ML081300255

Transmittal of 2007 Radiological Environmental Monitoring Program Report - Redacted Version

ML081300255
Person / Time
Site:	Crane
Issue date:	04/28/2008
From:	Dougherty T AmerGen Energy Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML081300255 (165)

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AmerGen5.

AmerGen Energy Company, LLC Three Mile Island Unit 1 Route 441 South, P.O. Box 48o Middletown, PA 17057 Telephone: 717-948-8ooo An Exelon Company 5pril 28, 2008 28-08-20098 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:

2007 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, 2007, for the Three Mile Island Nuclear Station.

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

Sincerely, Thomas J.,1Iou 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 08034 625

Docket No:

50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS l and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2007 Prepared By Teledyne Brown Engineering Environmental Services An Exelon Company Three Mile Island Nuclear Station Middletown, PA 17057 April 2008

Table Of Contents I. Sum m ary and Conclusions............................................................................................

1 I1. In tro d u c tio n........................................................................................................................

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

3 B. Im plem entation of the O bjectives....................................................................

4 I1. Program Description.....................................................................................................

4 A. Sam ple Collection.............................................................................................

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

6 C. Data Interpretation...........................................................................................

7 D. Program Exceptions........................................................................................

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

11 IV. Results and Discussion............................................................................................

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

11

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

11

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

12

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

13

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

14

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

14

6. Fish......................................................................................................

15

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

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

16

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

16

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

16

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

17

2. Terrestrial.............................................................................................

17

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

17

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

17 C. Am bient G am m a Radiation............................................................................

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

19 E. Radiological Im pact of TM INS O perations......................................................

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

27 V. References......................................................................................................................

28

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Appendix B Tables Table B-i:

Table B-2:

Table B-3:

Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2007 Location Designation, Distance & Direction And Sample Collection &

Analytical Methods Location Designation and Identification System for the Three Mile Island Nuclear Station Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2007 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2007 Figures Figure B-i:

Figure B-2:

Figure B-3:

Appendix C Tables Table C-1.1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2007 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2007 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2007 Data Tables and Figures - Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

ii

Table C-1.2 Table C-1.3 Table C-11.1 Table C-11.2 Table C-11.3 Table C-I1.4 Table C-111.1 Table C-111.2 Table C-IV. 1 Table C-V.1 Table C-V.2 Table C-VI. 1 Table C-VII.1 Table C-VII.2 Table C-VII.3 Table C-VIII.1 Table C-IX.1 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

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, 2007.

Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Tritium and Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Strontium in Predator and Bottom Feeder (Fish)

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

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, 2007.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

iii

Table C-IX.2 Table C-IX.3 Table C-X.1 Table C-XI.1 Table C-XI.2 Table C-XI.3 Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Figure C-7 Figure C-8 Figure C-9 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Quarterly TLD Results for Three Mile Island Nuclear Station, 2007.

Mean Quarterly TLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2007.

Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2007.

Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2007.

Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2007.

Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2007.

Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2007.

Mean Cesium-1 37 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2007.

Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2007.

Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007.

Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2007.

Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2007.

iv

Appendix D Tables Table D-I.1 Table D-I.2 Table D-1.3 Table D-I.4 Table D-II.1 Table D-Ill.1 Table D-IV.1 Table D-V.1 Table D-V.2 Table D-VI.1 Figures Figure D-1 Figure D-2 Appendix E Tables Table E-1 Data Tables and Figures - Comparison Laboratory Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2007.

Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Iodine-1 31 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2007.

Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2007.

Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007 v

Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007 Table E-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2007 Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2007 Table E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2007 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 2007 through 31 December 2007. During that time period, 1,718 analyses were performed on 1318 samples. In assessing all the data gathered for this report and comparing these results with preoperational data and operational REMP data, it was concluded that the operation of TMINS had no adverse radiological impact on the environment.

Surface, drinking, effluent, and storm water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Surface, drinking, and effluent water samples were also analyzed for concentrations of 1-131. Drinking and effluent water samples were also analyzed for concentrations of gross beta.

Effluent water samples were also analyzed for concentrations of Sr-89 and Sr-90.

All groundwater results are now being reported in the ARGPPR, Appendix F. No 1-131, Sr-89 and Sr-90 activities were detected. Gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in several monthly surface water, drinking water, effluent water and storm water samples was due to TMINS activities or releases. The calculated dose due to the drinking water samples was <0.008 mrem. This dose is a small fraction of the 10 CFR 50 Appendix I dose limits. No other fission or activation products potentially attributed to TMI release were detected.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected. No fission or activation products were detected in fish samples. Cesuim-137 was detected in sediment samples at very low levels (just above LLD) and are not distinguishable from background levels.

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

High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.

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

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

Food Product samples were analyzed for concentrations of gamma emitting nuclides (including 1-131) and Sr-90. Sr-90 activities were detected in both the indicator and control samples. This was a result of plant uptake of Sr-90 in soil as a result of past nuclear weapons testing.

Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No 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 2007 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 2007 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 2007 through 31 December 2007.

A.

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

1.

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

2.

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

3.

To verify inplant controls for the containment of radioactive materials.

4.

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

5.

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

6.

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

B.

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

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

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

III.

Program Description A.

Sample Collection Samples for the TMINS REMP were collected for 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 2007. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, storm water, fish, and sediment. Two gallon water samples were collected monthly from continuous samplers located at three surface water locations (A3-2, J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and 09-1), and one effluent water location (K1-1). Control locations were A3-2 and Q9-1. Quarterly water samples were taken from one storm water runoff location (EDCB). All groundwater results are now being reported in the ARGPPR, Appendix F. All water samples were collected in either new amber glass or unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND) location.

Location IND could be affected by TMINS' effluent releases. Sediment samples composed of recently deposited substrate were collected semiannually at three locations (J2-1, K1-3 and A1-3). In addition, one sediment sample was collected annually at the EDCB. Location A1-3 was the control.

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulates, airborne iodine, milk, and food product. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (A3-1, 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 five locations (K1 5-3, D2-1, E2-2, F4-1, and G2-1) from March through November, and monthly from December through February. The control location was K15-3. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Food products were collected monthly at two locations (B10-2 and H11-2),

in lieu of milk sampling, and annually from the four food product groups at two locations (El-2 and B10-2). The control location was B10-2 was the control location for both annual and monthly sampling. Four different kinds of vegetation samples and seven different kinds of vegetation leaves were collected and placed in new. unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 814 calcium sulfate (CaSO 4) thermoluminescent dosimeters (TLD). The TLD locations are arranged in generally concentric rings on and around the TMINS site as follows:

A site boundary ring consisting of 18 locations (A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, J1-3, K1-4, 1-1-,

M1-1, N1-3, P1-2, Q1-2, and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release.

An indicator ring consisting of 61 locations (A3-1, A5-1, A9-3, B1-1, 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, H1-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, Ml-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, and R9-1) extending to approximately 10 miles from the site designed to measure possible exposures to close-in population.

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

The specific TLD locations were determined by the following criteria:

1.

The presence of relatively dense population;

2.

Site meteorological data taking into account distance and elevation for each of the sixteen-22 1/2 degree sectors around the site, where estimated annual dose from TMINS, if any, would be most significant;

3.

On hills free from local obstructions and within sight of the vents (where practical);

4.

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

Each TLD station consists of two primary program TLD badges, each of which has three 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 2007. The analytical procedures used by the laboratories are listed in Table B-3.

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

1.

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

2.

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

3.

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

4.

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

5.

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

6.

Ambient gamma radiation levels at various site environs.

C.

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

1.

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

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

2.

Net Activity Calculation and 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-1 34, 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 2007 the TMINS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

AIR

1. G2-1 air particulate and air iodine samples - During the weekly sampling period, the sample station was found with a fuse blown. The sample pump was replaced. Samples were sent for analysis with a low volume for the following period:

06/26/07 - 07/04/07

2. F1-3 air particulate and air iodine samples - During the weekly sampling period, no sample was available for this station. The sample pump failed and was replaced for the following period:

09/12/07 - 09/19/07

2. F1-3 air particulate and air iodine samples - During the weekly sampling period, the sample station was found with a fuse blown. The sample pump was replaced. Samples were sent for analysis with a low volume for the following period:

11/14/07 -11/20/07 WATER 1. TM-SW-Q9-1 surface water - During weekly sampling periods several hourly composite samples were missed due to unknown power losses and sediment blocking flow. No grab samples were required for the following periods:

01/23/07 - 01/30/07 04/17/07 - 04/24/07 04/24/07 - 05/01/07

2. TM-DW-Q9-1 drinking water - During weekly sampling periods several composite samples were missed due to unknown power loss. No grab samples were required for the following periods:

01/23/07 - 01/30/07 04/17/07 - 04/24/07

3. TM-SW-J 1-2 surface water - During weekly sampling periods hourly composite samples were missed due to the suction line freezing and becoming dislodged from its anchor during ice flows. Samples were also missed when trying to reposition the suction line, reattaching it to the anchor and during insulation installation and replacement of a broken heat trace. At no time was a grab sample required, there was always sufficient volume for the following periods:

01/23/07 - 01/30/07 01/30./07 - 02/06/07 02/06/07 - 02/13/07 02/13/07 - 02/20/07 02/20/07 - 02/27/07 02/27/07 - 03/06/07 03/06/07 - 03/13/07 03/27/07 - 04/03/07 04/17/07 - 04/24/0 7 11/13/07 -11/21/07 11/27/07 - 12/03/07 12/03/07 - 12/11/07 12/11/07 - 12/18/07 12/18/07 - 12/24/07

4. TM-EW-K1 -1 effluent water - During the sampling period, the effluent sampler was found stopped or missing hourly composite samples due to power interruptions and construction activities in the area and pump jammed error. No grab samples were required for the following periods:

01/16/07 - 01/23/07 07/03/07 - 07/10/07

5. TM-SW-A3-2 surface water - During the weekly sampling period no sample was available. The sample line was out of the water apparently as a result of a fisherperson snagging the line. The sample line was repositioned and returned to service. A grab sample was required for the following period:

09/18/07 - 09/25/07

6. G 15-2 drinking water - During the weekly sampling period no composite sample was available. At the time of collection (12/03/07 @

0955 EST), the water compositor was found laying on its side and the sample line was found disconnected from the compositor. (Apparently, a large iron rod fell on the sampler and caused the disruption.) The LCD read: 56 samples;, float/weight tripped. No water remained in the collection tube; a 1 gallon grab sample and a 1 liter grab sample were collected. The compositor was fixed and was operating properly upon departure for the following sampling period:

11/27/07 - 12/03/07

7. G 15-3 drinking water - During the weekly sampling period three hourly composite samples were missed due to a power outage at the facility.

No grab sample was required for the following period:

12/28/07 - 12/24/07 lIM 1. K8 During the sampling period 1 of 2 TLD badges was found missing. It was not located on the ground or in the general area so it was presumed stolen for the following period:

01/12/07 - 04/13/07

2. K3 During the sampling period, the station was vandalized. Badge 106 was found on the ground. It appears someone cut or pulled it from its frame. The TILD was send for analysis for the following period:

10/12/07 - 01/11/08 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 Indicator Farm F4-1 changed from quarterly sampling to monthly sampling on 05/16/2007.

In 2007, TMI started collecting vegetation samples monthly from location B-10-2 and H1-2.

Starting in 2007, the mean and two standard deviation values are calculated using the positive values only.

All groundwater results are now being reported in the ARGPPR, Appendix F.

IV.

Results and Discussion A.

Aquatic Environment

1.

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

Tritium Monthly samples from J1-2 and Q9-1 were analyzed for tritium activity (Table C-1.1, Appendix C). Positive tritium activity was detected in eight of 24 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 527 to 5,350 pCi/l. 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. lodine-131 was not detected.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). All nuclides were less than the MDC.

2.

Drinking Water Monthly samples were collected from continuous water samplers at three locations (G15-2, G15-3, and Q9-1). Two locations (G15-2 and G15-3) could be affected by TMINS' effluent releases. The following analyses were performed:

GrossBeta Monthly samples from all locations were analyzed for concentrations of gross beta. (Tables C-11.1, Appendix C). Gross beta activity was detected in 25 of 36 samples. The concentrations ranged from 2.2 to 5.4 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-3, Appendix C).

Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Activity was detected in three of 36 samples. Concentrations ranged from 188 to 447 pCi/l. Three samples had concentrations slightly above 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 all three time periods would have been <0.008 mrem to the liver of a child. The effluent combined projected dose for an adult for these time periods was 0.012 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).

Exelon specified that its laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-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 (KI-1). The following analyses were performed:

Gross Beta Monthly samples from location K1-1 were analyzed for concentrations of gross beta. (Tables C-111.1, Appendix C). Gross beta was detected in all 12 samples. The concentrations ranged from 2.9 to 10 pCi/I. Concentrations detected were consistent with those detected in previous years.

Iodine-131 Monthly samples from location K1-1 were analyzed for concentrations of iodine-131. (Tables C-I11.1, Appendix C). Iodine-131 was not detected. Effluent water is not consumed by humans.

Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-111.1, Appendix C). Tritium activity was detected in eight samples. The concentrations ranged from 5470 to 52,500 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 4.2 pCi/I for Sr-89 and at 0:9 pCi/I for Sr-90.

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

4.

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

Tritiuma All samples from location EDCB were analyzed for tritium activity (Table C-IV.1, Appendix C). Tritium activity was detected in three samples. The concentrations ranged from 231 to 244 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 During 2006, Exelon initiated a fleetwide Environmental Assessment program. Comprehensive groundwater studies and reports were developed. As a result of this assessment and the NEI initiative on groundwater protection, TMI developed a new Radiological Groundwater Protection Program (RGPP) that was implemented by the end of the year. For 2007, this more comprehensive groundwater program replaced TMI's previous groundwater monitoring program. The results from these special investigations and studies are discussed in Appendix F.

6.

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

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

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

Naturally occurring K-40 was found at all stations and ranged from 2,100 to 3,280 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were found.

7.

Sediment Aquatic sediment samples were collected at three locations (A1-3, J2-1 and K1-3) semiannually. In addition, location EDCB was sampled annually. Of these locations two (J2-1 and K1-3) could be affected by TMINS' effluent releases. The following analysis was performed:

Gamma Spectrometry.

Sediment samples from all four locations were analyzed for gamma emitting nuclides (Table C-VI.1, Appendix C). Potassium-40 was found at all stations and ranged from 7,370 to 14,900 pCi/kg dry.

Cesuim-137 was detected in sediment samples at very low levels (just above LLD) and are not distinguishable from background levels. No other fisson or activation products were found.

B.

Atmospheric Environment

1.

Airborne Particulates

a.

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

The following analyses were performed:

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

Detectable gross beta activity was observed at all locations.

Comparison of results aid in determining the effects, if any, resulting from the operation of TMINS. The results from the closest to the site boundary locations (Group I) ranged from

<7 to 34 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. The results from the intermediate offsite locations (Group II) ranged from <7 to 35 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Control location (Group Ill) ranged from <7 to 35 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3. Comparison of the 2007 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 2007 indicate no notable differences between indicator and control stations. (Figure C-7, Appendix C).

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

Naturally occurring Be-7 due to cosmic ray activity was detected in all 28 samples. These concentrations ranged from 42 to 126 E-3 pCi/m 3. All other nuclides were less than the MDC.

b.

Airborne Iodine Continuous air samples were collected from seven (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1, and Q15-1) locations and analyzed weekly for 1-131 (Table C-VIII.I, Appendix C). All results were less than the MDC.

2.

Terrestrial

a.

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

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

Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-IX.2, Appendix C). No Sr-89 activity was detected. Sr-90 activity was detected in 11 of 21 samples. The concentrations ranged from 0.6 to 1.4 pCi/I. The activity detected was consistent with those detected in the pre-operational years (Figure C-8, Appendix C).

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

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

The concentrations ranged from 784 to 1,460 pCi/I. All other nuclides were less than the MDC.

b.

Food Products Samples were collected from two locations (B10-2 and H1-2) monthly, in lieu of milk sampling. Samples from the four food product groups were collected from two locations (B130-2 and E1-2) annually. The following analyses were performed:

Each food product sample was analyzed for concentrations of Sr-90 (Table C-X.1, Appendix C). Sr-90 activity was detected in 24 of 26 samples. The concentrations ranged from 2 to 47 pCi/kg wet.

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

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

The concentrations ranged from 2,030 to 5,250 pCi/I. 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-XI.1 to C-XI.3, Appendix C.

All TLD measurements were below 10 mR/standard month, with a range of 4.1 to 9.4 mR/standard month. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 were consistently higher. The historical ambient gamma radiation data from Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 were plotted along with similar data from the Site, Indicator and Control Ring Locations (Figure C-9, Appendix C). Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and 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 2007 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 1/2/ degree sectors around the site. There were no changes required to the TMINS REMP, as a result of this survey. Two gardens were closer to TMINS. The gardens in sectors L (SW) and M (WSW) were closer by 1.3 miles (2.1 kilometers) and 0.1 miles (0.2 kilometers), respectively based on the recent 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 1 N 1.1 1.6 2.1 2 NNE 0.7 0.9 3 NE 0.5 0.8 4.1 4 ENE 0.5

.0.5 1.1 5 E 0.4 0.5 1.1 6 ESE 1.1 0.5 3.2 7SE 0.7 0.5 1.4 8 SSE 0.7 0.8 9S 2.3 2.7 10 SSW 0.6 1.6 4.9 11 SW 0.5 0.6 12 WSW 0.5 1.3 13 W 0.7 1.4 14 WNW 0.4 2.2 3.7 15 NW 0.4 2.1 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 2007 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2007 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 0.08 mrem. This dose is equivalent to <0.03% of the dose that an individual living in the TMI area receives each year from natural background radiation.

1.

Determination of Radiation Doses to the Public Dose assessments can be performed by using either effluent data and an environmental transport model or environmental sample data.

To the extent possible, doses to the public are based on the direct measurement of dose rates from external sources and the measurement of radionuclide concentrations in environmental media which may contribute to an internal dose of radiation.

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

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

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

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

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

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

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

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

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

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

When determining the dose to humans, it is necessary to consider all applicable pathways and all exposed tissues, summing the dose from each to provide the total dose for each organ as well as the whole body from a given radionuclide. Dose calculations involve determining the energy absorbed per unit mass in the various tissues.

Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted and half-life. The dose assessment model also contains dose conversion factors for the radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone and GI tract).

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

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

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

2.

Result of Dose Calculations The maximum hypothetical doses due to 2007 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 2007 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 2007 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.06 mrem. This dose is equivalent to <0.02% 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 2007 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 2007 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 2007 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 2007 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximnm Hypothetical Doses To An Individnal USNRC 10 CFR 50 APP. I Guidelines (mrem/yr)

From Radionuclides In Liquid Releases From Radionuclides In Airborne Releases (Noble Gases)

From Radionuclides In Airborne Releases (lodines, Tritium and Particulates) 3 total body, or 10 any organ 5 total body, or 15 skin 15 any organ Calculated Dose (mrem/yr)

TMI-1 TMI-2 5.68E-2 3.80E-4 7.25E-2 6.04E-4 1.87E-4 0*

3.29E-4 0*

8.14E-3 2.35E-5

• No noble gases were released from TMI-2.

USEPA 40 CFR 190 Limits (mrem/vr)

Calculated Dose (mrem/yr)

TMI-1 and TMI-2 Combined**

Total from Site 75 thyroid 0.29 0.33 25 total body or other organs

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

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

The direct radiation dose from 2007 TMINS operations was 0.25 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 (0.08 mrem) and the dose from direct radiation (0.25 mrem) yielded a maximum hypothetical dose of 0.33 mrem.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2007 TMI-1 and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)

TMI-!

TMI-2 From Radionuclides In Liquid Releases From Radionuclides in Airborne Releases (Noble Gases)

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

• No noble gases were released from TMI-2.

5.68E-2 3.80E-4 1.87E-4 0*

7.75E-3 2.35E-5 Individual Whole Body Dose Due to TMI-1 and TMI-2 Operatioon Individual Whole Body Dose Due to Natural Background Radiation 6.06 mrem/yr 3010 mrem/~yr Figure 1 Exposure Pathways For Radionuclides Routinely Released From TMINS ANIMALS (MILK, MEAT)

ScO'NSUN By Pito

"')! !*

AIRBORNE PLUMEi'EXPQSU"E AND *INHALATIGO E

14*

EDE PEOPLE CONSUMED LAf BY ANIMALS CONSLI BY gOPLE I

SHORE

/

EXPOS PREDOMINANT RADIONUCLIDES; NOBLE OASES (XeKr)

Plume exposure RADLOIGOINES (1-131, 1-13)

Inhalation and consumption of milk, water, fruits, and vegetables RA.DiOSTRONTIUMS (Sr-89, Sr-90)

Consumption of milk, meat.

fruits, and vegetablets ACTIVATION PRODUCTS,(Co-60, Mn-54)

Shoreline exposure RADIOCESIUMS (Cs-13l, Cs-437)

Shoreline exposure and consumption of milk, meat, fish, water. fruits, and vegetables TRITIUM (H-3)

Inhalation and consumption of water, mailk, fruits, and vegetable-s 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, 17 out of 19 analytes met the specified acceptance criteria. Two samples did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's Analytics March 2007 1-131 in charcoal result of 34.7 pCi was lower than the known value of 71.3, resulting in a found to known ratio of 0.49. A new technician counted the charcoal cartridge on the back rather than the face side. Due to decay of the 1-131, recounting could not be performed.

Counting the 2 nd quarter Analytics charcoal cartridge on the face and the back resulted in approximately 220% more activity on the face of the cartridge. This indicates that TBE would have had acceptable results (ratio approximately 1.07) if the cartridge had been counted on the face side.

2. Teledyne Brown Engineering's ERA July 2007 Cs-134 result of 57.6 pCi/L exceeded the lower acceptance limit of 60.2 pCi/L. The high activity of the sample resulted in the lower acceptance limit of 8.66, although the ratio of found to known was 83.6%, which is considered acceptable by TBE.

For the secondary laboratory, 18 out of 19 analytes met the specified acceptance criteria. One sample did not meet the specified acceptance criteria for the following reasons:

1.

Environmental Inc.'s ERA March 2007 air particulate Cs-137 result of 345.3 pCi/L exceeded the upper control limit of 336 pCi/L. The reported result was calculated using composite filter geometry rather than the single filter geometry. The recalculated result of 305.8 pCi/filter fell within the acceptance limits.

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 ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

H-3 1-131 24 12 24 2000 2343 (8/12)

(527/5350) 15 NA

<LLD

<LLD 2343 (8/8)

(527/5350)

J 1-2 INDICATOR WEST SHORE; TMI 0.5 MILES S OF SITE 0

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

ZR-95 CS-134 CS-137 BA-140 LA-140 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 4

3.7 (18/24)

(2.3/5.4) 1

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0 0

0 DRINKING WATER (PCI/LITER)

GR-B 36 3.4 (7/12)

(2.2/5.2) 3.8 (8/8)

(2.3/5.3)

G15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE 1-131 36

<LLD 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

H-3 36 36 2000 289 (3/24)

(188/447)

<LLD 340 (2/2)

(232/447)

G 15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE 0

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0 0

0 0

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

CS-134 CS-137 BA-140 LA-140 15

<LLD 18

<LLD 60

<LLD 15

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0 0

0 0

0 EFFLUENT WATER (PCI/LITER)

GR-B 1-131 12 12 12 5.7 (12/12)

(2.9/10)

I

<LLD NA NA NA NA 5.7 (12/12)

(2.9/10)

KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE H-3 2000 23340 (8/12)

(5470/52500) 5

<LLD 23340 (8/8)

(5470/52500)

KI-1 INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE SR-89

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS EFFLUENT WATER (PCI/LITER)

SR-90 2

12 2

<LLD NA 0

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD NA NA NA NA NA NA NA 0

0 0

0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS EFFLUENT WATER (PCI/LITER)

CS-134 CS-137 BA-140 LA-140 15

<LLD 18

<LLD 60

<LLD 15

<LLD NA NA NA NA NA 0

0 STORM WATER (PCI/LITER)

H-3 4

2000 237 (3/4)

(231/244) 237 (3/4)

(231/244)

EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE 0

GAMMA MN-54 4

CO-58 FE-59 15

<LLD 15

<LLD 30

<LLD NA NA NA 0

0

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS STORM WATER (PCI/LITER)

CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD NA NA NA NA NA NA NA NA 0

0 0

0 0

0 0

0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS BOTTOM FEEDER (PCI/KG WET)

SR-90 4

10

<LLD

<LLD 0

GAMMA K-40 I00 4

NA 2555 (2/2)

(2100/3010) 2600 (2/2)

(2410/2790) 2600 (2/2)

(2410/2790)

BKGB CONTROL CITY ISLAND UPSTREAM OF DISCHARGE MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 130

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD 130

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0 0

0 0

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS BOTTOM FEEDER (PCI/KG WET)

PREDATOR (PCI/KG WET)

CS-137 SR-90 GAMMA K-40 150

<LLD 10

<LLD

<LLD

<LLD 0

0

.4 4

MN-54 CO-58 FE-59 CO-60 ZN-65 NA 2775 (2/2)

(2270/3280) 130

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD 3140 (2/2)

(3110/3170) 3140 (2/2)

(3110/3170)

BKGP CONTROL CITY ISLAND UPSTREAM OF DISCHARGE

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS PREDATOR (PCI/KG WET)

CS-134 CS-137 130

<LLD 150

<LLD

<LLD

<LLD 0

0 SEDIMENT (PCI/KG DRY)

GAMMA K-40 7

MN-54 CO-58 CO-60 CS-134 CS-137 NA 9866 (7/7)

(7370/14900)

NA

<LLD NA

<LLD NA

<LLD 150

<LLD 180 157 (3/7)

(107/248)

NA NA NA NA NA NA 14900 (1/1)

EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE 0

0 0

0 248 (1/1)

EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

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

GR-B 363 GAMMA BE-7 28 MN-54 CO-58 CO-60 CS-134 CS-137 10 18 (306/311)

(7/35)

NA 85.3 (24/24)

(42/111)

NA

<LLD NA

<LLD NA

<LLD 50

<LLD 60

<LLD 19 (51/52)

(8/35) 19 (51/51)

(8/35) 93.2 (4/4)

(75/109) 92.9 (4/4)

="(72/126)"

Q15-1 CONTROL WEST FAIRVIEW 13.5 MILES NW.OF SITE E 1-2 INDICATOR TMI VISITORS CENTER 0.4 MILES E OF SITE

<LLD

<LLD

<LLD

<LLD

<LLD 0

0 0

0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS AIR IODINE (E-3 PCI/CU.METER)

MILK (PCI/LITER)

GAMMA 1-131 363 70

<LLD 1-131 SR-89 109 20

<LLD

<LLD

<LLD

<LLD 0

0 0

0 5 *

<LLD SR-90 GAMMA K-40 CS-134 CS-137 21 2

.8 (9/17)

(0.6/1.4)

NA 1274 (86/86)

(784/1460) 1 (2/4)

(0.9/1.0) 1308 (23/23)

(1100/1450) 1.1 (2/2)

(0.8/1.4) 1359 (17/17)

(1270/1430)

F4-I INDICATOR TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE F4-1 INDICATOR TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE 109 15

<LLD 18

<LLD

<LLD

<LLD 0

0 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR-STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS MILK (PCI/LITER)

BA-140 LA-140 FOOD PRODUCT (PCI/KG WET)

SR-90 26 32 60

<LLD 15

<LLD 10 16.4 (12/13)

(1.8/41.9)

NA 975 (8/16)

(414/2470)

NA 3541.3 (16/16)

(2080/4810)

<LLD

<LLD GAMMA BE-7 17.7 (12/13)

(2.6/47.4) 1703.6 (7/16)

(402/3640) 3536.9 (16/16)

(2030/5250) 17.7 (12/13)

(2.6/47.4) 1703.6 (7/16)

(402/3640) 3701.7 (12/12)

(2080/4810)

B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE HI-2 INDICATOR RED HILL MARKET 1.0 MILES SSE OF SITE 0

0 0

0 0

0 0

0 K-40 1-131 CS-134 CS-137 60

<LLD 60

<LLD 80

<LLD

<LLD

<LLD

<LLD

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2007 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility: MIDDLETOWN COUNTY PA REPORTING PERIOD:

2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS DIRECT RADIATION TLD-QUARTERLY 360 NA 5.7 (316/316)

(4.1/9.4) 6.3 (44/44)

(4.9/8.8) 8.9 (4/4)

(8.2/9.4)

H8-1 INDICATOR SAGINAW ROAD 7.4 MILES SSE OF SITE 0

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

APPENDIX B LOCATION DESIGNATION, AND SAMPLE COLLECTION DISTANCE & DIRECTION,

& ANALYTICAL METHODS

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

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

YY Radial Zone of Sampling Location in miles.

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

B-I

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2007 Sample Meiumrn AQS ID APAIlD SW ID ID ID ID ID ID ID FP ID ID ID ID ID AQF ID ID M

ID ID ID AP,AI,ID,FP ID M

ID ID Station A1-3 A1-4 A3-1 A3-2 A5-1 A9-3 B1-1 B1-2 B2-1 B5-1 B10-1 B 10-2 C1-1 C1-2 C2-1 C5-1 C8-1 Control D1-1 D1-2 D2-1 D2-2 D6-1 D15-1 E1-2 E1-4 E2-2 E2-3 E5-1 E7-1 F1-1 Fl-2 F1-3 F1-4 F2-1 F4-1 F5-1 F10-1 F25-1 G11-2 G1-3 G1-5 G1-6 G2-1 G2-4 G5-1 G10-1 G15-1 G15-2 G15-3 Map Distance Numb1 0.5RS) 1 0.5 1

0.3 2

2.7 2

2.7 2

4.4 3

8.0 1

0.6 1

0.4 2

1.9 2

4.9 3

9.2 3

10 1

0.7 1

0.3 2

1.5 2

4.7 3

7.1 1

0.2 1

0.5 2

2 3

3 2

2 2

3 2

2 2

3 1.1 1.6 5.2 10.8 0.4 0.2 1.1 2.0 4.7 6.7 0.5 0.2 0.6 0.2 1.3 3.2 4.7 9.4 Aimuith Desription 3590 N of site off north tip of TMI in Susquehanna River 60 N of Reactor Building on W fence adjacent to North Weather Station, TMI 357' N of site at Mill Street Substation 356' N of site at Swatara Creek, Middletown 30 N of site on Vine Street Exit off Route 283 20 N of site at Duke Street Pumping Station, Hummelstown 250 NNE of site on light pole in middle of North Bridge, TMI 230 NNE of Reactor Building on top of dike, TMI 170 NNE of site on Sunset Dr. (off Hillsdale Rd.)

190 NNE of site at intersection of School House and Miller Roads 210 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey 310 NNE of site at Milton Hershey School, Hershey 370 NE of site along Route 441 N 50' NE of Reactor Building on top of dike, TMI 440 NE of site at Middletown Junction 430 NE of site on Kennedy Lane 480 NE of site at Schenk's Church on School House Road All locations where finfish are collected above Dock St.

Dam, Harrisburg 760 ENE of Reactor Building on top of dike, TMI 670 ENE of site off Route 441 along lane between garden center and residence 620 ENE of site at farm on Gingrich Road 740 ENE of site along Hillsdale Rd. (S of Zion Rd.)

660 ENE of site off Beagle Road 64' ENE of site along Route 241, Lawn 970 E of site at TMI Visitor's Center 970 E of Reactor Building on top of dike, TMI 960 E of site at farm on Pecks Road 97' E of site along Hillsdale Rd. (N of Creek Rd.)

82' E of site at intersection of North Market Street (Route 230) and Zeager Road 880 E of site along Hummelstown Street, Elizabethtown 1170 ESE of site near entrance to 500 kV Substation 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI 1120 ESE of site in 500 kV Substation 1220 ESE of Reactor Building on top of dike, TMI 1190 ESE of site along Engle Road 1040 ESE of site at farm on Turnpike Road 1090 ESE of site along Amosite Road 1120 ESE of site along Donegal Springs Road, Donegal Springs 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster 1450 SE of site along Route 441 S 1300 SE of Reactor Building on top of dike, TMI 1430 SE of Reactor Building on top of dike, TMI 1390 SE of Reactor Building on top of dike, TMI 1260 SE of site at farm on Becker Road 1380 SE of site on Becker Road 131 0 SE of site at intersection of Bainbridge and Risser Roads 1280 SE of site at farm along Engles Tollgate Road, Marietta 1260 SE of site at Columbia Water Treatment Plant 1290 SE of site at Wrightsville Water Treatment Plant 124 SE of site at Lancaster Water Treatment Plant ID ID ID AP,Al ID ID M

ID ID ID ID ID ID ID AI,AP,M ID ID ID ID DW DW 3

22 1

0.7 1

0.2 1

0.3 1

0.3 2

1.4 2

1.7 2

4.8 3

9.7 3

14.4 3

13.3 3

15.7 B-2

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2007 Sample Medium~

ID FP AP,AI,ID ID ID ID Station Map Distance Cndp Numbher Lm-q)

AAzbnnt Desrmtin Hi-1 H1-2 H3-1 H5-1 H8-1 H15-1 2

2 0.5 1.0 2.2 4.1 AQF ID SW ID AQS ID ID ID ID EW AQS Indicator 3

7.4 3

13.2 1

0.8 1

0.5 1

0.3 2

1.4 ID ID ID ID ID ID M

ID ID ID ID ID ID ID J1-1 J1-2 J1-3 J2-1 J3-1 J5-1 J7-1 J15-1 K1-1 K1-3 K1 -4 K2-1 K3-1 K5-1 K8-1 K15-1 K15-3 Li-1 L1-2 L2-1 L5-1 L8-1 L15-1 M1-1 M1-2 M2-1 2

2 3

3 2.7 4.9 6.5 12.6 0.2 0.2 1

0.2 2

1.2 2

2.0 2

4.9 3

7.5 3

12.8 3

14.4 1

0.1 1670 SSE of site, TMI 1510 SSE of site along Route 441, Red Hill Market 160' SSE of site in Falmouth-Collins Substation 158° SSE of site by Guard Shack at Brunner Island Steam Electric Station 1630 SSE of site atong Saginaw Road, Starview 157' SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills All locations where finfish are collected downstream of the TMINS liquid discharge outfall 1760 S of site, TMI 1880 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River 1890 S of Reactor Building just S of SOB, TMI 1790 S of site in Susquehanna River just upstream of the York Haven Dam 179' S of site at York Haven/Cly 181o S of site along Canal Road, Conewago Heights 1760 S of site off of Maple Street, Manchester 1830 S of site in Met-Ed York Load Dispatch Station 210' On site at RML-7 Main Station Discharge Building 212° SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River 2090 SSW of Reactor Building on top of dike behind Warehouse 2, TMI 2000 SSW of site on S Shelley Island 2060 SSW of site along Rt. 262, N of Cly 2020 SSW of site along Conewago Creek Road, Strinestown 1960 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View 2030 SSW of site behind McDonald's and next to child care center, Weiglestown 2050 SSW of site at farm along S Salem Church Rd, Dover 2360 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI 221 SW of site on Beech Island 2240 SW of site along Route 262 2280 SW of site at intersection of Stevens and Wilson Roads 2250 SW of site along Rohlers Church Rd., Andersontown 2260 SW of site on W side of Route 74, rear of church, Mt.

Royal 2500 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI 252' WSW of site on E side of Shelley Island, Lot #157 2560 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown 2430 WSW of site along Alpine Road, Maytown 2740 W of site on W side of Shelley Island, between lots #13 and #14 2740 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI 261 W of site at Goldsboro Marina 2680 W of site off of Old York Road along Robin Hood Drive 2620 W of site along Route 382, 1/2 mile north of Lewisberry 275' W of site at intersection of Lisburn Road and Main Street, Lisbum 3030 WNW of site on Shelley Island 1

2 2

3 3

0.5 1.8 4.1 8.0 11.8 1

0.1 ID APAIID 1

2 0.4 1.3 4.3 ID ID ID ID ID ID ID ID ID M5-1 M9-1 N1-1 N11-3 3

8.7 1

0.7 1

0.1 N2-11 N5-1 N8-1 N15-2 2

2 3

3 1.2 5.0 7.7 10.4 P1-1 0.4 B-3

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2007 Sample Station Map Distance D*edium rgdp Number (mles)

Azmuth Dosrdipton ID P1-2 1

0.1 292' WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI ID P2-1 2

2.0 283' WNW of site along Route 262 ID P5-1 2

5.0 2840 WNW of site at intersection of Valley Road (Route 262) and Beinhower Road ID P8-1 3

8.0 292' 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 Q11-2 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

5.0 317' NW of site along Lumber Street, Highspire SW,DW,ID Q9-1 3

8.5 310' NW of site at the Steelton Water Company APAI,ID Q15-1 3

13.4 309° NW of site behind West Fairview Fire Dept. Social Hall (abandoned)

ID R1-1 3

0.2 3350 NNWof Reactor Building along Wfence, TMI ID R1-2 1

0.7 3340 NNW of site on central Henry Island ID R3-1 2

2.6 341° 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)

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, 2007 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

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

Nuclear Station)

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

Surface Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

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

Nuclear Station)

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

Drinking Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

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

Nuclear Station)

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

Drinking Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchange Effluent Water Iodine-131 Monthly composite from a continuous water compositor.

ER-TMI-06 Collection of water samples for radiological analysis (Three Mile Island Nuclear Station) 2 gallon TBE, TBE-2012 Radioiodine in various matrices Env. Inc., 1-131-01 Determination of I-131 in milk by 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, 2007 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-201 0 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor.

Nuclear Station)

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

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

Storm Gamma Quarterly composite ER-TMI-06 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy of monthly grab radiological analysis (Three Mile Island samples Nuclear Station)

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

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

Fish Gamma Semi-annual samples ER-TMI-1 3 Collection of fish samples for 1000 grams (wet)

TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station)

Env. Inc., GS-01 Determination of gamma emitters by other techniques gamma spectroscopy Fish Strontium 90 Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet)

TBE, TBE-2019 Radiostrontium analysis by ion exchange collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) other techniques

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2007 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Sediment Gamma Semi-annual grab ER-TMI-03 Collection of sediment samples for 500 grams (dry)

TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Three Mile Island Nuclear Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Gross Beta One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2008 Gross alpha and/or gross beta activity in Particulates composite of iodine samples for radiological analysis (Three (approximately various matrices continuous air Mile Island Nuclear Station) 280 cubic sampling through meters weekly)

Env. Inc., AP-02 Determination of gross alpha and/or gross glass fiber filter beta in air particulate filters paper Air Gamma Quarterly composite TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy of each station (approximately Env. Inc., AP-03 Procedure for compositing air 3600 cubic Env. Inc., GS-01 Determination of gamma emitters by particulate filters for gamma spectroscopic meters) gamma spectroscopy analysis Air Iodine Gamma One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy composite of iodine samples for radiological analysis (Three (approximately continuous air Mile Island Nuclear Station) 280 cubic Env. Inc., 1-131-02 Determination of 1-131 in charcoal sampling through meters weekly) canisters by gamma spectroscopy (batch method) charcoal filter Milk 1-131 Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices sample when cows radiological analysis (Three Mile Island Nuclear are on pasture.

Station)

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion Monthly all other exchange times Milk Strontium-Quarterly composite ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 of Bi-weekly and radiological analysis (Three Mile Island Nuclear monthly grab Station) samples TBE, TBE-2023 Compositing of samples Milk Gamma Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy sample when cows radiological analysis (Three Mile Island Nuclear are on pasture.

Station)

Env. Inc., GS-01 Determination of gamma emitters by Monthly all other gamma spectroscopy times Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear-Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2007 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscooy Vegetation Strontium-Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 grab sample radiological analysis (Three Mile Island Nuclear Station)

TLD Thermolumines Quarterly TLDs ER-TMI-02 Collection of TLD samples for 2 badges with 3 Global Dosimetry Solutions, Inc.

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

(containing 4 each CaSO4 elements) 00

Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2007 B-9

ao rnIipi VAior t,? 1 aid TNk..ý

?

3 Bas~nps, PAýSUteVlsneScih, NAD2T foet Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2007 B - 10

&id-- TA1 2.h-><-

Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2007 B-Il

Intentionally left blank

APPENDIX C DATA TABLES AND FIGURES -

PRIMARY LABORATORY

TABLE C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD J,1-2 Q9-1 01/02/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07

- 01/30/07

- 02/27/07

- 04/03/07

- 05/01/07

- 05/29/07

- 07/03/07

- 07/31/07

- 08/28/07

- 10/02/07

- 10/30/07

- 11/27/07 12/31/07 5040 +/- 564

< 179

< 154 1510 +/- 209 1120 +/- 172 5350 +/- 587

• 163 527 +/- 116 1720 +/- 244 2110 +/- 287

< 193 1370 +/- 208 2343 + 3640 183 183 158 157 164 179 160 155 185 186 184 178 MEAN

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

TABLE C-1.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/02/07 - 01/30/07 01/30/07 - 02/27/07 02/27/07 - 04/03/07 04/03/07 - 05/01/07 05/01/07 - 05/29/07 05/29/07 - 07/03/07 07/03/07 - 07/31/07 07/31/07 - 08/28/07 08/28/07 - 10/02/07 10/02/07 - 10/30/07 10/30/07 - 11/27/07 11/27/07 - 12/31/07 A3-2

< 0.5

< 0.5

< 0.6

< 0.6

< 0.8

< 0.7

• 0.7

< 0.6

< 0.5

< 0.9

< 0.7

< 0.6 MEAN C-2

TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION MN-54 PERIOD J1-2 01/02/07 -

01/30/07

< 7 01130/07 -

02/27/07

<* 6 02/27/07 -

04/03/07

< 2 04/03/07 -

05/01/07

< 7 05/01/07 -

05/29/07

< 3 05/29/07 -

07/03/07

< 4 07/03/07 -

07/31/07

< 5 07/31/07 -

08/28/07

< 2 08/28/07 -

10/02/07

< 2 10/02/07 -

10/30/07

< 5 10/30/07 -

11/27/07

< 2 11/27/07 - 12/31/07

< 5 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 MEAN

<8

<6

<2

<7

<3

<4

<4

<2

<2

<5

<2

<4

<6

<7

<2

<6

<5

<5

<3

<2

<2

<6

<2

<7

< 15

< 13

<4

< 14

<7

< 10

< 13

<6

<4

< 12

<5

< 11

< 11

< 11

<5

< 11

<9

< 10

<6

<4

<4

< 11

<4

< 12

<7

<6

<2

<7

<3

<5

<3

<2

<2

<6

<2

<5

<6

<6

<2

<5

<5

<4

<3

<1

<2

<5

<2

<5

< 14

< 13

<:4

< 12

<7

< 10

<9

<5

<4

< 10

<4

<8

< 15

< 14

<4

< 10

<8

< 10

<5

<3

<3

<9

<4

< 11

<7

<6

<2

<7

<4

<5

<6

<3

<2

<5

<2

<5

<7

<6

<2

<6

<4

<4

<3

<2

<2

<7

<2

<6

< 13

< 11

<4

< 11

<6

<8

<8

<4

<4

<9

<4

<9

< 12

< 10

<4

< 10

<7

<9

<5

<3

<3

<9

<4

< 11

<8

<6

<2

<4

<3

<4

<4

<2

<2

<4

<2

<4

<8

<5

<2

<5

<4

<4

<2

<1

<2

<5

<2

<6

<8

<7

<2

<6

<4

<5

<5

<2

<2

<5

<2

<5

<6

<6

<3

<5

<3

<5

<3

<1

<2

<5

<2

<6

< 34

< 29

<8

< 29

< 15

< 20

< 28

< 26

< 13

<31

< 13

< 24

< 31

< 32

<9

< 30

< 20

< 22

< 17

< 16

< 11

< 34

< 14

< 33

< 11

< 13

<2

< 12

<6

<6

< 11

<7

<4

< 11

<5

<7

<9

< 13

<3

< 12

<6

<7

<6

<5

<3

< 12

<4

<9 Q9-1 01/02/07 -

01/30/07 -

02/27/07 -

04/03/07 -

05/01/07 -

05/29/07 -

07/03/07 -

07/31/07 -

08/28/07 -

10/02/07 -

10/30/07 -

11/27/07 -

01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07 12/31/07

<6

<6

<2

<6

<4

<4

<2

<1

<2

<5

<2

<6 MEAN

TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G215-3 Q9-1 01/02/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07 12/31/07 2.4 +/-

3.1 +/-

4.2 +/-

4.3 +/-

2.5 +/-

< 2.1 2.8 +/-

2.8 +/-

5.4 +/-

4.5 +/-

4.5 +/-

< 2.4 1.5 1.3 1.5 1.4 1.3 1.5 1.5 1.7 1.7 1.5

< 2.0 3.4 +/- 1.4 2.3 +/- 1.4 2.6 +/- 1.2

< 1.8

< 2.3 3.0 +/- 1.6 4.9 +/- 1.7 5.3 +/- 1.8 4.8 +/- 1.7 4.0 +/- 1.4

< 2.4

< 2.0

< 1.7

< 1.8 2.2 +/- 1.2 4.5 +/- 1.5

< 2.1 2.2 +/- 1.5 2.3 +/- 1.5 4.7 +/- 1.6 5.2 +/- 1.7 2.7 +/- 1.3

< 2.3 3.4 +/- 2.7 MEAN 3.6 +/- 2.1 3.8 +/- 2.3 TABLE C-11.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/02/07 -

01/30/07 01/30/07 -

02/27/07 02/27/07 -

04/03/07 04/03/07-05/01/07 05/01/07 -

05/29/07 05/29/07 -

07/03/07 07/03/07-07/31/07 07/31/07 -

08/28/07 08/28/07 -

10/02/07 10/02/07 10/30/07 10/30/07 - 11/27/07 11/27/07 -

12/31/07 G15-2

< 0.4

< 0.6

< 0.6

< 0.6

< 0.7

< 0.6

< 0.6

< 0.6

< 0.5

< 0.9

< 0.7

< 0.8 G1 5-3

< 0.4

< 0.7

< 0.7

< 0.7

< 0.8

< 0.7

< 0.8

• 0.5

< 0.4

< 0.9

< 0.7

• 0.5 Q9-1

• 0.5

< 0.7

< 0.6

• 0.6

< 0.9

< 0.7

< 0.7

< 0.6

< 0.5

< 0.9

< 0.7

< 0.5 MEAN TABLE C-11.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/02/07-01/30/07 01/30/07-02/27/07 02/27/07-04/03/07 04/03/07 -

05/01/07 05/01/07-05/29/07 05/29/07 -

07/03/07 07/03/07-07/31/07 07/31/07-08/28/07 08/28/07 -

10/02/07 10/02/07 - 10/30/07 10/30/07 -

11/27/07 11/27/07 -

12/31/07 G1 5-2 G15-3 Q9-1 I

< 178

< 181

< 155

< 158

< 159

< 171

< 161 188

+ 101

• 174

< 184

< 192

< 172

< 182

< 184

< 157

< 161

• 159 447 +/- 129

< 164

• 148

< 174 232

+/- 124

< 189

< 173 340

+/- 304 180 183 156 157 158 168 159 146 171 184 191 174 MEAN 188 +/- 0

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-4

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 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-1 37 BA-140 LA-140 PERIOD G15-2 01/02/07 - 01/30/07

< 8 01/30/07 - 02/27/07

< 4 02/27/07 - 04/03/07

< 2 04/03/07 - 05/01/07

< 6 05/01/07

- 05/29/07

< 3 05/29/07

- 07/03/07

< 3 07/03/07

- 07/31/07

< 3 07/31/07 - 08/28/07

< 2 08/28/07

- 10/02/07

< 2 10/02/07 -

10/30/07

< 5 10/30/07 - 11/27/07

< 2 11/27/07 -

12/31/07

< 7

(-A MEAN

<9

<4

<2

<5

<3

<3

<3

<2

<2

<5

<2

<6

<7

<5

<2

<5

<2

<5

<3

<2

<2

<5

<2

<5

<16

<7

<9

<5

<4

<3

<11

<5

<5

<3

<6

<3

<6

<3

<5

<2

<5

<2

<11

<4

<4

<2

<12

<6

<15

<7

<10

<5

<5

<2

<10

<6

<6

<3

<9

<5

<6

<2

<5

<2

<4

<2

<11

<6

<4

<2

<12

<6

<26

<9

<9

<4

<4

<2

<12

<5

<5

<3

<6

<3

<5

<3

<4

<2

<4

<2

<11

<5

<4

<2

<9

<6

<18

<8

<12

<6

<5

<2

<10

<4

<5

<3

<8

<4

<5

<3

<3

<2

<4

<2

<9

<6

<4

<2

<11

<5

< 14

< 13

<9

<4

<3

<2

<10

<6

<4

<3

<5

<3

<4

<2

<4

<2

<4

<2

<9

<6

<4

<2

<9

<6

<14

<7

<10

<4

<4

<2

<9

<5

<5

<3

<7

<3

<5

<2

<3

<2

<3

<2

<9

<4

<3

<2

<9

<6

<8

<5

<2

<6

<3

<3

<3

<2

<<2

<5

<2

<6

<7

<5

<2

<6

<3

<4

<3

<2

<2

<5

<2

<6

< 41

< 13

<23

<8

<7

<3

<29

<6

<13

<4

<16

<5

<16

<6

<20

<7

<14

<5

< 31

< 10

<14

<4

<34

<8

<31

<11

< 30

< 12

<8

<3

< 24

< 10

<14

<6

<20

<6

<18

<6

<21

<6

<12

<4

< 36

< 11

<12

<4

<35

< 11 G15-3 01/02/07 - 01/30/07

< 7 01/30/07 - 02/27/07

< 5 02/27/07 - 04/03/07

< 2 04/03/07 - 05/01/07

< 5 05/01/07 - 05/29/07

< 3 05/29/07 - 07/03/07

< 4 07/03/07 - 07/31/07

< 2 07/31/07 - 08/28/07

< 2 08/28/07 -

10/02/07

< 2 10/02/07 -

10/30/07

< 5 10/30/07 -

11/27/07

< 2 11/27/07 -

12/31/07

< 5 MEAN

TABLE C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 PERIOD Q9-1 01/02/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10130/07 11/27/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07 12/31/07

<7

<5

<2

<5

<4

<4

<3

<2

<2

<5

<2

<6

<7

<6

<2

<5

<4

<4

<4

<2

<2

<5

<2

<6

< 16

< 12

<4

< 11

<9

<9

<9

<4

<5

< 11

<5

< 15

<7

<5

<2

<5

<6

<5

<4

<2

<2

<5

<2

<8

< 17

< 13

<4

< 10

<8

<7

<6

<3

<4

<9

<4

< 13

<9

<6

<2

<6

<4

<4

<4

<2

<2

<5

<2

<7

< 12

<9

<3

<9

<7

<7

<7

<3

<4

<9

<4

< 12

<8

<5

<2

<5

<4

<3

<3

<2

<2

<5

<2

<6

<8

<6

<2

<6

<5

<5

<4

<2

<2

<5

<2

<6 34 28 7

24 22 22 25 19 13 32 14 33

<8

< 11

<3

<4

<8

<7

<8

<6

<5

< 10

<5

< 12 MEAN

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA U

COLLECTION PERIOD 01/02/07 - 01/30/07 01/30/07 - 02/27/07 02/27/07 - 04/03/07 04/03/07 - 05/01/07 05/01/07 - 05/29/07 05/29/07 - 07/03/07 07/03/07 - 07/31/07 07/31/07 - 08/28/07 08/28/07 - 10/02/07 10/02/07 - 10/30/07 10/30/07 - 11/27/07 11/27/07 - 12/31/07 GROSS BETA 1-131 H-3 SR-89 SR-90 2.9 4.0 3.4 4.9 3.8 6.2 7.1 8.6 8.5 10 4.8 4.0

+/- 1.5

+/- 1.5

+/- 1.5

+/- 1.5

+/- 1.5

+/- 2.0

+/- 2.0

+/- 2.2

+/- 2.1

+/- 2.2

+/- 1.5

+/- 1.8

< 0.5

< 0.7

< 0.7

< 0.6

< 0.7

< 0.7

< 0.7

< 0.6

< 0.8

< 0.8

< 0.7

< 0.6 46200 +/- 4530

< 185

< 150 23200 +/- 2360 20400 +/- 2070 52500 +/- 4870

< 158 5470 +/- 589 12000 +/- 1250 18800 +/- 1950

< 185 8150 +/- 875

< 4.2

< 0.4

< 4.0

< 0.9 MEAN 5.7 +/- 4.6 23340 +/- 34483

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-7

TABLE C-1II.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 Ki-1 01/02/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07

- 01/30/07

- 02/27/07

- 04/03/07

- 05/01/07

- 05/29/07

- 07/03/07

- 07/31/07

- 08/28/07

- 10/02/07

- 10/30/07

- 11/27/07

- 12/31/07

<4

<5

<3

<4

<4

<4

<2

<2

<2

<5

<2

<5

<4

<5

<2

<5

<5

<4

<2

<2

<2

<6

<2

<4

<8

< 12

<5

< 12

<8

<8

<4

<5

<5

< 13

<4

< 10

<4

<5

<3

<6

<4

<4

<2

<2

<2

<5

<2

<5

<8

<9

<5

<7

<8

<8

<5

<4

<4

< 10

<4

<8

<3

<5

<3

<5

<4

<4

<2

<2

<2

<6

<2

<5

<7

<9

<5

<8

<9

<7

<4

<4

<4

<9

<4

<8

<4

<4

<3

<5

<4

<4

<2

<2

<2

<5

<2

<5

<4

<5

<3

<6

<4

<4

<2

<2

<2

<6

<2

<4

< 19

< 25

< 11

< 24

< 23

< 21

< 14

< 23

< 15

< 37

< 14

< 24

<7

<8

<4

<8

<7

<6

<4

<7

<4

< 13

<5

< 10 00 MEAN

TABLE C-IV.1 CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD EDCB 01/30/07 - 04/03/07 05/01/07 - 07/03/07 07/31/07 - 10/02/07 10/30/07 - 12/31/07 MEAN H-3 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 236 +/- 104 231 +/- 114 244 +/- 126

< 195

<2

<3

<5

<5

<2

<4

<6

<7

<4

<7

< 14

< 14

<2

<3

<8

<7

<4

<7

<9

< 13

<2

<4

<2

<2

<4

<5

<3

<4

<8

<11

<5

<6

<6

<11

<6

<6

<8

< 17

< 27

< 35

<3

<7

<8

< 12 237 +/- 13

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

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

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD INDP PREDATOR 06/06/07 10/17/07 Sr-90

<3

<3 MEAN INDB BOTTOM FEEDER 06/06/07 10/17/07

<4

<4 MEAN BKGP PREDATOR 06/06/07 10/15/07

<4

<4 MEAN BKGB BOTTOM FEEDER 06/06/07 10/15/07 MEAN

<4

<4 C-10

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

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD INDP PREDATOR 06/06/07 10/17/07 MEAN K-40 Mn-54 Co-58 Fe-59 Co-60

' Zn-65 Cs-1 34 Cs-137 2270 +/- 614

< 27 3280 +/- 685

< 47

< 39

< 43

< 74

• 101

• 41

• 51

• 91

< 110

< 39

< 42

< 40

< 49 2775 +/- 1428 INDB BOTTOM FEEDER 06/06/07 10/17/07 MEAN BKGP PREDATOR 06/06/07 10/15/07 MEAN BKGB BOTTOM FEEDER 06/06/07 10/15/07 2100 +/- 632

< 34 3010 +/- 688

< 44 2555 +/- 1287 3110 +/- 790

< 46 3170 +/- 754

< 47 3140 +/- 85 2790 +/- 544

< 34 2410 +/- 870

< 58

< 43

< 42

< 92

< 107

< 43

< 37

< 90

< 89

• 38

• 32

< 46

< 44

< 45

• 42

• 92

< 109

< 49

< 41

• 118

< 87

< 48

< 39

< 53

< 45

< 37

< 57

< 69

< 134

< 39

• 60

< 73

< 102

< 37

< 62

< 42

< 68 MEAN 2600 +/- 537

TABLE C-VI.1 STC COLLECTION PERIOD Al -3 06/11/07 - 06/11/07 11/21/07 - 11/21/07 MEAN J2-1 06/11/07 - 06/11/07 11/21/07 - 11/21/07 MEAN K1-3 06/11/07 - 06/11/07 11/21/07 - 11/21/07 MEAN EDCB 11/21/07 - 11/21/07 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA K-40 MN-54 CO-58 CO-60 CS-134 CS-137 7970 +/-

9280 +/-

8625 +/-

8800 +/-

13000 +/-

10900 +/-

7370 +/-

7740 +/-

7555 +/-

14900 +/-

14900 +/-

986 1300 1853 1880 1730 5940 1840 1260 523 2300 0

< 51

< 82

< 130

< 84

< 42

< 72

< 97

< 54

< 70

< 53

< 49

< 65

< 68

< 64

< 88

< 118

< 96

< 90

< 81

< 69

< 83

< 138

< 122

< 89

< 79

< 67

< 64

< 114

< 104

< 83

< 129 107 +/-

107 +/-

< 126 115 +/-

115 +/-

248 +/-

248 +/-

92 0

54 0

78 0

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-12

TABLE C-VII.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUPI I

GROUPI 11 GROUP III COLLECTION E1-2 F1-3 A3-1 G2-1 1-3-1 M2-1 Q15-1 PERIOD 01/03/07

-01/10/07 14 +/- 5 13 +/- 5 17 +/- 5 15 +/- 5 15 +/- 5 15 +/- 5 20 +/- 5 01/10/07 -01/17/07 16 +/- 5 15 +/- 5 8 +/- 4 12 +/- 5 12 +/- 5 16 +/- 5 14 +/- 5 01/17/07 -01/24/07 12 +/-5 13 +/-5 13 +/-5 12 +/-5 14 +/-5 10 +/-5 13 +/-5 01/24/07 -01/31/07 19 +/- 5 21 +/- 5 23 +/- 5 23 +/- 5 19 +/- 5 18 +/- 5 19 +/- 5 01/31/07 -02/07/07 16 +/- 5 19 +/- 5 20 +/- 5 12 +/- 5 21 +/- 5 18 +/- 5 21 +/- 5 02/07/07 -02/14/07 17 +/-5 17 +/-5 17 +/-5 14 +/-5 15 +/-5 15 +/-5 17+/- 5 02/14/07 -02/21/07 15 +/- 5 19 +/- 5 20 +/- 5 20 +/- 5 19 +/- 5 20 +/- 5 21 +/- 5 02/21/07

-02/28/07 7 +/- 5 10 +/- 5 10 +/- 5 12 +/- 5 11 +/- 5 11 +/-5 8 +/-5 02/28/07

-03/07/07 15 +/- 5 14 +/- 5 14 +/- 5 16 +/- 5 15 +/- 5 11 +/-5 11 +/-5 03/07/07-03/14/07 20 +/-5 18 +/-5 25 +/-6 19 +/-5 21 +/-5 22+/-5 23+/-5 03/14/07 -03/21/07 11 +/- 4 18 +/- 5 19 +/- 5 15 +/- 5 14 +/- 5 15 +/-5 12 +/-5 03/21/07

-03/28/07 12 +/- 5 17 +/- 5 12 +/- 5 15 +/- 5 18 +/- 5 18 +/-5 15 5

03/28/07

-04/04/07 14 +/- 5 16 +/- 5 14 +/- 5 16 +/- 5 14 +/- 5 12 +/-4 15 +/-5 04/04/07 -04/11/07 11 +/- 5 11 +/- 4 13 +/- 5 11

+/- 5 9 +/- 4 11 +/-5 15 +/-5 04/11/07-04/18/07

< 7

<7 10 +/-5

<7

< 7 7+/-5

< 7 04/18/07 -04/25/07 18 +/-5 12 +/-5 22 +/-5 16 +/-5 13 +/-5 10+/-5 13+/-5 04/25/07 -05/02/07 12 +/- 4 12 +/- 4 13 +/- 4 9 +/- 4 12 +/- 4 13 +/-5 15 +/-5 05/02/07 -05/09/07 12 +/-5 15 +/-5 12 +/-5 14 +/-5 14 +/-5 12+/-5 13+/-5 05/09/07 -05/16/07 12 +/-5 13 +/-5 13 +/-5 14 +/-5 12 +/-5 15+/-5 12+/-5 05/16/07 -05/23/07 9 +/-4 16 +/-5 14 +/-5 15 +/-5 16 +/-5 10+/-5 13+/-5 05/23/07-05/30/07 21 +/-5 23 +/-5 29 +/-6 20 +/-5 23 +/-5 26+/-6 23+/-5 05/30/07 -06/06/07 17 +/- 5 14 +/- 5 16 +/- 5 20 +/- 5 13 +/- 5 15 +/-5 17 +/-5 06/06/07 -06/13/07 17 +/- 5 10 +/- 5 14 +/- 5 16 +/- 5 17 +/- 5 13 +/-5 13 +/-5 06/13/07 -06/20/07 17 +/-5 19 +/-5 17 +/-5 16 +/-5 16 +/-5 19+/-5 17+/-5 06/20/07-06/27/07 20 +/-5 16 +/-5 20 +/-5 22 +/-5 17 +/-5 21+/-5 21+/-5 06/27/07 -07/04/07 15 +/- 5 15 +/- 5 15 +/- 5 21 +/- 10 15 +/- 5 14 +/-5 13 +/-5 07/04/07 -07/11/07 18 +/- 5 23 +/- 6 16 +/- 5 23 +/- 6 18 +/- 5 21 +/- 5 19 +/- 5 07/11/07

-07/18/07 15 +/- 5 18 +/- 5 18 +/- 5 22 +/- 6 17 +/- 5 21 +/- 5 22 +/- 6 07/18/07-07/25/07 11 +/-5 20 +/-5 18 +/-5 118+/- 5 16 +/-5 17 +/-5 20+/- 5 07/25/07 -08/01/07 14 +/-5 13 +/-5 23 +/-5 1 2 +/-5 20 +/-5 19 +/-5 23+/- 5 08/01/07-08/08/07 26 +/-6 34 +/-6 33 +/-6 32 +/-6 27 +/-6 31 +/-6 35 +/-6 08/08/07-08/15/07 17 +/-5 21 +/-5 23 +/-5 25 +/-5 22 +/-5 24 +/-5 24+/- 5 08/15/07-08/22/07 21 +/-5 21 +/-5 18 +/-5 19 +/-5 19 +/-5 18 +/-5 19 +/-5 08/22/07 -08/29/07 19 +/- 6 13 +/- 5 13 +/- 5 13 +/- 5 18 +/- 5 13 +/- 5 19 +/- 5 08/29/07-09/05/07 22 +/-6 24 +/-6 23 +/-6 28 +/-6 23 +/-6 26 +/-6 29+/- 6 09/05/07-09/12/07 24 +/-6 21 +/-6 24 +/-6 20 +/-6 26 +/-6 28 +/-6 27+/- 6 09/12/07 -09/19/07 17 +/- 5 (1) 16 +/- 5 20 +/- 5 16 +/- 5 16 +/- 5 15 +/- 5 09/19/07-09/26/07 24 +/-6 26 +/-6 25 +/-6 27 +/-6 23 +/-6 21 +/-5 28+/- 6 09/26/07-10/03/07 19 +/-5 19 +/-5 23 +/-6 25 +/-6 22 +/-5 22 +/-5 20 +/-5 10/03/07 -10/10/07 22 +/- 5 19 +/- 5 25 +/- 5 19 +/- 5 19 +/- 5 20 +/- 5 24 +/- 5 10/10/07 -10/17/07 15 +/-6 18 +/-6 18 +/-6 12 +/-6 17 +/-6 17+/-6 17+/- 6 10/17/07-10/24/07 27 +/-6 27 +/-6 23 +/-6 30 +/-6 23 +/-6 29+/-6 26+/- 6 10/24/07 -10/31/07 13 +/- 5 11 +/- 5 16 +/- 5 14 +/- 5 14 +/- 5 12 +/-5 18 +/- 5 10/31/07 -11/07/07 17 +/- 5 14 +/- 5 20 +/- 6 19 +/- 6 20 +/- 6 18 +/-5 15 +/- 5 11/07/07 -11/14/07 23 +/- 6 20 +/- 5 21 +/- 5 21 +/- 5 23 +/- 6 25 +/-5 22 +/- 5 11/14/07 -11/20/07 16 +/- 6 13 +/- 7 10 +/- 6 11 +/- 6

<8 15 +/-6 13 +/- 6 11/20/07 -11/28/07 24 +/- 5 23 +/- 5 25 +/- 5 20 +/- 5 21 +/- 5 26 +/-5 25 +/- 5 11/28/07 -12/04/07 22 +/- 6 20 +/- 6 18 +/- 6 15 +/- 6 22 +/- 6 16 +/-5 21 +/- 6 12/04/07 -12/12/07 21 +/- 5 19 +/-5 19 +/-5 21 +/- 5 20 +/-5 21+/-5 17+/- 5 12/12/07 -12/19/07 19 +/- 6 18 +/- 6 19 +/- 6 19 +/- 6 18 +/- 5 18 +/-5 17 +/- 5 12/19/07 -12/26/07 19 +/- 6 19 +/- 6 24 +/- 6 29 +/- 6 21 +/- 6 19 +/-5 26 +/- 6 12/26/07 -01/01/08 29 +/-6 34 +/-7 35 +/-7 29 +/-6 31 +/-6 32+/-6 29+/- 6 MEAN 17 +/-9 18+/-11 19 +/-11 18 +/-11 18 +/-9 18+/-11 19 +/-11

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C - 13

TABLE C-VII.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, 2007 GROUP I - CLOSEST TO THE SITE BOUNDARY COLLECTION MIN MAX MEAN +

PERIOD 2SD GROUP II - INTERMEDIATE OFFSITE COLLECTION MIN MAX MEAN +

PERIOD 2SD GROUP III - CONTROL LOCATIONS COLLECTION MIN MAX MEAN +

PERIOD 2SD 01/03/07 01/31/07 02/28/07 03/28/07 05/02/07 05/30/07 06/27/07 08/01/07 08/29/07 10/03/07 10/31/07 11/28/07

- 01/31/07

- 02/28/07

- 03/28/07

- 05/02/07

- 05/30/07

- 06/27/07

- 08/01/07

- 08/29/07

- 10/03/07

- 10/31/07

- 11/28/07 01/01/08 12 7

11

<7 9

10 11 13 17 11 13 18 21 19 20 18 23 20 23 34 26 27 24 34 15 +

15 +

16 +

12 +

15 +/-

16 +

16 +

21 +

22 +

19+

19+

22 +

6 9

6 7

10 6

7 13 6

12 9

11 U IIUji.1i 01/31/07 02/28/07 03/28/07 05/02/07 05/30/07 06/27/07 08/01/07 08/29/07 10/03/07 10/31/07 11/28/07 U DIo IU/

02/28/07 03/28/07 05/02/07 05/30/07 06/27/07 08/01/07 08/29/07 10/03/07 10/31/07 11/28/07 01/01/08

<7

<8 0

L3 10 21 11 25 22 10 29 13 22 12 23 13 33 16 28 12 30 26 15 35 16 +/- 8 17 +/- 7 12 +/- 7 16 +/- 11 17 +/- 5 18 +/- 6 22 +/- 13 23 +/- 7 19 +/- 11 19 +/- 11 22+/- 11 U IIU03UI 01/31/07 02/28/07 03/28/07 05/02/07 05/30/07 06/27/07 08/01/07 08/29/07 10/03/07 10/31/07 11/28/07 01/31/07 02/28/07 03/28/07 05/02/07 05/30/07 06/27/07 08/01/07 08/29/07 10/03/07 10/31/07 11/28/07 01/01/08 13 8

11 7

12 13 13 19 15 17 13 17 2u 21 23 15 23 21 23 35 29 26 25 29 17 +/- (

17 +/- 12 15 +/- 10 13 +/- 7 15 +/- 10 17 +/- 6 19 +/- 8 24 +/- 15 24 +/- 12 21 +/- 9 19 +/- 11 22 +/- 11 01/03/07 -

01/01/08 < 7 34 17'+/- 6 01/03/07 - 01/01/08

< 7 35 18+/- 6 01/03/07 - 01/01/08

< 7 35 19 +/-7

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

TABLE C-VII.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD BE-7 MN-54 CO-58 CO-60 CS-1 34 CS-1 37 A3-1 01/03 -

04/04 -

07/04 -

10/03 -

MEAN E1-2 01/03 -

04/04 -

• 07/04 10/03 -

MEAN F1-3 01/03 -

04/04 -

07/04 -

10/03 -

MEAN G2-1 01/03 -

04/04 -

07/04 -

10/03 -

MEAN H3-1 01/03 -

04/04 -

07/04 -

10/03 -

MEAN M2-1 01/03 -

04/04 -

07/04 -

10/03 -

MEAN Q15-1 01/03 -

04/04 -

07/04 -

10/03 -

MEAN U4/U4/IU 07/04/07 10/03/07 01/01/08 04/04/07 07/04/07 10/03/07 01/01/08 04/04/07 07/04/07 10/03/07 01/01/08 04/04/07 07/04/07 10/03/07 01/01/08 04/04/07 07/04/07 10/03107 01/01/08 04/04/07 07/04/07 10/03/07 01/01/08 04/04/07 07/04/07 10/03/07 01/01/08 76 +/- 24 84 +/- 27 111 +/- 36 60 +/- 25 83 +/- 43 84 +/-

109 +/-

105 +/-

75 +/-

37 31 38 29 93 +/- 33 83 +/-

102 +/-

95 +/-

93 +/-

20 49 36 34 93 +/- 16 106 +/-

99 +/-

75 +/-

80 +/-

31 42 32 26

< 2

<3

<3

<3

<4

<3

<3

<3

<2

<4

<4

<4

<3

<4

<3

<3

<4

<3,

<3

<2

<3

<2

<4

< 3,

<4

<2

<2

<3

< 3

<4

<5

<4

<5

<3

<4

<3

<3

<5

<5

<5

<4

<6

<3

<5

<3

<5

<5

<3

<4

<5

<4

<3

<3

<4

<3

<4

<3

< 3

<4

<3

<2

<3

<4

<2

<2

<3

<3

<3

<4

<4

<3

<4

<4

<2

<4

<2

<4

<3

<5

<2

<3

<3

<4

<3

<2

<3

<4

<4

<3

<3

<5

<3

<2

<5

<5

<4

<3

<5

<4

<3

<3

<4

<4

<2

<2

<2

<4

<3

<4

<3

<4

<3

<2

<4

<3

<3

<3

<4

<3

<4

<3

<2

<3

<2

<2

<3

<4

<2

<3

<3

<3

<2 90 +/- 30 94 +/-

105 +/-

71 +/-

61 +/-

32 30 29 21 83 +/- 40 99 +/-

61 +/-

81 +/-

42 +/-

31 36 31 24 3

3 5

3 71 +/- 49 92 +/-

126 +/-

72 +/-

82 +/-

39 35 37 33

<3

<2

<3

<3 93 +/- 47 C - 15

TABLE C-VIII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I I

GROUP 11 GROUP III Q15-1 COLLECTION PERIOD 01/03/07 0

01/10/07

-0' 01/17/07 0

01/24/07

-0 01/31/07

-0:

02/07/07

-0:

02/14/07

-0:

02/21/07

-0:

02/28/07

-0:

03/07/07

-0:

03/14/07

-0:

03/21/07

-0:

03/28/07

-0 04/04/07 -0 04/11/07 -0 04/18/07 -0 04/25/07 -0:

05/02/07

-0:

05/09/07

-0:

05/16/07

-0:

05/23/07

-0:

05/30/07

-0' 06/06/07

-01 06/13/07

-01 06/20/07 0

06/27/07

-0 07/04/07

-0' 07/11/07 0

07/18/07 0

07/25/07

-0:

08/01/07

-0:

08/08/07 -0:

08/15/07 -0:

08/22/07 -0:

08/29/07 0

09/05/07 0

09/12/07 0

09/19/07 0

09/26/07 1 i 10/03/07 1 i 10/10/07 1 i 10/17/07

-11 10/24/07 1 i 10/31/07 -1 11/07/07 -1 11/14/07 -1 11/20/07 -1 11/28/07

-1; 12/04/07

-1:

12/12/07

-1; 12/19/07

-1; 12/26/07 -0 El -2 Fl -3 A3-1 G2-1 1-3-1 M2-1 m

)1/10/07 1/17/07 1/24/07 1/31/07 2/07/07 2/14/07 2/21/07 2/28/07 3/07/07 3/14/07 3/21/07 3/28/07 4/04/07 4/11/07 4/18/07 4/25/07 5/02/07 5/09/07 5/16/07 5/23/07 5/30/07 6/06/07 6/13/07 6/20/07 6/27/07 7/04/07 7/11/07 7/18/07 7/25/07 8/01/07 8/08/07 3/15/07 8/22/07 8/29/07 9/05/07 9/12/07 9/19/07 9/26/07 0/03/07 0/10/07 0/17/07 0/24/07 0/31/07 1/07/07 1/14/07 1/20/07 1/28/07 2/04/07 2/12/07 2/19/07 2/26/07 1/01/08

• 13

• 18

• 21

• 42

• 26

• 32

• 37

• 44

• 27

• 24

• 17

• 23

• 35

• 36

• 33

• 21

• 23

• 37

• 63

• 57

• 41

• 31

< 11

• 43

• 18

< 40

• 52

• 44

• 47

• 45

• 31

• 48

• 56

• 69

• 40

• 48

• 39

• 52

• 32

• 39

• 50

• 65

• 30

• 28

• 65

• 40

• 40

• 57

• 20

• 55

• 57

• 46

• 12

• 18

• 20

• 42

• 14

• 31

• 37

• <43

• 27

• 24

• 17

• 23

< 34

• 36

• 33

• 21

• 23

• 37

• 63

• 57

< 41

• 31

< 11

• 21

• 18

• 40

• 53

• 56

• 47

• 46

• 31

• 48

• 45

• 69

• 40

• 48

• 52

• 32

• 40

• 50

• 65

• 30

• 28

• 66

• 49

• 40

• 58

• 20

• 54

• 58

• 46

• 12

• 37

• 21

• 37

• 33

• 31

• 39

• 47

• 29

• 27

• 31

• 28

• 27

• 28

• 30

• 20

• 23

• 37

• 50

• 54

• 66

• 28

< 9

• 33

• 19

• 37

• 53

• 66

< 43

• 54

• 24

• 47

• 65

• 61

• 69

• 55 (1)

< 69

• 57

< 41

< 48

• 65

• 69

• 39

• 28

• 65

• 50

• 39

• 64

• 24

• 59

• 27

• <44

• 13

• 19

• 21

< 43

• 26

• 32

• 38

< 45

• 28

• 24

• 18

• 23

• 35

• 37

• 34

• 21

• 24

• 30

• 64

• 59

< 42

• 31

< 11

• 43

• 18

• 69

• 53

• 56

• 48

• 46

• 31

• 50

• 56

• 70

• 40

• 48

• 39

• 55

• 32

< 40

• 51

• 66

• 30

• 28

• 67

• 40

• 40

• 25

• 21

• 54

• 59

• <47

• 13

• 19

• 14

• 43

• 26

• 32

• 38

• 44

• 28

• 24

• 17

• 17

• 35

• 36

• 33

• 21

• 24

• 38

• 63

• 59

• 42

• 31

< 11

• 43

• 18

< 41

• 53

• 54

• 47

• 45

• 35

• 48

• 55

• 68

< 40

• 47

• 38

• 54

• 31

• 39

• 50

• 35

• 30

• 28

• 66

• 39

• 38

• 57

• 20

• 53

• 35

• 45

• 12

• 36

• 20

• 37

• 25

• 32

• 39

< 47

• 29

• 27

• 31

• 29

• 34

• 28

• 30

• 20

• 23

• 37

• 52

• 53

• 66

• 28

< 9

• 43

• 20

• 22

• 27

• 53

< 41

• 51

• 34

< 44

• 62

• 57

• 66

• 52

• 68

• 53

• 39

< 46

• 61

• 62

• 37

• 27

• 62

< 47

• 37

• 61

• 23

• 55

• 34

• 42

• 12

• 36

• 21

• 37

• 32

• 17

• 38

• 47

• 29

• 26

• 30

• 28

• 34

• 28

• 30

• 20

• 22

• 37

• 51

• 53

• 66

• 28

< 9

• 33

• 20

• 36

• 52

• 64

< 42

• 52

• 35

• 46

• 64

• 59

• 68

• 54

• 69

• 55

• 40

• 47

• 63

• 67

• 38

• 28

• 51

• 49

• 38

• 64

• 23

• 57

• 35

• 44 MEAN--

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C -16

TABLE C-IX.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM I K15-3 COLLECTION PERIOD 01/10/07 02/07/07 03/07/07 03/21/07 04/04/07 04/18/07 05/02/07 05/16/07 05/30/07 06/13/07 06/27/07 07/11/07 07/25/07 08/08/07 08/22/07 09/05/07 09/19/07 10/03/07 10/17/07 10/31/07 11/14/07 11/28/07 12/12/07 D2-1 INDICATOR FARMS E2-2 F4-1 G2-1

< 0.5

< 0.4

< 0.7

< 0.5

< 0.8

< 0.7

< 0.5

< 0.7

• 1.0

• 0.7

• 0.9

< 0.7

< 0.5

< 0.7

< 0.6

< 0.7

< 0.7

< 0.6

< 0.8

< 0.7

< 0.6

< 0.6

< 0.6

< 0.4

< 0.3

< 0.6

< 0.5

< 0.6

< 0.6

• 0.5

< 0.5

< 0.8

< 0.7

< 0.6

• 0.7

• 0.4

< 0.5

< 0.6

• 0.7

< 0.6

< 0.5

< 0.6

< 0.6

< 0.5

< 0.5

< 0.6

< 0.6

< 0.7

< 0.6

< 0.8

< 0.9

< 0.8

< 0.6

< 0.7

< 0.7

< 0.7

< 0.7

< 0.9

< 0.6

< 0.7

< 0.6

< 0.8

< 0.7

< 0.8

< 0.6

< 0.6

< 0.6

< 0.6

< 0.6

< 0.5

< 0:7 (1)

< 0.8

< 0.9

< 0.5

< 0.7

< 0.8

< 0.5

< 0.6

• 0.6

< 0.8

< 0.6

< 0.7

< 0.5

< 0.6

< 0.6

• 0.5

< 0.5

< 0.4

< 0.6

< 0.6

< 0.8

< 0.8

< 0.5

< 0.7

• 0.7

< 0.7

< 0.6

< 0.8

< 0.5

< 0.7

< 0.8

• 0.7

< 0.7

< 0.6

< 0.7

< 0.6

< 0.7

< 0.6

< 0.6 MEAN (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C - 17

TABLE C-IX.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDICATOR FARMS COLLECTION PERIOD K15-3 SR-90 D2-1 E2-2 F4-1 G2-1 SR-89 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 01/10/07 01/10/07 03/21/07 04/04/07 05/16/07 07/11/07 10/03/07

- 03/21/07

- 03/21/07

- 03/21/07

- 06/27/07

- 05/16/07

- 09/19/07

- 12/12/07

< 3.8

• 1.6

• 3.0

< 4.5

• 0.8

• 0.6

< 3.8

• 1.8

• 0.7

• 0.7

< 3.7

• 2.0

< 0.8 0.9 +/- 0.5

< 3.2 1.0 +/- 0.6

< 1.7 0.6 +/- 0.4

< 2.6 0.9 +/- 0.2

< 1.8

< 0.9

< 0.7

< 2.0 1.1 +/- 0.4

<4.5 0.7 +/- 0.3

< 3.1 0.9 +/- 0.5 1.4 +/- 0.7

• 0.6 0.8 +/- 0.6

• 0.7

< 3.4

• 2.0

< 3.4

• 3.2

< 0.7 0.8 +/- 0.2 (1)

< 0.6 0.9 +/- 0.7 0.6 +/- 0.4 MEAN 1.0 +/- 0.2 0.7 +/- 0.4 1.1 +/- 0.8 0.8 +/- 0.4 00 (1) RERUN RESULT

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

TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD D2-1 01/10/07 1290 +/- 169

< 5

< 7

< 35

< 9 02/07/07 962 +/- 194

< 7

< 9

< 43

< 15 03/07/07 1270 +/- 195

< 8

< 10

< 40

< 12 03/21/07 1270 +/- 105

< 4

< 4

< 14

< 4 04/04/07 1410 +/- 187

< 7

< 7

< 24

< 8 04/18/07 1190 +/- 148

< 5

< 7

< 28

< 8 05/02/07 1370 +/- 169

< 6

< 7

< 36

< 9 05/16/07 1290 +/- 108

< 4

< 5

< 24

< 7 05/30/07 1150 +/- 83

< 3

< 3

< 29

< 8 06/13/07 1320 +/- 110

< 3

< 4

< 33

< 10 06/27/07 1260 +/- 124

< 4

< 5

< 43

< 13 07/11/07 1250 +/- 116

< 4

< 5

< 22

< 6 07/25/07 1290 +/- 82

< 3

< 4

< 22

< 7 08/08/07 1160 +/- 193

< 9

< 9

< 40

< 15 08/22/07 1390 +/- 83

< 3

< 3

< 33

< 10 09/05/07 1220 +/- 39

< 1

< 2

< 21

< 6 09/19/07 1290 +/- 128

< 5

< 5

< 32

< 10 10/03/07 1370 +/- 140

< 6

< 6

< 30

< 9 10/17/07 1460 +/- 81

< 3

< 3

< 44

< 14 10/31/07 1310 +/- 132

< 6

< 7

< 38

< 13 11/14/07 1280 +/- 94

< 3

< 4

< 47

< 15 11/28/07 1130 +/- 154

< 7

< 7

< 46

< 14 12/12/07 1340 +/- 51

< 2

< 2

< 14

< 4 MEAN 1273 +/- 214 E2-2 01/10/07 1240 +/- 195

< 9

< 8

< 36

< 13 02/07/07 1310 +/- 206

< 8

< 10

< 35

< 13 03/07/07 1180 +/- 136

< 5

< 5

< 22

< 10 03/21/07 1300 +/- 143

< 5

< 7

< 23

< 9 04/04/07 1080 +/- 166

< 8

< 9

< 32

< 9 04/18/07 1320 +/- 148

< 6

< 6

< 31

< 10 05/02/07 1310 +/- 142

< 6

< 6

< 25

< 9 05/16/07 1330 +/- 152

< 7

< 8

< 39

< 14 05/30/07 1160 +/- 102

< 4

< 5

< 38

< 12 06/13/07 1280 +/- 127

< 4

< 4

< 49

< 14 06/27/07 1320 +/- 154

< 5

< 7

< 50

< 13 07/11/07 1400 +/- 124

< 5

< 5

< 29

< 8 07/25/07 1390 +/- 85

< 3

< 4

< 23

< 6 08/08/07 1200 +/- 195

< 8

< 12

< 55

< 10 08/22/07 1400 +/- 93

< 4

< 5

< 41

< 12 09/05/07 1270 +/- 173

< 7

< 8

< 55

< 14 09/19/07 1330 +/- 100

< 4

< 4

< 26

< 8 10/03/07 1360 +/- 129

< 5

< 6

< 32

< 8 10/17/07 1310 +/- 62

< 3

< 3

< 41

< 13 10/31/07 1250 +/- 109

< 6

< 7

< 41

< 14 11/14/07 1250 +/- 91

< 3

< 4

< 46

< 15 11/28/07 1310 +/- 140

< 5

< 5

< 39

< 14 12/12/07 1290 +/- 60

< 2

< 3

< 19

< 5 MEAN 1287 +/- 155 C - 19

TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD F4-1 03/21/07 1370 +/- 145

< 5

< 5

< 22

< 7 05/16/07 1270 +/- 148

< 6

< 7

< 38

< 7 05/30/07 1320 +/- 117

< 4

< 5

< 40

< 11 06/13/07 1390 +/- 43

< 2

< 2

< 19

< 5 06/27/07 1380 +/- 115

< 5

< 5

< 42

< 13 07/11/07 1420 +/- 132

< 5

< 6

< 31

< 10 07/25/07 1430 +/- 84

< 3

< 4

< 25

< 7 08/08/07 1360 +/- 191

< 6

< 8

< 39

< 11 08/22/07 1340 +/- 77

< 3

< 3

< 31

< 8 09/05/07 1330 +/- 112

< 4

< 4

< 29

< 9 09/19/07 1400 +/- 131

< 5

< 6

< 37

< 15 10/03/07 1340 +/- 145

< 7

< 7

< 35

< 8 10/17/07 1330 +/- 51

< 2

< 2

< 28

< 8 10/31/07 1340 +/- 188

< 7

< 9

< 54

< 14 11/14/07 1390 +/- 105

< 3

< 4

< 53

< 15 11/28/07 1300 +/- 114

< 4

< 5

< 30

< 10 12/12/07 1400 +/- 57

< 2

< 2

< 16

< 4 MEAN 1359 +/- 87 G2-1 01/10/07 784 +/- 164

< 8

< 11

< 32

< 15 02/07/07 1250 +/- 195

< 7

< 7

< 26

< 9 03/07/07 1010 +/- 174

< 7

< 9

< 39

< 10 03/21/07 1220 +/- 123

< 4

< 5

< 19

< 5 04/04/07 967 +/- 150

< 10

< 10

< 40

< 13 04/18/07 1340 +/- 171

< 9

< 9

< 38

< 11 05/02/07 1160 +/- 147

< 7

< 7

< 31

< 12 05/16/07 1210 +/- 119

< 4

< 5

< 24

< 7 05/30/07 1220 +/- 102

< 4

< 4

< 35

< 11 06/13/07 1050 +/- 48

< 2

< 2

< 20

< 7 06/27/07 959 +/- 96

< 4

< 4

< 39

< 14 07/11/07 1220 +/- 148

< 5

< 6

< 31

< 11 07/25/07 1140 +/- 87

< 3

< 4

< 24

< 7 08/08/07 1260 +/- 184

< 7

< 9

< 38

< 13 08/22/07 1300 +/- 111

< 4

< 5

< 45

< 14 09/05/07 1400 +/- 163

< 7

< 7

< 53

< 14 09/19/07 1220 +/- 113

< 4

< 5

< 33

< 9 10/03/07 1400 +/- 120

< 4

< 6

< 22

< 8 10/17/07 1250 +/- 64

< 4

< 4

< 46

< 14 10/31/07 1250 +/- 120

< 9

< 8

< 46

< 14 11/14/07 1410 +/- 83

< 3

< 4

< 46

< 15 11/28/07 1300 +/- 110

< 4

< 4

< 30

< 11 12/12/07 1240 +/- 55

< 2

< 3

< 18

< 6 MEAN 1198 +/- 310 C - 20

TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD K15-3 01/10/07 02/07/07 03/07/07 03/21/07 04/04/07 04/18/07 05/02/07 05/16/07 05/30/07 06/13/07 06/27/07 07/11/07 07/25/07 08/08/07 08/22/07 09/05/07 09/19/07 10/03/07 10/17/07 10/31/07 11/14/07 11/28/07 12/12/07 K-40 Cs-134 Cs-137 Ba-140 La-140 1450 1310 1100 1340 1410 1180 1330 1210 1230 1400 1420 1210 1390 1200 1310 1280 1380 1220 1350 1330 1320 1400 1310

+/- 157

+/- 203

+/- 163

+/- 142

+/- 155

+/- 130

+/- 166

+/- 127

+/- 115

+/- 50

+/- 106

+/- 138

+/- 84

+/- 206

+/- 77

+/- 100

+/- 117

+/- 169

+/- 41

+/- 153

+/- 85

+/- 168

+/- 71

<5

<7

<6

<5

<6

<4

<6

<4

<4

<1

<3

<4

<3

<5

<3

<3

<5

<6

<2

<6

<3

<7

<3

<5

<9

<8

<5

<8

<6

<6

<5

<4

<1

<5

<4

<4

<10

<4

<4

<6

<7

<2

<7

<4

<8

<3

• 29

< 39

• 32

• 23

• 21

• 28

• 30

• 20

< 35

<15

• 38

• 20

• 21

< 39

• 36

• 31

• 38

< 33

• 27

< 54

< 53

• 42

• 21

<5

<11

<11

<7

<7

<8

<10

<8

<14

<4

<14

<9

<6

<9

<9

<9

<13

<9

<8

< 14

< 14

< 14

<6 MEAN 1308 +/- 181 C-21

TABLE C-X.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESUL SR-90 TS IN UNITS OF PCI/KG WET +/- 2 SIGMA Be-7 K-40 1-131 C-)

t'J STC COLLECTI PERIOD B10-2 06/29/07 B10-2 06/29/07 8310-2 06/29/07 8310-2 07/24/07 810-2 07/24/07 810-2 07/24/07 B10-2 08/01/07 B10-2 08/01/07 B10-2 08/01/07 B10-2 08/06/07 B10-2 08/29/07 B10-2 08/29/07 B10-2 08/29/07 Cs-134 Cucumber Leaves Sweet Corn Leaves Zucchini Leaves Cabbage Sweet Corn Tomatoes Cabbage Sweet Corn Leaves Zucchini Leaves Red Beets Cabbage Eggplant Leaves Squash Leaves 37 +

11

+

40 +

3+

3 3

3 1

<2 1280 +/- 263 643 +/- 188 402 +/- 101

< 55

< 95

• 42

< 143 1140 +/- 233 1700 +/- 201

< 109

< 149 3640 +/- 132 3120 +/- 125 5090 +/- 525 4470 +/- 404 3810 +/- 300 2510 +/- 133 2470 +/- 216 2740 +/- 99 2830 +/- 312 4160 +/- 469 4690 +/- 422 2960 +/- 309 3030 +/- 331 5250 +/- 210 4710 +/- 208

< 36

• 22

<16

< 21

< 40

< 20

< 28

< 46

< 29

< 21

< 47

< 27

• 29

• 26

<16

<12

<6

< 10

<4

<13

• 21

<15

< 11

<15

<8

<8 Cs-137

< 29

< 17

<13

<7

<10

<4

<12

< 23

< 17

<12

• 18

<8

<10 5+/-

6+/-

3+/-

15+/-

16 +/-

2 2

2

TABLE C-X.1 STC COLLECTI PERIOD B10-2 09/26/07 B10-2 09/26/07 B10-2 09/26/07 MEAN CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SR-90 Be-7 K-40 1-131 Cs-134 Cs-1 37 Broccoli Leaves Cabbage Cauliflower Leaves 47 +/-

12 +

18 +

18 +

5 2

3 30

< 191

< 181

< 201 1704 +/- 2459 2800 +/- 315 2030 +/- 327 3040 +/- 428 3537 +/- 2089 2280 +/- 110 2940 +/- 150 3040 +/- 138 3980 +/- 424 3060 +/- 1400

< 57

• 51

< 53

< 17

< 17

< 18

<17

< 20

< 23 E1-2 E1-2 E1-2 E1-2 07/24/07 07/24/07 07/24/07 08/06/07 MEAN Cabbage Sweet Corn Tomatoes Red Beets 3+/-1

<44

< 58

• 60

• 156 3+/-0

< 18

< 25

• 26

< 30

<4

<6

<6

< 17

<5

<7

<6

< 20

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

TABLE C-X.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION SR-90 Be-7 K-40 1-131 Cs-134 Cs-137 PERIOD H1-2 06/29/07 Sweet Corn Leaves 12 +/- 3 940 +/- 197 3980 +/- 506

< 30

< 23

< 26 H1-2 06/29/07 Yellow Squash Leaves 30 +/- 3 457 +/- 244 4140 +/- 586

< 35

< 26

< 30 H1-2 06/29/07 Zucchini Leaves 27 +/- 3

< 313 4760 +/- 662

< 38

< 24

< 26 H1-2 08/01/07 Cabbage & Leaves 2 +/- 1

< 177 4400 +/- 428

< 42

< 16

< 20 H1-2 08/01/07 Sweet Corn Leaves 7 +/- 2 1350 +/- 278 4810 +/- 523

< 53

< 24

< 29 H1-2 08/01/07 Zucchini Leaves 13 +/- 1 987 +/- 146 3420 +/- 297

< 34

< 15

< 16 H1-2 08/29/07 Cabbage

< 2

< 97 2080 +/- 247

< 34

< 10

< 12 H1-2 08/29/07 Squash Leaves 9 +/- 2 538 +/- 194 4660 +/- 488

< 58

< 19

< 21 H1-2 08/29/07 Sweet Corn Leaves 6 +/- 3 2470 +/- 284 3210 +/- 400

< 52

< 20

< 24 H1-2 09/26/07 Cabbage 15 +/- 2

< 204 2530 +/- 392

< 54

< 21

< 21 H1-2 09/26/07 Eggplant Leaves 32 +/- 2 644 +/- 160 3270 +/- 300

< 47

< 14

< 14 H1-2 09/26/07 Squash Leaves 42 +/- 4 414 +/- 162 3160 +/- 408

< 50

< 15

< 18 MEAN 18 +/- 26 975 +/- 1365 3702 +/- 1792

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

TABLE C-XI.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGENS/STD. MONTH STATION CODE Al-4 A3-1 A5-1 A9-3 B1-1 B1-2 B2-1 B5-1 B10-1 C1-1 C1-2 C2-1 C5-1 C8-1 Dl-1 D1-2 D2-2 D6-1 D15-1 El-2 El-4 E2-3 E5-1 E7-1 F1-1 Fl-2 Fl-4 F2-1 F5-1 F10-1 F25-1 G1-2 G1-3 G1-5 G1-6 G2-4 G5-1 G10-1 G15-1 Hi-l H3-1 H5-1 H8-1 H15-1 Ji-i MEAN

+/-2 S.D.

5.1 +/- 1.0 5.6 +/- 1.1 6.1 +/- 1.1 5.2 +/- 1.0 5.3 +/- 0.9 5.2 +/- 0.8 5.4 +/- 1.0 6.0 +/- 1.1 5.9 +/- 1.4 5.8 +/- 0.9 5.1 +/- 0.9 5.7 +/- 1.1 6.2 +/- 1.3 6.3 t 1.1 5.2 +/- 0.9 5.6 +/- 1.2 6.7 +/- 1.0 6.7 +/- 1.3 6.0 +/- 0.9 5.4 +/- 1.0 5.0 +/- 1.0 6.3 +/- 1.1 5.7 +/- 1.1 6.1 +/- 1.2 5.7 +/- 1.0 5.3 +/- 1.0 5.1 +/- 1.0 6.3 +/- 1.1 6.6 +/- 0.9 7.1 +/- 1.3 6.2 +/- 1.2 6.0 +/- 1.1 5.1 +/- 1.0 5.2 +/- 0.9 5.3 +/- 1.0 6.9 +/- 1.2 5.6 +/- 0.8 7.9 +/- 1.5 6.5 +/- 1.0 5.6 +/- 1.1 5.0 +/- 1.1 4.7 +/- 1.0 7.7 +/- 4.2 6.7 +/- 0.9 5.4 +/- 1.3 01/10/07 - 04/16/07 04/16/07 - 07/13/07 07/13/07 - 10/11/07 10/11/07 - 01/12/08 5.3 6.0 6.2 5.3 5.6 5.5 5.7 6.5 5.9 6.0 5.3 6.0 6.2 6.2 5.4 5.8 6.9 6.8 6.2 5.6 5.3 6.6 5.9 6.2 5.9 5.5 5.5 6.5 6.7 7.2 6.8 6.2 5.6 5.5 5.6 7.0 5.8 7.9 6.7 6.2 5.3 5.2 9.2 6.9 5.6

+/- 0.6

+/- 0.4

+/- 0.6

+/- 0.4

+/- 0.4

+/- 0.5

+/- 0.9

+/- 0.3

+/- 0.5

+/- 0.6

+/- 0.2

+/- 0.6

+/- 0.5

+/- 0.3

+/- 0.3

+/- 0.3

+/- 0.4

+/- 0.5

+/- 0.4

+/- 0.4

+/- 0.3

+/- 0.3

+/- 0.4

+/- 0.3

+/- 0.6

+/- 0.2

+/- 0.3

+/- 0.3

+/- 0.6

+/- 0.3

+/- 0.7

+/- 0.4

+/- 0.2

+/- 0.5

+/- 0.4

+/- 0.3

+/- 0.5

+/- 0.2

+/- 0.7

+/- 0.4

+/- 0.3

+/- 0.4

+/- 0.5

+/- 0.6

+/- 0.4 5.2 +/- 0.6 5.6 +/- 0.2 6.1 +/- 0.2 5.4 +/- 0.2 5.3 +/- 0.6 5.1

+/- 0.4 5.4 +/- 0.4 6.0 +/- 0.3 6.0 +/- 0.3 5.9 +/- 0.4 5.2 +/- 0.7 5.9 +/- 0.3 6.2 +/- 0.3 6.6 + 0.5 5.3 +/- 0.5 5.8 +/- 0.8 6.9 +/- 0.5 6.8 + 0.4 6.0 +/- 0.3 5.3 +/- 0.4 4.8 +/- 0.4 6.3 +/- 0.3 5.8 +/- 0.7 6.3 +/- 0.4 5.7 +/- 0.2 5.4 +/- 0.4 4.9 +/- 0.5 6.3 +/- 1.0 6.7 +/- 0.5 7.3 +/- 0.3 6.1 +/- 0.5 5.7 +/- 0.3 5.0 +/- 0.5 5.2 +/- 0.2 5.3 +/- 0.2 6.9 +/- 0.3 5.5 +/- 0.6 7.9 +/- 0.9 7.0 +/- 1.0 5.8 +/- 0.2 5.3 +/- 0.9 4.5 +/- 0.5 8.6 +/- 0.3 6.5 +/- 0.8 5.3 +/- 0.7 5.5 +/- 0.7 5.9 +/- 0.6 6.6 +/- 0.4 5.6 +/- 0.4 5.5 +/- 0.5 5.4 +/- 0.3 5.8 +/- 0.4 6.2 +/- 0.4 6.7 +/- 1.0 6.1 +/- 0.5 5.3 +/- 0.5 6.1 +/- 0.3 6.9 +/- 0.3 6.8 +/- 0.5 5.5 +/- 0.5 6.0 +/- 0.3 7.1 +/- 0.7 7.4 +/- 0.4 6.4 +/- 0.6 5.8 +/- 0.6 5.5 +/- 0.4 6.8 +/- 0.4 6.1 +/- 0.4 6.5 +/- 0.7 6.2 +/- 0.2 5.8 +/- 1.1 5.6 +/- 0.8 6.9 +/- 0.3 7.0 +/- 0.3 7.8 +/- 0.3 6.6 +/- 0.4 6.7 +/- 0.7 5.4 +/- 0.9 5.5 +/- 0.3 5.7 +/- 0.4 7.5 +/- 0.7 5.9 +/- 0.2 8.8 +/- 0.5 6.5 +/- 0.3 5.3 +/- 0.6 5.2 +/- 0.4 4.9 +/- 0.2 9.4 +/- 0.4 7.1 +/- 0.6 6.1 +/- 0.4 4.4 +/- 0.4 4.8 +/- 0.6 5.3 +/- 0.6 4.5 +/- 0.4 4.6 +/- 0.4 4.6 +/- 0.2 4.7 +/- 0.5 5.2 +/- 0.7 5.0 +/- 0.4 5.1 +/- 0.4 4.4 +/- 0.4 4.9 +/- 0.3 5.3 +/- 0.5 5.5 +/- 0.4 4.5 +/- 0.3 4.7 +/- 0.3 6.0 +/- 0.9 5.8 +/- 0.5 5.4 +/- 0.3 4.7 +/- 0.5 4.4 +/- 0.5 5.5 +/- 0.6 4.9 +/- 0.5 5.2 +/- 0.5 5.0 +/- 0.4 4.6 +/- 0.5 4.5 +/- 0.4 5.6 +/- 0.7 5.9 +/- 0.6 6.2 +/- 0.5 5.4 +/- 0.5 5.4 +/- 0.5 4.5 +/- 0.5 4.5 +/- 0.3 4.6 +/- 0.2 6.0 +/- 0.3 5.0 +/- 0.3 7.0 +/- 0.4 5.8 +/- 0.4 5.0 +/- 0.8 4.2 +/- 0.5 4.1 +/- 0.6 8.2 +/- 1.3 6.1 +/- 0.5 4.6 +/- 0.7 C -25

TABLE C-XI.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGENS/STD. MONTH STATION CODE MEAN

+/- 2 S.D.

01/10/07 - 04/16/07 04/16/07 - 07/13/07 07/13/07 - 10/11/07 10/11/07 - 01/12/08 J1-3 J3-1 J5-1 J7-1 J15-1 K1 -4 K2-1 K3-1 K5-1 K8-1 K15-1 LI-1 L1-2 L2-1 L5-1 L8-1 L15-1 Mi-i M1-2 M2-1 M5-1 M9-1 Ni-1 N1-3 N2-1 N5-1 N8-1 N15-2 Pi-i P1-2 P2-1 P5-1 P8-1 Q1-1 Q1-2 Q2-1 Q5-1 Q9-1 Q15-1 Ri-i R1-2 R3-1 R5-1 R9-1 Ri 5-1 4.8 +/- 0.9 5.6 +/- 0.9 6.4 +/- 1.2 6.7 +/- 0.9 6.6 +/- 1.2 5.2 +/- 1.1 6.4 +/- 1.0 5.3 +/- 1.0 6.5 +/- 1.7 6.0 +/- 0.9 5.7 +/- 1.0 5.4 +/- 0.4 5.0 +/- 0.9 6.0 +/- 1.7 5.3 +/- 1.2 6.1 +/- 2.2 5.9 +/- 1.1 5.2 +/- 0.6 5.8 +/- 1.1 5.0 +/- 0.9 5.8 +/- 1.3 7.0 +/- 1.2 5.6 +/- 1.2 5.3 +/- 0.6 5.9 +/- 1.4 4.9 +/- 1.3 6.0 +/- 1.0 6.5 +/- 1.1 5.5 +/- 0.9 5.7 +/- 1.7 6.8 +/- 2.2 6.2 +/- 1.9 5.0 +/- 1.5 5.6 +/- 1.4 4.9 +/- 0.5 5.3 +/- 1.3 5.5 +/- 1.3 5.8 +/- 1.1 6.1 +/- 1.0 5.1 +/- 1.2 5.1 +/- 1.2 6.4 +/- 1.5 6.2 +/- 1.1 6.1 +/- 1.2 5.6 +/- 0.9 5.2 +/- 0.2 5.9 +/- 0.4 6.7 +/- 0.4 7.0 +/- 0.7 7.0 +/- 0.7 5.7 +/- 0.7 6.8 +/- 0.7 5.9 +/- 0.4 7.3 +/- 0.5 6.2 +/- 0.2 6.1 +/- 0.4 5.6 +/- 0.5 5.3 +/- 0.3 6.4 +/- 0.4 5.9 +/- 0.1 6.3 +/- 0.4 6.2 +/- 0.4 5.5 +/- 0.4 6.0 +/- 0.6 5.5 +/- 0.4 6.4 +/- 0.2 7.4 +/- 0.5 5.9 +/- 0.5 5.6 +/- 0.2 6.6 +/- 0.4 5.6 +/- 0.2 6.3 +/- 0.4 7.0 +/- 0.5 5.8 +/- 0.7 5.4 +/- 0.3 7.0 +/- 0.5 6.5 +/- 0.6 5.8 +/- 0.8 6.2 +/- 0.2 5.1 +/- 0.3 5.8 +/- 0.6 6.3 +/- 0.3 6.5 +/- 0.2 6.6 +/- 0.7 5.9 +/- 0.3 5.8 +/- 0.3 7.0 +/- 0.6 6.7 +/- 0.5 6.5 +/- 0.5 5.8 +/- 0.5 4.8 5.4 6.4 6.6 6.5 5.0 6.4 4.9 6.2 6.0 5.6 5.3 5.0 5.9 5.3 5.8 5.7 5.0 5.7 5.0 5.5 7.0 5.8 4.9 5.5 4.6 6.0 6.4 5.4 4.9 6.3 6.1 4.8 5.8 5.0 5.1 5.3 5.8 6.2 5.1 5.2 6.3 6.3 6.3 5.7

+/- 0.5

+/- 0.3

+/- 0.6

+/- 0.9

+/- 0.8

+/- 0.3

+/- 0.6

+/- 0.4

+/- 0.3

+/- 0.2

+/- 0.3

+/- 0.6

+/- 0.4

+/- 0.9

+/- 0.3

+/- 0.2

+/- 0.4

+/- 0.4

+/- 0.4

+/- 0.3

+/- 0.1

+/- 0.6

+/- 0.3

+/- 0.3

+/- 0.3

+/- 0.2

+/- 0.4

+/- 0.3

+/- 0.3

+/- 0.3

+/- 0.3

+/- 0.6

+/- 0.3

+/- 0.2

+/- 0.5

+/- 0.3

+/- 0.4

+/- 0.5

+/- 0.5

+/- 0.2

+/- 0.8

+/- 0.3

+/- 0.7

+/- 0.2

+/- 0.2 4.9 +/- 0.1 6.1 +/- 0.5 7.0 +/- 0.5 7.1 +/- 0.2 7.2 +/- 0.5 5.6 +/- 0.2 6.8 +/- 0.5 5.5 +/- 0.3 7.0 +/- 0.5 6.5 +/- 0.4 6.1 +/- 0.3 5.5 +/- 0.7 5.2 +/- 0.3 6.7 +/- 1.3 5.6 +/- 0.2 6.1 +/- 0.5 6.4 +/- 0.3 5.3 +/- 0.4 6.3 +/- 0.4 5.1 +/- 0.1 6.2 +/- 0.5 7.3 +/- 0.3 5.9 +/- 0.2 5.4 +/- 0.3 6.4 +/- 0.5 5.3 +/- 0.2 6.3 +/- 0.4 6.8 +/- 0.4 5.8 +/- 0.4 5.5 +/- 0.2 8.3 +/- 0.4 7.2 +/- 0.3 5.4 +/- 0.4 5.7 +/- 0.4 4.9 +/- 0.4 5.7 +/- 0.3 5.5 +/- 0.4 5.7 +/- 0.4 6.3 +/- 0.3 5.0 +/- 0.3 5.0 +/- 0.3 6.9 +/- 0.3 6.3 +/- 0.4 6.4 +/- 0.3 5.8 +/- 0.2 4.1 +/- 0.3 5.1 +/- 0.8 5.6 +/- 0.3 6.1 +/- 0.3 5.8 +/- 0.6 4.5 +/- 0.5 5.7 +/- 0.4 4.8 +/- 0.5 5.4 +/- 0.5 5.4 +/- 0.3 5.1 +/- 0.6 5.2 +/- 0.7 4.3 +/- 0.6 4.8 +/- 0.4 4.5 +/- 0.4 5.0 +/- 0.4 5.2 +/- 0.5 4.9 +/- 0.5 5.0 +/- 0.7 4.4 +/- 0.6 5.0 +/- 0.5 6.1 +/- 0.9 4.7 +/- 0.4 5.4 +/- 0.6 5.2 +/- 0.3 4.2 +/- 0.4 5.2 +/- 0.3 5.7 +/- 0.7 4.9 +/- 0.5 6.9 +/- 0.8 5.7 +/- 0.5 4.9 +/- 0.3 4.1 +/- 0.1 4.6 +/- 0.2 4.5 +/- 0.6 4.4 +/- 0.3 4.7 +/- 0.4 5.1 +/- 0.4 5.4 +/- 0.6 4.5 +/- 0.6 4.4 +/- 0.6 5.4 +/- 0.5 5.4 +/- 0.4 5.2 +/- 0.3 4.9 +/- 0.3 C -26

TABLE C-XII.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGENS/MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC SITE BOUNDARY

+/- 2 S.D.

5.5 +/- 0.4 5.1 +/- 0.4 5.4 +/- 0.5 4.7 +/- 1.2 INDICATOR CONTROL 6.3 +/- 1.3 5.9 +/- 1.4 6.3 +/- 1.7 5.1 +/- 1.3 6.7 +/- 1.2 6.3 +/- 1.3 6.7 +/- 1.6 5.6 +/- 1.2 TABLE C-XI.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES PERIOD PERIOD ANALYZED MINIMUM MAXIMUM SITE BOUNDARY INDICATOR CONTROL 72 244 44 4.1 4.1 4.9 6.9 9.4 8.8 PERIOD MEAN PRE-OP MEAN

+/- 2 S.D.

+/- 2 S.D.

5.2 +/- 0.9 4.8 +/- 1.5 5.9 +/- 1.7 5.2 +/- 1.5 6.3 +/- 1.6 5.8 +/- 1.7 SITE BOUNDARY STATIONS - A1-4, B1-2, C1-2, Di-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, J1-3, K1-4, Li-1, Mi-1, N1-3, P1-2, Q1-2, Ri-i CONTROL STATIONS - D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, R15-1 INDICATOR STATIONS - A3-1, A5-1, A9-3, B1-1, B10-1, B2-1, B5-1, Cl-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, Fl-1, F10-1, F2-1, F5-1, G1-2, G2-4, G5-1, H1-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, Ni-i, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-i, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, R9-1 C -27

FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2007 El Station J-2 (Downstream of Discharge)... 2.StationQ9-1 (Control) 09 F1 l

U 1 0 0 0 0 0 ---

2n 10000 aI)7 100 +

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

-j 0~

.0 a-)

1000000 100000 -

10000-1000-100-10 -

A.....

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 - 2007 Indicator Samples

-- Control Samples 12000 11000 10000 9000 Sienificaht Events Maior Atm. Nuclear Weapon Tests TMI-l Critical June 1974 June 1974 September 1974 TMI-2 Critical March 1978 September 1976 November 1976 TMI-2 Accident March 1979 September 1977 March 1978 TMI-2 RB Purge June 1980 December 1978 October 1980 44 Chernobyl April 1986 8000 -

A) 0 0._

7000 +

6000 +

5000 +

4000 -I 3000 -

2000 +

1000 +

0+

-1000 N-O o

r-.-

00 0

0 C

M0 o

r.-

o

'T O

(

0 w

M 0

N o

t

)O (0 r-00 0

0 E;

N M

I LO CO r-co I-I-

w-N-

N,-

co o

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)

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0) 0o)

03)

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0 0

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0 0

0 0

0 0

0 Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2007 0l Indicator Samples nl Control Samples 10 9

8 7

6

-j U) 5 0-

._o 4

2...---

0

__~

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

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2007 NOTE: The mean values are calculated using both the MDCs and LI Indicator Samples R-Control Samples the positive values.

500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L 400 200

.T ~I 2 0 o

100

.nII II I

I I L Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month N Station K1-1 (TMINS Liquid Discharge) 1000000 100000 S 10000 U) a_ *10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month

FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2007 Indicator Samples Control Samples 900 -

Significant Event Cheinobyl April 19861 800 700 E00 "2

CD,

.2 500 IO _ 4 0 0 -- -

't-C,,

00 100 0-

' T

)

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U) 0 O

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U Year) 0 0

0 C

0 0

0 0

0 0

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- ~~N C1 N

N1 N1 N1 N1 NI N4 N4 N

Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2007 Indicator

--- Control 0.4 0.35 -

Sienificant Events Major Atm. Nuclear Weapon Tests TMI-l Critical June 1974 March 1972 June 1973 TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chernobyl April 1986 December 1978 October 1980 0.3 +

0.25 -

C..

0.2 CL Cn 8 0.15 C.,

10_

0.1 -

v0A 0.05 0 1111111111111111111111111 11111111 liii 111111111 I 111111111111111 I 111111111111111111111111111111111111111 11111111111111111 III I 11111 I c~4 C'.) *~J-In N-N-

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0 0

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0 oD 2

CD CD CD o2 CD CD CD CD CD CD CD o

D CD CD CD CD CD CD C C

C 0

0 0

0 0

0 0

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

$0.070 co 0.060 0

~j0.050 (D.

09

.* 0.040 0

003060 000 0.0 2 0 -

0.0 0 00

- - - - -I

- - - - - - -I

- - -I - - - - - -I -I - - -I

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- - - - -I - - - - - - - - -

N-r- -

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,-c

FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2007 Indicator Samples

--- Control Samples 10 Significant Events Maior Atm. Nuclear Weapon Tests TMI-2 Accident March 1979 December 1978 October 1980 TMI-2 RB Purge June 1980 Chernobyl April 1986 8

7 a) a--

.3 6

C-)o 4

.6:

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0)

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0Y)

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0)

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0Y)

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0) 0 0

0 0

0 0

0 0

Year

FIGURE C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2007 Indicator

--- Control 50 45 -

Sipnificant Events Major Atm. Nuclear Weapon Tests TMI-l Critical June 1974 March 1972 June 1973 TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chernobyl April 1986 December 1978 October 1980 40 -ý 35 -

-2 CU 0-af E

30 4 25 -I 20 -I 15 4 10+

5+

• \\

• .44

~.4~***~4.~4*

• /

0 I~T LO (D

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0 0

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Year

APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

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

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

D-1

Intentionally left blank D-2

TABLE D-1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q9-1Q 01/02/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07

- 01/30/07

- 02/27/07

- 04/03/07 05/01/07

- 05/29/07 07/03/07 07/31/07

- 08/28/07

- 10/02/07

- 10/30/07

- 11/27/07 12/31/07

• 1.8

• 0.9 1.0 +/- 0.5

• 1.8

• 0.9 2.1 2.5 2.4 1.6 2.6 4.0

< 1.7

_+

+

+

_+

_+

_+

1.0 1.0 1.0 0.3 1.0 0.6 MEAN 2.3 +/- 1.9 TABLE D-1.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/02/07

-01/30/07 01/30/07

<02/27/07 02/27/07

-04/03/07 04/03/07

-05/01/07 05/01/07

-05/29/07 05/29/07

-07/03/07 07/03/07

-07/31/07 07/31/07

-08/28/07 08/28/07

-10/02/07 10/02/07

<10/30/07 10/30/07

-11/27/07 11/27/07

<12/31/07 Q9-1Q

• 147

• 137

• 155

• 187

• 177

• 152

• 160

• 159

• 196

• 187

• 157

• 182

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

TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q9-1Q 01/02/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07 01/30/07 02/27/07 04/03/07 05/01/07 05/29/07 07/03/07 07/31/07 08/28/07 10/02/07 10/30/07 11/27/07 12/31/07

< 0.2

< 0.3

< 0.4

< 0.3

< 0.3

• 0.4

< 0.2

< 0.4

< 0.3

< 0.3

< 0.3

< 0.3 D-4

TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD Q9-1Q 01/02/07 - 01/30/07 01/30/07 -

02/27/07 02/27/07 - 04/03/07 04/03/07 -

05/01/07 05/01/07 - 05/29/07 05/29/07 - 07/03/07 07/03/07 - 07/31/07 07/31/07 - 08/28/07 08/28/07 -

10/02/07 10/02/07 -

10/30/07 10/30/07 -

11/27/07 11/27/07 -

12/31/07 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140

< 1.6

• 1.6

< 2.3

< 4.3

< 2.4

• 3.0

< 2.0

< 3.5

< 3.5

< 3.3

< 1.9

< 4.2

• 2.9

< 3.0

< 3.1

< 5.1

• 1.5

< 3.3

< 2.6

• 5.1

< 2.6

< 2.5

< 2.7

• 4.8

< 5.7

< 5.0

< 5.5

< 15

< 6.6

< 8.9

• 8.4

< 12

< 11

< 10

• 4.0

< 9.7

< 2.7

< 2.2

• 3.6

• 3.6

• 2.3

< 2.1

• 2.7

< 4.3

< 3.6

< 4.8

< 1.1

< 3.8

< 5.3

< 4.4

< 8.5

• 9.1

< 5.8

< 4.1

< 2.3

< 6.5

< 5.0

< 7.0

• 2.7

< 4.2

< 4.6

< 6.1

• 5.8

• 6.2

< 4.1

< 4.9

< 6.4

< 9.0

< 7.0

< 9.2

• 2.0

< 8.2

• 2.4

< 1.8

• 3.0

< 5.7

< 4.2

< 3.7

< 3.0

< 3.8

• 3.6

• 3.6

< 2.8

< 3.4

< 2.5

• 3.6

< 4.3

< 4.9

< 3.3

• 3.8

< 1.5

< 5.5

< 4.1

< 3.6

< 2.0

<6.1

< 3.7

• 2.3

< 4.1

< 6.2

< 3.2

< 3.4

< 3.7

< 4.5

< 2.5

< 4.1

< 2.3

< 4.3

< 14

< 17

< 17

< 15

< 13

<11

< 17

< 27

< 10

< 15

< 6.5

<15

• 1.9

• 2.2

< 4.8

< 3.3

• 2.6

< 5.5

< 3.1

< 5.9

< 6.1

< 8.4

< 1.2

< 5.9

TABLE D-1I.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDPQ 11/15/07

< 13

< 6 2400 +/- 338

<9

<4

< 32

< 12

< 20

< 9

< 9

TABLE D-1I1.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD J2-1Q 11/21/07 K-40 Cs-1 34 Cs-137 11212 +/- 771

< 32 113 +/- 30 D-7

TABLE D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD K-40 1-131 Cs-134 Cs-137 Sr-89 Sr-90 B1O-2Q 07/24/07 2101 +/- 343

< 29

< 12

< 14

<3

<2 D-8

TABLE D-V.i CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION E1-2Q PERIOD 01/03/07

-01/10/07 19 +/- 4.

01/10/07

-01/17/07 19 +/- 4 01/17/07

-01/24/07 22 +/- 4 01/24/07

-01/31/07 28 +/- 5 01/31/07

-02/07/07 27 +/- 5 02/07/07

-02/14/07 28 +/- 5 02/14/07

-02/21/07 21 +/- 4 02/21/07

-02/28/07 16 +/- 4 02/28/07

-03/07/07 21 +/- 4 03/07/07

-03/14/07 31 +/- 5 03/14/07 - 03/21/07 19 t 4 03/21/07 - 03/28/07 16 +/- 4 03/28/07

- 04/04/07 18 +/- 4 04/04/07

- 04/11/07 13 +/- 4 04/11/07 - 04/18/07 8 +/- 4 04/18/07

- 04/25/07 22 +/- 4 04/25/07 - 05/02/07 13 +/- 4 05/02/07

- 05/09/07 18 +/- 4 05/09/07

- 05/16/07 20 +/- 4 05/16/07

- 05/23/07 20 +/- 4 05/23/07

- 05/30/07 25 +/- 5 05/30/07

- 06/06/07 29 +/- 5 06/06/07

- 06/13/07 22 +/- 4 06/13/07

- 06/20/07 22 +/- 4 06/20/07

- 06/27/07 27 +/- 5 06/27/07

- 07/04/07 19 +/- 4 07/04/07

- 07/11/07 35 +/- 5 07/11/07

- 07/18/07 28 +/- 5 07/1 8/07 - 07/25/07 19 +/- 4 07/25/07 - 06/01/07 24 +/- 5 08101/07 - 08/08/07 51 +/- 5 08/08/07 - 08/15/07 23 +/- 5 08/15/07 - 06/22/07 26 +/- 5 08/22/07 - 08/29/07 20 +/- 4 08/29/07 - 09/05/07 33 +/- 5 09/05/07

- 09/12/07 34 +/- 4 09/12/07

- 09/19/07 19 +/- 5 09/19/07 09/26/07 35 +/- 5 09/26/07

-10/03/07 28 +/- 5 10/03/07

-10/10/07 21 +/- 4 10/10/07

-10/17/07 21 +/- 4 10/17/07

-10/24/07 32 +/- 4 10/24/07

-10/31/07 19 +/- 4 10/31/07

-11/07/07 25 +/- 5 11/07/07

-11/14/07 23 +/- 5 11/14/07

-11/20/07 18 +/- 5 11/20/07

-11/28/07 27 +/- 4 11/28/07

-12/04/07 28 +/- 5 12/04/07

-12/12/07 38 +/- 5 12/12/07

-12/19/07 20 +/- 5 12/19/07

-12/26/07 29 +/- 5 12/26/07

-01/01/08 32 +/- 6 MEAN 24 +/- 15 D-9

TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD E1-2Q 01/03/07 - 03/28/07 03/28/07

- 06/28/07 06/28/07 - 10/03/07 10/03/07

- 01/01/08 MEAN Be-7 Cs-134 Cs-137 66 107 92 64

+ 12

+/- 20

+ 16

+19

• 0.6

< 0.8

• 0.7

< 0.3

< 0.7

< 0.4

< 0.5

• 0.5 82 +/- 42

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

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

STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD G2-1Q 01/10/07 02/07/07 03/07/07 03/21/07 04/04/07 04/18/07 05/02/07 05/16/07 05/30/07 06/13/07 06/27/07 07/11/07 07/25/07 08/08/07 08/22/07 09/05/07 09/19/07 10/03/07 10/17/07 10/31/07 11/14/07 11/28/07 12/12/07 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90

• 0.4

< 0.4

• 0.3

• 0.5

< 0.3

< 0.4

< 0.4

< 0.4

< 0.3

• 0.4

< 0.3

< 0.3

< 0.2

• 0.3

< 0.3

< 0.4

• 0.3

< 0.3

• 0.4

< 0.3

• 0.3

• 0.3

• 0.2 991 +/- 103 1415 +/- 93 1311 +/- 109 1283 +/- 104 862 +/- 147 1404 +/- 114 1294 +/- 116 1188 +/- 109 1189 +/- 119 1386 +/- 204 1086 +/- 116 1295 +/- 127 1339 +/- 126 1385 +/- 195 1370 +/- 127 1396 +/- 181 1361 +/- 165 1234 +/- 112 1401 +/- 110 1294 +/- 120 1328 +/- 116 1157 +/- 99 1282 +/- 115

< 3.5

• 2.8

< 2.9

< 3.0

• 7.2

< 3.0

• 5.6

< 4.3

• 4.6

< 5.1

• 6.1

< 4.7

< 2.4

< 8.0

< 3.9

• 4.2

< 3.6

< 3.4

< 3.6

• 5.2

< 2.9

• 2.4

< 2.4

• 3.0

• 2.0

< 2.7

< 2.8

< 8.0

< 3.7

< 4.4

< 3.9

< 3.5

• 4.8

• 6.2

< 3.8

< 4.3

• 7.1

< 2.9

< 3.7

• 5.6

< 3.5

• 1.9

< 4.6

• 2.6

< 3.4

< 2.7

<18

< 16

<13

<10

• 34

• 17

< 17

• 16

< 12

< 33

• 17

< 19

<19

<15

< 11

< 35

• 26

< 21

< 13

< 15

< 12

< 19

< 24

• 4.0

• 3.0

• 1.2

< 2.3

< 4.8

< 2.4

< 3.0

< 2.8

< 3.8

< 7.4

• 2.3

• 4.0

< 2.9

< 6.8

< 1.9

< 8.4

< 6.6

< 2.0

• 2.5

• 6.3

< 4.0

• 3.1

< 3.9

< 1.7

< 0.8

< 0.8

< 0.9

< 0.7 1.0 +/- 0.5

• 0.8 0.7 +/- 0.3 MEAN 1272 +/- 281 0.9 +/- 0.4

• THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-11

Intentionally left blank

FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2007 4.QC-LAB 4

H-0-%

M A

0-

'&f 5

A E--

3 a) 2 0

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, 2007 50

,QC-LAB 40

-- PRIMARY-LAB E 30 m

I

°-0 ji l

C.).

0w.

1 4

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

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE I OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2007 E5255-396 Milk E5256-396 Milk E5258-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 125 pCi/L 10.8 pCi/L pCi/L.

pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 107 269 244 98.1 227 92.5 182.0 108.0 985 143 252 204 74.9 190.0 79.7 156 99.1 894 122 137 10 85.2 297 245 112 234 98.8 182 106 1000 152 245 202 92.3 197.0 81.6 151 87.2 826 126 71.3 E5257-396 Charcoal 1-131 pCi 34.7 0.91 1.08 1.26 0.91 1.00 0.88 0.97 0.94 1.00 1.02 0.99 0.94 1.03 1.01 0.81 0.96 0.98 1.03 1.14 1.08 0.97 0.49 1.03 1.25 1.01 0.88 0.90 0.81 0.93 0.91 0.98 0.95 0.95 0.89 0.83 0.87 0.80 0.89 0.88 0.99 1.03 1.02 0.89 1.00 A

A W

A A

A A

A A

A A

A A

A A

A A

A A

A A

N (1)

June 2007 E5384-396 Milk E5385-396 Milk E5387-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 98.3 95.2 pCi/L 16.1 12.9 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 71.0 176 459 197 158 180 163 158 318 212 87.5 232 101 78.9 91.8 85.6 89.8 178 ill 70.1 200 512 242 169 198 166 167 334 238 105 268 127 88.5 104.0 87 87.3 175 125 A

W A

A A

A A

A A

A A

A A

A A

A A

A A

A A

E5386-396 Charcoal 1-131 pCi 79.3 79.1 A

E-I

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

September 2007 E5492-396 Milk E5493-396 Milk E5495-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-1 41 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 99.0 94.9 pCi/L 13.9 13.1 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 81.9 200 271 131 131 114 171 117 212 143 128 181 85.9 83.2 69.4 112 79.6 159 92.0 85.2 211 289 147 131 114 168 111 202 148 136 186 94.7 83.9 73.3 108 71.1 130 95.2 E5494-396 Charcoal 1-131 pCi 70.8 69.5 pCi/L 87.6 93.7 pCi/L 15.5 15.2 1.04 1.06 0.96 0.95 0.94 0.89 1.00 1.00 1.02 1.05 1.05 0.97 0.94 0.97 0.91 0.99 0.95 1.04 1.12 1.22 0.97 1.02 0.93 1.02 1.00 0.97 0.97 0.85 1.00 0.91 1.00 1.01 0.99 0.94 0.95 1.04 0.93 1.01 0.98 1.07 1.21 1.11 0.97 A

A A

A A

A A

A A

A A

A A

A A

A A

A A

W A

A A

A A

A A

A A

A A

A A

A A

A A

A A

A W

A A

December 2007 E5749-396 Milk E5750-396 Milk E5752-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 60.6 137 497 117 166 159 190 149 231 198 88.6 352 84.6 ill 114 135 119 172 137 60.8 141 512 137 166 174 190 148 234 211 93.4 340 91.2 110.0 116.0 126 98.5 155 141 E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December2007 E5751-396 Charcoal 1-131 pCi 65.8 74.1 0.89 A

(1) New technician counted charcoal cartridge on the back rather than the face, resulting in low activity. If the charcoal cartridge had been counted on the face, the ratio would have been approximately 1.07, which is acceptable. NCR 07-02 (a) Teledyne Brown Engineering reported result.

(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

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

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

W-Acceptable with waming. 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, 2007 (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a)

Value (b)

Control Limits Evaluation (c)

July 2007 Rad 70 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 58.6 18.7 18.6 57.6 55.4 31.3 49.0 26.8 12 31.1 1700 58.2 19.0 19.4 68.9 61.3 33.5 54.6 27.1 11.5 26.5 1770 27.4 18.2 12.6 71.1 180 23.2 251 58.6 9.73 28.9 9700 49.5 -66.9 10.3 -27.7 10.7 -28.1 60.2 - 77.6 52.6 - 70.0 24.8 -42.2 45.2 - 64.0 15.4-38.8 2.84 - 20.2 21.3-31.7 1180-2360 19.3-33.9 12.9-21.6 8.64-15.5 58.0 - 78.2 162-200 19.9-28.3 226 - 294 30.6 - 72.9 4.26-18.2 24.0 - 33.8 8430- 10700 A

A A

N (1)

A A

A A

A A

A October 2007 RAD 71 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 27.07 17.40 12.57 63.33 168 21.93 245.33 55.60 15.23 27.43 9263.3 A

A A

A A

A A

A A

A A

(1) The Cs-134 TBE found/ERA known ratio is 83.6%, which TBE considers acceptable. NCR 07-07 (a) Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

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

E-4

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

TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 1)

Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a)

Value (b)

Range Evaluation (c)

February 2007 07-MaW1 7 Water Cs-1 34 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 74.5 162 140 27.9 346 125 8.90 117 83.5 163.0 143.7 26.9 283.0 123.8 8.87 114.8 07-GrW17 Water Gr-A Gr-B Bq/L 0.502 0.327 Bq/L 0.975 0.851 07-MaS17 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 322

.893 508.3 300.3 779 682 293 618.7 3.230 2.453 3.067 2.767 3.557 0.584 2.463 327.4 799.7 471.2 274.7 685.2 602 319.0 536.8 1.4960 2.5693 2.8876 2.9054 3.5185 0.6074 2.6828 58.5 - 108.6 114-1 -211.9 100.6-186.8 18.8-35.0 198.1 - 367.9 86.7-160.9 6.21-11.53 80.4 - 149.2

>0.0 - 0.654 0.426 - 1.277 229.2 - 425.6 559.8 - 1039.6 329.8 - 612.6 192.3 - 357.1 479.6 - 890.8 421 - 783 223.3 - 414.7 375.8 - 697.8 2.9372 - 5.4548 1.7985 - 3.3401 2.0213 - 3.7539 2.0338 - 3.7770 2.4630 - 4.5741 0.4252 7 0.7896 1.8780 - 3.4876 A

A A

A W

A A

A A

A A

A A

A A

A A

A W

A A

A A

A A

A A

A A

A A

A A

W 07-RdF17 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 07-GrF17 AP Gr-A Gr-B 07-RdV17 Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample 0.353 0.601

>0.0 - 1.202 Bq/sample 0.500 0.441 0.221 - 0.662 February 2007 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 6.207 7.80 8.64 6.10 9.41 63.5 1.51 7.15 6.2101 6.9949 8.1878 5.8215 8.4492 4.3471 -8.0731 4.8964 - 9.0934 5.7315 - 10.6441 4.0751 - 7.5680 5.9144 - 10.9840 Not evaluated by MAPEP 1.5351 1.0746-1.9956 5.6991 3.9894 - 7.4088 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

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

E-5

TABLE E-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007 (Page 1 of 2)

Concentration (pCi/L)

Lab Code

• Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STAP-1116 03/19/07 Gr. Alpha 34.64 +/- 2.56 STAP-1116 03/19/07 Gr. Beta 93.41 +/- 3.20 STAP-1 117 STAP-1 117 STAP-117 e STAP-1117' STAP-1 117 STAP-1 117 STSO-1 118 STSO-1118 STSO-1118 STSO-1118 STSO-1118 STSO-1118 STSO-1118' STSO-1 118 STSO-1118 STSO-1118 STSO-1118 STSO-1118' STVE-1119 STVE-1119 STVE-1119 STVE-1119 STVE-1119' STVE-1 119 STVE-1119 STW-1 120 STW-1120 STW-1120 STW-1 120' STW-1 120 STW-1 120 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 Ac-228 Bi-212 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Pb-212 Pb-214 Sr-90 Th-234 Zn-65 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 1610.00 +/- 8.40 1340.40 +/- 48.84 345.30 +/- 8.20

<5.0 156.10 +/- 6.60 363.80 +/- 11.90 3097.77 +/- 94.96 2467.87 +/- 114.33 7847.40 +/- 86.60 7910.60 +/- 356.88 4635.00 +/- 99.10 12201.60 +/- 423.20

< 34.0 2046.80 +/- 127.20 4142.80 +/- 110.40 6163.30 +/- 791.60 4329.40 +/- 569.10 0.00 +/- 0.00 2827.90 +/- 62.40 654.80 +/- 48.40 3307.30 +/- 58.80 40814.20 +/- 618.80

< 27.6 8999.70 +/- 580.90 474.30 +/- 45.70 541.40 +/- 9.00 1623.80 +/- 66.10 1839.10 +/- 17.90

<8.1 949.40 +/- 16.70 2009.00 +/- 36.40 25.8 79.5 1300.0 1120.0 255.0 0.0 156.0 245.0 2790.0 2500.0 7330.0 7560.0 4300.0 11100.0 0.0 1730.0 3330.0 7500.0 3590.0 0.0 2600.0 579.0 2920.0 37900.0 0.0 8890.0 366.0 536.0 1750.0 1850.0 0.0 989.0 1910.0 12.4 - 39 48.8-116 Pass Pass 1010.0 - 1620 732.0 -1380 192.0 -336 66.6 - 246 208.0 -412 1790.0 -3930 658.0 -3730 5340.0 -9820 4850.0 -9070 3290.0 -5580 8050.0 -15000 1120.0 -2430 1980.0 -4980 2610.0 - 12400 2190.0 -4560 0.0 -0 1760.0 -3720 308.0 -822 2150.0 -4060 27200.0 -53600 4900.0 -11800 267.0 -500 467.0 -631 1290.0 -2020 1570.0 -2220 630.0 -1320 1600.0 -2410 Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1121 04/09/07 Sr-89 STW-1121 04/09/07 Sr-90 30.7 +/- 4.3 39.3 +/- 1.8 35.4 42.1 26.7 -44.1 33.4 - 50.8 E-6

TABLE E-4 ERAIa) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007 (Page 2 of 2)

Concentration (pCi/L)

Lab Code

• Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1122 STW-1122 STW-1122 STW-1122 STW-1122 STW-1 123 STW-1 123 STW-1 124 STW-1 125 STW-i 127 STW-i 127 STW-1 128 STW-1 128 STW-1 128 STW-1 128 STW-1128 STW-1129 STW-1129 STW-1131 STW-1131 STW-1132 STW-1132 STW-1132 STW-1132 STW-1132 STW-1133 STW-1133 STW-1134 STW-1135 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 07109/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 Ba-133 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 30.0 +/- 2.4 118.5 +/-3.9 52.6 +/- 2.3 49.5 +/- 3.8 91.7 +/- 6.3 33.8 +/- 3.5 24.2 +/- 2.3 19.2 +/- 1.2 7540.0 +/- 255.0 51.7 21.4 19.4 32.8 67.0 61.6 55.6 19.2 9.1 27.3 17.7 12.2 23.8 70.5 178.2 263.9 54.7 11.9 33.0 9965.0

+/-5.0

+/-2.3

+/-2.2

+/-2.0

+/-2.9

+/- 3.8

+/-7.5

+/- 1.6

+/- 0.9

+/- 3.3

+/- 1.2

+/- 3.3

+/- 1.4

+/-4.2

+/- 3.3

+/- 6.9

+/- 2.1

+/- 0.9

+/- 1.5

+/- 250.0 29.3 119.0 54.3 50.3 88.6 56.5 25.3 18.9 8060.0 58.2 19.0 19.4 33.5 68.9 61.3 54.6 27.1 11.5 27.4 18.2 12.6 23.2 71.1 180.0 251.0 58.6 9.7 28.9 9700.0 20.6 -38.0 109.0 - 129.0 45.6 - 63.0 41.6 -59.0 73.3 - 104.0 32.0 - 81.0 16.6 - 34.0 13.7 -24.1 6660.0 - 9450.0 49.5 -66.9 10.3 -27.7 10.7 -28.1 24.8 - 42.2 60.2 - 77.6 52.6 - 70.0 45.2 - 64.0 15.4 -38.8 2.8 -20.2 19.3 - 33.9 12.9 -21.6 8.6 -15.5 19.9 -28.3 58.0 - 78.2 162.0 -200.0 226.0 - 294.0 30.6 - 72.9 4.3 - 18.2 24.0 - 33.8 8430.0 - 10700.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

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

a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

A high bias (- 20%) was observed in gamma results for air filters. A composite filter geometry was used in the calculations vs. a single filter geometry. Result of recalculation. Cs-137, 305.8 +/- 6.0 pCi/filter.

f Included in the testing series as a "false positive". No activity expected.

E_-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2007 (Page 1 of 1)

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1110 STW-1110 STW-1111 STW-1111 STW-1111 STW-1111 STW-1111 STW-1 111 STW-1 111 STSO-1 112 STSO-1 112 STSO-1112 STSO-1 112 STSO-1112 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Gr. Alpha Gr. Beta Co-57 Cs-1 34 Cs-1 37 H-3 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-1 34 Cs-137 Mn-54 0.45 +/- 0.08 0.90 +/- 0.14 151.60 +/- 10.00 79.20 +/- 8.00 168.70 +/- 12.10 262.20 +/- 9.10 130.60 +/- 11.50 9.60 +/- 1.40 123.70 +/- 17.00 501.20 +/- 2.90 285.90 +/- 2.10 325.90 +/- 7.40 855.70 +/- 4.60 750.90 +/- 4.70 0.27 +/- 0.04 0.57 +/- 0.05 3.51 +/- 0.07 2.98 +/- 0.10 4.02 +/- 0.16 2.75 +/- 0.12 3.94 +/- 0.12 0.58 +/- 0.18 2.70 +/- 0.10 8.90 +/- 0.20 6.50 +/- 0.20 6.90 +/- 0.30 8.20 +/- 0.30 10.10 +/- 0.30 0.33 0.85 143.70 83.50 163.00 283.00 123.80 8.87 114.80 471.20 274.70 327.40 799.70 685.20 0.60 0.44 2.89 2.91 4.20 2.57 3.52 0.61 2.68 8.19 5.82 6.21 6.99 8.46 0.00 -0.65 0.43 -1.28 100.60 -186.80 58.50 - 108.60 114.10 -211.90 198.10 - 367.90 86.70 - 160.90 6.21 -11.53 80.40 -149.20 329.80 -612.60 192.30 -357.10 229.20 -425.60 559.80 -1039.60 479.60 -890.80 0.00 -1.20 0.22 -0.66 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1113 01/01/07 Gr. Alpha STAP-1113 01/01/07 Gr. Beta STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STVE-1 115 STVE-1 115 STVE-1115 STVE-1115 STVE-1115 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 2.02 2.03 2.94 1.80 2.46 0.43 1.88 5.73 4.08 4.35 4.90 5.91

-3.75

-3.78

-5.45

-3.34

-4.57

-0.79

-3.49

-10.64

-7.57

-8.07

-9.09

-10.98 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-8

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 2007 Prepared By Teledyne Brown Engineering Environmental Services An

ýp'A' Exelon Company Three Mile Island Nuclear Station Middletown, PA 17057 April 2008

Table Of Contents I. Sum m ary and Conclusions..........................................................................................

1 II. In tro d u c tio n........................................................................................................................

3 A. O bjectives of the RG PP...................................................................................

3 B. Im plem entation of the O bjectives....................................................................

4 C. Program Description........................................................................................

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

5 I1. Program Description.....................................................................................................

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

6 B. Data Interpretation.............................................................................................

6 IV. Results and Discussion...............................................................................................

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

7 D. Leaks, Spills, and Releases............................................................................

8 G. Actions Taken..................................................................................................

9

Appendices Appendix A Tables Table A-1:

Location Designation Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2007 Figures Figure A-i:

Appendix B Tables Table B-I.1 Table B-1.2 Table B-I.3 Table B-I.4 Table B-1.5 Table B-1.6 Table B-1.7 Sampling Locations Near the Site Boundary of the Three Mile Island Nuclear Station, 2007 Data Tables Concentrations of Tritium and Strontium in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2007.

Concentrations of Tritium and Strontium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2007.

Concentrations of Tritium in Well Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2007.

Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Well Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

Concentrations of Gamma Emitters in Well Water Split Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2007.

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 2007. During that time period, 570 analyses were performed on 498 samples from 68 locations.

In assessing all the data gathered for this report, it was concluded that the operation of Three Mile Island Nuclear Station had no adverse radiological impact on the environment, and there were no known active releases at the end of 2007 into the groundwater at Three Mile Island Nuclear Station.

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

Strontium-89/90 was not detected at a concentration greater than the LLD of 2.0 picoCuries per liter (pCi/L) in the groundwater sample tested.

Tritium was detected in 15 groundwater samples at 3 locations 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. The elevated groundwater samples were a result of a leak in a condensate deice line. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 47 of 68 groundwater monitoring locations. The tritium concentrations ranged from 206 +/- 130 pCi/L to 29,600 + 3,430 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of the condensate deice line leak, 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/nuclear/Tritium.htm As a result of the Phase 1 study, the Radiological Groundwater Protection Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) on well water and surface water samples collected in 2007. 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 2007.

A.

Objective of the RGPP The long-term objectives of the RGPP are as follows:

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B.

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

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

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

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

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

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

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

C.

Program Description

1.

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

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

Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables as data are received.

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

D.

Characteristics of Tritium (H-3)

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

Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. This "cosmogenic" tritium combines with oxygen to form tritiated water, which will then enter the hydrologic cycle.

Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

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

The chemical properties of tritium are essentially those of ordinary hydrogen. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, all tritium is essentially cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

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

Ill.

Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE and EIML to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2007.

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.

Samples from 68 locations were analyzed for tritium activity (Table B-I.1 - B-1.3 Appendix B). Tritium values ranged from the detection limit to 29,600 pCi/I. Two of the locations were offsite drinking water wells with no detectable concentration of tritium.

Strontium-90 was not detected above the required detection limit of 2.0 pCi/liter. (Table B-1.1 - B-1.4, Appendix B).

Gamma Emitters and Strontium Potassium-40 was detected in 4 of 71 samples. The concentrations ranged from 96 pCi/liter to 151 pCi/liter. No other gamma emitting nuclides were detected. (Table B-1.5 - B-1.7, Appendix B).

B.

Leaks, Spills, and Releases As mentioned above, a leak was discovered in a condensate storage tank underground pipe flange connection in April 2007. The source of the water was TMI secondary plant water and the concentration of tritium in the source tank was 4.5E-5 uCi/ml. An investigation was performed under TMI's Corrective Action Program issue reports-618944, 618443 and 618929. Elevated groundwater results were being investigated at that time under separate issue reports (IR 609783, 616995, 630556) when the leak was discovered. A 30 day voluntary report was made to the NRC in May 2007. The leaking flange was a result of settling of the backfill from the 2006 pipe leak repair. The entire deice line was subsequently excavated and replaced during 2007.

On July 2, 2007, approximately 200 gallons of filtered water containing 1.15E-6 uCi/ml of tritium spilled on the ground from a hose rupture on an Ecolochem water treatment trailer. The leak was isolated immediately and the hose was repaired. Issue report 646650 documents this event and the review of similar hoses for extent of condition.

Six different issue reports document leakage from the industrial coolers onto the intermediate building roof which drains to the yard drains. See IRs 620466, 628416, 650810, 652199, 652211 and 686881. The makeup water for these coolers contains low level concentrations of tritium ranging from 1.18E-6 to 3.01 E-6 uCi/ml. The estimated volumes ranged from 129 to 2000 gallons for these spills/leaks in 2007.

Two issue reports also document the industrial cooler blowdown tank overflowing on 12/7/07 and 12/8/07 into the yard area. A check valve connected to a secondary sump was leaking by allowing secondary plant water to backflow into this system. Also contributing to this event was the fact that local drains in the building were clogged and water overflowed through a doorway to a grated fan intake area. The investigation, isolation and redirecting of leakage are all described in the correction actions to issue reports 709071 and 709169.

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. TMI continues to report this offsite effluent release in its Annual Radiological Effluent Release Report (ARERR). A total dose of <0.08 mrem was calculated for 2007.

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 complete and mitigation work for two environmentally important lines are at the 90% point for engineering, planning, and preparation. Buried anodes were purchased in 2007 and are available for installation for any pipe that is excavated for other reasons. Funding is in place for 2008 to perform the engineering work associated with installation of cathodic protection systems for the key high risk systems at TMI.

2. Installation of Monitoring Wells TMI installed 31 new monitoring wells in 2006. TMI 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

TABLE A-I:

Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2007 Site Site Type

1. 3 Monitoring Well 48S Production Potable Well E1-2 Monitoring Well, Offsite GP-12 Monitoring Well GP-6 Monitoring Well GP-8 Monitoring Well GP-9 Monitoring Well MS-1 Monitoring Well, MS-19 Monitoring Well MS-2 Monitoring Well MS-20 Monitoring Well MS-21 Monitoring Well MS-22 Monitoring Well MS-3 Monitoring Well MS-4 Monitoring Well MS-5 Monitoring Well MS-6 Monitoring Well MS-7 Monitoring Well MS-8 Monitoring Well MW-1 Monitoring Well MW-2 Monitoring Well MW-3 Monitoring Well MW-4 Monitoring Well N2-1 Monitoring Well, Offsite NW-A Production Well NW-B Production Well NW-C Production Well NW-CW Clearwell OS-13B Monitoring Well OS-14 Monitoring Well OS-16 Monitoring Well OS-17 Monitoring Well OS-18 Monitoring Well OSF Production Well RW-1 Monitoring Well RW-2 Monitoring Well SW-E-1 Surface Water SW-E-2 Surface Water SW-E-3 Surface Water MW-TMl-9S*

Monitoring Well MW-TMI-10D Monitoring Well MW-TMI-101 Monitoring Well

-MW-TMI-10S Monitoring Well MW-TMI-11S 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-TM 1-14S Monitoring Well MW-TMI-16D Monitoring Well MW-TMI-161 Monitoring Well

• NO WATER PRESENT TO SAMPLE A-1

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2007 Site Site Type MW-TMI-17D MW-TMI-171 MW-TMI-18D MW-TMI-19D MW-TMI-191 MW-TMI-1D MW-TMI-2D MW-TMI-31 MW-TMI-41 MW-TMI-4S MW-TMI-5D MW-TMI-6D MW-TMI-61 MW-TMI-7S MW-TMI-8S MW-TMI-91 TRAINING CENTER Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well A-2

Intentionally left blank

APPENDIX B DATA 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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE

1. 3 48N 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S 48S El-2 El-2 GP-12 GP-12 GP-6 GP-6 GP-8 GP-8 GP-9 GP-9 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 COLLECTION DATE 10/15/07 10/15/07 03/19/07 ORIGINAL 04/17/07 DUPLICATE 04/17/07 ORIGINAL 04/24/07 DUPLICATE 04/24/07 04/30/07 05/07/07 05/14/07 05/18/07 05/21/07 05/25/07 05/29/07 06/07/07 06/12/07 06/19/07 07/05/07 07/12/07 07/19/07 07/26/07 08/02/07 08/14/07 ORIGINAL 10/16/07 DUPLICATE 10/16/07 05/09/07 10/16/07 03/20/07 05/09/07 03/20/07 05/08/07 03/20/07 05/08/07 03/20/07 05/08/07 ORIGINAL 03/30/07 DUPLICATE 03/30/07 ORIGINAL 04/13/07 DUPLICATE 04/13/07 ORIGINAL 04/17/07 DUPLICATE 04/17/07 04/20/07 04/24/07 04/30/07 05/07/07 05/14/07 05/18/07 05/21/07 05/25/07 H-3 SR-90 636 + 143

< 187

< 190

< 181

< 188

< 175

< 173

< 196 173 106

< 163

< 168

< 168 146 +/- 95

< 161

< 175 180 +/- 113

< 150 189 +/- 108

< 165

< 162

< 155

< 157 258 + 102

< 188

< 188

< 194

< 188

< 200

< 192 311 + 134

< 192 473 + 144

< 188 206 +/-

265 +/-

2880 +/-

2830 +/-

6590 +/-

6520 +/-

5840 +/-

5930 +/-

4500 +/-

5030 +/-

4170 +/-

6160 +/-

5630 +/-

4600 +/-

5180 +/-

5420 +/-

130 133 364 357 723 715 647 657 502 558 221 661 615 511 556 591 B-I

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MS-1 05/29/07 5600 +/- 608 MS-1 ORIGINAL 06/07/07 4130 +/- 261 MS-1 DUPLICATE 06/07/07 4250 +/- 267 MS-1 06/12/07 3060 +/- 211 MS-1 06/19/07 1800 +/- 228 MS-1 ORIGINAL 06/29/07 1220 +/- 180 MS-1 DUPLICATE 06/29/07 1410 +/- 197 MS-I 07/05/07 1160 +/- 178 MS-1 07/12/07 670 +/- 132 MS-1 ORIGINAL 07/19/07 733 +/- 139 MS-1 DUPLICATE 07/19/07 684 +/- 135 MS-1 07/26/07 579 +/- 126 MS-1 ORIGINAL 08/02/07 646 +/- 131 MS-1 DUPLICATE 08/02/07 699 +/- 135 MS-1 08/09/07 427 +/- 129 MS-1 08/14/07 446 +/- 121 MS-1 08/23/07 571 +/- 125 MS-1 08/30/07 476 +/- 126 MS-1 09/05/07 382 + 123 MS-1 ORIGINAL 09/11/07 602 +/- 134 MS-1 DUPLICATE 09/11/07 591 +/- 132 MS-1 09/17/07 452 +/- 128 MS-1 10/16/07 444 +/- 134 MS-19 03/29/07 372 +/- 142 MS-19 03/29/07

< 0.9 MS-19 04/24/07 333 +/- 122 MS-19 04/30/07 523 +/- 135 MS-19 05/07/07 542 +/- 125 MS-19 05/14/07 653 +/- 134 MS-19 09/25/07 629 +/- 145 MS-19 10/01/07 636 +/- 153 MS-19 ORIGINAL 10/10/07 584 +/- 142

.MS-19 DUPLICATE 10/10/07 642 +/- 148 MS-2 05/08/07 270 +/- 115 MS-2 10/11/07 215 +/- 120 MS-20 03/28/07 463 +/- 145 MS-20 04/09/07 295 +/- 114 MS-20 04/17/07

< 187 MS-20 05108107 193 +/- 120 MS-20 08/09/07 250 +/- 120 MS-20 08/30/07 354 +/- 120 MS-20 09/05/07 590 +/- 137 MS-20 10/15/07 385 +/- 125 MS-20 11/28/07 910 +/- 141 MS-20 12/04/07 265 +/- 132 MS-20 12/20/07 657 +/- 134 MS-21 04/02/07 451 +/- 124 MS-21 04/17/07 227 +/- 127 MS-21 05/08/07 408 +/- 127 B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MS-21 05/29/07 547 +/- 128 MS-21 06/07/07 594 +/- 123 MS-21 ORIGINAL 10/15/07 2400 +/- 276 MS-21 RERUN 10/15/07 2310 +/- 302 MS-21 11/28/07 1420 +/- 153 MS-21 12/04/07 598 +/- 152 MS-21 12/20/07 779 +/- 137 MS-22 03/20/07 897 +/- 177 MS-22 05/09/07 754 +/- 142 MS-22 06/12/07 743 +/- 129 MS-22 08/30/07 926 +/- 156 MS-22 10/16/07 911 +/- 170 MS-3 05/08/07 172 +/- 109 MS-3 10/15/07 241 +/- 125 MS-4 05/09/07 398 +/- 124 MS-4 10/09/07 278 +/- 130 MS-5 ORIGINAL 05/08/07 336 +/- 125 MS-5 DUPLICATE 05/08/07 181 +/- 110 MS-5 10/11/07 199 +/- 117 MS-6 10/11/07

< 187 MS-7 05/10/07 278 +/- 124 MS-7 10/11/07

< 183 MS-8 05/08/07 297 +/- 124 MS-8 10/11/07 265 +/- 127 MS-8 ORIGINAL 10/11/07 260 +/- 118 MS-8 DUPLICATE 10/11/07 192 +/- 123 MW-i 05/10/07

< 185 MW-i 10/10/07

< 193 MW-2 04/02/07

< 159 MW-2 05/10/07

< 187 MW-2 ORIGINAL 05/29/07

< 159 MW-2 DUPLICATE 05/29/07

< 159 MW-2.

06/07/07

< 174 MW-2 ORIGINAL 06/19/07

< 152 MW-2 DUPLICATE 06/19/07

< 151 MW-2 08/09/07

< 173 MW-2 08/14/07

< 161 MW-2 ORIGINAL 08/23/07

< 153 MW-2 DUPLICATE 08/23/07 176 +/- 104 MW-2 08/30/07

< 167 MW-2 09/05/07

< 175 MW-2 09/11/07

< 167 MW-2 09/17/07

< 178 MW-2 09/25/07

< 182 MW-2 10/01/07

< 189 MW-2 10/10/07

< 187 MW-3 05/10/07

< 185 MW-3 10/10/07

< 195 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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-4 MW-4 MW-TM I-1 0D MW-TMI-10D MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-1 01 MW-TMI-10S MW-TMI-1 OS MW-TMI-1 OS MW-TMI-10S MW-TMI-1 OS MW-TMI-11S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TM I-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S COLLECTION DATE 05/10/07 10/10/07 05/10/07 10/15/07 ORIGINAL 03/21/07 DUPLICATE 03/21/07 04/13/07 05/10/07 08/14/07 10/16/07 03/21/07 ORIGINAL 05/09/07 DUPLICATE 05/09/07 08/14/07 10/15/07 03/28/07 03/21/07 03/28/07 03/30/07 04/02/07 04/05/07 04/09/07 04/13/07 04/17/07 04/20/07 04/24/07 04/30/07 ORIGINAL 05/07/07 DUPLICATE 05/07/07 05/18/07 05/21/07 05/25/07 05/29/07 06/07/07 06/12/07 06/20/07 06/29/07 07/05/07 07/12/07 07/19/07 07/26/07 08/02/07 08/09/07 ORIGINAL 08/16/07 DUPLICATE 08/16/07 08/23/07 08/30/07 09/05/07 H-3 SR-90

• 188

• 196 343 +/- 134 371 +/- 130 5010 +/- 570 4700 +/- 539 5130 +/- 577 5930 +/- 638 3740 +/- 420 3750 +/- 249 1800 +/- 260 5690 +/- 611 5010 +/- 550 7000 +/- 739 6040 +/- 671 821 +/- 174 22600 +/- 2310 8630 +/- 934 6340 +/- 701 5850 +/- 629 6490 +/- 704 5670 +/- 621 5390 +/- 596 8260 +/- 889 6230 +/- 673 1840 +/- 246 1330 +/- 157 1210 +/- 180 1200 +/- 180 2970 +/- 354 4290 +/- 483 7350 +/- 778 12100 +/- 1250 21800 +/- 1140 22000 +/- 1150 23700 +/- 2400 28100 +/- 2830 26100 +/- 2640 21600 +/- 2180 16500 +/- 1690 10800 +/- 1120 7560 +/- 801 4610 +/- 515 3120 +/- 364 3090 +/- 351 2680 +/- 315 2440 +/- 300 2060 +/- 268 B-4

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-TMI-12S 09/11/07 1470 +/- 211 MW-TMI-12S 09/17/07 1230 +/- 192 MW-TMI-12S 11/28/07 239 +/- 123 MW-TMI-12S 12/04/07

< 187 MW-TMI-12S 12/20/07 285 +/- 121 MW-TMI-131 03/30/07 3260 +/- 396 MW-TMI-131 ORIGINAL 04/02/07 3420 +/- 404 MW-TMI-131 DUPLICATE 04/02/07 3220 +/- 384 MW-TMI-131 04/13/07 4140 +/- 477 MW-TMI-1 31 04/20/07 4300 +/- 481 MW-TMI-131 05/09/07 5670 +/- 525 MW-TMI-131 08/09/07 8870 +/- 938 MW-TMI-1 31 08/30/07 9610 +/- 1010 MW-TMI-131 09/05/07 9440 +/- 1000 MW-TMI-131 09/11/07 9240 +/- 976 MW-TMI-131 09/17/07 9510 +/- 1010 MW-TMI-131 09/25/07 9440 +/- 1000 MW-TMI-131 ORIGINAL 10/01/07 9200 +/- 983 MW-TMI-131 DUPLICATE 10/01/07 9930 +/- 1060 MW-TMI-131 10/10/07 9030 +/- 961 MW-TMI-131 11/08/07 3710 +/- 441 MW-TMI-131 11/28/07 8160 +/- 373 MW-TMI-131 ORIGINAL 12/04/07 8110 +/- 885 MW-TMI-131 DUPLICATE 12/04/07 8010 +/- 872 MW-TMI-131 12/20/07 6460 +/- 705 MW-TMI-13S ORIGINAL 03/29/07 424 +/- 147 MW-TMI-13S DUPLICATE 03/29/07 355 +/- 137 MW-TMI-13S 04/20/07 253 +/- 112 MW-TMI-13S 05/09/07

< 187 MW-TMI-13S 08/14/07 12400 +/- 1280 MW-TMI-13S 08/23107 11700 +/- 1210 MW-TMI-13S 08/30/07 11200 +/- 1170 MW-TMI-13S 09/05/07 11400 +/- 1200 MW-TMI-13S 09/11/07 9890 +/- 1030 MW-TMI-13S 09/17/07 7510 +/- 809 MW-TMI-13S 09/25/07 7310 +/- 792 MW-TMI-13S 10/01/07 6840 +/- 741 MW-TMI-13S 10/10/07 4690 +/- 534 MW-TMI-13S 11/08/07 6360 +/- 700 MW-TMI-13S 11/28/07 248 +/- 123 MW-TMI-1 3S 12/04/07

< 195 MW-TMI-13S 12/20/07 351 +/- 126 MW-TMI-14D 04/13/07 1330 +/- 204 MW-TMI-14D 05/10/07 1690 +/- 224 MW-TMI-14D 10/10/07 1390 +/- 213 MW-TMI-14D 11/08/07 1330 +/- 153 MW-TMI-14D ORIGINAL 11/28/07 1420 +/- 154 MW-TMI-14D DUPLICATE 11/28/07 1480 +/- 155 B,-5

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-TMI-14D 12/04/07 1370 +/- 223 MW-TMI-14D 12/20/07 1390 +/- 151 MW-TMI-141 03/28/07 577 +/-'155 MW-TMI-141 05/10/07 940 +/- 170 MW-TMI-141 08/09/07 869 +/- 154 MW-TMI-141 08/14/07 873 +/- 151 MW-TMI-141 08/23/07 813 +/- 141 MW-TMI-141 10/10/07 788 +/- 160 MW-TMI-141 ORIGINAL 11/08/07 447 +/- 139 MW-TMI-141 DUPLICATE 11/08/07 453 +/- 142 MW-TMI-14S 03/30/07

< 200 MW-TMI-14S 04/24/07 253 +/- 118 MW-TMI-14S 04/30/07 322 +/- 130 MW-TMI-14S 05/07/07 674 +/- 131 MW-TMI-14S ORIGINAL 05/14/07 754 +/- 139 MW-TMI-14S DUPLICATE 05/14/07 807 +/- 146 MW-TMI-14S 08/09/07 430 +/- 124 MW-TMI-14S 08/14/07 325 +/- 115 MW-TMI-14S 08/23/07

< 153 MW-TMI-14S 08/30/07 450 +/- 122 MW-TMI-14S 09/05/07 608 +/- 136 MW-TMI-14S 09/11/07 523 +/- 127 MW-TMI-14S 09/17/07 368 +/- 123 MW-TMI-14S 10/11/07 471 +/- 135 MW-TMI-14S 11/08/07 392 +/- 132 MW-TMI-14S 11/28/07 481

+/- 129 MW-TMI-14S 12/04/07 806 +/- 174 MW-TMI-14S 12/20/07 291 +/- 122 MW-TMI-16D 03/29/07 4180 +/- 494 MW-TMI-16D 04/05/07 3930 +/- 453 MW-TMI-16D 04/09/07 4360 +/- 490 MW-TMI-16D 04/13/07 3510 +/- 416 MW-TMI-16D 04/20/07 2990 +/- 354 MW-TMI-16D 05/10/07 2630 +/- 314 MW-TMI-16D 05/18107 1020 +/- 169 MW-TMI-16D 05/29/07 3030 +/- 354 MW-TMI-16D 06/07/07 3700 +/- 241 MW-TMI-16D 06/12/07 3830 +/- 248 MW-TMI-16D 06/19/07 3950 +/- 439 MW-TMI-16D 06/29/07 3240 +/- 373 MW-TMI-16D ORIGINAL 09/25/07 3120 +/- 379 MW-TMI-16D DUPLICATE 09/25/07 4060 +/- 471 MW-TMI-16D 10/01/07 3490 +/- 422 MW-TMI-16D 10/09/07 3710 +/- 436 MW-TMI-16D 11/08/07 1340 +/- 213 MW-TMI-16D 11/28/07 2750 +/- 182 MW-TMI-16D 12/04/07 3180 +/- 395 MW-TMI-16D 12/20/07 2750 +/- 182 MW-TMI-161 03/29/07 15500

+/- 1620 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, 2007 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-TMI-161 04/02/07 14400 +/- 1490 MW-TMI-161 04/05/07 15400 +/- 1590 MW-TMI-161 ORIGINAL 04/09/07 19200

+/- 1960 MW-TMI-161 DUPLICATE 04/09/07 17100 +/- 1750 MW-TMI-161 04/13/07 20000 +/- 2050 MW-TMI-161 04/17/07 17400 +/- 1800 MW-TMI-161 04/20/07 17300

+/- 1780 MW-TMI-161 04/24/07 18700

+/- 1920 MW-TMI-161 04/30/07 18700

+/- 805 MW-TMI-161 05/07/07 19300 +/- 1960 MW-TMI-161 05/14/07 18000 +/- 1850 MW-TMI-161 05/18/07 16600 +/- 1710 MW-TMI-161 05/21/07 15800 +/- 1620 MW-TMI-161 ORIGINAL 05/25/07 24200 +/- 2460 MW-TMI-161 RERUN 05/25/07 21200 +/- 2150 MW-TMI-161 05/29/07 10100 +/- 1060 MW-TMI-161 06/07/07 6780 +/- 390 MW-TMI-161 06/19/07 4890 +/- 531 MW-TMI-161 06/29/07 4520 +/- 500 MW-TMI-161 07/05/07 4680 +/- 517 MW-TMI-161 ORIGINAL 07/12/07 3970 +/- 449 MW-TMI-161 DUPLICATE 07/12/07 4430 +/- 495 MW-TMI-161 07/19/07 4150 +/- 464 MW-TMI-161 07/26/07 4230 +/- 474 MW-TMI-161 08/02/07 9620 +/- 1010 MW-TMI-161 08/09/07 8650 +/- 917 MW-TMI-161 08/14/07 6910 +/- 740 MW-TMI-161 08/23/07 4990 +/- 546 MW-TMI-161 08/30/07 4300 +/- 483 MW-TMI-161 09/05/07 3820 +/- 441 MW-TMI-161 09/11/07 4860 +/- 543 MW-TMI-161 09/17/07 4430 +/- 501 MW-TMI-161 10/11/07 6960 +/- 323 MW-TMI-161 11/08/07 3620 +/- 430 MW-TMI-161 11/28/07 2340 +/- 173 MW-TMI-161 12/04/07 1740 +/- 258 MW-TMI-161 ORIGINAL 12/20/07 1280 +/- 149 MW-TMI-161 DUPLICATE 12/20/07 1070 +/- 183 MW-TMI-17D 05/10/07

< 186 MW-TMI-17D 05/18/07 177 +/- 113 MW-TMI-17D 05/21/07 259 +/- 116 MW-TMI-17D ORIGINAL 05/25/07 166 +/- 98 MW-TMI-17D DUPLICATE 05/25/07

< 141 MW-TMI-17D 10/16/07

< 188 MW-TMI-171 ORIGINAL 04/05/07

< 168 MW-TMI-171 DUPLICATE 04/05/07

< 174 MW-TMI-171 ORIGINAL 04/24/07

< 165 MW-TMI-171 DUPLICATE 04/24/07 217 +/- 115 B-7

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-TMI-171 ORIGINAL 04/30/07 252 +/- 127 MW-TMI-171 DUPLICATE 04/30/07 288 +/- 128 MW-TMI-171 05/07/07 294 +/- 112 MW-TMI-171 05/14/07

< 162 MW-TMI-171 ORIGINAL 05/18/07 221 +/- 112 MW-TMI-171 DUPLICATE 05/18/07

< 165 MW-TMI-171 05/21/07 233 +/- 111 MW-TMI-171 05/25/07 263 +/- 112 MW-TMI-171 05/29/07 238 +/- 107 MW-TMI-171 06/07/07 187 +/- 114 MW-TMI-171 ORIGINAL 06/12/07

< 179 MW-TMI-171 DUPLICATE 06/12/07 344 +/- 118 MW-TMI-171 06/19/07 260 +/- 107 MW-TMI-171 ORIGINAL 07/05/07 251 +/- 114 MW-TMI-171 DUPLICATE 07/05/07

< 163 MW-TMI-171 07/12/07 277 +/- 119 MW-TMI-171 07/19/07 265 +/- 115 MW-TMI-171 ORIGINAL 07/26/07 191 +/- 105 MW-TMI-171 DUPLICATE 07/26/07 169 +/- 100 MW-TMI-171 08/02/07 222 +/- 111 MW-TMI-171 10/16/07 228 +/- 120 MW-TMI-18D 05/09/07

< 159 MW-TMI-18D 10/15/07

< 188 MW-TMI-19D 05/09/07

< 186 MW-TMI-19D ORIGINAL 10/15/07

< 182 MW-TMI-19D DUPLICATE 10/15/07 197 +/- 123 MW-TMI-191 05/10/07

< 188 MW-TMI-191 10/15/07 238 +/- 131 MW-TMI-1D 04/05/07 446 +/- 132 MW-TMI-1D 05/10/07 456 +/- 134 MW-TMI-1D ORIGINAL 10/15/07 521 +/- 137 MW-TMI-1D DUPLICATE 10/15/07 430 +/- 134 MW-TMI-2D 03/20/07 659 +/- 158 MW-TMI-2D 05/10/07 671 +/- 144 MW-TMI-2D ORIGINAL 08/14/07 855 +/- 144 MW-TMI-2D DUPLICATE 08/14/07 775 +/- 136 MW-TMI-2D 08/30/07 631 +/- 132 MW-TMI-2D ORIGINAL 09/05/07 823 +/- 156 MW-TMI-2D DUPLICATE 09/05/07 819 +/- 155 MW-TMI-2D 09/11/07 920 +/- 161 MW-TMI-2D 09/17/07 829 +/- 157 MW-TMI-2D 09/25/07 662 +/- 148 MW-TMI-2D 10/01/07 788 +/- 165 MW-TMI-2D 10/10/07 718 +/- 155 MW-TMI-31 05/09/07 478 +/- 120 MW-TMI-31 10/16/07 385 +/- 125 MW-TMI-41 05/08/07

< 192 MW-TMI-41 10/12/07

< 182 B-8

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-TMI-41 MW-TMI-41 MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-5D MW-TMI-5D MW-TMI-6D MW-TMI-6D MW-TMI-61 MW-TMI-61 MW-TMI-61 MW-TMI-7S MW-TMI-8S MW-TMI-8S MW-TMI-91 MW-TMI-91 MW-TMI-91 N2-1 N2-1 NW-A NW-A NW-B NW-B NW-C NW-C NW-CW NW-CW OS-13B OS-14 OS-14 OS-16 OS-17 OS-18 OS-18 OS-18 OS-18 COLLECTION DATE ORIGINAL 10/12/07 DUPLICATE 10/12/07 ORIGINAL 05/08/07 DUPLICATE 05/08/07 05/18/07 ORIGINAL 05/21/07 DUPLICATE 05/21/07 05/25/07 05/29/07 06/07/07 06/12/07 06/19/07 ORIGINAL 08/09/07 DUPLICATE 08/09/07 08/14/07 08/23/07 10/16/07 05/09/07 10/12/07 05/10/07 10/11/07 ORIGINAL 05/10/07 DUPLICATE 05/10/07 10/11/07 05/09/07 05/09/07 10/15/07 05/09/07 ORIGINAL 10/15/07 DUPLICATE 10/15/07 05/09/07 10/10/07 05/10/07 10/14/07 05/10/07 10/14/07 05/10/07 10/14/07 05/10/07 10/14/07 05/08/07 05/08/07 10/11/07 10/16/07 10/15/07 03/20/07 05/09/07 ORIGINAL 08/14/07 DUPLICATE 08/14/07 H-3 SR-90

< 182 193 + 116

< 192

< 187

< 166

< 169

< 188

< 150

< 162

< 180

< 179

< 152

< 173

< 172

< 162

< 154

< 185

< 163

< 181 323 +/- 130 357 +/- 121

< 187 270 +/- 131 247 +/- 119

< 188 172 + 106

< 186

< 163

< 185 232 +/- 121

< 165

< 193 1560 1330 1160 679 3140 3360 1390 1180 257

< 162

< 181

+/- 211

+/- 149

+/- 177

+/- 134

+/- 364

+/- 229

+/- 195

+/- 191

+ 122 275 +/- 128

< 184 238 211 379 365

+/- 130

+/- 106

+/- 109

+/- 108 B-9

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE OS-18 OSF OSF OSF OSF RW-1 RW-1 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 RW-2 TRAINING CENTER COLLECTION DATE 10/15/07 03/19/07 05/08/07 08/14/07 10/11/07 05/08/07 10/11/07 ORIGINAL 03/21/07 DUPLICATE 03/21/07 03/28/07 03/30/07 04/05/07 04/09/07 04/13/07 04/17/07 04/20/07 04/24/07 04/30/07 05/07/07 05/18/07 05/21/07 05/25/07 05/29/07 06/07/07 06/12/07 06/20/07 06/29/07 07/05/07 07/12/07 07/19/07 07/26/07 08/02/07 08/09/07 08/16/07 08/23/07 ORIGINAL 08/30/07 DUPLICATE 08/30/07 09/05/07 09/11/07 ORIGINAL 09/17/07 DUPLICATE 09/17/07 09/25/07 10/01/07 10/09/07 11/08/07 11/28/07 12/04/07 12/20/07 10/16/07 H-3 SR-90

< 197 536 634 669 748

< 166 423 13600 12900 12100 10700 11700 11800 9060 8100 7850 6670 6420 5100 4390 3520 4120 4760 13700 17500 24300 23500 29600 25000 20800 23600 17400 14600 10000 8360 6190 7080 4950 3610 3510 3440 4660 4600 4810 1250 823 951 777

< 184

+/- 148

+/- 157

+/- 128

+/- 157

+/- 123

+/- 1410

+/- 1350

+/- 1280

+/- 1140

+/- 1220

+/- 1230

+/- 967

+/- 868

+/- 838

+/- 722

+/- 319

+/- 557

+/- 491

+/- 407

+/- 459

+/- 522

+/- 732

+/- 923

+/- 2460

+/- 2380

+/- 3430

+/- 2540

+/- 2120

+/- 2400

+/- 1780

+/- 1510

+/- 1050

+/- 877

+/- 668

+/- 756

+/- 552

+/- 415

+/- 409

+/- 402

+/- 532

+/- 529

+/- 547

+/- 206

+/- 140

+/- 186

+/- 137 B-10

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-E-1 SW-E-1 SW-E-1 SW-E-1 SW-E-2 SW-E-2 SW-E-2 SW-E-2 SW-E-3 SW-E-3 SW-E-3 SW-E-3 SW-E-3 COLLECTION DATE 03/20/07 05/10/07 08/15/07 10/16/07 03/20/07 05/09/07 08/15/07 10/16/07 03/20/07 ORIGINAL 05/09/07 DUPLICATE 05/09/07 08/15/07 10/16/07 H-3

< 182

< 155

< 140

< 182

< 189

< 188

< 139

• 187

< 186

< 190

< 190 143 + 93

< 181 SR-90 B-11

TABLE B-I.3 CONCENTRATIONS OF TRITIUM IN WELL WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE 48S 48S 48S MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-19 MS-19 MS-5 MS-8 MW-i MW-2 MW-2 MW-2 MW-2 MW-TMI-101 MW-TMI-101 MW-TMI-10S MW-TMI-12S MW-TMI-12S MW-TMI-131 MW-TMI-1 31 MW-TMI-131 MW-TMI-13S MW-TMI-14D MW-TMI-141 MW-TMI-14S MW-TMI-16D MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-17D MW-TMI-17D MW-TMI-171 MW-TMI-171 MW-TMI-171 MW-TMI-171 MW-TMI-171 MW-TMI-171 MW-TMI-171 MW-TMI-171 H-3 04/17/07 04/24/07 10/15/07 03/30/07 04/13/07 04/17/07 06/07/07 06/29/07 07/19/07 08/02/07 10/10/07 10/10/07 05/08/07 10/11/07 09/11/07 05/29/07 ORIGINAL 06/19/07 DUPLICATE 06/19/07 08/23/07 ORIGINAL 03/21/07 DUPLICATE 03/21/07 05/09/07 05/07/07 08/16/07 04/02/07 10/01/07 12/04/07 03/29/07 11/28/07 11/08/07 05/14/07 09/25/07 04/09/07 07/12/07 12/20/07 ORIGINAL 05/25/07 DUPLICATE 05/25/07 04/05/07 ORIGINAL 04/24/07 DUPLICATE 04/24/07 04/30/07 05/18/07 06/12/07 07/05/07 07/26/07

< 159

< 155 235 +/- 83 2474 +/- 161 6061 +/- 232 5593 +/- 224 3598 1127 699 776 406 494

+

+

+

+

185 123 107 129 114 116

< 181

• 184 781 +/- 108

< 177

< 169

< 169

< 154 4973 +/- 209 5190 +/- 213 5351 +/- 216 1019 +/- 122 3245 +/- 181 3213 +/- 177 9092 +/- 270 7787 +/- 253 413 +/- 92 1125 +/- 133 481 +/- 110 779 +/- 120 3564 +/- 179 14243 +/- 344 4684 +/- 205 1093 +/- 127

< 177

< 177 191 +/- 90 175 +/- 89

< 155 205 +/- 120 261 +/- 93 285 +/- 91 219 +/- 102 202 +/- 101 B-12

TABLE B-I.3 CONCENTRATIONS OF TRITIUM IN WELL WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE H-3 MW-TMI-19D MW-TMI-1 D MW-TMI-2D MW-TMI-2D MW-TMI-41 MW-TMI-4S MW-TMI-4S MW-TMI-4S MW-TMI-61 MW-TMI-91 OS-18 RW-2 RW-2 RW-2 10/15/07 10/15/07 08/14/07 09/05/07 10/12/07 05/08/07 05/21/07 08/09/07 05/10/07 10/15/07 08/14/07 03/21/07 08/30/07 09/17/07 168 +/- 80 373 +/- 89 741 +/- 114 781 +/- 108 233 +/- 106

< 181

< 153 425 +/- 117 256 +/- 103

< 144 419 12143 6892 3625

+/- 102

+/- 306

+/- 260

+/- 181 B - 13

TABLE B-I.4 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE SW-E H-3

.-3 U0/U0/07

< 181 B - 14

TABLE B-I.5 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 K-40 PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 I-,

1. 3 10/15/07 48N 10/15/07 48S 10/16/07 48S 10/16/07 E1-2 10/16/07 MS-1 10/16/07 MS-19 10/10/07 MS-19 10/10/07 MS-19 10/10/07 MS-2 10/11/07 MS-20 10/15/07 MS-21 10/15/0.7 MS-22 10/16/07 MS-3 10/15/07 MS-4 10/09/07 MS-5 10/11/07 MS-6 10/11/07 MS-7 10/11/07 MS-8 10/11/07 MS-8 10/11/07 MS-8 10/11/07 MW-i 10/10/07 MW-2 10/10/07 MW-3 10/10/07 MW-4 10/10/07 MW-TMI-1 OD 10/15/07 MW-TMI-101 10/16/07 MW-TMI-10S 10/15/07 MW-TMI-131 10/10/07 MW-TM I-13S 10/10/07

<37

<35

<4

<4

<9

<4

<<8

< 47

< 90

< 5

< 5

< 13

< 5

< 11

<41

< 86

< 4

<4

< 10

<4

< 9

<45

< 84

< 5

< 5

< 12

<6

< 12

< 46

< 48

< 5

< 5

< 11

< 6

< 11

<44

<43

<5

<5

<9

<3

<7

< 41

< 45

< 4

< 4

< 11

< 5

< 9

< 37

< 47

< 5

< 4

< 10

< 3

< 5

< 49 151

+ 47

< 4

< 5

< 10

< 5

< 9

< 53

< 57

< 5

< 5

< 13

< 6

< 11

< 47

< 42

< 6

< 6

< 12

< 6

< 10

<41

<65

<4

<5

<8

<4

<9

< 49

< 106

< 5

< 5

< 10

< 7

< 11

< 40

< 70

< 4

< 5

< 11

< 5

< 10

< 42

< 68

< 4

< 4

< 10

< 5

< 10

<41

<48

<3

<5

<9

<4

<9

<48

<38

<5

<5

<11

<5

<9

< 42

< 33

< 4

< 4

< 11

< 6

< 9

< 43

< 94

< 5

< 5

< 10

< 3

< 9

< 49

< 91

< 5

< 5

< 13

< 4

< 10

<33

<58

<3

<4

<8

<3

<7

< 49

< 75

< 4

< 4

< 13

< 5

< 9

< 40

< 97

< 6

< 5

< 10

< 5

< 9

<38

<64

<4

<5

<9

<5

<8

< 58

< 91

< 5

< 4

< 11

< 5

< 11

< 52

< 57

< 5

< 6

< 13

< 6

< 13

< 54

< 93

< 5

< 6

< 11

< 4

< 10

< 61

< 102

< 6

< 5

< 13

< 5

< 16

<46

<43

<4

< 5

< 11

<4

< 10

< 43

< 97

< 5

< 5

< 12

< 5

< 9

<6

<8

<5

<6

<6

<5

<6

<4

<5

<7

<6

<6

<6

<6

<5

<5

<6

<5

<5

<6

<4

<5

<5

<5

<5

<7

<6

<7

<5

<5

< 7

<9

<7

< 10

<9

< 10

<9

<7

<8

< 10

< 10

<9

< 10

<8

<8

<7

<8

<8

< 9

< 10

<7

< 10

< 10

<8

<8

<9

< 10

< 10

<9

<8

<4

<5

<4

<5

<5

<4

<3

<4

<5

<4

<5

<4

<5

<5

<4

<4

<4

<4

<4

<5

<3

<4

<4

<4

<4

<5

<6

<6

<4

<4

<5

<5

<4

<5

<5

<4

<4

<5

<5

<6

<5

<5

<5

<5

<4

<4

<5

<4

<5

<4

<4

<5

<5

<4

<6

<5

<5

<6

<4

<4

< 29

< 34

< 30

< 37

< 32

< 28

< 37

< 37

< 39

< 47

< 31

< 33

< 32

< 29

< 36

< 34

< 39

< 37

< 37

< 43

< 23

< 40

< 38

< 32

< 44

< 37

< 35

< 44

< 41

< 36

<8

< 11

<8

< 11

< 10

< 10

< 14

<9

< 14

< 12

< 12

< 12

<8

<9

< 13

< 14

< 14

< 15

< 14

< 14

<9

< 14

< 13

< 10

< 14

< 14

< 12

< 15

< 12

< 15

TABLE B-I.5 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD tz MW-TMI-14D MW-TMI-141 MW-TMI-14S MW-TMI-1 6D MW-TMI-161 MW-TMI-17D MW-TMI-171 MW-TMI-18D MW-TMI-19D MW-TMI-19D MW-TMI-191 MW-TMI-1D MW-TMI-ID MW-TMI-2D MW-TMI-31 MW-TMI-41 MW-TMI-41 MW-TMI-41F MW-TMI-4S MW-TMI-5D MW-TMI-6D MW-TMI-61 MW-TMI-8S MW-TMI-91 MW-TMI-91 N2-1 NW-A NW-B NW-C NW-CW 10/10/07 10/10/07 10/11/07 10/09/07 10/11/07 10/16/07 10/16/07 10/15/07 10/15/07 10/15/07 10/15/07 10/15/07 10/15/07 10/10/07 10/16/07 10/12/07 10/12/07 10/12/07 10116107 10/12/07 10/11/07 10/11/07 10/15/07 10/15/07 10/15/07 10/10/07 10/16/07 10/16/07 10/16/07 10/16/07

< 43

< 29

< 41

< 30

< 40

< 51

< 42

< 47

< 44

< 46

< 41

< 45

< 47

< 36

< 53

< 40

< 40

< 48

• 29

< 51

< 51

< 44

< 43

< 52

< 45

• 36

< 52

< 50

< 43

< 47

• < 66

< 4

< 5

< 10

<49

<3

<3

<7

<36

<4

<4

<9

<46

<4

<4

<7

<60

<4

<4

<8

< 110

< 5

< 6

< 13

< 103

< 5

< 6

< 13

<47

<5

<5

<10

< 122

< 4

< 4

< 11

<91

<5

<5

<12

<37

<4

<4

<9

<40

<4

<6

< 10 96 58 <5

<5

<12

<61

<4

<4

<9

<47

<5

<6

<13

<80

<5

<4

<10

<36

<5

<5

<11

< 105

< 5

< 6

< 11

<61

<3

<3

<5

<77

<5

<5

<10

<97

<5

<5

<11

<97

<5

<5

<11 147 +/-57 <4

<5

<11

< 103

< 6

< 6

< 13

<50

<5

<4

<10

<31

<4

<4

<8

<50

<5

<5

<11

< 44

< 6

< 6

< 13

<82

<4

<5

<11

<94

<6

<5

<10

<3

<3

<4

<3

<2

<5

<6

<6

<5

<5

<5

<6

<5

<3

<6

<5

<4

<5

<3

<5

<5

<5

<5

<5

<4

<4

<5

<3

<5

<5

<9

<5

<8

<6

<8

< 12

<9

< 12

< 10

<9

<9

< 14

< 10

<8

<13

<9

<9

<10

<5

< 10

< 10

< 10

<9

< 10

<9

<7

<8

< 12

< 11

< 12

<5

<4

<5

<3

<5

<7

<6

<6

<6

<6

<5

<6

<7

<4

<7

<5

<6

<6

<4

<7

<7

<6

<6

<7

<6

<5

<6

<6

<5

<7

<8

<4

<4

<37

<10

<6

<3

<3

<25

<11

<8

<4

<4

<39

<12

<*7

<3

<3

<27

<8

<6

<5

<4

<36

<13

<10

<5

<6

<36

<11

<10

<4

<5

<33

<12

<9

<4

<6

<31

<12

<10

<4

<4

<32

<9

<10

<5

<5

<32

<7

<8

<4

<4

<35

<11

<9

<5

<6

<37

<13

<10

<5

<5

<35

<12

<7

<4

<4

<31

<8

<10

<5

<6

<44

<12

<8

<3

<5

<34

<12

<9

<4

<5

<38

<13

<10

<4

<5

<33

<15

<4

<3

<3

<20

<7

<9

<5

<5

<44

<14

<9

<5

<6

<43

<14

<9

<4

<4

<34

<14

<10

<4

<5

<34

<10

<10

<6

<7

<41

<12

<9

<4

<4

<33

<10

<7

<4

<4

<29

<11

<10

<5

<5

<39

<12

<9

<6

<6

<37

<14

<8

<4

<5

<33

<11

<9

<5

<5

<36

<10

TABLE B-1.5 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 OS-14 10/11/07 OS-16 10/16/07 OS-17 10/15/07 OS-18 10/15/07 OSF 10/11/07 RW-1 10/11/07 RW-2 10/09/07 tol TRAINING CENTER 10/16/07

• 36

< 38

< 50

< 46

< 43

< 43

< 41

• 58

< 79

• 41 143 +/- 69

< 61

< 88

< 63

< 69

< 52

<3

<4

<8

<4

<4

<5

<10

<6

<5

<5.

<10

<5

<5

<6

<13

<5

<4

<5

<12

<4

<4

<4

<10

<4

<4

<4

<10

<4

<6

<7

<14

<6

<7

<9

<11

<11

<9

<9

<8

< 14

<3

<7

<3

<4

<28

<5

<7

<4

<4

<29

<6

<10

<5

<5

<40

<5

<10

<4

<5

<41

<5

<8

<4

<5

<28

<5

<9

<3

<4

<34

<4

<7

<4

<4

<35

<8

<9

<6

<6

<43

<8

< 13

< 12

< 12

<9

< 12

< 14

< 12

TABLE B-1.6 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 PERIOD SW-E-1 10/16/07

< 49 SW-E-2 10/16/07

< 56 SW-E-3 10/16/07

< 43 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

< 111

< 43

< 45

<7

<6

<4

<6

<6

<5

<9

<6

<13

<6

<13

<6

<15

<7

<11

<7

<10

<7

<10

<5

<10

<6

<9

<5

<7

<6

<5

<33

< 11

< 39

< 13

< 32

< 15 00

TABLE B-1.7 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA s

STC COLLECTION Be-7 PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34 Cs-137 Ba-140 La-140 48S MS-19 MS-8 MW-TM I-19D MW-TMfI-1 D MW-TMI-41 MW-TMI-91 10/15/07 10/10/07 10/11/07 10/15/07 10/15/07 10/12/07 10/15/07

< 24

< 63

< 68

< 31

< 18

< 46

< 41

• 62

< 55

• 51

< 63 60

< 68

< 71

+ 32

<3

<2

<4

<1

<2

<5

<16

<2

<3

<3

<17

<2

<2

<2

<6

<2

<3

<3

<2

<3

<3

<6

<4

<2

<3

<6

<6

< 18

< 12

<3

<5

<3

<4

< 11

< 10

<4

<5

< 2

<3

<3

<2

<2

<3

<3

<2

<2

<2

<3

<2

<3

<3 22 672 949 21 13 974 27

<3

• 129

< 228

<3

<4

< 319

<9

<2

<2

<3

<3

<5

<2

<5

< 30

<6

<3

<3

<2