 5 12 +/- 4 10 +/- 4 7 +/- 4 15 +/- 5 16 +/- 5 12 +/- 4 15 +/- 6 16 +/- 5 11 +/- 4 23 +/- 6 18 +/- 4 36 +/- 6 28 +/- 6 18 +/- 6 22 +/- 4 17 +/- 5 11 +/- 4 19 +/- 5 18 +/- 5 14 +/- 5 22 +/- 5 10 +/- 4 18 +/- 5 13 +/- 5 17 +/- 4 41 +/- 6 25 +/- 5 20 +/- 6 9 +/- 4 17 +/- 13 -14 +/- 5 13 +/- 5 21 +/- 6 24 +/- 5 23 +/- 5 23 +/- 6 18 +/- 5 16 +/- 6 14 +/- 4 14 +/- 5 13 +/- 5 13 +/- 5 < 7 12 +/- 4 12 +/- 4 15 +/- 5 10 +/- 6 13 +/- 7 8 +/- 5 9 +/- 5 10 +/- 4 (1) < 8 21 +/- 5 15 +/- 5 18 +/- 5 11 +/- 5 17 +/- 5 17 +/- 5 28 +/- 6 -16 +/- 4 32 +/-.6 28 +/- 6 14 +/- 6 20 +/- 4 16 +/- 5 12 +/- 5 15 +/- 5 17 +/- 5 12 +/- 5 21 +/- 5 14 +/- 5 17 +/- 5 16 +/- 5 14 +/- 4 39 +/- 6 29 +/- 6 21 +/- 6 8 +/- 4 17 +/- 13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-11 M2-1 20 +/- 6 14 +/- 5 22 +/- 6 16 +/- 5 11 +/- 5 21 +/- 6 24 +/- 5 27 +/- 6 20 +/- 5 19 +/- 5 15 +/- 6 18 +/- 5 12 +/- 5 14 +/- 5 12 +/- 5 10 +/- 5 12 +/- 4 12 +/- 5 14 +/- 5 12 +/- 5 21 +/- 5 10 +/- 5 15 +/- 6 14 +/- 4 12 +/- 5 13 +/- 5 17 +/- 5 16 +/- 5 17 +/- 5 16 +/- 5 14 +/- 5 16 +/- 5 21 +/- 6 18 +/- 4 34 +/- 6 29 +/- 6 25 +/- 6 22 +/- 4 20 +/- 5 10 +/- 4 14 +/- 5 14 +/- 5 14 +/- 5 17 +/- 5 18 +/- 5 19 +/- 5 14 +/- 5 15 +/- 4 41 +/- 6 26 +/- 6 22 +/- 6 6 +/- 4 17 +/- 13 GROUP Ill Q15-1 23 +/- 6 21 +/- 5 23 +/- 6 15 +/- 5 14 +/- 5 (1) 25 +/- 7 28 +/- 6 22 +/- 5 18 +/- 5 14 +/- 5 14 +/- 4 15 +/- 5 14 +/- 5 13 +/- 5 10 +/- 5 11 +/- 4 16 +/- 5 17 +/- 5 11 +/- 5 19 +/- 5 10 +/- 5 13 +/- 6 13 +/- 4 11 +/- 5 9 +/- 5 22 +/- 5 16 +/- 5 17 +/- 5 12 +/- 5 9 +/- 5 14 +/- 5 25 +/- 6 16 +/- 4 32 +/- 5 30 +/- 6 21 +/- 6 22 +/- 4 14 +/- 5 11 +/- 4 23 +/- 5 20 +/- 5 13 +/- 5 23 +/- 5 -13 +/- 5 19 +/- 5 19 +/- 5 13 +/- 4 36 +/- 6 34 +/- 6 18 +/- 6 7 +/- 4 18 +/- 13 Table C-Vl.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/Cl.J METER+/- 2 SIGMA GROUP I -CLOSEST TO THE SITE BOUNDARY GROUP II -INTERMEDIATE OFFSITE GROUP Ill -CONTROL LOCATIONS COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- PERIOD 2SD PERIOD 2SD PERIOD 2SD 01/01/15 -01/29/15 13 23 18 +/- 6 01/01/15 -01/29/15 14 23 18 +/- 6 01/01/15 -01/29/15 15 23 20 +/- 8 01/29/15 -02/26/15 11 26 20 +/- 11 01/29/15 -02/26/15 11 27 19 +/- 10 01/29/15 -02/26/15 14 28 23 +/- 15 02/26/15 -04/02/15 10 20 15 +/- 6 02i26/15 -04/02/15 12 25 17 +/- 8 02/26/15 --04/02/15 14 22 17 +/- 7 04/02/15 -04/30/15 8 16 12 +/- 5 04/02/15 -04/30/15 8 14 12 +/- 4 04/02/15 -04/30/15 10 14 12 +/- 3 04/30/15 -05/28/15 12 18 15 +/- 5 04/30/15 -05/28/15 10 21 14 +/- 6 04/30/15 -05/28/15 11 19 16 +/- 7 05/28/15 -07/02/15 8 15 11 +/- 5 05/28/15 -07/02/15 7 15 11 +/- 5 05/28/15 -07/02/15 9 13 11 +/- 4 07 /02/15 -07 /30/15 7 19 15 +/- 7 07/02/1.5
-07/30/15 11 21 16 +/- 5 07/02/15 -07/30/15 12 22 17 +/- 9 07 /30/15 -09/03/15 9 31 17 +/- 16 07130/15 -09/03/15 ' 11 36 21 +/- 15 07/30/15 -09/03/15 9 32 19 £ 18 09/03/15 -10/01/15 15 27 20 +/- 9 09/03/15 -10/01/15 14 29 21 +/- 10 09/03/15 -10/01/15 14 30 22 +/- 13 10/01/15 -10/29/15 11 17 15 +/- 4 10/01/15 -10/29/15 10 19 15 +/- 6 10/01/15 -10/29/15 11 23 17 +/- 11 ("') 10/29/15 -12/03/15 *10 22 15 +/- 7 10/29/15 -12/03/15 10 22 16 +/- 6 10/29/15 -12/03/15 13 23 17 +/- 8 I 12/03/15 -12/31/15 6 31 21 +/- 19 12/03/15 -12/31/15 6 41 24 +/- 24 12/03/15 -12/31/15 7 36 24 +/- 28 ...... N 01/01/15 -12131/15 6 31 16 +/- 11 01/01/15 -12/31/15 6 41 17 +/- 12 01/01/15 -12/31/15 7 36 18 +/- 13 Table C-Vl.3 SITE COLLECTION PERIOD A3-1 01/01/15 -04/02/15 04/02115 -07/02115 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN E1-2 01/01/15 -04/02115 04/02/15 -07 /02/15 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN F1-3 01/01/15 -04/02115 04/02/15 -07 /02/15 07/02/15 -10/01/15 10/01/15 -12/31/15 MEAN G2-1 01/01/15 -04/02,115 04/02/15 -07 /02/15 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN H3-1' 01/01/15 -04/02/15 04/02/15 -07 /02/15 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN* M2-1 01/01/15 -04/02/15 04/02/15 ° 07 /02115 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN 015-1 01/01/15 -04/02115 04/02115 -07 /02115 07/02115 -10/01/15 10/01/15 -12/31/15 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA Be-7 Mn-54 Co-58 81 +/-'46 <6 76+/-28 <3 53 +/- 39 < 3 41 +/- 20 < 2 63 +/- 38 68 +/- 37 < 4 62+/-32 <3 80 +/- 28 < 3 42 +/- 21 < 3 63 +/- 32 < 69 < 6 67+/-32 <5 68 +/- 36 < 3 63 +/- 21 < 2 66 +/- 5 64+/-38 <3 74 +/- 28 < 2 63 +/- 37 < 3 49+/-28 <4 62 +/- 20 < 94 < 5 112+/-52 <5 54+/-26 <2 39 +/- 24 < 2 68 +/- 77 85 +/- 37 < 4 65 +/- 30 < 4 103 +/- 28 < 2 44+/-22 <2 74 +/- 51 78 +/- 34 < 3 53+/-28 <3 75 +/- 30 < 3 42 +/- 28 < 4 62 +/- 35 <7 <4 <3 <2 < 5 <4
<3 <4 < 9 <4 <4 < 3 < 5 <3 <4 < 3 <9 <9 <3 <3 <4 <4 <4 <3 <5 <2 <4 <4 Co-60 < 3 <_4 .< 2 < .. 3 <4 < 3 <2 <2 <7 <4 <4
<4 < 3 <4 < 3 <6 <5
<2 < 2 <3 <2 < 3 <2
<2 <4 < 3 <4 < 3 Nb-95 <6 <4 <4 <3 <6 <5 <4 < 3 <7 <5 <5 <4 <4 <4 < 5 < 5 <9 <7 <3 <3 <4 <6 < 4. < 3. <5 < 1 <4 <4 Zr-95 <9 <6 < 6 <4 <8 <6 < 5 <6 < 13 < 10 < 9 < 5 < 9 <6 < 7 < 8 < 14 < 13 <5 <7 < 10 < 9 < 8 < 5 < 9 <6 < 8 < 9 Cs-134 Cs-137 < 5 < 3 < 3 <2 <3 <3 < 3 <-3 <4 <5 <4
<2 <_4 < 3 < 3 <4 <5 < 5 < 3 <2 <2 <4 <2 <3 <4 <4 <3 <4 <4 <3 <3 <2 <3 <2 <2 <3 <4 <5
<3 < 3 <3 < 3 <2 <3 <6 <6 <2 < 3 <2 <3 <2 <3 <4 <3 <3
<3 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-13 Table C-Vll.1 COLLECTION PERIOD 01/01/15 -01/08/15 01/08/15 -01/15/15 01 /15/15 -01 /22/15 01/22/15 -01/29/15 01/29/15 -02/05/15 02/05/15 -02/12/15 02/12/15 -02/19/15 02/19/15 -02/26/15 02/26/15 -03/05/15 03/05/15 -03/12/15 03/12/15 -03/18/15 03/18/15 -03/26/15 03/26/15 -04/02/15 04/02/15 -04/09/15 04/09/15 -04/16/15 04/16/15 -.04/23/15 04/23/15 -04/30/15 04/30/15 -05/07 /15 05/07 /15 -05/14/15 05/14/15 -05/21/15 05/21/15 -05/28/15 05/28/15 -06/04/15 06/04/15 -06/10/15 06/10/15 -06118/15 06/18/15 -06/25/15 06/25/15 -07/02/15 07 /02/15 -07 /09/15 07/09/15 -07/16/15 07116/15 -07/23/15 07/23/15 -07/30/15 07 /30/15 -08/06/15 08/06/15 -08/13/15 08/13/15 -08/19/15 08/19/15 -08/27/15 08/27 /15 -09/03/15 09/03/15 -09/10/15 09/10/15 -09/16/15 09/16/15 -09/24115 09/24/15 -10/01/15 10/01/15 -10/08/15 10/08/15 -10/15/15 10/15/15 -10/22/15 10/22/15 -10/29/15 10/29/15 -11 /05/15 11/05/15 -11/12/15 11/12/15 -11/19/15 11/19/15 -11/25/15 11/25/15 -12/03/15 12/03/15 -12/1 0/15 12/10/15 -12117/15 12117/15 -12/23/15 12/23/15 -12/31/15 MEAN CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I E1-2 F1-3 < 29 < 29 < 43 < 42 < 47 < 18 < 26 < 57 < 63 < 61 < 64 < 52 < 62 < 26 < 69 < 44 < 46 < 64 < 29 < 64 < 67 < 45 < 55 < 43 < 58 < 41 < 59 < 59 < 47 < 48 < 43 < 35 < 54 < 42 < 41 < 49 < 51 < 43 < 43 < 43 < 41 < 27 < 38 < 68 < 47 < 17 < 55 < 33 < 37 < 62 < 69 < 69 < 54 < 61 < 61 < 29 < 45 < 63 < 52 < 61 < 26 < 68 < 43 < 45 < 24 < 10 < 63 < 66 < 44 < 53 < 42 < 57 < 41 < 59 < 59 < 47 < 48 < 43 < 35 < 55 < 42 \. < 41 < 49 < 52 < 43 < 44 < 43 < 41 < 65 < 38 < 68 < 47 < 17 < 55 < 33 < 37 < 62 < 69 < 69 < 54 < 38 < 62 < 29 < 45 A3-1 < 29 < 26 < 43 < 52 < 67 < 69 < 60 < 48 < 23 < 54 < 60 < 38 < 67 < 26 < 64 < 55 < 42 < 43 < 66 < 62 < 38 < 58 < 33 < 13 < 45 < 60 < 15 < 40 < 39 < 43 < 64 < 55 < 51 < 28 < 22 < *57 < 68 < 27 < 58 < 55 < 15 < 43 < 42 < 29 < 61 < 60 < 51 < 47 < 54 < 55 < 36 < 24 GROUP II G2-1 H3-1 < 30 < 30 < 43 < 48 < 48 < 47 < 60 < 59 < 23 < 63 < 66 < 54 < 64 < 27 < 70 < 45 < 47 < 68 < 30 < 64 < 69 < 46 < 22 < 44 < 60 < 43 < 66 < 58 < 46 < 48 < 42 < 35 < 56 < 41 < 47 <*48 < 51 < 44 < 43 < 42 < 16 < 28 < 37 < 67 < 46 < 17 < 23 < 33 < 36 < 24 < 68 < 68 < 53 < 37 < 23 < 11 < 44 < 25 < 53 < 49 < 27 < 70 < 61 < 46 < 64 < 30 < 64 < 68 < 45 < 55 < 43 < 56 < 62 < 68 < 59 < 36 < 51 < 36 < 55 < 41 < 45 < 49 < 52 < 42 < 44 < 43 < 42 < 66 < 67 < 69 < 47 < 17 < 55 < 34 < 37 < 63 < 62 < 54 < 54 < 38 < 62 < 29 < 49 (1) M2-1 < 30 < 48 < 44 < 53 < 69 < 70 < 61 < 20 < 23 < 23 < 24 < 39 < 63 < 26 < 65 < 56 <43 < 54 < 67 < 63 < 38 < 66 < 33 < 35 < 45 < 60 < 35 < 40 < 40 < 44 < 65 < 55 < 50 < 67 < 53 < 57 < 68 < 65 < 59 < 55 < 15 < 43 < 43 < 29 < 61 < 60 < 52 < 47 < 54 < 55 < 37 < 47 I GROUP Ill Q15-1 < 29 < 47 < 42 < 53 < 68 < 42 < 48 < 23 < 54* < 60 < 38 < 67 < 26 < 64 < 55 < 42 < 43 < 66 < 62 < 38 < 58 < 33 < 35 < 45 < 61 < 36 < 40 < 40 < 44 < 65 55 < 50 < 68 < 53 < 58 < 68 < 66 < 59 < 56 < 15 < 44 < 46 < 29 < 61 < 61 < 52 < 47 < 55 < 56 < 37 < 48 (1) (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-14 Table C-Vlll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA CONTROL FARM INDICATOR FARM COLLECTION TM-M-K15-3 I TM-M-E2-2 TM-M-F4-1 TM-M-G2-1 TM-M-P4-1 PERIOD 01/07/15 < 0.6 < 0.4 < 0.5 < 0.5 < 0.5 02/11/15 < 0.4 < 0.5 < 0.5 < 0.8 < 0.5 03/11/15 < 0.4 < 0.6 < 0.4 < 0.5 < 0.5 03/25/15 < 0.3 < 0.4 < 0.2 < 0.4 < 0.3 04/08/15 < 0.6 < 0.6 < 0.7 < 0.6 < 0.6 04/22/15 < 0.3 < 0.5 < 0.7 < 0.4 < 0.4 05/06/15 < 0.5 < 0.9 < 0.5 < 0.8 < 0.9 05/20/15 < 0.6 < 0.7 < 0.7 < 0.7 < 0.6 06/03/15 < 0.7 < 0.9 < 0.6 < 0.7 < 0.5 06/17/15 < 0.4 < 0.7 < 0.6 < 0.6 < 0.7 07/01/15 < 0.5 < 0.7 < 0.5 < 0.7 < 0.6 07/15/15 < 0.9 < 0.8 < 0.8 < 0.8 < 0.7 07/29/15 < 0.7 < 0.8 < 0.9 < 0.9 < 0.9 08/12/15 < 0.6 < 0.6 < 0.6 < 0.5 < 0.5 08/26/15 < 0.5 < 0.7 < 0.5 < 0.7 . < 0.7 09/09/15 < 0.3 < 0.5 < 0.4 < 0.6 < 0.6 09/23/15 < 0.6 < 0.5 < 0.5 < 0.5 < 0.4 10/07/15 < 0.4 < 0.5 < 0.6 < 0.5 < 0.7 10/21/15 < 0.6 < 0.4 < 0.6 < 0.5 : < 0.4. 11/04/15 < 0.4 < 0.6 < 0.6 < 0.7 < 0.6 11/18/15 < 0.8 < 0.8 < 0.9 < 0.6 < 0.9 12/02/15 < 0.9 < 1.0 < 0.6 < 0.8 < 1.0 MEAN C-15 Table C-Vlll.2 COLLECTION PERIOD 01/07/15 -03/25/15 04/08/15 -06/17/15 07/01/15 -09/23/15 10/07/15 -12/02/15 MEAN (") I -O"I CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+ 2 SIGMA CONTROL FARM INDICATOR FARM K15-3 P4-1 E2-2 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 < 4.0 < 0.4 < 2.1 < 0.4 < 2.0 < 0.4 < 3.6 < 3.9 < 0.6 < 3.5 < 0.7 < 4.3 < 0.7 < 4.2 < 3.5 < 0.3 < 3.6 < 0.7 < 3.6 < 0.3 < 3.5 < 3.9 < 0.7 < 4.2 < 0.4 < 2.6 < 0.5 < 3.0 F4-1 G2-1 SR-90 SR-89 SR-90 < 0.4 < 4.6 < 0.4 < 0.6 < 4.9 < 0.7 < 0.4 < 3.7 < 0.4 < 0.7 < 3.9 < 0.6 Table C-Vlll.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION K-40
Cs-137 Ba-140
La-140 PERIOD E2-2 *01/07/15 1343 +/- 148 < 6 < 8 < 34 <7 02/11/15 1355 +/- 187 < 7 < 6 < 48 < 15 03/11/15 1362 +/- 191 < 8 < 9 < 49* < 14 03/25/15 1276 +/- 134 < 5 < 6 < 55 < 13 04/08/15 1172 +/- 155 < 6 < 7 < 42 < 13 04/22/15 1309 +/- 98 <4 <4 < 41 < 13 05/06/15 1197 +/- 213 < 7 < 11 < 38 < 14 05/20/15 1045 +/- 172 < 6 < 7 < 40' < 10 06/03/15 1409 +/- 185 <7 <7 < 35 < 7 06/17/15 1505 +/- 174 < 8 < 7 < 42 < 12 07/01/15 1200 +/- 206 < 10 < 10 < 48 < 13 07/15/15 1343 +/- 173 < 5 < 6 < 43 < 10 07/29/15 1447 +/- 161 <7 <7 < 35 < 12 08/12/15 1369 +/- 278 <7 < 11 < 58 < 14 08/26/15 1310 +/- 197 < 8 < 12 < 40 < 13 09/09/15 1408 +/- 165 < 7 < 9 < 37 < 9 09/23/15 1422 +/- 194 < 7 < 7 < 27 < 12 10/07/15 1296 +/- 184 < 9 < 12 < 35 < 10 10/21/15 1340 +/- 214 <8 < 12 < 29 < 9 11/04/15 1063 +/- 216 < 9 < 10 < 47 < 15 11/18/15 1321 +/- 161 < 7 <6 < 27 < 7 12/02/15 -1260 +/- 140 < 7 < 6 < 36 < 13 MEAN 1307 +/- 231 F4-1 01/07/15 1396 +/- 160 <7 <7 < 29 < 12 02/11/15 1522 +/- 175 <6 < 7 < 45 < 15 03/11/15 1360 +/- 187 < 8 < 8 < 34 < 11 03/25/15 1431 +/- 101 <4 < 5 < 42 < 12 04/08/15 1657 +/- 175 < 6 < 7 < 42 < 9 04/22/15 1367 +/- 89 < 3 <4 < 37 < 10 05/06/15 1395 +/- 198 < 5 < 7 < 35 < 11 05/20/15 1390 +/- 98 < 6 < 5 < 28 < 8 06/03/15 1464 +/- 162 < 8 < 8 < 39 < 11 06/17/15 1433 +/- 177 < 5 < 9 < 32. < 11 07/01/15 1404 +/- 217 < 7 < 7 < 46 < 13 07/15/15 1266 +/- 135 < 5 < 6 < 36 <7 07/29/15 '1330 +/- 149 <6 < 7 < 30 < 9 08/12/15 1479 +/- 243 < 10 < 8 < 46 < 12 08/26/15 1242 +/- 199 < 7 < 10 < 46 <7 09/09/15 1381 +/- 156 < 6 <7 < 24 < 8 09/23/15 1346 +/- 199 < 10 < 11 < 37 < 14 10/07/15 1487 +/- 184 <*7 < 7 < 26 < 9 10/21/15 1617 +/- 251 < 10 < 9 < 32 < 12 11/04/15 1395 +/- 216 "< 9 < 9 < 40 < 9 11/18/15 1477 +/- 146 < 10 < 10 < 35 < 10 12/02/15 1347 +/- 165 <7 < 6 < 38 < 11 MEAN 1418 +/- 197 C-17 Table C-Vlll.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD G2-1 01/07/15 1146 +/- 157 < 7 < 7 < 34 < 9 02/11/15 975 +/- 153, < 7 < 8 < 36 < 9 03/11/15 1151 +/- 181 <6 < 9 < 42 < 14 03/25/15 1065 +/- 112 < 5 < 6 < 49 < 13 04/08/15 773 +/- 123 < 6 < 7 < 47 < 15 04/22/15 859 +/- 88 <4 < 5 < 46 < 15 05/06/15 703 +/- 141 < 9 < 10 < 49 < 12 05/20/15 1387 +/- 169 < 7 < 8 < 43 < 9 06/03/15 1089 +/- 147 < 6 < 7 < 36 < 13 06/17/15 831 +/- 121 < 7 <7 < 35 < 14 07/01/15 829 +/- 155 < 10 < 10 < 47 < 14 07/15/15 1115 +/- 151 < 7 < 6 < 42 < 15 07/29/15 1074 +/- 124 < 7 < 7 < 36 < 11 08/12/15 895 +/- 159 < 8 < 9 < 47 < 15 08/26/15 1012 +/- 148 < 8 < 9 < 40 < 10 09/09/15 1077 +/- 147 < 7 < 8 < 31 < 7 09/23/15 827 +/- 164 < 9 < 9 < 37 < 13 10/07/15 1021 +/- 155 < 6 < 6 < 19 < 8 10/21/15 777 +/- 134 < 8 < 8 < 37 < 13 11/04/15 934 +/- 165 < 9 < 9 < 41 < 10 11/18/15 1239 +/- 130 < 6 < 6 < 20 < 6 12/02/15 885 +/- 175 ' < 7 < 9 < 40 < 8 MEAN 985 +/- 341 K15-3 01/07/15 1204 +/- 133 < 5 < 5 < 27 <6 02/11/15 1319 +/- 166 <7 < 7 < 45 < 11 03/11/15 1202 +/- 160 < 7 ' < 8 < 36 < 10 03/25/15 1330 +/- 126 <5 < 5 < 54 < 13 04/08/15 1247 +/- 141 <"5 < 6 < 35 < 10 04/22/15 1477 +/- 161 < 5 < 5 < 52 < 13 05/06/15 1216 +/- 175 < 7 < 7 < 46 < 12 05/20/15 1214 +/- 128 <4 < 6 < 26 < 9 06/03/15 1267 +/- 125 < 5 < 5 < 23 < 9 06/17/15 '1334 +/- 150 < 6 <6 < 31 < 8 07/01/15 1157 +/- 173 < 7 < 8 < 43 < 14 07/15/15 1120 +/- 121 < 5 < 6 < 37 < 8 07/29/15 1360 +/- 147 < 5 < 5 < 24 <"9 08/12/15 "1366 +/- 233 < 8 < 9 < 51 < 11 08/26/15 1368 +/- 149 < 7 < 6 < 26 < 9 09/09/15 1335 +/- 177 <6 < 6 < 26 < 9 09/23/15 1248 +/- 140 "< 7 <7 < 28 < 5 10/07/15 1222 +/- 126 < 5 < 5 < 18 < 6 10/21/15 1234 +/- 239 < 7 < 13 < 40 <: 8 11/04/15 1220 +/- 188 < 7 < 10 < 46 < 13 11/18/15 1147 +/- 143 <4 < 6 < 19 < 2 12/02/15 1282 +/- 193 < 12 < 10 < 56 < 12 MEAN 1267 +/- 173 C-18 Table C-Vlll.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD P4-1 01/07/15 1389 +/- 163 < 6 < 7. < 29 < 9 02/11/15 1478 +/- 187 < 7 < 7 < 45 < 14 03/11/15 1526 +/- 160 < 9 < 10 < 48 < 12 03/25/15 1271 +/- 120 <4 < 5 < 34 < 13 04/08/15 1375 +/- 143 < 5 <6' < 37 < 8 04/22/15 1487 +/- 101 <4 <4 < '38 < 12 05/06/15 1491 +/- 200 < 8 < 8 < 44 < 12 05/20/15 1485 +/- 195 < 11 < 12 < 56 < 14 06/03/15 1367 +/- 205 < 7 < 8 < 41 < 9 06/17/15 1396 +/- 139 < 5 < 7 < 27 < 7 07/01/15 1315 +/- 150 < 5 < 6 < 27 < 9 07/15/15 1421 +/- 164 < 6 <7 < 47 < 14 07/29/15 1346 +/- 134 <4 < 5 < 24 < 6 08/12/15 1332 +/- 241 < 9 < 11 < 54 < 10 08/26/15 1508 +/- 201 < 8 < 10 < 35 < 10 09/09/15 1501 +/- 195 < 9 < 8 < 34 < 11 09/23/15 1493 +/- 140 < 6 < 6 < 23 < 6 10/07/15 1475 +/- 166 < 5 < 8 < 24 < 6 10/21/15 1484 +/- 193 <7 .< 8 < 27 < 8. 11/04/15 1193 +/- 221 <4 <. 7 < 27 < 14 11/18/15 1382 +/- 128 < 5 < 5 < 18 <4 12/02/15 1382 +/- 200 < 7 < 9 < 42 < 11 MEAN 1414 +/- 175 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, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION SR-90 Be-7 K-40 1-131 *Cs-134 Cs-137 PERIOD 810-2 Brocolli Leaves 06/29/15 8 +/-0 2 395 +/- 227 4272 +/- 544 < 58 < 25 < 29 Cabbage (& Leaves) 06/29/15 < 1 160 +/- 77 3661 +/- 193 < 17 < 8 < 9 Sunflow¢r Leaves 06/29/15 8 +/- 2 1965 +/- 326 6947' +/- 690. < 53 < 19 < 27 Cabbage (& Leaves) 07/20/15 <4 153 +/- 128 2261 +/- 333 < 44 < 15 < 19 Brocolli Leaves 07/27/15 7 +/- 2 296 +/- 58 4532 +/- 166 < 38. < 6 <6 Cabbage (& Leaves) 07/27/15 < 2 < 86 3123 +/- 174 < 50 < 8 < 8 Sunflower .Leaves 07/27/15 < 3 1452 +/- 114 7653 +/- 234 < 52 < 8 < 9 Sweet Corn 08/03/15 < 122 2175 +/- 271 < 50 < 9 < 13 Tomatoes 08/03/15 < 117 1999 +/- 252 < 53 < 10 < 12 Cabbage (& Leaves) 08/31/15 4 +/- 2 < 389 3164 +/- 901 < 51 < 50 < 55 Cabbage (& Leaves) 09/28/15 < 3 < 202 3640 +/- 557 < 46 < 24 < 29 Sweet Potatoes 10/05/15 < 137 3530 +/- 482 < 22 < 18 < 21 MEAN 7 +/- 3 737 +/- 1550 3913 +/- 3547 E1-2 Cabbage (&Leaves) 07/20/15 < 3 263 +/- 25.4 7428 +/- 576 < 47 << 18 < 19 Sweet Corn 08/03/15 < 124 2339 +/- 318 < 56 < 13 < 14 Tomatoes 08/03/15 < 103 3406 +/- 243 < 51 < 10 < 10 Sweet Potatoes 10/05/15 < 100 3480 +/- 369 < 17 < 12 < 14 MEAN 263 +/- 0 4163 +/- 4476 H1-2 Eggplant Leaves 07/27/15 <3 996 +/- 106 6136 +/- 210 < 49 <7 < 8 Squash Leaves 07/27/15 3 +/- 2 1019 +/- 101 4172 +/- 167 < 40 < 6 <6 Zuchinni Leaves 07/27/15 < 3 \ 860 +/- 85 3662 +/- 180 < 47 < 7 < 8 Eggplant Leaves 08/31/15 10 +/- 5 1212 +/- 499 4681 +/- 1382 < 47 < 30 < 38 Squash Leaves 08/31/15 < 5 627 +/- 265 3355 +/- 892 < 57 < 39 < 49 Zuchinni Leaves 08/31/15 11 +/- 4 < 475 3026 +/- 914 < 52 < 46 < 54 Squash Leaves 09/28/15 < 3 1654 +/- 271 2715 +/- 474 < 43 < 22 < 26 Turnip Greens 09/28/15 6 +/- 3 < 306 3860 +/- 558" < 54 < 25 < 27 Zuchinni Leaves 09/28/15 <4 499 +/- 215 2079 +/- 408 < 40 < 18 < 24 MEAN 7 +/- 8 981 +/- 766 3743 +/- 2377 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE* POSITIVE VALUES C-20 Table C-X.1 QUARTERLY OSLO RES UL TS FOR THREE MILE ISLAND NUCLEAR STATION, 2015 . RESULTS IN UNITS OF MILLI REM/QUARTER
STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +/-2 S.D. A1-4 19.9 +/- 2.9 18.1 19.3 21.5 20.5 A3-1 19.7 +/- 2.6 18.6 18.8 21.4 20.1 A5-1 23;6 +/- 3.0 23.0 22.2 25.7 23.5 A9-3 20.5 +/- 3.1 18.7 19.7 22.1 *21.4 81-1 20.4 +/- 3.5 19.0 18.8 21.6 22.2 81-2 20:6 +/- 2.2 19.4 20.0 22.0 20.8 82-1 . .Z0.3 +/- 3.3 18.9 18.9 22.3 20.9 85-1 23.1 +/- 3.2 21.9 21.6 24.6 24.4 C1-1 23.2 +/- 2.5 21.6 23.3 24.6 23.3 C1-2 19.7 +/- 1.3 19.1 19.2 20.4 20.1 C2-1 22.6 +/- 4.2 21.5 20.7 25.5 22.5 C5-1 23.9 +/- 4.0 22.0 22.4 26.2 24.8 C8-1 24.3 +/- 5.0 21.3 23.1 26.5 26.2 01-1 20.3 +/- 2.6 19.7 18.8 21.6 21.1 01-2 21.3 +/- 3.1 19.8 20.1 22.6 22.6 02-2 26.1 +/- 4.1 24.3 25.4 29.0 25.5 06-1 26.0 +/- 4.6 22.8 26.0 28.3 26.7 E1-2 20.7 +/- 2.3 20.0 19.7 22.2 21.0 E1-4 20.0 +/- 3.7 18.3 18.4 21.2 21.9 E2-3 24.4 +/- 3.4 22.3 23.8 26.2 25.2 E5-1 25.9 +/- 2.8 24.3 26.2 27.6 25.4 E7-1 23.7 +/- 4.8 21.3 22.6 26.9 23.9 F1-1 .. 22.3 +/- 1.9 21.3 21.9 23.5 22.6 F1-2 21.0 +/- 3.1 19.il 19.5 22.6 21.9 F1-4 20.3 +/- 3.7 19.3 18.2 21.3 22.3 F2-1 25.1 +/- 3.5 23.8 24.1 27.6 25.0 F5-1 25.6 +/- 4.6 23.3 24.6 28.7 25.9 G1-2 23.3 +/- 4.1 21.1 22.3 25.8 24.1 G1-3 19.6 +/- 2.0 18.6 19.0 20.8 20.0 G1-5 20.0 +/- 2.0 18.6 19.9 20.7 20.7 G1-6 20.5 +/- 2.4 19.0 20.1 21.5 21.4 G2-4 27.0 +/- 3.9 24.6 26.8 29.4 27.0 G5-1 23.0 +/- 3.8 20.7 22.1 24.7 24.3 H1-1 22.3 +/- 2.1 21.1 21.6 23.0 23.3 H3-1 19.6 +/- 2.1 19.1 18.5 20.0 20.9 H5-1 19.1 +/- 2.6 17.8 18.4 20.8 19.3 H8-1 33.1 +/- 6.9 30.1 31.0 37.8 33.3 J1-1 20.4 +/- 2.1 19.4 19.8 21.7 20.8 J1-3 18.1 +/- 1.8 17.6 17.2 19.1 18.6 J3-1 22.6 +/- 4.2 21.0 20.6 24.4 24.5 J5-1 25.2 +/- 4.4 22.6 24.3 27.6 26.2 J7-1 26.1 +/- 4.9 24.0 24.6 29.5 26.2 K1-4 20.3 +/- 2.4 18.9 19.9 21.7 20.8 K2-1 24.5 +/- 3.6 22.5 24.4 26.9 24.3 K3-1 20.4 +/- 2.8 19.0 19.4 21.7 21.5 K5-1 23.9 +/- 2.3 22.5 23.4 24.3 25.2 K8-1 23.5 +/- 3.3 23.1 21.4 24.5 25.1 C-21 Table 9-X.1 QUARTERLY OSLO RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF MILLIREM/QUARTER STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +/-2S.D. L 1-1 21.2 +/- 4.7 19.3 19.8 24.5 21.3 L 1-2 21.0 +/- 2.5 19.8 20.2 22.4 21.7 L2-1 22.9 +/- 2.9 21.2 -24.0 23.4 L5-1 20.4 +/- 2.7 20.0 18.7 21.7 21.2 L8-1 22.8 +/- 3.8 20.4 22.1 24.5 24.1 M1-1 20.0 +/- 3.8 17.7 19.2 21.9 21.2 M1-2 22.2 +/- 2.6 21.2 21.4 24.1 22.2 M2-1 20.5 +/- 2.4 19.3 19.6 21.2 21.8 M5-1 22.2 +/- 2.9 21.0 20.9 23.1 23.8 M9-1 26.7 +/- 5.2 23.1 26.3 28.8 28.4 N1-1 21.6 +/- 3.3 20.3 20.4 23.8 21.7 N1-3 22.2 +/- 5.0 19.7 21.4 25.6 22.1 N2-1 22.9 +/- 2.6 21.4 22.2 24.2 23.7 N5-1 20.1 +/- 3.9 18.2 19.0 20.4 22.6 N8-1 23.2 +/- 2.9 21.7 22.7 25.2 23.3 P1-1 21.2 +/- 4.2 19.1 19.9 23.7 22.2 P1-2 24.7 +/- 13.0 18.0 23.5 33.6 23.8 P2-1 25.6 +/- 3.3 23.9 24.5 27.2 26.8 P5-1 22.6 +/- 3.2 20.7 21.7 23.8 24.0 P8-1 20.3 +/- 2.3 19.8 19.0 21.7 20.6 Q1-1 21.8 +/- 4.4 19.5 20.5 24.4 22.7 Q1-2 19.6 +/- 4.6 17.2 18.7 22.6 19.9 Q2-1 20.0 +/- 1.8 18.8 19.7 20.9 20.4 Q5-1 21.4 +/- 2.5 21.1 20.0 23.0 21.4 Q9-1 21.8 +/- 2.2 21.2 20.5 22.7 22.7 R1-1 20.6 +/- 4.6 17.7 20.0 23.1 21.4 R1-2 20.2 +/- 2.3 19.0 19.5 20.9 21.4 R3-1 25.0 +/- 4.0 22.7 24.0 26.9 26.5 R5-1 24.4 +/- 3.1 22.9 23.3 25.9 25.6 R9-1 24.1 +/- 2.7 22.6 23.3 25.0 25.5 810-1 23.2 +/- 3.0 22.8 21.7 25.3 22.8 015-1 23.3 +/- 2.9 21.8 22.4 24.8 24.2 F10-1 26.9 +/- 4.7 24.1 25.8 29.0 .28.6 F25-1 24.0 +/- 1.9 23.5 23.2 25.3 24.1 G10-1 31.0 +/-4.2 28.8 30.7 33.9 30.7 G15-1 26.3 +/- 4.0 24.4 25.9 29.1 25.6 H15-1 22.6 +/- 3.5 20.9 21.3 24.4 23.7 J15-1 27.2 +/- 4.9 24.5 25.9 29.9 28.5 K15-1 21.7 +/- 3.4 19.8 20.8 23.1 23.2 L 15-1 22.9 +/- 3.0 20.9 22.9 24.5 23.2 N15-2 24.4 +/- 2.1 22.9 24.2 25.3 25.0 015-1 24.6 +/- 3.4 22.4 24.5 26.5 25.1 R15-1 22.1 +/- 2.9 20.5 21.4 23.8 22.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-22 TABLEC-X.2 COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC TABLE C-X.3 LOCATION SITE BOUNDARY INDICATOR CONTROL MEAN QUARTERLY OSLO RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF MILLIREM/OUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA SITE BOUNDARY INDICATOR CONTROL +/-2 S.D. 18.8 +/- 1.9 21.4 +/-4.3 22.8 +/- 5.1 19.7 +/- 2.8 22.0 +/- 5.1 23.9 +/- 5.7 22.6 +/- 6.1 24.8 +/- 6.1 26.4 +/- 6.5 21.2 +/- 2.4 23.7 +/- 5.0 25.1 +/- 4.9
SUMMARY
OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF NJILLIREMOUARTER SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/-2S.D. 76 17.2 33.6 20.6 +/- 4.6 239 17.8 37.8 23.0 +/- 5.8 44 19.8 33.9 24.5 +/- 6.0 SITE BOUNDARY STATIONS -A1-4, 81-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, L1-1, M1-1, N1-3, P1-2, 01-2, R1-1 INDICATOR STATIONS -A3-1, AS-1, A9-3, 81-1, 810-1, 82-1, 85-1, C1-1, C2-1, C5-1, C8-1, D1-2, 02-2, 06-1, E1-2, E2-3, ES-1, E7-1, F1-1, F10-1, F2-1, F5-1, G1-2, G2-4, GS-1, H3-1, H5-1, HB-1, J1-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, KB-1, L1-2, L2-1, L5-1, LB-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, NB-1, P1-1, P2-1, P5-1, PB-1, 01-1, 02-1, 05-1, 09-1, R1-2, R3-1, R5-1, R9-.1 CONTROL STATIONS -D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L 15-1, N15-2, 015-1, C-23 n I N ..j::. FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2015 o Station*J1-2
(Downstream of
,_ -.. -* *rullill Station* (Goritr61) 100000 .._ Q) :!::::! _J 10000 .._ Q) 0.. Cf) 1000 Q) *;:: :J 100 () 0 () 0:: 10 Jan 1000000 .._ Q) 100000 +" :.:::i .._ Q) 0. 10000 --(/) Q) 1000 --*c:: :J (.) 0 100 --(.) a. 10 Jan Feb Mar Apr _ May Jun Jul Month Aug Sep Oct Nov *Station K1-1 (TMINS Liquid Discharge)
Feb Mar Apr -May Jun Jul Aug Sep Oct Nov Dec Month Dec
..... Q) n -I ::i N ..... Vl Q) c.. I/) Q) *c:: :::::i t) 0 t) a: FIGURE C-2' -Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2015 -Indicator Samples -----Control Samples Significant Events Major Atm. Nuclear Weapon Tests 11000 TMI-1 Critical June 1974 June 1974 September 197 -----------------
TMI-2 Critical March 1978 September 1976 November 197 10000 TMI-2 Accident March 1979 September 1977 March 1978 TMI-2 RB Purge June 1980 December 1978 October 1980 8000 7000 6000 5000 ------------------------------------------------------
4000 ---------------------------------
3000 ---------------------------------
2000 1000 0 -1000 "<I" LO co r-co Ol 0 ...... N (') "<I" Lb co r-co Ol 0 ...... N (') "<I" LO co r-co Ol 0 ...... N (') "<I" LO co r-co Ol 0 N r-r-r-r-r-r-co co co co co co co co . co co Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 .0 0 0 0 0 0 ...... ...... ...... Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 0 0 0 0 0 0 ...... ...... ...... ...... ...... ...... ...... N N N N N N N N N N N N N Year (') "<I" LO co ...... ...... ...... ...... 0 0 0 0 N N N N
..... Q) ("') -I ::::i N ..... 0\ Q) a. II) Q) *c:: :::::i (.) 0 0.. FIGURE C-3 .Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2015 D Indicator Samples IT! Control Samples 9 _,_ -------------------------------------------------------------------------------8 -----------------------------------------------------------
-* ---------------------7 _ ... --------------------------------------------------------------------------------
6 _,_ --------------------------------------------------------------------------------
5 _,_ --------------------------------------------------------------------------------
4 _._ ------------------------------------------------------
-,.::_------3 _,_ --------------------------------------------

2 1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month n I N -..J FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Mile Island Nuclear Station, 2015 ,_ (]) +-' :..:::i ,_ (]) 0.. "' (]) *c:: ::l 0 0 0 a: ,_ (]) +-' :..:::i ,_ (]) 0.. "' (]) *c:: ::l 0 0

0 0.... NOTE: The mean values are calculated using both the MDCs and the positive values. D Indicator Samples 500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L 400 300 liilll Control Samples 200 ------------------------

100 0 11111 :l!l!l!l! --iiiiliil --_.:* ... -**'1 __ ... *****'1 ___ ..... -'1_. __ ... *****'i_ ... ******'i_
...... -**'1 __ ... -****'1 __ ... ***=::!1---.. ********'i_
... ******'i_
.... *****'i_ ... *******'i_
... ******'i_
... ******'i_
... ******'1 __ ... *****'i ;iiiiiili iiiilili Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month *Station K1-1 (TMINS Liquid Discharge) 1000000 100000 10000 1000 100 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month n I N 00 800 700 -"'O --E aoo C> 0 500 :S2 L... Q) a. 400 en Q) *c ::J g '300 (.) a.. .200 100 0 FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984-2015 -Indicator Samples --Control Samples Significant Event -GhemobyJ -----Apr-il-1986. --------.. --------------------------------------------------
"'" LO co I"-CX) O'l 0 .,.... N C') "'" LO co I"-CX) O'l 0 .,.... N C') "'" LO co I"-CX) O'l 0 .,.... N C') "'" LO CX) CX) CX) CX) CX) CX) O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l 0 0 0 0 0 0 0 0 0 0 0 .,.... .,.... .,.... .,.... .,.... O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l O'l 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... .,.... N N N N N N N N N N N N N N N N Year
.... Q) -Q) 2 n CJ I :..c N \0 ::J (.) .... Q) a. (/) Q) *c:: ::J CJ 0 CJ c:: FIGURE C-6 Mean 'Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2015 -Indicator
-"---+---Control
---=S1>.:'gn=1='fi=c=an=t-=E...,.v""'en::.:t,,_s
__ Ma'or Atm. Nuclear Wea on Test TMI-1 Critical June 1974 March 1972 June 1973 0.35 1MI-2 Critical March 1978 June 1974 September 19 1MI-2 Accident March 1979 September 1976 November 197 1MI-2 RB Purge
JUne 1980 September 1977 , March 1978 0.3 Chemob 1 A ril 1986 December 1978 October 1980 .......
_____________________________________
_ 0.25 0.2 .0.15 0.1 0.05. 0 N C') "<!' in co I' co mo ..... N C') "<!' in co I' co mo ..... N C'> "<!' in co I' co m 0 ..-N C') "<!' in co I' co m 0 ..-N C') "<!' in co I' I' I' I' I' I' I' I' co co co co co co co co co co .m m mm m mm m mm 0 00 0 0 0 0 0 00 ..... ..... ..... ..... ..... ..... ..... m mm m mm m mm m m mm m mm m mm m mm m mm m mm 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 0 ..........
..... ..........
..... ..... N NN N N NN N NN N NN N NN N Year (1 I I w 0 FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007-: 2015 0.100 * -Indicator
--+---Control 0.090 0.080 .... 0.070 Q) -Q) 2 u 0.060 :.a :::J () (D 0.050 a. en Q) '§ 0.040 u 0 u a: 0,030 0.020 0.010 0.000 I"-r--r--r--tO tO tO O'l O'l O'l O'l 0 0 0 ...... ...... ...... ...... N C\I N (") (") (") (") '<I' '<I' '<I' lO lO 0 Q Q 0 Q 0 .Q 0 Q 0 ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ...... ..---.. -.. -.. -.. -.. <<; -.. -.. -.. ;:::: -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. ;:::: 0 lO tO 0 lO tO ..--N 0 (") O'l r--0 0 (") r--N lO r--C\I lO O'l C\I ..--Q Q ...... Q ...... ...... ...... Q ...... Q ...... 0 Q ...... ...... ...... 0 -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. -.. ...... '<I' tO ...... (") co 0 ..--'<I' tO ...... (") co 0 ...... lO tO ..--(") co 0 ...... tO ...... (") co 0 ..--0 0 0 ...... 0 0 ..--0 0 0 ...... 0 0 ...... 0 0 0 ...... 0 0 ..--0 0 0 ..--0 0 0 0 Month I Day I Year lO lO ..--...... -.. -.. O'l (") ...... 0 -.. -.. tO C\I 0 I.... Q) +-' ::::i (j I.... I Q) w _. a. CJ) Q) *c::: ::J (.) 0 (.) a..: FIGURE C-8. Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2015 -Indicator Samples ----+-Control Samples Significant Events Major Atm. Nuclear Weapon Tests 9 TMI-2 Accident March 1979December 1978 October 1980 TMI-2 RB Purge June 1980 Chernobyl April 1986 8 7 6 5 4 3 2 1 0 Ol 0 ..--N C') '<t LO (!) I"-c:o Ol 0 ..--N C') '<t LO (!) I"-c:o Ol 0 ..--N C') '<t LO (!) I"-c:o Ol 0 N C') I"-c:o c:o c:o c:o c:o c:o c:o c:o c:o c:o Ol Q) Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 0 0 0 ..--..--..--..--Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol Ol 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ..--..--..--N N N N N N N N N N N N N N Year '<t LO (!) ..--..--..--0 0 0 N N N Intentionally left blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY Intentionally left blank The following section presents the results of data analysis performed by the QC laborator}', Environmental Inc. Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TSE) and the QC laboratory.
Comparison of the results for most media were within expected ranges. D-1 Intentionally left blank D-2
--TABLE D-1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31 /15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07/28/15 07 /28/15 -09/01 /15 09/01/15 -09/29/15 09/29/15 -11/03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN TABLE D-1.2 COLLECTION PERIOD 12/30/14 -02/03/15 02/03/15 -03/03/15 03/03/15 -03/31/15 03/31/15 -04/28/15 04/28/15 -06/02/15 06/02/15 -06/30/15 06/30/15 -07 /28/15 07/28/15 -09/01/15 09/01/15 -09/29/15 09/29/15 -11 /03/15 11/03/15 -12/01/15 12/01/15 -12/29/15 MEAN TABLE D-1.3 IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA Q9-1Q 1.4'+/-0.7 1.2 +/- 0.5 < 1.8 < 1.7 1.8 +/- 0.7 < 0.9 1.0 +/- 0.5 < 0.9 1.6 +/- 0.6 2.1 +/- 1.0 < 0.9 2.4 +/- 1 1.6 +/- 1.0 CONCENTRATIONS OF TRITIUM IN DRINKING WAT.ER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA Q9-1Q < 189 < 151 < 149 < 147 < 155 < 149 < 146 < 149 < 149 < 148 < 144 < 144 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION Q9-1Q PERIOD 12/30/14 -02/03/15 < 0.4 02/03/15 -03/03/15 < 0.4 03/03/15 -03/31/15 < 0.4 03/31/15 -04/28/15 < 0.2 04/28/15 -06/02/15 < 0.4 06/02/15 -06/30/15 < 0.3 06/30/15 -07/28/15 < 0.3 07/28/15 -09/01/15 < 0.4 09/01/15 -09/29/15 < 0.3 09/29/15 -11/03/15 < 0.5 11/03/15 -12/01/15 < 0.4 12/01/15 -12/29/15 < 0.3 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, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q9-1Q 12/30/14 -
02/03/15 < 1 < 3 < 1 < 1 < 2 < 2 < 1 < 1 < 1 < 8 < 3 02/03/15 -03/03/15 < 4 < 7 < 3 < 3 < 6 <4 <4 < 2 <5 < 11 < 3 03/03/15 -03/31/15 < 2 <4 < 1 < 2 < 2 < 3 < 1 < 1 < 1 < 12 < 6 03/31 /15 -04/28/15 < 1 < 5 <2 < 2 <4 <3 <4 < 2 <2 < 25 <2 04/28/15 -06/02/15 < 5 < 10 <5 <4 < 6 < 8 <4 <4 <6 < 31 < 8 06/02/15 -06/30/15 < 3 < 4* < 2 < 1 < 3 < 5 < 3 < 3 < 3 < 20 <2 06/30/15 -07 /28/15 < 4 <.6 < 5 < 5 < 9 < 6 <3 <4 < 3 < 17 < 8 07/28/15 -09/01/15 < 2 <3 < 2 < 2 < 4 < 5 < 3 < 2 < 1 <
20 <4 09/01/15 -09/29/15 < 1 < 6 <2 < 2 <4 <4 < 3 < 3 < 4 < 19 < 3 u 09/29/15 -11/03/15 < 1
<2 < 1 < 1 <2 <2 < 1 < 1 < 1 <
11 < 3 I 11/03/15 -12/01/15 < 4
., <4 < 5 <4 <3 < 8 < 3 < 3 < 6 < 24 < 6 ..j:>. 12/01/15 -12/29/15 < 3 <
10 < 5 <4 < 11 < 9 <4 <4 < 6 < 26 <6 ti I VI ,f ** : .** *' TABLE D-11.1 SITE COLLECTION PERIOD INDP 10/08/15 ,_.,;**';::_-;
CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA Sr-89 SHJO K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 < 12 <5 3350 +/- 410 < 10 < 19 < 40 < 10 < 29 < 20 < 15 TABLE D-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA I SITE COLLECTION KJ40 Cs-134 Cs-137 PERIOD J2-1 10/29/15 13750 +/- 736 < 19 56 +/- 20 MEAN 13750 +/- 0 ' .-(' D-6 TABLE D-IV.1 SITE COLLECTION PERIOD H1-2Q 07/27/15 B10-2Q 07/20/15 MEAN CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA K-40 4010 +/- 370 2330 +/- 290 3170 +/- 2376 1-131 < 13 < 15 D-7 Cs-134 < 9 < 9 Cs-137
Sr-89 < 16 < 11 < 9 <4 Sr-90 35 +/- 5 2 +/- 1 19 +/- 47 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, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION E1-2Q E1-2Q PERIOD GROSS BETA 1-131 61/61115 -61/68115 36 +/- 5 < .19
-01/15/15 28 +/- 4 < 16 01/15/15 -01/22/15 27 +/- 5 <. 11 01/22/15 -01/29/15 19 +/- 4 < 13 01 /29/15 -02/05/15 19 +/- 4 < 16 02/05/15 -02/12/15 24 +/- 4 < 17 02/15/15 -02/19/15 31 +/- 4 < 27 02/19/15 -02/26/15 42 +/- 6 < 21 02/26/15 -03/05/15 29 +/- 5 < 11 03/05/15 -03/12/15 23 +/- 5 < 27 03/12/15 -03/18/15 17 +/- 5 < 17 03/18/15 -03/26/15 26 +/- 4 < 18 03/26/15 -04/02/15 21 +/- 5 < 21 04/02/15 -04/09/15 23 +/- 5 < 12 04/09/15 -04/16/15 18 +/- 4 < 25 04/16/15 -04/23/15 16 +/- 4 < 20 04/23/15 -04/30/15 13 +/- 4 < 16 04/30/15 -05/07 /15 23 +/- 5 < 14 05/07/15 -05/14/15 22 +/- 4 < 20 05/14/15 -05/21/15 21 +/- 4 < 28 05/21/15 -05/28/15 26 +/- 5 < 24 05/15/15 -06/04/15 16 +/- 4 < 18 06/04/15 -06/10/15 20 +/- 5 < 33 06/10/15 -06/18/15 18 +/- 4 < 26 06/18/15 -06/25/15 25 +/- 5 < 15 06/25/15 -07/02/15 18 +/- 5 < 16 07/02/15 -07/09/15 23 +/- 5 < 18 07/09/15 -07/16/15 23 +/- 5 < 17 07/16/15 -07/23/15 24 +/- 5 < 26 07/23/15 -07/30/15 34 +/- 5 < 24 07 /30/15 -08/06/15 29 +/- 5 < 21 08/06/15 -08/13/15 23 +/- 5 < 52 08/13/15 -08/19/15 40 +/- 6 < 25 08/19/15 -08/27/15 28 +/- 4 < 22 08/27 /15 -09/03/15 56 +/- 6 < 25 09/03/15 -09/10/15 47 +/- 6 < 20 09/10/15 -09/16/15 32 +/- 6 < 12 09/16/15 -09/24/15 36 +/- 5 < 20 09/24/15 -10/01/15 21 +/- 5 < 14 10/01 /15 -10/08/15 15 +/- 5 < 26 10/08/15 -10/15/15 26 +/- 5 < 16 10/15/15 -10/22/15 28 +/- 5 < 19 10/22/15 -10/29/15 23 +/- 5 < 23 10/29/15 -11 /05/15 32 +/- 5 < 18 11/05/15 -11/12/15 24 +/- 5 < 22 11/12/15 -11/19/15 31 +/- 5 < 22 11/19/15 -11/25/15 20 +/- 5 < 35 11/25/15 -12/03/15 29 +/- 4 < 11 12/03/15 -12/10/15 69 +/- 6 < 20 12/10/15 -12/17/15 50 +/- 6 < 21 12/17/15 -12/23/15 32 +/- 6 < 24 12123/15 -12/31/15 16 +/- 4 < 20 MEAN 27 +/- 21 D-8 TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA SITE COLLECTION Be-7 Cs-134 Cs-137 PERIOD E1-2Q 01/01/15 -04/02/15 79 +/- 13 < 0.8 < 0.7 04/02/15 -07 /02/15 88 +/- 16 < 0.7 < 0.8 07/02/15 -10/01/15 98 +/- 19 < 0.8 < 1.0 10/01/15 -12/31/15 62 +/- 16 < 0.5 < 0.5 MEAN 82 +/- 31 D-9 TABLE DNl.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, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 DATE G2-1Q 01/07/15 < 0.2 1106 +/- 94 <2 <4 < 31 < 5 02/11/15 < 0.4 1026 +/- 90 <2 < 3 < 31 < 6 03/11/15 < 0.5 1059 +/- 86 <2 <3 < 22 < 3 03/25/15 < 0.2 1136 +/- 88 < 3 < 3 < 23 < 5 < 0.6 < 0.6 04/08/15 < 0.4 966 +/- 77 <2 < 3 < 26 <4 04/22/15 < 0.4 837 +/- 75 < 2 < 3 < 25 < 6 05/06/15 < 0.2 863 +/- 66 < 2 < 2 < 30 < 5 05/20/15 < 0.4 1389 +/- 101 < 2 < 3 < 16 < 4 06/03/15 < 0.3 740 +/- 80 <3 < 2 < 38 < 8 06/17/15 < 0.4 1009 +/- 106 <4 <4 < 18 < 5 < 0.5 < 0.6 07/01/15 < 0.5 1065 +/- 118 < 6 < 7 < 19 < 8 07/15/15 < 0.4 1108 +/- 100 <3 < 3 < 27 <4 07/29/15 < 0.3 1308 +/- 150 < 6 < 6 < 24 < 6 08/12/15 < 0.2 1084 +/- 85 <2 <4 < 49 < 12 08/26/15 < 0.4 1130 +/- 109 <3 < 3 < 35 < 9 09/09/15 < 0.4 1122 +/- 78 < 2 < 2 <
39 < 5 09/23/15 < 0.4 777 +/- 75 < 3 < 3 < 27 < 7 < 0.6 < 0.5 10/07/15 < 0.5 998 +/- 85 < 3 < 3 <
28 < 14 10/21/15 < 0.3 927 +/- 86 < 3 < 3 < 43 < 6 11/04/15 < 0.2 895 +/- 36 < 1 < 2 < 11 < 5 11/18/15 < 0.4 1473 +/- 98 < 3 <4 < 31 <4 12/02/15 < 0.4 1328 +/- 137 <5 < 5 < 27 < 5 < 0.5 < 0.4 MEAN 1061 +/- 382 D-10 I --FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2015 ---QC-LAB s ---------------------------*---------------------------------------
__.___PRIMARY
-LAB --4 -----------------------------------------------------------------------------*----------------------------------:
... s 3 0 c. 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTl:I I -N FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2015 ------QC -LAB 50 *-* --'*--PRIMARY
-LAB 40 -G) E .c :I 30 0 c. C? . w 20 10 1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.
APPENDIX E INTER-LABORATORY COMPARISON PROGRAM Intentionally left blank TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 {PAGE 1OF3) Identification Reported Known Ratio (c) MonthNear Number Matrix Nuclide Units Value (a) Value (b)
Evaluation (d) March 2015 .E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 w E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A E11184 AP Ce-141 pCi 107 85.0 1.26 w Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 *77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 *Water Fe-55 pCi/L 1950 ' 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 w Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143 125 1. 14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 w Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1) Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 .A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi . 198 210 0.94 . A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A E-1 TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE2 OF3) Identification Reported Known Ratio (c) Month/Year Number Matrix .Nuclide Units Value(a) Value (b) TSE/Analytics Evaluation (d) June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A Zn-65 pCi/L 392 353 1.11 A Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 .Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A .. Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg '311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 pCi/L 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L .265 281 0.94 A Cs-134. pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A E-2 TABLE E-1 ANAL Y.TICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (bl TSE/Analytics Evaluation (d) December 2015 E11357 AP Ce-141 pCi 89.9 84.0 1.07 Cr-51 pCi 215 184 1.17 Cs-134 pCi 103 105 0.98 Cs-137 *pCi 76.6 74.8 1.02 Co-58 pCi 76.2 71.9 1.06 Mn-54 pCi 91.4 94.4 0.97 Fe-59 pCi 78.6 70.3 1.12 Zn-65 pCi 173 162 1.07 Co-60 pCi 138 139 0.99 . E11422 AP Sr-89 pCi 98.0 96.9 1.01 Sr-90 pCi 10.0 14.0 0.71 E11356 Charcoal:
1-131 pCi 74.9 75.2 1.00 E11358 Water Fe-55 pCi/L 2160 1710 1.26 E11353 Soil Ce-141 pCi/kg 252 222 1.14
Cr-51 pCi/kg 485 485 1.00 Cs-134 pCi/kg 319 277 1.15 Cs-137 pCi/kg 292 276 1.06 Co-58 pCi/kg 193 190 1.02 Mn-54 pCi/kg 258 250 1.03 Fe-59 pCi/kg 218 186 1.17 Zn-65 pCi/kg 457 429 1.07 Co-60 pCi/kg 381 368 1.04 (1) AP Cr-51 -Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable.
NCR 15-18 (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 o'f W-Acceptable with warning, reported result falls within o. 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 A A A A A A A A A A w A w A A A A A A A A A TABLE E-2 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance
Month/Year Number Media Nuclide* Units Value (a) Value (b) Range *Evaluation (c) Mcirch 2015 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 -*0.850 A Ni-63 Sq/L 2.5 (1) A Pu-238 Sq/L 0.0204 0.0089 (2) A Pu-239/240 Sq/L 0.9 0.8 0.582 -1.082 A 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314 -582 A Sr-90 Sq/kg 286 653 487 -849 N (3) 15-RdF32 AP Sr-90 Sq/sample
-0.0991 (1) A U-234/233 Sq/sample 0.0211 0.0155 0.0109 -0.0202 N (3) U-238 Sq/sample 0.095 0.099 0.069 -0.129 A 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53-3.01 N (3) Gr-S Sq/sample 0.7580 0.75 0.38 -1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample . 8.08 7.32 5.12 -9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 -11.93 w Co-57 Sq/sample
-0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 -7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample
0.999 1.08 0.76-1.40 A Zn-65. Sq/sample (1) A September 2015 15-MaW33 Water
Am-241 Sq/L 1.012 1.055 0.739-1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4) Pu-238 Sq/L 0.727 0.681 0.477 -0.885 A Pu-239/240 Sq/L 0.830 0.900 0.630 -1.170 A 15-MaS33 Soil Ni-63 Sq/kg 635 682 477 -887 A Sr-90 Sq/kg 429 425 298 -553 A 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53-2.83 N (4) U-234/233 Sq/sample 0.143 0.143 0.100-0.186 A U-238 Sq/sample 0.149 0.148 0.104-0.192 A 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 A Gr-S Sq/sample 1.34 1.56 0.78 -2.34 A 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06 -7.54 A Cs-137 Sq/sample 0.0002 (1) A Co-57 Sq/sample 8.01 6.62 4.63 -8.61 w Co-60 Sq/sample 4.97 4.56 3.19 -5.93 A Mn-54 Sq/sample 8.33 7.68 5.38 -9.98 A Sr-90 Sq/sample 0.386 1.30 0.91-1.69 N (4) .(1) False positive test. Zn-65 Sq/sample 6.07 5.46 3.82-7.10 A (2) Sensitivity evaluation.
(3) Soil Sr-90 -incomplete digestion of the sample resulted in low results; AP U-2341233
-extremely low activity was difficult to quantify AP Gr-A -the MAPEP filter has the activity embedded in the fitter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult tci quantify; AP & Vegetation Sr-90 was lost during separation,.
possible from substance added by MAPEP NCR 15-21. (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) DOE/MAPEP evaluation:
A=acceptable, W=acceptable with warning, N=not acceptable.
E-4 TABLE E-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 -71.2 Sr-90 pCi/L 28.0 41.9 30.8 -48.1 Ba-133 pCi/L 80.6 82.5 63.9 -90.8 Cs-134 pCi/L 71.7 75.7 61.8 -83.3 Cs-137 pCi/L 187 189 170 -210 Co-60 pCi/L 85.7 84.5 76.0-95.3 Zn-65 pCi/L 197 203 183 -238 Gr-A pCi/L 26.1 42.6 22.1 -54.0 Gr-B pCi/L 28.8 32.9 21.3 -40.6 1-131 'pCi/L 23.5 23.8 19.7 -28.3 U-Nat pCi/L 6.19 6.59 4.99-7.83 H-3 pCi/L 3145 3280 2770-3620 November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 -42.5 Sr-90 pCi/L 29.3 31.1 22.7 36.1 Ba-133 pCi/L 31.5 32.5 25.9 -36.7 Cs-134 pCi/L 59.65 62.3 50.6 -68.5 Cs-137
pCi/L 156 157 141 -175 Co-60 pCi/L 70.6 71.1 64.0-80.7 Zn-65 pCi/L 145 126 113-149 Gr-A pCi/L 38.2 51.6 26.9-64.7 Gr-8 pCi/L 42.0 36.6 24.1 -44.2 1-131 pCi/L 24.8 26.3 21.9-31.0 U-Nat pCi/L 146.90 56.2 45:7 -62.4 H-3 pCi/L 21100 21300 18700 -23400 (1) Yield on the high side of our acceptance range indicates possibility of calcium interference.
NCR 15-09 (2) Technician failed to dilute original sample. If dilulted, the result would have been 57. 1, which fell within the acceptance limits. NCR 15-19 (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-5 Evaluation (c) N (1) N (1) A A A A A A A A A A A A A A A A A A A A N(2) A TABLE E-4 ERA (a) STATISTICAL
SUMMARY
PROFICIENCY TESTING PROGRAM 8 ENVIRONMENTAL, INC., 2015 (Page 1 of 1) Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 -48.10 ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 -90.80 ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 -83.30 ERW-1448 04/06/15 Cs-137 -191.92 +/-5.9 189 -170.00 -210.0 ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 -95.30 ERW-1448 04/06/15 Zn-65 -195.97 +/- 12.0 203 -183.00 -238.0 ERW-1450 04/06/15 Gr. Alpha 34.05 +/- .1.90 42.60 22.10 -54.00 ERW-1450 04/06/15 G. Beta 26.93 +/- 1.12 32.90 21.30 -40.60 ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 -3620 ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 -36.70 ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 -175.0 ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 -80. 70 ERW-5531 10/05/15 Zn-65 . -138.94 +/- 5.7 126 -113.00 -149.0 ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 -44.20 ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 -31.00 ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45. 70 -62.40 ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 -23400.0
Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crossche.ck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA). b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. E-6 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass TABLE E-5
DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 1of2) Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 02/01/15 Nic63 341 +/- 18 448 314 -582 Pass MAS0-975 02/01/15 sr-90 523 +/- 12 653 457 -849 Pass MAS0-975 02/01/15 Cs-134 533 +/- 6 678 475 -881 Pass MAS0-975 02/01/15 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 02/01/15 Co-57 0.5 +/- 1 0.0 NA c Pass MAS0-975 02/01/15 Co-60 741 +/- 8 817 572 -1062* Pass MAS0-975 02/01/15 Mn-54 1,153 +/- 9 1,198 839 -1557 Pass MAS0-975 02/01/15 Zn-65 892 +/- 18 1064 745 -1383 Pass MAW-969 02/01/15 Am-241 0.650 +/- 0.078 0.654 0.458 -0.850 Pass MAW-969 02/01/15 Cs-134 21.09 +/- 0.25 23.5 16.5 -30.6 Pass MAW-969 02/01/15 Cs-137 19.63 +/- 0.34 19.1 13.4 -24.8 Pass MAW-969 d 02/01/15 Co-57 10.2 +/- 0.4 29.9 20.9' -38.9 Fail MAW-969 02/01/15 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 02/01/15 H-3 *569+/-13 563 394 -732 Pass MAW-969 02/01/15 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 02/01/15.
Mn-54 0.02 +/- 0.07 0.00 NAC Pass MAW-969 02/01/15 Ni-63 2.9 +/- 3 0.00 NAC Pass MAW-969 02/01/15 Zn-65 16.54 +/-. 0.85 18.3 . 1*2.8 -23.8 Pass MAW-969 02/01/15 Pu-238 0.02 +/- 0.03 0.01 NA 0 Pass MAW-969 02/01/15 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 02/01/15 Sr-90 9.40 +/- 1.30 9.48 6.64 -12.32 Pass MAW-950 02/01/15 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 02/01/15 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAAP-978 02/01/15 Cs-134 1.00 +/- 0.04 1.15 0.81 -1.50 Pass MAAP-978 02/01/15 Cs-137 0.004 +/- 0.023 o,oo NA c Pass MAAP-978 e 02/01/15 Co-57 0.04 +/- 0.04 1.51 1.06 -1.96 Fail MAAP"978 02/01/15 Co-60 0.01 +/- 0.02 0.00 NAC Pass MAAP-978 02/01/15 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978 02/01/15 Zn-65 0.83 +/- 0.10 0.83 0.58 -1.08 Pass MAAP-981 02/01/15 Sr-89 38.12 +/- 1.01 47.5 33.3 -61.8 Pass MAAP-981 02/01/15 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 02/01/15 Gr. Alpha 0.59 +/- 0.06 *1.77 0.53 -3.01 Pass MAAP-984 02/01/15 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 02/01/15 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 02/01/15 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 02/01/15 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 02/01/15 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 02/01/15 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 02/01/15 Zn-65 0.09 +/- 0.12 0.00 . NA c Pass E-7 TABLE E-5 DOE'S MIXEDANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 2 of 2) Concentration a Known Lab Code b Date Analysis Laboratory result Activity MAS0-4903 08/01/15 Ni-63 556 +/- 18 682 MAS0-4903 f 08/01/15 Sr-90 . 231 +/- 7 425 MAS0-4903
f. 08/01/15 Sr-90 352 +/- 10 425 MAS0-4903 08/01/15 Cs-134 833 +/- 10 1,010 MAS0-4903 08/01/15 *Cs-137 ' 808 +/- 11 809.00 MAS0-4903 08/01115 Co-57 1,052 +/- 10 1, 180 MAS0-4903 08/01/15' Co-60 2 +/- 2 1.3 MAS0-4903 08/01/15 Mn-54 1.,331 +/- 13 1,340 MAS0-4903 08/01/15 Zn-65 686 +/- 15 662 MAW-5007 08/01/15 Cs-134 16.7 +/- 0.4 23.1 MAW-5007 08/01/15 Cs-137 -0.36 +/- 0.13 0 MAW-5007 08/01/15 Co-57 21.8 +/- 0.4 20.8 MAW-5007 08/01/15 Co-60 17.3 +/- 0.3 17.1 MAW-5007 08/01/15 H-3 227.5 +/- 8.9 216 MAW-5007 g 08/01/15 Fe-55 4.2 +/- 14.1 13.1 MAW-5007 08/01/15 Mn-54 16.6 +/- 0.5 15.6 MAW-5007 08/01/15 Ni-63 '9.1 +/- 2.6 8.55 MAW-5007 08/01/15 Zn-65 15.5 +/- 0.9 13.9 MAW-5007 08/01/15 Sr-90 4.80 +/- 0.50 4.80 MAW-5007 08/01/15 Gr. Alpha 0.41 +/- 0.04 0.43 MAW-5007 08/01/15 Gr. Beta 3.45 +/- 0.07 3.52 MAAP-4911 08/01/15 Sr-89 3.55 +/- 0.67 3.98 MAAP-4911 08/01/15 Sr-90 0.94 +/- 0.16 1.05 MAAP-4907 08/01/15 Gr. Alpha 0.30 +/- 0.04 0.90 MAAP-4907 08/01/15 Gr. Beta 1.85 +/- 0.09 1.56 MAVE-4901 . 08/01/15 Cs-134 5.56 +/- 0.16 5.80 MAVE-4901 08/01/15 Cs-137
+/- 0.06 0.00 MAVE-4901 08/01/15 Co'-57 7.74+/-0.18 6.62 MAVE-4901 08/01/15 Co-60 4.84 +/- 0.15 4.56 MAVE-4901 08/01/15 Mn-54 *8.25 +/- 0.25 7.68 MAVE-4901 08/01/15 Zn-65 5.78 +/- 0.29 5.46
Results are reported in units of Bq/kg (soil), Bq/L (water).,or Sq/total sample (filters, vegetation).
b Laboratory codes as follows: MAW (water), MAAP {air filter), MASO (soil), MAVE (vegetation).
Control Limits c 477 -887 298 -553 298 -553 707 -1313 566 -1052 826 -1534 NA 0 938 -1742 463 -861 16.2 -30 NA c 14.6 -27 12 -22.2 151 -281 92 -17 10.9 -20.3 5.99 -11.12 9.7 -18.1 3.36 -6.24 0.13 -0.73 1.76 -5.28 , 2.79 -5.17 0.74 -1.37 0.27 -1.53 0.78 -2.34 4.06 -7.54 NA c 4.63 -8.61 3.19 -5.93 5.38 -9.98 3.82 -7.10 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 Lab result was 27.84. Data entry error resulted in a non-acceptable result.
Lab result was 1.58. Data entry error resulted in a non-acceptable result. f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.
g The known activity was below the routine laboratory detection limits for the available aliquot fraction.
E-8 Acceptance Pass Fail Pass Pass Pass Pass, Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)
Intentionally left blank Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1and2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January Through 31 December 2015 Prepared By Teledyne Brown Engineering Environmental Services E*:. ***. *. xe Three Mile Island Nuclear Station Middletown, PA 17057 April 2016 Intentionally left blank Table Of Contents I. Summary and Conclusions
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1 II. Introduction
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..... 3 A. Objectives of the RGPP ......................................................................................
4 B. Implementation of the Objectives
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4 C. Program Description
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5 D. Characteristics of Tritium (H-3) ...........................................................................
5 Ill. Program Description
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6 A. Sample Analysis ..................................................................................................
6 B. Data Interpretation
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.' .. 7 IV. Results and Discussion
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8 A. Groundwater Results: ..........................................................................................
8 B. Surface Water Results ..............................
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10 C. Storm Water Results .... : ...................................................... ......*......................
10 D. Precipitation Water Results ........................................................................ ...... 11 E. Leaks, Spills, and Releases ................
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11 F. Actions Taken ............................
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12 Appendix A Tables Table A-1 Figures Figure A-1 Appendix B Tables Table 8-1.1 Table 8-1.2 Table 8-1.3 Table B-11 .1 Table B-11.2 Table B-111.1 Table B-111.2 Table 8-IV.1 Appendices Location Designation Radiological Groundwater Protection Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2015 Sampling Locations at the Three Mile Island Nuclear Station, 2015 Data Tables Concentrations of Tritium, Strontium, Gross Alpha, and Gross. Beta in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. ' Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2015. Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuc.lear Station, 2015. Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2015. Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. ii Appendix C Data Tables -Comparison Tables Table C-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2015. Table C-1.2 Concentrations of Gamma Emitters in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection ,Program, Three Mile Island Nuclear Station, 2015. Table C-1.3 Concentrations of Hard-To-Detects in Groundwater Split Samples Collected Part of the Radiological Groundwater Protection
Program, Mile Island Generating Station, 2015. Table C-11.1 Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile
Island Nuclear Station, 2015.
Ta,ble C-11.2 Concentrations of Gamma Emitters in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Statio.n, 2015. Table C-111.1 Concentrations of Tritium in Predpitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, : Three Mile Island Nuclear Station, 2015. iii I. Summary and Conclusions In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Three Mile Island Nuclear Station. At Three Mile Island Nuclear, 31 new p*ermanent groundwater monitoring wells were installed in 2006. The results for all TMI wells are included in this report. This report covers groundwater, surface water, storm water and precipitation samples collected from the environment, both on and off .station property in 2015. During that time period 617 analyses were performed on 377 samples from 68 locations.
In assessing all the data gathered for this report, it was concluded that the operation of Three Mile Island Nuclear*Station had no adverse radiological impact on the environment.*
1 , ' Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as speCified in the Offsite Dose Calculation Manual (ODCM) 'in any of the groundwater, surface water, storm water and precipitation samples. In the case of tritium, Exelon specified that its laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.
Strontium-89 and strontium-90 were not detected at a concentration greater than their respective LLD of 10 and 1 picoCurie .per liter (pCi/L) in the groundwater samples tested. Tritium was not detected in any surface water, storm water or precipitation water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Tritium was detected in groundwater samples above the 20,000 pCi/L limit at 2 locations ranging from 6, 150 to 37 ,200 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 33 of 58 groundwater monitoring locations.
The groundwater tritium concentrations ranged from 203 +/- 128 pCi/L to 37,200 +/- 3,740 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of a tank leakage, historical releases, the recapture of gaseous tritium releases via rainwater and/or background from external sources greater than 200 pCi/L. Tritium was not detected at any surface water location.
Tritium was detected in two of four storm water samples at concentrations of 316 +/- 135 pCi/L to 424 +/- 146 pCi/L. Tritium was detected in five of six precipitation water locations.
The concentration ranged from 192 +/- 125 to 8, 170 +/- 870 pCi/L.
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2015. Gross Alpha (dissolved) was not detected at any of the groundwater locations
.. Gross Alpha (suspended) was detected at two of 25 groundwater locations
.. The concentrations ranged from 1.9 to 6.9 pCi/L. Gross Beta (dissolved) was detected at 25 of 25 groundwater locations.
The concentrations ranged from 1.5 to 11.0 pCi/L.
Gross Beta (suspended) was not detected in any of the 25 groundwater locations.
*Hard-To-Detect analyses, which include Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238, were not analyzed i.n 2015.
11. Introduction The Three Mile Island Nuclear Station (TMINS) established a revised and more comprehensive groundwater monitoring program in 2006 as part of an Exelon Nuclear fleetwide assessment.
Conestoga Rovers & Associates (CRA) performed the initial assessment.
CRA prepared a Hydrogeologic Investigation Report (HIR) for Exelon to determine whether groundwater at and near TMINS has been adversely impacted by any releases of radionuclides.
The CRA report documents the results of the May 2006 Hydrogeologic Investigation Work Plan. CRA assessed groundwater quality at the Station and identified locations designated as Areas for Further Evaluation.
The results and conclusions of this Phase 1 study were made available to state and federal regulators, as well as the public on an Exelon web site for station specific reports. As a result of the Phase 1 study, the Radiological Groundwater Protection
Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on well water, surface water, precipitation water and storm water samples collected in 2015. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides. In September 2015, GHD completed an additional five-year update hydrogeologic investigation report for the Station (NE/ 07-07, Hydrogeo/ogic Investigation Report). The referenced report summarized station activities since the 2006 hydrogeologic investigation report, including changes at the Station as well as RGPP sampling activities and groundwater flow. Relevant conclusions from the report are:
None of the Areas of Further Evaluation (AFEs) identified in 2006 indicate current impacts to groundwater and are no longer considered AFEs.
One new AFE, AFE-TMl-6-BWST, was identified based on laboratory analytical data.
In July 2012, elevated tritium concentrations were noted for a sample collected from an electric vault west of MS-22. The source of this elevated tritium concentration is believed to be the BWST.
Tritium is not migrating off of the Station property at concentrations greater than the USEPA Drinking Water Standard of 20,000 pCi/L.
Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective LLDs.
Strontium 89 or 90 were not detected at concentrations greater than their respective LLDs.
This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2015. A. Objective of the RGPP The long-term objectives of the Radiological Groundwater Protection Program (RGPP) are as follows: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources. 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.
3. Perform routine water sampling and radiological analysis of water from selected locations.
4. Notify stakeholders in a timely manner for new leaks, spills, or other detections with potential radiological significance.
5. Regularly assess analytical results to identify adverse trends. 6. , Take necessary corrective actions to protect groundwater resources.
R Implementation of the Objectives The objectives*
identified have been implemented at Three Mile Island Nuclear Station as discussed below:
1. Three Mile Island Nuclear Station continues to sample and monitor the groundwater at the station in accordance with station procedures.
Sample frequencies and locations are adjusted based on monitoring results and investigations.
2. The Three Mile Island Nuclear Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing
measurements.
3. Three Mile Island Nuclear Station will continue to perform routine sampling and radiological analysis of water from selected locations.
4. Three Mile Island Nuclear Station has implemented procedures to identify and report leaks, spills, or other detections with potential
-4..:
radiological significance in a timely manner.. 5. Three Mile Island Nuclear Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends. C. Program Description
1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1 and A-2, Appendix A. Groundwater.
Surface Water. Storm Water. and Precipitation Samples of water are collected, managed, transported and analyzed.in accordance with approved procedures.
Groundwater, surface water, storm water and precipitation are collected.
Sample locations, sample .collection frequencies and analytical frequencies are controlled in accordance with approved station procedures.
Contractor and/or station personnel are trained in the collection, preservation management and shipment of samples, as well as in documentation of sampling events. For split samples, collectors will periodically collect samples that are sent to Midwest Labs to confirm that TBE is producing comparable data. Analytical laboratories are subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables as data are received.
Analytical data results are reviewed.
by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.
D. Characteristics of Tritium (H-3) Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen.
The most common form of tritium is tritium oxide, which is also called "tritiated water." Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the .same velocity as the average groundwater velocity.*
Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., made) sources. Tritium is produ.ced naturally in the upper atmosphere when cosmic rays strike air molecules.
This "cosmogenic' 1 tritium combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.
A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere.
The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
The chemical properties of tritium are essentially those of ordinary hydrogen.
Tritium can be taken into the-body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, all tritium is essentially cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period. Tritium has a radiological half-life of approximately 12.3 years. It decays spontaneously to helium-3 (He-3). This radioactive decay releases a beta particle (low-energy electron).
The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides, because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue. Ill. Program Description A. Sample Analysis *. This section describes the general analytical methodologies used by TSE
and Midwest Labs to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2015. In order to achieve the stated objectives, the current program includes the following analyses, as applicable:
1. Concentrations of gamma emitters in groundwater, surface water and storm water. 2. Concentrations of strontium in groundwater.
3: Concentrations of tritium in groundwater, surface water,
precipitation water and storm water. 4. Concentrations of Am-241 in groundwater.
5. . Concentrations of Cm-242 and Cm-243/244 in groundwater.
6. Concentrations of Pu-238 and PU-239/240 in groundwater.
7. . Concentrations
of U-234, U-235 and U-238' in groundwater.
8. Concentrations of Fe-55 in groundwater.
9. .Concentrations of Ni-63 in groundwater.
10.. *Concentrations.
of Gross Alpha and Gross Beta (Dissolved and Suspended) in groundwater.
8: Data Interpretation
1.
Lower Limit of Detection and Minimum Detectable Concentration
The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.
2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value. Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence.
The convention is to report results with a 95% level of confidence.
The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of-a measurement created by statistical process (counting error). Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR. Gamma spectroscopy results for each type of sample were grouped as follows: For groundwater, surface water, and storm water 13 nuclides, 8e-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, 8a-140 and La-140 were reported.
The radio-analytical laboratory is counting tritium results to an LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 -240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from b.ackground at this
.. IV. Results and Discussion A. Groundwater Results Samples were collected from on and off-site wells in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below. Tritium Samples from 58 locations were analyzed for tritium activity.
Tritium values ranged from the detection limit to 37,200 pCi/L (Table 8-1.1, Appendix 8). *
Tritium Split Samples Tritium values ranged from *143 to 952 pCi/L (Table C-1.1, Appendix C). Strontium Strontium-89 and strontium-90 were not detected above their required detection limit of 10 and 1.0 pCi/L, respectively (Table
B-1.1, Appendix B). Strontium Split Samples Strontium-89 and Strontium-90 were not detected above the required detection limit (Table C-1.1, Appendix C). Gross Alpha and Gross Beta (dissolved and suspended)
Gross Alpha and:Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during th_e quarter sampling in 2015. Gross Alpha (dissolved) was not detected at any of the groundwater locations.
Gross Alpha* (suspe'nded) was detected at two of 25 groundwater locations.
The concentrations ranged from 1.9 to 6.9 pCi/L. Gross Beta (dissolved) was dete.cted at 25 of 25 groundwater locations.
The concentrations ranged from 1.5 to 11.0 pCi/L. Gross Beta (suspended) was not detected in any of the 25 groundwater locations. (Table B-1.1, Appendix B). Gross Alpha and Gross Beta Split Samp.les Two split samples were analyzed for Gross Alpha and Gross Beta iri 2015. Gross Alpha was .not detected at either groundwater location.
Gross beta was detected in one sample analyzed.
The concentration was 2.5 pCi/L (Table C-1.3, Appendix C). Gamma Emitters Potassium-40 was detected in three of 63 samples with concentrations ranging from 74 pCi/L to 139 pCi/L. No other gamma-emitting nuclides were detected (Table B-1.2, Appendix B). Gamma Emitters Split Samples Five locations were analyzed for gamma-emitting nuclides in 2015. Potassium-40 was detected in one of five samples with a concentration of 94 pCi/L. No other gamma-emitting nuclides were . detected in any split samples C-1.2, Appendix C).
Hard-To-Detect Hard-To-Detect analyses, .which include Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238, were not analyzed in 2015 {Table B-1.3, Appendix B). Hard-To-Detect Split Samples Hard to detects were not analyzed on any split samples in 2015 (Table C-1.3, Appendix C). B. Surface Water Results Samples were collected from surface water locations in accordance
with the station radiologica*I groundwater protection program. Analytical results and anomalies are discussed below. Tritium Three locations were analyzed for tritium in 2015. Tritium was not . detected above the* required detection limit of 200 pCi/L in any of . the 13 samples analyzed (Table B-11.1, Appendix B). Tritium Split Samples One location was analyzed for tritium iii 2015. Tritium was not detected above the required detection limit of 200 pCi/L in the. *sample analyzed (Table C-IL 1, Appendix C). Gamma Emitters Three locations were analyzed for gamma-emitting nuclides in 2015. None of the three samples detected gamma-emitting nuclides {Table B-11.2, Appendix B).-* Gamma Emitters Split Samples Surface water samples were not analyzed for gamma-emitting*
nuclides in 2015 {Table C-11.2, Appendix C). ' . C. Storm WaterHesults Samples were collected from *storm water locations in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.
Tritium One location was analyzed for tritium. Tritium was detected in two . *of four samples above the required detection limit of 200 pCi/L at concentrations of 316 and 424 pCi/L (Table B-111.1, Appendix B). Gamma Emitters Samples from one location were analyzed for gamma-emitting nuclides.
No gamma emitting nuclide? were detected (Table* B-111.2, Appendix B). D. Precipitation Water Results Samples were collected at six locations.
The following analyses were* performed:
Tritium .Samples from six locations were analyzed for tritium activity .. Tritium .activity was detected five of six locations, The concentrations ranged.from
.192 to 8, 170 pCi/L (Table B-IV.1, Appendix B). Tritium Split Samples Samples fron:i one location were analyzed for tritium activity.
Tritium . activity was detected in :two of four samples. The concentrations ranged from235 to 1.,073 pCi/L (Table C-111.1, Appendix C). Gamma Emitters Precipitation water was not analyzed for Gamma Emitters in 2015. Gamma Emitters Split Samples No gamma-emitting nuclides were analyzed in 2015. E. Leaks, Spills, and Releases ' ' A potential leak was identified at TMI in 2012 due to elevated MS-22 tritium concentration readings.
TMI continues to monitor MS-22 and surrounding wells, .in addition to tritium plumes from previous years, and reports the activity and dose to the public in the ARERR. The elevated MS-22 well tritium concentrations were voluntarily repo.rted under the reporti.ng requirements for the NEI Groundwater Protection Initiative (GPI) as implemented in Exelon's Reportability procedure LS-AA-1120, RAD 1.34 ( IR 1385497/1515261
). In May and June 2015, it was determined that multiple Borated Water Storage Tank (BWST) connections (10 of 13 bolted flange connections) had evidence of leakage in the form of boron deposits in addition to the main 24-inch flange (IR 1670674/2427517/2508405/2509685).
F. Actions Taken 1. Compensatory/Corrective Actions Fully encapsulating enclosures were installed around all BWST connections including the 24-inch main outlet flange. Each enclosure was fitted with a tygon tubing discharge point, connected to a water collection bottle to prevent tritiated water from reaching the ground surface. The outlet flange and leaking connections were repaired during the TMI refueling outage in November 2015. TMI has an extensive groundwater monitoring program with over 50 monitoring wells. No monitoring wells outside the BWST investigation area have seen elevated tritium concentrations.
TMI continues to monitor the BWST area wells closely. The leakage has been mitigated by repairing the leaking flanges.
Intentionally left blank APPENDIX A LOCATION DESIGNATION
& DISTANCE Intentionally left blank TABLEA-1:
Site #3 48N 48S E1-2 EOC8 GP-12 GP-6 GP-8 GP-9 MS-1 MS-19 MS-2 MS-20 MS-21 MS-22 MS-3 MS-4 MS-5 MS-6 MS-7 MS-8 MW-1 MW-2 MW-3 MW-4 N2-1 NW-A NW-8 NW-C NW-CW OS-138 OS-14 OS-16 OS-17 OS-18 OSF RW-1 RW-2 SW-E-1 SW-E-2 SW-E-3 MW-TMl-9S*
MW-TMl-100 MW-TMl-101
MW-TMl-10S MW-TMl-11S*
MW-TMl-128 MW-TMl-131 MW-TMl-13S MW-TMl-140 MW-TMl-141 MW-TMl-14S MW-TMl-160 MW-TMl-161 MW-TMl-170 MW-TMl-171 MW-TMl-180 MW-TMl-190 MW-TMl-191 MW-TMl-10 MW-TMl-200**
Radiological Groundwater"Protection Program -Sampling Locations and Distance, Three MileJsland Nuclear Station, 2015 Site Type Monitoring Well Monitoring Well Production Potable Well Monitoring Well, Offsite Storm Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring.
Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well, Offsite Production Well Production Well Production Well Clearwell Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Production Potable Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well A-1 TABLE A-1: Site MW-TMl-20I**
MW-TMl-210**
MW-TMl-211**
MW-TMl-21S**
MW-TMl-220**
MW-TMl-221**
MW-TMl-22S**
MW-TMl-20 MW-TMl-31 MW-TMl-41 MW-TMl-4S MW-TMl-50 MW-TMl-60 MW-TMl-61 MW-TMl-7S MW-TM I-BS MW-TMl-91 MW-TMl-9S TRAINING CENTER TM-PR-ESE TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-20 TM-PR-MS-22 TM-PR-MS-4 TM-PR-NW-B Radiological Groundwater Protection Program -Sampling Locations and Distance, Three Mile Island Nuclear Station, 2015 Site Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Offsite Monitoring Well Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water
NO WATER PRESENT TO SAMPLE **NEW WELLS INSTALLED 2014 A-2 Q p L N t R J ...... ..........
'**'ooF H* B H
Ol.Tt' 0 2/03/15 .,.._, Figure A-1 *-0::: co c:: c:: co a: RGPP Groundwater Sampling Locations at Three Mile Island Nuclear Station Sampling Locations at the Three Mile Island Nuclear Station, 2015 A-3 Intentionally left blank APPENDIX B DATA TABLES Intentionally left blank TABLE B-1.1 . CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015
RESULTS.IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr"A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) < 48S 04/17/15 < 194 < 7.7 < 0.7 < 6.4 < 0.5 4.1 +/- 1.5 < 1.5 48S 07/28/15 < 187 48S 10/06/15 Original 397 +/- 140 48S 10/06/15 Recount 387 +/- 135 48S 10/06/15 Reanalysis 311 +/- 137 MS-1 01/29/15 < 187 MS-1 04/23/15 < 197 < 6.9 < 0.6 < 4.6 < 0.5 4.8 +/- 2.8 < 1.5 MS-1 07/28/15 < 190 MS-1 10/06/15 Original 326 +/- 136 MS-1 10/06/15 Recount 276 +/-. 132 MS-1 10/06/15 Reanalysis 311 +/- 131 MS-2 01/28/15 < 186 MS-2 04/22/15 328 +/- 141 < 6.4 < 0.6 < 1.1 < 0.7* 2.8 +/- 0.8 < 1.6 MS-2 07/28/15 280 +/- 133 MS-2 10/06/15 203 +/- 128 MS-20 01/27/15 495 +/- 142 MS-20 02/26/15 456 +/- 140 MS-20 04/21/15 57.8 +/- 152 < 5.8 < 0.7 < 1.9 < 0.7 6.6 +/- 1.2 < 2.2. MS-20 07/27/15 384 +/- 141 MS-20 07/27/15 453 +/- 148 MS-20 10/06/15 425 +/- 139 MS-21 01/27/15 < 153 MS-21 01/27/15 < 187 MS-21 04/21/15 < 189 < 5.5 < 0.6 < 0.8 < 0.5 2.0 +/- 0.7 < 1.5 MS-21 07/27/15 < 199 MS-21 10/07/15 < 195 MS-21 10/07/15 < 196 MS-22 01/27/15 1330 +/- 189 MS-22 02/03/15 6060 +/- 645 MS-22 02/12/15 10200 +/- 1060 MS-22 02/18/15 11100 +/- 1150 MS-22 03/10/15 2370 +/- 289 MS-22 03/25/15 9110 +/- 957 MS-22 04/09/15 16900 +/- 1720 MS-22 04/21/15 15600 +/- 1610 < 7.0 < 0.9 < 0.6 < 0.5 6.0 +/- 1'.0 < 1.6 MS-22 05/07/15 17800 +/- 1830 MS-22 05/21/15 14700 +/- 1510 MS-22 06/02/15 14500 +/- 1490 MS-22 06/16/15 Original 6990 +/- 753 06/16/15 Recount 7370 +/- 786 MS-22 06/16/15 Reanalysis 7250 +/- 764 MS-22 06/30/15 2250 +/- 274 MS-22 07/16/15 5230 +/- 556 MS-22 07/27/15 7980 +/- 850 MS-22 08/11/15 Original 8560 +/- 887 MS-22 08/11/15 Recount 8330 +/- 885 MS-22 08/11/15 Reanalysis 7650 +/- 815 MS-22 08/25/15 Original 2940 +/- 346 MS-22 08/25/15 Recount 2580 +/- 318 08/25/15 Reanalysis 2420 +/- 302 MS-22 09/09/15 Original 6960 +/- 750 MS-22 09/09/15 Recount 6850 +/- 730 MS-22 09/21/15 2830 +/- 338 MS-22 10/05/15 Original 720 +/- 149 MS-22 10/05/15 Recount 710 +/- 156 B-1 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus) MS-22 10/05/15 Reanalysis 609 +/- 147 MS-22 10/20/15 Original 3300 +/- 387 MS-22 10/20/15 Recount 3700 +/- 428 MS-22 11/17/15 2500 +/- 307 MS-22 12/04/15 4270 +/- 480 MS-22 12/21/15 3850 +/- 443 MS-3 01/28/15 306 +/- 114 MS-3 04/22/15 347 +/- 143 < 6.1 < 0.5 < 1.5 < 0.7 10.1 +/- 1.3 < 1.6 MS-3 07/28/15 279 +/- 131 MS-3 10/06/15 225 +/- 131 MS-4 04/22/15 261 +/- 137 MS-5 01/28/15 < 185 MS-5 04/22/15 < 200 < 8.5 < 1.0 < 1.4 < 0.5 7.0 +/- 1.2 < 1.5 MS-5
< 193 MS-5 10/06/15 < 192 MS-7 01/29/15 < 188 MS-7 04/22/15 < 196 < 5.5 < 0.6 < 1.1 < 0.5 4.6 +/- 1.0 < 1.5 MS-7 07/28/15 < 187 MS-7 10/06/15 < 194 MS-7 10/06/15 Original 206 +/- 131 MS-7 10/06/15 Recount 205 +/- 125 MS-7 10/06/15 Reanalysis 204 +/- 131 MS-8 01/27/15 < 188 MS-8 04/22/15 260 +/- 131 < 5.5 < 0.5 < 1.1 6.9 +/- 1.6 4.0 +/- 0.8 < 4.1 MS-8 07/28/15 < 185 MS-8 10/06/15 < 189 MW-1 04/21/15 < 194 MW-2 04/21/15 < 194 MW-TMl-10D 04/22/15 336 +/- 139 MW-TMl-101 01/29/15 779 +/- 158 MW-TMl-101 04/22/15 903 +/- 170 MW-TMl-101 04/22/15 1000 +/- 175 MW-TMl-101 07/28/15 793 +/- 158 MW-TMl-101 10/07/15 691 +/- 151 MW-TMl-101 10/07/15 576 +/- 148 MW-TMl-10S 01/29/15 1470 +/- 202 MW-TMl-10S 04/22/15 1260 +/- 189 < 6.0 < 0.6 < 1.4 < 0.5 6.8 +/- 1.3 < 1.5 MW-TMl-10S 07/29/15 1540 +/- 216 MW-TMl-10S 10/07/15 1410 +/- 209 MW-TMl-12S 01/28/15 < 162 MW-TMl-12S 04/22/15 < 195 < 6.2 < 0.6 < 0.9 < 0.5 5.6 +/- 0.9 < 1.5 MW-TMl-12S 07/28/15 < 192 MW-TMl-12S 10/07/15 < 193 MW-TMl-131 01/29/15 < 188 MW-TMl-131 04/21/15 < 194 MW-TMl-131 07/28/15 < 189 MW-TMl-131 10/06/15 < 196 MW-TMl-14D 01/29/15 251 +/- 129 MW-TMl-14D 01/29/15 262 +/- 131 MW-TMl-14D 04/21/15 253 +/- 136 MW-TMl-14D 07/28/15 333 +/- 135 MW-TMl-14D 10/07/15 367 +/- 138 MW-TMl-14D 10/07/15 329 +/- 134 MW-TMl-141 01/29/15 < 178 MW-TMl-141 04/21/15 286 +/- 137 MW-TMl.-141 07/28/15 209 +/- 126 B-2
TABLE SITE MW-TMl-141 MW-TMl-141 MW-TMl-160 MW-TMl-171 MW-TMl-180 MW-TMl-191 MW-TMl-10 MW-TMl-201
MW-TMl-201 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl"21D MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-210 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211
MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-211
MW-TMl-211 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND* NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) 07/28/15 231 +/- 131 10/07/15 287 +/- 134 04/23/15 595 +/- 154 04/23/15 < 191 04/21/15 286 +/- 135 04/22/15 < 197 04/21/15 247 +/- 136 04/22/15 445 +/- 148 04/22/15 415 +/- 144 01/27/15 3890 +/- 431 02/03/15 4440 +/- 483 02/12/15 3410 +/- 382 02/18/15 4210 +/- 466 02/26/15 4240 +/- 470 03/10/15 4210 +/- 469 03/25/15 4260 +/- 474 04/09/15 4670 +/- 514 04/21/15 4540 +/- 503 05/07/15 3980 +/- 441 05/21/15 5210 +/- 559 06/02/15 4840 +/- 535 06/16/15 4440 +/- 499 06/30/15 5240 +/- 567 07/16/15 4690 +/- 503 07/27/15 4740 +/- 527 08/11/15 5660 +/- 599 08/25/15 5620 +/- 611 09/09/15 5440 +/- 597 09/21/15 4930 +/- 545 10/05/15 5040 +/- 550 10/20/15 5130 +/- 568 11/17/15 6240 +/- 675 12/04115 5750 +/- 628 12/21/15 5260 +/- 583 01/27/15 8500 +/- 891 02/03/15 7800 +/- 815 02/12/15 5930 +/- 631 02/18/15 5190 +/- 564 02/26/15 8820 +/- 926 03/10/15 10700 +/- 1120 03/25/15 8540 +/- 900 04/09/15 8200 +/- 864 04/21/15 10200 +/- 1060 05/07/15 6720 +/- 713 05/21/15 5270 +/- 569 06/02/15 5140 +/- 566 06/16/15 3900 +/- 446 06/30/15 4600 +/- 499 07/:16/15 6700 +/- 702 07/27/15 6040 +/- 656 08/11/15 6230 +/- 656 08/25/15 5780 +/- 626 09/09/15 5770 +/- 630 09/21/15.
5750 +/- 629 10/05/15 4680 +/- 513 10/20/15 4750 +/- 529 B-3 Gr-B (Sus)
TABLE B-1.1 SITE MW-TMl-211 MW-TMl-211 MW-TMl-211 MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S MW-TMJ-21S MW-TMl-21S
MW-TMl-21S MW-TMl-218 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMJ-220 MW-TMJ-220 MW-TMJ-220
MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMl-220 MW-TMJ-220
MW-TMl-220 MW-TMlc22D MW-TMl-220 MW-TMl-220
MW-TMJ-220 MW-TMl-220 MW-TMJ-220 MW-TMl-220 MW-TMJ-220 MW-TMl-220 MW-TMl-221 MW-TMl-221 MW-TMJ-221 CONCENTRATIONS OF*TRITIUM, STRONTIUM, GROSS ALPHA'AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION DATE
H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) 11/17/15 5120 +/- 564 12/Q4/15 5520 +/- 604 12/21/15 4430 +/- 500 01/27/15 692 +/- 151 02/03/15 648 +/- 147 02/12/15 544 +/- 132 02/18/15 489 +/- 144 02/26/15 6580 +/- 702 03/10/15 527 +/- 142 03/25/15 521 +/- 142 04/09/15 658 +/- 152 04/21/15 753 +/- 158 < 8.0 < 0.8 < 0.8 < 0.5 11.0 +/- 1.5 05/07/15 647 +/- 142 05/21/15 678 +/- 148 06/02/15 310 +/- 139 06/16/15 500 +/- 147 06/30/15 491 +/- 141 07/16/15 677 +/- 135 07/27/15 476 +/- 144 08/11/15 624 +/- 127 08/25/15 580 +/- 140 09/09/15 675 +/- 151 09/21/15 451 +/- 144 10/05/15 431 +/- 133 10/20/15 614 +/- 147 11/17/15 728 +/- 154 12/04/15 548 +/- 143 12/21/15 937 +/- 164 01/27/15 4990 +/- 543 02/03/15 5900 +/- 627 02/12/15 4070 +/- 446 02/18/15 5760 +/- 621 02/26/15 5590 +/- 602 03/10/15 5070 +/- 553 03/25/15 4780 +/- 526 04/09/15 7390 +/- 784 04/21/15 6050 +/- 650 05/07/15 5320 +/- 574 05/21/15 5160 +/- 556 06/02/15 8600 +/- 909 06/16/15 6870 +/- 740 06/30/15 6920 +/- 747 07/16/15 7130 +/- 745 07/27/15 7260 +/- 777 08/11/15 7060 +/- 738 08/25/15 7210 +/- 769 09/09/15 8300 +/- 882 09/21/15 7340 +/- 782 10/05/15 6540 +/- 696 10/20/15 7340 +/- 787 11/17/15 5630 +/- 615 12/04/15 6070 +/- 659 12/21/15 4380 +/- 496 01/27/15 8420 +/- 883 02/03/15 8990 +/- 937 02/12/15 8080 +/- 844 B-4 Gr-8 (Sus) < 1.6 TABLE. B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) MW-TMl-221 02/18/15 9470 +/- 991 MW-TMl-221 02/26/15 11300 +/- 1170 MW-TMl-221 03/10/15 9290 +/- 973 MW-TMl-221 03/25/15 8680 +/- 914 MW-TMl-221 04/09/15 11400 +/- 1190 MW-TMl-221 04/21/15 Original 19500 +/- 1990 MW-TMl-221 . 04/21/15 Reanalysis 16200 +/- 1660 MW-TMl-221 05/07/15 24500 +/- 2480 MW-TMl-221 05/21/15 27400 +/- 2770 MW-TMl-221 06/02/15 26000 +/- 2640 MW-TMl-221 06/16/15 23400 +/- 2380 MW-TMl-221 06/30/15 21900 +/- 2240 MW-TMl-221 07/16/15 21200 +/- 2150 MW-TMl-221 07/27/15 22900 +/- 2340 MW-TMl-221 08/11/15 23400 +/- 2370 MW-TMl-221 08/25/15 21700 +/- 2190 MW-TMl-221 09/09/15 23100 +/- 2360 MW-TMl-221 09/21/15 19000 +/- 1950 MW-TMl-221 10/05/15 17000 +/- 1730 MW-TMl-221 10/20/15 17700 +/- 1820 MW-TMl-221 10/20/15 18500 +/- 1900 MW-TMl-221 11/17/15 21200 +/- 2160 MW-TMl-221 12/04/15 18500 +/- 1890 MW-TMl-221 12/21/15 17000 +/- 1750 MW-TMl-22S 01/27/15 16600 +/- 1690 MW-TMl-22S 01/29/15 28200 +/- 2850 MW-TMl-22S 02/03/15 23100 +/- 2350 MW-TMl-22S 02/12/15 24700 +/- 2500 MW-TMl-22S 02/18/15 25500 +/- 2580 MW-TMl-22S 02/26/15 8560 +/- 897 MW-TMl-22S 03/10/15 11000 +/- 1140 MW-TMl-22S 03/25/15 6150 +/- 659 . MW"TMl-22S 04/09/15 27000 +/- 2740 MW-TMl-22S 04/21/15 Original 37200 +/- 3740 < 6.5 < 0.6 < 1.5 < 0.5 8.0 +/- 1.4 < 1.6 MW-TMl-22S 04/21/15 Reanalysis 36900 +/- 3710 MW-TMl-22S 05/07/15 30300 +/- 3070 MW-TMl-22S 05/21/15 5580 +/- 599 MW-TMl-22S 06/02/15 8010 +/- 852 MW-TMl-22S 06/16/15 7610 +/- 812 MW-TMl-22S 06/30/15 Original 15400 +/- 1590 MW-TMl-22S 06/30/15 Recount 14600 +/- 1510 MW-TMl-22S 06/30/15 Reanalysis 14900 +/- 1530 MW-TMl-22S 07/16/15 7560 +/- 788 MW-TMl-22S 07/27/15 13500 +/- 1400 MW-TMlc22S 08/11/15 14000 +/- 1430 MW-TMl-22S 08/25/15 12600 +/- 1290 MW-TMl-22S 09/09/15 14500 +/- 1500 MW-TMl-22S 09/21/15 10900 +/- 1130 MW-TMl-22S 10/05/15 8780 +/- 921 MW-TMl-22S 10/20/15 7720 +/- 824 MW-TMl-22S 11/17/15 6380 +/- 689 MW-TMl-22S 12/04/15 6170 +/- 668 MW-TMl-22S 12/21/15 5470 +/- 602 B-5 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus) MW-TMl-2D 04/21115 206 +/- 134 MW-TMl-2D 04/21/15 274 +/- 135 MW-TMl-31 01/29/15 < 186 MW-TMl-31 04/23/15 < 199 < 6.6 < 0.6 < 2.1 < 0.7 6.8 +/- 1.6 < 1.6 MW-TMl-31 04/23/15 < 194 < 7.0 < 0.6 < 2.0 < 0.7 6.8 +/- 1.6 < 1.6 MW-TMl-31 07/29/15 < 191 MW-TMl-31 10/07/15 Original 251 +/- 131 MW-TMl-31 10/07/15 Recount 220 +/- 128 MW-TMl-31 10/07/15 Reanalysis 279 +/- 139 MW-TMl-41 04/23/15 < 198 MW-TMl-4S 04/22/15 < 199 MW-TMl-6D 01/29/15 < 189 MW-TMl-6D 04/22/15 < 186 < 4.2 < o.5 < 1.6 < 0.5 2.9 +/- 0.9 < 1.5 MW-TMl-6D 07/28/15 < 190 MW-TMl-6D 10/06/15 < 188 MW-TMl-61 01/29/15 < 184 MW-TMl-61 01/29/15 < 185 MW-TMl-61 04/22/15 < 189 < 7.1 < 0.6 < 1.3 1.9 +/- 1.0 3.6 +/- 1.1 < 2.0 MW-TMl-61 07/28/15 < 190 MW-TMl-61 10/06/15 < 194 MW-TMl-7S 04/22/15 < 199 MW-TMl-8S 04/21/15 < 191 MW-TMl-91 04/21/15 < 196 MW-TMl-91 04/21/15 217 +/- 131 N2-1 04/20/15 < 195 NW-A 01/29/15 870 +/- 159 NW-A 04/23/15 1290 +/- 186 < 4.3 < 0.6 < 0.8 < 0.6 3.8 +/- 0.9 < 1.5 NW-A 07/28/15 1000 +/- 169 NW-A 10/06/15 791 +/- 157 NW-B 01/29/15 233 +/- 129 NW-B 04/23/15 319 +/- 133 < 4.3 < 0.6 < 1.0 < 0.6 1.5 +/- 1.0 < 1.5 NW-B 07/28/15 259 +/- 135 NW-B 10/06/15 240 +/- 132 NW-C 01/29/15 911 +/- 164 NW-C 04/23/15 1250 +/- 179 < 5.1 < 0.7 < 0.8 < 0.6 2.4 +/- 0.8 < 1.5 NW-C 07/28/15 1050 +/- 172 NW-C 10/14/15 1110 +/- 177 NW-CW 01/29/15 388 +/- 138 NW-CW 04/17/15 611 +/- 155 < 7.2 < 0.6 < 1.7 < 0.5 1.9 +/- 0.9 < 1.5 NW-CW 07/28/15 671 +/- 154 NW-CW 07/28/15 820 +/- 160 NW-CW 10/06/15 663 +/- 160 OS-14 01/27/15 < 188 OS-14 04/22/15 < 197 < 5.5 < 0.6 < 2.1 < 0.7 10.8 +/- 1.6 < 1.6 B-6 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATE.R SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) OS-14 07/28/15 < 197 OS-14 10/06/15 < 188 OS-16 01/28/15 246 +/- 130 OS-16 04/22/15 382 +/- 143 < 7.8 < 0.6 < 0.9 < 0.7 5.4 +/- 0.8 OS-16 07/28/15 326 +/- 133 OS-16 10/07/15 305 +/- 132 OS-18 04/22/15 258 +/- 134 OSF 01/29/15 332 +/- 134 OSF 04/17/15 376 +/- 146 < 6.5 < 0.7 < 4:8 < 0.5 8.1 +/- 1.8 OSF 07/28/15 269 +/- 131 OSF 10/06/15 282 +/- 133 RW-1 01/28/15 < 178 RW-1 01/28/15 < 164 RW-1 04/21/15 < 193 < 8.5 < 0.7 < 0.8 < 0.7 10.5 +/- 1.5 RW-1 07/28/15 < 191 RW-1 10/07/15 < 193 TRAINING CENTEF104/20/15
< 190 _; ' B-7 Gr-B (Sus) < 1.6 < 1.5 < 1.6 to I °" TABLE B-1.2 SITE 488 MS-1 MS-2 MS-20 MS-21 MS-22 MS-3 MS-3 MS-3 MS-3 MS-4 MS-5 MS-5 MS-5 MS-5 MS-7 MS-8 MS-8 MS-8 MS-8 MW-1 MW-2 MW-TMl-100 MW-Tlllil-108 MW-TMl-128 MW-TMl-160 MW-TMl-171 MW-TMl-180 MW-TMl-191 MW-TMl-10 MW-TMl-201 MW-TMl-20I MW-TMl-218 MW-TMl-228 MW-TMl-20 MW-TMl-20 MW-TMl-31 MW-TMl-31 MW-TMl-41 MW-TMl-48 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTIOI\
Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 .,Ba-140 La-140 04/17/15 04/23/15 04/22/15 04/21/15 04/21/15 04/21/15 01/28/15 04/22/15 07/28/15 10/06/15 04/22/15 01/28/15 04/22/15 07/28/15 10/06/15 04/22/15 01/27/15 04/22/15 07/28/15 10/06/15 04/21/15 04/21/15 04/22/15 04/22/15 04/22/15 04/23/15 04/23/15 04/21/15 04/22/15 04/21/15 04/22/15 04/22/15 Q4/21/15 04/21/15 04/21/15 04/21/15 04/23/15 04/23/15 04/23/15 04/22/15 < 18 < 43 < 35 < 31 < 35 < 22 < 59 < 40 < 36 < 51 < 45 < 63 < 31 < 29 < 58 < 37 < 44 < 40 < 34 < 44 < 36 < 35 < 33 < 33 < 33 < 53 < 27 < 35 < 39 < 31 < 44 < 43 < 24 < 25 < 31 < 27 < 38 < 41 < 48 < 40 < 17 < 2 < 103 < 5 < 29 < 4 < 51 < 3 < 47 < 3 < 17 < 2 < 138 < 6 < 94 < 4 < 74 < 4 < 35 < 6 < 89 < 5 117 +/- 62 < 7 < 25 < 3 < 28 < 3 < 105 < 7 < 35 < 4 < 52 < 5 < 41 < 4 < 29 < 4 < 81 < 4 < 34 < 4 < 36 < 4 < 42 < 4 < 38 < 4 < 72 < 3 < 48 < 6 < 27 < 3 < 54 < 3 < 73 < 4 < 50 < 3 < 42 < 4 139 +/- 90 < 5 74 +/- 33 < 2 < 48 < 2 < 28 < 3 < 25 < 3 < 37 < 4 < 95 < 4 < 41 < 5 < 71 < 4 <2 < 5 <4 <4 <4 < 3 < 7 <4 <4 < 5 < 5 < 7 <4
<4 < 7 <4 <4 <4 <4 < 3 <4 < 3 <3 <4 < 3 <6 < 3 <4 < 5 < 3 < 5 < 5 < 2 < 3 < 3 < 3 < 5 <4 < 5 <4 < 4 < 9 < 8 < 9 < 8 < 5 < 14 < 9 <7 < 8 < 11 < 13 < 6 < 8 < 15 < 9 < 11 < 10 < 7 < 8 < 9 < 7 < 8 < 9 < 7 < 13 < 7 < 8 < 10 < 6 < 10 < 10 < 5 < 7 <7 < 6 < 10 < 8 < 12 < 9 < 2 <4 <4 < 3 < 3 <2 <6 <4 < 4 <7 < 5 < 6 < 3 <3 < 13 < 4 <3 <4 <4 <4 <4 <4 < 5 <4 <4 < 6 <2
<4
<4 <3 < 5 < 5 <2 < 2 < 3 < 3 <4 <4 < 5 . < 5 < 3 < 8 < 8 < 7 < 7 <4 < 11 < 8 < 9 < 10 < 11 < 14 < 5 <7 < 14 < 7 < 10 < 9 < 7 < 5 <7 < 7 < 8 < 8 < 6 < 11 <6 < 7 < 9 <6 < 9 < 10 <5 < 5 < 6 <5 < 10 < 7 < 11 < 9 < 2 < 5 <4 <4 <4 <2 < 6 <4 <4 < 6 < 5 <7 < 3 < 3 < 8 <4 < 5 '5 5 <4 < 5 < 5 <4 <4 <4 < 3 < 6 < 3 <4 < 5 < 3 < 6 < 5 <2 < 3 <4 < 3 < 5 < 5 < 6 < 5 < 3 < 8 < 7 < 7 < 7 <4 < 11 < 8 <7 <7 < 8 < 12 < 5 < 6 < 14 <7 < 8 < 8 <6 < 9 < 8 <6 < 8 < 7 <6 < 11 < 5 <7 < 8 < 5 < 9* < 9 <4 < 5 < 6 < 6 < 8 < 8 < 10 < 7 < 2 <4 < 3 <3 < 3 < 2 <6 <4 <4 < 6 <4 < 8 < 3 <3 <7 < 3 <4 <4 <4 <4 <4 <4 <4 <3 < 3 < 6 <3 < 3 <4 <3 <4 < 5 < 2 < 2 < 3 <3 <4 <4 <5 <4 . < 2 < 5 <4 <4 < 3 <2 < 7 <4 <4 < 5 < 6 < 7 < 3 < 3 < 7 <4 < 5 < 5 < 3 < 6 <4 <4 <4 <4 <4 <6 <4
<4 <4 < 3 < 5 <4 < 2 < 3 < 3 < 3 <4 <4 <6 <4 < 16 < 27 < 23 < 25 < 26 <<21 < 33 < 31 -< 22 < 31 < 31 < 38 _< 21 < 19 < 32 < 27 < 26 < 33 < 21 < 20 < 30 < 27 < 28 < 24 < 24 < 34 < 23 < 29 < 28 < 23 < 32 < 32 < 23 < 26 < 22 < 23 < 32 < 30 < 36 < 28 < 5 < 11 < 9 < 8 < 7 < 8 < 12 < 9 < 7 < 8 < 11 <* 11 <_6 < 6 < 14 <7 < 8 < 9 < 6 < 8 < 9 < 6 < 8 < 7 <7 < 11 < 6 < 11 < 10 < 8 < 12 < 12 < 7 < 9 <7 < 7 < 11 < 9 < 11 < 11 TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTIOI\
Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 MW-TMl-60 04/22/15 MW-TMl-61 04/22/15 MW-TMl-78 04/22/15 MW-TMl-88 04/21/15 MW-TMl-91 04/21/15 MW-TMl-91 04/21/15 N2-1 04/20/15 NW-A 04/23/15 NW-B 04/23/15 NW-C 04/23/15 NW-CW 04/17/15 OS-14 01/27/15 OS-14 04/22/15 OS-14 07/28/15 OS-14 10/06/15 OS-16 01/28/15 OS-16 04/22/15 OS-16 07/28/15 OS-16 10/07/15 OS-18 04/22/15 OSF 04/17/15 RW-1 04/21/15 TRAINING CENTER 04/20/15 < 39 < 33 < 33 < 26 < 27 < 30 < 37 < 9 < 11 < 7 < 20 < 49 < 39 < 41 < 51 < 45 < 33 < 28 < 54 < 39 < 18 < 32 < 32 < 74 < 68 < 27 < 43 < 21 < 65 < 38 < 19 < 8 < 5 < 19 < 59 < 44 < 50 < 107 < 47 < 34 < 34 < 131 < 66 < 17 < 31 < 26 < 5 < 3 < 3 < 3 < 2 < 3 <4 < 1 < 1 < 1 <2 < 6 < 3 < 5 < 5 < 6 < 3 < 3 <6 <4 <2 < 3 < 3 <4 <4 < 3 < 3 < 2 < 3 <4 < 1 < 1 < 1 < 2 < 6 <4 < 5 < 6 < 5 <4 < 3 < 7 <4 <2 <4 < 3 < 9 < 9 <7 < 6 < 7 < 7 < 7 <2 <2 <2 < 5 < 13 < 9 < 11 < 12 < 9 < 8 < 6 < 14 <.9 <5 < 8 < 8 <'4 < 3 < 3 < 2 < 2 < 3 <4 < 1 < 1 < 1 < 2 < 5 <4 < 5 < 5 <-5 <4 <3 <7 < 5 < 2 <4 < 3 < 8 <7 < 6 <4 < 5 < 6 < 9 < 1 <2 < 1 <4 < 12 < 8 < 12 < 8 < 8 < 8 < 6 < 13 < 7 <4 < 7 < 6 <4 <4 <4 < 3 < 2 < 3 < 5 < 1 < 1 < 1 < 2 < 7 < 5 < 5 < 6 < 5 <4 < 3 < 6 < 5 < 2 <4 < 3 <7 <7 < 6 <4 <4 <6 < 8 <2 <2 < 1 <4 < 10 < 8 < 9 < 7 < 8 <7 <6 < 11 < 8 <4 < 7 < 6 <4 <4 < 3 < 3 <2 <3 <4 < 1 < 1 < 1 < 2 < 6 <4
<4 < 5 < 5 < 3 < 3 < 6 <4 <2 < 3 < 3 <4 <4 <4 <2 < 3 < 3 <4 < 1 < 1 < 1 < 2 < 6 <4 < 5 < 5 < 5 <4 < 3 < 6 <4 <2 <4 < 3 < 27 < 24 < 29 < 21 < 23 < 25 < 29 < 14 < 18 < 14 < 18 < 30 < 31 < 26 < 23 < 26 < 27 < 19 < 28 < 28 < 16 < 31 < 22 < 9 < 7 < 8 < 7 <6 < 8 < 9 <5 <4 <4 < 6 < 9 < 8 < 9 < 7 <6 < 9 <6 < 9 < 8 < 5 < 10 < 8 ttl I ...... 0 TABLE B-1.3 CONCENTRATiONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 SITE RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 There were no hard to detect analyses analyzed in 2015 U-235 U-238 Fe-55 Ni-63 TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-1 01/28/15 < 184 SW-E-1 04/21/15 < 192 SW-E-1 07/29/15 < 195 SW-E-1 10/07/15 < 192 SW-E-2 01/28/15 < 184 SW-E-2 04/21/15 < 192 SW-E-2 07/29/15 < 193 SW-E-2 07/29/15 < 190 SW-E-2 10/07/15 < 196 SW-E-3 01/28/15 < 184 SW-E-3 04/21/15 < 194 SW-E-3 07/29/15 < 191 SW-E-3 10/07/15 < 195 B-11 TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE SW-E-1 04/21/15 < 34 < 33 <3 < 3 < 9 <4 < 8 <4 < 7 < 3 < 3 <
25 < 9 SW-E-2 04/21/15 < 37 < 24 < 3 <4 < 7 < 3 <6 <4 < 7 <4 <4 < 28 < 6 SW-E-3 04/21/15 < 43 < 35 <4 <4 < 8 <4 < 9 < 5 < 7
<4 < 5 < 31 < 9 t:t:I I -N TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 EDCB 02/06/15 424 +/- 146 EDCB 04/28/15 < 189 EDCB 07/28/15 < 186 EDCB 11/03/15 316 +/- 135 B-13 TABLE B-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE EDCB 02/06/15 < 32 < 59 <4 < 3 < 7 <4 < 6 <4 < 6 <4 <4 < 28 < 9 EDCB 04/28/15 < 31 < 90 < 5 < 5 <
11 < 4 < 8 . < 6 < 10 <4 < 5 < 33 < 5 EDCB 07/28/15 < 97 < 221 < 9 < 9 <
19 < 10 < 18 < 9 < 14 < 11 < 9 < 35 < 12 EDCB 11/03/15 < 45 < 87 < 6 < 6 <
12 < 6 < 14 < 5 < 9 < 5
<6 < 29 < 9 TABLE B-IV.1 SITE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE; TM-PR-ESE TM-PR-ESE TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-22 TM-PR-MS-22 TM-PR-MS-22 TM-PR-MS-4 TM-PR-MS-4
TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MW"22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S
TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S TM-PR-MW-22S CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION DATE H-3 03/09/15 380 +/- 135 05/11/15 266 +/- 130 07/20/15 < 181 10/09/15 Original 1290 +/- 193 10/09/15 Recount 1310 +/- 203 10/09/15 Rerun 1220 +/- 186 03/09/15 < 183 05/11/15 < 183 07/20/15 < 179 10/09/15 < 187 03/09/15 401 +/- 134 05/11/15 < 186 07/20/15 < 178 10/09/15 Original 1220 +/- 186 10/09/15 Recount 988 +/- 172 10/09/15 Rerun 908 +/- 162 05/07/15 Original 3110 +/- 355 05/07/15 Rerun 3260 +/- 370 05/07/15 Rerun/recount 2770 +/- 321 03/09/15 373 +/- 133 05/11/15 .192 +/- 125 07/20/15 < 178 10/09/15 Original 544 +/- 142 10/09/15 Recount 466 +/- 144 10/09/15 Rerun 637 +/- 154 05/21/15 560 +/- 146 06/02/15 461 +/- 144 06/16/15 < 175 06/30/15 1270,+/- 182 07/16/15 Original 2640 +/- 322 07/16/15 Recount 3140 +/- 367 07/16/15 Rerun/recount 3110 +/- 369 07/27/15 5940 +/- 644 08/11/15 Original < 185 08/11/15 Recount < 190 08/11/15 Rerun < 197 08/25/15 823 +/- 161 09/21/15 665 +/- 155 10/05/15 650 +/- 153 10/20/15 256 +/- 131 11/17/15 Original 7680 +/- 819 11/17/15 Recount 8020 +/- 854 11/17/15 Rerun 8170 +/- 870 12/04/15 2970 +/- 354 12/21/15 4110 +/-474 B-15 Intentionally left blank APPENDIX C DATA TABLES-COMPARISON TABLE C-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A Gr-B MS-20 07/27/15 484 +/- 101 MS-21 01/27/15 222 +/- 104 MS-21 10/07/15 186 +/- 81 MS-7 10/06/15 < 149 MW-TMl-10l 04/22/15 952 +/- 120 MW-TMl-10l 10/07/15 580 +/- 99 MW-TMl-140 01/29/15 262 +/- 106 MW-TMl-140 10/07/15 184 +/- 81 MW-TMl-141 07/28/15 143 +/- 86 MW-TMl-201 04/22/15 382 +/- 98 MW-TMl-20 04/21/15 162 +/- 88 MW-TMl-31 04/23/15 243 +/- 92 < 0.5 < 0.4 < 2.4 < 1.6 MW-TMl-61 01/29/15 < 180 MW-TMl-91 04/21/1.5 162 +/- 88 NW-CW 07/28/15 721 +/- 110 OSF 04/17/15 296 +/- 95 < 0.5 < 0.5 < 2.9 2.5 +/- 1.4 RW-1 01/28/15 < 180 C-1 TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER+/-
2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD MW-TMl-201 04/22/15 < 26 94 +/- 50 <4 <4 < 3 < 2 < 5 < 5 < 3 < 2
<2 < 22 < 3 MW-TMl-20 04/21/15 < 35 70 < 3 < 3 <2 < 2 < 7 < 6 < 2 < 2 < 3 < 25 <4 MW-TMl-31 04/23/15 < 30 61 < 2 < 3 <2 < 2 < 3 < 3 < 3 < 2 < 1 <
13 < 4 MW-TMl-91 04/21/15 < 26 43 < 3 < 3 <2 <2 < 4 <4 < 2 <2 < 3 < 20 < 3 OSF 04/17/15 < 29 40 < 2 < 5 < 3 < 1 < 4 < 5 <2 < 2 <2 < 16 <4 n I N
(") I w TABLE C-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-233/234 U-235 U-238 Fe-55 Ni-63 PERIOD NONE FOR 2015 TABLE C-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-2 07/29/15 < 150 C-4 n I Vi TABLE C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD NONE FOR 2015 TABLE C-111.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2015 SITE TM-PR-MS-20 TM-PR-MS-20 TM-PR-MS-20 TM-PR-MS-20 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION DATE 03/30/15 06/24/15 09/02/15 11/16/15 H-3 < 149 235 +/- 83 < 147 1073 +/- 122 C-6

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