ML091260669

Three Mile Island, Units 1 & 2, Annual Radiological Environmental Operating Report for 1 January Through 31 December 2008

ML091260669
Person / Time
Site:	Three Mile Island
Issue date:	04/30/2009
From:	Exelon Nuclear, Teledyne Brown Engineering Environmental Services
To:	Office of Nuclear Reactor Regulation
References
TMI-09-053
Download: ML091260669 (165)

Text

Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS I and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2008 Prepared By Teledyne Brown Engineering Environmental Services Exelkn..Nuclear Three Mile Island Nuclear Station Middletown, PA 17057 April 2009 Table Of Contents I. Sum m ary and Conclusions

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

1 I1. In tro d u ctio n ........................................................................................................................

3 A. O bjectives of the REM P ....................................................................................

3 B. Im plem entation of the O bjectives

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

4 I11. Program Description

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

4 A. Sam ple Collection

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

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

6 C. Data Interpretation

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

7 D. Program Exceptions

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

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

11 IV. Results and Discussion

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

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

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

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

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

12 4. Storm W ater ....... .................................................................................

.. 14 5. Ground W ater ......................................................................................

14 6 .F is h ....................................................................................

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

1 4 7. Sediment .........................................

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

15 1. Airborne Particulates

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

15 a. Air Particulates

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

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

16 2. Terrestrial

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

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

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

17 C. Am bient Gam m a Radiation

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

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

18 E. Errata Data ............................................

19 F. Radiological Im pact of TM INS Operations

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

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

27 V. References

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

28 Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Appendix B Tables Table B-I: Table B-2: Table B-3: Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2008 Location Designation, Distance & Direction And Sample Collection

&Analytical Methods Location Designation and Identification System for the Three Mile Island Nuclear Station Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2008 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2008 Figqures Figure B-I: Figure B-2: Figure B-3: Appendix C Tables Table C-1.1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2008 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2008 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2008 Data Tables and Figures -Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.ii Table C-1.2 Table C-1.3 Table C-I1.1 Table C-I1.2 Table C011.3 Table C-I1.4 Table C-111.1 Table C-111.2 Table C-IV.1 Table C-V.1 Table C-V.2 Table C-VI.1 Table C-VII. 1 Table C-VII.2 Table C-VII.3 Table C-VIII.1 Table C-IX.1 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.V Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.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, 2008.Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Tritium and Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Strontium in Predator and Bottom Feeder (Fish)Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.'Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.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, 2008.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.iii Table C-IX.2 Table C-IX.3 Table C-X,1 Table C-XI.1 Table C-XI.2 Table C-XI.3 Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Figure C-7 Figure C-8 Figure C-9 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Quarterly TLD Results for Three Mile Island Nuclear Station, 2008.Mean Quarterly TLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2008.Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2008.Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2008.Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2008.Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2008.Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2008.Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2008.Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2008.Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2008, Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2008.Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 -2008.iv Appendix D Tables Table D-I.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-11.1 Table D-1Il.1 Table D-IV.1 Table D-V.1 Table D-V.2 Table D-VI.1 Figures Figure D-1 Figure D-2 Data Tables and Figures -Comparison Laboratory Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2008.Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Iodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2008.Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2008.Appendix E Errata Data v Appendix F Tables Table F-1 Table F-2 Table F-3 Table F-4 Table F-5 Appendix G Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Teledyne Brown Engineering, 2008 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2008 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Environmental, Inc., 2008 Radiological Groundwater Protection Program Report (ARGPPR)vi

1. 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 2008 through 31 December 2008. During that time period, 1,710 analyses were performed on 1,311 samples. In assessing all the data gathered for this report and comparing these results with preoperational data and operational REMP data, it was concluded that the operation of TMINS had no adverse radiological impact on the environment.

Surface, drinking, effluent, and storm 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 results are now being reported in the ARGPPR, Appendix F. No Sr-89 and Sr-90 activities were detected.

Iodine-131 and gross beta concentrations detected were consistent with those detected in previous years.Tritium activity in several monthly effluent water and storm water samples was due to TMINS activities or releases.

No other fission or activation products potentially attributed to TMI release 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. Cesuim-137 was detected in sediment samples at very low levels (just above LLD) and are not distinguishable from background levels.Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides.

Cosmogenic Be-7 was detected at levels consistent with those detected in previous years. No fission or activation products were detected.High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.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 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 2008 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 2008 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 one-half 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), Global Dosimetry Solutions, Inc., and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2008 through 31 December 2008.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.

III. 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 2008. 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, storm 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 (KI1-1). Control locations were A3-2 and Q9-1. Quarterly water samples were taken from one storm water runoff location (EDCB). All groundwater results are now being reported in the ARGPPR, Appendix F. All water samples were collected in either new amber glass or 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 (J2-1, K1-3 and A1-3). 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, EI-2, F1-3, G2-1, H3-1, M2-1, and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached.

The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.Milk samples were collected biweekly at five locations (K1 5-3, D2-1, E2-2, F4-1, and G2-1) from March through November, and monthly from December through February.

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

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

Five different kinds of vegetation samples and four 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 ring consisting of 19 locations (A1-4, B1-2, C1-2, D1-1, EI-4, FI-2, F1-4, GI-3, GI-5, G1-6, H1-1, J1-3, Kl-4, 1-1i, M1-1, Ni-3, P1-2, Q1-2, and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release.An indicator ring consisting of 60 locations (A3-1, A5-1, A9-3, B1i-1, B2-1, B5-1, B10-1, C1-1, C2-1, C5-1, C8-1, Di-2, D2-2, D6-1, EI-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 Global Dosimetry 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 2008. 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, effluent, and storm water, air particulates, milk, fish, sediment, and food products.3. Concentrations of tritium in surface, drinking, effluent, and storm 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 Reportinq 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, effluent, storm, and ground water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, Cs-1 34, Cs-1 37, Ba-140 and La-140 were reported.For fish eight nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-1 34 and Cs-1 37 were reported.For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were reported.For air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-1 34 and Cs-137 were reported.For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-140 and La-140 were reported.For food products four nuclides, K-40, 1-131, Cs-134 and Cs-137 were reported.Means and standard deviations of the results were calculated.

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

D. Program Exceptions For 2008 the TMINS REMP had a sample recovery rate in excess of 99%.Exceptions are listed below: AIR 1. The pump was found stopped and a replacement pump was installed for the following samples: 04/09/08 -04/16/08, Location M2-1 07/30/08 -08/06/08, Location A3-1 2. During the following sampling periods the run time was slightly lower due to a malfunctioning timer. On 12/10/08, an alternate timer was installed to validate the malfunction.

This replacement timer was used until the entire unit was replaced on 2/2/09. IR 870855 describes this issue and the evaluation of the lower volume impact to results for the following samples.10/22/08 -10/29/08, Location A3-1 11/12/08 -11/19/08, Location A3-1 11/19/08 -11/25/08, Location A3-1 11/25/08 -12/03/08, Location A3-1 12/03/08 -12/10/08, Location A3-1 WATER 1. Surface water -During the following weekly sampling periods some of the hourly composite samples were missed due to weather related conditions, frozen sample lines, the sample suction line detaching from the anchor during ice flows and the failure of the controller to detect liquid. The controller was replaced and returned to service, and the ,sample line was repositioned.

Sufficient sample was available for sampling periods so no grab samples were required, except as noted, for the following samples.01/15/08 -01/21/08, Location J1-2 01/21/08 -01/29/08, Location J 1-2 01/29/08 -02/05/08, Location J1-2 02/05/08 -02/12/08, Location JA-2 02/12/08 -02/19/08, Location JA-2 02/26/08 -03/04/08, Location J 1-2 03/04/08 -03/12/08, Location JA-2 03/12/08 -03/18/08, Location J1-2 11/18/08 -11/24/08, Location J1-2 11/24/08 -12/02/08, Location J1-2 12/02/08 -12/09/08, Location J 1-2 12/16/08 -12/23/08, Location JA-2 12/23/08 -12/30/08, Location JA-2, grab sample required.2. Drinking water -During the weekly sampling period, 27 hourly composite samples were not collected due to the sampler being moved by the water treatment plant personnel probably for plant maintenance.

The relocation caused the strainer to be out of the collection bucket resulting in the missed samples. There was sufficient volume collected so no grab sample was required for the following sample: 04/22/08 -4/29/08, Location Q9-1

3. Surface water -During the weekly sampling period, a lower than normal amount of sample was collected or the compositor was found not running. There was sufficient volume collected so no grab sample was required for the following samples: 09/16/08 -09/23/08, Location JA-2 09/03/08 -09/09/08, Location JA-2 4. Drinking water -During the weekly sampling period, the Steelton water plant had a planned power outage for maintenance.

The surface water sampler missed seven hourly samples, but sufficient volume was available for the week so no grab sample was required.

For the drinking water sample the same 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> were missed and the unit was not returned to service properly, so an additional 120 hourly samples were missed. The environmental sampler returned the unit to service properly.

IR 870913 describes this issue. Sufficient volume was not collected for the weekly composite so a grab sample was taken and mixed half and half with the volume available from the sampler for the following sample: 11/11/08-11/18/08, Location Q9-1, grab samplerequired TLD 1. Frozen river condition made it unsafe to travel by boat to the TLDs located on the islands west of the plant. Therefore, the TLD stations were not changed out for the 4th quarter 2008. The TLDs will remain in place and will be changed out for the first quarter 2009 for the following samples: 10/10/08 -01/16/09, Location K2-1 10/10/08 -01/16/09, Location L1-2 10/10/08 -01/16/09, Location M 1-2 10/10/08 -01/16/09, Location N 1-1 10/10/08 -01/16/09, Location P1-1 10/10/08 -01/16/09, Location Q1-1 10/10/08 -01/16/09, Location R1-1 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 in 2008.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-I.1, Appendix C). Positive tritium activity was detected in five of 24 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 266 to 2,380 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 was not detected.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). All nuclides were less than the MDC.2. Drinking Water Monthly samples were collected from continuous water samplers at three locations (G15-2, G15-3, and Q9-1). Two locations (G15-2 and G15-3) could be affected by TMINS' effluent releases.

The following analyses were performed:

Gross Beta Monthly samples from all locations were analyzed for concentrations of gross beta. (Tables C-I1.1, Appendix C). Gross beta activity was detected in 30 of 36 samples. The concentrations ranged from 2.1 to 5.9 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-3, Appendix C).Tritium Monthly ,samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was not detected (Figures C-4, Appendix C).Exelon specified that its laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-I1.4, Appendix C). All nuclides were less than the MDC.3. Effluent Water Monthly samples were collected from a continuous water sampler at one location (K1-1). The following analyses were performed:

Gross Beta Monthly samples from location K1-1 were analyzed for concentrations of gross beta. (Tables C-111.1, Appendix C). Gross beta was detected in all 12 samples. The concentrations ranged from 3.5 to 8.7 pCi/l. Concentrations detected were consistent with those detected in previous years.Iodine-131 Monthly samples from location K1-1 were analyzed for concentrations of iodine-131. (Tables C-I11.1, Appendix C). Iodine-131 was detected in two of 12 samples. The concentrations ranged from 1.2 to 2.0 pCi/L. The positive results are not believed.

to be due to TMINS effluents.

Historically, 1-131 has been detected sporadically in effluent water and not in the control stations.

No 1-131 was identified in any tank effluent pre-release samples, and 1-131 was not detected in any other downstream surface or drinking water samples. Effluent water is not consumed by humans.Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-I11.1, Appendix C). Tritium activity was detected in six samples. The concentrations ranged from 232 to 24,400 pCi/l.The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations.

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

The highest MDC was calculated at 3.3 pCi/I for Sr-89 and at 0.8 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 Monthly grabs from the storm water collection basin (EDCB) were composited quarterly.

The following analyses were performed:

Tritium All samples from location EDCB were analyzed for tritium activity (Table C-IV.1, Appendix C). Tritium activity was detected in one sample at a concentration of 424 pCi/I and was due to airborne releases of H-3 from TMI. The concentration detected was consistent with those detected in previous years.Gamma Spectrometry Samples from location EDCB were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). All nuclides were less than the MDC.5. Ground Water During 2006, Exelon initiated a fleetwide Environmental Assessment program. Comprehensive groundwater studies and reports were developed.

As a result of this assessment and the NEI initiative on groundwater protection, TMI developed a new Radiological Groundwater Protection Program (RGPP) that was implemented by the end of the year. For 2008, this more comprehensive groundwater program replaced TMI's previous groundwater monitoring program. The results from these special investigations and studies are discussed in 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-V.1, Appendix C). No strontium activity was detected.

The highest MDC was calculated at <5 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-V.2, Appendix C).Naturally occurring K-40 was found at all stations and ranged from 2,160 to 3,390 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were found.7. Sediment Aquatic sediment samples were collected at three locations (A1-3, J2-1 and K1-3) semiannually.

In addition, location EDCB was sampled annually.

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 four locations were analyzed for gamma emitting nuclides (Table C-VI.1, Appendix C). Potassium-40 was found at all stations and ranged from 8,080 to 15,700 pCi/kg dry.Cesuim-137 was detected in sediment samples at very low levels (just above LLD) and are not distinguishable from background levels. No other fisson or activation products were found.B. Atmospheric Environment 1 .Airborne Particulates

a. Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. Six locations (E1-2, Fl-3, G2-1, A3-1, M2-1 and H3-1) 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-VII.1 and C-VII.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 36 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.The results from the intermediate offsite locations (Group II)ranged from <7 to 39 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.The results from the Control location (Group Ill)ranged from <7 to 37 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3.Comparison of the 2008 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 2008 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-VII.3, Appendix C).Naturally occurring Be-7 due to cosmic ray activity was detected in all 28 samples. These concentrations ranged from 43 to 125 E-3 pCi/m 3.All other nuclides were less than the MDC.b. Airborne Iodine Continuous air samples were collected from seven (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1, and Q15-1) locations and analyzed weekly for 1-131 (Table C-VIII.1, Appendix C). All results were less than the MDC.2. Terrestrial

a. Milk Samples were collected from five locations (K15-3, D2-1, E2-2, F4-1 and G2-1) biweekly March through November and monthly December through February.

The following analyses were performed:

Iodine-1 31 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-IX.1, Appendix C). All results were less than the MDC.Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-IX.2, Appendix C). No Sr-89 activity was detected.

Strontium-90 activity was detected in 11 of 21 samples. The concentrations ranged from 0.6 to 1.4 pCi/I. The activity detected was consistent with those detected in the pre-operational years (Figure C-8, Appendix C).Gamma Spectrometry Milk samples from all locations were analyzed for concentrations of gamma emitting nuclides (Table C-IX.3, Appendix C).Naturally occurring K-40 activity was found in all samples.The concentrations ranged from 627 to 1,570 pCi/I. All other nuclides were less than the MDC.b. Food Products Samples were collected from two locations (B10-2 and HI-2)monthly, in lieu of milk sampling.

Samples from the four food product groups were collected from two locations (B10-2 and E1-2) annually.

The following analyses were performed:

Strontium Each food product sample was analyzed for concentrations of Sr-90 (Table C-X.1, Appendix C). Strontium-90 activity was detected in 20 of 20 samples. The concentrations ranged from 6 to 67 pCi/kg wet.Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-X.1, Appendix C).

Naturally occurring K-40 activity was found in all samples.The concentrations ranged from 1,520 to 7,090 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-XI.1 to C-XI.3, Appendix C.All TLD measurements were below 10 mR/standard month, with a range of 3.5 to 8.9 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 were consistently higher. 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 R1 5-1 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 September, October and November 2008 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 2.15 and 3.4.2 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. There were no changes required to the TMINS REMP, as a result of this survey. Five gardens from the 2007 census were not established in 2008. As such, five new gardens were identified.

The locations where new gardens were identified include sectors F (ESE), G (SE), K (SSW), M (WSW) and Q (NW). Of the five new gardens, none were located closer to TMINS than those identified in 2007. The results of this survey are summarized below.

Distance in Miles from the TMINS Reactor Buildings Sector Residence Garden Milk Farm Miles Miles Miles 1 N 1.1 1.6 2.1 2 NNE 0.7 0.9 -3 NE 0.5 0.8 4.1 4 ENE 0.5 0.5 1.1 5 E 0.4 0.5 1.1 6 ESE 1.1 1.2 3.2 7 SE 0.7 0.9 1.4 8 SSE 0.7 0.8 -9 S 2.3 2.7 10 SSW 0.6 2.5 4.9,14.5 11 SW 0.5 0.6 12 WSW 0.5 1.3 13 W 0.7 1.4 14 WNW 0.4 2.2 3.7 15 NW 0.4 2.2 -16 NNW 1.1 2.4 E. Errata Data There was not at least one TLD listed for each sector for the site boundary ring. The program description in section 11I.A has been corrected for the 2008 report and a revised Table C-XI.2 for the 2007 TLD measurement results is included in Appendix E.F. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2008 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation.

The 2008 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 0.03 mrem. This dose is equivalent to <0.01% 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 2008 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 2008 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 100 mrem/yr (Ref. 5). Additionally, the average individual living in the United States receives an annual dose of about 2,400 mrem to the lung from natural radon gas. This lung dose is considered to be equivalent to a whole (or total) body dose of 200 mrem (Ref. 5). Therefore, the average person in the United States receives a whole body dose of about 300 mrem/yr from natural background radiation sources. -As shown on Table 2, the maximum hypothetical whole body dose received byan individual from 2008 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.03 mrem. This dose is equivalent to <0.01% percent of the dose that an individual living in the TMI area receives each year from natural background radiation (300 mrem).The low doses calculated for 2008 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).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 2008 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 2008 did not have any adverse effects on the health of the public or on the environment.

TABLE 1 Calculated Maximum Hypothetical Doses to an Individual from 2008 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual USNRC 10 CFR 50 APP. I Guidelines (mrem/yr)From Radionuclides In Liquid Releases From Radionuclides In Airborne Releases (Noble Gases)From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates) 3 total body, or 10 any organ 5 total body, or 15 skin 15 any organ Calculated Dose (mrem/yr)TMI-1 TMI-2 1.88E-2 3.65E-4 2.12E-2 5.81E-4 2.50E-6 0*2.26E-5 0*6.96E-3 1.72E-3*No noble gases were released from TMI-2.USEPA 40 CFR 190 Limits (mrem/yr)Calculated Dose (mrem/yr)TMI-1 and TMI-2 Combined**

0.21 Total from Site 75 thyroid 25 total body or other organs 0.22* *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 2008 TMINS operations was 0.19 mrem. This dose was based on a maximum net fence-line exposure rate of 5.1 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 (0.03 mrem) and the dose from direct radiation (0.19 mrem) yielded a maximum hypothetical dose of 0.22 mrem.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2008 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 From Radionuclides in Airborne Releases (Noble Gases)From Radionuclides In Airborne Releases (Iodines, Tritium and Particulates)

• No noble gases were released from TMI-2.1.88E-2 3.65E-4 2.50E-6 0*6.75E-3 1.72E-2 Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations:

Individual Whole Body Dose Due to Natural Background Radiation 0.03 mrem/yr 300 mrem/yr Figure 1 Exposure Pathways For Radionuclides Routinely Released From TMINS NOBLE GASES (Xe,Kr)Plume exposure R-AD10OIODINES (I -131, f-133)Inhalation and oonsumption of milk, water, fruits, and vegetables RADtOSTRONTIUMS (Sr-89, Sr-90)Consumption of milk, meat, fruits, and vegetables ACTIVATION PRODUCTS.(Co-60, Mn.54)Shoreline exposure RADIOCESIUMS (Cs-134, Cs-137)Shoreline exposure and consumption of milk, meat, fish, water, fruits, and vegetables TR[TIUJM (H-3)Inhalation and consumnption of water, milk, fruits, and vegetables G. Summary of Results -Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria: 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable.

The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.The MAPEP defines three levels of performance:

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

For the primary laboratory, 16 out of 18 analytes met the specified acceptance criteria.

Two samples did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's Analytics December 2008 Sr-89 in milk result of 18.0 pCi/L was higher than the known value of 12.6 pCi/L, resulting in a found to known ratio of 1.43. NCR 09-02 was initiated to investigate this failure.2. Teledyne Brown Engineering's Analytics' ERA Quik Response water sample January 2008 Sr-89 result of 37.33 pCi/L exceeded the upper acceptance limit of 25.2 pCi/L. No cause could be found for the failure. Studies bracketing these results, RAD 71 and RAD 72 had acceptable Sr-89 results. NCR 08-03 For the secondary laboratory, all of the 15 analytes met the specified acceptance criteria.The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.V. References 1 .Three Mile Island Nuclear Station, Unit 1, Technical Specifications, DPR 50.2. Three Mile Island Nuclear Station, Unit 2, PDMS Technical Specifications, DPR 73.3. Radiation Management Corporation. "Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1974 -June5, 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.93. "Ionizing Radiation Exposure of the Population of the United States." 1987.

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING

-REPORT

SUMMARY

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER (PCI/LITER)

H-3 1-131 24 12 24 2000 1090 (5/12)(266/2380) 1 NA<LLD<LLD 1090 (5/12)(266/2380)

TM-SW-J1-2 INDICATOR WEST SHORE; TMI 0.5 MILES S OF SITE 0 0 GAMMA MN-54 CO-58 FE-59 15 <LLD 15 <LLD 30 <LLD 15 <LLD<LLD<LLD<LLD<LLD 0 0 0 n CO-60 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M), MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER (PCI/LITER)

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER (PCI/LITER)

GR-13 1-131 36 36 36 36 4 3.6 (22/24)(2.1/5.9)3.1 (8/12)(2.3/4.0)4.1 (11/12)(2.9/5.9)G15-2 INDICATOR WRIGHTS WATER SUPPLY 13.6 MILES SE OF SITE<LLD<LLD 0 0 0 H-3 GAMMA MN-54 2000 <LLD 15 <LLD 15 <LLD 30 <LLD<LLD<LLD CO-58 FE-59<LLD 0 0 0<LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER (PCI/LITER)

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER (PCI/LITER)

EFFLUENT WATER (PCI/LITER)

LA- 140 15 <LLD 4 5.5"(12/12)(3.5/8.7)<LLD GR-B 1-131 12 NA 5.5 (12/12)(3.5/8.7)1.6 (2/12)(1.2/2.0)12 12 H-3 1 1.6 (2/12)(1.2/2.0)2000 10547 (6/12)(232/24400)

NA <LLD 2 <LLD NA NA NA NA KI-1 INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE KI-1 INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 0 0 0 0 0 0 10547 (6/12)(232/24400)

SR-89 SR-90 2 2 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER (PCI/LITER)

GAMMA MN-54 12 15 <LLD NA CO-58 FE-59 CO-60 ZN-65 NB-95 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD NA NA NA NA NA 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER (PCI/LITER)

ZR-95--.1 CS-134 CS-137 BA-140 LA-140 30 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD 2000 424 (1/4)NA NA 0 0 0 0 NA NA NA NA 0 0 STORM WATER (PCI/LITER)

H-3 4 424 (1/4)EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 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 STORM WATER (PCI/LITER)

GAMMA M/1N-54 4 15 <LLD NA 00 0 0 CO-58 FE-59 CO-60 ZN-65 NB-95 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD NA NA NA NA NA 0 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 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 STORM WATER (PCI/LITER)

ZR-95 30 <LLD NA 0 CS-134 CS-137 BA-140 LA-140 15 <LLD 18 <LLD 60 <LLD 15 <LLD NA NA NA NA<LLD 0 0 0 0 BOTTOM FEEDER (PCI/KG WET)SR-90 4 10 <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)I TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER (PCI/KG WET)GAMMA 4 K-40 NA 2760 (2/2)(2160/3360) 2765 (2/2)(2430/3100) 2765 (2/2)(2430/3100)

BKGB CONTROL CITY ISLAND UPSTREAM OF DISCHARGE 0 MN-54 CO-58 FE-59 CO-60 ZN-65 130 <LLD 130 <LLD 260 <LLD 130 <LLD 260 <LLD<LLD<LLD<LLD<LLD 0 0 0 0 0<LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER (PCI/KG WET)CS-134 CS-137 SR-90 GAMMA K-40 130 <LLD 150 <LLD 10 <LLD<LLD<LLD 0 0 0 PREDATOR (PCI/KG WET)4 4<LLD NA 3385 (2/2)(3380/3390) 2810 (2/2)(2430/3190) 3385 (2/2)(3380/3390)

INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE MN-54 CO-58 130 <LLD<LLD<LLD 0 0 0 130 <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)I TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS PREDATOR (PCI/KG WET)FE-59 CO-60 ZN-65 CS-134 CS-137 260 <LLD 130 <LLD 260 <LLD 130 <LLD 150 <LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0 SEDIMENT (PCI/KG DRY)GAMMA K-40 7 NA 11584 (5/5)(8080/15700) 9160 (2/2)(9020/9300) 15700 (1/1)EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT (PCI/KG DRY)MN-54 CO-58 CO-60 CS-134 CS-137 NA <LLD NA <LLD NA <LLD 150 <LLD 180 131 (3/5)(86/194)10 18 (307/311)(7/39)<LLD<LLD 0 0 0<LLD<LLD 0<LLD 18 (50/52)(8/37)194 (1/1)18 (50/52)(8/37)EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE Q15-1 CONTROL WEST FAIRVIEW 13.5 MILES NW OF SITE 0 0 AIR PARTICULATE (E-3 PCI/CU.METER)

GR-B 363 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE (E-3 PCI/CU.METER)

GAMMA BE-7 MN-54 CO-58 28 NA 78 (24/24)(43/125)NA <LLD NA <LLD NA <LLD 50 <LLD 60 <LLD 78.7 (4/4)(50/97)<LLD<LLD<LLD<LLD<LLD 85.8 (4/4)(43/125)M2-1 INDICATOR FISHING CREEK; GOLDSBORO 1.3 MILES WSW OF SITE 0 0 CO-60 CS-134 CS-137 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 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 IODINE (E-3 PCI/CU.METER)

MILK (PCI/LITER)

GAMMA 1-131 363 1-131 115 SR-89 20 20 70 <LLD 1 <LLD NA <LLD 2 .9 (9/16)(0.6/1.1)NA 1256 (92/92)(627/1570)

<LLD<LLD<LLD 0 0 0 0 SR-90 GAMMA K-40 CS-134 1 (2/4)(0.6/1.4)1339 (23/23)(1210/1560) 1 (2/4)(1.0/1.1)1339 (23/23)(1210/1560)

TM-M-F4-1 INDICATOR TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE TM-M-K15-3 CONTROL MEYER'S FARM 14.5 MILES SSW OF SITE 115 0 0 15 <LLD<LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK (PCI/LITER)

CS-137 BA-140 18 <LLD 60 <LLD 15 <LLD<LLD<LLD<LLD 0 0 0 0 VEGETATION (PCI/KG WET)LA-140 SR-90 GAMMA BE-7 20 26 10 28.2 (10/10)(10.5/44.8)

NA 688 (8/13)(85/1860)NA 3642 (13/13)(1520/6080) 27.3 (10/10)(6.3/66.8) 672 (5/13)(314/1100) 3375 (13/13)(1600/7090) 30.1 (9/9)(12.6/44.8) 774 (7/9)(194/1860) 3786 (9/9)(1520/6080)

HI -2 INDICATOR RED HILL MARKET ALONG ROUTE 441 1.0 MILES SSE OF SITE H 1-2 INDICATOR RED HILL MARKET ALONG ROUTE 441 1.0 MILES SSE OF SITE H 1-2 INDICATOR RED HILL MARKET ALONG ROUTE 441 1.0 MILES SSE OF SITE 0 K-40 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2008 Name of Facility:

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

MIDDLETOWN COUNTY PA REPORTING PERIOD: 2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION (PCI/KG WET)1-131 CS-134 CS-137 60 <LLD 60 <LLD 80 <LLD NA 4.9 (309/309)(3.5/8.9)<LLD 0<LLD<LLD 0 DIRECT RADIATION TLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.)

353 5.5 (44/44)(4.3/7.4)8.0 (4/4)(7.4/8.9)H8-1 INDICATOR SAGINAW ROAD, STARVIEW 7.4 MILES SSE OF SITE 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

Intentionally left blank APPENDIX B LOCATION DESIGNATION, AND SAMPLE COLLECTION DISTANCE & DIRECTION,& 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-1 TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2008 Sample Medium AQS ID APAIID SW ID ID ID ID ID ID ID FP ID ID ID ID ID AQF ID ID M ID ID ID AP,AI,ID,FP ID M ID ID ID ID ID AP,Al ID ID M ID ID ID ID ID ID ID AI,AP,M ID ID ID ID DW DW Station Code A1-3 A1-4 A3-1 A3-2 A5-1 A9-3 B1-1 B1-2 B2-1 B5-1 B10-1 B10-2 C1-1 C1-2 C2-1 C5-1 C8-1 Control D1-1 D1-2 D2-1 D2-2 D6-1 D15-1 E1-2 -E1-4 E2-2 E2-3 E5-1 E7-1 F1-1 F1-2 F1-3 F1-4 F2-1 F4-1 F5-1 F10-1 F25-1 G1-2 G1-3 G1-5 G1-6 G2-1 G2-4 G5-1 G10-1 G15-1 G15-2 G15-3 Map Number 1 1 2 2 2 3 2 2 Distance (miles)0.5 0.3 2.7 2.7 4.4 8.0 0.6 0.4 1.9 4.9 3 9.2 10 0.7 0.3 1.5 4.7 7.1 0.2 0.5 1.1 1.6 5.2 10.8 0.4 0.2 1.1 2.0 4.7 6.7 0.5 0.2 0.6 0.2 1.3 3.2 4.7 9.4 Azimuth Description 3590 N of site off north tip of TMI in Susquehanna River 60 N of Reactor Building on W fence adjacent to North Weather Station, TMI 3570 N of site at Mill Street Substation 3560 N of site at Swatara Creek, Middletown 30 N of site on Vine Street Exit off Route 283 20 N of site at Duke Street Pumping Station, Hummelstown 250 NNE of site on light pole in middle of North Bridge, TMI 230 NNE of Reactor Building on top of dike, TMI 170 NNE of site on Sunset Dr. (off Hillsdale Rd.)190 NNE of site at intersection of School House and Miller Roads 210 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey 310 NNE of site at Milton Hershey School, Hershey 370 NE of site along Route 441 N 500 NE of Reactor Building on top of dike, TMI 440 NE of site at Middletown Junction 430 NE of site on Kennedy Lane 480 NE of site at Schenk's Church on School House Road-All locations where finfish are collected above Dock St.Dam, Harrisburg 760 ENE of Reactor Building on top of dike, TMI 670 ENE of site off Route 441 along lane between garden center and residence 620 ENE of site at farm on Gingrich Road 740 ENE of site along Hillsdale Rd. (S of Zion Rd.)660 ENE of site off Beagle Road 640 ENE of site along Route 241, Lawn 970 E of site at TMI Visitor's Center 970 E of Reactor Building on top of dike, TMI 960 E of site at farm on Pecks Road 970 E of site along Hillsdale Rd. (N of Creek Rd.)820 E of site' at intersection of North Market Street (Route 230) and Zeager Road 880 E of site along Hummelstown Street, Elizabethtown 1170 ESE of site near entrance to 500 kV Substation 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI 1120 ESE of site in 500 kV Substation 1220 ESE of Reactor Building on top of dike, TMI 1190 ESE of site along Engle Road 1040 ESE of site at farm on Turnpike Road 1090 ESE of site along Amosite Road 1120 ESE of site along Donegal Springs Road, Donegal Springs 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster 1450 SE of site along Route 441 S 1300 SE of Reactor Building on top of dike, TMI 1430 SE of Reactor Building on top of dike, TMI 1390 SE of Reactor Building on top of dike, TMI 1260 SE of site at farm on Becker Road 1380 SE of site on Becker Road 1310 SE of site at intersection of Bainbridge and Risser Roads 128' SE of site at farm along Engles Tollgate Road, Marietta 1260 SE of site at Columbia Water Treatment Plant 1290 SE of site at Wrightsville Water Treatment Plant 124 SE of site at Lancaster Water Treatment Plant 3 22 1 2 2 2 3 3 3 3 0.7 0.2 0.3 0.3 1.4 1.7.4.8 9.7 14.4 13.3 15.7 B-2 TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2008 Sample Medium Station Map Distance Code Number (miles)Azimuth Description ID FP APAIID ID Hi-i Hi1-2 H3-1 H5-1 H8-1 Hi5-1 2 2 0.5 1.0 2.2 4.1 ID ID 3 7.4 3 13.2 AQF ID SW ID AQS ID ID ID ID EW AQS Indicator ID ID ID ID ID ID M ID ID ID ID ID ID ID JA-1 JA-2 JA-3 J2-1 J3-1 J5-1 J7-1 J15-1 K1-1 K1-3 K1-4 K2-1 K3-1 K5-1 K8-1 K15-1 K15-3 1-1-1 L1-2 L2-1 L5-1 L8-1 L15-1 M1-1 M1-2 M2-1 M5-1 M9-1 N1-1 N1-3 N2-1 N5-1 N8-1 N15-2 1 1 1 0.3 2 1.4 2 2 3 3 2 2 2 3 2.7 4.9 6.5 12.6 0.2 0.2 0.8 0.5 0.2 1.2 2.0 4.9 7.5 1670 SSE of site, TMI 151' SSE of site along Route 441, Red Hill Market 1600 SSE of site in Falmouth-Collins Substation 1580 SSE of site by Guard Shack at Brunner Island Steam Electric Station 1630 SSE of site along Saginaw Road, Starview 157' SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills-All locations where finfish are collected downstream of the TMINS liquid discharge outfall 1760 S of site, TMI 188' S of site downstream of the TMINS liquid discharge outfall in Susquehanna River 1890 S of Reactor Building just S of SOB, TMI 1790 S of site in Susquehanna River just upstream of the York Haven Dam 1790 S of site at York Haven/Cly 1810 S of site along Canal Road, Conewago Heights 1760 S of site off of Maple Street, Manchester 1830 S of site in Met-Ed York Load Dispatch Station 2100 On site at RML-7 Main Station Discharge Building 212' SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River 2090 SSW of Reactor Building on top of dike behind Warehouse 2, TMI 200' SSW of site on S Shelley Island 2060 SSW of site along Rt. 262, N of Cly 2020 SSW of site along Conewago Creek Road, Strinestown 1960 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View 203' SSW of site behind McDonald's and next to child care center, Weiglestown 2050 SSW of site at farm along S Salem Church Rd, Dover 2360 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI 2210 SW of site on Beech Island 2240 SW of site along Route 262 2280 SW of site at intersection of Stevens and Wilson Roads 2250 SW of site along Rohlers Church Rd., Andersontown 2260 SW of site on W side of Route 74, rear of church, Mt.Royal 2500 WSW of Reactor Building on SE corner of U-2 Screenhouse fence, TMI 252' WSW of site on E side of Shelley Island, Lot #157 2560 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown 243' WSW of site along Alpine Road, Maytown 274' W of site on W side of Shelley Island, between lots #13 and #14 274' W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI 2610 W of site at Goldsboro Marna 2680 W of site off of Old York Road along Robin Hood Drive 2620 W of site along Route 382, 1/2 mile north of Lewisberry 2750 W of site at intersection of Lisburn Road and Main Street, Lisbum 3030 WNW of site on Shelley Island 3 12.8 3 14.4 1 0.1 1 2 2 3 3 0.5 1.8 4.1 8.0 11.8 ID APAIID ID ID ID ID ID ID ID ID ID 1 0.1 1 0.4 2 1.3 2 4.3 3 8.7 1 0.7 1 0.1 2 2 3 3 1.2 5.0 7.7 10.4 P1-1 0.4 B-3 TABLE B-2: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2008 Sample Medium Station Map Distance Code Number (miles Azimuth Description ID ID ID ID ID ID.ID ID SW,DW,ID APAIID P1-2 P2-1 P5-1 P8-1 Q1-1 Q1-2 Q2-1 Q5-1 Q9-1 Q15-1 R1-1 Ri-2 R3-1 R5-1 1 0.1 2 2.0 2 5.0 3 2 2 3 3 3 1 2 2 8.0 0.5 0.2 1.9 5.0 8.5 13.4 0.2 0.7 2.6 4.9 2920 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 2830 WNW of site along Route 262 284' WNW of site at intersection of Valley Road (Route 262)and Beinhower Road 292' WNW of site along Evergreen Road, Reesers Summit 3170 NW of site on E side of Shelley Island 321 0 NW of Reactor Building on fence W of Warehouse 1, TMI 3100 NW of site along access road along river 3170 NW of site along Lumber Street, Highspire 3100 NW of site at the Steelton Water Company 3090 NW of site behind West Fairview Fire Dept. Social Hall (abandoned) 3350 NNW of Reactor Building along W fence, TMI 3340 NNW of site on central Henry Island 3410 NNW of site at Crawford Station, Middletown 3390 NNW of site at intersection of Spring Garden Drive and Route 441 341' NNW of site at intersection of Derry and 66th Streets, Rutherford Heights 332' NNW of site at intersection of Route 22 and Colonial Road, Colonial Park ID ID ID ID ID ID R9-1 3 8.0 3 11.2 R15-1 IDENTIFICATION KEY ID SW Al AP FP= Immersion Dose (TLD)= Surface Water= Air Iodine= Air Particulate

= Food Products (Green Leafy Vegetation, Fruits, Vegetables)

EW DW M AFT AQS= Effluent Water= Drinking Water= Milk (Cow)= Finfish= Aquatic Sediment B-4 TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2008 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) I Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchange Effluent Water Iodine-131 Monthly composite from a continuous water compositor.

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

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

TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2008 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Gamma Monthly composite ER-TM1-06 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 89/90 Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange Water 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 I 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)other techniques W

TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2008-3 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 composite ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2008 Gross alpha and/or gross beta activity in Particulates of continuous air iodine samples for radiological analysis (Three (approximately various matrices sampling through Mile Island Nuclear Station) 280 cubic glass fiber filter meters weekly) Env. Inc., AP-02 Determination of gross alpha and/or gross paper beta in air particulate filters 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 composite ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy of continuous air iodine samples for radiological analysis (Three (approximately sampling through Mile Island Nuclear Station) 280 cubic Env. Inc., 1-131-02 Determination of 1-131 in charcoal charcoal filter meters weekly) canisters by gamma spectroscopy (batch method)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-89/90 Quarterly composite ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange of Bi-weekly and radiological analysis (Three Mile Island Nuclear monthly grab Station)samples TBE, TBE-2023 Compositing of samples Milk Gamma Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., GS-01 Determination of gamma emitters by Monthly all other gamma spectroscopy times Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy TABLE B-3: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2008 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Vegetation Strontium-89/90 Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange grab sample radiological analysis (Three Mile Island Nuclear Station)TLD Thermolumines Quarterly TLDs ER-TMI-02 Collection of TLD samples for 2 badges with 3 Global Dosimetry Solutions, Inc.cence comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Dosimetry Panasonic 814 Station)(containing 4 each CaSO 4 elements)W COO 9~d* Loabftare w ed byr suwa*2 Locabons we bawd an GPS teadng rubteftte.

I* a nrldpunfd belvieeuTM-1 andTM.2 I sabo"P T1 PAS stmepwowieti~

N4AM, fte Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2008 B-9

!/1. Locations am. based on GPS raig eeea to a midiotu*betwm TWA- andTM-2 2. Okasenap .n PA tatepan. Sonulk NAD27, feet-----r-----Locations of Landuse Stations for Three Mile Island Generating Station 2008 NORMANDEAU ASSOCIATES ENVIRONMENTAL CONSULTANTS am*~ %Adarenn by t.-ey Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2008 B-10 Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2008 B-1I Intentionally left blank APPENDIX C DATA TABLES AND FIGURES -PRIMARY LABORATORY TABLE C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04101/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08 J,1-2 Q9-1< 159< 170< 180 266 +/- 120 1600 +/- 229 516 +/- 127< 171< 140 2380 +/- 291 687 +/- 144< 185< 173< 156< 172< 166< 193< 166< 165< 167< 139< 153< 166< 191< 175 MEAN 1090 +/- 1759 TABLE C-I.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD A3-2 12/31/U 01/29/08 02/26/08 04/01/08 04/29/08 06/03/08 07/01/08 07/29/08 09/03/08 09/30/08 10/28/08 12/02/08 U1I/29/u 02/26/08 04/01/08 04/29/08 06/03/08 07/01/08 07/29/08 09/03/08 09/30/08 10/28/08 12/02/08 12/30/08< uJ~< 0.7< 0.6< 0.6* 0.7< 0.8< 0.8* 0.7< 0.6< 0.8< 0.6< 0.5 MEAN* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-i TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD J1-2 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 MEAN<5<6<6<5<4<4<1<1<1<4<4<4<7<4<6<3<4<5<1<2<1<4<4<6<6<6<6< 6<4<5<1<2<1<4<4< "1z< 12< 10< 13< 10<8< 12<3<4<2<9<8<11< 12<8< 14<8<9< 11<3<4<2<9<9<4<6<5<5<4<6<1<2<0<4<4<6<7<5<8<5<4<5<1<2<1<4<4< 115< 11< 12< 14< 11<8< 11<3< 3<1<8<8< 12< 14<7< 16<8< 11 ,< 12<2<3<1<9<8<5<6<5<5<5<6<1<2<1<4<5<7<8<4<7<5<4<5<1<2<1<5<6<11< 10< 10<9<8<9<3<3<1<8<7<10<11<8< 11<7<8<8<3<3<2<8<8<5<5< 5<7<4<4<4<1<1<0<4<4<6<6<4<8<4<5<5<1<1<1<4<4<6<6<6<6<5<5< 5<1<2<0<4<4<5<7<5<7<4<4<4<1<2<1<4<4< 22< 23< 28< 35< 31< 34< 18< 18< 18< 23< 26< 22< 28< 17< 34< 31< 31< 26< 18< 19< 22< 25< 29< 6<7<5< 10< 12< 11< 15<6<6<5<8< 10<7<9<5< 11< 11<9< 11<6<6<8<7<8 Q9-1 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08<5<5<5<7<4<4<5<1<2<1<4<4 MEAN TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+ 2 SIGMA COLLECTION PERIOD G15-2 G15-3 09-1 A nA Il/3, iUf 01/29/08 02/26/08 04/01/08 04/29/08 06/03/08 07/01/08 07/29/08 09/03/08 09/30/08 10/28/08 12/02/08-U IILdlUtO-02/26/08-04/01/08-04/29/08-06/03/08-07/01/08-07/29/08-09/03/08-09/30/08-10/28/08-12/02/08-12/30/08 4.9 5.9 3.2< 2.0 2.9 3.1 3.3 4.0 3.9 4.4 4.0 5.1+/-+/-++/-+++++++1.5 1.6 1.5 1.5 1.5 1.5 1.8 1.7 1.6 1.7 1.8 2.9 2.8 2.6 2.1 2.3 2.7 4.3 3.3 4.2 3.6 3.8< 2.1+/- 1.3+/- 1.3+/- 1.4+/- 1.4+/- 1.5+/- 1.5+/- 1.6+/- 1.8+/- 1.8+/- 1.6+/- 1.6 3.3 +/- 1.3 2.8 +/- 1.2< 1.9 2.4 +/- 1.4 3.6 +/- 1.6 2.3 +/- 1.4 2.6 +/- 1.4< 2.4 3.4 +/- 1.6 4.0 +/- 1.6< 2.2< 2.1 3.1 +/- 1.2 MEAN 4.1 +/- 1.9 3.1 +/- 1.5 TABLE C-11.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA U COLLECTION PERIOD 12/31/07 -01/29/08 01129/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08 G15-2 G15-3 Q9-1< 0.4< 0.8< 0.9< 0.5< 0.7< 0.8< 0.7< 0.6< 0.9< 0.9< 0.5< 0.6< 0.4< 0.8< 1.0< 0.6< 0.8< 0.8< 0.7< 0.8< 0.6< 0.8< 0.6< 0.4< 0.6< 0.7< 0.9< 0.6< 0.7< 0.7< 0.7< 0.7< 0.7< 0.9< 0.6< 0.6 MEAN TABLE C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08 G15-2 G15-3 Q9-1< 151< 172< 171< 176< 170< 167< 168< 141< 169< 163< 188< 173< 156< 166< 172< 174< 173< 165< 167< 140< 169< 170< 190< 174 156 170 177 175 169 167 173 141 162 169 180 175 MEAN* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-3 TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 G15-2 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08 cm MEAN<5<4<6<4<4<4<2<2<1<4<3<5<5<5<6<4<4<4<2<2<1<4<5<5<3<6<5<4<5<2<2<2<5<3<5<5<5<5<4<5<5<2<2<1<4<5<10 <4<7 <4<14 <7<10 <5<10 <4<11 <5<4 <2<5 <2<4 <1<9 <3<8 <3<10 <5<10 <6<9 <8<12 <6<9 <4<9 <4<9 <4<4 <2<5 <2<4 <2<8 <4<13 <5<8 <5<8 <5<14 <7<9 <5<7 <4<7 <5<3 <2<4 <2<3 <2<7 <4<7 <4<9 <4<11 <6<10 <5<13 <6<7 <5<8 <4<8 <5<3 <2<4 <2<2 <2<8 <3<8 <5<IU<9<6< 11<8<8<8<3<4<3<8<6<5<3<6<3<4<5<1<2<1<4<3<4<4< 4<7<4<4<5<2<2<1<4<3<5<6<6<5<5<4<5<2<2<1<4<5<20 <8<14 <6<35 < 12< 31 < 10<30 <9<32 < 10<19 <6<19 <6<36 < 13<23 <7<21 <6<18 <5<20 <8<21 <7<31 <7<29 < 10<28 <8<27 < 10<19 <7<19 <6< 37 < 12<22 <6<34 < 11 G15-3 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08<8 <4<10 <5<9 <5<9<7<7<8<3<3<3<7<9<5<4<3<4<2<2<1<3<4 MEAN TABLE C-II.4 'CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA STC 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 12/31/07 -01/29/08

< 5 < 4 < 10 < 5 < 10 < 4 < 9 < 5 < 5 < 21 < 6 01/29/08 -02/26/08 < 6 < 6 < 9 < 6 < 11 < 5 < 8 < 5 < 7 < 22 < 8 02/26/08 -04/01/08 < 5 < 4 < 8 < 5 < 10 < 5 < 7 < 4 < 5 < 18 < 6 04/01/08 04/29/08 < 6 < 5 < 13 <7 < 10 < 6 < 9 < 5 <5 <29 < 8 04/29/08 -06/03/08

< 4 < 4 < 9 < 4 < 8 < 4 < 6 < 3 < 4 < 26 < 7 06/03/08 -07/01/08 < 4 < 4 < 10 < 4 < 7 < 4 < 9 < 4 <4 < 31 < 8 07/01/08 -07/29/08 < 6 < 5 < 15 < 6 < 10 < 5 < 11 < 5 <5 < 37 < 12 07/29/08 -09/03/08

<2 <2 <4 <2 < 3 <2 < 3 < 2 <2 < 19 <6 09/03/08 -09/30/08

< 2 < 2 < 5 < 1 <13 < 2 < 4 < 2 < 2 < 19 < 6 09/30/08 -10/28/08 < 1 < 1 < 3 < 1 <2 < 2 < 3 < 1 < 1 < 35 < 10 61 10/28/08 -12/02/08 < 4 <4 < 10 <4 < 10 < 5 < 8 <4 <5 <23 < 8 12/02/08 -12/30/08

<4 <4 < 9 <4 <8 < 5 <8 <4 < 5 <26 < 8 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, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD GROSS BETA 1-131 H-3 SR-89 SR-90 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08 3.5 +/- 1.4 4.5 +/- 1.5 5.0 +/- 1.7 4.7 +/- 1.7 5.4 +/- 1.9 6.4 +/- 2.0 4.4 +/- 1.8 7.5 +/- 2.3 6.2 +/- 2.0 8.7 +/- 2.1 5.1 +/- 1.9 4.5 +/- 1.7 5.5 +/- 2.9< 0.9< 0.6< 0.8< 0.4< 0.9< 0.9< 0.7 1.2 +/- 0.3< 0.7 2.0 +/- 0.5< 0.6< 0.6 1.6 +/- 1.1< 151< 172< 175 3040 +/- 370 24400 +/- 2490-9490 +/- 1000 < 3.3< 166< 140 19400 +/- 2010 6720 +/- 717< 191 232 +/- 123 < 2.9 10547 +/- 18948< 0.6< 0.8 MEAN* 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, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-14012/3IIU7 01/29/08 02/26/08 04/01/08 04/29/08 06/03/08 07/01/08 07/29/08 09/03/08 09/30/08 10/28/08 12/02/08 U Il/IU90 02/26/08 04/01/08 04/29/08 06/03/08 07/01/08 07/29/08 09/03/08 09/30/08 10/28/08 12/02/08 12/30/08<:4<4<5<5<4<4< 4<1<2<1<3<3<4 <7 <4 <7<4 <9 <3 <8<6 <9 <5 <11<6 <9 <6 <12<5 <11 <4 <10<5 <11 <5 <8<5 <11 <3 <9<1 <3 <1 <2<2 <4 <2 <4<1 <3 <1 '<2<3 <6 <3 <6<3 <6 <3 <7<4<5<6<5<5<5<5<1<2<2<3<3<6<8<9<8<8<8< 10<2<3<3<6<6<4<5<5<5<4<4<4<1<2<1<3<3<4<4<6<6<5<4<4<1<2<1<3<4< 16< 19< 21< 25< 29< 30< 31< 18< 21< 36< 16< 21<5<4<7< 10< 10< 10<9<5<7< 10<4<7 MEAN TABLE C-IV.1 CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD H-3 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 EDCB 01/29/08 -04/01/08 04/29/08 -07/01/08 07/29/08 -09/30/08 10/28/08 -12/30/08 MEAN 424 +/- 123< 164< 161< 192<5 <6 <12<2 <2 <5<4<2<10 <5 <9 <6 <6<5 <3 <4 <2 <2<10 <6 <9 <5 <5<4 <3 <4 <2 <2< 27< 16< 30< 25<7<5< 11<8<5<2<4 <11 <4<2 <6 <2 1 424 +/- 0 C)

TABLE C-V.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH)SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD INDP PREDATOR 06/16/08 10/07/08 Sr-90<3<5 MEAN INDB BOTTOM FEEDER 06/03/08 10/07/08<4<3 MEAN BKGP BOTTOM FEEDER 06/17/08 10/20/08<4<3 MEAN BKGB BOTTOM FEEDER 06/17/08 10/20/08 MEAN<2<4 C-9 TABLE C-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/-'2 SIGMA STC COLLECTION PERIOD BKGB BOTTOM FEEDER 06/17/08 10/20/08 MEAN BKGP PREDATOR 06/17/08 10/20/08 MEAN INDB BOTTOM FEEDER 06/03/08 10/07/08 MEAN INDP PREDATOR 06/16/08 10/07/08 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 0 3100 +/- 638 < 34 2430 +/- 816 < 62 2765 +/- 948 -3190 +/- 560 < 39 2430 +/- 692 < 49 2810 +/- 1075 -3360 +/- 687 < 36 2160 +/- 797 < 41 2760 +/- 1697 -3380 +/- 603 < 37 3390 +/- 660 < 46< 45< 57< 88< 113< 37< 57< 85< 76< 32< 45< 42< 54<88< 101< 36< 48< 80< 131< 37< 43< 42< 47< 33< 52< 49< 54< 117< 119< 29< 60< 94< 80< 29< 40< 40< 57< 41< 64< 96< 130< 42< 36< 69< 97< 32< 38< 35< 51 MEAN 3385 +/- 14 TABLE C-VI.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA STC COLLECTION PERIOD A1-3 06/18/08 11/05/08 MEAN J2-1 06/18/08 11/05/08 MEAN K1-3 06/18/08 11/05/08 MEAN EDCB 11/05/08 MEAN K-40 9020 +/- 1300 9300 +/- 973 9160 +/- 396 12100 +/- 1390 13900 +/- 1410 13000 +/- 2546 8080 +/- 1270 8140 +/- 982 8110 +/- 85 15700 +/- 1240 15700 +/- 0 Mn-54< 75< 57< 67< 62<61< 55< 56 Co-58 Co-60< 77< 69< 75< 51< 60 < 60< 65 < 47< 71 < 66< 63 < 49 Cs-134< 79< 47< 54< 53* 58* 51< 49 Cs-137< 96< 60 86 +/- 54< 71 86 +/- 0 113 +/- 52< 56 113 +/- 0 194 +/- 74 194 +/- 0 U< 73< 55* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-11 TABLE C-VII.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I GROUP 11 I GROUP II COLLECTION PERIOD El -2 Fl -3 A3-1 G2-1 1-3-1 M2-1 Q15-1 I 01/01/08 01/09/08 01/16/08 01/23/08 01/30/08 02/06/08 02/13/08 02/20/08 02/27/08 03/05/08 03/12/08 03/19/08 03/26/08 04/02/08 04/09/08 04/16/08 04/23/08 04/30/08 05/07/08 05/13/08 05/21/08 05/28/08 06/04/08 06/11/08 06/18/08 06/25/08 07/02/08 07/09/08 07/16/08 07/23/08 07/30/08 08/06/08 08/13/08 08/20/08 08/27/08 09/04/08 09/10/08 09/17/08 09/24/08 10/01/08 10/08/08 10/15/08 10/22/08 10/29/08 11/05/08 11/12/08 11/19/08 11/25/08 12/03/08 12/10/08 12/17/08 12/24/08 U 1/U9/08 01/16/08 01/23/08 01/30/08 02/06/08 02/13/08 02/20/08 02/27/08 03/05/08 03/12/08 03/19/08 03/26/08 04/02/08 04/09/08 04/16/08 04/23/08 04/30/08 05/07/08 05/13/08 05/2 1/08 05/28/08 06/04/08 06/11/08 06/18/08 06/25/08 07/02/08 07/09/08 07/16/08 07/23/08 07/30/08 08/06/08 08/13/08 08/20/08 08/27/08 09/04/08 09/10/08 09/17/08 09/24/08 10/01/08 10/08/08 10/15/08 10/22/08 10/29/08 11/05/08 11/12/08 11/19/08 11/25/08 12/03/08 12/10/08 12/17/08 12/24/08 12/31/08 24f 18 18 33 19 18 22 16 12 18 16 15 13 9 8 23 15 18 14 11 8 9 15 19 10 16 17 19 30 21 21 15 24 22 23 20 15 23 13 14 27 12 9 26 18 11 11 17 21 16 21 36 53+/-5+/-5+/-6+/-5+/-5+/-6+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-4+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-6+/-5+/-5+/-5+/-6+/-5+/-5+/-6+/-5+/-6+/-5+/-5+/-6+/-5+/-5+/-6+/-5+/-5+/-6+/-4+/-5+/-5+/-5+/-6 26+/- 5 20 +/- 5 20 +/- 5 33 +/- 6 20 +/- 5 19 +/- 5 21 +/- 6 17 +/- 5 19 +/- 5 18 +/- 5 20 +/- 6 14 +/- 5 17 +/-5 9+/-5 11 +/-5 25 +/-6 13 +/-5 17 +/-5 14 +/-5 14 +/-5<7 14 5 13 +/-5 17 +/-5 14 +/-5 16 +/-5 18 +/-5 12 +/-5 28 +/-6 19 +/-5 24 +/-5 15 +/-5 20 +/- 5 17 +/- 5 19 +/- 5 24 +/- 6 11 +/-5 21 +/-5 10 +/-5 15 +/-5 26 +/-6 12 +/-5<7 24 +/-5 16 +/-5 11 +/-5 13 +/-6 17 +/- 4 21 +/- 5 14 +/- 5 20 +/- 5 35 +/- 6 25 +/- 5 14 +/- 5 23 +/- 5 31 +/- 6 28 +/- 6 21 +/- 6 21 +/- 6 16 +/- 5 14 +/-5 15 +/-5 16 +/-5 15 +/-5 15 +/-5 10 +/-5 9+/-5 18 5 12 +/-5 20 +/-5 13 +/- 6 12 +/- 5< 7 16 +/- 5 16 +/- 5 18 +/- 5 10 +/- 5 16 +/- 5 14+/- 5 18 +/- 5 29 +/- 6 24 +/- 6 (1)12 +/- 5 14 +/- 5 20 +/- 5 23 +/- 5 23 +/- 6 9+/-5 19 +/-5 17 +/-5 19 +/-5 29 +/-6 18 +/-6 7+/-5 25 +/-5 14 +/-5 10 +/-5 12 +/-6 16 +/-5 18 +/- 6 15 +/- 5 32 +/- 6 34 +/- 6 22 5 20 +/-5 22 +/-5 37 +/-6 24 +/-6 21 +/-6 21 +/-6 17 +/-5 18 +/-5 16 +/-5 15 5 16 +/-5 15 +/-5 8+/-5 9+/-5 24 +/-6 15 5 23 +/-6 15 +/- 6 14 +/- 5 9+/-5 12 +/-5 18 +/-5 16 +/-5 17 +/-5 14 +/-5 20 +/- 5 17 +/- 5 26 +/- 6 17 +/-5 20 +/-5 14 5 18 +/-5 18 +/-5 16 +/-5 23 +/- 6 12 +/- 5 27 +/-6 14 +/-5 17 +/-5 30 +/-6 17 +/-6 9+/-5 23 +/-5 13 +/-5 12 +/-5 12 +/- 6 20 +/- 5 15 +/- 5 20 +/- 5 20 +/- 5 30 + 6 26+/- 5 13 +/- 5 23 +/- 5.29 +/- 6 20 +/- 5 22 +/- 5 20 +/- 5 14 +/- 5 17 +/-5 14 +/-5 15 +/-5 10 5 13 +/-5 10 +/-5 8+/-5 23 +/-5 21 +/-6 20 +/-5 11 +/-5 11 +/-4 7+/-5 7+/-4 12 5 16 +/-5 9+/-5 14 5 19 5 17 +/-5 35 +/-6 24 +/-6 21 +/-5 12 +/-5 13 +/-5 17 +/-5 20 +/-5 19 +/-6 10 +/- 5 16 +/- 5 16 +/- 5 15 +/- 5 25 +/- 6 13 +/- 5 11 +/-5 28 +/-6 17 +/-5 12 +/-5 11 +/-6 21 +/-5 18 +/- 5 19 +/- 5 24 +/- 6 39 +/- 6 17 23 27 22 17 20 15 11 23 17 16 16 8<9 23 17 22 11 13 11 13 13 21 14 10 16 14 26 21 20 9 18 16 21 17 11 22 14 13 28 18 8 25 17 10 10 18 14 16 22 28+/-.5+/-5+/-6+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-5+/-4+/-5+/-5+/-5+/-5+/-4+/-5+/-5+/-5+/-5+/-5+/-4+/-5+/-5+/-6+/-5+/-5+/-5+/-5+/-5+/-5+/-6+/-5+/-6+/-5+/-5+/-6+/-6+/-5+/-5+/-5+/-6+/-5+/-5+/-5+/-6+/-6 252 +/- 5 16 +/- 5 23 +/- 5 30 +/- 6 25 +/- 6 15 +/- 5 22 +/-6 14 +/-5 11 +/-5 16 +/-5 14 +/-5 16 +/-5 15 +/-5 11 +/-5<7 26 +/-6 15 +/-5 21 +/-5 15 +/-6 11 +/-4<7 13 +/-5 18 +/-5 18 +/-5 11 +/-5 13 +/-5 20 +/-5 19 +/-5 30 +/-6 22 +/-5 23 +/- 6 12 +/- 5 20 +/- 5 20 +/- 5 22 +/- 5 23 +/- 6 9+/-5 24 +/-6 14 +/-5 16 +/-5 29 +/-6 16 +/-6 8+/-5 26 +/-6 13 +/-5 9+/-5 10 +/-6 21 +/-5 19 +/-5 15 +/-5 23 +/-6 37 +/-6 MEAN 18 +/- 12 18 +/- 11 18 +/- 13 18 +/- 11 17 +/- 13 17 +/- 11 18 +/- 13*THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-12 TABLE C-VII.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I- CLOSEST TO THE SITE BOUNDARY GROUP II -INTERMEDIATE OFFSITE COLLECTION MIN MAX MEAN +PERIOD 2SD GROUP III -CONTROL LOCATIONS COLLECTION MIN MAX MEAN +PERIOD 2SD COLLECTION K PERIOD 01/01/08 -01/30/08 01/30/08 -02/27/08 02/27/08 -04/02/08 04/02/08 -04/30/08 04/30/08 -05/28/08 < 7 05/28/08 -07/02/08 07/02/08 -07/30/08 07/30/08 -09/04/08 09/04/08 -10/01/08 10/01/08 -10/29/08 < 7 10/29/08 -12/03/08 12/03/08 -12/31/08'IlN MAX 18 33 16 22 12 20 8 25 18 9 19 12 30 15 24 10 24 27 11 26 14 36 MEAN +/-2SD 24 +/- 12 19 +/- 4 16 +/- 5 14 +/- 13 14 +/- 7 14 +/- 6 21 +/- 11 20 +/- 7 17 +/- 11 16 +/- 14 17 +/- 11 23 +/- 17 01/01/08 01/30/08 02/27/08 04/02/08 04/30/08 05/28/08 07/02/08 07/30/08 09/04/08 10/01/08 10/29/08 12/03/08 01/30/08 02/27/08 04/02/08 04/30/08 05/28/08 07/02/08 07/30/08 09/04/08 10/01/08 10/29/08 12/03/08 12/31/08 13 14 10<9<7 7 14 9 9 7 10 14 37 28 23 24 23 21 35 23 27 30 28 39 23 +/- 12 20 +/- 7 15 +/- 5 14 +/- 12 14 +/- 10 14 +/- 7 21 +/- 12 17 +/- 7 17 +/- 10 17 +/- 15 16 +/- 11 23 +/- 15 01/01/08 01/30/08 02/27/08 04/02/08 04/30/08 05/28/08 07/02/08 07/30/08 09/04/08 10/01/08 10/29/08 12/03/08 01/30/08 02/27/08 04/02/08 04/30/08 05/28/08 07/02/08 07/30/08 09/04/08 10/01/08 10/29/08 12/03/08 12/31/08 16 14 11<7<7 11 19 12 9 8 9 15 30 25 16 26 21 18 30 23 24 29 26 37 23 +/- 12 19 +/- 11 14 +/- 4 17 +/- 15 16 +/- 9 15 +/- 7 23 +/- 10 20 +/- 9 17 +/- 14 17 +/- 17 16 +/- 15 23 +/- 19 01/01/08 -12/31/08 < 7 36 18 + 12 01/01/08 -12/31/08 < 7 39 18 +/- 12 01/01/08 -12/31/08 < 7 37 18 +/- 13* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES TABLE C-VII.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 A3-1 01/U1/U8 04/02/08 07/02/08 10/01/08 MEAN E1-2 01/01/08 04/02/08 07/02/08 10/01/08 MEAN F1-3 01/01/08 04/02/08 07/02/08 10/01/08 MEAN G2-1 01/01/08 04/02/08 07/02/08 10/01/08 MEAN H3-1 01/01/08 04/02/08 07/02/08 10/01/08 MEAN M2-1 01/01/08 04/02/08 07/02/08 10/01/08 MEAN Q15-1 01/01/08 04/02/08 07/02/08 10/01/08 MEAN U4/U2/U0 07/02/08 10/01/08 12/31/08 04/02/08 07/02/08 10/01/08 12/31/08 04/02/08 07/02/08 10/01/08 12/31/08 04/02/08 07/02/08 10/01/08 12/31/08 04/02/08 07/02/08 10/01/08 12/31/08 04/02/08 07/02/08 10/01/08 12/31/08 04/02/08 07/02/08 10/01/08 12/31/08 7u +/- 31 81 +/- 22 80 +/- 34 61 +/- 28 73 +/- 19 72 +78 +/-89 +/-68 +/-30 35 33 23 77 +/- 18 76 +/-98 +/-95 +/-44 +/-35 24 33 22 78 +/- 50 56 +/-68 +/-93 +/-72 +/-25 25 45 28< 3<2<3<3<3<4<3<3<4<2<3<3<2<4<2<4<4<3<3<3<3<3<2<3<3<3<3<3< 3<4<3<3<3<4<4<4<5<4<4<2<2<4<5<4<4<4<4<4<3<5<3<3<3<4<5<3<2<2<3<1<3<4<4<2<3<3<4<3<2<2<2<4<2<3<3<4<3<4<2<3<3<3<3<3< 3<3<3<3<2<4<3<4<3<2<3<2<3<3<2<3<3<3<4<3<2<4<2<3<3<3<3<3 3 2 2 3 3 3 3 4 3 2 3 2 2 2 3 3 2 3 3 2 2 3 3 3 72 +/- 31 60 100 107 62+/-+/-+/-+/-25 27 31 21 82 +/- 49 65 +/- 19 125 +/- 37 110 +/- 45 43 +/- 24 86 +/- 76 50 +/- 27 92 +/- 27 76 +/- 38 97 +/- 28 79 +/- 42 2 2 3 3 C-14 TABLE C-VIII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I GROUP 11 I GROUP III COLLECTION PERIOD El -2 F11-3 A3-11 G2-1 H3-1 M2-11 Q15-1 01/09/08 01/16/08 01/23/08 01/30/08 02/06/08 02/13/08 02/20/08 02/27/08 03/05/08 03/12/08 03/19/08 03/26/08 04/02/08 04/09/08 04/16/08 04/23/08 04/30/08 05/07/08 05/13/08 05/21/08 05/28/08 ,06/04/08 06/11/08 06/18/08 06/25/08 07/02/08 07/09/08 07/16/08 07/23/08 07/30/08 08/06/08 08/13/08 08/20/08 08/27/08 09/04/08 09/10/08 09/17/08 09/24/08 10/01/08 10/08/08 10/15/08 10/22/08 10/29/08 11/05/08 11/12/08 11/19/08 11/25/08 12/03/08 12/10/08 12/17/08 12/24/08-01/16/08-01/23/08-01/30/08-02/06/08-02/13/08-02/20/08-02/27/08-03/05/08-03/12/08-03/19/08-03/26/08-04/02/08-04/09/08-04/16/08-04/23/08-04/30/08-05/07/08-05/13/08-05/21/08-05/28/08-06/04/08-06/11/08-06/18/08-06/25/08-07/02/08-07/09/08-07/16/08-07/23/08-07/30/08-08/06/08-08/13/08-08/20/08-08/27/08-09/04/08-09/10/08-09/17/08-09/24/08-10/01/08-10/08/08-10/15/08-10/22/08-10/29/08-11/05/08-11/12/08-11/19/08-11/25/08-12/03/08-12/10/08-12/17/08-12/24/08-12/31/08*26*27*24*38* 47*<43< 41*38*30*52* 39* 39* 54* 39* 55* 59* 44* 55*32*61*60*60< 48< 45*67< 42* 53*20*46*52*31* 33*31* 49*69* 37*46* 34*56* 35* 45*56* 47*66*52*69*56*60*60*64* 49*27*27*24*38*48* 43*41*38*30*52* 39< 40* 54* 39* 55*60< 44* 55* 33*62*60*61< 49* 45*67< 40*51*19< 44*51*42*32*30* 47*67*36* 45* 33* 54* 34* 44* 54*46*64<51.<67* 54*58*58*63* 47*26*29*24< 41* 45*52*42* 44*30*46< 41*29< 45*36< 49*65*62*50* 54*64*66*38* 39< 43*63*50< 42*17< 45* 49*42* 57* 43*60* 33*58*32* 57< 42< 49* 59* 35*56< 47*67*51*70*66*67*58*27*28*24* 39< 48* 43*42* 39*30* 54* 39< 40* 55*51* 55*61*36* 55* 33< 63*61*61* 49< 46*68< 42* 53*20< 45 (1 <52*31* 33*31*48*68* 37< 46* 33* 55* 35*25*56< 47*66*52*69* 55*60* 59*64< 48*26*16*24*38< 47< 42< 40*38*29* 53*29*40* 53* 39* 53* 59< 43* 53*32*61* 59*60*48* 45*66-<41*52*20< 45*52*31* 33*31*48*69*38*46* 34* 55* 35< 45*56< 47*67*52*69* 55*61* 59*64*48*25*27*23*38* 43* 49*40*42*28* 44* 39* 35* 43* 44*48*62*58*50*50*61*65* 35* 37< 41*60*51< 42*17* 45* 55*48*42*58* 44*61* 33*58*32* 57< 43*50* 57*36* 57*46*63< 46* 59*66*67*58*26*28*23*40* 35*51*41* 44*28*46*40*36* 44* 35*48*65*60*51*52*63*66* 37* 39*42*62*51*42*17* 45* 55*48*41*58* 44*61* 33*58*32* 57* 43*50* 57*36* 57< 46*63< 46* 60* 67* 67* 58 MEAN--(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-i15 TABLE C-IX.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA CONTROL FARM I INDICATOR FARM COLLECTION PERIOD 01/09/08 02/06/08 03/05/08 03/19/08 04/02/08 04/16/08 04/30/08 05/14/08 05/28/08 06/11/08 06/25/08 07/09/08 07/23/08 08/06/08 08/20/08 09/03/08 09/17/08 10/01/08 10/15/08 10/29/08 11/12/08 11/25/08 12/10/08 K15-3 D2-1 E2-2 F4-1 G2-1< 1.0< 0.7< 0.6< 0.6< 0.7< 0.6* 0.5< 0.7< 0.4< 0.8< 0.6< 0.8< 0.8< 0.5< 0.8* 0.9* 0.5* 0.8* 0.8* 0.7* 0.9< 0.9< 0.8* 0.6< 0.5* 0.8* 0.4* 0.6< 0.7< 0.5< 0.7< 0.6< 0.7< 0.7< 0.7< 0.6< 0.6< 0.8< 0.7< 0.5< 0.8* 0.8< 0.7< 0.7< 0.7< 0.7< .7< 0.7< 0.6< 0.5< 0.8< 0.9< 0.6< 0.9< 0.4< 0.7< 0.7< 0.8< 0.7* 0.7* 0.8* 0.7< 0.6* 0.8* 0.8* 0.7* 0.9< 0.7< 0.7< 0.5< 0.5< 0.6< 0.6* 0.5< 0.6< 0.6< 0.6< 0.6< 0.7< 0.8< 0.6< 0.6* 0.6< 0.7< 0.8 Z 0.5< 0.7< 0.8< 0.7* 0.7< 0.8< 0.6* 0.8< 0.7* 0.6* 0.6< 0.7< 0.8< 0.6< 0.7< 0.4< 0.6< 0.8< 0.9* 0.7* 0.6< 0.8< 0.8< 0.6< 0.9< 0.9< 0.8< 0.8< 0.8< 0.8 MEAN C-16 TABLE C-IX.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA CONTROL FARM K15-3 INDICATOR FARMS COLLECTION PERIOD D2-1.E2-2 SR-89 F4-1 G2-1 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-90 SR-89 SR-90 01/09/08 04/02/08 07/09/08 10/01/08-03/19/08-06/25/08-09/17/08-12/10/08< 3.6< 2.9< 3.6< 4.4 0.6 +/- 0.2< 0.5 1.4 +/- 0.5< 0.6< 3.9< 3.9< 4.6< 4.3 0.8 0.7 0.9 0.7+/- 0.3+/- 0.4+/- 0.5+/- 0.5< 3.9< 3.1< 3.6< 3.5 1.1 +/- 0.3 0.6 +/- 0.4 1.0 +/- 0.5< 0.7< 3.7 < 0.5 < 3.2< 1.7 < 0.5 < 3.3< 3.5 1.1 +/- 0.4 < 3.5< 4.8 1.0 +/- 0.5 < 3.7< 0.7< 0.7< 0.6< 0.6 MEAN 1.0 +/- 1.1 0.8 +/- 0.2 0.9 +/- 0.6 1.0 +/- 0.2* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD K-40 Cs- 134 Cs-137 Ba-140 La- 140 LD2-1 U-I IU0IU 02/06/08 03/05/08 03/19/08 04/02/08 04/16/08 04/30/08 05/14/08 05/28/08 06/11/08 06/25/08 07/09/08 07/23/08 08/06/08 08/20/08 09/03/08 09/17/08 10/01/08 10/15/08 10/29/08 11/12/08 11/25/08 12/10/08 MEAN E2-2 01/09/08 02/06/08 03/05/08 03/19/08 04/02/08 04/16/08 04/30/08 05/14/08 05/28/08 06/11/08 06/25/08 07/09/08 07/23/08 08/06/08 08/20/08 09/03/08 09/17/08 10/01/08 10/15/08 10/29/08 11/12/08 11/25/08 12/10/08 MEAN]I UU 1320 1160 1310 1210 1300 1270 1310 1190 1310 1160 1330 1220 1300 1360 1340 1330 1300 1320 1220 1270 1340 1150 158 118 153 157 155 146 116 144 146 141 145 146 114 146 137 119 58 126 56 54 28 113 1270 +/- 132< 4<6<4<6<5<6<6<4<6<5<4<7<5<3<5<5<4<2<6<1<1<0<4<6<6<6<6<5<6<5<6<5<5<8<5<7<3<6<3<7<2<3<1<1<1<5< 4<7<5<6<6<8<7<5<8<6<5<7<7<4<6<7<5<2<6<1<1<0<4<6<8<7<7<7<7<6<7<6<6<9<5<8<3<6<3<7<2<4<1<1<1<6< 30< 18< 34< 26< 32< 28< 25< 45< 34< 29< 48< 39< 49< 33< 53< 23< 40< 60< 44< 56< 16< 22< 25< 31< 29< 31< 28< 30< 27< 45< 34< 26< 47< 33< 43< 47< 41< 29< 33< 45< 32< 39< 49< 28< 27< b<7<5< 11<6< 11<8<7< 12<8< 10<14<12< 13< 10< 15<6<12< 13< 14< 14<4<6 1220 1350 1380 1300 1130 1260 1160 1210 1280 1190 1360 1320 1130 1230 1330 1360 1290 1380 1340 1380 1230 1350 1370 133 166 142 139 147 146 127 153 121 137 173 151 174 89 140 136 152 60 91 52 42 34 134< 10<7<8< 10<9< 12<8< 14< 11<7< 13< 13< 13< 12< 12< 10<9< 15< 11< 13< 14<7<7 1285 +/- 165 C-18 TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD F4-1 01/09/08 1460 +/- 126 < 5 < 6 < 26 < 8 02/06/08 1340 +/- 165 < 6 < 7 < 28 < 12 03/05/08 1240 +/- 154 <6 < 7 < 28 < 8 03/19/08 1270 +/- 119 <4 < 5 <24 < 7 04/02/08 1310 +/- 125 < 4 < 4 < 28 < 6 04/16/08 1290 +/- 170 < 5 < 7 < 28 < 12 04/30/08 1230 +/- 129 < 5 < 5 < 23 < 9 05/14/08 1220 +/- 112 < 5 < 5 < 34 < 11 05/28/08 1150 +/- 129 < 5 < 6 < 32 < 10 06/11/08 1300 +/- 127 < 5 < 6 < 28 < 9 06/25/08 1340 +/- 188 < 6 < 8 < 44 < 11 07/09/08 1360 +/- 148 < 5 < 7 < 40 < 10 07/23/08 1330 +/- 134 < 5 < 6 < 38 < 12 08/06/08 1340 +/- 80 < 3 < 3 <44 < 13 08/20/08 1300 +/- 139 < 5 < 6 < 38 < 15 09/03/08 1370 +/- 111 < 2 < 3 < 29 < 10 09/17/08 1270 +/- 130 < 4 < 5 < 20 < 7 10/01/08 1350 +/- 52 < 2 < 2 < 49 < 14 10/15/08 1360 +/- 107 < 4 < 4 < 45 < 12 10/29/08 1390 +/- 48 < 1 < 1 < 38 < 12 11/12/08 1350 +/- 31 < 1 < 1 < 49 < 14 11/25/08 1360 +/- 54 < 1 < 1 < 42 < 14 12/10/08 1570 +/- 224 < 8 < 10 <43 < 7 MEAN 1326 +/- 169 ----G2-1 01/09/08 1080 +/- 114 < 5 < 6 < 23 < 7 02/06/08 1140 +/- 138 < 7 < 7 < 32 < 9 03/05/08 1120 +/- 113 < 5 < 6 < 27 < 9 03/19/08 1380 +/- 158 <5 <6 <36 <8 04/02/08 1220 +/- 154 <7 <8 <30 <8 04/16/08 989 +/- 133 < 6 < 7 < 30 < 10 04/30/08 1360 +/- 125 < 4 < 5 < 22 < 7 05/14/08 1370 +/- 144 < 4 < 6 < 39 < 10 05/28/08 1030 +/- 116 < 5 < 5 < 39 < 10 06/11/08 1290 +/- 155 < 6 < 7 < 33 < 8 06/25/08 1110 +/- 150 < 6 < 8 <45 < 13 07/09/08 1310 +/- 159 < 5 < 6 < 38 < 9 07/23/08 1240 +/- 118 < 5 < 6 < 39 < 13 08/06/08 627 +/- 86 < 3 < 3 < 36 < 14 08/20/08 850 +/- 125 < 6 < 7 < 50 < 13 09/03/08 1370 +/- 129 < 2 < 3 < 27 < 7 09/17/08 1470 +/- 151 < 8 < 8 < 47 < 12 10/01/08 978 +/- 48 < 2 < 2 < 46 < 14 10/15/08 963 +/- 75 <3 <3 <34 < 9 10/29/08 1030 +/- 49 < 1 < 1 < 36 < 10 11/12/08 1040 +/- 45 < 1 < 1 < 55 < 15 11/25/08 1190 +/ < 0 < 0 < 16 < 4 12/10/08 1120 +/- 106 < 4 < 5 < 22 < 7 MEAN 1142 +/- 395 ----C-19 TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD K-40 Cs- 134 Cs-137 Ba-140 La-140 K15-3 01/09/08 02/06/08 03/05/08 03/19/08 04/02/08 04/16/08 04/30/08 05/14/08 05/28/08 06/11/08 06/25/08 07/09/08 07/23/08 08/06/08 08/20/08 09/03/08 09/17/08 10/01/08 10/15/08 10/29/08 11/12/08 11/25/08 12/10/08 MEAN 1400 1560 1380 1300 1280 1330 1320 1400 1510 1270 1340 1260 1370 1330 1330 1260 1280 1280 1390 1370 1300 1320 1210+/- 148+/- 180+ 140+ 128+ 163+ 154+ 143+ 132+ 155+ 157+ 178+ 166+ 155+/- 91+/- 139+/- 136+/- 161+/- 52+/- 107+/- 53+/- 28+/- 42+/- 131<6<7<6<5<6<6<5<5<7<6<6<6<6<3<6<3<6<2<4<1<1<1<5<7<7<7<6<7<7<5<5<8<7<7<7<6<3<6<3<8<2<5<1<1<1<6< 27< 31< 29< 26< 33< 27< 28< 39< 46< 31< 42< 46< 44< 51< 40< 37< 33< 50< 42< 43< 52< 46< 26<8< 11<8<9< 11<8<6< 12< 12< 11<9< 13< 14< 15<12<7< 11< 14< 14< 12< 14< 11<7 1339 +/- 160 C-20 TABLE C-X.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS iN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA n t-j STC COLLECTION PERIOD B10-2 07/18/08 07/18/08 07/18/08 07/30/08 08/12/08 08/12/08 08/12/08 08/22/08 08/22/08 08/22/08 09/24/08 09/24/08 09/24/08 MEAN SR-90 Be-7 K-40 1-131 Cs-134 Eggplant Leaves Squash Leaves Zucchini Leaves Cabbage Red Beets Sweet Corn Tomatoes Cabbage Eggplant Leaves Zucchini Leaves Broccoli Leaves Cabbage Turnip Greens 18 +/- 1 29 +/- 2 32 +/- 2 6+/-2 11 +/-3 46 +/-8 67 +2 30 +2 11 +1 24 +/- 2 27 +/- 36 759t +/- 76 823 +/- 70 314 +/- 52< 63< 50< 35< 45< 57 1100 +/- 89 366 +/- 58< 40< 30< 39 672 +/- 660 7u0u 3840 3060 2730 3590 1600 2220 2990 5330.3280 2040 1950 4150 3375+/- LU3+/- 163+/- 140+/- 146+/- 144+/- 84+/- 102+/- 127+/- 184+/- 130+/- 107+/- 90+/- 152+/- 3025< zU< 17< 18< 53< 29< 22< 30< 32< 34< 30< 48< 36< 42<6<5<6<5<3<4<5<6<5<3<2<3<7<7<6<6<5<3<4<6<7<6< 10<3<3 Cs-137* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES TABLE C-X.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD SR-90 Be-7 K-40 1-131 Cs-134 Cs- 137 E1-2 07/30/08 08/12/08 08/12/08 08/12/08 MEAN H1-2 07/18/08 07/18/08 07/18/08 08/22/08 08/22/08 08/22/08 09/24/08 09/24/08 09/24/08 MEAN CabUdge Red Beets Sweet Corn Tomatoes 11 +/-I: Oz +/- 0I< 56< 46< 50 Eggplant Leaves Squash Leaves Zucchini Leaves Cabbage Eggplant Leaves Zucchini Leaves Cabbage Eggplant Leaves Turnip Greens 11 +/-18 +/-36 +/-42 +/-36 +/-18 +/-27 +/-13 +/-45 +/-36 +/-30 +/-0 2 2 2 2 1 10 1 2 3 23 85 +/- 0 362 +/- 37 757 +/- 63 730 +/- 63 718 +/- 96< 85 797 +/- 105< 35 1860 +/- 134 194 +/- 47 774 +/- 1062 3780 4880 2120 2500 3320 6080 2400 5260 5700 4630 2730 1520 2530 3220 3786+/- 142+/- 165+/- 112+/- 114+/- 2519+/- 131+/- 133+/- 159+/- 232+/- 201+/- 199+/- 101+/- 178+/- 115+/- 3308< 52< 34< 27< 31< 11< 17< 16< 49< 40< 47< 51< 55< 36<5<5<4<5< 6< 6< 5< 5<4<6<5< 10<8<9<3<4<2< 4< 6< 6< 10< 9< 9< 3< 4< 3* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES TABLE C-Xl.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGENS/STD.

MONTH STATION MEAN JAN -MAR APR -JUN JUL -SEP OCT -DEC CODE +/- 2 S.D.A1-4 4.1 +/- 1.0 3.6 +/- 0.2 4.6 +/- 0.4 3.7 +/- 0.2 4.4 +/- 0.7 A3-1 4.6 +/- 1.2 4.1 +/- 0.4 5.2 +/- 0.5 4.1 +/- 0.2 5.0 +/- 0.2 A5-1 5.0 +/- 1.1 4.6 +/- 0.3 5.7 +/- 0.4 4.5 +/- 0.7 5.3 +/- 0.3 A9-3 4.2 +/- 0.8 3.7 +/- 0.3 4.7 +/- 0.4 4.0 +/- 0.4 4.2 +/- 0.4 B1-1 4.2 +/- 1.0 3.8 +/- 0.4 4.9 +/- 0.6 3.9 +/- 0.4 4.3 +/- 0.4 B1-2 4.4 +/- 0.8 4.0 +/- 0.4 4.9 +/- 0.6 4.4 +/- 0.5 4.2 +/- 0.5 B2-1 4.4 +/- 0.6 4.0 +/- 0.8 4.6 +/- 0.4 4.6 +/- 0.5 4.5 +/- 0.3 B5-1 5.1 +/- 1.4 4.1 +/- 0.3 5.5 +/- 0.3 5.4 +/- 0.7 5.5 +/- 0.6 B10-1 4.8 +/- 1.1 4.0 +/- 0.3 5.2 +/- 0.8 4.9 +/- 0.3 5.0 +/- 0.6 Cl-i 4.9 +/- 1.1 4.1 +/- 0.5 5.3 +/- 0.3 5.2 +/- 1.2 5.0 +/- 0.6 C1-2 4.3 +/- 0.7 3.8 +/- 0.4 4.7 +/- 0.6 4.3 +/- 0.8 4.4 +/- 0.2 C2-1 4.9 +/- 0.8 4.3 +/- 0.1 5.1 +/- 0.5 4.9 +/- 0.5 5.2 +/- 0.5 C5-1 5.5 +/- 0.7 5.2 +/- 0.4 6.0 +/- 0.3 5.3 +/- 0.4 5.4 +/- 0.3 C8-1 5.6 +/- 0.7 5.1 +/- 0.2 5.7 +/- 0.5 5.9 +/- 1.2 5.5 +/- 0.4 D1-i 4.3 +/- 0.6 3.9 +/- 0.4 4.3 +/- 0.2 4.2 +/- 1.0 4.6 +/- 0.4 D1-2 4.9 +/- 0.9 4.6 +/- 0.7 5.5 +/- 0.2 4.9 +/- 0.3 4.5 +/- 0.2 D2-2 6.1 +/- 0.6 5.6 +/- 0.6 6.3 +/- 0.5 6.1 +/- 0.6 6.2 +/- 0.6 D6-1 6.0 +/- 0.9 5.5 +/- 0.3 6.6 +/- 0.8 5.9 +/- 0.3 5.8 +/- 0.8 D15-1 5.1 +/- 0.9 4.9 +/- 0.5 5.7 +/- 0.6 4.7 +/- 0.4 5.1 +/- 0.5 E1-2 4.4 +/- 1.0 4.2 +/- 0.5 5.1 +/- 0.4 4.0 +/- 0.3 4.4 +/- 0.8 E1-4 4.2 +/- 1.1 4.0 +/- 0.6 4.7 +/- 0.6 3.5 +/- 0.3 4.5 +/- 0.4 E2-3 5.5 +/- 0.9 5.4 +/- 0.6 6.1 +/- 0.7 5.0 +/- 0.4 5.3 +/- 1.0 E5-1 4.7 +/- 1.0 4.5 +/- 0.4 5.4 +/- 0.7 4.2 +/- 0.4 4.8 +/- 0.9 E7-1 5.1 +/- 0.6 4.9 +/- 0.3 5.4 +/- 0.4 4.7 +/- 0.8 5.2 +/- 0.8 Fl-1 4.6 +/- 0.8 4.5 +/- 0.5 5.1 +/- 0.2 4.2 +/- 0.7 4.7 +/- 0.6 F1-2 4.4 +/- 0.8 4.3 +/- 0.7 4.9 +/- 0.4 3.9 +/- 0.4 4.5 +/- 0.6 F1-4 4.1 +/- 0.9 3.8 +/- 0.5 4.6 +/- 0.5 3.7 +/- 0.5 4.4 +/- 0.3 F10-1 6.2 +/- 0.7 6.3 +/- 0.4 6.5 +/- 0.4 5.7 +/- 0.5 6.4 +/- 0.4 F2-1 5.4 +/- 0.7 5.2 +/- 0.5 5.8 +/- 0.3 5.0 +/- 0.5 5.5 +/- 0.4 F5-1 5.6 +/- 0.3 5.7 +/- 0.7 5.8 +/- 0.5 5.4 +/- 0.7 5.6 +/- 0.3 F25-1 5.4 +/- 0.5 5.3 +/- 0.4 5.7 +/- 0.4 5.1 +/- 0.6 5.3 +/- 0.4 G1-2 5.0 +/- 0.4 4.9 +/- 0.7 5.2 +/- 0.3 4.7 +/- 0.6 5.1 +/- 0.2 G1-3 4.2 +/- 0.7 4.1 +/- 0.6 4.5 +/- 0.4 3.7 +/- 0.5 4.4 +/- 0.2 G1-5 4.4 +/- 0.9 4.3 +/- 0.5 4.8 +/- 0.5 3.8 +/- 0.3 4.7 +/- 0.3 G1-6 4.5 +/- 0.6 4.4 +/- 0.5 4.8 +/- 0.5 4.1 +/- 0.2 4.6 +/- 0.1 G2-4 6.1 +/- 0.4 6.1 +/- 0.7 6.4 +/- 0.4 5.9 +/- 0.9 6.0 +/- 0.5 G5-1 4.7 +/- 0.8 4.6 +/- 0.7 4.8 +/- 0.4 4.2 +/- 0.6 5.2 +/- 0.5 G10-1 6.9 +/- 0.8 6.7 +/- 0.8 7.4 +/- 0.4 6.5 +/- 0.6 7.1 +/- 0.8 G15-1 5.8 +/- 1.0 5.7 +/- 1.1 6.3 +/- 0.5 5.2 +/- 0.6 6.1 +/- 0.3 Hi-i 4.7 +/- 0.9 4.5 +/- 0.7 5.2 +/- 0.2 4.2 +/- 0.4 4.9 +/- 0.6 H3-1 4.0 +/- 0.5 3.8 +/- 0.7 4.3 +/- 0.3 3.7 +/- 0.5 4.0 +/- 0.4 H5-1 3.9 +/- 0.3 3.8 +/- 1.0 4.1 +/- 0.2 3.8 +/- 0.7 3.8 +/- 0.3 H8-1 8.0 +/- 1.3 7.6 +/- 1.1 8.1 +/- 0.9 9 +/- 0.8 7.4 +/- 0.3 H15-1 5.8 +/- 0.7 5.8 +/- 0.6 6.0 +/- 0.4 6.0 +/- 0.4 5.3 +/- 0.2 J1-1 4.6 +/- 0.2 4.5 +/- 0.7 4.7 +/- 0.3 4.6 +/- 0.3 4.5 +/- 0.4 C-23 TABLE C-XI.1.QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGENS/STD.

MONTH STATION CODE J1i-3 J3-1 J5-1 J7-1 J15-1 Ki -4 K2-1 K3-1 K5-1 K8-1 K15-1 Li-1 Li-2 L2-1 L5-1 L8-1 L15-1 Mi-i Ml-2 M2-1 M5-1 M9-1 Ni-i N1-3 N2-1 N5-1 N8-1 N15-2 P1-i P1-2 P2-1 P5-1 P8-1 Qi-i Q1-2 Q2-1 Q5-1 Q9-1 Q15-1 Ri-i R1i-2 R3-1 R5-1 R9-1 R15-1 MEAN+/-2 S.D.4.1 +/- 0.7 5.0 +/- 0.6 5.8 +/- 0.4 5.9 +/- 0.5 6.1 +/- 0.5 4.6 +/- 0.4 5.8 +/- 0.6 4.4 +/- 0.6 5.6 +/- 0.4 5.3 +/- 1.0 5.0 +/- 1.0 4.7 +/- 0.6 4.3 +/- 0.3 5.0 +/- 0.7 4.4 +/- 0.8 5.0 +/- 1.3 5.0 +/- 0.9 4.3 +/- 0.6 5.0 +/- 1.0 4.1 +/- 0.7 4.9 +/- 0.8 6.0 +/- 0.4 4.9 +/- 1.0 4.5 +/- 0.5 5.0 +/- 0.8 4.2 +/- 0.6 5.4 +/- 1.0 5.7 +/- 1.1 4.7 +/- 1.6 4.6 +/- 0.4 5.9 +/- 1.1 5.2 +/- 0.6 4.4 +/- 1.1 5.0 +/- 2.1 3.9 +/- 0.5 4.5 +/- 1.1 4.5 +/- 0.9 4.8 +/- 0.9 5.4 +/- 1.1 3.9 +/- 0.7 4.0 +/- 0.9 5.3 +/- 0.9 5.1 +/- 0.8 5.1 +/- 0.7 4.7 +/- 0.8 JAN -MAR APR -JUN JUL -SEP OCT -DEC 3.7 +/- 0.6 4.7 +/- 0.6 5.6 +/- 0.6 5.8 +/- 0.8 5.8 +/- 0.5 4.3 +/- 0.4 5.4 +/- 0.5 4.2 +/- 0.5 5.4 +/- 0.9 4.9 +/- 0.6 4.5 +/- 0.4 4.6 +/- 0.7 4.1 +/- 0.6 4.5 +/- 0.4 3.8 +/- 0.3 4.2 +/- 0.2 4.4 +/- 0.5 4.0 +/- 0.4 4.5 +/- 0.5 3.6 +/- 0.6 4.3 +/- 0.3 5.7 +/- 0.9 4.4 +/- 0.3 4.3 +/- 0.5 4.5 +/- 0.3 3.9 +/- 0.6 4.7 +/- 0.3 5.2 +/- 0.4 4.0 +/- 0.3 4.7 +/- 0.4 5.4 +/- 0.6 5.0 +/- 0.9 3.8 +/- 0.3 4.0 +/- 0.4 3.6 +/- 0.4 3.9 +/- 0.3 4.1 +/- 0.4 4.3 +/- 0.4 4.8 +/- 0.4 3.9 +/- 0.3 3.9 +/- 0.4 5.1 +/- 0.2 5.0 +/- 0.6 5.1 +/- 0.7 4.6 +/- 0.8 4.5 +/- 0.7 5.0 +/- 0.4 5.9 +/- 0.3 6.0 +/- 0.3 6.2 +/- 0.6 4.7 +/- 0.3 6.0 +/- 0.6 4.7 +/- 0.2 5.8 +/- 0.5 5.7 +/- 0.5 5.3 +/- 0.5 5.1 +/- 0.3 4.4 +/- 0.3 5.2 +/- 0.5 4.6 +/- 0.3 5.5 +/- 0.4 5.0 +/- 0.3 4.5 +/- 0.3 4.9 +/- 0.2 4.1 +/- 0.2 4.9 +/- 0.4 6.0 +/- 0.5 5.0 +/- 1.0 4.6 +/- 0.6 5.4 +/- 0.8 4.3 +/- 0.5 5.5 +/- 0.5 5.7 +/- 0.5 4.6 +/- 0.7 4.8 +/- 0.4 5.8 +/- 0.3 5.1 +/- 0.2 4.8 +/- 0.4 5.0 +/- 0.4 3.9 +/- 0.4 4.7 +/- 0.4 5.0 +/- 0.8 4.8 +/- 0.5 5.6 +/- 0.7 4.3 +/- 0.4 4.5 +/- 0.3 5.7 +/- 0.5 5.6 +/- 0.5 5.5 +/- 0.3 5.2 +/- 0.5 4.0 +/- 0.9 5.4 +/- 0.3.6.1 +/- 0.4 6.2 +/- 0.3 6.3 +/- 0.6 4.6 +/- 0.2 5.9 +/- 0.5 4.7 +/- 0.7 5.8 +/- 0.2 5.8 +/- 1.1 5.5 +/- 0.4 4.6 +/- 0.5 4.4 +/- 0.7 5.2 +/- 1.0 4.7 +/- 0.7 5.5 +/- 0.2 5.4 +/- 0.6 4.6 +/- 0.3 5.5 +/- 0.4 4.4 +/- 0.2 5.3 +/- 0.7 6.2 +/- 0.5 5.4 +/- 0.4 4.7 +/- 0.5 5.1 +/- 1.0 4.6 +/- 0.2 5.9 +/- 0.3 6.4 +/- 0.4 5.6 +/- 0.6 4.6 +/- 1.3 6.7 +/- 1.0 5.6 +/- 0.4 4.8 +/- 1.8 6.1 +/- 1.4 4.2 +/- 0.4 5.2 +/- 0.5 4.8 + 0.5 5.4 +/- 0.5 6.0 + 0.5 3.5 +/- 0.5 3.6 +/- 0.6 4.8 +/- 0.5 4.7 +/- 0.2 4.9 +/- 0.3 4.3 +/- 0.7 4.0 +/- 0.3 4.9 +/- 0.4 5.7 +/- 0.3 5.6 +/- 0.2 5.9 +/- 0.6 4.7 +/- 0.6 (1)4.1 +/- 0.4 5.5 +/- 1.7 4.8 +/- 0.4 4.6 +/- 0.7 4.4 +/- 0.3 (1)4.9 +/- 0.3 4.4 + 0.4 4.8 +/- 0.3 5.3 +/- 0.3 4.2 +/- 0.3 (1)4.1 +/- 0.3 4.9 +/- 0.6 6.0 +/- 0.4 (1)4.2 +/- 0.3 4.8 +/- 0.3 4.1 +/- 0.3 5.3 +/- 0.4 5.4 +/- 0.4 (1)4.3 +/- 0.3 5.6 +/- 0.4 4.9 +/- 0.3 4.0 +/- 0.5 (1)3.9 +/- 0.7 4.2 +/- 0.3 4.2 +/- 0.3 4.6 +/- 0.6 5.1 +/- 0.7 4.0 +/- 0.5 (1)5.7 +/- 0.6 5.2 +/- 0.1 4.7 +/- 0.5 4.6 +/- 0.3 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-24 TABLE C-XI.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGENS/MONTH

+/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC SITE BOUNDARY+/- 2 S.D.4.1 +/- 0.7 4.7 +/- 0.6 4.1 +/- 0.8 4.4 +/- 0.5 INDICATOR CONTROL 4.7 +/- 1.5 5.3 +/- 1.4 5.1 +/- 1.7 5.0 +/- 1.4 5.2 +/-5.8 +/-5.6 +/-5.4 +/-1.4 1.3 1.4 1.4 TABLE C-XI.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/STD.

MONTH LOCATION SAMPLES PERIOD ANALYZED MINIMUM 76 3.5 SITE BOUNDARY INDICATOR CONTROL PERIOD MAXIMUM 5.2 8.9 7.4 PERIOD MEAN+/-2 S.D.PRE-OP MEAN+/- 2 S.D.233 3.6 4.3 +/- 0.8 5.0 +/- 1.6 5.5 +/- 1.4 4.8 +/- 1.5 5.2 +/- 1.5 5.8 +/--1.7 44 4.3 SITE BOUNDARY STATIONS -Al-4, B1-2, Cl-2, Dl-1, El-4, Fl-2, Fl-4, G1-3, G1-5, Gl-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, 62-1, B5-1, Cl-1, 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-l, Q2-1, Q5-1, Q9-1, Rl-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-25 Intentionally left blank FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2008 C3 Station J1-2 (Downstream of Discharge)-

l Station Q9-1 (Control)

K] E II U 1000001 0 00 .. ................................................ ........ .......- ........ ......... .....a_ 10000I','

, 0.-'Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month 0 Station K1-1 (TMINS Liquid Discharge)

_1"t-0.1000000 100000-10000-1000-100-10-Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month FIGURE C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2008 Indicator Samples ---- Control Samples 12000_Significant Events Major Atm. Nuclear Weapon Tests 11000 TMI- I Critical June 1974 June 1974 September 1974 TMI-2 Critical March 1978 September 1976 November 1976 10000 TMI-2 Accident March 1979 September 1977 March 1978 TMI-2 RB Purge June 1980 December 1978 October 1980 9000 Chernobyl April 1986 8000 S7000 8000 --------------------------------------------------

---

---

• ---~w 6 000 C., 0 0-1 4 0 0 0 .. ..----- ------------------------------------So0 L ý! -------.- -. ..- -. .- -. ----------- -----01 0 ... ...I. .. .. i i i i 2i i i i i i ii i i i i i i i i m M i ii i s i i e i i i i i i i i ii i i i i b i i't IO N- wI M 0 ; N M) I0 t O W -w M 0) 0 o o o o ) o -wo Mo 0 o o o o o o N o Co Co SCCCC0 0 0 0 rrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrr ON ON ON NO ON N N N Year FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2008 El Indicator Samples El Control Samples 10 9 8 76-J cn5 Q-a)0.y 4 -- -- --- -----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, 2008 (D (D 0)0.NOTE: The mean values are calculated using both the MDCs and ED the positive values.500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L 400 3 0 0 --- ------------------------2 0 0 --- ------------------------100-0-Indicator Samples 0 Control Samples Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month N Station K1-1 (TMINS Liquid Discharge)

U)0 1000000 100000-10000-1000-100-10-Jan 10-IE-Jul---

Jan ~~~~~Jul Au Se Oc No Dc---t--Feb Mar Apr May Jun Aug Sep Oct Nov Dec Month FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2008 Indicator Samples -,-- Control Samples 900 *Significant Event I Chemobyl April 19861 800 ------------------------------------------------------------------------

700 ------------------------------------------------------------------------

600 E..2 500 -400 -100 -- -- .---- -0 a) a a) a) ) a a) a) ) a a) a) ) a a) a) ) a a) a) 0) C) C. CD 0 0 0 C) CD a) a) a ) a ) a ) a ) a a) ) i) a) ) a) ) a) C ) ) C ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,4 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 -2008-Indicator-Control 0.4 0.35 Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chernobyl April 1986 December 1978 October 1980 0.3 +=3 a)0~0 0L 0.25.0.2-0.15.I 0.1 0.05 0---- ----------------------------------------------------------------------

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

---

JL.1..... .... ... ... .. ... .... *. .. ... ... .. .... ... .... ................... ... ... ...... .. .... ... ... ... ... .. ...,, , , , , , ... .. ... ... ... ..... ... ... ...0 00 C) 0 ý0 N M 'IT U) W N- W0 t- N- -N- N-- N- N- Nl- co co coC) CC ) 0) co M 0) M) COT) 0) 0M M0) 0) CD C) 0)0CD )0 C 0 0C0 C) 0 0) M)0 )0 )0 )0 )0 )0 )0 0) 0) 0) M) 0) 0Y) 0) 0) 0) 0) 0) 0) 0) C CD CD 0D CD C CD ) C C0----------------------------------------------------------------

N N 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, 2008 0.100---Indicator-Control 0.090+0.080-0.070 -o 0.060 C-)0.050 cn 0.040 0 0 0 1-4-1-U.U3U-------------------------

---

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

---

---

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

-- ---------

---

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

---

--- -----0.020-0.010-0.000.................................I .......................1 1 .1 ....rp N- r N N N N r- [I- [- r- t- N- 00 c0 c0 co c0 0o 00 Co Co cO co CC co oD CC00 0CD C: CD CD CD CD CD C Q C C C C Q C C Q C Q C C---r- o -Nj C --I Z) C -- 3 o -o o \J 0)o (C L -- u- ) o -) p- in -° C- co m N C' 1 U') U') CD f- w 0m C -( N C) m 4 U-) cc N- mO 0 C3 -(C Co C C C Co ,- ,- C-- C C C o C o C o C C0 C C -,- ,- C Month / Day of 2008 FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2008 Indicator Samples -.-- Control Samples 10-Significant Events Major Atm. Nuclear Weapon Tests TMI-2 Accident March 1979 December 1978 October 1980 TMI-2 RB Purge June 1980 Chernobyl April 1986 8-i 6 I,...U, 5")0 8*- ------------------------------------------------0) ~ ~ ~ ~ ~ ~ ~ 0 CD0 4 M ý O 0 [- W M C -ci C') It L 0 r 0 0 ) ý I 0 I- 0 1-- 0 0 ) 00 00 CC) 00 0) 0) 00 00 0) 0') 0z C) 0Y ) 0D 0) a) 0) C0 CD 0 CD 0 0 0) 0..........................................................

C) CN C) C) C:' CD. CD 04) 04 Year FIGURE C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 -2008--Indicator-Control 50 45+Significant Events Major Atm. Nuclear Weapon Tests TMI-I Critical June 1974 March 1972 June 1973 TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chernobyl April 1986 December 1978 October 1980 40-351-_-_C: 0 2 Ca U)E 30--25+-20+/-15+10+-5--0 A...............................................................................................................................................................

i iA 2 i i i i i i i i i i S i i iA i i i i i i 2 i i i i i 2 ii i i i i 2 i I i i i i i i i Ti i rii r r2 r2 r r TarA i ir i i i i i i 2 i i i a i i i i i i i i ill l l l l l l l l , , i, I M- M N N 0 M M 0 M 0) C 0 0 0 C C Year I Intentionally left blank 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 blar)k D-2 TABLE D-I.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/31/U7 -01/29/01/29/08 -02/26 02/26/08 -04/01 04/01/08 -04/29 04/29/08 -06/03 06/03/08 -07/01 07/01/08 -07/29 07/29/08 -09/03J 09/03/08 -09/30, 09/30/08 -10/28 10/28/08 -12/02 12/02/08 -12/30 Q9-1Q'08'08'08'08'08/08'08'08'08'08/08.< 1.1* 1.8 1.6 +/- 0.6 0.8 +/- 0.4 1.9 +/- 1.0 0.9 +/- 0.5* 1.0 1.0 +/-0.6 3.0 +/-1.1* 3.6* 1.9 2.0 +/-0.9 1.9 +/-2.1 MEAN TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12131107 -01/29/01/29/08 -02/26/02/26/08 -04/01/04/01/08 -04/29/04/29/08 -06/03/06/03/08 -07/01/07/01/08 -07/29/07/29/08 -09/03/09/03/08 -09/30/09/30/08 -10/28/10/28/08 -12/02/12/02/08 -12/30/Q9-1Q 08 08 08 08 08 08 08 08 08 08 08<016<155b* 177* 180* 158* 167* 171* 142* 152* 161* 160* 152* 132 MEAN TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD 12/31/07 -01/29/08 01/29/08 -02/26/08 02/26/08 -04/01/08 04/01/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 07/01/08 -07/29/08 07/29/08 -09/03/08 09/03/08 -09/30/08 09/30/08 -10/28/08 10/28/08 -12/02/08 12/02/08 -12/30/08 Q9-1Q* 0.1< 0.1< 0.2< 0.2< 0.4< 0.4* 0.3< 0.4< 0.4* 0.4< 0.3< 0.4 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, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q9-1Q 12/31/07 -01/29/08 < 2.2 01/29/08 -02/26/08 < 2.7 02/26/08 -04/01/08 < 4.5 04/01/08 -04/29/08 < 3.1 04/29/08 -06/03/08 < 2.3 06/03/08 -07/01/08 < 2.4 07/01/08 -07/29/08 < 3.3 07/29/08 -09/03/08 < 1.7 09/03/08 -09/30/08 < 4.4 09/30/08 -10/28/08 < 2.6 10/28/08 -12/02/08 < 2.8 12/02/08 -12/30/08 < 3.0< 2.4< 1.5< 3.0< 2.3< 2.2< 1.7< 1.8< 3.1< 3.8< 3.7< 3.9< 1.7< 3.8 < 1.6< 5.9 < 2.8< 8.1 < 5.4< 3.5 < 3.3< 2.5 < 2.5< 7.1 < 2.1< 4.0 < 2.4< 6.7 < 2.2< 9.6 < 3.6< 8.9 < 2.9< 7.3 < 3.2< 7.9 < 3.1< 3.9< 2.3< 9.1< 4.9< 4.1< 6.4< 5.9< 5.5< 4.8< 4.2< 3.8< 4.7< 3.6 < 2.3 < 1.9<4.0 < 1.8 <2.7< 7.2 < 5.1 < 4.0< 5.9 < 4.5 < 4.6< 6.1 < 2.3 < 3.6<3.8 < 1.6 < 3.5< 4.2 < 2.0 < 2.8< 3.5 < 3.3 < 3.7< 9.2 < 4.6 < 5.7< 6.2 < 2.4 < 5.3< 5.6 < 3.5 < 2.8< 5.0 < 2.1 < 2.5< 2.2 < 9.4< 3.1 < 13< 4.2 < 20< 3.8 < 22<3.7 < 11< 2.9 < 20< 2.7 < 16< 2.7 < 30<4.6 < 10< 3.2 < 14<4.8 < 13<2.4 < 15< 2.1< 1.6< 6.0< 2.7< 1.7< 3.8< 2.6< 6.2< 2.5< 5.1< 4.0< 3.7 TABLE D-II.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDPQ 10/09/08 < 33 < 11 2960 +/- 450 < 15 < 26 < 78 < 20 < 52 < 21 < 16 TABLE D-Ill.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION

.PERIOD K-40 Cs-134 Cs-137 J2-1Q 11/05/08 10778 +/- 677 41 +/- 18 38 +/- 17 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, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD B10-2Q 07/30/08 Hi -2Q 08/22/08 K-40 1-131 Cs-134 Cs-137 Sr-89 Sr-90 3470 +/- 360 4110 +/- 380< 25< 34< 13<15< 16< 12<3<5<3<3 D-7 TABLE D-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION E1-20 PERIOD 01/01/08 -01/09/08 34 +/- 4 01/09/08 -01/16/08 19 +/- 4 01/16/08 -01/23/08 30 +/- 5 01/23/08 -01/30/08 39 +/- 5 01/30/08 -02/06/08 27 +/- 5 02/06/08 -02/13/08 27 +/- 4 02/13/08 -02/20/08 31 +/- 5 02/20/08 -02/27/08 22 +/- 5 02/27/08 -03/05/08 22 +/- 5 03/05/08 -03/12/08 22 +/- 4 03/12/08 -03/19/08 25 +/- 5 03/19/08 -03/26/08 19 +/- 5 03/26/08 -04/02/08 22 +/- 4 04/02/08 -04/09/08 17 +/- 4 04/09/08 -04/16/08 16 +/- 4 04/16/08 -04/23/08 31 +/- 5 04/23/08 -04/30/08 22 +/- 4 04/30/08 -05/07/08 33 +/- 5 05/07/08 -05/13/08 17 +/- 5 05/13/08 -05/21/08 16 +/- 4 O5/2 1/08 -05/28/08 11 +/- 4 05/28/08 -06/04/08 20 +/- 4 06/04/08 -06/11/08 23 +/- 4 06/11/08 -06/18/08 22 +/- 4-06/18/08

-06/25/08

-19 +/- 4 06/25/08 -07/02/08 19 +/- 4 07/02/08 -07/09/08 21 +/- 5 07/09/08 -07/16/08 25 +/- 4 07/16/08 -07/23/08 37 +/- 5 07/23/08 -07/30/08 28 +/- 4 07/30/08 -08/06/08 27 +/- 4 08/06/08 -08/13/08 18 +/- 4 08/13/08 -08/20/08 26 +/- 4 08/20/08 -08/27/08 20 +/- 4 08/27/08 -09/04/08 23 +/- 4 09/04/08 -09/10/08 27 +/- 5 09/10/08 -09/17/08 13 +/- 4 09/17/08 -09/24/08 26 +/- 4 09/24/08 -10/01/08 34 +/- 4 10/01/08 -10/08/08 19 +/- 4 10/08/08 -10/15/08 35 +/- 5 10/15/08 -10/22/08 21 +/- 4 10/22/08 -10/29/08 16 +/- 4 10/29/08 -11/05/08 29 +/- 4 11/05/08 -11/12/08 22 +/- 4 11/12/08 -11/19/08 11 +/- 4 11/19/08 -11/25/08-18 +/- 4 11/25/08 -12/03/08 24 +/- 4 12/03/08 -12/10/08 31 +/- 5 12/10/08 -12/17/08 21 +/- 4 12/17/08 -12/24/08 32 +/- 4 12/24/08 -12/31/08 47 +/- 5 MEAN 24 +/- 15 D-8 TABLE D-Ill.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD J2-1Q 11/05/08 K-40 Cs-134 Cs-137 10778 +/- 677 41 +/- 18 38 +/- 17 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, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 G2-1Q 01/09/08 02/06/08 03/05/08 03/19/08 04/02/08 04/16/08 04/30/08 05/14/08 05/28/08 06/11/08 06/25/08 07/09/08 07123108 08/06/08 08/20/08 09/03/08 09/17/08 10/01/08 10/15/08 10/29/08 11/12/08 11/25/08 12/10/08< 0.3< 0.4< 0.2< 0.3< 0.3< 0.2< 0.2< 0.4< 0.4< 0.3< 0.3< 0.3< 0.3< 0.2< 0.4< 0.4< 0.3< 0.2< 0.4< 0.2 0.4 +/- 0.2< 0.4< 0.3 1240 +/-1163 +/-1269 +/-1436 +/-1274 +/-1400 +/-1434 +/-1289 +/-1078 +/-1380 +/-1327 +/-1331 +/-1272 +/-636 +/-1050 +/-1358 +/-1466 +/-1247 +/-1185 +/-1078 +/-1244 +/-1285 +/-1383 +/-102 104 115 126 115 114 125 121 121 114 111 123 101 92 117 133 107 108 86 107 108 110 125< 4.3* 2.5* 3.8< 3.7< 3.3< 4.4* 3.0< 3.4< 4.3* 2.8< 5.7* 3.6* 3.6<4.8<6.1< 4.2< 3.3< 3.9* 2.9* 3.2< 3.9< 4.8* 4.8< 2.8* 2.7< 3.3* 2.5< 3.4* 3.2* 2.9< 3.4* 2.4< 3.2< 4.9< 5.7< 3.9<4.8< 4.3<4.1* 3.0* 3.0* 2.8* 2.4< 3.9< 4.7* 4.0<21<14* 25* 8.2* 23* 14* 21<13<18* 9.0* 21<17< 20<18<13* 20* 26* 25<19* 20* 8.8<13<12* 2.7< 5.4* 2.7* 1.3* 2.8* 1.8* 3.2* 1.7< 3.4< 2.4< 4.6< 2.9< 4.9<4.1* 5.0<6.1< 6.3* 2.8* 6.9< 4.2* 1.2< 3.9< 3.7< 1.0< 0.7< 0.7 0.7 +/- 0.3< 0.7< 0.5< 0.8 0.8 +/- 0.4 MEAN 0.4 +/- 0.0 1253 +/- 354 0.7 +/-0.1* 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, 2008 5-- QC-LAB 4 i- PR IM A R Y -LA B -------------------------

-----------

L.a, C., a.3 2 0 Jan Feb Mar Apr May Jun Jul Aug Sep MONTH Oct Nov, Dec FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2008 50__ _ _ _ _ _ _ _ _ _ _ _ _ _QC -LAB 40 -- APRIMARY -LAB E 30 -20 0 .... .. ..........

...... .. .. ..... .. .... .. .. ......1 0 -' --------------------------

..........

........' ...................................

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

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

APPENDIX E ERRATA DATA TABLE C-XII.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGENS/MONTH

+/-2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD SITE BOUNDARY+/- 2 S.D.INDICATOR CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 5.5 +/- 0.5 5.1 +/- 0.5 5.4 +/- 0.5 4.7 +/- 1.2 6.3 +/- 1.3 5.9 +/- 1.4 6.3 +/- 1.7 5.1 +/- 1.3 6.7 +/- 1.2 6.3 +/- 1.3 6.7 +/- 1.6 5.6 +/- 1.2 TABLE C-XI.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGEN/STD.

MONTH LOCATION SAMPLES PERIOD PERIOD ANALYZED MINIMUM MAXIMUM PERIOD MEAN+/-2 S.D.PRE-OP MEAN+/- 2 S.D.SITE BOUNDARY INDICATOR CONTROL 76 240 44 4.1 4.1 4.9 6.9 9.4 8.8 5.2 +/- 0.9 5.9 +/- 1.7 6.3 +/- 1.6 4.8 +/- 1.5 5.2 +/- 1.5 5.8 +/- 1.7 SITE BOUNDARY STATIONS -A1-4, B1-2, C1-2, Di-1, E1-4, F1-2, G1-6, H1-1, J1-3, K1-4, LI-1, Mi-1, N1-3, P1-2, Q1-2, Ri-i, F1-4, G1-3, G1-5, INDICATOR STATIONS -A3-1, A5-1, A9-3, B1-1, B10-1, B2-1, B5-1, Cl-1, 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-27 Intentionally left blank APPENDIX F INTER-LABORATORY COMPARISON PROGRAM TABLE F-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)March 2008 E5847-396 Milk E5848-396 Milk E5850A-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs- 134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 83.5 95.8 pCi/L 13.9 12.9 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 57.3 229 336 106 141 71.8 98.1 102 135 230 163 233 72.6 98.3 46.7 69.8 72.2 106 156 60.0 249 359 125 146 70.8 94.2 102 137 236 157 227 79.0 92.0 44.7 59.4 64.5 86.4 149 E5849-396 Charcoal 1-131 pCi 65.5 60.1 pCi/L 83.9 85.0 pCi/L 14.4 15.8 0.87 1.08 0.96 0.92 0.94 0.85 0.97 1.01 1.04 1.00 0.99 0.97 1.04 1.03 0.92 1.07 1.04 1.18 1.12 1.23 1.05 1.09 0.99 0.91 0.99 0.90 1.15 0.91 0.99 0.95 1.03 1.07 1.02 0.97 1.00 1.05 1.05 1.03 0.98 1.13 0.99 1.06 1.04 A A A A A A A A A A A A A A A A A A A W A A A A A A A A A A A A A A A A A A A A A A A June 2008 E5971-396 Milk E5972-396 Milk E5974-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 70.9 157 159 69.7 115 59.1 139 98.4 129 101 206 173 95.9 142.0 72.0 180 108.0 159 129 71.4 174 138 76.7 116 61.9 135 91.7 127 104 207 164 91.0 138.0 73.4 160.0 109.0 150 124 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 F-1 TABLE F-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 2 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)June 2008 E5973-396 Charcoal 1-131 pCi 73.8 84.1 pCi/L 76.2 73.9 pCi/L 12.3 11.0 September 2008 E6284-396 E6285-396 E6287-396 E6286-396 December 2008 E6415-396 E6416-396 E6418-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 65.7 145 406 196 147 167 165 161 305 218 79.5 208 106 79.3 87.7 90.3 81.7 144 111 67.9 161 421 232 162 179 166 144 319 234 76.3 199 110 76.7 84.4 78.6 68.3 151 111 AP Ce-141 Cr-51 Cs-I134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 0.88 1.03 1.12 0.97 0.90 0.96 0.84 0.91 0.93 0.99 1.12 0.96 0.93 1.04 1.05 0.96 1.03 1.04 1.15 1.20 0.95 1.00 1.04 1.07 1.43 0.87 0.93 0.94 0.87 0.99 1.00 1.01 1.00 0.97 1.00 1.01 1.08 1.01 1.05 1.03 0.97 1.00 0.88 1.07 A pCi 93.2 90.0 pCi/L 98.4 91.9 pCi/L 18.0 12.6 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 69.2 177 231 117 119 104 153 99.6 177 133 148 202 103 95.4 81.4 113 76.5 122 108 79.9 191 246 134 120 104 152 100 183 133 146 187 102 91.2 79.2 116.0 76.4 139 101 A N (1)A A A A A A A A A A A A A A A A A A A AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 F-2 TABLE F-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 3 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)December 2008 E6417-396 Charcoal 1-131 pCi 65.8 74.1 0.89 A (1) NCR 09-02 initiated to investigate the failure.(a) Teledyne Brown Engineering reported result.(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) Ratio of Teledyne Brown Engineering to Analytics results.(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable.

Reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.

N =Not Acceptable.

Reported result falls outside the ratio limits of < 0.70 and> 1.30.F-3 TABLE F-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 1)Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)January 2008 Quiktm Response Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-137 Co-60 Zn-65 Gr-A Gr-B H-3 January 2008 RAD 72 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 37.33 40.40 87.8 80.67 222.33 98.9 352 13.0 32.7 11100 69.0 35.6 25.9 86.5 155 16.0 214 13.3 21.2 22.8 3390 65.47 39.80 59.63 45.00 97.97 75.47 109 41.03 50.20 26.67 11633 19.0 42.7 90.5 88.9 231 101.0 350 12.7 36.2 11300 65.3 41.4 25.7 92.6 158 14.4 204 14.8 22.5 23.6 3540 60.4 39.2 58.3 46.6 102 76.6 106 50.8 51.4 28.7 12000 11.8-25.2 31.5 -49.0 76.2 -99.6 72.9- 97.8 208 -256 90.9-113 315-408 6.02-18.7 23.8 -43.8 9840- 12400 53.0 -73.4 30.5 -47.6 20.0 -29.5 76.0- 102 142- 176 11.4-18.7 184 -240 7.15-21.2 13.7 -30.6 19.6 -28.0 3000-3910 48.6- 68.2 28.8 -45.1 48.3 -64.3 37.4-51.3 91.8- 115 68.9 -86.7 95.4- 126 26.5 -63.7 35.0 -58.4 23.9 -33.6 10400 -13200 N (1)A A A A A A A A A A A A A A A A A A A A April 2008 Rad 73 A A A A A A A A A A A (1) Could find no cause for Sr-89 failure. Sample sent to outside lab for verification, but the outside laboratory was unable to confirm our numbers or ERA numbers. Studies bracketing these results, RAD 71 and RAD 72, had acceptable Sr-89 results. NCR 08-03 (a) Teledyne Brown Engineering reported result.(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) ERA evaluation:

A=acceptable.

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

Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.F-4 TABLE F-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 2)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)January 2008 07-MaW18 07-GrW18 07-MaS18 07-RdF18 07-GrF18 January 2008 07-RdV18 Water Cs- 134 Cs- 137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/L -0.26 Bq/L 0.029 Bq/L 21 22.8 Bq/L 8.2 8.40 Bq/L 473 472 Bq/L 12 12.1 Bq/L 10.70 11.4 Bq/L 15.6 16.3 Bq/L 1.4 1.399 Bq/L 3.06 2.43 Bq/kg .790 854.0 Bq/kg 568 545 Bq/kg 424 421 Bq/kg 2.307 2.9 Bq/kg 611 570 Bq/kg 6.09 571 Bq/kg 454 493.0 Bq/kg 0.162 Bq/sample 2.73 2.5200 Bq/sample 2.88 2.7 Bq/sample 3.493 3.55 Bq/sample 1.357 1.31 Bq/sample 0.006 Bq/sample 1.61 1.548 Bq/sample 2.59 2.04 Bq/sample 0.131 0.348 Bq/sample 0.261 0.286 Bq/sample 5.25 6.28 Bq/sample 3.13 3.41 Bq/sample 6.837 6.89 Bq/sample 2.44 2.77 Bq/sample 4.45 4.74 Bq/sample 61.3 Bq/sample 1.33 1.273 Bq/sample 0.085 Bq/L 17.1 19.5 Bq/L 21.4 23.6 Bq/L -0.044 Bq/L 10.8 11.6 Bq/L 334 341 Bq/L 13.0 13.7 Bq/L 6.55 6.45 Bq/L 16.5 17.1 (1)(1)16.0 -29.6 5.88-10.92 330-614 8.5- 15.7 7.98- 14.82 11.4-21.2>0.0 -2.798 1.22 -3.65 598-1110 382 -709 295 -547 (2)399 -741 400 -742 345 -641 (1)1.76 -3.28 1.89-3.51 2.49 -4.62 0.92 -1.70 (1)1.084 -2.012 1.43 -2.65>0.0 -0.696 0.143 -0.429 4.40-8.16 2.39 -4.43 4.82 -8.96 1.94-3.60 3.32-6.16 (1)0.891 -1.655 (1)A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A August 2008 08-MaW19 13.7-25.4 16.5-30.7 (1)8.1 -15.1 239 -443 9.6- 17.8 4.52- 8.39 12.0 -22.2 F-5 TABLE F-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWN ENGINEERING, 2008 (PAGE 2 OF 2)Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)August 2008 08-GrWl9 08-MaS19 Water Gr-A Gr-B Bq/L 0.0612 <0.56 Bq/L 0.222 <1.85 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 546 2.52 340 157 460 650 1.40-1.53 581 2.8 333 145.0 415 571 (3)(3)407-755 (2)233-433 102-189 291- 540 399- 741 (1)(1)A A A A A A A A A A A A A A A W A 08-RdF19 08-GrF19 08-RdV19 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 2.46 0.0063 1.36 0.0143 2.70 1.42 0.975 Bq/sample

-0.0037 Bq/sample 0.540 2.6300 1.84 -3.42 (1)1.50 1.05-1.95 (1)2.64 1.85-3.43 1.12 0.78-1.46 0.94 0.66 -1.22 (4)0.525 0.263 -0.788 5.5 3.9 -7.2 (1)7.1 5.0-9.2 4.70 3.3 -6.1 5.8 4.1-7.5 (1)1.9 1.3-2.5 6.9 4.8 -9.0 A A Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 4.36-0.03 6.72 4.04 5.22 64.4 1.62 6.160 W A A A A A A (1) Not evaluated by MAPEP.(2) Reported a statistically zero result.(3) Designed to test the Safe Drinking Water screening levels. Labs reporting values less than ref values were found to be acceptable.

(4) False positive test.(a) Teledyne Brown Engineering reported result.(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) DOEIMAPEP evaluation:

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

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

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2008 (Page 1 of 1)Concentration (pCi/L)Lab Code 0 Date Analysis STAP-1 143 STAP-1 143 STAP-1 143 STAP-1 143 e STAP-1 143 STAP-1 143 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 STAP-1 144 03/24/08 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1145 STSO-1 145 STSO-1 145 e STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STVE-1 146 STVE-1 146 STVE-1 146 STVE-1 146 STVE-1 146 e STVE-1 146 STVE-1 146 STW-1 147 STW-1 147 STW-1 147 STW-1 147 e STW-1 147 STW-1 147 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 Gr. Beta Ac-228 Bi-212 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Sr-90 Th-234 Zn-65 Co-60 Cs-134 Cs-137 K-40 Mn-54 Sr-90 Zn-65 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 Zn-65 Laboratory Result c 650.72 +/- 3.00 467.50 +/- 5.53 1375.90 +/- 25.41 0.00 +/- 0.00 157.60 +/- 7.70 889.90 +/- 15.90 ERA Result d 730.0 523.0 1450.0 0.0 152.0 872.0 99.90 +/- 3.09 1269.02 +/- 36.81 1407.10 +/- 56.64 5219.70 +/- 90.30 5427.30 +/- 102.94 6346.60 +/- 201.80 11052.70 +/- 181.80 0.00 +/- 0.00 1198.20 +/- 96.58 2253.30 +/- 291.60 6407.00 +/- 277.00 2421.80 +/- 321.00 2936.20 +/- 73.50 912.41 +/- 13.59 1547.70 +/- 38.81 1163.80 +/- 20.62 22186.00 +/- 339.40 0.00 +/- 0.00 3825.90 +/- 140.66 1676.80 +/- 43.00 1430.00 +/- 33.33 730.18 +/- 33.39 1947.80 +/- 13.80 0.00 +/- 0.00 512.03 +/- 43.37 708.90 +/- 29.00 2009.00 +/- 36.40 92.2 1180.0 1360.0 5130.0 5640.0 6010.0 11000.0 0.0 1080.0 2020.0 5360.0 2030.0 2660.0 888.0 1540.0 1100.0 24600.0 0.0 4130.0 1430.0 1420.0 751.0 1990.0 0.0 512.0 694.0 56.80 -135.0 757.0 -1660.0 357.0 -2030.0 3730.0 -6890.0 3630.0 -6790.0 4600.0 -7810.0 7980.0 -14900.0 0.0 -10.0 697.0 -1520.0 1210.0 -3010.0 1940.0 -8750.0 644.0 -3870.0 2110.0 -3570.0 600.0 -1280.0 882.0 -2130.0 807.0 -1530.0 17700.0 -34800.0 0.0 -10.0 2310.0 -5480.0 1030.0 -1960.0 1240.0 -1680.0 555.0 -862.0 1690.0 -2380.0 0.0 -10.0 325.0 -684.0 588.0 -865.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Control Limits 565.0 -912.0 341.0 -647.0 1090.0 -1900.0 0.0 -10.0 66.9 -236.0 604.0 -1210.0 Acceptance Pass Pass Pass Pass Pass Pass STW-1120 03/19/07 1910.0 1600.0 -2410.0 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

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

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.Included in the testing series as a "false positive".

No activity expected.F-7 TABLE F-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2008 (Page 1 of 2)Concentration

)Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1 137 STW-1 137 STW-1 137 STW-1 137 STW-1 137 STW-1 137 STW-1 137 STW-1 137 STW-1 138 STAP-1 139 STAP-1 139 STAP-1 139 STAP-1 139 STAP-1 139 STAP-1 139 STAP-1 139 STAP-1 140 STVE-1 141 STVE-1 141 STVE-1 141 STVE-1 141 STVE-1 141 STVE-1 141 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1158 STSO-1 158 STSO-1 158 STSO- 1158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 Co-57 Co-60 Cs-134 Cs-1 37 H-3 Mn-54 Sr-90 Zn-65 23.80 8.60-0.021 0.00 515.10 12.90 12.00 16.90+/- 0.60+/- 0.50+/- 0.10+/- 0.10+/- 12.70+/- 0.80+/- 1.50+/- 1.40 22.80 8.40 0.00 0.00 472.00 12.10 11.40 16.30 16.00 -29.60 5.88 -10.92-1.00 -1.00-1.00 -1.00 330.00 -614.00 8.50 -15.70 7.98 -14.82 11.40 -21.20 Pass Pass Pass Pass Pass Pass Pass Pass 01/01/08 Gr. Beta 2.30 +/- 0.15 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 3.90 1.43 2.59 3.05 0.43 1.30 2.36+/- 0.07+/- 0.07+/- 0.16+/- 0.12+/- 0.58+/- 0.27+/- 0.18 2.43 3.55 1.31 2.52 2.70 0.00 1.55 2.04 0.29 6.89 2.77 6.28 3.41 4.74 0.00 1.22 -3.65 2.49 -4.62 0.92-1.70 1.76 -3.28 1.89 -3.51 0.00 -1.00 1.08 -2.01 1.43 -2.65 0.14 -0.43 4.82 -8.96 1.94 -3.60 4.40 -8.16 2.39 -4.43 3.32 -6.16 0.00 -1.00 01/01/08 Gr. Beta 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 0.34 +/- 0.04 8.30 +/- 0.18 3.03 +/- 0.13 6.53 +/- 0.29 3.90 +/- 0.19 5.43 +/- 0.21 0.033 +/- 0.10 483.00 +/- 3.00 3.00 +/- 0.80 896.50 +/- 7.40 624.40 +/- 4.10 667.20 +/- 3.80 0.093 +/- 0.91 353.02 +/- 2.01 151.99 +/- 1.58 499.72 +/- 2.65 2.54 +/- 0.25 643.94 +/- 15.50 452.14 +/- 2.96 1.95 +/- 2.04 0.10 +/- 2.04 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 421.00 2.90 854.00 545.00 570.00 0.00 333.00 145.00 581.00 2.80 570.00 415.00 0.00 0.00 295.00 -547.00 0.00 -5.00 598.00 -1110.00 382.00 -709.00 399.00 -741.00 0.00 -1.00 233.00 -433.00 102.00 -189.00 407.00 -755.00 0.00 -5.00 399.00 -741.00 291.00 -540.00 0.00 -5.00 0.00 -5.00 F-8 TABLE F-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2008 (Page 2 of 2)Concentration D Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1 159 STVE-1 159 STVE-1 159 STVE-1 159 STVE-1 159 STVE-1 159 STW-1 162 STW-1162 STW-1 162 STW-1 162 STW-1 162 STW-1 162 STW-1 162 STW-1 162 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 H-3 Mn-54 Sr-90 Zn-65 8.52 +/- 0.23 5.08 +/- 0.19 5.26 +/- 0.18 0.01 +/- 0.14 6.39 +/- 0.28 7.73 +/- 0.45 0.03 +/- 0.16 11.27 +/- 0.23 17.93 +/- 0.52 23.72 +/- 0.43 385.15 +/- 8.93 13.87 +/- 0.37 6.49 +/- 1.12 17.64 +/- 0.61 0.12 +/- 0.05 7.10 4.70 5.50 0.00 5.80 6.90 5.00 -9.20 3.30 -6.10 3.90 -7.20 0.00-1.00 4.10 -7.50 4.80 -9.00 Pass Pass Pass Pass Pass Pass 0.00 11.60 19.50 23.60 341.00 13.70 6.45 17.10 0.00 0.00 -5.00 8.10 -15.10 13.70 -25.40 16.50 -30.70 239.00 -443.00 9.60 -17.80 4.52 -8.39 12.00 -22.20 0.00 -1.85 Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1163 08/01/08 Gr. Beta 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).

' 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.F-9 Intentionally left blank APPENDIX G 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 2008 Prepared By Teledyne Brown Engineering Environmental Services Exel"n,.Nuclear Three Mile Island Nuclear Station Middletown, PA 17057 April 2009 Table Of Contents I. Sum m ary and Conclusions

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

1 I1. 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 III. Program Description

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

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

6 B. Data Interpretation

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

6 IV .Results and Discussion

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

7 A .G roundw ater Results .........................................................................................

7 B. Surface W ater Results.....................................................................................

8 C .Precipitation Results .........................................................................................

8 D .Leaks, Spills, and Releases .............................................................................

9 E. Actions Taken ...................................................................................................

9 Appendices Appendix A Tables Table A-1: Location Designation Radiological Groundwater Protection Program -Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2008 Figures Figure A-1: Appendix B Tables Table B-1.1 Table B-1.2 Table B-11.1 Table B-11.2 Table B-Ill.1 Appendix C Tables Table C-1.1 Sampling Locations Near the Site Boundary of the Three Mile Island Nuclear Station, 2008 Data Tables Concentrations of Tritium and Strontium in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Well Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Tritium and Strontium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2008.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2008.Concentrations of Tritium in Precipitation Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2008.Data Tables Concentrations of Tritium in Well Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2008.ii Appendices (cont.)Appendix C Tables Table C-l.2 Table C-I1.1 Table C-111.1 Data Tables (cont.)Concentrations of Gamma Emitters in Well Water Split Samples Collected as Part f the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2008.Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2008.Concentrations of Tritium in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2008.iii

1. 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 of the special investigations for all TMI wells are included in this report. This report covers groundwater and surface water samples, collected from the environment, both on and off station property in 2008. During that time period, 426 analyses were performed on 244 samples from 74 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 2008 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 or surface water 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 2.0 picoCuries per liter (pCi/L) in the groundwater samples tested.Tritium was not detected in any groundwater, surface water or precipitation 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 45 of 65 groundwater monitoring locations and in five of six precipitation locations.

The groundwater tritium concentrations ranged from 201 +/- 112 pCi/L to 7,210 +/- 785 pCi/L, and the precipitation tritium concentrations ranged from 226 +/- 117 pCi/L to 706 +/- 149 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.

Intentionally left blank 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 in 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 in station specific reports. The summary report for the Three Mile Island Nuclear Station may be found at the following web page: http://www.exeloncorp.com/ourcompanies/powergen/nuclear/Tritium.htm 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) on well water and surface water samples collected in 2008. All wells that-were established were located in the owner controlled areas of the site. No offsite wells were established because the groundwater movement is to the Susquehanna River.This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2008.A. Objective of the RGPP The long-term objectives of the 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 new procedures to identify and report new 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 and Surface Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures.

Both groundwater and surface water 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. 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 half-life of approximately 12.3 years. It decays spontaneously to helium-3 (He-3). This radioactive decay releases a beta particle (low-energy electron).

The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides, because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2008.In order to achieve the stated objectives, the current program includes the following analyses: 1. Concentrations of gamma emitters in groundwater and surface water.2. Concentrations of strontium in groundwater and surface water.3. Concentrations of tritium in groundwater and surface water.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 and surface 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.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 throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.Tritium Samples from 65 locations were analyzed for tritium activity (Table B-1.1, Appendix B). Tritium values ranged from the detection limit to 7,210 pCi/I. Two of the locations were offsite drinking water wells with no detectable concentration of tritium.I Strontium Strontium-90 was not detected above the required detection limit of 2.0 pCi/liter. (Table B-1.1, Appendix B).Gamma Emitters Potassium-40 was detected in nine of 65 samples. The concentrations ranged from 37 pCi/liter to 130 pCi/liter.

No other gamma emitting nuclides were detected. (Table B-1.2, Appendix B).B. Surface Water Results Samples were collected from surface water locations throughout the year 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/liter. (Table B-11.1, Appendix B).Strontium Strontium-90 was not detected above the required detection limit of 2.0 pCi/liter. (Table B-11.1, Appendix B).Gamma Emitters No gamma emitting nuclides were detected. (Table B-11.2, Appendix B).C. Precipitation Results Samples were collected from temporary precipitation collection devises from January through June. Analytical results and anomalies are discussed below.

Tritium Samples from six locations were analyzed for tritium activity (Table B-ll1.1 Appendix B). Tritium values ranged from the detection limit to 706 pCi/I.Strontium Strontium-90 was not analyzed in 2008.Gamma Emitters Gamma emitters were not analyzed in 2008.D. Leaks, Spills, and Releases No new active leaks were identified at the TMI in 2008. TMI continues to monitor tritium plumes from previous years and reports the dose to the public in the ARERR. 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.E. Actions Taken 1. Compensatory Actions TMI continues to monitor groundwater radioactivity as part of natural monitored attenuation of historical leaks.

APPENDIX A LOCATION DESIGNATION

& DISTANCE TABLE A-1: Radiological Groundwater Protection Program -Sampling Locations and Distance, Three Mile Island Nuclear Station, 2008 Site Site Type#3 48N 48S E1-2 GP-12 GP-6 GP-8 GP-9 J1-3 MS-1 MS-19 MS-2 MS-20 MS-21 MS-22 MS-3 MS-4 MS-5 MS-6 MS-7 MS-8 MW-1 MW-2 MW-3 MW-4 N2-1 NW-A NW-B NW-C NW-CW OS-13B OS-14 OS-16 OS-17 OS-18 OSF RW-1 RW-2 SW-E-1 SW-E-2 SW-E-3 MW-TMl-9S*

MW-TMI-10D MW-TMI-101 MW-TMI-10S MW-TMI-11S*

MW-TMI-12S MW-TMI-131 MW-TMI-13S MW-TMI-14D MW-TMI-141 MW-TMI-14S MW-TMI-16D MW-TMI-161 Monitoring Well Monitoring Well Production Potable Well Monitoring Well, Offsite Monitoring Well Monitoring Well Monitoring Well Monitoring Well Precipitation Monitoring Well, Precipitation Monitoring Well, Precipitation Monitoring Well, Precipitation Monitoring Well, Precipitation Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well, Offsite Production Well Production Well, Precipitation Production Well Clearwell Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Production Potable Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well* NO WATER PRESENT TO SAMPLE A-1 TABLE A-1: Radiological Groundwater Protection Program -Sampling Locations and Distance, Three Mile Island Nuclear Station, 2008 Site Site Type MW-TMI-17D MW-TMI-171 MW-TMI-1 8D MW-TMI-19D MW-TMI-191 MW-TMI-1D MW-TMI-2D MW-TMI-31 MW-TMI-41 MW-TMI-4S MW-TMI-5D MW-TMI-6D MW-TMI-61 MW-TMI-7S MW-TMI-8S MW-TMI-91 TRAINING CENTER Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well A-2 SUSQU EllANNA RFIER-7-Ij I -L!1 4~ __ ~ $car_DRAFT PRIVILEGED AND CONFIDENTAL ATTORNEY-CLIENT COMMUNICATION ATTORNEY WORK PRODUCT-'1 ~JI~ !~~ --EXELON GENERATION COMPANY, LLC SLSOUEHANA

~RrVE1 FLEETWIDE ASSESSMENT GROUNDWATER MONfTORING WELL LOCATIONS THREE MILE ISLAND GENERATING STATION MIDDLETOWN.

PENNSYLVANIA Exelon 753M 0,21 f-w.'r4.2 APPENDIX B DATA TABLES TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS.IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE#3#3 48N 48N 48S 48S 48S 48S El-2 El-2 GP-12 GP-6 GP-6 GP-8 GP-8 GP-9 GP-9 MS-1 MS-1 MS-19 MS-19 MS-19 MS-2 MS-2 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-21 MS-21 MS-21 MS-21 MS-21 MS-21 MS-22 MS-22 MS-22 MS-22 MS-22 MS-3 MS-3 MS-4 MS-4 COLLECTION DATE 05/15/08 10/22/08 05/14/08 10/23/08 03/03/08 05/16/08 08/11/08 10/28/08 05/13/08 10/28/08 03/03/08 03/03/08 05/15/08 03/03/08 05/15/08 03/03/08 05/13/08 05/16/08 10/24/08 05/14/08 10/21/08 10/21/08 05/14/08 10/22/08 01/14/08 01/29/08 03/05/08 04/09/08 05/13/08 07/02/08 08/13/08 09/16/08 10/21/08 12/08/08 01/14/08 01/29/08 03/05/08 03/05/08 04/09/08 10/21/08 03/05/08 05/13/08 05/15/08 08/13/08 10/23/08 05/13/08 10/22/08 05/14/08 10/23/08 H-3 SR-90< 164 175 +/- 116 414 +/- 125< 188< 165< 163< 188< 163< 170< 167 201 +/- 112< 1.0< 1.9< 1.1< 1.3 249 167 204 292 341 259 378+/-++/-112 106 115 114 119 110 123 205 +/- 112 537 +/- 131< 168 -< 184 221 +/- 113< 165 568 486 358 246 453 330 337 289 257 309 361 259 263 209< 180 234 945 187 1130 1160 985 226 215 297 321 125 133 116 115 128 125 119 104 112 107 101 109 112 112 118 165 112 185 181 162 113 114 122 127< 1.3< 1.5< 1.5< 0.9< 1.5< 1.5< 1.5< 0.8< 1.4 B-1 TABLE B-1.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE MS-5 MS-5 MS-6 MS-6 MS-7 MS-7 MS-8 MS-8 MS-8 MW-i MW-i MW-i MW-2 MW-2 MW-2 MW-3 MW-3 MW-4 MW-4 MW-TMI-10D MW-TMI-10D MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 COLLECTION DATE 05/13/08 10/21/08 05/13/08 10/21/08 05/13/08 10/22/08 05/13/08 05/13/08 10/21/08 05/15/08 10/23/08 10/23/08 05/15/08 05/15/08 10/23/08 05/15/08 10/23/08 05/15/08 10/23/08 05/15/08-10/24/08 03/04/08 05/14/08 08/13/08 10/22/08 10/22/08 03/04/08 03/04/08 05/14/08 08/13/08 10/24/08 01/14/08 03/05/08 05/14/08 08/12/08 10/23/08 01/14/08 01/29/08 01/29/08 03/06/08 04/08/08 04/08/08 05/16/08 05/16/08 07/02/08 08/12/08 09/16/08 10/24/08 12/08/08 H-3 SR-90* 166* 158* 161* 175* 182 196 +/- 112 307 +/- 130 365 +/- 118 247 +/- 115* 173* 171* 187* 197 185* 186* 142* 163* 143* 164 386 303 3570 3640 2540 2240 1840 4600 4720 3890 4790 3970 224* 160+/- 108< 0.9* 0.8* 1.3* 0.8* 1.3* 1.9< 1.1* 1.2* 1.3* 1.4* 1.9* 1.4* 1.8+/- 137+/- 120+/- 417 425+/- 310+/- 292+/- 252+/- 516+/- 532+/- 451+/- 531+/- 459+/- 101 194 + 113< 163 628 7030 7060 7210 6670 4710 5280 4740 4530 3920 3290 3000 2210 2120+/- 134+/- 761+/- 767+/- 785+/- 740+/- 529+/- 592+/- 533+/- 521+/- 451+/- 385+/- 345+/- 290+/- 263< 1.3* 1.7 B-2 TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D COLLECTION DATE 01/14/08 01/14/08 01/29/08 03/04/08 04/08/08 05/15/08 07/02/08 08/12/08 09/16/08 10/24/08 12/08/08 01/14/08 01/29/08 03/04/08 04/08/08 05/14/08 07/02/08 08/12/08 08/12/08 09/16/08 10/22/08 12/08/08 04/08/08 05/14/08 07/02/08 08/12/08 09/16/08 10/21/08 12/08/08 12/08/08 01/14/08 01/29/08 03/04/08 04/08/08 05/14/08 07/02/08 08/12/08 09/16/08 10/22/08 12/08/08 01/14/08 01/29/08 03/04/08 03/04/08 04/09/08 05/14/08 05/14/08 07/02/08 07/02/08 H-3 SR-90 452 +/- 118 422 +/- 114 490 +/- 133< 164 220 435 732 215 425 385 450 1370 1140 1120 1340 1510 1130 1190 1040 1030 1190 1270 745 849 609 438 331 237< 191 374 686 806< 164 605 197 399 273 177< 171< 148 2660 2530 2670 3110 2800 2520 2750 1970 2250+/- 117+/- 140+/- 145+/- 110+/- 111+/- 126+/- 116+/- 196+/- 192+/- 183+/- 201+/- 217+/- 180+/- 179+/- 170+/- 156+/- 188+/- 183+/- 146+/- 158+/- 140+/- 124+/- 106+/- 128+/- 116+/- 136+/- 155+/- 136+/- 114+/- 129+/- 114+/- 96+/- 323+/- 323+/- 327+/- 374+/- 338+/- 327+/- 339+/- 280+/- 286* 1.6* 1.6< 1.0< 1.3 B-3 TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-17D MW-TMI-17D MW-TMI-17D MW-TMI-171 MW-TMI-171 MW-TMI-18D MW-TMI-18D MW-TMI-19D MW-TMI-19D MW-TMI-191 MW-TMI-191 MW-TMI-191 MW-TMI-1 D MW-TMI-1D MW-TMI-2D MW-TM I-2D MW-TM I-2D MW-TM I-2D MW-TMI-31 MW-TMI-31 MW-TMI-41 MW-TMI-41 MW-TMI-4S MW-TMI-4S MW-TMI-5D MW-TMI-5D MW-TMI-6D MW-TMI-6D MW-TMI-61 MW-TMI-61 MW-TMI-61 MW-TMI-7S MW-TMI-7S MW-TMI-8S COLLECTION DATE 08/12/08 09/16/08 10/22/08 12/08/08 01/14/08 01/29/08 03/04/08 04/09/08 05/14/08 07/02/08 08/12/08 09/16/08 09/16/08 10/22/08 12/08/08 05/14/08 10/23/08 10/23/08 05/16/08 10/23/08 05/14/08 10/22/08 05/13/08 10/23/08 05/19/08 05/19/08 10/23/08 05/15/08 10/23/08 03/04/08 05/15/08 08/13/08 10/23/08 05/16/08 10/23/08 05/14/08 10/21/08 05/14/08 10/21/08 05/14/08 10/21/08 05/13/08 10/21/08 05/13/08 05/13/08 10/21/08 05/13/08 10/22/08 05/13/08 H-3 SR-90 2040 2000 1540 1360 1090 795 987 1110 1130 1020 671 448 374 757 1450< 195< 167< 171+/- 263+/- 248+/- 219+/- 190+/- 171+/- 160+/- 169+/- 181+/- 186+/- 170+/- 135+/- 110+/- 108+/- 154+/- 198 238 +/- 129< 165< 190* 171* 187< 170< 196* 187* 161< 1.6< 1.8< 1.8< 1.0* 1.5< 1.5* 1.5< 1.5< 1.3< 1.7< 1.5* 1.7< 1.5* 1.7* 1.3< 1.5< 1.6 380 459 533 349 591 581 278+/- 119+/- 127+/- 130+/- 118+/- 130+/- 137+/- 129* 171< 195* 173< 191< 165* 195< 170 287 246 408 270 217+/- 116+/- 123+/- 123+/- 115+/- 126< 195< 168 253 +/- 129 B-4 TABLE B-1.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION DATE SITE MW-TMI-8S MW-TMI-8S MW-TMI-91 MW-TMI-91 N2-1 N2-1 NW-A NW-A NW-B NW-B NW-C ORIGINAL NW-C RERUN NW-C NW-CW NW-CW OS-13B OS-14 OS-14 OS-16 OS-17 OS-17 OS-18 OS-18 OS-18 OS-18 OS-18 OSF OSF OSF OSF OSF RW-1 RW-1 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 ORIGINAL RW-2 RERUN TRAINING CENTER TRAINING CENTER H-3 10/22/08 10/22/08 05/13/08 10/22/08 05/12/08 10/22/08 05/15/08 10/28/08 05/15/08 10/28/08 05/15/08 05/15/08 10/28/08 05/15/08 10/28/08 05/13/08 05/13/08 10/21/08 05/13/08 05/14/08 10/23/08 03/04/08 05/15/08 08/12/08 10/21/08 10/21/08 03/03/08 05/16/08 08/11/08 08/11/08 10/28/08 05/14/08 10/22/08 01/14/08 01/29/08 03/05/08 04/09/08 05/14/08 07/02/08 08/13/08 08/13/08 09/16/08 10/23/08 10/23/08 12/08/08 12/08/08 05/12/08 10/28/08* 170* 170* 198* 170* 164* 169 704 1120 881 483 4460 5020 2750 932 958 279 317* 167 SR-90* 1.6* 1.6* 1.7* 1.2+ 144+ 185+/- 158-128+/- 505+/- 540+ 342+/- 165+/- 172+ 114+/- 119* 1.2* 1.6* 1.3* 1.6* 1.0 374 +/- 121 439 +/- 127* 163 369 +/- 116* 190 592 220 279 720 547 517 414 599* 171* 176+/- 131+/- 117+/- 116+/- 143+/- 129+/- 127+/- 122+/- 139 449 +/- 113 297 +/- 118 365 +/- 117 259 +/- 118 245 +/- 117 288 +/- 124 249 +/- 112 232 +/- 113 308 +/- 103 929 +/- 168 979 +/- 160 2250 +/- 298 2070 +/- 265* 169* 168* 1.7< 1.8< 1.6< 1.1< 1.3< 0.9< 1.2 B-5 TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC 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#3 10/22/08 <9 < 14 < 1 < 1 < 2 < 1 < 1 <1 <2 < 1 < 1 < 41 < 13 48N 10/23/08 < 9 < 4 < 1 < 1 < 2 < 1 < 1 < 1 < 1 < 0 < 0 < 41 < 11 48S 10/28/08 < 10 < 6 < 1 < 1 < 2 < 1 < 1 < 1 < 2 < 1 < 1 < 35 < II E1-2 10/28/08 < 15 < 7 < 1 < 2 < 4 < 1 < 2 < 2 < 3 < 1 < 1 < 51 < 14 MS-1 10/24/08 < 16 < 24 < 1 < 1 < 4 < 1 < 2 < 1 < 2 < 1 < 1 < 56 < 15 MS-19 10/21/08 < 14 < 7 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 58 < 14 MS-19 10/21/08 < 8 < 4 < 0 < 1 < 2 < 0 < 1 < 1 < 1 < 0 < 0 < 39 < 11 MS-2 10/22/08 < 12 < 5 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 49 < 14 MS-20 10/21/08 < 9 < 17 < 1 < 1 -< 2 < 1 < 1 < 1 < 2 < 1 < 1 < 44 < 14 MS-21 10/21/08 < 11 < 17 < 1 < 1 < 2 < 1 < 1 < 1 < 2 < 1 < 1 < 43 < 14 MS-22 10/23/08 < 10 < 14 < 1 < 1 < 2 < 1 < 1 < 1 < 2 < 1 < 1 < 43 < 15 MS-3 10/22/08 < 12 < 5 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 49 < 15 MS-4 10/23/08 < 10 < 14 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 59 < 13 MS-5 10/21/08 < 11 61 +/- 26 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 52 < 15 MS-6 10/21/08 < 10 < 13 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 50 < 13 MS-7 10/22/08 < 10 130 +/- 17 < 1 < 1 < 2 < 0 < 1 < 1 < 2 < 1 < 1 < 41 < 14 MS-8 10/21108 < 11 123 +/- 24 < 1 < 1 < 2 < 1 < 1 < 1 < 2 < 1 < 1 < 47 < 15 MW-i 10/23/08 < 13 51 +/- 23 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 54 < 15 MW-i 10/23/08 < 11 < 6 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 50 < 15 MW-2 10/23/08 < 10 < 5 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 46 < 15 MW-3 10/23/08 < 11 < 4 < 1 < 1. < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 58 < 11 MW-4 10/23/08 < 13 37 +/- 23 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 58 < 14 MW-TMI-10D 10/24/08 < 13 < 23 < 1 < 1 < 4 < 1 < 2 < 1 < 2 < 1 < 1 < 44 < 14 MW-TMI-101 10/22108 < 15 < 9 < 1 < 1 < 4 < 1 < 2 < 2 < 3 < 1 < 1 < 57 < 14 MW-TMI-101 10/22/08 < 12 62 +/- 24 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 47 < 15 MW-TMI-10S 10/24/08 < 12 < 7 < 1 < 1 < 3 < 1 < 2 <1 < 2 < 1 < 1 < 47 < 12 MW-TMI-12S 10/23/08 < 11 < 6 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 46 < 15 MW-TMI-131 10/24/08 < 11 < 5 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 41 < 13 MW-TMI-13S 10/24/08 < 12 < 8 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 39 < 14 MW-TMI-14D 10/22/08 < 7 < 4 < 0 < 1 < 2 < 1 < 1 < 1 < 1 < 0 < 1 < 37 < 14 MW-TMI-141 10/21108 < 9 < 14 < 1 < 1 < 3 < 1 < 1 < 1 < 2 < 1 < 1 < 48 < 15 MW-TMI-14S 10/22/08 < 7 59 +/- 17 < 0 < 1 < 2 < 0 < 1 < 1 < 1 < 0 < 0 < 32 < 11 MW-TMI-16D 10/22/08 < 9 < 15 < 1 < 1 < 2 < 0 < 1 < 1 < 2 < 0 < 1 < 43 < 14 MW-TMI-161 10/22/08 < 8 < 16 < 1 < 1 < 2 < 0 < 1 < 1 < 1 < 0 < 1 < 41 < 13 MW-TMI-17D 10/23/08 < 11 < 26 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 44 < 13 MW-TMI-17D 10/23/08 < 13 119 +/- 22 < 1 < 1 < 3 < 1 < 2 < 1 < 2 < 1 < 1 < 52 < 14 TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC MW-TM I-1 71 MW-TMI-18D MW-TMI-19D MW-TMI-191 MW-TMI-1D MW-TMI-2D MW-TMI-31 MW-TMI-41 MW-TMI-4S MW-TM I-5D MW-TMI-6D MW-TM 1-61 MW-TMI-7S MW-TMI-8S MW-TMI-8S MW-TMI-91 N2-1 NW-A NW-B NW-C NW-CW OS-14 OS-18 OS-18 OSF RW-1 RW-2 RW-2 COLLECTION PERIOD 10/23/08 10/22/08 10/23/08 10/23/08 10/23/08 10/23/08 10/23/08 10/21/08 10/21/08 10/21/08 10/21/08 10/21/08 10/22/08 10/22/08 10/22/08 10/22/08 10/22/08 10/28/08 10/28/08 10/28/08 10/28/08 10/21/08 10/21/08 10/21/08 10/28/08 10/22/08 10/23/08 10/23/08 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<8< 26<8<7 62< 29<6< 20<7< 21<19<5< 23< 8<6<6< 22<8<9<9< 8< 5<6< 20* 24< 16<7<5<1<1<1<1+/-25 <1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1<1< 1< 1<1<1<1<1<1<1<1<1<1< 1<1<1<1<1<1<1<1<2<2<2<1<.1<1<1<1<1< 1< 1<3<3<3<3<3<4<3<3<3<3<3<3<3<4<3<3<3<4<4<4<3<2<3<3<3<2<3<2< 50< 53< 50< 44< 42< 46< 43< 46< 52< 39< 56< 51< 45< 54< 40< 47< 44< 56* 42< 57< 45< 35* 46< 51< 40< 40< 44< 37 TRAINING CENTER 10/28/08<13 <8 <1 <1 <3 <1 <2 <1 <2 <1 <1 <39 <15 TABLE B-11.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION DATE SITE SW-E-1 SW-E-1 SW-E-1 SW-E-1 SW-E-1 SW-E-2 SW-E-2 SW-E-2 SW-E-2 SW-E-3 SW-E-3 SW-E-3 SW-E-3 H-3 SR-90 03/03/08 05/12/08 05/12/08 08/11/08 10/28/08 03/03/08 05/12/08 08/11/08 10/28/08 03/03/08 05/15/08 08/11/08 10/28/08< 165< 191< 197* 165< 171< 166* 192< 162< 167< 166< 191* 161* 158< 1.0< 1.6< 1.8 B-8 TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 200B RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION Be-7 K-40 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 TM-SW-E-1 TM-SW-E-2 TM-SW-E-3 10/28/08 10/28/08 10/28/08< 16 < 10< 16 < 32< 14 < 25<1<1<1<2 <4 <1<2 <3 <1<1 <3 <1<2<2<2<2<2< 1<3<3<2<1<1<1<1<1<1<47 < 12< 45 < 13< 41 < 14

0) (p TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM -THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COL SITE PR-J1-3 PR-J1-3 PR-J1-3 PR-J1-3 PR-J1-3 PR-MS-1 PR-MS-1 PR-MS-1 PR-MS-1 PR-MS-1 PR-MS-19 PR-MS-19 PR-MS-19 PR-MS-19 PR-MS-19 PR-MS-2 PR-MS-2 PR-MS-2 PR-MS-2 PR-MS-2 PR-MS-20 PR-MS-20 PR-MS-20 PR-MS-20 PR-MS-20 PR-MS-20 PR-NW-B PR-NW-B PR-NW-B PR-NW-B PR-NW-B 01/28/08 02/26/08 03/31/08 04/29/08 06/03/08 01/28/08 02/26/08 03/31/08 04/29/08 06/03/08 01/28/08 02/26/08 03/31/08 04/29/08 06/03/08 01/28/08 02/26/08 03/31/08 04/29/08 06/03/08 01/28/08 02/26/08 ORIGINAL 03/31/08 RERUN 03/31/08 04/29/08 06/03/08 01/28/08 02/26/08 03/31/08 04/29/08 06/03/08 LECTION DATE-02/26/08-03/31/08-04/29/08-06/03/08-07/01/08-02/26/08-03/31/08-04/29/08-06/03/08-07/01/08-02/26/08-03/31/08-04/29/08-06/03/08-07/01/08-02/26/08-03/31/08-04/29/08-06/03/08-07/01/08-03/31/08-04/29/08-04/29/08-04/29/08-06/03/08-07/01/08-02/26/08-03/31/08-04/29/08-06/03/08-07/01/08 H-3< 171< 178< 173* 172< 166< 167< 169< 167< 172< 167< 172< 177 175 +/- 114* 168 172 +/- 111 463 +/- 132 181 +/- 115< 174< 162< 168 475 + 131 425 +/- 130 706 +/- 149 512 +/- 131< 169 196 +/- 112 290 +/- 117 265 +/- 116 191 +/- 113 226 +/- 117* 168 B-1O 4 APPENDIX C DATA TABLES TABLE C-I.1 CONCENTRATIONS OF TRITIUM IN WELL WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCIILITER

+/- 2 SIGMA COLLECTION DATE SITE H-3 SR-90 MW-TMI-13S MW-TMI-131 MW-TMI-131 MW-TMI-16D MW-TMI-10S MS-21 MW-TMI-131 MW-TMI-61 MW-TMI-16D MW-2 MS-8 MW-TMI-131 MW-TMI-191 MW-TMI-16D RW-2 MW-TMI-14D OSF MW-TMI-161 OS-18 MW-TMI-8S MW-TMI-17D RW-2 MS-19 MW-TMI-101 MW-i MW-TMI-141 01/14/08 ORIGINAL 01/29/08 DUPLICATE 01/29/08 03/04/08 03/04/08 03/05/08 04/08/08 05/13/08 05/14/08 05/15/08 05/13/08 05/16/08 05/19/08 07/02/08 08/13/08 08/12/08 08/11/08 09/16/08 10/21/08 10/22/08 10/23/08 10/23/08 10/21/08 10/22/08 10/23/08 12/08/08 446 +/- 111 8159 +/- 268 7913 +/- 264 3095 +/- 180 4811 +/- 214 258 +/- 102 6123 +/- 242 411 +/- 91 2817 +/- 163< 147 403 +/- 91 5385 +/- 214 179 +/- 81 2246 +/- 159 205 +/- 97 1317 +/- 133 591 +/- 111 570 +/- 97* 154 249 +/- 89 182 +/- 86 877 +/- 115 173 +/- 85 2058 +/- 152* 154< 160< 0.5< 0.5< 0.5* 0.7* 0.5< 0.5< 0.6 C-1 TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION Be-7 K-40 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 MS-1 MS-19 MW-TMI-101 MW-TMI-17D MW-TMI-8S OS-18 RW-2 10/24/08 10/21/08 10/22/08 10/23/08 10/22/08 10/21/08 10/23/08< 48< 39< 28< 36< 45< 31< 34< 81< 85< 83< 78< 85< 65< 81<3 <3 <10 <3<3 <3 <6 <2<4 <4 <7 <2<3 <4 <6 <2<3 <3 <9 <2<3 <2 <6 <2<2 <2 <5 <3<5 <3 <6 <5 <2 <31 <6<6 <4 <8 <3 <4 <16 <4<6 <4 <8 <3 <4 <16 <4<10 <2 <6 <3 <4 <16 <4<4 <3 <6 <4 <4 <31 <3<7 <3 <6 <4 <3 <17 <4<4 <3 <7 <3 <2 <23 <3 4 o 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, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION DATE SITE H-3 05/12/08< 147 C-3 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, 2008 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE PR-MS-iQ PR-MS-iQ PR-MS-iQ PR-MS-iQ PR-MS-iQ COLLECTION DATE 01/28/08 -02/26/08 02/26/08 -03/31/08 03/31/08 -04/29/08 04/29/08 -06/03/08 06/03/08 -07/01/08 H-3< 177< 180< 155< 167 251 +/- 95 C-4