TMI-02-066, Submittal of 2011 Radiological Environmental Monitoring Program Report

Submittal of 2011 Radiological Environmental Monitoring Program Report

ML121220224
Person / Time
Site:	Three Mile Island
Issue date:	04/25/2012
From:	Newcomer M Exelon Nuclear, Exelon Generation Co
To:	Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
TMI-02-066
Download: ML121220224 (173)

Text

Exekb-n.

Three Mile Island Unit 1 Telephone 717-948-8000 Nuclear Route 441 South, P.O. Box 480 Middletown, PA 17057 April 25, 2012 TMI-12-066 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION UNIT 1 AND UNIT 2 RENEWED OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR 73 DOCKET NOS. 50-289 AND 50-320

SUBJECT:

2011 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT In accordance with TMI-1 Technical Specification 6.9.3.1, TMI-2 Technical Specifications 6.8.1.1, enclosed is the Annual Radiological Environmental Operating Report covering the time-period of January 1 through December 31, 2011, for the Three Mile Island Nuclear Station.

Please contact Laura Weber of TMI-1 Chemistry at (717) 948-8947 if you have any questions regarding this submittal.

Sincerely, Ma* M. omer Plant Manager MMN/Ikw Attachments/Enclosures cc: Region 1 Administrator TMI Senior Resident Inspector TMI-1 Senior Project Manager TMI-2 Project Manager GPU Nuclear Cognizant Officer Department of Environmental Protection, Bureau of Radiation Protection

Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2011 Prepared By Teledyne Brown Engineering Environmental Services Exelkn.

Nuclear Three Mile Island Nuclear Station Middletown, PA 17057 April 2012

Table Of Contents I. Sum mary and Conclusions .......................................................................................... 1 I1. Introduction ............................................................................................................. 3 A. Objectives of the REM P .................................................................................. 3 B. Im plementation of the Objectives .................................................................. 4 Ill. Program Description ................................................................................................ 4 A. Sam ple Collection ......................................................................................... 4 B. Sam ple Analysis .............................................................................................. 6 C. Data Interpretation ......................................................................................... 7 D. Program Exceptions ....................................................................................... 8 E. Program Changes ......................................................................................... 13 IV. Results and Discussion ......................................................................................... 13 A. Aquatic Environm ent .................................................................................... 13

1. Surface W ater ..................................................................................... 13

2. Drinking W ater .................................................................................. 14

3. Effluent W ater ..................................................................................... 15

4. Storm W ater ....................................................................................... 16

5. Ground W ater ..................................................................................... 16 6 . F is h ................................................................................................... .. 16

7. Sedim ent ............................................................................................ 17 B. Atmospheric Environm ent ........................................................................... 17

1. Airborne Particulates .............................................................................. 17

a. Air Particulates ......................................................................... 17

b. Airborne Iodine ........................................................................ 18

2. Terrestrial ............................................................................................ 18 a . Milk ........................................................................................ . . 18

b. Food Products ........................................................................ 19 C. Am bient Gam ma Radiation ......................................................................... 20 D. Land Use Survey .......................................................................................... 20 E. Radiological Im pact of TM INS Operations ................................................... 21 F. Summary of Results - Inter-laboratory Comparison Program ..................... 29 V . R e fe re n c e s ................................................................................................................... 31

Table C-I1.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-11.2 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-11.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-111.1 Concentrations of Gross Beta, 1-131, Tritium, and Strontium in Effluent Water Samples for Station K1 -1 Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-l11.2 Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-IV.1 Concentrations of Strontium in Predator and Bottom Feeder (Fish)

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

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, 2011.

Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-VI.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-VI.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-VII.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-VIII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-VIII.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-VIII.3 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-IX.1 Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

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SAppendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2011 Appendix B Location Designation, Distance & Direction And Sample Collection &

Analytical Methods Tables Table B-1 Location Designation and Identification System for the Three Mile Island Nuclear Station Table B-2 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2011 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2011 Figures Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2011 Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2011 Figure B-3 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2011 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-1.2 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

ii

Table C-X.1 Quarterly TLD Results for Three Mile Island Nuclear Station, 2011.

Table C-X.2 Mean Quarterly TLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2011.

Table C-X.3 Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2011.

Figures Figure C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2011.

Figure C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2011.

Figure C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2011.

Figure C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2011.

Figure C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2011.

Figure C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2011.

Figure C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2011.

Figure C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2011.

Figure C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2011.

Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-1.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2011.

Table D-1.2 Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table D-1.3 Concentrations of Iodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table D-1.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table D-11.1 Concentrations of Strontium and Gamma Emitters in Fish Samples iv

Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table D-1Il.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table D-IV.1 Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

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, 2011.

Table D-V.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table D-VI.1 Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Figures Figure D-1 Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2011.

Figure D-2 Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2011.

Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011 Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2011 Table E-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2011 Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2011 Table E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2011 Appendix F 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 2011 through 31 December 2011. During that time period, 1,723 analyses were performed on 1,319 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.

On March 11, 2011 an earthquake off the Japanese islands produced a massive tsunami that caused a nuclear accident at four of the six Fukushima Daiichi reactors. In planning for the potential radioactive plume reaching the United States, Exelon Nuclear increased the sampling frequency and added additional analyses of select media from pathways that were expected to be the most sensitive to any increase in ambient radiation levels. Low level 1-131 analyses and gamma spectroscopy analyses were performed on air particulates, air iodine, and milk, as appropriate.

The resulting radioactive plume was first detected in the environs of Three Mile Island Nuclear Station on March 16, 2011. The final date of positive detection was April 13, 2011. The radionuclide identified was Iodine-1 31. Maximum activity levels found by media were 87 E-3 pCi/m 3 for air iodine. Samples collected were compared to offsite control locations to verify that these positive detections were not attributable to licensed activities. All other radionuclides analyzed for were below MDL.

The radioactive half-life of 1-131 is about 8 days. This short half-life allowed the affects of this radioactive plume to subside over about 4 weeks. As of April 14, 2011 no further impacts from the Fukushima Daiichi accident was evident.

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, surface water, precipitation water and storm water results are now being reported in the ARGPPR, Appendix F. No Sr-89 and Sr-90 activities were detected. lodine-131 and gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in nine surface water samples and monthly effluent water samples was due to TMINS activities or releases. No other fission or activation products potentially attributed to TMI liquid releases were detected.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected. No fission or activation products were detected in fish samples. Cesium-1 37 was detected in two sediment samples. Occasionally Cs-1 37 is detected at very low levels (just above LLD) and is not distinguishable from background levels.

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

High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity, with the exception of 19 samples that were positive for 1-131. The positive activity is directly attributed to the Fukushima event in March of 2011.

Cow milk samples were analyzed for concentrations of 1-131, gamma emitting nuclides, Sr-89 and Sr-90. No 1-131 and Sr-89 activities were detected.

Concentrations of naturally occurring K-40 were consistent with those detected in previous years. Sr-90 activities detected were consistent with those detected in previous years and were attributed to fallout from nuclear weapons testing. No other fission or activation products were found.

Food Product samples were analyzed for concentrations of gamma emitting nuclides (including 1-131) and Sr-90. Sr-90 activities were detected in both the indicator and control samples. This was a result of plant uptake of Sr-90 in soil as a result of past nuclear weapons testing. Concentrations of naturally occurring Be-7 and K-40 were consistent with those detected in previous years.

No other fission or activation products were detected.

Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years.

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 2011 were well below applicable dose limits and only a small fraction of the doses received from natural background radiation. Additionally, the results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.

Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2011 did not have any adverse effects on the health of the public or on the environment.

II. Introduction The Three Mile Island Nuclear Station (TMINS), consisting of two pressurized water reactors (PWR), is located on the northern end of Three Mile Island in the Susquehanna River approximately 2.5 miles south of Middletown in Londonderry Township, Dauphin County, Pennsylvania. TMI-1 is owned and operated by Exelon and became operational in 1974. TMI-2 is operated by GPU Nuclear, Inc. and owned by Metropolitan Edison (50%), Pennsylvania Electric (25%) and Jersey Central Power & Light (25%). TMI-2 became operational in 1978 and was shut down following the 1979 accident. At the end of 1993, TMI-2 was placed in a condition called Post-Defueling Monitored Storage. TMI-2 is maintained by Exelon under contract with GPU Nuclear.

A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Mirion Technologies, and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2011 through 31 December 2011.

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

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

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

3. To verify inplant controls for the containment of radioactive materials.

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

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

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

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

1. Identifying significant exposure pathways.

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

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

Ill. Program Description A. Sample Collection Samples for the TMINS REMP were collected for Exelon by Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used by RMC to obtain environmental samples for the TMINS REMP in 2011. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, fish, and sediment. Two gallon water samples were collected monthly from continuous samplers located at three surface water locations (A3-2, J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9-1), and one effluent water location (KM-1). Control locations were A3-2 and Q9-1.

All groundwater and storm water results are now being reported in the ARGPPR, Appendix F. All water samples were collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND) location. Location IND could be affected by TMINS' effluent releases. Sediment samples composed of recently deposited substrate were collected semiannually at three locations (A1-3, J2-1, and KM-3). In addition, one sediment sample was collected annually at the EDCB. Location A1-3 was the control.

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

Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product. Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K1 5-3 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 two locations (B10-2 and H1-2),

in lieu of milk sampling, and annually from the four food product groups at two locations (810-2 and E1-2). B10-2 was the control location for both annual and monthly sampling. Nine 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 Direct radiation measurements were made using Panasonic 814 calcium sulfate (CaSO 4 ) thermoluminescent dosimeters (TLD). The TLD locations are arranged in generally concentric rings on and around the TMINS site as follows:

A site boundary ringq consisting of 19 locations (A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, GI-3, G1-5, G1-6, H1-1, J1-3, K1-4, 1-1i, M1-1, N1-3, P1-2, Qi-2, and Ri-1i) 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, 15-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, and R9-1) extending to approximately 10 miles from the site designed to measure possible exposures to close-in population.

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

The specific TLD 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 TLD station consists of two primary program TLD badges, each of which has three CaSO 4 thermoluminescent phosphors enclosed in plastic, placed at each location in a frame located approximately three to six feet above ground level. Since each TLD responds to radiation independently, this provides six independent detectors at each station. The TLDs were exchanged quarterly and sent to Mirion Technologies for analysis.

B. Sample Analysis This section describes the general analytical methods used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the TMINS REMP in 2011. The analytical procedures used by the laboratories are listed in Table B-3.

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

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

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

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

4. Concentrations of 1-131 in surface, drinking, and effluent water, air, milk and food products.

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

6. Ambient gamma radiation levels at various site environs.

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

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

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

2. Net Activity Calculation and Reportingq of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity effecting 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-1 37 were reported.

For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-1 34 and Cs-137 were reported.

For air particulate eight nuclides, Be-7, Mn-54, Co-58, Co-60, Nb-95, Zn-95, Cs-1 34 and Cs-1 37 were reported.

For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-140 and La-140 were reported.

For food products five nuclides, Be-7, K-40, 1-131, Cs-1 34 and Cs-1 37 were reported.

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

D. Program Exceptions For 2011 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

1. During the sampling period 01/19/11 - 01/26/11, the pump for location H3-1 was found not operating. Per procedure the sample volume was invalid and samples were not sent for analyses. The pump was replaced and the sampler was returned to service. (IR 1173549)

2. On 03/02/11, location G2-1 sample pump vacuum reading was low and pump was replaced after sample collection. Samples were valid and sent for analyses.

3. During sampling period 03/08/11 - 03/16/11, there was a low run time and air volume due to a pump malfunction at location A3-1. The vanes were replaced and the sample was restarted satisfactorily.

Samples were valid and sent for analysis.

4. The following sample periods and locations were impacted due to power supply problems at the visitor center. Newly installed GFCI's were tripping and causing the samplers to not operate. The GCFI's were replaced with a single outlet per code to prevent power interruptions:

03/30/11 - 04/06/11, Location E1-2Q, low volume invalid not sent for analysis (IR 1199251) 04/13/11 - 04/20/11, Locations El -2 & El -2Q sufficient sample volume obtained 04/20/11 - 04/27/11, Locations E1-2 & E1-2Q sufficient sample volume obtained (IR 1207261) 04/27/11 - 05/04/11, Location E1-2Q substituted for E1-2 which had a low volume (IR 1212173)

5. For the sampling period 07/06/11 - 07/13/11, there was low sample volume due to a tripped breaker at location A3-1. The samples were valid per procedure and were sent for analyses. The breaker was reset and sampler operated normally. Due to the low volume the LLD requirements were not met for the 1-131 analyses.

6. For the sampling period 08/24/11 - 08/31/11, there was low sample volume due to a breaker trip probably due to Hurricane Irene at location A3-1. The samples were valid per procedure and were sent for analyses. The breaker was reset and sampler operated normally.

7. For the sampling period 08/24/11 - 08/31/11, there was low sample volume due to power outages probably related to Hurricane Irene at location Q1 5-1. The samples were valid per procedure and sent for analyses.

8. For the sampling periods 08/31/11 - 09/08/11 and 09/08/11 -

09/14/11, the samples and sampler were damaged due to being submerged during flooding at location A3-1. There were no samples available for these time periods. Access to the area and power were restored following the flood water receding and the sampler was replaced on 09/14/11. (IR 1262803)

9. For the sampling periods 08/31/11 - 09/08/11 and 09/08/11 -

09/14/11, the sampler was inaccessible and damaged due to flooding at location M2-1. The samples were not submerged, but power was lost to the sampler and it was damaged on 09/09/11. When accessible the samples were sent to the lab for analyses with the extended sample time until power was lost. (IR 1262803)

10. For the sampling periods 08/31/11 - 09/08/11 and 09/08/11 -

09/14/11, the sampler was inaccessible due to flooding at location Q15-1. The sampler was accessed on 09/10/11 resulting in an extended run time for 08/31/11 to 09/10/11 and a four day run time for 09/10/11 to 09/14/11. All samples were considered valid and sent for analyses. (IR 1262803)

11. During 10/26/11 - 11/02/11 sampling period, there were lower than expected run times and air sample volumes probably due to power outages due to early season snow storms and downed trees for the following locations:

Locations A3-1, E1-2, E1-2Q, and G2-1 All samples were considered valid and sent for analyses.

12. During 11/16/11 - 11/22/11 sampling period, breaker was found tripped and reset at location E1-2. Sample volume was lower than expected but sample was still available and sent for analyses. During 11/30/11 - 12/07/11 sampling period, breaker was found tripped and could not be reset. Enough sample volume was collected for valid samples and they were sent for analyses. Unit and pump were both replaced on 12/09/11. (IR 1326489)

WATER

1. During the following sampling periods, several samples were missed due to power interruptions while replacing the pole supplying power to the building (IR1170705):

01/04/11 - 01/11/11, Location A3-2, no grab sample required 01/11/11 - 01/18/11, Location A3-2, no grab sample required

2. During the following sampling period, hourly aliquots were missing due to frozen water in the sampling line (IR1170705):

01/18/11 - 01/25/11, Location A3-2, sufficient volume, no grab required.

3. Due to a frozen sample line, numerous hourly aliquots were missing from the weekly composite at the downstream surface water sampler at J1-2. The following sampling periods were impacted (IR 1170705):

12/28/10 - 01/04/11, sufficient volume, no grab sample required.

01/04/11 - 01/11/11, sufficient volume, no grab sample required.

01/11/11 - 01/18/11, sufficient volume, no grab sample required.

01/18/11 - 01/25/11, sufficient volume, no grab sample required.

01/25/11 - 02/01/11, sufficient volume, no grab sample required.

02/01/11 - 02/08/11, sufficient volume, no grab sample required.

02/08/11 - 02/15/11, sufficient volume, no grab sample required.

02/15/11 - 02/22/11, sufficient volume, no grab sample required.

02/22/11 - 03/01/11, sufficient volume, no grab sample required.

03/01/11 - 03/08/11, sufficient volume, no grab sample required.

4. For the sampling period 09/06/11 - 09/13/11, no composite sample was available due to the sampler being damaged due to flooding at location J1-2. A grab sample was taken for the week. A replacement sampler was calibrated and installed on 09/16/11. After installation no sample could be collected due to the sample line out of water. The sampler line was weighted and relocated on 09/23/11. (IR 1262803)

5. For the sampling period 09/06/11 - 09/13/11, no composite was available due to the sampler being damaged due to flooding at location A3-2. A grab sample was taken. The compositor building was also damaged and power has not been restored by the borough. Weekly grab samples continue to be taken. (IR 1262803)

6. For the sampling period 11/08/11 - 11/15/11, sampler was found with no source water to the compositor at location G15-3. Sufficient sample volume was collected so no grab was required. The old water treatment facility was taken out of service. After piping modifications by the facility personnel, a sampler was setup in the new treatment building and calibrated on 11/18/11. (IR 1296143)

7. Accumulated debris caused the sample line to submerge and also detach from weight/anchor at location J1-2. Sufficient sample volume was collected. No grab samples were necessary. A temporary anchor/weight was attached on 12/28/11. (IR 1326489):

12/06/11 - 12/13/11, sufficient volume, no grab sample required.

12/20/11 - 12/27/11, insufficient volume, grab sample required.

TLD

1. Locations K2-1, L1-2, M1-2, N1-1, P1-1, Q1-1, and R1-2 were collected with a six month exposure. TLDs were not collected with other 4th quarter TLDs due to unsafe ice conditions on the river.

(IR 1170705)

2. During the first quarter collection, station C8-1 was found on the ground. TLDs were sent for analyses and TLD holder was remounted satisfactorily.

3. During the second quarter collection, TLDs were missing from sample station E7-1. (IR 1255611)

4. TLDs for the third quarter were missing from the sampling station L1-2.

The tree, hardware and TLD badges were all swept away by recent local area flooding. New hardware and 4th quarter badges were installed. (IR 1262803)

5. During the fourth quarter collection, badges 171 and 172 for location R1-2 were missing and no samples available. Both bags/pouches were sliced or cut and badges were taken. (IR 1326489)

6. During the fourth quarter collection, badge 20 bag/pouch for location C1-1 was sliced/cut and badge was found on the ground. Badge was sent for analysis.

7. During the fourth quarter collection, badges in mounting frame were found on the ground for location E5-1. Frame was reattached and badges were exchanged.

VEGETATION

1. There was no grain or root vegetables at location E1-2 due to extreme heat conditions and no rain.

2. For location H1-2, substitutions were obtained. Field corn was collected due to no sweet corn available and turnips were collected on 10/19/11.

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

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

E. Program Changes There were no program changes for 2011.

IV. Results and Discussion A. Aquatic Environment

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

Tritium Monthly samples from J1-2 and Q9-1 were analyzed for tritium activity (Table C-1.1, Appendix C). Positive tritium activity was detected in nine of 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 324 to 8230 pCi/I. The increased tritium concentrations detected were a result of TMINS releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. The indicator surface water sample is taken just downstream of the liquid discharge outfall where mixing of liquid effluents with the river water is incomplete. More complete mixing is not achieved until liquid effluents pass over the York Haven Dam. This water is normally not consumed by humans. The concentrations detected were well below any regulatory limits (Figures C-1 and C-2, Appendix C).

Iodine Monthly samples from location A3-2 were analyzed for 1-131 activity (Table C-1.2, Appendix C). This is a control or background station sampled because known medical discharges of radiopharmaceuticals occur into the surface water upstream of TMI from a nearby hospital. Iodine-131 from medical discharges was detected in two of twelve samples. The concentration ranged from 1.0 to 2.5 pCi/l. (IR 1183397)

Gamma Spectrometrv Locations J1-2 and Q9-1 were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C), all nuclides were less than the MDC.

2. Drinking Water Monthly samples were collected from continuous water samplers at three locations (G15-2, G15-3, and Q9-1). Two locations (G15-2 and G1 5-3) 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 seven of 36 samples. The concentrations ranged from 2.0 to 6.5 pCi/l. Concentrations detected were consistent with those detected in previous years (Figure C-3, Appendix C).

Iodine Monthly samples from all locations were analyzed for concentrations of lodine-131 (Table C-11.2, Appendix C).

Iodine-131 activity was not detected in any samples.

Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was detected in two of 36 samples at concentrations just above the LLD. The concentrations ranged from 184 to 230 pCi/L (Figures C-4, Appendix C). The hypothetical dose to the maximum exposed individual from consuming this water from two locations was calculated as <0.005 mrem. (IR 1217864)

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 10 of 12 samples. The concentrations ranged from 3.2 to 10.7 pCi/I. Concentrations detected were consistent with those detected in previous years.

Iodine-1 31 Monthly samples from location K1-1 were analyzed for concentrations of 1-131 (Tables C-111.1, Appendix C). Iodine-131 was detected in one sample at a concentration of 1.4 pCi/l. 1-131 was detected in the upstream control sample location for the same period of time. No 1-131 was identified in any tank effluent pre-release samples, and 1-131 was not detected in any other downstream drinking water samples. Effluent water is not consumed by humans. The 1-131detected was attributed to upstream medical discharges and not plant related activities. (IR 1183397)

Tritium Monthly samples from location KI-1 were analyzed for tritium activity (Table C-I11.1, Appendix C). Tritium activity was detected in 11 of 12 samples. The concentrations ranged from 982 to 77,200 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.

15-

Strontium Semiannual composite samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-111.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at 4.2 pCi/I for Sr-89 and at 0.7 pCi/I for Sr-90.

Gamma Spectrometry Samples from location K1-1 were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). All nuclides were less than the MDC.

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

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

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

Strontium The edible portions of fish samples from both locations were analyzed for Sr-90. (Table C-IV.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <4 pCi/kg wet for Sr-90.

Gamma Spectrometry The edible portions of fish samples from both locations were analyzed for gamma emitting nuclides (Table C-IV.2, Appendix C).

Naturally occurring K-40 was found in all fish samples and ranged from 1,310 to 3,730 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were detected.

7. Sediment Aquatic sediment samples were collected at three locations (A1-3, J2-1 and K1-3) semiannually. Of these locations two (J2-1 and K1-

3) could.be affected by TMINS' effluent releases. The following analysis was performed:

Gamma Spectrometry Sediment samples from all locations were analyzed for gamma emitting nuclides (Table C-V.1, Appendix C). Potassium-40 was found in all sediment samples and ranged from 8,580 to 17,600 pCi/kg dry. Cesium-137 was detected in two sediment samples.

The concentrations ranged from 187 to 306 pCi/L. Cesium-137 is occasionally found in sediment at very low levels (just above LLD) and is not distinguishable from background levels. No other fission or activation products were detected (Figure C-5, Appendix C).

B. Atmospheric Environment

1. Airborne Particulates

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

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

Detectable gross beta activity was observed at all locations.

Comparison of results aid in determining the effects, if any, resulting from the operation of TMINS. The results from the closest to the site boundary locations (Group I) ranged from 7 to 39 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . The results from the intermediate offsite locations (Group II) ranged from 7 to 88 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3 . The results from the Control location (Group IlI) ranged from 9 to 43 E-3 pCi/mr3 with a mean of 20 E-3 pCi/m 3 . Comparison of the 2011 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 2011 indicate no notable differences between indicator and control stations (Figure C-7, Appendix C).

Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-VI.3, Appendix C).

Naturally occurring Be-7 due to cosmic ray activity was detected in all 28 samples. These concentrations ranged from 25 to 92 E-3 pCi/m3. All other nuclides were less than the MDC. Additional sampling occurred in the weeks immediately following the Fukushima event in 2011. All nuclides were less than the MDC.

b. Airborne Iodine Continuous air samples were collected from seven (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1, and Q15-1) locations and analyzed weekly for 1-131 (Table C-VII.L1, Appendix C). All results were less than the MDC, with the exception of 19 samples that were positive for 1-131. The positive activity is directly attributed to the Fukushima event in March of 2011.

2. Terrestrial

a. Milk Samples were collected from five locations (K15-3, E2-2, F4-1 G2-1 and P4-1) biweekly March through November and monthly December through February. The following analyses were performed:

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

Additional sampling occurred in the weeks immediately following the Fukushima event in 2011. All results were less than the MDC.

Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-IX.2, Appendix C). No Sr-89 activity was detected. Strontium-90 activity was detected in four of 20 samples. The concentrations ranged from 0.6 to 0.7 pCi/l. The activity detected was consistent with those detected in the pre-operational years (Figure C-8, Appendix C).

Gamma Spectrometry Milk samples from all locations were analyzed for concentrations of gamma emitting nuclides (Table C-VIII.3, Appendix C).

Naturally occurring K-40 activity was found in all samples.

The concentrations ranged from 745 to 1,670 pCi/I. All other nuclides were less than the MDC.

b. Food Products Samples were collected from two locations (B10-2, and H1-

2) on a monthly basis, in lieu of milk sampling. Samples from the four food product groups were collected annually from three locations (B10-2, E1-2, and H1-2) this year due to unavailability of sweet corn and a root vegetable at E1-2.

The following analyses were performed:

Strontium Twenty-six of 32 food product samples was analyzed for concentrations of Sr-90 (Table C-IX.1, Appendix C).

Strontium-90 activity was detected in 11 of 26 samples. The concentrations ranged from 3 to 17 pCi/kg wet.

Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C).

Naturally occurring Be-7 due to cosmic ray activity was detected in 18 of 32 samples. These concentrations ranged from 152 to 3,650 pCi/I. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 1,900 to 8,260 pCi/I. All other nuclides were less than the MDC.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO 4 ) thermoluminescent dosimeters. Ninety TLD locations were established around the site. Results of TLD measurements are listed in Tables C-X.1 to C-X.3, Appendix C.

All of the TLD measurements were below 10 mR/standard month, with a range of 2.7 to 8.7 mR/standard month. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 averaged higher than indicator stations. The historical ambient gamma radiation data from Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 were plotted along with similar data from the Site, Indicator and Control Ring Locations (Figure C-9, Appendix C). Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 have a historical high bias, but tracked with the data from all three groups, this bias is most likely due to radon and other naturally occurring nuclides, e.g. K-40, emanating from the ground.

D. Land Use Survey A Land Use Survey conducted in the July, August, September, and October 2011 growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Normandeau Associates, RMC Environmental Services Division for Exelon to comply with Sections 8.2 of the Plant's Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident, milk-producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1/2 degree sectors around the site. The results of this survey are summarized below.

Distance in Miles from the TMINS Reactor Buildings Sector Residence Garden Milk Farm Meat Animal Miles Miles Miles Miles 1 N 1.1 1.6 2.1 2.1 2 NNE 0.7 0.9 2.4 3 NE 0.5 1.5 4.1 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 1.1 1.4 1.4 8 SSE 0.7 0.8 9 S 2.3 2.7 3.3 10 SSW 0.6 2.5 4.9,14.4 11 SW 0.5 1.0 12 WSW 0.5 1.3 13 W 0.7 1.3 14 WNW 0.4 2.2 3.7 2.4 15 NW 0.4 1.2 16 NNW 0.7 2.4 E. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2011 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2011 whole body dose potentially received by an assumed maximum exposed individual from TMI-1 and TMI-2 liquid and airborne effluents was conservatively calculated to be 0.17 mrem. This dose is equivalent to 0.05% of the dose that an individual living in the TMI area receives each year from natural background radiation.

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

Thermoluminescent dosimeters (TLDs) positioned in the environment around TMINS provide measurements to determine external radiation doses to humans. Samples of air, water and food products are used to determine internal doses.

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

Doses are calculated using an advanced "class A" dispersion model.

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

Therefore, the model predicts doses that are higher than actual doses received by people. The type and amount of radioactivity released from TMINS is calculated using measurements from effluent sample analyses. Once released, the dispersion of radionuclides in the environment is readily determined by computer modeling.

Airborne releases are diluted and carried away from the site by atmospheric diffusion, which continuously acts to disperse radioactivity. Variables that affect atmospheric dispersion include wind speed, temperature at different elevations, terrain, and shift in wind direction. A weather station on the north end of TMI is linked to a data logger that records the meteorological data.

Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Susquehanna River.

Actual monthly Susquehanna River flows are obtained from the York Haven Hydroelectric Station.

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

Numerous data files are used in the calculations that describe the area around TMI in terms of population distribution and foodstuffs production. Data files include such information as the distance from the plant stack to the site boundary in each sector, the population groupings, milk cows, milk goats, gardens of more than 500 square feet, meat animals, downstream drinking water users, and crop yields.

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

Doses are calculated for what is termed the "maximum hypothetical individual". This individual is assumed to be affected by the combined maximum environmental concentrations wherever they occur.

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

For airborne releases, the maximum hypothetical individual would live at the location of highest radionuclide concentration for inhalation and direct plume exposure. Additionally, this individual each year would consume 106 gallons of cow milk, 141 pounds of leafy vegetables, 1389 pounds of non-leafy vegetables and fruits and 243 pounds of meat produced at the locations with the highest predicted radionuclide concentrations. Consumption of goat milk is not included, since this exposure pathway does not currently exist.

2. Result of Dose Calculations The maximum hypothetical doses due to 2011 TMI-1 and TMI-2 liquid and airborne effluents are summarized in Tables 1 and 2.

Table 1 compares the calculated maximum hypothetical individual doses to the USNRC 10 CFR 50 App. I guidelines. This table also compares the calculated doses (to an individual of the public) from effluents and direct radiation to USEPA 40 CFR 190 dose limits.

Table 2 presents the maximum hypothetical whole body doses to an individual.

As shown in Table 1, the doses calculated for 2011 operations at TMINS were well below the Federal dose limits (USEPA 40 CFR 190) and the guidelines of USNRC 10 CFR 50 App. I. This conclusion was supported by radionuclide concentrations detected in actual environmental samples.

Doses from natural background radiation provide a baseline for assessing the potential public health significance of radioactive effluents. Natural background radiation from cosmic, terrestrial and natural radionuclides in the human body (not including radon),

averages about 81 mrem/yr (Ref. 5). Additionally, the average individual living in the United States receives an annual dose of about 2,760 mrem to the lung from natural radon gas. This lung dose is considered to be equivalent to a whole (or total) body dose of 230 mrem (Ref. 5). Therefore, the average person in the United States receives a whole body dose of about 311 mrem/yr from natural background radiation sources.

As shown on Table 2, the maximum hypothetical whole body dose received by an individual from 2011 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.17 mrem. This dose is equivalent to 0.05% percent of the dose that an individual living in the TMI area receives each year from natural background radiation (311 mrem).

The low doses calculated for 2011 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).

In conclusion, radioactive materials related to 2011 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 2011 were well below applicable dose limits and only a small fraction of the doses received from natural background radiation. Additionally, the results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.

Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2011 did not have any adverse effects on the health of the public or on the environment.

TABLE I Calculated Maximum Hypothetical Doses to an Individual from 2011 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual USNRC 10 CFR 50 APP. I Calculated Dose Guidelines (mrem/yr)

(mrem/yr) TMI-1 TMI-2 From Radionuclides 3 total body, or 2.42E-2 3.63E-4 In Liquid Releases 10 any organ 2.66E-2 5.77E-4 From Radionuclides In 5 total body, or 1.21E-3 0*

Airborne Releases (Noble Gases) 15 skin 3.79E-3 0*

From Radionuclides In Airborne 15 any organ 1.37E-1 1.06E-5 Releases (Jodines, Tritium and Particulates)

• No noble gases were released from TMI-2.

USEPA Calculated Dose 40 CFR 190 (mrem/yr)

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

Total from Site 75 thyroid 0.60 25 total body 0.71 or other organs

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

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

The direct radiation dose from 2011 TMINS operations was 0.54 mrem. This dose was based on a maximum net fence-line exposure rate of 8.7 mR/std month and a shoreline/fence-line occupancy factor of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> (Regulatory Guide 1.109). The combination of the maximum organ dose from TMI-1 and TMI-2 effluents (0.17 mrem) and the dose from direct radiation (0.54 mrem) yielded a maximum hypothetical dose of 0.71 mrem.

- 26 -

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2011 TMI-1 and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)

TMI-1 TMI-2 From Radionuclides In Liquid Releases 2.42E-2 3.63E-4 From Radionuclides in Airborne Releases 1.21E-3 0*

(Noble Gases)

From Radionuclides In Airborne 1.37E-1 1.06E-5 Releases (Iodines, Tritium and Particulates)

• No noble gases were released from TMI-2.

Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations: 0. 17 mrem/vr Individual Whole Body Dose Due to Natural Background Radiation (1) 311 mrem/yr (1) NCRP 160 - (2009)

Figure 1 Exposure Pathways For Radionuclides Routinely Released From TMINS NOBLE GASES (Xe,Kr) ACTIVATION PRODUCTS.(Co-60, Mn-54)

Plume exposure Shoreline exposure RAD1OIODINES ([-131, 1-133) RADIOCESIUMS (Cs-134, Cs-137)

Inhalation and consumption of milk, Shoreline exposure and consumption of milk, water, fruits, and vegetables meat, fish, water, fru its, and vegetables RADIOSTRONTIUMS (Sr-89, Sr-90) TRITIIJM (H-3)

Consumption of milk, meat, Inhalation and consumption of water, fruits, and vegetables milk, fruits, and vegetables F. Summary of Results - Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:

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

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

3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.

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

For the primary laboratory, 14 out of 18 analytes met the specified acceptance criteria. Four analytes did not meet the specified acceptance criteria for the following reason:

1. Teledyne Brown Engineering's Analytics March 2011 Cr-51 in milk result of 398 pCi/L was higher than the known value of 298 pCi/L, resulting in a found to known ratio of 1.34. NCR 11-13 was initiated to investigate this failure. There was a slightly high bias in all the gamma activities. The June gamma results in milk did not show a high bias. No further action was required.

2. Teledyne Brown Engineering's ERA May 2011 Gross Alpha in water result of 64.1 pCi/L was higher than the known value of 50.1 pCi/L, which exceeded the upper control limit of 62.9 pCi/L. NCR 11-08 was initiated to investigate this failure. The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve.

Teledyne Brown Engineering's MAPEP March 2011 Gross Alpha in air particulate result of 0.101 Bq/sample was lower than the known value of 0.659 Bq/sample, which exceeded the lower control limit of 0.198 Bq/sample. NCR 11-11 was initiated to investigate this failure. The air particulate filter was counted on the wrong side.

3. Teledyne Brown Engineering's ERA November 2011 Sr-89 in water result of 81.0 pCi/L was higher than the known value of 69.7 pCi/L, which exceeded the upper control limit of 77.9 pCi/L. NCR 11-16 was initiated to investigate this failure. The TBE reported value to known ratio of 1.16 fell within the acceptable range of +/- 20%, which TBE considers acceptable.

4. Teledyne Brown Engineering's MAPEP March 2011 Sr-90 in soil, air particulate and vegetation were non-reports that were evaluated as failed. NCR 11-11 was initiated to investigate these failures.

MAPEP evaluated the non-reports as failed due to not reporting a previously reported analyte.

For the secondary laboratory, Environmental, Inc., 12 out of 14 analytes met the specified acceptance criteria.

1. Environmental Inc.'s ERA October 2011 Cs-1 34 in water result of 38.8 pCi/L was higher than the known value of 33.4 pCi/L, which exceeded the upper control limit of 36.7 pCi/L. The sample was reanalyzed. The reanalyzed result of 32.9 was acceptable.

2. Environmental Inc.'s MAPEP February 2011 Sr-90 in air particulate result of 1.89 Bq/sample was higher than the known value of 1.36 Bq/sample, which exceeded the upper control limit of 1.77 Bq/sample. No errors were found in the calculation or procedure.

The reanalyzed result of 1.73 Bq/sample was acceptable.

Environmental Inc.'s MAPEP August 2011 Sr-90 in soil result of 219.4 Bq/kg, less than the known value of 320 Bq/kg, was below the lower control limit of 224 Bq/kg. The sample was reanalyzed in triplicate through a strontium column. The reanalyzed result of 304.2 Bq/kg was acceptable.

The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.

V. References

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

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

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

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

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

160. "Ionizing Radiation Exposure of the Population of the United States."

2009.

Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER H-3 24 2000 2166 <LLD 2166 TM-SW-JI-2 INDICATOR 0 (PCI/LITER) (9/12) (9/12) WEST SHORE; TMI (324/8230) (324/8230) 0.5 MILES S OF SITE 1-131 12 I NA 1.8 1.8 TM-SW-A3-2 CONTROL 0 (2/12) (2/12) SWATARA CREEK (1.0/2.5) (1.0/2.5) 2.5 MILES N OF SITE GAMMA 24 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER NB-95 15 <LLD <LLD 0 (PCI/LITER)

ZR-95 30 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA- 140 15 <LLD <LLD DRINKING WATER GR-B 36 3.5 2 3.7 TM-DW-G 15-2 INDICATOR (PCI/LITER) (6/24) (1/12) (5/12) WRIGHTS WATER SUPPLY (2.5/6.5) (2.5/6.5) 13.3 MILES SE OF SITE 1-131 36 <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER H-3 36 2000 207 <LLD 230 TM-DW-G 15-3 INDICATOR 0 (PCI/LITER) (2/24) (1/12) LANCASTER WATER AUTHORITY (184/230) 14.8 MILES SE OF SITE GAMMA 36 MN-54 15 <LLD <LLD CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER ZR-95 30 <LLD <LLD 0 (PCI/LITER)

CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-I140 15 <LLD <LLD 0 EFFLUENT WATER GR-B 12 5.8 NA 5.8 TM-EW-KI-I INDICATOR (PCILITER) (10/12) (10/12Y MAIN STATION LIQ. DISCHARGE (3.2/10.7) (3.2/10.7) ONSITE 1-131 12 1.4 NA 1.4 TM-EW-KI-1 INDICATOR (1/12) (1/12) MAIN STATION LIQ. DISCHARGE ONSITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER H-3 12 2000 20378 NA 20378 TM-EW-KI-I INDICATOR 0 (PCILITER) (11/12) (11/12) MAIN STATION LIQ. DISCHARGE (982/77200) (982/77200) ONSITE SR-89 2 5 <LLD NA 0 SR-90 2 <LLD NA 0 GAMMA 12 MN-54 15 <LLD NA 0 CO-58 15 <LLD NA 0 FE-59 30 <LLD NA 0 CO-60 15 <LLD NA 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER ZN-65 30 <LLD NA 0 (PCI/LITER)

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER SR-90 4 10 <LLD <LLD (PCI/KG WET)

GAMMA 4 K-40 NA 2270 2700 2700 BKGB CONTROL 0 (2/2) (2/2) (2/2) CITY ISLAND (1310/3230) (2110/3290) (2110/3290) UPSTREAM OF DISCHARGE MN-54 130 <LLD <LLD 0 CO-5R 130 <LLD <LLD 0 FE-5 9 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS 1S INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER CS-134 130 <LLD <LLD 0 (PCI/KG WET)

CS-137 150 <LLD <LLD 0 PREDATOR SR-90 4 10 <LLD <LLD 0 (PCUKG WET)

GAMMA 4 K-40 NA 3350 3020 3350 INDP INDICATOR 0 (2/2) (2/2) (2/2) YORK HAVEN DAM (2970/3730) (2920/3120) (2970/3730) DOWNSTREAM OF DISCHARGE MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS PREDATOR CO-60 130 <LLD <LLD 0 (PCI/KG WET)

ZN-65 260 <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 SEDIMENT GAMMA 7 (PCI/KG DRY) K-40 NA 14700 9790 16000 J2-1 INDICATOR 0 (5/5) (2/2) (2/2) YORK HAVEN DAM (12400/17600) (8580/11000) (14400/17600) 1.5 MILES S OF SITE NMN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEANý (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT CO-60 NA <LLD <LLD 0 (PCI/KG DRY)

CS-134 150 <LLD <LLD 0 0 CS-137 180 247 <LLD 306 EDCB INDICATOR 0 (2/5) (1/1) STORM WATER BASIN (187/306) 0.2 MILES SE OF SITE AIR PARTICULATE GR-B 360 10 18 20 20 TM-AP-G2-1 INDICATOR 0 (E-3 PCI/CU.METER) (299/308) (51/52) (49/52) BECKER FARM (7/88) (9/43) (9/88) 1.4 MILES SE OF SITE GAMMA 28 BE-7 NA 59 61 67 TM-AP-FI-3 INDICATOR 0 (24/24) (4/4) (4/4) 500 KV SUBSTATION (25/92) (38/84) (32/92) 0.6 MILES ESE OF SITE MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE CO-60 NA <LLD <LLD 0 (E-3 PCI/CU.METER)

NB-95 NA <LLD <LLD ZR-95 NA <LLD <LLD CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 AIR IODINE GAMMA 360 (E-3 PCI/CU.METER) 1-131 70 54 71 71 TM-AI-Q15-1 CONTROL 0 (16/308) (3/52) (3/52) WEST FAIRVIEW (37/74) (57/87) (57/87) 13.5 MILES NW OF SITE MILK 1-131 115 <LLD <LLD (PCI/LITER)

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK SR-89 20 <LLD <LLD 0 (PCI/LITER)

SR-90 20 0.7 0.6 0.7 TM-M-E2-2 INDICATOR 0 (3/16) (1/4) (2/4) NISSLEY FARM (0.7/0.7) (0.7/0.7) 1.1 MILES E OF SITE GAMMA 115 K-40 NA 1259 1231 1359 P4-I INDICATOR (92/92) (23/23) (23/23)

(745/1670) (1100/1380) (1110/1670)

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2011 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION

.MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION SR-90 26 10 9 5 9 HI -2 INDICATOR 0 (PCI/KG WET) (7/13) (4/13) (7/12) RED HILL MARKET, ALONG ROUTE 441 (3/17) (3/10) (3/17) 1.0 MILES SSE OF SITE GAMMA 32 BE-7 NA 1124 746 1190 H 1-2 INDICATOR 0 (13/16) (5/16) (12/14) RED HILL MARKET, ALONG ROUTE 441 (242/3650) (152/1720) (242/3650) 1.0 MILES SSE OF SITE K-40 NA 4486.3 3629.4 4526.4 H1-2 INDICATOR 0 (16/16) (16/16) (14/14) RED HILL MARKET, ALONG ROUTE 441 (1930/8260) (1900/5800) (1930/8260) 1.0 MILES SSE OF SITE 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 DIRECT RADIATION TLD-QUARTERLY 357 NA 4.6 5.2 7.3 H8-1 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (313/313) (44/44) (4/4) SAGINAW ROAD, STARVIEW (2.7/8.7) (3.8/7.8) (6.6/8.6) 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)

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

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

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

YY - Radial Zone of Sampling Location in miles.

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

B-I

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2011 Sample Station Map Distance Medium Code Number (miles) Azimuth Description AQS A1-3 1 0.5 3590 N of site off north tip of TMI in Susquehanna River ID A1-4 1 0.3 60 N of Reactor Building on W fence adjacent to North Weather Station, TMI APAIlD A3-1 2 2.7 3570 N of site at Mill Street Substation SW A3-2 2 2.7 356' N of site at Swatara Creek, Middletown A5-1 2 4.4 30 N of site on Vine Street Exit off Route 283 ID ID A9-3 3 8.0 20 N of site at Duke Street Pumping Station, Hummelstown ID B1-1 0.6 250 NNE of site on light pole in middle of North Bridge, TMI ID B1-2 0.4 230 NNE of Reactor Building on top of dike, TMI ID B2-1 2 1.9 170 NNE of site on Sunset Dr. (off Hillsdale Rd.)

ID B5-1 2 4.9 190 NNE of site at intersection of School House and Miller Roads ID B10-1 3 9.2 210 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey FP B10-2 3 10 310 NNE of site at Milton Hershey School, Hershey ID C1-1 0.7 37' NE of site along Route 441 N ID C1-2 0.3 500 NE of Reactor Building on top of dike, TMI ID C2-1 2 1.5 440 NE of site at Middletown Junction ID C5-1 2 4.7 430 NE of site on Kennedy Lane ID C8-1 3 7.1 480 NE of site at Schenk's Church on School House Road AQF Control - All locations where finfish are collected above Dock St.

Dam, Harrisburg ID D1-1 1 0.2 760 ENE of Reactor Building on top of dike, TMI ID D1-2 1 0.5 670 ENE of site off Route 441 along lane between garden center and residence ID D2-2 2 1.6 74' ENE of site along Hillsdale Rd. (S of Zion Rd.)

ID D6-1 3 5.2 660 ENE of site off Beagle Road ID D15-1 3 10.8 640 ENE of site along Route 241, Lawn AP, Al, ID, FP E1-2 0.4 970 E of site at TMI Visitor's Center ID E1-4 0.2 970 E of Reactor Building on top of dike, TMI M E2-2 2 1.1 960 E of site at farm on Pecks Road ID E2-3 2 2.0 970 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 6.7 880 E of site along Hummelstown Street, Elizabethtown ID F1-1 0.5 1170 ESE of site near entrance to 500 kV Substation ID F1-2 0.2 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI AP, Al F1-3 0.6 1120 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 1190 ESE of site along Engle Road M F4-1 2 3.2 1040 ESE of site at farm on Tumpike Road ID F5-1 2 4.7 1090 ESE of site along Amosite Road ID F10-1 3 9.4 1120 ESE of site along Donegal Springs Road, Donegal Springs ID F25-1 3 22 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster ID G1-2 1 0.7 1450 SE of site along Route 441 S ID G1-3 0.2 1300 SE of Reactor Building on top of dike, TMI ID G1-5 0.3 143' SE of Reactor Building on top of dike, TMI ID G1-6 0.3 1390 SE of Reactor Building on top of dike, TMI Al, AP, M G2-1 2 1.4 1260 SE of site at farm on Becker Road ID G2-4 2 1.7 1380 SE of site on Becker Road ID G5-1 2 4.8 1310 SE of site at intersection of Bainbridge and Risser Roads ID G10-1 3 9.7 1280 SE of site at farm along Engles Tollgate Road, Marietta ID G15-1 3 14.4 1260 SE of site at Columbia Water Treatment Plant DW G15-2 3 13.3 1290 SE of site at Wrightsville Water Treatment Plant DW G15-3 3 15.7 1240 SE of site at Lancaster Water Treatment Plant B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2011 Sample Station Map Distance Medium Code Number (miles) Azimuth Description 0

ID H1-1 1 0.5 167 SSE of site, TMI FP H1-2 1 1.0 1510 SSE of site along Route 441, Red Hill Market AP, Al, ID H3-1 2 2.2 1600 SSE of site in Falmouth-Collins Substation ID H5-1 2 4.1 1580 SSE of site by Guard Shack at Brunner Island Steam Electric Station ID H8-1 3 7.4 1630 SSE of site along Saginaw Road, Starview ID H15-1 3 13.2 1570 SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills AQF Indicator - - - All locations where finfish are collected downstream of the TMINS liquid discharge outfall ID J1-1 1 0.8 1760 S of site, TMI SW JA-2 1 0.5 1880 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River ID J1-3 1 0.3 1890 S of Reactor Building just S of SOB, TMI AQS J2-1 2 1.4 1790 S of site in Susquehanna River just upstream of the York Haven Dam ID J3-1 2 2.7 1790 S of site at York Haven/Cly ID J5-1 2 4.9 1810 S of site along Canal Road, Conewago Heights ID J7-1 3 6.5 1760 S of site off of Maple Street, Manchester ID J15-1 3 12.6 1830 S of site in Met-Ed York Load Dispatch Station EW K1-1 0.2 2100 On site at RML-7 Main Station Discharge Building AQS K1-3 0.2 2120 SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River ID K1-4 0.2 2090 SSW of Reactor Building on top of dike behind Warehouse 2, TMI ID K2-1 2 1.2 2000 SSW of site on S Shelley Island ID K3-1 2 2.0 2060 SSW of site along Rt. 262, N of Cly ID K5-1 2 4.9 202° SSW of site along Conewago Creek Road, Strinestown ID K8-1 3 7.5 1960 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View ID K15-1 3 12.8 2030 SSW of site behind McDonald's and next to child care center, Weiglestown M K15-3 3 14.4 205° SSW of site at farm along S Salem Church Rd, Dover ID 1_1-1 0.1 2360 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI ID L1i-2 0.5 2210 SW of site on Beech Island ID L2-1 2 1.8 224' SW of site along Route 262 ID L5-1 2 4.1 2280 SW of site at intersection of Stevens and Wilson Roads ID L8-1 3 8.0 225 SW of site along Rohlers Church Rd., Andersontown ID L1 5-1 3 11.8 2260 SW of site on W side of Route 74, rear of church, Mt.

Royal ID M1-1 0.1 2500 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI ID M1-2 0.4 2520 WSW of site on E side of Shelley Island, Lot #157 AP, Al, ID M2-1 2 1.3 256' WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro ID M5-1 2 4.3 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown ID M9-1 3 8.7 2430 WSW of site along Alpine Road, Maytown ID N1-1 0.7 2740 W of site on W side of Shelley Island, between lots #13 and #14 ID N1-3 0.1 2740 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI ID N2-1 2 1.2 2610 W of site at Goldsboro Marina ID N5-1 2 5.0 2680 W of site off of Old York Road along Robin Hood Drive ID N8-1 3 7.7 2620 W of site along Route 382, 1/2 mile north of Lewisberry ID N15-2 1 10.4 275' W of site at intersection of Lisburn Road and Main Street, Lisbum ID P1-1 0.4 3030 WNW of site on Shelley Island B-3

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2011 Sample Station Map Distance Medium Code Number (miles Azimuth Description ID P1-2 1 0.1 292' WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI ID P2-1 2 2.0 283' WNW of site along Route 262 M P4-1 2 3.7 295' WNW of site at farm on Valley Road ID P5-1 2 5.0 284' WNW of site at intersection of Valley Road (Route 262) and Beinhower Road ID P8-1 3 8.0 2920 WNW of site along Evergreen Road, Reesers Summit ID Q1-1 0.5 317* NW of site on E side of Shelley Island ID Q1-2 0.2 3210 NW of Reactor Building on fence W of Warehouse 1, TMI ID Q2-1 2 1.9 310' NW of site along access road along river ID Q5-1 2 5.0 317' NW of site along Lumber Street, Highspire SW, DW, ID Q9-1 3 8.5 310' NW of site at the Steelton Water Company AP, Al, ID Q15-1 3 13.4 3090 NW of site behind West Fairview Fire Dept. Social Hall (abandoned)

ID R1-1 3 0.2 3350 NNW of Reactor Building along W fence, TMI ID R1-2 1 0.7 3340 NNW of site on central Henry Island ID R3-1 2 2.6 341i NNW of site at Crawford Station, Middletown ID R5-1 2 4.9 339' NNW of site at intersection of Spring Garden Drive and Route 441 ID R9-1 3 8.0 341° NNW of site at intersection of Derry and 66th Streets, Rutherford Heights ID R15-1 3 11.2 3320 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park IDENTIFICATION KEY ID = Immersion Dose (TLD) EW = Effluent Water SW = Surface Water DW = Drinking Water Al = Air Iodine M = Milk (Cow)

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

B-4

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2011 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor. Nuclear Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

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

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

Drinking Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor. Nuclear Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

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

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

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2011 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Effluent Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor. Nuclear Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

Effluent Strontium Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange Water 89/90 composite from monthly samples.

Storm Gamma Quarterly composite ER-TMI-06 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy of monthly grab radiological analysis (Three Mile Island samples Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Storm Tritium Quarterly composite ER-TMI-06 Collection of water samples for 1 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water of monthly grab radiological analysis (Three Mile Island scintillation samples Nuclear Station)

Env. Inc., T-02 Determination of tritium in water (direct method)

Fish Gamma Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by other techniques gamma spectroscopy Fish Strontium 90 Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet) TBE, TBE-2019 Radiostrontium analysis by ion exchange collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in other techniques Ashed Samples

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2011 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Sediment Gamma Semi-annual grab ER-TMI-03 Collection of sediment samples for 500 grams (dry) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Gross Beta One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2008 Gross alpha and/or gross beta activity in Particulates composite of iodine samples for radiological analysis (Three (approximately various matrices continuous air Mile Island Nuclear Station) 280 cubic sampling through meters weekly) Env. Inc., AP-02 Determination of gross alpha and/or gross glass fiber filter beta in air particulate filters paper Air Gamma Quarterly composite TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy of each station (approximately Env. Inc., AP-03 Procedure for compositing air 3600 cubic Env. Inc., GS-01 Determination of gamma emitters by particulate filters for gamma spectroscopic meters) gamma spectroscopy analysis Air Iodine Gamma One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy composite of iodine samples for radiological analysis (Three (approximately continuous air Mile Island Nuclear Station) 280 cubic Env. Inc., 1-131-02 Determination of 1-131 in charcoal sampling through meters weekly) canisters by gamma spectroscopy (batch method) charcoal filter Milk 1-131 Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion Monthly all other exchange times Milk Strontium- Quarterly composite ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 of Bi-weekly and radiological analysis (Three Mile Island Nuclear monthly grab Station) Enc. Inc., SR-07, Determination of Sr-89 and Sr-90 in Milk samples (Ion Exchange Batch Method)

TBE, TBE-2023 Compositing of samples Milk Gamma Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., GS-01 Determination of gamma emitters by Monthly all other gamma spectroscopy times Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by I_ I gamma spectroscopy

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2011 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Vegetation Strontium- Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in Ashed Samples TLD Thermolumines Quarterly TLDs ER-TMI-02 Collection of TLD samples for 2 badges with 3 Mirion Technologies cence comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Dosimetry Panasonic 814 Station)

(containing 3 each CaSe 4 elements) 00

Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2011 B-9

I . Lomailm. ar lite by staton cods.

2. Locations are based con PS reudings relarenced to a nvidokin between TM-I and TM-2. 0 05 1 3

3. Basenutp inPA StatpIane SoMiw NAD27 . feet 6i MiWes Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2011 B-10

Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2011 B-11

Intentionally Left Blank vi

APPENDIX C DATA TABLES AND FIGURES -

PRIMARY LABORATORY

TABLE C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION J,1-2 Q9-1 PERIOD 12/28/10 - 02/01/ /11 324 +/- 119 (1) < 177 02/01/11 - 03/01/ /11 8230 +/- 866 (1) < 166 03/01/11 - 03/29/ /11 < 147 (1) < 143 03/29/11 - 05/03/ /11 < 192 < 189 05/03/11 - 05/31/ /11 645 +/- 135 < 168 05/31/11 - 06/28/ /11 2190 +/- 273 < 178 06/28/11 - 08/02/ /11 1980 +/- 250 < 177 08/02/11 - 08/30/ /11 900 +/- 152 < 171 08/30/11 - 09/27/ /11 3660 +/- 417 (1) < 185 09/27/11 - 11/01/ /11 912 +/- 166 < 199 11/01/11 - 11/29//i11 < 165 < 163 11/29/11 - 01/03/ /12 656 +/- 154 (1) < 163 MEAN 2166 +/- 5010 TABLE C-I.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION A3-2 PERIOD 12/28/10 02/01/11 2.5 +/- 0.7 (1) 02/01/11 03/01/11 1.0 +/- 0.6 03/01/11 03/29/11 < 0.6 03/29/11 05/03/11 < 0.4 05/03/11 05/31/11 < 0.8 05/31/11 06/28/11 < 0.6 06/28/11 08/02/11 < 0.7 08/02/11 08/30/11 < 0.9 08/30/11 09/27/11 < 0.4 (1) 10/04/11 11/01/11 < 0.8 (1) 11/08/11 11/29/11 < 0.6 (1) 12/06/11 01/03/12 < 0.7 (1)

MEAN 1.8 +/- 2.1

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1

TABLE C-l.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/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 J1-2 12/28/10 -02/01/11 (1) < 5 <5 < 11 < 5 <10 <5 < 8 <5 <5 < 25 <7 02/01/11 - 03/01/11 (1) < 5 <6 < 10 <5 <11 <5 <9 <4 <5 < 29 < 13 03/01/11 - 03/29/11 (1) < 1 <2 <3 <1 <3 <2 <3 <1 <2

• 14 <4 03/29/11 - 05/03/11 < 1 <1 <3 <1 <2 <1 <2 <1 <1 < 17 <6 05/03/11 - 05/31/11 < 2 <2 <4 <2 <3 <2 <4 <1 <2 < 21 <7 05/31/11 - 06/28/11 < 4 <4 <8 <4 <7 <5 <7 <4 <4 < 29 <9 06/28/11 - 08/02/11 < 4 <6 < 11 <5 <11 <5 <8 <6 <6 < 23 <6 08/02/11 - 08/30/11 < 6 <6 <9 <6 <11 <6 <9 <5 <5 < 27 <7 08/30/11 - 09/27/11 (1) < 5 <5 <11 <6 <10 <5 < 10 <5 <6 < 24 <7 09/27/11 - 11/01/11 < 7 <7 < 15 <6 <16 <8 < 12 <7 <7

• 40 < 12 11/01/11 - 11/29/11 <4 <4 <9 <5 <10 <5 <8 <4 <5 < 24 <8 11/29/11 - 01/03/12 (1) <5 <6 < 12 <5 <14 <7 < 10 <6 <6

• 32 <9 MEAN Q9-1 12/28/10 - 02/01/11 < 6 <5 < 12 <5 <10 <6 <9 <4 <4 < 27 <9 02/01/11 - 03/01/11 < 3 <4 <7 <3 <7 <4 <7 <4 <4 < 28 <8 03/01/11 - 03/29/11 < 2 <2 <4 <2 <3 <2 <4 <2 <2 < 17 <5 03/29/11 - 05/03/11 < 1 <1 <2 <1 <1 <1 <1 <1 <1 < 12 <3 05/03/11 - 05/31/11 < 1 <1 <2 <1 <2 <1 <2 <1 <1 < 12 <3 05/31/11 - 06/28/11 < 4 <4 <9 <4 <7 <5 <7 <4 <4 < 28 < 10 06/28/11 - 08/02/11 < 5 <6 < 14 < 5 <9 <4 < 11 <5 <5 < 21 <8 08/02/11 - 08/30/11 < 5 <6 <9 <6 <10 <6 <9 <5 <4

• 29 < 10 08/30/11 - 09/27/11 < 4 <4 <9 <4 <8 <4 <8 <4 <5 < 22 <6 09/27/11 - 11/01/11 < 5 <6 < 13 <5 <9 <6 < 11 <6 <8 < 27 < 14 11/01/11 - 11/29/11 < 5 <6 < 11 <7 <14 <6 < 11 <6 <6 < 26 < 10 11/29/11 -01/03/12 < 7 <6 < 13 <6 <9

<12 < 13 <6 <7

• 31 < 10 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/28/10 - 02/01/11 < 3.4 < 3.6 < 3.4 02/01/11 - 03/01/11 2.5 +/- 1.6 < 2.2 < 2.1 03/01/11 - 03/29/11 < 3.3 < 3.0 < 2.9 03/29/11 - 05/03/11 < 3.4 < 3.2 < 3.0 05/03/11 - 05/31/11 3.2 +/- 1.5 < 1.9 < 1.8 05/31/11 - 06/28/11 < 3.3 < 3.3 < 3.2 06/28/11 - 08/02/11 < 2.4 < 2.5 < 2.4 08/02/11 - 08/30/11 < 3.2 < 3.2 < 3.1 08/30/11 - 09/27/11 3.1 +/- 0.8 2.8 +/- 0.8 2.0 +/- 0.7 09/27/11 - 11/01/11 < 2.3 < 2.1 < 1.6 11/01/11 - 11/29/11 6.5 +/- 2.2 < 2.8 (1) < 2.7 11/29/11 - 01/03/12 3.1 +/- 1.5 < 2.0 < 2.0 MEAN 3.7 +/- 3.2 -

TABLE C-II.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/28/10 - 02/01/11 < 0.4 < 0.7 < 0.4 02/01/11 - 03/01/11 < 0.5 < 0.5 < 0.9 03/01/11 - 03/29/11 < 0.6 < 0.6 < 0.5 03/29/11 - 05/03/11 < 0.8 < 0.6 < 0.6 05/03/11 - 05/31/11 < 0.5 < 0.6 < 0.6 05/31/11 - 06/28/11 < 0.6 < 0.7 < 0.6 06/28/11 - 08/02/11 < 0.7 < 0.7 < 0.7 08/02/11 - 08/30/11 < 0.9 < 0.9 < 0.8 08/30/11 - 09/27/11 < 0.6 < 0.5 < 0.6 09/27/11 - 11/01/11 < 0.9 < 0.9 < 0.7 11/01/11 - 11/29/11 < 0.5 < 0.7 (1) < 0.7 11/29/11 - 01/03/12 < 0.5 < 0.9 < 0.5 MEAN TABLE C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 ppl~fll(r PERIOD 12/28/10 U2/01/11 < 167 < 168 < 170 02/01/11 03/01/11 < 166 230 +/- 113 < 165 03/01/11 03/29/11 184 +/- 116 < 172 < 173 03/29/11 05/03/11 < 187 < 189 < 189 05/03/11 05/31/11 < 165 < 164 < 168 05/31/11 06/28/11 < 175 < 178 < 175 06/28/11 08/02/11 < 175 < 174 < 179 08/02/11 08/30/11 < 169 < 173 < 171 08/30/11 09/27/11 < 189 < 190 < 186 09/27/11 11/01/11 < 195 < 195 < 196 11/01/11 11/29/11 < 165 < 162 (1) < 162 11/29/11 01/03/12 < 200 < 198 < 195 MEAN THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-137 Ba-140 La-140 PERIOD G15-2 12/28/10 - 02/01/11 <4 <4 <9 <4 7 <4 <7 <3 <4 < 19 <5 02/01/11 - 03/01/11 <2 <3 <7 <3 6 <4 <5 <3 <3 < 21 <6 03/01/11 - 03/29/11 <1 <2 <3 <1 3 <2 <3 <1 <2 < 14 <4 03/29/11 - 05/03/11 <1 <2 <3 <1 2 <2 <3 <1 <1 < 22 <7 05/03/11 - 05/31/11 <3 <3 <7 <2 5 <3 <5 <2 <2

• 24 <9 05/31/11 - 06/28/11 <6 <7 < 14 <7 13 <7 < 13 <6 <7 < 41 < 14 06/28/11 - 08/02/11 <5 <5 < 12 <6 10 <7 <9 <6 <5 < 27 <5 08/02/11 - 08/30/11 <6 <6 < 12 <6 11 <6 < 12 <4 <6 < 28 <6 08/30/11 - 09/27/11 <7 <9 < 16 <8 15 <9 < 12 <7 <8 < 41 < 12 09/27/11 - 11/01/11 <4 <4 < 12 <5 11 <5 <9 <5 <6 < 22 <9 11/01/11 - 11/29/11 <4 <4 < 11 <5 12 <5 <9 <5 <6 < 21 <8 11/29/11 - 01/03/12 <6 <7 < 13 <8 18 <6 < 11 <6 <7 < 31 <9 MEAN G15-3 12/28/10 02/01/11 <4 <3 <7 <4 <5 <2 <5 <3 <3 < 21 <5 02/01/11 03/01/11 <5 <4 < 12 <4 <6 <4 <6 <5 <5 < 29 < 10 03/01/11 03/29/11 <2 <2 <4 <2 <3 <2 <3 <2 <2 < 16 <5 03/29/11 05/03/11 <1 <2 <3 <1 <2 <1 <2 <1 <1 < 20 <6 05/03/11 05/31/11 <2 <2 <4 <1 <4 <2 <4 <2 <2 < 24 <6 05/31/11 06/28/11 <5 <5 <9 <4 <8 <6 <8 <5 <5

• 36 < 13 06/28/11 08/02/11 <6 <6 < 13 <6 < 13 <7 < 11 <6 <6 < 26 <7 08/02/11 08/30/11 <5 <6 < 13 <6 < 10 <5 < 12 <6 <6 < 26 <6 08/30/11 09/27/11 <5 <5 < 10 <5 < 10 <6 <9 <4 <5 < 24 <6 09/27/11 11/01/11 <6 <6 < 12 <6 < 11 <7 <11 <6 <6 < 29 <8 11/01/11 11/29/11 (1) <4 <4 <8 <4 <8 <4 <6 <4 <4 < 19 <5 11/29/11 01/03/12 <8 <9 < 20 < 11 < 21 < 10 < 17 < 8 <9 <42 < 14 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANTION

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/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 Q9-1 12/28/10 02/01/11 <4 <3 <6 <4 <8 <4 <5 <4 <3 <18 <2 02/01/11 03/01/11 <3 <4 <9 <5 <8 <3 <6 <4 <5 < 29 < 10 03/01/11 03/29/11 <2 <2 <4 <2 <3 <2 <3 <2 <2 < 16 <4 03/29/11 05/03/11 <1 <1 <3 <1 <2 <1 <2 <1 <1 < 17 <6 05/03/11 05/31/11 <2 <2 <4 <1 <4 <3 <4 <2 <2 < 22 <5 05/31/11 06/28/11 <6 <5 <8 <4 < 10 <7 <9 <5 <6 < 40 < 15 06/28/11 08/02/11 <6 <7 < 14 <7 < 14 <7 < 11 <7 <7 < 27 < 14 08/02/11 08/30/11 <5 <5 < 11 <6 <9 <5 <8 <5 <5 < 23 <9 08/30/11 09/27/11 <4 <4 < 11 <4 <9 <6 <10 <5 <5 < 24 <8 09/27/11 11/01/11 <5 <5 < 13 <7 <13 <6 <11 <5 <6 < 25 <9 11/01/11 11/29/11 <5 <5 < 11 <5 <10 <6 <9 <5 <5 < 22 <9 11/29/11 01/03/12 <7 <7 < 16 <4 <12 <7 <11 <6 <7 < 30 < 11 MEAN

TABLE C-II1.1 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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION GR-B 1-131 H-3 SR-89 SR-90 PERIOD 12/28/10 - 02/01/11 < 3.8 1.4 + 0.5 5810 +/- 657 < 4.2 < 0.6 02/01/11 - 03/01/11 4.2 +/- 1.8 < 0.4 77200 +/- 7740 03/01/11 - 03/29/11 6.7 +/- 2.3 < 0.6 982 +/- 149 03/29/11 - 05/03/11 4.0 +/- 2.2 < 0.5 3700 +/- 426 05/03/11 - 05/31/11 4.3 +/- 1.6 < 0.9 4700 +/- 513 05/31/11 - 06/28/11 7.6 +/- 2.6 < 0.9 30300 +/- 3070 06/28/11 - 08/02/11 3.6 +/- 2.0 < 0.6 19400 +/- 1980 < 3.7 < 0.7 08/02/11 - 08/30/11 8.5 +/- 2.6 < 0.8 6540 +/- 702 08/30/11 - 09/27/11 10.7 +/- 1.4 < 0.5 60500 +/- 6020 09/27/11 - 11/01/11 5.2 +/- 1.3 < 0.7 12100 +/- 1260 11/01/11 - 11/29/11 < 2.7 < 0.6 < 164 11/29/11 - 01/03/12 3.2 +/- 1.4 < 0.7 2930 +/- 352 MEAN 5.8 +/- 5.0 - 20378 +/- 51438

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-6

TABLE C-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/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 12/28/10 - 02/01/11 <4 <5 < 10 <5 < 11 <4 < 10 <5 <6 < 29 <8 02/01/11 - 03/01/11 <4 <5 < 11 <4 <6 <4 <7 <4 <4 < 30 <7 03/01/11 - 03/29/11 <2 <2 <4 <2 <3 <2 <3 <2 <2 < 17 <5 03/29/11 - 05/03/11 <1 <1 <2 <1 <2 <1 <2 <1 <1 < 15 <4 05/03/11 - 05/31/11 <2 <2 <5 <2 <5 <3 <4 <2 <2 < 26 <5 05/31/11 - 06/28/11 <5 <7 < 12 <6 < 12 <8 < 11 <6 <6 < 45 < 14 06/28/11 - 08/02/11 <6 <6 < 13 <6 < 12 <5 < 11 <6 <6 < 21 <7 08/02/11 - 08/30/11 <6 <5 <9 <5 < 12 <5 < 10 <5 <5 < 24 <7 08/30/11 - 09/27/11 <4 <4 <9 <4 <6 <4 <6 <4 <4 < 22 <6 09/27/11 - 11/01/11 <4 <4 <9 <4 <7 <4 <7 <4 <4 < 21 <5 11/01/11 - 11/29/11 <7 <7 < 16 <5 < 10 <6 < 11 <6 <8 < 37 <8 11/29/11 - 01/03/12 <6 <8 <12 <7 <15 <6 <12 <7 <6 <28 < 12 MEAN

TABLE C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Sr-90 PERIOD INDP PREDATOR 06/06/11 <3 10/04/11 <3 MEAN INDB BOTTOM FEEDER 06/06/11 <3 10/04/11 MEAN BKGP PREDATOR 06/08/11 <4 10/07/11 <3 MEAN BKGB BOTTOM FEEDER 06/08/11 <4 10/07/11 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, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs- 137 PERIOD BKGB BOTTOM FEEDER 06/08/11 3290 +/- 1110 < 74 < 97 < 208 < 77 < 146 < 72 < 79 10/07/11 2110 +/- 794 < 48 < 50 < 82 < 45 < 99 < 49 < 42 MEAN 2700 +/- 1669 -

BKGP PREDATOR 06/08/11 2920 +/- 1010 < 78 < 65 < 168 < 90 < 135 < 68 < 77 10/07/11 3120 +/- 785 < 38 < 39 < 83 < 51 < 84 < 42 < 44 MEAN 3020 +/- 283 -

INDB BOTTOM FEEDER 06/06/11 3230 +/- 856 < 61 < 67 < 185 < 61 < 96 < 56 < 56 10/04/11 1310 +/- 798 < 74 < 74 < 162 < 63 < 155 < 65 < 59 MEAN 2270 +/- 2715 -

INDP PREDATOR 06/06/11 3730 +/- 1150 < 95 < 96 < 226 < 78 < 186 < 97 < 102 10/04/11 2970 +/- 904 < 65 < 65 < 150 < 71 < 128 < 67 < 73 MEAN 3350 +/- 1075

TABLE C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/KG DRY + 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-i134 Cs-137 PERIOD A1-3 06/17/11 8580 +/- 1580 < 93 < 85 < 95 < 86 < 88 11/08/11 11000 +/- 2050 < 123 < 119 < 122 < 110 < 142 MEAN 9790 +/- 3422 EDCB 11/08/11 15600 +/- 2090 < 109 < 96 < 128 < 102 306 +/- 144 MEAN J2-1 06/17/11 14400 +/- 1860

• 83 < 96 < 74 < 66 < 105 11/08/11 17600 +/- 2530

• 116 < 108 < 117 < 98

• 133 MEAN 16000 +/- 4525 K1-3 06/17/11 13500 +/- 1760 < 81 < 95 < 112 < 83 187 +/- 75 11/08/11 12400 +/- 1430 < 31 < 20 < 30 < 21 < 36 MEAN 12950 +/- 1556

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-10

TABLE C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUPI I GROUPI11 GROUP III PERIOD E11-2 F1 A3-1 G2- I H3-1 Mz-1 Q1S-1 12/29/10 -01/05/11 26 +/- 4 39 +/- 5 36 +/- 5 38 +/- 5 35 +/- 5 41 +/- 5 43 +/- 5 01/05/11 -01/12/11 25 +/-6 29 +/-6 28 +/-6 28 +/-6 29 +/-6 27 +/-6 24+/- 6 01/12/11 -01/19/11 11 +/- 5 14 +/- 5 11 +/- 5 10 +/- 5 18 +/- 6 14 +/- 5 16 +/- 5 01/19/11 -01/26/11 17 +/- 6 25 +/- 6 22 +/- 6 21 +/- 6 (1) 23 +/- 6 29 +/- 6 01/26/11 -02/02/11 17 +/- 5 21 +/- 6 16 +/- 5 20 +/- 6 14 +/- 5 19 +/- 5 21 +/- 6 02/02/11 -02/09/11 7 +/- 5 17 +/- 5 17 t 5 9 +/- 5 13 +/- 5 18 +/- 5 17 +/- 5 02/09/11 -02/16/11 13 +/- 5 18 +/- 5 15 +/- 5 18 +/- 5 17 +/- 5 18 +/- 5 23 +/- 6 02/16/11 -02/23/11 15 +/- 5 16 +/- 5 20 t 5 20 +/- 5 21 +/- 5 22 +/- 5 17 +/- 5 02/23/11 -03/02/11 9 +/- 5 15 +/- 5 18 +/- 5 16 +/- 5 (1) 18 +/- 5 18 +/- 5 20 +/- 5 03/02/11 -03/08/11 <8 12 +/- 6 15 +/- 6 (1) < 8 10 +/- 6 11 +/- 6 9 +/- 6 03/08/11 -03/16/11 9 +/- 4 11 +/- 4 17 +/- 11 < 6 11 +/- 4 10 +/- 4 14 +/- 5 03/16/11 -03/23/11 15 +/- 6 24 +/- 6 22 +/- 6 24 +/- 6 23 +/- 6 25 +/- 6 33 +/- 7 03/23/11 -03/30/11 23 +/-6 27 +/-6 23 +/-6 88 +/-9 35 +/-7 26 +/-6 32+/- 7 03/30/11 -04/06/11 19 +/- 6 (1) 28 +/- 7 31 +/- 7 28 +/- 7 31 +/- 7 25 +/- 6 26 +/- 6 04/06/11 -04/13/11 12 +/- 5 20 +/- 6 19 +/- 6 17 +/- 6 17 +/- 6 17 +/- 6 19 +/- 6 04/13/11 -04/20/11 12 +/- 5 (1) 15 +/- 5 15 +/- 5 17 +/- 5 17 +/- 5 19 +/- 5 15 +/- 5 04/20/11 -04/27/11 11 +/- 6 (1) 12 +/- 6 11 +/- 6 13 +/- 6 13 +/- 6 13 +/- 6 11 +/- 6 04/27/11 -05/04/11 11 +/- 6 (1) 11 +/- 6 12 +/- 6 9 +/- 6 <8 11 +/- 6 9 +/- 6 05/04/11 -05/11/11 9 +/- 5 14 +/- 5 18 +/- 5 15 +/- 5 16 +/- 5 14 +/- 5 13 +/- 5 05/11/11 -05/18/11 <7 9 +/- 5 <7 < 7 7 +/- 5 8 +/- 5 10 +/- 5 05/18/11 -05/25/11 16 +/- 5 12 +/- 5 14 +/- 5 14 +/- 5 9 +/- 5 11 +/- 5 11 +/- 5 05/25/11 -06/01/11 21 +/- 6 24 +/- 6 21 +/- 6 26 +/- 7 22 +/- 6 24 +/- 6 22 +/- 7 06/01/11 -06/08/11 22 +/- 5 20 +/- 5 24 +/- 5 24 +/- 6 21 +/- 5 23 +/- 5 19 +/- 5 06/08/11 -06/15/11 10 +/- 5 17 +/- 5 15 +/- 5 16 +/- 5 17 +/- 5 15 +/- 5 18 +/- 6 06/15/11 -06/22/11 15 +/- 5 13 +/- 5 19 +/- 5 18 +/- 5 16 +/- 5 19 +/- 5 23 +/- 6 06/22/11 -06/29/11 10 +/- 5 15 +/- 5 15 +/- 5 12 +/- 5 16 +/- 5 14 +/- 5 16 +/- 5 06/29/11 -07/06/11 17 +/- 5 22 +/- 5 22 +/- 5 24 +/- 5 19 +/- 5 18 +/- 5 22 +/- 6 07/06/11 -07/13/11 17.+/- 5 26 +/-6 22 +/-14 (1) 23 +/-6 24 +/-6 24 +/-6 19+/- 6 07/13/11 -07/20/11 15 +/- 5 14 +/- 5 17 +/- 5 16 +/- 5 15 +/- 5 16 +/- 5 17 +/- 5 07/20/11 -07/27/11 20 +/-6 20 +/-6 26 +/-6 26 +/-6 22 +/-6 25 +/-6 16+/- 6 07/27/11 -08/03/11 16 +/- 6 25 +/- 6 25 +/- 6 21 +/- 6 23 +/- 6 22 +/- 6 22 +/- 6 08/03/11 -08/10/11 16 +/- 5 12 +/- 5 13 +/- 5 16 +/- 5 16 +/- 5 17 +/- 5 14 +/- 5 08/10/11 -08/17/11 17 +/- 5 12 +/- 5 16 +/- 5 16 +/- 5 17 +/- 5 16 +/- 5 16 +/- 5 08/17/11 -08/24/11 21 +/- 6 18 +/- 6 14 +/- 6 19 +/- 6 21 +/- 6 16 +/- 6 24 +/- 7 08/24/11 -08/31/11 16 +/- 6 11 +/- 6 < 13 (1) 9 +/- 5 12 +/- 6 12 +/- 5 11 +/- 6 (1) 08/31/11 -09/10/11 22 +/- 5 20 +/- 5 (1) 19 +/- 5 20 +/- 5 19 +/- 5 (1) 17 +/- 4 (1) 09/08/11 -09/14/11 20 +/- 7 11 +/- 6 (1) 18 +/- 7 16 +/- 7 (1) 35 +/- 11 (1) 09/14/11 -09/21/11 13 +/- 5 16 +/- 5 17 +/- 5 14 +/- 5 11 +/- 5 14 +/- 5 16 +/- 5 09/21/11 -09/28/11 9 +/- 5 11 +/- 5 11 +/- 5 12 +/- 5 15 +/- 6 17 +/- 6 13 +/- 6 09/28/11 -10/05/11 10 +/- 5 11 +/- 5 < 7 12 +/- 5 11 +/- 5 10 +/- 5 < 7 10/05/11 -10/12/11 26 +/- 6 22 +/- 6 30 +/- 6 32 +/- 6 26 +/- 6 29 +/- 6 29 +/- 6 10/12/11 -10/19/11 13 +/- 5 14 +/- 5 12 +/- 5 13 +/- 5 14 +/- 5 12 +/- 5 17 +/- 6 10/19/11 -10/26/11 10 +/- 6 11 +/- 6 15 +/- 6 11 +/- 5 11 +/- 6 17 t 6 16 +/- 6 10/26/11 -11/02/11 23 +/- 6 (1) 15 +/- 6 17 +/- 6 (1) 17 +/- 6 (1) 18 +/- 6 21 +/- 6 18 +/- 6 11/02/11 -11/09/11 15 +/- 6 16 +/- 6 20 +/- 6 20 +/- 6 16 +/- 6 21 +/- 6 21 +/- 6 11/09/11 -11/16/11 15 +/- 6 18 +/- 6 27 +/- 7 25 +/- 6 26 +/- 6 23 +/- 6 24 +/- 7 11/16/11 -11/22/11 16 +/- 5 (1) 19 +/- 7 21 +/- 7 17 +/- 7 18 +/- 7 19 +/- 7 19 +/- 7 11/22/11 -11/30/11 8 +/- 4 11 +/- 5 13 +/- 5 10 +/- 4 8 +/- 4 9 +/- 4 11 +/- 5 11/30/11 -12/07/11 14 +/- 6 (1) 12 +/- 5 15 +/- 5 12 +/- 5 15 +/- 5 14 +/- 5 17 +/- 5 12/07/11 -12/14/11 25 +/- 8 24 +/- 6 19 +/- 5 25 +/- 6 21 +/- 5 20 +/- 5 29 +/- 6 12/14/11 -12/21/11 31 +/- 6 27 +/- 6 24 +/- 6 28 +/- 6 31 +/- 6 28 +/- 6 27 +/- 6 12/21/11 -12/28/11 15 +/- 5 16 +/- 5 24 +/- 6 19 +/- 5 16 +/- 5 1S +/- 5 19 +/- 6 MEAN 16 +/-11 18 +/-13 19 +/-11 20 +/-24 18 +/-13 18 +/-12 20 +/-14

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 I

TABLE C-VI.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS INAIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - CLOSSEST TO THE SITE BOUNDARY GROUP II - INTERMEDIATE OFFSITE GROUP III- CONTROL LOCATIONS COLLECTION MIN MAX MEAN+ COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN +

PERIOD 2SD PERIOD 2SD PERIOD 2SD 12/29/10 - 02/02,/1 1 11 39 22 + 16 12/29/10 02/02/11 10 41 24 +/- 18 12/29/10 - 02/02/11 16 43 27 +/- 21 02/02/11 - 03/02,/11 7 18 14 +8 02/02/11 03/02/11 9 22 17 +/- 6 02/02/11 03/02/11 17 23 19 +/- 6 03/02/11 - 03/30 /11 9 27 17 +/- 15 03/02/11 03/30/11 10 88 24 +/- 39 03/02/11 03/30/11 9 33 22 +/- 24 03/30/11 - 04/27,/11 11 28 16 + 12 03/30/11 04/27/11 11 31 19 +/- 13 03/30/11 04/27/11 11 26 18 +/- 13 04/27/11 - 06/01 /11 9 24 14 +11 04/27/11 06/01/11 7 26 15 +/- 11 04/27/11 06/01/11 9 22 13 +/- 10 06/01/11 - 06/29 /11 10 22 15 +9 06/01/11 06/29/11 12 24 18 +/- 7 06/01/11 06/29/11 16 23 19 +/- 6 06/29/11 - 08/03 /11 14 26 19 +/-8 06/29/11 08/03/11 15 26 22 +/- 7 06/29/11 08/03/11 16 22 19 +/- 6 08/03/11 - 08/31 /11 11 21 15 +7 08/03/11 08/31/11 9 21 15 +/- 6 08/03/11 08/31/11 11 24 16 +/- 11 08/31/11 - 09/28 '11 9 22 15 + 10 08/31/11 09/28/11 11 20 16 +/- 6 08/31/11 09/28/11 13 35 20 +/- 21 09/28/11 - 11/02/'11 10 26 16 +/-12 09/28/11 11/02/11 10 32 17 +/- 14 10/05/11 11/02/11 16 29 20 +/- 12 11/02/11 - 11/30//11 8 19 15 +7 11/02/11 11/30/11 8 27 18 +/- 12 11/02/11 11/30/11 11 24 19 +/- 11 11/30/11 - 12/28//11 12 31 21 + 14 11/30/11 12/28/11 12, 31 20 +/- 11 11/30/11 12/28/11 17 29 23 +/- 12 12/29/10 - 12/28/11 7 39 17 +/- 12 12/29/10 - 12128/11 7 88 19 +/- 16 12/29/10 - 12/28/11 9 43 20 +/- 14

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-VI.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 PERIOD A3-1 12/29/10 - 03/30/11 81 +/- 32 <3 <5 <3 <4 <7 <3 <3 03/30/11 - 06/29/11 66 +/- 40 <4 <5 <3 <6 <9 <4 <3 06/29/11 - 09/28/11 66 t 47 <3 <5 <3 <4 <9 <4 <4 09/28/11 - 12/28/11 25 +/- 8 <1 <1 <1 <1 <2 <1 <1 MEAN 60 +/- 48 E1-2 12/29/10 03/30/11 78 +/- 36 <3 <5 <3 <5 < 10 <3 <3 03/30/11 06/29/11 71 +/- 30 <3 <4 <3 <4 <8 <4 <2 06/29/11 09/28111 74 +/- 26 <3 <3 <3 <3 <5 <3 <3 09/28/11 12/28/11 33 +/- 9 <1 <2 <1 <2 <3 <1 <1 MEAN 64 +/- 42 F1-3 12/29/10 03/30/11 90 +/- 40 <3 <4 <4 <5 <9 <3 <4 03/30/11 06/29/11 92 +/- 36 <3 <4 <4 <5 < 10 <5 <4 06/29/11 09/28/11 55 +/- 28 <3 <3 <3 <3 <8 <4 <3 09/28/11 12/28/11 32 +/- 7 <1 <1 <1 <1 <2 <1 <1 MEAN 67 +/- 58 G2-1 12/29/10 03/30/11 65 +/- 38 <3 <5 <3 <5 <8 <4 <4 03/30/11 06/29/11 60 +/- 36 <4 <5 <4 <6 <10 <5 <4 06/29/11 09/28/11 65 +/- 25 <3 <4 <3 <4 <7 <3 <3 09/28/11 12/28/11 30 +/- 8 <1 <1 <1 <1 <2 <1 <1 MEAN 55 +/- 33 H3-1 12/29/10 03/30/11 64 +/- 42 <3 <5 <3 <6 <8 <3 <3 03/30/11 06/29/11 44 +/- 26 <2 <3 <2 <3 <4 <2 <2 06/29/11 09/28/11 52 +/- 23 <2 <4 <3 <4 <7 <3 <3 09/28/11 12/28/11 33 +/- 11 <1 <1 <1 <1 <2 <1 <2 MEAN 49 +/- 26 M2-1 12/29/10 03/30/11 65 +/- 30 <2 <4 <2 <4 <5 <3 <3 03/30/11 06/29/11 82 +/- 33 <3 <4 <3 <5 <7 <4 <3 06/29/11 09/28/11 56 +/- 32 <3 <4 <4 <5 <7 <4 <3 09/28/11 12/28/11 42 +/- 13 <2 <1 <1 <1 <3 <1 <1 MEAN 61 +/- 33 Q15-1 03/08/11 - 03/16/11 < 249 < 28 < 28 < 23 < 23 < 49 < 32 < 28 03/16/11 - 03/23/11 < 317 < 35 < 32 < 37 < 39 < 67 < 36 < 36 03/23/11 - 03/30/11 < 268 < 41 < 33 < 40 < 28 < 57 < 32 < 33 03/30/11 - 04/06/11 < 280 < 41 < 38 < 46 < 31 < 53 < 40 < 47 04/06/11 - 04/13/11 < 250 < 35 < 25 < 41 < 30 < 51 < 28 < 32 12/29/10 - 03/30/11 84 +/- 35 <4 <5 <4 <6 < 10 <3 <3 03/30/11 - 06/29/11 62 +/- 23 <3 <3 <3 .4 < 5 <3 <3 06/29/11 - 09/28/11 60 +/- 23 <3 <3 <3 4 < 6 <3 <3 09/28/11 - 12/28/11 38 +/- 11 <1 <2 <2 .2 < 3 <1 <1 MEAN 61 +/- 38

• THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT C-13

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP 11 IGROUP III

-PERIOD El -2 Fl-3 A3-1 G2-1 H3-1 M2-1 Q15-1 12/29/10 -01/05/11

• 53

• 54

• 67

• 55

• 54 <67 01/05/11 -01/12/11

• 39 *<40

• 55

• 22

• 40

• 52 < 56

• 30

• 31

• 30

• 31

• 31

• 29 <<30 01/12/11 -01/26/11

• 29 *<30

• 34

• 30 (1) < I( <<34 01/26/11 -02/02/11

• 22

• 23

• 32

• 23 *<23 < 3: 2 < 33 02/02/11 -02/09/11

• 40 *<41

• 38 *<41

• 38 < 318 < 29 02/09/11 -02/16/11 < 47

• 48

• 65 *<48

• 48 <6 3 < 65 02/16/11 -02/23/11

• 34

• 35

• 18

• 35 *<41 < 4( 0 < 41 02/23/11 -03/02/11

• 53

• 54

• 64 < 55 (1)

• 55 <6 3 < 65 03/02/11 -03/08/11

• 65

• 28 < 61 (1)

• 67

• 66 < 6(0 < 61 03/08/11 -03/16/11 < 26

• 27

• 32

• 27

• 27

• 12 < 13 03/16/11 -03/23/11

• 26 55 +/- 36

• 52 44 +/- 33 45 +/- 30 69+/-t41 57 +/-27 03/23/111- 03/30/11 60 +/-30 42 +/- 26 51 +/- 29 *<56 64 +/- 18 37 +/-26 87 +/-41 03/30/11 -04/06/11

• 47 (1) 74 +/- 30 60 +/- 24 48 +/- 24 65 +/- 35 67+/-t28 71 +/-44 04/06/11 -04/13/11 38 +/- 21

• 37 39 +/- 20

• 48

• 31

• 31 <

<42 04/13/11 -04/20/11 *<51 (1)

• 52

• 54

• 53

• 23 < 5: 3 < 55 04/20/11 -04/27/11

• 58 (1)

• 55

• 68

• 55

• 69 < 316 < 68 04/27/11 -05/04/11

• 69 (1)

• 63

• 58

• 64 *<63 < 51 8 < 60 05/04/11 -05/11/11

• 52

• 52

• 39

• 53

• 39 < 313 < 39 05/11/11 -05/18/11

• 42

• 43

• 57

• 43

• 42 < 5( 6 < 57 05/18/11 -05/25/11

• 21

• 21

• 22

• 21

• 20 < 2 2 < 23 05/25/111 06/01/11 *<53 < 55 < 59

• 55 *<60 <5.7 < 62 06/01/11 -06/08/11 < 63

• 65

• 64

• 65 *<64 < 6: 3 < 65 06/08/11 -06/15/11

• 42

• 57

• 56

• 43 < 43 < 5~

06/15/11 -06/22/11

• 50

• 52

• 69

• 52

• 52 < 6;7 < 69 06/22/11 -06/29/11 *<28

• 59

• 67

• 60

• 59 < 616 < 67 06/29/11 -07/06/11

• 46

• 47

• 65

• 45 *<46 < 6:2 < 66 07/06/11 -07/13/11

• 58

• 59

• 112 (1)

• 34

• 59 < 5I6 < 41 07/13/11 -07/20/11

• 54

• 55

• 50

• 53

• 55 <4 3 < 51 07/20/11 -07/27/11 *<28

• 29

• 36

• 28

• 16 < 3~ 5 < 36 07/27/11 -08/03/11

• 29

• 29

• 30

• 28 *<29 < 219 < 31 08/03/11 -08/10/11

• 41

• 42

• 60

• 40

• 60 < 2~5 < 60 08/10/11 -08/17/11

• 27

• 28

• 23

• 27

• 28 < 2: 2 < 23 08/17/11 -08/24/11

• 50

• 51

• 51

• 48

• 51 < 419 < 28 08/24/11 -08/31/11

• 43

• 44 *<64 (1)

• 42 < 44 < 313 < 43 (1) 08/31/11 -09/10/11

• 38

• 16 (1)

• 37

• 38 5 (1) < 26 (1) 09/08/11 -09/14/11 < 40

• 41 (1)

• 39

• 41 1) < 62 (1)

<4 09/14/11 -09/21/11

• 19

• 36 < 49

• 35

• 36 5 <47 09/21/11 -09/28/11

• 47

• 48

• 51 *<46

• 48 9 < 51 09/28/11 -10/05/11

• 57

• 58

• 63

• 30

• 57 < 61 < 63 10/05/11 -10/12/11

• 50

• 51

• 61 < 49

• 51 < 51 8 < 61

• 68

• 70 *<66

• 66 *<29 < 6' 4 < 66 10/19/11 -10/26/11

• 25

• 25

• 35

• 24

• 25 < 3' 4 < 36 10/26/11 -11/02/111

• 68 (1)

• 66 < 57 (1)

• 66 (1)

• 56 < 2:3 < 56

• 53

• 54

• 52

• 52

• 54 <4 9 < 52

• 65

• 66

• 55

• 63

• 55 < 5:3 < 31 11/302/11 -12/07/11

• 69 (1)

• 42

• 67

• 41

• 43 < 6' 4 < 67

• 49

• 50 < 45 < 47

• 43 <4 3 < 44

• 52 (1)

• 39

• 51

• 37 *<40 <4 9 < 52 12/07/11 -12/14/11

• 69

• 27

• 57

• 47 < 49 < 5I5 < 57

• 33

• 33 *<41

• 32

• 33 < 3' 9 < 41 12/214/11 -12/28/11

• 22

• 53 *<49

• 51

• 53 7 < 49 MEAN 49 +/-30 57 +/-32 50 +/-21 46 +/-6 58 +/-23 58 +/-36 71 +/-30

• THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-14

TABLE C-VIII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDICATOR FARM COLLECTION K1 5-3 E2-2 F4-1 G2-1 P4-1 PERIOD 01/05/11 < 0.6 < 0.6 < 0.5 < 0.6 < 0.5 02/02/11 < 0.3 < 0.5 < 0.3 < 0.4 < 0.4 03/02/11 < 0.6 < 0.6 < 0.4 < 0.7 < 0.4 03/16/11 < 0.5 < 0.5 < 0.6 < 0.5 < 0.7 03/23/11 < 0.7 03/30/11 < 0.6 < 0.6 < 0.5 < 0.8 < 0.7 04/06/11 < 0.4 04/13/11 < 0.4 < 0.5 < 0.3 < 0.4 < 0.3 04/20/11 < 0.4 04/27/11 < 0.5 < 0.4 < 0.4 < 0.5 < 0.5 05/11/11 < 0.6 < 0.7 < 0.4 < 0.6 < 0.4 05/25/11 < 0.3 < 0.3 < 0.2 < 0.3 < 0.6 06/08/11 < 0.6 < 0.9 < 0.6 < 0.8 < 0.7 06/22/11 < 0.8 < 0.7 < 0.7 < 0.7 < 0.7 07/06/11 < 0.9 < 0.9 < 1.0 < 0.9 < 0.8 07/20/11 < 0.6 < 0.7 < 0.8 < 0.7 < 0.6 08/03/11 < 0.5 < 0.5 < 0.4 < 0.5 < 0.5 08/17/11 < 0.5 < 0.6 < 0.4 < 0.5 < 0.6 08/31/11 < 0.6 < 0.7 < 0.6 < 0.7 < 0.8 09/14/11 < 0.6 < 0.6 < 0.5 < 0.7 < 0.8 09/28/11 < 0.6 < 0.6 < 0.5 < 0.6 < 0.5 10/12/11 < 0.4 < 0.4 < 0.4 < 0.4 < 0.4 10/26/11 < 0.6 < 0.8 < 0.9 < 0.7 < 0.7 11/09/11 < 0.8 < 0.8 < 0.7 < 0.9 < 0.7 11/22/11 < 0.6 < 0.7 < 0.6 < 0.7 < 0.7 12/07/11 < 0.8 < 0.8 < 0.5 < 0.7 < 0.7 MEAN BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT C-15

TABLE C-VIII.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA CONTROL FARM I INDICATOR FARM COLLECTION K15-3 P4-1 E2-2 F4-1 G2-1 PERIOD SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 01/05/11 - 03/30/11 < 1.7 < 0.9 < 1.5 < 0.6 < 1.7 < 0.7 < 1.7 < 0.7 < 2.1 < 1.0 03/30/11 - 06/22/11 < 4.5 0.6 +/- 0.4 < 4.4 0.7 +/- 0.4 < 4.9 0.7 +/- 0. 5 < 4.9 < 0.8 < 4.8 < 0.6 07/06/11 - 09/28/11 < 1.7 < 0.4 < 1.8 < 0.5 < 1.7 0.7 +/- 0. 4 < 1.7 < 0.4 < 1.9 < 0.5 09/28/11 - 12/07/11 < 3.1 < 0.6 < 2.9 < 0.6 < 2.9 < 0.6 < 3.6 < 0.7 < 3.3 < 0.9 MEAN

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES

TABLE C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD E2-2 01/05/11 1250 +/- 143 <6 <5

• 27 < 11 02/02/11 1340 +/- 112 <5 <5 < 31 <8 03/02/11 1320 +/- 108 <4 <5

• 38 < 11 03/16/11 1140 +/- 102 <4 <4

• 38 < 13 03/30/11 1290 +/- 175 <6 <7 < 25 <6 04/13/11 1380 +/- 158 <6 <7 < 47 < 14 04/27/11 1270 +/- 121 <4 <5 < 47 < 15 05/11/11 1190 +/- 150 <5 <7 < 28 <9 05/25/11 1230 +/- 123 <5 <6 < 44 <13 06/08/11 1450 +/- 162 <4 <7 < 49 < 11 06/22/11 1300 +/- 150 <5 <6 < 48 < 14 07/06/11 1360 +/- 149 <6 <6 < 32 <8 07/20/11 1530 +/- 159 <6 <6 < 39 <9 08/03/11 1260 +/- 118 <4 <5 < 20 <7 08/17/11 1410 +/- 121 <5 <6 < 27 <7 08/31/11 1260 +/- 141 <5 <5 < 21 <8 09/14/11 1340 +/- 52 <2 <2 < 13 <4 09/28/11 1160 +/- 161 < 11 < 10 < 48 < 11 10/12/11 1150 +/- 148 <5 <6 < 45 <12 10/26/11 1310 +/- 138 <6 <6 < 26 <8 11/09/11 943 +/- 173 <7 <8 < 31 <11 11/22/11 1250 +/- 174 <6 <7 < 37 <8 12/07/11 1200 +/- 162 <7 <8

• 32 <7 MEAN 1275 +/- 241 F4-1 01/05/11 1430 +/- 153 <4 <6 < 35 < 10 02/02/11 1460 +/- 114 <5 <5

• 36 < 12 03/02/11 1530 +/- 126 <5 <6 < 42 < 12 03/16/11 1280 +/- 143 <5 <6 < 53 < 12 03/30/11 1210 +/- 150 <6 <7 < 22 <9 04/13/11 1470 +/- 158 <6 <7

• 46 < 15 04/27/11 1240 +/- 106 <4 <4 < 44 < 13 05/11/11 1310 +/- 127 <6 <6 < 27 <9 05/25/11 1280 +/- 117 <5 <6 < 49 < 15 06/08/11 1430 +/- 150 <5 <6 < 41 <13 06/22/11 1330 +/- 122 <4 <5 < 31 < 10 07/06/11 1390 +/- 167 <7 <7 < 29 <9 07/20/11 1360 +/- 143 <7 <6 < 39 < 11 08/03/11 1460 +/- 160 <7 <7 < 29 <9 08/17/11 1410 +/- 134 <5 <6 < 25 < 10 08/31/11 1370 +/- 126 <5 <5 < 23 <8 09/14/11 1400 +/- 50 <2 <2 < 15 <4 09/28/11 1170 +/- 114 <5 <5 < 27 <9 10/12/11 1380 +/- 118 <5 <5 < 32 < 10 10/26/11 1250 +/- 168 <7 <7 < 37 <11 11/09/11 1310 +/- 184 <8 <9 < 30 <9 11/22/11 1260 +/- 207 <7 <8 < 49 < 15 12/07/11 1380 +/- 180 <7 <7

• 38 <9 MEAN 1353 +/- 185 C-17

TABLE C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD G2-1 01/05/11 1110 +/- 129 <5 <5 < 33 <9 02/02/11 1320 +/- 116 <4 <5 < 31 <9 03/02/11 919 +/- 117 <4 <6 < 41 < 14 03/16/11 1380 +/- 136 <5 <6 < 52 < 13 03/30/11 781 +/- 161 <7 < 10 < 36 < 13 04/13/11 1020 +/- 137 <7 <6 < 49 < 13 04/27/11 1090 +/- 128 <5 <6 < 59 < 15 05/11/11 1030 +/- 132 <7 <7 < 38 < 11 05/25/11 1080 +/- 114 <6 <6 < 59 < 14 06/08/11 781 +/- 109 <5 <6 < 42 < 12 06/22/11 1300 +/- 141 <3 <3 < 21 <6 07/06/11 841 +/- 153 <7 <9 < 31 < 10 07/20/11 793 +/- 151 <7 <6 < 50 < 12 08/03/11 1190 +/- 132 <5 <6 < 30 <9 08/17/11 822 +/- 124 <6 <6 < 30 < 10 08/31/11 966 +/- 105 <5 <5 < 26 <7 09/14/11 1200 +/- 43 <2 <2 < 12 <3 09/28/11 1350 +/- 124 <5 <6 < 28 <7 10/12/11 978 +/- 187 <8 <8 < 47 < 14 10/26/11 1190 +/- 184 <6 <7 < 33 <9 11/09/11 1380 +/- 169 <6 <7 < 37 <8 11/22/11 910 +/- 136 <6 <7 < 35. < 10 12/07/11 745 +/- 156 <6 <8 < 31 < 12 MEAN 1051 +/- 418 P4-1 01/05/11 1380 +/- 149 <6 <6 < 36 <9 02/02/11 1420 +/- 92 <3 <4 < 23 <6 03/02/11 1460 +/- 124 <4 <5 < 33 < 10 03/16/11 1330 +/- 142 <6 <7 < 56 < 11 03/30/11 1670 +/- 198 <8 <8 < 21 <5 04/13/11 1410 +/- 150 <6 <6 < 48 < 15 04/27/11 1390 +/- 122 <4 <5 < 41 < 13 05/11/11 1280 +/- 153 <6 <7 < 30 < 11 05/25/11 1460 +/- 161 <6 <6 < 42 < 12 06/08/11 1300 +/- 130 <5 <5 < 37 < 12 06/22/11 1230 +/- 115 <4 <5 < 32 < 12 07/06/11 1520 +/- 221 <8 <7 < 45 <7 07/20/11 1340 +/- 164 <6 <7 < 42 < 12 08/03/11 1380 +/- 169 <7 <6 < 36 < 11 08/17/11 1110 +/- 147 <5 <6 < 30 <8 08/31/11 1210 +/- 121 <3 <5 < 21 <6 09/14/11 1340 +/- 55 <2 <2 < 13 <4 09/28/11 1180 +/- 159 <7 <8 < 37 < 12 10/12/11 1260 +/- 152 <5 <7 < 42 <8 10/26/11 1380 +/- 150 <7 <8 < 29 <8 11/09/11 1320 +/- 180 <6 <8 < 31 <7 11/22/11 1400 +/- 144 <6 <6 < 26 <7 12/07/11 1480 +/- 226 <7 <8 < 34 < 12 MEAN 1359 +/- 243 C-18

TABLE C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-1 34 Cs-1 37 Ba-140 La-140 PERIOD K15-3 01/05/11 1100 +/- 115 <4 <5 < 27 <7 02/02/11 1260 +/- 102 <4 <4 < 26 <8 03/02/11 1280 +/- 112 <5 <6 < 45 < 14 03/16/11 1320 +/- 136 <5 <6 < 52 < 13 03/23/11 1330 +/- 126 <6 <6 < 25 <7 03/30/11 1290 +/- 180 <7 <9 < 29 <8 04/06/11 1240 +/- 114 <4 <6 <44 < 15 04/13/11 1190 +/- 132 <6 <7 < 42 < 15 04/20/11 1240 +/- 149 <5 <5 < 53 < 11 04/27/11 1110 +/- 95 <3 <4 < 42 < 13 05/11/11 1140 +/- 123 <5 <5 < 23 <7 05/25/11 1380 +/- 96 <3 <4 < 38 < 13 06/08/11 1220 +/- 137 <6 <6 < 45 < 14 06/22/11 1360 +/- 158 <6 <8 < 50 < 15 07/06/11 1240 +/- 145 <6 <8 < 24 < 10 07/20/11 1230 +/- 162 <6 <7 < 36 <6 08/03/11 1270 +/- 113 <5 <5 < 22 <7 08/17/11 1200 +/- 114 <2 <3 < 15 <3 08/31/11 1230 +/- 142 <<6 <6 < 28 <8 09/14/11 1160 +/- 41 <2 <2 < 13 <3 09/28/11 1280 +/- 161 <5 <6 < 28 <8 10/12/11 1120 +/- 153 <7 <7 < 50 < 12 10/26/11 1190 +/- 162 <6 <8 < 33 < 13 11/09/11 1290 +/- 194 <6 <8 < 34 <8 11/22/11 1110 +/- 141 <6 <6 < 32 <8 12/07/11 1350 +/- 173 <6 <7 < 35 < 11 MEAN 1236 +/- 161 BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT C-1 9

TABLE C-IX.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION SR-90 Be-7 K-40 1-131 Cs-134 Cs-137 PERIOD B10-2 06/29/11 (Green) Cabbage < 4 152 +/- 54 4340 +/- 170 < 41 <6 <7 06/29/11 Cauliflower Leaves 5+/-3 <98 3600 +/- 196 < 51 <9 <9 06/29/11 Red Cabbage <4 < 74 4520 +/- 197 < 44 <6 <7 07/27/11 (Green) Cabbage 3 +/-2 <156 2790 +/- 365 < 30 < 17 < 16 07/27/11 Pak Choi 3 +/- 2 < 332 5800 +/- 721 < 52 < 24 < 31 07/27/11 Red Cabbage <2 < 253 4150 +/- 594 < 46 < 25 < 28 08/01/11 Cabbage <3 < 181 2110 +/- 321 < 39 < 17 < 19 08/01/11 Tomatoes < 230 3470 +/- 450 < 51 < 26 < 25 08/15(11 Red Beets < 53 3680 +/- 144 < 13 <6 <6 08/15/11 Sweet Corn < 42 2530 +/- 128 < 12 <5 <6 08/26/11 (Green) Cabbage < 3 < 175 1900 +/- 302 < 23 < 17 < 20 08/26/11 Pumpkin Leaves < 4 1080 +/- 192 3660 +/- 445 < 26 < 16 < 21 08/26/11 Squash Leaves 10 +/-2 1720 +/- 237 4840 +/- 451 < 24 < 16 < 15 09/21/11 (Green) Cabbage 3 < 151 2410 +/- 299 < 33 < 15 < 17 09/21/11 Cauliflower Leaves 3 337 +/- 168 4300 +/- 361 < 33 < 16 < 16 09/21/11 Chinese Cabbage < 33 443 +/- 157 3970 +/- 389 < 34 < 17 < 19 MEAN 5 +/- 6 746 +/- 1293 3629 +/- 2132 -

E1-2 08/01/11 Cabbage <3 336 +/- 171 5530 +/- 559 < 50 < 23 < 26 08/01/11 Tomatoes < 267 2880 +/- 464 < 51 < 24 < 25 08/01/11 Grain or root vegetable (1) -

MEAN 4205 +/- 3748 H1-2 06/29/11 Eggplant Leaves 8 +/- 3 242 +/- 171 6510 +/- 558 < 58 < 18 < 19 06/29/11 Summer Squash Leaves <4 502 +/- 176 3800 +/- 338 < 56 < 15 < 13 06/29/11 Zucchini Leaves 17 +/- 4 322 +/- 94 5560 +/- 211 < 44 <7 <7 07/27/11 Eggplant Leaves < 3 326 +/- 164 8260 +/- 707 < 41 < 22 < 27 07/27/11 Squash Leaves < 3 627 +/- 177 3770 +/- 422 < 32 < 18 < 19 07/27/11 Zucchini Leaves < 3 379 +/- 183 5110 +/- 501 < 35 < 17 < 21 08/26/11 Eggplant Leaves 11 +/- 2 2680 +/- 298 4700 +/- 550 < 29 < 18 < 21 08/26/11 Field Corn (1) - < 41 1930 +/- 98

• 17 <4 <5 08/26/11 Neck Pumpkin Leaves 11 +/- 3 1320 +/- 228 4210 +/- 387 < 27 < 18 < 19 08/26/11 Zucchini Leaves 4 +/- 2 520 +/- 192 3550 +/- 373 < 34 < 20 < 22 09/21/11 Eggplant Leaves 6 +/- 2 3650 +/- 450 5100 +/- 646 < 54 < 27 < 27 09/21/11 Squash Leaves <3 2950 +/- 215 4330 +/- 315 < 24 < 12 < 13 09/21/11 Zucchini Leaves 3 +/- 2 761 +/- 311 3710 +/- 551 < 54 < 29 < 32 10/19/11 Turnips (1) - < 45 2830 +/- 119 < 25 <4 <5 MEAN 9+/-9 1190 +/- 2402 4526 +/- 3144

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR FURTHER EXPLANATION C-20

TABLE C-X.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT- DEC CODE +/-2 S.D.

A1-4 4.1 +/- 1.5 4.2 +/- 0.4 3.1 +/- 0.3 4.9 +/- 0.8 4.2 +/- 0.2 A3-1 4.2 +/- 0.6 4.0 +/- 0.4 4.1 +/- 1.4 4.6 +/- 0.5 4.0 +/- 0.2 A5-1 5.2 +/- 0.9 4.9 +/- 0.4 5.2 + 3.7 5.9 +/- 0.6 4.9 +/- 0.7 A9-3 4.2 +/- 1.0 4.3 +/- 0.3 3.5 +/- 0.3 4.6 +/- 0.7 4.4 +/- 0.3 B13-1 4.1 +/- 1.4 4.4 +/- 0.4 3.2 +/- 0.3 4.8 +/- 0.8 4.1 +/- 0.2 Bi-2 4.2 +/- 1.3 4.2 +/- 0.2 3.3 +/- 0.5 4.9 +/- 0.6 4.3 +/- 0.6 B2-1 4.3 +/- 1.3 4.4 +/- 0.4 3.5 +/- 0.4 5.1 +/- 1.0 4.1 +/- 0.8 B5-1 4.7 +/- 1.1 4.8 +/- 0.3 3.9 +/- 0.5 5.2 +/- 0.7 4.8 +/- 0.4 Cl-i 4.8 +/- 1.2 4.7 +/- 0.5 3.9 +/- 0.3 5.2 +/- 0.4 5.2 +/- 0.9 (1)

C11-2 4.1 +/- 1.6 4.7 +/- 1.2 3.0 +/- 0.4 4.7 +/- 0.6 4.1 +/- 0.9 C2-1 4.5 +/- 1.0 4.7 +/- 0.6 3.8 +/- 0.4 5.0 +/- 0.5 4.6 +/- 0.5 C5-1 5.0 +/- 1.6 5.1 +/- 0.4 4.0 +/- 0.5 5.9 +/- 0.9 4.9 +/- 0.3 C8-1 5.3 +/- 1.1 5.6 +/- 0.5 (1) 4.7 +1.1 5.9 +/- 0.8 4.9 +/- 0.8 D1-1 4.3 +/- 1.5 4.9 +/- 0.7 3.2 +/- 0.3 4.6 +/- 0.3 4.5 +/- 0.4 Dl-2 4.2 +/- 0.9 4.1 +/- 0.1 3.6 +/- 0.3 4.7 +/- 0.8 4.4 +/- 0.6 D2-2 5.5 +/- 1.2 5.1 +/- 0.3 5.2 +/- 1.3 6.4 +/- 0.6 5.4 +/- 1.0 D6-1 5.3 +/- 0.9 5.1 +/- 0.4 4.8 + 0.4 5.8 +/- 0.4 5.6 +/- 0.6 El-2 4.3 +/- 1.7 4.2 +/- 0.5 3.2 +/- 0.3 5.3 +/- 1.0 4.4 +/- 0.7 El-4 4.7 +/- 2.8 4.3 +/- 0.6 3.2 + 0.3 4.8 +/- 0.9 6.6 +/- 1.0 E2-3 5.1 +/- 1.4 4.8 +/- 0.3 4.3 +/- 0.5 5.9 +/- 0.6 5.2 +/- 0.5 E5-1 4.9 +/- 1.4 4.8 +/- 0.4 4.2 +/- 0.5 5.9 +/- 0.6 4.8 +/- 0.4 (1)

E7-1 5.0 +/- 0.9 4.5 +/- 0.2 (1) 5.4 +/- 0.4 5.0 +/- 1.2 Fl-i 4.4 +/- 1.2 4.3 +/- 0.3 3.7 +/- 0.2 5.2 +/- 0.4 4.5 +/- 0.4 Fl-2 5.7 +/- 4.3 4.5 +/- 0.3 3.8 +/- 0.6 5.9 +/- 0.7 8.7 +/- 0.8 Fl-4 5.3 +/- 3.8 4.4 +/- 0.4 3.5 +/- 0.4 5.2 +/- 0.3 7.9 +/- 1.0 F2-1 5.2 +/- 1.5 5.0 +/- 0.8 4.2 +/-0.1 5.8 +/- 0.9 5.8 +/- 0.6 F5-1 5.5 +/- 1.8 5.3 +/- 0.2 4.4 +/- 0.2 6.4 +/- 0.6 6.0 +/- 0.4 G1-2 4.8 +/- 1.1 4.4 +/- 0.3 4.2 +/- 0.3 5.4 +/- 0.5 5.0 +/- 0.5 Gl-3 4.8 +/- 3.1 4.3 +/- 0.3 3.2 + 0.4 4.8 +/- 0.3 6.9 +/- 0.8 G1-5 4.4 +/- 1.9 4.2 +/- 0.5 3.2 + 0.4 4.7 +/- 0.6 5.4 +/- 0.6 G1-6 4.7 +/- 2.0 4.1 +/- 0.3 3.7 +/- 0.8 5.0 +/- 0.2 6.0 +/- 0.5 G2-4 5.8 +/- 1.6 5.5 +/- 0.4 4.8 +/- 0.4 6.4 +/- 0.4 6.5 +/- 0.3 G5-1 4.8 +/- 1.4 4.6 +/- 0.2 3.9 +/- 0.7 4.9 +/- 0.3 5.6 +/- 0.6 H11-1 4.5 +/- 1.3 4.5 +/- 0.4 3.6 +/- 0.2 5.2 +/- 1.0 4.7 +/- 0.6 H3-1 3.8 +/- 1.1 3.9 +/- 0.4 3.1 +/- 0.5 4.5 +/- 0.7 3.8 +/- 0.3 H5-1 3.7 +/- 1.3 3.7 +/- 0.4 2.8 + 0.3 4.3 +/- 0.7 4.0 +/- 0.9 H8-1 7.3 +/- 1.8 6.7 +/- 0.5 6.6 +/- 0.8 8.6 +/- 0.6 7.3 +/- 0.4 J1-1 4.1 +/- 1.4 4.0 +/- 0.2 3.3 + 0.5 5.0 +/- 0.6 4.0 +/- 0.6 J.1-3 3.7 +/- 1.5 4.0 +/- 0.9 2.7 + 0.2 4.4 +/- 0.4 3.6 +/- 0.8 J3-1 4.3 +/- 1.4 4.2 +/- 0.9 3.5 + 0.2 5.2 +/- 0.5 4.2 +/- 0.3 J5-1 5.0 +/- 1.1 4.7 +/- 0.7 4.4 + 0.5 5.7 +/- 0.5 5.2 +/- 0.2 J7-1 5.4 +/- 1.3 5.0 +/- 0.6 4.9 +/- 0.5 6.3 +/- 0.7 5.4 +/- 0.8 K1-4 4.1 +/- 1.5 4.1 +/- 0.6 3.1 + 0.4 4.9 +/- 0.6 4.3 +/- 0.4 K2-1 4.9 +/- 1.7 4.2 +/- 0.3 (1) 4.1 + 0.5 5.8 +/- 0.5 5.4 +/- 1.0 K3-1 3.9 +/- 1.0 3.7 +/- 0.3 3.3 +/- 0.3 4.4 +/- 0.3 4.2 +/- 0.3 K5-1 5.1 +/- 1.3 4.8 +/- 0.3 4.5 +/- 0.5 6.0 +/- 0.3 5.2 +/- 0.3 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-21

TABLE C-X,1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE +/- 2 S.D.

K8-1 4.9 +/- 1.5 4.6 +/- 0.5 4.2 +/- 0.3 5.9 +/- 0.4 4.9 +/- 1.1 Li-i 4.2 +/- 1.5 4.3 +/- 0.6 3.2 +/- 0.5 5.0 +/- 0.7 4.4 +/- 0.3 L1-2 3.5 +/- 1.4 3.1 +/- 0.2 (1) 3.1 +/- 0.2 (1) 4.3 +/- 0.5 L2-1 4.8 +/- 1.3 4.8 +/- 0.5 3.9 +/- 0.5 5.5 +/- 0.4 4.8 +/- 0.6 L5-1 4.2 +/- 1.0 4.1 +/- 0.2 3.5 +/- 0.4 4.7 +/- 0.6 4.4 +/- 0.4 L8-1 4.7 +/- 1.1 4.4 +/- 0.2 4.1 +/- 0.8 5.4 +/- 0.6 4.7 +/- 0.3 Mi-1 4.1 +/- 1.2 4.2 +/- 0.2 3.3 +/- 1.0 4.7 +/- 0.5 4.1 +/- 0.3 M1-2 4.2 +/- 1.5 3.6 +/- 0.2 (1) 3.5 +/- 0.6 4.9 +/- 0.5 4.7 +/- 0.4 M2-1 3.9 +/- 1.0 3.8 +/- 0.3 3.2 +/- 0.4 4.4 +/- 0.4 4.1 +/- 0.5 M5-1 4.6 +/- 1.0 4.6 +/- 0.5 3.9 +/- 0.3 5.1 +/- 0.5 4.6 +/- 0.5 M9-1 5.7 +/- 1.4 5.6 +/- 0.3 4.9 +/- 0.4 6.6 +/- 0.8 5.5 +/- 0.5 Ni-i 4.2 +/- 1.5 3.5 +/- 0.3 (1) 3.7 +/- 0.5 5.1 +/- 0.5 4.4 +/- 0.6 N1-3 4.2 +/- 1.4 4.1 +/- 0.2 3.2 +/- 0.4 4.7 +/- 0.3 4.6 +/- 0.5 N2-1 4.7 +/- 1.3 4.6 +/- 0.6 3.9 +/- 0.6 5.5 +/- 0.4 4.7 +/- 0.5 N5-1 4.0 +/- 1.3 4.1 +/- 0.3 3.3 +/- 0.2 4.8 +/- 1.2 3.8 +/- 0.4 N8-1 5.1 +/- 1.2 4.9 +/- 0.6 4.3 +/- 0.7 5.8 +/- 0.5 5.2 +/- 0.4 P1-i 4.1 +/- 1.2 3.6 +/- 0.3 (1) 3.6 +/- 0.6 4.8 +/- 0.8 4.4 +/- 0.5 P1-2 4.3 +/- 1.8 3.9 +/- 0.3 3.2 +/- 0.7 5.0 +/- 0.6 5.0 +/- 0.5 P2-1 5.4 +/- 1.2 5.1 +/- 0.4 4.7 +/- 0.6 6.1 +/- 0.7 5.5 +/- 0.7 P5-1 4.7 +/- 1.1 4.4 +/- 0.3 4.3 +/- 0.7 5.5 +/- 0.5 4.4 +/- 0.5 P8-1 4.0 +/- 1.0 3.9 +/- 0.6 3.3 +/- 0.3 4.5 +/- 0.7 4.2 +/- 0.3 Q1-1 4.3 +/- 1.7 3.5 +/- 0.2 (1) 3.6 +/- 0.6 5.2 +/- 0.6 4.7 +/- 0.3 Q1-2 3.6 +/- 1.3 3.5 +/- 0.4 2.7 +/- 0.3 4.3 +/- 1.0 3.7 +/- 0.3 Q2-1 4.0 +/- 1.1 3.6 +/- 0.3 3.5 +/- 0.6 4.6 +/- 0.4 4.3 +/- 0.6 Q5-1 4.4 +/- 1.6 4.3 +/- 0.2 3.5 +/- 0.5 5.4 +/- 0.7 4.5 +/- 0.6 Q9-1 4.5 +/- 1.2 4.7 +/- 0.6 3.7 +/- 0.5 5.1 +/- 0.7 4.6 +/- 0.6 Ri-i 4.1 +/- 1.4 4.0 +/- 0.2 3.2 +/- 0.4 4.8 +/- 0.7 4.4 +/- 0.6 R1-2 3.8 +/- 1.4 3.4 +/- 0.3 (1) 3.4 +/- 0.3 4.6 +/- 0.4 (1)

R3-1 5.3 +/- 1.8 4.7 +/- 0.5 4.4 +/- 0.3 6.3 +/- 0.3 5.7 +/- 0.4 R5-1 5.2 +/- 1.2 5.0 +/- 0.6 4.4 +/- 0.3 5.7 +/- 0.7 5.5 +/- 0.6 R9-1 5.1 +/- 1.5 5.2 +/- 0.8 4.1 +/- 0.6 5.8 +/- 0.4 5.4 +/- 0.7 B10-1 4.8 +/- 1.5 5.0 +/- 0.3 3.7 +/- 0.4 5.5 +/- 0.9 4.8 +/- 0.4 D15-1 4.8 +/- 1.3 4.7 +/- 0.3 4.0 +/- 0.3 5.6 +/- 0.3 4.7 +/- 0.4 F10-1 5.9 +/- 1.7 5.4 +/- 0.8 5.0 +/- 0.6 6.7 +/- 0.6 6.6 +/- 1.1 F25-1 5.1 +/- 1.7 4.9 +/- 0.2 4.0 +/- 0.3 5.9 +/- 0.7 5.7 +/- 0.5 G10-1 6.8 +/- 1.9 6.2 +/- 0.3 5.8 +/- 0.5 7.5 +/- 0.5 7.8 +/- 0.5 G15-1 5.9 +/- 1.2 5.9 +/- 0.6 5.1 +/- 0.5 6.6 +/- 0.6 6.1 +/- 0.3 H15-1 5.2 +/- 1.0 4.8 +/- 0.3 4.8 +/- 1.1 5.9 +/- 0.8 5.2 +/- 1.4 J15-1 5.4 +/- 1.3 5.2 +/- 0.5 4.6 +/- 0.4 6.2 +/- 0.3 5.4 +/- 0.5 K15-1 4.6 +/- 1.4 4.3 +/- 0.4 3.8 +/- 0.4 5.4 +/- 0.3 4.8 +/- 0.9 L15-1 4.7 +/- 1.2 4.6 +/- 0.7 4.0 +/- 0.5 5.5 +/- 0.3 4.7 +/- 0.3 N15-2 5.0 +/- 1.0 4.8 +/- 0.3 4.6 +/- 0.3 5.7 +/- 0.4 4.8 +/- 0.3 Q15-1 5.4 +/- 1.7 5.1 +/- 0.6 4.4 +/- 0.3 5.7 +/- 0.3 6.4 +/- 1.4 R15-1 4.7 +/- 1.5 4.4 +/- 0.6 3.8 +/- 0.4 5.2 +/- 0.5 5.4 +/- 0.8 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-22

TABLE C-X.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/MONTH STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY INDICATOR CONTROL PERIOD +/- 2 S.D.

JAN-MAR 4.2 +/- 0.6 4.5 +/- 1.3 5.0 +/- 1.2 APR-JUN 3.2 +/- 0.6 4.0 +/- 1.3 4.4 +/- 1.2 JUL-SEP 4.9 +/- 0.7 5.4 +/- 1.5 5.9 +/- 1.3 OCT-DEC 5.1 +/-2.9 4.9 +/- 1.4 5.5 +/- 1.9 TABLE C-X.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN ANALYZED MINIMUM MAXIMUM +/- 2 S.D. +/-2 S.D.

SITE BOUNDARY 76 2.7 8.7 4.4 +/- 2.1 4.8 +/- 1.5 INDICATOR 237 2.8 8.6 4.7 +/- 1.7 5.2 +/- 1.5 CONTROL 44 3.8 7.8 5.2 +/- 1.8 5.8 +/- 1.7 SITE BOUNDARY STATIONS - A1-4, B1-2, Cl-2, Di-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, Li-1, Mi-1, N1-3, P1-2, Q1-2, Ri-i INDICATOR STATIONS -A3-1, A5-1, A9-3, B1-1, B10-1, B2-1, B5-1, Cl-i, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, Fl-1, F10-1, F2-1, F5-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, Ni-i, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, R9-1 CONTROL STATIONS - D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, R15-1 C-23

FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2011 ol Station J1-2 (Downstream of Discharge) El Station Q9-1 (Control) 100000 .......................................................................................................................

10000 10 .0 . ... .. . . .. . . . .. . . . .. . . .. . . . .. . ....... "-........ . . . . . . . ......

10 Jan Feb Mar Apr May Jun JulI Aug Sep Oct Nov Dec Month 0 Station K1-1 (TMINS Liquid Discharge) 1000000 a)

-J 100000-a) 10000- a...........

0.

a) 1000- Mar Apr May Jun Jul-Ag-Sep .. Oct-Nv.De C-,

0 100-0 10-Jan Mar Apr May Jun Jul Aug Sep Oct Nov Dec Feb Month

FIGURE C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2011

-Indicator Samples -- Control Samples 12000 11000 10000 9000 8000 U) 7000 n) a) 6000 0~

U) 0)

5000 U

0 0

0~ 4000 3000 2000 1000 0

-1000 N-.. LO W) r- W) M) C~ ' C) ) U - U C; '- N M' It C')t U LO N-U) r-(0 UW) C) C C) C -

C) - Nl- N- N-N-ý w w w M w w w w w M M YeaM M M M M M M 0 CD CD CD C C CD C)C ) C)C) ) ) M) M) M) M) M) M) M M M ) M) M) M) M) M) M M M CD C CDCO CC CC Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2011 01 Indicator Samples nL' Control Samples 110 9

8 7

4 - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - -

U, 6

-J a,

0~

ci, 5 a,

C, 0

C.,

0~

3 ..

2 1

0 Jan Feb Mar Apr May Jun Jul Aug

• Sep Oct Nov Dec Month

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2011 NOTE: The mean values are calculated using both the MDCs and 13 Indicator Samples a Control Samples the positive values.

500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L 5 400 o~300

.* 200 . . .......  :,: ,,:*

400 -dO- ... -. - - -- ... - -- -- - - - -..-

10 0 ..

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month 1 Station K1-1 (TMINS Liquid Discharge) 1000000 ll ooo--- ----- - -

100000 10000 - ---

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

FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2011 Indicator Samples --- Control Samples 900 Significant Event Chemobyl April 19861 700 "p600

-50 E 600-- --- - -

200 0

' t D,O - CO M 0 - C 'M Ifl M N0 P. O 0M 0 N- M, IcT U") CO t- CO M ) 0 - N CO CO CO CO CO CO 0) 0) 0) 0) 0) 0) 0) 0) 0M 0 0 C 0 0 0 0 0 0 0 0 0 x--

0M 0M 0) 0) 0) 0M 0) 0M 0M 0M 0M M) 0M M) 0M 0M 0 0 .0 0 0 0 0 0 0 0 0 0 Year CN R N N N N N N N N N Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2011 Indicator -+- Control 0.4 Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 0.35 TMI-2 Critical March 1978 June 1974 September 1974-----------------------------------------------

TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chemobyl April 1986 December 1978 October 1980 0.3 a) S0.25 C) 3 0.2 0~

,0.15 ....

NC14n It C) N( 0 MC; -w N M 'IT LCO (N r_ wM C) ; N M~)I LO CO - w M CD N M) N D LACO I- MM 0a t-N- Nl N- N. N- Nl N m w wO w w w M) ~w M M M 0M M M 0M M M C C 0 0ý 0 CD 0 0ý 0 ý- CD C' rrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrNN- NN- N N N' N N N N N Year

FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2011 0.100 0.090 0.080 0.070

(,

0.060 a,

C-.

0 0.050 0~

0.040 0

0.030 0.020 0.010 0.000 r,. N- N, N- t- Nl mO mO mO mO 00 00 0) 0) mO ) m m C C C CD 0 0 o 0 C) 0 0 C C> C C C C> 0 C C C C---------------------------

0 o - C C CC C CO C0 C C C C 0 C 0 0 00 C - -0 C 0 -

o Q Ný NZ Ný Q !N Q Q Q Q Q N N N Ný4 N N N N N Ný N N N N N N X M M O M- - ,-M -T C N , 0 fN M 0 P- M No C-N Nt 24 N N N N- CO O r-m~ U)5 Nz mO x- Cm It) p)

N0 CEJ 'ITOCOCO CO 2 C1 N O Month / Day / Year The high value on 11/24/2009 was caused by an airborne release on 11/21/2009

FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2011 Indicator Samples -Control Samples 10 9

8 7

(-I 6

a) 5 0~

4 0-3 2

1 0

N*l o'00 -"0 (O (0 c'.1 (0 C0) (0

• W W (*0 I-0 W0 (0 (0

W0 (0 (0

W0 0O=

M0 '- 01 (0 ' (0L OM C.O (0 IN.

(0 (O (0 (0 (0 00 0*' 004 00) 0'* 0C.0 0,. N-0CO 0(0 (

0C)- 0 *-'- 0'4 (0 (0 O0 OM M0* (M0* M0 MO* M0 M0 OM0 M0 M OM0 (0 M0 (0 M 0 0 0 0 0 0 0 0 0 0 0 0 0

......................................................................- -4 -4 -4 -4 -4 -4 -4 -4 N4 N4 N4 N 04N Year

FIGURE C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2011

- Indicator Control 50 Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 45+ TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 40- Chernobyl April 1986 December 1978 October 1980 35+

0 30+

CU 25-Cf) I 20-E 15+/-

10-

, t / -- -- -

5-U 1

'ýT Lo (0 r.- Wo M C -0C) MO 'I U) 0 N- Wo M CD ý; N4 M "T Lo (0 N-_ Mo M) C '- N4 M (D I'- W 0M 0 -0 r-N r- N- r- Mo Co Co Co Co Co Co Co M) Co M) M) M) M) M M M M 0 C C 0 C C C C -0 -~

C)C M)

)C M) ) C) C) C) M) C) C) CD CY) C) C) C) C7) M) M) ) C) M) C) ) CD 0 CD 0 0 CD C) 0 0 1~~~~~~~ 40 40 40 0 40 N- N- N40 N N4 Year

APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

The following section contains data and figures illustrating the analyses performed by the quality control laboratory, Environmental Inc. (Env). Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and Environmental Inc.

(Env). Comparison of the results for most media were within expected ranges.

D-1

Intentionally left blank D-2

TABLE D-I.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 12/28/10 - 02/01/11 1.0 +/- 0.4 02/01/11 - 03/01/11 0.7 +/- 0.4 03/01/11 - 03/29/11 < 3.6 03/29/11 - 05/03/11 < 3.5 05/03/11 - 05/31/11 < 0.9 05/31/11 - 06/28/11 1.4 +/- 0.8 06/28/11 - 08/02/11 1.3 +/- 0.6 08/02/11 - 08/30/11 1.0 +/- 0.6 08/30/11 - 09/27/11 < 0.9 09/27/11 - 11/01/11 < 0.8 11/01/11 - 11/29/11 2.0 +/- 1.0 11/29/11 - 01/03/12 1.0 +/- 0.5 MEAN 1.2 +/- 0.8 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 12/28/10 - 02/01/11 < 155 02/01/11 - 03/01/11 < 159 03/01/11 - 03/29/11 < 165 03/29/11 - 05/03/11 < 143 05/03/11 - 05/31/11 < 144 05/31/11 - 06/28/11 < 150 06/28/11 - 08/02/11 < 149 08/02/11 - 08/30/11 < 150 08/30/11 - 09/27/11 < 144 09/27/11 - 11/01/11 < 143 11/01/11 - 11/29/11 < 166 11/29/11 - 01/03/12 < 143 MEAN TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 12/28/10 - 02/01/11 < 0.2 02/01/11 - 03/01/11 < 0.4 03/01/11 - 03/29/11 < 0.4 03/29/11 - 05/03/11 < 0.4 05/03/11 - 05/31/11 < 0.3 05/31/11 - 06/28/11 < 0.4 06/28/11 - 08/02/11 < 0.3 08/02/11 - 08/30/11 < 0.3 08/30/11 - 09/27/11 < 0.2 09/27/11 - 11/01/11 < 0.3 11/01/11 - 11/29/11 < 0.3 11/29/11 - 01/03/12 < 0.5 MEAN

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-3

TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-137 Ba-140 La-140 PERIOD Q9-lQ 12/28/10 - 02/01/11 <3 <5 <2 <3 <3 <3 <2 <2 <3 < 12 <1 02/01/11 - 03/01/11 <3 <6 <3 <2 <3 <4 <3 <3 <4 < 18 <2 03/01/11 - 03/29/11 <3 <4 <2 <2 <5 <5 <2 <3 <3 <9 <2 03/29/11 - 05/03/11 <6 <9 <4 <4 <7 <6 <5 <7 <4 < 25 <7 05/03/11 - 05/31/11 <3 <2 <2 <2 <7 <4 <3 <2 <2 < 13 <3 05/31/11 - 06/28/11 <2 <6 <2 <2 <3 <5 <3 <4 <2 < 15 <3 06/28/11 - 08/02/11 <2 <4 <2 <1 <2 <3 <2 <2 <2 < 14 <5 08/02/11 - 08/30/11 <2 <4 <2 <2 <6 <4 <3 <3 <2 < 10 <2 08/30/11 - 09/27/11 <3 <7 <3 <2 <3 <3 <3 <3 <2 < 16 <4 09/27/11 - 11/01/11 <3 <4 <1 <2 <4 <4 <2 <2 <2 < 17 <2 11/01/11 - 11/29/11 <5 < 13 <4 <5 <3 <9 <4 <6 <3 < 27 <3 11/29/11 - 01/03/12 <2 <4 <3 <2 <6 <4 <2 <2 <4 < 11 <2

TABLE D-II.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-1 34 Cs-137 PERIOD INDP 10/04/11 < 5 <4 2780 +/- 440 < 13 < 14 < 15 < 11 < 24 <5 < 11

TABLE D-Ill.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 Cs-1 34 Cs-137 PERIOD J2-1 11/08/11 12002 +/- 682 < 41 66 +/- 22 D-6

TABLE D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 1-131 Cs-134 Cs-137 Sr-89 Sr-90 PERIOD H1-2Q 07/27/11 4950 +/- 430 <16 < 15 < 15 < 11 33 +/- 6 B10-2Q 08/01/11 2410 +/- 240 <12 <4 <7 <3 <2 MEAN 3680 +/- 3592 D-7

TABLE D-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND 1-131 INAIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION El-2Q El-2Q PERIOD GROSS BETA 1-131 ILIL./ I U U I/UZ/ I I 51 +/--5 < 18 01/05/11 01/12/11 37 +/- 5 <9 01/12/11 01/19/11 22 +/- 4 < 22 01/19/11 01/26/11 35 +/- 4 < 12 01/26/11 02/02/11 23 +/- 4 < 13 02/02/11 02/09/11 20 +/- 4 < 13 02/09/11 02/16/11 25 +/- 4 < 24 02/16/11 02/23/11 38 +/- 5 <7 02123/11 03/02111 28 +/- 4 < 16 03/02/11 03/08/11 16 +/- 4 < 12 03/08/11 03/16/11 12 +/- 3 < 16 03/16/11 03/23/11 30 +/- 5 95 +/- 25 03/23/11 03/30/11 52 +/- 5 92 +/- 28 03/30/11 04/06/11 (1) (1) 04/06/11 04/13/11 18- 4 26 +/- 12 04/13/11 04/20/11 20 +4 (1) < 17 (1) 04/20/11 04/27/11 17 - 4 (1) < 14 (1) 04/27/11 05/04/11 (1) (1) 05/04/11 05/11/11 18 -+4 < 21 05/11/11 05/18/11 12 -+4 < 10 05/18/11 05/25/11 20 -+4 < 10 05/25/11 06/01/11 29 -+4 <8 06/01/11 06/08/11 31 -+5 < 17 06/08/11 06/15/11 24 -+4 < 18 06/15/11 06/22/11 27 -+4 < 11 06/22/11 06/29/11 15 -+4 < 17 06/29/11 07/06/11 26 -+4 < 15 07/06/11 07/13/11 32 -+4 < 16 07/13/11 07/20/11 27 -+4 < 15 07/20/11 07/27/11 36 -+5 < 23 07127/11 08/03/11 27 -+4 < 17 08/03/11 08/10/11 27 -+4 < 16 08/10/11 08/17/11 22 -+4 < 20 08/17/11 08/24/11 26 +/- 4 < 13 08/24/11 08/31/11 22 +/- 4 <8 08/31/11 09/10/11 23 +/- 4 < 15 09/08/11 09/14/11 23 +/- 5 < 17 09/14/11 09/21/11 16 +/- 4 < 14 09/21/11 09/28/11 10 +/- 4 < 10 09/28/11 10/05/11 10 +/- 4 < 13 10/05/11 10/12/11 39 +/- 5 < 30 10/12/11 10/19/11 22 +/- 4 < 23 10/19/11 10/26/11 18 +/- 4 < 18 10/26/11 11/02/11 26 +/- 4 (1) < 22 (1) 11/02/11 11/09/11 31 +/- 4 < 15 11/09/11 11/16/11 28 +/- 4 < 25 11/16/11 11/22/11 27 +/- 5 < 23 11/22/11 11/30/11 21 +/- 3 < 15 11/30/11 12/07/11 14 +/- 4 < 29 12/07/11 12/14/11 39 +/- 5 < 18 12/14/11 12/21/11 39 +/- 5 < 10 12/21/11 12/28/11 20 +/- 4 < 17 MEAN 25 +/- 19 71 +/- 39

• THE MEAN AND 2 STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION D-8

TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION Be-7 Cs-134 Cs-137 PERIOD E1-2Q 03/16/11 - 03/23/ /11 130 +/- 65 < 6.2 < 7.2 12/29/10 - 03/30/ /11 86 +/- 15

• 0.9

• 0.5 03/30/11 - 06/29/ /i11 92 +/- 20 < 0.8 < 0.7 06/29/11 - 09/28/ /11 75 +/- 14 < 0.5 < 0.5

/i11 09/28/11 - 12/28/ 76 +/- 16 < 1.2

• 0.6 MEAN 82 +/- 16 BOLDED VALUES INDICATE ADDITIONAL SAMPLING DUE TO THE FUKUSHIMA EVENT D-9

TABLE D-VI.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION, GAMMA EMITTERS, AND STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 DATE G2-1Q 01/05/11

• 0.3 1211 +/- 97 <4 <4 <11 <4 02/02/11

• 0.3 1399 +/- 106 <3 <3 <12 <2 03/02/11

• 0.2 944 +/- 103 <5 <4

• 21 <4 03/16/11

• 0.3 1510 +/- 119 <4 <5 <16 <2 03/30/11 0.4 +/- 0.2 1123 +/- 105 <4 <5

• 18 <3 < 0.6 < 0.7 04/13/11

• 0.3 549 +/- 80 <4 <4

• 27 <5 04/27/11

• 0.4 912 +/- 92 <4 <3

• 24 <6 05/11/11

• 0.3 661 +/- 80 <4 <3

• 23 <3 05/25/11

• 0.3 1066 +/- 105 <4 <4 < 16 <3 06/08/11

• 0.2 1190 +/- 88 <3 <4 <13 <3 06/22/11

• 0.4 1397 +/- 108 <3 <4 <14 <2 < 0.6 < 0.5 07/06/11

• 0.3 924 +/- 77 <3 <3 <13 <4 07/20/11

• 0.2 838 +/- 88 <4 <3

• 22 <5 08/03/11

• 0.3 1039 +/- 92 <3 <3

• 28 <6 08/17/11

• 0.2 1136 +/- 91 <4 <4

• 19 <5 08/31/11

• 0.4 946 +/- 111 <6 <6

• 18 <4 09/14/11

• 0.3 1426 +/- 120 <3 <4

• 22 <5 09/28/11

• 0.3 1397 +/- 97 <4 <2 <12 <4 < 0.7 < 0.6 10/12/11

• 0.3 1026 +/- 88 <4 <3

• 20 <3 10/26/11

• 0.4 1510 +/- 92 <4 <3 <11 <3 11/09/11

• 0.2 1110 +/- 94 <2 <4

• 30 <4 11/22/11

• 0.3 1308 +/- 97 <3 <3

• 25 <4 12/07/11

• 0.3 1060 +/- 128 <3 <5

• 20 <5 < 0.8 0.9 +/- 0.3 MEAN 1117 +/- 515

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

FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2011 6

QC-LAB

---

& PRIMARY - LAB 4

3 C.)

2 1

0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH

FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2011 60 _ _ _ _ _ _ _ _ _ _ _ _ _

-- QC - LAB 50 + . ----------------------

---

I --- PRIM A RY - LAB CL 40 E

30 LL 0.I 20 10 0

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

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

March 2011 E7460-396 Milk Sr-89 pCi/L 98.8 97.4 1.01 A Sr-90 pCi/L 15.2 15.8 0.96 A E7461-396 Milk 1-131 pCi/L 92.9 96.9 0.96 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 398 298 1.34 N (1)

Cs-1 34 pCi/L 130 130 1.00 A Cs-137 pCi/L 232 205 1.13 A Co-58 pCi/L 121 113 1.07 A Mn-54 pCi/L 289 266 1.09 A Fe-59 pCi/L 201 175 1.15 A Zn-65 pCi/L 287 261 1.10 A Co-60 pCi/L 186 172 1.08 A E7463-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pCi 243 215 1.13 A Cs-134 pCi 85.0 94.2 0.90 A Cs-137 pCi 168 148 1.14 A Co-58 pCi 89.2 81.8 1.09 A Mn-54 pCi 171 192 0.89 A Fe-59 pCi 129 126 1.02 A Zn-65 pCi 159 189 0.84 A Co-60 pCi 132 124 1.06 A E7462-396 Charcoal 1-131 pCi 96.5 96.3 1.00 A June 2011 E7851-396 Milk Sr-89 pCi/L 96.7 103 0.94 A Sr-90 pCi/L 13.8 15.6 0.88 A E7852-396 Milk 1-131 pCi/L 110 103.0 1.07 A Ce-141 pCi/L 68.1 79.9 0.85 A Cr-51 pCi/L 186 206 0.90 A Cs-134 pCi/L 164 190 0.86 A Cs-137 pCi/L 140 138 1.01 A Co-58 pCi/L 141 152 0.93 A Mn-54 pCi/L 136 138 0.99 A Fe-59 pCi/L 128 123 1.04 A Zn-65 pCi/L 263 261 1.01 A Co-60 pCi/L 189 195 0.97 A E7854-396 AP Ce-141 pCi 49.9 42.9 1.16 A Cr-51 pCi 95.6 11o 0.87 A Cs-134 pCi 104 102 1.02 A Cs-137 pCi 83.8 74.0 1.13 A Co-58 pCi 90.7 81.3 1.12 A Mn-54 pCi 74.5 73.9 1.01 A Fe-59 pCi 62.0 66.1 0.94 A Zn-65 pCi 140 140 1.00 A Co-60 pCi 119 104 1.14 A E7853-396 Charcoal 1-131 pCi 76.2 86.1 0.89 A E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

September 2011 E8070-396 Milk Sr-89 pCi/L 102 90.8 1.12 A Sr-90 pCi/L 13.2 14.7 0.90 A E8071-396 Milk 1-131 pCi/L 74.2 89.2 0.83 A Ce-141 pCi/L 66.9 66.7 1.00 A Cr-51 pCi/L 249 226 1.10 A Cs-134 pCi/L 116 128 0.91 A Cs-1 37 pCi/L 106 114 0.93 A Co-58 pCi/L 95.4 97.5 0.98 A Mn-54 pCi/L 147 151 0.97 A Fe-59 pCi/L 53.1 54.8 0.97 A Zn-65 pCi/L 175 180 0.97 A Co-60 pCi/L 150 157 0.96 A E8073-396 AP Ce-141 pCi 66.6 67.5 0.99 A Cr-51 pCi 263 229 1.15 A Cs-1 34 pCi 139 130 1.07 A Cs-1 37 pCi 110 115 0.96 A Co-58' pCi 108 98.6 1.10 A Mn-54 pCi 152 153 0.99 A Fe-59 pCi 57.5 55.5 1.04 A Zn-65 pCi 190 183 1.04 A Co-60 pCi 156 159 0.98 A E8072-396 Charcoal 1-131 pCi 77.6 80.6 0196 A December, 2011 E8230-396 Milk Sr-89 pCi/L 93.3 93.1 1.00 A Sr-90 pCi/L 12.7 15.4 0.82 A E8231-396 Milk 1-131 pCi/L 82.5 90.2 0.91 A Ce-141 pCi/L not provided by Analytics for this study Cr-51 pCi/L 465 566 0.82 A Cs-134 pCi/L 142 171 0.83 A Cs-1 37 pCi/L 185 210 0.88 A Co-58 pCi/L 177 221 0.80 A Mn-54 pCi/L 208 241 0.86 A Fe-59 pCi/L 164 183 0.90 A Zn-65 pCi/L 259 291 0.89 A Co-60 pCi/L 224 270 0.83 A E8233-396 AP Ce-141 pCi not provided by Analytics for this study Cr-51 pCi 344 368 0.93 A Cs-134 pCi 105 111 0.95 A Cs-137 pCi 129 137 0.94 A Co-58 pCi 145 144 1.01 A Mn-54 pCi 137 157 0.87 A Fe-59 pCi 119 119 1.00 A Zn-65 pCi 145 190 0.76 W Co-60 pCi 168 176 0.95 A E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2011 E8232-396 Charcoal 1-131 pCi 100 89.5 1.12 A (1) Sample appears to be biased high. Corrective Action evaluated after the 2nd QuarterAnalytics PE sample; no action required. NCR 11-13 (a) Teledyne Brown Engineeringreported result.

(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytics evaluation basedon TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning. Reported result falls within 0. 70-0.80 or 1.20-1.30. N =Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)

May 2011 RAD-85 Water Sr-89 pCi/L 59.8 63.2 51.1 -71.2 A Sr-90 pCi/L 42.5 42.5 31.3 -48.8 A Ba-133 pCi/L 73.3 75.3 63.0 - 82.8 A Cs-134 pCi/L 64.9 72.9 59.5 - 80.2 A Cs-137 pCi/L 74.6 77.0 69.3 - 87.4 A Co-60 pCi/L 87.8 88.8 79.9 - 100 A Zn-65 pCi/L 103 98.9 89.0-118 A Gr-A pCi/L 64.1 50.1 26.1 -62.9 N (1)

Gr-B pCi/L 51.8 49.8 33.8 - 56.9 A 1-131 pCi/L 27.4 27.5 22.9 - 32.3 A U-Nat pCi/L 38.5 39.8 32.2 - 44.4 A H-3 pCi/L 10057 10200 8870-11200 A MRAD-14 Filter Gr-A pCi/filter 79.7 74.3 38.5-112 A November 2011 RAD-87 Water Sr-89 pCi/L 81.0 69.7 56.9 - 77.9 N (2)

Sr-90 pCi/L 35.5 41.4 30.2 - 47.2 A Ba-133 pCi/L 90.7 96.9 81.8-106 A Cs-134 pCi/L 36.6 33.4 26.3 - 36.7 A Cs-137 pCi/L 44.7 44.3 39.4-51.7 A Co-60 pCi/L 118.7 119 107-133 A Zn-65 pCi/L 80.2 76.8 68.9 - 92.5 A Gr-A pCi/L 34.2 53.2 27.8 - 66.6 A Gr-B pCi/L 39.3 45.9 30.9 - 53.1 A 1-131 pCi/L 22.9 27.5 22.9 - 32.3 A U-Nat pCi/L 46.8 48.6 39.4 - 54.0 A H-3 pCi/L 15733 17400 15200 - 19100 A MRAD-1 5 Filter Gr-A pCi/filter 44.6 58.4 30.3 - 87.8 A (1) The solids on the planchetexceeded 100 mg, which was beyond the range of the efficiency curve. NCR 11-08 (2) Sr-89 TBE to known ratio of 1.16 fell within acceptable range of +/- 20%. No action required.NCR 11-16 (a) Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurementsmade during standardpreparation.

(c) ERA evaluation:A=acceptable. Reported result falls within the WarningLimits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=checkfor Error. Reported result falls within the ControlLimits and outside of the Warning Limit.

E-4

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 1 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

March 2011 11-MaW24 Water Cs-134 Bq/L 19.1 21.5 15.1 -28.0 A Cs-137 Bq/L 29.0 29.4 20.6 - 38.2 A Co-57 Bq/L 0.139 (1) A Co-60 Bq/L 23.9 24.6 17.2 - 32.0 A H-3 Bq/L 265 243 170-316 A Mn-54 Bq/L 31.8 31.6 22.1-41.1 A K-40 Bq/L 94.8 91 64-118 A Sr-90 Bq/L 9.64 8.72 6.10-11.34 A Zn-65 Bq/L -0.142 (1) A 11-GrW24 Water Gr-A Bq/L 0.767 1.136 0.341 - 1.931 A Gr-B Bq/L 3.43 2.96 1.48-4.44 A 11-MaS24 Soil Cs-134 Bq/kg 612 680 476-884 A Cs-137 Bq/kg 772 758 531 -985 A Co-57 Bq/kg 910 927 649- 1205 A Co-60 Bq/kg 500 482 337 - 627 A Mn-54 Bq/kg 0.607 (1) A K-40 Bq/kg 569 540 378 - 702 A Sr-90 Bq/kg NR 160 112-208 N (2)

Zn-65 Bq/kg 1497 1359 951 - 1767 A 11-RdF24 AP Cs-134 Bq/sample 3.26 3.49 2.44 -4.54 A Cs-137 Bq/sample 2.36 2.28 1.60 -2.96 A Co-57 Bq/sample 3.30 3.33 2.33 - 4.33 A Co-60 Bq/sample 0.0765 (1) A Mn-54 Bq/sample 2.84 2.64 1.85-3.43 A Sr-90 Bq/sample NR 1.36 0.95 - 1.77 N (2)

Zn-65 Bq/sample 3.30 3.18 2.23-4.13 A 11-GrF24 AP Gr-A Bq/sample 0.101 0.659 0.198 - 1.120 N (3)

Gr-B Bq/sample 1.23 1.323 0.662 - 1.985 A 11-RdV24 Vegetation Cs-134 Bq/sample 4.97 5.50 3.85-7.15 A Cs-1 37 Bq/sample 0.0356 (1) A Co-57 Bq/sample 10.8 9.94 6.96 - 12.92 A Co-60 Bq/sample 4.89 4.91 3.44 - 6.38 A Mn-54 Bq/sample 6.42 6.40 4.48 - 8.32 A Sr-90 Bq/sample NR 2.46 1.72 - 3.20 N (2)

Zn-65 Bq/sample 3.07 2.99 2.09 - 3.89 A September 2011 11-MaW25 Water Cs-134 Bq/L 16.0 19.1 13.4-24.8 A Cs-137 Bq/L 0.0043 (1) A Co-57 Bq/L 33.1 36.6 25.6 -47.6 A Co-60 Bq/L 26.9 29.3 20.5 - 38.1 A H-3 Bq/L 1011 1014 710- 1318 A Mn-54 Bq/L 23.2 25.0 17.5 - 32.5 A K-40 Bq/L 147 156 109-203 A Sr-90 Bq/L 15.8 14.2 9.9 - 18.5 A Zn-65 Bq/L 27.3 28.5 20.0 - 37.1 A E-5

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2011 (PAGE 2 OF 2)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

September 2011 11-GrW25 Water Gr-A Bq/L 0.894 0.866 0.260 - 1.472 A Gr-B Bq/L 5.87 4.81 2.41 - 7.22 A 11-MaS25 Soil Cs-134 Bq/kg -0.213 (1) A Cs-137 Bq/kg 1110 979 685-1273 A Co-57 Bq/kg 1290 1180 826-1534 A Co-60 Bq/kg 731 644 451 -837 A Mn-54 Bq/kg 987 848 594-1102 A K-40 Bq/kg 753 625 438-813 W Sr-90 Bq/kg 276 320 224-416 A Zn-65 Bq/kg 1870 1560 1092-2028 A September 2011 11-RdF25 AP Cs-134 Bq/sample -0.043 (1) A Cs-137 Bq/sample 3.09 2.60 1.82-3.38 A Co-57 Bq/sample 5.36 5.09 3.56 - 6.62 A Co-60 Bq/sample 3.41 3.20 2.24-4.16 A Mn-54 Bq/sample 0.067 (1) A Sr-90 Bq/sample 1.84 1.67 1.17-2.17 A Zn-65 Bq/sample 5.17 4.11 2.88-5.34 W 11-GrF25 AP Gr-A Bq/sample 0.0058 (1) A Gr-B Bq/sample -0.01 (I) A 11ýRdV25 Vegetation Cs-134 Bq/sample 0.0081 (1) A Cs-1 37 Bq/sample 4.94 4.71 3.30 - 6.12 A Co-57 Bq/sample 0.0639 (1) A Co-60 Bq/sample 3.36 3.38 2.37 - 4.39 A Mn-54 Bq/sanmple 5.89 5.71 4.00 - 7.42 A Sr-90 Bq/sample 1.31 1.26 0.88- 1.64 A Zn-65 Bq/sample 6.54 6.39 4.47 - 8.31 A (1) Falsepositive test.

(2) Evaluatedas failed due to not reportinga previously reported analyte. NCR 11-11 (3) The filter for GrossAlpha was counted on the wrong side. Recounted on the correctside resulted in acceptableresults. NCR 11-11 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameterpresent in the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

(c) DOE/MAPEP evaluation:A=acceptable, W=acceptable with warning, N=not acceptable.

E-6

TABLE E-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2011 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance STW-1243 04/04/11 Sr-89 68.2 +/- 5.8 63.2 51.1 -71.2 Pass STW-1243 04/04/11 Sr-90 44.3 +/- 2.4 42.5 31.3 -48.8 Pass STW-1 244 04/04/11 Ba-1 33 69.8 +/- 3.9 75.3 63.0 - 82.8 Pass STW-1 244 04/04/11 Co-60 87.9 +/- 3.8 88.8 79.9 - 100.0 Pass STW-1244 04/04/11 Cs-134 69.5 +/- 3.7 72.9 59.5 - 80.2 Pass STW-1244 04/04/11 Cs-137 77.9 +/- 5.3 77.0 69.3 - 87.4 Pass STW-1 244 04/04/11 Zn-65 105.2 +/- 8.4 98.9 89.0-118.0 Pass STW-1245 04/04/11 Gr. Alpha 41.5 +/- 2.3 50.1 26.1 - 62.9 Pass STW-1245 04/04/11 Gr. Beta 48.9 +/- 1.8 49.8 33.8 - 56.9 Pass STW-1246 04/04/11 1-131 26.6 +/- 1.7 27.5 22.9 - 32.3 Pass STW-1 248 04/04/11 H-3 10322 +/-285 10200.0 8870 -11200 Pass STW-1 256 10/07/11 Sr-89 68.7 +/- 6.0 69.7 56.9 - 77.9 Pass STW-1256 10/07/11 Sr-90 36.9 +/- 2.4 41.1 30.2 -47.2 Pass STW-1257 10/07/11 Ba-133 88.2 +/- 7.8 96.9 81.8 - 106.0 Pass STW-1 257 10/07/11 Co-60 116.5 +/-7.1 119.0 107.0 -133.0 Pass STW-1257d 10/07/11 Cs-134 38.8 +/- 8.0 33.4 26.3 - 36.7 Fail STW-1257 10/07/11 Cs-137 45.6 +/- 7.3 44.3 39.4 -51.7 Pass STW-1257 10/07/11 Zn-65 84.9 +/- 15.4 76.8 68.9 - 92.5 Pass STW-1 258 10/07/11 Gr. Alpha 35.7 +/- 3.8 53.2 27.8 - 66.6 Pass STW-1 258 10/07/11 Gr. Beta 36.1 +/-3.3 45.9 30.9 - 53.1 Pass STW-1259 10/07/11 1-131 25.0 +/- 1.1 27.5 22.9 - 32.3 Pass STW-1 261 10/07/11 H-3 17435 +/-382 17400 15200 -19100 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

d The sample was reanalyzed. Result of reanalysis was acceptable, 32.9 +/- 7.4 pCi/L.

E-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2011 (Page 1 of 2) b Concentration Lab Code C Date Analysis Laboratory result Activity Limits d Acceptance STW-1237 02/01/11 Co-57 <0.2 0.00 Pass STW-1237 02/01/11 Co-60 24.10 +/- 0.40 24.60 17.20 -32.00 Pass STW-1237 02/01/11 Cs-134 19.80 +/- 0.40 21.50 15.10 -28.00 Pass STW-1237 02/01/11 Cs-137 29.40 +/- 0.50 29.40 20.60 -38.20 Pass STW-1237 02/01/11 H-3 238.90 +/- 8.80 243.00 170.00 -316.00 Pass STW-1237 02/01/11 K-40 95.40 +/- 3.10 91.00 64.00 -118.00 Pass STW-1237 02/01/11 Mn-54 32.50 +/- 0.60 31.60 22.10 -41.10 Pass STW-1237 02/01/11 Sr-90 8.70 +/- 0.70 8.72 6.10 -11.34 Pass STW-1237 02/01/11 Zn-65 <0.5 0.00 Pass STW-1238 02/01/11 Gr. Alpha 0.82 +/- 0.07 1.14 0.34 -1.93 Pass STW-1238 02/01/11 Gr. Beta 2.82 +/- 0.07 2.96 1.48 -4.44 Pass, STVE-1239 02/01/11 Co-57 11.27 +/- 0.21 9.94 6.96 -12.92 Pass STVE-1 239 02/01/11 Co-60 4.95 +/- 0.16 4.91 3.44 - 6.38 Pass STVE-1239 02/01/11 Cs-1 34 5.18 +/- 0.19 5.50 3.85 -7.15 Pass STVE-1239 02/01/11 Cs-137 < 0.09 0.00 Pass STVE-1239 02/01/11 Mn-54 6.91 +/- 0.25 6.40 4.48 - 8.32 Pass STVE-1239 02/01/11 Zn-65 3.10 +/- 0.32 2.99 2.09 - 3.89 Pass STSO-1240 02/01/11 Co-57 984.10 +/- 4.10 927.00 649.00 - 1205.00 Pass STSO-1 240 02/01/11 Co-60 540.70 +/- 3.00 482.00 337.00 -627.00 Pass STSO-1240 02/01/11 Cs-1 34 726.70 +/- 5.92 680.00 476.00 -884.00 Pass STSO-1240 02/01/11 Cs-137 883.10 +/- 4.70 758.00 531.00 -985.00 Pass STSO-1240 02/01/11 K-40 622.70 +/- 16.70 540.00 378.00 -702.00 Pass STSO-1240 02/01/11 Mn-54 -0.30 +/- 1.00 0.00 Pass STSO-1240 02/01/11 Zn-65 1671.00 +/- 13.10 1359.00 951.00 -1767.00 Pass STAP-1241 02/01/11 Co-57 3.48 +/- 0.06 3.33 2.33 -4.33 Pass STAP-1 241 02/01/11 Co-60 0.00 +/- 0.02 0.00 -0.10 -0.10 Pass STAP-1241 02/01/11 Cs-134 3.44 +/- 0.27 3.49 2.44 -4.54 Pass STAP-1241 02/01/11 Cs-137 2.46 +/- 0.27 2.28 1.60 -2.96 Pass STAP-1241 02/01/11 Gr. Alpha 0.39 +/- 0.05 0.66 0.20 -1.12 Pass STAP-1241 02/01/11 Gr. Beta 1.54 +/- 0.07 1.32 0.66 - 1.99 Pass STAP-1241 02/01/11 Mn-54 2.90 +/- 0.10 2.64 1.85 -3.43 Pass STAP-1241 e 02/01/11 Sr-90 1.89 +/- 0.15 1.36 0.95 - 1.77 Fail STAP-1241 02/01/11 Zn-65 3.80 +/- 0.18 3.18 2.23 -4.13 Pass STVE-1250 08/01/11 Co-57 0.01 +/- 0.02 0.00 Pass STVE-1250 08/01/11 Co-60 3.57 +/- 0.13 3.38 2.37 -4.39 Pass STVE-1250 08/01/11 Cs-134 -0.02 +/- 0.04 0.00 -0.10 -0.10 Pass STVE-1250 08/01/11 Cs-137 5.28 +/- 0.20 4.71 3.30 -6.12 Pass STVE-1250 08/01/11 Mn-54 6.48 +/- 0.22 5.71 4.00 - 7.42 Pass STVE-1250 08/01/11 Zn-65 7.35 +/- 0.34 6.39 4.47 - 8.31 Pass E-8

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2011 (Page 2 of 2)

Concentration b Known Control Lab Code C Date Analysis Laboratory result Activity Limits d Acceptance STSO-1 251 08/01/11 Co-57 1333.90 +/- 4.20 1180.00 826.00 - 1534.00 Pass STSO-1251 08/01/11 Co-60 701.30 +/- 3.40 644.00 451.00 - 837.00 Pass STSO-1251 08/01/11 Cs-1 34 0.71 +/- 1.05 0.00 Pass STSO-1251 08/01/11 Cs-1 37 1106.00 +/- 5.60 979.00 685.00 - 1273.00 Pass STSO-1251 08/01/11 K-40 749.20 +/- 19.00 625.00 438.00 -813.00 Pass STSO-1251 08/01/11 Mn-54 984.30 +/- 5.40 848.00 594.00 - 1102.00 Pass STSO-1251 f 08/01/11 Sr-90 219.40 +/- 16.70 320.00 224.00 -416.00 Fail STSO-1251 08/01/11 Zn-65 1639.90 +/- 11.40 1560.00 1092.00 -2028.00 Pass STAP-1252 08/01/11 Co-57 5.06 +/- 0.08 5.09 3.56 - 6.62 Pass STAP-1252 08/01/11 Co-60 3.13 +/- 0.09 3.20 2.24 -4.16 Pass STAP-1252 08/01/11 Cs-1 34 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1 252 08/01/11 Cs-137 2.61 +/- 0.09 2.60 1.82 - 3.38 Pass STAP-1 252 08/01/11 Mn-54 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1252 08/01/11 Sr-90 1.65 +/- 0.16 1.67 1.17 -2.17 Pass STAP-1252 08/01/11 Zn-65 4.46 +/- 0.23 4.11 2.88 - 5.34 Pass STW-1254 08/01/11 Co-57 37.20 +/- 0.50 36.60 25.60 -47.60 Pass STW-1254 08/01/11 Co-60 28.80 +/- 0.40 29.30 20.50 - 38.10 Pass STW-1 254 08/01/11 Cs-1 34 18.00 +/- 0.60 19.10 13.40 -24.80 Pass STW-1254 08/01/11 Cs-1 37 0.06 +/- 0.13 0.00 Pass STW-1 254 08/01/11 H-3 1039.90 +/- 17.90 1014.00 710.00 - 1318.00 Pass STW-1254 08/01/11 K-40 161.40 +/- 4.10 156.00 109.00 -203.00 Pass STW-1254 08/01/11 Mn-54 25.70 +/- 0.50 25.00 17.50 - 32.50 Pass STW-1254 08/01/11 Sr-90 15.60 +/- 1.80 14.20 9.90 - 18.50 Pass STW-1254 08/01/11 Zn-65 30.20 +/- 0.90 28.50 20.00 -37.10 Pass STW-1255 08/01/11 Gr. Alpha 0.72 +/- 0.12 0.87 0.26 - 1.47 Pass STW-1255 08/01/11 Gr. Beta 4.71 +/- 0.15 4.81 2.41 - 7.22 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d 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.

a No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.

f The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.

E-9

Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January Through 31 December 2011 Prepared By Teledyne Brown Engineering Environmental Services Exe n.

Nuclear Three Mile Island Nuclear Station Middletown, PA 17057 April 2012

Table Of Contents I. Sum m ary and Conclusions ......................................................................................... 1 II. Introduction ............................................................................................................. 3 A. O bjectives of the RG PP .................................................................................. 3 B. Im plem entation of the O bjectives .................................................................. 4 C. Program Description ...................................................................................... 4 D. Characteristics of Tritium (H-3) ...................................................................... 5 Ill. Program Description ................................................................................................ 6 A. Sam ple Analysis .............................................................................................. 6 B. Data Interpretation .......................................................................................... 7 IV. Results and Discussion ........................................................................................... 8 A. G roundwater Results ..................................................................................... 8 B. Surface W ater Results .................................................................................. 10 C. Storm W ater Results ..................................................................................... 10 D. Precipitation W ater Results ......................................................................... 11 E. Leaks, Spills, and Releases ......................................................................... 11 F. Actions Taken .............................................................................................. 12

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2011 Figqures Figure A-1 Sampling Locations at the Three Mile Island Nuclear Station, 2011 Appendix B Data Tables Tables 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, 2011.

Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2011.

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, 2011.

Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table B-111.1 Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2011.

Table B-111.2 Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2011.

Table B-IV.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2011.

Table B-IV.2 Concentrations of Gamma Emitters in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2011.

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Appendix C Data Tables 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, 2011.

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, 2011.

Table C-1.3 Concentrations of Hard-To-Detects in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2011.

Table C-I1.1 Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2011.

Table C-I1.2 Concentrations of Gamma Emitters in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2011.

Table C-I11.1 Concentrations of Tritium in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2011.

Table C-I11.2 Concentrations of Gamma Emitters in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2011.

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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 permanent 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 2011. During that time period, 594 analyses were performed on 279 samples from 64 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, and there were no known active releases at the end of 2011 into the groundwater at Three Mile Island Nuclear Station.

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-89/90 was not detected at a concentration greater than the LLD of 1.0 picoCurie per liter (pCi/L) in the groundwater samples tested.

Tritium was not detected in any groundwater, surface water, storm water, or precipitation water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 33 of 52 groundwater monitoring locations. The groundwater tritium concentrations ranged from 170 +/- 110 pCi/L to 3,780 +/- 430 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of historical releases, the recapture of gaseous tritium releases via rainwater and/or background from external sources greater than 200 pCi/L.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the first and second quarter sampling in 2011. Gross Alpha (dissolved) was not detected in any of the groundwater locations. Gross Alpha (suspended) was detected in 3 of 31 groundwater locations. The concentrations ranged from 1.2 to 17.5 pCi/L.

Gross Beta (dissolved) was detected in 27 of 31 groundwater locations. The concentrations ranged from 1.8 to 44.3 pCi/L. Gross Beta (suspended) was detected in 2 of 31 groundwater locations. The concentrations ranged from 5.1 to 10.6 pCi/L.

Hard-To-Detect analyses were performed on a select group of groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. The isotopes of U-233/234 and U-238 were detected in three of four groundwater monitoring locations. The U-233/234 concentrations ranged from 0.4 to 0.9 pCi/L and the U-238 concentrations ranged from 0.2 to 0.5 pCi/L. The levels detected are from naturally occurring isotopes and are considered background.

All other hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs. The concentrations detected are from naturally occurring isotopes and are considered background.

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

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

As a result of the Phase 1 study, the Radiological Groundwater Protection Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on well water, surface water, precipitation water and storm water samples collected in 2011. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2011.

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

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

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

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

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

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

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

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

C. Program Description

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

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

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

Station personnel review and evaluate all analytical data deliverables as data are received.

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

D. Characteristics of Tritium (H-3)

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

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

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

The chemical properties of tritium are essentially those of ordinary hydrogen. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body.

Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, all tritium is essentially cleared.

Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

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

II1. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2011.

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

1. Concentrations of gamma emitters in groundwater, surface water, precipitation 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.

B. Data Interpretation

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

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

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

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

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

For groundwater, surface water, and storm water 13 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-1 34, Cs-1 37, Ba-140 and La-1 40 were reported.

The radio-analytical laboratory is counting tritium results to an LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 - 240 pCi/L or 140 +/- 100 pCi/L.

Clearly, these sample results cannot be distinguished as different from background at this concentration.

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

Analytical results and anomalies are discussed below.

Tritium Samples from 52 locations were analyzed for tritium activity (Table B-1.1, Appendix B). Tritium values ranged from the detection limit to 3,780 pCi/L. Two of the locations were offsite drinking water wells with no detectable concentration of tritium.

Tritium Split Samples Tritium values ranged from detection limit to 2,912 pCi/L (Table C-1.1, Appendix C).

Strontium Strontium-90 was not detected above the required detection limit of 1.0 pCi/L (Table B-1.1, Appendix B)

Strontium Split Samples Strontium-89 and Strontium-90 were not detected above the required detection limit of 1.0 pCi/L (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 water samples during the second sampling in 2011. Gross Alpha (dissolved) was not detected in any of the groundwater locations.

Gross Alpha (suspended) was detected in 3 of 31 groundwater locations. The concentrations ranged from 1.2 to 17.5 pCi/L.

Gross Beta (dissolved) was detected in 27 of 31 groundwater locations. The concentrations ranged from 1.8 to 44.3 pCi/L.

Gross Beta (suspended) was detected in 2 of 31 groundwater locations. The concentrations ranged from 5.1 to 10.6 pCi/L (Table B-1.1, Appendix B).

Gross Alpha and Gross Beta (dissolved and suspended) Split Samples Gross Alpha (dissolved) was not detected in any of the groundwater locations. Gross Alpha was detected in 1 of 3 groundwater locations at a concentration of 2.1 pCi/L. Gross Beta was detected in all 3 groundwater locations. The concentrations ranged from 1.4 to 2.9 pCi/L. (Table C-1.1, Appendix B).

Gamma Emitters Potassium-40 was detected in one of 68 samples at a concentration of 65 pCi/L. No other gamma-emitting nuclides were detected (Table B-1.2, Appendix B).

Gamma Emitters Split Samples No gamma-emitting nuclides were detected (Table C-1.2, Appendix C).

Hard-To-Detect Hard-To-Detect analyses were performed on a select group of groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. The isotopes of U-233/234 and U-238 were detected in three of four groundwater monitoring locations. The U-233/234 concentrations ranged from 0.4 to 0.9 pCi/L and the U-238 concentrations ranged from 0.2 to 0.5 pCi/L. The concentrations detected are from naturally occurring isotopes and are considered background (Table B-1.3, Appendix B).

Hard-To-Detect Split Samples Hard to detects were not analyzed on split samples in 2011 (Table C-1.3, Appendix B).

B. Surface Water Results Samples were collected from surface water locations in accordance with the station radiological groundwater protection program.

Analytical results and anomalies are discussed below.

Tritium Tritium was not detected above the required detection limit of 200 pCi/L (Table B-11.1, Appendix B).

Tritium Split Samples Tritium was not detected above the required detection limit of 200 pCi/L (Table C-11.1, Appendix C)

Strontium Surface water samples were not analyzed for Strontium-90 in 2011 (Table B-11.1, Appendix B).

Gamma Emitters No gamma-emitting nuclides were detected (Table B-11.2, Appendix B).

Gamma Emitters Split Samples No gamma-emitting nuclides were detected (Table C-11.2, Appendix C C. Storm Water Results Samples were collected from storm water locations in accordance with the station radiological groundwater protection program.

Analytical results and anomalies are discussed below.

Tritium Tritium was detected in two samples above the required detection limit of 200 pCi/L. The concentration ranged from 233 to 337 pCi/L (Table B-Ill.1, Appendix B).

Gamma Emitters Samples from three locations were analyzed for gamma-emitting nuclides. No gamma emitting nuclides were detected (Table B-111.2, Appendix B).

D. Precipitation Water Results Samples were collected at seven locations. The following analysis was performed:

Tritium Samples from seven locations were analyzed for tritium activity.

Tritium activity was detected at six of seven locations. The concentrations ranged from 200 to 783 pCi/L (Table B-IV.1, Appendix B).

Tritium Split Samples Samples from one location were analyzed for tritium activity. Tritium activity was detected in seven of nine samples. The concentrations ranged from 153 to 685 pCi/L (Table C-111.1, Appendix C).

Gamma Emitters Samples from four locations were analyzed for gamma-emitting nuclides. Naturally occurring K-40 was detected in two of seven samples. The concentrations ranged from 78 to 469 pCi/L. No other gamma-emitting nuclides were detected (Table B-IV.2, Appendix B).

Gamma Emitters Split Samples No gamma-emitting nuclides were detected (Table C-111.2, Appendix C).

E. Leaks, Spills, and Releases No new active leaks were identified at TMI in 2011. TMI continues to monitor tritium plumes from previous years and reports the dose to the public in the AREOR. No spills were determined to be reportable under voluntary reporting requirements for the NEI Groundwater Protection Initiative (GPI) as implemented in Exelon's Reportability procedure LS-AA-1120, RAD 1.34.

F. Actions Taken

1. Compensatory Actions TMI continues to monitor groundwater radioactivity as part of natural monitored attenuation of historical leaks.

Intentionally left blank APPENDIX A LOCATION DESIGNATION & DISTANCE

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2011 Site Site Type

1. 3 Monitoring Well 48N Monitoring Well 48S Production Potable Well E1-2 Monitoring Well, Offsite EDCB Storm Water GP-12 Monitoring Well GP-6 Monitoring Well GP-8 Monitoring Well GP-9 Monitoring Well MS-1 Monitoring Well MS-19 Monitoring Well MS-2 Monitoring Well MS-20 Monitoring Well MS-21 Monitoring Well MS-22 Monitoring Well MS-3 Monitoring Well MS-4 Monitoring Well MS-5 Monitoring Well MS-6 Monitoring Well MS-7 Monitoring Well MS-8 Monitoring Well MW-1 Monitoring Well MW-2 Monitoring Well MW-3 Monitoring Well MW-4 Monitoring Well N2-1 Monitoring Well, Offsite NW-A Production Well NW-B Production Well NW-C Production Well NW-CW Clearwell OS-13B Monitoring Well OS-14 Monitoring Well OS-16 Monitoring Well OS-17 Monitoring Well OS-18 Monitoring Well OSF Production Potable Well RW-1 Monitoring Well RW-2 Monitoring Well SW-E-1 Surface Water SW-E-2 Surface Water SW-E-3 Surface Water MW-TMl-9S* Monitoring Well MW-TMI-10D Monitoring Well MW-TMI-101 Monitoring Well MW-TMI-10S Monitoring Well MW-TM-1i1 S* Monitoring Well MW-TMI-12S Monitoring Well MW-TMI-131 Monitoring Well MW-TMI-13S Monitoring Well MW-TMI-14D Monitoring Well MW-TMI-141 Monitoring Well MW-TMI-14S Monitoring Well MW-TMI-16D Monitoring Well MW-TMI-161 Monitoring Well TM-PR-ESE Precipitation Water TM-PR-MS-1 Precipitation Water TM-PR-MS-2 Precipitation Water TM-PR-MS-20 Precipitation Water TM-PR-MS-4 Precipitation Water TM-PR-NW-B Precipitation Water A-i

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2011 Site Site Type MW-TMI-17D Monitoring Well MW-TMI-171 Monitoring Well MW-TMI-18D Monitoring Well MW-TMI-19D Monitoring Well MW-TMI-191 Monitoring Well MW-TMI-1D Monitoring Well MW-TMI-2D Monitoring Well MW-TMI-31 Monitoring Well MW-TMI-41 Monitoring Well MW-TMI-4S Monitoring Well MW-TMI-5D Monitoring Well MW-TMI-6D Monitoring Well MW-TMI-61 Monitoring Well MW-TMI-7S Monitoring Well MW-TMI-8S Monitoring Well MW-TMI-91 Monitoring Well MW-TMI-9S Monitoring Well TRAINING CENTER Offsite Monitoring Well

• NO WATER PRESENT TO SAMPLE A-2

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Intentionally left blank APPENDIX B DATA TABLES

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS) 3 U1/2b/1 1 < 163 3 04/15/11 < 182 3 05/03/11 < 171 < 0.7 < 0.8 1.7 +/- 0.9 < 1.4 < 2.2 3 07/26/11 525 + 133 3 10/19/11 < 196 3 10/19/11 < 199 48S 01/27/11 < 177 48S 05/03/11 < 180 < 0.7 < 1.3 < 0.4 < 2.2 < 1.9 48S 07/27/11 < 184 48S 10/18/11 < 182 MS-1 01/25/11 172 + 111 MS-1 05/04/11 < 200 < 0.8 < 2.4 < 0.5 6.4 +/- 1.7 < 2.0 MS-1 07/27/11 < 183 MS-1 10/19/11 179 + 118 MS-19 01/27/11 < 179 MS-19 01/27/11 < 179 MS-19 05/05/11 < 174 < 0.6 < 0.6 < 0.4 1.8 +/- 0.9 < 1.9 MS-19 07/26/11 < 184 MS-19 10/19/11 450 +/- 135 MS-2 01/27/11 286 + 117 MS-2 01/27/11 < 178 MS-2 04/15/11 394 +/- 132 MS-2 05/03/11 325 +/- 127 < 0.7 < 1.0 < 0.7 1.9 +/- 1.1 < 1.9 MS-2 06/01/11 < 182 MS-2 06/29/11 217 +/- 119 MS-2 07/26/11 353 +/- 123 MS-2 10/19/11 332 +/- 135 MS-20 01/25/11 517 +/- 124 < 2.9 < 0.7 4.4 +/- 2.6 < 2.6 MS-20 05/03/11 404 +/- 128 < 0.7 < 1.1 < 0.6 5.5 +/- 1.3 < 2.1 MS-20 07/26/11 461 +/- 129 MS-20 10/19/I1 < 197 MS-21 01/25/11 1490 +/- 203 MS-21 04/15/11 525 +/- 138 MS-21 05/03/11 348 +/- 131 < 0.7 < 0.7 < 0.6 3.9 +/- 1.0 < 1.8 MS-21 06/01/11 189 +/- 119 MS-21 06/29/11 < 174 MS-21 07/26/11 190 +/- 115 MS-22 01/25/11 846 +/- 143 MS-22 05/03/11 928 +/- 155 < 0.8 < 1.2 < 0.6 10.9 +/- 1.5 < 2.1 MS-22 07/26/11 867 +/- 150 MS-22 10/19/11 767 +/- 157 MS-3 01/27/11 250 +/- 115 MS-3 04/15/11 198 +/- 119 MS-3 05/03/11 321 +/- 128 < 0.6 <1.1 1.5 +/- 0.9 4.3 +/- 1.2 < 1.9 MS-3 05/03/11 243 +/- 124 < 0.7 <1.1 1.2 +/- 0.8 3.7 +/- 1.2 < 1.9 MS-3 06/01/11 198 +/- 118 MS-3 06/29/11 252 +/- 120 MS-3 07/26/11 448 +/- 129 MS-3 10/19/11 314 +/- 137 MVS-4 04/15/11 214 +/- 122 B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS)

MS-4 05/04/11 208 +/- 121 MS-4 06/01/11 196 +/- 123 MS-4 06/29/11 262 +/- 121 MS-5 01/27/11 < 168 MS-5 05/04/11 < 177 < 0.8 MS-5 06/01/11 < 176 MS-5 06/29/11 < 177 MS-5 07/26/11 < 166 MS-5 10/19/11 < 193 MS-7 01/25111 < 178 MS-7 05/03/11 < 179 < 0.6 < 1.2 < 0.6 8.9 +/- 1.5 < 1.8 MS-7 06/01/11 < 177 MS-7 06/29/11 < 176 MS-7 07/26/11 < 182 MS-7 10/19111 < 196 MS-8 01/27/11 248 +/- 111 < 2.1 < 0.8 4.9 +/- 0.9 < 2.6 MS-8 05/04/11 252 +/- 118 < 0.6 MS-8 07/26/11 236 +/- 126 MS-8 07/26/11 263 +/- 118 MS-8 10/19/11 223 +/- 129 MW-i 05/05/11 < 168 MW-2 05/05/11 < 173 MW-TMI-10D 01/25/11 < 169 MW-TMI-10D 05/04/11 293 +/- 123 MW-TMI-10D 07/27/11 270 +/- 122 MW-TMI-10D 10/19/11 249 +/- 125 MW-TMI-101 01/25/11 1320 +/- 192 MW-TMI-101 02/07/11 880 +/- 141 < 0.9 < 2.6 < 1.4 3.1 +/- 1.3 5.1 + 1.9 MW-TMI-101 05/04/11 1560 +/- 213 < 0.6 < 0.8 < 0.8 3.9 +/- 1.1 < 2.0 MW-TMI-101 07/27/11 1570 +/- 206 MW-TMI-1 01 10/19/11 1630 +/- 226 MW-TMI-101 10/19/11 1510 +/- 214 MW-TMI-10S 01/25/11 3780 +/- 430 MW-TMI-10S 05/04/11 1200 +/- 180 < 0.7 < 0.8 < 0.8 5.7 +/- 1.2 < 2.0 MW-TMI-10S 07/27/11 3310 +/- 374 MW-TMI-10S 07127111 2640 +/- 318 MW-TMI-10S 10/19/11 2140 +/- 275 MW-TMI-12S 01/25/11 < 159 < 3.3 < 0.8 24.1 +/- 4.4 < 2.6 MW-TMI-12S 05/03/11 < 175 < 0.7 < 0.6 < 0.4 2.3 +/- 0.9 < 1.9 MW-TMI-12S 07/27/11 < 199 MW-TMI-12S 10/19/11 < 194 MW-TMI-1 31 01/27/11 419 +/- 122 MW-TMI-131 05/04/11 282 +/- 140 MW-TMI-131 07/26/11 350 +/- 124 MW-TMI-131 10/18/11 231 +/- 125 MW-TMI-131 10/18/11 301 +/- 129 MW-TMI-13S 01/27/11 < 166 MW-TMI-13S 05/04/11 < 179 < 0.7 < 0.9 < 0.5 8.0 +/- 1.3 < 2.0 MW-TMI-13S 05/04/11 < 200 < 0.6 < 0.8 < 0.5 5.7 +/- 1.1 < 2.0 MW-TMI-1 3S 07/26/11 < 180 B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS)

MW-TMI-13S 10/18/11

• 182 MW-TMI-14D 01/27/11 694 +/- 136 MW-TMI-14D 05/03/11 475 +/- 150 MW-TMI-14D 07/26/11 400 +/- 139 MW-TMI-14D 10/19/11 399 +/- 133 MW-TMI-141 01/27/11

• 172 MW-TMI-141 05/03/11

• 198 MW-TMI-141 07/26/11 250 +/- 124 MW-TMI-141 10/19/11 187 +/- 122 MW-TMI-14S 01/27/11

• 168 MW-TMI-14S 05/03/11

• 177 <1.0 <0.5 <0.5 2.2 +/- 0.9 < 2.0 MW-TMI-14S 07/26/11 245 +/- 125 MW-TMI-14S 07/26/11 344 +/- 131 MW-TMI-14S 10/19/11

• 178 MW-TMI-16D 01/27/11 729 +/- 139 MW-TMI-16D 01/27/11 591 +/- 136 MW-TMI-16D 05/04/11 562 +/- 135 MW-TMI-16D 07/27/11 266 +/- 127 MW-TMI-16D 10/19/11 423 +/- 141 MW-TMI-161 01/27/11 170 +/- 110 MW-TMI-161 05/04/11

• 179 MW-TMI-161 07/27/11

• 181 MW-TMI-161 10/19/11

• 195 MW-TMI-171 05/04/11

• 173 MW-TMI-18D 05/04/11

• 182 MW-TMI-18D 05/04/11

• 176 MW-TMI-191 05/03/11

• 191 MW-TMI-1D 05/05/11 413 +/- 133 MW-TMI-2D 01/27/11 513 +/- 126 MW-TMI-2D 05/04/11 357 +/- 127

• 0.6 <0.5 <0.8 5.0 +/- 0.9 < 2.0 MW-TMI-2D 07/26/11 657 +/- 140 MW-TMI-2D 10/19/11 358 +/- 136 MW-TMI-31 01/25/11 190 +/- 112 MW-TMI-31 05/05/11 368 +/- 131

• 0.5 <2.2 <0.6 6.3 +/- 1.6 < 1.9 MW-TMI-31 07/27/11 254 +/- 116 MW-TMI-31 10/20/11

• 175 MW-TMI-31 10/20/11

• 175 MW-TMI-41 05/03/11

• 193 MW-TMI-41 05/03/11

• 191 MW-TMI-4S 05/03/11

• 190 <0.7 <1.7 <0.5 6.5 +/- 1.7 < 1.9 MW-TMI-6D 01/25/11

• 169 MW-TMI-6D 05/03/11

• 191 < 1.0 <2.3 <0.9 12.7 +/- 1.8 < 2.0 MW-TMI-6D 05/03/11

• 192 <0.7 <2.3 <0.9 44.3 +/- 2.7 < 2.0 MW-TMI-6D 07/26/11 364 +/- 125 MW-TMI-6D 10/19/11

• 194 MW-TMI-61 01/25/11 348 +/- 119 MW-TMI-61 05/03/11 201 +/- 127 < 0.6 <1.1 <0.9 < 1.6 < 2.0 MW-TMI-61 07/26/11

• 178 MW-TMI-61 10/19/11

• 194 MW-TMI-7S 05/05/11

• 181 B-3

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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS)

MW-TMI-8S 05/03/11 < 200 MW-TMI-91 05/03/11 < 191 MW-TMI-9S 05/03/11 < 192 NW-A 01/27/11 512 +/- 134 NW-A 05/03/11 494 +/- 136 < 0.6 <1.1 <1.0 3.3 +/- 1.1 < 1.9 NW-A 08/02/11 448 +/- 133 NW-A 10/20/11 462 +/- 133 NW-B 01/27/11 405 +/- 129 NW-B 05/03/11 627 +/- 145 < 0.5 <1.2 <1.0 3.6 +/- 1.2 < 1.9 NW-B 08/02/11 501 +/- 138 NW-B 10/20/11 361 +/- 124 NW-C 01/27/11 1380 +/- 200 < 0.9 <2.2 <1.1 < 1.9 < 2.3 NW-C 05/03/11 1660 +/- 221 < 0.6 <1.1 <1.0 2.2 +/- 1.0 < 1.9 NW-C 08/02/11 1450 +/- 200 NW-CW 01/27/11 759 +/- 149 NW-CW 01/27/11 636 +/- 139 NW-CW 05/03/11 654 +/- 147 < 0.7 <1.2 <1.0 2.7 +/- 1.1 < 1.9 NW-CW 08/02/11 602 +/- 140 NW-CW 10/20/11 463 +/- 132 OS-13B 10/19/11 206 +/- 131 OS-14 01/27/11 < 166 < 2.7 17.5 +/- 2.7 77.8 +/- 3.4 10.6 +/- 2.2 OS-14 05/04/11 < 167 < 0.5 OS-14 07/26/11 < 177 OS-14 07/26/11 < 183 OS-14 10/19/11 < 195 OS-16 01/27/11 394 +/- 121 OS-16 04/15/11 489 +/- 136 OS-16 05/03/11 400 +/- 127 < 0.6 <0.5 <0.5 4.6 +/- 1.0 < 1.9 OS-16 07/26/11 522 +/- 134 OS-16 10/19/11 379 +/- 140 OS-17 04/15/11 252 +/- 126 OS-18 01/25/11 307 +/- 123 OS-18 05/03/11 247 +/- 130 < 0.6 <0.8 <0.9 3.0 +/- 1.0 < 2.0 OS-18 06/01/11 < 178 OS-18 06/01/11 184 +/- 117 OS-18 06/29/11 < 176 OS-18 06/29/11 < 178 OS-18 07/26/11 186 +/- 122 OS-18 10/20/11 < 175 OSF 01/27/11 304 +/- 122 OSF 05/03/11 218 +/- 137 < 0.9 <2.6 <0.4 7.9 +/- 2.0 < 1.9 OSF 07/27/11 < 180 OSF 10/18/11 253 +/- 123 RW-1 01/25/11 < 161 RW-1 05/03/11 < 175 < 0.6 < 0.7 < 0.6 2.1 +/- 0.9 < 2.1 RW-1 07/26/11 < 199 RW-1 10/19/11 < 197 RW-2 01/25/11 < 161 RW-2 05/03/11 < 180 <0.8 <1.1 <0.7 4.2 +/- 1.3 < 1.9 RW-2 06/01/11 < 186 B-4

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS)

RW-2 06/29/11 182 +/- 119 RW-2 07/27/11 < 176 RW-2 10/19/11 < 199 TRAINING CENTEF 05/04/11 < 173 B-5

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE 3 05/03/11 < 26 < 19 <2 <3 <6 <3 <5 <3 <5 <2 <2 < 26 <6 MS-19 05/05/11 < 25 < 47 <2 <3 <7 <2 <5 <3 <5 <2 <3 < 25 <8 MS-2 05/03/11 < 24 < 19 <2 <3 <7 <2 <4 <3 <4 <2 <2 < 47 < 14 MS-20 05/03/11 < 23 < 51 <2 <3 <5 <2 <4 <2 <4 <2 <2 < 24 <7 MS-21 05/03/11 < 26 < 14 <2 <2 <6 <2 <4 <3 <5 <2 <2

• 41 <11 MS-22 05/03/11 < 24 < 21 <2 <2 <6 <2 <4 <3 <4 <2 <2

• 22 <5 MS-3 01/27/11 < 41 < 40 <4 <4 <9 <5 <8 <5 <7 <4 <5 < 22 <9 MS-3 05/03/11 < 28 < 14 <2 <3 <5 <2 <3 <3 <5 <2 <2 < 34

• 14 MS-3 05/03/11 < 26 < 70 <2 <3 <7 <2 <4 <3 <5 <2 <2 < 48 < 14 MS-3 07/26/11 < 49 < 55 <4 <5 <11 <5 <9 <5 <9 <4 <5 < 39

• 12 MS-3 10/19/11 < 39 < 76 <4 <4 <8 <4 <7 <5 <8 <4 <4

• 28 <11 MS-4 05/04/11 < 19 < 34 <1 <2 <4 <1 <3 <2 <3 <1 <2 < 35 <9 MS-5 01/27/11 < 43

• 52 <5 <6 <11 <5 < 12 <6 < 10 <4 < 6 < 26 <9 w

MS-5 05/04/11 < 26 < 57 <2 <3 <7 <1 <4 <2 <5 <2 <2 < 42 < 15 MS-5 07/26/11 < 45 < 80 <4 <5 <11 <4 <9 <5 <8 <5 <4 < 30 < 10 MS-5 10/19/11 < 32 < 100 <4 <4 <11 <4 <7 <4 <8 <4 <4 < 26 <9 MS-7 05/03/11 < 28 < 17 <2 <3 <6 <2 <5 <3 <5 <2 <2 < 44 < 13 MS-8 05/04/11 < 25

• 20 <2 <2 <6 <2 <4 <3 <4 <2 <2 < 37 <15 MS-8 07/26/11 < 45 < 81 <5 <5 <11 <5 < 10 <4 <8 <4 <4 < 32 <9 MS-8 07/26/11 < 36 < 61 <4 <4 <11 <4 <9 <4 <8 <4 <4 < 33 <9 MS-8 10/19/11 < 34 < 28 <3 <3 <8 <3 <7 <4 <6 <3 <4 < 26 <7 MW-i 05/05/11 < 17 < 13 <2 <2 <4 <1 <3 <2 <3 <1 <1 < 19 <7 MW-2 05/05/11 < 22 < 22 <2 <2 <5 <2 <4 <3 <5 <2 <3 < 20 <7 MW-TMI-101 02/07/11 < 46

• 51 <6 <6 < 10 <6 < 12 <6 <9 <5 <6 < 32 < 10 MW-TMI-101 05/04/11 < 44 < 45 <4 <5 <8 <4 <7 <5 <7 <5 <5 < 35 <9 MW-TMI-101 10/19/11 < 23 < 31 <2 <3 <8 <3 <4 <3 <6 <3 <3 < 21 <9 MW-TMI-101 10/19/11 < 36 < 25 <3 <4 <7 <3 <7 <4 <6 <3 <3 < 24 <8 MW-TMI-lOS 05/04/11 < 34 < 72 <3 <4 <9 <4 <7 <4 <8 <4 <4 < 26 <8 MW-TMI-lOS 10/19/11 < 40 < 105 <5 <5 < 10 <5 < 10 <6 < 10 <4 <5 < 33 < 11 MW-TMI-12S 05/03/11 < 21 65 +/- 41 < 2 <2 <5 <2 <4 <3 <4 <2 <2 < 24 <7 MW-TMI-13S 05/04/11 < 18 <11 <1 <2 <3 <1 <3 <2 <2 <1 <2 < 27 < 14 MW-TMI-13S 05/04/11 < 22 <14 <2 <2 <6 <2 <3 <3 <4 <2 <2 < 41 < 12 MW-TM1-14S 05/03/11 < 24 <15 <2 <2 <6 <2 <4 <2 <5 <2 <2 < 44 < 13 MW-TMI-171 05/04/11 < 28 <27 <3 <3 <7 <3 <6 <4 <6 <3 <3 < 23 <8

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE MW-TMI-18D 05/04/11 < 31 < 73 <3 <3 <8 <3 <7 <5 <6 <3 <4 <26 <9 MW-TMI-18D 05/04/11 < 30 < 65 <3 <4 <7 <3 <7 <4 <6 <3 <4 <26 <8 MW-TMI-191 05/03/11 < 11 < 25 <1 <1 <3 <1 <2 <1 <2 <1 <1 <18 <5 MW-TMI-1D 05/05/11 < 28 < 15 <2 <3 <7 <2 <3 <3 <4 <2 <2 <40 <13 MW-TMI-2D 05/04/11 < 41 < 97 <5 <5 <10 <5 <9 <5 <9 <4 <5 <37 <6 MW-TMI-31 05/05/11 < 23 < 57 <2 <3 <6 <2 <4 <3 <4 <2 <2 <40 <12 MW-TMI-41 05/03/11 < 10 < 27 <1 <1 <2 <1 <2 <1 <2 <1 <1 <15 <5 MW-TMI-41 05/03/11 < 11 < 23 <1 <1 <2 <1 <2 <1 <2 <1 <1 <16 <5 MW-TMI-4S 05/03/11 < 9 < 6 <1 <1 <2 <1 <2 <1 <2 <1 <1 <14 <4 MW-TMI-6D 05/03/11 < 10 < 8 <1 <1 <2 <1 <2 <1 <2 <1 <1 <16 <5 MW-TMI-6D 05/03/11 < 11 < 7 <1 <1 <3 <1 <2 <1 <2 <1 <1 <17 <6 MW-TMI-61 05/03/11 < 7 < 13 <1 <1 <2 <1 <1 <1 <1 <1 <1 <11 <4 MW-TMI-7S 05/05/11 < 22 < 19 <2 <3 <5 <1 <4 <2 <4 <2 <2 <37 <8 MW-TMI-8S 05/03/11 < 9 < 5 <1 <1 <2 <1 <1 <1 <1 <1 <1 <14 <4 MW-TMI-91 05/03/11 < 8 < 6 <1 <1 <2 <1 <1 <1 <1 <1 <1 <14 <4 MW-TMI-9S 05/03/11 < 9 < 7 <1 <1 <2 <1 <2 <1 <2 <1 <1 <17 <6 NW-C 01/27/11 < 20 < 41 <2 <2 <4 <2 <4 <2 <4 <2 <2 <15 <4 OS-13B 10/19/11 < 36 < 38 <4 <4 <8 <4 <8 <4 <7 <4 <4 <32 <9 OS-14 05/04/11 < 22 < 18 <2 <2 <4 <2 <3 <2 <4 <2 <2 <36 <13 OS-14 07/26/11 < 36 < 37 <3 <3 <8 <3 <7 <4 <8 <4 <4 <27 <9 OS-14 07/26/11 < 36 < 94 <4 <4 <10 <6 <9 <5 <10 <4 <5 <30 <10 OS-14 10/19/11 < 35 < 36 <3 <3 <8 <3 <6 <4 <6 <3 <3 <27 <9 OS-16 01/27/11 < 40 < 95 <5 <5 <8 <4 <9 <6 <9 <4 <5 <24 <7 OS-16 05/03/11 < 23 < 22 <2 <2 <6 <2 <4 <3 <5 <2 <2 <23 <9 OS-16 07/26/11 < 37 < 35 <3 <4 <9 <3 <7 <5 <6 <3 <4 <28 <9 OS-16 10/19/11 < 40 < 76 <4 <4 <9 <5 <7 <5 <8 <4 <4 <27 <10 RW-1 05/03/11 < 24 < 20 <2 <2 <6 <2 <4 <3 <5 <2 <2 <23 <8 RW-2 05/03/11 < 29 < 24 <2 <2 <8 <2 <3 <3 <4 <2 <3 <48 <12 TM-48S 05/03/11 < 26 < 49 <2 <2 <4 <2 <4 <3 <4 <2 <2 <43 <15 TM-MS-1 05/04/11 < 37 < 76 <2 <4 <5 <2 <3 <3 <5 <2 <3 <44 <14 TM-NW-A 05/03/11 < 24 < 12 <1 <2 <5 <1 <3 <2 <4 <2 <2 <37 <11 TM-NW-B 05/03/11 < 21 < 14 <2 <2 <5 <2 <4 <3 <5 <1 <2 <34 <15 TM-NW-C 05/03/11 < 24 < 17 <2 <2 <6 <2 <3 <2 <4 <2 <2 <36 <14 TM-NW-CW 05/03/11 < 19 < 15 <2 <2 <4 <2 <3 <2 <4 <2 <2 <35 <12

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE TM-OS-1 8 05/03/11 <8 <18 <1 <1 <2 <1 <1 <1 <2 <1 <1 <15 <4 TM-OSF 05/03/11 < 25 < 82 <2 <3 <8 <3 <4 <4 <6 <2 <3 < 52 < 13 TRAINING CENTER 05/04/11 < 40 < 67 <4 <4 <9 <4 <9 <6 <8 <4 <4 <30 <9 80

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/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 MW-TMI-101 02/07/11 < 0.12 < 0.10 < 0.04 < 0.03

• 0.05 0.4 +/- 0.2 < 0.07 0.4 +/- 0.2 < 153 < 3.0 MW-TMI-101 05/04/11 < 0.10 < 0.10 < 0.06 < 0.14 < 0.05 0.4 +/- 0.2 < 0.06 0.2 +/- 0.1 < 166 < 3.7 MW-TMI-10S 05/04/11 < 0.12 < 0.11 < 0.05 < 0.06 < 0.07 < 0.1 < 0.07 < 0.1 < 72 < 3.6 NW-C 01/27/11 < 0.03 < 0.12 < 0.13 < 0.08 < 0.08 0.9 +/- 0.2 < 0.03 0.5 +/- 0.2 < 127 < 3.1

TABLE B-II.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-1 01/24/11 < 176 SW-E-1 05/04/11 < 199 SW-E-1 07/27/11 < 182 SW-E-1 10/18/11 < 183 SW-E-2 01/25/11 < 174 SW-E-2 05/04/11 < 200 SW-E-2 07/27/11 < 185 SW-E-2 10/18/11 < 182 SW-E-3 01/25/11

• 167 SW-E-3 05/04/11 < 199 SW-E-3 05/04/11 < 199 SW-E-3 07/27/11 < 183 SW-E-3 10/18/11 < 182 B-10

TABLE B-1I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE SW-E-1 05/04/11 <40 <12 <4 <3 <8 <3 <7 <4 <7 <3 <3 <57 < 15 SW-E-2 05/04/11 < 34 < 69 < 3 <4 <8 <3 <7 <4 <6 <3 <3 <29 <8 SW-E-3 05/04/11 < 39 < 39 <4 <4 <6 <4 <8 <4 <7 <3 <4 <31 <9 SW-E-3 05/04/11 < 34 < 28 < 3 < 3 <7 <3 <6 <4 <7 <3 <3 <26 <6

TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE PERIOD H-3 EDCB 02/08/11 - 03/29/11 233 +/- 102 EDCB 05/03/11 - 06/28/11 < 178 EDCB 08/02/11 - 09/27/11 < 188 EDCB 11/08/11 - 01/03/12 337 +/- 124 B-12

TABLE B-Ill.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD EDCB 02/08/11 - 03/29/11 < 14 < 11 <1 <1 <3 <1 <2 <2 <2 <1 <1 <12 <3 EDCB 05/03/11 - 06/28/11 < 45 < 47 <5 <3 <9 <3 <8 <5 <8 <4 <5 <32 <12 EDCB 08/02/11 - 09/27/11 < 14 < 30 <2 <2 <3 <2 <3 <2 <3 <2 <2 <7 <2 EDCB 11/01/11 - 01/03/12 < 45 < 90 <4 <4 <11 <4 <9 <5 <8 <4 <5 <24 <6

TABLE B-IV.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 TM-PR-ESE 03/07/11

• 198 TM-PR-ESE 03/15/11 461 +/- 131 TM-PR-ESE 04/12/11

• 180 TM-PR-ESE 05/03/11 307 +/- 130 TM-PR-ESE 05/27/11 315 +/- 124 TM-PR-ESE 06/11/11

• 181 TM-PR-ESE 06/24/11 487 +/- 147 TM-PR-ESE 07/10/11 211 +/- 125 TM-PR-ESE 10/04/11

• 184 TM-PR-MS-1 03/07/11

• 178 TM-PR-MS-1 03/15/11

• 170 TM-PR-MS-1 04/12/11

• 181 TM-PR-MS-1 05/03/11

• 173 TM-PR-MS-1 05/27/11

• 172 TM-PR-MS-1 06/11/11

• 184 TM-PR-MS-1 06/24/11

• 195 TM-PR-MS-1 07/10/11

• 182 TM-PR-MS-1 10/04/11

• 181 TM-PR-MS-2 03/07/11

• 175 TM-PR-MS-2 03/15/11 489 +/- 133 TM-PR-MS-2 04/12/11

• 180 TM-PR-MS-2 05/03/11 218 +/- 125 TM-PR-MS-2 05/27/11 323 +/- 124 TM-PR-MS-2 06/11/11

• 182 TM-PR-MS-2 06/24/11 343 +/- 139 TM-PR-MS-2 07/10/11 228 +/- 124 TM-PR-MS-2 10/04/11

• 187 TM-PR-MS-20 05/10/11 242 +/- 125 TM-PR-MS-20 05/27/11 < 186 TM-PR-MS-20 06/11/11 200 +/- 120 TM-PR-MS-20 06/24/11

• 198 TM-PR-MS-20 07/10/11

• 182 TM-PR-MS-20 10/04/11 405 +/- 138 TM-PR-MS-4 03/07/11

• 193 TM-PR-MS-4 03/15/11 239 +/- 119 TM-PR-MS-4 04/12/11

• 179 TM-PR-MS-4 05/03/11

• 183 TM-PR-MS-4 05/27/11 230 +/- 119 TM-PR-MS-4 06/11/11

• 180 TM-PR-MS-4 06/24/11

• 198 TM-PR-MS-4 07/10/11

• 187 TM-PR-MS-4 10/04/11

• 185 TM-PR-NW-B 05/03/11

• 185 TM-PR-NW-B 05/10/11 300 +/- 131 TM-PR-NW-B 05/18/11 < 184 TM-PR-NW-B 05/27/11 < 176 TM-PR-NW-B 06/01/11 306 +/- 135 TM-PR-NW-B 06/11/11 < 167 TM-PR-NW-B 06/17/11 < 176 TM-PR-NW-B 06/24/11 < 195 B-14

TABLE B-IV.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 TM-PR-NW-B 07/10/11 < 184 TM-PR-NW-B 10/04/11 483 _+ 131 TM-PR-RW-2 05/10/11 214 + 124 TM-PR-RW-2 05/27/11 297 + 127 TM-PR-RW-2 06/11/11 231 + 122 659 + 154 TM-PR-RW-2 06/24/11 TM-PR-RW-2 07/10/11 783 + 153 TM-PR-RW-2 10/04/11 < 176 B-15

TABLE B-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE TM-PR-ESE 03/07/11 < 73 < 64 <8 <8 <18 <9 < 16 <8 < 15 <8 <9 < 57 < 18 TM-PR-ESE 03/15/11 < 39 < 28 <3 <4 <8 <2 <7 <4 < 6 <4 <4 < 24 <8 TM-PR-MS-1 03/07/11 < 58 < 139 <6 <5 <12 <6 < 12 <7 < 10 <6 <7 < 42 < 12 TM-PR-MS-2 03/07/11 < 78 < 74 <8 <8 <17 <8 < 16 <9 < 14 <8 <9 < 58 < 18 TM-PR-MS-2 03/15/11 < 33 < 59 <3 <4 <7 <3 <6 <4 < 6 <3 <4 < 27 <8 TM-PR-MS-4 03/07/11 < 60 469 +/-155 <6 <6 <14 <6 < 14 <7 < 11 <7 <7 < 45 < 13 TM-PR-MS-4 03/15/11 < 34 78 +/-40 <3 <4 <8 <3 <7 <4 < 6 <3 <4 < 26 <8 ON

APPENDIX C DATA TABLES

TABLE C-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SPLIT SAMPLES COLLECTEDAS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-89 SR-90 GR-A GR-B 3 10/19/11 159 +/- 84 MS-19 01/27/11 233 +/- 85 MS-2 01/27/11 296 +/- 87 MS-3 05/03/11 212 +/- 82 < 0.7 < 0.5 < 1.8 2.4 +/- 1.1 MS-8 07/26/11 246 +/- 96 MW-TMI-101 10/19/11 1727 +/- 140 MW-TMI-1OS 07/27/11 2912 +/- 177 MW-TMI-131 10/18/11 281 +/- 90 MW-TMI-13S 05/04/11 177 +/- 83 < 1.0 < 0.6 < 0.9 2.9 +/- 0.6 MW-TMI-14S 07/26/11 217 +/- 95 MW-TMI-16D 01/27/11 783 +/- 107 MW-TMI-18D 05/04/11 142 MW-TMI-31 10/20/11 145 MW-TMI-41 05/03/11 142 MW-TMI-6D 05/03/11 191 +/- 84 < 0.8 < 0.6 2.1 +/- 0.9 1.4+ 0.6 NW-CW 01/27/11 724 +/- 104 OS-14 07/26/11 202 +/- 94 TM-OS-18 06/01/11 235 +/- 84 TM-OS-18 06/29/11 174 +/- 82 C-I

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, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD MW-TMI-6D 05/03/11 < 26 < 68 <3 <2 <7 <3 <4 <2 <5 <3 <3 <24 <4 MW-TMI-41 05/03/11 < 21 < 48 <2 <2 <7 <2 <3 <3 <5 <3 <3 <14 <3 MW-TMI-13S 05/04/11 < 32 < 73 <3 <2 <5 <3 <5 <4 <3 <4 <2 <24 <3 MW-TMI-18D 05/04/11 < 35 < 70 <3 <2 <7 <3 <5 <3 <5 <4 <4 <18 <4 MS-3 05/03/11 < 31

• 67 <3 <3 <5 <3 <4 <2 <4 <3 <2 <29 <4 OS-14 07/26/11 < 32 < 50 <3 <3 <6 <2 <3 <4 <5 <3 <2 <24 <3 MS-8 07/27/11 < 26 < 46 <1 <3 <5 <2 <3 <2 <5 <2 <2 <21 <4 MW-TMI-101 10/19/11 < 27 < 54 <3 <2 <6 <2 <5 <5 <5 <3 <3 <10 <3

TABLE C-l.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/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 2011

TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-3 5/4/2011 < 142 C-4

TABLE C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD SW-E-3 05/04/11 < 39 < 96 < 3 < 2 < 3 <3 < 6 < 4 < 4 < 3 < 3 < 19 < 4

TABLE C-II1.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION SITE DATE H-3 TM-PR-MS-2Q 03/07/11 < 156 TM-PR-MS-2Q 03/15/11 407 +/- 97 TM-PR-MS-2Q 04/12/11 153 +/- 83 TM-PR-MS-2Q 05/03/11 225 +/- 96 TM-PR-MS-2Q 05/27/11 215 +/- 87 TM-PR-MS-2Q 06/11/11 378 +/- 106 TM-PR-MS-2Q 06/24/11 685 +/- 113 TM-PR-MS-2Q 07/10/11 171 +/- 93 TM-PR-MS-2Q 10/18/11 < 149 C-6

TABLE C-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2011 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-1 37 Ba-140 La-140 PERIOD TM-PR-MS-2Q 04/12/11 <33 < 55 <2 <3 <6 <2 <4 <4 <4 <3 <3 <11 <2