Text

2013 Radiological Environmental Monitoring Program Report
	ML14120A343
Person / Time
Site:	Crane
Issue date:	04/25/2014
From:	Newcomer M; Exelon Generation Co
To:	; Document Control Desk, NRC/FSME, Office of Nuclear Reactor Regulation
References
	TMI-14-051
	Download: ML14120A343 (189)
	v • d • e

A Exeton Generation Three Mile Island Unit 1 Route 441 South P.O. Box 480 Middletown, PA 17057 717-948-8000 Office www.exeloncorp.com April 25, 2014 TMI-14-051 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION UNIT 1 AND UNIT 2 RENEWED OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR 73 DOCKET NOS. 50-289 AND 50-320

SUBJECT:

2013 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT In accordance with TMI Technical Specification 6.9.3.1, TMI-2 Technical Specifications 6.8.1.1, enclosed is the Annual Radiological Environmental Operating Report covering the time period of January 1 through December 31, 2013, for the Three Mile Island Nuclear Station.

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

Sincerely, Ma.*M.ewcomer Plant Manager MMN/LKW/dam Attachments/Enclosures cc:

Region 1 Administrator TMI Senior Resident Inspector TMI-1 Senior Project Manager TMI-2 Project Manager GPU Nuclear Cognizant Officer Department of Environmental Protection, Bureau of Radiation Protection FfYL1~~

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 2013 Prepared By Teledyne Brown Engineering Environmental Services SExeton Generation, Three Mile Island Nuclear Station Middletown, PA 17057 April 2014

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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 III. Program Description................................................................................................

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

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

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

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

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

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

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

11

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

11

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

12

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

13

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

14

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

14

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

14

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

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

15

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

15

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

15

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

16

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

16

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

16

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

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

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

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

19 F. Errata Data..................................................................................................

27 G. Summary of Results - Inter-laboratory Comparison Program.................... 27 V. References...................................................................................................................

30

Appendices Appendix A Tables Table A-1 Appendix B Tables Table B-1 Table B-2 Table B-3 Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2013 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, 2013 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2013 Figqures Figure B-1 Figure B-2 Figure B-3 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2013 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2013 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2013 Data Tables and Figures - Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

ii

Table C-11.1 Table C-II.2 Table C-11.3 Table C-11.4 Table C-I11.1 Table C-111.2 Table C-IV.1 Table C-IV.2 Table C-V.1 Table C-VI.1 Table C-VI.2 Table C-VI.3 Table C-VII.1 Table C-VIII.1 Table C-VIII.2 Table C-VIII.3 Table C-IX.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

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, 2013.

Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Strontium in Predator and Bottom Feeder (Fish)

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

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, 2013.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

iii

Table C-X.1 Table C-X.2 Table C-X.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 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-11.1 Quarterly OSLD Results for Three Mile Island Nuclear Station, 2013.

Mean Quarterly OSLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2013.

Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2013.

Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2013.

Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974-2013.

Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2013.

Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2013.

Mean Cesium-1 37 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2013.

Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2013.

Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2013.

Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2013.

Data Tables and Figures - Comparison Laboratory Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2013.

Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of lodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

iv

Table D-111.1 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 Table E-2 Table E-3 Table E-4 Table E-5 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2013.

Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2013.

Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2013 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2013 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2013 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2013 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2013 Errata Data Annual Radiological Groundwater Protection Program Report (ARGPPR)

Appendix F Appendix G v

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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 2013 through 31 December 2013. During that time period, 1,703 analyses were performed on 1,307 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 and effluent water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Surface, drinking and effluent water samples were also analyzed for concentrations of 1-131. Drinking and effluent water samples were also analyzed for concentrations of gross beta. Effluent water samples were also analyzed for concentrations of Sr-89 and Sr-90. All groundwater, precipitation water and storm water results are now being reported in the ARGPPR, Appendix G. No Sr-89 and Sr-90 activities were detected.

Iodine-1 31 and gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in ten surface water samples and monthly effluent water samples was due to TMINS activities or releases. No other fission or activation products potentially attributed to TMI liquid releases were detected.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected. No fission or activation products were detected in fish samples. Cesium-137 was detected in one sediment sample. Occasionally Cs-1 37 is detected at very low levels (just above LLD) and is not distinguishable from background levels.

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

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

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

Concentrations of naturally occurring K-40 were consistent with those detected in previous years. Occasionally Sr-90 activities are detected and are 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. Strontium-90 activity was 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.

Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued. This change resulted in a slight change in process and reporting of quarterly results. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).

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 2013 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 2013 did not have any adverse effects on the health of the public or on the environment.

IH.

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

A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Landauer and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2013 through 31 December 2013.

A.

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

1.

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

2.

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

3.

To verify inplant controls for the containment of radioactive materials.

4.

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

5.

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

6.

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

B.

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

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

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

Ill.

Program Description A.

Sample Collection Samples for the TMINS REMP were collected for Exelon by Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used by RMC to obtain environmental samples for the TMINS REMP in 2013. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, fish and sediment. Two gallon water samples were collected monthly from continuous samplers located at three surface water locations (A3-2, J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9-1), and one effluent water location (K1 -1). Control locations were A3-2 and Q9-1.

All groundwater and storm water results are now being reported in the ARGPPR, Appendix F. All water samples were collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND) location. Location IND could be affected by TMINS' effluent releases. Sediment samples composed of recently deposited substrate were collected semiannually at three locations (A1-3, J2-1 and K1-3). In addition, one sediment sample was collected annually at the EDCB. Location A1-3 was the control.

AtmosDheric 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.

Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product. Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K1 5-3 and P4-1) from March through November, and monthly from December through February. The control location was K15-3. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory.

Food products were collected monthly at three locations (B1 0-2, El -2 and H 1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2 and H1-2). B10-2 was the control location for both annual and monthly sampling. Five different kinds of vegetation samples and eleven different kinds of vegetation leaves were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation). The OSLDs were placed at locations on and around the TMINS site as follows:

A site boundary ring consisting of 19 locations (A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, 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, B1-1, B2-1, B5-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, 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, 15-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1 and R9-1) extending to approximately 10 miles from the site designed to measure possible exposures to close-in population.

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

The specific dosimeter 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 station has two A120 3:C Optically Stimulated Luminescence Dosimeters enclosed in plastic placed at each location in a frame located approximately three to six feet above ground level. Since each OSLD responds to radiation independently, this provides two independent detectors at each station.

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 2013. The analytical procedures used by the laboratories are listed in Table B-3.

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

1.

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

2.

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

3.

Concentrations of tritium in surface, drinking and effluent water.

4.

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

5.

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

6.

Ambient gamma radiation levels at various site environs.

C.

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

1.

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

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

2.

Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.

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

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

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

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

For food products five nuclides, Be-7, K-40, 1-131, Cs-1 34 and Cs-137 were reported.

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

D.

Program Exceptions For 2013 the TMINS REMP had a sample recovery rate in excess of 99%.

Issue Reports (IR) were initiated to document significant exceptions and missing samples. All exceptions are listed below:

AIR Q15-1

1. For the following sampling periods, the breaker was found tripped.

There was a low volume but the samples were valid and sent for analyses. Breaker was reset and sampler operated normally.

(IR 488572) 01/31/13 - 02/07/13 02/27/13 - 03/07/13 03/14/13 - 03/21/13 A3-1

2. Numerous weekly samples impacted due to substation maintenance and power outages. Temporary power was supplied when available.

Lower than normal volumes occurred, but samples were valid and sent for analyses (IR 1499482). The following weeks were impacted:

03/28/13 - 04/04/13 04/17/13 - 04/25/13 04/25/13 - 05/02/13 05/02/13 - 05/09/13 05/16/13 - 05/23/13 05/23/13 - 05/30/13 Q1 5-1

3. For the following sampling periods, the breaker was found tripped.

There was insufficient or low volume. On 6/26/13 the sampler unit was replaced. Replacement sampler operated normally (IR 1523365/1534450).

04/25/13 - 05/02/13 - sufficient volume, sample was sent, breaker reset 05/30/13 - 06/06/13 - insufficient volume, sample not sent, breaker reset 06/13/13 - 06/20/13 - sufficient volume, sample was sent, breaker reset 06/20/13 - 06/26/13 - insufficient volume, sample not sent, sampler replaced H3-1

4. For the sampling period 05/30/13 - 06/06/13, the sampler was found not running with the breaker tripped. The pump and timer were not operating. The sample volume was insufficient. The samples were not valid and were not sent for analysis. The pump was replaced and breaker reset and the sampler was returned to service (IR 1523365).

E1-2Q

5. For the sampling period 07/04/13 - 07/11/13, the sample pump malfunctioned with the timer still running. The sample volume was insufficient. Per procedure, the samples were not valid and were not sent to the laboratory for analysis. The pump was replaced on 07/13/13 and the sampler was returned to service (IR 1538298).

G2-1

6. For the following sampling periods 09/25/13 - 10/02/13, the sampler was found not running with the breaker tripped. The sample volume was insufficient. The samples were not valid and were not sent to the laboratory for analysis. The pump was replaced on 10/09/13 and the sampler was returned to service. (IR 1574816) 09/25/13 - 10/02/13 - insufficient volume, sample not sent, breaker reset.

10/02/13 - 10/09/13 - insufficient volume, sample not sent, pump replaced.

WATER J1-2

1. Hourly composite samples were missed when the sample line into the Susquehanna became lifted or disconnected from its anchoring cinderblocks due to river conditions. The line was repositioned and reconnected to anchor and sampler verified operating during sample collection. At all times enough sample was collected for the weekly composite sample so no grab sampling was required. (IR 488572)

The impacted sampling periods were:

01/29/13 - 02/05/13 - sufficient volume, no grab sample required 02/05/13 - 02/12/13 - sufficient volume, no grab sample required Q9-1 Surface water

2. For the sampling period 03/26/13 - 04/02/13, the sampler was found unplugged. Plant personnel removed plug to use outlet and inadvertently did not replug. Power was re-established and 26 samples were missed. Sufficient volume was available so no grab sample was required. (IR 488572)

G15-2

3. For the sampling period 06/18/13 - 06/25/13, sampler pump error due to pump jammed/power loss. Unplugged sampler and reset. Sampler operated normally. Sufficient sample volume collected. No grab sample was required. (IR 488572)

G15-3

4. For the following sampling periods, hourly samples were missed when sampler was turned off by water treatment plant personnel due to maintenance and equipment problems with the sewage system (IR 488572).

07/15/13 - 07/23/13 - sufficient volume, no grab required.

07/23/13 - 07/30/13 - sufficient volume, no grab required.

07/30/13 - 08/07/13 - sufficient volume, no grab required.

08/07/13 - 08/13/13 - sufficient volume, no grab required.

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 No program changes for 2013.

IV.

Results and Discussion A.

Aquatic Environment

1.

Surface Water Samples were taken weekly from a continuous sampler at two locations (J1-2 and Q9-1) and weekly grab samples from one location (A3-2). Weekly samples were 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 10 of 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 735 to 5,580 pCi/I. The increased tritium concentrations detected were a result of TMINS releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. The indicator surface water sample is taken just downstream of the liquid discharge outfall where mixing of liquid effluents with the river water is incomplete. More complete mixing is not achieved until liquid effluents pass over the York Haven Dam. This water is normally not consumed by humans. The concentrations detected were well below any regulatory limits (Figures C-1 and C-2, Appendix C).

Iodine Monthly samples from location A3-2 were analyzed for 1-131 activity (Table C-1.2, Appendix C). This is a control or background station sampled because known medical discharges of radiopharmaceuticals occur into the surface water upstream of TMI from a nearby hospital. Iodine-131 from medical discharges was detected in one sample, at a concentration of 1.1 pCi/I.

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

2.

Drinking Water Monthly samples were collected from continuous water samplers at three locations (G15-2, G15-3 and Q9-1). Two locations (G15-2 and 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-11.1, Appendix C). Gross beta activity was detected in 24 of 36 samples. The concentrations ranged from 1.7 to 5.2 pCi/l. Concentrations detected were consistent with those detected in previous years (Figure C-3, Appendix C).

Iodine Monthly samples from all locations were analyzed for concentrations of 1-131 (Table C-11.2, Appendix C). lodine-131 activity was not detected in any samples.

Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was detected in two of 36 samples at concentrations just above the LLD. The concentration ranged from 386 to 537 pCi/L (Figures C-4, Appendix C). The hypothetical dose to the maximum exposed individual from consuming this water during both the time periods was calculated as <0.0061 mrem. (IR 1566255/1596165)

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 all 12 samples. The concentrations ranged from 2.9 to 7.0 pCi/l. Concentrations detected were consistent with those detected in previous years.

Iodine-131 Monthly samples from location K1-1 were analyzed for concentrations of 1-131 (Tables C-111.1, Appendix C). Iodine-131 was not detected in any of the samples.

Tritium Monthly samples from location K1 -1 were analyzed for tritium activity (Table C-111.1, Appendix C). Tritium activity was detected in 11 of 12 samples. The concentrations ranged from 645 to 97,000 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 composite samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-111.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <3.4 pCi/I for Sr-89 and at <0.8 pCi/I for Sr-90.

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

4.

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

5.

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

6.

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

Strontium The edible portions of fish samples from both locations were analyzed for Sr-90 (Table C-IV.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <4.0 pCi/kg wet for Sr-90.

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

Naturally occurring K-40 was found in all fish samples and ranged from 2,924 to 5,278 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were detected.

7.

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

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

Gamma Spectrometry Sediment samples from all locations were analyzed for gamma emitting nuclides (Table C-V.1, Appendix C). Potassium-40 was found in all sediment samples and ranged from 8,026 to 19,290 pCi/kg dry. Cesium-137 was detected in one sediment sample at a concentration of 202 pCi/L. Cesium-1 37 is occasionally found in sediment at very low levels (just above LLD) and is not distinguishable from background levels. No other fission or activation products were detected (Figure C-5, Appendix C).

B.

Atmospheric Environment 1.

Airborne Particulates

a.

Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. Six locations (A3-1, El1-2, F1-3, G2-1, H3-1 and M2-1) were indicator stations located in the highest D/Q sectors and the nearest communities to TMI. One sample (Q15-1) represents the control location at a remote distance from TMINS. The following analyses were performed:

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

Detectable gross beta activity was observed at all locations.

Comparison of results aid in determining the effects, if any, resulting from the operation of TMINS. The results from the closest to the site boundary locations (Group I) ranged from 7 to 38 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3. The results from the intermediate offsite locations (Group II) ranged from 6 to 48 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3. The results from the Control location (Group Ill) ranged from 8 to 44 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. Comparison of the 2013 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 2013 indicate no notable differences between indicator and control stations (Figure C-7, Appendix C).

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

Naturally occurring Be-7 due to cosmic ray activity was detected in 27 samples. These concentrations ranged from 51 to 118 E-3 pCi/m3. All other nuclides were less than the MDC.

b.

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

2.

Terrestrial

a.

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

Iodine-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VIII.1, Appendix C). 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-VIII.2, Appendix C). No Sr-89 or Sr-90 activity was detected. Occasionally Sr-90 is detected and is consistent with those detected in the pre-operational years (Figure C-8, Appendix C).

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

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

The concentrations ranged from 715 to 1,793 pCi/I. All other nuclides were less than the MDC.

b.

Food Products Food products were collected monthly at three locations (B10-2, E1-2 and H1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2, E1-2 and H11-2). B10-2 was the control location for both annual and monthly sampling. The following analyses were performed:

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

Strontium-90 activity was detected in 21 of 26 samples. The concentrations ranged from 3 to 30 pCi/kg wet.

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

Naturally occurring Be-7 due to cosmic ray activity was detected in 20 of 32 samples. These concentrations ranged from 141 to 2,637 pCi/l. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 2,005 to 9,046 pCi/I. All other nuclides were less than the MDC.

C.

Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Optically Stimulated Luminescence Dosimeter (OSLD). Ninety OSLD locations were established around the site. Results of OSLD measurements are listed in Tables C-X.1 to C-X.3, Appendix C All of the OSLD measurements were below 40 mR/quarter, with a range of 14.0 to 30.9 mR/standard quarter. 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, G1 0-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 averaged higher than indicator stations. Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 have a historical high bias, but tracked with the data from all three groups this bias is most likely due to radon and other naturally occurring nuclides, e.g. K-40, emanating from the ground.

D.

Land Use Survey A Land Use Survey conducted in the July through December 2013 and January 2014 growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Normandeau Associates, RMC Environmental Services Division for Exelon to comply with Sections 8.2 of the Plant's Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident, milk-producing animal and garden of greater than 500 ft in each of the sixteen 22 1/2 degree sectors around the site. The results of this survey are summarized below.

Distance in Miles from the TMINS Reactor Buildings 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 Sector Residence Miles N

1.1 NNE 0.7 NE 0.5 ENE 0.5 E

0.4 ESE 1.1 SE 0.7 SSE 0.7 S

2.3 SSW 0.6 SW 0.5 WSW 0.5 W

0.7 WNW 0.4 NW 0.4 NNW 1.1 Garden Miles 1.6 1.2 0.6 0.5 0.5 1.2 1.6 0.8 2.7 2.5 1.0 1.3 1.4 2.2 1.2 2.4 Milk Farm Miles 2.1 4.2 4.5 1.1 3.2 1.4 4.9, 14.4 3.7 Meat Animal Miles 2.1 2.4 2.4 1.1 1.1 1.1 1.4 3.3 4.9 2.4 E.

Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2013 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2013 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 0.21 mrem. This dose is equivalent to 0.07% 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. Optically Stimulated Luminescent Dosimetry (OSLDs) positioned in the environment around TMINS provide measurements to determine external radiation doses to humans. Samples of air, water and food products are used to determine internal doses.

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

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

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

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

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

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

Actual monthly Susquehanna River flows are obtained from the USGS Stream gauging station 01570500 located at Harrisburg, PA.

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, 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 receptors. 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, each year the hypothetical individual 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. The exposure pathway through goat milk does not currently exist. Therefore, goat milk is not included.

2.

Result of Dose Calculations The maximum hypothetical doses due to 2013 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 2013 operations at TMINS were well below the Federal dose limits (USEPA 40 CFR 190) and the guidelines of USNRC 10 CFR 50 App. I. This conclusion was supported by radionuclide concentrations detected in actual environmental samples.

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

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

As shown on Table 2, the maximum hypothetical whole body dose received by an individual from 2013 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.21 mrem. This dose is equivalent to 0.07% percent of the dose that an individual living in the TMI area receives each year from natural background radiation (311 mrem).

The low doses calculated for 2013 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).

In conclusion, radioactive materials related to 2013 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 2013 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 2013 did not have any adverse effects on the health of the public or on the environment.

TABLE 1 Calculated Maximum Hypothetical Doses to an Individual from 2013 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 2.48E-2 1.84E-4 2.59E-2 2.92 E-4 1.04E-4 0*

1.60E-4 0*

1.81E-I 2.67E-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-1 and TMI-2 Combined**

0.58 Total from Site 0.72

*This sums together TMII-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 dosimeter data. For this calculation, exposure is assumed to be equal to dose.

The direct radiation dose from 2013 TMINS operations was 0.51 mrem. This dose was based on a maximum net fence-line exposure rate of 0.94 mR/std qtr 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-I and TMI-2 effluents (0.21 mrem) and the dose from direct radiation (0.51 mrem) yielded a maximum hypothetical dose of 0.72 mrem.

TABLE 2 Calculated Whole Body Doses to the Maximum Individual From 2013 TMI-1 and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)

TMI-I TMII-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.

2.48E-2 1.84E-4 1.04E-4 0*

4.50E-2 2.67E-5 Individual Whole Body Dose Due to TNMI-I and TMI-2 Operations:

Individual Whole Body Dose Due to Natural Background Radiation (1) 0.21 mren/vyr 311 mrem/yr (1) NCRP 160- (2009)

Figure 1 Exposure Pathways For Radionuclides Routinely Released From TMINS NOBLE GASES (Xe,Kr)

Plume exposure RADIOIODINES (1-131, 1-133)

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

Consumption of milk, meat.

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

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

Shoreline exposure and consumption of milk, meat, fish, water, fru its, and vegetables TR(TIUM (H-3)

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

Errata Data Teledyne Brown Engineering (TBE) provides data results [activity, uncertainty and minimum detectable concentration {MDC}]. We are required to calculate the MDC using a multiplier of 4.66.

4.66

MDA =

At 2.22 (v)(y) (a)(')

Where:

At = counting time for sample (minutes) p3 = background rate of instrument blank (cpm) 2.22 = dpm/pCi or: 2.22 x 106 dpm/ItCi v = volume or mass of sample analyzed y = chemical yield F = efficiency of the counter The formulas for calculating the activity, uncertainty and MDC are contained in the software of the counting equipment. For the gamma system, when the new detector number 08 was added to the system in January 2012, the default value of 3.29 was used to calculated the MDCs on detector 08. The activity and uncertainty were not affected. The multiplier has been changed from 3.29 to the required 4.66.

When the MDCs are recalculated using 4.66, the MDC values will increase by 41.6%. The greatest impact will be on the short-lived nuclides which have an LLD requirement, e.g. 1-131, Ba-140 and La-140. Which means there could be some missed LLDs which will be identified in the Errata Data Appendix table of the 2013 annual report. This is not a reportable issue for the NRC. There is also the possibility that naturally produced nuclides that were detected would become a non-detect, e.g Th-228, Th-230, etc.

G.

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

1.

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

2.

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

3.

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

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

For the TBE laboratory, 178 out of 185 analyses performed met the specified acceptance criteria. Seven analyses (Sr-89 and Sr-90 in milk, Co-57, Zn-65 and Sr-90 in soil, Cs-1 34 in air particulate and Sr-90 in vegetation [two low warning in a row]) did not meet the specified acceptance criteria or internal QA requirements for the following reason:

1.

Teledyne Brown Engineering's Analytics September 2013 Sr-89 in milk result of 63.9 pCi/L was lower than the known value of 96.0 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15

2.

Teledyne Brown Engineering's Analytics September 2013 Sr-90 in milk result of 8.88 pCi/L was lower than the known value of 13.2 pCi/L. The failure was a result of analyst error and was specific to the Analytics sample. Client samples for the associated time period were evaluated and no client samples were affected by this failure. NCR 13-15

3. & 4.Teledyne Brown Engineering's MAPEP September 2013 Co-57 and Zn-65 in soil were evaluated as failing the false positive test.

While MAPEP evaluated the results as failures, the gamma software listed the results as non identified nuclides. The two nuclides would never have been reported as detected nuclides to a client. MAPEP does not allow laboratories to put in qualifiers for the submitted data nor "less than" results. MAPEP evaluates results based on the relationship between the activity and the uncertainty. MAPEP spiked the soil sample with an extremely large concentration of Eu-1 52, which was identified by the gamma software as an interfering nuclide, resulting in forced activity results that were evaluated by MAPEP as detected Co-57 and Zn-65. No client samples were affected by these failures. NCR 13-14

5.

Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in soil result of 664 Bq/kg was higher than the known value of 460 Bq/kg, exceeding the upper control limit of 598 Bq/kg. An incorrect Sr-90 result was entered into the MAPEP database. The correct Sr-90 activity of 322 Bq/kg would have been evaluated as acceptable with warning.

No client samples were affected by this failure. NCR 13-14

6.

Teledyne Brown Engineering's MAPEP September 2013 Cs-1 34 in air particulate activity of -0.570 Bq/sample was evaluated as a failed false positive test, based on MAPEP's evaluation of the result as a significant negative value at 3 standard deviations. A negative number would never have been reported as a detected nuclide to a client, therefore no client samples were affected by this failure.

NCR 13-14

7.

Teledyne Brown Engineering's MAPEP September 2013 Sr-90 in vegetation result was investigated due to two low warnings in a row. It appears the September sample was double spike with carrier, resulting in a low activity. With a recovery of around 50%

lower, the Sr-90 result would have fallen within the acceptance range. No client samples were affected by this issue. NCR 13-14 For the EIML laboratory, 89 of 92 analyses met the specified acceptance criteria. Three analyses (AP - Gross Alpha, Soil - Sr-90 and Co-57) did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc., Midwest Laboratory's MAPEP February 2013 air particulate gross alpha result of 0.14 Bq/total sample was lower than the known value of 1.20 Bq/total sample, exceeding the lower control limit of 0.36 Bq/total sample. The filter was recounted overnight. No significant activity could be detected.

2. Environmental Inc., Midwest Laboratory's MAPEP February 2013 soil Co-57 result of 408.40 Bq/kg was lower than the known value of 628.0 Bq/kg, exceeding the lower control limit of 440.0 Bq/kg.

The sample was reanalyzed using additional fuming nitric separations. The reanalysis result of 574.4 fell within the control limits.

3. Environmental Inc., Midwest Laboratory's MAPEP August 2013 soil C-57 result of 699.60 Bq/kg was higher than the known value of 0.00 Bq/kg, exceeding the upper control limit of 5.00 Bq/kg.

Interference from Eu-152 resulted in misidentification of Co-57.

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

V.

References 1.

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

2.

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

3.

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

4.

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

5.

National Council of Radiation Protection and Measurements Report No.

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

2009.

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Intentionally left blank

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2013 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

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 1-131 24 12 24 2000 2025 (10/12)

(735/5580)

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

NA 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD

<LLD 1.1 (1/12)

<LLD

<LLD 1.1 (1/12) 2025

(.10/12)

(735/5580) 0 0

0 J 1-2 INDICATOR WEST SHORE; TMI 0.5 MILES S OF SITE A3-2 CONTROL SWATARA CREEK 2.5 MILES N OF SITE SURFACE WATER (PCI/LITER) 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, 2013 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

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

<LLD 18

<LLD 60

<LLD 15

<LLD 4

3.1 (1/824)

(1.8/5.2) 1

<LLD 2000 462 (2/24)

(386/537)

<LLD

<LLD 0

0 0

0 DRINKING WATER (PCIVLITER) 6 R-B 1-131 36 36 36 2.4 (6/12)

(1.7/2.9) 3.3 (11/12)

(1.8/5.2)

G 15-2 INDICATOR WRIGHTS WATER SUPPLY 13.3 MILES SE OF SITE

<LLD

<LLD 0

H-3 462 (2/12)

(386/537)

G 15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE DRINKING WATER (PCI/LITER)

GAMMA 36 MN-54 15

<LLD

<LLD 0

0 CO-58 15

<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, 2013 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

MEAN (M.)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD

<LLD 0

0 0

DRINKING WATER (PCI/LITER) 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, 2013 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

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)

GR-13 1-131I 12 12 12 4

4.8 (12/12)

(2.9/7.0)

<LLD H-3 2000 20928 (11/12)

(645/97000)

NA NA NA NA NA 4.8 (12/12)

(2.9/7.0)

KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 20928 (11/12)

(645/970001 KI-I INDICATOR MAIN STATION LIQ. DISCHARGE ONSITE 0

0 0

SR-89 SR-90 2

5

<LLD 2

<LLD EFFLUENT WATER (PCI/LITER)

GAMMA MN-54 12 CO-58 FE-59 I5

<LLD 15

<LLD 30

<LLD NA NA NA 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, 2013 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

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

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 18

<LLD 60

<LLD 15

<LLD I0

<LLD NA NA NA NA NA NA NA NA 0

0 0

EFFLUENT WATER (PC ULITER) 0 0

BOTTOM FEEDER (PCI/KG WET)

SR-90 4

<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, 2013 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (NM)

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 GAMMA K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 4

NA 3300 (2/2)

(2924/3676) 130

<LLD 130

<LLD 260

<LLD 3669 (2/2)

(3492/3846) 3669 (2/2)

(3492/3846)

BKGB CONTROL CITY ISLAND UPSTREAM OF DISCHARGE BOTTOM FEEDER (PCIJKG WET) 130

<LLD 260

<LLD 130

<LLD 150

<LLD 10

<LLD

<LLD 0

0 0

PREDATOR (PCI/KG WET)

SR-90 4

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, 2013 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

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 LIM]T (F)

(F)

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

(LLD)

MEASUREMENTS GAMMA K-40 MN-54 4

NA 3588 (2/2)

(3349/3826) 130

<LLD 4130 (2/2)

(2982/5278) 4130 (2/2)

(2982/5278)

BKGP CONTROL CITY ISLAND UPSTREAM OF DISCHARGE

-~

CO-58 PREDATOR (PCI/KG WET)

FE-59 CO-60 ZN-65 CS-134 CS-137 GAMMA 130

<LLD 260

<LLD 130

<LLD 260

<LLD 130

<LLD 150

<LLD

<LLD 0

0 0

0 SEDIMENT 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, 2013 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (MI 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 (PCI/KG DRY)

K-40 Ge SEDIMENT (PCI/KG DRY)

MN-54 CO-58 CO-60 CS-134 CS-137 GR-B NA 14580 (5/5)

(8026/19290)

NA

<LLD NA

<LLD 150

<LLD 180 202 (1/5) 10 17 (297/309)

(6/48)

NA 72 (23/24)

(51/118)

NA

<LLD 15915 (2/2)

(13750/18080) 18710 (I/I)

<LLD

<LLD 0

0 EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE 0

AIR PARTICULATE (E-3 PCI/CU.METER) 359 28

<LLD 18 (47/50)

(8/44) 70 (4/4)

(58/77)

<LLD 202 (1/1) 18 (47/50)

(8/44) 78 (4/4)

(70/94)

EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE OF SITE Q15-I CONTROL WEST FAIRVIEW 13.5 MILES NW OF SITE A3-1 INDICATOR MIDDLETOWN 2.6 MILES N OF SITE 0

GAMMA BE-7 0

0 MN-54 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, 2013 NAME OF FACILITY:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

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)

CO-58 CO-60 NB-95 ZR-95 CS-134 CS-137 GAMMA 1-131 1-131 NA

<LLD NA

<LLD 50

<LLD 60

<LLD

<LLD 0

0 0

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

MILK (PCI/LITER) 359 70

<LLD

<LLD 110 20

<LLD SR-89 5

<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, 2013 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (MN)

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 SR-90 20 110 2

<LLD

<LLD 0

MILK (PCI/LITER) 0 GAMMA K-40 CS-134 CS-137 BA-140 LA-140 NA 1265 (88/88)

(715/1793) 1312 (22/22)

(1132/1465) 1395 (22/22)

(1129/1526)

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

<LLD 18

<LLD 60

<LLD 15

<LLD

<LLD 0

0 0

VEGETATION SR-90 26 10 13 (PCI/KG WET)

(12/13)

(4/27)

GAMMA 32 BE-7 NA 615 (11/16)

(141/1435)

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) 10 (9/13)

(3/30) 930 19/16)

(147/2637) 14 (11/12)

(4/27) 930 (9/16)

(147/2637)

H 1-2 INDICATOR RED HILL MARKET, ALONG ROUTE 44 1.0 MILES SSE OF SITE B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2013 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 2013 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:

INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (N1)

LOCATIONS LOCATION MEDJUM 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)

K-40 1-131I NA 4186 (16/16)

(2431/8483) 4903 (16/16)

(2005/9046) 4903 (16/16)

(2005/9046)

B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.1 MILES NNE OF SITE 0

CS-134 CS-137 60

<LLD 60

<LLD 80

<LLD

<LLD 0

0 DIRECT RADIATION (MILLI-ROENTGEN/STD.MO.)

OSLD-QUARTERLY 360 NA 19.9 (316/316)

(14.0/30.9) 22.1 (44144)

(17.6/29.7) 29.6 (4/4.)

(29.4/29.9)

H8-1 INDICATOR SAGINAW ROAD, STARVIEW 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

Intentionally left blank

TABLE B-i:

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

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, 2013 Sample Medium Station Map Distance Code Number (miles)

Azimuth Description AQS ID APAIID SW ID ID ID ID ID ID A1-3 A1-4 A3-1 A3-2 A5-1 A9-3 B1-1 B1-2 B2-1 B5-1 B10-1 1

0.5 1

0.3 2

2 2

3 1

2 2

2.7 2.7 4.4 8.0 0.6 0.4 1.9 4.9 ID 3

9.2 FP ID ID ID ID ID AQF ID ID ID ID ID AP, Al, ID, FP ID M

ID ID ID ID ID B10-2 C1-1 C1-2 C2-1 C5-1 C8-1 Control D1-1 D1-2 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 GI-5 G1-6 G2-1 G2-4 G5-1 G10-1 G15-1 G15-2 G15-3 1

0.2 1

0.5 3

1 1

2 2

3 AP, Al ID ID M

ID ID 10 0.7 0.3 1.5 4.7 7.1 1.6 5.2 10.8 0.4 0.2 1.1 2.0 4.7 6.7 0.5 0.2 0.6 0.2 1.3 3.2 4.7 9.4 22 0.7 0.2 0.3 0.3 1.4 1.7 4.8 9.7 14.4 13.3 15.7 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 356' N of site at Swatara Creek, Middletown 30 N of site on Vine Street Exit off Route 283 20 N of site at Duke Street Pumping Station, Hummelstown 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 210 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey 310 NNE of site at Milton Hershey School, Hershey 370 NE of site along Route 441 N 500 NE of Reactor Building on top of dike, TMI 440 NE of site at Middletown Junction 430 NE of site on Kennedy Lane 480 NE of site at Schenk's Church on School House Road All locations where finfish are collected above Dock St.

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

660 ENE of site off Beagle Road 640 ENE of site along Route 241, Lawn 970 E of site at TMI Visitor's Center 970 E of Reactor Building on top of dike, TMI 960 E of site at farm on Pecks Road 970 E of site along Hillsdale Rd. (N of Creek Rd.)

820 E of site at intersection of North Market Street (Route 230) and Zeager Road 880 E of site along Hummelstown Street, Elizabethtown 1170 ESE of site near entrance to 500 kV Substation 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI 1120 ESE of site in 500 kV Substation 1220 ESE of Reactor Building on top of dike, TMI 1190 ESE of site along Engle Road 1040 ESE of site at farm on Turnpike Road 1090 ESE of site along Amosite Road 1120 ESE of site along Donegal Springs Road, Donegal Springs 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster 1450 SE of site along Route 441 S 1300 SE of Reactor Building on top of dike, TMI 1430 SE of Reactor Building on top of dike, TMI 1390 SE of Reactor Building on top of dike, TMI 1260 SE of site at farm on Becker Road 1380 SE of site on Becker Road 131' 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 1240 SE of site at Lancaster Water Treatment Plant ID ID ID ID ID Al, AP, M ID ID ID ID DW DW B-2

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2013 Sample Medium ID FP AP, Al, ID ID Station Map Distance Code Number (miles)

Azimuth Description H1-1 Hi1-2 H3-1 H5-1 H8-1 H15-1 2

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

7.4 3

13.2 1

0.8 1

0.5 1

0.3 2

1.4 ID ID ID ID ID ID M

ID ID ID ID ID ID ID J1-1 J11-2 J 1-3 J2-1 J3-1 J5-1 J7-1 J15-1 K1-1 K1-3 K1.-4 K2-1 K3-1 K5-1 K8-1 K15-1 K15-3 U1-11 L1-2 L2-1 L5-1 L8-1 L15-1 M1-1 M1-2 M2-1 M5-11 M9-1 N11-11 N1-3 N2-1 N5-1 N8-1 N15-2 2

2 3

3i 1

2 2

2 3

2.7 4.9 6.5 12.6 0.2 0.2 0.2 1.2 2.0 4.9 7.5 167' SSE of site, TMI 1510 SSE of site along Route 441, Red Hill Market 160' SSE of site in Falmouth-Collins Substation 158' SSE of site by Guard Shack at Brunner Island Steam Electric Station 163' SSE of site along Saginaw Road, Starview 1570 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 176' S of site, TMI 1880 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River

189, S of Reactor Building just S of SOB, TMI 1790 S of site in Susquehanna River just upstream of the York Haven Dam 1790 S of site at York Haven/Cly 181' S of site along Canal Road, Conewago Heights 176' S of site off of Maple Street, Manchester 1830 S of site in Met-Ed York Load Dispatch Station 210' On site at RML-7 Main Station Discharge Building 212' SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River 2090 SSW of Reactor Building on top of dike behind Warehouse 2, TMI 200' SSW of site on S Shelley Island 206' SSW of site along Rt. 262, N of Cly 202' SSW of site along Conewago Creek Road, Strinestown 1960 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View 2030 SSW of site behind McDonald's and next to child care center, Weiglestown 2050 SSW of site at farm along S Salem Church Rd, Dover 236' SW of site on top of dike W of Mech. Draft Cooling Tower, TMI 221 SW of site on Beech Island 2240 SW of site along Route 262 228' SW of site at intersection of Stevens and Wilson Roads 2250 SW of site along Rohlers Church Rd., Andersontown 226' SW of site on W side of Route 74, rear of church, Mt.

Royal 2500 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI 2520 WSW of site on E side of Shelley Island, Lot #157 2560 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newbenytown 2430 WSW of site along Alpine Road, Maytown 2740 W of site on W side of Shelley Island, between lots #13 and #14 2740 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI 2610 W of site at Goldsboro Marina 2680 W of site off of Old York Road along Robin Hood Drive 2620 W of site along Route 382, 1/2 mile north of Lewisberry 2750 W of site at intersection of Lisburn Road and Main Street, Lisbum 3030 WNW of site on Shelley Island 3

12.8 3

14.4 1

0.1 2

2 3

3 0.5 1.8 4.1 8.0 11.8 ID AP, Al, ID ID ID ID ID ID ID ID ID ID 1

0.1 1

0.4 2

1.3 2

4.3 3

8.7 1

0.7 1

0.1 2

2 3

3 1.2 5.0 7.7 10.4 P1-1 1

0.4 B-3

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2013 Sample Medium Station Map Distance Code Number (miles)

Azimuth Description ID ID M

ID ID ID ID P1-2 1

ID ID SW, DW, ID AP, Al, ID P2-1 P4-1 P5-1 P8-1 Q1-1 Q1-2 Q2-1 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 2

2 3

3 0.1 2920 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 2.0 2830 WNW of site along Route 262 3.7 2950 WNW of site at farm on Valley Road 5.0 284' WNW of site at intersection of Valley Road (Route 262) and Beinhower Road 8.0 2920 WNW of site along Evergreen Road, Reesers Summit 0.5 317° NW of site on E side of Shelley Island 0.2 321' NW of Reactor Building on fence W of Warehouse 1, TMI 1.9 3100 NW of site along access road along river 5.0 317' NW of site along Lumber Street, Highspire 8.5 3100 NW of site at the Steelton Water Company 13.4 309' NW of site behind West Fairview Fire Dept. Social Hall (abandoned) 0.2 3350 NNW of Reactor Building along W fence, TMI 0.7 334' NNW of site on central Henry Island 2.6 3410 NNW of site at Crawford Station, Middletown 4.9 339' NNW of site at intersection of Spring Garden Drive and Route 441 8.0 341' NNW of site at intersection of Derry and 66th Streets, Rutherford Heights 11.2 3320 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park ID ID ID ID ID ID IDENTIFICATION KEY ID

= Immersion Dose (OSLD)

SW = Surface Water Al

= Air Iodine AP = Air Particulate FP = Food Products (Green Leafy Vegetation, Fruits, Vegetables)

EW DW M

AQF 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, 2013 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

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

Nuclear Station)

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

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

Nuclear Station)

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

Nuclear Station)

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

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

Nuclear Station)

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

Nuclear Station)

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

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

Nuclear Station)

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

Nuclear Station)

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

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2013 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

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

Nuclear Station)

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

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

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

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

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

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

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

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

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

Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in other techniques Ashed Samples w

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2013 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Sediment Gamma Semi-annual grab ER-TMI-03 Collection of sediment samples for 500 grams (dry)

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

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

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

Station)

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion Monthly all other exchange times Milk Strontium-Quarterly composite ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 of Bi-weekly and radiological analysis (Three Mile Island Nuclear monthly grab Station)

Enc. Inc., SR-07, Determination of Sr-89 and Sr-90 in Milk samples (Ion Exchange Batch Method)

TBE, TBE-2023 Compositing of samples Milk Gamma Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy sample when cows radiological analysis (Three Mile Island Nuclear are on pasture.

Station)

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

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

I I gamma spectroscopy

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2013 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Vegetation Strontium-Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 grab sample radiological analysis (Three Mile Island Nuclear Station)

Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in Ashed Samples OSLD Optically Quarterly OSLDs ER-TMI-02 Collection of OSLD samples for 2 badges with 3 Landauer Incorporated Stimulated comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Luminescence A120 3:C Landauer Station)

Dosimetry Incorporated elements.

0

AL Figure B-1 Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2013 B-9

Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2013 B-10

Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2013 B-11

Intentionally left blank

APPENDIX C DATA TABLES AND FIGURES -

PRIMARY LABORATORY

Intentionally left blank

Table C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD J1-2 Q9-1 12/31/12 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 12/03/13 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 12/03/13 12/31/13 735 935 1180 1500 1890 1220 5580 955 2730 3520

< 172

< 178

+/- 143

+/- 158

+/- 171

+/- 203

+/- 242

+/- 185

+/- 597

+/- 167

+/- 314

+/- 401

< 169 (1)

< 166

< 161 (1)

< 169

< 178

< 194

< 180

< 186

< 164

< 197

< 172

< 166 MEAN 2025 +/- 3057 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 Table C-1.2 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD A3-2 01/08/13 02/05/13 03/05/13 04/09/13 05/07/13 06/03/13 07/09/13 08/07/13 09/10/13 10/08/13 11/05/13 12/10/13 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 12/03/13 12/31/13

< 0.5 1.1 +/- 0.6

< 0.8

< 0.9

< 0.8

< 0.7

< 0.6

< 0.7

< 0.6

< 0.7

< 0.8 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD J1-2 12/31/12 -01/29/13

< 5

< 6

< 9

< 7

< 9

< 7

< 11

< 5

< 7

< 29

< 9 01/29/13 -02/26/13 (1)

< 4

<4

< 8

< 3

< 7

< 3

< 7

< 3

< 4

<20

< 6 02/26/13 -04/02/13

< 4

< 10

< 5

< 8

< 5

< 7

< 4

< 5

< 23

< 8 04/02/13 -04/30/13

< 6

< 13

< 5

< 11

<6

< 10

< 6

< 25

< 8 04/30/13 -05/28/13

< 6

< 12

< 5

< 9

< 5

< 8

< 5

< 6

< 25

< 7 05/28/13 -07/02/13

< 4

< 10

< 5

< 9

< 4

< 9

< 4

< 5

< 24

< 8 07/02/13 -07/30/13

< 6

< 5

< 12

< 7

< 11

< 7

< 12

< 5

< 6

< 35

< 11 07/30/13 -09/03/13

< 5

< 4

< 11

< 6

< 12

< 6

< 9

< 5

< 6

< 34

< 11 09/03/13 -10/01/13

< 7

< 15

< 8

< 17

< 7

< 14

< 6

< 8

< 30

< 12 10/01/13 -10/29/13

< 5

< 12

< 6

< 12

< 6

< 11

< 5

< 6

< 30

< 7 10/29/13 -12/03/13

< 7

< 6

< 11

< 5

< 11

< 7

< 10

< 5

< 6

< 27

< 13 12/03/13 - 12/31/13

< 4

< 3

< 9

< 4

< 8

< 3

< 8

< 3

< 4

< 28

< 11 MEAN Q9-1 12/31/12 - 01/29/13

< 5

< 12

< 7

< 12

< 6

< 11

< 6

< 27

< 9 01/29/13 -02/26/13

< 4

< 8

< 4

< 9

< 5

< 8

< 4

< 5

< 21

< 8 02126113 -04/02/13 (1)

< 5

< 10

< 5

< 10

< 5

< 9

<4

< 5

< 22

<8 04/02/13 - 04/30/13

< 7

< 6

< 15

< 6

< 10

< 7

< 11

< 6

< 7

< 34

< 13 04/3013 -05/28/13

< 6

< 5

< 10

< 5

< 9

< 5

< 9

< 5

< 26

< 9 05/28/13 -07/02/13

< 5

< 11

< 4

< 10

< 4

< 9

< 5

< 6

< 27

< 8 07/02/13 -07130113

< 5

< 10

< 5

< 10

< 5

< 11

< 5

< 29

< 9 07/30/13 -09/03/13

< 6

< 13

< 5

< 7

< 5

< 10

< 5

< 28

< 7 09/03/13 -10/01/13

< 6

< 7

< 13

< 4

< 12

< 6

< 10

< 5

< 7

< 32

< 11 10/01/13 -10/29/13

< 7

< 6

< 11

< 6

< 13

< 7

< 11

< 5

< 7

< 33

< 11 10/29/13 - 12/03/13

< 6

< 10

< 8

< 14

< 7

< 13

< 6

< 35

< 11 12/03/13 - 12/31/13

< 4

< 8

< 4

< 8

< 4

< 6

< 3

< 4

< 26

< 9 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/31/12 - 01/29/13 2.3 +/- 1.4

< 2.1

< 2.0 01/29/13 - 02/26/13 1.8 +/- 1.1

< 1.5

< 1.5 02/26/13 - 04/02/13 3.3 +/- 1.1

< 1.5

< 1.6 04/02/13 - 04/30/13 3.0 +/- 1.1 1.9 +/- 0.9 1.7 +/- 0.9 04/30/13 - 05/28/13

< 2.1

< 2.0

< 2.0 05/28/13 - 07/02/13 2.0 +/- 1.0 (1) 1.8 +/- 1.0 2.3 +/- 0.9 07/02/13 - 07/30/13 3.4 +/- 1.3 2.2 +/- 1.2 (1) < 1.8 07/30/13 - 09/03/13 3.8 +/- 1.1 2.8 +/- 1.0 (1) 2.6 +/- 1.0 09/03/13 - 10101/13 3.5 +/- 1.0 3.3 +/- 1.0 2.7 +/- 1.0 10/01/13 - 10/29/13 2.5 +/- 1.1 2.7 +/- 1.1 2.6 +/- 1.0 10/29/13 - 12/03/13 5.1 +/- 1.1 4.5 +/- 1.1 2.9 +/- 1.0 12/03/13 - 12/31/13 5.2 +/- 1.9

< 2.4

< 2.3 MEAN 3.3 +/- 2.2 2.7 +/- 1.9 2.4 +/- 0.8 Table C-11.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 1/31/12 - u11/913

<..6

< 0.6

< 0.5 01/29/13 - 02/26/13

< 0.6

< 0.6 02/26/13 - 04/02/13

< 0.7

< 0.6

< 0.6 04/02/13 - 04/30/13

< 0.6

< 0.9 04/30/13 - 05/28/13

< 0.5

< 0.7

< 0.5 05/28/13 - 07/02/13

< 0.7 (1)

< 0.9

< 0.8 07/02/13 - 07/30/13

< 0.8

< 0.6 (1)

< 0.7 07/30/13 - 09/03/13

< 0.7

< 0.7 (1)

< 0.7 09/03/13 - 10/01/13

< 0.7

< 0.9

< 0.8 10/01/13 - 10/29/13

< 0.8

< 0.7

< 0.7 10/29/13 - 12/03/13

< 0.6

< 0.7

< 0.6 12/03/13 - 12/31/13

< 0.5

< 0.8

< 0.8 MEAN Table C-II.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/31/12 01/29/13

< 166

< 174

< 171 01/29/13 - 02/26/13

< 183

< 153

< 166 02/26/13 - 04/02/13

< 172

< 163

< 157 04/02/13 - 04/30/13

< 169

< 167

< 166 04/30/13 - 05/28/13

< 174

< 175

< 172 05/28/13 - 07/02/13

< 192 (1)

< 193

< 193 07/02/13 - 07/30/13

< 179 537 +/- 144 (1) < 182 07/30/13 - 09/03/13

< 188

< 187 (1) < 190 09/03/13 - 10/01/13

< 172

< 184

< 171 10/01/13 - 10/29/13

< 200 386 +/- 141

< 193 10/29/13 - 12/03/13

< 171

< 172

< 168 12/03/13 - 12/31/13

< 176

< 180

< 172 MEAN 462 +/- 214 THE MEAN AND TWO STANDARD DEVIATION 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, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 SITE COLLECTION PERIOD G15-2 12/31/12 - 01/291 01/29/13 - 02/261 02/26/13

- 04/021 04/02/13 - 04/301 04/30/13 - 05128/

05/28/13 - 07/021 07/02/13 - 07/301 07/30/13 - 09/03/

09/03/13 - 10/01/

10/01/13 - 10/291 10/29/13 - 12/031 12/03/13 - 12/31/

'13

<6

<4

<3

<5

<4 (1) < 9

<6

<7

<6

<5

<6

<4

<6

<4

<3

<6

<4

<9

<5

<6

<5

<6

<4 MEAN

< 12

<9

<5

< 13

< 10

< 18

< 10

< 13

< 14

< 11

<8

< 12

<9

< 10

< 13

< 11

< 12

<15

< 13

< 12

< 14

<9

<5

<3

<6

<5

<9

<5

<6

<8

<6

<3

<4

<5

<8

<6

<5

<7

<6

<7

<4

< 12

<8

<6

<9

<8

< 21

< 11

< 13

< 15

< 11

<7

<8

<9

< 10

< 12

< 13

< 12

< 10

< 14

<9

< 10

< 15

<9

<6

<5

<4

<6

<4

<9

<6

<7

<6

<4

<6

<4

<5

<6

<7

<6

<5

<6

<5

<8

<5

< 12

<8

<6

< 11

<9

< 16

<9

< 11

<9

< 10

<9

<7

< 10

<7

<9

< 11

<9

< 10

<9

< 13

< 10

<9

< 12

<8

<5

<4

<3

<5

<4

< 10

<5

<6

<3

<6

<5

<3

<6

<5

<8

<5

<6

<7

<8

<7

<4

<6

<4

<7

<6

<5

<6

<7

<6

<5

< 25

23

< 16

< 27

< 21

< 43

< 32

< 35

< 31

< 29

< 28

< 32

21

< 27

< 31

< 24

< 30

< 39

< 33

<34

< 30

< 34

< 29

<8

<6

<5

<9

<8

< 13

<11

< 10

< 12

< 10

< 13

<8 G15-3 12/31/12 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10129113 12/03/13

- 01/29/13

- 02/26/13

- 04/02/13

- 04/30/13

- 05/28/13

- 07/02/13

- 07/30/13

- 09103113

- 10/01/13

- 10/29/13

- 12103/13

- 12/31/13

<6

<4

<5

<6

<5

<4

<6

<5

<6

<4

<5

<4

<5

<7

<5

<6

<4

<5

<6

<4

<5

<3

<4

<6

<5

<7

<5

<6

<4 6

7 8

12 7

9 11 11 11 9

11 9

(1)

MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION

Table C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE 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 12/31/12 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 12/03/13

<5

<4

<5

<6

<5

<6

<5

<4

<5

<7

<6

<5

<7

<9

<11

< 13

< 11

< 10

< 15

<5

<4

<5

<6

<5

<7

<6

<5

<6

<9

<8

< 10

< 11

< 10

< 13

< 14

< 11

<9

< 10

< 15

<5

<4

<5

<4

<6

<5

<6

<7

<8

<7

<8

<9

< 12

< 10

<9

< 10

< 11

<4

<5

<6

<5

<7

<5

<6

< 24

< 20

< 23

< 21

< 25

< 28

< 31

< 32

< 29

< 36

<7

<6

<8

< 11

<9

<4

< 11

<8

< 11

< 10

<7 12/03/13 - 12/31/13

<4

<9

<4

<8

<4

<7

<4

<5

<29

<9 MEAN

Table C-II.1 CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION KI-1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD GR-B 1-131 H-3 SR-89 SR-90 K1-1 12/31/12 12131/12 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/02/13 08/07/13 09/03/13 10/01/13 10/29/13 12/03/13

- 01/29/13

- 07/02/13

- 02/26/13

- 04/02/13

- 04/30/13

- 05/28/13

- 07/02/13

- 07/30/13

- 12/31/13

- 09/03/13

- 10/01/13

- 10/29/13

- 12/03/13

- 12/31/13 3.5 +/- 1.5

< 0.5 3.0 +/- 1.1 2.9 +/- 1.2 3.7 +/- 1.1 3.0 +/- 1.5 6.4 +/- 1.3 7.0 +/- 1.6 6.0 +/- 1.6 5.0 +/- 1.3 6.2 +/- 1.3 4.2 +/- 1.1 6.5 +/- 2.0 4.8 +/- 3.1

< 0.5

< 0.8

< 0.7

< 0.9

< 0.6

< 0.7

< 0.7 4060 +/- 454 4980 +/- 545 4680 +/- 510 15600 +/- 1610 28000 +/- 2840 12900 +/- 1330 97000 +/- 7060 7840 +/- 838 30800 +/- 3110 23700 +/- 2410 645 +/- 138

< 177 20928 +/- 54481

< 3.2

< 0.8

< 3.4

< 0.6 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-6

Table C-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE 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 12/31/12 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 08/07/13 09/03/13 10/01/13 10/29/13 12/03/13 MEAN 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 12/03/13 12/31/13

<6

<4

<3

<4

<6

<5

<3

<4

<6

<8

<6

<4

<6

<4

<3

<5

<6

<5

<4

<5

<6

<9

<5

<4

< 13

<8

< 11

<9

< 11

<9

<8

< 10

< 19

< 11

< 10

<5

<3

<6

<5

<3

<4

<6

<8

<7

<5

< 10

<9

<7

< 14

< 11

<9

<8

<7

< 11

< 14

< 11

<9

<7

<4

<5

<6

<4

<5

<8

<6

<5

< 10

<7

<6

< 10

<6

< 10

< 12

< 11

<8

<6

<4

<3

<5

<3

<4

<5

<7

<4

<6

<4

<3

<6

<5

<3

<4

<5

<8

<6

<4

< 30

< 17

< 16

< 24

< 23

< 24

< 21

< 27

< 37

< 35

< 31

<9

<7

<4

< 10

<9

<6

<9

< 10

< 12

< 11

Table C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH) SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Sr-90 PERIOD INDP PREDATOR 06/07113 09/24/13

< 2.9

< 2.9 MEAN INDB BOTTOM FEEDER 06/07/13 09/24/13 MEAN BKGP PREDATOR 06/11/13 09/25/13 MEAN BKGB BOTTOM FEEDER 06/11/13 09/25/13 MEAN

< 3.2

< 4.0

< 3.0

< 2.3

< 2.8

< 2.8 C-8

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

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD BKGB BOTTOM FEEDER 06/11/13 09/25/13 MEAN BKGP PREDATOR 06/11/13 09/25113 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 3846 +/- 904

< 54 3492 +/- 777

< 46

< 53

< 106

< 54

< 109

< 54

< 48

< 142

< 54

< 95

< 47

< 53

< 48 3669 +/- 501 MEAN 2982 +/- 962

< 54 5278 +/- 737

< 48 4130 +/- 3247 3676 +/- 871

< 63 2924 +/- 709

< 46

< 57

< 123

< 52

< 88

< 50

< 58

< 128

< 55

< 100

<44

< 60

< 51 r)

INDB BOTTOM FEEDER 06/07/13 09/24/13 MEAN INDP PREDATOR 06/07/13 09/24/13

< 65

< 127

< 63

< 117

< 60

< 49

< 118

< 46

< 100

< 43

< 66

< 40 3300 +/- 1063 3349 +/- 681

< 38 3826 +/- 868

< 53

< 47

< 91

< 53

< 102

< 40

< 50

< 142

< 46

< 123

< 44

< 54

< 55 MEAN 3588 +/- 675

Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLEI ##

IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD A1-3 06/14/13 13750 +/- 1261

< 66

< 62

< 64

< 65

< 81 10/30/13 18080 +/- 2233

< 98

< 99

< 107

< 84

< 128 MEAN 15915 +/- 6124 EDCB 10/30/13 18710 +/- 1836

< 77

< 87

< 99

< 77 202 +/- 114 MEAN J2-1 06/14/13 10/30/13 MEAN K1-3 06/14/13 10/30/13 MEAN 17790 +/- 1717 19290 +/- 1785 18540 +/- 2121 8026 +/- 1000 9084 +/- 1317 8555 +/- 1496

< 88

88

< 52

< 72

< 65

< 89

< 70

< 94

< 85

< 107

< 88

< 93

< 53

< 59

< 49

< 71

< 88

< 76

< 71

< 90 C-I0

Table C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION. 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 01/02/13 -01/09/13 01/09/13 -01/17/13 01/17/13

-01/24/13 01/24/13 -01/31/13 01/31/13 -02/07/13 02/07/13

-02/15/13 02/15/13 -02/21/13 02/21/13 -02/27/13 02/27/13 -03/07/13 03/07/13

-03/14/13 03/14/13 -03/21/13 03/21/13 -03/28/13 03/28/13 -04/04/13 04/04/13 -04/11/13 04/11/13

-04/17/13 04/17/13 -04/25/13 04/25/13 -05/02/13 05/02/13

-05/09/13 05/09/13

-05/16/13 05/16/13

-05/23/13 05/23/13

-05/30/13 05/30/13

-06/06/13 06/06/13

-06/12/13 06/12/13

-06/20/13 06/20/13

-06/26/13 06/26/13

-07/04/13 07/04/13

-07/10/13 07/10/13

-07/18/13 07/18/13

-07/25/13 07/25/13

-08/01/13 08/01/13

-08/08/13 08/08/13

-08/15/13 08/15/13

-08/21/13 08/21/13

-08/29/13 08/29/13

-09/05/13 09/05/13

-09/12/13 09/12/13

-09/19/13 09/19/13

-09/25/13 09/25/13

-10/02/13 10/02/13

-10/10/13 10/10/13

-10/17/13 10/17/13

-10/24/13 10/24/13

-10/31/13 10/31/13

-11/07/13 11/07/13

-11/14/13 11/14/13

-11/21/13 11/21/13 -11/27/13 11/27/13

-12/05/13 12/05/13

-12/11/13 12/11/13 -12/19/13 12/19/13 -12/26/13 12/26/13 -01/02/14 MEAN GROUP I I

E1-2 38 +/- 6 27 +/- 6 23 +/- 6 20 +/- 6 21 +/- 6 19 +/- 5 18 +/- 6

< 10 8+/- 4

< 8 11 9

11 15 17 9

13

<7 10 9

18 17 10 15 17 7

18 13 15 8

15 15 17 18 9

15 14

<9 17 28 14 19 18 14 9

17 11 32

.17 19 20 18

+/-5

+/-6

+/-4

+/-5

+/-6

+/-4

+/-6

+/-4 1+/-6

+/-4

+/-5

+/-4

+/-5

+/-6

+/-5

+/-5 t-1-.j 38 +/- 6 21 +/- 5 22 +/-5 19 +/-5 28 +/-6 18 +/-5 11 +/-5

<9 7+/-4 8+/-5 17 5

9+/-4 14 +/-5 18 +/-5 10 +/-5 15 +/-5 15 +/-5 7+/-4 15 +/-5 13 +/- 5 19 +/- 5 12 +/- 5

<8 15 +/- 4 18 +/- 6 10 +/- 4 10 +/- 5 17 +/- 4 17 +/- 5 19 +/-5 21 +/-5 16 +/-5 13 +/-6 25 +/-5 17 +/-6 20 +/-6 14 +/-5 11 +/-6 14 +/-5 25 +/-5 14 +/-5 16 +/-5 14 +/-5 11 +/-5 13 +/- 5 18 +/- 5 16 +/- 5 32 +/- 5 20 +/- 6 26 +/- 5 17 +/- 5 17 +/- 5 A3-1 41 +/- 6 19 +/- 5 21 +/- 5 26 +/- 6 26 +/- 6 15 +/- 4 17 +/- 5

<9 10 +/- 4 13 +/- 5 20 +/- 5 8+/-4 13 +/-5 20 +/-5 14 +/-6 13 +/-5 14 +/-5 9+/-5 16 +/-5 15 +/-5 17 +/-5 13 +/- 5 14 +/- 6 19 +/- 4 17 +/- 5 7+/-4 13 +/-5 16 +/-4 15 +/-5 16 +/-5 24 +/-5 18 +/-5 11 +/-6 28 +/-5 21 +/-6 19 +/-5 15 +/-5 11 +/-6 18 +/-5 26 +/-5 21 +/-5 14 +/-5 26 +/-6 15 +/-5 16 +/-5 15 +/-5 17 +/-6 35 +/- 6 13 +/- 6 26 +/- 5 20 +/- 5 21 +/- 5 GROUP 11 9

10 13 9

(1) 11 15

< 8 (1) 10 (1) 19 (1) 10 14 (1) 15 (1) 17 12

< 8 20 19 14 12 17 17 13 20 14 13 24 21 21 11 11

+/-

+

+/-

+

+/-

G,2-1 40 +/-

21 +/-

17 +/-

20 +/-

23 +/-

15 +/-

16 +/-

< 9 1-3-1 42 +/- 6 20 +/- 5 18 +/- 5 17 +/- 5 26 +/- 6 17 +/- 5 15 +/- 5 10 +/- 6 12 +/- 5 11 +/-5 20 +/-5 8+/-4 14 +/-5 17 +/-5 18 +/-6 13 +/-5 23 +/-6 8+/-5 15 +/-6 13 +/-5 20 +/-5 8+/-5 21 +/-5 16 +/-6 9+/-4 10 +/-5 19 +/-5 15 +/-5 15 +/-5 20 +/-5 24 +/-6 9+/-6 22 +/-5 20 +/-6 28 +/-6 17 +/- 5 12 +/- 6 17 +/- 6 27 +/- 5 18 +/- 5 18 +/- 6 16 +/- 5 12 +/- 5 14 +/- 5 20 +/- 5 12 +/- 5 30 +/- 5 14 +/- 6 29 +/- 5 19 +/- 6 18 +/- 5 M2-1 48 +/- 7 23 +/- 5 19 +/- 5 18 +/- 5 22 +/- 6 20 +/- 5 13 +/- 5

<9 6+/-4 13 +/-6 11 +/-5 8+/-4 14 +/-5 16 +/- 5 18 +/- 6 14 +/- 4 21 +/- 6 8+/-5 13 +/-5 22 +/-6 14 +/-5 17 +/-6

<8 16 +/- 4 20 +/- 6 10 +/- 4 21 +/- 6 20 +/- 5 15 +/- 5 16 +/- 5 18 +/- 5 15 +/- 5 14 +/- 6 27 +/- 5 21 +/- 6 22 +/- 6 16 +/-t 5 10 +/- 6 19 +/- 6 28 +/- 5 19 +/- 5 15 +/- 5 20 +/- 5 18 +/- 5 12 +/- 5 18 +/- 5 12 +/- 5 31 +/- 6 15 +/- 6 24 +/- 5 17 +/- 5 20 +/- 5 IGROUP III 015-1 44 +/- 6 23 +/- 5 17 +/- 5 21 +/- 5 24 +/-9 (1) 17 +/- 4 27 +/- 6

< 9

< 10 (1) 8+/-5 19 +/-6 (1) 8+/-4 14 +/-5 17 +/-5 18 +/-6 13 +/-4 21 +/-14 (1)

< 6 16 +/- 5 13 +/- 5 14 +/- 5 11 +/-6 9+/-5 12 +/-4 12 +/-5 14 +/- 4 15 +/- 5 16 +/- 5 18 +/- 5 19 +/-5 20 +/-6 18 +/-5 17 +/-6 18 +/-6 11 +/-5 13 +/-6 20 +/-6 27 +/-5 19 +/-5 16 +/-5 20 +/-5 16 +/-5 14 +/-5 20 +/-5 15 +/-6 35 +/-6 16 +/- 6 24 +/- 5 16 +/- 5 24 +/- 6 (1)

+/-

15 14 19 17 15 16 14 29 14 29 13 21 16 +/- 12 17 +/-12 18 +/-13 17 +/- 12 17 +/-13 18 +/-13 18 +/-13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1lI

Table C-VI.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - CLOSEST TO THE SITE BOUNDARY COLLECTION MIN MAX MEAN +

PERIOD 2SD 01/02/13 - 01/31/13 19 38 26 +/- 15 GROUP II - INTERMEDIATE OFFSITE GROUP III - CONTROL LOCATIONS COLLECTION PERIOD MIN MAX MEAN +

2SD COLLECTION PERIOD MIN MAX MEAN+

2SD U1/U2/13 - 01/31i13 17 48 26 +/- 21 01/02/13 -

01/31/13 17 44 26 +/- 24 01/31/13 02/27/13 04/04/13 05/02/13 05/30/13 07/04/13 08/01/13 08/29/13 10/02/13 10/31/13 11/27/13

- 02/21/13

- 04/04/13

- 05/02/13

- 05/30/13

- 07/04/13

- 08/01/13

- 08/29/13

- 10/02/13

- 10/31/13

- 11/27/13

- 01/02/14 11 7

9 7

7 8

13 9

14 9

17 28 17 18 19 18 19 25 20 28 18 32 19 10 14 13 13 15 17 15 18 14 22

+ 11

+/-6

+6

+9

+/-8

+6

+/- 10

+/-6

+/- 12 01/31/13 02/27/13 04/04/13 05/02/13 05/30/13 07/04/13 08/01/13 08/29/13 10/02/13 10/31/13 11/27/13 02/27/13 04/04/13 05/02/13 05/30/13 07/04/13 08/01/13 08/29/13 10/02/13 10/31/13 11/27/13 01/02/14 10 6

10 8

7 10 9

10 14 12 13 26 20 23 22 21 21 28 28 28 20 35 18 +/- 10 12 +/- 7 16 +/- 7 14 +/- 8 15 9

16 6

19 +/- 11 17 9

20 +/- 10 15 5

22 + 14 01/31/13 03/07/13 04/04/13 05/09/13 06/06/13 07/04/13 08/01/13 08/29/13 10/02/13 10/31/13 11/27/13 02/21/13 04/04/13 05/02/13 05/30/13 07/04/13 08/01/13 08/29/13 10/02/13 10/31/13 11/27/13 01/02/14 17 8

13 13 9

12 18 11 16 14 16 27 19 21 16 12 16 20 20 27 20 35 22 12 17 14 11 14 19 16 20 16 23

+/-

10 11 7

3 3

3 1

7 9

5 16 t'J 01102/13 - 01/02/14 7

38 16 +/- 12 01/02/13 - 01/02/14 6

48 17 +/- 13 01/02/13 - 01/02/14 8

44 18 +/- 13

Table C-VI.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION PERIOD A3-1 01/02/13 - 04/04/13 03/28/13 - 06/26113 06/26/13 - 10/02/13 10/02/13 - 01/02/14 Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 74 94 70 73 1 24

+/- 32

+ 24

+/- 24 MEAN 78 +/- 22 E1-2 01/02/13 03/28/13 06/26/13 10/02/13 MEAN F1-3 01/02/13 03/28/13 06/26/13 10/02/13 MEAN G2-1 01/02/13 03/28/13 06/26113 10/10/13 MEAN H3-1 01/02/13 03/28/13 06/26/13 10/02/13 MEAN M2-1 01/02/13 03/28/13 06/26/13 10/02/13 MEAN Q15-1 01/02/13 03/28/13 06/26/13 10/02/13 MEAN

- 04/04/13

- 06/26/13

- 10/02/13

- 01/02/14

- 04/04/13

- 06/26/13

- 10/02/13

- 01/02/14

- 04/04/13

- 06/26/13

- 10/02/13

- 01/02/14

- 04/04/13

- 06/26/13

- 10/02/13

- 01/02/14

- 04/04/13

- 06/26/13

- 10/02/13

- 01/02/14

- 04/04/13

- 06/26/13

- 10/02/13

- 01/02/14 59 83 53 61 64 +/- 26

+/- 25

+/- 35

+/- 21

+ 25 59 118 59 70

+/- 19

+/- 32

+/- 27

+/- 24 76 +/- 57 65 79 51 74

+/- 23

+/- 39

+/- 18

+/- 26

<2

<3

<2

<3

<2

<4

<2

<3

<5

<2

<4

<2

<3

<4

<3

<2

<3

<2

<4

<3

<4

<3

<2

<3

<4

<3

<5

<2

<4

<2

<5

<3

<5

<3

<5

<3

<4

<3

<6

<4

<5

<4

<2

<3

<2

<1

<2

<3

<2

<4

<2

<3

<2

<5

<1

<4

<3

<5

<2

<3

<2

<3

<1

<3

<4

<3

<4

<3

<4

<5

<4

<3

<5

<3

<5

<4

<5

<3

<4

<6

<5

<4

<3

<4

<5

<6

<4

<5

<7

<5

<6

<7

<9

<6

<8

<6

<9

<6

< 10

<5

<8

< 10

<7

<5

<6

<8

<5

<7

<8

< 10

<7

<9

<2

<3

<2

<3

<2

<3

<4

<3

<4

<3

<5

<3

<5

<3

<2

<3

<4

<5

<4

<2

<3

<1

<2

<3

<2

<3

<2

<4

<1

<5

<2

<3

<5

<3

<2

<3

<2

<3

<4

<3

<3 67 +/- 25 66 85 63 74

+/- 38

+/- 39

+/- 22

+/- 24 72 +/- 19 74 85 55

< 38

+/- 35

+/- 23

+/- 27 72 +/- 30 70 73 77 58

+/- 45

+/- 32

+/- 35

+/- 30 70 +/- 17 C-13

Table C-VII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 01/02/13

-01/09/13 01/09/13

-01/17/13 01/17/13

-01/24/13 01/24/13

-01/31/13 01/31/13

-02/07/13 02/07/13

-02/15/13 02/15/13

-02/21/13 02/21/13

-02/27/13 02/27/13

-03/07/13 03107/13

-03/14/13 03/14/13

-03/21/13 03/21/13

-03/28/13 03/28/13

-04/04/13 04/04/13

-04/11/13 04/11/13

-04/17/13 04/17/13

-04/25/13 04/25/13

-05/02/13 05/02/13

-05/09/13 05/09/13

-05/16/13 05/16/13

-05/23/13 05/23/13

-05/30/13 05/30/13

-06/06/13 06/06/13

-06/12/13 06/12/13

-06/20/13 06/20/13

-06/26/13 06/26/13

-07/04/13 07/04/13

-07/10/13 07/10/13

-07/18/13 07/18/13

-07/25/13 07/25/13

-08/01/13 08/01/13

-08/08/13 08/08/13

-08/15/13 08/15/13

-08/21/13 08/21/13

-08/29/13 08/29/13

-09/05/13 09/05/13

-09/12/13 09/12/13

-09/19/13 09/19/13

-09/25/13 09/25/13

-10/02/13 10/02/13

-10/10/13 10/10/13

-10/17/13 10/17/13

-10/24/13 10/24/13

-10/31/13 10/31/13

-11/07/13 11/07/13

-11/14/13 11/14/13

-11/21/13 11/21/13

-11/27/13 11/27/13

-12/05/13 12/05/13-12/11/13 12/11/13

-12/19/13 12/19/13

-12/26/13 12/26/13

-01/02/14 GROUP I I

GROUP 11 El 2

17

49

39

40

33

21

68

< 44

36

54

42

39

49

54

33

17

34

67

48

< 47

< 48

31

62

< 46

34

35

25

52

62

43

61

54

57

34

< 48

28

40

67

62

59

67

20

65

59

57

59

64

54

39

58

69

57 Fl1-3

39

48

38

39

32

21

66

43

35

53

41

38

48

23

32

40

33

65

46

46

< 47

16

60

45

33

14

64

50

60

15

59

52

56

33

47

27

39

65

60

57

65

< 46

63

57

56

57

63

53

38

56

67

55 A3-1

38

42

48

52

36

27

58

38

36

37

42

12

36(

50

45

30(

27(

42 (1

35

40 (1

54 (1

30

66

< 7

32

31

47

59

51

46

53

38

43

38

48

34

50

66

67

60

59

52

54

68

62

50

60

51

51

66

67

23 G2-1

< 40

< 20

< 39

< 33

< 21

< 67

< 43

< 35

< 53

< 41

< 39

1)

< 48

< 53

< 32

1)

< 41

1)

< 33 I <

<22

< 47 I < <47

< <47

< 30

< 61

< 45

< 34

< 64

< 51

< 61

< 16

< 60

< 53

< 56

< 34

< 49

< 28

< 39

< 67 (1)

(1)

< 66

< 47

< 64

< 24

< 57

< 58

< 63

< 53

< 39

< 57

< 68

< 56 1-3-1

41

50

40

16

33

28

69

44

36

38

42

36

49

55

33

< 42

34

67

48

< 18

< 48 (1)

67

19

33

35

66

53

64

44

56

55

18

41

49

36

41

69

62

60

68

56

68

60

58

< 60

25

54

40

59

70

63 M2-1

38

42

49

52

36

< 11

58

38

36

37

42

36

30

51

45

28

26

41

36

37

53

30

34

18

32

31

48

59

51

47

54

39

<43

16

48

34

51

66

68

60

59

53

55

68

63

52

59

51

16

67

68

60 IGROUPIII 015-1

37

42

< 48

52

61 (1)

26

58

37

68 (1)

15

49 (1)

34

30

49

44

27

68 (1)

41

35

37

52 (1)

66

63 (1)

(1)

32

47

60

51

47

54

39

43

39

48

18

51

67

69

61

60

53

55

69

63

52

59

50

53

67

68

61

-1 MEAN---

(1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-14

Table C-VIII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD CONTROL FARM I INDICATOR FARM K15-3 E2-2 F4-1 G2-1 P4-1 01/16/13 02/13/13 03/13/13 03/27/13 04/10/13 04/24/13 05/08/13 05/22/13 06/05/13 06/19/13 07/03/13 07/17/13 07/31/13 08/14/13 08128/13 09/11/13 09/25/13 10/09/13 10/23/13 11/06/13 11/20/13 12/04/13

< 0.9

< 0.7

< 0.6

< 0.8

< 0.4

< 0.7

< 0.6

< 0.8

< 0.7

< 0.8

< 0.7

< 0.6

0.8

< 0.9

< 0.6

< 0.9

< 0.6

< 0.8

< 0.7

0.8

< 0.6

< 0.9

< 0.8

< 0.7

< 0.8

0.6

< 0.8

< 0.7

< 0.5

< 0.6

< 0.7

0.9

< 1.0

< 0.7

< 0.9

< 0.7

< 0.6

0.9

< 0.4

< 0.6

< 1.0

< 0.7

< 0.6

< 0.5

< 0.7

< 0.6

< 1.0

< 0.7

< 0.9

< 0.8

< 0.7

< 0.6

< 0.8

< 0.5

< 0.6

< 0.8

< 0.5

< 0.7

< 0.5

< 0.7

< 0.5

< 0.7

0.7

< 0.9

< 0.6

< 1.0

< 0.7

< 0.8

< 0.6

< 0.7

< 0.8

< 0.4

< 0.6

< 0.8

< 0.7

< 0.8

< 0.9

< 0.6

< 0.9

< 0.7

< 0.5

< 0.6

< 1.0

< 0.9

< 0.7 MEAN C-15

Table C-VIII.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROLFARM I

COLLECTION PERIOD SR-89 01/16/13 - 03/27/13

< 2.3 04/10/13 - 06/19/13

< 4.9 07/03/13 - 09/25/13

< 4.9 10/09/13 - 12/04/13

' 4.0 K15-3 SR-90

< 1.0

< 0.7

< 0.6 P4-1 SR-89 SR-90

< 2.6

< 0.9

< 4.6

< 0.7

< 4.8

< 0.8

< 3.8

< 0.9 I

E2-2 INDICATOR FARMS I

F4-1 SR-90 SR-89 SR-90 SR-89 SR-89 SR-90 IG2-1

< 2.5

< 4.7

< 4.3

< 4.2

< 0.9

< 0.8

< 0.6

< 2.7

< 4.6

< 3.9

< 1.0

< 0.7

< 0.8

< 2.4

< 4.8

< 2.9

< 4.2

< 0.8

< 0.7

< 0.9

< 0.6 MEAN

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA SITE E2-2 COLLECTION PERIOD 01/16/13 02/13/13 03/13/13 03/27/13 04/10/13 04/24/13 05/08/13 05/22/13 06/05/13 06/19/13 07/03/13 07/17/13 07/31/13 08/14/13 08/28/13 09/11/13 09/25/13 10/09/13 10/23/13 11/06/13 11/20/13 12/04/13 MEAN 1/16/2013 02/13/13 03/13/13 03/27/13 04/10/13 04/24/13 05/08/13 05/22/13 06/05/13 06/19/13 07/03/13 07/17/13 07/31/13 08/14/13 08128/13 09/11/13 09/25/13 10/09/13 10/23/13 11/06/13 11/20/13 12/04/13 K-40 Cs-134 Cs-137 Ba-140 La-140 1253 +/- 97 1224 +/- 169 1233 +/- 146 1355 +/- 113 1189 +/- 127 1193 +/- 144 1253 +/- 123 1146 +/- 169 1147 +/- 187 1276 +/- 168 1484 +/- 140 1521 +/- 160 1322 +/- 139 1397 +/- 187 1338 +/- 113 1223 +/- 161 1314 +/- 153 1208 +/- 137 1440 +/- 135 1151 +/- 150 1278 +/- 145 1319 +/- 164 1285 +/- 212 1438 +/- 94 1374 +/- 170 1482 +/- 171 1403 +/- 129 1474 +/- 190 1362 +/- 125 1313 +/- 169 1427 +/- 164 1361 +/- 164 1439 +/- 155 1321 +/- 134 1129 +/- 148 1341 +/- 148 1403 +/- 177 1450 +/- 105 1224 +/- 153 1411 +/- 144 1513 +/- 150 1415 +/- 119 1464 +/- 152 1424 +/- 140 1526 +/- 156

<4

<9

<5

<4

<5

<8

<7

<5

<6

<7

<4

<6

<5

<6

<5

<8

<3

<7

<6

<5

<6

<5

<6

<5

<4

<7

<4

<5

<6

<5

<7

<5

<11

<7

<5

<6

<9

<8

<6

<7

<4

<7

<6

<5

<6

<7

<8

<4

<9

<7

<6

<8

<6

<7

<6

<8

<6

<7

<6

<7

<4

<6

<7

<6

<8

27

51

27

22

20

< 33

28

< 46

< 42

< 37

< 41

29

31

32

< 46

< 37

52

30

< 33

40

< 47

< 43

28

36

36

23

< 31

< 34

32

< 45

32

< 22

41

31

24

< 36

41

31

< 43

30

36

< 44

< 39

38

< 10

<10

10

<8

<6

<11

<7

<15

<9

14

10

<8

<9

<10

13

<6

14

10

<9

<11

< 12

<13

<8

12

10

<8

<12

<7

< 10

12

<11

<9

<12

<7

<8

<10

12

<10

<11

< 13

< 15

< 12 F4-1 MEAN 1395 +/- 184 C-17

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PFRIODf K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD G2-1 1/16/2013 2/13/2013 3/13/2013 03/27/13 04/10/13 04/24/13 05/08/13 05/22/13 06/05/13 06/19/13 07/03/13 07/17/13 07/31/13 08/14/13 08/28/13 09/11/13 09/25/13 10/09/13 10/23/13 11/06/13 11/20/13 12/04/13 MEAN 866 +/- 92 1220 +/- 133 785 +/- 134 1306 +/- 115 996 +/- 130 1194 +/- 116 1139 +/- 158 912 +/- 135 718 +/- 151 1031 +/- 140 740 +/- 131 1793 +/- 152 1010 +/- 144 966 +/- 158 920 +/- 109 925 +/- 134 1113 +/- 150 715 +/- 140 788 +/- 98 745 +/- 128 1003 +/- 127 902 +/- 143 990 +/- 492 1262 +/- 100 1217 +/- 151 1232 +/- 130 1266 +/- 114 1336 +/- 148 1369 +/- 141 1325 +/- 151 1419 +/- 152 1132 +/- 172 1353 +/- 147 1426 +/- 148 1211 +/- 131 1465 +/- 145 1336 +/- 161 1410 +/- 141 1368 +/- 146 1308 +/- 138 1243 +/- 125 1429 +/- 130 1187 +/- 132 1264 +/- 137 1300 +/- 137 1312 +/- 178

<4

<6

<7

<4

<6

<5

<8

<5

<7

<6

<5

<7

<8

<4

<6

<4

<7

<6

<7

<4

<8

<5

<4

<8

<6

<7

<5

<6

<5

<6

<5

<4

<6

<5

<6

<7

<5

<8

<5

<9

<7

<8

<7

<8

<9

<5

<7

<6

<4

<8

<6

<7

<4

<8

<6

<5

<8

<7

<6

<7

<5

<7

<6

<5

<6

<7

<6

<5

<6

<7

<6

< 30

< 38

< 26

< 33

< 30

< 43

< 48

< 38

< 35

< 42

< 30

< 37

< 50

< 44

< 30

< 46

< 35

< 33

< 48

< 42

< 40

< 28

< 40

< 31

< 20

< 37

< 36

< 29

< 48

< 33

< 30

< 39

< 31

< 28

< 35

< 54

< 35

< 43

< 30

< 36

< 43

< 49

< 34

< 10

< 11

< 10

<6

< 11

<9

< 13

< 11

< 12

< 10

< 13

<9

< 14

< 12

< 15

< 11

< 13

<9

< 12

< 11

<9

<8

<6

<8

< 10

<6

< 11

<9

<8

< 11

<8

< 12

< 15

<9

< 13

<8

< 11

<9

< 15

<9 K15-3 01/16/13 02/13/13 03/13/13 03/27/13 04/10/13 04/24/13 5/8/2013 05/22/13 6/5/2013 06/19/13 07/03/13 07/17/13 07/31/13 08/14/13 08/28/13 09/11/13 09/25/13 10/09/13 10/23/13 11/06/13 11/20/13 12/04/13 MEAN C-18

Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PFRIC)fl K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD P4-1 01/16/13 02/13/13 03/13/13 03/27/13 04/10/13 04/24/13 05/08/13 05/22/13 06/05/13 06/19/13 07/03/13 07/17/13 07/31/13 08/14/13 08/28/13 09/11/13 09/25/13 10/09/13 10/23/13 11/06/13 11/20/13 12/04/13 1371 1325 1309 1345 1373 1296 1398 1419 1289 1412 1393 1362 1507 1418 1350 1481 1475 1464 1412 1395 1483 1257

+/- 106

+/- 150

+/- 121

+/- 86

+/- 133

+/- 151

+/- 168

+/- 166

+/- 192

+/- 166

+/- 110

+/- 162

+/- 149

+/- 173

+/- 110

+/- 175

+/- 156

+/- 170

+/- 135

+/- 185

+/- 146

+/- 138

<4

<6

<4

<5

<6

<7

<5

<7

<5

<6

<4

<6

<5

<6

<5

<6

<5

<4

<7

<4

<6

<7

<6

<8

<6

<4

<7

<6

<7

<5

<9

<6

<5

<7

28

32

21

18

27

< 44

31

< 44

32

< 34

32

< 39

< 28

30

< 41

< 33

< 44

28

< 37

< 39

29 10 10 7

5 8

10 9

12 10 11 8

12 10 11 10 11 15 9

11 11 14 7

MEAN 1388 +/- 137 C-19

Table C-IX.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD Sr-90 Be-7 K-40 1-131 Cs-134 Cs-137 B10-2 Cauliflower Leaves Green Cabbage Sunflower Leaves Cabbage Broccoli Leaves Green Cabbage Sunflower Leaves Sweet Corn Tomatoes Neck Pumpkin Leaves Red Beet Greens Sunflower Leaves Gourd Leaves Radish Greens Sunflower Leaves Sweet Potatoes 06/25/13 06/25/13 06/25/13 07/09/13 07/22/13 07/22/13 07/22/13 07/31/13 07/31/13 08/28/13 08/28/13 08/28/13 09/30/13 09/30/13 09130/13 09/30/13 5 +/-2

<172

< 3

< 204 8 +/- 3 362 +/- 175 3 +/- 2

< 215 7 +/- 3 386 +/- 189

< 5

< 175 8 +/- 3 736 +/- 239

< 121

< 174 7 +/- 3 1538 +/- 208

< 4 387 +/- 169

< 4 1021 +/- 173 30 +/- 3 2637 +/- 127 14 +/- 2 147 +/- 65 9 +/- 2 1153 +/- 98

< 53 4304 3836 7715 2416 3660 2005 8009 2205 2182 5273 9046 6884 4848 5850 5934 4274

+/- 431

+/- 463

+/- 525

+/- 448

+/- 461

+/- 416

+/- 734

+/- 309

+/- 305

+/- 375

+/- 465

+/- 477

+/- 192

+/- 171

+/- 204

+/- 141

< 33

< 35

< 34

< 44

< 47

< 38

< 32

< 40

< 49

< 48

51

< 58

< 48

< 57

< 39

<17

< 19

< 16

< 20

< 24

< 18

< 21

< 16

< 19

< 17

< 15

< 17

<7

<5

<7

<5

< 18

< 22

< 20

< 24

< 16

23

< 17

17

< 18

< 16

< 21

<8

<6

<7

<6 MEAN 10 +/- 16 930 +/- 1566 4903 +/- 4426 EI-2 Cabbage Sweet Corn Tomatoes Sweet Potatoes 07/09/13 07/31/13 07/31/13 09/30/13 7 +/- 2

< 196

128

129

62 3536 2576 2431 3534

+/- 452

+/- 379

+/- 341

+/- 147

< 43

< 32

< 28

< 46

< 17

< 14

<6

< 20

< 18

17

<6 MEAN H11-2 Eggplant Leaves Squash Leaves Zucchini Leaves Eggplant Leaves Squash Leaves Zucchini Leaves Eggplant Leaves Neck Pumpkin Leaves Zucchini Leaves Squash Leaves Turnip Greens Zucchini Leaves 06/25/13 06/25/13 06/25/13 07/22/13 07/22/13 07/22/13 08/28/13 08/28/13 08/28/13 09/30/13 09/30/13 09/30/13 12 +/-

7+/-

17 +/-

16 +/-

27 +/-

16 +/-

12 +/-

<4 3

4 3

4 5

4 3

359 +/- 155

< 146 141 +/- 96 610 +/- 248 869 +/- 282 768 +/- 228 1435 +/- 192 888 +/- 179 261 +/- 171 723 +/- 84 188 +/- 62 527 +/- 71 3019 +/- 1197 8483 +/- 488 5337 +/- 458 5472 +/- 350 4113 +/- 620 3476 +/- 571 4663 +/- 574 3087 +/- 311 4083 +/- 344 4272 +/- 361 3217 +/- 149 5369 +/- 148 3334 +/- 153

38

< 32

< 25

< 54

50

< 49

< 42

< 48

< 56

< 45

< 56

< 17

< 16

< 12

< 21

< 20

< 15

14

<6

<5

<6

< 17

18

< 13

< 31

< 19

< 21

< 16

< 17

<7

<6

<7 8

24 4

11

+3

+/-3

+/-2

+/-2 MEAN 14 +/- 14 615 +/- 762 4576 +/- 2994 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-20

Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE

+/- 2 S.D.

A1-4 17.2 +/- 2.9 18.9 16.4 15.6 17.7 A3-1 16.9 +/- 2.5 18.2 16.1 15.7 17.8 A5-1 21.1 +/- 0.8 21.7 21.0 20.8 21.0 A9-3 18.4 +/- 2.6 19.6 18.9 16.6 18.5 B1-1 17.7 +/- 2.4 19.3 17.2 16.5 17.8 B1-2 17.4 +/- 3.4 19.5 16.2 15.8 18.1 B2-1 18.1 +/- 1.8 18.6 18.0 16.9 19.0 B5-1 20.5 +/- 2.9 21.7 21.3 18.5 20.7 Cl-i 20.1 +/- 2.3 21.3 20.3 18.5 20.4 C1-2 17.2 +/- 3.7 19.2 16.2 15.2 18.3 C2-1 20.2 +/- 2.6 20.9 20.8 18.3 20.9 C5-1 20.9 +/- 3.2 22.5 21.0 18.7 21.6 C8-1 21.3 +/- 3.7 23.1 21.9 18.7 21.8 D1-1 18.3 +/- 3.3 19.8 17.4 16.5 19.6 D1-2 19.2 +/- 2.5 20.7 19.2 17.7 19.2 D2-2 23.3 +/- 3.0 24.4 23.0 21.4 24.7 D6-1 22.3 +/- 2.8 23.3 22.8 20.2 22.7 E1-2 18.3 +/- 3.5 20.1 17.5 16.3 19.5 E1-4 20.7 +/- 5.1 22.3 19.2 17.9 23.3 E2-3 21.7 +/- 2.0 22.6 21.8 20.3 22.2 E5-1 20.6 +/- 2.7 21.5 21.1 18.7 21.4 E7-1 20.3 +/- 3.2 22.0 19.8 18.3 21.0 F1-1 19.7 +/- 2.6 21.1 18.3 18.9 20.5 F1-2 25.5 +/- 8.3 25.5 24.7 20.8 30.9 F1-4 23.8 +/- 7.5 24.2 22.0 20.2 28.8 F2-1 22.1 +/- 2.3 23.6 22.0 20.8 22.2 F5-1 23.0 +/- 2.7 24.2 23.9 21.3 22.8 G1-2 20.1 +/- 2.7 20.9 19.3 18.6 21.5 G1-3 20.9 +/- 3.7 21.9 19.6 19.0 22.9 G1-5 18.3 +/- 2.5 18.7 17.4 17.2 19.9 G1-6 19.8 +/- 2.4 20.3 18.9 18.7 21.2 G2-4 24.2 +/- 2.3 25.4 24.5 22.7 24.5 G5-1 19.8 +/- 2.6 21.4 18.8 18.7 20.3 H1-1 19.4 +/- 2.0 20.7 19.4 18.3 19.2 H3-1 16.8 +/- 2.1 18.1 16.4 15.6 17.2 H5-1 15.8 +/- 3.2 17.3 14.8 14.0 16.9 H8-1 29.6 +/- 0.5 29.4 29.9 29.5 29.6 J1-1 18.2 +/- 2.8 19.5 18.9 16.3 18.1 J1-3 15.9 +/- 2.5 17.3 15.3 14.5 16.5 J3-1 19.7 +/- 2.3 21.3 19.8 18.6 19.1 J5-1 21.8 +/- 2.4 23.4 20.9 20.9 22.0 J7-1 22.9 +/- 2.2 23.8 23.0 21.3 23.4 K1-4 17.7 +/- 1.4 18.3 17.5 16.8 18.2 K2-1 21.7 +/- 2.1 21.7 22.2 20.3 22.7 K3-1 18.0 +/- 2.0 18.6 18.7 16.5 18.1 C-21

Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE

+/- 2 S.D.

K5-1 21.7 +/- 1.5 22.8 21.3 21.2 21.5 K8-1 21.1 +/- 2.9 22.4 20.8 19.2 22.1 LI-1 18.1 +/- 2.6 19.8 17.2 16.9 18.5 L1-2 18.3 +/- 2.4 19.5 18.2 16.7 18.8 L2-1 19.9 +/- 2.5 21.3 19.3 18.6 20.5 L5-1 18.2 +/- 2.3 19.2 18.4 16.5 18.6 18-1 19.8 +/- 1.5 20.7 20.1 18.9 19.5 Mi-i 16.6 +/- 2.9 18.2 16.2 14.8 17.1 MI1-2 19.8 +/- 2.6 21.0 20.1 18.0 20.3 M2-1 17.6 +/- 2.0 19.0 17.4 16.6 17.4 M5-1 20.1 +/- 2.6 21.4 20.4 18.3 20.3 M9-1 23.9 +/- 1.8 25.1 23.9 22.9 23.9 N1-1 18.9 +/- 1.9 19.4 19.5 17.5 19.3 N1-3 17.7 +/- 3.0 19.5 16.5 16.5 18.5 N2-1 20.5 +/- 2.1 21.9 20.4 19.3 20.4 N5-1 17.0 +/- 2.4 18.5 16.6 15.6 17.3 N8-1 21.0 +/- 2.3 22.6 20.9 19.8 20.6 P1-i 19.0 +/- 1.7 20.0 18.7 18.0 19.3 PI-2 18.4 +/- 3.9 20.1 18.7 15.6 19.3 P2-1 22.9 +/- 1.8 23.9 22.9 21.8 23.3 P5-1 20.0 +/- 3.1 21.6 19.6 18.0 20.8 P8-1 17.3 +/- 2.9 18.8 17.3 15.4 17.7 Q1-1 19.2 +/- 2.0 19.8 19.1 17.8 20.0 Q1-2 16.4 +/- 3.2 18.2 16.0 14.4 16.9 Q2-1 18.0 +/- 1.6 19.0 17.8 17.1 18.0 Q5-1 18.2 +/- 2.4 19.8 17.6 17.1 18.3 Q9-1 19.3 +/- 1.6 20.2 18,8 18.5 19.7 Ri-1 17.0 +/- 3.2 18.8 15.6 15.8 17.9 RI-2 17.8 +/- 2.0 18.8 17.7 16.5 18.4 R3-1 22.1 +/- 2.1 23.1 22.7 20.7 22.1 R5-1 21.5 +/- 2.3 23.0 21.3 20.3 21.6 R9-1 21.5 +/- 2.4 22.5 20.9 20.1 22.5 B10-1 19.9 +/- 2.5 20.8 19.8 18.3 20.9 D15-1 20.3 +/- 1.8 21.2 20.1 19.1 20.7 F10-1 24.2 +/- 1.6 25.0 23.8 23.3 24.7 F25-1 21.1 +/- 2.1 22.3 21.0 19.8 21.3 G10-1 28.4 +/- 2.7 29.5 27.1 27.5 29.7 G15-1 25.2 +/- 2.8 26.3 25.4 23.1 25.9 H15-1 21.3 +/- 2.9 22.6 22.1 19.3 21.3 J15-1 23.3 +/- 3.1 25.0 22.6 21.6 24.2 K15-1 19.7 +/- 2.5 21.3 19.6 18.3 19.6 L15-1 20.5 +/- 2.3 21.3 20.5 18.9 21.3 N15-2 22.1 +/- 0.9 22.5 21.9 22.5 21.6 Q15-1 21.9 +/- 2.3 23.0 21.4 20.5 22.6 R15-1 19.2 +/- 2.4 20.5 19.6 17.6 19.3 C-22

TABLE C-X.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD JAN-MAR APR-JUN JUL-SEP OCT-DEC TABLE C-X.3 SITE BOUNDARY INDICATOR CONTROL

+/- 2 S.D.

20.0 +/- 4.2 21.3 +/- 4.4 23.2 +/- 5.4 17.9 +/- 4.7 20.1 +/- 5.0 21.9 +/- 4.8 16.8 +/- 3.7 18.8 +/- 4.9 20.7 +/- 5.7 20.1 +/- 7.8 20.6 +/- 4.6 22.5 +/- 6.1

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION SAMPLES PERIOD PERIOD ANALYZED MINIMUM MAXIMUM PERIOD MEAN

+/- 2 S.D.

SITE BOUNDARY INDICATOR CONTROL 76 14.4 240 44 14.0 17.6 30.9 29.9 29.7 18.7 +/- 6.0 20.2 +/- 5.1 22.1 +/- 5.6 SITE BOUNDARY STATIONS-A1-4, B1-2, Cl-2, Di-1, E1-4, F1-2, G1-6, H1-1, J1-3, K1-4, Li-1, Mi-1, N1-3, Pi-2, Q1-2, Ri-i F1-4, G1-3, G1-5, INDICATOR STATIONS -A3-1, A5-1, A9-3, B1-1, B10-1, B2-1, B5-1, Cl-1, C2-1, C5-1, C8-1, Di-2, D2-2, D6-1, Ei-2, E2-3, E5-1, E7-1, Fi-1, F10-1, F2-1, F5-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-i, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, Li-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, Ni-i, N2-1, N5-1, N8-1, Pi-1, P2-1, P5-1, P8-1, Qi-i, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, R9-1 CONTROL STATIONS - Di5-1, F25-1, G10-1, GI5-1, Hi5-1, J15-1, Ki5-1, Li5-1, N15-2, Q15-1, R15-1 C-23

FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2013 100000 LO 10000 u,

1000 010 S

10 El Station J1-2 (Downstream of Discharge) ui Station Q9-1 (Control)

Jan Feb Mar Apr May Jun Ij1 Aug Sep Oct Nov Dec t--

IV II-,---

V"I "I ~

U Station K1-1 (TMINS Liquid Discharge) 1000000 1000000 -----------------------------------------------.-.----

100

.I-100

.o)a 100 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 - 2013 Indicator Samples Control Samples 12000 Significant Events Major Atm. Nuclear Weapon Tests 11000 TMI-I Critical June 1974 June 1974 September 1974 TMI-2 Critical March 1978 September 1976 November 1976 10000 TMI-2Accident March 1979 September 1977 March 1978 TMI-2 RB Purge June 1980 December 1978 October 1980 9000 Chernobyl April 1986 8000 7000 tb

-J 6000

j 5000 U

h" 4000 2000 1000

-1000 11111 1

................. 11111111111........

1"1

'"11 I......

1 11 1 1 1...... ',,,11,..1111111 1 1 1 1 1 1 8 0 0 0..

- -,l i l

.2 70 0 LA CLO 0

w 0M 0 1-

"4 M~ V*

LO 0

M M) 0 "4

M~ 'I A

(0 Nl-w0 M 0

Is "4

M~ IT A

CO M

0) 0 0 ~

N-N-

N-N-N-

N-wO (

M w

w w

M w

w w

0)

0) 0 M

0 M

0)

C) (

0 0D 0 03 0 0

0) 0-----------

0) 0M 0)

0)

0) 0M M

0n 0M 0) 0)0M) 0

0)

0) 0D 0) 0D) 0)0 0

0) 0 0

0 0

0 0 3

0

0 Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2013 El Indicator Samples I] Control Samples 10 9

8 7

6 5

.2 4

0.

3 8f -----

F

} 1FH----

rf7R-----

2 ----

Ff2 0

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

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2013 NOTE: The mean values are calculated using both the MDCs and El Indicator Samples D., Control Samples the positive values.

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

0 0

400-00 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month n-N Station K1-1 (TMVINS Liquid Discharge)

3 I.-

(0

"-)

0 C.

0o 1000000 100000-10000 1000 100-10.

-H

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

FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2013 Indicator Samples

-_ Control Samples ec 900 800 700 E 600 o 500 I--

a)

C:L CA 400 a) 0 300 0..

200 100 0 IT CO D

00

0) 0 N

M 11; M"

M N-Cw

0) 0 N

c*

U)

CO N

CO

0) 0

(

CO 00 00 CD CD 00 CO C 0)

M0 M 0)

0)

C) 0 0) 0 0) 0 0 0 0

0; 0

CD-'-

M CM

0) 0 0

C 0

0)

D

-M)

M M

CD

' M 0

0 0

0 N

N (N

N CN N

N (N

1 (N

Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2013 Indicator Control 0.4 0.35 +

Significant Events Major Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 March 1972 June 1973 TMI-2 Critical March 1978 June 1974 September 1974 TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RB Purge June 1980 September 1977 March 1978 Chernobyl April 1986 December 1978 October 1980 0.3+/-

0.25 (D 0.25 C..

c--

Co 0 0.15 -

(.)CL 0.1 0.05 0

.41111~~~~~~~~~~

1111 ti 1111 11111 lii

11 ll~l 11111 1111 1111 II:I 1:::

C1 C0

0) 0

" t0 (0 r--

0

0) 0 o-04 CQ 'I-T (0D r-00

0) 0 0

CQ

" L.O (0D -

00 0) 0 S

4-M 'q" L0 (0 00 0) 0

C'. C*"

r-N.

1-1-

N-00 0D CD C) 0 0D 0 00 00D

0)

0) 0l) CT) 0e )

0) 0)

(j)

0) 0 0 0 0 0 0

0 0 0 03 E; -

0)

0) 0D 0) 0) 0Y) 0) 0)

0) 0)

0)

0) 0) 0)

0)

0) 0)

0)

0) 0) 0) a)

0

0) C0 0) C00 0

0C0 0

0 0

0 r------- --------

0 04 CN N NNNNNNNNN Year

FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2013 0.100*

Indicator Control 0.090 0.080 0.070 o 0.060 a.)

0.

0.0 3 0 --

"D 0.050 CL 0.020-0.010 -- - -

-~

--'s-0. 0 i "imm iii iiii i mi"" m iimi i2ii m""

N-r-

I-N.

r-CX)

O m

W 0

)

m (0)

0) 0 0

0 0

0

ý'-

C'-

(4

('

ý)

C")

C) r*)

o 0

0 0

0..............

o o

o 0

0 0

o 0

0 0

o 0

0 Lo 0

0 r 0 0

0 o

0 (0

0) 0J L

cc)

V-rN-0 Mo (0 0M O

Y r

Month I

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

FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2013 Indicator Samples Control Samples Significant Events Major Atm. Nuclear Weapon Tests TMI-2 Accident March 1979 December 1978 October 1980 TMI-2 RB Purge June 1980 Chernobyl April 1986 8

7 U1)

-J 6

L..

U1) 5 (3

1 1 Y O

I i l l l l l l I I I I I I I I l

l l i l I I I I I I I l l li*l l l l m l l

l l l I

l l M) 0 N

M~ 'IT LO (D r-W) C 0 C N

Q~ 'I LO D

t-W)

M 0

E; Q

c')

q1 U)

(0 N-O

0) 0 x

~

N-0 W

W W

W M

U

)

)U)0)0 0)0)C0)

0)

30)

0) 0 0 0

0 C)0 0 00 0

0 r-rrrrrrrrrr-rrr-r'-

r r-r r'-

r r-r-r r

r r

r rr-r-

rr1N N

N N

CN N

N N

N Year

Intentionally left blank

APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

Intentionally left blank

The following section presents the results of data analysis performed by the QC laboratory, Environmental Inc. Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and the QC laboratory. Comparison of the results for most media were within expected ranges.

D-1

Intentionally left blank D-2

TABLE D-1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q9-1Q 12131112 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 12/03/13 01/29/13 02/26/13 04/02/13 04/30/13 05/28/13 07/02/13 07/30/13 09/03/13 10/01/13 10/29/13 12/03/13 12/31/13 1.6 +/- 0.7 1.9 +/- 1.0

< 1.2 1.3 +/- 0.7

< 0.8 0.7 +/- 0.4 1.8 +/- 0.6

< 0.9 1.9 +/- 0.9 1.3 +/- 0.4 0.9 +/- 0.3

1.3 MEAN 1.4 +/- 0.9 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/31/12 - 01/29/

01/29/13 - 02/26/

02/26/13 - 04/02/

04/02/13 - 04/30/

04/30/13 - 05/28/

05/28/13 - 07/02/

07/02/13 - 07/30/

07/30/13 - 09/03/

09/03/13 - 10/01/

10/01/13 - 10/29/

10/29/13 - 12/03/

12/03/13 - 12/31/

Q9-1Q 13 13 13 13 13 13 13 13

'13 13 13 13

< 143

< 139

< 150

< 142

< 188

< 165

< 156

< 150

< 152

< 145

< 148

< 150 MEAN TABLE D-1.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/31/12 - 01/29/13 01/29/13 - 02/26/13 02/26/13 - 04/02/13 04/02/13 - 04/30/13 04/30/13 - 05/28/13 05/28/13 - 07/02/13 07/02/13 - 07/30/13 07/30/13 - 09/03/13 09/03/13 - 10/01113 10/01/13 - 10/29/13 10/29/13 - 12/03/13 12/03/13 - 12/31/13 Q9-1Q

< 0.5

< 0.4

< 0.3

< 0.4

< 0.5

< 0.3

< 0.4

< 0.2

< 0.4 MEAN

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

TABLE D-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Q9-1Q 12/31/12 -01/29/13 01/29/13 - 02/26/13 02/26/13 - 04/02/13 04/02/13 - 04/30/13 04/30113

- 05128113 05/28/13 - 07/02/13 07/02/13 - 07/30/13 07/30/13 - 09/03/13 09/03/13 - 10/01/13 10101113

- 10/29/13 10/29/13 - 12/03/13 12/03/13 - 12/31/13

<3

<2

<6

<2

<3

< 1

<2

<3

<2

<9

<6

<5

<9

<5

<3

<5

<3

<7

<6

<2

<4

<2

<3

<6

<2

<3

<8

<11

<3

<2

<4

<2

<3

<2

<3

<2

<3

<2

<1

<2

<5

<2

<3

<2

<3

<5

< 4

<3

<7

<4

<3

<5

<3

<4

<3

< 3

<2

<3

<4

<1

<4

<3

<2

<3

<2

<4

<3

<7

<3

<2

<4

<3

<1

<2

<3

<2

<3

<8

<3

<2

<3

<1

<3

28

< 14

< 18

< 38

< 19

< 26

< 22

19

< 16

< 18

< 12

<5

<3

<5

<3

<5

<4

<3

<5

<2

<3

TABLE D-11.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/-:2 SIGMA SITE COLLECTION Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDP 09/24/13

< 8

<4 3220 +/- 360

< 8

< 13

< 34

< 8

< 17

< 12

<6

TABLE D-111.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION PERIOD K-40 Cs-134 Cs-137 J2-1 10/30/13 13490 +/- 8800

< 38 88 +/- 43 D-6

TABLE D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 1-131 Cs-134 Cs-137 Sr-89 Sr-90 PERIOD H1-2Q 07/22/13 4710 +/- 360

< 24

< 15

< 16

< 17 15 +/- 4 B10-2Q 07/09/13 1520 +/- 160

< 11

< 5

< 2

< 1 MEAN 3115 +/- 4511 D-7

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, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD UllUZII,.i 01/09/13 01/17/13 01/24/13 01/31/13 02/07/13 02/15/13 02/21/13 02/27/13 03/07/13 03/14/13 03/21/13 03/28/13 04/04/13 04/11/13 04/17/13 04/25/13 05/02/13 05/09/13 05/16/13 05/23/13 05/30/13 06/06/13 06/12/13 06/20/13 06/26/13 07/04/13 07/10/13 07/18/13 07/25/13 08/01/13 08/08/13 08/15/13 08/21/13 08/29/13 09/05/13 09/12/13 09/19/13 09/25/13 10/02/13 10/10/13 10/17/13 10/24/13 10/31/13 11/07/13 11/14/13 11/21/13 11/27/13 12/05/13 12/11/13 12/19/13 12/26/13 01/17/13 01/24/13 01/31/13 02/07/13 02/15/13 02/21/13 02/27/13 03/07/13 03/14/13 03/21/13 03/28/13 04/04/13 04/11/13 04/17/13 04/25/13 05/02/13 05/09/13 05/16/13 05/23/13 05/30/13 06/06/13 06/12113 06/20/13 06126113 07/04/13 07/10/13 07/18/13 07/25/13 08/01/13 08/08/13 08/15/13 08/21/13 08/29/13 09/05/13 09/12/13 09/19/13 09/25/13 10102/13 10/10/13 10/17/13 10/24/13 10/31/13 11/07/13 11/14/13 11/21113 11127113 12/05/13 12/11/13 12/19/13 12/26/13 01/02/14 E1-2Q GROSS BETA 55 +/--6 32 +/- 4 34 +/- 5 28 +/- 5 38 +/- 5 24 +/- 4 19 +/- 5 13 +/- 5 13 +/- 4 18 +/- 4 26 +/- 4 11+/- 4 21 +/-4 29 +/-5 17+/- 5 20 +/-4 30 +5 12 +4 21

+5 19+/- 5 25 +/-4 23+/- 5 14+/- 5 22 +/-4 38 +/-5 16 +/-4 (1) 31 +/-6 19+/- 5 19+/- 4 28 +/-5 24 +/- 5 30 +/- 5 36 +/- 5 38 +/- 5 41 +/- 5 18 +/- 4 20 +/- 5 25 +/- 5 38 +/- 5 25 +/- 4 27 +/- 5 29 +/- 5 27 +/- 5 16 +/- 4 28 +/- 5 20 +/- 5 48 +/- 5 27 +/- 5 40 +/- 5 25 +/- 4 28 +/- 5 El-2Q 1-131

< 21

< 15

< 16

< 20

< 24

< 12

< 15

< 13

< 20

< 24

< 13

< 24

< 25

< 12

< 18

< 17

< 26

< 24

< 13

< 16

< 10

< 18

< 24

< 22

< 17

< 27 (1)

< 35

< 22

< 21

< 18

< 21

< 17

< 25

< 14

< 20

<8

< 21

< 16

< 25

< 14

< 12

< 26

<9

< 19

< 15

< 21

< 10

< 22

< 24 MEAN 26 +/- 19 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION D-8

TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION Be-7 Cs-134 Cs-137 PERIOD E1-2Q 01/02/13 - 03/28/13 60 +/- 18

< 1.2

< 0.6 03/28/13 - 06/26/13 95 +/- 14

< 0.4

< 0.7 06/26/13 - 10/02/13 95 +/- 18

< 1.0

< 0.5 10/02/13 - 01/02/14 77 +/- 16

< 0.9

< 0.5 MEAN 82 +/- 34 D-9

TABLE D-VI.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION, GAMMA EMITTERS, AND STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION DATE 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 Sr-89 Sr-90 G2-1Q 01/16/13 02/13/13 03/13/13 03/27/13 04/10/13 04/24/13 05/08/13 05/22/13 06/05/13 06/19/13 07/03/13 07/17/13 07/31/13 08/14/13 08/28/13 09/11/13 09/25/13 10/09/13 10/23/13 11/06/13 11/20/13 12/04/13 S0A4

< 0.4

0.4

0.5

0.3

0.4

0.4

0.3

0.5

0.3

0.3

0.2

0.3

0.1

0.3

0.5

0.2

0.5

< 0.4

0.3

0.2

0.3 774 t 123 1069 +/- 85 913 +/- 87 1428 +/- 113 946 +/- 98 1275 +/- 97 1287 +/- 113 1126 +/- 85 952 +/- 78 918 +/- 121 1050 +/- 95 1665 +/- 119 935 +/- 95 880 +/- 84 978 +/- 102 1295 +/- 98 1086 +/- 100 937 +/- 118 1002 +/- 84 850 +/- 180 1224 +/- 105 933 +/- 88

<8

<4

<3

<6

<4

<3

<4

<3

<4

<5

<3

<6

<4

<6

<4

<6

<2

<4

<3

<4

<3

<6

<4

<3

<4

<5

<2

<7

<3

<4

< 33

19

20

16

24

18

16

12

28

23

22

22

28

< 24

29

18

27

< 44

27

< 43

<18

28

<5

<6

<4

<5

<3

<4

<3

<7

<5

<3

<4

<3

<2

<5

<4

<2

<4

< 0.6

< 0.5

< 0.6

< 0.5

< 0.8

< 0.7

< 0.5

< 0.5 MEAN 1069 +/- 436 D-10

FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2013 6

QC-LAB A PRIM A RY - LA B 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, 2013 60 50 I'-.)

E C?wj 40 30 20 10 0

1 4

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

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

Intentionally left blank

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b) TBE/Analytics Evaluation (d)

March 2013 E10477 E10478 E10480 E10479 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 120 99.7 pCi/L 9.21 11.0 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 87.1 186 463 201 262 200 215 266 311 384 95.3 264 123 142 112 115 139 163 212 100 187 472 214 266 208 208 252 301 400 95.6 241 109 136 106 106 129 153 204 AP Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 June 2013 E10481 E10564 E10545 E10547 E10546 pCi 90.1 92.6 pCi/L 1840 1890 pCi/L 110 95.0 pCi/L 15.8 17.0 1.20 0.84 0.87 0.99 0.98 0.94 0.98 0.96 1.03 1.06 1.03 0.96 1.00 1.10 1.13 1.04 1.06 1.08 1.08 1.07 1.04 0.97 0.97 1.16 0.93 0.97 0.92 1.01 0.94 0.95 0.93 0.99 1.04 1.01 0.97 1.00 1.07 1.09 1.07 1.06 1.16 1.14 1.24 1.05 0.96 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-1 37 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 A

A A

92.6 83.1 253 118 143 87.1 171 125 220 169 56.8 168 85.2 101 62.7 125 85.7 169 116 95.5 90.4 250 125 151 94.0 172 120 217 175 56.7 157 78.4 94.6 58.9 108 75.0 136 110 A

A A

W A

AP Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi 86.5 89.7 A

E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

TBE/Analytics Evaluation (d)

June 2013 E10549 Water Fe-55 pCi/L 1610 1610 pCi/L 63.9 96.0 pCi/L 8.88 13.2 September2013 E10646 E10647 E10672 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 93.9 98.3 272 150 125 105 138 125 264 187 208 143 106 97.0 116 98.6 219 166 277 172 131 108 139 130 266 196 223 139 105 86.5 112 105 214 158 AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Water Fe-55 E10648 E10673 pCi 76.3 71.7 pCi/L 1790 1690 pCi/L 97.3 93.8 pCi/L 13.3 12.9 1.00 0.67 0.67 0.96 0.98 0.87 0.95 0.97 0.99 0.96 0.99 0.95 0.93 1.03 1.01 1.12 1.04 0.94 1.02 1.05 1.06 1.06 1.04 1.03 0.93 0.91 1.00 0.91 1.00 1.04 0.99 1.06 1.02 0.96 0.97 1.17 1.08 1.01 0.94 0.98 1.14 0.85 1.00 N (1)

N (1)

A NA (2)

A A

NA (2)

A A

A December2013 E10774 E10775 E10777 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 89.7 99.8 297 129 126 116 167 117 757 141 85.1 278 123 102 84.4 132 101 506 118 96.1 110 297 142 126 112 168 110 741 147 88.0 238 114 101 89.9 135 88.3 595 118 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, 2013 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

December 2013 E10776 E10778 Charcoal 1-131 Water Fe-55 pCi 84.7 80.5 pCi/L 2010 1910 1.05 1.05 A

A (1)

(2)

(a)

(b)

(C)

(d)

Milk, Sr-89/90 - The failure was due to analyst error. No client samples were affected by this failure. NCR 13-15 The sample was not spiked with Ce-141.

Teledyne Brown Engineering reported result.

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.

Ratio of Teledyne Brown Engineering to Analytics results.

Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0.80-1.20.

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

E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2013 (PAGE 1 OF 1)

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

Value (b)

Limits Evaluation (c)

May 2013 RAD-93 MRAD-18 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 U-Nat H-3 Filter Gr-A pCi/L 48.3 41.3 pCi/L 19.3 23.9 pCi/L 81.9 82.1 pCi/L 40.9 42.8 pCi/L 44,0 41.7 pCi/L 61.9 65.9 pCi/L 202 189 pCi/L 34.2 40.8 pCi/L 18.0 21.6 pCi/L 23.8 23.8 pCi/L 60.4 61.2 pCi/L 3970 4050 pCi/filter Lost during processing 31.6-48.4 17.2 - 28.0 69.0 - 90.3 34.2-47.1 37.0 - 48.8 59.3 - 75.0 170-222 21.1 -51.9 13.0-29.7 19.7 -28.3 49.8 - 67.9 3450 - 4460 A

A A

November 2013 RAD-95 pCi/L 25.5 pCi/L 14.3 pCi/L 57.2 pCi/L 83.3 pCi/L 201 pCi/L 104 pCi/L 361 pCi/L 29.5 pCi/L 30.1 pCi/L 23.1 pCi/L 5.53 pCi/L 17650 pCi/filter 33.0 21.9 18.1 54.2 86.7 206 102 333 42.8 32.2 23.6 6.24 17700 14.4-28.2 12.8-21.5 44.7 - 59.9 71.1 -95.4 185-228 91.8-114 300 - 389 22.2 - 54.3 20.8-39.9 19.6 - 28.0 4.70 - 7.44 15500- 19500 MRAD-19 83.0 27.8-129 (a) Teledyne Brown Engineering reported result.

(b) The EZRA 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, 2013 (PAGE 1 OF 2)

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

Range Evaluation (c)

March 2013 13-MaW28 13-GrW28 13-MaS28 13-RdF28 13-GrF28 13-RdV28 September 2013 13-MaW29 13-GrW29 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 AP Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 K-40 Sr-90 Zn-65 Water Gr-A Gr-B Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 21.0 24.4 17.1 -31.7 0.0446 (1) 28.3 30.9 21.6-40.2 18.2 19.56 13.69 - 25.43 506 507 355 - 659 25.7 27.4 19.2 - 35.6 2.09 (1) 10.5 10.5 7.4-13.7 29.2 30.4 21.3-39.5 A

A A

Bq/L 2.74 2.31 Bq/L 15.6 13.0 0.69 - 3.93 6.5-19.5 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 859 887 621-1153 633 587 411-763 0.256 (1) 738 691 484-898 0.671 (1) 714 625.3 437.7 - 812.9 442 628 440-816 1057 995 697-1294 Bq/sample 1.73 1.78 1.25-2.31 Bq/sample 2.73 2.60 1.82-3.38 Bq/sample 2.38 2.36 1.65-3.07 Bq/sample 0.0302 (1)

Bq/sample 4.36 4.26 2.98 - 5.54 Bq/sample 1.43 1.49 1.04-1.94 Bq/sample 3.14 3.13 2.19-4.07 Bq/sample 0.767 1.20 0.36-2.04 Bq/sample 0.871 0.85 0.43-1.28 Bq/sample

-0.197 (1)

Bq/sample 7.39 6.87 4.81 - 8.93 Bq/sample 9.87 8.68 6.08 - 11.28 Bq/sample 6.08 5.85 4.10-7.61 Bq/sample

-0.0104 (1)

Bq/sample 1.28 1.64 1.15-2.13 Bq/sample 6.84 6.25 4.38-8.13 Bq/L 29.1 30.0 21.0-39.0 Bq/L 34.5 31.6 22.1-41.1 Bq/L 0.0358 (1)

Bq/L 24.6 23.58 16.51 - 30.65 Bq/L 2.45 (1)

Bq/L 0.0337 (1)

Bq/L 0.193 (1)

Bq/L 9.12 7.22 5.05 - 9.39 Bq/L 38.1 34.6 24.2 -45.0 Bq/L 1.13 0.701 0.210- 1.192 Bq/L 7.61 5.94 2.97 - 8.91 E-5

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

TELEDYNE BROWN ENGINEERING, 2013 (PAGE 2 OF 2)

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

Range Evaluation (c)

September 2013 13-MaS29 13-RdF29 Soil Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 1150 1100 670 502 758 796 664 210

-0.570 2.85 3.30 2.41 3.65 1.40 2.90 1172 820-1524 977 684-1270 (1) 451 316-586 674 472-876 633 443-823 460 322-598 (1) 13-GrF29 13-RdV29 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 2.7 3.4 2.3 3.5 1.81 2.7 (1) 1.9-3.5 2.4-4.4 1.6-3.0 2.5-4.6 1.27 -2.35 1.9-3.5 A

A N (2)

A A

W N (2)

N (2)

A A

W A

A A

A W (2)

W Bq/sample 0.872 0.9 0.3-1.5 Bq/sample 1.57 1.63 0.82-2.45 Bq/sample Bq/sample Bq/sample Sq/sample Bq/sample Bq/sample Bq/sample 5.29 7.48 0.0129 0,0523 8.78 1.63 3.18 5.20 3.64 - 6.76 6.60 4.62 - 8.58 (1)

(1) 7.88 5.52 - 10.24 2.32 1.62 - 3.02 2.63 1.84-3.42 (1) False positive test.

(2) Soil, Co-57 & Zn-65 identified by gamma software as not detected, MAPEP evaluated as failing the false positive test. A large concentration of Eu-152 was spiked into the sample, causing interference in the analysis. Gamma software recognized the interference and identified them as not detected. MAPEP does not allow clients to enter non-detect designation. NCR 13-04 Soil, Sr incorrect results were submitted to MAPEP. Actual result was 332 bq/kg, which is within the acceptance range. NCR 13-04 AP, Cs-134 - MAPEP evaluated the -0. 570 as a failed false positive test. No client samples were affected by these failures. NCR 13-04 Vegetation, Sr it appears that the carrier was double spiked into the sample, resulting in the low activity for this sample. NCR 13-04 (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 gravim etric 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 PROGRAMa ENVIRONMENTAL, INC., 2013 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result (b)

Result (c)

Limits Acceptance ERW-1593 ERW-1 593 ERW-1 596 ERW-1 596 ERW-1596 ERW-1 596 ERW-1596 ERW-1598 ERW-1 598 ERW-1600 ERW-1600 ERW-1606 ERW-6009 ERW-6009 ERW-6012 ERW-6012 ERW-6012 ERW-6012 ERW-6012 ERW-6015 ERW-6015 ERW-6019 ERW-6024 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 04/08/13 10/07/13 10/07/13 10/07/13 10/07/13 10/07/13 10/07/13 10/07/13 10/07/13 10/07/13 10/07/13 10/07/13 Sr-89 Sr-90 Ba-133 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 1-131(G)

H-3 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 43.6 +/- 4.3 23.2 +/- 1.7 74.80 4.00 65.50 3.42 41.10 3.47 42.30 4.03 200.3 +/- 10.1 34.30 1.98 18.70 0.98 23.00 +/- 1.10 23.48 +/- 9.44 4041 +/- 194 22.00 2.80 17.10 2.55 48.20 4.29 100.8 +/- 4.7 87.30 4.35 199.6 +/- 7.4 356.2 +/- 13.2 30.70 11.90 25.70 6.48 22.50 1.01 18397 695 41.30 23.90 82.10 65.90 42.80 41.70 189.0 40.80 21.60 23.80 23.80 4050 21.90 18.10 54.20 102.0 86.70 206.0 333.0 42.80 32.20 23.60 17700 31.6 -48.4 17.2 -28.0 69.00 90.30 59.30 75.00 34.20 47.10 37.00 48.80 170.0 - 222.0 21.10 51.90 13.00 29.70 19.70 - 28.30 19.70 +/- 28.30 3450 -4460 14.40 28.20 12.80 21.50 44.70 59.90 91.8-114.0 71.10 95.40 185.0 - 228.0 300.0 - 389.0 22.20 54.30 20.80 39.90 19.60 28.00 15500 19500 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

E-7

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

ENVIRONMENTAL, INC., 2013 (Page 1 of 2)

Concentration (a)

Known Control Lab Code (b) Date Analysis Laboratory result Activity Limits (c)

Acceptance MAAP-738 MAAP-738 MAAP-738 MAAP-738 MAAP-738 MAAP-738 MAAP-738 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 Gr. Alpha Gr. Beta 2.58 +/- 0.06 0.01 +/- 0.03 1.82 +/- 0.13 2.93 +/- 0.10 4.87 +/- 0.13 1.39 +/- 0.14 3.84 +/- 0.20 0.14 +/- 0.03 0.93 +/- 0.06 2.36 0.00 1.78 2.60 4.26 1.49 3.13 1.20 0.85 1.65 -3.07 0.00 -0.10 1.25 -2.31 1.82 -3.38 2.98 - 5.54 1.04-1.94 2.19 -4.07 0.36 -2.04 0.43 - 1.28 Pass Pass Pass Pass Pass Pass Pass Fail (1)

Pass MAAP-738 d 02/01/13 MAAP-738 02/01/13 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 MAW-806 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 H-3 K-40 Mn-54 Sr-90 Zn-65 MAW-811 02/01/13 Gr. Alpha MAW-811 02/01/13 Gr. Beta MASO-739 MASO-739 MASO-739 MASO-739 MASO-739 MASO-739 MASO-739 MASO-744 e MAVE-747 MAVE-747 MAVE-747 MAVE-747 MAVE-747 MAVE-747 MASO-5043 f MASO-5043 MASO-5043 MASO-5043 MASO-5043 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 02/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Zn-65 Sr-90 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Zn-65 Co-57 Cs-134 Cs-1 37 K-40 Mn-54 31.20 0.40 19.70 +/- 0.30 23.20 +/- 0.50 0.03 +/- 0.12 34.00 +/- 3.30 511.60 +/- 12.50 2.20 +/- 0.90 27.60 +/- 0.50 9.30 +/- 0.80 31.60 +/- 0.80 1.87 +/- 0.09 13.04 +/- 0.13 0.60 +/- 0.50 739.20 +/- 28.50 863.30 +/- 34.10 661.80 +/- 25.70 745.80 +/- 33.30 1.10 +/- 1.00 1109.60 +/- 44.10 408.40 +/- 14.00 10.37 +/- 0.17 6.48 +/- 0.17 0.02 +/- 0.04 7.79 +/- 0.21 0.00 +/- 0.05 7.29 +/- 0.33 699.60 +/- 3.90 1191.70 +/- 23.00 1072.00 +/- 5.10 760.00 +/- 16.20 753.80 +/- 4.90 30.90 16.56 24.40 0.00 44.00 507.00 0.00 27.40 10.50 30.40 2.31 13.00 0.00 691.00 887.00 587.00 625.30 0.00 995.00 628.00 8.68 5.85 0.00 6.87 0.00 6.25 0.00 1172.00 977.00 633.00 674.00 0.69 - 3.93 6.50 -19.50 0.00 484.00 621.00 411.00 437.70 0.00 21.60 13.69 17.10 0.00 30.80 355.00 0.00 19.20 7.40 21.30 40.20

-25.43

-31.70

-1.00

-57.20

-659.00

-5.00

-35.60

-13.70

-39.50 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

-5.00

-898.00

-1153.00

-763.00

-812.90

-5.00 697.00 - 1294.00 440.00 - 816.00 6.08-11.28 4.10 -7.61 0.00 -0.10 4.81 -8.93 0.00 -0.10 4.38 -8.13 0.00 -5.00 820.00 -1524.00 684.00 - 1270.00 443.00 - 823.00 472.000 -876.000 Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail (2)

Pass Pass Pass Pass Pass Pass Fail (3)

Pass Pass Pass Pass E-8

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

ENVIRONMENTAL, INC., 2013 (Page 2 of 2)

Concentration (a)

Known Control Lab Code (b) Date Analysis Laboratory result Activity Limits (c)

Acceptance MASO-5043 08/01/13 MASO-5043 08/01/13 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAW-5094 MAVE-5046 MAVE-5046 MAVE-5046 MAVE-5046 MAVE-5046 MAVE-5046 MAAP-5046 MAAP-5046 MAAP-5046 MAAP-5046 MAAP-5046 MAAP-5046 MAAP-5046 MAAP-5046 MAAP-5046 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 08/01/13 Sr-90 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 Gr. Alpha Gr. Beta H-3 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-137 Gr. Alpha Gr. Beta Mn-54 Sr-90 Zn-65 383.90 +/- 14.50

-351.50 +/- 5.50 0.01 +/- 0.09 23.20 +/- 0.32 27.60 +/- 0.58 32.31 +/- 0.52 39.20 +/- 3.50 0.54 +/- 0.05 5.85 +/- 0.09 1.20 +/- 3.00 2.22 +/- 0.90 0.010 +/- 0.11 6.40 +/- 0.60 35.30 +/- 0.90 460.00 0.00 0.00 23.58 30.40 31.60 53.30 0.70 5.94 0.00 0.00 0.00 7.22 34.60 322.00 - 598.00 0.00 - 0.00 0.00 - 5.00 16.51 - 30.65 21.00 - 39.00 22.10 - 41.10 37.30 - 69.30 0.21 -1.19 2.97 - 8.91 0.00 - 5.00 0.00 - 5.00 0.00 - 5.00 5.05 - 9.39 24.20 - 45.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 0.01 +/- 0.03 0.00 +/- 0.04 5.71 +/- 0.23 7.64 +/- 0.20 9.08 +/- 0.24 2.92 +/- 0.25 3.48 +/- 0.14 2.44 +/- 0.08 0.01 +/- 0.03 3.09 +/- 0.13 0.28 +/- 0.04 1.90 +/- 0.08 3.95 +/- 0.12 1.69 +/- 4.10 3.27 +/- 0.18 0.00 0.00 5.20 6.60 7.88 2.63 3.40 3.40 0.00 2.70 0.90 1.63 3.50 1.81 2.70 0.00 - 0.00 0.00 - 0.00 3.64 -6.76 4.62 - 8.58 5.52 - 10.24 1.84 -3.42 1.90 -3.50 1.60 -3.00 0.02 - 0.04 1.90 -3.50 0.27 -1.53 0.82 - 2.45 2.50 - 4.60 1.27 -2.35 2.50 - 4.60 a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

(1) The filter was recounted overnight, no significant alpha activity could be detected.

(2) The sample was reanalyzed using additional fuming nitric separations. Result of reanalysis: 574.4 +/- 35.2 Bq/kg.

(3) Interference from Eu-1 52 resulted in misidentification of Co-57.

E-9

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APPENDIX F ERRATA DATA

Intentionally left blank

Due to an incorrect setting on gamma detector 08, 3.29 rather than 4.66 was used in the minimum detectable concentration (MDC) calculation.

Nonconformance 13-07 was initiated and corrective actions have been implemented to address this issue. All samples counted on detector 08 were reprocessed using the correct calculation. As a result, all MDCs for these samples have increased by 41.6%. The previously reported activities and uncertainties were not affected. In some cases, the increased MDC resulted in missed LLDs. All samples with MDCs affected by this issue are listed below. The samples with missed LLDs are shown in the table for 2011, 2012, and 2013. All other required LLDs were met.

Because of the quantity of tables involved over multiple years, individual tables are not provided. (IR 1646280)

F-i

2011 START END CLIENT ID DATE DATE MATRIX 4Q11 TM-AP-Q15-1 09/28/11 12/28/11 Air Particulate REQUIRED REVISED NUCLIDE MDC MDC UNITS F-2

2012 START END REQUIRED REVISED CLIENT ID DATE DATE MATRIX NUCLIDE MDC MDC UNITS 1Q12 TM-AP-Q15-1 12/28/11 03/28/12 Air Particulate TM-EW-K1-1 01/03/12 01/31/12 Effluent Water OS-16 01/31/12 RGPP 1-131

<15

<16.84 pCi/L TM-M-G2-1 03/07/12 03/07/12 Milk 2Q12 TM-AP-H3-1 03/28/12 06/27/12 Air Particulate TM-M-P4-1 04/18/12 04/18/12 Milk MW-TMI-171 04/30/12 RGPP OSF 04/30/12 RGPP TM-EW-K1-1 05/01/12 05/29/12 Effluent Water MS-2 05/01/12 RGPP MW-TMI-31 05/02/12 RGPP MS-3 05/03/12 RGPP TM-SW-Q9-1 05/29/12 07/03/12 Surface Water TM-M-F4-1 05/30/12 05/30/12 Milk TM-M-P4-1 06/13/12 06/13/12 Milk TM-FPL-B10-2 06/26/12 06/26/12 Vegetation 3Q12 TM-AP-G2-1 06/27/12 10/03/12 Air Particulate 3Q12 TM-AP-Q15-1 06/27/12 09/26/12 Air Particulate TM-M-K15-3 06/27/12 06/27/12 Milk La-140

<15

<19.44 pCi/L TM-FPV-B10-2 07/17/12 07/17/12 Vegetation OS-14 07/24/12 RGPP 1-131

<15

<20.55 pCi/L OS-14 07/24/12 RGPP La-140

<15

<15.9 pCi/L TM-M-F4-1 07/25/12 07/25/12 Milk TM-M-P4-1 07/25/12 07/25/12 Milk TM-SW-J1-2 07/31/12 08/28/12 Surface Water 1-131

<15

<15.45 pCi/L TM-DW-Q9-1 08/28/12 10/02/12 Drinking Water 1-131

<15

<18.1 pCi/L TM-M-F4-1 09/19/12 09/19/12 Milk TM-FPL-B10-2 09/26/12 09/26/12 Vegetation 1-131

<60

<79.06 pCi/kg Wet TM-SW-Q9-1 10/02/12 10/30/12 Surface Water 4Q12 TM-AP-H3-1 10/03/12 01/02/13 Air Particulate MS-8 10/17/12 RGPP 1-131

<15

< 16.04 pCi/L MS-8 10/17/12 RGPP La-140

<15

<17.86 pCi/L TM-M-E2-2 10/17/12 10/17/12 Milk TM-SW-J 1-2 10/30/12 11/27/12 Surface Water EDCB 10/30/12 12/31/12 RGPP TM-M-P4-1 10/31/12 10/31/12 Milk La-140

<15

<15.24 pCi/L TM-SW-Q9-1 11/27/12 12/31/12 Surface Water 1-131

<15

<17.38 pCi/L TM-SW-Q9-1 11/27/12 12/31/12 Surface Water La-140

<15

<18.63 pCi/L F-3

2012 START END REQUIRED REVISED CLIENT ID DATE DATE MATRIX NUCLIDE MDC MDC UNITS TM-M-K15-3 11/28/12 11/28/12 Milk Ba-140

<60

<70.14 pCi/L F-4

2013 START END REQUIRED REVISED CLIENT ID DATE DATE MATRIX NUCLIDE MDC MDC UNITS MS-3 01/22/13 RGPP 1-131

<15

< 19.17 pCi/L TM-M-E2-2 02/13/13 02/13/13 TM-M-F4-1 02/13/13 02/13/13 F-5

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APPENDIX G ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank

Docket No:

50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS I and 2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January Through 31 December 2013 Prepared By Teledyne Brown Engineering Environmental Services SExeton Generation.

Three Mile Island Nuclear Station Middletown, PA 17057 April 2014

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

1 II. Introduction.............................................................................................................

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

3 B. Im plem entation of the Objectives..................................................................

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

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

5 I1l. Program Description................................................................................................

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

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

7 IV. Results and Discussion...........................................................................................

8 A. Groundwater Results.....................................................................................

8 B. Surface W ater Results..................................................................................

9 C. Storm W ater Results.....................................................................................

10 D. Precipitation W ater Results.........................................................................

11 E. Leaks, Spills, and Releases.........................................................................

11 F. Actions Taken................................................................................................

12

Appendices Appendix A Tables Table A-1 Figqures Figure A-1 Appendix B Tables Table B-1.1 Table B-1.2 Table B-1.3 Table B-11.1 Table B-11.2 Table B-ll1.1 Table B-111.2 Table B-IV.1 Location Designation Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2013 Sampling Locations at the Three Mile Island Nuclear Station, 2013 Data Tables Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2013.

Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2013.

Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

ii

Appendix C Data Tables Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-11.1 Table C-11.2 Table C-111.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

Concentrations of Hard-To-Detects in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2013.

Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

Concentrations of Gamma Emitters in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

Concentrations of Tritium in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2013.

iii

I.

Summary and Conclusions In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Three Mile Island Nuclear Station. At Three Mile Island Nuclear, 31 new permanent groundwater monitoring wells were installed in 2006. The results for all TMI wells are included in this report. This report covers groundwater, surface water, storm water and precipitation samples collected from the environment, both on and off station property in 2013. During that time period 802 analyses were performed on 452 samples from 68 locations.

In assessing all the data gathered for this report, it was concluded that the operation of Three Mile Island Nuclear Station had no adverse radiological impact on the environment.

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

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

Tritium was not detected in any groundwater, surface water, storm water or precipitation water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 37 of 59 groundwater monitoring locations. The groundwater tritium concentrations ranged from 174 +/- 111 pCi/L to 11,900 +/- 1,240 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of a potential leak, historical releases, the recapture of gaseous tritium releases via rainwater and/or background from external sources greater than 200 pCi/L. Tritium was detected in two of five precipitation water locations. The concentration ranged from 218 +/-

116 to 530 +/- 133 pCi/L. Tritium was not detected at any surface water location.

Tritium was detected in three storm water samples. The concentrations ranged from 217 +/- 131 to 289 +/- 116 pCi/L.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second and fourth quarter sampling in 2013. Gross Alpha (dissolved) was detected in two of the 39 groundwater locations. The concentrations were 0.9 and 1.2 pCi/L. Gross Alpha (suspended) was detected in six of 39 groundwater locations. The concentrations ranged from 0.9 to 10.8 pCi/L. Gross Beta (dissolved) was detected at all 39 groundwater locations. The concentrations ranged from 1.6 to 14.7 pCi/L. Gross Beta (suspended) was detected in five of 39 groundwater locations. The concentrations were 2.3 and 6.3 pCi/L.

Hard-To-Detect analyses were performed on a select group of groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238.

The U-234 isotope was detected at all four groundwater location. The concentration ranged from 0.3 to 4.9 pCi/L. The U-238 isotope was detected at three of four groundwater locations. The concentration ranged from 0.4 to 3.4 pCi/L. The levels detected are from naturally occurring isotopes and are considered background.

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

II.

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

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

As a result of the Phase 1 study, the Radiological Groundwater Protection Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on well water, surface water, precipitation water and storm water samples collected in 2013. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2013.

A.

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B.

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

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

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

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

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

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

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

C.

Program Description

1.

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

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

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

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

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

D.

Characteristics of Tritium (H-3)

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

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

Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

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

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

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

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

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

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 2013.

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

1.

Concentrations of gamma emitters in groundwater, surface water and storm water.

2.

Concentrations of strontium in groundwater.

3.

Concentrations of tritium in groundwater, surface water, precipitation water and storm water.

4.

Concentrations of Am-241 in groundwater.

5.

Concentrations of Cm-242 and Cm-243/244 in groundwater.

6.

Concentrations of Pu-238 and PU-239/240 in groundwater.

7.

Concentrations of U-234, U-235 and U-238 in groundwater.

8.

Concentrations of Fe-55 in groundwater.

9.

Concentrations of Ni-63 in groundwater.

10.

Concentrations of Gross Alpha and Gross Beta (Dissolved and Suspended) in groundwater.

B.

Data Interpretation

1.

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

2.

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

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

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

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

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

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

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

IV.

Results and Discussion A.

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

Analytical results and anomalies are discussed below.

Tritium Samples from 59 locations were analyzed for tritium activity. Tritium values ranged from the detection limit to 11,900 pCi/L (Table B-1.1, Appendix B).

Tritium Split Samples Tritium values ranged from 389 to 7,822 pCi/L (Table C-1.1, Appendix C).

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

Strontium Split Samples Strontium-89 and Strontium-90 were not detected above the required detection limit (Table C-1.1, Appendix C).

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second and fourth quarter sampling in 2013. Gross Alpha (dissolved) was detected in two of the 39 groundwater locations. The concentrations were 0.9 and 1.2 pCi/L. Gross Alpha (suspended) was detected in six of 39 groundwater locations. The concentrations ranged from 0.9 to 10.8 pCi/L. Gross Beta (dissolved) was detected at all 39 groundwater locations. The concentrations ranged from 1.6 to 14.7 pCi/L. Gross Beta (suspended) was detected in five of 39 groundwater locations. The concentrations were 2.3 and 6.3 pCi/L (Table B-1.1, Appendix B).

Gross Alpha and Gross Beta Split Samples Four split samples were analyzed for Gross Alpha and Gross Beta in 2013. Gross Alpha was detected one of four samples at a concentration of 2.4 pCi/L. Gross beta was detected in all four sample analyzed. The concentrations ranged from 2.3 to 6.7 pCi/L (Table C-1.1, Appendix C).

Gamma Emitters Potassium-40 was detected in two of 75 samples with concentrations ranging from 82 pCi/L to 91 pCi/L. No other gamma-emitting nuclides were detected (Table B-1.2, Appendix B).

Gamma Emitters Split Samples Seven locations were analyzed for gamma-emitting nuclides in 2013. Potassium-40 was detected in one sample at a concentration of 57 pCi/L. No other gamma-emitting nuclides were detected in any split samples (Table C-1.2, Appendix C).

Hard-To-Detect Hard-To-Detect analyses were performed on a select group of groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238. The U-234 isotope was detected at all four groundwater location. The concentration ranged from 0.3 to 4.9 pCi/L. The U-238 isotope was detected at three of four groundwater locations. The concentration ranged from 0.4 to 3.4 pCi/L. The concentrations detected are from naturally occurring isotopes and are considered background (Table B-1.3, Appendix B).

Hard-To-Detect Split Samples Hard to detects were not analyzed on any split samples in 2013 (Table C-1.3, Appendix C).

B.

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

Analytical results and anomalies are discussed below.

Tritium Three locations were analyzed for tritium in 2013. Tritium was not detected above the required detection limit of 200 pCi/L in any of the 14 samples analyzed (Table B-11.1, Appendix B).

Tritium Split Samples Two locations were analyzed for tritium in 2013. Tritium was not detected above the required detection limit (Table C-11.1, Appendix C).

Strontium Surface water samples were not analyzed for Sr-90 in 2013 (Table B-11.1, Appendix B).

Gamma Emitters Three locations were analyzed for gamma-emitting nuclides in 2013. None of the four samples detected gamma-emitting nuclides (Table B-11.2, Appendix B).

Gamma Emitters Split Samples One location was analyzed for gamma-emitting nuclides in 2013.

No gamma emitting nuclides were detected (Table C-11.2, Appendix C).

C.

Storm Water Results Samples were collected from storm water locations in accordance with the station radiological groundwater protection program.

Analytical results and anomalies are discussed below.

Tritium One location was analyzed for tritium. Tritium was detected in one of samples above the required detection limit of 200 pCi/L. A recount and reanalysis was performed and the concentrations ranged from 217 to 289 pCi/L (Table B-Ill.1, Appendix B).

Gamma Emitters Samples from one location were analyzed for gamma-emitting nuclides. No gamma emitting nuclides were detected (Table B-Ill.2, Appendix B).

D.

Precipitation Water Results Samples were collected at five locations. The following analyses were performed:

Tritium Samples from five locations were analyzed for tritium activity. Tritium activity was detected at two of five locations. The concentrations ranged from 218 to 530 pCi/L (Table B-IV.1, Appendix B).

Tritium Split Samples Samples from one location were analyzed for tritium activity. Tritium activity was detected in two of four samples. The concentrations ranged from 173 to 244 pCi/L (Table C-111.1, Appendix C).

Gamma Emitters Precipitation water was not analyzed for Gamma Emitters in 2013.

Gamma Emitters Split Samples No gamma-emitting nuclides were analyzed in 2013.

E.

Leaks, Spills, and Releases A potential leak was identified at TMI in 2012 due to elevated MS-22 tritium concentration readings. TMI continues to monitor MS-22 and surrounding wells, in addition to tritium plumes from previous years and reports the activity and dose to the public in the ARERR. The elevated MS-22 well tritium concentrations were voluntarily reported under the reporting requirements for the NEI Groundwater Protection Initiative (GPI) as implemented in Exelon's Reportability procedure LS-AA-1120, RAD 1.34. (IR1385497/1515261)

F.

Actions Taken

1. Compensatory Actions TMI has an extensive groundwater monitoring program with over 50 monitoring wells. No monitoring wells outside the investigation area have seen elevated tritium.

In 2013, TMI installed eight new wells to help isolate the area of the leak. The tritium concentrations in the new wells ranged from 222 to 7,870 pCi/L. TMI also mitigated a number of potential sources for tritium during 2013. The Borated Water Storage Tank (BWST) tunnel sump was repaired and recoated and the BWST had an internal surface inspection during the TMI refueling outage. Additionally, an active input to the BWST tunnel sump (packing leak-off of a BWST isolation valve) was corrected. Two different leaks on the Condensate Storage Tank B were also identified and repaired. Finally, in December BS-T-1 & 2 and ancillary piping were drained and emptied.

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APPENDIX A LOCATION DESIGNATION & DISTANCE

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TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2013 Site Site Type

3 48N 48S E1-2 EDCB GP-12 GP-6 GP-8 GP-9 MS-1 MS-19 MS-2 MS-20 MS-21 MS-22 MS-3 MS-4 MS-5 MS-6 MS-7 MS-8 MW-1 MW-2 MW-3 MW-4 N2-1 NW-A NW-B NW-C NW-CW OS-13B OS-14 OS-16 OS-17 OS-18 OSF RW-1 RW-2 SW-E-1 SW-E-2 SW-E-3 MW-TMI-9S*

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

MW-TMI-12S MW-TMI-131 MW-TMI-13S MW-TMI-14D MW-TMI-141 MW-TMI-14S MW-TMI-16D MW-TMI-161 MW-TMI-17D MW-TMI-171 MW-TMI-18D MW-TMI-19D MW-TMI-191 MW-TMI-1D MW-TMI-20D**

Monitoring Well Monitoring Well Production Potable Well Monitoring Well, Offsite Storm Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well, Offsite Production Well Production Well Production Well Clearwell Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Production Potable Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well A-i

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2013 Site Site Type MW-TMI-201**

MW-TMI-21D**

MW-TMI-211**

MW-TMI-21S**

MW-TMI-22D**

MW-TMI-221**

MW-TMI-22S**

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 MW-TMI-9S TRAINING CENTER TM-PR-ESE TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-20 TM-PR-MS-22 TM-PR-MS-4 TM-PR-NW-B 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 Monitoring Well Offsite Monitoring Well Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water Precipitation Water

NO WATER PRESENT TO SAMPLE

- NEW WELLS INSTALLED 2013 A-2

A Z

-I11AW'I Sampling Locations at Three Mile Island 2~

75 550 1,1too Fee(

I NI*f'.1ylpm**

.............Nuclear Station 400 Old Reading Pike ldg A Suite101 Stowe, PA 19444

'0W0tlt3 I

,a ser. zzns Wn

r. w Figure A - I Sampling Locations at the Three Mile Island Nuclear Station, 2013 A-3

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APPENDIX B DATA TABLES

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TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION DATE H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS) 3 3

3 3

48S 48S 48S 48S 48S 48S 48S 48S 48S MS-1 MS-1 MS-1 MS-1 MS-19 MS-19 MS-19 MS-19 MS-2 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-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 01123/13 04/23113 07/24/13 10/23/13 01/21/13 02/19/13 04/15/13 04/25/13 05/20/13 07/01/13 07/25/13 09/04/13 10/24/13 01/23/13 04/25/13 07/23/13 10/22/13 01/23/13 04/24/13 07/24/13 10/23/13 01/22/13 01/22/13 04/23/13 07/23/13 10/22/13 01/07/13 01/14/13 01/21/13 01/28/13 02/04/13 02/11/13 02/19/13 02/25/13 03/04/13 03/11/13 03/18/13 03/25/13 04/01/13 04/08/13 04/15/13 04/18/13 04/22/13 04/29/13 05/06/13 05/13/13 05/20/13 05/28/13 06/03/13 06/10/13

< 178 269 + 134

< 161

< 172

181

181

< 193

< 183

< 166

< 171

< 186

< 168

< 177

< 175

< 179

188 195 + 121

< 171

< 179

182

< 176

< 7.6

< 0.7

< 0.4 1.3 +/- 0.8 2.1 +/- 0.7 2.3 +/- 1.1

<8.4

<0.7

<1.4

< 0.4 2.4 +/- 1.2

< 1.6

<9.0

<0.8

<2.3

< 7.3

< 0.7

< 0.7 467 536 359 226 219 588 514 652 698

< 169 293 455 518 349 371 369 533 540 569 754 521 893 567 526 535 435 237 316 430

+/- 148

+/- 136

+/- 143

+/- 110

+/- 125

+/- 138

+/- 136

+/- 137

+/- 159

+/- 133

+/- 131

+/- 156

+/- 129

+/- 151

+/- 144

+/- 131

+/- 138

+/- 134

+/- 164

+/- 127

+/- 147

+/- 142

+/- 150

+/- 137

+/- 124

+/- 141

+/- 127

+/- 130

6.6

< 7.9

< 0.7

< 0.6

< 0.4

0.4

< 0.7

< 0.4 5.4 +/- 1.5

< 1.6 3.0 +/-0.9

< 1.5 3.8 +/-0.9

< 1.6 4.0 +/-0.9

< 1.6 B-I

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION DATE H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS)

MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-20 MS-21 MS-21 MS-21 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 06/17/13 06/24/13 07/01/13 07/08/13 07/15/13 07/23/13 09/03/13 10/22/13 10/22/13 11/25/13 12/16/13 01/22/13 04/23/13 07/23/13 01/07/13 01/14/13 01/21/13 01/28/13 02/04/13 02/11/13 02/19/13 02/25/13 03/04/13 03/11/13 03/18/13 03/25/13 04/01/13 04/08/13 04/15/13 04/18/13 04/22/13 04/29/13 05/06/13 05/13/13 05/20/13 05/28/13 06/03/13 06/10/13 06/17/13 06/24/13 07/01/13 07/08/13 07/15/13 07/22/13 07/29/13 08/05/13 08/12/13 08/19/13 08/26/13 09/03/13 378 +/- 133 342 +/- 126 415 +/- 127 512 +/- 132 547 +/- 144 415 +/- 138 640 +/- 133 742 +/- 141 528 +/- 134 620 +/- 158 416 +/- 133 278 +/- 123 270 +/- 140

< 7.7 289 +/- 113 4350 +/- 482 6230 +/- 670 3960 +/- 435 6310 +/- 672 3010 +/- 349 4200 +/- 477 3050 +/- 358 5070 +/- 541 2450 +/- 298 2570 +/- 319 2570 +/- 312 3070 +/- 352 4150 +/- 474 6260 +/- 668 11000 +/- 1150 9870 +/- 1020 9650 +/- 1010 < 6.8 9470 +/- 995 11900 +/- 1240 7110 +/- 758 9450 +/- 985 4560 +/- 529 6110 +/- 663 4480 +/- 501 2310 +/- 283 5830 +/- 633 8260 +/- 864 8690 +/- 910 9080 +/- 945 9830 +/- 1020 1860 +/- 248 4720 +/- 527 6120 +/- 651 1980 +/- 245 6900 +/- 728 5180 +/- 561

< 0.8

< 0.6

< 0.7

< 0.8

< 0.4 1.9 +/- 0.7

< 1.4 3.5 +/- 1.1 4.7 +/- 0.9 6.0 +/- 1.4 B-2

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-22 MS-3 MS-3 MS-3 MS-3 MS-3 MS-4 MS-4 MS-5 MS-5 MS-5 MS-5 MS-7 MS-7 MS-7 MS-7 MS-7 MS-8 MS-8 MS-8 MS-8 MS-8 MVS-8 MVS-8 IVS-8 IVS-8 MVS-8 MVS-8 MVS-8 MVS-8 IVS-8 MVS-8 MVS-8 MVS-8 MS-a MW-2 MW-2 MW-TMI-10D MW-TMVI-10D MW-TMVI-10D MW-TMI-10D COLLECTION DATE 09/09/13 09/16/13 09/23/13 09/30/13 10/07/13 10/22/13 11/04/13 11/25/13 Origina 11/25/13 Recour 12/16/13 01/22/13 04/23/13 07/23/13 07/23/13 10/22/13 04/23/13 01/22/13 04/23/13 04/23/13 07/23/13 10/22/13 01/23/13 04125/13 07/24/13 07/24/13 10/23/13 01/07/13 01/21/13 02/04/13 02/19/13 03/04/13 03/18/13 04/01/13 04/15/13 04/23/13 05/06/13 05/20/13 06/03/13 06/17/13 07/01/13 07/23/13 09/03/13 10/22/13 04/25/13 04/25/13 04/25/13 01/22/13 04/24/13 07/24/13 10/23/13 H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS) 6750 +/- 729 5910 +/- 629 5070 +/- 551 3090 +/- 356 2720 +/- 324 2050 +/- 251 4100 +/- 452 1 6290 +/- 679 it 5890 +/- 634 1190 +/- 182 513 +/- 134 596 +/- 157 471 +/- 128 388 +/- 136 233 +/- 126 217 +/- 136

176

199

200

159

187

179

180

189

191

180 267 +/- 121 368 +/- 121

167 303 +/- 126 198 +/- 117 297 +/- 136 268 +/- 130 328 +/- 139

195 199 +/- 131 174 - 111 303 + 126 194 +/- 123 289 +/- 118 318 +/- 119 322 121 277 + 129

177

179

196 234 + 121

< 180 332 +/- 119 292 + 134

< 6.7

< 0.6

< 0.7 1.3 +/- 0.8 7.0 +/- 1.1 < 1.6

< 6.9

< 0.8

< 7.8

< 1.0 0.9 +/- 0.6 < 0.7

< 0.7

< 0.6 5.7 +/- 1,0

< 1.6 5.5 +/- 1.1 < 1.8 2.0 +/- 0,6

< 1.6

< 7.0

< 0.7

< 0.4

< 6.9

< 0.7

< 0.6

< 0.7 10.8 +/- 1.9 12.9 +/- 1.2 6.3 +/- 1.5 B-3

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION DATE H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS)

MW-TMI-10D MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-101 MW-TMI-10S MW-TM I-10S MW-TMI-10S MW-TM I-10S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-12S MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-131 MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-13S MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-14D MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-141 MW-TMI-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-161 MW-TMI-161 MW-TMI-161 MW-TMI-161 MW-TMI-171 MW-TMI-18D MW-TMI-191 MW-TMI-1D0 MW-TMI-20D 10/23/13 01/22/13 01/22/13 04/24/13 07/24/13 10/23/13 01/22/13 04/24113 07/24/13 10/23/13 01/23/13 04/23/13 07/24/13 10/23/13 01/22/13 04/24/13 07/24/13 10/22/13 10/22/13 01122/13 04124/13 07/24/13 10/22/13 01/23/13 04/24/13 07/24/13 10/23/13 01/23/13 04/24/13 07/24/13 10/23/13 01/23/13 01/23/13 04/24/13 07/24/13 10/23/13 01124/13 01/24/13 04/25/13 07123113 10122/13 01/24/13 04/25/13 07/23/13 10/22/13 04/22/13 04/24/13 04/24/13 04/24/13 07/15/13 323 +/- 127 752 +/- 148 987 +/- 175 1020 +/- 167 903 +/- 147 818 +/- 161 1080 +/- 171 1530 +/- 211 1940 +/- 241 1170 +/- 179

< 176

< 191

< 159

< 178 326 +/- 126 341 +/- 127 415 +/- 123 295 +/- 135 388 +/- 130 239 +/- 123 282 +/- 124 422 +/- 124

186 473 +/- 136 289 +/- 125

< 181 345 +/- 136

< 179

< 180

< 184 250 +/- 131

< 174

< 177

< 188

185 439 +/- 129 520 +/- 150 602 +/- 139 389 +/- 132 744 +/- 147 249 +/- 120 185 +/- 117

183

< 176

< 179

< 200

< 182 230 +/- 121 413 +/- 137

< 7.6

6.5

< 0.7

0.7

< 1.1

< 0.7

< 0.7 4.2 +/- 1.0

< 1.6 6.6 +/- 1.2

< 1.6

< 6.6

< 0.7

< 0.5 1.4 +/- 0.8 5.8 +/- 0.8 3.1 +/- 1.2

< 3.3

< 0.7

< 0.4

< 0.4 5.2 +/- 1.0

< 1.5 2.8 +/- 0.8

< 1.6

< 8.1

< 0.7

< 0.6 B-4

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-TMI-20D MW-TMI-20D MW-TMI-20D MW-TMI-20D MW-TMI-201 MW-TMI-201 MW-TMI-201 MW-TMI-201 MW-TMI-201 MW-TMI-21D MW-TMI-21D MW-TMI-21D MW-TMI-21 D MW-TMI-21D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21 D MW-TMI-21D MW-TMI-21D MW-TMI-21D MW-TMI-21D MW-TMI-21D MW-TMI-21D MW-TMI-21D MW-TMI-21D MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-211 MW-TMI-211 MW-TMI-211 MW-TMI-21 I MW-TMI-211 MW-TMI-211 MW-TMI-211 MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21 I MW-TMI-21S MW-TMI-21 S MW-TMI-21S MW-TMI-21S COLLECTION DATE 07/22/13 07/29/13 09/04/13 10/21/13 07/15/13 07/22/13 07/29/13 09/04/13 10/21/13 07/15/13 07/16/13 07/22/13 07/29/13 08/05/13 08/12/13 08/19/13 08/26/13 09/03/13 09/09/13 09/16/13 09/23/13 09/30/13 10/07/13 10/21/13 11/04/13 11/25/13 12/16/13 07/15/13 07/22/13 07/29/13 08/05/13 08/12/13 08/19/13 08/26/13 Original 08/26/13 Recount 09/03/13 09/09/13 09/16/13 09/23/13 09/30/13 10/07/13 10/21/13 10/21/13 11/04/13 11/25/13 12/16/13 07/15/13 07/22/13 07/29/13 08/05/13 H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS) 287 +/- 133 234 +/- 141 222 +/- 127 274 +/- 123 496 +/- 142 493 +/- 148 435 +/- 154 335 +/- 130 435 +/- 134 2850 +/- 332 2530 +/- 299 2790 +/- 328 3040 +/- 362 2540 +/- 297 2370 +/- 284 3160 +/- 371 2810 +/- 323 2450 +/- 306 2650 +/- 313 2800 +/- 318 2650 +/- 362 2800 +/- 333 2410 +/- 285 2770 +/- 334 3150 +/- 366 2720 +/- 321 2890 +/- 334 584 +/- 148 723 +/- 159 539 +/- 156 820 +/- 140 937 +/- 149 1360 +/- 199 1680 +/- 214 1790 +/- 230 1770 +/- 240 2730 +/- 320 3900 +/- 427 4940 +/- 582 5760 +/- 625 4080 +/- 449 5500 +/- 587 6290 +/- 684 4440 +/- 493 4730 +/- 519 1690 +/- 216 736 +/- 156 652 +/- 157 660 +/- 166 840 +/- 144

< 4.5

< 3.6

< 5.0

< 5.5

< 0.7

< 2.7

< 0.5

< 4.3

< 0.5

< 1.7

< 0.6

< 0.9

< 0.7

< 1.1

< 0.5

< 0.4

< 0.9

0.9

0.9 5.1 +/- 1.5

< 1.6 14.7 +/- 2.0

< 1.6 3.0 +/- 1.1

< 1.6 2.9 +/- 0.7

< 1.6 2.9 +/- 0.8

< 1.6 B-5

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TMI-21S MW-TM I-21 S MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-22D MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-221 MW-TMI-22S MW-TMI-22S MW-TMI-22S COLLECTION DATE 08/12/13 08/19/13 08/26/13 09/03/13 09/09/13 09/16/13 09123113 09/30/13 10/21/13 11/04113 11/25/13 12/16/13 07/15/13 07/22/13 07/29113 08/05/13 08/12/13 08/19/13 08/26/13 09/03/13 09/09/13 09/16/13 09/23/13 09/30/13 10/07/13 10/21/13 11/04/13 11/25/13 12/16/13 07/15/13 07/16/13 07/22/13 07/29/13 08/05/13 08/12/13 08/19/13 08/26/13 09/03/13 09/09/13 09/16113 09/23/13 09/30/13 10/07/13 10/21113 11/04/13 11/25/13 12/16/13 07/15113 07/16/13 07/22/13 H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS) 662 +/- 136 652 +/- 149 832 +/- 137 439 +/- 138 504 +/- 127 702 +/- 133 361 +/- 171 641 +/- 153 387 +/- 149 536 +/- 148 692 +/- 145 940 +/- 148 4910 +/- 534 4640 +/- 508 5550 +/- 607 4670 +/- 507 4810 +/- 525 5360 +/- 587 5130 +/- 551 4890 +/- 545 4790 +/- 524 4670 +/- 504 4090 +/- 502 4590 +/- 509 4860 +/- 528 5320 +/- 584 5580 +/- 605 4940 +/- 539 3980 +/- 439 6540 +/- 696 6910 +/- 730 6150 +/- 660 7050 +/- 757 6540 +/- 691 6080 +/- 651 7560 +/- 803 6990 +/- 737 6610 +/- 716 7370 +/- 779 7310 +/- 767 6470 +/- 732 7870 +/- 835 6230 +/- 659 7870 +/- 837 7540 +/- 799 7750 +/- 817 6790 +/- 719 7350 +/- 774 7410 +/- 781 6910 +/- 735

< 4.5

< 5.4

<4.1

< 0.5

< 0.7

< 0.6

< 0.9

< 0.4

< 0.9

< 1.1

< 1.1 9.0 +/- 1.0

< 1.6 5.2 +/- 1.0

< 1.6 7.8 +/- 1.0

< 1.6 B-6

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS)

DATE MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-22S MW-TMI-2D MW-TMI-2D MW-TMI-2D MW-TMI-2D MW-TMI-2D MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-31 MW-TMI-41 MW-TMI-4S MW-TMI-6D MW-TMI-6D MW-TMI-6D MW-TMI-6D MW-TMI-6D MW-TMI-61 MW-TMI-61 MW-TMI-61 MW-TMI-61 07/22/13 07/29/13 08/05/13 08/12/13 08/19/13 08/26/13 09/03/13 09/09/13 09/16/13 09/23/13 09/30/13 10/07/13 10/21/13 11/04/13 11/25/13 Origina 11/25/13 Recour 12/16/13 01/22/13 04/24/13 07/24/13 07/24/13 10/22/13 01/07/13 01/21/13 02/04/13 02/19/13 03/04/13 03/18/13 04/01/13 04/15/13 04/25/13 05/06/13 05/20/13 06/03/13 06/17/13 07/01/13 07/25/13 09/04/13 10/23/13 04/24/13 04/24/13 01/23/13 04/25/13 04/25/13 07/24/13 10/23/13 01/23/13 04/25/13 07/24/13 10/23/13 7320 +/- 776 7190 +/- 773 6240 +/- 663 5710 +/- 614 5290 +/- 579 4870 +/- 526 5990 +/- 653 5790 +/- 622 5130 +/- 551 3250 +/- 416 2800 +/- 328 2650 +/- 310 3560 +/- 414 3330 +/- 385 1 4540 +/- 497 it 4370 +/- 482 3860 +/- 426 200 +/- 120 323 +/- 141 386 +/- 121 508 +/- 148 258 +/- 123

< 168

< 179

168 205 +/- 118 178 +/- 118

197

191 328 +/- 140

< 182 329 +/- 139

< 160 200 +/- 122 255 +/- 126 268 +/- 118 304 +/- 126 382 +/- 123 210 +/- 121

< 184

< 179

178

182

< 194 216 +/- 111

< 179

< 175

< 180

< 188

< 186

< 4.9

< 6.0

< 3.4

< 0.6

< 0.7

< 0.6

< 0.5

< 0.7

< 1.4

< 1.1

0.7

< 0.4 9.2 +/- 1.0

< 1.6 4.1 +/- 0.8

< 1.6 3.4 +/- 1.2

< 1.5 2.3 +/- 1.0

< 1.6 1.8 +/- 1.0

< 1.8 4.3 +/- 1.0

< 1.6

< 7.3

< 0.8

< 5.2

< 0.8

< 0.7

< 0.4 1.2 +/- 0.7 < 0.6

< 8.5

< 0.7

< 0.4 B-7

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-TMI-7S MW-TMI-7S MW-TMI-8S MW-TMI-91 N2-1 NW-A NW-A NW-A NW-A NW-A NW-A NW-A NW-A NW-B NW-B NW-B NW-B NW-B NW-B NW-B NW-C NW-C NW-C NW-C NW-C NW-C NW-C NW-C NW-C NW-CW NW-CW NW-CW NW-CW NW-CW NW-CW OS-14 OS-14 OS-14 OS-14 OS-16 OS-16 OS-16 OS-16 OS-18 OS-18 OS-18 OS-18 OSF OSF OSF 197 199 179 COLLECTION DATE 04/25/13 04125/13 04/25/13 04/25/13 01/28/13 01/22/13 03/05/13 04/13/13 05/12/13 07/01/13 07/23/13 09/08/13 10/22/13 03/05/13 04/13/13 05/12/13 07/01/13 07/23/13 09/08/13 10/22/13 01/22/13 03/05/13 04/13/13 05/12/13 07/01113 07/23/13 07/23/13 09/08/13 10/22/13 01/22/13 03/08/13 05/12/13 07/02/13 07/23/13 10/22/13 01/22/13 04/23/13 07/23/13 10/22/13 01/22/13 04/23/13 07/23/13 10/22/13 01/23/13 04/25/13 07/25/13 10/22/13 01/21/13 02/19/13 04/15/13

197

199

179 H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS)

182

174 818 +/- 165 606 +/- 162 672 +/- 158 783 +/- 147

732 809 +/- 144 854 +/- 144 841 +/- 149 246 +/- 142 449 +/- 145 201 +/- 119

464 359 +/- 119 266 +/- 112 184 +/- 117 1060 +/- 178 1220 +/- 194 1310 +/- 191 1170 +/- 177

751 1270 +/- 189 1140 +/- 165 1010 +/- 153 1110 +/- 175 558 +/- 136 744 +/- 172

177

< 479 632 +/- 150 233 +/- 117

173

179

186

179 666 +/- 143 404 +/- 142

158 220 +/- 124

178

177

182

179 455 +/- 128 263 +/- 121 333 +/- 137

6.5

6.9

< 5.4

< 0.5

< 0.8

< 0.6

< 0.7

< 0.6

< 0.8

0.8

0.8

0.8

0.8

0.4

0.5 2.3 +/- 0.8

< 1.5 2.9 +/- 0.8

< 1.5 1.6 +/- 0.8

< 1.5 3.0 +/- 0.7

< 1.5 9.1 +/- 1.3

< 1.5 5.5 +/- 0.8

< 1.4

< 7.1

< 0.6

< 7.5

< 0.5

< 0.9

< 8.0

< 0.7

< 0.6

< 7.6

< 0.8

< 0.7 0.9 +/- 0.6 4.7 +/- 1.1

< 1.6 B-8

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION DATE OSF 04/25/13 OSF 05/20/13 OSF 07/08/13 OSF 07/25/13 OSF 09/04/13 OSF 10/24/13 RW-1 01/23/13 RW-1 04/23/13 RW-1 07/24/13 RW-1 10/23/13 RW-2 01/23/13 RW-2 04/23/13 RW-2 04/23/13 RW-2 07/24/13 RW-2 10/23/13 TRAINING CENTER 04/25/13 H-3 Sr-89 Sr-90 Gr-A (DIS)

Gr-A (SUS)

Gr-B (DIS)

Gr-B (SUS) 651 +/- 140

< 7.5

< 0.8

< 1.6

< 0.4 5.5 +/- 1.3

< 1.6

< 162 310 +/- 120 226 +/- 125 417 +/- 125 235 +/- 120

< 179

199

< 185

< 174

< 176

< 196

< 189 224 +/- 113

< 179

< 7.8

< 0.6

< 0.8

< 7.4

< 0.7

< 0.4

< 6.7

< 0.7

< 0.6

< 0.4

< 0.7

< 0.6 3.9 + 0.9

< 1.4 6.2 + 0.9

< 1.5 5.5 + 0.9 3.4 +/- 1.3 B-9

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 0o 3

48S MS-1 MS-19 MS-2 MS-20 MS-21 MS-22 MS-3 MS-3 MS-3 MS-3 MS-3 MS-4 MS-5 MS-5 MS-5 MS-5 MS-5 MS-7 MS-8 MS-8 MS-8 MS-8 MW-i MW-2 MW-2 MW-TMI-101 MW-TMI-10S MW-TMI-12S MW-TMI-13S MW-TMI-14S MW-TMI-171 MW-TMI-18D MW-TMI-191 MW-TMI-1D 04/23/13

< 20

< 18 04/25/13

< 41

< 65 04/25/13

< 52

< 60 04/24/13

< 47

< 37 04/23/13

< 29

< 59 04/22/13

< 35

< 66 04/23/13

< 17

< 15 04/22/13

< 32

< 59 01/22/13

< 47

< 101 04/23/13

< 34

< 30 07/23/13

< 38

< 83 07/23/13

< 38

< 37 10/22/13

< 15

< 28 04/23/13

< 38

< 26 01/22/13

< 32

< 60 04/23/13

< 35

< 33 04/23/13

< 30

< 32 07/23/13

< 42

< 81 10/22/13

< 19

< 32 04/25/13

< 40

< 43 01121113

< 29

< 28 04/23/13

< 31

< 33 07/23/13

< 38

< 45 10/22/13

< 21

< 40 04/25/13

< 47

< 104 04/25/13

< 39

< 90 04/25/13

< 42

< 90 04/24/13

< 33

< 52 04/24/13

< 43

< 48 04/23/13

< 18

< 32 04/24/13

< 33

< 61 04/24/13

< 40

< 38 04/22/13

< 43

< 42 04/24/13

< 40

< 78 04/24/13

< 44

< 87 04/24/13

< 34

< 32

<2

<4

<6

<4

<3

<4

<2

<3

<5

<3

<5

<4

<1

< 4

<3

<4

<3

< 4

<2

<4

< 3

<3

<4

<2

<6

<4

<3

<4

<2

<3

<4

<2

<4

<5

<4

< 3

<4

< 2

<3

<6

<4

<5

<4

<2

<4

<3

<4

<:4

<4

<2

<4

<3

<4

<2

<6

<4

<5

<4

<5

<2

<4

<5

< 5

<4

< 4

<4

<5

<2

<10

<4

<10

<7

<9

<5

<7

<3

<9

<4

<2

<8

<3

<12

<6

<9

<3

<9

<5

<8

<4

<9

<8

<1

<4

<3

<8

<3

<9

<4

<8

< 4

<4

<1

<10

<4

<7

<3

<8

<3

<8

<4

<5

<2

<14

<6

<10

<5

<10

<5

<6

<4

< 10

<5

<4

<2

<8

<4

<8

<4

<10

<4

<10

<4

<10

< 6

<8

<4

<9

< 14

<9

<6

<8

<3

<7

<11

<6

<9

<8

< 3

<8

<7

<3

<9

<6

<7

<4

<11

<10

<11

<6

<8

<4

<7

<8

<9

<8

<10

<8

<2

<5

<6

<5

<3

<4

<2

<4

<6

<4

<5

<4

<2

<4

<3

<4

<5

<2

<5

<3

<4

<5

<2

<6

<4

<6

<3

<5

<2

<3

<5

<4

< 4

<4

<8

< II

< 10

<6

<7

<3

<6

<11

<7

<8

<3

<8

<6

<8

<3

<8

<6

<7

<4

<11

<7

< 10

<6

<10

<4

<7

<8

<9

<8

<7

<2

<4

<6

<4

<3

<2

<3

< 5

<3

<4

< 1

<4

<3

<4

<2

<4

<3

<2

<5

<4

<5

<3

<2

<3

<4

<2

<4

<6

<5

<3

<4

<2

<3

<5

<3

<4

<2

<4

<3

<4

<3

<4

<2

<4

<3

<4

<2

<6

<4

<6

<4

<5

<2

<3

<4

<5

<4

<15

28

31

31

20

23

<13

26

38

27

30

27

14

< 33

27

25

25

29

17

27

25

23

< 26

19

30

27

31

< 24

27

<15

24

30

29

31

29

< 26

<5

<8

< 13

<8

<9

<4

<7

< 14

<8

< 11

<9

<5

<9

<7

<8

<9

<8

<4

<8

<7

<8

< 10

<7

< 14

< 8

< 11

<8

<12

<5

<8

< 12

<9

<8

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE MW-TMI-20D 10/21/13

< 20

< 39

< 2

< 5

< 2

< 5

< 2

< 4

< 2

< 19

< 7 MW-TMI-201 10/21/13

< 15

< 26

< 1

< 2

< 4

< 2

< 3

< 2

< 3

< 1

< 2

< 14

< 5 MW-TMI-21D 10/21/13

< 16

< 15

< 2

< 4

< 2

< 3

< 2

< 3

< 2

< 13

< 4 MW-TMI-211 10/21/13

< 26 91 +/-42 < 3

< 3

< 6

< 2

<6

< 3

< 5

< 3

< 22

< 7 MW-TMI-211 10/21/13

< 19

< 17

< 2

< 4

< 2

< 3

< 2

< 3

< 2

< 15

< 5 MW-TMI-21S 10/21/13

< 15

< 2

< 4

< 2

< 3

< 2

< 3

< 2

< 13

< 4 MW-TMI-22D 10/21/13

< 19

< 17

< 2

< 5

< 2

< 4

< 2

< 4

< 2

< 15

< 5 MW-TMI-221 10/21/13

< 18

< 35

< 2

< 4

< 2

< 4

< 2

< 4

< 2

< 15

< 5 MW-TMI-22S 10/21/13

< 18

< 41

< 2

< 4

< 2

< 4

< 2

< 4

< 2

< 15

< 5 MW-TMI-2D 04/24/13

< 34

< 85

< 4

< 9

< 4

< 9

< 4

< 8

< 3

< 4

< 26

< 10 MW-TMI-31 04/25/13

< 40

< 85

< 4

< 5

< 11

< 5

< 10

< 5

< 9

< 4

< 5

< 26

< 11 MW-TMI-41 04/24/13

< 42

< 90

< 5

< 4

< 10

< 5

< 9

< 5

< 10

< 4

< 6

< 31

< 11 MW-TMI-4S 04/24/13

< 48

< 43

< 5

< 10

< 5

< 9

< 6

< 10

< 5

< 34

< 8 MW-TMI-6D 04/25/13

< 49

< 62

< 6

< 5

< 13

< 5

< 11

< 7

< 10

< 6

< 33

< 11 MW-TMI-6D 04/25/13

< 47

< 84

< 5

< 10

< 4

< 9

< 5

< 9

< 5

< 35

< 10 MW-TMI-61 04/25/13

< 38

< 37

< 4

< 9

< 4

< 8

< 5

< 7

< 4

< 23

< 10 MW-TMI-7S 04/25/13

< 46

< 32

< 5

< 12

< 5

< 10

< 6

< 9

< 5

< 6

< 34

< 8 MW-TMI-7S 04/25/13

< 39

< 31

< 4

< 3

< 8

< 3

< 8

< 4

< 8

< 4

< 3

< 25

< 8 MW-TMI-8S 04/25/13

<48 82 48 < 5

< 5

< 9

< 5

< 10

< 5

< 9

< 5

< 31

< 8 MW-TMI-91 04/25/13

< 40

< 74

< 4

< 9

< 4

< 8

< 5

< 8

< 4

< 28

< 9 N2-1 01/28/13

< 44

< 36

< 5

< 4

< 10

< 5

< 9

< 5

< 9

< 4

< 5

< 30

< 9 NW-A 05/12/13

< 34

< 41

< 4

< 5

< 9

< 5

< 10

< 5

< 8

< 3

< 4

< 23

< 9 NW-B 05/12/13

< 34

< 67

< 4

<4

< 7

< 3

< 7

<4

< 6

<4

< 3

< 22

< 6 NW-C 05112/13

< 53

< 38

< 6

< 11

< 6

< 10

< 6

< 9

< 6

< 34

< 9 NW-CW 05/12/13

< 41

< 38

< 3

< 4

< 8

< 4

< 8

< 4

< 8

< 4

< 24

< 7 OS-14 01/22/13

< 36

< 33

< 4

< 8

< 4

< 8

< 4

< 7

< 4

< 30

< 11 OS-14 04/23/13

< 46

< 87

< 4

< 5

< 11

< 3

< 9

< 6

< 8

< 4

< 5

< 35

< 10 OS-14 07/23/13

< 29

< 34

< 3

< 7

< 3

< 6

< 3

< 5

< 3

< 20

< 7 OS-14 10/22/13

< 16

< 31

< 2

< 4

< 2

< 3

< 2

< 3

< 2

< 16

< 5 OS-16 01/22/13

< 31

< 28

< 4

< 3

< 8

< 3

< 7

< 4

< 6

< 3

< 4

< 28

< 9 OS-16 04/23/13

< 33

< 25

< 3

< 4

< 7

< 3

< 8

< 4

< 7

< 3

< 4

< 26

< 9 OS-16 07/23/13

< 49

< 97

< 5

< 13

< 5

< 10

< 5

< 10

< 4

< 5

< 32

< 12 OS-16 10/22/13

< 16

< 14

< 2

< 4

< 2

< 3

< 2

< 3

< 1

< 2

< 15

< 5 OS-18 04/25/13

< 51

< 46

< 5

< 13

< 5

< 9

< 6

< 9

< 5

< 6

< 31

< 13 OSF 04/25/13

< 46

< 83

< 5

< 12

< 6

< 10

< 6

< 9

< 5

< 6

< 32

< 12

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE RW-1 04/23/13

< 25 RW-2 04/23/13

< 24 RW-2 04/23113

< 23 TRAINING CENTER 04/25/13

< 48 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

< 26

< 39

22

< 49

<2

<6

<3

<5

<6

<5

< 11

<3

<5

<3

<5

<3

<5

<4

<5

<8

<2

<5

<3

<2

<5

< 18

< 21

< 17

31

<6

< 10

<2

<6

<4

<9 i

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 SITE MW-TMI-101 MW-TMI-10S MW-TMI-20D MW-TMI-20D MW-TMI-201 MW-TMI-201 COLLECTION DATE 04/24/13 04/24/13 10/21/13 Ori 10/21/13 Re 10/21/13 Ori 10/21/13 Re U-234 U-235 U-238 Fe-55 Ni-63

< 0.14

< 0.08

< 0.10

< 0.09

< 0.05

< 0.07

< 0.04

< 0.10

< 0.02

< 0.12

< 0.09

0.04

< 0.11 0.9 +/- 0.3 0.3 +/- 0.1 0.9 +/- 0.3 1.2 +/- 0.3

< 0.06

< 0.03

< 0.05 ginal

< 0.16 analysis ginal

< 0.14 analysis 0.6 +/- 0.2

< 165

< 0.1

< 70 0.4 +/- 0.2

< 86 0.7 +/- 0.2 3.4 +/- 0.7

< 152 2.8 +/- 0.5

< 3.4

< 3.8

< 4.5

< 0.11

< 0.12

< 0.17

< 0.1 4.9 +/- 1.0

< 0.03 4.2 +/- 0.6 u.J

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-E-1 SW-E-1 SW-E-1 SW-E-1 SW-E-1 SW-E-2 SW-E-2 SW-E-2 SW-E-2 SW-E-2 SW-E-3 SW-E-3 SW-E-3 SW-E-3 COLLECTION DATE 01/24/13 04/25/13 07/25/13 10/24/13 10/24/13 01/24/13 04/25/13 04/25/13 07/25/13 10/24/13 01/24/13 04/25/13 07125113 10/24/13 U

H-3

< 192

< 176

184

< 181

< 176

194

< 198

< 181

< 184

< 180

< 188

< 178

< 184

< 177 B-14

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 SVV-t--

SW-E-2 SW-E-2 SW-E-3 U4/2l5/13 04/25/13 04/25/13 04/25/13

36

< 36

< 40

< 53

<32

<4

<3

<10

<3

<44

<4

<8

<4

<90

<4

<10

<5

<43

<5

<6

<12

<4

<86

<8

< 8

< 10

<4

<6

<8

< 9

<3

<4

<24

<4

<27

<5

<30

<5

<33

<6

<9

<9 LAh

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 EDCB EDCB EDCB EDCB EDCB EDCB EDCB 01131113 04/30/13 07/02/13 07/30/13 10/29/13 10/29/13 10/29/13

181

< 191

< 471

< 188 233 +/- 121 289 +/- 116 217 +/- 131 Original Recount Reanalysis B-16

TABLE B-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 DATE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 EDCB 01/31/13 EDCB EDCB EDCB 04/30/13 07/30/13 10/29/13

< 16

< 32

< 44

< 48

< 42

< 38

< 37

< 70

<2

<4

<5

< 4

< 10

<2

<6

< 4

<2

< 3

<2

<13

< 4

9

<6

< 7

<4

<18

< 6

< 10

< 5

< 8

< 4

< 23

< 9

<5

<11

<5

<3

<4

< 9

<3

<7

<4

< 7

<4

<31

< 8

TABLE B-IV.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE PR-MS-22 PR-MS-22 PR-MS-22 PR-MS-22 TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-ESE TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-1 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-2 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 TM-PR-MS-4 H-3 01/07/13 01/14/13 02/19/13 02/25/13 02/26/13 05/01/13 07/15/13 10/08/13 02/26/13 05/01/13 07/15/13 10/08/13 02/26/13 05/01113 07/15/13 10/08/13 02/26/13 05/01/13 07/15/13 10/08/13 530 +/- 133 498 +/- 136 441 +/- 130 525 +/- 156

< 172

< 166

< 198

< 171

< 175

< 166

< 169 218 + 116

170

167

< 200

168

< 173

< 168

< 199 B-18

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

Intentionally left blank

TABLE C-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE MS-2 MW-TMI-101 MW-TMI-14S MW-TMI-16D MW-2 MW-TMI-7S MS-5 RW-2 MW-TMI-6D MW-TMI-22S MS-3 NW-C MS-7 MW-TMI-2D MW-TMI-21 I MS-20 MW-TMI-131 MW-TMI-10D DATE 01/22/13 01/22/13 01/23/13 01/24/13 04/25/13 04/25/13 04/23/13 04/23/13 04/25/13 07/22/13 07/23/13 07/23/13 07/24/13 07/24/13 10/21/13 10/22/13 10/22/13 10/23/13 H-3 503 +/- 93 896 +/- 108 Sr-89 Sr-90 Gr-A Gr-B

< 140 495 +/- 93

< 193

< 193 7822 +/- 270 425 +/- 107 1328 +/- 139

< 179

< 0.8

< 0.7

< 0.8

< 0.6

< 0.9

< 0.5

< 0.9

< 0.7 2.4 +/- 1.0

< 0.5

< 1.3 3.3 +/- 1.2 6.7 +/- 1.1 3.3+/- 1.2 2.3 + 0.8 442 6499 746 389 453

+/- 108

+/- 241

< 0.8

+/- 111

+/- 97

+/- 99 C-I

TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MS-3 MS-5 MW-2 MW-TMI-21 I MW-TMI-6D MW-TMI-7S RW-2 COLLECTION Be-7 PERIOD 07/23/13

< 28 04/23/13

< 23 04/25/13

< 29 10/21/13

< 13 04/25/13

< 36 04/25/13

< 26 04/23/13

< 24 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140

59 57 1 31

< 73

< 21

< 57

< 61

< 63

<3

<2

< 2

<1

<2

<3

<2

<7

<6

< 6

<1

<4

<9

<7

<3

< 3

<1

<2

<3

<2

<1

<3

<1

<3

<2

<4

<2

<5

<2

<4

<6

<4

<7

<2

<5

<4

<2

<5

<1

<3

<2

<3

<1

<3

<2

<4

<2

<3

<4

<1

<2

<3

<2

<19

< 12

< 21

<8

< 17

< 10

< 18

<4

<3

<5

<3

TABLE C-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 PERIOD Cm-2431244 Pu-238 Pu-239/240 U-233/234 U-235 U-238 Fe-55 Ni-63 NONE FOR 2013

TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-E-1 SW-E-2 COLLECTION DATE 10/24/13 04/25/13 H-3

< 149

< 193 C-4

TABLE C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION PERIOD Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65

<5

<3

<2

<5 Zr-95 Nb-95 Cs-134 Cs-137

<5

<2

<3

<4 Ba-140 La-140

<13

<2 SW-E-2 04/25/13

< 30

< 53

<2 L Ji

TABLE C-I11.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2013 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE H-3 TM-PR-MS-2Q TM-PR-MS-2Q TM-PR-MS-2Q TM-PR-MS-2Q 03/15/13 05/20/13 08/12/13 10/16/13 244 +/- 88

139

152 173 +/- 101 C-6

TMI-14-051, 2013 Radiological Environmental Monitoring Program Report

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