ML072960680

Radiological Environmental Monitoring Program Report

ML072960680
Person / Time
Site:	Three Mile Island
Issue date:	04/30/2007
From:	Dougherty T AmerGen Energy Co, Exelon Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Bamford, Peter J., NRR/DORL 415-2833
References
5928-07-20095
Download: ML072960680 (169)

Text

AmerGen Energy Company, LLC Telephone: 717-948-8ooo AmerGen. An Exelon Company C

Three Mile Island Unit Route 441 South, P.O. Box 480 Middletown, PA 17057 April 30, 2007 5928-07-20095 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR-73 DOCKET NOS. 50-289 AND 50-320

SUBJECT:

2006 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT In accordance with TMI-1 Technical Specification 6.9.3.1 and TMI-2 Technical Specification 6.8.1.1, enclosed is the Annual Radiological Environmental Operating Report covering the time-period of January 1 through December 31, 2006, for the Three Mile Island Nuclear Station.

Please note the map, Figure A-1 in Appendix F contains sensitive information related to security, and it needs to be stripped from the REMP package prior to posting as a public document.

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

Sincerely, Thomas J. Dou~ghZ Plant Manager TJD/awm Enclosure cc: Region I Administrator TMI-1 Senior Project Manager TMI-2 Project Manager TMI-1 Senior Resident Inspector GPU Nuclear TMI-2 Cognizant Officer File 07027

Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2006 Prepared By Teledyne Brown Engineering Environmental Services An Exe ion Company Three Mile Island Nuclear Station Middletown, PA 17057 April 2007

Table Of Contents I. Sum mary and Conclusions ................................................................................................ 1 I1.Intro d uctio n ........................................................................................................................ 3 A. O bjectives of the REM P ................................................................................... 3 B. Implem entation of the O bjectives .................................................................... 4 I1l. Program Description ..................................................................................................... 4 A. Sam ple Collection .............................................................................................. 4 B. Sam ple Analysis ............................................................................................... 6 C . Data Interpretation ............................................................................................. 7 D. Program Exceptions ........................................................................................ 8 E. Program Changes .......................................................................................... 12 IV. Results and Discussion ............................................................................................ 13 A. Aquatic Environm ent ..................................................................................... 13.

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

2. Drinking Water ...................................................................................... 14

3. Effl uent Water ...................................................................................... 14

4. Storm Water ......................................................................................... 15

5. Ground Water ........................................................................................... 16

6. Fish ...................................................................................................... 17

7. Sedim ent ............................................................................................. 17 B. Atm ospheric Environm ent .............................................................................. 18

1. Airborne ............................................................................................... 18

a. Air Particulates ......................................................................... 18

b. Airbom e Iodine ......................................................................... 19

2. Terrestrial ............................................................................................. 19

a. Milk .......................................................................................... 19

b. Food Products ......................................................................... 20 C . Am bient Gam ma Radiation ............................................................................ 20 D. Land Use Survey ........................................................................................... 21 E. Radiological Impact of TM INS O perations ...................................................... 21 F. Summary of Results - Inter-laboratory Comparison Program ........................ 29 V. References ...................................................................................................................... 31

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2006 Appendix B Location Designation, Distance & Direction And Sample Collection &

Analytical Methods Tables Table B-I: Location Designation and Identification System for the Three Mile Island Nuclear Station Table B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2006 Table B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2006 Eigures Figure B-i: Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2006 Figure B-2: Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2006 Figure B-3: Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2006 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1. 1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

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Table C-1.2 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-11.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-11.2 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-11.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-111.1 Concentrations of Gross Beta, 1-131, Tritium, and Strontium in Effluent Water Samples for Station K1 -1 Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-111.2 Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-IV.1 Concentrations of Tritium and Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-V.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-V.2 Concentrations of Strontium and Gamma Emitters in Ground Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

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

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-VI.2 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-VII.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-VIII.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-VIII.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

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Table C-VIII.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-IX.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-X.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-X.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-X.3 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-XI.1 Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table C-XII.1 Quarterly TLD Results for Three Mile Island Nuclear Station, 2006.

Table C-XlI.2 Mean Quarterly TLD Results for the Site Boundary, Offsite and Control Locations for Three Mile Island Nuclear Station, 2006.

Table C-XII.3 Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2006.

Figures Figure C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2006.

Figure C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2006.

Figure C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2006.

Figure C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2006.

Figure C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2006.

Figure C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2006.

Figure C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2006.

Figure C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2006.

Figure C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2006.

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Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-1.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2006.

Table D-I.2 Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-I.3 Concentrations of Iodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-1.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-I.5 Concentrations of Tritium, Strontium, and Gamma Emitters in Ground Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-I.6 Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-I.7 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-1.8 Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-II.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-1I.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table D-Ill.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, 2006.

Figures Figure D-1 Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2006.

Figure D-2 Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2006.

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Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2006 Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2006 Table E-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2006 Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2006 Table E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2006 Appendix F Radiological Groundwater Protection Program Report (ARGPPR) vi

I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Three Mile Island Nuclear Station (TMINS) by AmerGen covers the period 1 January 2006 through 31 December 2006. During that time period, 1,743 analyses were performed on 1346 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, storm, and ground 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.

Ground water samples were also analyzed for concentrations of Sr-90. No Sr-89 and Sr-90 activities were detected. Gross beta and 1-131 concentrations detected were consistent with those detected in previous years. Tritium results in groundwater and several monthly results in surface, drinking and effluent water samples were due to TMINS activities or releases. The calculated dose due to the drinking water samples was <0.004 mrem. This dose is a small fraction of the 10 CFR 20 Appendix I dose limits. Iodine-1 31 detected in effluent water was from upstream medical users. 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-89 and Sr-90. No Sr-89 and Sr-90 activity was detected.

No fission or activation products were detected in fish or sediment samples.

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. No Sr-90 activity was detected in food products. One weed leaf sample had low levels of Sr-90. Concentrations of naturally occurring K-40 were consistent with those detected in previous years.

No 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 2006 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 2006 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 AmerGen 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 Amergen 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 2006 through 31 December 2006.

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

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

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

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

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

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

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

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

1. Identifying significant exposure pathways.

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

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

Ill. Program Description A. Sample Collection Samples for the TMINS REMP were collected for AmerGen 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 2006. 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, ground water, fish, and sediment. Two gallon water samples were collected monthly from continuous samplers located at three surface water locations (A3-2, J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9-1), and one effluent water location (K1-1). Control locations were A3-2 and Q9-1. Monthly grab water samples were taken from one storm water runoff location (EDCB). Grab ground water samples were collected quarterly at eight locations (48S, GP-1, GP-6, GP-8, GP-9, MS-22, OSF and OS-18), semiannually at 12 locations (GP-12, MS-2, MS-5, MS-8, MS-20, NW-A, NW-B, NW-C, NW-CW, OS-14, RW-1 and RW-2) and annually at seven locations (EI-2, MS-I, MS-4, MS-7, MS-19, MS-21 and N2-1). In response to a special investigation, selected wells were sampled more frequently. 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, E1-2, F1-3, G2-1, H3-1, M2-1, and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

Milk samples were collected biweekly at four locations (K15-3, D2-1, E2-2, and G2-1) from March through November, and monthly from December through February. Milk was also collected at station F4-1 quarterly (March, June, September, and December). The control location was K15-

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

Food products were collected annually at two locations (B10-2 and E1-2).

The control location was B10-2. Four different kinds of vegetation samples 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 (CaS04) thermoluminescent dosimeters (TLD). The TLD locations were placed on and around the TMINS site as follows:

A site boundary ring consisting of 21 locations (Ai-4, B1-1, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-1, J1-3, K1-4, L1-1, M1-1, N1-3, P1-2, Q1-2, and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release.

An offsite ring consisting of 58 locations (A3-1, A5-1, A9-3, B2-1, B5-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, 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-i, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, and R9-1) extending to approximately 5 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 CaSO4 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 2006. 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, storm, and ground water, air particulates, milk, fish, sediment, and food products.

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

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

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

6. Ambient gamma radiation levels at various site environs.

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

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

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

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity 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-134, Cs-137, Ba-140 and La-140 were reported.

For fish eight nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-1 34 and Cs-1 37 were reported.

For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-134 and Cs-1 37 were reported.

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

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

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

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

D. Program Exceptions For 2006 the TMINS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

WATER

1. Q9-1 drinking water samples - During eight weekly sampling periods the sampler was found with a pump jammed error, sample flow interupted or other malfunction. For four of these sample periods, insufficient composite sample was collected and a grab sample had to be taken to make up the required volume. The impacted sample periods are as follows:

01/31/2006 - 02/07/2006, Grab sample required 04/04/2006 - 04/12/2006, Grab sample required 05/16/2006 - 05/23/2006, Grab sample required 05/30/2006 - 06/06/2006, Grab sample required 06/19/2006 - 06/26/2006, No grab sample required; sampler was replaced and powered from a different outlet.

08/01/2006 - 08/08/2006, No grab sample required 10/03/2006 - 10/10/2006, No grab sample required 11/14/2006 - 11/22/2006, No grab sample required

2. Q9-1 surface water samples - During three weekly sampling periods there were missed samples due to power interruptions, sampler malfunction and debris clogging the supply line. Sufficient sample was always available and no grab samples were required.

03/14/2006 - 03/21/2006 03/21/2006 - 03/28/2006 04/25/2006 - 05/02/2006

3. G15-3 drinking water samples - A planned maintenance power outage at the facility affected two weekly sampling periods with missed samples. No grab samples were required. Sufficient sample volume was available for the following periods:

03/21/2006 - 03/28/2006 03/28/2006 - 04/04/2006

4. J1-2 surface water samples - During fifteen weekly sampling periods there were missed hourly composite samples. At no time was a grab sample required; there was always sufficient volume.

Missed samples were due to freezing conditions on the river, unknown sampler malfunction and the suction line separating from its anchor buoy.

12/27/2006 - 01/03/2006 01 /10/2006 - 01/17/2006 01/24/2006 - 01/31/2006 02/07/2006 - 02/14/2006 02/14/2006 - 02/21/2006 02/28/2006 - 03/07/2006 03/07/2006 - 03/14/2006 03/14/2006 - 03/21/2006 06/26/2006 - 07/03/2006 07/03/2006 - 07/11/2006 07/18/2006 - 07/25/2006 08/22/2006 - 08/29/2006 08/29/2006 - 09/05/2006 11/28/2006 - 12/05/2006 12/05/2006 - 12/12/2006

5. A3-2 surface water samples - During six weeks hourly composite samples were missed. On 07/01/06 the sample station was flooded. The sampler had to be replaced and the entire composite sample was lost. This is an extra upstream control station used for informational purposes. The impacted sample periods are as follows:

02/14/2006 - 02/22/2006, No grab sample required 02/28/2006 - 03/07/2006, No grab sample required 05/02/2006 - 05/09/2006, No grab sample required 06/26/2006 - 07/03/2006, Sampler replaced due to flooding. Grab sample required due to short run time.

07/25/2006 - 08/01/2006, No grab sample required 10/24/2006 - 10/31/2006, No grab sample required

6. G15-2 and Q9-1 drinking water samples - The 1-131 LLD of 1.0 pCi/L was missed due to the discontinuation and poor performance of two types of filter paper used in the 1-131 analysis. Although sample aliquots were increased (up to 8 liters, when possible) and count times extended (up to 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br />, in some cases), LLD requirements were missed due to low chemical yield and decay of the iodine during the investigation. TBE initiated NCR 06-13 to investigate and document this event. The following period was effected:

05/30/2006 - 06/26/2006 AIR During periods of missed samples other sample locations were available to fulfill ODCM requirements.

6. A3-1 air particulate and air iodine samples - There were intermittent power problems due to a faulty GFI circuit breaker.

There were two missed samples and nine samples with low volume. One of the low volume samples also did not meet LLD requirements from the analysis lab for the following periods:

02/08/2006 - 02/15/2006, Low volume 03/01/2006 - 03/08/2006, No sample 03/15/2006 - 03/22/2006, Low volume 03/29/2006 - 04/05/2006, Low volume 04/05/2006 - 04/12/2006, Low volume 04/19/2006 - 04/25/2006, Low volume 04/25/2006 - 05/02/2006, No sample, replaced pump 05/02/2006 - 05/10/2006, Low volume 05/10/2006 - 05/17/2006, Low volume 05/17/2006 - 05/26/2006, Low volume, GFI circuit replaced 08/23/2006 - 08/30/2006, Low volume, degraded wiring replaced

7. G2-1 air particulate and air iodine samples - During eleven weekly sample periods power interruptions and breaker trips caused lost sample time. Five samples had insufficient volume to be sent for analysis. A refurbished air sampler with new wiring and controls was installed and a separate outlet and breaker were installed for non-REMP equipment. The impacted sample periods are as follows:

04/12/2006 - 04/19/2006, No sample 06/07/2006 - 06/14/2006, Low volume 06/14/2006 - 06/21/2006, No sample 07/04/2006 - 07/12/2006, Low volume 07/12/2006 - 07/19/2006, No sample 07/19/2006 - 07/26/2006, No sample 07/26/2006 - 08/02/2006, No sample 08/02/2006 - 08/09/2006, Low volume 08/09/2006 - 08/16/2006, Low volume 08/16/2006 - 08/23/2006, Low volume 08/30/2006 - 09/06/2006, Low volume

8. M2-1 air particulate and air iodine samples - Five weekly sampling periods were impacted due to power outages and sample pump failure. Sufficient volume was achieved to send for analysis for the following periods:

01/11/2006 - 01/18/2006, Low volume, pump stopped 01/18/2006 - 01/25/2006, Low volume, pump replaced on 01/19/06 07/12/2006 - 07/19/2006, Low volume 09/06/2006 - 09/13/2006, Low volume 11/08/2006 - 12/05/2006, Low volume

9. E1-2Q air particulate and air iodine samples - This sample station had low volume when a pump nipple broke during sampling and the pump was replaced. Sufficient volume was achieved to send for analysis for the following period:

10/04/2006 - 10/11/2006 MILK

10. Milk samples - The milk 1-131 LLD of 1.0 pCi/L was missed due to the discontinuation and poor performance of two types of filter paper used in the 1-131 analysis. Although sample aliquots were increased (up to 8 liters, when possible) and count times extended (up to 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br />, in some cases), LLD requirements were missed due to low chemical yield and decay of the iodine during the investigation. TBE initiated NCR 06-13 to investigate and document this event. The following periods and locations were effected:

06/07/2006, Location E2-2 06/07/2006, Location G2-1 06/07/2006, Location K15-3 06/21/2006, Location G2-1 ILD

11. Q5-1 TLD sample - One of two TLDs were stolen/vandalized for the following period:

01/12/2006 - 04/13/2006

12. P5-1 TLD sample -All TLDs and hardware were missing after installation of a new utility pole after a vehicular accident for the following period:

07/13/2006 - 10/20/2006 FOOD

13. B10-2 and E1-2 food samples - Corn leaves were collected instead of cabbage for the broad leaf vegetable. The cabbage at the visitor center had drowned and Red Hill farm had sold all locally grown cabbage for the following period:

08/10/2006 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 changes to the program in 2006.

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.

Monthly samples from J1-2 and Q9-1 were analyzed for tritium activity (Table C-1.1, Appendix C). Positive tritium activity was detected in nine of 24 samples, primarily at location J1-2 which is located immediately downstream of the TMINS effluent outfall. All samples ranged from <133 to 9,830 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 iodine-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 activity was detected in two of 12 samples. All samples ranged from <0.4 to 1.0 pCi/I.

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:

Monthly samples from all locations were analyzed for concentrations of gross beta. (Tables C-11.1, Appendix C). Gross beta activity was detected in 20 of 36 samples. The values ranged from <1.7 to 4.1 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-3, Appendix C).

Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Activity was detected in two of 36 samples. All samples ranged from <133 to 193 pCi/l. The concentrations were below the required LLD of 200 pCi/liter. Dose estimates were performed for the positive drinking water tritium results. The hypothetical dose to the maximum exposed individual from consuming this water during both time periods would have been <0.004 mrem to the liver of a child. The effluent combined projected dose for an adult for these time periods was 0.028 mrem.

Given the error for tritium at these low concentrations, the effluent predictions are in good agreement with the environmental sample results. (Figures C-4, Appendix C).

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.4, Appendix C). All nuclides were less than the MDC.

3. Effluent Water Monthly samples were collected from a continuous water sampler at one location (K1-1). The following analyses were performed:

GrossBeta Monthly samples from location KI-1 were analyzed for concentrations of gross beta. (Tables C-111.1, Appendix C). Gross beta was detected in 11 of 12 samples. The values ranged from

<2.2 to 7.9 pCi/l. Concentrations detected were consistent with those detected in previous years.

lodine-131 Monthly samples from location K1-1 were analyzed for concentrations of iodine-131. (Tables C-111.1, Appendix C). Iodine-131 activity was detected in one sample with a concentration of 0.8 pCi/I. The values ranged from <0.3 to <0.9 pCi/I. The positive result is not due to TMINS effluents. During the time period for the positive result, 1-131 was also detected in the upstream control station A3-2. 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.

Monthly samples from location K1 -1 were analyzed for tritium activity (Table C-I11.1, Appendix C). Tritium activity was detected in eight samples. The values ranged from <171 to 99,600 pCi/I. The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. These results 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-111.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at 5.0 pCi/I for Sr-89 and at 0.7 pCi/I for Sr-90.

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

4. Storm Water Monthly grabs from the storm water collection basin (EDCB) were composited quarterly. The following analyses were performed:

Tritum All samples from location EDCB were analyzed for tritium activity (Table C-IV.1, Appendix C). Tritium activity was detected in three samples. The values ranged from <188 to 480 pCi/I and were due to airborne releases of H-3 from TMI. Concentrations detected were 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 Quarterly, semiannual and annual grab samples were collected at 27 locations (48S, GP-1, GP-6, GP-8, MS-22, OSF, OS-18, GP-9, GP-12, MS-2, MS-5, MS-20, NW-A, NW-B, NW-C, NW-CW, OS-14, RW-1, RW-2, E1-2, MS-i, MS-4, MS-7, MS-8, MS-19, MS-21 and N2-1). The following analyses were performed:

All samples from the locations were analyzed for tritium activity (Table C-V. 1, Appendix C). Tritium activity was detected in 44 of 55 samples. The values ranged from 168 to 5,280 pCi/I. In June 2006, water with tritium activity was found leaking from a manhole in TMI's North Parking Lot. The results of the investigation determined that plant related water had leaked into a telephone equipment room and flowed through conduit to the manhole. The leak developed in a 4" condensate tank underground de-ice line.

Backfill material caused a flaw in the external pipe coating which caused localized corrosion and a through wall leak. The line was excavated and repaired. Offsite groundwater tritium concentrations were unaffected by this event. In addition during 2006, Exelon initiated a fleetwide Enironmental Assessment program.

Comprehensive groundwater studies and reports were developed.

The results from these special investigations and studies are discussed in Appendix F. 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 2007, this more comprehensive groundwater program will replace TMI's previous groundwater monitoring program.

Strontium Annual samples from six locations (48S, OSF, MS-2, MS-5, MS-8 and OS-14) were analyzed for Sr-90 (Table C-V.2, Appendix C).

No Sr-90 activity was detected. The highest MDC was calculated at <0.7 pCi/I.

Gamma Spectrometry Quarterly samples from two locations (48S and OSF) and annual composite samples from eight locations (MS-2, MS-5, MS-8, MS-20, MS-22, OS-14, RW-1 and RW-2) and annual grab samples from two locations (E1-2 and N2-1) were analyzed for gamma emitting nuclides (Table C-V.2, Appendix C). All nuclides were less than the MDC.

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-89 and Sr-90. (Table C-VI.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <34 pCi/kg wet for Sr-89 and 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-VI.2, Appendix C).

Naturally occurring K-40 was found at all stations and ranged from 2,440 to 3,910 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 Spectrometr Sediment samples from all four locations were analyzed for gamma emitting nuclides (Table C-VII.1, Appendix C). Potassium-40 was found at all stations and ranged from 12,600 to 19,800 pCi/kg dry.

No TMINS fission or activation products were found.

B. Atmospheric Environment

1. Airborne

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:

GrossBeta Weekly samples were analyzed for concentrations of beta emitters (Table C-VIII.1 and C-VIII.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 29 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . The results from the intermediate offsite locations (Group II) ranged from <6 to 34 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 <6 to 34 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3 . Comparison of the 2006 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 2006 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-VIII.3, Appendix C).

Naturally occurring Be-7 due to cosmic ray activity was detected in 19 of 28 samples. These values ranged from

<22 to 143 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-IX.1, Appendix C). All results were less than the MDC.

2. Terrestrial

a. Milk Samples were collected from four locations (K15-3, D2-1, E2-2, and G2-1) biweekly March through November and monthly December through February. Station F4-1 was sampled quarterly. The following analyses were performed:

Iodine-1 31 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-X.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-X.2, Appendix C). No Sr-89 activity was detected. Sr-90 activity was detected. The values ranged from 0.5 to 2.9 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-X.3, Appendix C).

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

The values ranged from 1070 to 1,530 pCi/l. All other nuclides were less than the MDC.

b. Food Products Samples were collected from two locations (B10-2, E1-2, H11-2, ESE1, ESE2, and ESE3) annually. The following analyses were performed:

Strontium Each food product sample was analyzed for concentrations of Sr-90 (Table C-XI. 1, Appendix C). Sr-90 activity was detected in one weed leaf at a concentration of 5.6 pCi/kg wet.

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

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

The values ranged from 2,240 to 5,060 pCi/l. All other nuclides were less than the MDC.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO4) thermoluminescent dosimeters. Ninety TLD locations were established around the site. Results of TLD measurements are listed in Tables C-XII.1 to C-XII.3, Appendix C.

All TLD measurements but one were below 10 mR/standard month, with a range of 3.6 to 10.2 mR/standard month. A comparison of the Site Boundary and Intermediate Distance 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, Intermediate Distance and Outer Ring Locations (Figure C-9, Appendix C). Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 have a historical high bias, but tracked with the data from all three groups, this bias is most likely due to radon and other naturally occurring nuclides, e.g. K-40, emanating from the ground.

D. Land Use Survey A Land Use Survey conducted in the September and October 2006 growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Normandeau Associates, RMC Environmental Services Division for AmerGen 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 'A degree sectors around the site. There were no changes required to the TMINS REMP, as a result of this survey. The nearest residence in the West sector changed from 560 m to 1120 m based on the residence survey. The results of this survey are summarized below.

Distance in Miles from the TMINS Reactor Buildings Sector Residence Garden Milk Farm Miles Miles Miles IN 1.1 1.6 2.1 2 NNE 0.7 0.9 3 NE 0.5 0.6 4.1 4 ENE 0.5 0.5 1.1 5E 0.4 0.5 1.1 6 ESE 1.1 0.5 3.2 7SE 0.7 0.5 1.4 8 SSE 0.7 0.8 9S 2.3 2.4 10 SSW 0.6 1.6 4.9 11 SW 0.5 1.9 12 WSW 0.5 1.4 13W 0.7 1.4 14 WNW 0.4 0.6 3.7 15 NW 0.4 1.3 16 NNW 1.1 2.4 E. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2006 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2006 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 0.025 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 permanently 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 FirstEnergy Corp. at 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 tohumans, 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 2006 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 2006 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 by an individual from 2006 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.025 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 2006 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 2006 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 2006 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 2006 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Dosey To An Individual USNRC 10 CFR 50 APP. I Calculated Dose Guidelines (mrem/yr)

(mrem/yr) TMI-1 TMI-2 From Radionuclides 3 total body, or 1.35E-2 4.39E-4 In Liquid Releases 10 any organ 1.41E-2 6.90E-4 From Radionuclides In 5 total body, or 7.91E-6 0*

Airborne Releases (Noble Gases) 15 skin 1.54E-4 0*

From Radionuclides In Airborne 15 any organ 1.07E-2 3.97E-5 Releases (Iodines, Tritium and Particulates)

• No noble gases were released from TMI-2.

USEPA Calculated Dose 40 CFR 190 (mrem/yr)

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

Total from Site 75 thyroid 0.25 25 total body 0.26 or other organs

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

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

The direct radiation dose from 2006 TMINS operations was 0.2 mrem. This dose was based on a maximum net fence-line exposure rate of 3 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 (0.2 mrem) yielded a maximum hypothetical dose of 0.26 mrem.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2006 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 1.35E-2 4.39E-4 From Radionuclides in Airborne Releases 7.91E-6 0*

(Noble Gases)

From Radionuclides In Airborne 1.06E-2 3.97E-5 Releases (Iodines, Tritium and Particulates)

• No noble gases were released from TMI-2.

Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations 0,0l25 mremA Individual Whole Body Dose Due to Natural Background Radiation 300lmremj~y Figure 1 Exposure Pathways For Radionuclides Routinely Released From TMINS PREDOMINANT RADIONUCLIDES!

'NOBLE GASES fXeKr) ACTIVATION PRODUCTS,(Co-60, Mn-54)

Plumoe xposure Shoreline exposure RADIOJODIN ES (I-t31, 1-]33) RADIOCESIUMS (Cs-134, Cs-137)

Inhalation and consumption of milk; Shoreline exposure and consumption of milk, water, fruits, and Yeegbet~s meat, fish, waLer, fru its, and vegetables RADIOSTRONTIUMS (Str-89, Sr-90) TRITIUM (H-3)

Consumnption of mil1k, ineat, Inhalation and consumption of water, fruits, and vegetables miik, fruits, and vegctables F. Summary of Results - Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc.,

Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:

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

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

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

The MAPEP defines three levels of performance: Acceptable (flag =

"A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value.

Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% <

bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

For the primary laboratory, 24 out of 28 analytes met the specified acceptance criteria. Four samples did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's MAPEP Series 15 January 2006 soil Cs-134 was evaluated as a false positive, although TBE considered the result a non-detect due to the peak not being identified by the gamma software. MAPEP suggests the Bi-214 is not being differentiated from the Cs-134 peak. When the ratio of activity to uncertainty exceeds 3, TBE will use a key line analysis rather than a weighted mean analysis when evaluating MAPEP non-detects.

2. Teledyne Brown Engineering's MAPEP Series 15 January 2006 Sr-90 in vegetation result of 2.22 Bq/kg exceeded the upper acceptance range of 2.029 Bq/kg. The samples were analyzed in triplicate and the results averaged. One high result of 2.43 Bq/kg biased the submitted results on the high side. TBE was unable to determine the cause for the higher result. The Sr-90 in vegetation results for MAPEP Series 14 and MAPEP Series 16 were acceptable. No client samples were analyzed during the MAPEP Series 14 time period.

3. Teledyne Brown Engineering's MAPEP Series 15 January 2006 Pu-238 and Pu-239/240 in vegetation result of 2.22 Bq/kg "failed the required acceptance ranges. TBE was evaluating the current preparation method for vegetation samples, which proved insufficient for the analyses. TBE does not perform isotopic Pu on client's vegetation samples.

For the secondary laboratory, 20 out of 25 analytes met the specified acceptance criteria. Seven samples did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc.'s ERA November 2006 water 1-131 result of 28.4 pCi/L exceeded the upper control limit of 27.3 pCi/L. The reported result was an average of three analyses, results ranged from 25.36 pCi/L to 29.23 pCi/L. A fourth analysis was performed, with a result of 24.89 pCi/L.

2. Environmental Inc.'s MAPEP January 2006 vegetation Pu-238 result of 0.08 Bq/sample exceeded the lower control limit of 0.10 Bq/sample due to incomplete dissolution of the sample.

3. Environmental Inc.'s MAPEP January 2006 air particulate Pu-238 result of 0.03 Bq/sample exceeded the lower control limit of 0.05 Bq/sample due to incomplete dissolution of the sample.

4. Environmental Inc.'s MAPEP January 2006 soil Pu-238, Pu-239/240, U-233/234 and U-238 results of 14.6, 14.6, 13.5 and 15.4 Bq/kg, respectively, exceeded the lower control limits of 42.81, 32.09, 25.9 and 27.2 Bq/kg, respectively, due to incomplete dissolution of the sample.

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. AmerGen. "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.

Intentionally left blank APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER H-3 24 200 1927 170 1927 J1-2 INDICATOR 0 (PCI/LITER) (8/12) (0/12) (8/12) WEST SHORE; TMI

(<164/9830) (<133/<189) (<164/9830) 0.5 MILES S OF SITE 1-131 12 1 N/A 0.6 0.6 A3-2 CONTROL 0 (2/12) (2/12) SWATARA CREEK

(< 0.4/1.0) (< 0.4/1.0) 2.5 MILES N OF SITE

>! GAMMA 24 MN-54 15 4 4 4 Q9-1 CONTROL 0 (0/12) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<7) (<I/<8) (<1/<8) 8.5 MILES NW OF SITE CO-58 15 4 5 5 Q9-1 CONTROL (0/12) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<8) (<I/<8) (<I/<8) 8.5 MILES NW OF SITE FE-59 30 10 9 10 JI-2 INDICATOR 0 (0/12) (0/12) (0/12) WEST SHORE; TMI

(<2/<15) (<2/< 17) (<2/<15) 0.5 MILES S OF SITE CO-60 15 4 5 5 Q9-1 CONTROL 0 (0/12) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<7) (<1/<8) (<I/<8) 8.5 MILES NW OF SITE ZN-65 30 10 10 10 Q9-1 CONTROL 0 (0/12) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<17) (<I/<22) (<1/<22) 8.5 MILES NW OF SITE NB-95 15 5 5 5 Q9-1 CONTROL 0 (0/12) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<8) (<1/<9) (<1/<9) 85 MILES NW OF SITE

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZR-95 30 8 8 8 JI-2 INDICATOR 0 (PCI/LITER) (0/12) (0/12) (0/12) WEST SHORE; TMI

(<2/<13) (<1/<14) (<2/<13) 0.5 MILES S OF SITE CS-134 15 5 5 5 Q9-1 CONTROL 0 (0/12) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<8) (<l/<10) (<1/<10) 8.5 MILES NW OF SITE

>! CS-137 18 5 4 5 HI-2 INDICATOR 0 (0/12) (0/12) (0/12) WEST SHORE; TMI

(<1/<8) (<1/<8) (<1/<8) 0.5 MILES S OF SITE BA-140 60 28 27 28 JI-2 INDICATOR 0 (0/12) (0/12) (0/12) WEST SHORE; TMI

(<10/<37) (< 12/<40) (<10/<37) 0.5 MILES S OF SITE LA- 140 15 9 9 9 JI-2 INDICATOR 0 (0/12) (0/12) (0/12) WEST SHORE; TMI

(<3/<13) (<4/< 13) (<3/<13) 0.5 MILES S OF SITE DRINKING WATER GR-B 36 4 2.8 2.3 2.9 G15-2 INDICATOR 0 (PCI/LITER) (15/24) (5/12) (8/12) WRIGHTS WATER SUPPLY

(< 1.7/4.1) (1.9/3.3) (< 1.7/4.1) 13.6 MILES SE OF SITE 1-131 36 0.6 0.6 0.6 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(< 0.3/< 1.2) (< 0.3/< 1.4) (< 0.3/< 1.4) 8.5 MILES NW OF SITE H-3 36 200 171 168 173 GIS-3 INDICATOR 0 (2/24) (0/12) (2/12) LANCASTER WATER AUTHORITY

(<134/193) (<133/<181) (<1 35/193) 14.8 MILES SE OF SITE

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER GAMMA 36 (PCI/LITER) MN-54 15 4 4 4 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<7) (<1/<7) (<1/<7) 8.5 MILES NW OF SITE CO-58 15 4 5 5 Q9-1 CONTROL (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<2/<8) (<2/<9) (<2/<9) 8.5 MILES NW OF SITE FE-59 30 9 10 10 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<3/<16) (<4/<18) (<4/<18) 8.5 MILES NW OF SITE CO-60 15 4 5 5 Q9-1 CONTROL (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<8) (<2/<8) (<2/<8) 8.5 MILES NW OF SITE ZN-65 30 9 11 11 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<3/<19) (<3/<18) (<3/<18) 8.5 MILES NW OF SITE NB-95 15 4 5 5 Q9-1 CONTROL (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<2/<8) (<2/<8) (<2/<8) 8.5 MILES NW OF SITE ZR-95 30 8 9 9 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<3/<14) (<3/< 14) (<3/<14) 8.5 MILES NW OF SITE CS-134 15 4 5 5 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<1/<10) (<1/<10) (<1/<10) 8.5 MILES NW OF SITE

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER CS-137 18 4 5 5 Q9-1 CONTROL 0 (PCI/LITER) (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(< 1/<7) (<2/<8) (<2/<8) 8.5 MILES NW OF SITE BA- 140 60 29 32 32 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<10/<44) (< 12/<42) (< 12/<42) 8.5 MILES NW OF SITE

>! LA-140 15 10 10 10 Q9-1 CONTROL 0 (0/24) (0/12) (0/12) STEELTON WATER COMPANY

(<3/<14) (<4/< 14) (<4/<14) 8.5 MILES NW OF SITE EFFLUENT WATER GR-B 12 4 4.8 N/A 4.8 KI-I INDICATOR 0 (PCI/LITER) (11/12) (11/12) MAIN STATION LIQ. DISCHARGE

(< 2.2/7.9) (< 2.2/7.9) ONSITE 1-131 12 0.6 N/A 0.6 KI-I INDICATOR 0 (1/12) (1/12) MAIN STATION LIQ. DISCHARGE

(< 0.4/< 0.9) (< 0.4/< 0.9) ONSITE H-3 12 200 19609 N/A 19609 KI-I INDICATOR 0 (8/12) (8/12) MAIN STATION LIQ. DISCHARGE

(< 171/99600) (< 171/99600) ONSITE SR-89 2 5 3.6 N/A 3.6 KI-I INDICATOR 0 (0/2) (0/2) MAIN STATION LIQ. DISCHARGE

(< 2.2/< 5.0) (< 2.2/< 5.0) ONSITE SR-90 2 1 0.6 N/A 0.6 KI-I INDICATOR 0 (0/2) (0/2) MAIN STATION LIQ. DISCHARGE

(< 0.6/< 0.7) (< 0.6/< 0.7) ONSITE

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS. LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER GAMMA 12 (PCI/LITER) MN-54 15 4 N/A 4 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<1/<8) (<1/<8) ONSITE CO-58 15 "5 N/A 5 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<2/<8) (<2/<8) ONSITE I

FE-59 30 10 N/A 10 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ DISCHARGE

(<4/<19) (<4/< 19) ONSITE CO-60 15 5 N/A 5 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<1/<10) (<]/<10) ONSITE ZN-65 30 11 N/A 11 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<3/<21) (<3/<2 1) ONSITE NB-95 15 5 N/A 5 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<2/<8) (<2/<8) ONSITE ZR-95 30 9 N/A 9 KI-I INDICATOR 0 C,

(0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<3/<14) (<3/<14) ONSITE CS-134 15 5 N/A 5 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<1/<9) (<1/<9) ONSITE

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION 4 NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER CS-137 18 5 N/A 5 KI-I INDICATOR 0 (PCI/LITER) (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<1/<10) (<1/<10) ONSITE BA-140 60 32 N/A 32 KI-I INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<13/<40) (<13/<40) ONSITE

>! LA-140 15 10 N/A 10 KI-1 INDICATOR 0 (0/12) (0/12) MAIN STATION LIQ. DISCHARGE

(<4/<14) (<4/<14) ONSITE STORM WATER H-3 4 200 290 N/A 290 EDCB INDICATOR 0 (PCI/LITER) (3/4) (3/4) STORM WATER BASIN

(<188/480) (<188/480) 0.2 MILES SE OF SITE GAMMA 4 MN-54 15 4 N/A 4 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<2/<7) (<2/<7) 0.2 MILES SE OF SITE CO-58 15 4 N/A 4 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<2/<7) (<2/<7) 0.2 MILES SE OF SITE FE-59 30 9 N/A 9 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<4/<13) (<4/<13) 0.2 MILES SE OF SITE CO-60 15 5 N/A 5 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<2/<9) (<2/<9) 0.2 MILES SE OF SITE

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR C THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION 4 NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS STORM WATER ZN-65 30 9 N/A 9 EDCB INDICATOR 0 (PCI/LITER) (0/4) (0/4) STORM WATER BASIN

(<3/<15) (<3/<15) 0.2 MILES SE OF SITE NB-95 15 5 N/A 5 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<2/<7) (<2/<7) 0.2 MILES SE OF SITE ZR-95 30 7 N/A 7 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<3/<11) (<3/<11) 0.2 MILES SE OF SITE CS-134 15 4 N/A 4 EDCB INDICATOR (0/4) (0/4) STORM WATER BASIN

(<2/<7) (<2/<7) 0.2 MILES SE OF SITE CS-137 18 4 N/A 4 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<2/<7) (<2/<7) 0.2 MILES SE OF SITE BA-140 60 24 N/A 24 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(< 12/<34) (<12/<34) 0.2 MILES SE OF SITE LA-140 15 8 N/A 8 EDCB INDICATOR 0 (0/4) (0/4) STORM WATER BASIN

(<4/<] 1) (<4/<1 1) 0.2 MILES SE OF SITE GROUND WATER H-3 61 200 693 N/A 4840 RW-2 INDICATOR (PCI/LITER) (44/61) (2/2) ONSITE WELL (168/5280) (4400/5280)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE . DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER SR-90 6 0.6 N/A 0.7 OS-14 INDICATOR (PCI/LITER) (0/6) (0/I) ONSITE WELL

(< 0.4/< 0.7) (< 0.7)

GAMMA 18 MN-54 15 3 N/A 5 48S INDICATOR 0 (0/18) (0/4) ONSITE WELL

(<0/<7) (<2/<7)

I 15 3 N/A 5 N2-1 INDICATOR 0 00 CO-58 (0/18) (0/I) GOLDSBORO MARINA

(<o/<6) (<5) 1.2 MILES W OF SITE FE-59 30 6 N/A 10 48S INDICATOR 0 (0/18) (0/4) ONSITE WELL

(<1/<14) (<4/<14)

CO-60 15 3 N/A 5 48S INDICATOR (0/18) (0/4) ONSITE WELL

(<0/<8) (<1/<8)

ZN-65 30 7 N/A 12 OSF INDICATOR 0 (0/18) (0/4) ONSITE WELL

(<1/<20) (<4/<20)

NB-95 15 3 N/A 6 OSF INDICATOR 0 (0/18) (0/4) ONSITE WELL

(<0/<8) (<2/<8)

ZR-95 30 5 N/A 9 OSF INDICATOR 0 (0/18) (0/4) ONSITE WELL

(<1/<11) (<4/<11)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER CS-134 15 3 N/A 6 OSF INDICATOR 0 (PCI/LITER) (0/18) (0/4) ONSITE WELL

(<0/<11) (<2/<11)

CS-137 18 3 N/A 9 MS-22 INDICATOR 0 (0/18) (0/1) ONSITE WELL

(<0/<9) (<9)

>I BA-140 60 23 N/A 35 N2-1 INDICATOR 0 (0/18) (0/1) GOLDSBORO MARINA

(< 11/<49) (<35) 1.2 MILES W OF SITE LA-140 15 8 N/A 12 OSF INDICATOR 0 (0/18) (0/4) ONSITE WELL

(<3/<15) (<6/<15)

BOTTOM FEEDER (FISH) SR-89 4 15 12 15 INDB INDICATOR 0 (PCI/KG WET) (0/2) (0/2) (0/2) YORK HAVEN DAM

(<5/<25) (<5/<18) (<5/<25) DOWNSTREAM OF DISCHARGE SR-90 4 5 3 3 3 INDB INDICATOR 0 (0/2) (0/2) (0/2) YORK HAVEN DAM

(<I/<5) (<2/<4) (<1/<5) DOWNSTREAM OF DISCHARGE GAMMA 4 K-40 N/A 3405 2460 3405 INDB INDICATOR 0 (2/2) (2/2) (2/2) YORK HAVEN DAM (3250/3560) (2440/2480) (3250/3560) DOWNSTREAM OF DISCHARGE MN-54 130 59 77 77 BKGB CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<52/<66) (<71/<83) (<71/<83) UPSTREAM OF DISCHARGE

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER (FISH) CO-58 130 76 86 86 BKGB CONTROL (PCI/KG WET) (0/2) (0/2) (0/2) CITY ISLAND

(<65/<87) (<79/<93) (<79/<93) UPSTREAM OF DISCHARGE FE-59 260 163 219 219 BKGB CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<132/<193) (<184/<253) (<184/<253) UPSTREAM OF DISCHARGE CO-60 130 53 72 72 BKGB CONTROL 0 0

(0/2) (0/2) (0/2) CITY ISLAND

(<49/<58) (<70/<74) (<70/<74) UPSTREAM OF DISCHARGE ZN-65 260 136 152 152 BKGB CONTROL (0/2) (0/2) (0/2) CITY ISLAND

(<101/<170) (<112/<192) (<112/<192) UPSTREAM OF DISCHARGE CS-134 100 70 79 79 BKGB CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<57/<84) (<67/<9 1) (<67/<91) UPSTREAM OF DISCHARGE CS-137 100 64 80 80 BKGB CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<50/<78) (<77/<82) (<77/<82) UPSTREAM OF DISCHARGE PREDATOR (FISH) SR-89 4 19 19 19 BKGP CONTROL 0 (PCI/KG WET) (0/2) (0/2) (0/2) CITY ISLAND

(<5/<32) (<5/<34) (<5/<34) UPSTREAM OF DISCHARGE SR-90 4 4 4 4 BKGP CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<3/<4) (<4/<4) (<4/<4) UPSTREAM OF DISCHARGE

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS PREDATOR (FISH) GAMMA 4 (PCI/KG WET) K-40 N/A 3505 3805 3805 BKGP CONTROL 0 (2/2) (2/2) (2/2) CITY ISLAND (3100/3910) (3790/3820) (3790/3820) UPSTREAM OF DISCHARGE MN-54 130 54 70 70 BKGP CONTROL (0/2) (0/2) (0/2) CITY ISLAND

(<45/<62) (<66/<74) (<66/<74) UPSTREAM OF DISCHARGE I

CO-58 130 65 82 82 BKGP CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<45/<84) (<79/<86) (<79/<86) UPSTREAM OF DISCHARGE FE-59 260 156 207 207 BKGP CONTROL (0/2) (0/2) (0/2) CITY ISLAND

(<113/<198) (<204/<210) (<204/<210) UPSTREAM OF DISCHARGE CO-60 130 60 68 68 BKGP CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<28/<93) (<58/<77) (<58/<77) UPSTREAM OF DISCHARGE ZN-65 260 137 156 156 BKGP CONTROL (0/2) (0/2) (0/2) CITY ISLAND

(<63/<210) (<117/<195) (<117/<195) UPSTREAM OF DISCHARGE CS- 134 100 60 71 71 BKGP CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<38/<82) (<55/<87) (<55/<87) UPSTREAM OF DISCHARGE CS-137 100 64 72 72 BKGP CONTROL 0 (0/2) (0/2) (0/2) CITY ISLAND

(<46/<83) (<55/<88) (<55/<88) UPSTREAM OF DISCHARGE

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT GAMMA (PCI/KG DRY) BE-7 N/A 2607 1640 5200 AI-3 INDICATOR 0 (4/6) (0/I) (i/I) 0.5 MILES N OF SITE

(<1130/5200) (< 1640) (5200)

K-40 N/A 15733 13400 19800 J2-1 INDICATOR 0 (6/6) (1/1) (1/1) YORK HAVEN DAM (12600/19800) (13400) (19800) 1.5 MILES S OF SITE MN-54 N/A 103 123 123 A1-3 CONTROL 0 (0/6) (0/i) (0/1) NORTH TIP OF TMI

(<83/<122) (<123) (<123) 0.5 MILES N OF SITE CO-58 N/A 127 82 160 J2-1 INDICATOR 0 (0/6) (0/I) (0/i) YORK HAVEN DAM

(<93/< 160) (<82) (<160) 1.5 MILES S OF SITE CO-60 N/A 110 109 136 J2-1 INDICATOR (0/6) (0/1) (0/i) YORK HAVEN DAM

(<81/<136) (<109) (<136) 1.5 MILES S OF SITE CS- 134 150 119 105 138 A 1-3 CONTROL 0 (0/6) (0/1) (0/1) NORTH TIP OF TMI

(<79/<1 38) (<105) (<138) 0.5 MILES N OF SITE CS-137 180 130 155 219 EDCB INDICATOR 0 (1/6) (0/I) (I/I) STORM WATER BASIN

(<84/219) (<155) (219) 0.2 MILES SE OF SITE AIR PARTICULATE GR-B 364 10 17 18 19 A3-1 INDICATOR (E-3 PCI/CU.METER) (301/311) (52/53) (46/51) MIDDLETOWN

(<6/34) (<6/34) (<7/31) 2.6 MILES N OF SITE

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE GAMMA 28 (E-3 PCI/CU.METER) BE-7 N/A 81.7 78.7 101 H3-1 INDICATOR 0 (16/24) (3/4) (3/4) FALMOUTH-COLLINS SUBSTATION

(<22.4/143) (54.8/<93.7) (61/143) 2.3 MILES SSE OF SITE MN-54 N/A 3 3.5 4 G2-1 INDICATOR (0/24) (0/4) (0/4) BECKER FARM

(< 1.3/< 6.3) (< 1.91< 6.4) (<3/<6) 1.4 MILES SE OF SITE CO-58 N/A 4.7 4.9 6 G2-1 INDICATOR (0/24) (0/4) (0/4) BECKER FARM

(< 1.7/<10) (< 2.5/< 9.0) (<3/<8) 1.4 MILES SE OF SITE CO-60 N/A 3.2 4 4 M2-1 INDICATOR (0/24) (0/4) (0/4) FISHING CREEK; GOLDSBORO

(< 1.4/< 8.1) (<2.6/<7.1) (<3/<8) 1.3 MILES WSW OF SITE CS-134 10 2.5 2.2 3 G2-1 INDICATOR (0/24) (0/4) (0/4) BECKER FARM

(< 1.2/< 4.2) (< 1.8/< 3.0) (<2/<4) 1.4 MILES SE OF SITE CS-137 10 2.5 2.8 3 G2-1 INDICATOR (0/24) (0/4) (0/4) BECKER FARM

(< 1.2/< 5.2) (< 1.8/< 5.3) (<2/<5) 1.4 MILES SE OF SITE AIR IODINE GAMMA 364 (E-3 PCI/CU.METER) 1-131 70 46 47 49 A3-1 INDICATOR (0/311) (0/53) (0/51) MIDDLETOWN

(<15/<104) (<22/<69) (<15/<104) 2.6 MILES N OF SITE

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK 1-131 96 0.5 0.5 0.6 K 15-3 CONTROL 0 (PCI/LITER) (0/69) (0/27) (0/23) MEYER'S FARM

(< 0.2/< 1.2) (< 0.2/< 1.8) (< 0.2/< 1.8) 14.5 MILES SSW OF SITE SR-89 20 5 3.8 3.5 3.9 G2-1 INDICATOR 0 (0/12) (0/8) (0/4) BECKER FARM

(< 2.9/< 4.7) (< 1.5/< 5.0) (< 3.1/< 4.7) 1.4 MILES SE OF SITE SR-90 20 1 0.9 0.8 1.2 D2-1 INDICATOR 0 (4/12) (4/8) (1/4) ALWINE FARM

(< 0.5/ 2.9) (0.5/1.0) (< 0.5/2.9) 1.1 MILES ENE OF SITE GAMMA 96 K-40 N/A 1291 1352 1363 F4-1 CONTROL 0 (69/69) (27/27) (4/4) TURNPIKE ROAD FARM (1070/1510) (1220/1530) (1230/1480) 3.0 MILES ESE OF SITE CS-134 15 7 7 9 F4-1 CONTROL 0 (0/69) (0/27) (0/4) TURNPIKE ROAD FARM

(<3/<14) (<2/<12) (<6/<l 1) 3.0 MILES ESE OF SITE CS-137 18 7 7 9 F4-1 CONTROL 0 (0/69) (0/27) (0/4) TURNPIKE ROAD FARM

(<2/<13) (<2/<12) (<7/<11) 3.0 MILES ESE OF SITE BA- 140 60 38 38 42 F4-1 CONTROL 0 (0/69) (0/27) (0/4) TURNPIKE ROAD FARM

(< 11/<60) (<9/<57) (<34/<49) 3.0 MILES ESE OF SITE LA-140 15 11 11 12 E2-2 INDICATOR 0 (0/69) (0/27) (0/23) NISSLEY FARM

(<3/<15) (<3/<15) (<3/<15) 1.1 MILES E OF SITE

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2006 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY, PA REPORTING PERIOD: 2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIREC REPORTED MEASUREMENT) (LLD) MEASUREMENTS FOOD PRODUCT SR-90 5 5 4 3 6 ESE3 INDICATOR 0 (PCI/KG WET) (1/4) (0/1) (1/1)

(<2/6) (<3) (6)

GAMMA 11 BE-7 N/A 558 177 1630 ESEI INDICATOR 0 (4/7) (1/4) (1/1)

(<37/1630) (<36/585) (1630)

K-40 N/A 4260 2878 6710 ESEI INDICATOR 0 (7/7) (4/4) (1/1)

(1860/6710) (2250/3870) (6710) 1-131 60 44 39 58 ESE] INDICATOR 0 (0/7) (0/4) (0/1)

(<30/<58) (<27/<56) (<58)

CS-134 60 10 7 19 ESEI INDICATOR 0 (o/7) (0/4) (0/1)

(<3/<19) (<3/<18) (<19)

CS-137 80 13 8 31 ESEI INDICATOR 0 (0/7) (0/4) (0/1)

(<3/<3 1) (<4/<20) (<31)

DIRECT RADIATION TLD-QUARTERLY 359 N/A 6 6 20 H8-1 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (315/315) (44/44) (4/4) SAGINAW ROAD (4/10) (4/9) (9/10) 7.4 MILES SSE OF SITE

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

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

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

Radial Zone of Sampling Location in miles.

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

B-I

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2006 Sample Station Map Distance Medium Numbar (mile) Azimuth Dasciridian AQS A1-3 1 0.5 359' N of site off north tip of TMI in Susquehanna River ID A1-4 1 0.3 60 N of Reactor Building on W fence adjacent to North Weather Station, TMI APAI,ID A3-1 2 2.7 357' N of site at Mill Street Substation SW A3-2 2 2.7 356' N of site at Swatara Creek, Middletown ID A5-1 2 4.4 30 N of site on Vine Street Exit off Route 283 ID A9-3 3 8.0 20 N of site at Duke Street Pumping Station, Hummelstown ID B11-1 1 0.6 250 NNE of site on light pole in middle of North Bridge, TMI ID B13-2 1 0.4 23' NNE of Reactor Building on top of dike, TMI ID B2-1 2 1.9 170 NNE of site on Sunset Dr. (off HillsdaleRd.)

ID B5-1 2 4.9 190 NNE of site at intersection of School House and Miller Roads ID B10-1 3 9.4 210 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey FP B10-2 3 10 310 NNE of site at Milton Hershey School, Hershey ID C1-1 1 0.7 370 NE of site along Route 441 N ID C1-2 1 0.3 500 NE of Reactor Building on top of dike, TMI ID C2-1 2 1.5 440 NE of site at Middletown Junction ID C5-1 2 4.7 43' NE of site on Kennedy Lane ID C8-1 3 7.1 48' NE of site at Schenk's Church on School House Road AQF Control - - - All locations where finfish are collected above Dock St.

Dam, Harrisburg ID D1-1 1 0.2 760 ENE of Reactor Building on top of dike, TMI ID D1-2 1 0.5 670 ENE of site off Route 441 along lane between garden center and residence M D2-1 2 1.1 620 ENE of site at farm on Gingrich Road ID D2-2 2 1.6 740 ENE of site along Hillsdale Rd. (S of Zion Rd.)

ID D6-1 3 5.2 660 ENE of site off Beagle Road ID D15-1 3 10.8 640 ENE of site along Route 241, Lawn APAI,ID,GW,FP E1-2 1 0.4 97' E of site at TMI Visitor's Center ID E1-4 1 0.2 970 E of Reactor Building on top of dike, TMI M E2-2 2 1.1 96' E of site at farm on Pecks Road ID E2-3 2 2.0 970 E of site along Hillsdale Rd. (N of Creek Rd.)

ID E5-1 2 4.7 820 E of site at intersection of North Market Street (Route 230) and Zeager Road ID E7-1 3 6.7 880 E of site along Hummelstown Street, Elizabethtown ID F1-1 1 0.5 1170 ESE of site near entrance to 500 kV Substation ID F1-2 1 0.2 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI AP,AI F1-3 1 0.6 1120 ESE of site in 500 kV Substation ID F1-4 1 0.2 1220 ESE of Reactor Building on top of dike, TMI ID F2-1 2 1.3 1190 ESE of site along Engle Road M F4-1 2 3.2 1040 ESE of site at farm on Tumpike Road ID F5-1 2 4.7 1090 ESE of site along Amosite Road ID F10-1 3 9.4 1120 ESE of site along Donegal Springs Road, Donegal Springs ID F25-1 3 22 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster ID G1-2 1 0.7 1450 SE of site along Route 441 S ID G1-3 1 0.2 1300 SE of Reactor Building on top of dike, TMI ID G1-5 1 0.3 1430 SE of Reactor Building on top of dike, TMI ID G1-6 1 0.3 1390 SE of Reactor Building on top of dike, TMI AI,AP,M G2-1 2 1.4 1260 SE of site at farm on Becker Road ID G2-4 2 1.7 1380 SE of site on Becker Road ID G5-1 2 4.8 1310 SE of site at intersection of Bainbridge and Risser Roads ID G10-1 3 9.7 1280 SE of site at farm along Engles Tollgate Road, Marietta ID G15-1 3 14.4 1260 SE of site at Columbia Water Treatment Plant DW G15-2 3 13.3 129' SE of site at Wdghtsville Water Treatment Plant DW G15-3 3 15.7 124 SE of site at Lancaster Water Treatment Plant B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2006 Sample Station Map Distance Medium Code Numb&r Lha) Amuh Descpion ID 0.5 1670 SSE of site, TMI FP H1-2 1.0 1510 SSE of site along Route 441, Red Hill Market AP,AI,ID H3-1 2 2.2 1600 SSE of site in Falmouth-Collins Substation ID H5-1 2 4.1 1580 SSE of site by Guard Shack at Brunner Island Steam Electric Station ID H8-I 3 7.4 1630 SSE of site along Saginaw Road, Starview ID H15-1 3 13.2 1570 SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills AQF Indicator - All locations where finfish are collected downstream of the TMINS liquid discharge outfall ID JA-1 1 0.8 1760 S of site, TMI SW J1-2 1 0.5 1880 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River ID J1i-3 1 0.3 1890 S of Reactor Building just S of SOB, TMI AQS J2-1 2 1.4 1790 S of site in Susquehanna River just upstream of the York Haven Dam ID J3-1 2 2.7 1790 S of site at York Haven/Cly ID J5-1 2 4.9 1810 S of site along Canal Road, Conewago Heights ID J7-1 3 6.5 1760 S of site off of Maple Street, Manchester ID J15-1 3 12.6 1830 S of site in Met-Ed York Load Dispatch Station EW K1-1 1 0.2 2100 On site at RML-7 Main Station Discharge Building AQS K1 -3 0.2 2120 SSW of site downstream of the TMINS liquid discharge 1 outfall in the Susquehanna River ID K1 -4 0.2 2090 SSW of Reactor Building on top of dike behind Warehouse 2, TMI ID K2-1 2 1.2 2000 SSW of site on S Shelley Island ID K3-1 2 2.0 2060 SSW of site along Rt. 262, N of Cly ID K5-1 2 4.9 2020 SSW of site along Conewago Creek Road, Strinestown ID K8-1 3 7.5 1960 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View ID K15-1 3 12.8 203.0 SSW of site behind McDonald's and next to child care center, Weiglestown M K15-3 3 14.4 2050 SSW of site at farm along S Salem Church Rd, Dover ID 1-1i 1 0.1 236' SW of site on top of dike W of Mech. Draft Cooling Tower, TMI ID L1-2 1 0.5 2210 SW of site on Beech Island ID L2-1 2 1.8 2240 SW of site along Route 262 ID L5-1 2 4.1 2280 SW of site at intersection of Stevens and Wilson Roads ID L8-1 3 8.0 2250 SW of site along Rohlers Church Rd., Andersontown ID L15-1 3 11.8 2260 SW of site on W side of Route 74, rear of church, Mt.

Royal ID M1-1 1 0.1 2500 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI ID M1-2 1 0.4 2520 WSW of site on E side of Shelley Island, Lot #157 APAIID M2-1 2 1.3 2560 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro ID M5-1 2 4.3 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown ID M9-1 3 8.7 2430 WSW of site along Alpine Road, Maytown ID N1-1 1 0.7 2740 W of site on W side of Shelley Island, between lots #13 and #14 ID N1-3 1 0.1 2740 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI ID,GW N2-1 2 1.2 2610 W of site at Goldsboro Marina ID N5-1 2 5.0 2680 W of site off of Old York Road along Robin Hood Drive ID N8-1 3 7.7 2620 W of site along Route 382, 1/2 mile north of Lewisberry ID N15-2 3 10.4 2750 W of site at intersection of Lisbum Road and Main Street, Lisburn ID P1-1 0.4 3030 WNW of site on Shelley Island B-3

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2006 Sample Station Map Distance Madium dL Number Limles) Azimuth Dmdrflon ID P1-2 1 0.1 2920 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI ID P2-1 2' 2.0 2830 WNW of site along Route 262 ID P5-1 2 5.0 2840 WNW of site at intersection of Valley Road (Route 262) and Beinhower Road ID P8-1 3 8.0 2920 WNW of site along Evergreen Road, Reesers Summit ID Q1-1 1 0.5 3170 NW of site on E side of Shelley Island ID Q1-2 1 0.2 3210 NW of Reactor Building on fence W of Warehouse 1, TMI ID Q2-1 2 1.9 3100 NW of site along access road along river ID Q5-1 2 5.0 3170 NW of site along Lumber Street, Highspire SW,DW,ID Q9-1 3 8.5 3100 NW of site at the Steelton Water Company APAI,ID Q15-1 3 13.4 3090 NW of site behind West Fairview Fire Dept. Social Hall (abandoned)

ID R1-1 3 0.2 3350 NNW of Reactor Building along W fence, TMI ID R1-2 1 0.7 3340 NNW of site on central Henry Island ID R3-1 2 2.6 3410 NNW of site at Crawford Station, Middletown ID R5-1 2 4.9 3390 NNW of site at intersection of Spring Garden Drive and Route 441 ID R9-1 3 8.0 3410 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights ID R1 5-1 3 11.2 3320 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park IDENTIFICATION KEY ID = Immersion Dose (TLD) GW = Ground Water (offsite) EW = Effluent Water SW = Surface Water DW = Drinking Water Al = Air Iodine M = Milk (Cow)

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

B]-4

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2006 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 0 water compositor. Nuclear Station)

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

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

Drinking Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchange Effluent Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchanqe 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, 2006 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Effluent Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor. Nuclear Station)

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

Effluent Strontium 89/90 Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 0 Water composite from 0%, monthly samples.

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

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

Ground Gamma Quarterly, Semi- ER-TMI-1 0 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy Annual and Annual radiological analysis (Three Mile Island samples Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy TBE, TBE-2023 Compositing of samples Ground Tritium Quarterly, Semi- EM-TMI-10 Collection of water samples for I gallon or 125 mL TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water Annual and Annual radiological analysis (Three Mile Island scintillation samples, or as Nuclear Station) needed Env. Inc., T-02 Determination of tritium in water (direct method)

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2006 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Ground Strontium 89/90 Quarterly, Semi- ER-TMI-1 0 Collection of water samples for 1 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange Water Annual and Annual radiological analysis (Three Mile Island Nuclear samples Station)

TBE, TBE-2023 Compositing of samples Fish Gamma Semi-annual ER-TMI-1 3 Collection of fish samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples collected radiological analysis (Three Mile Island Nuclear (wet) via electroshocking Station) Env. Inc., GS-01 Determination of gamma emitters by or other techniques gamma spectroscopy Fish Strontium 89/90 Semi-annual ER-TMI-1 3 Collection of fish samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange samples collected radiological analysis (Three Mile Island Nuclear (wet) via electroshocking Station) or other techniques Sediment Gamma Semi-annual grab ER-TMI-03 Collection of sediment samples for 500 grams (dry) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Gross Beta One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2008 Gross alpha and/or gross beta activity in Particulates composite of iodine samples for radiological analysis (Three (approximately various matrices continuous air Mile Island Nuclear Station) 280 cubic sampling through meters weekly) Env. Inc., AP-02 Determination of gross alpha and/or gross glass fiber filter beta in air particulate filters paper Air Gamma Quarterly composite TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy of each station (approximately Env. Inc., AP-03 Procedure for compositing air 3600 cubic Env. Inc., GS-01 Determination of gamma emitters by particulate filters for gamma spectroscopic meters) gamma spectroscopy analysis Air Iodine Gamma One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy composite of iodine samples for radiological analysis (Three (approximately continuous air Mile Island Nuclear Station) 280 cubic Env. Inc., 1-131-02 Determination of 1-131 in charcoal sampling through meters weekly) canisters by gamma spectroscopy (batch method) charcoal filter Milk 1-131 Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion Monthly all other exchange times Milk Strontium- Quarterly composite ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2006 89/90 of Bi-weekly and radiological analysis (Three Mile Island Nuclear monthly grab Station) samples TBE. TBE-2023 Compositing of samples Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method 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 Annual grab sample ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Vegetation Strontium- Annual grab sample ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 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.

00 cence comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Dosimetry Panasonic 814 Station)

(containing 4 each CaSO4 elements)

I Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2006 B-9

Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2006 B- 10

2 4 1 Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2006 B-lI

APPENDIX C DATA TABLES AND FIGURES -

PRIMARY LABORATORY

TABLE C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION J,1-2 Q9-1 PERIOD 01/03/06 - 01/31/06 575 + 136 < 167 01/31/06 - 02/28/06 427 +/- 121 < 177 02/28/06 - 03/28/06 1330 + 173 < 133 03/28/06 - 05/02/06

• 171 < 173 05/02/06 - 05/30/06 < 175 < 173 05/30/06 - 06/26/06 < 187 < 184 06/26/06 - 08/01/06 277 +/- 128 < 189 08/01/06 - 08/29/06 < 164

• 172 08/29/06 - 10/03/06 1050 +/- 174 < 178 10/03/06 - 10/31/06 1240 +/- 143

• 174 10/31/06 - 11/28/06 9830 +/- 1020 < 184 11/28/06 - 01/02/07 7700 +/- 808 < 141 MEAN 1927 +/- 6508 170 + 34 C-1

TABLE C-1.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION A3-2 PERIOD 01/03/06 - 01/31/06 < 0.4 01/31/06 - 02/28/06 < 0.6 02/28/06 - 03/28/06 < 0.4 03/28/06 - 05/02/06 < 0.4 05/02/06 - 05/30/06 < 0.5 05/30/06 - 06/26/06 1.0 +/- 0.4 06/26/06 - 08/01/06 0.8 +/- 0.5 08/01/06 - 08/29/06 < 0.6 08/29/06 - 10/03/06 < 0.6 10/03/06 - 10/31/06 < 0.6 10/31/06 - 11/28/06 < 0.7 11/28/06 - 01/02/07 < 0.4 MEAN 0.6 +/- 0.4 C-2

TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 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 J1-2 01/03/06 -01/31/06 < 7 < 6 < 14 < 7 <16 <7 <13 <8 <7 < 31 < 10 01/31/06 - 02/28/06 < 6 < 6 < 15 < 6 <16 <7 <12 <8 <8 <37 < 13 02/28/06 - 03/28106 < 6 < 8 < 14 < 6 <17 <8 <13 <8 <7 <37 <9 03/28/06 - 05/02/06 < 7 < 7 < 12 < 7 <15 <7 <12 <6 <7 <31 <11 05/02/06 - 05/30/06 < 3 < 4 < 8 < 3 <7 <4 <6 <4 <3 <35 < 11 05/30/06 - 06/26/06 < 6 < 6 < 12 < 6 <14 <6 <11 <7 <6 <33 < 10 06/26/06 - 08/01/06 < 1 < 1 < 2 < 1 <1 <1 <1 <1

<2 <16 <5 08/01/06 - 08/29/06 < 3 < 3 < 8 < 3 <6 <3 <5 <3 <3 <26 <8 08/29/06 - 10/03/06 < 1 < 1 < 4 < 1 <3 <2 <3 <1 <1 <17 <6 10/03/06 - 10/31/06 < 3 < 4 < 10 < 4 <8 <4 <9 <4 <4 <29 < 12 10/31/06 - 11/28/06 < 5 < 5 < 10 < 5 <10 <5 <9 <5 <5 <34 < 11 11/28/06 - 01/02/07 < 2 < 2 < 4 < 3 <3 <2 <4 <2 <2 <10 <3 MEAN 4 14 4 +/- 5 10 +/- 9 4 +/- 5 10 +/- 12 5 +/- 5 8 +/- 8 5 +/-6 5+/-5 28 +/- 18 9 +/- 6 Q9-1 01/03/06 - 01/31/06 < 6 < 7 < 12 < 7 <14 <7 <11 <8 <7 < 32 < 11 01/31/06 - 02/28/06 < 7 < 7 < 13 < 8 <19 <7 <13 <9 <7 <31 <11 02/28/06 - 03/28/06 < 8 < 7 < 16 < 8 <22 <9 <12 <10 <7 <40 < 11 03/28/06 - 05/02/06 < 6 < 7 < 12 < 7 <15 <7 <12 <7 <6 < 31 < 12 05/02/06 - 05/30/06 <3 <4 < 8 < 3 <7 <4 <7 <4 <3 <35 < 10 05/30/06 - 06/26/06 < 8 < 8 < 17 < 8 <18 <7 <14 <9 <8 <40 < 13 06/26/06 - 08/01/06 < I < 1 < 2 < 1 <1 <1 <1 <1 <1 <16 <5 08/01/06 - 08/29/06 < 2 < 2 <4 < 2 <5 <2 <4 <1 <2 <17 <6 08/29/06 - 10/03/06 < 1 < 2 <4 < 1 <3 <2 <3 <1 <1 <22 <6 10/03/06 - 10/31/06 < 3 < 3 <6 < 3 <6 <3 <6 <3 <3 <22 <8 10/31/06 - 11/28/06 < 6 < 5 < 8 < 5 <10 <5 <11 <5 <6 <32 <9 11/28/06 - 01/02/07 < 2 < 2 <4 < 2 <5 <2 <4 <2 <2 <12 <4 MEAN 4 +/- 5 5 +/- 5 9 +/- # 5 +/- 6 10:+/-114 5 +/- 5 8 +/- 9 5 +/- 7 4+/-5 27+/-19 9 +/- 6 C-3

TABLE C-11.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 09-1 PERIOD 01/03/06 01/31/06 < 2.3 < 2.2 < 2.1 01/31/06 02/28/06 3.3 +/- 1.3 3.1 +/- 1.3 3.0 +/- 1.3 02/28/06 03/28/06 2.9 +/- 1.5 < 2.1 < 2.1 03/28/06 05/02/06 < 2.2 < 2.1 2.6 +/- 1.5 05/02/06 05/30106 3.5 +/- 1.6 2.5 +/- 1.4 3.3 +/- 1.4 05/30/06 06/26/06 2.4 +/- 1.4 2.7 +/- 1.5 < 2.1 06/26/06 - 08/01/06 < 2.2 < 2.3 < 2.2 08/01/06 - 08/29/06 3.4 +/- 1.6 3.0 +/- 1.4 < 2.0 08/29/06 - 10/03/06 4.1 +/- 1.6 4.1 +/- 1.6 < 1.9 10/03/06 - 10/31/06 < 1.7 3.6 +/- 1.4 1.9 +/- 1.2 10/31/06 - 11/28/06 3.8 +/- 1.4 2.8 +/- 1.3 2.8 +/- 1.3 11/28/06 - 01/02/07 3.0 +/- 1.5 < 2.1 < 2.1 MEAN 2.9 +/- 1.5 2.7 +/- 1.3 2.3 +/- 0.9 TABLE C-11.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 01/03/06 - 01/31/06 < 0.5 < 0.3 < 0.3 01/31/06 - 02/28/06 < 0.7 < 0.7 < 0.5 02/28/06 - 03/28/06 < 0.3 < 0.4 < 0.4 03/28/06 - 05/02/06 < 0.5 < 0.4 < 0.4 05/02/06 - 05/30/06 < 0.5 < 0.6 < 0.5 05/30/06 - 06/26/06 < 1.2 (1) < 0.8 < 1.4 (1) 06/26/06 - 08/01/06 < 0.8

• 0.8 < 0.7 08/01/06 - 08/29/06 < 0.6 < 0.6 < 0.7 08/29/06 - 10/03/06 <.0.5 < 0.5 < 0.5 10/03/06 - 10/31/06 < 0.6 < 0.5 < 0.5 10/31/06 - 11/28/06 < 0.6 < 0.8 < 0.8 11/28/06 - 01/02/07 < 0.4 < 0.5 < 0.5 MEAN 0.6 +/- 0.5 0.6 +/- 0.4 0.6 +/- 0.6 TABLE C-11.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 01/03/06 - 01/31/U0 < 165

• 166 < 163 01/31/06 - 02/28/06 < 177 < 177 < 176 02/28/06 - 03/28/06 < 134 < 135 < 133 03/28/06 - 05/02/06 < 174 < 172 < 172 05/02/06 - 05/30/06 < 173 < 172 < 173 05/30/06 - 06/26/06 < 181 < 186 < 181 06/26/06 - 08/01/06 < 178 < 178 < 176 08/01/06 - 08/29/06 < 173 < 174 < 167 08/29/06 - 10/03/06 < 176 < 174 < 172 10/03/06 - 10/31/06 < 177 193 +/- 116

• 177 10/31/06 - 11/28/06 < 182

• 182 < 180 11/28/06 - 01/02/07 < 144 172 +/- 98.3 < 144 MEAN 170 +/- 30 173 +/- 28 168 +/- 30 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-4

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 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 G15-2 01/03106 - 01/31/06 <7 <7 < 16 <7 < 15 <8 < 12 <8 <7 < 29 < 12 01/31/06 - 02/28/06 <7 <7 < 15 <8 < 18 <7 < 11 < 10 <7 < 36 < 13 02/28/06 - 03/28/06 <2 <:3 <6 <2 <6 <3 <5 <3 <2

• 23 <8 03/28106 - 05/02/06 <7 <7 < 13 <8 < 15 <7 < 12 <8 <7 < 34 < 12 05/02/06 - 05/30/06 <3 <3 <8 <4 <7 <4 <6 <3 <3 < 32 < 11 05/30/06 - 06/26/06 <6 <5 < 12 <6 < 13 <6 <9 <6 <6 < 28 < 10 06/26/06 - 08/01/06 <2 <2 <6 <2 <4 <2 <4 <2 <2

• 41 < 14 08/01/06 - 08/29/06 <3 <4 <7 <3 <7 <4 <7 <3 <3 < 27 <9 08/29/06 - 10/03/06 <1 <2 <3 <1 <3 <2 <3 <1 <1

• 14 <5 10/03/06 - 10/31/06 <3 <3 <7 <3 <6 <3 <6 <3 <3 < 22 <7 10/31/06 - 11/28/06 <5 <:5 < 12 <5 <9 <6 <9 <5 <5

• 32 < 10 11/28/06 - 01/02/07 <2 <2 <4 <2 <4 <2 <3 <2 <2

• 10 <3 MEAN 4 +/- 5 4 +/- 4 9 +/- 8 4 +/- 5 9 +/- 10 4 +/- 4 7 +/- 7 4 +/- 6 4 +/- 4 27 +/- 18 9 +/- 6 G15-3 01/03/06 - 01/31/06 <5 <6 < 12 <7 < 14 <6 < 12 <8 <7 < 29 < 10 01/31/06 - 02/28/06 <6 <6 < 14 <6 < 17 <6 < 12 < 8 <7 < 33 < 11 02/28/06 - 03/28/06 <2 <3 <6 <3 <5 <3 <5 <3 <3 < 25 <8 03/28/06 - 05/02/06 <7 <:8 < 13 <7 < 19 <7 < 14 <9 <7 < 39 < 13 05/02/06 - 05/30/06 <:4 <4 < 10 <4 <9 <5 <9 <5 <4 < 43 < 14 05/30/06 - 06/26/06 <5 <6 < 12 <6 < 12 <7 <11 <"6 <6 < 31 <12 06/26/06 - 08/01/06 <2 <2 <6 <2 <4 <3 <4 <2 <2 < 44 < 14 08/01/06 - 08/29/06 <3 <4 <8 <4 <6 <3 <6 < 3 <3 < 27 <9 08/29106 - 10/03/06 <1 <2 <4 <1 <3 <2' <3 <1 <1 < 16 <5 10/03/06 - 10/31/06 <3 <3 <8 <3 <7 <4 <6 <3 <3 < 27 <9 10/31/06 - 11/28/06 <5 <5 < 11 <5 < 10 <6 <9 <4 <5 < 31 < 10 11/28/06 - 01/02/07 <2 <2 <5 <2 <5 <2 <4 <2 <2 <11 <3 MEAN 4 +/- 3 4 +/- 4 9 +/- 7 4+/-4 9+/-10 5 +/-14 8+/-7 4+/-5 4+/-4 30+/-20 10+/-6

TABLE C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 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 Q9-1 01/03/06 - 01/31/06 <7 <7 <18 <8 <17 <8 < 13 < 10 <8 <42 < 10 01/31/06 - 02/28/06 <7 <9 <16 <7 <18 <8 < 13 <9 <8 < 35 < 13 02/28/06 - 03/28/06 <6 <6 < 13 <6 <18 <7 < 10 <9 <6 < 29 < 10 03/28/06 - 05/02/06 <7 <8 < 15 <8 <17 <8 < 14 <7 <8 < 41 < 14 05/02/06 - 05/30/06 <3 <3 <8 <3 <7 <4 <6 <3 <3 < 32 < 11 05/30/06 - 06/26/06 <6 <7 < 15 <6 <13 <6 < 12 <7 <6 < 35 < 11 06/26/06 - 08/01/06 <1 <2 <5 <2 <3 <2 <4 <1 <2 < 39 < 12 08/01/06 - 08/29/06 <3 <3 <7 <3 <7 <4 <7 <3 <4 < 28 <8 08/29/06 - 10/03/06 <1 < 2 <4 <2 <3 <2 <3 <1 <2 < 17 <5 10/03/06 - 10/31/06 <3 <4 <9 <4 <8 <4 <7 <3 <4 < 30 < 10 10/31/06 - 11/28/06 <6 <5 < 12 <6 *<11 <7 < 10 <6 <6 < 40 < 14 11/28/06 - 01/02/07 <2 <2 <5 <2 <5 <2 <4 <2 <2 < 12 <4 MEAN 4 +/- 4 5 +/- 5 10 +/- 10 5 +/- 5 11 +/- 12 5 +/- 5 9 +/- 8 5 +/- 6 5 +/- 5 32 +/- 19 10 +/- 6

TABLE C-I11.1 CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION KI-1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Gross Beta 1-131 H-3 Sr-89 Sr-90 PERIOD U0/U3/0U6 U1/31/U0 < Z.Z *U.4 3920 +/- 353 01/31/06 02/28/06 4.5 +/- 1.5 < 0.7 2710 +/- 176 02/28/06 03/28/06 5.1 +/- 1.9 < 0.4 5460 +/- 581 03/28/06 05/02/06 3.4 +/- 1.8 < 0.4 < 174 05/02/06 05/30/06 4.6 +/- 1.6 < 0.5 < 189 < 5.0 < 0.7 05/30/06 06/26/06 5.1 +/- 1.8 0.8 + 0.4 < 188 06/26/06 08/01/06 7.9 +/- 2.1 < 0.9 28700 +/- 661 08/01/06 08/29/06 7.5 +/- 2.1 < 0.6 < 171 08/29/06 10/03/06 6.1 +/- 1.9 < 0.6 13800 +/- 1450 10/03/06 10/31/06 4.4 +/- 1.6 < 0.6 17300 +/- 914 10/31/06 11/28/06 4.1 +/- 1.4 < 0.7 99600 +/- 9970 < 2.2 < 0.6 11/28/06 01/02/07 2.5 +/- 1.6 < 0.5 63100 +/- 6210 MEAN 4.8 +/- 3.5 0.6 +/- 0.3 19609 +/- 62242 3.6 +/- 3.9 0.6 +/- 0.2 C-7

TABLE C-1I1.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTEE IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 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-1 34 Cs-137 Ba-140 La-140 PERIOD K1-1 01/03106 - 01/31/ 06 <8 <8 <19 < 10 < 21 < 8 < 14 <9 <10 <39 < 14 01/31106 - 02/28106 <7 <8 < 15 <6 < 16 <8 < 13 <9 <8 < 40 < 12 02128106 - 03/28/ 06 <5 <6 < 13 <7 < 15 <7 < 11 <8 <6 < 34 < 11 03/28/06 - 05/02/ 06 <6 <7 < 13 <7 < 16 <7 < 12 <7 <7 < 36 < 12 05/02/06 - 05/30/ 06 <3 <4 <8 <3 <8 <4 <7 <4 <3 < 37

• 12 05/30/06 - 06/26/ 06 <6 <6 < 12 <6 < 14 <6 < 11 <7 <6 < 35 < 10 06/26/06 - 08/01/ 06 <2 <2 <5 <2 <3 <2 <4 <2 <2

• 40 < 12 08/01/06 - 08/29/ 06 <4 <4 <7 <3 <7 <4 <7 <4 <4 < 31 < 10 08/29/06 - 10/03/ 06 <1 <2 <4 <1 <3 <2 <3 <1 <1

• 21 <7 10/03/06 - 10/31/ 06 <3 <3 <8 <3 <7 <4 <5 <3 <3 < 24 <6 10/31/06 - 11/28/ 06 <5 <5 <11 <5 < 13 <6 < 11 <5 <6 < 40 < 12 00 11/28/06 - 01/02/ 07 <3 <3 .<5 <3 <5 <3 <5 <3 <3 <13 <4 MEAN 4 +/- 4 5 +/- 5 10 +/- 9 5 +/- 5 11 +/- 12 5 +/- 4 9 +/- 8 5 +/- 5 5 +/- 5 32 +/- 17 10 +/- 6

TABLE C-IV.1 CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION H-3 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD EDCB 01/31/06 - 03/28/06 480 +/- 126 <7 <7 <13 <9 < 15 <7 <11 <7 <7 < 31 <11 05/02/06 - 06/26/06 < 188 <6 <6 <13 <7 < 14 <7 <11 <6 <7 < 34 <11 08/01/06 - 10/03/06 253 +/- 124 <2 <2 <4 <2 <3 <2 <3 <2 <2 < 18 <6 10/31/06 - 01/02/07 240 +/- 100 <2 <2 <5 <3 <5 <3 <4 <2 <2 < 12 <4 MEAN 223 +/- 351 4 +/- 5 4 +/- 5 9 +/- 9 5 +/- 7 9 +/- 12 5 +/- 5 7 +/- 8 4 +/- 5 4 +/- 5 24 +/- 21 8+/-7

TABLE C-V.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STATION CODE 03/09/06 06/08/06 09/08/06 12/09/06 MEAN II 48S 236 +/- 135 < 178 < 182 < 179

• 194 +/- 56 GP-1 305 +/- 158 (1) 196 +/- 118* 459 +/- 138* 320 +/- 264 GP-6 1220 +/- 193 530 +/- 129 319 +/- 127* < 186 564 +/- 920 GP-8 462 +/- 148 580 +/- 136 456 +/- 136" < 189 422 +/- 331 GP-9 601 +/- 158 545 +/- 129 262 +/- 123* < 188 399 +/- 409 MS-22 492 +/- 159 1080 +/- 161 964 +/- 161* 501 +/- 135* 759 +/- 614 OSF 586 +/- 157 303 +/- 125 397 +/- 133* 328 +/- 125* 404 +/- 256 OS-18 463 +/- 156 472 +/- 145 < 181 < 187

• 326 +/- 327 GP-12 (1) < 184 184 MS-2 214 +/- 123 295 +/- 124* 255 +/- 115 MS-5 < 179 < 175 177 +/- 6 MS-8 831 +/- 155 < 181 506 +/- 919 MS-20 486 +/- 131 269 +/- 124* 378 +/- 307 NW-A 1460 +/- 203 1130 +/- 182* 1295 +/- 467 NW-B 1060 +/- 166 278 +/- 124*

NW-C 3410 +/- 391 3090 +/- 369* 3250 +/- 453 NW-CW 1340 +/- 194 1050 +/- 175* 1195 +/- 410 OS-14 168 +/- 106 < 186 177 +/- 25 RW-1 330 +/- 119 < 185 258 +/- 205 RW-2 5280 +/- 570 4400 +/- 503* 4840 +/- 1245 E1-2 < 186 MS-1 1370 +/- 199 MS-4 288 +/- 126 MS-7 238 +/- 113 MS-19 < 188 MS-21 436 +/- 125 N2-1 < 174

• INDICATES DISTILLED ANALYSIS (1) SAMPLES WERE UNAVAILABLE; THE WELLS WERE DRY.

C-10

TABLE C-V.2 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Sr-90 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD 48S 03/09/06 < 0.6 <5 <6 < 14 <8 < 19 <7 <11 <9 <6 < 34 < 13 06/09/06 <4 <5 < 10 <4 < 10 <5 <9 <5 <5 < 41 < 13 09/08/06 <2 <2 <4 < 1 <3 <2 <3 <1 <1 < 12 <4 12/10/06 <7 <6 < 13 <8 < 11 <7 <11 <6 <6 < 31 < 11 MEAN 5 4 5 4 10 +/- 9 5 +/- 6 11 +/- 13 5 5 8+/-8 5+/-6 5 +/-4 30 +/- 25 10 +/- 9 OSF 03/09/06 < 0.6 <5 <5 < 13 <5 < 20 <7 <11 < 11 <6 < 33 < 13 06/09/06 <5 <6 < 12 <5 < 11 <6 < 10 <6 <5 < 49 < 15 09/08/06 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 15 <6 12/10/06 <4 <6 < 11 <6 < 13 <8 < 11 <5 <5 < 36 < 13 MEAN 4 3 5 4 10 +/- 7 5 +/- 4 12 +/- 13 6 +/-5 9+/-7 6+/-7 5 3 33 +/- 28 12 +/- 8 El-2 06/06/06 <3 <4 <8 <3 <7 <4 <7 <4 <4 < 26 <9 MS-2 06/08/06 < 0.4 <1 <2 <4 <1 <2 <2 <3 <1 <1 < 13 <3 MS-5 06/08/06 < 0.5 < 0.3 < 0.5 <1 < 0.3 <1 < 0.5 <1 < 0.3 < 0.4 < 12 <3 MS-8 06/08/06 < 0.7 < 0.4 <1 <1 < 0.3 <1 <1 <1 < 0.3 < 0.4 < 12 <4 MS-20 06/08/06 < 0.4 <1 <1 < 0.4 <1 <1 <1 < 0.3 < 0.4 < 11 <4 MS-22 03/09/06 <1 <1 <3 <1 <2 <1 <2 <1 <9 < 12 <4 N2-1 06/06/06 <4 <5 < 10 <4 < 10 <5 <8 <5 <5 < 35 < 11 OS-14 06/09/06 < 0.7 < 0.4 < 0.4 <1 < 0.3 <1 <1 <1 < 0.3 < 0.3 < 11 <3 RW-1 06/08/06 < 0.4 <1 <1 < 0.4 <1 <1 <1 < 0.4 < 0.4 < 12 <4 RW-2 06/08/06 < 0.4 <1 <1 < 0.4 <1 <1 <1 < 0.3 < 0.4 < 13 <4

TABLE C-VI.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR & BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Sr-89 Sr-90 PERIOD INDP PREDATOR 06/15/06 < 32 <3 11/14/06 <5 <4 MEAN 19 +/- 39 4++/-2 INDB BOTTOM FEEDER 06/09/06 < 25 <1 11/06/06 <5 <5 MEAN 15 +/- 28 3+/-_5 BKGP PREDATOR 06/12/06 < 34 <4 10/05/06 <5 <4 MEAN 19 +/- 40 4-+/-1 BKGB BOTTOM FEEDER 06/12/06 < 18 <2 10/05/06 <5 <4 MEAN 12 +/- 19 3-+/-2 C- 12

TABLE C-VI.2 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR & BOTTOM FEEDER (FISH)

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-1 34 Cs-1 37 PERIOD INDP PREDATOR 06/15 - 06/15/2006 3910 +/- 802 < 62 <84 < 198 < 93 < 210 < 82 < 83 11/14 - 11/14/2006 3100 +/- 781 < 45 < 45 < 113 < 28 < 63 < 38 < 46 MEAN 3505 +/- 1146 54 +/- 25 65 +/- 54 156 +/- 120 60 +/- 92 137 +/- 207 60 +/- 63 64 +/- 52 INDB BOTTOM FEEDER 06/09 - 06/09/2006 3560 +/- 994 < 66 < 87 < 193 < 58 < 170 < 84 < 78 11/06 - 11/06/2006 3250 +/- 719 < 52 < 65 < 132 < 49 < 101 < 57 < 50 MEAN 3405 +/- 438 59 +/- 20 76 +/- 31 163 +/- 86 53 +/- 12 136 +/- 98 70 +/- 39 64 +/- 40 BKGP PREDATOR I~ 06/12 - 06/12/2006 3790 +/- 987 < 74 < 86 < 210 < 77 < 195 < 87 < 88 10/05 - 10/05/2006 3820 +/- 943 < 66 < 79 < 204 < 58 < 117 < 55 < 55 MEAN 3805 +/- 42 70 +/- 11 82 +/- 10 207 +/- 8 68 +/- 27 156 +/- 110 71 +/- 44 72 +/- 46 BKGB BOTTOM FEEDER 06/12 - 06/12/2006 2440 +/- 642 < 83 < 93 < 184 < 70 < 192 < 91 < 82 10/05 - 10/05/2006 2480 +/- 1070 < 71 < 79 < 253 < 74 < 112 < 67 < 77 MEAN 2460 +/- 57 77 +/- 17 86 +/- 21 219 +/- 98 72 +/- 5 152 +/- 113 79 +/- 33 80 +/- 8

TABLE C-VII.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-1 34 Cs-1 37 PERIOD Al-3 06/09/06 14200 +/- 1220 < 104 < 118 < 103 < 138 < 104 10/10/06 13400 +/- 2290 < 123 < 82 < 109 < 105 < 155 MEAN 13800 +/- 1131 114 +/- 27 100 +/- 51 106 +/- 8 122 +/- 47 130 +/- 72 J2-1 06/09/06 19800 +/- 1750 < 122 < 146 < 109 < 132 < 120 10/10/06 19600 +/- 2840 < 121 < 160 < 136 < 136 < 147 MEAN 19700 +/- 283 122 +/- 1 153 +/- 20 123 + 38 134 +/- 6 134 +/- 38 K1-3 06/09/06 12800 +/- 1230 < 89 < 93 < 81 < 129 < 84 10/10/06 12600 +/- 2190 < 97 < 136 < 124 < 102 < 107 MEAN 12700 +/- 283 93 +/- 11 115 +/- 60 103 +/- 61 116 +/- 38 96 +/- 33 EDCB 10/10/06 15400 +/- 1580 < 83 < 107 < 109 < 79 219 +/- 87 C- 14

TABLE C-VIII.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I GROUP II I GROUP III COLLECTION El-2 Fl-3 A3-1 G2-1 H3-1 M2-1 Q15-1 PERIOD 12/28/05 - 01/04 /06 15 1 5 19- 5 12 -5 18 +/- 5 15 +/- 5 01/04/06 - 01/11 /06 20 +/- 5 18+/- 5 18 -5 22 +/- 5 13 +/- 5 01/11/06 - 01/18 /06 17 +/- 5 16- 5 20 -5 20 +/- 9 17 +/- 5 01/18/06 - 01/25 /06 21 +/- 5 17+/- 5 16 -5 13 +/- 5 15+/- 5 01/25/06 02/01 /06 15 +/- 5 20 +/--5 18 -5 22 +/- 5 20+/- 5 02/01/06 - 02/08 /06 20 +/- 5 19- 5 17 -5 19+/- 5 17 +/--5 02/08/06 - 02/15 /06 17 +/- 5 13- 5 17 -5 16 +/-5 16+/- 5 02/15/06 - 02/22//06 24 +/- 5 27 +/- 5 22 -5 21 +/-5 27 +/-5 02/22/06 - 03/01 /06 14 +/- 5 15 +/- 5 16 -5 14+/- 5 18+/- 6 03/01/06 - 03/08 /06 11 +/-5 (1) 14 +/-5 10 +/-5 11 +/--5 03/08/06 - 03/15 /06 14 +/-5 14- 5 15 -5 17+/- 5 17+/- 5 03/15/06 - 03/22//06 14 +/-5 < 21 15 +/-5 11 +/-5 11 +/--5 03/22/06 - 03/29 /06 11 +/-4 11+/- 5 9 -5 10 5 15+/- 5 03/29/06 - 04/05 /06 15 4 27 +/-8 20 +/-5 18+/- 5 19+/- 5 04/05/06 - 04/12 /06 14 +5 < 16 13 +/-5 17+/- 5 18+/- 5 04/12/06 - 04/19 /06 11 +5 17+/- 5 (1) 14+/- 5 12+/- 5 04/19/06 - 04/25 /06 9+/-5 <9 12 +5 <7 12+/- 5 04/25/06 - 05/02 /06 7+/-4 (1) 8 +/-5 13 +/-5 10+/- 5 05/02/06 - 05/10//06 16 +/-4 13- 5 17 -5 13 +/-5 12+/- 5 05/10/06 - 05/17./06 7+/-4 <8 <7 <7 8 -5 8+/-5 05/17/06 - 05/24 /06 9+/-4 <7 9 -5 <6 <6 <6 05/24/06 - 05/31./06 18 5 22 +/--5 19 -5 21 +/- 5 21 +/-5 05/31/06 - 06/07./06 13+/- 5 14- 5 11 -5 15 +/- 5 13+/- 5 06/07/06 - 06/14./06 9+/-4 9+/-4 14 +/-6 12 +/- 5 10 +/- 5 06/14/06 - 06/21./06 24 +/-5 22+/- 5 (1) 19 +/- 5 18 +/- 5 06/21/06 - 06/27./06 14+/- 5 31 +/--6 18 +/-6 13 +/- 5 13 +/- 5 06/27/06 - 07/04./06 18 5 17+/- 5 22 +/-6 19 +/- 5 18 +/- 5 07/04/06 - 07/12//06 26 +/-4 27 4 25 -5 26 +/- 4 27 +/- 4 07/12/06 - 07/19./06 22 +/- 5 29- 6 (1) 22 +/- 5 29 +/- 6 07/19/06 - 07/26./06 18 +/- 5 19- 5 (1) 20 +/- 6 18 +/- 5 07/26/06 - 08/02 /06 25 +/- 6 26+/- 6 (1) 27 +/- 6 30 +/- 6 08/02/06 - 08/09 /06 22 +/- 5 18- 5 23 +/-5 20 +/- 5 22 +/- 5 08/09/06 - 08/16./06 23 +/-5 20 +5 26 -7 17 +/- 5 22 +/- 5 08/16/06 - 08/23 /06 19+/- 5 17+/- 5 19 +/-5 20 +/- 5 17 +/- 5 08/23/06 - 08/30 /06 21 +5 26+/- 6 27 +/-6 22 +/- 5 19 +/- 5 08/30/06 - 09/06./06 9+/-5 10+/- 5 10 -5 13 +/- 5 9+/-5 09/06/06 - 09/13 /06 23 +/-5 26 +/-6 14 +/-5 19 +/- 5 22 +/--5 09/13/06 - 09/20./06 20 +/-5 21 +/--5 13 -5 16 +/- 5 20 +/--5 09/20/06 - 09/27./06 15 5 21 +/--5 16 -5 18 +/- 5 19+/- 5 09/27/06 - 10/04./06 15 5 22- 5 18 +/-5 20 +/- 5 22 +/--5 10/04/06 - 10/11. /06 18+/- 5 18+/- 5 13 -5 16+/- 5 21 +/- 6 10/11/06 - 10/18./06 19 5 18+/- 5 20 -5 17+/- 5 18 +/- 5 10/18/06 - 10/25./06 21 +/-5 17+/- 5 9 -5 16 +/-5 15+/- 5 10/25/06 - 10/31. /06 9+/-5 15 +/- 5 8 -5 12+/- 5 8+/-5 10/31/06 - 11/07 /06 25 +5 23 +/- 5 21 -5 26 +/--5 25 +/--5 11/07/06 - 11/15./06 15 5 16 +/- 5 17 -5 13 +/- 4 14+/- 5 11/15/06 - 11/21. /06 17 +/- 6 10 +/- 5 16 +/-6 13 +/- 6 21 +/--6 11/21/06 - 11/28./06 25 +/- 5 28 +/- 6 18 -5 23 +/- 5 34 +/- 6 11/28/06 - 12/06./06 26 +/- 5 28 +/--5 29 -5 27 +/- 5 27 +/- 5 12/06/06 - 12/12 /06 29 +/- 6 23 +/--6 25 +/-6 24 +/- 6 24 +/- 6 12/12/06 - 12/20./06 24 +/- 5 23+/- 5 27 +/--5 20 +/- 5 24 +/- 5 12/20/06 - 12/27//06 23 +/- 5 17+/- 5 19 +/--5 18 +/- 5 20 +/- 5 12/27/06 - 01/03./07 18 +/- 5 19+/- 5 23 +/--5 18 +/- 5 26 +/- 5 MEAN 17 +/- 11 17 +/- 11 19 +/- 12 17 +/- 11 18 +/- 11 17 +/- 10 18 +/- 12 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15

TABLE C-VIII.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS (E-3 PCIiCU METER) IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 GROUP I - CLOSEST TO THE SITE BOUNDARY GROUP I - INTERMEDIATE OFFSITE GROUP III- CONTROL LOCATIONS COLLECTION MIN. MAX. MEAN + COLLECTION MIN. MAX. MEAN+/- COLLECTION MIN. MAX. MEAN +

PERIOD 2 SD PERIOD 2 SD PERIOD 2 SD IU I 0 DU;,- U4-IUII U I=1" LI 4 1 It I1 +/----.b ILILOIUD - UzIU IIUO II LL i1 -- 12/28/05 - 02/01/06 13 20 16 +/- 5 02/01/06 - 03/01/06 14 24 18 +6 02/01/06 03/01/06 13 27 18 8 02/01/06 03/01/06 16 27 20 +/- 10 03/01/06 - 03/29/06 10 15 12 +4 03/01/06 03/29/06 <9 21 14 7 03/01/06 03/29/06 11 17 14 +/- 6 03/29/06 - 05/02/06 7 18 12 +7 03/29/06 05/02/06 <7 27 14 10 03/29/06 05/02/06 10 19 14 +/- 8 05/02/06 - 05/31/06 7 24 13 +13 05/02/06 05/31/06 <6 22 12 12 05/02/06 05/31/06 <6 21 12 +/- 13 05/31/06 - 06/27/06 9 24 14 +11 05/31/06 06/27/06 9 31 15 11 05/31/06 06/27/06 10 18 13 +/- 7 06/27/06 - 08102/06 16 28 22 +/-8 06/27/06 08/02/06 17 34 24 9 06/27/06 08/02/06 18 30 25 +/- 12 08/02/06 - 08/30/06 18 25 21 +4 08/02/06 08/30/06 14 27 20 7 08/02/06 08/30/06 17 22 20 +/- 5 08/30/06 - 09/27/06 9 24 17 +11 08/30/06 09/27/06 9 26 17 10 08/30/06 09/27/06 9 22 17 +/- 11 09/27/06 - 10131/06 9 21 17 +/-8 09/27/06 10/31/06 8 22 16 7 09/27/06 10/31/06 8 22 17 +/- 12 10/31/06 - 11/28/06 14 25 20 +10 10/31/06 11/28/06 10 28 19 12 10/31/06 11/28/06 14 34 24 +/- 17 11/28/06 - 01/03/07 18 29 24 +/-8 11/28/06 01/03/07 17 29 23 7 11/28/06 01/03/07 20 27 24 +/- 6 12/28/05 - 01/03/07 7 29 17 +/--8 12/28/05 - 01/03/07 < 6 34 18 +/- 7 12/28/05 - 01/03/07 < 6 34 18 +/- 9

TABLE C-VIII.3 CONCENTRATION OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLEE COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD A3-1 12/28 -03/29/06 < 96 < 4 < 2 < 4 < 3 < 4 03/29 -06/27/06 96 +/- 71 < 3 < 10 < 3 < 3 < 3 06/27 -09/27/06 84 +/- 27 < 2 < 3 < 3 < 2 < 2 09/27 -01/03/07 53 +/- 18 < 1 < 2 < 1 < 1 < 2 MEAN 82+/-41 3 +/- 3 4 +/- 8 3 +/- 2 2 +/- 2 3 +/- 2 El-2 12/28 -03/29/06 < 62 < 4 < 8 < 4 < 3 < 3 03/29 -06/27/06 < 97 < 3 < 6 < 3 < 2 < 2 06/27 -09/27/06 66 +/- 39 < 2 < 3 < 2 < 2 < 2 09/27 -01/03/07 64 +/- 19 < 3 < 2 < 2 < 3 < 2 MEAN 72 +/- 33 3 +/- 2 5 +/-6 3 +/- 2 3 +/- 2 2 +/- 1 F1-3 12/28 - 03/29/06 118 +/- 53 < 5 < 9 < 4 < 3 < 4 03/29 -06/27/06 < 93 < 2 < 4 < 2 < 1 < 2 06/27 -09/27/06 74 +/- 25 < 1 < 3 < 2 < 2 < 1 09/27 -01/03/07 47 +/- 19 < 2 < 3 < 2 < 3 < 3 MEAN 83 +/-60 3 +/- 3 5 +/-6 2 +/- 2 2 +/- 1 2 +/- 3 G2-1 12/28 -03/29/06 114 +/- 50 < 6 < 7 < 6 < 4 < 5 03/29 -06/27/06 < 106 < 3 < 8 < 3 < 2 < 3 06/27 -09/27/06 95 +/- 46 < 3 < 5 <4 < 3 < 2 09/27 -01/03/07 42 +/- 33 < 3 < 3 < 3 < 3 < 3 MEAN 89 +/-65 4 +/- 3 6 4 4 +/- 3 3 +/- 2 3 +/- 3 H3-1 12/28 -03/29/06 < 110 < 4 < 7 < 4 < 4 < 2 03/29 -06/27/06 143 +/- 52 < 3 < 7 < 3 < 2 < 2 06127 -09/27/06 88 +/- 33 < 2 < 3 < 2 < 2 < 2 09/27 -01/03/07 61 +/- 19 < 2 < 3 < 3 < 2 < 3 MEAN 101 +/- 69 3 +/- 2 5 +/- 5 3 +/- 2 3 +/- 2 2 +/- 1 M2-1 12/28 -03/29/06 < 85 < 6 < 9 < 8 < 4 < 4 03/29 -06/27/06 < 22 < 2 < 2 < 3 < 2 < 2 06/27 -09/27/06 80 +/- 28 < 3 < 3 < 3 < 2 < 2 09/27 -01/03/07 64 +/- 23 < 2 < 3 < 3 < 2 < 2 MEAN 63 +/-57 3 +/-4 4 +/-7 4 +/- 5 2 +/- 2 3 +/-2 Q15-1 12/28 -03/29/06 84 +/- 48 < 6 < 9 < 7 < 3 < 5 03/29 -06/27/06 < 94 < 3 < 5 < 4 < 2 < 2 06/27 -09/27/06 83 +/- 37 < 3 < 3 < 3 < 2 < 2 09/27 -01/03/07 55 +/- 20 < 2 < 2 < 3 < 2 < 2 MEAN 79 +/- 33 3 +/- 4 5 +/-6 4 +/- 4 2 +/- 1 3 +/- 3 C- 17

TABLE C-IX.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUPI I GROUPII GROUPIII COLLECTION E1-2 F1-3 A3-1 G2-1 H3-1 M2-1 Q15-1 PERIOD 12-28/05 - 01/04/06 < 23 < 23 < 21.4 < 25 < 24. < 21 < 22 01/04/06 - 01/11/06 < 31 < 31 < 32.9 < 33 < 31 < 33 < 34 01/11/06 - 01/18/06 < 32 < 32 < 25.2 < 34 < 33 < 53 < 26 01/18/06 - 01/25/06 < 32 < 31 < 37.7 < 34 < 18 < 44 < 39 01/25/06 - 02/01/06 < 38 < 37 < 32.3 < 40 < 38 < 33 < 33 02/01/06 - 02/08/06 < 30 < 30 < 30.7 < 32 < 30 < 31 < 31 02/08/06 - 02/15/06 < 51 < 50 < 41.3 < 54 < 51 < 37 < 37 02/15/06 - 02/22/06 < 28 < 28 < 24.8 < 30 < 28 < 25 < 25 02/22/06 - 03/01/06 < 39 < 38 < 44.5 < 41 < 39 < 45 < 45 03/01/06 - 03/08/06 < 40 < 39 (1) < 42 < 40 < 44 < 44 03/08/06 - 03/15/06 < 23 < 23 < 31.1 < 24 < 23 < 31 < 32 03/15/06 - 03/22/06 < 37 < 37 < 104 (1) < 39 < 21 < 33 < 34 03/22/06 - 03/29/06 < 44 < 43 < 55.1 < 46 < 44 < 56 < 56 03/29/06 - 04/05/06 < 26 < 25 < 55.1 < 27 < 32 < 34 < 34 04/05/06 - 04/12/06 < 45 < 44 < 69.1 < 47 < 45 < 27 < 28 04/12/06 - 04/19/06 < 44 < 44 < 39.9 (1) < 45 < 41 < 41 04/19/06 - 04/25/06 < 48 < 47 < 48.1 < 51 < 48 < 38 < 39 04/25/06 - 05/02/06 < 33 < 33 (1) < 35 < 48 < 49 < 50 05/02/06 - 05/10/06 < 52 < 51 < 48.3 < 41 < 52 < 43 < 44 05/10/06 - 05/17/06 < 47 < 47 < 61.2 < 50 < 48 < 56 < 56 05/17/06 - 05/24/06 < 63 < 62 < 66.5 < 69 < 65 < 59 < 60 05/24/06 - 05/31/06 < 58 < 57 < 59.5 < 61 < 57 < 60 < 61 05/31/06 -06/07/06 < 65 < 64 < 63.1 < 69 < 62 < 63 < 64 06/07/06 - 06/14/06 < 52 < 51 < 62.3 < 56 < 52 < 63 < 64 06/14/06 - 06/21/06 < 45 < 44 < 42.9 (1) < 45 < 43 < 44 06/21106 - 06/27/06 < 39 < 30 < 48.9 < 41 < 38 < 39 < 49 06/27/06 -07/04/06 < 38 < 38 < 57 < 40 < 38 < 58 < 59 07/04/06 - 07/12/06 < 35 < 43 < 39.9 < 55 < 44 < 40 < 40 07/12/06 - 07/19/06 < 68 < 68 < 60.9 (1) < 70 < 62 < 61 07/19/06 - 07/26/06 < 63 < 63 < 67.1 (1) < 63 < 66 < 66 07/26/06 - 08/02/06 < 44 < 44 < 48.1 (1) < 45 < 49 < 48 08/02/06 - 08/09/06 < 38 < 38 < 33.8 < 40 < 43 < 42 < 42 08/09/06 - 08/16/06 < 45 < 45 < 46.5 < 63 < 46 < 47 < 46 08/16/06 - 08/23/06 < 34 < 27 < 46 < 34 < 47 < 46 < 45 08/23/06 -08/30/06 < 56 < 55 < 55 < 57 < 57 < 55 < 54 08/30/06 - 09/06/06 < 60 < 60 < 69.5 < 61 < 60 < 70 < 69 09/06/06 - 09/13/06 < 64 < 64 < 51.2 < 66 < 65 < 52 < 51 09/13/06 - 09/20/06 < 38 < 38 < 38.3 < 39 < 39 < 38 < 38 09/20/06 - 09/27/06 < 68 < 68 < 63.9 < 70 < 65 < 64 < 64 09/27/06 - 10/04/06 < 35 < 34 < 34.4 < 35 < 30 < 30 < 29 10/04/06 - 10/11/06 < 59 < 58 < 64.5 < 60 < 59 < 65 < 64 10/11/06 - 10/18/06 < 48 < 48 < 62.7 < 49 < 63 < 63 < 62 10/18/06 - 10/25/06 < 48 < 47 < 63.8 < 49 < 39 < 47 < 63 10/25/06 - 10/31/06 < 53 < 53 < 68 < 54 < 53 < 68 < 67 10/31/06 - 11/07/06 < 47 < 47 < 51.4 < 48 < 52 < 52 < 51 11/07/06 - 11/15/06 < 32 < 32 < 29.3 < 33 < 30 < 29 < 29 11/15/06 - 11/21/06 < 69 < 68 < 65.8 < 70 < 69 < 66 < 65 11/21/06 - 11/28/06 < 57 < 57 < 47 < 58 < 57 < 49 < 48 11/28/06 - 12/06/06 < 38 < 38 < 40.3 < 29 < 39 < 39 < 39 12/06/06 - 12/12/06 < 57 < 57 < 66.9 < 59 < 58 < 67 < 66 12/12/06 - 12/20/06 < 35 <35 < 15 < 31 < 30 < 30 < 30 12/20/06 - 12/27/06 < 43 < 42 < 39.8 < 43 < 41 < 40 < 39 12/27/06 - 01/03/07 < 35 < 34 < 42.9 < 35 < 35 < 43 < 43 MEAN 45 +/- 25 44 +/- 25 49 +/- 33 46 +/- 26 45 +/- 26 47 +/- 26 47 +/- 27 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-18

TABLE C-X.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDICATOR FARMS COLLECTION K15-3 D2-1 E2-2 F4-1 G2-1 PERIOD 01/04/06 < 0.4 < 0.3 < 0.4 < 0.4 02/01/06 < 0.3 < 0.2 < 0.4 < 0.3 03/01/06 < 0.6 < 0.3 < 0.6 < 0.5 03/15/06 < 0.6 < 0.3 < 0.6 < 0.4 03/29/06 < 0.6 < 0.5 < 0.4 < 0.3 < 0.4 04/12/06 < 0.6 < 1.0 < 0.9 < 0.9 04/26/06 < 0.5 < 0.3 < 0.6 < 0.5 05/10/06 < 0.4 < 0.4 < 0.4 < 0.4 05/24/06 < 0.3 < 0.4 < 0.2 < 0.2 06/07/06 < 1.8 (1) < 1.0 < 1.2 (1) < 1.2 (1) 06/21/06 < 0.8 < 0.8 < 0.9 < 0.7 < 1.2 (1) 07/05/06 < 0.5 < 0.4 < 0.6 < 0.4 07/19/06 < 0.6 < 0.7 < 0.6 < 0.8 08/02/06 < 0.7 < 0.6 < 0.6 < 0.6 08/16/06 < 0.3 < 0.3 < 0.5 < 0.4 08/30/06 < 0.4 < 0.8 < 0.6 < 0.4 09/13/06 < 0.2 < 0.2 < 0.2 < 0.2 09/27/06 < 0.5 < 0.3 < 0.3 < 0.4 < 0.4 10/11/06 < 0.6 < 0.5 < 0.5 < 0.5 10/25/06 < 0.6 < 0.4 < 0.7 < 0.5 11/07/06 < 0.4 < 0.6 < 0.5 < 0.6 11/21/06 < 0.9 < 0.8 < 0.7 < 0.6 12/06/06 < 0.4 < 0.3 < 0.4 < 0.4 < 0.3 MEAN 0.6 +/- 0.5 0.5 +/- 0.4 0.6 +/- 0.4 0.5 +/- 0.5 0.5 +/- 0.5 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C- 19

TABLE C-X.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDI CATOR FARMS COLLECTION K15-3 D2-1 E2-2 f-4-1 G2-1 PERIOD Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 01/04/06 - 03/29/06 < 3.5 < 0.8 < 3.4 < 0.8 < 3.9 < 0.9 < 1.5 1.0 +/- 0.4 < 3.9

• 0.8 03/29/06 - 06/21/06 < 2.9 < 0.6 < 4.4 2.9 + 0.6 < 3.8 1.2 +/- 0.5 < 5.0 < 0.8 *<3.1 0.6 0.3 07105/06 - 09/27106 < 3.8 < 0.8 < 2.9 < 0.5 < 3.7 0.8 +/-.0.5 < 4.6 0.9

• 0.6 < 4.7

• 0.8 10/11106 - 12/06/06 < 2.6 0.5 +/- 0.3 < 4.5 < 0.7 < 3.7 < 0.5 < 4.5 0.9 +/- 0.5 < 4.0 < 0.6 MEAN 3.2 +/- 1.1 0.7 +/- 0.3 3.8 +/- 1.6 1.2 -2.3 3.8 +/- 0.2 0.9 +/- 0.6 3.9 +/- 3.2 0.9 - 0.1 3.9 +/- 1.3 0.7 + 0.3 t'J

TABLE C-X.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD D2-1 01/04/06 1310 +/- 150 < 4 < 4 < 19 <4 02/01/06 1240 +/- 138 < 9 < 8 < 32 < 9 03/01/06 1220 +/- 138 < 9 < 8 < 33 < 11 03/15/06 1370 +/- 158 < 10 < 9 < 37 < 12 03/29/06 1380 +/- 207 < 11 < 13 < 42 < 13 04/12/06 1310 +/- 49.6 < 3 < 3 < 13 < 4 04/26/06 1140 +/- 138 < 9 < 9 < 35 < 12 05/10/06 1220 +/- 150 < 10 < 9 < 42 < 13 05/24/06 1510 +/- 66.8 < 4 < 4 < 40 < 12 06/07/06 1240 +/- 73.9 < 4 < 4 < 37 < 11 06/21/06 1200 +/- 119 < 10 < 10 < 43 < 14 07/05/06 1280 +/- 177 < 13 < 11 < 42 < 15 07/19/06 1350 +/- 157 < 8 < 8 < 39 < 11 08/02/06 1400 +/- 148 < 6 < 6 < 35 < 8 08/16/06 1490 +/- 203 < 8 < 9 < 42 < 10 08/30/06 1420 +/- 196 < 7 < 9 < 39 < 10 09/13/06 1160 +/- 137 < 6 < 6 < 30 < 12 09/27/06 1200 +/- 121 < 4 < 6 < 25 < 6 10/11/06 1220 +/- 109 < 4 < 4 < 48 < 13 10/25/06 1360 +/- 105 < 4 < 4 < 44 < 15 11/07/06 1390 +/- 113 < 3 < 3 < 53 < 15 11/21/06 1310 +/- 124 < 3 < 4 < 43 < 14 12/06/06 1390 +/- 148 < 5 < 5 < 27 < 11 MEAN 1309 +/- 204 7 +/- 6 7 +/- 6 36 +/- 19 11 +/- 6 E2-2 01/04/06 1260 +/- 144 < 10 < 9 < 37 < 11 02/01/06 1170 +/- 142 < 10 < 10 < 37 < 11 03/01/06 1270 +/- 136 < 8 < 7 < 29 < 8 03/15/06 1280 +/- 137 < 10 < 9 < 39 < 13 03/29/06 1280 +/- 156 < 10 < 9 < 38 < 14 04/12/06 1270 +/- 43.3 < 3 < 2 < 11 < 3 04/26/06 1120 +/- 134 < 10 < 9 < 36 < 11 05/10/06 1290 +/- 134 < 11 < 9 < 40 < 14 05/24/06 1340 +/- 62 < 4 < 4 < 34 < 10 06/07/06 1400 +/- 76.6 < 4 < 4 < 39 < 12 06/21/06 1450 +/- 161 < 9 < 10 < 46 < 14 07/05/06 1410 +/- 212 < 14 < 12 < 57 < 11 07/19/06 1430 +/- 137 < 8 < 8 < 39 < 13 08/02/06 1400 +/- 140 < 5 < 6 < 34 < 12 08/16/06 1070 +/- 165 < 7 < 8 < 35 < 14 08/30/06 1260 +/- 160 < 7 < 7 < 41 < 14 09/13/06 1340 +/- 141 < 5 < 7 < 33 < 11 09/27/06 1160 +/- 159 < 6 < 7 < 28 < 10 10/11/06 1360 +/- 116 < 4 < 4 < 49 < 15 10/25/06 1390 +/- 146 < 5 < 6 < 59 < 14 11/07/06 1340 +/- 109 < 4 < 4 < 60 < 14 11/21/06 1390 +/- 96.7 < 4 < 4 < 44 < 15 12/06/06 1150 +/- 156 < 6 < 7 < 43 < 12 MEAN 1297 +/- 212 7 +/- 6 7 +/- 5 39 +/- 21 12 +/- 5 C-21

TABLE C-X.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD F4-1 03/29/06 1480 +/- 189 < 11 <11 < 44 *13 06/21/06 1390 +/- 172 < 11 < 10 < 49 < 12 09/27/06 1350 +/- 149 < 6 <8 < 34 <7 12/06/06 1230 +/- 191 < 7 <7 < 40 < 13 MEAN 1363 +/- 207 9 +/- 6 9+/-4 42 +/- 12 11 +/- 6 G2-1 01/04/06 1170 +/- 126 <9 <8 < 30 < 10 02/01/06 1170 +/- 157 < 13 < 10 < 43 < 13 03/01/06 1250 +/- 149 < 10 < 11 < 44 < 12 03/15/06 1220 +/- 127 <8 <8 < 33 <9 03/29/06 1310 +/- 165 < 11 <9 < 44 < 13 04/12/06 1230 +/- 47.7 <3 <3 < 13 <4 04/26/06 1220 +/- 127 <9 <8 < 32 <9 05/10/06 1220 +/- 52.2 <3 <3 < 29 <9 05/24/06 1150 +/- 62.8 <3 <4 < 33 < 11 06/07/06 1270 +/- 73.4 <4 <4 < 35 < 10 06/21/06 1260 +/- 148 <9 <9 < 40 < 14 07/05/06 1470 +/- 144 < 10 <8 < 35 < 10 07/19/06 1280 +/- 123 <8 <7 < 36 < 13 08/02/06 1310 +/- 203 <8 <8 < 59 < 14 08/16/06 1440 +/- 195 <7 <8 < 28 <7 08/30/06 1270 +/- 167 <6 <8 < 36 <8 09/13/06 1260 +/- 134 <5 <7 < 37 < 10 09/27/06 1340 +/- 193 <6 <8 < 25 <9 10/11/06 1320 +/- 130 <5 <6 < 53 < 14 10/25/06 1250 +/- 104 <3 <4 < 40 < 15 11/07/06 1110 +/- 101 <4 <4 < 58 < 14 11/21/06 1290 +/- 107 <3 <4 < 46 < 14 12/06/06 1310 +/- 142 <5 <6 < 31 < 10 MEAN 1264 +/- 169 7 +/- 6 7 +/-5 38 +/- 21 11 +/-6 K1 5-3 01/04/06 1300 +/- 150 < 10 <9 < 34 <11 02/01/06 1370 +/- 130 <8 <7 < 31 <9 03/01/06 1530 +/- 136 <9 <8 < 34 <7 03/15/06 1270 +/- 150 < 11 <9 < 39 < 12 03/29/06 1410 +/- 191 < 12 < 12 < 41 <13 04/12/06 1350 +/- 41.4 <2 <2 <9 <3 04/26/06 1480 +/- 144 < 10 <9 < 38 < 12 05/10/06 1430 +/- 139 <8 <9 < 40 < 13 05/24/06 1310 +/- 80.8 <5 <4 < 40 < 11 06/07/06 1270 +/- 85.3 <4 <4 < 36 < 10 06/21/06 1410 +/- 201 < 12 <11 < 50 < 15 07/05/06 1500 +/- 141 < 11 < 11 < 44 < 14 07/19/06 1330 +/- 91 <4 <5 < 22 <7 08/02/06 1220 +/- 221 <9 <9 < 57 < 12 08/16/06 1280 +/- 181 <6 <7 < 33 <9 08/30/06 1400 +/- 151 <6 <8 < 34 < 11 09/13/06 1380 +/- 145 <6 <6 < 41 < 11 09/27/06 1280 +/- 162 <6 <6 < 30 <8 10/11/06 1300 +/- 113 <4 <4 < 48 < 15 10/25/06 1340 +/- 109 <3 <4 < 38 < 12 11/07/06 1300 +/- 101 <4 <4 < 57 < 14 11/21/06 1290 +/- 107 <4 <5 < 44 < 15 12/06/06 1300 +/- 135 <6 <6 < 30 <7 MEAN 1350 +/- 162 7 +/- 6 7+/-5 38 +/- 21 11 +/- 6 C -22

TABLE C-XI.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Sr-90 K-40 1-131 Cs-134 Cs-137 PERIOD B10-2 07/27/06 2270 +/- 115 < 40 < 5 <5 Tomatoes B10-2 07/27/06 2250 +/- 86 < 27 < 3 < 4 Sweet Corn B10-2 08/10/06 < 3 3120 +/- 365 < 32 < 18 < 20 Corn Leaf B10-2 08/21/06 3870 +/- 142 < 56 < 3 < 4 Red Beets MEAN 2878 +/- 1552 39 +/- 25 7 + 14 8 + 16 E1-2 07/27/06 2240 +/- 93.7 < 33 < 4 < 4 Tomatoes E1-2 07/27/06 2820 +/- 122 < 40 < 5 < 5 Sweet Corn E1-2 08/10/06 < 2 5060 +/- 147 < 30 < 5 < 5 Corn Leaf MEAN 3373 +/-+2978 34 +/- 10 5 +/- 1 5 +/- 1 H1-2 08/21/06 4830 +/- 141 < 55 < 3 < 3 Red Beets MEAN 4830 55 3 3 ESE1 10/10/06 < 3 6710 +/- 727 < 58 < 19 < 31 Elephant Ear Leaves ESE2 10/10/06 1860 +/- 416 < 48 < 18 < 22 Grape Leaves ESE3 10/10/06 6 +/- 3 6300 +/- 538 < 46 < 18 < 20 MEAN 5 + 3 4957 +/- 5379 51 +/- 13 18 +/- 2 24 +/- .12 C -23

TABLE C-XII.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH STATION MEAN 01/13 - 04/14/06 04/14 - 07/14/06 07/14 - 10/21/06 10/21 - 01/12/07 CODE +/-2S. D.

Al-4 5.4 +/- 0.8 5.3 5.0 5.9 5.3 A3-1 6.1 +/- 0.6 5.7 6.1 6.4 6.0 A5-1 6.6 +/- 0.5 6.9 6.5 6.7 6.3 A9-3 5.6 +/- 0.4 5.4 5.5 5.9 5.7 B1-1 5.7 +/- 0.4 5.4 5.6 5.9 5.8 B1-2 5.6 +/- 0.3 5.5 5.6 5.8 5.6 B2-1 5.6 +/- 0.3 5.4 5.6 5.8 5.6 B5-1 6.5 +/- 0.7 6.3 6.3 7.0 6.4 B10-1 6.2 +/- 0.9 5.9 5.8 6.8 6.2 Cl-i 6.2 +/- 0.9 6.0 5.8 6.8 6.1 Cl-2 5.5 +/- 0.6 5.2 5.2 5.8 5.7 C2-1 6.4 +/- 1.8 6.1 5.8 7.7 5.9 C5-1 6.5 +/- 0.9 6.1 6.4 7.1 6.2 C8-1 6.7 +/- 0.7 6.4 6.6 7.2 6.5 D1-1 5.7 +/- 0.5 5.5 5.6 6.0 5.5 D1-2 6.2 +/- 0.9 6.2 5.9 6.8 5.8 D2-2 7.2 +/- 0.7 7.1 7.1 7.7 6.9 D6-1 7.2 +/- 0.8 6.9 7.0 7.8 7.0 D15-1 6.6 +/- 0.8 6.3 6.3 7.0 6.9 El-2 5.7 +/- 0.6 5.5 5.5 6.1 5.6 El-4 5.4 +/- 0.5 5.6 5.2 5.7 5.2 E2-3 6.8 +/- 0.4 6.6 6.9 7.1 6.7 E5-1 6.0 +/- 0.4 5.9 5.7 6.1 6.1 E7-1 6.5 +/- 0.8 6.0 6.4 7.0 6.4 Fl-1 6.1 +/- 0.9 5.8 5.8 6.7 6.0 Fl-2 5.9 +/- 0.5 5.7 5.7 6.2 5.8 Fl-4 5.5 +/- 0.5 5.4 5.4 5.8 5.2 F2-1 6.9 +/- 0.8 6.8 6.5 7.4 6.7 F5-1 7.1 +/- 0.8 6.7 7.0 7.7 7.0 F10-1 7.6 +/- 0.6 7.2 7.8 7.6 7.8 F25-1 6.5 +/- 0.1 6.5 6.6 6.5 6.5 G1-2 6.3 +/- 0.7 6.1 6.5 6.7 6.0 G1-3 5.4 +/- 0.9 5.1 5.1 6.0 5.5 G1-5 5.6 +/- 0.7 5.3 5.5 6.1 5.6 G1-6 5.9 +/- 0.2 5.9 6.0 5.8 5.9 G2-4 7.4. +/- 0.6 7.3 7.0 7.6 7.6 G5-1 6.0 +/- 0.6 5.8 5.7 6.4 5.9 G10-1 8.5 +/- 0.7 8.6 8.1 8.9 8.3 G15-1 6.7 +/- 0.5 6.4 6.6 7.0 6.8 Hi-1 6.1 +/- 0.6 5.9 5.9 6.5 6.1 H3-1 5.2 +/- 0.8 4.8 5.1 5.8 5.2 H5-1 5.4 +/- 0.5 5.2 5.2 5.7 5.3 H8-1 9.2 +/- 1.5 8.5 9.2 10.2 8.9 H15-1 5.4 +/- 0.5 5.2 5.2 5.7 5.3 Ji-i 5.6 +/- 0.6 5.5 5.4 6.0 5.4 C - 24

TABLE C-XII.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH STATION MEAN 01/13 - 04/14/05 04/14 - 07/14/05 07/14 - 10/13/05 10/13 - 01/13/06 CODE +/- 2 S. D.

J1-3 5.2 +/- 0.7 5.1 4.8 5.6 5.3 J3-1 6.1 +/- 1.0 5.8 5.6 6.7 6.2 J5-1 6.8 +/- 1.0 6.7 6.3 7.5 6.7 J7-1 7.3 +/- 1.3 6.6 7.0 7.7 8.0 J15-1 7.0 +/- 0.8 6.9 6.9 7.6 6.7 K1-4 5.8 +/- 0.4 5.7 5.8 6.1 5.6 K2-1 6.7 +/- 0.4 6.4 6.8 6.9 6.7 K3-1 5.8 +/- 0.8 5.4 6.1 6.1 5.4 K5-1 6.9 +/- 0.6 6.6 7.0 7.2 6.7 K8-1 6.6 +/- 0.7 6.3 6.7 7.0 6.3 K15-1 6.3 +/- 0.5 6.2 6.4 6.6 6.0 Li-i 6.1 +/- 0.8 5.8 6.1 6.6 5.7 L1-2 5.6 +/- 0.4 5.4 5.6 5.8 5.4 L2-1 6.3 +/- 0.8 6.0 6.4 6.8 6.0 L5-1 5.9 +/- 0.4 5.9 6.0 6.1 5.6 L8-1 6.4 +/- 0.6 6.2 6.5 6.7 6.1 L15-1 6.4 +/- 0.5 6.1 6.4 6.7 6.4 Mi-i 5.7 +/- 0.9 5.8 5.8 6.2 5.1 M1-2 6.2 +/- 1.1 5.5 6.3 6.8 6.0 M2-1 5.5 +/- 0.4 5.3 5.6 5.7 5.3 M5-1 6.0 +/- 0.8 5.4 6.2 6.3 6.0 M9-1 7.3 +/- 1.7 6.2 7.6 8.2 7.0 NI-1 5.6 +/- 1.4 4.7 5.7 6.4 5.6 N1-3 5.7 +/- 0.8 5.3 6.0 6.1 5.4 N2-1 6.2 +/- 1.4 5.2 6.4 6.8 6.3 N5-1 5.2 +/- 1.5 4.1 5.6 5.8 5.4 N8-1 6.4 +/- 1.4 5.4 6.7 7.0 6.3 N15-2 6.7 +/- 1.5 5.7 7.0 7.4 6.6 P1-i 5.8 +/- 1.6 4.6 6.1 6.4 6.0 P1-2 5.6 +/- 0.5 5.6 5.3 5.9 5.5 P2-1 6.7 +/- 1.5 5.8 7.1 7.5 6.5 P5-1 5.5 +/- 1.3 4.8 5.8 (1) 6.0 P8-1 5.2 +/- 1.2 4.4 5.1 5.9 5.3 Q1-i 5.8 +/- 1.4 4.9 5.7 6.6 6.0 Q1-2 5.1 +/- 0.9 4.5 4.9 5.3 5.5 Q2-1 5.4 +/- 1.3 4.5 5.3 6.0 5.6 Q5-1 5.1 +/- 1.3 4.7 5.5 4.4 5.8 Q9-1 5.9 +/- 1.0 5.2 5.7 6.3 6.2 Q15-1 6.3 +/- 1.2 5.4 6.4 6.7 6.5 Ri-1 5.3 +/- 1.1 4.7 5.2 6.0 5.4 R1-2 5.3 +/- 1.1 4.6 5.3 5.8 5.6 R3-1 6.6 +/- 0.9 6.0 6.8 7.0 6.5 R5-1 6.4 +/- 1.0 5.7 6.6 6.8 6.5 R9-1 6.2 +/- 1.1 5.4 6.4 6.7 6.3 R15-1 5.1 +/- 2.4 4.8 5.8 6.3 3.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C - 25

TABLE C-XII.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, OFFSITE AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF MILLI-ROENTGEN PER STD. MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA STATION SITE BOUNDARY OFFSITE CONTROL CODE +/- 2 S. D.

JAN-MAR 5.4 +/- 0.7 5.8 +/- 1.7 6.4 +/- 2.0 APR-JUN 5.5 +/- 0.8 6.2 +/- 1.5 6.7 +/- 1.2 JUL-SEP 6.0 +/- 0.6 6.7 +/- 1.7 7.3 +/- 2.1 OCT-DEC 5.5 +/- 0.5 6.2 +/- 1.4 6.5 +/- 2.3 TABLE C-XII.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN ANALYZED MINIMUM MAXIMUM +2S D +2S D SITE BOUNDARY 80 4.5 6.6 5.6 +/- 0.8 4.8 +/- 1.5 OFFSITE 235 4.1 10.2 6.2 +/- 1.7 5.2 +/- 1.5 CONTROL 44 3.6 8.9 6.7 +/- 2.0 5.8 +/- 1.7 THE PRE-OPERATIONAL MEAN WAS CALCULATED FROM MONTHLY TLD READINGS 1980 TO 1985.

SITE BOUNDARY STATIONS - A1-4, Bi-1, B1-2, C1-2, Di-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, Hi-i, Ji-i, J1-3, K1-4, 1-1i, Mi-1, N1-3, P1-2, Q1-2, Ri-i OFFSITE STATIONS- A3-1, A5-1, A9-3, B2-1, B5-1, B10-1, Cl-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, Fl-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, 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 -26

FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2006 IDStation J1-2 (Downstream of Discharge) El Station Q9-1 (Control) E 12 1 N 100000 1

IL 1000 -

o~ * .. . .,'I..

,(. .' . . . . . . . . . . . . .

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month 0 Station K1-1 (TMINS Liquid Discharge) 1000000 100000 ............................ ... .............................................................. . . .. . . . .

10000 10000 .............................................

. I........... . .. . . . . . . . l

.............. - - l - - . ..

0~

a-)

100 - - . ..

- -i-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 - 2006 Indicator Samples - Control Samples 12000 _

Significant Events Major Atm. Nuclear Weapon Tests 11000 TMI-! 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

. ~7000 S6000 (n) k_- 5000 70 0 0 -- - - - - - - - - - - - - - -- - - - - - - - - - - - - - - -- - -- - - -- - - -- - - -- - -

0

• _ 4000 .. .

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

2000 100 --------------------------- ---- ---- ---

SN N N N N C C C C C C C C C C 0 0 ) 0)

• 0 ) 0 0) 0 0 00 0 0 0

0) 0b 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0M)M 0) 0)

M) 0) 0M 0 0 0 0 0 0 0 0 Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2006 I- Indicator Samples 09 Control Samples 10 9

8 7

a,*

• 6

"-J

-)

._Ž 4 3

2 -

0 ,- -- - -- --_-_-.

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

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station-, 2006 NOTE: The mean values are calculated using both the MDCs and El Indicator Samples MJ Control Samples.

the positive values.

500 NOTE: USEPA Drinking Water Limit for Tritium:

20,C00 pCi/L CD 400 300 Cn 200 D

0 100 - --

06 0

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month U Station K1-1 (TMINS Liquid Discharge) 1000000 100000 10000 0~ 1000 C.2 100 a-10 10 - -H i i ----

-IKH--H-MENEEL-----

I.- 1 -JEEEEI--

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

FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2006

-- Indicator Samples -Control Samples 900 Significant Event . I Chemobyl April 19861 800 700 E 600 0 500 -

CL 400 -

80 300 -

0~

200-100-0 .. . . . . . . . .

CO O 0) O0 0O 0) 0) ) 0') 0) 0') 0) O) 0) 0) 0) 0M) 0 0M 0C) 0) 0 0 0 0 0 0 0 0 0 0 F?- ) 0') 0) 0") 0) 0) 0) 0) 0) O 0) 0) 0) 0) 0) 0) 0) 0) 0M) 0 0) 0 0 0 0 0 0 0 0 0 Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2006

- Indicator - Control 0.4 Significant Events Major Atm. Nuclear Weanon Tests TMI-I Critical June 1974 March 1972 June 1973 0.35 TMI-2 Critical March 1978 June 1974

• September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September.1977 March 1978 Chernobyl April 1986 December 1978 October 1980 0.3 --

0.25 0.2 C1. 0.2 a-"

8 0.15 0.1 0.05 0

r'. c *" U) 1.J C N-

'O a) C ~ 0 ~

N-~~~~~~~~

• '-) ~~ ~ ~ )C aa C(r1 D U) )0N-N CO N-* N-

)0 N-

")0) )0 N-N0-a

- C4

.)0 cO )1" U) 0 LJ- (0)0 N )0 O 0) 0 -- (\J CtO0000

'* U* 0CO N 0 0 ý0) 0* 0) C) 0) 0) 0) 0M c2 m 0" C)

M 0 0) 0) M) M 0) M C2C C2 0)

C0 M M ) 0 0 0 0 0 0 0 0 Year

FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2006

- Indicator - Control 0.100 0.090 0.080 0.070

._ 0.060 0

S0.050 a)

• 0.040 0

n 0.030 0.020 0.010 0.000 CD (0 C.0 0 (D CO C0 D ( D 0D (0 C( 0 w O (0 (0 (D D (0D C0 CD C0 CD CD (D C (D Iw.-

o 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

- O Mont'/Day df2006 asO 0 Q00- - Q

FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2006 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 Cherfiobyl April 1986 7

L..

-.i 6 L...

5 "5 C.)-

.6_

70 - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - -

2 0 --

1--- ------- ------- ------- ------- ------- ------- ------

0)

N*- 0CO Z6 (N O M~ 1; COC)O U CO CD O rl-O W O 0M O 0 0 0); (N

0) M~

0)

0) IT- 0)0D 0) fCO

0) 0) W- CD

0) 0 00 0  ; 0"N 0M' 0v 0M) C 0

00 0 0 0) 0) 0)) 0) 0 0 C0) 0)

- - - - - M

- - - Y- 0a-

-- 0M

- 0) 0)

0

0) 0) 0 0 0 0 0 0 0 Year

FIGURE C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2006

- Indicator -- Control 50

• Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 45 + TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 40 -I- Chernobyl April 1986 December 1978 October 1980 35 4-(-.

0 30 +

cu "E

25 +/-

(U U-20 +

E 15 +

10o-

- - -~ A 5 4-0 . . .~~ ~~ . . . . ,. , , ~~

. . . ... . ... . ... . .., . ... . ..o . ... . ..°.

I.-J tO co r- co 0) 0 - (N CO) LO. (0 ri CO 0) 0 - M 'IT - ( -) M (W 0 0 (N M' I UO L (0

03) 0) 0) 0) 0) 0) 0) ) 0 M 0) 0) 00) 0)

M) 0)

M) 0)

M) ) 0) 0)

M 0) 0) 0) 0 0 0 0 0 0 0 Year

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 Blank D-2

TABLE D-I.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 01/03/06 01/31/06 < 1.9 01/31/06 02/28/06 < 0.9 02/28/06 03/28/06 < 1.7 03/28/06 05/02/06 3 +/- 1.0 05/02/06 05/30/06 < 1.8 05/30/06 - 06/26/06 1.2 +/- 0.5 06/26/06 - 08/01/06 1.4 +/- 0.6 08/01/06 - 08/29/06 2.5 +/- 1.0 08/29/06 - 10/03/06 3.8 +/- 1.1 10/03/06 - 10/31/06 2.3 +/- 1.1 10/31/06 - 11/28/06 2.1 +/- 1.0 11/28/06 - 01/02/07 < 1.8 MEAN 2.0 +/- 1.6 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 01/03/06 01/31/06 151 01131/06 02/28/06 159 02/28/06 03/28/06 159 03/28/06 05/02/06 133 05/02/06 05/30/06 136 +/- 71 05/30/06 06/26/06 126 +/- 90 06126/06 08/01/06 138 08/01/06 08/29/06 132 08/29/06 10103/06 182 10/03/06 10/31/06 147 10/31/06 11/28/06 171 11/28/06 01/02/07 146 MEAN 148 +/- 34 D-3

TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 01/03/06 - 01/31/06 < 0.2 01/31/06 - 02/28/06 < 0.3 02/28/06 - 03/28/06 < 0.4 03/28/06 - 05/02/06 < 0.3 05/02/06 - 05/30/06 < 0.3 05/30/06 - 06/26/06 < 0.2 06/26/06 - 08/01106 < 0.3 08/01/06 - 08/29/06 < 0.5 08/29/06 - 10/03/06 < 0.4 10/03/06 - 10/31/06 < 0.3 10/31/06 - 11/28/06 < 0.4 11/28/06 - 01/02/07 < 0.3 MEAN 0.3 + 0.2 D-4

TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINIIh OF THREE MILE ISLAND NUCLEAR STATION, 2006 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 01/03/06 - 01/31/06 < 3.9 < 2.0 < 5.0 3.2 +/- 1.9 < 6.7 < 5.6 < 2.9 < 3.6 < 2.2 < 13 < 1.4 01/31/06 - 02/28/06 < 3.0 < 2.4 < 8.7 < 4.2 < 7.5 < 9.2 < 4.6 < 6.2 < 4.6 < 17 < 1.6 02/28/06 - 03/28/06 < 1.8 < 2.2 < 5.4 < 2.7 < 3.7 < 3.9 < 1.7 < 2.9 < 1.5 < 10 < 2.8 03/28/06 - 05/02/06 < 2.0 < 3.3

• 7.8 < 3.0 < 7.3 < 5.1 < 1.6 < 3.0 < 2.3 < 15 < 3.9 05/02/06 - 05/30/06 < 4.6 < 4.0 < 7.6 < 4.4 ;c 9.6 < 7.9 < 3.6 < 5.3 <4.1 < 22 < 3.4 05/30/06 - 06/26/06 < 5.8 < 5.0 < 11.4 < 3.8 < 7.7 < 9.6 < 4.3 < 5.0 < 3.0 < 12 < 3.0 06/26/06 - 08/01/06 < 2.7 < 1.6 < 4.0 < 2.6 < 3.0 < 3.9 < 3.0 < 2.7 < 2.9 <8

• 2.6 08/01/06 - 08/29/06

• 2.5 < 2.2 < 5.1 < 1.2 < 4.0 < 4.2 < 2.0 < 2.5 < 2.1 <7 < 2.7 08/29/06 - 10/03/06 < 2.1 < 2.6 < 7.7 < 3.0 < 5.2 < 4.5 < 2.7 < 4.7 < 2.6 < 16 < 3.6 10/03/06 - 10/31/06 < 1.6 *2.5 < 5.3 < 3.5 < 4.2 < 5.5 < 3.0 < 3.9 *2.1 < 11 < 1.8 10/31/06 - 11/28/06 < 2.6 < 1.7 < 6.9 < 2.6 < 4.6 < 3.6 < 3.2 < 4.7 < 3.2 < 13 < 1.4 11/28/06 - 01/02/07 < 3.4

• 2.7

• 6.6 < 3.5 < 3.8 < 3.8 < 2.7 < 3.7 < 3.4 < 18 4.5 +/- 2.4 Ei I MEAN 3.0 +/- 2.5 2.7 +/- 2.0 6.8 +/- 4.1 3.0 +/- 1.8 5.6 +/- 4.2 5.6 +/- 4.3 2.9 +/- 1.9 4.0 +/- 2.3 2.8 +/- 1.8 13 +/- 8 2.6 +/- 1.7

TABLE D-I.5 CONCENTRATIONS OF TRITIUM, STRONTIUM, AND GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION H-3 Sr-90 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-1 34 Cs-1 37 Ba-140 La-140 PERIOD MS-2Q 01/16/06 311 +/- 107 03/28/06 331 +/- 100 06/08/06 306 +/- 81 12/09/06 288 +/- 87 < 0.5 < 2 0.3 +/- 2.1 <8 <3 <7 <4 <4 <5 <4 <25 <3 (7N

TABLE D-I.6 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 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-1 34 Cs-1 37 PERIOD INDPQ 11/14/06 < 10 < 4.7 2881 +/- 289 < 7 < 11 < 35 < 16 27 +/- 23 < 16 < 12 I

TABLE D-I.7 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 PERIOD J2-1Q 10/10/06 3435 +/- 212 <7 <7 D-8

TABLE D-1.8 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION K-40 1-131 Cs-134 Cs-137 Sr-89 Sr-90 PERIOD B10-2Q 08/10/06 4713 +/- 633 < 28 < 20.5 < 18.3 < 18.0 < 8.0 D-9

TABLE D-11.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION E1-2Q PERIOD 12/28/06 0 1/04/06 19 +/- 4 01/04/06 -01/11/06 21 +/- 5 01/11/06 -01/18/06 17 +/- 4 01/18/06 -01/25/06 20 +/- 4 01/25/06 -02/01/06 20 +/- 5 02/01/06 -02/08/06 19 +/- 4 02/08/06 -02/15/06 16 +/- 4 02/15/06 -02/22/06 36 +/- 5 02/22/06 -03/01/06 29 +/- 5 03/01/06 -03/08/06 15 +/- 4 03/08/06 -03/15/06 20 +/- 4 03/15/06 -03/22/06 21 +/- 4 03/22/06 -03/29/06 13 +/- 4 03/29/06 -04/05/06 19 +/- 4 04/05/06 -04/12/06 21 +/-4 04/12/06 -04/19/06 18 +/-4 04/19/06 -04/25/06 10 +/-4 04/25/06 -05/02/06 16 +/-4 05/02/06 -05/10/06 18 +/-5 05/10/06 -05/17/06 10 +/-4 05/17/06 -05/24/06 12 +/-4 05/24/06 -05/31/06 29 +/-5 05/31/06 -06/07/06 21 +/-4 06/07/06 -06/14/06 13 +/-4 06/14/06 -06/21/06 21 +/-4 06/21/06 -06/27/06 18 +/-5 06/27/06 -07/04/06 26 +/-5 07/04/06 -07/12/06 27 +/-4 07/12/06 -07/19/06 28 5 07/19/06 -07/26/06 23 +/-5 07/26/06 -08/02/06 44 +/-5 08/02/06 -08/09/06 29 +/-5 08/09/06 -08/16/06 26 +/-5 08/16/06 -08/23/06 24 +/- 5 08/23/06 -08/30/06 28 +/- 5 08/30/06 -09/06/06 12 +/- 4 09/06/06 -09/13/06 32 +/- 5 09/13/06 -09/20/06 17 +/- 4 09/20/06 -09/27/06 21 +/- 4 09/27/06 -10/04/06 25 +/- 4 10/06/06 -10/11/06 31 +/- 6 (1) 10/11/06 -10/18/06 24 +/- 5 10/18/06 -10/25/06 22 +/- 4 10/25/06 -10/31/06 9+/-5 10/31/06 -11/07/06 29 +/-6 11/07/06 -11/15/06 17 +/-4 11/15/06 -11/21/06 19 +/-5 11/21/06 -11/28/06 27 +/-5 11/28/06 -12/06/06 34 +/- 4 12/06/06 -12/12/06 36 +/- 5 12/12/06 -12/20/06 33 +/- 4 12/20/06 -12/27/06 28 +/- 4 12/27/06 -01/03/07 25 +/- 4 MEAN 22 +/- 15 (1) Pump replaced 10/06/2006 due to faulty vacuum gauge.

D -10

TABLE D-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Be-7 Cs-134 Cs-1 37 PERIOD E1-2Q 12/28/05 - 03/29/06 61 +/- 14 < 0.9 < 0.7 03/29/06 - 06/27/06 86 +/- 23 < 0.7 < 0.6 06/27/06 - 09/27/06 85 +/- 14 < 0.6 < 0.5 09/27/06 - 01/03/07 60 +/- 12 < 0.6 < 0.6 MEAN 73 +/- 29 0.7 +/- 0.3 0.6 +/- 0.2 D-11

TABLE D-Ill.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION,GAMMA EMITTERS, &

STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION 1-131 K-40 Cs- 134 Cs-1 37 Ba-140 La-140 Sr-89 Sr-90 PERIOD G2-1Q 01/04/06 < 0.2 1157 +/- 176 < 4.1 < 5.4 < 39 < 4.7 02/01/06 < 0.1 982 +/- 91 < 3.7

• 3.8

• 38 < 3.2 03/01/06 < 0.2 1173 +/- 193 < 6.6 < 4.5 < 22 < 5.6 03/15/06 < 0.3 1214 +/- 160 < 4.7 < 3.1 < 19 < 5.1 03/29/06 < 0.3 1431 +/- 181 < 5.2 < 6.9 < 34 < 2.5 < 0.6 < 0.5 04/12/06 < 0.2 1195 +/- 174 < 4.5 < 4.7 < 22 < 7.3 04/26/06 < 0.2 1282 +/- 150 < 5.8 < 5.9 < 18 < 2.7 05/10/06 < 0.2 1291 +/- 120 < 3.1 < 3.1 < 17 < 3.2 05/24/06 < 0.3 1260 +/- 117 < 4.8 < 1.9 < 22 <3 06/07/06 < 0.4 1135 +/- 125 < 3.5 < 4.3 < 13 < 3.1 06/21/06 < 0.4 1327 +/- 104 < 3.3 < 3.7 < 14 < 2.4 < 0.6 < 0.7 07/05/06 < 0.3 1303 +/- 112 < 4.1 < 4.1 <8 < 2.2 07/19/06 < 0.3 1414 +/- 111 < 3.8 < 2.6 < 11 < 2.8 08/02/06 < 0.3 1336 +/- 181 < 7.0 < 4.7 < 23 < 5.6 08/16/06 < 0.3 1424 +/- 120 < 4.1 < 2.8 <13

• 2.5 08/30/06 < 0.2 1365 +/- 118 < 4.7 < 3.6 < 11 < 2.6 09/13/06

• 0.5 1124 +/- 166 < 6.6 < 6.1 < 29 < 4.6 09/27/06 < 0.3 1258 +/- 101 < 3.7 < 2.4

• 12 < 2.2 < 0.7 < 0.4 10/11/06 < 0.3 1167 +/- 110

• 2.9 < 4.1 *17

• 2.6 10/25/06 < 0.4 1347 +/- 115 < 2.0 < 4.0 <7 < 3.3 11/07/06 < 0.4 1161 +/- 110 < 4.7 < 4.1 < 21 < 4.5 11/21/06 < 0.4 1327 +/- 116 < 3.7 < 4.0 < 14 < 1.9 12/06/06

• 0.3 1294 + 121

• 4.2

• 2.4

• 17 < 3.4 < 0.8 0.6 +/- 0.3 MEAN 0.3 +/- 0.2 1259 +/- 222 4.4 +/- 2.5 4.0 +/- 2.5 19 +/- 18 3.5 +/- 2.8 0.7 +/- 0.2 0.5 +/- 0.2 D-12

FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2006 5

-- QC-LAB 4 . rlMlRI A iMf' I AM 3

0) 0 0.

2 1

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

FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2006 50 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

QC - LAB 40 - P R IMA RY - LA B ......... ........................................

U ~ l l l l lI I I I I I ~l l l l l l I I I I I l l l l i l l ll l l l l l l l l l l l l ~ ~ l l l l

.C-)

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

Intentionally left blank APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

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

March 2006 E4964-396 Milk Sr-89 pCi/L 91.5 99.2 0.92 A Sr-90 pCi/L 12.2 10.8 1.13 A E4965-396 Milk 1-131 pCi/L 74.4 78.0 0.95 A Ce-141 pCi/L 95.1 104 0.91 A Cr-51 pCi/L 278 280 0.99 A Cs-134 pCi/L 103 121 0.85 A Cs-1 37 pCi/L 87.6 88.8 0.99 A Co-58 pCi/L 93.9 105 0.89 A Mn-54 pCi/L 90.0 93.3 0.96 A Fe-59 pCi/L 83.0 86.6 0.96 A Zn-65 pCi/L 178 176 1.01 A Co-60 pCi/L 118 128 0.92 A E4967-396 AP Ce-141 pCi 89.9 74 1.21 W Cr-51 pCi 253 200 1.27 W Cs-i 34 pCi 71.5 86.1 0.83 A Cs-i 37 pCi 67.5 63.3 1.07 A Co-58 pCi 79.7 74.6 1.07 A Mn-54 pCi 74.9 67 1.12 A Fe-59 pCi 75.5 61.8 1.22 W Zn-65 pCi 146 126 1.16 A Co-60 pCi 91.2 91 1.00 A E4966-396 Charcoal 1-131 pCi 87.4 86.2 1.01 A June 2006 E5018-396 Milk Sr-89 pCi/L 118 129 0.91 A Sr-90 pCi/L 9.29 9.74 0.95 A E5019-396 Milk 1-131 pCi/L 49.9 63.2 0.79 W Ce-141 pCi/L 174 184 0.95 A Cr-51 pCi/L 266 259 1.03 A Cs-134 pCi/L ill 127 0.88 A Cs-i 37 pCi/L 116 117 0.99 A Co-58 pCi/L 101 100 1.01 A Mn-54 pCi/L 144 146 0.98 A Fe-59 pCi/L 96.7 93.6 1.03 A Zn-65 pCi/L 182 185 0.98 A Co-60 pCi/L 126 129 0.98 A E5021-396 AP Ce-141 pCi 113 124 0.91 A Cr-51 pCi 176 174 1.01 A Cs-134 pCi 63.7 85.1 0.75 W Cs-137 pCi 76.8 79.0 0.97 A Co-58 pCi 63.1 67.4 0.94 A Mn-54 pCi 102 99 1.04 A Fe-59 pCi 64.6 62.9 1.03 A Zn-65 pCi 131 125 1.05 A Co-60 pCi 81.6 86.5 0.94 A E5020-396 Charcoal 1-131 pCi 65.4 65.9 0.99 A E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

September 2006 E5120-396 Milk Sr-89 pCi/L 90.3 89.2 1.01 A Sr-90 pCi/L 11.6 12.4 0.94 A E5121-396 Milk 1-131 pCi/L 67.8 73.8 0.92 A Ce-141 pCi/L 85.0 86.0 0.99 A Cr-51 pCi/L 263 282 0.93 A Cs-1 34 pCi/L 74.7 85.0 0.88 A Cs-137 pCi/L 172 175 0.98 A Co-58 pCi/L 107 109 0.98 A Mn-54 pCi/L 110 113 0.98 A Fe-59 pCi/L 46.6 43.7 1.07 A Zn-65 pCi/L 144 145 0.99 A Co-60 pCi/L 127 134 0.95 A E5123-396 AP Ce-141 pCi 67.1 66.4 1.01 A Cr-51 pCi 223 217 1.03 A Cs-1 34 pCi 51.7 65.6 0.79 W Cs-137 pCi 134 135.0 0.99 A Co-58 pCi 84.8 84.3 1.01 A Mn-54 pCi 95.2 87 1.10 A Fe-59 pCi 41.6 33.7 1.23 W Zn-65 pCi 123 112 1.10 A Co-60 pCi 98.9 103 0.96 A Co-57 pCi 0.922 (1) NA NA E5122-396 Charcoal 1-131 pCi 77.7 90.7 0.86 A December 2006 E5172-396 Milk Sr-89 pCi/L 72.4 72.0 1.01 A Sr-90 pCi/L 7.05 5.90 1.19 A E5173-396 Milk 1-131 pCi/L 71.9 70.8 1.02 A Ce-141 pCi/L 268 294 0.91 A Cr-51 pCi/L 420 433 0.97 A Cs-1 34 pCi/L 128 147 0.87 A Cs-137 pCi/L 231 237 0.97 A Co-58 pCi/L 82.0 83.8 0.98 A Mn-54 pCi/L 113 ill 1.02 A Fe-59 pCi/L 79.8 79.7 1.00 A Zn-65 pCi/L 170 164 1.04 A Co-60 pCi/L 265 281 0.94 A E5175-396 AP Ce-141 pCi 220 210 1.05 A Cr-51 pCi 343 309 1.11 A Cs-134 pCi 90.8 105 0.86 A Cs-137 pCi 185 169.0 1.09 A Co-58 pCi 65.0 59.7 1.09 A Mn-54 pCi 90.6 79 1.15 A Fe-59 pCi 70.7 56.7 1.25 W Zn-65 pCi 136 117 1.16 A Co-60 pCi 208 200 1.04 A E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

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

December 2006 E5174-396 Charcoal 1-131 pCi 77.4 85.4 0.91 A (1) Impurity detected but not measured by Analytics.

(a) Teledyne Brown Engineering reported result.

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

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

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

W-Acceptable with warning. Reported result falls within 0. 70-0. 80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2006 (PAGE I OF 1)

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

May 2006 Rad 65 Water Sr-89 pCi/L 30.2 32.4 23.6 -41.1 A Sr-90 pCi/L 8.74 9.00 0.340- 17.7 A Ba-133 pCi/L 10.9 10.0 1.34-18.7 A Cs-134 pCi/L 39.7 43.4 34.7-52.1 A Cs-137 pCi/L 199 214 195 - 233 A Co-60 pCi/L 111 113.0 103- 123 A Zn-65 pCi/L 146 152 126-178 A Gr-A pCi/L 22.9 21.3 12.1 -30.5 A Gr-B pCi/L 23.7 23.0 14.3-31.7 A Ra-226 pCi/L 2.64 3.02 2.23 - 3.81 A U-Nat pCi/L 74.9 69.1 57.1 -81.1 A H-3 pCi/L 7950 8130 6720 - 9540 A Rad 65 Water 1-131 pCi/L 18.2 19.1 13.9 - 24.3 A November 2006 Rad 67 Water Sr-89 pCi/L 40.0 39.9 31.2 -48.6 A Sr-90 pCi/L 16.2 16.0 7.34 - 24.7 A Ba-133 pCi/L 65.0 70.2 58.1 -82.3 A Cs-i 34 pCi/L 27.4 29.9 21.2 -38.6 A Cs-1 37 pCi/L 74.4 78.2 69.5 - 86.9 A Co-60 pCi/L 61.6 62.3 53.6 - 71.0 A Zn-65 pCi/L 277 277 229 - 325 A Gr-A pCi/L 23.3 28.7 16.3 -41.1 A Gr-B pCi/L 22.0 20.9 12.2 -29.6 A U-Nat pCi/L 3.18 3.20 0.00 - 8.40 A H-3 pCi/L 2930 3050 2430 - 3670 A Water 1-131 pCi/L 19.8 22.1 16.9 -27.3 A (a) Teledyne Brown Engineering reportedresult.

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

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

E-4

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

TELEDYNE BROWN ENGINEERING, 2006 (PAGE I OF 3)

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

January 2006 06-MaW15 Water Am-241 Bq/L 1.29 1.30 0.91-1.69 A Cs-134 Bq/L 79.2 95.1 66.57- 123.63 A Cs-1 37 Bq/L -0.188 A Co-57 Bq/L 151 166.12 116.28 -215.96 A Co-60 B~q/L 141 153.50 107.45 - 199.55 A H-3 Bq/L 988 952.01 666.41 - 1237.61 A Fe-55 Bq/L 106.0 129.60 90.72 - 168.48 A Mn-54 Bq/L 297 315.00 220.50 - 409.50 A Ni-63 Bq/L 61.5 60.34 44.24 - 78.44 A Pu-238 Bq/L 0.961 0.91 0.64-1.18 A Pu-239/240 Bq/L 0.00965 0.00710 (1) A Sr-90 Bq/L 12.6 13.16 9.21- 17.11 A Tc-99 Bq/L 22.5 23.38 16.37 - 30.39 A U-234/233 Bq/L 2.20 2.09 1.46-2.72 A U-238 Bq/L 2.23 2.17 1.52-2.82 A Zn-65 Bq/L 219 228.16 159.71 - 296.61 A 06-GrW15 Water Gr-A Bq/L 0.575 0.581 >0.0 - 1.162 A Gr-B Bq/L 1.52 1.13 0.56-1.70 A 06-MaS15 Soil Am-241 Bq/kg 48.8 57.08 39.96 - 74.20 A Cs-1 34 Bq/kg 15.9 N (1)

Cs-1 37 Bq/kg 370 339.69 237.78 - 441.60 A Co-57 Bq/kg 667 656.29 459.40 - 853.18 A Co-60 Bq/kg 478 447.10 312.97 - 581.23 A Mn-54 Bq/kg 384 346.77 242.74 - 450.80 A Ni-63 Bq/kg 394 323.51 226.46 - 420.56 W K-40 Bq/kg 667 604 423-785 A Sr-90 Bq/kg 253 314.35 220.04 - 408.66 A Tc-99 Bq/kg 146 154.76 108.33 - 201.19 A Zn-65 Bq/kg 740 657.36 460.15 - 854.57 A 06-RdF15 AP Am-241 Bq/sample 0.0850 0.093 0.065 - 0.121 A Cs-134 Bq/sample 2.34 2.934 2.054 - 3.814 A Cs-137 Bq/sample 2.45 2.531 1.772 - 3.290 A Co-57 Bq/sample 3.87 4.096 2.867 - 5.325 A Co-60 Bq/sample 2.12 2.186 1.530 - 2.842 A Mn-54 Bq/sample 0.0206 A Pu-238 Bq/sample 0.0766 0.067 0.047 - 0.087 A Pu-239/240 Bq/sample 0.00520 0.00041 (1) A Sr-90 Bq/sample 0.761 0.792 0.554 - 1.030 A U-234/233 Bq/sample 0.0217 0.020 0.014 - 0.026 A U-238 Bq/sample 0.0220 0.021 0.015 - 0.027 A Zn-65 Bq/sample 3.86 3.423 2.396 - 4.450 A 06-GrF15 AP Gr-A Bq/sample 0.257 0.361 >0.0 - 0.722 A Gr-B Bq/sample 0.398 0.481 0.241 - 0.722 A E-5

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

TELEDYNE BROWN ENGINEERING, 2006 (PAGE 2 OF 3)

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

January 2006 06-RdV15 Vegetation Am-241 Bq/sample 0.156 0.156 0.109- 0.203 A Cs-134 Bq/sample 0.369 A Cs-137 Bq/sample 3.15 3.074 2.152 - 3.996 A Co-57 Bq/sample 10.1 8.578 6.005 - 11.151 A Co-60 Bq/sample 4.69 4.520 3.164 - 5.876 A Mn-54 Bq/sample 6.53 6.247 4.373 - 8.121 A Pu-238 Bq/sample 0.183 0.137 0.096 - 0.178 N (2)

Pu-239/240 Bq/sample 0.111 0.164 0.115- 0.213 N (2)

Sr-90 Bq/sample 2.22 1.561 1.093 - 2.029 N (2)

U-234/233 Bq/sample 0.208 0.208 0.146 - 0.270 A U-238 Bq/sample 0.176 0.216 0.151 -0.281 A Zn-65 Bq/sample 10.5 9.798 6.859 - 12.737 A July 2006 06-MaW16 Water Am-241 Bq/L 2.09 2.31 1.62-3.00 A Cs-1 34 Bq/L 99.8 112.82 78.98-146.66 A Cs-137 Bq/L 191 196.14 137.30-254.98 A Co-57 Bq/L 203 213.08 149.16- 277.00 A Co-60 Bq/L 46.2 47.5 33.2-61.8 A H-3 Bq/L 471 428.85 300.20 - 557.50 A Fe-55 Bq/L 173 165.4 115.8-215.0 A Ni-63 Bq/L 109 118.62 83.03- 154.21 A Pu-238 Bq/L 1.50 1.39 0.97-1.81 A Pu-239/240 Bq/L 2.01 1.94 1.36-2.52 A Sr-90 Bq/L 13.7 15.69 10.98- 20.40 A Tc-99 Bq/L 29.0 27.15 19.00 - 35.29 A U-234/233 Bq/L 2.19 2.15 1.50-2.80 A U-238 Bq/L 2.25 2.22 1.55-2.89 A Zn-65 Bq/L 178 176.37 123.46- 229.28 A 06-GrW16 Water Gr-A Bq/L 1.52 1.033 >0.0 - 2.066 A Gr-B Bq/L 1.18 1.03 0.52-1.54 A 06-MaS16 Soil Am-241 Bq/kg 83.6 105.47 73.83-137.11 W Cs-1 34 Bq/kg 393 452.13 316.49-587.77 A Cs-137 Bq/kg 522 525.73 368.01 - 683.45 A Co-57 Bq/kg 636 676.33 473.43 - 879.23 A Co-60 Bq/kg 3.78 1.98 A (3)

Mn-54 Bq/kg 598 594.25 415.98- 772.52 A Ni-63 Bq/kg 571 627.3 470.6 - 874.0 A Pu-238 Bq/kg 71.2 82 57-107 A Pu-239240 Bq/kg 0.487 0.93 A (3)

K-40 Bq/kg 615 604 423-785 A Sr-90 Bq/kg 178 223.3 156.3 - 290.3 W Tc-99 Bq/kg 175 218.01 152.61 -283.41 A U-234/233 Bq/kg 119 152.44 106.71 -198.17 W U-238 Bq/kg 115 158.73 111.11 -206.35 W Zn-65 Bq/kg 937 903.61 632.53-1174.69 A E-6

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

TELEDYNE BROWN ENGINEERING, 2006 (PAGE 3 OF 3)

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

July 2006 06-RdF16 AP Am-241 Bq/sample 0.124 0.142 0.099 - 0.185 A Cs-1 34 Bq/sample 2.62 3.147 2.203 - 4.091 A Cs-1 37 Bq/sample 1.98 1.805 1.263 - 2.346 A Co-57 Bq/sample 2.65 2.582 1.807 - 3.357 A Co-60 Bq/sample 1.63 1.577 1.104 - 2.050 A Mn-54 Bq/sample 2.10 1.92 1.34 -2.50 A Pu-238 Bq/sample 0.118 0.118 0.083 - 0.153 A Pu-239/240 Bq/sample 0.00822 NA A Sr-90 Bq/sample 0.549 0.62 0.43 - 0.81 A U-234/233 Bq/sample 0.140 0.134 0.094 - 0.174 A U-238 Bq/sample 0.136 0.139 0.097 - 0.181 A Zn-65 Bq/sample -0.163 NA A 06-GrF16 AP Gr-A Bq/sample 0.134 0.290 >0.0 - 0.580 A Gr-B Bq/sample 0.358 0.359 0.180 - 0.538 A (1) Falsepositive test (2) Evaluated as a false positive by MAPEPalthough we consideredthe result a non-detect due to the peak not being identified by the gamma software. For Cs-134, MAPEP suggests the Bi-214 is not being differentiatedfrom the Cs-134 peak. See email attachedwith MAPEP results in Appendix A. NCR 06-07.

(3) Sr samples analyzed in triplicate and one high result of 2.43 pCi/kg biased the submitted results on the high side.

We were unable to determine the cause for the higherresult. Since we do not analyze vegetation for isotpic Pu, no NCR was initiated for the Pu failure. MAPEP suggest pyrosulfate fusion preparationprior to analysis for isotopic Pu in vegetation samples.

(4) Not detected, reported a statisticallyzero result. (Falsepositive test)

(a) Teledyne Brown Engineering reportedresult.

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

(c) DOEIMAPEPevaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

E-7

TABLE E-4 ERAka) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2006 (Page 1 of 2)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 078 01/16/06 Sr-89 49.9 +/- 3.5 50.2 41.5 -58.9 Pass STW-1 078 01/16/06 Sr-90 31.5 +/- 1.5 30.7 22.0 -39.4 Pass STW-1 079 01/16/06 Ba-1 33 86.5 +/-4.1 95.0 78.6 -111.0 Pass STW-1079 01/16/06 Co-60 96.3 +/-4.1 95.3 86.6 - 104.0 Pass STW-1079 01/16/06 Cs-1 34 22.6 +/- 3.0 23.1 14.4 -31.8 Pass STW-1 079 01/16/06 Cs-1 37 109.0 +/- 5.9 111.0 101.0 - 121.0 Pass STW-1 079 01/16/06 Zn-65 198.0 +/- 11.2 192.0 159.0 - 225.0 Pass STW-1 080 01/16/06 Gr. Alpha 10.8 +/- 1.4 9.6 1.0-18.3 Pass STW-1080 01/16/06 Gr. Beta 56.9 +/- 1.9 61.9 44.6 - 79.2 Pass STW-1 081 01/16/06 Ra-226 4.3 +/- 0.4 4.6 3.4 -5.8 Pass STW-1 081 01/16/06 Ra-228 7.1 +/-1.8 6.6 3.7 -9.5 Pass STW-1081 01/16/06 Uranium 20.7 +/- 0.5 22.1 16.9 -27.3 Pass STW-1088 04/10/06 Sr-89 29.0 +/- 1.8 32.4 23.7 -41.1 Pass STW-1088 04/10/06 Sr-90 8.7 +/- 1.0 9.0 0.3 - 17.7 Pass STW-1089 04/10/06 Ba-1 33 10.3 +/- 0.4 10.0 1.3 -18.7 Pass STW-1089 04/10/06 Co-60 114.0 +/-2.8 113.0 103.0 - 123.0 Pass STW-1089 04/10/06 Cs-1 34 41.9 +/- 1.4 43.4 34.7 -52.1 Pass STW-1089 04/10/06 Cs-1 37 208.0 +/- 1.1 214.0 195.0 - 233.0 Pass STW-1089 04/10/06 Zn-65 154.0 +/- 0.8 152.0 126.0 - 178.0 Pass STW-1090 04/10/06 Gr. Alpha 13.4 +/- 1.1 21.3 12.1 -30.5 Pass STW-1090 04/10/06 Gr. Beta 27.7 +/- 2.1 23.0 14.3 -31.7 Pass STW-1091 04/10/06 1-131 22.0 +/- 0.3 19.1 13.9 -24.3 Pass STW-1092 04/10/06 H-3 7960.0 +/- 57.0 8130.0 6720.0 - 9540.0 Pass STW-1092 04/10/06 Ra-226 2.9 +/- 0.4 3.0 2.2 -3.8 Pass STW-1092 04/10/06 Ra-228 20.9 +/- 1.2 19.1 10.8 -27.4 Pass STW-1092 04/10/06 Uranium 68.6 +/- 3.4 69.1 57.1 -81.1 Pass STW-1094 07/10/06 Sr-89 15.9 +/-0.7 19.7 11.0 -28.4 Pass STW-1094 07/10/06 Sr-90 24.3 +/- 0.4 25.9 17.2 -34.6 Pass STW-1 095 07/10/06 Ba-1 33 94.9 +/- 8.9 88.1 72.9 -103.0 Pass STW-1i095 07/10/06 Co-60 104.0 +/- 1.8 99.7 91.0 -108.0 Pass STW-1095 07/10/06 Cs-1 34 48.7 +/- 1.3 54.1 45.4 - 62.8 Pass STW-1095 07/10/06 Cs-1 37 236.0 +/- 3.0 238.0 217.0 -259.0 Pass STW-1095 07/10/06 Zn-65 126.0 +/- 8.0 121.0 100.0 - 142.0 Pass STW-1096 07/10/06 Gr. Alpha 10.9 +/- 1.0 10.0 1.3-18.6 Pass STW-1096 07/10/06 Gr. Beta 9.7 +/- 0.4 8.9 0.2 - 17.5 Pass STW-1097 07/10/06 Ra-226 11.0 +/-0.5 10.7 7.9 - 13.5 Pass STW-1 097 07/10/06 Ra-228 12.2 +/- 0.8 10.7 6.1 - 15.3 Pass STW-1 097 07/10/06 Uranium 43.4 +/- 0.1 40.3 33.3 -47.3 Pass E-8

TABLE E-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2006 (Page 2 of 2)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1104 10/06/06 Sr-89 38.4 +/- 1.3 39.9 31.2 -45.7 Pass STW-1104 10/06/06 Sr-90 15.5 +/- 0.5 16.0 7.3 -24.7 Pass STW-1105 10/06/06 Ba-1 33 64.9 +/- 2.8 70.2 58.1 -82.3 Pass STW-1105 10/06/06 Co-60 61.6 +/- 1.0 62.3 53.6 -71.0 Pass STW-1105 10/06/06 Cs-1 34 29.0 +/- 0.9 29.9 21.2 -38.6 Pass STW-1105 10/06/06 Cs-1 37 77.8 +/- 2.4 78.2 69.5 - 86.9 Pass STW-i 105 10/06/06 Zn-65 293.0 +/- 2.4 277.0 229.0 - 325.0 Pass STW-1 106 10/06/06 Gr. Alpha 23.9 +/- 2.5 28.7 16.3 -41.1 Pass STW-1106 10/06/06 Gr. Beta 23.7 +/- 1.4 20.9 12.2 -29.6 Pass STW-1107 d 10/06/06 1-131 28.4 +/- 1.2 22.1 16.9 -27.3 Fail STW-1108 10/06/06 Ra-226 14.5 +/- 0.5 14.4 10.7 - 18.1 Pass STW-1108 10/06/06 Ra-228 6.6 +/- 0.4 5.9 3.3 - 8.4 Pass STW-1108 10/06/06 Uranium 2.9 +/- 0.1 3.2 0.0 -8.4 Pass STW-1109 10/06/06 H-3 3000.0 +/- 142.0 3050.0 2430.0 - 3670.0 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.

A fourth analysis was performed, result of analysis, 24.89 pCi/L.

E-9

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPa ENVIRONMENTAL, INC., 2006 (Page 1 of 3)

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1082 01/01/06 Am-241 0.16 +/- 0.06 0.16 0.11 -0.20 Pass STVE-1082 01/01/06 Co-57 10.40 +/- 0.20 8.58 6.00-11.15 Pass STVE-1 082 01/01/06 Co-60 5.00 +/- 0.20 4.52 3.16 -5.88 Pass STVE-1082 e 01/01/06 Cs-134 < 0.20 0.00 Pass STVE-1082 01/01/06 Cs-137 3.40 +/- 0.20 3.07 2.15 -4.00 Pass STVE-1082 01/01/06 Mn-54 6.90 +/- 0.20 6.25 4.37 -8.12 Pass S1VE-1082 01/01/06 Pu-238 0.08 +/- 0.03 0.14 0.10 -0.18 Fail STVE-1082 01/01/06 Pu-239/40 0.17 +/- 0.03 0.16 0.11 -0.21 Pass STVE-1082 01/01/06 Sr-90 1.40 +/- 0.20 1.56 1.09 - 2.03 Pass STVE-1082 01/01/06 U-233/4 0.24 +/- 0.05 0.21 0.15 -0.27 Pass STVE-1082 01/01/06 U-238 0.19 +/- 0.04 0.22 0.15 -0.28 Pass STVE-1082 01/01/06 Zn-65 11.10 +/- 0.50 9.80 6.86 - 12.74 Pass STSO-1083 01/01/06 Am-241 54.60 +/- 5.50 57.08 39.96 - 74.20 Pass STSO-1083 01/01/06 Co-57 762.90 +/- 12.70 656.29 459.40 -853.18 Pass STSO-1 083 01/01/06 Co-60 504.90 +/- 3.10 447.10 312.97 -581.23 Pass STSO- 1083 01/01/06 Cs-134 < 1.70 0.00 Pass STSO-1083 01/01/06 Cs-137 406.50 +/- 3.70 339.69 237.78 -441.60 Pass STSO-1083 01/01/06 K-40 719.20 +/- 18.40 604.00 422.80 - 785.20 Pass STSO-1083 01/01/06 Mn-54 415.60 +/- 4.80 346.77 242.74 -450.80 Pass STSO-1083 01/01/06 Ni-63 261.40 +/- 14.70 323.51 226.46 - 420.56 Pass STSO-1083 01/01/06 Pu-238 14.60 +/- 2.90 61.15 42.81 - 79.50 Fail STSO-1083 01/01/06 Pu-239/40 14.60 +/- 2.40 45.85 32.09 - 59.61 Fail STSO-1083 01/01/06 U-233/4 13.50 +/- 1.70 37.00 25.90 - 48.10 Fail STSO-1083 01/01/06 U-238 15.40 +/- 1.80 38.85 27.20 - 50.50 Fail STSO-1083 01/01/06 Zn-65 783.40 +/- 7.00 657.36 460.15 - 854.57 Pass STAP-1084 01/01/06 Gr. Alpha 0.26 +/- 0.02 0.36 0.00 - 0.72 Pass STAP-1084 01/01/06 Gr. Beta 0.51 +/- 0.03 0.48 0.24 - 0.72 Pass STAP-1085 01/01/06 Am-241 0.12 +/- 0.02 0.09 0.07 -0.12 Pass STAP-1085 01/01/06 Co-57 4.32 +/- 0.10 4.10 2.87 - 5.32 Pass STAP-1085 01/01/06 Co-60 2.24 +/- 0.16 2.19 1.53 -2.84 Pass STAP-1085 01/01/06 Cs- 134 2.96 +/- 0.19 2.93 2.05 - 3.81 Pass STAP-1085 01/01/06 Cs- 137 2.64 +/- 0.20 2.53 1.77 -3.29 Pass STAP-108 5 ' 01/01/06 Pu-238 0.03 +/- 0.01 0.07 0.05 -0.09 Fail STAP- 1085e 01/01/06 Pu-239/40 < 0.01 0.00 Pass STAP-1085 01/01/06 Sr-90 0.77 +/- 0.21 0.79 0.55 - 1.03 Pass STAP-1085 01/01/06 U-233/4 0.03 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1085 01/01/06 U-238 0.02 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1085 01/01/06 Zn-65 3.94 +/- 0.44 3.42 2.40 - 4.45 Pass E- 10

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPr ENVIRONMENTAL, INC., 2006 (Page 2 of 3) b Concentration Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1086 01/01/06 Am-241 1.29 +/- 0.,05 1.30 0.91 - 1.69 Pass STW-1 086 01/01/06 Co-57 177.10 +/- 1.00 166.12 116.28 -215.96 Pass STW-1 086 01/01/06 Co-60 158.30 +/- 1.00 153.50 107.45 -199.55 Pass STW-1 086 01/01/06 Cs-1 34 96.40 +/- 1.50 95.10 66.57 - 123.63 Pass STW-1 086 e 01/01/06 Cs-1 37 < 0.80 0.00 Pass STW-1086 01/01/06 Fe-55 102.50 +/- 18.10 129.60 90.72 - 168.48 Pass STW-1086 01/01/06 H-3 956.60 +/- 16.50 952.01 666.41 -1238.00 Pass STW-1086 01/01/06 Mn-54 335.30 +/- 2.20 315.00 220.50 - 409.50 Pass STW-1 086 01/01/06 Ni-63 62.90 +/- 3.60 60.34 42.24 - 78.44 Pass STW-1 086 01/01/06 Pu-238 0.96 +/- 0.07 0.91 0.70 - 1.30 Pass STW-1086 e 01/01/06 Pu-239/40 < 0.20 0.00 Pass STW-1 086 01/01/06 Sr-90 12.80 +/- 1.60 13.16 9.21 -17.11 Pass STW-1086 01/01/06 Tc-99 22.30 +/- 1.20 23.38 16.37 - 30.39 Pass STW-1086 01/01/06 U-233/4 2.02 +/- 0.12 2.09 1.46 -2.72 Pass STW-1086 01/01/06 U-238 2.03 +/- 0.12 2.17 1.52 -2.82 Pass STW-1086 01/01/06 Zn-65 249.50 +/- 3.40 228.16 159.71 -296.61 Pass STW-1087 01/01/06 Gr. Alpha 0.59 +/- 0.10 0.58 0.00- 1.16 Pass STW-1087 01/01/06 Gr. Beta 1.69 +/- 0.07 1.13 0.56 -1.70 Pass STVE-1098 e 07/01/06 Co-57 <0.14 0.00 Pass STVE-1098 g 07/01/06 Co-60 6.89 +/- 0.17 5.81 4.06 -7.55 Pass STVE-1098 07/01/06 Cs-134 8.46 +/- 0.16 7.49 5.24 - 9.73 Pass STVE-1 098 07/01/06 Cs-137 6.87 +/- 0.29 5.50 3.85 -7.14 Pass STVE-1098 07/01/06 Mn-54 10.36 +/- 0.29 8.35 5.85 - 10.86 Pass STVE-1098 07/01/06 Zn-65 7.46 +/- 0.50 5.98 4.19 -7.78 Pass STSO-1099 07/01/06 Am-241 130.00 +/- 11.60 105.47 73.83 - 137.11 Pass STSO-1099 07/01/06 Co-57 784.90 +/- 3.80 676.33 473.43 - 879.23 Pass STSO-1099 07/01/06 Co-60 2.10 +/- 0.90 1.98 0.00 - 5.00 Pass STSO-1099 07/01/06 Cs-134 500.70 +/- 7.40 452.13 316.49 - 587.77 Pass STSO-1099 07/01/06 Cs-137 624.20 +/- 4.90 525.73 368.01 - 683.45 Pass STSO-1099 07/01/06 K-40 701.30 +/- 3.40 604.00 423.00 - 785.00 Pass STSO-1099 07/01/06 Mn-54 699.20 +/- 5.20 594.25 415.98 -772.52 Pass STSO-1099 07/01/06 Ni-63 614.40 +/- 17.10 672.30 470.60 - 874.00 Pass STSO-1099 07/01/06 Pu-238 79.90 +/- 5.80 82.00 57.00 - 107.00 Pass STSO- 1099 e 07/01/06 Pu-239/40 < 0.70 0.00 Pass STSO-1099 07/01/06 U-233/4 150.50 +/- 5.90 152.44 106.71 - 198.17 Pass STSO-1 099 07/01/06 U-238 151.60 +/- 6.00 158.73 111.11 - 206.35 Pass STSO-1099 07/01/06 Zn-65 1021.90 +/- 9.20 903.61 632.53 - 1175.00 Pass E-11

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

ENVIRONMENTAL, INC., 2006 (Page 3 of 3)

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP-1 100 07/01/06 Am-241 0.16 +/- 0.03 0.14 0.10 -0.19 Pass STAP-1 100 07/01/06 Co-57 2.17 +/- 0.06 2.58 1.81 -3.36 Pass STAP-1 100 07/01/06 Co-60 1.38 +/- 0.07 1.58 1.10 -2.05 Pass STAP-1 100 07/01/06 Cs-134 2.52 +/- 0.13 3.15 2.20 - 4.09 Pass STAP-1 100 07/01/06 Cs-137 1.64 +/- 0.08 1.81 1.26 -2.35 Pass STAP-1 100 07/01/06 Mn-54 1.76 +/- 0.18 1.92 1.34 -2.50 Pass STAP-1 100 07/01/06 Pu-238 0.09 +/- 0.02 0.12 0.08 -0.15 Pass STAP-1 100 07/01/06 Sr-90 0.66 +/- 0.21 0.62 0.43 - 0.81 Pass STAP-1 100 07/01/06 U-233/4 0.15 +/- 0.02 0.13 0.09 -0.17 Pass STAP-1 100 07/01/06 U-238 0.13 +/- 0.02 0.14 0.10 -0.18 Pass STAP-1 100 e 07/01/06 Zn-65 < 0.07 0.00 Pass STAP-1101 07/01/06 Gr. Alpha 0.08 +/- 0.03 0.29 0.00 - 0.58 Pass STAP-1101 07/01/06 Gr. Beta 0.41 +/- 0.05 0.36 0.18 -0.54 Pass STW-1102 07/01/06 Gr. Alpha 0.76 +/- 0.07 1.03 0.00 -2.07. Pass STW-1102 07/01/06 Gr. Beta 1.23 +/- 0.06 1.03 0.52 -1.54 Pass STW-1103 07/01/06 Am-241 1.86 +/- 0.09 2.31 1.62 -3.00 Pass STW-1 103 07/01/06 Co-57 224.10 +/- 1.20 213.08 149.16 -277.00 Pass STW-1 103 07/01/06 Co-60 49.40 +/- 0.50 47.50 33.20 -61.80 Pass STW-1103 07/01/06 Cs-134 112.70 +/- 0.90 112.82 78.97 - 146.66 Pass STW-1 103 07/01/06 Cs-137 206.60 +/- 1.40 196.14 137.30 -254.98 Pass STW-1103 07/01/06 Fe-55 138.40 +/- 5.40 165.40 115.80 -215.00 Pass STW-1103 07/01/06 H-3 446.50 +/- 11.80 428.85 300.20 -557.50 Pass STW-1103 e 07/01/06 Mn-54 < 0.30 0.00 Pass STW-1103 07/01/06 Ni-63 116.70 +/- 3.60 118.62 83.03 - 154.21 Pass STW-1103 07/01/06 Pu-238 1.27 +/- 0.07 1.39 0.97 -1.81 Pass STW-1103 07/01/06 Pu-239/40 1.67 +/- 0.08 1.94 1.36 -2.52 Pass STW-1103 07/01/06 Sr-90 16.40 +/- 1.90 15.69 10.98 -20.40 Pass STW-1103 07/01/06 Tc-99 29.40 +/- 1.10 27.15 19.00 -35.29 Pass STW-1103 07/01/06 U-233/4 1.97 +/- 0.08 2.15 1.50 -2.80 Pass STW-1103 07/01/06 U-238 1.97 +/- 0.08 2.22 1.55 -2.89 Pass STW-1103 07/01/06 Zn-65 192.50 +/- 2.40 176.37 123.46 -229.28 Pass Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.

e Included in the MAPEP as a false positive.

f Difficulties with the analyses for transuranics isoiopes in solid samples (Filters, Soil and vegetation),

were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:

Pu-238, 53.1 +/- 5.3 bq/kg. Pu-239/240, 42.4 +/- 4.7 bq/kg. U-233/4, 33.3 +/- 3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.

9 The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.

E - 12

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January Through 31 December 2006 Prepared By Teledyne Brown Engineering Environmental Services Sim An E-elon Company Three Mile Island Nuclear Station Middletown, PA 17057 April 2007

Table Of Contents I. Sum mary and Conclusions ................................................................................................ 1 I1.Intro d uctio n ............................................... ........................................................................ 4 A. O bjectives of the RG PP .................................................................................. 4 B. Implem entation of the O bjectives .................................................................... 5 C. Program Description ........................................................................................ 5 D. Characteristics of Tritium (H-3) ......................................................................... 6 III. Program Description .................................................................................................... 7 A. Sam ple Analysis ............................................................................................... 7 B. Data Interpretation ............................................................................................. 7 IV. Results and Discussion .............................................................................................. 8 A. G roundwater Results ........................................................................................ 8 D. Leaks, Spills, and Releases .............................................................................. 9 G . Actions Taken .................................................................................................. 10

Appendices Appendix A Location Designation Tables Table A-I: Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2006 Figures Figure A-I: Sampling Locations Near the Site Boundary of the Three Mile Island Nuclear Station, 2006 Appendix B Data Tables Tables 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, 2006.

Table B-1.2 Concentrations of Tritium and Strontium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2006.

Table B-1.3 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

Table B-1.4 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2006.

ii

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 2006. During that time period, 613 analyses were performed on 340 samples from 76 locations. The monitoring was conducted in two phases. Phase 1 of the monitoring was part of a comprehensive study initiated by Exelon to determine whether groundwater or surface water at and in the vicinity of Three Mile Island Nuclear Station had been adversely impacted by any releases of radionuclides. Phase 1 was conducted by Connestoga Rovers and Associates (CRA) and the conclusions were made available to state and federal regulators as well as the public on an Exelon web site httpillwww.exeloncorp.com/ourcompanies/powergen/nuclearlTritium htm. Phase 2 of the RGPP was conducted to initiate follow up of Phase 1 and begin long-term monitoring at groundwater and surface water 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 2006 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 any of the groundwater or surface water samples tested.

Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 46 of 76 groundwater monitoring locations. The tritium concentrations ranged from 201 +/- 111 pCi/L to 14,100 + 1460 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of isolated historical releases 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/nuclearfTritium. 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 2006. 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 2006.

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. Exelon and its consultant identified additional groundwater well locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as Well as the public on an Exelon web site in station specific reports.

http://www.exeloncorp.com/ourcompanies/powergen/nuclearlTritiu m.htm

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 following EPA methods. 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 2006.

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 76 locations were analyzed for tritium activity (Table B-1.1 and B-1.2, Appendix B). Tritium values ranged from the detection limit to 14,100 pCi/I. Two of the locations were offsite drinking water wells with no detectable concentration of tritium.

The results of samples from the initial stage of Phase 1 wells were used in conjunction with a discovered leak from a condensate storage tank underground line to locate additional monitoring wells.

Elevated tritium results elsewhere in the owner controlled area are attributable to historical leaks that have been reported previously in Annual Radiological Environmental Operating Reports (AREOR).

Strontium Strontium-90 was detected in one of 136 samples at a concentration of 1.4 pCi/liter. This was less than the required detection limit of 2.0 pCi/liter, and reanalysis of this sample showed no detectable Strontium-90. (Table B-1.3 and B-1.4, Appendix B).

Gamma Emitters and Strontium Potassium-40 was detected in 28 of 137 samples. The concentrations ranged from 24 pCi/liter to 263 pCi/liter. No other gamma emitting nuclides were detected. (Table B-1.5 and B-1.6, Appendix B).

B. Leaks, Spills, and Releases As discussed above, a leak was discovered in a condensate storage tank underground pipe in June 2006. Water with tritium activity was found leaking from a manhole in TMI's North Parking Lot. The source of the water was TMI secondary plant water and the concentration of tritium in the source tank was 5.12 E-5 uCi/ml. An investigation was performed under TMI's Corrective Action Program in issue report number 495884.

The results of the investigation determined that water had leaked from a pipe into a telephone equipment room and flowed through conduit to the manhole. The leak developed in a 4" condensate tank underground de-ice line. Backfill material caused a flaw in the external pipe coating which caused localized corrosion and a through wall leak. The line was excavated and repaired. Offsite groundwater tritium concentrations were unaffected by this event.

On August 4, 2006, Operations was bypassing FS-T-1 (Altitude Tank) in preparation for scheduled maintenance on FS-T-1. While performing the bypass evolution, an Auxiliary Operator stationed at the Pretreatment Building reported observing water emerging from the blacktop/pavement and draining into a yard drain. A pressure spike caused the pipe to leak the leak was contained and diverted. Approximately 2140 gals with a tritium concentration of 1.78E-6 uCi/mI was estimated to have flowed to the yard drain system before the leak was contained. Issue Report 517006 documents this event in TMI's corrective action program.

On October 24, 2006, a leak collection bucket for the Industrial Coolers was found to be overflowing due to the sump pump breaker being tripped.

The breaker was reset, and approximately 1440 gallons of water with a tritium concentration of 1.34 E-6 uCi/mI was estimated to have gone into the roof drain system, and then to the yard drains before the spill was discovered. Issue Report 548691 documents this event in TMI's corrective action program.

As a result of the comprehensive groundwater study performed by consultants at TMI during 2006, peripheral wells near the edge of the island were installed. Because of low levels of tritium being present in these wells notifications were made to federal, state and local officials that TMI now believes very low levels of tritium in groundwater are now migrating from the site into the river. A release L200612627 was calculated to account for this unplanned release from the site boundary. A detailed hydrogeologist calculation determined the groundwater flow from the island and the expected average tritium concentration. The adult total body dose was determined to be 2.34E-2 mrem/yr. Corrective actions for this issue were under issue report 528426.

C. Actions Taken

1. Compensatory Actions TMI has implemented a buried pipe program in accordance with ER-AA-5400, Buried Pipe and Raw Water Corrosion Guide. TMI has completed the identification, database and ranking phases of the program. Soil data collection is on going and mitigation for some pipes will occur in 2007. Funding is in place for 2007 to put in three buried anodes. Funding in 2006 was used to purchase equipment to collect soil data. A training session completed recently for the engineering department shared the extent of condition for TMI's recent underground pipe leaks.

2. Installation of Monitoring Wells TMI installed 31 new monitoring wells in 2006. TMI now has over 60 monitoring locations that it regularly samples for trending historical leaks and detecting new leaks.

Intentionally left blank APPENDIX A LOCATION DESIGNATION & DISTANCE Figure A - 1

TABLE A-I: Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2006 Site Site Type

1. 3 Monitoring Well 48N Monitoring Well 48S Production Potable Well.

A3-2 Surface Water CLOSED DEMO DW10 Monitoring Well E1-2 Monitoring Well, Offsite FS-H22 Monitoring Well GP-1 Monitoring Well GP-12 Monitoring Well GP-6 Monitoring Well GP-8 Monitoring Well GP-9 Monitoring Well J11-2 Surface Water MS-1 Monitoring Well MS-19 Monitoring Well MS-2 Monitoring Well MS-20 Monitoring Well MS-21 Monitoring Well MS-22 Monitoring Well MS-3 Monitoring Well MS-4 Monitoring Well MS-5 Monitoring Well MS-6 Monitoring Well MS-7 Monitoring Well MS-8 Monitoring Well MW-1 Monitoring Well MW-2 Monitoring Well MW-3 Monitoring Well MW-4 Monitoring Well N2-1 Monitoring Well, Offsite NW-A Production Well NW-B Production Well NW-C Production Well NW-CW Clearwell OS-1 3B Monitoring Well OS-14 Monitoring Well OS-16 Monitoring Well OS-17 Monitoring Well OS-18 Monitoring Well OSF Production Well Q9-1 Surface Water RW-1 Monitoring Well RW-2 Monitoring Well SW-E-1 Surface Water SW-E-2 Surface Water SW-E-3 Surface Water MW-TMI-10D Monitoring Well MW-TMI-101 Monitoring Well MW-TMI-10S Monitoring Well MW-TMI-12S Monitoring Well MW-TMI-131 Monitoring Well MW-TMI-13S Monitoring Well MW-TMI-14D Monitoring Well MW-TMI-141 Monitoring Well MW-TMI-14S Monitoring Well MW-TMI-16D Monitoring Well MW-TMI-161 Monitoring Well

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2006 Site Site Type MW-TMI-1 7D Monitoring Well MW-TMI-171 Monitoring Well MW-TMI-18D Monitoring Well MW-TMI-19D Monitoring Well MW-TMI-191 Monitoring Well MW-TMI-1 D Monitoring Well MW-TMI-2D Monitoring Well MW-TMI-31 Monitoring Well MW-TMI-41 Monitoring Well MW-TMI-4S Monitoring Well MW-TMI-5D Monitoring Well MW-TMI-6D Monitoring Well MW-TMI-61 Monitoring Well MW-TMI-7S Monitoring Well MW-TMI-8S Monitoring Well MW-TMI-91 Monitoring Well TRAINING CENTER Monitoring Well UST CLOSURE WELL Monitoring Well

0 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 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90

1. 3 06/06/06 < 183 < 1.36

1. 3 10/23/06 360 +/- 118" < 0.78

1. 3 10/23/06 236 +/- 124" 48N 05/31/06 223 +/- 114 < 1.70 48N 05/31/06 < 175 < 1.53 48S 05/31/06 223 +/- 116 < 1.17 48S 10/31/06 <154 * < 1.35 48S 01/19/06 184 +/- 103 48S 07/24/06 < 178

• CLOSED DEMO DW10 06/13/06 < 167 < 1.24 CLOSED DEMO DW10 10/31/06 <154 < 1.16 E1-2 06/06/06 < 167 < 1.18 E1-2 10/31/06 < 179 * < 1.70 E1-2 01/19/06 < 164 FS-H22 05/04/06 515 +/- 132 GP-1 01/19/06 < 176 GP-1 04120/06 432 +/- 148 GP-12 01/19/06 < 168 GP-6 10/27/06 348 +/- 102*

GP-6 10/27/06 263 +/- 121 GP-6 01/19/06 < 168 GP-6 04/20/06 224 +/- 122 GP-8 10/27/06 359 +/- 120*

GP-8 10/27/06 400 +/- 125" GP-8 01/19/06 < 175 GP-9 01/19/06 < 168 GP-9 04/20/06 393 +/- 131 MS-1 01/16/06 561 +/- 115 MS-1 03/28/06 728 +/- 134 MS-1 04/20/06 312 +/- 123 MS-1 04/24/06 322 +/- 115 MS-1 04/26/06 305 +/- 116 MS-1 05/01/06 < 176 MS-1 05/03/06 289 +/- 117 MS-1 05/08/06 701 +/- 142 MS-1 05/11/06 504 +/- 130 MS-1 05/18/06 1430 +/- 198 MS-1 07/24/06 576 +/- 148*

MS-1 05/31/06 2870 +/- 176 < 0.76 MS-1 10/26/06 356 +/- 116* < 0.81 MS-1 10/26/06 < 181

• MS-19 01/16/06 187 +/- 105 MS-19 04/24/06 609 +/- 149 MS-19 04/26/06 246 +/- 116 MS-19 05/01/06 < 183 MS-1 9 05/03/06 244 +/- 116 MS-19 05/08/06 321 +/- 124 MS-19 05/11/06 255 +/- 112 MS-19 05/18/06 243 +/- 113

• Indicates Distilled Analysis Indicates Fast Analysis 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 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90 MS-19 07124/06 < 182 MS-19 05/31/06 254 +/- 117 < 1.76 **

MS-19 10/25/06 416 +/- 114* 1.37 +/- 0.51" MS-19 10/25/06 456 +/- 132* < 1.08 MS-2 01/16/06 431 +/- 111 MS-2 03/28/06 356 +/- 118 MS-2 06/02/06 < 156 < 1.05 MS-2 10/24/06 < 173 < 0.79 MS-20 01/16/06 454 +/- 113 MS-20 03/02/06 488 +/- 119 MS-20 03/28/06 482 +/- 120 MS-20 04/20/06 555 +/- 137 MS-20 04/24/06 504 +/- 126 MS-20 04/26/06 444 +/- 131 MS-20 05/01/06 < 199 MS-20 05/03/06 462 +/- 130 MS-20 05/08/06 356 +/- 118 MS-20 05/11/06 362 +/- 117 MS-20 05/18/06 569 +/- 135 MS-20 07/25/06 317 +/- 127*

MS-20 06/07/06 390 +/- 127 < 1.88 MS-20 10/24/06 732 +/- 155* < 0.98 MS-20 10/24/06 663 +/- 125*

MS-20 04/09/07 295 +/- 114*

MS-21 01/16/06 382 +/- 111 MS-21 04/20/06 358 +/- 137 MS-21 04/24/06 506 +/- 127 MS-21 04/26/06 314 +/- 123 MS-21 05/01/06 523 +/- 122 MS-21 05/03/06 598 +/- 134 MS-21 05/08/06 582 +/- 135 MS-21 05/11/06 591 +/- 127 MS-21 05/18/06 566 +/- 135 MS-21 05/25/06 389 +/- 129 MS-21 07/25/06 207 +/- 122*

MS-21 06/07/06 408 +/- 129 < 1.60 MS-21 10/25/06 524 +/- 132* < 0.87 MS-21 10/25/06 299 +/- 124*

MS-21 04/02/07 451 +/- 124*

MS-22 01/16/06 477 +/- 115 MS-22 04/20106 768 +/- 158 MS-22 04/24/06 4040 +/- 445 MS-22 04/26/06 826 +/- 179 MS-22 05/01/06 676 +/- 136 MS-22 05/03/06 949 +/- 153 MS-22 05/08/06 927 +/- 152 MS-22 05/11/06 1160 +/- 172 MS-22 05/18/06 1380 +/- 191 MS-22 05/25/06 950 +/- 237

• Indicates Distilled Analysis

• • Indicates Fast Analysis B-2

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 2006 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90 MS-22 07/25/06 1170 +/- 178*

MS-22 06/07/06 1050 +/- 166 < 1.45 MS-22 10/25/06 1120 +/- 123" < 1.20 MS-22 10/25/06 775 +/- 185" MS-3 06/05/06 278 +/- 122 < 1.54 MS-3 10/25/06 278 +/- 120* < 0.82 MS-3 10/25/06 271 +/- 118*

MS-3 DUP 06/05/06 < 151 < 1.32 MS-4 01/16/06 563 +/- 115 MS-4 03/28/06 480 +/- 121 MS-4 06/07/06 472 +/- 131 < 1.75 **

MS-4 10/25/06 195 +/- 1085 < 0.87 MS-4 DUP 06/07/06 426 +/- 128 < 1.62 MS-5 01/16/06 233 +/- 106 MS-5 06/06/06 185 +/- 120 < 1.64 MS-5 10/24/06 < 166 * < 0.82 **

MS-6 06/06/06 < 180 < 1.82 MS-6 10/24/06 < 173 * < 1.10 **

MS-7 01/16/06 334 +/- 108 MS-7 05/25/06 205 +/- 126 MS-7 05/31/06 305 +/- 115 < 1.51 MS-7 10/25/06 201 +/- 111" < 0.82 MS-7 10/25/06 262 +/- 126" MS-8 01/16/06 926 +/- 125 MS-8 03/28/06 1050 +/- 136 MS-8 04/20/06 928 +/- 155 MS-8 04/24/06 983 +/- 155 MS-8 04/26/06 733 +/- 140 MS-8 05/01/06 862 +/- 131 MS-8 05/03/06 866 +/- 148 MS-8 05/08/06 980 +/- 162 MS-8 05/11/06 1080 +/- 166 MS-8 05/18/06 1190 +/- 174 MS-8 05/25/06 1090 +/- 172 MS-8 06/05/06 799 +/- 126 < 1.00 MS-8 10/25/06 314 +/- 123' < 0.83 **

MS-8 10/25/06 276 +/- 123*

MW-1 01116/06 223 +/- 104 MW-1 05/26/06 < 167 < 1.95

• MW-1 10/31/06 355 +/- 118" < 1.05 MW-1 10/31/06 239 +/- 121*

MW-2 01/16/06 < 160 MW-2 05/26/06 263 +/- 121 < 1.56 **

MW-2 10/31/06 181 +/- 115" < 1.48 MW-3 05/26/06 180 +/- 113 < 1.49 **

MW-3 10/31/06 < 180 * < 1.38 MW-4 01/16/06 301 +/- 106 MW-4 05/26/06 < 169 < 0.81 MW-4 10/30/06 281 +/- 117' < 1.45 **

• Indicates Distilled Analysis

• • Indicates Fast Analysis 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 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90 MW-4 10/30/06 < 190

• MW-TMI-10D 06/13/06 522 +/- 130 < 1.81 MW-TMI-I 0D 10/27/06 396 +/- 133* < 1.01 MW-TMI-10D 10/27/06 555 +/- 140*

MW-TMI-10D 07/24/06 714 +/- 149" MW-TMI-10D DUP 06113/06 631 +/- 136 < 1.66 MW-TMI-101 06/01/06 13500 +/- 1390 < 1.23 MW-TMI-101 10/27/06 3750 +/- 240* < 1.33 MW-TMI-101 10/27/06 4190 +/- 488*

MW-TMI-101 10/27/06 3880 +/- 244* < 1.87 MW-TMI-101 10/27/06 4730 +/- 536*

MW-TMI-101 07/24/06 7180 +/- 769*

MW-TMI-10S 06/06/06 11500 +/- 1200 < 1.32 MW-TMI-10S 10/27/06 3250 +/- 227* < 1.26 MW-TMI-10S 10/27/06 3370 +/- 400*

MW-TM I-10S 07/24/06 14100 +/- 1460" MW-TMI-12S 06/13/06 2690 +/- 319

,k*

MW-TMI-12S 10/23/06 9230 +/- 1020" < 0.86 MW-TMI-12S 10/23/06 9010 +/- 505*

MW-TMI-12S 10/23/06 9370 +/- 1060' < 0.88 MW-TMI-12S 10/23/06 9280 +/- 514" MW-TMI-12S 04/02/07 5850 +/- 629*

MW-TMI-12S 04/09/07 5670 +/- 621" MW-TMI-12S 07/25/06 < 176

• MW-TM I-13H 04/02/07 3220 +/- 384*

MW-TMI-131 06/08/06 2250 +/- 161 < 0.92 MW-TMI-131 10/26/06 1770 +/- 254* < 0.81 MW-TMI-131 10/26/06 1570 +/- 155*

MW-TMI -131 04/02/07 3420 +/- 404*

MW-TMI-131 07/24/06 2270 +/- 282*

MW-TMI-13S 06/08/06 403 +/- 115 < 0.76 MW-TMI-13S 10/31/06 234 +/- 126* < 1.27 MW-TMI-13S 10/31/06 307 +/- 132*

MW-TMI-14D 06/13/06 1510 +/- 204 < 1.14 MW-TMI-14D 10/26/06 1950 +/- 276* < 0.84 MW-TMI-14D 10/26/06 1740 +/- 161*

MW-TMI-14D 07/24/06 1160 +/- 179*

MW-TMI-141 06/07/06 597 +/- 140 < 1.89 MW-TMI-141 10/26/06 664 +/- 139" < 0.88 MW-TMI-141 10/26/06 626 +/- 135*

MW-TMI-141 07/24/06 539 +/- 142*"

MW-TMI-14S 10/26/06 561 +/- 131" < 0.83 MW-TMI-14S 10/26/06 427 +/- 130*

MW-TMI-14S 07/24/06 294 +/- 127*

MW-TMI-16D 08/08/06 416 +/- 131* < 1.31 MW-TMI-16D 10/26/06 256 +/- 111* < 1.00 MW-TMI-16D 10/26/06 223 +/- 122*

MW-TMI-16D 04/09/07 4360 +/- 490*

MW-TMI-16H 04/09/07 17100 +/- 1750*

• Indicates Distilled Analysis Indicates Fast Analysis 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 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90 MW-TMI-161 08/08/06 504 +/-+135* < 1.59 MW-TMI-161 10/26/06 652 +/- 145* < 0.87 MW-TMI-161 10/26/06 635 +/- 134*

MW-TMI-161 10/26/06 513 +/- 130* < 0.87 MW-TMI-161 10/26/06 600 +/- 135*

MW-TMI-161 04/02/07 14400 +/- 1490*

MW-TMI-161 04/09/07 19200 +/- 1960*

MW-TMI-17D 08/04/06 < 177 * < 1.31 MW-TMI-17D 10/31/06 < 176 * < 1.59 MW-TMI-171 08/04/06 292 +/- 124* < 1.70 MW-TMI-171 10/31/06 252 +/- 125* < 1.32 MW-TMI-171 10/31/06 231 +/- 131*

MW-TMI-18D 08/08/06 225 +/- 119* < 1.30 MW-TMI-18D 10/30/06 200 +/- 115* < 1.39 MW-TMI-19D 08/09/06 317 +/- 126* < 1.39 MW-TMI-19D 08/09/06 331 +/- 129* < 1.51 MW-TMI-19D 10/30/06 200 +/- 120* < 1.18 MW-TMI-191 08/09/06 257 +/- 119* < 0.89 MW-TMI-191 10/30/06 381 +/- 121* < 0.95 MW-TMI-191 10/30/06 336 +/- 132*

MW-TM I-1D 06/01/06 440 +/- 127 < 0.99 MW-TMI-1D 10/30/06 395 +/- 125* < 0.68 MW-TM I-1D 10/30/06 431 +/- 134*

MW-TM I-1D 07/24/06 384 +/- 132*

MW-TMI-2D 06/01/06 954 +/- 153 < 1.65 MW-TMI-2D 10/30/06 943 +/- 154* < 1.61 MW-TMI-2D 10/30/06 886 +/- 165*

MW-TMI-2D 07/24/06 1130 +/- 176*

MW-TMI-31 06/08/06 292 +/- 112 < 0.84 MW-TMI-31 11/01/06 322 +/- 123* < 1.47 MW-TMI-31 11/01/06 227 +/- 130*

MW-TMI-41 06/01/06 236 +/- 114 < 1.40 MW-TMI-41 10/30/06 < 181 * < 1.17 MW-TMI-4S 06/08/06

• 166 < 0.96 MW-TMI-4S 10/31/06 < 182

• MW-TMI-5D 06/08/06 298 +/- 112 < 0.57 MW-TMI-5D 10/30/06 195 +/- 114* < 1.64 MW-TMI-6D 05/31/06 275 +/- 117 < 1.34 MW-TMI-6D 10/25/06 396 +/- 121* < 0.83 MW-TMI-6D 10/25/06 416 +/- 130*

MW-TMI-61 05/31/06 772 +/- 144 < 1.63 MW-TMI-7S 06/08/06 237 +/- 117 < 1.18 MW-TMI-7S 10/31/06 < 176 * < 1.24 MW-TMI-8S 06/01/06 246 +/- 109 < 1.37 MW-TMI-8S 10/30/06 219 +/- 118* < 1.28 MW-TMI-8S 10/30/06 286 +/- 126*

MW-TMI-8S DUP 06/01/06 349 +/- 112 < 1.25 MW-TMI-91 08/04/06 198 +/- 119* < 1.56 MW-TMI-91 10/30/06 < 177 * < 1.16

• Indicates Distilled Analysis Indicates Fast Analysis B-5

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICALGROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90 N2-1 01/19/06 < 162 N2-1 06/06/06 < 180 < 1.54 N2-1 10/31/06 < 180 < 1.10 NW-A 02/02/06 11110 +/- 129 NW-A 04/20/06 ld480 +/- 203 NW-A 05/30/06 ld480 +/- 200 < 1.61 NW-A 10/29/06 754 +/- 147* < 1.88 NW-A 10/29/06 873 +/- 170*

NW-B 02/02/06 1 430 +/- 138 NW-B 04/20/06 1 390 +/- 195 NW-B 05/30/06 24420 +/- 293 < 0.74 NW-C 02/02/06 3 040 +/- 172 NW-C 04/20/06 3 740 +/- 423 NW-C 05/30/06 3E650 +/- 416

• 0.67 NW-C 10/29/06 31840 +/- 241" < 1.27 NW-C 10/29/06 3 570 +/- 429*

NW-C 10/29/06 3 520 +/- 227* < 1.02 **

NW-C 10/29/06 3 960 +/- 463*

NW-CW 02/02/06 1(080 +/- 130 NW-CW 04/20/06 1 440 +/- 202 OS-13B 06/05106 261 +/- 107 < 1.09 **

OS-14 01/16/06 < 166 OS-14 06/06/06 < 183 < 1.35 OS-16 10/24/06 < 172 < 1.04 OS-17 10/24/06 204 +/- 111* < 1.02 OS-17 10/24/06 355 +/- 119*

OS-18 01/19/06 347 +/- 111 OS-18 04/20/06 429 +/- 151 OS-18 04/24/06 431 +/- 123 OS-18 04/26/06 335 +/- 122 OS-18 05/01/06 < 190 OS-18 05/03/06 462 +/- 125 OS-18 05/08/06 337 +/- 123 OS-18 05/11/06 341 +/- 117 OS-18 05/18/06 498 +/- 131 OS-18 05/25/06 261 +/- 123 OS-18 07/24/06 < 178 OS-18 05/31/06 399 +/- 126 < 1.60 OS-18 10/31/06 261 +/- 124* < 1.07 OS-18 10/31/06 378 +/- 135*

OSF 01/19/06 526 +/- 114 OSF 04/20/06 523 +/- 133 OSF 04/24/06 538 +/- 131 OSF 04/26/06 497 +/- 126 OSF 05/01/06 477 +/- 121 OSF 05/03/06 575 +/- 133 OSF 05/08/06 548 +/- 133 OSF 05/11/06 408 +/- 121 OSF 05/18/06 565 +/- 135

• Indicates Distilled Analysis

• • Indicates Fast Analysis B-6

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 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90 OSF 05/30/06 424 +/- 124 < 1.16 OSF 10/31/06 +/- < 1.32 OSF 10/31/06 377 +/- 136*

OSF 10/31/06 491 +/- 127" RW-1 01/16/06 < 168 RW-1 03/02/06 < 171 RW-1 04/20/06 < 180 RW-1 04/24/06 286 +/- 115 RW-1 04/26/06 < 173 RW-1 05/01/06 < 181 RW-1 05/03/06 218 +/- 117 RW-1 05/08/06 < 178 RW-1 05/11/06 < 157 RW-1 05/18/06 268 +/- 111 RW-1 10/23/06 < 168 * < 0.92 RW-2 01/16/06 421 +/- 112 RW-2 03/02/06 424 +/- 115 RW-2 03/28/06 5580 +/- 224 RW-2 03/28/06 5960 +/- 652 RW-2 04/18/06 12000 +/- 1250 RW-2 04/20/06 11800 +/- 1310 RW-2 04/24/06 12400 +/- 1290 RW-2 04/26/06 10500 +/- 1090 RW-2 04/28/06 < 0.33 RW-2 05/01/06 5170 +/- 212 RW-2 05/03/06 3800 +/- 425 RW-2 05/05/06 3220 +/- 371 RW-2 05/08/06 2300 +/- 283 RW-2 05/11/06 2370 +/- 287 RW-2 05/18/06 2420 +/- 284 RW-2 05/25/06 2150 +/- 272 RW-2 07/25/06 436 +/- 138*

RW-2 06/06/06 5660 +/- 621 < 1.35 RW-2 10/23/06 7490 +/- 872* < 0.79 RW-2 10/23/06 7630 +/- 468*

RW-2 10/23/06 8410 +/- 937* < 0.80 RW-2 10/23/06 8150 +/- 462*

RW-2 04/09/07 11800 +/- 1230*

RW-2 Dup 04/24/06 12500 +/- 1300 RW-2 (24.39') 05/05/06 3660 +/- 417 RW-2 (26.39') 05/05/06 3180 +/- 370 RW-2 (28.39') 05/05/06 2860 +/- 339 RW-2 (30.39') 05/05/06 2950 +/- 345 RW-2 30.65FT 04/28/06 7950 +/- 254

• t RW-2 DUP 06/06/06 6700 +/- 723 < 1.56 t*

TRAINING CENTER 06/06/06 < 168 < 1.16 t*

TRAINING CENTER 10/31/06 < 177 * < 1.53 UST CLOSURE WELL 05/30/06 < 153 < 1.29 UST CLOSURE WELL 10/31/06 < 178 * < 1.51

• Indicates Distilled Analysis

• • Indicates Fast Analysis B]-7

TABLE B-I.2 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE H-3 Sr-90 uuiuUoU < 166

< 1.5 J1-2 06/06/06 < 178

< 1.5 Q9-1 06/06/06 < 170 SW-E-1 10/31/06 169 +/- 98* < 1.7 SW-E-2 10/31/06 157 +/- 96* < 1.2

• t SW-E-3 10/31/06 < 152 * < 1.4

• Indicates Distilled Analysis

• • Indicates Fast Analysis B]-8

TABLE B-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE 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

1. 3 06/06/06 < 46 < 70 <5 <5 <10 <5 <13 <5 <9 <6 <5 <29 <9

1. 3 10/23/06 < 17 < 23 <1 <2 <4 <1 <3 <2 <3 <1 <1 < 21 <7 48N 05/31/06 < 27 < 27 < 3 <3 <7 <3 <7 <3 <5 <3 <3 < 19 <7 48N 05/31/06 < 25 32 + 31 < 3 <3 <6 <3 <6 <3 <5 <3 <3 < 18 <5 48S 05/31/06 < 36 < 33 < 4 <4 <8 <4 .<9 <4 <7 <5 <4 < 23 <7 48S 10/31/06 < 31 < 69 < 3 <4 <8 <3 <6 <3 <7 <3 <3 < 42

• 14 A3-2 06/06/06 < 43 < 79 < 5 <5 <11 <5 <12 <5 <9 <5 <6 < 29 < 10 CLOSED DEMO DW10 06/13/06 < 29 < 59 < 3 <3 <6 <3 <8 <4 <6 <4 <4 < 14 <5 CLOSED DEMO DW10 10/31/06 < 27 < 49 < 2 <3 <7 <2 <5 <3 <5 <2 <2 < 38 <11 E1-2 06/06/06 < 45 < 73 < 5 <5 <9 <5 <15 <6 <8 < 10 <5 < 28 <9 E1-2 10/31/06 < 25 < 37 < 2 <3 <6 <2 <4 <3 <5 <2 <2 < 46 < 14 tz J1-2 06/06/06 < 36 < 37 < 4 <4 <8 <4 <9 <4 <7 <4 <4 < 19 <6 MS-1 05/31/06 < 37 < 65 < 4 <4 <8 <3 <9 <4 <7 <4 <4 < 24 <8 MS-1 10/26/06 < 27 < 18 < 2 <3 <6 <2 <5 <3 <5 <2 <2 < 32 < 11 MS-19 05/31/06 < 38 < 62 < 4 <4 <9 <4 <9 <5 <7 <5 <4 < 25 <8 MS-19 10/25/06 < 20 < 39 < 2 <2 <5 <2 <4 <2 <4 <2 <2 < 25 <8 MS-2 06/02/06 < 54 < 51 < 6 <6 <12 <5 <12 <6 <10 <6 <6 < 39 < 12 MS-2 10/24/06 < 22 < 39 < 2 <2 <6 <2 <4 <2 <4 <2 <2 < 29 *10 MS-20 06/07/06 < 36 < 38 < 4 <4 <9 <4 <9 <4 <7 <4 <4 < 19 <7 MS-20 10/24/06 < 22 < 16 < 2 <2 <6 <2 <4 <2 <4 <2 <2 < 42 < 14 MS-21 06/07/06 < 48 < 47 < 6 <6 <12 <6 <14 <6 <9 <7 <6 < 31 <11 MS-21 10/25/06 < 42 < 36 < 4 <5 <11 <4 <7 <5 <8 <4 <4 < 56 <15 MS-22 06/07/06 < 47 < 68 < 5 <5 <10 <5 <12 <6 <10 <7 <5 < 26 <9 MS-22 10/25/06 < 28 31 +/- 29 < 2 <3 <6 <2 <4 <3 <5 <2 <2 < 42 <15 MS-3 06/05/06 < 34 < 34 < 4 <4 <8 <4 <9 <4 <7 <4 <4 < 22 <8 MS-3 DUP 06/05/06 < 33 64 +/- 40 < 4 <3 <7 <4 <8 <4 <7 <4 <4 < 20 <7 MS-3 10/25/06 < 24 < 36 < 2 <2 <6 <2 <4 <3 <5 <2 <2 < 42 < 15 MS-4 06/07/06 < 48 < 47 < 6 <6 <10 <6 <13 <6 <10 <6 <6 < 30 < 11 MS-4 DUP 06/07/06 < 55 < 50 < 6 <6 <11 <5 <13 <6 <10 <7 <6 < 32 < 10 MS-4 10/25/06 < 19 < 41 < 2 <2 <5 <2 <3 <2 <4 <2 <2 < 25 <8 MS-5 06/06/06 < 31 < 35 < 4 <4 <8 <4 <9 <4 <6 <4 <3 < 19 <6 MS-5 10/24/06 < 24 < 18 < 2 <2 <6 <2 <4 <3 <4 <2 <2

• 40 < 14 MS-6 06/06/06 < 40 141 +/- 40 < 5 <5 <10 <5 <11 <5 <9 <5 <5 < 24 <8 MS-6 10/24/06 < 25 < 18 < 2 <3 <6 <2 <4 <3 <5 <2 <2 <*47 < 15 MS-7 05/31/06 < 45 < 84 < 5 <5 <11 <5 <12 <5 <10 <5 <5 < 30 < 10

TABLE B-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE 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 MS-7 10/25/06 < 22 < 16 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 27 <8 MS-8 06/05/06 < 46 90 +/- 48 <5 <5 <12 <5 <11 <5 <9 <6 <5 < 28 <8 MS-8 10/25/06 < 29 35 +/- 32 <3 <3 <7 <3 <5 <3 <6 <2 <3 < 42 < 11 MW-i 05/26/06 < 52 < 47 <5 <6 <13 <5 <14 <6 <10 <6 <6 < 36 < 10 MW-i 10/31/06 < 34 < 30 <3 <3 <9 <3 <6 <4 <7 <3 <3 < 44 < 15 MW-2 05/26/06 < 49 < 51 <5 <6 <12 <6 <12 <6 <10 <6 <5 < 35 < 13 MW-2 10/31/06 < 33 < 31 <3 <4 <8 <3 <7 <3 <6 <3 <3 < 45 < 15 MW-3 05/26/06 < 46 < 82 <5 <5 <10 <4 <11 <5 <9 <5 <5 < 33 < 10 MW-3 10/31/06 < 39 < 34 <3 <4 <9 <4 <7 <5 <7 <3 <3 < 53 < 14 MW-4 05/26/06 < 37 < 33 <4 <4 <9 <4 <8. <5 <8 <4 <4 < 30 < 10 MW-4 10/30/06 < 30 < 25 <3 <3 <7 <2 <6 <4 <6 <3 <3 < 43 < 13

! MW-TMI-10D 06/13/06 < 45 < 67 <5 <<5 <9 <5 <13 <5 <9 <7 <5 < 22 <6 MW-TMI-10D DUP 06/13/06 < 33 < 54 <4 <4 <8 <4 <11 <4 <7 <6 <4 < 16 <5 MW-TMI -100 10/27/06 < 18 < 23 <1 <2 <5 <1 <3 <2 <3 <1 , <1 < 39 < 12 MW-TMI-101 06/01/06 < 37 < 40 <4 <4 <9 <4 <10 <4 <8 <5 <4 < 23 <7 MW-TMI-101 10/27/06 < 20 < 12 <2 <2 <4 <2 <3 <2 <3 <1 <1 < 39 < 13 MW-TMI-101 10/27/06 < 21 < 15 <2 <2 <6 <2 <3 <2 <4 <2 <2 < 43 < 15 MW-TM I-lOS 06/06/06 < 50 < 56 <5 <5 <12 <5 <13 <6 <9 <6 <5 < 27 <9 MW-TM I-lOS 10/27/06 < 19 < 28 <1 <2 <5 <1 <3 <2 <4 <1 <2 < 40 < 14 MW-TMI-1 2S 10/23/06 < 35 < 62 <3 <4 <8 <3 <7 <4 <7 <3 <3 < 52 < 14 MW-TMI-12S 10/23/06 < 25 43 + 28 <2 <3 <7 <2 <4 <3 <4 <2 <2 < 45 < 15 MW-TMI-1 31 06/08/06 < 53 < 49 <6 <6 <11 <6 <16 <6 <10 <9 <6 < 28 <9

<3 <3 MW-TMI-131 10/26/06 < 31 < 63 <3 <3 <8 <4 <6 <4 <6 < 38 < 11 MW-TMI-1 3S 06/08/06 < 49 < 59 <5 <5 <11 <6 <15 <6 <10 <7 <6 < 28 < 10 MW-TMI-1 3S 10/31/06 < 21 < 17 <2 <2 <6 <2 <4 <3 <5 <2 <2 < 41 < 13 MW-TMI-14D 06/13/06 < 29 < 57 <3 <3 <7 <3 <9 <4 <6 <4 <4 < 14 <5 MW-TMI-14D 10/26/06 < 47 < 75 <4 <4 <11 <4 <8 <5 <8 <4 <4 < 57 < 14 MW-TMI-141 06/07/06 < 39 < 69 <5 <4 <10 <5 <12 <5 <8 <6 <4 < 22 <8 MW-TMI-141 10/26/06 < 19 < 17 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 23 <8 MW-TMI-14S 10/26/06 < 16 < 13 <1 <2 <4 <1 <3 <2 <3 <1 <2 < 20 <6 MW-TMI-16D 08/08/06 < 41 < 52 <5 <5 <11 <6 <11 <6 <9 <5 <5 < 20 <8 MW-TMI-16D 10/26/06 < 20 < 35 <2 <2 <5 <2 <3 <2 <4 <2 <2 < 23 <7 MW-TMI-161 08/08/06 < 40 < 49 <4 <5 <12 <6 <13 <6 <9 <5 <5 < 20 <7 MW-TMI-161 10/26/06 < 24 < 42 <2 <2 <6 <2 <5 <3 <5 <2 <2 < 28 <9 MW-TMI-161 10/26/06 < 17 < 14 <1 <2 <4 <2 <3 <2 <3 <1 <2 < 19 <6

TABLE B-I.3 CONCENTRATIONS OF GAMMA EMITTERS INWELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE 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 MW-TMI-17D 08/04/06 < 23 < 54 <3 <3 <5 <3 <5 <3 <4 <3 <3 < 11 <3 MW-TMI-17D 10/31/06

• 32 < 68 <3 <3 <9 <3 <7 <4 <7 <3 <3 < 45 < 14 MW-TMI-171 08/04/06 < 30 < 35 <3 <3 <7 <4 < 10 <4 <6 <4 <4 < 14 <5 MW-TMI-171 10/31/06

• 22 < 16 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 38 <13 MW-TMI-18D 08/08/06 < 43 < 46 <5 <5 < 10 <5 < 11 <6 <9 <5 <5 < 20 <7 MW-TMI-18D 10/30106 < 34 < 24 <3 <3 <8 <3 <5 <4 <6 <3 <3 < 47 < 15 MW-TMI-19D 08/09/06 < 56 < 72 <6 <6 <9 <6 < 11 <8 < 10 <7 <7 < 24 <6 MW-TMI-19D 08/09/06 < 46 < 87 <5 <5 < 11 <6 <12 <7 <9 <5 <6 < 19 <7 MW-TMI-19D 10/30/06 < 21 < 15 <2 <2 <5 <2 <3 <2 <4 <2 <2 < 46 < 12 MW-TMI-191 08/09/06 < 51

• 58 <6 <5 < 10 <5 < 12 <8 <9 <6 <5 < 22 <9 MW-TMI-191 10/30/06 < 21 < 16 <2 <2 <6 <2 <4 <2 <4 <2 <2 < 43 < 14 o

I MW-TMI-ID 06/01/06 < 33 169 + 43 < 3 <4 <8 <4 <8 <4 <6 <4 <4 < 21 <7 MW-TMI-1 D 10/30/06 < 21 89 + 46 < 1 <2 <5 <2 <3 <2 <4 <2 <2 < 38 < 13 MW-TMI-2D 06/01/06 < 38 < 39 <4 <4 <9 <4 < 10 <4 <8 <5 <4 < 22 <8 MW-TMI-2D 10/30/06 < 26 < 16 <2 <3 <6 <3 <4 <3 <5 <2 <2 < 46 < 14 MW-TMI-31 06/08/06

• 36 < 35 <4 <4 <8 <4 <9 <4 <7 <5 <4

• 20 <6 MW-TMI-31 11/01/06 < 30 43 +/- 39 < 3 <3 <7 <3 <5 <4 <6 <3 <3

• 40 < 13 MW-TMI-41 06/01/06 < 34 < 38 <3 <4 <8 <4 <8 <4 <7 <4 <4 < 21 <8 MW-TMI-41 10/30/06 < 22 < 28 <2 <2 <5 <2 <3 <2 <4 <2 <2 < 41

• 14 MW-TMI-4S 06/08/06

• 51 77 +/-54 <6 <6 < 13 <6 < 13 <6 < 10 <7 <6 < 29 < 10 MW-TMI-5D 06/08/06 < 54 < 52 <6 <6 < 11 <5 <11 <6 <9 <7 <6 < 27 <11 MW-TMI-5D 10/30/06 < 20 < 40 <2 <2 <5 <2 <3 <2 <4 <1 <2 < 37 < 13 MW-TMI-6D 05/31/06 < 40 < 41 <4 <5 < 10 <5 <9 <4 <8 <5 <5 < 24 <9 MW-TMI-6D 10/25/06 < 19 < 14 <2 <2 <5 <2 <3 <2 <4 <2 <2 < 24 <8 MW-TMI-61 05/31/06 < 40 < 39 <4 <4 <9 <4 < 10 <5 <8 <5 <4 < 27 <9 MW-TMI-7S 06/08/06 < 49 < 77 <5 <5 < 12 <6 < 14 <6 < 10 <7 <6

• 29 <8 MW-TMI-7S 10/31/06 < 19 < 32 <2 <2 <5 <2 <4 <2 <4 <1 <2

• 36 <13 MW-TMI-8S 06/01/06 < 36 < 38 <4 <4 <9 <4 <9 <4 <7 <4 <4

• 25 <9 MW-TMI-8S DUP 06/01/06

• 36 < 62 <4 <4 <8 <4 <8 <4 <7 <4 <4 < 25 <8 MW-TMI-8S 10/30/06

• 21 < 47 <2 <2 <5 <2 <4 <3 <5 <2 <2 < 43 < 14 MW-TMI-91 08/04/06 < 37 < 39 <4 <4 <9 <4 .< 14 <5 <7 <8 <5 < 18 <5 MW-TMI-91 10/30/06 < 26 < 20 <2 <3 <7 <3 <5 <3 <5 <2 <3 < 36 < 14 N2-1 06/06/06 < 33 67 ++/-37 <4 <4 <8 <4 <9 <4 <7 <5 <4 < 21 <7 N2-1 10/31/06 < 22 < 31 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 43 < 15 NW-A 05/30/06 < 40 < 41 <4 <4 < 10 <5 < 10 <5 <8 <5 < 5 < 29 <9

TABLE B-I.3 CONCENTRATIONS OF GAMMA EMITTERS INWELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE 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 NW-A 10/29/06 < 20 < 34 < 2 < 2 < 5 < 2 < 3 < 2 < 4 < 1 < 2 < 39 < 14 NW-B 05/30/06 < 39 < 65 < 4 < 4 < 9 < 4 <11 < 5 < 8 < 5 < 5 < 26 < 9 NW-C 05/30/06 < 31 < 54 < 4 < 4 < 7 < 3 < 8 <4 < 6 < 4 < 4 < 21 < 6 NW-C 10/29/06 < 28 < 27 < 3 < 3 < 7 < 3 < 6 < 3 < 5 < 2 < 3 < 45 < 15 NW-C 10/29/06 < 19 30 +/-27 < 2 < 2 < 5 < 2 < 3 < 2 < 4 < 1 < 2 < 40 < 13 OS-13B 06/05/06 < 51 < 47 < 5 < 6 < 12 < 6 < 14 < 6 < 10 < 6 < 6 < 30 <10 OS-14 06/06/06 < 30 < 35 < 3 < 4 < 8 < 4 < 8 <4 < 6 < 4 < 4 < 19 < 6 OS-16 10/24/06 < 26 < 17 < 2 < 3 < 6 < 2 < 4 < 3 < 5 < 2 < 2 < 47 < 14 OS-17 10/24/06 < 22 < 52 < 2 < 2 < 6 < 2  !<4 < 3 < 5 < 2 < 2 < 44 < 14 OS-18 05/31/06 < 39 < 70 < 4 < 4 < 9 < 4 < 10 <4 < 8 < 5 < 5 < 27 < 9 OS-18 10/31/06 < 25 36 32 < 2 < 3 < 6 < 3 < 4 < 3 < 5 < 2 < 2 < 46 < 12 W OSF 05/30/06 < 43 < 44 < 5 < 5 < 10 < 5 < 11 < 5 < 8 < 5 < 5 < 30 < 10 OSF 10/31/06 < 19 < 14 < 2 < 2 < 5 < 2 < 3 < 2 < 4 < 1 < 1 < 37 < 13 Q9-1 06/06/06 < 27 < 47 < 3 < 3 < 6 < 3 < 7 < 3 < 6 < 4 < 3 < 16 < 5 RW-1 10/23/06 < 30 < 55 < 2 < 3 < 8 < 3 < 5 < 3 < 6 < 2 < 2 < 54 < 15 RW-2 04/18/06 < 181 < 390 < 25 < 24 < 46 < 29 < 58 < 24 < 40 < 26 < 25 < 105 < 39 RW-2 04/28/06 < 52 81 +/-55 < 6 < 6 < 13 < 7 < 21 < 7 < 11 < 11 <6 < 26 < 10 RW-2 06/06/06 < 32 < 34 < 4 < 4 < 7 < 3 < 8 < 4 < 7 < 4 <4 < 19 < 6 RW-2 DUP 06/06/06 < 39 < 36 < 4 < 4 < 8 < 4 < 10 < 4 < 7 < 5 <4 < 22 < 7 RW-2 10/23/06 < 31 < 56 < 3 < 3 < 8 < 3 < 6 < 4 < 6 < 3 < 3 < 44 < 15 RW-2 10/23/06 < 19 < 13 < 2 < 2 < 5 < 2 <4 < 2 < 4 < 2 <2 < 28 < 8 TRAINING CENTER 06/06/06 < 46 101 47 < 5 < 5 < 12 < 5 < 14 < 6 < 10 < 7 <6 < 29 < 10 TRAINING CENTER 10/31/06 < 34 < 60 < 3 < 4 < 8 < 4 < 6 < 4 < 6 < 3 < 3 < 47 < 15 UST CLOSURE WELL 05/30/06 < 32 < 30 < 3 < 3 < 7 < 3 < 7 < 4 < 6 < 4 < 3 < 21 < 7 UST CLOSURE WELL 10/31/06 < 27 < 53 < 2 < 3 < 7 < 2 < 5 < 3 < 5 < 2 <2 < 36 < 13

TABLE B-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION 2006 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION LOCATION DATE 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 SW-E-1 10/31/06 < 36 < 62 <3 <4 <9 <3 <7 <4 <7 <3 <3 <47 <12 SW-E-2 10/31/06 < 31 156 +38 <3 <3 <8 <3 <6 <3 <6 <3 <3 <40 <13 SW-E-3 10/31/06 < 27 218 + 44 < 3 <3 <7 <3 <5 <3 <5 <2 <3 <36 <13

Intentionally left blank