Text

Transmittal of Annual Radiological Environmental Operating Report Covering the Time-Period of January 1 Through December 31, 2005, for the Three Mile Island Nuclear Station, Units 1 & 2
	ML061220487
Person / Time
Site:	Crane
Issue date:	04/26/2006
From:	Chick G; AmerGen Energy Co, Exelon Corp
To:	; Document Control Desk, NRC/FSME
References
	5928-06-20448
	Download: ML061220487 (126)
	v • d • e

AmerGlen M AmerGen Energy Company, LLC Telephone: 717-948-8000 An Exelon Company Three Mile Island Unit 1 Route 44i South, P.O. Box 480 Middletown, PA 17057 April 26, 2006 5928-0D3-20448 U. S. Nuclear Regulatory Commission Attenticn: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION Units 1 and 2 OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR-73 DOCKET NOS. 50-289 AND 50-320

SUBJECT:

2005 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT In accordance with TMI-1 Technical Specification 6.9.3.1 and TMI-2 Technical Specification (3.8.1.1, enclosed is the Annual Radiological Environmental Operating Report covering the time-period of January 1 through December 31, 2005, for the Three Mile Island Nuclear Station.

Please contact Steven Acker of TMI-1 Chemistry at (717) 948-8183 if you have any questions regarding this submittal.

Sincerely, Glen E. Cc Plant Manager GEC/awvm Enclosure cc:

Region I Administrator TMI-1 Senior Project Manager TMI-2 Project Manager TMI-1 Senior Resident Inspector GPU Nuclear TMI-2 Cognizant Officer File 06024

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 2005 Prepared By Teledyne Brown Engineering Environmental Services Aner~m

'M An Exelon Company Three Mile Island Nuclear Station Middletown, PA 17057 April 2006

Table Of Contents I. Summary and Conclusions...................................................

1 II. Introduction.........................................................................................................................3 A. Objectives of the REMP..........

3......................

B. Implementation of the Objectives....................................................

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

4 A. Sample Collection....................................................

4 B. Sample Analysis...................................................

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

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

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

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

11 A. Aquatic Environment.........

11

1. Surface Water...................................................

11

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

12

3. Effluent Water................................................... 12

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

14

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

14

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

15

7. Sediment...................................................

15 B. Atmospheric Environment...................................................

16

1. Airborne...................................................

16

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

16

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

17

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

17

a. Milk...................................................

17

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

18

c. Rodents...................................................

18 C. Ambient Gamma Radiation....................................................

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

19 E. Summary of Results - Inter-laboratory Comparison Program............................ 21 V. Reierences...................................................

22

-'Appendices

-en Appendix A TIaleS Table A-1 Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2005 Appendix B Tables Table B-I

Table B-2:

Table B-3:

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, 2005 Radiological Environmental Monitoring Program -'Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2005 Figures Figure B-1:

Figure B-2:-

Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2005 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2005 Figure B-3:

Environmrental Sampling Locations'Greate'r'Than Five Miles from the

'Three Mile Island'Nu'clea'r'Station',' 2005 Appendix C.

DaaaleadI-P r L Data Tables and Figures'- Primary Laboratory Tables I..

... I..... -..

. 1..:

Table C-1.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

ii

i A

Table C-1.2 Table C-1.3 Table C-11.1 Table C-11.2 Table C-11.3 Table C-11.4 Table C-111.1 Table C-111.2 Table C-IV.1 Table C-V.1 Table C-V.2 Table C-VI.1 Table C-VI.2 Table C-VII.1 Table C-VIII.1 Table C-VIII.2 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

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, 2005.

Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Tritium and Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Strontium and Gamma Emitters in Ground Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Strontium in Predator and Bottom Feeder (Fish)

Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

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, 2005.

Mii

Table C-VI1.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Table C-IX.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Table C-X.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Table C-X.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Table C-X.3 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Table C-XI.1 Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Table C-XI1.1 Quarterly TLD Results for Three Mile Island Nuclear Station, 2005.

Table C-XI1.2 Mean Quarterly TLD Results for the Site Boundary, Offsite and Control Locations for Three Mile Island Nuclear Station, 2005.

Table C-XI1.3 Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2005.

Figures Figure C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2005.

Figure C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2005.

Figure C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2005.

Figure C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2005.

Figure C-5 Mean Cesium-1 37 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2005.

Figure C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2005.

Figure C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2005.

Figure C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2005.

Figure C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2005.

iv

Appendix D Data Tables and Figures - Comparison Laboratory Tahlp i Table D-1.1 Table D-1.2 Table D-1.3 Table D-1.4 Table D-1.5 Table D-1.6 Table D-1.7 Table D-1.8 Table D-11.1 Table D-11.2 Table D-111.1 Figure D Figure D-1 Figure D-2 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2005.

Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of lodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Tritium, Strontium, and Gamma Emitters in Ground Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2005.

Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location El-2Q, 2005.

v

Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2005 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2005 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2005 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2005 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2005 Appendix F Table F-1.1 Special Groundwater Sampling Data Concentrations of Tritium in Special Ground Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2005.

vi

I.

Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Three Mile Island Nuclear Station (TMINS) by AmerGen covers the period 1 January 2005 through 31 December 2005. During that time period, 1,730 analyses were performed on 1334 samples. In assessing all the data gathered for this report and comparing these results with preoperational data and operational REMP data, it was concluded that the operation of TMINS had no adverse radiological impact on the environment.

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

Effluent water samples were also analyzed for concentrations of Sr-89 and Sr-!)0.

Ground water samples were also analyzed for concentrations of Sr-90. No Sr-89 and Sr-90 activities were detected. Gross beta and 1-131 concentrations detected were consistent with those detected in previous years. Tritium results in groundwater and several monthly results in surface, drinking and effluent water samples were due to TMINS activities or releases. These results will be discussed later in the report. Iodine-1 31 detected in effluent water was from upstream medical users. No other fission or activation products attributed to TMI release were detected.

Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. Fish samples were also analyzed for concentrations of Sr-89 and Sr-90. No Sr-89 and Sr-90 activity was detected.

No fission or activation products were detected in fish. Cesium-137 levels detected in sediment were consistent with levels detected in previous years and were due to plant releases and fallout from nuclear weapons testing. No other TMINS-produced fission or activation products were detected in sediment.

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

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

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

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

Food Product samples were analyzed for concentrations of gamma emitting nuclides (including 1-131) and Sr-90. Sr-90 activities were detected in both the indicator and control samples. This was a result of plant uptake of Sr-90 in soil as a result of past nuclear weapons testing. Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.

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

A practice of the TMI site is to analyze rodents for radioactivity as a part of the Non-routine REMP. This program is to determine the transport of radioactive materials to unrestricted areas by rodents. Analyses are performed by TMI personnel when samples are available. These results are presented in this report. A pest control program is in place at TMI. This program minimizes the potential for rodents to transport radioactive material to unrestricted areas.

II.

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

A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Global Dosimetry Solutions, Inc., and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2005 through 31 December 2005.

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 environmE nt and changes in background radiation levels.

5.

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

6.

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

B.

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

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

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

Ill.

Program Description A.

Sample Collection Samples for the TMINS REMP were collected for AmerGen by Normandeau Associates, RMC Environmental Services Division (RMC).

This section describes the general collection methods used by RMC to obtain environmental samples for the TMINS REMP in 2005. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3.

Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, storm water, ground water, fish, and sediment. Two gallon water samples were collected monthly from continuous samplers located at three surface water locations (A3-2, J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9-1), and one effluent water location (K1-1). Control locations were A3-2 and Q9-1. Monthly grab water samples were taken from one storm water runoff location (EDCB). Grab ground water samples were collected quarterly at eight locations (48S, GP-1, GP-6, GP-8, GP-9, MS-22, OSF and OS-18), semiannually at 12 locations (GP-12, MS-2, MS-5, MS-8, MS-20, NW-A, NW-B, NW-C, NW-CW, OS-14, RW-1 and RW-2) and annually at seven locations (El-2, MS-1, MS-4, MS-7, MS-19, MS-21 and N2-1). In response to a special investigation, selected wells were sampled more frequently. All water samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND) location.

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

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulates, airborne iodine, milk, and food product. Airborne iodine and particulate samples were collected and analyzed weekly at seven locations (A3-1, E1-2, Fl-3, G2-1, H3-1, M2-1, and Ql 5-1). The control location was Ql 5-1. 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 1br analysis.

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

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

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

The control location was B10-2. Four different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

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

A site boundary ring consisting of 21 locations (A1-4, B1-1, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, Ji-i, J1-3, K1-4, 1-1, Mi-1, N1-3, P1-2, Q1-2, and Ri-i) 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 TMIINS release.

An offsite ring consisting of 58 locations (A3-1, A5-1, A9-3, B2-1, B5-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, El-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, L1-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, NI-I, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, QM-A, Q2-1, Q5-1, Q9-1, R1 -2, R3-1, R5-1, and R9-1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

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

The specific TLD locations were determined by the following criteria:

1.

The presence of relatively dense population;

2.

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

3.

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

4.

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

Each TLD station consists of two primary program TLD badges, each of which has three CaSO4 thermoluminescent phosphors enclosed in plastic, placed at each location in a frame located approximately three to six feet above ground level. Since each TLD responds to radiation independently, this provides six independent detectors at each station. The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis.

B.

Sample Analysis This section describes the general analytical methods used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the TMINS REMP in 2005. The analytical procedures used by the laboratories are listed in Table B-3.

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

1.

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

2.

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

3.

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

4.

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

5.

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

6.

Ambient gamma radiation levels at various site environs.

C.

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

1.

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

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

2.

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

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

For surface, drinking, effluent, storm, and ground water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, Cs-1 34, Cs-1 37, Ba-1 40 and La-140 were reported.

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

For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were reported.

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

For milk five nuclides, K-40, Cs-134, Cs-137, Ba-140 and La-140 were reported.

For food products four nuclides, K-40, 1-131, Cs-134 and Cs-137 were reported.

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

D.

Program Exceptions For 2005 the TMINS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

1.

Surface water samples were collected as grab samples for the following periods and locations, due to frozen sample lines:

12/28/2004 - 02/01/2005, Location J1-2 11/30/2005 - 01/03/2006, Location J1-2

2.

TLD - One of two badges was found on the ground for the following period and location:

01/14/2005 - 04/15/2005, Location R9-1

3.

Air particulate and air iodine samples lost approximately 58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months for the following period and location, due to power failure/sampler malfunction:

03/23/2005 - 03/30/2005, Location G2-1

4.

Air particulate and air iodine samples lost approximately 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months for the following period and location, due to sampler malfunction:

03/30/2005 - 04/06/2005, Location M2-1

5.

Air particulate and air iodine samples lost approximately 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months for the following period and location, due to sampler malfunction and pump replacement:

04/06/2005 - 04/13/2005, Location M2-1

6.

TLD hardware and both badges were found on the ground for the following period and location:

04/14/2005 - 07/14/2005, Location P5-1

7.

TLDs were not sent and analyzed for the following periods and locations, due to hardware malfunction/failure:

04/15/2005 - 07/15/2005, Location B1-1 04/15/2005 - 07/15/2005, Location B1-I Q

8.

Effluent water samples were collected as grab samples for the following period and location, due to sampler malfunction or workers installing new equipment that effected sampler operations:

06/28/2005 - 08/02/2005, Location K1-1

9.

Air particulate and air iodine QC samples were sent to the primary laboratory for analysis for the following periods and locations, due to sampler malfunction:

06/22/2005 - 06/29/2005, Location El-2Q 08/10/2005 - 08/17/2005, Location El-2Q 09/21/2005 - 09/28/2005, Location El -2Q

10.

Air particulate and air iodine samples lost approximately six hours for the following period and location, due to sampler malfunction and pump replacement:

06/29/2005 - 07/06/2005, Location El-2

11.

Air particulate and air iodine samples lost approximately 69 hours7.986111e-4 days 0.0192 hours 1.140873e-4 weeks 2.62545e-5 months for the following period and location, due to sampler malfunction:

08/02/2005 - 08/10/2005, Location M2-1

12.

Air particulate and air iodine samples lost approximately 61 hours7.060185e-4 days 0.0169 hours 1.008598e-4 weeks 2.32105e-5 months for the following periods and locations, due to sampler malfunction:

08/17/2005 - 08/24/2005, Location E1-2 09/14/2005 - 09/21/2005, Location El-2

13.

Air particulate and air iodine samples lost approximately four hours for the following period and location, due to sampler/timer malfunction:

09/14/2005 - 09/21/2005, Location G2-1

14.

Air particulate and air iodine samples lost approximately 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months for the following period and location, due to timer malfunction:

09/14/2005 - 09/21/2005, Location El-2Q

15.

Air particulate and air iodine samples lost approximately 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months for the following period and location, due to sampler malfunction:

11/02/2005 - 11/09/2005, Location A3-1

16.

Air particulate and air iodine samples lost approximately 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months for the following period and location, due to station being vandalized and sampler being unplugged:

1 1/02/2005 - 11/09/2005, Location Q15-1

17.

Drinking water samples were collected as grab samples for the following periods and locations, due to sampler malfunction:

08/30/2005 - 09/27/2005, Location Q9-1 08/30/2005 - 09/27/2005, Location Q9-1Q

18.

TLD primary badges were missing/stolen for the following period and location, due to station being vandalized:

10/13/2005 - 01/12/2006, Location Q15-1

19.

Effluent water samples were collected as grab samples for the following periods and locations, due to sampler malfunction:

11/30/2005 - 01/03/2006, Location Kl-1 Each program exception was reviewed to understand the causes of the program exception. Occasional equipment breakdowns and power outages were unavoidable.

The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

- E.

Program Changes There were no changes to the program in 2005.

IV.

Results and Discussion A.

Aquatic Environment 1.

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

Tritium Monthly samples from J1-2 and Q9-1 were analyzed for tritium activity (Table C-1.1, Appendix C). Positive tritium activity was detected in six of 24 samples, primarily at location J1-2 which is located immediately downstream of the TMINS effluent outfall. All samples ranged from <156 to 33,500 pCi/I. The increased tritium concentrations detected in March, August and September samples were a result of TMINS releasing more waste water in preparation of the Unit 1 refueling outage. The indicator surface water sample is taken just downstream of the liquid discharge outfall where mixing of liquid effluents with the river water is incomplete. More complete mixing is not achieved until liquid effluents pass over the York Haven Dam. This water is normally not consumed by humans. The concentrations detected were well below any regulatory limits. (Figures C-1 and C-2, Appendix C).

Iodine Monthly samples from location A3-2 were analyzed for iodine-131 activity (Table C-1.2, Appendix C). This is a control or background station sampled because of a known medical facility that has discharges into the surface water upstream of TMI. Iodine-131 activity was not detected.

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

2.

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

Gross Beta Monthly samples from all locations were analyzed for concentrations of gross beta. (Tables C-11.1, Appendix C). Gross beta activity was detected in 30 of 36 samples. The values ranged from <2.0 to 5.4 pCi/l. Concentrations detected were consistent with those detected in previous years (Figures C-3, Appendix C).

Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium activity was detected in one of 36 samples. Activity was detected in eight of 36 samples. All samples ranged from <153 to 600 pCi/l. The elevated results for September and October were a result of releasing more waste water in preparation of the Unit 1 refueling outage. Additionally, these releases occurred during abnormally low river flows. The concentrations were well below any regulatory limits. A dose estimate was performed by averaging the sample results for these two months. The hypothetical dose to the maximum exposed individual from consuming this water would have been 0.01 mrem/year to the liver of a child. (Figures C-4, Appendix C).

Gammai 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:

12 -

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 11 of 12 samples. The values ranged from

<2.6 to 9.9 pCi/l. Concentrations detected were consistent with those detected in previous years.

lodine-1 31 Monthly samples from location KI-1 were analyzed for concentrations of iodine-131. (Tables C-111.1, Appendix C). Iodire-131 activity was detected in one sample. The values ranged from

<0.3 to 1.3 pCi/l. The positive result is not believed to be due to TMINS effluents. Historically, 1-131 has been detected sporadically in effluent water and not in the control stations. No 1-131 was identified in any tank effluent pre-release samples, and 1-131 was not detected in any other downstream surface or drinking water samples. Effluent water is not consumed by humans.

Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-111.1, Appendix C). Tritium activity was detected in four samples. The values ranged from <158 to 157,000 pCi/l. The elevated results for March, July, August and September were a result of releasing more waste water in preparation of the Unit I refueling outage. These results are from the liquid discharge mixing basin. The concentrations detected agree with those obtained from the TMINS Effluent Monitoring Program. The concentrations were well below any regulatory limits.

Strontium Semiannual samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-111.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at 2.3 pCi/I for Sr-89 and at 0.6 pCi/l for Sr-90.

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

4.

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

Trititim All samples from location EDCB were analyzed for tritium activity (Table C-IV.1, Appendix C). Tritium activity was detected in three samples. The values ranged from <167 to 393 pCi/I and were due to airborne releases of H-3 from TMI. Concentrations detected were consistent with those detected in previous years.

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

5.

Ground Water Quarterly, semiannual and annual grab samples were collected at 27 locations (48S, GP-1, GP-6, GP-8, MS-22, OSF, OS-18, GP-9, GP-12, MS-2, MS-5, MS-20, NW-A, NW-B, NW-C, NW-CW, OS-14, RW-1, RW-2, El-2, MS-1, MS-4, MS-7, MS-8, MS-19, MS-21 and N2-1). The following analyses were performed:

Tritium All samples from the locations were analyzed for tritium activity (Table C-V.1, Appendix C). Tritium activity was detected in 43 of 55 samples. The values ranged from <103 to 18,500 pCi/l. In July of 2005 TMINS responded to elevated results in well RW-2. The sampling frequency for selected wells was increased. The results are listed in Table F-1.1, Appendix F. Tritium activity was detected in 83 of 104 samples. The values ranged from <103 to 31,100 pCi/l. TMINS discovered and fixed a leaking pipe in September.

The maximum concentration in RW-2 was detected in September.

Tritium concentrations trended downward the remainder of the year. Offsite groundwater tritium concentrations were unaffected by this event.

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

No Sr-90 activity was detected. The highest MDC was calculated at <0.4 pCi/I.

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

6.

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

Strontium The edible portions of fish samples from both locations were analyzed for Sr-89 and Sr-90. (Table C-VI.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <21 pCi/kg wet for Sr-89 and at <5 pCi/kg wet for Sr-90.

Gamma Spectrometry The edible portions of fish samples from both locations were analyzed for gamma emitting nuclides (Table C-V1.2, Appendix C).

Naturally occurring K-40 was found at all stations and ranged from 2,290 to 4,020 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were found.

7.

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

Gamma Spectrometry Sediment samples from all four locations were analyzed for gamma emitting nuclides (Table C-VII.1, Appendix C). Nuclides detected were naturally occurring K-40, and the fission product Cs-137.

K-40 was found at all stations and ranged from 7,720 to 16,300 pCi/kg dry. Concentrations of the fission product Cs-1 37 were found in six of seven samples (Figure C-5, Appendix C). Location EDCB had the highest average concentration of 294 pCi/kg dry.

The activity detected was consistent with those detected in the previous years. No other TMINS fission or activation products were found.

B.

Atmospheric Environment

1.

Airborne

a.

Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. The seven locations were separated into three groups: Group I represents locations within the TMINS site boundary (El-2 and F1-3),

Group II represents the location at an intermediate distance from the TMINS site (A3-1, G2-1, M2-1, and H3-1), and Group IlIl represents the control location at a remote distance from TMINS (Q15-1). The following analyses were performed:

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

Detectable gross beta activity was observed at all locations.

Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of TMINS. The results from the On-Site locations (Group I) ranged from <7 to 32 E-3 pCi/M3 with a mean of 17 E-3 pCi/M3. The results from the Offsite location (Group II) ranged from <6 to 37 E-3 pCi/M3 with a mean of 18 E-3 pCi/M3. The results from the Control locations (Group l1l) ranged from <6 to 34 E-3 pCi/M3 with a mean of 17 E-3 pCi/M3. Comparison of the 2005 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 2005 indicate no notable differences among the three groups (Figure C-7, Appendix C).

Gamma Spectrometry Weekly samples were composited quarterly and analyzed 1or gamma emitting nuclides (Table C-VIl.3, Appendix C).

Naturally occurring Be-7 due to cosmic ray activity was detected in 27 of 28 samples. These values ranged from

<21 to 96 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-IX.1, Appendix C). All results were less than the MDC.

2.

Terrestrial

a.

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

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

Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-X.2, Appendix C). No Sr-89 activity was detected. Sr-90 activity was detected. The values ranged from <0.3 to 2.5 pCi/I. The activity detected was consistent with those detected in the pre-operational years (Figure C-8, Appendix C).

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

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

The values ranged from 944 to 1,680 pCi/I. All other nuclides were less than the MDC.

b.

Food Products Samples were collected from two locations (B10-2 and E1-2) annually. The following analyses were performed:

Strontium Each food product sample was analyzed for concentrations of Sr-90 (Table C-XI.1, Appendix C). Sr-90 activity was not detected.

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

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

The values ranged from 1,790 to 4,030 pCi/I. All other nuclides were less than the MDC.

c.

Rodents No rodents were collected during 2005.

C.

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

TLD measurements were below 10 mR/standard month, with a range of 2.0 to 7.7 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 were consistently higher. The historical ambient gamma radiation data from Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 were plotted along with similar data from the Site, Intermediate Distance and Outer Ring Locations (Figure C-9, Appendix C). Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, and R15-1 have a historical high bias, but tracked with the data from all three groups, this bias is most likely due to radon and other naturally occurring nuclides, e.g. K-40, emanating from the ground.

D.

Land Use Survey A Land Use Survey conducted in the September and October 2005 growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Normandeau Associates,.RMC Environmental Services Division for AmerGen to comply with Sections 2.15 and 3.4.2 of the Plant's Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident and milk-producing animal in each of the sixteen 22 Y/2 degree sectors around the site. There were no changes required to the TMINS REMP, as a result of this survey. The nearest residence in the West sector changed from 560 m to 1120 m based on the residence survey. The Receptor files in the dose calculation software were changed. The results of this survey are summarized below.

Distance in Miles from the TMINS Reactor Buildings Sector Residence Milk Farm 1 N 1.1 2.1 2 NNE 0.7 3 NE 0.5 4.1 4 ENE 0.5 1.1 5E 0.4 1.1 6 ESE 1.1 3.2 7SE 0.7 1.4 8 SSE 0.7 9S 2.3 10 SSW 0.6 4.9 11 SW 0.5 12 WSW 0.5 13W 0.7 14 WNW 0.4 3.7 15 NW 0.4 16 NNW 0.7 As permitted by the ODCM, in lieu of a garden survey, sampling of broadleaf vegetation was performed. The sampling locations were in east southeast (ESE) and southeast (SE) sectors. A control sample was taken in the north northeast (NNE). The results are presented below.

2005 RADIOLOGICAL ENWIRONMENTAL MONITORING REPORT Exelon TMI 2006 Broad Leaf Vegetation Sampling Resultsl Cote=:n SmFfe Lotrto Vegetatiln Gurna

&.40 Ca!e Typc Result Resat (F-_1.g wet) to~kg, %t) 51^XC5 T1FL.CSE1 Syfen teLeaveBs

7.

9 A 1 75 35 t a

)(.-

tCM a 211 0g'1Ze5 TlFL.ESE2 Csm Leme:

Be-7:

1000 I 79 27 k 5 K.40 4800 2 1S3 caO1.s5 Wh1PL.ESE3 WatermelonLeaves Be?7:

8E l 277 66 a 5 K

29feO a 54 Cal1s5 TM.FPL4JNE1 Soybean Lees Be7.

1010 a as 27 t 4 KX-40 4430 a 2=

C9,'1ZfS TU.FPL4INEZa Can Lemves Be.7" 1920 2 106 15 t S X-0 5740a 1 1

C'i^Cs5 Tl-FPL-+Nr4Eua FurvkhiLeaves Be7:

54 it 67 165 t a K.3 4810 & 172 COJIZCS ThFPL.SE1 Soypean Leave-Bc7:

799 t 344 61 k s X-C 520 1 74a CMJZI.5 1U-4PL.SE2 Corn Lemes Bef:

tt1l0 a 218 35

5 X-.4 406-0 a A4 C=1^25 TIA-FPL.SE2 V'rtonLeames Be-7:

B32 A 277 53 A 4 K-40 4480 & 652 (1) Cole-ion and arnytis of broadezfv,-ctn was pebrfnrd in fiku of:a rarlen ctesUS.

C1 Cor nSamok No reactor produced gamma emitting radionuclides were detected.

Strontium-90 was detected in these samples. The detection of Sr-90 in these samples is not due to TMINS effluents for the following reasons:

Sr-90 was not detected in any in-plant effluent sample results 1-131 was released into the atmosphere at low levels from TMINS consistently and it was not detected in these environmental samples

Sr-90 is detectable in the soil from fallout from past nuclear weapon tests Plants uptake strontium as a soil nutrient via their roots

Sr-90 was detected in the control samples The Sr-90 detected in all these samples was a result of plant uptake of Sr-90 in the soil. The large variation in the concentrations is due to different bioaccumulation factors between plant species.

E.

Summary of Results - Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc.,

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

1.

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

2.

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

3.

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

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

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

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

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

For the primary laboratory, 18 out of 19 analytes met the specified acceptance criteria. Two samples did not meet the specified acceptance criteria for the following reasons:

1.

Teledyne Brown Engineering's Analytics' September 2005 air particulate Fe-59 ratio of 1.35 exceeded the upper control limit of 1.30 due to a new technician not counting the air particulate in a petri dish.

For the secondary laboratory, 19 out of 23 analytes met the specified acceptance criteria. Four samples did not meet the specified acceptance criteria for the following reasons:

1.

Environmental Inc.'s ERA's November 2005 water Gross Alpha result of 41.1 pCi/L exceeded the upper control limit of 33.4 pCi/L.

This was due to using an Am-241 efficiency instead of a Th-232 efficiency when counting the sample. Using the correct efficiency gave a result of 27.0 pCi/L.

2.

Environmental Inc.'s ERA's November 2005 water Ra-228 result of 5.5 pCi/L exceeded the upper control limit of 5.0 pCi/L due to presence of radium daughters. Delay in counting 100 minutes gave a result of 4.01 pci/L.

3.

Environmental Inc.'s MAPEP's January 2005 air particulate Sr-90 result of 2.2 exceeded the upper control limit of 1.76 Bq/kg.

Reanalysis result was 1.56 Bq/kg.

4.

Environmental Inc.'s MAPEP's July 2005 soil Am-241 result of 48.4 exceeded the lower control limit of 56.77 Bq/kg due to incorrect sample weight being used in the calculation. When recalculated with the correct sample weight, the result was 97.0 Bq/kg.

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

V.

References

1.

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

2.

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

3.

Radiation Management Corporation. "Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1974 - June5, 1974." RMC-TR-75-17, January 1975.

4.

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

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

THREE MIILE ISLAND NUCLEAR STATION DOCKET NUMIBER:

50-289 & 50-320 Location of Facility:

IIIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITH IIIGIIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHIWVAY SAMPLED ANALYSES ANALYSES 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)

TRITIUM 24 2000 3744 (5/12)

(<157/33500) 175 (1/12)

(<156/<191) 3744 (5/12)

(<157133500)

J1-2 INDICATOR WEST SHORE, TMI 0.5 MILES S OF SITE 0

1-131 12 I

N/A 0.4 0.4 (0/12)

(0/12)

(< 0.2/< 0.6)

A3-2 CONTROL SWATARA CREAK 2.5 MILES N OF SITE 0

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 24 15 5

(0/12)

(<41<7) 15 5

(0/12)

(<4/<8) 30 11 (0/12)

(<8/<15)

Is 5

(0/12)

(<3/<9) 30 12 (0/12)

(<9/<16) 15 6

(0/12)

(<4/<8) 5 (0/12)

(<41<8) 5 (0/12)

(<41<9) 1 1 (0/12)

(<8/<16) 6 (0/12)

(<4< 10)

I 1 (0/12)

(<8/<17) 6 (0/12)

(<41<8) 5 (0/12)

(<4/<8) 5 (0112)

(<4/<8) 1 1 (0/12)

(<8/<16) 6 (0/12)

(<4/<10) 12 (0/12)

(<9/<16) 6 (0/12)

(<4/<8)

Q9-1 CONTROL STEELTON WATER COMPANY 8.5 MILES NW OF SITE 11-2 INDICATOR WEST SHORE, TMI 0.5 MILES S OF SITE Q9-1 CONTROL STEELTON WATER COMPANY 8.5 MILES NW OF SITE Q9-I CONTROL STEELTON WATER COMPANY 8.5 MILES NW OF SITE J1-2 INDICATOR WEST SHORE, TMI 0.5 MILES S OF SITE 11-2 INDICATOR WEST SHORE, TMI 0.5 MILES S OF SITE

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUNINIARY FOR TIHE THREE MILE ISLAND NUCLEAR STATION, 2005 Name or Facility:

THREE MIILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

IMIIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WVITII HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SURFACE WATER (PCI/LITER)

ZR-95 CS-134 CS-137 BA-140 LA-140 30 10 (0/12)

(<6/<16) 15 5

(0/12)

(<21<8) 18 6

(0/12)

(<41<7) 60 28 (0/12)

(<15/<40) 15 8

(0/12)

(<51<12)

I'.)

9 (0/12)

(<7/<14) 5 (0/12)

(<41<8) 6 (0/12)

(<4/<8) 27 (0/12)

(<21/<37) 8 (0/12)

(<6/<11) 2.6 (9/12)

(< 1.7/ 4.3) 0.4 (0/12)

(< 0.2/< 0.8) 180 (2/12)

(<1541263) 10 (0/12)

(<61<16) 5 (0/12)

(<2/<8) 6 (0/12)

(<41<7) 28 (0/12)

(<15/<40) 8 (0/12)

(<6/<11) 3.5 (11/12)

( 2.2/ 5.4) 0.5 (0/12)

(< 0.3/< 0.9) 286 (4112)

(<1541601)

JI-2 INDICATOR WEST SIIORE, TMI 0.5 MILES S OF SITE Jl-2 INDICATOR WEST SHORE, TMI 0.5 MILES S OF SITE JI-2 INDICATOR WEST SHORE, TMI 0.5 MILES S OF SITE JI-2 INDICATOR WEST SHORE, TMI 0.5 MILES S OF SITE Q9-I CONTROL STEELTON WATER COMPANY 8.5 MILES NW OF SITE 015-2 INDICATOR WRIGIHTSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE G15-3 INDICATOR LANCASTER WATER AUTHORITY 14.8 MILES SE OF SITE DRINKING WATER (IPCI/LITER)

GROSS BETA 1-131 TRITIUM 36 36 36 4

3.3 (21124)

(< 2.0/ 5.4) 1 0.5 (0124)

(< 0.2/< 0.9) 2000 240 (6124)

(<153/601)

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIlE THREE MILE ISLAND NUCLEAR STATION, 2005 Namne of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

MIIIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITII HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS DRINKING WATER (PCI!LITER)

GAMMA MN-54 36 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 fC 11A 15 5

(0/24)

(<31<9) 15 5

(0/24)

(<21<9) 30 10 (0/24)

(<6/<14) 15 5

(0/24)

(<4/<10) 30 10 (0/24)

(<5/<21) 15 5

(0/24)

(<3/<9) 30 9

(0/24)

(<51<15)

!<A (0/24)

(<3/<7) 4 (0/12)

(<31<6) 4 (0/12)

(<31<6) 9 (0/12)

(<4/<13) 5 (0/12)

(<31<7) 8 (0/12)

(<6/<13) 5 (0/12)

(<31<8) 8 (0/12)

(<51<1 1)

A (0/12)

(<31<6) 5 (0/12)

(<31<9) 5 (0/12)

(<31<9) 10 (0/12)

(<8/<14) 6 (0/12)

(<4/<10)

I 1 (0/12)

(<5/<21) 6 (0/12)

(<41<9) 9 (0/12)

(<71<13)

(0/12)

(<31<7)

G15-2 INDICATOR WRIG1ITSVILLE WATER SUPPLY 13.6 MILES SE OF SITE 015-2 INDICATOR WRIGHTSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G15-2 INDICATOR WRIGHTSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G15-2 INDICATOR WRIGIITSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G15-2 INDICATOR WRIGHTSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G15-2 INDICATOR WRIGIITSVILLE WATER SUPPLY 13.6 MILES SE OF SITE 015-2 INDICATOR WRIGIITSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G!5 2 T!1D!IATOR WRIGHTSVILLE WATER SUPPLY 13.6 MILES SE OF SITE

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIlE TIIREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

MIIIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITH IIIGIIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PAThiWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS DRINKING WATER (PCI/LITER)

CS-137 BIA-140 LA-140 IS 5

(0/24)

(<4/<8) 60 25 (0/24)

(<15/<41) 15 8

(0/24)

(<31<13)

EFFLUENT WATER (PCI/LITER)

GROSS BETA 1-131 11-3 SR-89 SR-90 12 12 12 2

2 N/A 5.4 (11/12)

(2.419.9)

N/A 0.6 (1/12)

(< 0.3/ 1.3)

N/A 21324 (7/12)

(<158/157000)

N/A 1.9 (0/2)

(< 1.5/< 2.3)

N/A 0.6 (0/2)

(< 0.6/< 0.6) 5 (0/12)

(<3/<7) 22 (0/12)

(<18/<30) 7 (0/12)

(<4/<1 2)

N/A N/A N/A N/A N/A 6

(0/12)

(<4/<8) 27 (0/12)

(<17/<41) 8 (0/12)

(<4/<12) 5.4 (11/12)

(2.4/ 9.9) 0.6 (1/12)

(< 0.3/ 1.3) 21324 (7/12)

(<158/157000) 1.9 (0/2)

(< 1.51< 2.3) 0.6 (0/2)

(< 0.6/< 0.6)

G15-2 INDICATOR WRIGIITSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G15-2 INDICATOR WRIGIITSVILLE WATER SUPPLY 13.6 MILES SE OF SITE G15-2 INDICATOR WRIGIITSVILLE WATER SUPPLY 13.6 MILES SE OF SITE KI-1 INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-1 INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

TIIREE MNILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

MIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITII 1IIGIIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS EFFLUENT WATER (PC[ILITER)

GAMMA NMN-54 12 N/A 5

(0/12)

(<31<6)

CO-58 FE-59 CO-60 ZN-65 N/A 4

(0/12)

(<3/<5)

N/A 9

(0/12)

(<6/<1 1)

N/A 4

(0/12)

(<3/<6)

N/A 9

(0/12)

(<6/<1 1)

N/A N/A N/A N/A N/A 5

(0/12)

(<3/<6) 4 (0/12)

(<3/<5) 9 (0/12)

(<6/<1 1) 4 (0/12)

(<31<6) 9 (0/12)

(<6/<1 1)

KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-1 INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE 0

0 0

V, 0

NB-95 ZR-95 CS-134 N/A 5

(0/12)

(<41<7)

N/A 8

(0/12)

(<6/<12)

N/A 4

(0/12)

(<31<5)

N/A N/A N/A S

(0/12)

(<41<7) 8 (0/12)

(<6/<12) 4 (0/12)

(<3/<5)

KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE 0

0 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

MIIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOIR CONTROL LOCATION WITII HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBlER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS EFFLUENT WATER (PCIIlITER)

CS-137 BA-140 LA-140 N/A 5

(0/12)

(<3/<6)

N/A 23 (0/12)

(<17/<29)

N/A 7

(0/12)

(<51<10)

N/A N/A N/A N/A 5

(0/12)

(<3/<6) 23 (0/12)

(<17/<29) 7 (0/12)

(<5/<1 0) 287 (314)

(<167/393)

KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE KI-I INDICATOR MAIN STATION LIQ. DISCHARGE 0.2 MILES SSW ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE 0

0 0

0 STORM WVATER (PCI/LITER)

TRITIUM 4

N/A 287 (3/4)

(<167/393)

GAMMA MIN-54 4

N/A 4

(0/4)

(<3/<5)

N/A 5

(0/2)

(<4/<5)

EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE 0

CO-58 FE-59 N/A 4

(0/4)

(<31<6)

N/A 8

(0/4)

(<6/<1 1)

N/A N/A 5

(0/2)

(<31<6) 10 (0/2)

(<9/<1 1)

EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

TIIREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

MIDI)DLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITII IIIGIIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED -

ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS STORMN WATER (PCI'LITER)

CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 N/A 5

(0/4)

(<31<7)

N/A 9

(0/4)

(<71<1 1)

N/A 4

(0/4)

(<3/<5)

N/A 7

(0/4)

(<61<9)

N/A 4

(0/4)

(<3/<4)

N/A 5

(0/4)

(<31<7)

N/A 19 (0/4)

(<16/<24)

N/A 5

(n/41

(<4/<6)

N/A N/A N/A N/A N/A N/A N/A N/A 7

(0o2)

(<61<7) 10 (0/2)

(<9/<1 1) 5 (0/2)

(<4/<5) 7 (0/2)

(<71<8) 4 (0/2)

(<41<4) 6 (0/2)

(<51<7) 21 (0o2)

(<191<24) 6

(<51<6)

EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR RTORM XVATFR nAqIM 0.2 MILES SE ON SITE 0

0 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMIBER:

50-289 & 50-320 Location of Facility:

AIIDDLETOWN COUNTY', PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBEROF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS GROUND WATER (PCI/LITER) 11-3 55 6

N/A 955 (43/55)

(<103/18500)

N/A 0.3 (0/6)

(< 0.3/< 0.4)

N/A N/A 9613 (2/2)

(725/18500) 0.4 (0/1)

(< 0.4)

RW-2 INDICATOR ONSITE WELL MS-5 INDICATOR ONSITE WELL 0

SR-90 GAMMA MN-54 0

18 N/A 3

(0/18)

(<1/<8)

N/A 7

(0/1)

(<7)

N2-1 INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE 0

CO-58 Co FE-59 CO-60 ZN-65 N/A 4

(0/18)

(<1/<7)

N/A 8

(0/18)

(<4/<18)

N/A 4

(0/18)

(<1/<9)

N/A 7

(0/18)

(<2/<15)

N/A N/A N/A N/A 7

(0/1)

(<7) 14 (0/1)

(<14) 7 (0/1)

(<7) 13 (0/1)

(<13)

N2-1 INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE N2-1 INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE N2-1 INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE N2-1 INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE 0

0 0

0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUMMN1ARY FOR THE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

TUREE MNILE ISLAND NUCLEAR STATION DOCKET NUNMBER:

50-289 & 50-320 Location of Facility:

1IIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITh IIIGIIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS I

i I

GROUND WATER (PCI/LITER)

NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 N/A 4

(0/18)

(<1/< 1)

N/A 7

(0/18)

(<3/<14)

N/A 3

(0/18)

(<11<8)

N/A 3

(0/18)

(<1/<8)

N/A 34 (0/18)

(<11/<46)

N/A 11 (0/18)

(<3/<15)

N/A N/A N/A N/A NIA N/A 18 (0/2)

(<16/<20) 4 (0/2)

(<41<4) 7 (0/4)

(<3/<1 1) 14 (0/1)

(<14) 7 (0/1)

(<7) 7 (0/I)

(<7) 45 (0/1)

(<45) 15 (0/1)

(<15) 18 (0/2)

(<15/<21) 4 (0/2)

(<4/<4)

OSF INDICATOR ONSITE WELL N2-I INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE N2-1 INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE N2-1 INDICATOR GOLDSBORO MARINA 1.2 MILES W OF SITE MS-5 INDICATOR ONSITE WELL OS-14 INDICATOR ONSITE WELL INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE BKGI3 CONTROL CITY ISLAND UPSTREAM OF DISCHARGE 0

0 0

0 BOTTOM FEEDER (FISH)

(PCI/KG WET)

SR-89 4

4 N/A 18 (0/2)

(<15/<21) 10 2

(0/2)

(<2/<3) 0 0

SR-90

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

TABLE A-I RADIOLOGICAL ENVIRONMIENTAL IONITORING PROGRAM ANNUAL SUMMNNARY FOR TIIE TIIREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

THREE MIILE ISLAND NUCLEAR STATION DOCKET NUMIBER:

50-289 & 50-320 Location of Facility:

MIIDDLETOWVN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WVITII HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS BOTTOM FEEDER (FISH)

(PCI/KG WET)

GAMMA K40 4

I MN-54 CO-58 FE-59 CO-60 ZN-65 CS-134 CS-137 N/A 2925 (2n2)

(2400/3450) 130 35 (0/2)

(<28/<42) 130 39 (0/2)

(<29/<48) 260 70 (0/2)

(<681<72) 130 35 (0/2)

(<27/<44) 260 81 (0/2)

(<73"<89) 130 37 (0/2)

(<33/<41) 150 42 (0/2)

(<361<48) 2320 (2/2)

(2290/2350) 31 (0/2)

(<261<35) 22 (0/2)

(<15/<28) 61 (0/2)

(<39/<83) 34 (0/2)

(<33/<35) 54 (0/2)

(<34/<74) 26 (0/2)

(<21/<30) 32 (0/2)

(<24/<41) 2925 (212)

(2400/3450) 35 (0/2)

(<281<42) 39 (0/2)

(<29/<48) 70 (0/2)

(<68/<72) 35 (0/2)

(<27/<44) 81 (0/2)

(<73/<89) 37 (0/2)

(<33/<41) 42 (0/2)

(<36/<48)

INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE INDB INDICATOR YORK IIAVEN DAM DOWNSTREAM OF DISCHARGE INDB INDICATOR YORK I AVEN DAM DOWNSTREAM OF DISCHARGE INDB INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE INDB INDICATOR YORK I AVEN DAM DOWNSTREAM OF DISCHARGE

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

TlIREE M\\ILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

MIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITII IIIGIIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBEROF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS PREDATOR (FISIl)

(PCI!KG WET)

SR-89 N/A 18 (0/2)

(<161<19)

SR-90 GAMMA K-40 4

4 MN-54 CO.58 FE-59 CO-60 7N-65 10 4

(0/2)

(<41<5)

N/A 2985 (2/2)

(2890/3080) 130 38 (0/2)

(<20/<55) 130 38 (0/2)

(<141<63) 260 75 (0/2)

(<51/<99) 130 46 (0/2)

(<381<55)

Ufn 8Q (0/2)

(<56/<123) 18 (0/2)

(<17/<19) 3 (0/2)

(<2/<3) 3640 (2/2)

(3260/4020) 30 (0/2)

(<2 1<38) 33 (0/2)

(<24/<41) 78 (0/2)

(<45/<1 12) 39 (0/2)

(<291<48) 74 (0/2)

(<52/<97) 18 (0/2)

(<17/<19) 4 (0/2)

(<4/<5) 3640 (2/2)

(3260/4020) 38 (0/2)

(<20/<55) 38 (0/2)

(<14/<63) 78 (0/2)

(<45/<l 12) 46 (012)

(<38/<55) 89 (0/2)

(<561<123)

BKGP CONTROL CITY ISLAND UPSTREAM OF DISCHARGE INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE BKGP CONTROL CITY ISLAND UPSTREAM OF DISCHARGE INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE BKGP CONTROL CITY ISLAND UPSTREAM OF DISCHARGE INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE

!NDP IND!CATOR.

YORK HAVEN DAM DOWNSTREAM OF DISCHARGE 0

0 0

0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL M1ONITORING PROGRtAI ANNUAL SUMNIMARY FORI TIIE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

TIIREE MIILE ISLAND NUCLEAR STATION DOCKET NUMIBER:

50-289 & 50-320 Location of Facility:

MIDI)LETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITII IIIGIIEST ANNUAL MIEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS PREDATOR (FISII)

(PCI/KG WVET)

CS-134 130 43 (0o2)

(<23/<63) 150 44 (0/2)

(<28/<60) 30 (0/2)

(<23/<38) 32 (0/2)

(<24/<39) 43 (0/2)

(<23/<63) 44 (0/2)

(<28/<60)

INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE INDP INDICATOR YORK HAVEN DAM DOWNSTREAM OF DISCHARGE 0

0 CS-137 SEDIMENT (PCI/KG DRY)

GAMMA K-40 7

MN-54 I

CO-58 CO-60 CS-134 CS-137 N/A 9844 (4/5)

(<4470/16300)

N/A 57 (0/5)

(<361<95)

N/A 54 (0/5)

(<411<85)

N/A 57 (0/5)

(<34/< 12) 150 51 (0/5)

(<33/<80) 180 162 (515)

(98/294) 8215 (2/2)

(7720/8710) 36 (0/2)

(<31/<41) 33 (0/2)

(<271<38) 39 (0/2)

(<35/<43) 32 (0/2)

(<31/<32) 42 (1/2)

(<41/42) 16300 (1/1)

(16300) 95 (0/1)

(<95) 85 (0/1)

(<85) 112 (0/1)

(<112) 80 (0/1)

(<80) 294 (1/1)

(294)

J2-1 INDICATOR YORK IIAVEN DAM 1.5 MILES S OF SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM WATER BASIN 0.2 MILES SE ON SITE EDCB INDICATOR STORM \\VATER BASIN 0.2 MILES SE ON SITE 0

0 0

0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIlE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

MIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITII IhIGIIEST ANNUAL M1EAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS AIR PARTICULATE (E-3 PCIICU.METER)

GROSS BETA 364 10 17 (300/312)

(<6/37) 17 (49/52)

(<6/34) 18 (50/52)

(<7/36)

A3-1 INDICATOR MIDDLETOWN 2.6 MILES N OF SITE 0

GAMMA BE-7 28 N/A 65 (23/24)

(<21/88) 71 (4/4)

(54/96) 71 (4/4)

(63/82)

FI-3 INDICATOR 500 KV SUBSTATION 0.6 MLES ESE OF SITE 0

MN-54 N/A 1.6 (0/24)

(< 0.6/< 3.1)

CO-58 CO-60 CS-134 CS-137 N/A 2.0 (0/24)

(< 0.6/< 4.0)

N/A 1.7 (0/24)

(< 0.8/< 3.7) 50 1.5 (0/24)

(< 0.51< 3.5) 60 1.5 (0/24)

(< 0.6/< 3.5) 1.8 (0/4)

(< 1. I/< 2.5) 2.0 (0/4)

(< 1.3/< 2.7) 1.9 (0/4)

(< 1. I/< 2.9) 1.6 (0/4)

(< 1.0/< 2.7) 1.7 (0/4)

(< 1.2/< 2.4) 1.8 (0/4)

(<0.91<3.1) 2.3 (0/4)

(< 1.0/< 4.0) 1.9 (0/4)

(< 1. I/< 2.9) 1.7 (0/4)

(< 0.7/< 3.0) 1.7 (0/4)

(<0.9/<3.1) 113-1 INDICATOR FALMOUTH-COLLINS SUBSTATION 2.3 MILES SSE OF SITE 113-1 INDICATOR FALMOUTII-COLLINS SUBSTATION 2.3 MILES SSE OF SITE Q15-1 CONTROL WEST FAIRVIEW 13.5 MILES NW OF SITE 113-I INDICATOR FALMOUTII-COLLINS SUBSTATION 2.3 MILES SSE OF SITE 113-1 INDICATOR FALMOUTII-COLLINS SUBSTATION 2.3 MILES SSE OF SITE 0

0 0

AIR IODINE (E-3 PCI/CU.METER) 1-131 364 70 23 (0/312)

(<7/<60) 23 (0/52)

(<12/<50) 23 (0/52)

(<121<50) 015-I CONTROL WEST FAIRVIEW 13.5 MILES NW OF SITE 0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL SUNMNMARY FOR TIIE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

TIIREE MIILE ISLAND NUCLEAR STATION DOCKET NUMBER:

50-289 & 50-320 Location of Facility:

lIDD)LETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITII IIIGIIEST ANNUAL IIEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWVER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS MILK (PCI/LITER) 1-131 SR-89 SR-90 GAMMA K40 96 20 20 1

0.5 (om)

(< 0.2/< 1.0)

N/A 2.1 (0116)

(< 0.91< 4.2) 2 0.8 (15/16)

(0.3/2.5) 0.5 (0/23)

(< 0.3/< 1.0) 2.0 (0/4)

(< 0.9/< 3.4) 0.6 (314)

(< 0.3/0.7) 1360 (23123)

(1210/1530) 0.5 (0/23)

(< 0.2/< 1.0) 2.4 (0/4)

(< 0.91< 4.2) 1.2 (314)

( 0.4/ 2.5) 1398 (4/4)

(1360/1450)

K15-3 CONTROL MEYER'S FARM 14.5 SSW OF SITE E2-2 INDICATOR NISSLEY FARM 1.1 MILES E OF SITE 14-1 CONTROL TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE 14-1 CONTROL TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE 0

0 0

0 96 N/A 1284 (73/73)

(944/1680)

CS-134 CS-137 BA-140 LA-140 15 5

(o073)

(<1/<1 1)

I8 6

(0/73)

(<2/<13) 60 26 (o073)

(<71<45) 15 8

(0/73)

(<2/<15) 5 (0/23)

(<1/<9) 6 (0/23)

(<2/<10) 24 (0/23)

(<10/<45) 7 (0/23)

(<3/<11) 7 (0/4)

(<5/<8) 8 (0/4)

(<7/<10) 32 (0/4)

(<26/<38) 10 (0/4)

(<6/<13)

P4-1 CONTROL TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE F4-1 CONTROL TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE 174-1 CONTROL TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE F4-1 CONTROL TURNPIKE ROAD FARM 3.0 MILES ESE OF SITE 0

0 0

0

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

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE THREE MILE ISLAND NUCLEAR STATION, 2005 Name of Facility:

THREE MILE ISLAND NUCLEAR STATION DOCKET NUNIBER:

50-289 & 50-320 Location of Facility:

IIIDDLETOWN COUNTY, PA REPORTING PERIOD:

2005 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATIiWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS FOOD PRODUCT (PCI/KG WET)

SR-90 2

t0 4

(0/1)

(<4) 4 (0/1)

(<4) 4 (0/I)

(<4)

EI-2 INDICATOR TMI VISITORS CENTER 0.4 MILES E OF SITE 0

GAMMA K-40 1-131 CS-134 CS-137 8

N/A 2783 (4/4)

(2190/4030) 60 30 (0/4)

(<20/<42) 60 15 (0/4)

(<13/<17) 80 17 (0/4)

(<12/<20) 2238 (4/4)

(1790/2840) 28 (0/4)

(<221<42) 16 (0/4)

(<12/<20) 19 (0/4)

(<14/<23) 4.6 (43/43)

(3.3n.0) 4030 (1/1)

(4030) 42 (0/1)

(<42) 20 (0/1)

(<20) 20 (0/1)

(<23) 6.9 (4/4)

(6.2n.7)

EI-2 INDICATOR TMI VISITOR!S CENTER 0.4 MILES E OF SITE EI-2 INDICATOR TMI VISITOR'S CENTER 0.4 MILES E OF SITE B 10-2 CONTROL MILTON HERSHEY SCHOOL 10.3 MILES NNE OF SITE B 10-2 CONTROL MILTON HERSHEY SCIIOOL 10.3 MILES NNE OF SITE 118-I INDICATOR SAGINAW ROAD 7.4 MILES SSE OF SITE 0

0 0

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

TLD-QUARTERLY 356 N/A 4.0 (315/315)

(2.0n.7) 0

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

Intentionally Left Blank

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

& ANALYTICAL METHODS

TABLE B-1:

XYY-7_

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

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

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, 2005 Sample Medium AQS ID AP,AI,ID SW ID ID ID ID ID ID ID FP ID ID ID ID ID AQF GAD ID ID M

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

ID ID ID ID ID AP,AI ID ID M

ID ID Station Al-3 A1-4 A3-1 A3-2 A5-1 A9-3 B1-1 81-2 82-1 85-1 B10-1 B10-2 Cl-1 C1-2 C2-1 C5-1 C8-1 Control Control Dl -1 D13-2 D2-1 D2-2 D6-1 D1 5-1 E1-2 E1-4 E2-2 E2-3 E5-1 E7-1 Fl-i F1-2 F1-3 F1-4 F2-1 F4-1 F5-1 F10-1 F25-1 Map Nuzmbe 16 113 nigtanre 0.5 mi 0.3 39 2.6 40 2.5 44 4.3 127 8.1 2

0.6 114 0.4 132 1.9 45 4.8 61 9.4 1

10.1 17 0.7 116 0.3 43 1.6 46 4.5 62 7.2 3

18 29 133 47 80 19 117 109 134 48 64 20 118 149 154 135 156 49 66 0.2 0.6 1.1 1.7 5.2 10.9 0.4 0.2 1.1 1.9 4.6 6.8 0.5 0.2 0.6 0.3 1.2 3.2 4.7 9.4 Azimuith D

rpfn 0° N of site off north tip of TMI in Susquehanna River 5

N of Reactor Building on W fence adjacent to North Weather Station, TMI 358 N of site at Mill Street Substation 355 N of site at Swatara Creek, Middletown 3

N of site on Vine Street Exit off Route 283 3

N of site at Duke Street Pumping Station, Hummelstown 25 NNE of site on light pole in middle of North Bridge, TMI 26 NNE of Reactor Building on top of dike, TMI 16 NNE of site on Sunset Dr. (off Hillsdale Rd.)

18 NNE of site at intersection of School House and Miller Roads 21 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey 28 NNE of site at Milton Hershey School, Hershey 35 NE of site along Route 441 N 54 NE of Reactor Building on top of dike, TMI 48 NE of site at Middletown Junction 42 NE of site on Kennedy Lane 48 NE of site at Schenk's Church on School House Road All locations where finfish are collected upstream of the TMINS liquid discharge outfall (above Dock St. Dam, Harrisburg) are grouped together and referred to as

.control" All locations greater than 10 miles from TMINS 74 ENE of Reactor Building on top of dike, TMI 60 ENE of site on Laurel Road 65 ENE of site at farm on Gingrich Road 73 ENE of site along Hillsdale Rd. (S of Zion Rd.)

65 ENE of site off Beagle Road 63 ENE of site along Route 241, Lawn, PA 95 E of site at TMI Visitors Center 98 E of Reactor Building on top of dike, TMI 93 E of site at farm on Pecks Road 96 E of site along Hillsdale Rd. (N of Creek Rd.)

81 E of site at intersection of North Market Street (Route 230) and Zeager Road 86 E of site along Hummelstown Street, Elizabethtown 117 ESE of site near entrance to 500 kV Substation 109 ESE of Reactor Building on top of dike midway within Interim Solid Waste Staging Facility, TMI 105 ESE of site in 500 kV Substation 115 ESE of Reactor Building on top of dike, TMI 120 ESE of site along Engle Road 104 ESE of site at farm on Tumpike Road 107 ESE of site along Amosite Road 112 ESE of site along Donegal Springs Road, Donegal Springs 113 ESE of site at intersection of Steel Way and Loop Roads, Lancaster 143 SE of site along Route 441 S 129 SE of Reactor Building on top of dike, TMI 144 SE of Reactor Building on top of dike, TMI 141 SE of Reactor Building on top of dike, TMI 125 SE of site at farm on Becker Road 135 SE of site on Becker Road 131 SE of site at intersection of Bainbridge and Risser Roads 127 SE of site at farm along Engles Tollgate Road, Marietta 124 SE of site at Columbia Water Treatment Plant 128 SE of site at Wrightsville Water Treatment Plant 124 SE of site at Lancaster Water Treatment Plant 167 SSE of site, TMI B -2 ID ID ID ID ID AI,AP,M ID ID ID ID DW DW ID G1-2 G1-3 G1-5 G1-6 G2-1 G2-4 G5-1 G10-1 G15-1 G15-2 G15-3 Hi-i 82 21.1 22 0.6 119 0.3 139 0.3 140 0.3 104 1.4 136 1.7 50 4.8 67 9.8 84 14.4 85 13.6 86 14.8 5

0.5

TABLE 13-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2005 Sample Medillm _

Station Map rndL Niimhwn nsiqan~e-A~mnth np2eitnn APAIID ID H3-1 H1-1 ID ID H8-1 H15-1 AQF Indicator 41 2.3 mi 52 4.1 68 7.4 87 13.2 6

0.8 23 0.5 121 0.3 31 1.5 GAD ROD Indicator Indicator ID SW J1-1 J1-2 ID J1-3 ACS J2-1 ID ID ID ID EW AQS ID J3-1 J5-1 J7-1 J15-1 K1-1 K1-3 K1-4 141 53 69 88 7

24 123 32 142 54 70 2.7 4.9 6.5 12.6 0.2 0.3 0.2 1.1 2.1 5.0 7.4 ID ID ID ID K2-1 K3-1 K5-1 K8-1 1590 SSE of site in Falmouth-Collins Substation 157 SSE of site by Guard Shack at Brunner Island Shtam Electric Station 163 SSE of site along Saginaw Road, Starview 157 SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills All locations where finfish are collected downstream of the TMINS liquid discharge ouffall are grouped together and referred to as "indicator" All locations within ten miles of TMINS All locations where rodents are collected within the ovner controlled area, TMI 181 S of site, TMI 188 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River 189 S of Reactor Building on wooden post of Building 221, just S of Unit 2 Admin. Building, TMI 182 S of site in Susquehanna River just upstream of the "1ork Haven Dam 178 S of site at York Haven/Cly 182 S of site along Canal Road, Conewago Heights 177 S of site off of Maple Street, Manchester 180 S of site in Met-Ed York Load Dispatch Station 209 On site at RML-7 Main Station Discharge Building 202 SSW of site in Susquehanna River 208 SSW of Reactor Building on top of dike behind Warehouse 2, TMI 200 SSW of site on S Shelley Island 202 SSW of site along Rt. 262, N of Cly 200 SSW of site along Conewago Creek Road, Strinestown 196 SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View 204 SSW of site on the Bird's Nest Child Care Center Building, Weiglestown 205 SSW of site at farm along S Salem Church Rd, Dover 235 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI 221 SW of site on Beech Island 227 SW of site along Route 262 228 SW of site at intersection of Stevens and Wilson Roads 225 SW of site along Rohlers Church Rd., Andersontown 225 SW of site on W side of Route 74, rear of church, Mt.

Royal 249 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI 241 WSW of site on W side of unnamed island between N tip of Beech Island and Shelley Island 253 WSW of site adjacent to Fishing Creek, Goldsboro 249 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown 242 WSW of site along Alpine Road, Maytown 270 W of site on Shelley Island 270 W of Reactor Building on fence adjacent to Screenhcuse entrance gate, TMI 262 W of site at Goldsboro Marina 268 W of site off of Old York Road along Robin Hood Drive 260 W of site along Route 382, 1/2 mile north of Lewisberr/

274 W of site at intersection of Lisbum Road and Main Street, Lisbum 293 WNW of site on Shelley Island ID K15-1 M

ID K15-3 LI-1 ID ID ID ID ID LI-2 L2-1 1-5-1 1-8-11 L15-1 ID M1-1 ID M1-2 90 12.7 151 14.5 9

0.1 26 0.5 33 1.9 55 4.1 71 8.0 91 11.7 129 0.1 143 0.5 34 1.3 56 4.3 72 8.6 10 0.7 124 0.1 35 1.2 57 4.9 73 7.8 95 10.4 12 0.4 AP,AI,ID ID M2-1 M5-1 ID ID ID M9-1 N1-1 Ni -3 ID,GW ID ID ID N2-1 N5-1 N8-1 N15-2 ID P1-1 B -3

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Sample Mydlim Mile Island Nuclear Station, 2005 Station Map andp Number Drstanrp*

Azmuth neerripfn ID ID ID ID ID ID ID ID SW,DW,ID APAIID ID ID ID ID P1-2 P2-1 P5-1 P8-1 01-1 01-2 02-1 05-1 Q9-1 Q15-1 Ri-1 R1 -2 R3-1 R5-1 R9-1 R15-1 38 0.2 mi 36 1.9 58 4.9 74 8.0 13 0.5 125 0.2 37 1.8 59 5.0 76 8.5 97 13.5 14 0.2 27 0.7 107 2.6 60 4.9 77 8.1 99 11.2 290 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI 283 WNW of site along Route 262 285 WNW of site at intersection of Valley Road (Route 262) and Beinhower Road 292 WNW of site along Evergreen Road, Reesers Summit 317 NW of site on Shelley Island 318 NW of Reactor Building on fence W of Warehouse 1, TMI 310 NW of site along access road along river 318 NW of site along Lumber Street, Highspire 308 NW of site at the Steelton Water Company 305 NW of site behind West Fairview Fire Dept. Social Hall 335 NNW of Reactor Building along W fence, TMI 332 NNW of site on Henry Island 338 NNW of site at Crawford Station, Middletown 339 NNW of site at Interstection of Spring Garden Drive and Route 441 340 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights 330 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park ID ID IDENTIFICATION KEY ID

= Immersion Dose (TLD)

SW = Surface Water Al

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

GW DW M

GAD

= Ground Water (offsite)

= Drinking Water

= Milk (Cow)

= Meat (Game)

AQF

= Finfish AQS = Aquatic Sediment EW

=Effluent Water ROD = Rodents B-4

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2005 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

Env. Inc., GS-01 Determination of gamma emitters by Surface Water Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid 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 Water Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices 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 Water 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 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 Water Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis 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 Water Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid 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 Water lodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radiolodine in various matrices 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 ffluent Water Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchange Effluent Water 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 from a continuous radiological analysis (Three Mile Island various matrices water compositor.

Nuclear Station)

Env. Inc., W(DSY01 Determination of gross alpha and/or gross Bela in water (-Sssolved Solids or total residue)

B - 5

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2005 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Water Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, T8E-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor.

Nuclear Station)

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

_gamma sgectroscopy Effluent Water Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid 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 Water Strontium 89/90 Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by Ion exchange composite from monthly samples.

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

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

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

Ground Water Gamma Quarterly, Semi-ER-TMI-10 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy Annual and Annual radiological analysis (Three Mile Island samples Nuclear Station)

Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy TBE. TBE-2023 Compositing of samples Ground Water Tritium Quarterly, Semi-EM-TMI-10 Collection of water samples for I gallon or 125 mL TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Annual and Annual radiological analysis (Three Mile Island scintillation samples, or as needed Nuclear Station)

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

B - 6

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2005 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Ground Water Strontium 89/90 Quarterly, Semi-ER-TMI-10 Collection of water samples for 1 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange Annual and Annual radiological analysis (Three Mile Island samples Nuclear Station)

TBE. TBE-2023 Compositinr of samples 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 89/90 Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet)

TBE, TBE-2019 Radiostrontium analysis by ion exchange collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) other techniques Sediment Gamma Semi-annual grab ER-TMI-03 Collection of sediment samples 500 grams (dry)

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

Env. Inc., GS-01 Determination of gamma emitters by gamma spectrosconV Air Particulates Gross Beta One-week composite ER-TMI-14 Collection of air particulate and 1 filter TBE, TBE-2008 Gross alpha and/or gross beta activity in of continuous air air iodine samples for radiological analysis (approximately 280 various matrices sampling through (Three Mile Island Nuclear Station) cubic meters weekly) glass fiber filter paper Env. Inc., AP-02 Determination of gross alpha and/or gross beta in air particulate filters Air Particulates Gamma Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy each station (approximately 3600 Env. Inc., AP-03 Procedure for compositing cubic meters)

Env. Inc., GS-01 Determination of gamma emitters by air particulate filters for gamma spectroscopic gamma spectroscopy analysis Air Iodine Gamma One-week composite ER-TMI-14 Collection of air particulate and 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy of continuous air air iodine samples for radiological analysis (approximately 280 sampling through (Three Mile Island Nuclear Station) cubic meters weekly)

Env. Inc., 1-131-02 Determination of 1-131 in charcoal charcoal filter canisters by gamma spectroscopy (batch method)

Milk 1-131 Bi-weeklygrab sample ER-TMI-01 Collection of milk samples for 2 gallon TBETBE-2012 Radioiodine in various matrices when cows are on pasture. Monthly all other times radiological analysis (Three Mile Island Nuclear Station)

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchangeI Milk Strontium-89/90 Quarterly composite of Bi-weekly and monthly grab samples ER-TMI-01 Collection of milk samples for radiological analysis (Three Mile Island Nuclear Station)

TBE, TBE-2019 Radiostrontium analysis by ion exchange TOO RO rlnn of I

I IDC. "U=-xuzobomDosnlnoolsamoles B -7

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2005 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Milk Gamma Bi-weekly grab sample ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy when cows are on radiological analysis (Three Mile Island pasture. Monthly all Nuclear Station)

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

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

gamma spectroscopy Vegetation Strontium-89190 Annual grab sample ER-TMI-04 Collection of vegetation samples 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange for radiological analysis (Three Mile Island

_ uclear Station)

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

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

(containing 4 each CaSO4 elements)

B-8

Figure B-I Environmental Sampling Locations Within One Mile of the Three Mile Island Nuclear StatIon, 2005 B-9

191, I

16&75' Figure B-2 Environmental Sampling Locations Between One and Five Miles of the Three Mile Island Nuclear Station, 2005 B-10

~F LiL Figure B-3 Environmental Sampling Locations Greater than Five Miles of the Three Mile Island Nuclear Station, 2005 B-11

APPENDIX C DATA TABLES AND FIGURES -

PRIMARY LABORATORY

TABLE C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Ji -2 Q9-1 12128i04 - 02/01/05 02101,05 -03/01/05 03/01/05 - 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02/05 08/02/05 -08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 MEAN

< 192

< 188 33500 +/- 489 299 +/- 113

< 176

< 163

< 172 3510 +/- 418 6060 +/- 206 334 +/- 108

< 174

< 157 3744 +/- 19103

< 191

< 187

< 174 187 IF 110

< 176

< 164

< 171

< 183

< 172

< 164

< 172

< 156 175 +/- 21 C-1

TABLE C-1.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD A3-2 12128/04 - 02101/05 02101/05 - 03/01/05 03/01/05 - 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02105 08/02105 - 08/30/05 08/30/05 - 09/27/05 09127/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 MEAN

< 0.3

< 0.6

< 0.3

< 0.4

< 0.6

< 0.2

< 0.3

< 0.5

< 0.3

< 0.6

< 0.6 0.4

+/-

0.3 C-2

TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-14C La-140 I'ERIOD J1-2 12128/04 - 02/01/05

< 6

< 10

< 6 02/01/1)5 - 03/01/05

< 4

< 8

< 3 03/01/05 - 03/29/05

< 5

< 10

< 4 03/29/05 - 05/03/05

< 6

< 12

< 5 05/03/1)5 - 05/31/05

< 4

< 5

< 10

< 6 05/31/05 - 06/28/05

< 6

< 7

< 15

< 8 06/28/05 - 08/02/05

< 7

< 8

< 10

< 9 08/02/)5 - 08/30/05

< 5

< 4

< 10

< 5 08/30/()5 - 09/27/05

<6

< 5

< 14

< 6 09/271)5 - 11/01/05

< 4

< 5

< 10

< 4 11/01/05 - 11/30/05

< 5

< 12

< 5 11/30/(05 - 01/03/06

<6

< 13

<6

< 14

<6

<11

<5

<7

<9

<4

<6

<2

<4

<9

<4

<8

<4

<7

<11

<5

<9

<6

<11

<4

<8

<3

<5

<15

<7

<16

<5

<6

< 13

<8

< 12

<7

< 7

<10

<6

<8

<6

<6 c11

<6

<8

<6

<9

<6

<9

<4

<5

<13

<7

<9

<5

<7

<16

<7

<11

<8

<7

< 26

< 22

< 29

< 25

< 15

< 40

< 34

< 29

< 33

< 25

< 29

< 28

<9

<5

<6

<8

<5

<9

<8

< 12

< 10

<7

< 8

< 11 MEAN 5 + 2 5 +/- 2 11 +/- 4 5 +/- 3 12 +/- 5 6 +/- 3 10 +/- 5 5 +/- 3 6 +/- 2 28 +/- 12 8 +/- 4 Q9-1 12/28/014 - 02/01/05

<6

< 12

< 7 02/01/0(5 - 03/01/05

< 4

< 5

< 11

<6 03/01/(05 - 03/29/05

<6

< 13

<6 03/29/105 - 05/03/05

< 5

< 10

< 5 05/03/0(5 - 05/31/05

< 8

< 9

< 16

< 10 05/31/0(5 - 06/28/05

< 6

< 5

< 11

< 5 06/28/1(5 - 08/02/05

< 5

< 12

< 7 08/02/105 - 08/30/05

< 4

< 10

< 5 08/30/0(5 - 09/27/05

< 5

< 11

< 5 09/27/0(5 - 11/01/05

< 5

< 4

< 9

< 4 11/01/1(5 - 11/30/05

< 5

< 4

< 8

< 5 11/30/0(5 - 01/03/06

< 6

< 5

< 12

< 5

<12

<6

<8

<5

< 10

< 5

<9

<4

<17

<8

<9

<6

<11

<7

<9

<5

<12

<5

<10

<5

<11

<6

<14

<6

< 10

<5

< 8

<8

<5

<4

<8

<4

<6

<7

<4

< 14

< 8 c 8

<8

<5

<12

<5

<6

<7

<4

<5

<8

<5

<4

<8

<4

<5

< 10

<5

< 6

<9

<8

<6

< 25

< 23

< 32

< 21

< 37

< 25

< 31

< 27

< 28

< 24

< 22

< 28

<8

<7

<8

< 11

<9

< 10

<8

<6

<9

<8

<9 MEAN 5 +/- 2 5 +/- 2 11 +/- 4 6 +/- 3 11 +/- 5 6 +/- 2 9 + 4 5 +/-2 6 t3 27 9 9 8 +/- 3 C-3

TABLE C-11.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/28/04 - 02/01/05 02/01105 -03/01/05 03/01/05 - 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 -.08/02/05 08/02/05 -08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 MEAN G15-2 G15-3 09-1 2.6 +/- 1.3 2.2 +/- 1.4 3.8 +/- 1.4 2.3 +/- 1.3

< 2.3 3.3 +/- 1.6 4.4 +/- 1.7 4.3 +/- 1.7 2.9 +/- 1.5 5.4 +/- 1.6 4.6 +/- 1.6 4.5 +/- 1.6 3.5 +/- 2.2 2.6 +/- 1.3 2.2 +/- 1.4 2.6 +/- 1.3 4.4 +/- 1.4

< 2.4 2.8 +/- 1.6 3.5 +/- 1.7 3.3 +/- 1.7 3.4 +/- 1.6 4.0 +/- 1.5

< 2.0 3.1 +/- 1.5 3.0 +/- 1.4

< 1.7 2.0 +/- 1.4 2.8 +/- 1.3 2.6 +/- 1.3

< 2.3

< 2.3 2.9 +/- 1.6 4.3 +/- 1.7 2.5 +/- 1.5 3.3 +/- 1.4 2.0 +/- 1.4 2.3 +/- 1.4 2.6 +/- 1.4 TABLE C-11.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/28/04 - 02101/05 02/01/05 - 03/01/05 03/01/05 - 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02/05 08/02/05 - 08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 -01/03/06 MEAN G15-2 G15-3 09-1

< 0.2

< 0.4

< 0.7

< 0.4

< 0.3

< 0.6

< 0.4

< 0.5

< 0.3

< 0.6 0.4 +/- 0.3

< 0.3

< 0.5

< 0.6

< 0.3

< 0.4

< 0.6

< 0.9

< 0.6

< 0.8

< 0.4

< 0.6 0.5 +/- 0.4

< 0.3

< 0.5

< 0.6

< 0.4

< 0.5

< 0.8

< 0.5

< 0.2

< 0.5

< 0.3

< 0.6 0.4 +/- 0.3 TABLE C-11.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD G15-2 G15-3 09-1 12/28/04 - U0/U0/U0 02/01/05 - 03/01/05 03/01/05 - 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02/05 08/02/05 - 08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 MEAN

< 186

< 175

< 171

< 174

< 163

< 156

< 179 355 +/- 114 251 +/- 106

< 172

< 153 194 +/- 113

' 1d

< 187 500 +/- 119

< 193

< 174

< 164

< 174 360 +/- 119 601 +/- 120 568 +/- 112

< 172

< 154 286 +/- 346

' 187

< 183 263 +/- 103 179 +/- 109

< 174

< 159

< 179

< 176

< 172

< 161

< 172

< 154 180 +/- 56 C-4

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED iri THEi ViuiriY UtF lTHREE MiLE ISLANU NUCLEAR C-IAT ION, 20UU55 RESULTS IN UNITS OF PCVILITER +/- 2 SIGMA STC COLLECTION PERIOD G15-2 12/28/04

- 02/01105 02/01/05 - 03/01/05 03/01/05

- 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02/05 08/02/05 - 08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05

- 01/03/06 Mn-54 Co-58 Fe-59 Co-60 Zn-65 NB-95 ZR-95 Cs-1 34 Cs-137 Ba-140 La-140

< 5

< 6

< 10

< 5

< 4

< 9

< 3

< 4

< 11

< 5

< 6

< 9

< 7

< 13

< 9

< 11

< 6

< 4

< 12

< 4

< 10

< 6

< 7

< 14

< 7

< 8

< 3

< 8

< 3

< 8

< b

< 4

< 6

< 4

< 8

< 10

< 6

< 5

< 10

< 5

< 9

< 17

< 21

< 13

< 8

< 12

< 14

< 6

< 9

< 6

< 9

< 5

< 7

< 5

< 7

< 5

< 8

< 9

< 12

< 6

< 13

< 6

< 9

< 5

< 7

< 6

< 11

< 6

< 11

< 4

< 7

< 4

< 7

< 5

< 5<1

< 4

< 5

< 22

< 4

< 5

< 28

< 4

< 6

< 24

< 7

< 8

< 41

< 6

< 8

'<40

< 6

< 33

< 4

< 5

< 25

< 5

< 7

< 27

< 5

< 6

< 31

< 3

< 4

< 18

< 3

< 4

< 17

< 7

< 4

< 8

< 9

< 10

< 12

< 8

< 10

< 8

< 5 C) cn MEAN 5+/-i4 5 +/-3 10 +/-4 6 +/-3 11 +/-9 6 +/-2 9 +/-4 5 +/-2 6 +/-3 27 +/-16 8+/-

4 G15-3 12/28/04 02/01/05 03/01/05 03/29/05 05/03/05 05/31/05 06/28/05 08/02/05 08/30/05 09/27/05 11/01/05 11/30/05

- 02/01/05

- 03/01/05

- 03/29/05

- 05/03/05

- 05/31/05

- 06/28/05

- 08/02/05

- 08/30/05

- 09/27/05

- 11/01/05

- 11/30/05

- 01/03/06

< 3

< 2

< 6

< 4

< 3

< 7

< 6

< 14

< 4

< 5

< 11

< 5

< 6

< 10

< 3

< 4

< 8

< 5

< 10

< 3

< 4

< 10

< 5

< 4

< 10

< 4

< 12

< 5

< 4

< 10

< 4

< 5

< 10

< 5

< 7

< 5

< 6

< 7

< 15

< 4

< 10

< 5

< 9

< 5

< 6

< 9

< 4

< 8

< 4

< 11

< 4

< 8

< 5

< 9

< 5

< 9

< 3

< 6

<4.

< 5

< 7

< 15

< 5

< 9

< 6

< 10

< 3

< 7

< 13

< 5

< 8

< 4

< 8

< 5

< 6

< 5

< 7

< 5

< 7

< 3

< 4

< 15

< 3

< 4

< 19

< 6

< 8

< 41

< 4

< 6

< 24

< 5

< 6

< 23

< 4

< 5

< 18

< 5

< 25

< 4

< 21

< 4

< 23

< 4

< 5

< 22

< 4

< 5

< 24

< 4

< 21

< 3

< 6

< 13

< 7

< 8

< 6

< 9

< 5

< 8

< 7 MEAN 4 +/-2 4 +/-2 10 +/-4 5 +/-2 9 +/-5 5 +/-3 8 +/-6 4 +/-2 5 +/-3 23 +/-13 8 +/-5

TABLE C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 09-1 12128/04 - 02101/05 02101105 - 03/01/05 03/01/05 - 03/29/05 03/29105 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02/05 08/02/05 - 08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137.

I Ba-140 La-140

<5

<3

<10

<3

<4

<9

<4

<6

< 13

<4

<8

<5

<6

<5

<10

<4

<5

<13

<3

<6

<3

<4

<8

<4

<3

<7

<4

<9

<3

<4

<6

<7

<5

<8

< 5

< 12

<4

<9

<7

<9

< 7

< 13

< 7

< 10

<3

<6

<4

<6

<9

<3

<7

<4

<7

<4

<8

<4

<5

<19

<5

<9

<6

<8

<4

<7

<5

<10

<8

<11

<6

<9

<3

<5

<6

<4

<6

<4

<7

<3

<7

<4

<22

<5

<30

<4

<20

<4

<6

<25

<6

<7

<27

<4

<6

<25

<3

< 19

<4

< 18

<3

<4

<18

<3

<5

<20

<3

<4

<20

< 5

< 10

< 12

<6

<7

<9

<4

<8

<6

<5

<6 7 +/- 5 C)

MEAN 4 i 2 4 +/- 2 9 +/- 5 5 +/- 3 8 +/- 4 5 +/- 3 8 +/- 4 4 +/- 2 5 +/- 2 22 +/- 8

TABLE C-111.1 CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION Kl -1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Gross Beta 1-131 H-3 Sr-89 Sr-90 1 2/28W/U4 02/11/05 03/11105 03/E 9/05 05/C3/05 05/.1/05 06/2 8/05 08/C2/05 08/20/05 09/27/05 11/C1/05 11/20/05 u02u1/0u 03/01/05 03/29/05 05/03/05 05/31/05 06/28/05 08/02/05 08/30/05 09/27/05 11/01/05 11/30/05 01/03/06 Z.4 +/- i.3 2.6 +/- 1.5 3.3 +/- 1.4 9.9 +/- 1.9

<2.6 5.9 +/- 2.0 7.2 +/- 2.0 8.2 +/- 2.2 7.6 +/- 2.0 7.7 +/- 1.8 3.9 +/- 1.5 3.1 +/- 1.5

< U.5)

< 0.6

< 0.9

< 0.3

< 0.6

< 0.5 1.3 +/- 0.6

< 0.9

< 0.4

< 0.5

< 0.3

< 192

< 187 157000 182 175 218

< 174 43700 48500 5240

< 162

< 158

+/- 1590

+/- 111

+/- 108

+/- 105

< 2.3

+/- 1170

+/- 510

+/- 207

< 0.6

< 1.5 MEAN 5.6 +/- 5.4 0.6

+/- 0.6 23248 +/- 95903.

1.9

+/- 1.2 0.6 +/- 0.1 C-7

TABLE C-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTEC IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD K1-1 12/28104 -

02101/05 02/01/05 -03/01105 03/01/05 -

03129/05 03/29/05 -05/03/05 05/03/05 - 05/31/05 05/31/05 -

06128105 06/28105 - 08/02/05 08/02/05 - 08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 0

11/01/05 - 11/30/05 11/30/05 - 01/03/06 Mn-54 Co-58 Fe-59 Ca-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140

< 6

< 4

< 9

< 4

< 10

< 5

< 10

< 4

< 6

< 20

< 4

< 5

< 11

< 5

< 9

< 4

< 8

< 6

< 4

< 8

< 5

< 11

< 5

< 10

< 4

< 8

< 4

< 3

< 9

< 4

< 8

< 4

< 3

< 7

< 3

< 6

< 5

< 10

< 4

< 7

< 4

< 10

< 4

< 9

< 5

< 11

< 6

< 11

< 4

< 7

< 3

< 8

< 4

< 6

< 4

< 8

< 4

< 8

< 5

< 8

< 5

< 7

< 5

< 7

< 5

< 8

< 7

< 12

< 6

< 8

< 5

< 8

< 4

< 8

< 5

< 6

< 4

< 7

< 4

< 6

< 4

< 22

< 3

< 4

< 27

< 4

< 5

< 20

< 5

< 4

< 21

< 5

< 6

< 28

< 4

< 5

< 29

< 4

< 5

< 23

< 4

< 5

< 21

< 4

< 5

< 25

< 4

< 21

< 3

< 17

< 7

< 9

< 6

< 10

< 8

< 5

< 7

< 5

< 6 MEAN 5 +/-2 4 +/-1 9 +/-3 4 +/-1 9 +/-3 5 +/-2 8 +/-3 4 +/-1 5 +/-2 23 +/-8 7+/-

3

TABLE C-IV.1 CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED iNI THE viCiNi I Y IF THEE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD EDCB 02/01/05 - 03/29/05 05/03/05 - 06/28/05 08/02105 - 09/27/05 11/01/05 - 01/03106 H-3 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 282+/- 113

<5 393 +/- 109

< 4 304 +/- 116

< 3

<167

<3

<11

<6

<11

<4

<6

<4

<5

<19

<6

<9

<7

<9

<5

<9

<4

<7

<24

<4

<7

<5

<7

<4

<8

<4

< 16

<3

<6

<3

<8

<3

<7

<3

<17

<6

<4

<6

< 5 MEAN 264 +/- 279 4 +/- 1 4+/-3 8 +/- 4 5+/-3 9 +/- 4 4 +/-1 7+/-2 4 +/-1 5 +/- 3 19 +/- 7 5 +/- 2 C) cb

TABLE C-V.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STATION CODE 48S GP-1 GP-6 GP-8 GP-9 MS-22 OSF OS-18 03/10/05

< 188 (1) 471 +/- 118 836 +/- 127 655 +/- 124 1620 +/- 149 263 +/- 122 539 +/- 120 06/09/05

< 177 (1) 323 +/- 114 269 +/- 113 (1) 837 +/- 122 584 +/- 119 1400 + 131 09/08/05

< 173 (1)

< 113 (1) 912 +/- 128 351 +/- 115 345 +/- 112 12/08/05 225 +/- 109 (1)

MEAN 191 +/- 47

< 160 503 +/- 115 479 +/- 114 636 +/- 116 302 +/- 111 256 +/- 105 318 +/- 311 430 +/- 629 567 +/- 249 1001 +/- 857 375 +/- 288 635 +/- 1047 GP-12 MS-2 MS-5 MS-8 MS-20 NW-A NW-B NW-C NW-CW OS-14 RW-1 RW-2 212 +/- 111

< 164 218 +/- 113 271 +/- 112 597 +/- 116 1790 +/- 138 (1) 244 +/- 108 284 +/- 113

< 178

< 178 251 +/- 122 1380 +/- 141 1460 +/- 142 4160 +/- 192 1490 +/- 147 169 +/- 102

< 159 725 +/- 117 228 +/- 45 224 +/- 170 198 +/- 57 225 +/- 132 424 +/- 489 1585 +/- 580 3935 +/- 636 1560 +/- 198 187 +/- 49 191 +/- 89 9613 +/- 25138 3710 1630 204 222 18500

+/- 164

+/- 135

+/- 111

+/- 113

+/- 304 E1-2 MS-1 MS-4 MS-7 MS-19 MS-21 N2-1

< 103 249 +/- 113 581 +/- 118

< 168

' 174 264 +/- 112 189 +/- 111 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 0

TABLE C-V.2 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA 0

STC COLLECTION Sr-90 PERIOD 48S 03/10/05

< 0.3 06/09/05 09/08/05 12/08/05 MEAN OSF 03/10/05

< 0.4 06/09/05 09/08/05 12/08/05 MEAN E1-2 06/09/05 MS-2 06/10/05

< 0.3 MS-5 06/10/05

< 0.4 MS-8 06/10/05

< 0.3 MS-20 06/10/05 MS-22 03/10/05 N2-1 06/09/05 OS-14 06/10/05

< 0.4 RW-1 06/10/05 Mn-54

<5

<4

<3

< 3 4 +/-2

<8

<6

<2

<6 5 +/-5

<5

<1

< 7

<1

<1 Co-58

<4

<5

<3

< 5 4 +/- 1

<6

<7

<2

<6 5 +/- 4

<5

<2

<7

<2

<1 Fe-59

<9

<10

<7

<8 8+/-3

<18

<13

<4

< 14 12 +/- #

<11

<4

<5

<4

<5

< 14

<5

<4 Co-60

<7

<6

<3

< 7 6 +/-4

<9

<5

<2

<6 6 +/-6

<5

<1

<2

<7

<1

<1 Zn-65

<7

<9

<7

<8 8+/- 2

<12

< 13

<4

<15 11

+/- 9

< 10

<3

<4

<3

<13

<4

<2 Nb-95

<3

<6

<4

< 4 4 +/- 2

< 11

<6

<3

< 10 7 +/- 8

<5

<2

<7

<2

<1 g<

<8

<6

<7 7 +/-3

< 14

< 10

<4

< 11 10 +/- 8

< 10

<3

<4

< 14

<4

<3

<5

< 4

<3

< 3 4 +/- 1

<8

<5

<2

<5 5 +/- 5

<4

<1

<2

<1

<2

<7

<2

<1

<5

<3

< 4 4 +/- 1

<8

<7

<2

<6 6 +/-5

<4

<1

<7

<1

<20

< 26

< 18

<21 21 +/- 7

<46

<36

< 11

<27 30 +/- #

< 29

<39

<45

< 42

< 40

< 44

.< 43

< 43

< 35

<7

<10

<5

<7 7 +/-4

< 12

<12

<3

< 10 9 +/-8

<8

< 13

< 14

< 15

< 12

< 15

< 12 Zr-95 Cs-134 Cs-137 Ba-140 La-140 RW-2 06/10/05

<1

<2

<5

<1

<3

<2

<3

<2

<1

<43

<14

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

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD INDP.

PREDATOR 06/14/05 10/17/05 MEAN INDB BOTTOM FEEDER 06/14/05 10/17/05 MEAN BKGP PREDATOR 06/14/05 10/20/05 MEAN Sr-89 Sr-90

< 19

< 16 18 +/- 5

< 15

< 21 18 +/- 9

< 17

< 19 18 +/- 3

<5

< 4 4 +/- 1

<2

< 3 2 +/-1

<3

< 2 3 +/- 1 BKGB BOTTOM FEEDER 06/14/05 10/20/05 MEAN

< 16

< 20 18 +/- 5

<4

< 4 4 +/-0 C-1 2

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

SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 INDP PREDATOR 06/14 - 06/20/05 10/17 - 10/26/05 MEAN INDB BOTTOM FEEDER 06/14 - 06/14/05 10/17 - 10/17/05 2890 +/- 1110

<55

< 63

< 99

< 55

< 123

< 63 3080 +/- 642

< 20

< 14

< 51

< 38

< 56

< 23 2985 +/- 269 38 +/- 49 38 +/- 69 75 +/- 67 46 +/- 25 89

+/- 95 43 +/- 57 2400 +/- 633

< 28

< 29

< 68

< 27

< 73

< 33 3450 +/- 761

<42

<48

< 72

< 44

< 89

< 41

< 60

< 28 44 +/- 47

< 36

< 48 MEAN 2925 +/- 1485 35 +/- 21 39 +/- 26 70 +/- 7 35 +/- 24 81

+/-

22 37 +/- 11 42 +/- 17 0

C.,

BKGP PREDATOR 06/14 - 06/14/05 10/20 - 10/20105 3260 +/- 641

< 21 4020 +/- 797

< 38

< 24

< 41

< 45

< 112

< 29

< 48

< 52

< 97

< 23

< 38

< 24

< 39 MEAN 3640 +/- 1075 30 +/- 24 33 +/- 24 78

+/- 95 39 +/- 27 74

+/- 63 30 +/- 20 32 +/- 22 BKGB BOTTOM FEEDER 06/14 - 06/14/05 10/20 - 10120/05 2350 +/- 545

< 26 2290 +/- 789

< 35

. <15

< 28

< 39

< 83

< 35

< 33

< 34

< 74

< 21

< 30

< 24

< 41 MEAN 2320 +/- 85 31 +/- 12 22 +/-

18 61

+/- 62 34 +/- 3 54

+/-

56 26 +/- 13 32 +/- 24

TABLE C-V11.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA K-40 STC COLLECTION PERIOD A1-3 06/08/05 10/17105 MEAN Mn-54 Co-58 Co-60 Cs-1 34 Cs-137 8710 +/- 753 7720 +/- 905 8215 +/- 1400 16300 +/- 1350 12000 +/- 1440 14150 +/- 6081

< 41

< 31 36 +/- 14

<45

< 60 53 +/- 21

< 38

< 27 33

+/- 16

< 46

< 56 51

+/- 14

< 35

< 43 39

+/-

11

< 34

< 55 44

+/-

30

< 32

< 31 32 +/- 1

< 36

< 60 48 +/- 33 42 +/- 33

< 41 42 +/- 2 160 +/- 48 118 +/- 97 139 +/- 59 J2-1 06/08/05 10/17/05 MEAN K1-3 06/08/05 10/17/05 MEAN 8250 +/- 959 8200 t 937 8225 t 71

< 36

< 49 42

+/- 20

< 41

< 42 42 +/- 2

< 85

< 43

< 42 43

+/-

1

< 112

< 33

< 44 39 +/- 16

< 80 139 +/- 57 98

+/- 61 119 +/- 58 294 +/- 103 EDCB 10/17/05

<4470

< 95 C-14

TABLE C-Vl1.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I I

GROUP 11 I GROUP III I

COLLECTION PERIOD 12V29/04 - 01105/05 01/0511)5 - 01/12105 01/12/)5 - 01/19/05 01/19/05 - 01126/05 01/26/05 - 0210205 02/02/05 - 02109/05 02109/1)5 - 02116/05 02/16/1)5 - 02123/05 02/23/1)5 - 03/0205 03/021)5 - 03/09/05 03/09/I)5 - 03/16/05 03/16/1)5 - 03/23/05 03123/1)5 - 03/30/05 03/30/05 - 04/06/05 04/06/A)5 - 04/13/05 04/13/0)5 - 04/20/05 04/20/0)5 - 04/27/05 04127/1)5 - 05/04/05 05/04/1)5 - 05/11/05 05/11/0)5 - 05/18/05 05/18/0)5 - 05/25/05 05/25/0)5 - 06/01/05 06/01/1)5 - 06/08/05 06/081)5 - 06/15/05 06/15/0)5 - 06/22/05 06122/1)5 - 06/29/05 06/29/105 - 07/06/05 07/06/0)5 - 07/13/05 07/13/1)5 - 07/20/05 07/20/A)5 - 07/27/05 07127/1)5 - 08/0205 08/020)5 - 08/10/05 08/10/1)5 - 08/17/05 08/17/0)5 - 08/24/05 08/24/015 - 08/31/05 08/31/()5 - 09/07/05 09/07/A15 - 09/14/05 09/14/R5 - 09/21/05 09/21/()5 - 09/28/05 09/28/05 10/05/05 10/05/115 - 10/12105 10/12/(05 - 10/19/05 10/19/015 - 10/26/05 10/26/015 - 11/02105 11/02/015 -

11/09/05 11/09/05 - 11/16/05 11/16/(15 - 11/22105 11/22/105 - 11/30/05 11/30/105 - 12107/05 12107/015 - 1214/05 12/14105 - 12121/05 12121/015 - 1228/05 E1-2 F1-3 A3-1 G2-1 H3-1 M2-1 015-1 23+/-5 28+/-6 13+/-4 12+/-4 15+/-5 17+/-5 18+/-5 15+/-5 18+/-5 15+/-5 24+/-5 20+/-5 13+/-5 16+/-5 15+/-5 13+/-5 14+/-5 11+/-5 18+/-5 12+/-5 14+/-5 13+/-5 12+/-5 17+/-5

<7 8

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

5 13 +/- 5 16 +/- 5 9

4 13 +/- 5 12 +/- 5 22 +/- 5 14 +/- 5 26 +/- 5 19 +/- 5 28 +/- 5 32 +/- 6 25 +/- 8 13 t 5 20 +/- 5 31 +/- 6 16 +/- 7 25 +/- 6 25 +/- 5 9

4 14 +/- 5 12 +/- 4 20 +/- 5 31 +/- 6 17 +/- 5 23 +/- 6 9

4 20 +/- 5 28 +/- 5 22 +/- 5 32 +/- 6

<7

<7 14 +/- 5 17 +/- 5 7 4 11 +/- 5 17 +/- 5 12 +/- 5 10 +/- 4 13 +/- 5 14 +/- 5 15 +/- 5 11 +/- 4 16 +/- 5 13 +/- 5 17 +/- 5 11 +/- 5 22 +/- 5 20 +/- 5 29 +/- 5 29 +/- 5 21 +/- 5 12 +/- 5 18 +/- 5 30 +/- 6 19 +/- 5 24 +/- 5 23 +/- 5 9 4 16 +/- 5 15 +/-5 22 +/- 5 25 +/- 5 19 +/- 5 23 +/- 6 11 +/- 4 18 +/- 5 30 +/- 5 21 +/- 5 30 +/- 6 28 +/- 6 1 5 +/- 5 19 +/- 5 21 +/- 6 16 +/- 5 23 +/- 5 10 +/- 5 16 +/- 5 16 +/- 5 12 +/- 5 14 +/- 5 17 +/- 5

<7

<7 15 +/- 5 15 +/- 5 9+/-4 13 +/- 5 13 +/- 5 12 +/-5 9+/-4 8+/-5 15 +/- 5 14 +/- 5 8+/-4 19 +/- 5 20 +/-5 19 +/- 5 10 +/- 5 25 +/- 5 20 +/- 6 31 t 6 29 +/- 6 22 +/- 5 17 +/- 5 22 +/- 5 32 +/- 6 14 +/-5 21 +/- 5 23 +/- S 9+/-5 15 +/- 5 17 +/- 5 21 +/- 5 36 +/- 9 21 +/- 5 29 +/- 6 13 +/-4 18 +/- 5 29 +/- 6 21 +/- 5 32 +/- 6 32 +/- 6 11 +/- 4 20 +/- 5 14 +/- 5 22 +/- 5 25 +/- 5 13 +/- 5 13 +/- 5 17 +/- 5 16 +/- 5 13 +/- 5 15 +/- 5

< 11

< 7 15 +/- 5 17 +/- 5 10 +/- 5 14 +/- 5 14 +/- 5 13 +/- 5 12 +/- 5 9

5 11

+/- 5 20 +/- 6 11 +/- 5 22 +/- 6 13

+/- 5 20 +/- 5 12 +/- 5 21

+/- 5 24 +/- 6 30 +/- 6 23 +/- 5 25 +/- 6 11

+/-F 5 18

+/- 5 32 +/- 6 17 +/- 5 22 +/- 6 25 +/- 6 10 +/- 5 17 +/- 5 11 +/- 5 18 +/- 5 30 +/- 6 19 +/- 5 28 +/- 7 13 +/- 4 18 +/- 5 27 +/- 6 19 +/- 5 30 +/- 6 26 +/- 5 13 +/- 4 17 +/- 5 14 +/- 5 20 +/- 5 22 +/- 5 16 +/- 5 11 +/- 5 18 +/- 5 11 +/- 5 13 +/- 5 14 +/- 5

<7 14 +/- 5 13 +/- 5 15 +/- 5 8

4 17 +/- S 12 +/- 5 15 +/-.5 8

4 8

5 12 +/- 5 12 +/- 5 10 +/- 5 17 +/- 5 11 +/- 5 17 +/- 5 13 +/- 5 20 +/- 5 23 +/- 6 29 +/- 5 32 +/- 6 27 +/- 5 14

5 15 +/- 5 28 +/- 6 24 +/- 5 19 +/- 5 19 +/- 5

<6 12 +/- 4 12 +/- 4 21 +/- 5 23 +/- 5 17 +/-5 26 +/- 6 11 +/- 4 12 +/- 5 29 +/- 6 18 +/- 5 32 +/- 6 25 +/- 5 14 +/- 4 20 +/- 5 15 +5 20 +/-5 21 +/- 5 16 +/- 5 19 +/- 5 13 +/- 5 13 +/- 5 11 +/- 5 12 +/- 5

< 7

< 12 17 +/- 6 17 +5 7

4 20 +/- 5 20 +/- 5 13 +/- 5 10 +/- 5 10 +/- 5 15 +/-5 12 +/- 5 10 +/- 5 15 +/- 5 13 +/-5 18 +/- 5 9

5 21 +/- 5 20 +/- 6 37 +/- 8 28 +/-6 27 +/- 6 12 +/- 5 14 +/- 5 33 +/- 6 16 +/- 5 21 +/- 6 21 +/- 5

<7 18 +/- 5 14 +/- S 20 +/- 5 28 +/- 6 16 +/-5 25 +/- 6 10 +/- 4 16 +/- 5 29 +/-6 18 +/- 5 30 +/-6 33 +/- 6 13 +/-4 13 +/- 5 15 +/- 5 19 +/-5 23 +/-5 12 +/- 5 13 +/- 5 14 +/- 5 12 +/- 5 15 +/- 5 12 +/- 5

<7

<7 17 +/- 5 15 +/- 5 5

13 +/- 5 13 +/- 5 15 +/- 5 3 4 13 5

1

+/- 5 15 +/- 5 13 +/-4 13 +/- 5 15 +/-5 22 +/- 5

1) +/- 5 17 +/- 5 13 +/- 6 27 +/- 5 27 +/- 6 22 +/- 5 12 +/- 5 1.5 +/- 5 27 +/- 6 1.3 +/- 5 17 +/- 5 13 +/- 5 3 _ 5 25 +/- 5 23 +5 23 +/- 9 21 +/- 5 24 +/- 6 12 + 4 15 +/- 5 32 +/- 6 13 +/- 5 34 + 6 MEAN 17 t 14 17 +/- 12 18 +/-14 18

+/- 13 17 +/- 13 17 +/- 14 17 +/-13 C-15

TABLE C-VII.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS (E-3 PCI/CU METER) IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 GROUP I - SITE LOCATIONS GROUP II -OFFSITE LOCATIONS COLLECTION PERIOD 12/29/04 - 02/02/05 02/02/05 - 03/02/05 03/02/05 - 03/30/05 03/30/05 - 04/27/05 04/27/05 - 06/01/05 06/01/05 -06/29/05 06/29/05 - 08/02/05 08/02/05 - 08/31/05 08/31/05 - 09/28/05 09/28/05 - 11/02/05 11/02/05 - 11/30/05 11/30/05 - 12/28/05 12/29/04 - 1228/05 MIN.

MAX.

MEAN +/-

2 SD 12 28 17 +/- 10 11 24 16 +/- 9 7

18 1 3+/- 8 7

17 1 1+/- 8 7

17 12 +/- 6 9

16 13+/- 5 11 26 17 +/- 10 12 32 24 +/- 15 16 31 23 +/- 11 9

25 16 +/- 12 9

31 20 +/- 14 18 32 25 +/- 11 7

32 17+/-9 COLLECTION PERIOD 12/29/04 - 02/02/05 02/02/05 - 03/02/05 03/02/05 - 03/30/05 03/30/05 - 04/27/05 04/27/05 - 06/01/05 06/01/05 - 06/29/05 06/29/05 - 08/02/05 08/02/05 - 08/31/05 08/31/05 - 09/28/05 09/28/05 - 11/02/05 11/02/05 - 11/30/05 11/30/05 - 12/28/05 MIN. MAX.

MEAN +/-

2 SD GROUP III - CONTROL LOCATIONS COLLECTION MIN.

MAX.

MEAN +/-

PERIOD 2 SD 11 32 10 25 7

17 7

17 8

20 8

22 9

25 11 37 14 33 6

25 10 36 12 32 19 +/- 11 17 +/- 9 12 +/- 6 12 +/- 8 13 +/- 7 14 +/- 8 17 +/- 10 24 +/- 15 22 +/- 13 16 +/- 11 21 +/- 15 24 +/- 13 12/29/U4 02/02/05 03/02/05 03/30/05 04/27/05 06/01/05 06/29/05 08/02/05 08/31/05 09/28/05 11/02/05 11/30/05

- u2/u2/ub

- 03/02/05

-03/30/05

- 04/27/05

- 06/01/05

- 06/29/05

- 08/02/05

- 08/31/05

- 09/28/05

- 11/02/05

-11/30/05

- 12/28/05 13 33 20+/-15 12 23 16+/-9 7

16 12+/-7 6

17 11+/-11 9

18 13+/-7 10 19 14+/-9 10 22 17+/-9 12 27 22+/-14 15 27 19+/-10 9

20 16+/-8 12 28 21+/-14 16 34 25+/-19 C)

Cn 12/29/04 - 12/28/05 6

37 18 +/- 9 12/29/04 - 12/28/05 6

34 17 +/- 9

TABLE. C-VIII.3 CONCENTRATION OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTEE IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD A3-1 12/29 - 03/30/05 53 13

<1

< 1

<1

< 1 C3/30 -06/29/05 58 +/- 11

< 1

< 1 C6/29 - 09/28/05 88 29

< 2

< 3

<1

< 2

< 2 C9/28 - 1228/05 61 +/-18

< 2

< 3

< 2 MEAN 65 31 2

2 2 +/-3 2 +/-2 2

2 1

1 E1-2 12129 -03/30/05 63 13

<1

< 1

<1

<1 C3/30 -06/29/05 65 13

< 1

<1

<1 C6/29 -09/28/05 87 +/-28

< 1

< 3

< 2

< 1

< 2 C9/28 - 12/28/05 54 +/- 17

< 2

< 4

< 3

< 2 MEAN 67 28 1

1 2+/-2 2+/-2 1

2 1t1 F1-3 12/29 -03/30/05 69 12

<1

<1 03/30 -06/29/05 71 +/-12

<1

<1 06/29 -09/28/05 82 +/-29

< 2

< 1

<1 09/28-12/28/05 63 24

<3

< 3

< 3 MEAN 71 16 2 +/-2 2 +/-2 2 +/- 2 1 +/-2 1 +/-2 G2-1 12/29 -03/30/05 73+/- 12

<1

< 1

< 1 03/30 -06/29/05 62 +/-13

<1

< 1

< 1 06/29 -09/28/05 67+/-3 1

< 2

< 3

< 2

< 1

<2 09/28 - 12/28/05 73 +/- 24

< 3

< 4

< 3

< 4

<3 MEAN 69 10 2 +/-2 2 +/-3 2+/-2 1

3 2

3 H3-1 12/29 -03/30/05 64 +/-13

<1

< 1

<1

<1 03/30 -06/29/05 70 13

<1

< 1

<1

< 1

< 1 06/29 - 09/28/05 70 +/- 36

< 2

< 4

< 2

< 2 09/28 - 12/28/05 60 22

< 3

<3

< 3

< 3 MEAN 66 10 2 +/- 2 2 +/-3 2+/-2 2

2 2

2 M2-1 12/29 -03/30/05 77 12

< 1

<1

<1 03/30 -06/29/05 59 +/-18

< 1

<1

<1 06/29 -09/28/05

< 21

< 2

< 3

<1

<2

<1 09/28 - 12/28/05 60 +/- 19

< 2

<3

<2

<3

< 2 MEAN 54 47 1

1 2+/-2 1+/-1 2

2 1+/-1 Q15-1 12/29 -03/30/05 65 +/-16

<1

<1 03/30 -06/29/05 67 +/-15

< 1

<1

<1 06/29 - 09/28/05 96 +/- 29

<2

< 3

<2

<2 09/28 - 12/28/05 54+/-25

< 3

<3

<2 MEAN 70+/-35 2 +/- 1 2 +/- 2 2 +/- 2 2 +/- 2 2+/-1 C-17

TABLE C-IX.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I l

GROUP II l

GROUP III COLLECTION E1-2 F1-3 A3-1 G2-1 H3-1 M2-1 Q15-1 PERIOD 12/29/04 - 01/05/05

< 20

< 27

< 21

< 27

< 26 01/05/05 -01/12/05

< 14

<7

< 13 01/12/05 -01/19/05

< 23

< 21

< 24

< 23

< 21

< 21 01/19/05 -01/26/05

< 23

< 20

< 24

< 23

< 19

< 19 01/26/05 -02/02/05

< 22

< 21

< 22

< 21

< 21 02/02/05 - 02/09/05

< 22

< 20

< 22

< 21

< 20

< 20 02/09/05 - 02/16/05

< 20

< 21

< 20

< 21

< 21 02/16105 -02/23/05

< 16

< 15

< 12

< 16

< 12

< 12 02123105 - 03/02105

< 24

< 22

< 25

< 24

< 22

< 22 03102105 -03/09105

< 21

< 15

< 22

< 15

< 14 03/09/05 -03/16/05

< 21

< 20

< 17

< 21

< 17

< 17 03/16/05 -03/23/05

< 18

< 21

< 19

< 18

< 21

< 20 03/23/05 -03/30/05

< 24

< 17

< 25

< 17

< 17 03/30/05 -04/06/05

< 19

< 14

<19

< 19

< 17

< 14 04/06/05 -04/13/05

< 18

< 17

< 18

< 20

< 17 04/13/05 - 04/20/05

< 11

< 15

< 12

< 11

< 15

< 14 04/20/05 - 04/27/05

< 22

< 24

< 22

< 25

< 24 04127/05 - 05/04/05

< 27

< 21

< 28

< 21

< 21 05/04/05 -05/11/05

<19

< 19

< 20

< 19

< 19 05/11/05 -05/18/05

< 17

< 20

< 17

< 20

< 20 05/18/05 - 05/25/05

< 26

< 27

< 22

< 22 05/25/05 -06/01/05

< 17

< 16

< 20

< 17

< 20

< 19 06101/05 - 06/08/05

< 20

< 21

< 20

< 21

< 21 06/08/05 -06/15/05

< 27

< 28

< 27

< 27 06/15/05 -06/22/05

< 29

< 27

< 30

< 29

< 27

< 26 06/22/05 -06/29/05

< 22

< 21

< 22

< 21

< 20 06/29/05 -07/06/05

< 16

< 17

< 16

< 17

< 17 07/06105 - 07/13/05

< 24

< 22

< 25

< 22

< 22 07/13/05 -07/20/05

< 24

< 30

< 25

< 24

< 30

< 30 07/20/05 -07/27/05

< 16

< 18

< 17

<16

< 17 07/27/05 - 08102/05

< 20

< 25

< 21

< 25

< 26 08/02/05 -08/10/05

< 18

< 20

<19

< 19

< 20

< 20 08/10/05 -08/17/05

< 25

< 24

< 19

< 26

< 19

< 19 08/17/05 - 08/24/05

< 26

< 22

< 28

< 24

< 22

< 28

< 29 08/24/05 -08/31/05

< 18

' 18

< 30

< 19

< 30

< 31 08/31/05 -09/07/05

< 16

< 17

< 16

< 17

< 17 09107/05 - 09114/05

< 26

< 25

< 32

< 27

< 26

< 32

< 32 09/14/05 -09/21/05

< 20

< 16

< 12

< 18

< 17

< 12

<12 09/21/05 -09128/05

< 26

< 24

< 18

< 26

< 25

< 18

< 19 09/28/05 - 10/05/05

< 57

< 56

< 48

< 60

< 56

< 50

< 50 10/05105 - 10/12/05

< 24

< 23

< 27

< 26

< 14

< 27 10/12/05 - 10/19/05

< 24

< 28

< 26

< 24

< 28

< 28 10/19/05 - 10126/05

< 20

< 19

< 21

< 13

< 21

< 19 10/26/05 - 11/02/05

< 25

< 24

< 43

< 26

< 25

< 44

< 44 11/02/05 - 11/09105

< 28

< 27

< 46

< 30

< 28

< 47 11/09/05 - 11/16/05

< 21

< 20

< 27

< 22

< 26

< 27

< 18 11/16/05 - 11/22/05

< 32

< 31

< 38

< 34

< 37

< 38

< 39 11/22/05 - 11/30/05

< 16

< 15

< 29

< 16

< 27

< 28

< 28 11/30/05 - 12/07/05

< 20

< 19

< 25

< 16

< 20

< 26

< 26 12/07/05 - 12/14/05

< 25

< 33

< 27

< 25

< 33

< 34 12/14/05 - 12/21/05

< 17

< 26

< 18

< 17

< 26

< 26 12/21/05 - 12/28/05

< 25

< 24

< 27

< 31

< 32

< 32 MEAN 22 + 13 22 +/- 13 23 +/- 16 23 +/- 14 22 +/- 14 23 +/- 15 23 +/- 17 C-18

TA13LE C-X.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM I K15-3 INDICATOR FARMS E2-2 F4-1 m

CDLLECTION PERIOD 01/05/05 02/02/05 03/02/05 03/16/05 03/30/05 04/13/05 04/27/05 05/11/05 05/25/05 06/08/05 06/22/05 07/06/05 07/20/05 08/03/05 08/17/05 08/31/05 09/14/05 09/28/05 10/12/05 10/26/05 11/09/05 11/22/05 12/07/05 MEAN D2-1 G2-1

< 0.9

< 0.5

< 0.4

< 0.5

< 1.0

< 0.3

< 0.7

< 0.3

< 0.5

< 0.7

< 0.3

< 0.7

< 0.6

< 0.4

< 0.3

< 0.7

< 0.6

< 0.9

< 0.6

< 0.4

< 0.4 0.5

+/-

0.4

< 0.5

< 0.2

< 0.3

< 0.2

< 0.7

< 0.2

< 0.3

< 0.2

< 0.6

< 0.4

< 0.3

< 0.9

< 0.4

< 0.8

< 0.4

< 0.5

< 0.3

< 0.5 0.4

+/-

0.4

< 0.8

< 0.2

< 0.3

< 0.4

< 0.5

< 0.8

< 0.3

< 0.6

< 0.4

< 0.2

< 0.9

< 0.6

< 0.3

< 1.0

< 0.6

< 0.4

< 0.6

< 0.8

< 0.3

< 0.5

< 0.3 0.5

+/-

0.4

< 0.4

< 0.3

< 0.6

< 0.3 0.4

+/-

0.3

< 0.7

< 0.2

< 0.4

< 0.3

< 0.6

< 0.3

< 0.6

< 0.3

< 0.2

< 0.7

< 0.6

< 0.4

< 0.9

< 0.4

< 0.8

< 0.7

< 0.3

< 0.4

< 0.3 0.5

+/-

0.4 C-19

TABLE C-X.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/05/05 - 03/30/05 04113/05 - 06/22/05 07/06/05 - 09/28/05 10/12/05 - 12/07/05 CONTROL FARM I

K15-3 Sr489 Sr-90

' 1.6

'c 0.3

' 0.9 0.6 +/- 0.1

< 3.4 0.7 +/- 0.3

< 2.4 0.5 +/- 0.2

<9 D2-1 Sr-89 Sr-90 Sr-89

' 1.3 0.6 +/- 0.2

' 1.3

1.0 1.0 +/- 0.2

< 0.9 c 3.7 0.9 +/- 0.3

' 4.2 c 2.2 0.7 +/- 0.2

< 3.3 E2-2 Sr-90 Sr-89 0.4 t 0.2

'2.6 0.8 t 0.1

< 1.3 0.9 +/- 0.3

' 2.8 1.0 +/- 0.4

< 2.3 INDICATOR FARMS F4-1

-Sr-90 Sr-89 1.4 +/- 0.5

' 1.6 0.4 t 0.2

< 1.0 2.5 +/- 0.9

' 2.9

< 0.6

< 2.3 G2-1 Sr-90 0.3 t 0.2 0.7 +/- 0.3 0.6 +/- 0.2 0.5 +/- 0.3 MEAN 2.0 t 2.2 0.6 t 0.4 2.0 t 2.4 0.8 t 0.4 2.4 t 3.2 0.8 t 0.5 2.2 i 1.3 1.2 +/- 1.9 1.9 t 1.7 0.5 +/- 0.3 C-20

TABI.E C-X.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD 02-1 01/05/05 1430 +/- 118

<4

< 4 c 18

< 5 02/02105 1330 +/-156

<6

< 6

< 30

<9 03/02/05 1250 +/-119

<4

< 5

< 20

< 6 03/16/05 1380 +/-160

< 6

< 7

< 26

< 9 03/30/05 1340 +/-173

< 7

< 8

< 30

< 9 04113/05 1220 +/-150

< 4

< 5

< 19

< 7 04/27105 1350 +/- 141

< 5

< 6

< 26

< 8 05/11/05 1280 +/-134

< 5

< 22

< 6 05/25/05 1190 +/- 179

< 8

< 11

<40

< 15 06/08/05 1170 +/-166

< 4

< 5

< 24

<6 06/22/05 1220 +/- 218

< 8

< 11

< 42

<11 07/06/05 1100 +/-182

< 5

< 8

< 31

< 8 07/20/05 1230 +/-128

< 4

< 5

< 25

< 8 08/03/05 1310 +/-164

< 7

< 6

< 24

< 8 08/17/05 1310 +/-143

< 5

< 7

< 24

< 7 08/31/05 1550 +/- 157

< 6

< 7

< 27

<10 09/14105 1210 +/- 236

< 11

< 13

< 41

< 12 09/28/05 1320 +155

< 4

< 3

< 19

<6 10/12105 1290 +/-148

< 4

< 20

<5 10/26/05 1200 +/- 144

< 4

< 19

<5 11/09/05 1220 +/-157

< 6

< 8

< 29

< 9 11/22/05 1340 +/-139

< 3

< 4

< 18

<5 12/07/05.

1290 +/- 223

< 5

< 6

< 23

<6 MEAN 1284 +/- 191 5 +/- 4 6 +/- 5 26 +/- 14 8 +/-5 E2-2 01/05/05 1330 +/- 131

< 5

< 20

< 5 02/02/05 1250 +/-113

< 4

< 6

< 22

< 6 03/02/05 1300 +/-131

< 4

< 20

< 6 03/16/05 1420 +/-194

< 5

< 8

<24

< 7 03/30/05 1230 +/-164

< 4

< 6

<25

<9 04/13/05 1290 +/- 178

< 7

< 8

< 32

< 11 04/27/05 1290 +/- 45

< 1

< 2

< 7

< 2 05/11/05 1230 +/- 149

< 5

< 7

< 23

<8 05/25/05 1340 +/-172

< 6

< 8

< 30

<9 06/08/05 1420 +/-161

< 7

< 30

< 9 06/22/05 1310 +/-192

< 7

< 9

< 33

<13 07/06/05 1340 +/-140

< 5

< 6

< 27

< 7 07/20/05 1140 +/-140

< 4

< 14

< 7 08/03/05 1160 +/-204

< 5

< 23

<7 08/17/05 1450 +/- 165

< 4

< 7

< 20

< 4 08/31/05 1390 +/-145

< 6

< 26

<8 09/14/05 1430 +/-256

< 11

< 45

<8 09/28/05 1200 +/-161

< 6

< 8

< 31

<8 10/12/05 1230 +/-159

< 7

< 34

<10 10/26/05 1390 +/-145

< 6

< 8

< 27

< 6 11/09/05 1170 +/-147

< 4

< 21

< 4 11/22/05 1300 +/-123

< 5

< 24

<8 12/07/05 1220 +/-225

< 7

< 10

< 43

<9 MEAN 1297 +183 5 + 4 6 +/- 4 26 +/- 17 7 +/- 5 C-21

TABLE C-X.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD F4-1 03/30/05 1380 + 193

< 8

< 10

< 38

< 10 06/22/05 1400 +/-210

< 7

< 9

<30

<11 09/28/05 1450 152

< 5

< 7

< 26

< 6 12/07/05 1360 200

<8

< 9

<35

<13 MEAN 1398 +/- 77 7 +/- 2 8 +/- 3 32 +/- 11 10 +/- 6 G2-1 01/05/05 1350 +/- 124

<4

<5

< 23

< 7 02/02/05 1220 147

< 6

< 7

< 32

< 10 03/02/05 1200 106

<5

< 5

< 22

<8 03/16/05 1120 +/- 216

< 8

< 9

< 38

< 11 03/30/05 1390 +/- 139

< 5

< 6

< 25

< 7 04/13/05 1400 +/- 153

< 5

< 7

< 21

< 7 04/27/05 1300 +/- 134

< 4

< 6

< 23

<6 05/11/05 976 +/- 141

< 5

< 25

< 5 05/25/05 1130 +/- 139

< 5

< 7

< 31

< 11 06/08/05 1040 +/- 171

< 6

< 9

< 35

< 9 06/22/05 944 +/- 136

<6

< 5

< 23

< 7 07/06/05 1280 +/- 161

< 7

< 27

<9 07/20/05 1230 +/- 160

< 6

< 7

< 25

< 7 08/03/05 1180 +/- 175

< 5

< 6

< 28

< 8 08/17/05 1180 +/- 131

< 3

< 4

< 17

< 5 08/31/05 1680 +/- 147

< 4

< 19

< 4 09/14/05 1070 +/- 147

<5

< 7

< 27

<9 09/28/05 1400 +/- 130

< 5

< 22

< 7 10/12/05 1350 +/- 130

< 5

< 6

< 27

< 8 10/26/05 1120 +/- 124

< 6

< 7

< 25

< 8 11/09/05 1550 +/- 184

< 6

< 7

< 33

< 7 11/22/05 1350 +/- 150

< 4

< 5

< 21

< 9 12/07/05 1300 +/- 206

< 6

< 5

< 22

< 12 MEAN 1250 +/- 352 5 +/- 2 6 +/- 3 26 +/- 11 8 +/- 4 K15-3 01/05/05 1530 +/- 151

< 5

< 6

< 23

< 7 02/02/05 1400 +/- 142

< 3

< 5

<13

<5 03/02/05 1470 +/- 135

< 3

< 4

<16

<5 03/16/05 1400 +/- 217

< 8

< 10

< 45

< 11 03/30/05 1210 +/- 152

< 3

< 5

< 17

< 5 04/13/05 1290 +/- 174

< 5

< 21

<6 04/27/05 1280 +/- 152

< 4

< 7

< 28

< 9 05/11/05 1410 +/- 167

< 4

< 6

< 17

< 6 05/25/05 1370 +/- 144

< 5

< 6

< 29

<10 06/08/05 1430 +/- 129

< 4

< 5

< 25

< 6 06/22/05 1420 +/- 195

<8

< 7

<31

<10 07/06/05 1350 +/- 169

< 6

< 7

< 26

< 4 07/20/05 1320 +/- 123

< 5

< 21

< 7 08/03/05 1300 +/- 191

< 8

< 7

< 38

<9 08/17/05 1340 +/- 153

<5

< 6

< 25

<10 08/31/05 1470 +/- 197

< 5

< 28

<10 09/14/05 1270 +/- 54

<1

< 2

<10

<3 09/28/05 1420 +/- 150

<5

< 4

<19

< 7 10/12/05 1260 +/- 158

<5

< 4

< 20

< 8 10/26/05 1340 +/- 157

< 4

< 5

<18

<5 11/09/05 1480 +/- 130

< 5

< 6

< 26

<7 11/22/05 1290 +/- 152

< 5

< 6

< 32

< 11 12/07/05 1230 +/- 223

<9

< 10

<30

<10 MEAN 1360 +/- 173 5 +/- 4 6 +/- 4 24 +/- 16 7 +/- 5 C-22

TABLE C-XI.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC 110-2 Cabbage B10-2 Red Beets B10-2 Tomitoes B1 0-2 Sweet Com E1-2 Cabbage E1-2 Red Beets E1-2 Tomz.toes E1-2 Sweet Com COLLECTION Sr-90 K40 1-131 Cs-134 Cs-137 PERIOD 07/21/05 08/01/05 08/01/05 08/01/05 MEAN 07/21/05 08/01/05 08/01/05 08/01/05

< 4 1790 +/- 360 2840 +/- 509 1900 +/- 285 2420 +/- 406 2238 +/- 973

< 4 2190 +/- 266 4030 +/- 616 2560 +/- 430 2350 +/- 354

< 28

< 42

< 22

< 22 28 +/-

< 20

< 42

< 32

< 28

< 18

< 20

< 12

< 14 16 +/- 8

< 13

< 16

< 17

< 13

< 22

< 23

< 15

< 14 18 19

+/-

10

< 12

< 20

< 19

< 16 MEAN 2783 +/- 1691 30 +/-

19 15 +/- 4 17

+/- 7 C-23

TABLE C-XI1.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH STATION CODE Al-4 A3-1 AS-1 A9-3 B1-1 B1-2 B2-1 B5-1 B10-1 Cl-i C1-2 C2-1 C5-1 C8-1 D1-1 D1-2 D2-2 D6-1 D15-1 E1-2 E1-4 E2-3 E5-1 E7-1 F1-1 F1-2 F1-4 F2-1 FS-1 F10-1 F25-1 G1-2 Gi-3 G1-5 G1-6 G2-4 G5-1 G10-1 G15-1 Hi-1 H3-1 H5-1 H8-1 H15-1 Ji-1 MEAN

+/-2 S.D.

3.5 +/- 1.1 3.9 +/- 1.1 4.8 +/- 1.0 3.4 +/- 1.2 4.0 +/- 1.0 3.8 +/- 0.4 3.5 +/- 1.3 3.5 +/- 1.2 4.4 +/- 1.3 4.1 +/- 1.5 3.6 +/- 1.6 3.9 +/- 1.3 4.3 +/- 1.5 4.4 +/- 1.5 3.6 +/- 1.4 4.3 +/- 2.1 4.5 +/- 1.5 5.0 +/- 1.4 5.2 +/- 1.5 3.8 +/- 1.2 3.5 +/- 1.3 4.9 +/- 1.8 4.3 +/- 1.6 4.2 +/- 1.2 5.7 +/- 2.0 4.0 +/- 1.4 3.7 +/- 1.4 3.6 +/- 1.8 4.7 +/- 1.6 4.6 +/- 1.4 5.0 +/- 1.2 6.4 +/- 1.1 4.5 +/- 1.6 3.7 +/- 1.4 3.7 +/- 1.8 4.7 +/- 1.7 4.0 +/- 1.2 5.3 +/- 1.6 4.1 +/- 1.6 4.1 +/- 1.5 5.0 +/- 1.2 3.3 +/- 1.1 3.2 +/- 0.9 6.9 +/- 1.4 3.4 +/- 1.2 01/13 - 04/14/05 04/14 - 07/14/05 07/14 - 10/13/05 10/13 - 01/13/06 3.3 3.8 4.3 3.2 3.9 3.6 3.2 3.1 4.1 3.6 3.2 3.6 3.9 4.1 3.3 3.7 4.1 4.6 4.7 3.5 3.1 4.3 3.7 3.7 5.1 3.5 3.2 3.2 4.0 4.1 4.7 6.6 4.2 3.2 3.2 4.0 3.7 5.0 3.7 3.5 4.6 3.1 3.1 6.4 3.3 2.8 3.2 4.3 2.6 3.4 (1) 2.8 2.8 3.6 3.4 2.8 3.2 3.5 4.2 2.9 3.2 3.6 4.3 4.4 3.1 2.8 4.0 3.5 3.7 4.8 3.3 3.0 2.6 4.1 4.0 4.3 5.7 3.5 3.1 2.8 3.9 3.4 4.3 3.2 3.4 4.3 2.5 2.6 6.2 2.6 3.8 4.3 5.2 4.0 4.6 4.0 4.1 4.1 5.1 4.8 4.6 4.5 5.0 5.5 4.5 5.6 5.3 5.8 5.9 4.5 4.3 5.9 5.1 4.9 7.1 4.7 4.4 4.7 5.7 5.5 5.7 7.0 5.4 4.6 4.8 5.7 4.8 6.2 5.0 4.8 5.5 3.7 3.6 7.7 4.0 4.1 4.4 5.2 3.6 4.2 3.7 4.0 3.9 4.7 4.7 3.7 4.4 4.9 3.8 3.8 4.5 4.8 5.4 5.7 4.1 3.7 5.5 4.8 4.6 5.6 4.5 4.1 4.0 5.1 4.9 5.3 6.3 4.7 3.8 4.1 5.0 4.0 5.6 4.5 4.7 5.4 3.7 3.5 7.1 3.8 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-24

TAI3LE C-XII.1 QUARTERLY TLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH STATION CODE J1-3 J3-1 J5-1 J7-1 J15-I Kl-4 K2-1 K3-1 K5-1 K8-1 K1 5-1 Li-2 L2-1 L5-1 L8-1 L15-l Mi-i M2-1 M5-1 M9-1 NI-1 N1-3 N2-1 N5-1 N8-i N15-2 P1-i P1-2 P2-1 P5-1 P8-1 Q1-1 01-2 Q2-1 Q5-1 Q9-1 015-1 Ri-1 Ri-2 R3-1 R5-1 R9-1 R15-1 MEAN

+/-2 S.D.

3.0 +/- 1.5 4.8 +/- 1.1 3.9 +/- 1.4 4.7 +/- 1.2 5.0 +/- 1.4 3.6 +/- 1.0 4.1 +/- 0.7 4.6 +/- 1.9 3.5 +/- 1.0 4.5 +/- 1.1 4.7 +/- 1.1 3.7 +/- 1.1 3.4 +/- 1.2 4.2 +/- 1.0 4.2 +/- 1.2

.3.9 +/- 2.1 4.3 +/- 1.2 3.4 +/- 1.6 3.4 +/- 1.1 3.2 +/- 1.2 4.0 +/- 0.9 5.0 +/- 1.1 3.5 +/- 0.9 3.6 +/- 2.1 4.7 +/- 1.2 3.5 +/- 2.2 3.2 +/- 1.2 4.2 +/- 1.0 3.7 +/- 1.2 3.8 +/- 3.4 4.8 +/- 0.9 3.9 +/- 1.0 3.1 +/- 1.1 3.6 +/- 1.2 3.1 +/- 1.7 4.2 +/- 0.3 3.5 +/- 2.2 3.5 +/- 0.9 4.0 +/- 1.2 3.5 +/- 1.4 3.4 +/- 1.0 3.8 +/- 1.2 4.6 +/- 1.1 4.6 +/- 1.3 4.5 +/- 1.6 01/13 - 04/14105 04/14 - 07/14/05 07/14 - 10/13/05 10/13 - 01i13/36 2.8 4.4 3.6 4.3 4.5 3.4 4.4 3.9 3.2 4.1 4.7 3.6 3.4 4.2 3.9 3.5 3.8 3.4 3.2 2.8 4.1 4.7 3.3 3.4 4.3 3.0 2.9 4.0 3.8 3.1 4.6 3.7 3.0 3.0 2.8 4.4 2.2 3.4 3.8 3.3 3.1 3.5 4.2 4.7 4.5 2.0 4.2 3.1 4.0 4.2 2.9 3.6 3.7 3.0 4.0 3.9 2.9 2.6 3.5 3.5 2.7 3.7 2.7 3.0 2.8 3.4 4.6 3.1 2.7 4.1 2.8 2.8 3.8 3.1 2.8 4.6 3.5 2.7 3.4 2.4 4.1 3.0 3.1 3.5 3.1 3.0 3.3 4.2 3.9 3.7 3.7 5.4 4.6 5.2 5.7 4.1 4.3 5.4 3.8 5.1 5.1 3.9 4.0 4.6 4.7 5.2 4.7 3.0 3.3 3.1 3.8 4.9 3.3 3.3 4.8 3.0 3.0 3.9 3.5 3.0 4.5 3.6 2.9 3.6 2.8 4.2 4.6 3.4 3.7 3.1 3.4 3.6 4.7 4.4 4.3 3.3 5.1 4.3 5.2 5.4 3.8 4.1 5.4 4.1 4.8 5.0 4.2 3.6 4.5 4.7 4.3 4.9 4.5 4.2 4.1 4.5 5.8 4.1 5.1 5.4 5.1 4.1 4.9 4.5 6.4 5.5 4.6 3.9 4.4 4.3 (1) 4.2 4.2 4.8 4.6 4.1 4.6 5.4 5.5 5.6 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-25

V.

TABLE C-XII.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, OFFSITE AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF MILLI-ROENTGEN PER STD. MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA STATION CODE SITE BOUNDARY

+/- 2 S. D.

OFFSITE CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 3.3 +/- 0.5 2.8 +/- 0.6 4.0 +/- 1.3 4.2 +/- 1.3 3.9 +/- 1.4 3.5 +/- 1.4 4.6 +/- 2.0 4.7 +/- 1.4 4.4 +/- 1.6 4.0 +/- 1.3 5.1 +/- 1.8 5.0 +/- 1.2 TABLE C-XI1.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SITE BOUNDARY OFFSITE CONTROL SAMPLES ANALYZED 83 232 43 PERIOD PERIOD MINIMUM MAXIMUM 2.0 6.4 2.2 7.7 3.3 7.0 PERIOD MEAN

+/- 2 S. D.

3.6 +/- 1.5 4.2 +/- 1.8 4.6 +/- 1.7 PRE-OP MEAN

+/-2S. D.

4.8 +/- 1.5 5.2 +/- 1.5 5.8 +/- 1.7 THE PRE-OPERATIONAL MEAN WAS CALCULATED FROM MONTHLY TLD READINGS 1980 TO 1985.

SITE BOUNDARY STATIONS - A1-4, B1-1, B1-2, C1-2, Di-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-1, J1-3, K1-4, Li-1, Mi-1, N1-3, P1-2, Q1-2, Ri-i OFFSITE STATIONS - A3-1, AS-1, A9-3, B2-1, B5-1, 810-1, Cl-1, C2-1, C5-1, C8-1, DI-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, Fl-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, LI-2, L2-1, L5-1, L8-1, Mi-2, M2-1, M5-1, M9-1, Ni-i, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Qi-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, R9-1 CONTROL STATIONS - D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, R15-1 C-26

FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2005 100000 a) 0.4 Cn 10000 Cl) 1000 a)

3o 100 0

EL.

1 0 El Station J1-2 (Downstream of Discharge) 0E Station Q9-1 (Control) 0' jg-g r

t3/4 17;n

l x;n Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month

Station K1-1 (TMINS Liquid Discharge)

L.,

I a)

CL 0.

U)

3 0

0.6 1000000 100000 10000 1000 100 10 I

I-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 - 2005 Indicator Samples

- Control Samples 12000 11000 10000 9000 8000

I-

LIQ 6000 a) 5000 C-0 0ii:

4000 3000 2000 1000 0

-1000 Significant Events Maior Atm. Nuclear Weapon Tests TMI-1 Critical June 1974 June 1974 September 1974--

TMI1-2 Critical March 1978 September 1976 November 1976 TMI-2 Accident March 1979 September 1977 March 1978 TMI-2 RB Purge June 1980 December 1978 October 1980 Clherobyl April 1986 t t 111 :111 II 11 11111 11 --

to Co r -

cO M CD q

N

)

'9 to C

t,-

Co CD 0

N M

U) t CO M

0) 0 N

M

)

to CD C

CD 0)M CO CD D

CD D

CD CD CD CD CD C

CD CD 0

0 0

0D 0

Year

FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2005 0 Indicator Samples a Control Samples 10 -

9 8

7 6-6 a)

.Ca) 5 C-)

0 7

0~0 3

I F-lk 2;

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

FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2005 a) 4-'

0~

a, C.

0

.r C.,

a.

NOTE: The mean values are calculated using both (lie MDCs and tile positive values.

500 -

NOTE: USEPA Drinking Water Limit for Tritium: 20,0 400 0 300 0 200 1

00

{Thl ' 1mo rr El Indicator Samples 000 pCi/L El Control Samples Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month U Station KI-1 (TMINS Liquid Discharge) 1000000-Q-

100000-U) a) L-

.r a) 10000-

=

i 0

C.

1000-100 -

10 L.,

I-s s-I I

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

FIGURE C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2005 Indicator Samples

-- Control Samples 900 800 Significant Event IChemobyl April 19861 700 4-------------------------

0.1 cJ)

.2 500 -

L-.

a) c-400 -

C/)

0) 0 300 -

0 200 -

I 100 4---------

.w

-- a-

-- /P -

0.

-U

RT

'lt.

Li' co co r-co co o

o Co C-4 C

cM

-t

-C LO Co cc) ir-co co 0

C0 0

C 4

(Y)

(~

"It*

I 0

10 I-,!

~!I.~

W WIU LW L-,

WI L,

)

I U)

U)

0)

U)

U) 0 U)

U) E

0)

C)

CZ)

C;)

CD C)

C) 0>

1 r

r i

04 04 04 014 04 04 04 04 04 C4 Year

FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2005 Indicator

--- Control 0.4 Significant Events Maior Atm. Nuclear Weapon Tests 0.35 -

0.3 -

TMI-l Critical TMI-2 Critical TMI-2 Accident TMI-2 RB Purge Chemobyl June 1974 March 1978 March 1979 June 1980 April 1986 March 1972 June 1974 September 1976 September 1977 December 1978 June 1973 September 1974 November 1976 March 1978 October 1980 1

w

-0 I-Q)

Ca Co C)

C.,

0 C.)IL 0.25 0.2-0.15-0.1 0.05-n-

I I.

-~ ~ ---- -

I........

N 0

t Lo (D

I-co a) 0 N

c')

9 LO c r-cc 0

0 a

N 0

"t LO)

(D 1-0c C) 0 N

CO L)O Il-l-

[-

r-N-

I 1-0c 00 0 0 co c

co c0 00 w

c0 0C) a)

)

M) a)

)

o) 0 0

0 0

o 0

0 0

o a) a)

0

0) 0

0)

0) a)

0)

0) 0 a)

0) a)

a) a)

a)

0) a)

a) a)

a) o 0

0 0

Year

FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2005 Indicator Control 0.100 -

o0.0o90 w

0 LO 0

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Month / Day of 2003

FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2005 Indicator Samples Control Samples Q(n 0)

C.,

0d-10 -

Significant Events Major Atm. Nuclear Weapon Tests 9

TMI-2 Accident March 1979 December 1978 October 1980 TMI-2 RB Purge June 1980 Clernobyl April 1986 5-Z

t--------------------------------------------------------

1-\\-/---------

2 X

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FIGURE C-9 Mean Quarterly Gamma Exposure Rates Three Mile Island Nuclear Station, 1974 - 2005

-Indicator

--- Control 50 Sienificant Events Maior Atm. Nuclear Weapon Tests TMI-I Critical June 1974 March 1972 June 1973 45 -- -- -- --

TMT-2 Critical March 1978 June 1974 September 1974

TMI-2 Accident March 1979 September 1976 November 1976 TMI-2 RBI Purge June 1980 September 1977 March 1978 40 -------------------------

Chernobyl April 1986 December 1978 October 1980 I-C:2 2 5 E

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I Intentionally Left Blank

APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

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

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

D-1

t 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, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 09-1 Q 12/28/04 - 02101/05 02/01/05 - 03/01/05 03/01/05 03/29/05 05/03/05 05/31/05 06/28/05 08/02/05

- 03/29/05

- 05/03/05

- 05/31/05

- 06/28/05

- 08/02/05

- 08/30/05

< 1.9 '

< 1.7

< 1.8

< 0.9 2.6 +/- 1.1 1.0 +/- 0.5 2.2 +/- 1.0 3.1 +/- 1.1 1.3 +/- 0.6 2.5 +/- 1.1

< 1.9 1.9

+/- 1.0 1.9 +/- 1.3 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 MEAN TABLE: D-1.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA I

COI.LECTION PERIOD 12128/04 - 02/01/05 02/01/05 - 03/01/05 03/01/05 -03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02/05 08/02/05 - 08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 MEAN Q9-IQ

< 162

< 163

< 166

< 140

< 167

< 162 170

+/- 95 197 +/- 100 158 +/- 86

< 179

< 178

< 152 166 +/- 29 D-3

TABLE D-1.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/28/04 - 02/01/05 02101/05 - 03/01/05 03/01/05 - 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 08/02/05 08/02/05 - 08/30/05 08/30/05 - 09/27/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 MEAN Q9-1Q

< 0.3

<0.3

< 0.2

<0.4

< 0.3

<0.3

< 0.2

<0.2 0.3 +/- 0.1 D-4

TABLE D-1.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD Q9-1Q 12/28/04 - 0201105 02/01/05 - 03/01/05 03/01/05 - 03/29/05 03/29/05 - 05/03/05 05/03/05 - 05/31/05 05/31/05 - 06/28/05 06/28/05 - 0810205 08/02/05 - 08/30105 08/30/05 - 09127/05 09/27/05 - 11/01/05 11/01/05 - 11/30/05 11/30/05 - 01/03/06 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140

< 2.3

< 4.1

< 1.3

< 2.8

< 3.3

< 5.4

< 3.6

< 2.6

< 2.7

< 2.9

< 6.1

< 2.3

< 4.1

< 3.0

< 2.6

< 2.5

< 4.5

< 3.2

< 2.9

< 2.3

< 1.4

< 4.9

< 2.6

<4.1

< 10

<5.0

<9.7

<6.0

<4.2

<2.6

<6.3

< 9.1

<21

<7.4

< 2.1

< 2.2

< 3.0

< 2.5

< 2.2

< 2.5

< 1.5

< 1.2

< 8.8

< 3.0

< 6.4

< 7.8

< 7.3

< 4.4

< 3.7

< 3.8

< 4.7

< 5.0

< 4.3

< 3.2

< 9.7

< 4.0

< 6.7

< 4.8

< 5.5

< 7.4

< 5.7

< 7.5

< 7.6

< 5.2

< 5.7

< 13

< 4.0

< 4.7

< 4.2

< 3.8

< 4.7

< 4.9

< 4.0

< 3.5

< 4.2

< 3.2

< 5.1

< 7.1

< 3.7

< 2.4

< 4.6

< 3.3

<4.9

< 3.2

< 1.7

< 3.4

< 3.1

< 3.2

< 2.8

< 5.3

< 2.0

< 1.8

< 5.2

< 1.7

< 3.6

< 3.8

< 4.3

< 4.8

< 2.7

< 2.9

< 3.1

< 4.9

< 2.1

< 17

< 19

< 11

< 24

< 36

< 39

< 24

< 13

< 14

< 15

< 36

< 12

<4.3

< 3.7

< 1.4

< 5.5

< 4.9

< 12

< 6.1

< 4.2

< 3.4

< 5.7

< 13

< 1.7 a7 MEAN 3.3 +/- 2.7 3.1 +/- 2.0 7.6 i 9.6 2.8 +/- 3.9 5.4 i 4.0 6.6 +/- 4.7 4.4 +/- 2.0 3.3 i 2.2 3.4 +/- 2.4 22 +/- 20 5.5 +/- 7.2

TABLE D-1.5 CONCENTRATIONS OF TRITIUM, STRONTIUM, AND GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD MS-2Q 06/10/05 12108/05 H-3 Sr-90 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 218 +/- 92 251 +/- 112

< 0.5

< 4.8

< 3.7

< 13

<3.7

<9.8

<7.6 C <6.5

<4.5

<5.3

<18

<6.0 0

06)

TABLE D-1.6 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Sr-89 Sr-90 K40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDPQ 10126105

< 11

< 5.5 2810 +/- 568

< 14

< 30

< 79

< 15

< 54

< 19

< 14

-!4

TABLE D-1.7 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD J2-1Q 10/17/05 K-40 Cs-1 34 Cs-1 37 10765 +/- 745

< 36 90 +/- 35 D-8

l TABLE D-1.8 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION K-40 PERIOD 1-131 Cs-134 Cs-1 37 Sr-89 Sr-90 B10-2Q 07/21/05 1635 +/- 174

< 21

< 8.3

< 7.6

< 1.1 1.0 +/- 0.5 D-9

TABLE D-11.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION E1-2Q PERIOD 12/29/05 - 01/05/05 39 +/- 4 01/05/05 - 01/12/05 16 +/- 4 01/12/05 -01/19/05 23 +/- 5 01/19/05 - 01/26/05 28 +/- 5 01/26/05 - 02/02105 23 +/- 4 02/02/05 - 02/09/05 33 +/- 4 02/09/05 - 02/16/05 21 +/- 4 02/16/05 - 02/23/05 22 +/- 4 02/23/05 - 03/02/05 24 +/- 4 03/02/05 - 03/09/05 19 +/- 4 03/09/05 - 03/16/05 20 +/- 4 03/16/05 - 03/23/05 16 +/- 4 03/23/05 - 03/30/05 11 +/- 3 03/30/05 - 04/06/05 12 +/- 4 04/06/05 - 04/13/05 24 +/- 4 04/13/05 - 04/20/05 22 +/- 4 04/20/05 - 04/27/05 12 +/- 4 04/27/05 - 05/04/05 16 +/- 4 05/04/05 - 05/11/05 22 +/- 4 05/11/05 - 05118/05 21 +/- 4 05/18/05 - 05/25/05 11 +/- 4 05/25/05 - 06/01/05 13 +/- 4 06/01/05 - 06/08/05 16 +/- 4 06/08/05 - 06/15/05 20 +/- 4 06/15/05 - 06/22/05 11 +/- 4 06/22/05 - 06/29/05 (1) 06/29/05 - 07/06/05 21 +/- 4 07/06/05 - 07/13/05 22 +/- 5 07/13/05 - 07/20/05 18 +/- 4 07/20/05 - 07/27/05 19 +/- 4 07/27/05 - 08/02/05 23 +/- 5 08/02/05 - 08/10/05 38 +/- 4 08/10/05 - 08/17/05 (1) 08/17/05 - 08/24/05 39 +/- 5 08/24/05 - 08/31/05 21 +/- 4 08/31/05 - 09/07/05 19 +/- 5 09/07/05 - 09/14/05 40 +/- 5 09/14/05 - 09/21/05 27 +/- 6 09/21/05 - 09/28/05 (1) 09/28/05 - 10/05/05 29 +/- 5 10/05/05 - 10/12/05 8 +/- 4 10/12/05 - 10/19/05 13 +/- 4 10/19/05 - 10/26/05 11 +/- 4 10/26/05 - 11/02/05 24 +/- 4 11/02/05 - 11/09/05 33 +/- 5 11/09/05 - 11/16/05 23 +/- 5 11/16/05 - 11/22/05 33 +/- 5 11/22/05 - 11/30/05 20 +/- 3 11/30/05 - 12/07/05 25 +/- 4 12/07/05 - 12/14/05 36 +/- 5 12/14/05 - 12/21/05 26 +/- 5 12/21/05 - 12/28/05 42 f 5 MEAN 23 17 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION D-10

TABLE D-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD Be-7 Cs-134 Cs-137 El-2Q 12/29 - 03/30/05 03/30 - 06/22/05 06/29 - 09/21/05 09/28 - 12/28/05 MEAN 71 +/- 17 63 +/- 20 83 +/- 17 58 +/- 13

< 1.0

< 0.8

< 0.9

< 0.6

< 0.4

< 0.9

< 0.6

< 0.6 69 +/- 22 0.8 +/- 0.3 0.6

+/- 0.4 D-11

TABLE D-111.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION,GAMMA EMITTERS, &

STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2005 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 1-131 K-40 Cs-1 34 Cs-1 37 Ba-140 La-140 Sr-89 Sr-90 G2-1Q 01/05/05 02/02/05 03/02105 03/16/05 03/30/05 04/13/05 04/27/05 05/11/05 05/25/05 06/08/05 06/22105 07/06/05 07/20/05 08/03/05 08/17/05 08/31/05 09/14/05 09/28/05 10/12/05 10/26/05 11/09/05 11/22/05 12/07/05

< 0.3

< 0.2

< 0.3

< 0.2

< 0.3

< 0.2

< 0.3

< 0.2

< 0.3

< 0.2

< 0.3

< 0.4

< 0.2

< 0.3

< 0.2

< 0.3

< 0.4 1372 +/- 108 1252 +/- 100 1100 +/- 106 1228 +/- 116 1478 +/- 201 1346 +/- 111 1227 +/- 170 1243 +/- 120 886 +/- 152 1305 +/- 111 1229 +/- 113 1343 +/- 149 1329 f 156 1194 +/- 159 1465 +/- 196 1334 +/- 168 1071 +/- 144 1277 +/- 169 1071 +/- 104 1045 +/- 158 1254 +/- 117 1329 +/- 118 1369 +/- 115

< 4.5

< 5.3

< 4.3

< 2.9

< 4.8

< 6.2

< 4.1

< 5.3

< 2.5

< 4.1

< 4.8

< 5.5

< 5.9

< 5.4

< 5.2

< 6.6

< 3.5

< 4.1

< 8.2

< 3.8

< 2.8

< 4.6

< 5.1

< 2.9

< 3.6

< 4.1

< 3.6

< 2.0

< 4.4

< 2.5

< 7.1

< 4.0

< 2.3

< 2.1

< 4.9

< 5.9

< 5.7

< 6.9

< 4.8

< 4.5

< 4.6

< 5.8

< 2.1

< 4.5

< 3.6

< 19

< 23

< 22

< 20

< 25

< 22

< 39

< 23

< 14

< 37

< 30

< 53

< 19

< 57

< 33

< 35

< 27

< 10

< 34

< 18

< 16

< 22

< 11

< 3.4

< 5.3

< 3.2

< 4.5

< 3.9

< 3.5

< 4.1

< 6.2

< 10

< 5.7

< 5.8

< 9.8

< 4.0

< 6.7

< 3.4

< 6.5

< 8.7

< 4.6

< 7.3

< 5.5

< 4.4

< 3.1

< 4.3

< 0.5

< 0.7

< 0.6

< 0.7

< 0.7 0.7 + 0.4 MEAN 0.3 +/- 0.1 1250 +/- 281 4.7

+/- 2.6 4.2

+/- 3.0 26

+/- 24 5.4

+/- 4.1 0.6

+/- 0.2 0.7 +/- 0.1 D-12

FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2005 5

4 3

.0 C-0.

2 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 El-2Q, 2005 50 QC - LAB 40 P.PIMAR Y -

LAB......................

E 30i...X.

30.

j 2 0 X

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

°0 1

4 7

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

i APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2005 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b) TBE/Analytics Ev'aluation (d)

March 2005 E4522-396 Milk Sr-89 Sr-90 pCi/L 96.9 107 pCi/L 16.9 17.9 0.91 0.94 A

A E4523-396 Milk 1-131 Ce-141 Cr-51 Cs-1 34 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 pCViL pCi/L pci pci pCi pCi pCi pCi pCi pCi pCi 82.7 217 314 123 125 110 158 118 191 140 150 278 105 95.6 84.4 112 92.8 162 102 92.3 229 334 139 130 115 160 111 198 144 172 250 104 97.1 86.3 120 83.2 148 108 0.90 0.95 0.94 0.89 0.96 0.96 0.99 1.06 0.96 0.97 A

A A

A E4525-396 AP Ce-141 Cr-51 Cs-I 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 0.87 1.11 1.01 0.98 0.98 0.93 1.12 1.09 0.94 A

A A

A

'A A

A A

A E4524-396 Charcoal 1-131 June 2005 E4630-396 Milk Sr-89 Sr-90 pCi 67.4 60.7 pCi/L 89.4 88.1 pCi/L 11.6 11.4 1.11 A

1.01 1.02 A

A E4631-396 Milk 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 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 pC!

pCi pCi pCi pci pCi pci 82.3 91.6 278 81.1 180 124 61.1 156 136 79.2 263 69.7 135 94.9 48 120 104 86.9 92.4 303 95.0 189 125 63.9 155 145 64.2 210 66.1 131 87.0 44.4 108 101 0.95 0.99 0.92 0.85 0.95 0.99 0.96 1.01 0.94 A

A A

E4633-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Mn-54 Fe-59 Zn-65 Co-60 1.23 1.25 1.05 1.03 1.09 1.09 1.11 1.03 W

W A

A A

A E4632-396 Charcoal 1-131 pCi 88.9 92.5 0.96 A

E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2005 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

TBE/Analytics Evaluation (d)

September 2005 E4766-396 Milk E4767-396 Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 135.0 146.0 pCi/L 9.7 11.5 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pci pCi pci pc pci pci pci pci pci 87.5 203 279 102 178 55.3 81.8 59.9 120 146 193 267 78.4 166 53.7 81.6 59.6 107 133 94.3 233 338 122.0 195 63.4 92.0 61.0 123 167 169 246 88.8 142 46.0 66.8 44.3 89.6 122 0.92 0.84 0.93 0.87 0.83 0.84 0.91 0.87 0.89 0.98 0.98 0.87 1.14 1.09 0.88 1.17 1.17 1.22 1.35 1.19 1.09 A

A A

W N (1)

A A

E4769-396 AP Ce-141 Cr-51 Cs-I 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E4768-396 Charcoal 1-131 pCi 63.9 64.2 1.00 A

December 2005 E4766-396 Milk E4767-396 Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 114 128 pCi/L 11.6 10.3 pCiUL pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pci pCi pci pCi pci pci pci pci pci 79.6 202 185 74.9 177 73.9 152 97.5 161 102 221 195 68.4 194 77.4 171 94.2 173 109 74.6 224 193 87.3 189 77.5 152 82.4 154 111 201 173 78.3 170 69.4 137 73.9 138 99.1 0.89 1.13 1.07 0.90 0.96 0.86 0.94 0.95 1.00 1.18 1.05 0.92 1.10 1.13 0.87 1.14 1.12 1.25 1.27 1.25 1.10 A

A A

W W

W A

E4633-396 AP Ce-141 Cr-51 Cs-134 Cs-I 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2005 (PAGE 3 OF 3)

Identification Number Reported Known Units Value (a)

Value (b)

Ratio (c)

TBE/Analvtics Evaluation (d)

Month/Year Matrix Nuclide December 2005 E4632-396 Charcoal 1-131 pci 73.3 73.3 1.00 A

(1) New technician - AP not counted in petri dish resulted in high Fe-59 activity. Counting in petri dish, the Fe-59 would have been acceptable as evidenced by the 4005 AP recount data. NCR 06-01 (a) Teledyne E rown Engineering reported result.

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

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

(d) Analytics evaluation based on TEE intemal OC limits: A= Acceptable. Reported result falls within ratio limits of.80-1.20.

W-Acceptable with waming. Reported result falls ivithin 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, 2005 (PAGE 1 OF 1)

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

Control Limits Evaluation (c)

May 2005 Rad 61 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B H-3 pCi/L pCi/L pCi/L pCU/L pCi/L pCi/L pCi/L pCi/L pCi/L pCVL 37.5 5.37 88.6 70.5 201 37.5 122 35.5 35.6 24600 41.3 5.92 88.4 78.6 201 37.0 118 37.0 34.2 24400 32.6 - 50.0 0.00 - 14.6 73.1 - 104 69.9 - 87.3 184 - 218 28.3 - 45.7 97.6-138 21.0 - 53.0 25.5 - 42.9 20200 - 28600 A

A A

A Rad 61 Water 1-131 pCi/L 13.6 15.5 10.3 - 20.7 A

November 2005 Rad 63 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 18.0 16.6 31.7 30.8 26.8 83.9 109 19.5 34.0 12400 19.0 16.0 31.2 33.9 28.3 84.1 105 23.3 39.1 12200 10.3 - 27.7 7.37 - 24.7 22.5 - 39.9 25.2 - 42.6 19.6 - 37.0 75.4 - 92.8 86.8 - 123 13.2 - 33.4 30.4 - 47.8 10100- 14300 A

A A

A Rad 63 Water 1-131 pCi/L 17.8 17.4 12.2 - 22.6 A

(a) Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameterpresent 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 Waming Limit.

E-4

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

TELEDYNE BROWN ENGINEERING, 2005 (PAGE 1 OF 2)

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

Range Evaluation (c)

April2005 05-MaW13 Water Cs-134 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 108 305 215 241 283 314 0.093 509 127 332 227 251 280 331 88.90 - 165.10 232.40 - 461.60 158.90 - 295.10 175.70 - 326.30 196.00 - 364.00 231.70 - 430.30 A

A A

A no range given (1) 496 347.20 - 644.80 MaS13 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 655 310 234 219 512 642 890 759 315 242 212 485 604 810 531.30 - 986.70 220.50 - 409.50 169.40 - 314.60 148.40 - 275.60 339.50 - 630.50 422.80 - 785.20 567.00 - 1053 A

A A

GrW13 Water Gr-A Gr-B Bq/L 0.601 0.525

>0.0 - 1.05 Bq/L 1.54 1.67 0.84 - 2.51 RdF13 GrF13 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 3.26 2.05 4.78 3.02 3.31 1.15 3.14 3.51 2.26 4.92 3.03 3.33 1.35 3.14 2.46 - 4.56 1.58 - 2.94 3.44 - 6.40 2.12 - 3.94 2.33 - 4.33 0.95-1.76 2.20 - 4.08 A

A A

Bq/sample 0.0764 0.232

>0.0 - 0.46 Bq/sample 0.305 0.297 0.15 - 0.45 April 2005 RdV13 Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 5.45 4.80 13.4 3.67 6.45 1.49 7.71 5

4.1 9.88 3.15 5.18 1.65 6.29 3.50 - 6.50 2.88 - 5.34 6.92-12.84 2.21 - 4.10 3.63 - 6.73 1.16 - 2.15 4.40 - 8.18 A

A A*

A A

October 20C5 05-MaW14 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 142 302 251 243 547 383 8.75 324 167 333 272 261 527 418 8.98 330 116.90 - 217.10 233.10 - 432.90 190.40 - 353.60 182.70- 339.30 368.90- 685.10 292.60 - 543.40 6.29 - 11.67 231.00 - 429.00 A

A A

A E-5

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

TELEDYNE BROWN ENGINEERING, 2005 (PAGE 2 OF 2)

Identification Reported Known Acceptance MonthNear Number Media Nuclide Units Value (a) Value (b)

Range Evaluation (c)

October 2005 MaS14 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 494 446 506 289 460 626 889 568 439 524 287 439 604 823 397.60 - 738.40 307.30 - 570.70 366.80 - 681.20 200.90- 373.10 307.30 - 570.70 422.80 - 785.20 576.10 - 1070 A

A A

GrW14 Water Gr-A Gr-B Bq/L 0.858 0.79 Bq/L 1.22 1.35 0.21 - 1.38 0.85 - 1.92 A

A October 2005 RdF14 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 4.11 3.16 6.14 2.86 4.54 2.12 4.28 3.85 3.23 6.2 2.85 4.37 2.25 4.33 2.70 - 5.01 2.26 - 4.20 4.34 - 8.06 2.00 - 3.71 3.06 - 5.68 1.58 - 2.93 3.03 - 5.63 A

A A

GrF14 RdV1 3 AP Gr-A Gr-B Vegetation Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 0.304 0.858 4.35 5.99 17.0 4.87 7.40 2.03 11.8 0.482

>0.0 - 0.80 0.827 0.55 - 1.22 4.09 5.4 13.30 4.43 6.57 2.42 10.2 2.86 - 5.32 3.80 - 7.06 9.31 - 17.29 3.10 - 5.76 4.60 - 8.54 1.69 - 3.15 7.14-13.26 A

A A

A W

A A

Under investigation. MAPEP reported the result as acceptable although the reported value of 13.4 is higher than the acceptance range upper limit of 12.84.

(1) The Sr-90 in water was a MAPEP false positive test. The TBE reported result of 0.093 + 0.0908 Bq/L was the forced Sr-90 activity and uncertainty, as required by MAPEP. The MDC for the sample was 0.145 pCi/L.

(a) Teledyne Brown Engineering reported result.

(b)

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

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

E-6

TABLE E-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2005 (Page 1 of 2)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result?

Result' Limits Ac eptance STW-1 051 STW-1051 STW-1 052 STW-1 052 STW-1052 STW-1052 STW-1052 STW-1053 STW-1 053 STW-1054 STW-1 054 STW-1054 STW-1 055 STW-1 055 STW-1 056 STW-1 056 STW-1056 STW-1056 STW-1056 STW-1 057 SlW-1 057 STW-1 058 STW-1059 STW-1 059 STW-1 059 STW-1 060 STW-1067 STW-1067 STW-1 068 STW-1 068 STW-1 068 STW-1 068 STW-1 068 STW-1 069 S1W-1 069 STW-1 070 STW-1 070 STW-1 070 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 02/15/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 05/17/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 08/16/05 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium 28.0 i 1.2 25.1 +/- 0.7 52.9 +/- 2.8 54.4 +/- 0.4 67.7 +/- 1.8 39.6 +/- 1.8 159.7 +/- 3.0 55.1 +/- 1.8 46.8 +/- 1.3 13.7 +/- 1.5 13.3 +/- 0.6 5.1 +/-0.2 45.1 +/-4.1 7.5 +/- 0.9 87.1 +/- 2.0 38.4 +/- 0.8 75.3 +/- 0.7 201.0 +/- 8.4 130.0 +/- 6.7 42.7 +/- 2.9 34.0 +/- 0.4 14.7 +/- 0.5 6.6 +/- 0.1 19.3 +/- 0.7 9.6 +/- 0.1 24100.0 +/- 109.0 29.1 +/- 3.0 36.0 +/- 0.6 107.0 +/- 1.7 15.2 +/- 0.2 89.1 +/- 0.3 72.1 +/- 1.0 67.4 +/- 1.4 44.3 +/- 1.5 58.4 +/- 2.1 16.6 +/- 1.5 6.2 +/- 0.3 4.5 +/- 0.1 29.4 24.4 53.4 56.6 64.9 40.2 161.0 67.9 51.1 14.1 13.7 5.0 41.3 5.9 88.4 37.0 78.6 194.0 118.0 37.0 34.2 15.5 7.6 18.9 10.1 24400.0 28.0 33.8 106.0 13.5 92.1 72.7 65.7 55.7 61.3 16.6 6.2 4.5 20.7 - 38.1 15.7 - 33.1 44.2 - 62.6 47.9 - 65.3 56.2 - 73.6 31.5 - 48.9 133.0 - 189.0 38.5 - 97.3 38.5 - 97.3 10.4 - 17.8 7.8 - 19.6 0.0 - 10.2 32.6 - 50.0 0.0 - 14.6 73.1 - 104.0 28.3 - 45.7 69.9 - 87.3 184.0 - 218.0 97.6 - 138.0 21.0 - 53.0 25.5 - 42.9 10.3 - 20.7 5.6 - 9.5 10.7 - 27.1 4.9 - 15.3 20200.0 - 28600.0 19.3 - 36.7 25.1 - 42.5 87.7 - 124.0 4.8 - 22.2 83.4 - 101.0 64.0 - 81.4 54.3 - 77.1 31.6 - 79.8 44.0 - 78.6 12.3 - 20.9 3.5 - 8.9 0.0 - 9.7 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass E-7

TABLE E-4 ERAla) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2005 (Page 1 of 2)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result' Result' Limits Acceptance STW-1072 11/15/05 Sr-89 20.6 +/- 0.4 19.0 10.3 -27.7 Pass STW-1072 11/15/05 Sr-90 15.0 +/- 0.3 16.0 7.3 -24.7 Pass STW-1073 11/15/05 Ba-133 31.8 +/- 1.8 31.2 22.5 -39.9 Pass STW-1073 11/15/05 Co-60 85.0 +/- 1.4 84.1 75.4 - 92.8 Pass STW-1073 11/15/05 Cs-134 37.2 +/- 2.1 33.9 25.2 -42.6 Pass STW-1073 11/15/05 Cs-137 27.8 +/- 0.7 28.3 19.6 -37.0 Pass STW-1073 11/15/05 Zn-65 109.0 +/- 1.0 105.0 86.8 - 123.0 Pass STW-1074 0 11/15/05 Gr. Alpha 41.1 +/- 1.2 23.3 13.2 -33.4 Fail STW-1074 11/15/05 Gr. Beta 42.7 +/- 0.5 39.1 30.4 -47.8 Pass STW-1075 11/15/05 1-131 20.5 +/- 0.6 17.4 12.2 -22.6 Pass STW-1076 11(15/05 Ra-226 7.8 +/- 0.6 8.3 6.2 - 10.5 Pass STW-1076 e 11/15/05 Ra-228 5.5 +/- 0.6 3.5 2.0 - 5.0 Fail STW-1076 11/15/05 Uranium 15.5 +/-0.3 16.1 10.9 -21.3 Pass STW-1077 11/15/05 H-3 12500.0 +/- 238.0 12200.0 10100.0 - 14300.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

dThe original samples were calculated using an Am-241 efficiency. The samples were spiked with Th-232. Samples were recounted and calculated using the Th-232 efficiency. Results of the recount: 27.01 +/- 2.35 pCi/L.

e Decay of short-lived radium daughters contributed to a higher counting rate. Delay of counting for 100 minutes provided better results.

The reported result was the average of the first cycle of 100 minutes, the average of the second cycle counts was 4.01 pCi/L E-8

p TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPJ ENVIRONMENTAL, INC., 2005 (Page 1 of 3)

Concentration b Known Control Lab Code' Date Analysis Laboratory result Activity Limits "

Acceptance STW-1 045 01/01/05 Gr. Alpha STW-1045 01/01/05 Gr. Beta 0.45 +/- 0.10 1.90 +/- 0.10 0.53 1.67 0.00 - 1.05 0.84 - 2.51 PaEss Pass STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1047 STSO-1 048 STSO-1 048 STSO-1 048 STSO-1 048 STSO-1048 STSO-1048 STSO-1 048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1 048 STSO-1048 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-23314 U-238 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Am-241 Co-57 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 1.62 +/- 0.12 239.40 +/- 1.20 248.70 +/- 1.00 115.50 +/- 1.80 328.50 +/- 1.70 64.90 +/- 7.00 304.00 +/- 9.70 334.80 +/- 1.90 7.10 +/- 1.60 0.01 +/- 0.02 2.50 +/- 0.14 0.70 +/- 0.80 43.20 +/- 1.40 3.31 +/- 0.20 3.38 +/- 0.20 538.40 +/- 3.80 10.60 +/- 0.20 3.00 +/- 0.20 4.80 +/- 0.40 4.10 +/- 0.30 5.10 +/- 0.30 6.20 +/- 0.50 96.60 +/- 10.00 264.00 +/- 2.00 226.50 +/- 2.20 760.60 +/- 3.70 336.20 +/- 3.60 663.70 +/- 18.00 541.30 +/- 3.90 924.30 +/- 17.20 0.60 +/- 0.80 78.00 +/- 4.80 514.60 +/- 18.70 47.90 +/- 4.00 226.30 +/- 8.60 851.30 +/- 7.30 1.72 227.00 251.00 127.00 332.00 75.90 280.00 331.00 9.00 0.02 2.40 0.00 42.90 3.24 3.33 496.00 9.88 3.15 5.00 4.11 5.18 6.29 109.00 242.00 212.00 759.00 315.00 604.00 485.00 1220.00 0.48 89.50 640.00 62.50 249.00 810.00 1.20 - 2.24 158.90 - 295.10 175.70 - 326.30 88.90 - 165.10 232.40 - 431.60 53.13 - 98.67 196.00 - 364.00 231.70 - 430.30 0.00 - 20.00 0.00 - 1.00 1.68 - 3.12 0.00 - 5.00 30.03 - 55.77 2.27 - 4.21 2.33 - 4.33 347.20 - 644.80 6.92 - 12.84 2.21 - 4.10 3.50 - 6.50 2.88 - 5.34 3.63 - 6.73 4.40 - 8.18 76.30 - 141.70 169.40 - 314.60 148.40 - 275.60 531.30 - 986.70 220.50 - 409.50 422.80 - 785.20 339.50 - 630.50 854.00 - 1586.00 0.00 - 1.00 62.65 - 116.35 448.00 - 832.00 43.75 - 81.25 174.30 - 323.70 567.00 - 1053.00 Pass Pass PESs PESs Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1 050 STAP-l 050 01/01/05 Gr. Alpha 01/01/05 Gr. Beta 0.11 +/- 0.03 0.38 +/- 0.05 0.23 0.30 0.00 - 0.46 0.15 - 0.45 Pass Pass E-9

T TABLE E.5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPr ENVIRONMENTAL, INC., 2005 (Page 2 of 3)

Concentration b Known Control Lab Code' Date Analysis Laboratory result Activity Limits a Acceptance STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 e STAP-1 049 STAP-1 049 STAP-1 049 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 0.10 +/- 0.04 4.76 +/- 0.64 2.84 +/- 0.22 3.54 +/- 0.37 2.20 +/- 0.27 3.15 +/- 0.21 0.16 +/- 0.04 0.17 +/- 0.02 2.24 +/- 0.34 0.34 +/- 0.02 0.35 +/- 0.02 3.12 +/- 0.15 0.10 4.92 3.03 3.51 2.26 3.33 0.20 0.17 1.35 0.34 0.35 3.14 0.07 - 0.13 3.44 - 6.40 2.12 - 3.94 2.46 - 4.56 1.58 - 2.94 2.33 - 4.33 0.14 - 0.25 0.14 - 0.25 0.95 - 1.76 0.24 - 0.44 0.25 - 0.46 2.20 - 4.08 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass STW-1 061 STW-1061 STW-1061 STW-1061 STW-1 061 STW-1061 STW-1 061 STW-1 061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1061 STW-1 061 STW-1061 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 2.21 +/- 0.13 293.20 +/- 7.30 275.70 +/- 1.30 171.80 +/- 4.00 342.10 +/- 2.20 167.80 +/- 9.30 514.20 +/- 12.60 437.00 +/- 2.50 105.10 +/- 3.60 1.64 +/- 0.12 2.32 +/- 0.13 9.20 +/- 1.30 72.30 +/- 2.30 4.11 +/-0.18 4.14 +/- 0.18 364.60 +/- 4.90 0.57 +/- 0.05 1.36 +/- 0.05 2.23 272.00 261.00 167.00 333.00 196.00 527.00 418.00 100.00 1.91 2.75 8.98 66.50 4.10 4.26 330.00 0.79 1.35 1.56 - 2.90 190.40 - 353.60 182.70 - 339.30 116.90 - 217.10 233.10 - 432.90 137.20 - 254.80 368.90 - 685.10 292.60 - 543.40 70.00 - 130.00 1.34 - 2.48 1.93 - 3.58 6.29 - 11.67 46.55 - 86.45 2.87 - 5.33 2.98 - 5.54 231.00 - 429.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1 062 07/01/05 Gr. Alpha STW-1 062 07/01/05 Gr. Beta 0.21 - 1.38 0.85 - 1.92 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1063 STSO-1 063 STSO-1063 STSO-1 063 STSO-1 063 STSO-1063 STSO-1 063 STSO-1063 STSO-1063 STSO-1 063 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 48.40 +/- 3.90 608.30 +/- 2.80 322.70 +/- 2.40 632.10 +/- 5.20 512.40 +/- 4.20 720.50 +/- 19.00 516.80 +/- 5.10 366.50 +/- 13.30 68.80 +/- 15.00 0.00 +/- 0.00 602.90 +/- 17.20 61.50 +/- 1.00 164.50 +/- 16.70 874.70 +/- 8.40 81.10 524.00 287.00 568.00 439.00 604.00 439.00 445.00 60.80 0.00 757.00 52.50 168.00 823.00 56.77 - 105.43 366.80 - 681.20 200.90 - 373.10 397.60 - 738.40 307.30 - 570.70 422.80 - 785.20 307.30 - 570.70 311.50 - 578.50 42.56 - 79.04 0.00 - 0.00 529.90 - 984.10 36.75 - 68.25 117.60 - 218.40 576.10 - 1070.00 Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass E-1 0

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

ENVIRONMENTAL, INC., 2005 (Page 3 of 3)

Concentration b Known Control Lab Code' Date Analysis Laboratory result Activity Limits a Acceitance STVE-1 064 STVE-1 064 STVE-.1 064 STVE-1064 STVE-1 064 STVE1 064 STVE-1 064 STVE.*1 064 STVE-1 064 STVE-1 064 STVE-1 064 STVE..1 064 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-23314 U-238 Zn-65 0.18 +/- 0.03 15.90 +/- 0.20 4.80 +/- 0.10 4.60 +/- 0.20 5.90 +/- 0.30 7.20 +/- 0.20 0.04 +/- 0.02 0.13 +/- 0.02 2.80 +/- 0.30 0.28 +/- 0.03 0.33 +/- 0.04 11.00 +/- 0.50 0.23 13.30 4.43 4.09 5.43 6.57 0.00 0.16 2.42 0.33 0.35 10.20 0.16 - 0.30 9.31 - 17.29 3.10 - 5.76 2.86 - 5.32 3.80 - 7.06 4.60 - 8.54 0.00 - 1.00 0.11 - 0.21 1.69 - 3.15 0.23 - 0.43 0.24 - 0.45 7.14 - 13.26 P.3ss Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1 065 STAP-1 065 07/01/05 Gr. Alpha 07/01/05 Gr. Beta 0.30 +/- 0.04 0.97 +/- 0.06 0.48 0.83 0.00 - 0.80 0.55 - 1.22 Pass Pass STAP-1 066 STAP1 066 STAP.1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP.1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/011.05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 0.14 +/- 0.03 5.81 +/- 0.17 2.79 +/- 0.14 3.67 +/- 0.12 2.93 +/- 0.23 4.11 +/- 0.26 0.11 +/- 0.02 0.10 +/- 0.01 2.25 +/- 0.29 0.28 +/- 0.02 0.28 +/- 0.02 4.11 +/-0.26 0.16 6.20 2.85 3.85 3.23 4.37 0.10 0.09 2.25 0.27 0.28 4.33 0.11 - 0.21 4.34 - 8.06 2.00 - 3.71 2.70 - 5.01 2.26 - 4.20 3.06 - 5.68 0.07 - 0.13 0.06 - 0.12 1.58 - 2.93 0.19 - 0.35 0.20 - 0.37 3.06 - 5.68 P.3ss Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Result; obtained by Environmental, Inc., Midwest Laboratory as a participant In the Department of Energy's Mi:ed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported In units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as requested by the Department of Energy.

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

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

e The strontium carbonate precipitates were redissolved and processed. The average of the three analyses was 1.34 pCi/L, although the recovery was only 30%. The result of a new analysis was 1.56 pCi/L.

f Incorrect sample weight used in calculation. Result of recalculation: 97.0 +/- 7.8 Bq/kg.

E-1 1

4 a,

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APPENDIX F SPECIAL GROUNDWATER SAMPLING DATA

TABLE F-1.1 CONCENTRATIONS OF TRITIUM IN SPECIAL GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION - 2(105 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA Collecton Date 01/27/25 03110135 06/10/35 07107135 08101135 08/05135 08/08/)5 08/11/35 08/15/35 08/19/)5 08/22/25 08/241)5 08/261)5 081291)5 081311)5 09/021)5 09/06/1)5 09/08/)5 09/121)5 09/16/105 09/19/25 09/23/125 09/26/0)5 09/30/1)5 10/02/1)5 10/07/1)5 10/10/1)5 10/14/1)5 1017/1)5 10/20/)5 10/24/1)5 1 0/27/05 10/31/05 11/03/105 11/07/1)5 11/10/125 11/14/125 11/17/05 11/21/1)5 11/2310)5 12/02/1)5 MS-20 RW-1

< 190 1770 +/- 154 581 +/- 122 597 +/- 116 222 +/- 113 197 +/- 100 672 +/- 334

< 166

< 147 455 +/- 94

< 152

< 169 507 +/- 109

< 175

< 173

< 129 466 +/- 123 479 +/- 95 429 +/- 53 509 +/- 125 679 +/- 131 759 +/- 115 604 +/- 127 636 +/- 130 277 +/- 125 284 +/- 126

< 194 619 +/- 134 836 +/- 126 553 +/- 135 719 +/- 142 478 +/- 124 1310 +/- 140 2110 +/- 159 2410 +/- 164 1660 +/- 172 886 +/- 124 796 +/- 127 672 +/- 125 210 +/- 118 362 +/- 115

< 103 201 +/- 116 227 +/- 110 440 +/- 104 524 +/- 109 259 +/- 125

< 192

< 189

< 198 395 +/- 121 197 +/- 118

< 187

< 182

< 187

< 176 230 +/- 120

< 182

< 171

< 168

< 172 401 +/- 118 187 +/- 114 RW-2 881 +/- 143 5440 +/- 237 18200 +/- 295 22800 +/- 320 1850 + 136 2410 + 137 10300 +/- 242 19000 +/- 355 19400 +/- 357 19000 +/- 371 15400 +/- 349 18000 +/- 366 20200 +/- 387 19500 +/- 376 22300 +/- 495 20400 +/- 405 21600 +/- 406 31100 +/- 447 31400 +/- 331 32400 +/- 469 32800 +/- 476 32800 +/- 489 29300 +/- 463 33100 +/- 484 32600 +/- 485 30400 +/- 472 14700 +/- 334 5390 +/- 205 4910 +/- 207 2760 +/- 164 4120 +/- 202 1110 +/- 138 1580 +/- 143 2180 +/- 161 2110 +/- 158 1550 +/- 170 1010 +/- 128 639 +/- 121 868 +/- 128 1140 +/- 135 1350 +/- 130 AVG 777 +/- 552 231 +/- 112 14341 +/- 12044 F-1

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