Text

Annual Radiological Environmental Operating Report
	ML101250157
Person / Time
Site:	Crane
Issue date:	04/28/2010
From:	Libra R; Exelon Nuclear
To:	; Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
	TMI-10-030
	Download: ML101250157 (165)
	v • d • e

Exelkn Nuclear Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 TMI-10-030 April 28, 2010 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION UNITS 1 AND 2 RENEWED OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR-73 DOCKET NOS. 50-289 AND 50-320

SUBJECT:

2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING 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, 2009, 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, Richard W. Libra Plant Manager RWL/dbn 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 k c-*

Docket No:

50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2009 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Three Mile Island Nuclear Station Middletown, PA 17057 April 2010

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

1 I1. Introduction.............................................................................................................

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

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

4 I1l. Program Description................................................................................................

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

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

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

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

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

12 IV. Results and Discussion.........................................................................................

12 A. Aquatic Environm ent.....................................................................................

12

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

12

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

13

3. Effluent W ater..................................................................................... 14

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

15

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

15

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

16

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

16 B. Atm ospheric Environm ent...........................................................................

17

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

17

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

17

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

18

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

18

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

18

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

19 C. Am bient Gam m a Radiation.........................................................................

19 D. Land Use Survey..........................................................................................

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

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

29 V. References...................................................................................................................

30,

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, 2009 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, 2009 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2009 Figqures Figure B-i:

Figure B-2:

Figure B-3:

Appendix C Tables Table C-1.1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2009 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2009 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2009 Data Tables and Figures - Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station,,2009.

ii

Table C-1.2 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-I1.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-11.2 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-I1.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-II1.1 Concentrations of Gross Beta, 1-131, Tritium, and Strontium in Effluent Water Samples for Station K1 -1 Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-I11.2 Concentrations of Gamma Emitters in EffluentWater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-IV.1 Concentrations of Tritium and Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

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

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

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, 2009.

Table C-VI.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-VII.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

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, 2009.

Table C-VII.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Table C-VII.4 Concentrations of Strontium and Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009 iii

Table C-VIII.1 Table.-C-IX. 1 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 Concentrationsiý,of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations ýof 1-131 in Milk Samples Collected in. the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile-Island Nuclear Station, 2009.

Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Quarterly TLD Results for Three Mile Island Nuclear Station, 2009.

Mean Quarterly TLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2009.

Summary of the Ambient Dosimetry Program for Three Mile Island

.Nuclear Station, 2009.

Monthly Tritium: Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station,' 2009.

Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 -2009.

Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2009.

Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2009.

Mean Cesium-i 37 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 -2009.

Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 -2009.

Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2009.

Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 -2009.

Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 -2009.

iv

Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-11.1 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, 2009.

Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of lodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile. Island Nuclear Station, 2009.

Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2009.

Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2009.

Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2009 v

Table E-2 Table E-3 Table E-4 Table E-5 Appendix F ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2009 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne BrownEngineering, 2009 ERA Statistical y!Summary Proficiency Testing Program Environmental, Inc., 2009 DOE's Mixed A nalyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2009 Annual Radiological Groundwater Protection Program Report (ARGPPR) vi

1.

Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Three Mile Island Nuclear Station (TMINS) by Exelon covers the period 1 January 2009 through 31 December 2009. During that time period, 1,715 analyses were performed on 1,320 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 watersamples were analyzed for concentrations of tritium and gamma emitting nuclides. Surface, drinking, and effluent water samples were also analyzed for concentrations of 1-131. Drinking and effluent water samples were also analyzed for concentrations of gross beta.

Effluent water samples were also analyzed for concentrations of Sr-89 and Sr-90. All groundwater results are now being reported in the ARGPPR, Appendix F. No Sr-89 and Sr-90 activities were detected. lodine-131 and gross beta concentrations detected were consistent with those detected in previous years.

Tritium activity in one drinking water sample and several monthly effluent water samples was due to TMINS activities or releases. No other fission or activation products potentially attributed to TMI liquid releases were detected.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected. No fission or activation products were detected in fish samples. Cesuim-1 37 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. Cobalt-58, Co-60, Nb-95, and Zr-95 were detected in air particulate samples from a release to the environment in November 2009. No Sr-90 activity was detected. The dose to a member of the public based on this environmental sample result was calculated as 0.02 mrem.

No other activation products were detected.

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

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

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

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

No other fission or activation products were detected.

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

In conclusion, radioactive materials related to TMINS operations were detected in environmental samples, but.the measured concentrations were low and consistent with measured effluents. The environmental sample results verified that the doses received by the public from TMINS effluents in 2009 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 2009 did not have any adverse effects on the health of the public or on the environment.

II.

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

A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Global Dosimetry Solutions, Inc., and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2009 through 31 December 2009.

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 radidnuclides in the environment and changes in background radiation levels.

5.

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

6.

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

B.

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

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

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

Ill.

Program 'Description A.

Sample Collection Samples for the TMINS REMP were collected for Exelon by Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used by RMC to obtain environmental samples for the TMINS REMP in 2009. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, storm water, fish, and sediment. Two gallon water samples were collected monthly from continuous samplers located at three surface water locations (A3-2, J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9'-1), and one effluent water location (K1-1). Control locations were A3-2 and Q9-1. Monthly water samples composited quarterly for analysis were taken from one storm water runoff location (EDCB). All groundwaterresults are now being reported in the ARGPPR, Appendix F. All water samples were collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND.) location. Location IND could be affected by TMINS' effluent releases. Sediment samples composed of recently deposited substrate were collected semiannually at three locations (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 six locations (K1 5-3, D2-1, E2-2, F4-1, G2-1 and P4-1) from March through November, and monthly from December through February. The control location was K15-3. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Food products were collected monthly at two locations (B10-2 and H1-2),

in lieu of milk sampling, and annually from the four food product groups at two locations (E1-2 and B10-2). B10-2 was the control location for both annual and monthly sampling. Five different kinds of vegetation samples and four different kinds of vegetation leaves were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 814 calcium sulfate (CaSO4) thermoluminescent dosimeters (TLD). The TLD locations are arranged in generally concentric rings on and around the TMINS site as follows:

A site boundary ring consisting of 19 locations (A1-4, 81-2, C1-2, Di-1, E1-4, F1-2, F1-4, G1-3, G1-5, GI-6, H1-1, J1-3, K1-4, 1-1i, M1-1, N1-3, P1-2, Q1-2, and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release.

An indicator ring consisting of 60 locations (A3-1, A5-1, A9-3, 11-1, B2-1, B5-1, B10-1, C1-1, C2-1, C5-1, C8-1, DI-2, D2-2, D6-1, EI-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, GI-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1 -N5-1, N8-1, P11-1, 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 2009. 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 Reportin.qof Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity effecting a negative number. An MDC was reported in all cases where positive activity was not detected.

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

For surface, drinking, effluent, storm, and ground water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.

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

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

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

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

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

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

D.

Program Exceptions For 2009 the TMINS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

AIR

1. On 04/08/09 these' air sample stations were found not operating. Sample pumps were replaced, but it was determined to be an AC power problem.

On 04/21/09 the samplers were returned to service after the First Energy electricians repaired the main power supply. IR 905491 describes the issue for the following samples:

04/01/09 - 04/08/09, Locations E1-2, E1-2Q, LLDs not met 04/08/09 - 04/16/09, Locations E1-2, E1-2Q, No samples due to AC power problems 04/16/09 - 04/21/09, Locations E1-2, E1-2Q, No samples due to AC power problems

2. Slightly lower than expected sample volumes were due to power outages for the following samples:

08/05/09 - 08/12/09, Locations E1-2, E1-2Q, G2-1, H3-1 10/07/09 - 10/14/09, Locations E1-2, E1-2Q, G2-1 12/02/09 - 12/09/09, Location A3-1

3. "Noisy" vacuum pump was replaced for the following sampler:

10/22/09, Location M2-1 WATER

1. Surface water - During the following weekly sampling periods some of the hourly composite samples were missed due to weather related conditions. IR 870904 describes this issue. Insufficient sample was available for sampling periods so grab samples were required, except as noted, for the following samples.

12/30/08 - 01/06/09, Location J1-2, all samples missed 01/06/09 - 01/13/09, Location J1-2, all samples missed 01/13/08 -01/20/09, Location JA-2, all samples missed 01/20/09 - 01/27/09, Location J1-2, all samples missed 01/27/09 - 02/03/09, Location J1-2, all samples missed 02/03/09 - 02/10/09, Location A3-2, 22 samples missed, no grab sample required 02/10/09 - 02/17/09, Location J1-2, 80 samples missed 02/17/09 - 02/24/09, Location J1-2, 53 samples missed 02/24/09 - 03/03/09, Location J1-2, 47 samples missed 03/03/09 - 03/10/09, Location J1-2, 38 samples missed 03/10/09 - 03/17/09, Location J1-2, 9 samples missed, no grab sample required 04/15/09 - 04/21/09, Location J1-2, 5 samples missed, no grab sample required 04/21/09 - 04/28/09, Location J1-2, 9 samples missed, no grab sample required 10/27/09 - 11/03/09, Location J1-2, 3 samples missed, no grab sample required 12/01/09-12/08/09, Location J1-2, 2 samples missed, no grab sample required 12/08/09 - 12/15/09, Location J1-2, approximately 50 samples missed, no grab sample required 12/15/09 - 12/21/09, Location J1-2, approximately 75 samples missed 12/21/09 - 12/28/09, Location J1-2, approximately 70 samples missed

2. Surface water - During the sampling periods, the sampler had an error message stating that no sample was collected, but the collection bucket was half full. It was determined that a crimp in the line was causing air to become trapped in the sample stream fooling the liquid detector. The crimp was corrected. The following samples were affected:

08/11/09 - 08/18/09, Location J2-1 08/18/09 - 08/25/09, Location J2-1

3. Drinking water - During the weekly sampling periods, numerous samples were missed due to a pump jam error. The ISCO was calibrated and functioning normally. IR 1025964 describes this issue.

Sufficient sample was available for sampling periods so no grab samples were required.

12/09/09 - 12/15/09, Location Q9-1, approximately 60 samples missed

4. Effluent water - During the weekly sampling periods, the sampler liquid detector was malfunctioning and causing a missed sample message.

The sampler was replaced. The malfunction affected the following samples:

08/11/09 - 08/18/09, Location K1 -1 08/18/09 - 08/25/09, Location K1-1

5. Effluent water - During the weekly sampling period, insufficient sample was available for the sampling period so a grab sample was required.

The ISCO was re-calibrated and returned to service. IR 1025964 describes this issue.

12/15/09 - 12/21/09, Location K1-1

6. Effluent water -During the weekly sampling period, a refueling outage caused power interruptions. IR 1025964 describes this issue.

Sufficient volume was available, so no grab sample was required for the following sample.

12/21/09 - 12/28/09, Location K1-1, 13 samples missed

7. Drinking water - Maintenance and construction at the facility caused power interruptions. Sufficient sample was available for sampling period, so no grab samples were required for the following sample.

09/15/09 - 09/22/09, Location G15-3 TLD

1. Frozen river condition made it unsafe to travel by boat to the TLDs located on the islands west of the plant. Therefore, the TLD stations were not changed out for the 4th quarter 2008. The TLDs were collected in the first quarter of 2009 with a six month exposure period for the following samples:

10/10/08 - 04/23/09, Location K2-1 10/10/08 - 04/23/09, Location L1-2 10/10/08 - 04/23/09, Location M1-2 10/10/08 - 04/23/09, Location N1-1 10/10/08 - 04/23/09, Location P1-1 10/10/08 - 04/23/09, Location Q1-1 10/10/08 - 04/23/09, Location R1 -2

2. During the second quarter sampling period, the TLD badges were found missing during collection. It appears that someone cut the plastic pouches and took the badges. IR 958396 describes this issue for the following sample:

04/23/09 - 07/18/09, Location F10-1

3. During the fourth quarter sampling period, the 1 of 2 TLD badges were found missing during collection. It appears that someone cut the plastic pouch and took the badge. IR 1025964 describes this issue for the following sample:

10/19/09 - 01/22/10, Location R15-1

4. Frozen river conditions made it unsafe to travel by boat to the TLDs located on the islands west of the plant. Therefore, the TLDs were not collected with other 4th quarter 2009 TLDs. The TLDs were successfully collected two weeks later when the river thawed. These seven TLD locations and their outer island control have significantly higher exposure levels than the remaining fourth quarter TLDs. This exposure is not related to TMI, but had to occur in transit to the vendor analysis lab because the control is kept in a shielded pig except for traveling to collect the badges and shipping to the vendor. In addition, other TLDs in the same sectors as these badges were located closer to the plant and received lower exposures more typical of historical averages. The data from these badges is not considered valid and will not be included in this report. IR 1025964 describes this issue for the following samples:

10/19/09 - 01/22/10, Location K2-1 10/19/09 - 01/22/10, Location L1-2 10/19/09 - 01/22/10, Location M 1-2 10/19/09 - 01/22/10, Location N1-1 10/19/09 - 01/22/10, Location P1-1 10/19/09 - 01/22/10, Location Q1-1 10/19/09 - 01/22/10, Location R1-2 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, The D2-1 farm sold their milk herd in November. A new milk farm, P4-1, was added to the REMP. IR 976028 describes this change.

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 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 227 to 9,250 pCi/I. The increased tritium concentrations detected were a result of TMINS releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. The indicator surface water sample is taken just downstream of the liquid discharge outfall where mixing of liquid effluents with the river water is incomplete. More complete mixing is not achieved until liquid effluents pass over the York Haven Dam. This water is normally not consumed by humans. The concentrations detected were well below any regulatory limits. (Figures C-1 and C-2, Appendix C).

Iodine Monthly samples from location A3-2 were analyzed for 1-131 activity (Table C-1.2, Appendix C). This is a control or background station sampled because known medical discharges of radiopharmaceuticals occur into the surface water upstream of TMI from a nearby hospital. lodine-131 was detected in two of 12 samples. The concentration ranged from 1.4 to 1.8 pCi/l.

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

2.

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

Gross Beta Monthly samples from all locations were analyzed for concentrations of gross beta. (Tables C-I1.1, Appendix C). Gross beta activity was detected in 20 of 36 samples. The concentrations ranged from 2.0 to 5.5 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-3, Appendix C).

Iodine Monthly samples from all locations were analyzed for concentrations of iodine (Tables C-11.2, Appendix C). Iodine activity was not detected in any samples.,

Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was detected in one sample at a concentration of 448pCi/I (Figures C-4, Appendix C). The dose to a member of the public based on this environmental sample result was calculated as 0.0053 mrem.

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 (K1-1). The following analyses were performed:

Gross Beta Monthly samples from location K1-1 were analyzed for concentrations of gross beta. (Tables C-111.1, Appendix C). Gross beta was detected in eleven of 12 samples. The concentrations ranged from 3.1 to 6.1 pCi/I. Concentrations detected were consistent With those detected in previous years.

Iodine-1 31 Monthly samples from location K11 were analyzed for concentrations of 1-131. (Tables C-111.1, Appendix C). Iodine-131 was not detected. Historically, 1-131 has been detected sporadically in effluent water and not in the control stations. No 1-131 was identified in any tank effluent pre-release samples, and 1-131 was not detected in any other downstream surface or drinking water samples. Effluent water is not consumed by humans.

Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-l11.1, Appendix C). Tritium activity was detected in eight of 12 samples. The concentrations ranged from 2,970 to 101,000 pCi/l. The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. These results were from the liquid discharge mixing basin. The concentrations detected agree with those obtained from the TMINS Effluent Monitoring Program. The concentrations were well below any regulatory limits.

Strontium Semiannual samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-I11.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at 2.2 pCi/I for Sr-89 and at 0.5 pCi/I for Sr-90.

Gamma Spectrometry Samples from location K1-1 were analyzed for gamma emitting nuclides (Table C-I11.2, Appendix C). All nuclides were less than the MDC.

4.

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

Tritium All samples from location EDCB were analyzed for tritium activity (Table C-IV.1, Appendix C). Tritium activity was not detected.

Gamma Spectrometry Samples from location EDCB were analyzed for gamma emitting nuclides (Table C-IV.l, 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 2009, this more comprehensive groundwater program replaced TMI's previous groundwater monitoring program. The results from these special investigations and studies are discussed in Appendix F.

6.

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

Strontium The edible portions of fish samples from both locations were analyzed for Sr-90. (Table C-V.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <5 pCi/kg wet for Sr-90.

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

Naturally occurring K-40 was found at all stations and ranged from 2,090 to 3,300 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 9,960 to 17,600 pCi/kg dry.

Cesuim-1 37 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 8to 30 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 8 to 204 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Control location (Group III) ranged from 9 to 28 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. Comparison of the 2009 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 2009 indicate no notable differences between indicator and control stations except for the sample period 11/18/09-11/24/09. The higher activity during this time is related to a release from TMI's temporary containment opening. The dose to a member of the public based on this environmental sample result was calculated to be 0.02 mrem. (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,56 to 125 E-3 pCi/i 3. Fourth quarter composite for G2-1 and F1-3 did not include the sample period 11/18/09-11/24/09 because an individual gamma scan was performed on these samples and the filter was needed for Sr-90 analysis. All other nuclides were less than the MDC.

Strontium Samples collected during the time period of 11/18/09 -

11/24/09 were analyzed for concentrations of Sr-90. No Sr-90 was detected in any of the samples (Table C-VII.4, Appendix C).

b.

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

2.

Terrestrial

a.

Milk Samples were collected from six locations (K1 5-3, D2-1, E2-2, F4-1 G2-1 and P4-1) biweekly March through November and monthly December through February. The following analyses were performed:

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

Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-IX.2, Appendix C). No Sr-89 activity was detected. Strontium-90 activity was detected in 10 of 21 samples. The concentrations ranged from 0.5 to 1.2 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 915 to 1,440 pCi/l. 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 (810-2 and E1-2) annually. The following analyses were performed:

Strontium Twenty of 26 food product sample was analyzed for concentrations of Sr-90 (Table C-X.1, Appendix C).

Strontium-90 activity was detected in 18 of 20 samples. The concentrations ranged from 2 to 49 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 Be-7 due to cosmic ray activity was detected in 11 of 26 samples. These concentrations ranged from 200 to 1,690 pCi/l. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 1,990 to 5,650 pCi/l. All other nuclides were less than the MDC.

C.

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

All of the TLD measurements were below 10 mR/standard month, with a range of 2.7 to 7.7 mR/standard month. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations D1 5-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 were consistently higher. The historical ambient gamma radiation data from Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 were plotted along with similar data from the Site, Indicator and Control Ring Locations (Figure C-9, Appendix C).

Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R1 5-1 have a historical high bias, but tracked with the data from all three groups, this bias is most likely due to radon and other naturally occurring, nuclides, e.g. K-40, emanating from the ground.

D.

Land Use Survey A Land Use Survey conducted in the September, October and November 2009 growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Normandeau Associates, RMC Environmental Services Division for Exelon to comply with Sections 2.15 and 3.4.2 of the Plant's Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident, milk-producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1/2 degree sectors around the site. There were no changes required to the TMINS REMP, as a result of this survey. Six gardens from the 2008 census were not established (or were not the closest) in 2009. As such, six new gardens were identified and included in the 2009 land use census. The locations where new gardens were identified include sectors B (NNE), C (NE), D (ENE), G (SE), N (W) and Q (NW). The results of this survey are summarized below.

Distance Sector 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW in Miles from the TMINS Residence Miles 1.1 0.7 0.5 0.5 0.4 1.1 0.7 0.7 2.3 0.6 0.5 0.5 0.7 0.4 0.4 1.1 Reactor Buildings Garden Miles 1.6 0.9 1.5 0.5 0.5 1.2 1.0 0.8 2.7 2.5 0.6 1.3 1.3 2.2 1.2 2.4 Milk Farm Miles 2.1 4.1 1.1 1.1 3.2 1.4 4.9, 14.5 3.7 E.

Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2009 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2009 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 0.085 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 TM INS is calculated using measurements from effluent sample anralyses. 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 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months 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 2009 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 2009 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 2009 TMI-1 and TMI1-2 liquid and airborne effluents combined was conservatively calculated to be 0.085 mrem. This dose is equivalent to <0.03% 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 2009 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 2009 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 2009 did not have any adverse effects on the health of the public or on the environment.

TABLEt Calculated Maximum Hypothetical Doses to an Individual from 2009 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual USNRC 10 CFR 50 APP. I Guidelines (mrem/yr)

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

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

TMI-1 TMI-2 2.77E-2 3.28E-4 2.86E-2 5.22E-4 2.98E-5 0*

7.07E-5 0*

5.59E-2 4.38E-5

No noble gases were released from TMI-2.

USEPA 40 CFR 190 Limits (mrem/yr) 75 thyroid 25 total body or other organs Calculated Dose (mrem/yr)

TMI-l and TMI-2 Combined**

Total from Site 0.43 0.46

*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 2009 TMINS operations was 0.37 mrem. This dose was based ona maximum net fence-line exposure rate of 6.8 mR/std month and a shoreline/fence-line occupancy factor of 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months (Regulatory Guide 1.109). The combination of the maximum organ dose from TMI-1 and TMI-2 effluents (0.085 mrem) and the dose from direct radiation (0.37 mrem) yielded a maximum hypothetical dose of 0.46 mrem.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2009 TMI-1 and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)

TMI-I 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.

2.77E-2 3.28E-4 2.98E-5 0*

5.59E-2 4.38E-5 Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations:

Individual Whole Body Dose Due to Natural Background Radiation 0.085 mremL/yr 300 mrem/yr Figure 1 Exposure Pathways For Radionuclides Routinely Released From TMINS PREDOMINANT RADIONUCLIDES NOBLEj GASES (XeKr)

Phumo cxposure RADIOIOD[NS ([-131, 1-133)

Iuhalation and consurnption of milk, water, fruits, and vegetables RADIOSTRONTtUMS (Sr-99, Sr-90)

Consumption of milk, meat, fruits, and vegetables ACTIVATION PRODUCTS,(Co,60, Mn-54)

Shoreline exposure RADIOCESIUMS (Cs-134, Cs-137).

Shoreline exposure And consumption of milk, meat, fish, water, ftruits, and %,egetabJCs TRCTIUM (H--3)

Inhalation and consumnption of water, milk, fruits, and vegetables F.

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

1.

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

2.

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

3.

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

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

1.

For the primary laboratory, 17 out of 18 analytes met the specified acceptance criteria. One sample did not meet the specified acceptance criteria for the following reason:

1.

Teledyne Brown Engineering's Analytics June 2009 Zn-65 in AP result of 137 pCi/L was higher than the known value of 101 pCi/L, resulting in a found to known ratio of 1.36. NCR 09-23 was initiated to investigate this failure. The failure appears to be a result of a slightly high bias on Detector 7. A recount on Detector 17 resulted in a Zn-65 result of 101 pCi/L. The detector has been tagged out-of-service until a recalibration can be performed.

Detector 7 is not used for client samples.

For the secondary laboratory, Environmental, Inc., 11 out of 14 analytes met the specified acceptance criteria. Three samples did not meet the specified criteria for the following reasons:

1. Environmental Inc.'s ERA April 2009 Cs-1 37 in water result of 147.7 pCi/L exceeded the lower control limit of 151.0 pCi/L. All gamma emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Recounting in a different beaker gave an acceptable result of 155.33 +/- 14.55 pCi/L.

2. Environmental Inc.'s ERA April 2009 H-3 in water result of 22819 pCi/L exceeded the upper control limit of 22300 pCi/L. A recount of the original vials averaged 23,009 pCiiL. Reanalysis results were acceptable at 19,170 pCi/L. No cause could be found for the failure.

3. Environmental Inc.'s MAPEP January 2009 Sr-90 in AP result of 0.93 exceeded the upper control limit of 0.83. Reanalysis results were acceptable at 0.54 +/- 0.12 Bq/filter. No 6ause could be found for the failure.

4. Environmental Inc.'s MAPEP July 2009 Sr-90 in soil result of 310.5 Bq/kg exceeded the lower control limit of 319 Bq/kg. Reanalysis results were acceptable at 363.3 Bq/kg. Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity.

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 NuclearStation, Preoperational Radiological Environmental Monitoring Program, January 1, 1974 - June5, 1974." RMC-TR-75-17, January 1975.

4.

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

5.

National Council of Radiation Protection and Measurements Report No.

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

1987.

Intentionally left blank

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKETNUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

H-3 24 2000 3271 (8/12)

(227/9250)

<LLD 3271 (8/12)

(227/9250)

TM-SW-JI-2 INDICATOR WEST SHORE; TMI 0.5 MILES S OF SITE TM-SW-A3-2 CONTROL SWATARA CREEK 2.5 MILES N OF SITE 0

0 1-131 12 24 NA 1.6 (2/12)

(1.4/1.8) 1.6 (2/12)

(1.4/1.8)

GAMMA MN-54 CO-58 15

<LLD 15

<LLD 30

<LLD 15

<LLD FE-59 CO-60

<LLD

<LLD 0

0 ZN-65 30

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SURFACE WATER (PCIILITER)

NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 15

<LLD 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 4

3.3 (14/24)

(2.6/4.2) 1

<LLD

<LLD 0

0 0

0

<LLD

<LLD DRINKING WATER (PCI/LITER)

GR-B 1-131 36 36 2.9 (6/12)

(2.0/5.5) 3.3 (9/12)

(2.6/4.2)

TM-DW-GI 5-2 INDICATOR WRIGHTS WATER SUPPLY 13.6 MILES SE OF SITE

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

TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 2000 448 (1/24) 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD

<LLD 448 (1/12)

TM-DW-G15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE

<LLD

<LLD 0

0 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

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

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 4

4.6 (11/12)

(3.1/6.1) 1

<LLD

<LLD 0

0 0

EFFLUENT WATER (PCI/LITER)

GR-B 1-131 12 12 NA NA 4.6 (11/12)

(3.1/6.1)

TM-EW-KI-1 INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS EFFLUENT WATER (PCI/LITER)

H-3 12 2000 33789 (8/12)

(2970/101000)

SR-89 SR-90

<LLD NA NA NA 33789 (8/12)

(2970/101000)

TM-EW-KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 0

0 0

2 GAMMA MN-54 12 2

<LLD 15

<LLD 30

<LLD 15

<LLD CO-58 FE-59 NA NA NA 0

CO-60 NA THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE.MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

REPORTING PERIOD:

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS EFFLUENT WATER (PCI/LITER)

ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 30

<LLD 15

<LLD 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD 200

<LLD NA NA NA NA NA NA 0

0 0

LA-140 NA STORM WATER (PCI/LITER)

H-3 NA 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS STORM WATER (PCI/LITER)

GAMMA MN-54 4

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 0

0 0

0 NA 0

NA 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS STORM WATER (PCI/LITER) 00 CS-134 CS-137 BA-140 LA-140 SR-90 GAMMA K-40 15

<LLD 18

<LLD 60

<LLD 15

<LLD 10

<LLD NA NA NA NA 0

0 0

BOTTOM FEEDER (PCI/KG WET) 4

<LLD 4

NA 3170 (2/2)

(3120/3220) 130

<LLD 2775 (2/2)

(2730/2820) 3170 (2/2)

(3120/3220)

INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE 0

0 MN-54

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS BOTTOM FEEDER (PCIKG WET)

CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 SR-90 130

<LLD 260

<LLD 130

<LLD 260

<LLD 130

<LLD 150

<LLD 10

<LLD

<LLD 0

0 0

<LLD

<LLD 0

0 0

0 PREDATOR (PCI/KG WET) 4 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS PREDATOR (PCI/KG WET)

GAMMA K-40 4

NA 3190 (2/2)

(3080/3300) 2655 (2/2)

(2090/3220) 3190 (2/2)

(3080/3300)

INDP INDICATOR YORK HAVEN DAM DOWNSTREAM 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 0

0 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS PREDATOR (PCI/KG WET)

SEDIMENT (PCI/KG DRY)

CS-137 GAMMA K-40 MN-54 CO-58 CO-60 CS-134 CS-137 150

<LLD

<LLD 0

7 NA 14232 (5/5)

(9960/17600)

NA

<LLD N A

<LLD NA

<LLD 150

<LLD 180 129 (2/5)

(128/130) 12200 (2/2)

(10200/14200) 17500 (2/2)

(17400/17600)

J2-1 INDICATOR YORK HAVEN DAM 1.5 MILES S OF SITE

<LLD

<LLD 0

0 0

346 (2/2)

(336/355) 346 (2/2)

(336/355)

A1-3 CONTROL SUSQUEHANNA RIVER 0.5 MILES N OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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 362 GAMMA BE-7 28 10 18 (302/310)

(8/204)

NA 88 (24/24)

(56/125) 18 (52/52)

(9/28) 92 (4/4)

(89/94) 20 (50/52)

(8/204) 94 (4/4)

(77/105)

TM-AP-G2-1 INDICATOR BECKER FARM 1.4 MILES SE OF SITE TM-AP-E 1-2 INDICATOR TMI VISITOR'S CENTER 0.4 MILES E OF SITE MN-54 NA

<LLD CO-58 NA

<LLD CO-60 NA

<LLD NB-95 NA

<LLD ZR-95 NA

<LLD CS-134 50

<LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE

<LLD

<LLD 0

0 0

FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS AIR PARTICULATE (E-3 PCIICU.METER)

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

CS-137 60

<LLD

<LLD 0

GAMMA 1-131 362 70

<LLD

<LLD 0

MILK (PCI/LITER) 1-131 115

<LLD 0

SR-89 21 21

<LLD

<LLD 0

0 SR-90 GAMMA K-40 2

0.7 (7/17)

(0.5/1.0)

NA 1270 (92/92)

(915/1440) 0.8 (3/4)

(0.5/1.2) 1259 (23/23)

(1030/1430) 0.8 (1/4) 1343 (23/23)

(1170/1430)

TM-M-E2-2 INDICATOR NISSLEY FARM 1.1 MILES E OF SITE TM-M-F4-1 INDICATOR TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE 115 0

CS-134 15

<LLD

<LLD 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

.(F)

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

(LLD)

MEASUREMENTS MILK (PC1/LITER)

CS-137 BA-140 LA-140 SR-90 GAMMA BE-7 18

<LLD 60

<LLD 15

<LLD

<LLD 0

<LLD

<LLD 0

0 VEGETATION (PCI/KG WET) 20 26 10 20.5 (9/10)

(2.2/49.4)

NA

,659 (6/13)

(200/1690) 18.2 (9/10)

(3.4/37.9) 725 (5/13)

(332/1400) 3470 (13/13)

(1990/5650) 21.6 (8/9)

(2.2/49.4) 725 (5/13)

(332/1400) 4074 (9/9)

(2130/5300)

H 1-2 INDICATOR RED HILL MARKET 1.0 MILES SSE OF SITE B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE 0

0 0

K-40 NA 3773 (13/13)

(2130/5300)

H 1-2 INDICATOR RED HILL MARKET 1.0 MILES SSE OF SITE 1-131 60

<LLD

<LLD 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2009 Name of Facility: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

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

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS.

LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS VEGETATION (PCI/KG WET)

CS-134 CS-137 60

<LLD 80

<LLD

<LLD 0

DIRECT RADIATION TLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.)

352 NA 4.5 (308/308)

(2.7/7.7) 5.1 (44/44)

(4.1/7.0) 7.3 (4/4)

(6.9/7.7)

H8-1 INDICATOR SAGINAW ROAD 7.4 MILES SSE OF SITE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)

Intentionally left blank

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

TABLE B-i:

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

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

YY Radial Zone of Sampling Location in miles.

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

B-1

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2009 Sample Medium Station Map Distance Code Number (miles)

Azimuth Description AQS ID APAIID SW ID ID ID ID ID ID ID FP ID ID ID ID ID AQF ID ID M

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

ID ID A1-3 A1-4 A3-1 A3-2 A5-1 A9-3 B1-1 B1-2 B2-1 B5-1 B10-1 B10-2 C1-1 C1-2 C2-1 C5-1 C8-1 Control D1-1 D1-2 D2-1 D2-2 D6-1 D15-1 E1-2 E1-4 E2-2 E2-3 E5-1 E7-1 F1-1 F1-2 F1-3 F1-4 F2-1 F4-1 F5-1 F10-1 F25-1 G1-2 G1-3 G1-5 G1-6 G2-1 G2-4 G5-1 G10-1 G15-1 G15-2 G15-3 3

9.2 2

2 2

3 2

2 3

2 2

3 10 0.7 0.3 1.5 4.7 7.1 2.7 2.7 4.4 8.0 0.6 0.4 1.9 4.9 1

0.2 1

0.5 2

1.1 2

1.6 3

5.2 3

10.8 1

0.4 1

0.2 2

1.1 2

2.0 2

4.7 1

0.5 1

0.3 3590 N of site off north tip of TMI in Susquehanna River 60 N of Reactor Building on W fence adjacent to North Weather Station, TMI 3570 N of site at Mill Street Substation 3560 N of site at Swatara Creek, Middletown 30 N of site on Vine Street Exit off Route 283 20 N of site at Duke Street Pumping Station, Hummelstown 25',

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 21' NNE of site at intersection of West Areba Avenue and Mi!l Street, Hershey 310 NNE of site at Milton Hershey School, Hershey 37' 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 48' NE of site at Schenk's Church on School House Road All locations where finfish are collected above Dock St.

Dam, Harrisburg 76' 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.)

66' ENE of site off Beagle Road 640 ENE of site along Route 241, Lawn 970 E of site at TMI Visitor's Center 970 E of Reactor Building on top of dike, TMI 96' E of site at farm on Pecks Road 97' E of site along Hillsdale Rd. (N of Creek Rd.)

820 E of site at intersection of North Market Street (Route 230) and Zeager Road 880 E of site along Hummelstown Street, Elizabethtown 1170 ESE of site near entrance to 500 kV Substation 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI 1120 ESE of site in 500 kV Substation 1220 ESE of Reactor Building on top of dike, TMI 1190 ESE of site along Engle Road 1040 ESE of site at farm on Turnpike Road 1090 ESE of site along Amosite Road 1120 ESE of site along Donegal Springs Road, Donegal Springs 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster 1450 SE of site along Route 441 S 1300 SE of Reactor Building on top of dike, TMI 143' SE of Reactor Building on top of dike, TMI 1390 SE of Reactor Building on top of dike, TMI 1260 SE of site at farm on Becker Road 1380 SE of site on Becker Road 1310 SE of site at intersection of Bainbridge and Risser Roads 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,AI ID ID M

ID ID 3

2 2

2 3

6.7 0.5 0.2 0.6 0.2 1.3 3.2 4.7 9.4 ID 3

22 ID ID ID ID AI,AP,M ID ID ID ID DW DW 2

2 2

3 3

0.7 0.2 0.3 0.3 1.4 1.7 4.8 9.7 14.4 13.3 15.7 B-2

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2009 Sample Medium ID FP APAIID ID ID ID AQF ID SW ID AQS ID ID ID ID EW AQS Station Map Code Number H1-1 1

H1-2 1

H3-1 2

H5-1 2

H8-1 3

H15-1 3

Indicator J1-1 1

J11-2 1

J1-3 1

J2-1 2

J3-1 2

J5-1 2

J7-1 3

J15-1 3

K1-1 1.

K1-3 1

K1-4 1.

K2-1 2

K3-1 2

K5-1 2

K8-1 3

K15-1 3

Distance (miles~

ID ID ID ID ID ID M

ID ID ID ID ID ID ID Azimuth Description 0.5 1670 SSE of site, TMI 1.0 151*

SSE of site along Route 441, Red Hill Market 2.2 1600 SSE of site in Falmouth-Collins Substation 4.1 158' SSE of site by Guard Shack at Brunner Island Steam Electric Station 7.4 163' SSE of site along Saginaw Road, Starview 13.2 157' 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 0.8 176' S of site, TMI 0.5 1880 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River 0.3 1890 S of Reactor Building just S of SOB, TMI 1.4 1790 S of site in Susquehanna River just upstream of the York Haven Dam 2.7 1790 S of site at York Haven/Cly 4.9 181' S of site along Canal Road, Conewago Heights 6.5 176' S of site off of Maple Street, Manchester 12.6 183' S of site in Met-Ed York Load Dispatch Station 0.2 2100 On site at RML-7 Main Station Discharge. Building 0.2 2120 SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River 0.2 209' SSW of Reactor Building on top of dike behind Warehouse 2, TMI 1.2 2000 SSW of site on S Shelley Island 2.0 2060 SSW of site along Rt. 262, N of Cly 4.9 2020 SSW of site along Conewago Creek Road, Strinestown 7.5 1960 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View 12.8 2030 SSW of site behind McDonald's and next to child care center, Weiglestown 14.4 205' SSW of site at farm along S Salem Church Rd, Dover 0.1 2360 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI 0.5 2210 SW of site on Beech Island 1.8 2240 SW of site along Route 262 4.1 2280 SW of site at intersection of Stevens and Wilson Roads 8.0 2250 SW of site along Rohlers Church Rd., Andersontown 11.8 2260 SW of site on W side of Route 74, rear of church, Mt.

Royal 0.1 2500 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI 0.4 2520 WSW of site on E side of Shelley Island, Lot #157 1.3 2560 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro 4.3 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown 8.7 2430 WSW of site along Alpine Road, Maytown 0.7 274' W of site on W side of Shelley Island, between lots #13 and #14 0.1 2740 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI 1.2 261 W of site at Goldsboro Marina 5.0 2680 W of site off of Old York Road along Robin Hood Drive 7.7 2620 W of site along Route 382, 1/2 mile north of Lewisberry 10.4 2750 W of site at intersection of Lisburn Road and Main Street, Lisburn 0.4 303' WNW of site on Shelley Island ID APAIID K15-3 1-1i L1-2 L2-1 L5-1 L8-1 L15-1 M1-1 M1-2 M2-1 M5-1 M9-1 NI-i Ni-3.

N2-1 N5-1 N8-1 N15-2 P1-1 3

2 2

3 3

2 2

3 2

2 3

1 ID ID ID ID ID ID ID ID ID B-3

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2009 Sample Medium Station Map Distance Code Number (miles)

Azimuth Description ID ID M

ID ID ID ID ID ID SW,DW,ID APAIID P1-2 P2-1 P4-1 P5-1 P8-1 Q1-1 Q1-2 02-1 Q5-1 Q9-1 Q15-1 R1-1 R1-2 R3-1 R5-1 R9-1 R15-1 2

2 2

3 2

2 3

3 3

1 22 2.0 3.7 5.0 8.0 0.5

'0.2 1.9 5.0 8.5

,13.4 0.2

.0.7 2.6 4.9 1

0.1 2920 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 283' WNW of site along Route 262 295 WNW of site at farm on Valley Road 2840 WNW of site at intersection of Valley Road (Route 262) and Beinhower Road 2920 WNW of site along Evergreen Road, Reesers Summit 317' NW of site on E side of Shelley, Island 321' NW of Reactor Building on fence W of Warehouse 1, TMI 3100 NW of site along access road along river 317' NW of site along Lumber Street, Highspire 310*

NW of site at the Steelton Water Company 3090 NW of site behind West Fairview Fire Dept. Social Hall (abandoned) 3350 NNW of Reactor Building along W fence, TMI 3340 NNW of site on central Henry Island 341' NNW of site at Crawford Station, Middletown 339' NNW of site at intersection of Spring Garden Drive and Route 441 3410 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights 3320 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park ID ID ID ID ID ID 3

8.0 3

11.2 IDENTIFICATION KEY ID

= Immersion Dose (TLD)

SW = Surface Water Al

= Air Iodine AP = Air Particulate FP

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

EW DW M

AFT AQS Effluent Water

= Drinking Water Milk (Cow)

= Finfish

= Aquatic Sediment B-4

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2009 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-TIMI-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 1-131 in milk by anion exchanae Effluent Gross Beta Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in Water from a continuous radiological analysis (Three Mile Island various matrices water compositor.

Nuclear Station)

Env. Inc., W(DS)-wt 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, 2009 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

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

Nuclear Station)

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

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

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

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

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

Fish Gamma Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet)

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

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

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

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2009 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 I gamma spectroscopy

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2009 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Vegetation Strontium-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) 80

Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2009 B-9

I. Locatobns ae listed by station code.:

2. Loctions are based on GPS readingseferenced to a midpoint Letvecn TM-I and Tl,-2;~~>

3. Bacemap in PA St'Iteplanie So6ut, !JAD27, feel I

I

'hWes Figure B-2 Environmental Sampling, Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2009 B-10

2>Iccalices Lare ed m" COS r~eadirqa referrrrcd io a'midpoint benelTP&1 end Th-2.

4 U

1 aim PAh Stateplare Seuh. N4AD2?.,

feet I

Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2009 B-11

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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/30/08 - 02/03/

02/03/09 - 03/03/

03/03/09 - 03/31/

03/31/09 - 04/28/

04/28/09 - 06/02/

06/02/09 - 06/30/

06/30/09 - 07/28/

07/28/09 - 08/31/

08/31/09 - 09/29/

09/29/09 - 11/03/

11/03/09 - 12/01/

12/01/09 - 12/28/

J1-2 Q9-1 09 09 09 09

/09 09 09 09 09 09

'09

/09

< 179 2880 +/- 354 7540 +/- 808

< 159 1680 +/- 204 431 +/- 96 9250 +/- 958 227 +/- 137 1820 +/- 236 2340 +/- 292

< 168

< 170 3271 +/- 6632 (1)

(1)

< 179

< 187

< 190

< 159

< 113

< 111

< 125 (1)

< 198

< 181 (1)

< 179

< 171 (1)

< 169 (1)

MEAN TABLE C-I.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/30/08 -

02/03/09 02/03/09-03/03/09 03/03/09 -

03/31/09 03/31/09 04/28/09 04/28/09 -

06/02/09 06/02/09-06/30/09 06/30/09-07/28/09 07/28/09 08/31/09 08/31/09-09/29/09 09/29/09 -

11/03/09 11/03/09 -

12/01/09 12/01/09 -

12/28/09 A3-2

< 0.6 1.8 +/- 0.6

< 0.5 1.4 +/- 0.5

< 0.5

< 0.6

< 0.8

< 0.7

<0.7

< 0.7

< 0.5 (1)

MEAN 1.6 +/- 0.6

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

TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 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 J1-2 12/30/08 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 MEAN

- 02/03/09

- 03/03/09

- 03/31/09

- 04/28/09

- 06/02/09

- 06/30/09

- 07/28/09

- 08/31/09

- 09/29/09

- 11/03/09

- 12/01/09

- 12/28/09

- 02/03/09

- 03/03/09

- 03/31/09

- 04/28/09

- 06/02/09

- 06/30/09

- 07/28/09

- 08/31/09

- 09/29/09

- 11/03/09

- 12/01/09

- 12/28/09

<3

<4

<2

<1

<4

<2

<4

<2

<3

<1

<3

<2

<1

<4

<1

<2

<4

<2

<3

<1

<2

<1

<5

<4

<2

<5

<2

<3

<1

< 4'

<3

<2

<1

<4

<1

<2

<4

<2

<3

<1

<5

<2

<7

<9

<5

< 10

<6

<7

<3

<4

<8

<4

<11

<3

<7

<4

<6

<3

<4

<7

<5

<8

<4

<2

<4

<2

<4.

<2

<1

<2

<1

<2

<1

<5

<9

<5

<9

<4

<10

<6

<7

<4

<2

<4

<2

<4

<2

<3

<2

<4

<2

<6

<9

<5

<10

<5

<2

<4

<3

<4

<2

<3

<6

<3

<6

<3

<1

<3

<1

<3

<1

<3

<4

<2

<1

<5

<4

<2

<6

<2

<3

<1

<3

<2

<1

<4

<1

<2

<4

<2

<3

<1

< 26

< 32

< 21

< 19

< 25

< 31

< 22

< 19

28

< 16

< 20

< 15

< 27

< 24

21

< 16

< 21

26

<15

< 23

< 20

<13

< 19

< 11

<9

<11

<6

<4

<12

<8

<6

<8

.< 5

<7

<5

<8

<7

< 6

<12

<5

<8

<5

<7

<3 Q

Q9-1 12/30/08 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09

<8

<7

<5

<2

<8

<9

<4

<6

<9

<4

<7

<3

<2

<1

<4

<5

<1

<3

<5

<2

<3

<1

<7

<6

<4

<2

<9

<8

<3

<4

<9

<4

<5

<2

<4

<3

<2

<1

<5

<2

<5

<2

<3

<1

<6

<4

<2

<7

<8

<3

<4

<9

<3

<6

<2

<3

<2

<1

<4

<1

<2

<5

<2

<3

<1 MEAN

TABLE C-II.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 I

-,"I izIJUIUO 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 UzlIUa.IU 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 12/28/09 4.2 +/- 1.6 3.3 +/- 1.6 2.6 +/- 1.5 2.7 +/- 1.5 3.8 +/- 1.6 4.2 +/- 2.4

< 2.6

< 2.9 3.4 +/- 1.7 2.9 + 1.7 3.2 _ 1.6

< 2.5 2.7 +/- 1.5 2.7 +/- 1.5

< 1.9

< 2.0

< 2.1

< 2.6 3.1 +/- 1".8

< 2.9 4.1 +/- 1.8 (1)

< 2.5 2.8 +/- 1.6

< 2.4 3.1 +/- 1.2 2.6 +/- 1.4 2.6 +/- 1.4 2.0 +/- 1.3 2.3 +/- 1.4

< 2.0

< 2.5

< 2.4

< 2.8 2.5 +/- 1.6

< 2.4 5.5 +/- 2.0

< 2.3 2.9 +/- 2.5 MEAN 3.3 +/- 1.2 TABLE C-II.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 Q9-1 I LUlU/UO 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 UZlUJlUJ 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09.

08/31/09 09/29/09 11/03/09 12/01/09 12/28/09

< 0.5

< 0.7

< 0.8

< 0.5

< 0.8

< 0.6

< 0.8

< 0.6

< 0.9

< 0.5

< 0.6

< 0.7

< 0.9

< 0.5

< 0.6

< 0.5

< 0.9

< 0.7

< 0.6

< 0.7

< 0.8

< 0.9

< 0.8

< 0.5

< 0.6

< 0.7

< 0.5

< 0.7

< 0.6

< 0.7

< 0.6 MEAN TABLE C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION pp'Rnln G15-2 G15-3 Q9-1 PERIOD 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09

ULIUcfIU,

- 03/03/09

- 03/31/09

- 04/28/09

- 06/02/09

- 06/30/09

- 07/28/09

- 08/31/09

- 09/29/09 11/03/09 12/01/09 12/28/09

< 180

< 192

< 189

< 157

< 112

< 111

< 122

< 182

< 187

< 176

< 163

< 171

< 181

< 189

< 183

< 161

< 112

< 110 448 +/- 156

< 180

< 185

< 176

< 168

< 171 J

182 187 190 158 111 113 115 197 182 175 169 169 MEAN 448

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3

TABLE C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 PERIOD Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 G15-2 12/30/08 - 02/03/09

< 2 02/03/09 - 03/03/09

< 4 03/03/09 - 03/31/09

< 2 03/31/09 - 04/28/09

< 1 04/28/09 - 06/02/09

< 5 06/02/09 - 06/30/09

< 4 06/30/09 - 07/28/09

< 2 07/28/09 - 08/31/09

< 2 08/31/09 - 09/29/09

< 4 09/29/09 - 11/03/09

< 1 11/03/09

- 12/01/09

< 3 12/01/09

- 12/28/09

< 2

<2

<4

<2

<1

<5

<4

<2

<4

<2

<4

<3 41 MEAN

<4

<2

<3

<7

<4

<6

<5

<2

<4

<2

<1

<2

<12

<7

<11

<9

<5

<10

<5

<2

<4

<6

<2

<3

<9

<6

<9

<3

<2

<3

<7

<3

<6

<2

<5

<2

<4

<11

<4

<8

<5

<2

<4

<2

<1

<2

<7

<4

<10

<11

<5

<11

<5

<2

<4

<5

<2

<5

<9

<4

<9

<5

<2

<4

<8

<4

<7

<2

<1

<2

<3

<5

<8

<2

<4

<1

<2

<5

<9

<5

<6

<2

<4

<3

<5

<6

<9

<2

<3

<4

<6

<3

<5

<2

<4

<6

<8

<2

<4

<1

<2

<4

<6

<7

<9

<2

<4

<3

<5

<4

<7

<2

<4

<3

<6

<1

<2

<4

<2

<1

<5

<2

<4

<1

<3

<2

<5

<2

<1

<4

<5

<2

<4

<2

<3

<1

<2

<13

<4

<26

< 11

< 2

< 19

<.7

<1

<13

<4

<6

<26

<9

<4

<30

< 11

<2

<24

< 7

<2

<21

<8

<5

<22

<6

<2

<11

<3

<22

<7

<2

<24

<8 G15-3 12/30/08

- 02/03/09

< 2 02/03/09 - 03/03/09

< 4 03/03/09 - 03/31/09

< 2 03/31/09 - 04/28/09

< 1 04/28/09 - 06/02/09

< 4 06/02/09 - 06/30/09

< 5 06/30/09 - 07/28/09

< 2 07/28/09 - 08/31/09

< 2 08/31/09 - 09/29/09

< 5 09/29/09 - 11/03/09

< 2 11/03/09

- 12/01/09

< 3 12/01/09 - 12/28/09

<1

<2

<5

<2

<1

<4

<2

<3

<4

<2

<3

<1

< 2

< 15

<5

<31

<8

<2

<23

<7

<1

<14

<5

<4

<20

<7

<6.

<31

<11

<2

<22

<7

<3

<23

<9

<5

<19

<6

<2

<16

<5

<3

<21

<7

<1

<11

<4 MEAN

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 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 Q9-1 12/30/08 -

02/03/09 -

03/03/09 -

03/31/09 -

04/28/09 -

06/02/09 -

06/30/09 -

07/28/09 -

08/31/09 -

09/29/09 -

11/03/09 -

12/01/09 -

02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09

<4

<2

<1

<5

<3

<2

<4

<2

<1

<5

<3

<2

<3

<2

<3

<1

< 10

<4

<2

<9

<5

<6

<7

<5

<6

<3

<5

<2

<1

<5

<3

<2

<3

<2

<1

<7

<4

<7

<4

<29

<11

<6

<9

<4

<5

<30

<3

<2

<3

<1

<2

<18

< 2

< 1

< 2

< 1

< 15

<11

<5

<9

<5

<28

<6

<2

<3

<2

<3

<14

<4

<2

<4

<2

<22

<5

<3

<5

<2

<24

<8

<4

<7

<4

<21

<9

< 11

<6

<5

<8

<7

<9

<7 11/03/09

< 2 12/01/09

< 2 12/28/09

< 1

<5

<2

<4

<2

<17

<6

<3

<5

<2

<3

<18

<6

<2

<1

<2

<1

<12

<4 i~

(J*

MEAN

TABLE C-II1.1 CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION K1-1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD GROSS BETA 1-131 H-3 SR-89 SR-90 12/30/08 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 12/28/09 4.8 4.5 4.0 3.6 5.9 4.4 5.2 3.3 6.1 6.0 3.1

< 2.3

+/- 1.7

+/- 1.6

+/- 1.9

+/- 2.0

+/- 2.1

+/- 2.0

+/- 1.6

<0.4

< 0.8

< 0.5

< 0.6

< 0.7 (1)

< 0.6

< 0.7

< 0.6 (1)

< 0.5

< 183 19800 +/- 2040 64700 +/- 6500

< 156 38300 +/- 3850 5140 +/- 545 101000 +/- 10100 2970 +/- 346 17700 +/- 1790 20700 +/- 2120

< 164

< 170

< 1.8

< 2.2

< 0.5

< 0.5 MEAN 4.6 +/- 2.1 33789 +/- 67144

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-6

TABLE C-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 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 K1-1 12/30/08 - 02/03/09

<4

<3

<8

<4

<6

<4

<6

<4

<3

<26 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 12/28/09

<2

<1

<5

<4

<1

<2

<5

<2

<3

<1

<3

<2

<1

<5

<4

<2

<5

<2

<3

<2

<5

<4

<3

< 11

< 10

<4

<5

<8

<4

<6

<3

<2

<1

<6

<5

<2

<4

<2

<3

<1

<5

<3

<2

< 10

<8

<3

<4

<9

<4

<5

<2

<3

<5

<3

<19

<2

<3

<1

<2

<18

<1

<2

<1

<20

<6

<9

<6

<27

<4

<8

<4

<26

<2

<3

<1

<17

<3

<4

<2

<24

<5

<9

<5

<6

<24

<2

<4

<2

<16

<3

<5

<2

<3

<17

<2

<3

<1

<12

<8

<6

<5

<9

<8

<6

<8

<4

<6

<4 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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD H-3 Mn-54 Co-58 Fe-59 Co-60

Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 EDCB 02/03/09 04/28/09 07/28/09 11/03/09

- 03/31/09

- 06/30/09

- 09/29/09

- 12/28/09

< 182

< 111

< 179

172

<1

<2

<3

<1

<4

<5

<8

<4

<7

<4

<9

<4

<3

<9

<8

<7

<2

<4

<5

<3

<8

<7

<8

<1

<15

<3

<4

<29

<4

<21

<3

<4

<29

<4

< 11

<6

<9 MEAN 00

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

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD INDP PREDATOR 06/12/09 10/22/09 Sr-90

<4

<5 MEAN INDB BOTTOM FEEDER 06/12/09.

11/02/09

<4

<3 MEAN BKGP PREDATOR 06/11/09 11/03/09

<2

<3 MEAN BKGB BOTTOM FEEDER 06/11/09 11/03/09 MEAN

<3

<5 C-9

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

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 BKGB BOTTOM FEEDER 06/11/09 11/03/09 MEAN BKGP PREDATOR 06/11/09 11/03/09 MEAN INDB BOTTOM FEEDER 06/12/09 11/02/09 MEAN INDP PREDATOR 06/12/09 10/22/09 2820 +/- 709

< 33 2730 +/- 861

< 60 2775 +/- 127 3220 +/- 796

< 44 2090 +/- 680

<34 2655 +/- 1598 3220 +/- 661

< 35 3120 +/- 777

< 30 3170 +/- 141 3080 +/- 588

< 39 3300 +/- 1220

< 49

< 36

< 59

< 49

108

< 34

< 57

< 58

127

< 33

< 61

<34

< 65

< 37

< 49

< 97

< 98

< 47

< 35

< 91

< 99

< 38

< 36 53

< 43 0

< 49

< 41

< 80

< 74

< 37

< 42

< 82

92

< 35

< 43

< 37

< 48

< 43

< 56

104

174

< 37

66

< 89

< 126

< 35

< 52

< 41

< 61 MEAN 3190 +/- 311

TABLE C-VI.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA STC COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-134 PERIOD A1-3 06/11/09 11/23/09 MEAN EDCB 11/23/09 MEAN J2-1 06/11/09 11/23/09 MEAN K1-3 06/11/09 11/23/09 MEAN 14200 10200 12200 14800 14800 17600 17400 17500 11400 9960 10680

+/- 1580

+/- 1470

+/- 5657

+/- 2010

+/- 1810

+/- 1840

+/- 283

+/- 1420

+/- 2050

+/- 2036

< 77

< 72

< 113

< 94

< 78

< 79

< 102

< 69

< 80

< 81

< 58

< 61

< 70 Cs-137 336 +/- 93 355 +/- 90 346 +/- 27

< 117

< 109

< 103

< 94

< 73

< 92

< 74

< 82

< 67

< 73

< 70

< 98

< 99 128 +/- 78 128 130 +/- 74

< 93

< 91

< 80

< 116

< 91 130

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

TABLE C-VII.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION. 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUPI I

GROUPI 11 GROUP III COLLECTION E1-2 F1-3 A3-11 G2-11 1-3-1 M2-1 Q15-1 PERIOD 12/31/08 01/07/09 19 +/- 5 23 +/- 6 13 +/- 5 17 +/- 5 14 +/- 5 17 +/- 5 22 +/-6 01/07/09 -01/14/09 18 +/-5 15 +/-5 18 +/-5 19 +/-5 18 +/-5 19 +/-5 18+/-5 01/14/09 -01/21/09 27 +/-6 21 +/-5 19 +/-5 21

+/- 5 21 +/-6 24 +/-6 24+/-6 01/21/09

-01/28/09 20 +/- 5 23 +/-5 24 +/-6 20 +/- 5 18 +/-5 21 +/- 5 19+/-5 01/28/09-02/04/09 21 +/-5 20 +/-5 23 +/-5 27 +/-5 24 +/-5 25 +/-5 22+/-5 02/04/09-02/11/09 27 +/-6 30 +/-6 26 +/-5 23 +/-5 27 +/-6 22 +/-5 27 +/-6 02/11/09

-02/18/09 9 +/- 5 8 +/- 5

< 7 11 +/- 5 11 +/- 5 8 +/- 5 14 +/- 5 02/18/09

-02/25/09 16 +/- 5 19 +/- 5 16 +/- 5 17 +/- 5 15 +/- 5 17 +/- 5 18 +/- 5 02/25/09-03/04/09 15 +/-5 26 +/-6 22 +/-5 17 +/-5 20 +/-5 20 +/-5 19 +/-5 03/04/09-03/11/09 16 +/-5 20 +/-5 20 +/-6 20 +/-6 20 +/-5 20 +/-6 22+/- 6 03/11/09

-03/18/09 18 +/- 5 25 +/- 6 23 +/- 6 23 +/- 6 27 +/- 6 19 +/- 5 25 +/- 6 03/18/09

-03/25/09 20 +/- 5 22 +/-5 20+/-t5 17 +/- 5 16 +/-5 17 +/- 5 18+/- 5 03/25/09

-04/01/09 12 +/- 5 10 +/- 4 11 +/- 5 14 +/- 5 11 +/- 5 12 +/- 5 13 +/- 5 04/01/09

-04/08/09

< 19 (1)

<6 14 +/- 5 11 +/- 5 10 +/- 5 14 +/- 5 9 +/- 5 04/08/09

-04/16/09 (1) 20 +/- 5 14 +/- 4 17 +/- 5 17 +/- 5 17 +/- 4 17 +/- 5 04/16/09 -04/22/09 (1) 15 +/- 6 16 +/- 6 12 +/- 6 16 +/- 6 17 +/- 6 15 +/- 6 04/22/09-04/29/09 20 +/-5 15 +/-5

.21 +/-5 26 +/-6 19+/-t5 19 +/-5 17 +/-5 04/29/09

-05/06/09 15 +/- 5 14 +/- 5 16 +/- 5 14 +/- 5 11 +/- 5 19 +/- 5 16 +/- 5 05/06/09

-05/13/09 14 +/- 5 10 +/- 5 12 +/- 5 10 +/- 5 12 +/- 5 16 +/- 5 13 +/- 5 05/13/09

-05/20/09 13 +/- 5 12 +/- 5 13 +/- 5 11 +/- 5 12 +/- 5 12 +/- 5 14 +/- 5 05/20/09

-05/27/09 10 +/- 5 13 +/- 5 13 +/- 5 14 +/- 5 14 +/- 5 11 +/- 5 17 +/- 5 05/27/09-06/03/09 14 +/-5 9 +/-5 12 +/-5 8+/-t4 9+/-t5 13+/-t5 13+/- 5 06/03/09

-06/10/09 14 +/- 5 16 +/- 5 12 +/- 5 12 +/- 5 11 +/- 5 14 +/- 5 16 +/- 5 06/10/09

-06/18/09 9 +/- 4 19 +/- 5 13 +/- 5 11 +/- 5 10 +/- 4 13 +/- 5 14 +/- 5 06/18/09-06/24/09 11 +/-6 13 +/-6

<8

<8.

<8

<8 11+/-6 06/24/09

-07/01/09 17 +/- 6 17 +/- 5 15 +/- 5 14 +/- 5 16 +/- 5 13 +/- 5 18 +/-6 07/01/09

-07/07/09 15 +/- 6 17 +/- 6 15 +/- 6

< 8 12 +/- 6 9 +/- 6 12 +/-6 07/07/09-07/15/09 8 +/-4 10 +/-4 8 +/-4 14 +/-5 32 +/-6 9+/-5 11+/-5 07/15/09

-07/22/09 19 +/- 6 19 +/- 6 17 +/- 5 15 +/- 5 20 +/- 6 17 +/-5 17 +/-5 07/22/09

-07/29/09 21

+/- 5 19 +/- 5 19 +/- 5 16 +/- 5 17 +/- 5 19 +/-5 20 +/-5 07/29/09

-08/05/09 22 +/- 6 20 +/- 6 19 +/- 5 18 +/- 5 18 +/- 5 21 +/-6 17 +/-5 08/05/09

-08/12/09 15 +/- 5 17 +/- 5 15 +/- 5 16 +/- 5 15 +/- 5 20 +/-5 17 +/-5 08/12/09

-08/19/09 21 t 6 21+/-t6 20+/-t6 24 +/- 6 14 +/-5 17+/-6 20+/-6 08/19/09 -08/26/09 12 +/- 5 13 +/-5 16 +/-5 16 +/- 5 21 +/-6 15+/-5 13+/-5 08/26/09-09/02/09 20 +/-5 15 +/-5 19+/-t5 18+/-t5 20 +/-5 18+/-5 23+/-5 09/02/09-09/09/09 22 +/-6.

22 +/-6 20 +/-6 22 +/-6 20 +/-6 15+/-5 24+/-6 09/09/09 -09/16/09 21 +/-6 23 +/-6 20 +/-5 18 +/- 5 18 +/-5 23+/-6 19+/-6 09/16/09 -09/23/09 19 +/- 5 12 +/-5 17 +/-5 15 t 5 19 +/-5 18+/-t5 22+/-t6 09/23/09 -09/30/09 19 +/- 5 13 +/-5 19 +/-5 10 +/- 5 13 +/-5 16 +/-5 17+/- 5 09/30/09

-10/07/09 16 +/- 5 13 +/- 5 18 t 5 13 +/- 5 11 +/- 5 19 +/- 6 18 +/- 6 10/07/09

-10/14/09 13 +/- 5 14 +/- 5 10 +/- 5 14 +/- 5 16 +/- 6 12 +/- 5 13 +/- 5 10/14/09

-10/21/09 14 +/-5 15+/-t5 15+/-t5 16 +/- 5 21 +/-5 17 +/-5 16+/- 5 10/21/09

-10/28/09 18 +/- 5 16 +/- 5 21 +/- 5 23 +/- 5 18 +/- 5 16 +/- 5 18 +/- 5 10/28/09

-11/04/09 18 +/- 5 15 +/- 4 14 +/- 4 16 +/- 4 15 +/- 4 15 +/- 4 13 +/- 4 11/04/09

-11/11/09 28 +/- 6 19 +/- 6 27 +/- 6 24 +/- 6 20 +/- 6 24 +/- 6 26 +/- 6 11/11/09

-11/18/09 12

+/- 5 9 +/- 5 14 +/- 5 14 +/- 5 12 +/- 5 12 +/- 5 15 +/- 6 11/18/09

-11/24/09 19 +/- 5 28 +/- 6 25 +/- 5 204 +/-10 23 +/- 5 23 +/- 5 19 +/- 5 11/24/09

-12/02/09 12

+/- 4 19 +/- 5 18 +/- 5 14 +/-4 16 +/- 5 19 +/- 5 16 +/- 5 12/02/09

-12/09/09 17 +/- 5 14 +/- 5 17 +/- 5 15 +/-5 13 +/- 5 14 +/- 5 15 +/- 5 12/09/09-12/16/09 25+/-t6 22 +/-6 29 +/-6 22+/-6 26 +/-6 23 +/-6 28+/- 6 12/16/09

-12/22/09 26 +/- 6

22 +/- 5 21 +/- 5 22 +/-6 21 +/-5 24 +/-6 20+/- 5 12/22/09

-12/29/09 16 +/- 4 18 +/- 4 21 +/- 4 20 +/- 4 17 +/- 4 26 +/- 5 19 +/- 5 MEAN 17 +/- 10 17 +/-10 18 +/- 9 20 +/- '54 17 +/- 10 17 +/- 9 18 +/- 9

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

TABLE C-VII.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA 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 1lio IIUO 01/28/09 02/25/09 04/08/09 04/22/09 06/03/09 07/01/09 07/29/09 09/02/09 09/30/09 10/28/09 12/02/09 U IILOIUi 02/25/09 04/01/09 04/29/09 06/03/09 07/01/09 07/29/09 09/02/09 09/30/09 10/28/09 12/02/09 12/29/09 10 8

10 15 9

-9 8

12 12 13 9

14 L/

30 26 20 15 19 21 22 23 18 28 26 L I

" I 19 +/- 15 18 +/- 10 18 +/- 5 13 +/- 4 14 +/- 7 16 +/- 10 18 +/- 7 19 +/- 8 15 +/- 3 18 +/- 13 20 +/- 9 12/31/08 01/28/09 02/25/09 04/08/09 04/22/09 06/03/09 07/01/09 07/29/09 09/02/09 09/30/09 10/28/09 12/02/09

- 01/28/09

- 02/25/09

- 04/01/09

- 04/29/09

- 06/03/09

- 07/01/09

- 07/29/09

- 09/02/09

- 09/30/09

- 10/28/09

- 12/02/09

- 12/29/09 13 8

11 10 8

10 8

14 10 10 12 13 24 27 27 17 26 16 32 24 23 23 204 29 19 +/-

19 +/-

18 +/-

15 +/-

14 +/-

13 +/-

16 +/-

18 +/-

16 +/-

27 +/-

21 +/-

6 13 8

5 8

4 11 5

6 7

84 9

12/31/08 01/28/09 02/25/09 04/08/09 04/22/09 06/03/09 07/01/09 07/29/09 09/02/09 09/30/09 10/28/09 12/02/09 01/28/09 02/25/09 04/01/09 04/29/09 06/03/09 07/01/09 07/29/09 09/02/09 09/30/09 10/28/09 12/02/09 12/29/09 18 14 13 9

13 11

.11 13 17 13 13 15 24 27 25 17 17 18 20 23 24 18 26 28 21 +/- 6 20 +/- 12 19 +/- 9 14 +/- 9 15 +/- 4 15 +/- 6 15 +/- 8 18 +/- 7 20 +/- 6 16 +/- 5 18 +/- 10 21 +/- 11 12/31/08 - 12/29/09 8

30 17 +/- 10 12/31/08 - 12/29/09 8

204 18 +/- 28 12/31/08 - 12/29/09 9

28 18 +/- 9

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, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD A3-1 12/31/08 - 04/01/09 04/01/09 - 07/01/09 07/01/09 - 09/30/09 09/30/09 - 12/29/09 Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 MEAN E1-2 12/31/08 04/01/09 07/01/09 09/30/09 MEAN F1-3 12/31/08 04/01/09 07/01/09 09/30/09 MEAN G2-1 12/31/08 -

04/01/09 07/01/09 -

09/30/09 -

MEAN H3-1 12/31/08 -

04/01/09 -

07/01/09 -

09/30/09 MEAN M2-1 12/31/08 -

04/01/09 -

07/01/09 -

09/30/09 -

MEAN Q15-1 12/31/08 -

04/01/09 -

07/01/09 -

09/30/09 -

04/01/09 07/01/09 09/30/09 12/29/09 04/01/09 07/01/09 09/30/09 12/29/09 04/01/09 07/01/09 09/30/09 12/29/09 04/01/09 07/01/09 09/30/09 12/29/09 04/01/09 07/01/09 09/30/09 12/29/09 04/01/09 07/01/09 09/30/09 12/29/09 96 +/- 34 94 +/- 39 89 +/- 40 67 +/- 26 87 +/- 27 99 +/- 28 105 +/- 39 95 +/- 46 77 +/- 24 94 +/- 24 125 +/- 39 75 +/- 38 83 +/- 29 64 +/- 41 87 +/- 53 92 +/- 26 114 +38 86 +/- 45 61 + 30' 88 + 44 80 + 39 123 +/- 41 77 +/- 33 56 +/- 32 84 +/- 56 95 +/- 42 106 +/- 34 96 +/- 43 59 +/- 26 89 +/- 41, 94 +/- 31 92 +/- 40 93 +/- 27 89 +/- 28

<3

<5

<3

<2

<6

<4

<3

<6

<3

<5

<3

<2

<5

<3

<4

<5

<3

<4

<3

<5

<4

<3

<9

<5

<7

<4

<6

<5

<3

<5

<3

<5

<6

<3

<4

<7

<3

<4

<2

<6

<4

<3

<4

<5

<3

<6

<3

<6

<3

<4

<1

<6

<3

<6

<4

<3

<5

<3

<5

<6

<4

<6

<7

<4

<6

<5

<3

<8

<5

<6

<5

<4

<6

<5

<6

<8

<4

<5

<6 8

10 7

7

<4

<3

<4

<6

<3

<15

<5

<.9

<5

<6

<3

<8

<3

<10

<5

<7

<3

<11

<6

<8

<9

< 10

<9

<8

< 11

<8

< 12

< 10

< 11

< 14

<9

<4

<3

<4

<5

<3

<5

<3

<2

<4

<3

<4

<3

<4

<3

<4

<3

<5

<3

<5

<6

<3

<10

<3

<8

<3

<9

<4 MEAN 92 +/- 4 C-14

TABLE C-VII.4 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION AS A RESULT OF THE NOVEMBER 2009 RELEASE RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD Sr-90 Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 E1-2 11/18/09 F1-3 11/18/09 G2-1 11/18/09 11/24/09 11/24/09 11/24/09 (1)

(1)

<8

<2

< 123 127 +/- 86

< 196

< 11

<8 34 +/-12

<9

< 18 52 +/- 19 36

< 13

< 10

< 25

< 16

<9

<10

<8

< 16

< 18

<12

<11

+ 15 346 +/- 38 246 +/- 35 H3-1 11/18/09 - 11/24/09 120 +/- 83

< 12

< 13

< 15

< 23 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

TABLE C-VIII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I

.I GROUPI 11 GROUP III E2-1 F1-3 A3-1 G2-1 1-3-1 M2-1 Q15-1 COLLECTION PFR 100 12/31/08 01/07/09 01/14/09 01/21/09 01/28/09 02/04/09 02/11/09 02/18/09 02/25/09 03/04/09 03/11/09 03/18/09 03/25/09 04/01/09 04/08/09 04/16/09 04/22/09 04/29/09 05/06/09 05/13/09 05/20/09 05/27/09 06/03/09 06/10/09 06/18/09 06/24/09 07/01/09 07/07/09 07/15/09 07/22/09 07/29/09 08/05/09 08/12/09 08/19/09 08/26/09 09/02/09 09/09/09 09/16/09 09/23/09 09/30/09 10/07/09 10/14/09 10/21/09 10/28/09 11/04/09 11/11/09 11/18/09 11/24/09 12/02/09 12/09/09 12/16/09 12/22/09

-01/07/09

-01/14/09

-01/21/09

-01/28/09

-02/04/09

-02/11/09

-02/18/09

-02/25/09

-03/04/09

-03/11/09

-03/18/09

-.03/25/09

-04/01/09

-04/08/09

-04/16/09

-04/22/09

-04/29/09

-05/06/09

-05/13/09

-05/20/09

-05/27/09

-06/03/09

-06/10/09

-06/18/09

-06/24/09

-07/01/09

-07/07/09

-07/15/09

-07/22/09

-07/29/09

-08/05/09

-08/12/09

-08/19/09

-08/26/09

-09/02/09

-09/09/09

-09/16/09

-09/23/09

-09/30/09

-10/07/09

-10/14/09

-10/21/09

-10/28/09

-11/04/09

-11/11/09

-11/18/09

-11/24/09

-12/02/09

-12/09/09

-12/16/09

-12/22/09

-12/29/09

63

29

27

25

< 43

54

50

32

50

15

41

39

65

66 (1)

(1)

47

37

66

66

53

36

30

< 8

53

65

24

59

66

38

22

< 42 (1)

32

33

35

53

62

39

37

52

< 61 (1)

42

50

64

39

17

47

35

57

< 48

55

60

61

22

27

40

42

52

< 48

31

49

14

40

38

63

29

< 43

.< 52

53

< 45

<'65

64

51

35

29

< 8

52

63

24

58

66

38

22

< 41

32

33

35

53

63

39

<36

52

61

41

50

35

39

23

ý47

35

57

48

<,55

< 60

43

64

< 45

< 47

67

51

48

41

44

20

49

40

31

.< 34

48

63

64

61

63

59

< 44

38

69

15

53

65

32

59

61

15

27

< 44

31

34

< 43

54

48

37

22

66

41

19

61

69

38

59

47

50

< 64 (1)

64

68

63

63

29

27

41

43

32

< 49

32

50

<*15

41

38

65

29

< 44

67

< 54

< 46

66

35

52

36

30

53

64

24

59

67

38

22

< 43 (1)

32

21

35

54

63

39

37

52

62 (1)

45

51

64

39

23

26

35

58

49

57

60

63

29

27

41

< 43

53

49

18

50

20

< 41

39

66

63

44

67

54

46

66

65

53

20

30

< 8

54

66

13.

< 67

< 68

38

.< 22

< 43 (1)

33

34

36

30

< 64

39

21

52

63

45

51

64

< 40

23

47

<36

59

27

57

63

43

64

45

< 47

67

51

< 48

32

44

< 8

49

< 40

31

65

< 46

.< 68

64

62

63

64

44

39

34

< 9

53

65

24

67

61

23

27

< 44

32

34

< 44

53

49

37

36

66

< 42

< 45

< 61 (1)

69

39

59

47

50

63

64

69

63

43

64

45

47

68

51

49

< 41

44

20

49

32

32

64

47

65

64

62

63

58

< 44

39

70

15

53

35

14

68

62

17

27

< 45

32

35

44

54

< 49

38

16

67

42

46

62

70

39

59

48

50

65

65

70

< 64 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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARMI K15-3 INDICATOR FARM F4-1 COLLECTION PERIOD 01/07/09 02/04/09 03/04/09 03/18/09 04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09 08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09 D2-1 E2-2 G2-1 P4-1

< 0.7

< 0.5

< 0.6

< 0.5

< 0.6

< 0.7

< 0.5

< 0.6

< 0.8

< 0.4

< 0.8

< 0.7

< 0.5

< 0.8

< 0.7

< 0.6

< 0.7

< 0.5

< 0.6

< 0.8

< 0.5

< 0.6

< 0.5

< 0.6

< 0.4

< 0.6

< 0.7

< 0.6

< 0.9

< 0.6

< 0.7

< 0.5

< 0.6

< 0.5

< 0.6

< 0.7

< 0.6

< 0.8

< 0.5

< 0.8

< 0.5

< 0.6

< 0.9

< 0.7

< 0.6

< 0.5

< 0.4

< 0.5

< 0.6

< 0.7

< 0.5

< 0.8

< 0.6

< 0.4

< 0.8

< 0.9

< 0.4

< 0.6

< 0.8

< 0.6

< 0.7

< 0.6

< 0.7

< 0.6

< 0.8

< 0.6

< 0.8

< 0.4

< 0.6

< 0.7

< 0.4

< 0.7

< 0.4 (1)

< 0.7 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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM I

INDICATOR FARMS COLLECTION PERIOD 01/07/09

- 03/18/09 04/01/09

- 06/24/09 07/08/09

- 09/30/09 10/14/09 - 12/09/09 K15-3 D2-1 E2-2 F4-1 G2-1 SR-90 SR-89 SR-89

< 2.3

< 1.8

< 3.2

< 1.7 SR-90 1.2 +/- 0.4 0.5 +/- 0.3

< 0.7 0.7 +/- 0.3 SR-89

< 2.3

< 2.1

< 3.5

< 3.9 SR-90 0.6 +/- 0.4 0.5 +/- 0.3

< 0.7 1.0.+/- 0.4 SR-89

< 2.4

< 2.6

< 3.0

< 2.5 SR-90

< 0.6 0.8 +/- 0.4

< 0.5

< 0.7 SR-89

< 2.6

< 1.8

< 2.2

< 2.2 P4-1 SR-90

< 0.9 0.8 +/- 0.3

< 0.5

< 0.6 SR-89

< 2.3

< 2.0

< 2.7 SR-90

< 0.7

< 0.4

< 0.4 0.8 +/- 0.5

< 1.7 (1) 0.7 +/- 0.3 0.7 +/- 0.0 MEAN 0.8 +/- 0.7 0.7 +/- 0.6 0.8 +/- 0.0 0.8 +/- 0.0 0.8 +/- 0.0 00

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION

TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD D2-1 01/07/09 02/04/09 03/04/09 03/18/09 04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09

.08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09 MEAN E2-2 01/07/09 02/04/09 03/04/09 03/18/09 04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09 08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1260 +/- 83 1280 +/- 106 1090 +/- 137 1220 +/- 94 1290 +/- 113 1180 +/- 106 1270 +/- 41 1310 +/- 39 1220 +/- 112 1300 +/- 140 1280 +/- 50 1160 +/- 101 1270 +/- 132 1160 +/- 143 1270 +/- 118 1310 +/- 110 1140 +/- 154 1240 +/- 79 1270 +/- 151 1300 +/- 96 1220 +/- 98 (1)

(1)

<3

<4

<6

<4

<1

<5

<2

<3

<6

<5

<4

<5

<6

<3

<6

<4

<3

<4

<8

<4

<5

<2

<1

<5

<6

<2

<4

<6

<7

<5

<7

<3

<7

<5

<4

< 33

< 30

< 42

< 33

< 42

< 33

41

< 33

< 24

< 27

< 37

< 29

< 41

< 32

< 30

< 22

< 28

< 19

<9

<8

< 10

< 11

<7

<,14

<9

< 12

<8

<9

<8

< 10

<8

< 15

<9

<7

<8

<7

<5 1240 +/- 124 1340 1290 1430 1340 1290 1220 1390 1370 1240 1240 1350 1210 1390 1340 1430 1420 1420 1340 1420 1270 1230 1390 1280

+/- 80

+/- 129

+/- 145

+/- 96

+/- 149

+/- 109

+/- 51

+/- 44

+/- 134

+/- 174

+/- 43

+/- 135

+/- 117

+/- 150

+/- 156

+/- 133

+/- 120

+/- 92

+/- 166

+/- 114

+/- 120

+/- 136

+/- 100

<3

<5

<6

<4

<6

<4

<2

<1

<5

<6

<1

<6

<4

<6

<5

<3

<5

<4

<3

<7

<4

<7

<5

<2

<6

<8

<2

<6

<5

<6

<8

<5

<4

<6

<5

< 34

< 46

< 39

< 31

< 44

< 47

< 46

< 29

< 37

< 35

23

48

< 26

< 45

48

< 43

< 21

< 23

< 25

< 28

21

< 36

< 33

<11

<9

<11

<12

<15

< 13

<8

<11

< 14

<7

< 15

<8

< 11

< 13

< 14

<8

< 10

<7

< 10

<9 1332 +/- 147 (1) SEE PROGRAMS CHANGES SECTION FOR EXPLANATION C-19

TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD F4-1 01/07/09 02/04/09 03/04/09 03/18/09 04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09 08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09 MEAN G2-1 01/07/09 02/04/09 03/04/09 03/18/09 04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09 08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1250 +/- 81 1360 +/- 125 1420 +/- 134 1360 +/- 108 1410 +/- 147 1410 +/- 112 1330 +/- 51 1330 +/- 55 1340 +/- 126 1260 +/- 142 1390 +/- 46 1370 +/- 126 1240 +/- 122 1240 +/- 148 1380 +/- 136 1410 +/- 119 1170 +/- 117 1390 +/- 77 1360 +/- 156 1340 +/- 101 1430 +/- 117 1390 +/- 126 1300 +/- 102 1343 +/- 138 1420 +/- 92 1440 +/- 145 1280 +/- 147 1300 +/- 121 1060 +/- 135 1380 +/- 122 1190 +/- 46 1280 +/- 43 1000 +/- 131 966 +/- 159 1230 +/- 43 1180 +/- 132 1010 +/- 116 1160 +/- 115 1140 +/- 126 934 +/- 122 915 +/- 137 1070 +/- 76 993 +/- 148 1030 +/- 82 1360 +/- 124 1310 +/- 137 1050 +/- 97 1161 +/- 326

< 3

<4

<5

<4

<2

<5

<6

<2

<5

<4

<5

<4

<5

<3

<7

<4

<5

<4

<3

<5

<6

<4

<5

<2

<3

<4

<6

<2

<5

<4

<5

<6

<5

<6

<3

<8

<4

<6

<5

<4

< 37

< 42

< 35

< 41

< 40

< 43

< 48

< 49

< 31

< 25

29

< 50

< 21

38

< 38

< 36

< 24

< 21

38

< 28

< 25

36

< 33

< 10

< 13

<9

< 11

< 13

< 12

< 15

< 10

<8

< 12

<6

< 11

< 12

<9

<7

<6

<10

<8

<7

<13

< 10

<4

<5

<3

<5

<2

<5

<2

<5

<4

<.3

<6

<5

<6

<3

<6

<4

<5

<6

<4

<.3

<6

<7

<4

<7

<5

<2

<7

<2

<6

<4

<3

<6

<4

<7

<4

<6

<5

< 43

46

< 44

< 36

< 48

< 45

< 37

< 39

29

27

< 50

< 19

< 23

< 36

< 37

< 31

< 22

< 35

< 25

< 45

< 35

< 11

13

< 13

< 10.

< 15

< 12

< 11

< 14

<9

<8

< 12

<6

<7

< 14

< 10

<8

<7

<9

<7

<6

< 12

< 11 C-20

TABLE C-IX.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD K15-3 01/07/09 02/04/09 03/04/09 03/18/09 04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09 08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09 MEAN P4-1 01/07/09 02/04/09 03/04/09 03/18/09

'04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09 08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1340 1310 1200 1200 1280 1370 1320 1380 1360 1030 1280 1060 1430 1240 1200 1030 1380 1260 1210 1390 1250 1170 1270

+/- 104

+/- 133

+/- 140

+/- 93

+/- 112

+/- 122

+/- 56

+/- 54

+/- 130

+/- 166

+/- 89

+/- 131

+/- 130

+/- 89

+/- 150

+/- 100

+/- 142

+/- 73

+/- 117

+/- 115

+/- 98

+/- 121

+/- 89

<3

<5

<4

<5

<4

<2

<5

<6

<3

<5

<4

<7

<4

<5

<3

<6

<5

<4

<3

<4

<6

<5

<2

<6

<9

<3

<6

<4

<7

<4

<5

<3

<7

<5

<4

<5

<4

< 43

< 44

< 31

< 34

38

< 47

< 44

< 39

< 34

< 30

< 53

< 44

< 29

< 26

< 47

< 31

< 28

< 20

< 30.

< 30

< 20

< 38

< 25

< 13

< 11

<8

< 11

< 10

< 15

< 14

10

< 11

< 14

< 13

<10

<9

< 14

<8

<7

<6

<9

<6

< 11

<8 1259 +/- 225 1320 +/- 129 (1) 1260 +/- 117

<6

<7

<44

<5

<6

<43

< 13

< 12 1290 +/- 85 (1) SEE PROGRAMS CHANGES SECTION FOR EXPLANATION 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, 2009 RESULTS IN UNITS OF PCI/KG SR-90 Be-7 STC B10-2 nm COLLECTION PERIOD 07/07/09 Cabbage 07/07/09 Yellow Squash Leaves 07/07/09 Zucchini Leaves 07/29/09 Cabbage 08/12/09 Cabbage 08/12/09 Sweet Corn 08/12/09 Tomatoes 08/12/09 Yellow Squash Leaves 08/12/09 Zucchini Leaves 09/09/09 Broccoli Leaves 09/09/09 Cabbage 09/09/09 Pumpkin Leaves 09/09/09 Red Beets MEAN 28 +/- 3

< 194 38 +/- 3 332 +/- 140 38 +/- 3 440 +/- 154 4 +/-2

<95 9 +/-2

<77

< 67

< 51 17 +/- 2 1400 +/- 124 22 +/- 2 908 +/- 111 3 +/-2

<126 3

< 154 4 +/- 1 547 +/- 131

< 57 18 +/- 28 725 +/- 870 WET +/- 2 SIGMA K-40 4720 +/- 451 5650 +/- 347 4340 +/- 353 2320 +/- 185 1990 +/- 151 3180 +/- 150 2390 +/- 127 4830 +/- 262 3820 +/- 258 2400 +/- 236 2970 +/- 330 4240 +/- 329 2270 +/- 156 3471 +/- 2397 1-131 Cs-134 Cs-1 37

< 56

< 47

< 55

< 40

< 35

< 25

< 54

< 45

< 43

< 56

< 53

< 25

< 17

< 14

<9

<7

<6

<5

< 10

<9

< 12

< 16

< 14

<5

< 19

< 15

< 16

< 10

<8

<7

<5

< 12

< 11

< 13

< 16

< 15

<6

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

TABLE C-X.1 STC COLLECTION PERIOD E1-2 07/29/09 Cabbage 08/12/09 Sweet Corn 08/12/09 Tomatoes 09/09/09 Radishes MEAN CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SR-90 Be-7 K-40 1-131 Cs-134 11 +/- 1

< 119 3100 +/- 235

< 54

< 10

< 59 3090 +/- 136

< 33

< 6

< 43 2140 +/- 118

< 21

< 4

< 111 4060 +/- 257

< 50

< 11 11 +/- 0 3098 + 1568 Cs-137

<10

<6

<5

<11 H11-2 07/07/09 07/07/09 07/07/09 08/12/09 08/12/09 08/12/09 09/09/09 09/09/09 09/09/09 MEAN Cucumber_ Leaves Yellow Squash Leaves Zucchini Leaves Cabbage Neck Pumpkin Leaves Yellow Squash Leaves Cabbage Neck Pumpkin Leaves Zucchini Leaves 49 18 40 11 37 13

<2 3

2 22

+4

+/-2

+/-3

+/-2

+/-3

+/-2 31

+/-1

+/- 36 614 +/- 204

< 146 273 +/- 117

89 770 +/- 97 407 +/- 79

< 66 1690 +/- 158 200 +/- 103 659 +/- 1096 4200 4650

.5300 3610 3350 4050 2130 5290 4090 4074

+/- 404

+/- 473

+/- 400

+/- 220

+/- 212

+/- 195

+/- 168

+/- 309

+/- 357

+/- 1981

<54

< 51

< 46

< 38

< 31

< 27

50

< 54

< 19

< 18

< 15

<9

<8

<6

<7.

<14

<15

< 18

< 20

< 19

< 10

<9

<7

< 14

< 16

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, 2009 RESULTS IN UNITS OF MILLI-ROENTGENS/STD. MONTH STATION CODE Al-4 A3-1 A5-1 A9-3 B10-1 B1-1 61-2 B2-1 B5-1 Cl-i C1-2 C2-1 C5-1 C8-1 D1-1 D1-2 D15-1 D2-2 D6-1 El-2 El-4 E2-3 E5-1 E7-1 F10-1 Fl-1 Fl-2 F1-4 F2-1 F25-1 F5-1 G10-1 G1-2 G1-3 G1-5 G15-1 G1-6 G2-4 G5-1 H1-i H15-1 H3-1 H5-1 H8-1 Ji-1 J11-3 MEAN

+/-2 S.D.

4.3 +/- 0.8 4.4 +/- 1.0 5.3 +/- 0.9 4.1 +/- 0.8 4.6 +/- 0.6 4.4 +/- 0.7.

4.2 +/- 0.7 4.1 +/- 0.5 4.8 +/- 0.5 4.7 +/- 0.7 4.2 +/- 0.8 4.5 +/- 0.6 5.1 +/- 0.6 5.1 +/- 0.7 4.0 +/- 0.8 4.4 +/- 0.3 4.8 +/- 0.8 5.6 +/- 0.9 5.2 +/- 0.9 4.1 +/- 0.6 4.0 +/- 0.8 5.0 +/- 0.7 4.7 +/- 1.1 4.7 +/- 0.4 6.0 +/- 1.3 4.5 +/- 0.6 4.4 +/- 0.6 4.1 +/- 1.0 5.3 +/- 0.6 4.9 +/- 0.7 5.1 +/- 0.5 6.6 +/- 0.8 4.6 +/- 0.8 4.0 +/- 0.5 4.2 +/- 0.6 6.1 +/- 0.8 4.4 +/- 0.3 5.6 +/- 0.2 4.5 +/- 1.2 4.8 +/- 1.4 4.8 +/- 0.5 3.7 +/- 0.3 3.4 +/- 0.6 7.3 +/- 0.8 3.9 +/- 0.5 3.8 +/- 0.6 JAN - MAR 3

0 3.7 +/- 0.5 3.7 +/-- 0.4 4.6 +/- 1.0 3.7 +/- 0.5 4.4 +/- 0.5 3.9 +/-,0.9 3.8 +/- 0.3 3.9 +/- 0.7 4.6 +/- 1.0 4.3 +/- 0.3 4.7 +/- 2.0 4.5 +/- 0.5 5.0 +/- 0.5 4.7 +/- 0.8 3.5 +/- 0.4 4.4 +/- 0.5 4.6 +/- 0.5 5.5 +/- 1.2 4.9 +/- 0.6 3.9 +/- 0.6 3.8 +/- 0.6 4.9 +/- 0.5 4.2 +/- 0.5 4.5 +/- 0.9 5.6 +/- 1.3 4.1 +/- 0.9 4.1 +/- 0.3 3.7 +/- 0.3 5.1 +/- 0.7 4.6 +/- 0.5 4.9 +/- 0.5 6.5 +/- 0.6 4'.1 +/- 0.3 3.8 +/- 0.3 3.9 +/- 0.4 5.6 +/- 0.3 4.2 +/- 0.3 5.7 +/- 0.3 3.9 +/- 1.0 4.4 +/- 0.5 4.9 +/- 0.8 3.6 +/- 0.4 3.0 +/- 0.3 7.6 +/- 0.7 3.6 +/- 0.3 3.5 +/- 0.4 APR - JUN JUL - SEP OCT-DEC 4.6 +/- 0.4 4.4 4.7 +/- 0.3 4.7 5.6 +/- 0.8 5.5 4.6 +/- 0.4 4.0 4.2 +/- 0.5 4.8 4.6 +/- 0.3 4.4 3.9 +/- 0.5 4.4 3.9 +/- 0.4 4.2 4.6 +/- 0.9 5.0 4.5 +/- 0.8 4.9 3.7 +/- 0.4 4.0 4.1 +/- 0.2 4.8 4.8 +/- 1.2 5.4 4.8 +/- 0.5 5.5 3.7 +/- 0.3 4.2 4.2 +/- 0.8 4.5 4.3 +/- 0.3 5.2 5.1 +/- 0.6 6.2 4.8 +/- 0.3 5.8 3.9 +/- 0.5 4.5 3.6 +/- 0.7 4.2 4.6 +/- 0.5 5.4 4.4 +/- 0.5 5.4 4.6 +/- 0.5 4.9 (1) 6.7 4.6 +/- 0.5 4.7 4.2 +/- 0.3 4.3 3.7 +/- 0.3 4.3 5.5 +/- 1.7 5.6 5.0 +/- 0.3 5.4 5.0 +/- 0.7 5.5 6.7 +/- 0.6 7.0 4.9 +/- 0.7 4.9 3.8 +/- 0.5 4.3 4.6 +/- 1.0 4.1 6.3 +/- 0.6 6.5 4.3 +/- 0.4 4.5 5.7 +/- 0.3 5.6 4.5 +/- 0.6 5.3 4.5 +/- 0.6 5.8 4.4 +/- 0.3 5.0 3.5 +/- 0.8 3.9 3.2 +/- 0.3 3.5 6.9 +/- 0.4 7.7 3.8 +/- 0.3 4.1 3.7 +/- 0.3 3.7

+/- 1.1

+ 0.3

+/- 0.3

+/- 0.5

+/- 0.2

+ 0.3

+ 0.5

- 0.4

+/- 0.9

+ 0.8

- 1.6

+ 0.8

- 0.4

+ 0.3

+/- 0.4

+/- 0.5

+/- 0.7

+/- 0.5

+/- 1.4

+/- 0.3

+/- 0.7

+/- 0.9

+/- 0.3

+/- 1.2

+/- 0.8

+/- 0.6

+/- 0.4

+/- 0.6

+/- 0.9

+/- 0.5

+/- 0.7

+/- 0.4

+/- 0.6

+/- 0.4

+/- 2.0

+/- 1.7

+/- 0.7

+/- 0.3

+/- 0.4

+/- 0.7

+/- 0.4

+/- 0.5 4.3 4.5 5.3 3.9 4.8 4.6 4.5 4.4 5.0 5.0 4.2 4.7 5.3 5.2 4.4 4.4 5.0 5.6 5.4 4.2 4.5 5.2 4.9 4.9 5.6 4.7 4.8 4.7 5.0 4.7 5.1 6.1 4.4 4.0 4.0 5.8 4.4 5.5 4.2 4.4 4.9 3.6 3.7 7.1 4.1 4.2

+/- 0.9

+/- 0.4

+/- 0.5

+/- 0.4

+/- 0.8

+/- 0.2

+/- 0.3

+/- 0.4

+/- 0.2

+/- 0.4

+/- 0.3

+/- 0.7

+/- 0.2

+/- 0.4

+/- 0.2

+/- 0.5

+/- 0.4

+/- 0.3

+/- 0.4

+/- 0.3

+/- 0.4

+/- 0.3

+/- 0.4

+/- 0.5

+/- 0.6

+/- 0.3

+/- 0.4

+/- 0.3

+/- 0.5

+/- 0.1

+/- 0.4

+/- 0.5

+/- 0.5 (1) SEE PROGRAMS EXCEPTIONS SECTION FOR EXPLANATION C-24

TABLE C-XI.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF MILLI-ROENTGENS/STD. MONTH STATION CODE J15-1 J3-1 J5-1 J7-1 Ki-4 K15-1 K2-1 K3-1 K5-1 K8-1 Li-i Li -2 L15-1 L2-1 L5-1 L8-1 Mi-i M1-2 M2-1 M5-1 M9-1 Ni-i N1-3 N15-2 N2-1 N5-1 N8-1 P1-i P1-2 P2-1 P5-1 P8-1 Q1-i Q1-2 Q15-1 Q2-1 Q5-1 09-1 Ri-i R1-2 R15-1 R3-1 R5-1 R9-1 MEAN

+/- 2 S.D.

5.2 +/- 0.4

.4.4 +/- 0.3 5.1 +/- 0.3 5.5 +/- 0.9 3.9 +/- 0.4 4.6 +/- 0.7 5.0 +/- 1.0 3.9 +/- 0.7 4.9 +/- 0.8 4.6 +/- 0.4 4.0 +/- 0.8 3.8 +/- 0.3 4.5 +/- 0.5 4.5 +/- 0.3 4.3 +/- 0.4 4.3 +/- 0.4 4.1 +/- 1.6 4.9 +/- 0.3 3.7 +/- 0.3 4.7 +/- 0.6 5.5 +/- 0.6 4.6 +/- 0.8 4.2 +/- 1.1 5.0 +/- 0.1 4.5 +/- 1.1 3.9 +/- 0.7 4.7 +/- 0.4 4.1 +/- 0.4 4.7 +/- 3.0 5.3 +/- 1.7 4.4 +/- 0.7 3.7 +/- 0.6 4.6 +/- 0.3 3.6 +/- 1.3 5.0 +/- 1.1 3.9 +/- 0.8 4.1 +/- 1.0 4.2 +/- 0.9 3.8 +/- 0.5 4.0 +/- 0.7 4.6 +/- 0.5 5.1 +/- 0.9 4.7 +/- 1.0 5.1 +/- 0.3 JAN - MAR APR - JUN JUL - SEP OCT - DEC 5.0 +/-

4.5 +/-

5.0 +/-

6.1 +/-

3.8 +/-

4.3 +/-

4.9 +/-

3.5 +/-

4.6 +/-

4.4 +/-

3.8 +/-

3.9 +/-

4.6 +/-

4.4 +/-

4.1 +/-

4.1 +

3.4 +/-

5.1 +/-

3.5 +/-

4.5 +/-

5.2 +/-

4.6 +/-

3.8 +/-

4.9 +/-

4.2 +

3.6 +/-

4.5 +/-

4.3 +/-

3.4 +/-

4.2 +/-

3.9 +

3.2 +/-

4.7 +/-

2.7 +/-

4.5 +/-

3.7 +/-

3.4 +/-

3.8 +/-

3.5 +/-

4.4 +/-

4.3 +/-

4.7 +/-

4.0 +/-

4.9 +/-

0.6 0.6 0.6 1.7 0.2 0.2 0.5 0.4 0.9 0.5 0.5 0.3 0.6 0.4 0.5 0.1 0.8 0.5 0.5 1.4 0.6 0.3 0.5 0.3 0.7 0.6 0.8 0.3 0.4 0.3 0.3 0.5 0.5 0.4 0.2 0.3 0.1 0.6 1.3 0.5 0.2 0.5 0.4 0.6 5.1 +/-

4.2 +/-

4.9 +/-

5.7 +/-

3.7 +/-

4.3 +/-

4.6 +/-

4.2 +/-

4.9 +/-

3.9 +/-

3.6 +/-

4.5 +/-

4.6 +/-

4.2 +/-

4.4 +

3.5 +/-

4.8 +/-

3.6 +/-

4.3 +/-

5.8 +/-

4.2 +/-

3.7 +/-

5.0 +/-

4.2 +/-

4.0 +/-

4.7 +/-

3.9 +/-

5.2 +/-

4.6 +/-

'3.9 +/-

4.4 +/-

4.0 +/-

5.3 +/-

3.6 +/-

4.2 +/-

4.3 +/-

3.7 +/-

4.6 +/-

5.0 +/-

5.1 +/-

5.5 +/- 0.5 4.4 +/- 0.6 5.3 +/- 1.2 5.2 +/- 0.2 4.2 +/- 0.5 4.7 +/- 1.0 5.6 +/- 0.5 4.2 +/- 0.3 5.4 +/- 0.6 4.5 +/- 0.3 4.6 +/- 0.9 3.9 +/- '0.5 4.6 +/- 0.6 4.4 +/- 0.1 4.4 +/- 0.2 4.6 +/- 0.6 4.2 +/- 0.3 4.8 +/- 1.1 3.9 +/- 0.5 4.9 +/- 0.6 5.7 +/- 0.5 5.0 +/- 0.7 4.3 +/- 0.3 5.0 +/- 0:9 5.3 +/- 0.9 4.3 +/- 0.3 4.9 +/- 0.6 4.0 +/- 0.5 4.5 +/- 1.8 5.4 +/- 0.8 4.6 +/- 0.5 3.8 +/- 1.0 4.6 +/- 0.4 3.7 +/- 0.4 5.7 +/- 0.9 4.5 +/- 0.4 4.6 +/- 0.6 4.7 +/- 0.5 4.0 +/- 0.3 4.0 +/- 1.1 4.9 +/- 0.7 5.7 +/- 0.7 5.1 +/- 0.8 5.2 +/- 0.5 5.2 4.5 5.1 5.1 3.9 5.0 3.8 4.5 4.5 3.8

+/- 0.5

+/- 0.4

+/- 0.5

+/- 0.3

+/- 0.6

+/- 0.4

+/- 0.3

+/- 0.3 (1) 4.1 +/- 0.4 4.7 +/- 1.1 4.6 +/- 0.7 4.2 +/- 0.6 5.1 +/- 0.7 3.6 +/- 0.3 4.9 +/- 1.0 5.4 +/- 1.0 (1)

(1)

(1) 4.9 5.0 4.4 3.5 4.5 6.8 6.3 4.4 3.7 4.1 4.6 3.8 4.1 3.8 4.0 4.4 4.9 4.6 5.0

+/- 0.8

+/- 0.7

+/- 0.2

+/- 0.5

+/- 0.4

+/- 1.9

+/- 0.5

+/- 1.2

+/- 0.6

+/- 0.5

+/- 0.2

+/- 0.7

+/- 0.5

+/- 0.4

+/- 0.3

+/- 0.4

+/- 0.3

+/- 0.7 (1)

(1)

(1) SEE PROGRAMS EXCEPTIONS SECTION FOR EXPLANATION C-25

TABLE C-XI.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2009.

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.

3.8 +/- 0.8 3.9.+/- 0.7 4.3 +/- 0.9 4.5 +/- 1.3 INDICATOR CONTROL 4.4 +/- 1.5 4.5 +/- 1.3 4.9 +/- 1.5 4.7 +/- 1.4 4.9 +/- 1.3 5.0 +/- 1.6 5.4 +/- 1.5 5.0 +/- 1.2 TABLE C-XI.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SITE BOUNDARY INDICATOR CONTROL SAMPLES PERIOD PERIOD ANALYZED MINIMUM MAXIMUM 76 2.7 6.8 232 3.0 7.7 44 4.1 7.0 PERIOD MEAN

+/- 2 S.D.

PRE-OP MEAN

+/- 2 S.D.

4.1.+/- 1.1 4.6 +/- 1.5 5.1 +/- 1.4 4.8 +/- 1.5 5.2 +/- 1.5 5.8 +/- 1.7 SITE BOUNDARY STATIONS - A1-4, B1-2, C1-2, Di-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, KI-4, Li-1, Mi-1, N1-3, P1-2, Q1-2, Ri-i INDICATOR STATIONS.- A3-1, A5-1, A9-3, B1-1, B10-1, B2-1, B5-1, Cl-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, Fl-1, F10-1, F2-1, F5-1, G1-2, G2-4, G5-1, H3-1, H5-'1, H8-1, J1-l, J3-1, J5-1, J7-4, K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, R9-1 CONTROL STATIONS - D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, R15-1 C-26

FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2009

.o Station'J1-2 (Downstream of Discharge) oi Station Q9-1 (Control)

Im c]

Ei m

100000.......................................................................................................................

U, 1 0 0 00 ---

1000 CD

.a) an 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month E Station K1-1 (TMINS Liquid Discharge)

U)

-J U,a.

CO U,

C-,

0 C-)

0~

1000000 100000-10000-1000-100-10-Jan Feb Mar Apr.

May Jun Jul Aug Sep Oct Nov Dec Month

FIGURE C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2009 Indicator Samples Control Samples 12000 11000 10000 9000 Significant Events Major 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 Chernobyl April 1986 8000 +

0 7000+

6000+

5000 +

4000+/--

3000 +/--

2000+

1000-0+

-1000 *~Ij liii 11111111 I 1111111111111111111111111111111111111111111111111111111111111 liii 11111111111111111111111111111111111 liii I 111111111111111111111 u-uO U3 N*-

U, 0N 0

04 rO U

CO 1-w-

M 0

N M

'l) (0 rN-wo M

0 0

S N

M

't U)

CD r-

0)

M r-I-

N-N-

N--

N-m U

U U

U M

M M

M. M M

M M

0 0

0 4

00

)

0 000000 N

N1 ON RN N

N N

N Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2009 El Indicator Samples a Control Samples 10 9

8 7

O-

._o 4 13.2 1

7 6 ------- ------

0 lDi~i Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2009 NOTE: The mean values are calculated using both the MDCs and El Indicator Samples

..- Control Samples the positive values.

500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L S400 300 0

100O 0

a_ 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month U Station K1-1 (TMINS Liquid Discharge) 1000000 100000 a)0- 10000 U)

.0 1000 0

0 r__o n100 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 - 2009 Indicator Samples Control Samples 900O Significant Event Chernobyl April 1986 800 70

600 I.-..-

i250 I.-

00 100 --

7~~- -

0

'T U')

(0 r-C0O~ CD (D

N4 M~ 1q, O

(D

0) 0CD4C~

O C

N 0

CO CO (0

CO w0 w0 M

0 a)

M) 0M M

M 0M

0)

0) 0ý.

0 0

C0 C

C0 CD CD 0:

0

0)

)

0 0

0)

)

0 0

0

0)

0) 0D 0D 0

Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2009 Indicator

--- Control 0.4 Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 0.35 TMI-2 Critical March 1978 June 1974 September 1974-TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chemobyl April 1986 December 1978 October 1980 0.3 0) 0 CLS0.2 a,

0.1 0.05 0

0.-1 T-

-- T

-N -~ -i -t -o -- -

-~ -

o Year

FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2009 0.100 0.090 0.080 0.070 o 0.060 0 S0.050 C,,

-) 0.040 00 0.030 Indicator Control 0.020 0.010 0.000 o0 0

CD 0

0 0

o o 0 00 0

0 0

o m

4 LO

~N N

N-N-

cO GO c

O c

O O

O C

Ob 0O, 03 03 0")" 0, O)

03) 0")

0) 0)

0 o

o 0o0 0

0 0

0 0)0 0

0 0

CD 0

0 CD 0

0 0

Month / Day of 2009 The high value on 11/24/2009 was caused by an airborne release on 11/21/2009

FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2009 Indicator Samples Control Samples 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 7

L..

"g 0~

04 3

2

0) 0D 0-

1 0 N-O v.'-.

04

0) 1" (0

N--

W0

0)

C 1

0N M

..O

(..O 0

0W

)

C WO (0

(0 (0

0)

0) 0")

0)

0) 0

0) 0O) C C

O O C C)

O C

C

0)

0) 0 CD C

C CD CD C

0 C

0 CO arr4 04 04 04 C4 N

N N

04 04 Year

FIGURE C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2009 Indicator

- Control 50 45+

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

35+

0 2

C'2 U)

E 30+

25+

20+

15+

10+

5+

.4~

V.

0 11111I111 ill 1;11111 11111111 11 ill~ll l !1111111111111111111 liilll li 1 111111111 11111112111111111jiil

,~J.

N-0)

N- ~

~

0 N-N

-N C

OC O

O O

COC O0

0) 0

0) 0)

Year U')

(0 N-CO

0) 0 Z;

M' It U)

C N-CO 0) 0

0)

M) M 0)0 0

0 0

C 0

0 0

0)0C)C

0)

M) M)

M 0

0 0

0) 0

0) 0) 0 0

0)C N

N N

N NN

Intentionally left blank

APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

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

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

D-1

Intentionally left blank D-2

TABLE D-I.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q9-1Q 12/30/08 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09

- 02/03/09

- 03/03/09

- 03/31/09

- 04/28/09

- 06/02/09

- 06/30/09

- 07/28/09

- 08/31/09

- 09/29/09

- 11/03/09

- 12/01/09

- 12/28/09

<1.8 1.9 +/- 1.0

< 0.9

0.9 0.9 +/- 0.5

< 1.2

< 0.8

< 0.6 1.6 +/- 0.7

< 1.2

< 0.9 0.8 +/- 0.4 1.0 +/- 0.7 MEAN TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q9-1Q 12/30/08 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09

- 02/03/09

- 03/03/09

- 03/31/09

- 04/28/09

- 06/02/09

- 06/30/09

- 07/28/09

- 08/31/09

- 09/29/09

- 11/03/09

- 12/01/09

- 12/28/09 157 151 158 167 154 148 169 142 147 155 150 152 MEAN TABLE D-1.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q9-1Q 12/30/08 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/30/09 07/28/09 08/31/09 09/29/09 11/03/09 12/01/09 12/28/09

< 0.3

< 0.5

< 0.4

< 0.3

0.3

< 0.4

< 0.2

< 0.3

0.3

0.1

< 0.3 MEAN

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

TABLE D-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD.

Q9-1 Q 12/30/08 - 02/03/09 02/03/09 - 03/03/09 03/03/09 - 03/31/09 03/31/09 - 04/28/09

-04/28/09 - 06/02/09 06/02/09 - 06/30/09 06/30/09 - 07/28/09 07/28/09 - 08/31/09 08/31/09 - 09/29/09 09/29/09 - 11/03/09 11/03/09 - 12/01/09 12/01/09 - 12/28/09 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140

5.0

< 1.9

< 2.4

< 1.9

2.2

< 2.4

< 2.8

3.6

< 1.9

<4.1

< 2.8

< 2.2

3.2

2.4

2.8

< 2.0

< 3.1

< 2.8

< 1.5

< 1.9

< 2.1

< 3.1

< 2.2

9.2

3.8

6.9

<4.1

7.6

4.6

< 9.0

< 6.8

< 6.0

< 5.4

2.2

< 3.8

< 5.4

< 1.1

< 2.8

< 1.2

< 2.0

2.0

1.8

< 2.2

< 1.9

< 2.7

< 2.3

1.9

< 5.5

< 5.4

< 3.7

< 3.8

< 2.9

< 5.2

<4.1

< 3.5

2.5

6.4

< 4.7

< 3.0

< 10.7

< 4.5

< 5.2

< 3.3

< 4:4

< 4.9

3.2

< 7.3

< 4.7

< 7.5

< 3.6

< 3.1

< 3.8

< 1.9

< 2.5

< 2.4

< 3.0

2.4

1.5

<2.1

< 3.0

< 4.2

< 2.1

< 2.6

< 4.4

< 2.0

< 2.6

< 3.6

< 2.6

3.0

2.7

4.0

< 4.1

3.6

< 3.4

< 4.8

< 2.3

< 1.9

< 1.8

< 2.9

< 3.0

< 2.2

< 2.0

< 1.6

< 4.5

< 2.4

< 2.3

< 15

< 11

<11

< 8.2

< 15

< 16

<11

< 17

< 20

<16

< 16

< 4.0

< 2.5

< 2.4

< 1.6

< 3.5

< 2.3

< 5.2

< 1.4

< 3.8

< 4.5

< 1.9

< 2.3

TABLE D-II.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 C0-60 Zn-65 Cs-i 34 Cs-137 PERIOD INDP 10/22/09

< 0.6

< 0.4 3302 +/- 3302

< 7

< 14

< 35

< 13

< 11

< 8

TABLE D-Ill.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD K-40 Cs-134 Cs-1 37 J2-1 11/23/09 16607 +/- 1169 52 +/- 29 110 +/- 43 D-4

TABLE D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD K-40 1-131 Cs-134 Cs-137 Sr-89 Sr-90 Hi -2Q 07/07/09 B10-2Q 07/29/09 4641 +/- 393 1684 +/- 216 3163 +/- 4182

< 12

< 10

< 13

< 10

< 14

< 20

<2

<.1

<9

<10 MEAN D-5

TABLE D-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/31/08 01/07/09 01/14/09 01/21/09 01/28/09 02/04/09 02/11/09 02/18/09 02/25/09 03/04/09 03/11/09 03/18/09 03/25/09 04/01/09 04/08/09 04/16/09 04/22/09 04/29/09 05/06/09 05/13/09 05/20/09 05/27/09 06/03/09 06/10/09 06/18/09 06/24/09 07/01/09 07/07/09 07/15/09 07/22/09 07/29/09 08/05/09 08/12/09 08/19/09 08/26/09 09/02/09 09/09/09 09/16/09 09/23/09 09/30/09 10/07/09 10/14/09 10/21/09 10/28/09 11/04/09 11/11/09 11/18/09 11/24/09 12/02/09 12/09/09 12/16/09 12/22/09 MEAN

-01/07/09

-01/14/09

-01/21/09

-01/28/09

-02/04/09

-02/11/09

-02/18/09

-02/25/09

-03/04/09

-03/11/09

-03/18/09

-03/25/09

-04/01/109

-04/08/09

-04/16/09

-04/22/09

-04/29/09

-05/06/09

-05/13/09

-05/20/09

-05/27/09

-06/03/09

-06/10/09

-06/18/09

-06/24/09

-07/01/09

-07/07/09

-07/15/09

-07/22/09

-07/29/09

-08/05/09

-08/12/09

-08/19/09

-08/26/09

-09/02/09

-09/09/09

-09/16/09

-09/23/09

-09/30/09

-10/07/09

-10/14/09

-10/21/09

-10/28/09

-11/04/09

-11/11/09

-11/18/09

-11/24/09

-12/02/09

-12/09/09

-12/16/09

-12/22/09

-12/29/09 El -20 GROSS BETA 26 +/- 4 26 +/- 4 32 +/- 4 25 +/- 4 29 +/- 4 31

+/- 4 18 +/- 4 27 +/- 4 26+/- 4 24 +/- 4 35 +/- 4 26 +/- 4 14

+/- 4 13 +/- 4 El -20 1-131

< 17

10

16

17

< 11

19

10

< 11

17

14

16

<. 20

14

10 (1

(1)

(1) 26ý +/-

21 +/-

15 +/-

22 +/-

23 +/-

14 +/-

18 +/-

15 +/-

12 +/-

20 +/-

21 +/-

20 +/-

23 +/-

22 +/-

29 +/-

25 +/-

33 +/-

20 +/-

25 +/-

31

+/-

23 +/-

27 +/-

18 +/-

17 +/-

16 +/-

20 +/-

16 +/-

35 +/-

18 +/-

27 +/-

14 +/-

20. t 30 +/-

32 +/-

15. +/-

12

17

10

22

16

< 2

13

15

14

15

27

14

18

10

13

13

< 9

< 11

13

14

16

10

19

< 12

12

10

16

16

< 9

10

12

< 8

13

14

17

12 23 +/- 12 (1) NO SAMPLE DUE TO AC POWER PROBLEMS

D-6

TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD Be-7 Cs-134 Cs-137 E1-2Q 12/31/08 - 04/01/09 04/01/09 - 07/01/09 07/01/09 - 09/30/09 09/30/09 - 12/29/09 MEAN 72 +/- 13 100 +/- 18 97 +/- 20 73 +/-:13 86 +/- 30

< 1.1

< 0.7

0.5

< 0.9

< 0.8

< 0.5

< 0.5 D-7

TABLE D-VI.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION, GAMMA EMITTERS, AND STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 1-131 K40.

Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 G2-1Q 01/07/09 02/04/09 03/04/09 03/18/09 04/01/09 04/15/09 04/29/09 05/13/09 05/27/09 06/10/09 06/24/09 07/08/09 07/22/09 08/05/09 08/19/09 09/02/09 09/16/09 09/30/09 10/14/09 10/28/09 11/11/09 11/24/09 12/09/09

< 0.3

< 0.4

< 0.3

< 0.4

< 0.1

< 0.4

< 0.2

< 0.3

< 0.2

< 0.3

< 0.2

< 0.3

< 0.4

< 0.3 1351 +/- 122 1537 +/- 120 1331 +/- 106 1267 +/- 107 1061 +/- 104 1335 +/- 114 1296 +/- 109 1263 +/- 112 1095 +/- 117 1101 +/- 105 1369 +/- 108 1097 +/- 1.11 1061 +/- 115 1302 +/- 113 1381 +/- 118 990 +/- 106 892 +/- 96 1174 +/- 107 1350 +/- 110 1173 +/- 128 1414 +/- 109 1352 +/- 113 1228 +/- 103 1236 +/- 312

< 3.6

< 4.6

< 2.8

< 3.8

< 3.3

< 2.2

< 4.0

< 4.7

< 5.3

< 2.2

< 3.4

< 3.5

< 5.0

< 3.7

< 3.9

< 5.1

< 4.2

< 3.9

< 2.9

< 3.1

< 4.2

< 3.2

< 2.9

< 3.7

< 4.1

< 3.9

< 3.3

< 3.7

< 3.4

< 4.0

< 2.0

< 2.9

< 3.5

< 3.6

< 4.8

< 2.8

< 3.6

< 3.3

< 4.7

< 3.2

< 3.7

< 4.7

< 3.6

< 3.5

< 17

< 15

< 12

< 13

< 14

< 12

< 10

< 17

< 24

< 12

,< 10

< 16

< 13

< 17

< 18

< 15

< 21 1< 20

< 17

< 16

< 15

< 21

< 2.3

< 2.5

< 3.9

< 1.4

< 3.1

< 1.2

< 2.5

< 2.4

< 5.0

< 1.9

< 4.4

< 3.6

< 1.9

< 2.2

< 2.4

< 5.3

< 5.5

< 3.8

< 3.1

< 3.8

< 3.2

< 3.0

< 0.6 0.8 +/- 0.3

< 0.6 0.6 +/- 0.3

< 0.9

< 0.4

< 0.8 0.6 +/- 0.4 MEAN 0.7 +/- 0.2

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-8

FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2009 6

5 4

C-)

3 2

1 0

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

FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2009 50 QC - LAB

--PRIMARY - LAB 40 4 0

..........................I......................

2 0 - -- - -- - ----...

0, i i, i, i i i

1.

1. 1. 1, lq

1. 1

. 1. 1,!

1. 1, : 1,1 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, 2009 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b)

TBE/Analytics Evaluation (d)

March 2009 E6533-396 Milk E6534-396 Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi/L 102 97.7 pCi/L 14.9 15.6 66.7 87.5 275 82.0 111 114 136 1i12 160 142 120 385 113 149 153 155 118 195 190 79.3 94.9 305 93.7 111 119 128 99.9 156 142 115 371 114 135 145 155 121 189 173 E6536-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E6535-396 Charcoal 1-131 pCi 82.8 79.4 pCi/L 107 112 pCi/L 19.0 16.7 1.04 0.96 0.84 0.92 0.90 0.88 1.00 0.96 1.06 1.12 1.03 1.00 1.04 1.04 0.99 1.10 1.06 1.00 0.98 1.03 1.10 1.04 0.96 1.14 0.96 0.92 0.97 0.87 0.96 0.95 0.97 1.03 0.99 0.96 1.14 1.13 1.06 1.22 1.16 1.05 1.19 1.36 1.12 0.96 June 2009 E6742-396 Milk E6743-396 Milk Sr-89 Sr-90 A

A 1-131 Ce-141 Cr-51 Cs-134 Cs-1137 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 98.1 260 389 144.0 185 86.9 133 126 173 298 186 262 101 135 61 83.1 84 137 202 102.0 284 400 166 192 91.9 137 122 175 312 163 231 95 111 53 79 70 101 180 A

A A

W A

A A

N (1)

A E6745-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E6744-396 Charcoal 1-131 pCi 92.2 95.8 A

E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

September 2009 E6897-396 E6898-396 E6900-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 113 pCi/L 17.4 pCi/L 89.2 pCi/L 249 pCi/L 213 pCi/L 104.0 pCi/L 172 pCi/L 96.3 pCi/L 201 pCi/L pCi/L pCi/L AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi pCi pCi pCi pCi pCi pCi pCi pCi 154 213 154 181 145 71.8 115 62 129 97 110 98.7 107 18.8 98.6 275 221 123 185 99.4 206 147 204 160 161 130 72 109 58 121 98 120 94.1 1.06 0.93 0.90 0.91 0.96 0.85 0.93 0.97 0.98 1.05 1.04 0.96 1.12 1.12 0.99 1.06 1.06 1.07 0.98 0.92 1.05 E6899-396 pCi 89.5 92.3 pCi/L 131 131 pCi/L 19.3 17.9 December 2009 E6946-396 E6947-396 E6949-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 79.2 193 512 222 163 200 178 176 326 240 103 290 116 93.4 111 81.0 106 155 135 87.3 202 548 253 179 211 178 178 345 256 103 280 129 91.5 108 90.8 90.8 176 131 0.97 1.00 1.08 0.91 0.96 0.93 0.88 0.91 0.95 1.00 0.99 0.94 0.94 1.00 1.04 0.90 1.02 1.03 0.89 1.17 0.88 1.03 A

A A

A AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b)

TBE/Analytics Evaluation (d)

December 2009 E6948-396 Charcoal 1-131 pCi 93.3 93.9 0.99 A

(1) Detector 7 appears to have a slightly high bias. Detector 7 was removed from service until it can be recalibrated. NCR 09-23 (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 intemal QC limits: A= Acceptable. Reported result falls within ratio limits of0.80-1.20.

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

E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 1)

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

Control Limits Evaluation (c)

April 2009 RAD 77 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCi/L 57.4 pCi/L 30.6 pCi/L 55.2 pCi/L 65.8 pCi/L 157 pCi/L 86.4 pCi/L 85.5 pCi/L 47.7 pCi/L 45.2 pCi/L 25.2 pCi/L 19733 pCi/L 64.75 pCi/L 30.30 pCi/L 97.9 pCi/L 76.8 pCi/L 59.9 pCi/L 121 pCi/L 115 pCi/L 19.6 pCi/L 28.5 pCi/L 22.1 pCi/L 16133 48.3 31.4 52.7 72.9 168 88.9 84.4 54.2 43.5 26.1 20300 62.2%

30.7 92.9 79.4 54.6 117 99.5 23.2 26.0 22.2 16400 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 59.5 - 80.2 151 - 187 80.0- 100 76.0 - 101 28.3 - 67.7 29.1 - 50.8 21.7-30.8 17800 - 22300 50.2-70.1 22.4 - 35.6 78.3 - 102 65.0 - 87.3 49.1 -62.9 105 - 131 89.6-119 11.6-31.1 16.2 - 33.9 18.4 -26.5 14300- 18000 N (1)

A A

A October 2009 RAD 79 (1) Calculation did not allow for Y-90 ingrowth on the Sr-89 mount. NCR 09-14 (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, 2009 (PAGE 1 OF 2)

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

Range Evaluation (c)

March 2009 09-MaW20 09-GrW20 09-MaS20 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B Soil Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Bq/L 18.8 22.5 Bq/L 0.0601 Bq/L 17.0 18.9 Bq/L 16.1 17.21 Bq/L 332 330.9 Bq/L 13.8 14.7 Bq/L 6.88 7.21 Bq/L 13.2 13.6 Bq/L 0.529 0.635 Bq/L 1.87 1.27 Bq/kg 433 467 Bq/kg 649 605 Bq/kg

-0.120 Bq/kg 3.91 4.113 Bq/kg 339 307 Bq/kg 644 570 Bq/kg 245 257 Bq/kg 272 242 Bq/sample 2.77 2.93 Bq/sample 1.41 1.52 Bq/sample 1.24 1.30 Bq/sample 1.33 1.22 Bq/sample 2.42 2.2709 Bq/sample 0.713 0.64 Bq/sample 1.30 1.36 Bq/sample 0.188 0.348 Bq/sample 0.313 0.279 09-RdF20 09-GrF20 18.5-29.3 (1) 13.2 - 24.6 12.05 - 22.37 231.6 - 430.2 10.26-19.06 5.05-9.37 9.5-17.7

>0.0 - 1.270 0.64-1.91 327 - 607 424 - 787 (1)

(2) 215-399 399 - 741 180 - 334 169 - 315

.2.05 - 3.81 1.06-1.98 0.91 - 1.69 0.85-1.59 1.5898 - 2.9522 0.448 - 0.832 0.95 - 1.77

>0.0 - 0.696 0.140 - 0.419 2.38 - 4.42 0.65-1.21 1.65 - 3.07 (1) 1.61 -2.99 (4) 0.882 - 1.638 0.948 - 1.760 22.5-41.9 28.8 - 53.6 25.6 -47.6 10.8-20.0 443.9 - 824.3 (1) 9.09-16.89 18.8 - 35.0

>0.0 - 2.094 3.77-11.30 A

A A

March 2009 09-RdV20 September 2009 09-MaW21 Vegetation Cs-1 34 Bq/sample 3.48 3.40 Cs-137 Bq/sample 1.15 0.93 Co-57 Bq/sample 3.12 2.36 Co-60 Bq/sample

-0.0105 Mn-54 Bq/sample 2.98 2.3 K-40 Bq/sample 64.1 Sr-90 Bq/sample 1.09 1.260 Zn-65 Bq/sample 1.73 1.3540 A

W N (3)

A W

A A

A A,

AA Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B Bq/L 26.5 32.2 Bq/L 37.2 41.2 Bq/L 32.2 36.6 Bq/L 14.0 15.40 Bq/L 705 634.1 Bq/L

-0.1015 Bq/L 13.9 12.99 Bq/L 26.2 26.9 Bq/L 1.27 1.047 Bq/L 9.70 7.53 09-GrW21 A

A E-5

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

TELEDYNE BROWN ENGINEERING, 2009 (PAGE 2 OF 2)

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

Value (b)

Range Evaluation (c)

September 2009 09-MaS21 Soil Am-241 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/kg 74.7 0.554 706 606 350 876 425 505 1370

-0.02 1.4 5.98 1.01 5.16 0.925 4.39.

89.8 62.9-116.7 (1) 669 468-870 586 410-762 327.000 229-425 796 557-1035 375 263-488 455 319-592 1178 825-1531 09-RdF21 09-GrF21 09-RdV21 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 1.4 6.48 1.03 5.49 0.0835 3.93 (1) 0.98-1.82 4.54 - 8.42 0.72-1.34 3.84-7.14 0.585 - 1.086 2.75-5.11 A

A A

A-Bq/sample 0.357 0.659

>0.0- 1.318 Bq/sample 1.403 1.320 0.66-1.98 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample

-0.0027 2.36 2.58 8.36 57.8 1.73

-0.59 (1) 2.43 1.70-3.16 2.57 1.80-3.34 7.9 5.5 - 10.3 (4) 1.78 1.25-2.31 (1)

(1) False positive test.

(2) Sensativity evaluation.

(3) Homogeniety problem. MAPEP requires using entire sample but due to geometry limitations we can only use part of the sample. NCR 09-13 (4) Not evaluated by MAPEP.

(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-6

TABLE E-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2009 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory Resultb ERA Control Resultc Limits Acceptance STW-1181 STW-1181 STW-1182 STW-1182 STW-1182 STW-1182 a STW-1182 STW-1 183 STW-1 183 STW-1 184 STW-1 186 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 Sr-89 Sr-90 Ba-133 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 41.0 +/- 5.8 32.4 +/- 2.4 44.6 +/- 3.1 81.0 +/- 3.1 65.6 +/- 5.2 147.7 +/- 5.3 79.8 +/- 7.5 47.6 +/- 2.1 38.5 +/- 1.3 24.4 +/- 2.5 22819.0 +/- 453.0 48.3 31.4 52.7 88.9 72.9 168.0 84.4 54.2 43.5 26.1 20300.0 37.8 -55.7 22.9 -36.4 43.4 -58.3 80.0 -100.0 59.5 -80.2 151.0 - 187.0 76.0-101.0 28.3 -67.7 29.1 -50.8 21.7 -30.8 17800.0 -22300.0 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Fail STW-1 193 10/05/09 Sr-89 53.0 +/- 6.0 62.2 50.2 - 70.1 Pass STW-1193 10/05/09 Sr-90 31.1 +/- 2.2 30.7 22.4 -35.6 Pass STW-1194 10/05/09 Ba-133 82.5 +/- 3.5 92.9 78.3-102.0 Pass STW-1194 10/05/09 Co-60 116.8 +/- 3.3 117.0 105.0 - 131.0 Pass STW-1 194 10/05/09 Cs-1 34 78.8 +/- 5.7 78.8 65.0 - 87.3 Pass STW-1 194 10/05/09 Cs-137 54.2 +/- 3.7 54.6 49.1 -62.9 Pass STW-1194 10/05/09 Zn-65 102.5 +/- 6.2 99.5 89.6-119.0 Pass STW-1195 10/05/09 Gr. Alpha 20.3 +/- 2.0 23.2 11.6 -31.1 Pass STW-1195 10/05/09 Gr. Beta 23.7 +/- 1.4 26.0 16.2 -33.9 Pass STW-1196 10/05/09 1-131 22.4 +/- 1.4 22.2 18.4 -26.5 Pass STW-1198 10/05/09 H-3 17228.0 +/- 694.0 16400.0 14300.0 - 18000.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Assc (ERA),

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

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

c All gamma -emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Result of recount in a different beaker, Cs-137, 155.33

+/- 14.55 pCi/L.

Samples were recounted and also reanalyzed. A recount of the original vials averaged 23,009 pCi/L.

Reanalysis results were acceptable, 19,170 pCi/L.

E-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2009 (Page 1 of 2)

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1 170 STW-1 170 STW-1 170 STW-1 170 e STW-1 170 STW-1 170 STW-1 170 STW-1170 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Co-57 Co-60 Cs-134 Cs-137 H-3 Mn-54 Sr-90 Zn-65 19.60 +/- 0.40 16.60 +/- 0.30 K 20.40 +/- 0.50 0.10 +/- 0.20 359.90 +/- 33.90 15.00 +/- 0.40 7.87 +/- 1.39 14.00 +/- 0.70 18.90 17.21 22.50 0.00 330.90 14.66 7.21 13.60 13.20 - 24.60 12.05 - 22.37 15.80 -29.30 0.00 - 1.00 231.60 -430.20 10.26 - 19.06 5.05 - 9.37 9.50 - 17.70 STW-1171 01/01/09 Gr. Alpha STW-1171 01/01/09 Gr. Beta 0.56 +/- 0.06 1.29 +/- 0.05 0.64 1.27 0.00 - 1.27 0.64-1.91 STSO-1172 e STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STVE-1 173 STVE-1173 e STVE-1 173 STVE-1 173 STVE-1 173 STVE-1 173 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174' STAP-1 174 STAP-1 175 STAP-1 175 STW-1 192 STW-1 192 STW-1192' STW-1192 STW-1192 STW-1 192 e STW-1 192 STW-1 192 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Co-57 Cs-134 Cs-137 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 0.00 +/- 0.00 458.60 +/- 7.40 652.30 +/- 3.50 636.40 +/- 9.50 346.40 +/- 3.10 180.60 +/- 12.10 268.30 +/- 4.00 0.00 467.00 605.00 570.00 307.00 257.00 242.00 0.00 -1.00 327.00 -607.00 424.00 - 787.00 360.40 - 669.40 215.00 -399.00 180.00 -334.00 169.00 - 315.00 2.75 +/- 0.11 0.06 +/- 0.09 3.49 +/- 0.22 1.01 +/- 0.11 2.52 +/- 0.14 1.52 +/- 0.18 1.25 +/- 0.05 1.17 +/- 0.06 2.67 +/- 0.14 1.53 +/- 0.08 2.34 +/- 0.09 0.93 +/- 0.14 1.44 +/- 0.14 0.22 +/- 0.03 0.36 +/- 0.04 2.36 0.00 3.40 0.93 2.30 1.35 1.30 1.22 2.93 1.52 2.27 0.64 1.36 0.35 0.28 1.65 -3.07 0.00 -1.00 2.38 -4.42 0.65 -1.21 1.61 -2.99 0.95 -1.76 0.91 -1.69

/0.85 -1.59 2.05 -3.81 1.06-1.98 1.59 -2.95 0.45 -0.83 0.95-1.77 0.00 -0.70 0.14 -0.42 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 Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 01/01/09 Gr. Alpha 01/01/09 Gr. Beta 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 H-3 Mn-54 Sr-90 Zn-65 37.20 +/- 1.50 15.10 +/- 0.90 30.30 +/- 2.10 41.90 +/- 1.80 680.30 +/- 33.60 0.01 +/- 0.26 12.90 +/- 1.70 28.50 +/- 2.40 36.60 15.40-32.20 41.20 634.10 0.00 12.99 26.90 25.60 - 47.60 10.80 - 20.00 22.50 - 41.90 28.80 - 53.60 443.90 - 824.30 0.00 - 1.00 9.09 - 16.89 18.80 - 35.00 E-8

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2009 (Page 2 of 2)

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1191 07/01/09 Gr. Alpha STW-1191 07/01/09 Gr. Beta 0.88 +/- 0.07 7.29 +/- 0.10 1.05 7.53 0.00 - 2.09 3.77 -11.30 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 g 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 674.60 +/- 9.00 356.40 +/- 6.30 0.20 +/- 1.90 767.50 +/- 12.00 433.00 +/- 37.20 931.60 +/- 14.10 310.50 +/- 12.20 1433.90 +/- 25.20 586.00 327.00 0.00 669.00 375.00 796.00 455.00 1178.00 410.00 - 762.00 229.00 -425.00 0.00-1.00 468.00 - 870.00 263.00 - 488.00 557.00 -1035.00 319.00 -592.00 825.00 -1531.00 STAP-1189 07/01/09 Gr. Alpha STAP-1189 07/01/09 Gr. Beta 8.90 +/- 0.60 2.50 +/- 0.36 0.01 +/- 0.11 2.42 +/- 0.16 8.35 +/- 0.70 0.01 +/- 0.26 0.33 +/- 0.04 1.57 +/- 0.07 6.78 +/- 0.27 1.06 +/- 0.18 0.01 +/- 0.06 1.49 +/- 0.27 6.00 +/- 0.45 0.79 +/- 0.13 4.55 +/- 0.66 8.00 2.57 0.00 2.43 7.90 0.00 0.66 1.32 6.48 1.03 0.00 1.40 5.49 0.84 3.93 5.60-10.40 1.80-3.34 0.00 -0.10 1.70 -3.16 5.50 -10.30 0.00 -0.10 0.00 -1.32 0.66-1.98 4.54 -8.42 0.72-1.34 0.01 -0.05 0.98 -1.82 3.84 -7.14 0.59 -1.09 2.75-5.11 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

,Pass Pass Pass Pass STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 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 Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

e Included in the testing series as a "false positive".

No reason was determined for the initial high results. The analysis was repeated; result of reanalysis; 0.54 +/- 0.12 Bq/filter.

g Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity. The analysis was repeated; result of reanalysis 363.3 +/- 28.6 Bq/kg.

E-9

Intentionally left blank

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER

.PROTECTION PROGRAM REPORT (ARGPPR)

Docket No:

50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January Through 31 December 2009 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Three Mile Island Nuclear Station Middletown, PA 17057 April 2010

Table Of Contents I. Sum mary and Conclusions..............................................................................................

J I1. Introduction.............................................................................................................

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

3 B. Im plementation of the Objectives..................................................................

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

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

5 II1. Program Description...........................................................

!.......................................... 6 A, Sam ple Analysis.............................................................................................

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

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

7 A, Groundwater Results....................................................................................

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

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

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

9

Appendices Appendix A Tables Table A-i:

Location Designation Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2009 Figures Figure A-I:

Appendix B Tables Table B-1.1 Table B-1.2 Table B-11.1 Table B-11.2 Appendix C Tables Table C-1.1 Table C-1.2 Sampling Locations Near the Site Boundary of the Three Mile Island Nuclear Station, 2009 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, 2009.

Concentrations of Gamma Emitters in Well Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Concentrations of Tritium and Strontium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2009.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2009.

Data Tables Concentrations of Tritium and Strontium in Well Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2009.

Concentrations of Gamma Emitters in Well Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2009.

ii

iii

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 2009. During that time period, 517 analyses were performed on 368 samples from 67 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 2009 into the groundwater at Three Mile Island Nuclear Station.

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

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

Tritium was not detected in any groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L.

Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 41 of 64 groundwater monitoring locations. The groundwater tritium concentrations ranged from 154 +

102 pCi/L to 8,510 +/- 904 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of historical releases, the recapture of gaseous tritium releases via rainwater and/or background from external sources greater than 200 pCi/L.

Intentionally left blank II.

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

Conestoga Rovers & Associates (CRA) performed the initial assessment. CRA prepared a Hydrogeologic Investigation Report (HIR) for Exelon to determine whether groundwater at and near TMINS has been adversely impacted by any releases of radionuclides. The CRA report documents the results of the May 2006 Hydrogeologic Investigation Work Plan. CRA assessed groundwater quality at the Station in locations designated as Areas for Further Evaluation.

The results and conclusions of this Phase 1 study were made available to state and federal regulators as well as the public on an Exelon web site in station specific reports.

As a result of the Phase 1 study, the Radiological Groundwater Protection Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on well water and surface water samples collected in 2009. 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 2009.

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, LI

preservation management, and shipment of samples, as well as in documentation of sampling events. For split samples, collectors will periodically collect samples that are sent to Midwest Labs to confirm that TBE is producing comparable data. Analytical laboratories are subject to internal quality assurance programs,,

industry cross-check programs, as well as nuclear industry audits.

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

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

D.

Characteristics of Tritium (H-3)

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

Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. This "cosmogenic" tritium combines with oxygen to form tritiated water, which will then enter the hydrologic cycle.

Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources dueto 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 Midwest Labs to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2009.

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

1.

Concentrations of gamma emitters in groundwater and surface water.

2.

Concentrations of strontium in groundwater and surface water.

3.

Concentrations of tritium in groundwater and surface water.

B.

Data Interpretation

1.

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

2.

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

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

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

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

For groundwater and surface water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.

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

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

IV.

Results and Discussion A.

Groundwater Results Samples were collected from on and off-site wells throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

Tritium Samples from 64 locations were analyzed for tritium activity (Table B-1.1, Appendix B). Tritium values ranged from the detection limit to 8,510 pCi/I. One of the locations was offsite drinking water wells with no detectable concentration of tritium.

Tritium Split Samples Tritium values ranged from detection limit to 6,054 (Table C-1.1, Appendix C).

Strontium Strontium-90 was not detected above the required detection limit of 2.0 pCi/liter. (Table B-1.1, Appendix B)

Strontium Split Samples Strontium-90 was not detected above the required detection limit of 2.0 pCi/liter (Table C-1.1, Appendix C).

Gamma Emitters Potassium-40 was detected in one of 66 samples. The concentration was 74 pCi/liter. No other gamma emitting nuclides were detected (Table B-1.2, Appendix B).

Gamma Emitters Split Samples Potassium-40 was detected in six of 8 samples. The concentration ranged from 74 to 163 pCi/liter. No other gamma emitting nuclides were detected (Table C-1.2, Appendix C).

B.

Surface Water Results Samples were collected from surface water locations throughout the year in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.

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

Strontium Strontium-90 was not detected above the required detection limit of 2.0 pCi/liter. (Table B-Il.1, Appendix B).

Gamma Emitters No gamma'emitting nuclides were detected. (Table B-II.2, Appendix B).

C.

Leaks, Spills, and Releases No new active leaks were identified at the TMI in 2009. TMI continues to monitor tritium plumes from previous years and reports the dose to the public in the AREOR. No spills were determined to be reportable under voluntary reporting requirements for the NEI Groundwater Protection Initiative (GPI) as implemented in Exelon's Reportability procedure LS-AA-1120, RAD 1.34.

D.

Actions Taken

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

APPENDIX A LOCATION DESIGNATION

TABLE A-I:

Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2009 Site Site Type

3 Monitoring Well 48N 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 J1-3 Precipitation MS-1 Monitoring Well, Precipitation MS-19 Monitoring Well, Precipitation MS-2 Monitoring Well, Precipitation MS-20 Monitoring Well, Precipitation 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, Precipitation NW-C Production Well NW-CW Clearwell OS-1 3B Monitoring Well OS-14 Monitoring Well OS-16 Monitoring Well OS-17 Monitoring.Well OS-18 Monitoring Well OSF Production Potable Well RW-1 Monitoring Well RW-2 Monitoring Well SW-E-1 Surface Water SW-E-2 Surface Water SW-E-3 Surface Water MW-TMl-9S*

Monitoring Well MW-TMI-10D Monitoring Well MW-TMI-101 Monitoring Well MW-TMI-10S Monitoring Well MW-TMI-1 1S*

Monitoring Well MW-TMI-12S Monitoring Well MW-TMI-1 31 Monitoring Well MW-TMI-1 3S Monitoring Well MW-TMI-14D Monitoring Well MW-TMI-141 Monitoring Well MW-TMI-14S Monitoring Well MW-TMI-16D Monitoring Well MW-TMI-161 Monitoring Well

NO WATER PRESENT TO SAMPLE A-1

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2009 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

APPENDIX B DATA TABLES

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM - THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE

3

3 48N 48N 48S 48S 48S 48S 48S 48S 48S GP-6 GP-9 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-1 MS-19 MS-19 MS-2 MS-2 MS-2 MS-2 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-21 MS-21 MS-22 MS-22 MS-22 MS-3 MS-3 MS-4 MS-4 MS-5 MS-5 MS-6 MS-6 MS-6 MS-7 ORIGINAL RERUN ORIGINAL RERUN COLLECTION DATE 05/13/09 10/15/09 05/14/09 10/15/09 03/18/09 03/18/09 05/18/09 05/18/09 08/11/09 10/16/09 10/16/09 05/15/09 05/14/09 01/13/09 02/17/09 03/17/09 04/22/09 04/29/09 05/13/09 10/14/09 05/15/09 10/15/09 05/12/09 05/12/09 10/14/09 10/14/09 04/22/09 05/07/09 05/12/09 05/19/09 05/19/09 06/18/09 07/16/09 08/12/09 09/10/09 10/15/09 05/12/09 05/12/09 03/18/09 05/14/09 08/10/09 05/12/09 10/14/09 05/13/09 10/20/09 05/12/09 10/14/09 05/12/09 10/14/09 10/14/09 05/12/09

< 167

< 142

< 147

< 182 268 +/- 130

< 173 213 +/- 113 255 +/- 133

< 184

< 185

175 154 +/- 102 184 +/- 105 246 +/- 117 250 +/- 126

< 179 233 +/- 121

< 179

< 161

< 158

< 141

182

< 169

< 167 415 +/- 121 437 +/- 128 357 +/- 127 352 +/- 115 483 +/- 128, 427 +/- 114 388 +/- 112 622 +/- 128 692 +/- 133 575 +/- 135 404 +/- 149 597 +/- 133 748 t 143 781

+/- 144 798 +/- 165 1680 +/- 216 608 t 134 476 +/- 140 192 +/- 104 216 +/- 122 166 +/- 103

170

< 140

171 200 +/- 104

< 171

145

< 0.5

< 0.9

0.5

< 0.7

< 0.5

< 0.4

< 0.8

< 0.5

< 0.5 H-3 SR-90 B-1

TABLE B-1.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM - THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MS-7 MS-8 MS-8 MW-i MW-i MW-i MW-2 MW-2 MW-2 MW-3 MW-3 MW-4 MW-4 MW-TMI-10D MW-TMI-10D MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-10S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-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-131 MW-TMI-131 MW-TMI-131 COLLECTION DATE 10/14/09 05/12/09 10/14/09 05/12/09 10/20/09 10/20/09 05/12/09 05/12/09 10/20/09 05/12/09 10/20/09 05/12/09 10/20/09 05/12/09 10/14/09 03/17/09 05/15/09 08/11/09 08/11/09 10/14/09 10/14/09 03/17/09 05/15/09 05/15/09 08/11/09 10/15/09 01/13/09 01/20/09 01/27/09 02/03/09 02/10/09 02/17/09 03/18/09 03/18/09 04/16/09 04/16/09 04/22/09 04/22/09 04/29/09 05/07/09 05/13/09 05/19/09 06/18/09 07/16/09 08/12/09 09/10/09 10/20/09 11/19/09 01/13/09 01/20/09 02/03/09 H-3 SR-90

< 196

< 0.9 380 + 125

< 178

< 0.5

< 167

< 178

< 0.7

< 173

< 0.5

< 173

< 172

< 182

< 0.6

< 167

< 179

< 0.6

< 167

< 186

< 0.7 290 +/- 115 302 +/- 114

< 0.7 2070 +/- 280 2510 +/- 291 1780 +/- 241 1950 +/- 259 1170 +/- 179

< 1.0 1300 +/- 191

< 0.7 4710 +/- 541 4430 +/- 477 4820 +/- 518 8510 +/- 904 4560 +/- 507

< 0.9

< 174

< 175

< 185 285 +/- 115

< 186 501

+/- 135 3020 +/- 363 3240 +/- 398 6010 +/- 657 6880 +/- 759 5210 +/- 582 5130 +/- 574 838 +/- 158 481 +/- 121

< 162 308 +/- 109 332 +/- 114 215 +/- 110

< 184

< 187

< 147

< 0.8

< 178 2370 +/- 300 1850 +/- 245 2050 +/- 252 ORIGINAL RERUN ORIGINAL RERUN B-2

TABLE B-1.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM - THREE MILE ISLAND NUCLEAR STATION, 2009' RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-1 31 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D COLLECTION DATE 02/17/09 03/17/09 03/17/09 04/16/09 04/29/09 05/07/09 05/13/09 05/19/09 06/18/09 07/16/09 07/16/09 08/11/09 09/10/09 10/22/09 11/19/09 11/19/09 01/13/09 01/20/09 02/03/09 02/17/09 03/17/09 04/16/09 04/16/09 04/29/09 05/07/09 05/13/09 05/19/09 06/18/09 07/16/09 08/11/09 09/10/09 10/22/09 11/19/09 01/13/09 01/27/09 02/10/09 02/17/09 03/18/09 04/16/09 04/22/09 04/29/09 05/07/09 05/07/09 05/13/09 05/19/09 06/18/09 07/16/09 08/11/09 09/10/09 09/10/09 10/15/09 H-3 1950 +/- 264 1500 +/- 218 1450 +/- 208 1520 +/- 219 1380 +/- 209 1390 +/- 186 1460 +/- 205 1710 +/- 224 1460 +/- 200 984 +/- 154 1310 +/- 186 991 +/- 168 1050 +/- 168 828 +/- 150 841 +/- 152 775 +/- 148 405 +/- 125 247 +/- 122 376 +/- 119 366 +/- 125 577 +/- 145

< 176

181

< 191

< 147

< 162

< 153

160 174 +/- 110

< 179

< 178 157 +/- 99

< 180 1150 +/- 183 1160 +/- 192 973 +/- 167 1260 +/- 203 900 +/- 164 1230 +/- 196 1190 +/- 193 906 +/- 163 798 +/- 138 1140 +/- 164 876 +/- 153 1050 +/- 162 1080 +/- 164 1020 +/- 161 723 +/- 142 814 +/- 150 753 +/- 144 616 +/- 145 SR-90

< 0.9

< 0.8

< 0.7 B-3

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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-TMI-14D MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141I MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S.

MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-14S MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-1 6D COLLECTION DATE 11/19/09 01/13/09 01/27/09 02/10/09 02/17/09 02/17/09 03/18/09 04/16/09 04/22/09 04/29/09 04/29/09 05/07/09 05/13/09 05/19/09 06/18/09 07/16/09 08/11/09 09/10/09 10/15/09 11/19/09 01/13/09 01/27/09 02/10/09 02/17/09 03/18/09 04/16/09 04/22/09 04/29/09 05/07/09 05/13/09 05/19/09 06/18/09 07/16/09 08/11/09 09/10/09 10/15/09 11/19/09 01/13/09 01/20/09 01/27/09 02/03/09 02/10/09 02/17/09 03/18/09 ORIGINAL 04/16/09 RERUN 04/16/09 04/22/09 04/29/09 05/07/09 05/13/09 05/13/09 H-3 702 +/- 141 266 +/- 114 259 +/- 125

< 179

< 179 248 +/- 125

< 183

< 180 256 +/- 120 252 +/- 120 214 +/- 118 237 +/- 107 177 +/- 106 228 +/- 106 269 +/- 108 264 +/- 115

< 179 248 +/- 122

< 182

< 177

< 173 232 +/- 121 208 +/- 126 307 +/- 127 232 +/- 130

< 175

< 181 426 +/- 128

< 149

< 159

< 154

< 157 235 + 112

< 182

< 183

< 177 1810 +/- 246 1630 +/- 224 1710 +/- 245 1500 +/- 201 1180 +/- 188 1320 +/- 207 955 +/- 170 1550 +/- 227 1580 +/- 243 1580 +/- 229 1700 +/- 240 1010 +/- 151 987 +/- 161 1090 +/- 171 SR-90

< 0.8

< 0.5 B-4

TABLE B-1.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM - THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE H-3 SR-90 MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-16D MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-1 61 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-1 61 MW-TMI-1 61 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-17D MW-TMI-17D MW-TMI-171 MW-TMI-171 MW-TMI-18D MW-TMI-18D MW-TMI-19D MW-TMI-19D MW-TMI-191 MW-TMI-191 MW-TMI-191 MW-TMI-iD MW-TMI-1D MW-TMI-2D MW-TMI-2D MW-TMI-2D MW-TMI-2D MW-TMI-31 MW-TMI-31 MW-TMI-41 MW-TMI-41 MW-TMI-41 MW-TMI-4S MW-TMI-4S MW-TMI-4S 05/19/09 06/18/09 07/16/09 08/12/09 09/10/09 10/14/09 01/13/09 01/20/09 01/20/09 01/27/09 02/03/09 02/10/09 02/17/09 03/18/09 04/16/09 04/22/09 04/29/09 05/07/09 05/13/09 05/19/09 06/18/09 07/16/09 08/12/09 08/12/09 09/10/09 10/14/09 05/14/09 10/15/09 05/14/09 10/15/09 05/14/09 10/15/09 05/14/09 10/15/09 05/14/09 10/14/09 10/14/09 05/12/09 10/20/09 03/17/09 05/15/09 08/11/09 10/20/09 05/12/09 10/14/09 05/12/09 05/12/09 10/14/09 05/12/09 10/14/09 11/19/09 1050 +/- 162 1560 +/- 209 1220 +/- 178 1230 +/- 192 773 +/- 147 693 +/- 150 563 +/- 132 586 +/- 142 542 +/- 139 513 +/- 137 457 +/- 123

< 190 280 +/- 123 218 +/- 128

< 184 332 +/- 123 433 +/- 129 654 +/- 132 606 +/- 129 542 +/- 118 856 +/- 146 625 +/- 129 660 +/- 135 623 +/- 138 682 +/- 140 474 +/- 137

< 139

< 135 181 +/- 101

< 142

< 168 171 +/- 107

< 166

< 131

< 168-

< 151

< 170 556 +/- 132 286 +/- 115 439 +/- 142 356 + 136 393 + 127 390 + 124 293 +/- 115

< 151.

< 142

< 165

< 144

< 137

< 145

< 165

< 0.8

< 0.5

< 0.6

< 0.9

< 0.6

< 0.8

< 1.0

< 0.5

< 0.6

< 0.7

< 0.7 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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-TMI-5D MW-TMI-5D MW-TMI-6D MW-TMI-6D MW-TMI-6D MW-TMI-6D MW-TMI-61 MW-TMI-61 MW-TMI-7S MW-TMI-7S MW-TMI-8S MW-TMI-8S MW-TMI-91 MW-TMI-91 N2-1 N2-1 NW-A NW-A NW-B NW-B NW-C NW-C NW-CW NW-CW OS-13B OS-14 OS-14 OS-16 OS-16 OS-17 OS-17 OS-18 OS-18 OS-18 OS-18 OS-18 OS-18 OS-18 OSF OSF OSF OSF OSF RW-1 RW-1 RW-1 RW-1 RW-1 RW-1 RW-2 RW-2 COLLECTION DATE 05/12/09 10/14/09 05/12/09 05/12/09 10/14/09.

10/14/09 05/12/09 10/14/09 05/14/09 10/20/09 05/14/09 10/15/09 05/15/09 10/22/09 05/13/09 10/14/09 05/16/09 10/18/09 05/16/09 10/18/09 05/16/09 10/18/09 05/16/09 10/18/09 05/12/09 05/12/09 10/14/09 05/13/09 10/14/09 05/13/09 10/14/09 03/17/09 03/17/09 04/16/09 05/12/09 08/10/09 08/10/09 10/20/09 03/18/09 03/18/09 05/18/09 08/11/09 10/16/09 04/22/09 05/07/09 05/13/09 05/19/09 09/10/09 10/15/09 01/13/09 01/13/09 H-3 SR-90

< 189

< 153 247 +/- 110 233 +/- 108

< 192

< 172 210 +/- 107

< 186

< 165

< 146

< 166

< 144

< 184

< 147

< 173 1080 +/- 161 934 +/- 159 905 +/- 147 675 +/- 137 1910 +/- 238 3210 +/- 375 943 +/- 151 915 +/- 156 294 +/- 120

< 171

< 139 176 +/- 114 183 +/- 100

< 173 173 +/- 105 849 +/- 165 815 +/- 164 957 +/- 171 200 +/- 104 1120 +/- 179 1030 +/- 167 191 +/- 108 349 +/- 135 440 +/- 135 827 +/- 145 559 +/- 134 596 +/- 135

< 180

< 149

< 171

< 154

< 191

< 145 651 +/- 140 836 +/- 157

< 0.7

< 0.6

< 0:7

< 0.7

< 0.4

< 0.6

< 0.9

< 0.7

< 0.9

< 0.5 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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE 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 TRAINING CENTER COLLECTION DATE 01/20/09 01/27/09 02/03/09 02/10/09 02/17/09 ORIGINAL 03/18/09 RERUN 03/18/09 04/16/09 04/22/09 04/29/09 05/07/09 05/13/09 05/19/09 06/18/09 06/18/09 07/16/09 08/12/09 09/10/09 10/20/09 11/19/09 05/18/09 10/16/09 618 663 438 260 327 2360 2170 2250 1720 730 320 212 240 299 353 284 251

< 191

< 144

< 158

< 165

< 173 H-3

+ 139

+/- 149

+ 121

+ 128

+/- 128

+ 301

+/- 281

+ 294

+ 241

+/- 149

+ 115

+ 108

+ 106

+/- 112

+/- 116

+/- 114

+/- 120 SR-90

< 0.6

< 0.9

.B-7

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 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-1 34 Cs-1 37 Ba-140 La-140 PERIOD

3 48N 48S 48S MS-1 MS-19 MS-2 MS-2 MS-20 MS-3 MS-4 MS-5 MS-6 MS-6 MS-7 80 IMS-8 MW-i MW-i MW-2 MW-3 MW-4 MW-TMI-10D MW-TMI-101 MW-TMI-101 MW-TMI-1OS MW-TMI-12S MW-TMI-12S MW-TMI-131 MW-TMI-13S MW-TMI-14D MW-TMI-141 MW-TMI-14S MW-TMI-16D MW-TMI-161 MW-TMI-1 7D 10/15/09 10/15/09 10/16/09 10/16/09 10/14/09 10/15/09 10/14/09 10/14/09 10/15/09 10/14/09 10/20/09 10/14/09 10/14/09 10/14/09 10/14/09 10/14/09 10/20/09 10/20/09 10/20/09 10/20/09 10/20/09 10/14/09 10/14/09 10/14/09

'10/15/09 04/29/09 10/20/09 10/22/09 10/22/09 10/15/09 10/15/09 10/15/09 10/14/09 10/14/09 10/15/09

< 29

< 45

< 19

< 41

< 15

< 18

< 15

< 18

< 15

< 19

< 32

< 39

< 74

< 20

< 59

< 31

< 30

< 60

< 35

< 31

< 33

< 77

< 37

< 73

< 19

< 16

< 22

< 31

< 28

< 33

< 13

< 12

< 17

<33

< 13

< 31

< 14

< 12

< 31

< 41

< 22

< 39

< 20

< 16

< 10

< 15

< 41

< 110

< 37

< 80

< 15

< 29

< 35

< 79

< 18

<29

< 21

< 43

< 13

< 22

< 17

< 33

< 12

< 10

< 41

< 91

<3

<2

<1

<2

<4

<2

<3

<4

<2

<3

<1

<2

<1

<4

<2

<1

<5

<4

<2

<4

<2

<1

<2

<1

<3

<6

<2

<5

<2

<4

<2

<4

<2

<4

<2

<5

<4

<10

<2

<5

<4

<8

<3

<7

<4

<8g

<4

<8

<3

<9

<2

<4

<2

<5

<3

<7

<2

<3

<1

<3

<2

<4

<1

<3

<1

<3

<4

<8

<2

<5

<2

<5

<1

<2

<5

<10

<4

<9

<2

<4

<9.

<2

<4

<2

<5

<1

<3

<2

<4

<1

<3

<2

<4

<2

<4

<3

< 6

<3

<2

<3'

<1

<2

<1

<6

<2

<1

<5

<4

<2

<4

<2

<1

<2

<1

<7

<4

<3

<4

<8

< 4

<6

< 7

< 10

<7

<4

<6

<3

< 3

<7

<4

<2

<11

<8

<3

<8

<4

<3

<4

<2

<3

<6

<2

<4

<2

<3

<2

<3

<2

<3

<2

<4

<8

<2

<4

<7

<4

<6

<4

<7

<4

<7

<4

<6

<2

<4

<3

<4

<5

<2

<3

<1

<3

<2

<3

<2

<3

<4

<8

<2

<4

<2

<4

<1

<2

<6

<8

<4

<7

<2

<3

<5

<<7

<2

<3

<2

<4

<2

<3

<2

<3

<1

<2

<3

<2

<1

<2

<4

<2

<3

<4

<3

<2

<3

<1

<3

<2

<1

<5

<4

<1

<3

<2

<1

<2

<1

<3

<2

<4

<2

<4

<3

<4

<3

<2

<3

<1

<2

<1

<2

<4

<2

<1

<6

<4

<2

<4

<2

<1

<2

<1

<22

<7

<19

<6

<13

<4

<18

<5

<18

<5

<16

<6

<29

<9

<18

<6

<25

<7

<19

<7

<21

<6

<25

<7

< 24

<9

<20

<5

<19

<5

< 23

<7

<10

<3

<9

<3

<12

<3

< 10

<3

<10

<3

<27

<9

<23

<7

<20

<6

<10

<3

<22

<9

<21

<7

<12

<4

<20

<9

<15

<5

<18

<6

<12

<3

<17

<5

<12

<3

<4

<5

<10

<4

<9

<4

<8

< 4

<5

<28

<11

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 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-1 34 C s'-,137 Ba-140 La-140 MW-TMI-171 MW-TMI-18D MW-TMI-19D MW-TMI-191 MW-TMI-191 MW-TMI-1 D MW-TMI-2D MW-TMI-31 MW-TMI-41 MW-TMI-4S MW-TMI-5D MW-TMI-6D MW-TMI-6D MW-TMI-61 MW-TMI-7S MW-TMI-8S MW-TMI-91 N2-1 NW-A NW-B NW-C NW-CW OS-14 OS-16 OS-17 OS-18 OSF RW-1 RW-2 10/15/09 10/15/09 10/15/09 10/14/09 10/14/09 10/20/09 10/20/09 10/14/09 10/14/09 10/14/09 10/14/09 10/14/09 10/14/09 10/14/09 10/20/09 10/15/09 10/22/09 10/14/09 10/18/09 10/18/09 10/18/09 10/18/09 10/14/09 10/14/09 10/14/09 10/20/09 10/16/09 10/15/09 04/29/09

< 39

< 32

< 36

< 35

< 34

< 30

< 34

< 20

< 18

< 22

< 19

< 13

< 32

< 34

< 39

< 74

< 36

< 76

< 41

< 47

< 26

< 23

< 18

< 16

< 23

< 21

< 33

< 37

< 35

< 29

< 37

< 43

< 15-

< 29

< 32

< 47

< 20

< 18

< 24

< 20

< 22

< 21

< 31

< 29

< 36

< 89

<45

<44

< 41

< 77

< 15

< 13

< 43

< 38

< 47

< 52

< 31 78 49

< 13

< 24

<4

<8

<4

<8

<4

<9

<3

<4

<7

<2

<5

<2

<5

<1

<2

<3

<6

<4

<9

<4

<8

<3

<4

<9

<3

<6

<2

<4

<2

<3

<5

<.4

<4

<7

<3

<4

<7

<4

<5

<10

<1

<2

<4

<3

<4

<8

<2

<5

<2

<5

<2

<6

<3

<6

<4

<8

<4

<5

<11

<4

<5

<10

<1

<2

<3

<4

<5

<10

<5

<8

<4

<3

<7

<1

<3

<4

<3

<4

<2

<1

<3

<5

<4

<2

<4

<3

<5

<1

<3

<2

<3

<4

<1

<4

<6

<4

<1

<7

<8

<7

<4

<3

<6

<9

<7

<9

< 5

<4

<7

<9

<3

<8

<4

<6

<7

<9

<3

<8

< 14

<8

<2

<4

<8

<4

<6

<5

<8

<4

<6

<2

<4

<2

<4

<2

<3

<4

<5

<4

< 7

<4

<6

<4

<8

<3

<6

<2

<3

<4

<5

<7

<4

<6

<8

<2

<3

<4

<6

<2

<4

<3

<4

<3

<4

<3

<5

<4

<7

<5

.<8

<4

<7

<2

<3

<5

<8

<7

<8

<4

<7

<1

<2

<4

<3

<2

<1

<3

<4

<2

.< 2

<2

<3

<5

<1

<4

<2

,< 2

<3

<4.

<4

<5

<1

<4

<5

<3

<1

<4

<2

<1

<3

<4

<3

<2

<4

<5

<1

<3

<2

<3

<4

<5

<1

<5

<6

<5

<1

<28

<9

<29

<8

<29

<9

<23

<9

<20

<7

<16

<5

<11

<3

<25

<6

<31

<9

<28

<9

< 32

< 11

<23

<7

<19

<7

< 22

<7

< 22

<6

<25

<8

<20

<7

<16

<5

< 29

< 10

<18 c'

<5

<19

<6

<20

<7

<19

<6

<28

<9

<30-

<9

<23

<8

<15

<4

< 30

< 10

<24

<8

<22

<7

<13

<4 RW-2 10/20/09 TRAINING CENTER 10/16/09

TABLE B-II.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM - THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTIONS DATE SITE H-3 SR-90 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 03/17/09 05/18/09 08/11/09 10/16/09 03/17/09 05/18/09 08/11/09 10/16/09 03/17/09 05/18/09 08/11/09 10/16/09

192

164

< 175

153

< 176

< 162

< 183

< 154

< 194

< 162

< 178

<'156

< 0.9

< 0.7

< 0.7 B-10

TABLE B-I1.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 PERIOD TM-SW-E-1 10/16/09

< 34 TM-SW-E-2 10/16/09

< 29 TM-SW-E-3 10/16/09

< 34 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

< 66

< 29

< 32

<3

<4

<8

<3

<7

<3

.<3

<7

<3

<6

.<4

<4

<8

<4

<7

<4

<6

<3

<24

<8

<3

<4

<23

<8

<3

<4

<26

<9

Intentionally left blank

APPENDIX C DATA TABLES

TABLE C-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN WELL WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE 48S MS-2 MS-2 MS-20 MS-21 MS-6 MS-6 MW-i MW-2 MW-TMI-101 MW-TMI-101 MW-TMI-1 OS MW-TMI-12S MW-TMI-1 31 MW-TMI-1 31 MW-TMI-131 MW-TMI-131 MW-TMI-13S MW-TMI-14D MW-TMI-14D MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-16D MW-TMI-161 MW-TMI-161 MW-TMI-191 MW-TMI-41 MW-TMI-6D MW-TMI-6D OS-18 OS-18 RW-2 RW-2 H-3 SR-90 10/16/09 05/12/09 10/14/09 05/19/09 05/12/09 ORIGINAL 10/14/09 DUPLICATE 10/14/09 10/20/09 05112109 08/11/09 10/14/09 05/15/09 04/22/09 03/17/09 ORIGINAL 07/16/09 DUPLICATE 07/16/09 11/18/09 04/16/09 05/07/09 09/10/09 ORIGINAL 02/17/09 DUPLICATE 02/17/09 04/29/09 05/13/09 01/20/09 08/12/09 10/14/09 05/12/09 05/12/09 10/14/09 03/17/09 08/10/09 01/13/09 06/18/09

155

< 158 325 446 737

< 155

< 163 1891 1373 5737 6054 2201 1362 1312 1004 174 1113 937 173 223 271 1221 614 693

< 155

< 158 265 196 909 1097 726 229

+/- 97

+/- 100

+/- 114

< 0.5

< 0.6

< 0.5

0.8

< 0.5 146 134 237 244 162 127 125 119 87 134 116 84 86 113 130 101 107 94 91 122 122 101 89

< 0.8

< 0.6

+

C-1

TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC MS-2 MW-TMI-191 MW-TMI-6D 48S MS-6 MS-6 MW-TMI-101 MW-i COLLECTION PERIOD 10/14/09 10/14/09 10/14/09 10/16/09 10/14/09 10/14/09 10/14/09 10/20/09 N

Be-7 K-40 Mn-54 Co-58 Fe-59 I Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

< 27

< 36

< 32

< 30 ORIGINAL

< 21 DUPLICATE< 30

<18

<18 110 +/- 31

< 2

<61

<3 74 +/- 30

< 2 163 +/- 60

< 3 95 31

< 2

<62

<3 89 32

< 3 135 35

< 2

<3

<2

<3

<4

<3

<4

<8

<3

<4

<2

<8

<4

<6

<3

<1

<3

<2

<3

<2

<3

<5

<2

<5

<4

<6

<5

<3

<2

<3

<5

< 2

<4

<2

<3

<5

<2

<4

<7

< 6

<5

<7

<5

<3

<4

<3

<2

<3

<4

< 26

< 28

< 26

31

<5

<3

<5

<3

"<4

<3

<2

<3

<14

<4

<3

<20

<2

<15

<3

<21

TMI-10-030, Annual Radiological Environmental Operating Report

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