ML15125A023
ML15125A023 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
Issue date: | 04/30/2015 |
From: | Haaf T Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
References | |
TM1-15-053 | |
Download: ML15125A023 (177) | |
Text
Three Mile Island Unit 1 A Exelon Generation, Route 441 South P.O. Box 480 Middletown, PA 17057 717-948-8000 Office www.exeloncorp.com April 30, 2015 TM1-15-053 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 THREE MILE ISLAND NUCLEAR STATION UNIT 1 AND UNIT 2 RENEWED OPERATING LICENSE NO. DPR-50 AND POSSESSION ONLY LICENSE NO. DPR 73 DOCKET NOS. 50-289 AND 50-320
SUBJECT:
2014 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT In accordance with TMI Technical Specification 6.9.3.1, TMI-2 Technical Specifications 6.8.1.1, enclosed is the Annual Radiological Environmental Operating Report covering the time period of January 1 through December 31, 2014, for the Three Mile Island Nuclear Station.
Please contact Laura Weber of TMI-Chemistry at (717) 948-8947 if you have questions regarding this submittal.
Sincerely, Plant Manager TPH/LKW/dam Attachments/Enclosures cc: Region 1 Administrator TMI Senior Resident Inspector TMI-1 Senior Project Manager TMI-2 Project Manager GPU Nuclear Cognizant Officer Department of Environmental Protection, Bureau of Radiation Protection A~Q
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 2014 Prepared By Teledyne Brown Engineering Environmental Services A" Exeton Generation, Three Mile Island Nuclear Station Middletown, PA 17057 April 2015
I Intentionally left blank
Table Of Contents I. Sum m ary and Conclusions .............................................................................................. 1 I1. Introduction ..................................... 3........
A. Objectives of the REM P ................................................................................. 3 B. Im plem entation of the Objectives .................................................................... 4 Ill. Program Description .................................................................................................. 4 A. Sam ple Collection .......................................................................................... 4 B. Sam ple Analysis ............................................................................................. 6 C. Data Interpretation .......................................................................................... 7 D. Program Exceptions ........................................................................................ 8 E. Program Changes ........................................................................................ 12 IV. Results and Discussion .......................................................................................... 12 A. Aquatic Environm ent ................................................................................... 12
- 1. Surface W ater .................................................................................... 12
- 2. Drinking W ater .................................................................................... 13
- 3. Effluent W ater .................................................................................... 14
- 4. Storm W ater ..................................................................................... 15
- 5. Ground W ater .................................................................................... 15
- 6. Fish ................................................................................................... 15
- 7. Sedim ent ............................................................................................. 16 B. Atm ospheric Environm ent ............................................................................. 16
- 1. Airborne Particulates .......................................................................... 16
- a. Air Particulates ......................................................................... 16
- b. Airborne Iodine ........................................................................ 17
- 2. Terrestrial .......................................................................................... 17
- a. Milk ........................................................................................... 17
- b. Food Products ........................................................................ 18 C. Am bient Gam m a Radiation ........................................................................... 19 D. Land Use Survey ........................................................................................... 19 E. Radiological Impact of TM INS Operations .................................................... 20 F. Errata Data ................................................................................................... 27 G. Summary of Results - Inter-laboratory Comparison Program .................... 27 V. References ................................................................................................................... 30 i
Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables ' I Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Three Mile Island Nuclear Station, 2014 Appendix B Location Designation, Distance & Direction And Sample Collection &
Analytical Methods Tables Table B-1 Location Designation and Identification System for the Three Mile Island Nuclear Station Table B-2 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Table B-3 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Figures Environmental Sampling Locations Within One Mile of the Three Mile Figure B-1 Island Nuclear Station, 2014 Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Three Mile Island Nuclear Station, 2014 Figure B-3 Environmental Sampling Locations Greater Than Five Miles from the Three Mile Island Nuclear Station, 2014 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-1.2 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
ii
Table C-I1.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-11.2 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-11.3 Concpntrations of Tritium in Drinking Water Samples Cqllected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-111.1 Concentrations of Gross Beta, 1-131, Tritium, and Strontium in Effluent Water Samples for Station K1-1 Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-111.2 Concentrations of Gamma Emitters in Effluent Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-IV. 1 Concentrations of Strontium in Predator and Bottom Feeder (Fish)
Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-IV.2 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-VI.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-VI.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, 2014.
Table C-VI.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-VII.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-VIII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-VIII.2 Concentrations of Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-VIII.3 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table C-IX. 1 Concentrations of Strontium and Gamma Emitters in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
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Table C-X.1 Quarterly OSLD Results for Three Mile Island Nuclear Station, 2014.
Table C-X.2 Mean Quarterly OSLD Results for the Site Boundary, Indicator and Control Locations for Three Mile Island Nuclear Station, 2014.
Table C-X.3 Summary of the Ambient Dosimetry Program for Three Mile Island Nuclear Station, 2014. I Figures Figure C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2014.
Figure C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2014.
Figure C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2014.
Figure C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2014.
Figure C-5 Mean Cesium-137 Concentrations in Aquatic Sediments Three Mile Island Nuclear Station, 1984 - 2014.
Figure C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2014.
Figure C-7 Mean Weekly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 2007 - 2014.
Figure C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2014.
Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-1.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity Of Three Mile Island Nuclear Station, 2014.
Table D-1.2 Concentration of Tritium in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table D-1.3 Concentrations of Iodine-131 in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table D-1.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table D-11.1 Concentrations of Strontium and Gamma Emitters in Fish Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
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Table D-Ill.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table D-IV.1 Concentrations of Gamma Emitters and Strontium in Food Product Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table D-V. 1 Concentrations of Gross Beta in Air Particulate and 1-131 in Air Iodine Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table D-V.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table D-VI.1 Concentrations of 1-131 by Chemical Separation, Gamma Emitters, and Strontium in Milk Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Figures Figure D-1 Monthly Gross Beta Concentrations in Drinking Water Samples Collected From TMINS Location Q9-1Q, 2014.
Figure D-2 Weekly Gross Beta Concentrations in Air Particulate Samples Collected from TMINS Location E1-2Q, 2014.
Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2014 Table E-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Teledyne Brown Engineering, 2014 Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2014 Table E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Environmental, Inc., 2014 Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) v
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I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program conducted for the Three Mile Island Nuclear Station (TMINS) by Exelon covers the period 1 January 2014 through 31 December 2014. During that time period, 1,931 analyses were performed on 1,325 samples. In assessing all the data gathered for this report and comparing these results with preoperational data and operational REMP data, it was concluded that the operation of TMINS had no adverse radiological impact on the environment.
Surface, drinking and effluent water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Surface, drinking and effluent water samples were also analyzed for concentrations of 1-131. Drinking and effluent water samples were also analyzed for concentrations of gross beta. Effluent water samples were also analyzed for concentrations of Sr-89 and Sr-90. All groundwater, precipitation water and storm water results are now being reported in the ARGPPR, Appendix G. No Sr-89 and Sr-90 activities were detected.
lodine-131 and gross beta concentrations detected were consistent with those detected in previous years. Tritium activity in four surface water samples and monthly effluent water samples was due to TMINS activities or releases. No other fission or activation products potentially attributed to TMI liquid releases were detected.
Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. Fish samples were also analyzed for concentrations of Sr-90. No Sr-90 activity was detected. No fission or activation products were detected in fish samples. Cesium-1 37 was not detected in any sediment samples. Occasionally Cs-137 is detected at very low levels (just above LLD) and is not distinguishable from background levels.
Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Gross beta activity is consistent with data from previous years. Cosmogenic Be-7 was detected at levels consistent with those detected in previous years. No other activation products were detected.
High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity for 1-131.
Cow milk samples were analyzed for concentrations of 1-131, gamma emitting nuclides, Sr-89 and Sr-90. One milk sample was initially positive for 1-131.
Upon further investigation, recounting the sample twice showed an increase in activity, which is not congruent with 1-131 decay. Additionally, a gamma spectroscopy analysis was performed on the 1-131 sample, which determined that K-40 was the interfering isotope. No Sr-89, Sr-90 activities were detected.
Concentrations of naturally occurring K-40 were consistent with those detected in previous years. Occasionally Sr-90 activities are detected and are consistent with those detected in previous years and were attributed to fallout from nuclear weapons testing. No other fission or activation products were found. No Sr-90 was detected in milk samples for this year.
Food Product samples were analyzed for concentrations of gamma emitting nuclides (including 1-131) and Sr-90. Strontium-90 activity was detected in both the indicator and control samples. This was a result of plant uptake of Sr-90 in soil as a result of past nuclear weapons testing. Concentrations of naturally occurring Be-7 and K-40 were consistent with those detected in previous years.
No other fission or activation products were detected. I Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued. This change resulted in a slight change in process and reporting of quarterly results. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation).
In conclusion, radioactive materials related to TMINS operations were detected in environmental samples, but the measured concentrations were low and consistent with measured effluents. The environmental sample results verified that the doses received by the public from TMINS effluents in 2014 were well below applicable dose limits and only a small fraction of the doses received from natural background radiation. Additionally, the results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.
Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2014 did not have any adverse effects on the health of the public or on the environment.
II. Introduction The Three Mile Island Nuclear Station (TMINS), consisting of two pressurized water reactors (PWR), is located on the northern end of Three Mile Island in the Susquehanna River approximately 2.5 miles south of Middletown in Lpndonderry Township, Dauphin County, Pennsylvania. TMI-1 is owned and operated by Exelon and became operational in 1974. TMI-2 is operated by GPU Nuclear, Inc. and owned by Metropolitan Edison (50%), Pennsylvania Electric (25%) and Jersey Central Power & Light (25%). TMI-2 became operational in 1978 and was shut down following the 1979 accident. At the end of 1993 TMI-2 was placed in a condition called Post-Defueling Monitored Storage. TMI-2 is maintained by Exelon under contract with GPU Nuclear.
A Radiological Environmental Monitoring Program (REMP) for TMINS was initiated in 1974. This report covers those analyses performed by Teledyne Brown Engineering (TBE), Landauer and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2014 through 31 December 2014.
A. Objective of the REMP The objectives of the REMP are to:
- 1. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
- 2. Provide data on measurable levels of radiation and radioactive materials in the site environs.
- 3. To verify inplant controls for the containment of radioactive materials.
- 4. To determine buildup of long-lived radionuclides in the environment and changes in background radiation levels.
- 5. To provide reassurance to the public that the program is capable of adequately assessing impacts and identifying noteworthy changes in the radiological status of the environment.
- 6. To fulfill the requirements of the TMI-1 and TMI-2 Technical Specifications.
B. Implementation of the Objectives The implementation of the objectives is accomplished by:
- 1. Identifying significant exposutre pathways.
- 2. Establishing baseline radiological data of media within those pathways.
- 3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.
Ill. Program Description A. Sample Collection Samples for the TMINS REMP were collected for Exelon by Normandeau Associates, RMC Environmental Services Division (RMC). This section describes the general collection methods used by RMC to obtain environmental samples for the TMINS REMP in 2014. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by RMC are listed in Table B-3.
Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, effluent water, fish and sediment. Two gallon water samples were collected monthly from continuous samplers located at two surface water locations (J1-2 and Q9-1), three drinking water locations (G15-2, G15-3 and Q9-1), and one effluent water location (KM-1). A composite of weekly grab samples at one surface water location (A3-2) were collected. The control locations were A3-2 and Q9-1. All groundwater and storm water results are now being reported in the ARGPPR, Appendix F. All water samples were collected in unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, bottom feeders and predators, were collected semiannually at an upstream control (BKG) and a downstream Indicator (IND) location.
Location IND could be affected by TMINS' effluent releases. Sediment samples composed of recently deposited substrate were collected semiannually at three locations (A1-3, J2-1 and KM-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 Ihy 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, FI-3, G2-1, H3-1, M2-1 and Q15-1). The control location was Q15-1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.
Terrestrial Environment The terrestrial environment was evaluated by performing radiological analyses on samples of milk and food product. Milk samples were collected biweekly at five locations (E2-2, F4-1, G2-1, K15-3 and P4-1) from March through November, and monthly from December through February. The control location was K1 5-3. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite and shipped promptly to the laboratory.
Food products were collected monthly at three locations (B10-2, E1-2 and H1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2 and H1-2). B10-2 was the control location for both annual and monthly sampling. Five different kinds of vegetation samples and ten different kinds of vegetation leaves were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Ambient Gamma Radiation Beginning in 2012, Exelon changed the type of dosimetry used for the Radiological Environmental Monitoring Program (REMP). Optically Stimulated Luminescent Dosimetry (OSLD) were deployed and Thermo-luminescent Dosimetry (TLD) were discontinued. This change may result in a step change in readings, up or down, depending on site characteristics. The relative comparison to control locations remains valid. OSLD technology is different than that used in a TLD but has the same purpose (to measure direct radiation). The OSLDs were placed at locations on and around the TMINS site as follows:
A site boundary ring consisting of 19 locations (A1-4, B1-2, C1-2, D1-1, E1-4, F1-2, F1-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, 1-1I, M1-1, N1-3, P1-2, Q1-2 and R1-1) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from TMINS release.
I I An indicator rinq consisting of 60 locations (A3-1, A5-1, A9-3, B1-1, 12-1, 85-1, B10-1, C1-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, E1-2, E2-3, E5-1, E7-1, F1-1, F2-1, F5-1, F10-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, J1-1, J3-1, J5-1, J7-1 K2-1, K3-1, K5-1, K8-1, LI-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, N1-1, N2-1, N5-1, N8-1, P1-1, P2-1, P5-1, P8-1, Q1-1, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1 and R9-1) extending to approximately 10 miles from the site designed to measure possible exposures to close-in population.
The balance of 11 locations (D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, Lb5-1, N15-2, Q15-1 and R1 5-1) represent control areas.
The specific dosimeter locations were determined by the following criteria:
- 1. The presence of relatively dense population;
- 2. Site meteorological data taking into account distance and elevation for each of the sixteen-22 1/2 degree sectors around the site, where estimated annual dose from TMINS, if any, would be most significant;
- 3. On hills free from local obstructions and within sight of the vents (where practical);
- 4. And near the closest dwelling to the vents in the prevailing downwind direction.
Each station has two A120 3 :C Optically Stimulated Luminescence Dosimeters enclosed in plastic placed at each location in a frame located approximately three to six feet above ground level. Since each OSLD responds to radiation independently, this provides two independent detectors at each station.
B. Sample Analysis This section describes the general analytical methods used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the TMINS REMP in 2014. The analytical procedures used by the laboratories are listed in Table B-3.
In order to achieve the stated objectives the current program includes the following analyses:
- 1. Concentrations of beta emitters in drinking and effluent water and air particulates.
- 2. Concentrations of gamma emitters in surface, drinking, and effluent water, air particulates, milk, fish, sediment and food products.
- 3. Concentrations of tritium in surface, drinking and effluent water.
- 4. Concentrations of 1-131 in surface, drinking and effluent water, air, milk and food products.
- 5. Concentrations of strontium in effluent water, fish, milk and food products.
- 6. Ambient gamma radiation levels at various site environs.
C. Data Interpretation Data were compared to previous years' operational data for consistency and trending. In addition, comparison to pre-operational data is sometimes made. For the purpose of this report, TMINS was considered operational at initial criticality. Several factors were important in the interpretation of the data:
- 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required TMINS detection capabilities for environmental sample analysis.
The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.
- 2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity~was not detected.
Gamma spectroscopy results for each type of sample were grouped as follows:
For surface, drinking, and effluent water 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.
For fish eight nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134 and Cs-137 were reported.
For sediment six nuclides, K-40, Mn-54, Co-58, Co-60, Cs-134 and Cs-137 were reported.
For air particulate eight nuclides, Be-7, Mn-54, Co-58, Co-60, Nb-95, Zn-95, Cs-134 and Cs-137 were reported.
For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-140 and La-140 were reported.
For food products five nuclides, Be-7, K-40, 1-131, Cs-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 2014 the TMINS REMP had a sample recovery rate in excess of 99%.
Issue Reports (IR) were initiated to document significant exceptions and missing samples. All exceptions are listed below:
AIR E2-1, E2-1Q
- 1. During the sampling period 2/7/14 to 2/14/14, the E1-2 pump malfunctioned but the timer continued to operate. Per procedure, the sample was invalid. The QC sample was sent to the primary lab for analysis. Station E1-2 pump was replaced on 2/14/14. (IR 1662133)
M2-1
- 2. During the sampling period 3/6/14 to 3/12/14, the pump malfunctioned but the timer continued to operate. Per procedure, the sample was invalid. The pump was repaired and installed on 3/13/14. (IR 1662133)
H3-1
- 3. For the sampling period 5/7/14 to 5/15/14, the sampler had a low run time and air volume due to power interruptions from a breaker trip.
Per procedure, sample was still valid and sent to the lab for analysis.
Offsite lab still achieved required LLD for iodine sampling and particulate results were normal. (IR 488572)
A3-1
- 4. For the sampling period 6/5/14 to 6/11/14, the timer was found reset for unknown reason. Per procedure, the sample was not valid and was not sent for analysis. The timer is currently functioning and the sampler was returned to service. (IR 1670228)
For the sampling period 6/11/14 to 6/19/14, the sample volume was lower than expected probably due to power interruptions from thunderstorms. Per procedure the sample was still valid and was sent for analysis. (IR 1670228)
F1-3
- 5. For the sampling period 6/25/14-7/3/14, the sampler was found not operating with the breaker tripped. The pump and timer were not operating. The sample volume was insufficient. The samples were not valid and were not sent for analysis. The pump was replaced on 7/4/14 and the sampler was returned to service. (IR 2115414)
For the sampling period 7/3/14-7/10/14, there was a lower volume due to pump replacement on 7/4/14. Samples were valid and sent for analysis.(IR 2115414)
E1-2Q
- 6. For the sampling period 7/17/14-7/24/14, the sampler was found with the air intake coupler sheared off due to a fallen tree limb. Per procedure, the sample volume was insufficient, and the samples were not valid. They were not sent for analysis. The sample station was repaired and the sampler was returned to service.(IR 2423641)
A3-1
- 7. For the sampling periods 8/21/14-8/28/14 and 8/29/14-9/4/14, the air samples had low volumes due to a breaker tripped due to a pump malfunction. Per procedure, samples were valid and sent to lab for analysis. The pump was replaced on 8/29/14 and returned to service.
M2-1
- 8. The sampler was found not running and did not operate due to a faulty breaker which required repair. This impacted two sampling periods.
For 11/20/14 to 11/26/14, the sample volume collected was sufficient per procedure, and the samples weye valid and sent for analysis. For 11/26/14 to 12/4/14, the sample volume was insufficient, and the samples were not valid per procedure. They were not sent to the laboratory for analysis. The sampler was repaired and returned to service on 12/4/14. (IR 2458509)
WATER
- 1. J1-2 Numerous hourly samples missed due to ice in the sampling tubing and river ice dislodging/submerging sample tubing anchor and buoy.
(IR 1617591/1662133) 12/31/13-1/7/14, 38 samples missed, sufficient volume, no grab required 1/7/14-1/14/14, 44 samples missed, sufficient volume, no grab required 1/14/14-1121/14, 22 samples missed, sufficient volume, no grab required 1/21/14-1/28/14, all but 1 sample missed, insufficient sample, grab sample required 1/28/14-2/4/14, 3L of sample collected, no grab sample taken due to hazardous conditions 2/4/14-2/11/14, all but 29 samples missed, insufficient sample, grab sample required 2/11/14-2/18/14, 77 samples missed, sufficient volume, no grab required 2/18/14-2/25/14, 21 samples missed, sufficient volume, no grab required 2/25/14-3/5/14, 117 samples missed, sufficient volume, no grab required 3/5/14-3/11/14, 17 samples missed, sufficient volume, no grab required 3/11/14-3/18/14, 30 samples missed, sufficient volume, no grab required 3/18/14-3/25/14, 20 samples missed, sufficient volume, no grab required 3/25/14-4/1/14, 27 samples missed, sufficient volume, no grab required
- 2. G15-2 During sampling period 2/25/14 to 3/5/14, sampler had an error, per data logger FLOAT/WEIGHT TRIPPED, 119 samples were collected.
Sufficient sample volume was collected and no grab sample required.
During sampling period 3/5/14 to 3/11/14, sampler was found with no LCD on ISCO and unable to retrieve data from data logger. The cause for the malfunction is not known. The electronics were replaced and the unit was calibrated on 3/11/14. Sufficient sample volume was collected and no grab sample required. (IR 1662133)
- 3. A3-2 Due to Swatara Creek being frozen over could not break ice and collect grab sample for 1/21/14-1/28/14 sampling period. January composite will consist of 3 rather than 4 samples. (IR 1617591)
- 4. Q9-1 Drinking Water For the sampling period 6/24/14-7/1/14, No weekly sample was available and a grab sample was collected. The suction strainer was found not submerged in the source bucket. Suspect strainer did not reseat in source water bucket after sample collection on 6/24/14.
During previous weekly sample collection the regular TMI REMP sampler was on vacation. Backup sampler was coached to self check and ensure first sample after collection operates correctly. A supplier FMS observation was submitted to document inadequate human performance. (IR 2115414)
- 5. G15-2 For the sampling periods 7/22/14-7/29/14 and 7/29/14-8/5/14, there were low collection volumes in the compositor. Sufficient sample was collected for analyses and no grab samples were required. The lost volume was due to ISCO hose problems and the hose was replaced on 7/30/14. (IR 2423641)
Milk
- 1. K15-3 Control The 7/23/14 sample initially showed activity for 1-131. The sample was recounted two days later and again the next day. Both recounts showed an increase in activity. These results are not congruent with normal 1-131 decay. A gamma scan was then performed and K-40 was detected. The non-decaying activity was attributed to this naturally occurring isotope. No 1-131 analysis result is available for this sample.
Dosimeter
- 1. A5-1 New pole recently installed. Old pole still standing but third quarter dosimeters not attached/found. The dosimeters were presumably removed and discarded by utility personnel during new pole installation. Fourth quarter dosimeters mounted on newly installed pole. (IR 2384588)
- 2. E5-1 New pole recently installed. Per personnel (who were present) old pole will be removed. Fourth quarter dosimeters mounted on newly installed pole instead. (IR 2384588)
Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
E. Program Changes No program changes for 2014.
IV. Results and Discussion A. Aquatic Environment
- 1. Surface Water Samples were taken weekly from a continuous sampler at two locations (J1-2 and Q9-1) and weekly grab samples from one location (A3-2). Weekly samples were composited on a monthly schedule. Of these locations only J1-2 located downstream could be affected by TMINS' effluent releases. The following analyses were performed:
Tritium Monthly samples from J1-2 and Q9-1 were analyzed for tritium activity (Table C-1.1, Appendix C). Positive tritium activity was detected in four of 12 samples at location J1-2 which is located immediately downstream of the TMINS effluent outfall. The concentrations ranged from 291 to 2,280 pCi/l. The increased tritium concentrations detected were a result of TMINS releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. The indicator surface water sample is taken just downstream of the liquid discharge outfall where mixing of liquid effluents with the river water is incomplete. More complete mixing is not achieved until liquid effluents pass over the York Haven Dam. This water is normally not consumed by humans. The concentrations detected were well below any regulatory limits (Figures C-1 and C-2, Appendix C).
Iodine Monthly samples from location A3-2 were analyzed for 1-131 activity (Table C-1.2, Appendix C). This is a control or background station sampled because known medical discharges of radiopharmaceuticals occur into the surface water upstream of TMI from a nearby hospital.
Gamma Spectrometrv Locations J1-2 and Q9-1 were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). All nuclides were less than the MDC.
- 2. Drinking Water Monthly samples were collected from continuous water samplers at three locations (G15-2, G15-3 and Q9-1). Two locations (G15-2 and G15-3) could be affected by TMINS' effluent releases. The following analyses were performed:
Gross Beta Monthly samples from all locations were analyzed for concentrations of gross beta (Tables C-I1.1, Appendix C). Gross beta activity was detected in 22 of 36 samples. The concentrations ranged from 1.9 to 4.2 pCi/l. Concentrations detected were consistent with those detected in previous years (Figure C-3, Appendix C).
Iodine Monthly samples from all locations were analyzed for concentrations of 1-131 (Table C-11.2, Appendix C). lodine-131 activity was not detected in any samples.
Tritium Monthly samples from all locations were analyzed for tritium activity (Table C-11.3, Appendix C). Tritium was not detected in any samples (Figures C-4, Appendix C).
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.4, Appendix C). All nuclides were less than the MDC.
- 3. Effluent Water Monthly samples were collected from a continuous water sampler at one location (K1-1). The following analyses were performed:
Gross Beta Monthly samples from location K1-1 were analyzed for concentrations of gross beta (Tables C-111.1, Appendix C). Gross beta was detected in all 12 samples. The concentrations ranged from 2.8 to 7.0 pCi/l. Concentrations detected were consistent with those detected in previous years.
Iodine-1 31 Monthly samples from location K1-1 were analyzed for concentrations of 1-131 (Tables C-111.1, Appendix C). lodine-131 was not detected in any of the samples.
Tritium Monthly samples from location K1-1 were analyzed for tritium activity (Table C-111.1, Appendix C). Tritium activity was detected in 4 of 12 samples. The concentrations ranged from 2,300 to 27,000 pCi/I. The elevated results were a result of TMI releasing radwaste treatment system effluent water under permitted discharges in accordance with NRC regulations. These results were from the liquid discharge mixing basin. The concentrations detected agree with those obtained from the TMINS Effluent Monitoring Program.
The concentrations were well below any regulatory limits. (Figure C-4, Appendix C)
Strontium Semiannual composite samples from location K1-1 were analyzed for Sr-89 and Sr-90 (Table C-I11.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <4.6 pCi/I for Sr-89 and at <0.9 pCi/I for Sr-90.
Gamma Spectrometry Samples from location K1-1 were analyzed for gamma emitting nuclides (Table C-I11.2, Appendix C). All nuclides were less than the MDC.
- 4. Storm Water Storm water results are now included in the Annual Radiological Groundwater Protection Program (ARGPPR), Appendix F.
- 5. Ground Water Groundwater results are now included in the Annual Radiological Groundwater Protection Program (ARGPPR), Appendix F.
- 6. Fish Fish samples comprised of bottom feeders and predators were collected at two locations (IND and BKG) semiannually. Location IND could be affected by TMINS' effluent releases. The following analyses were performed:
Strontium The edible portions of fish samples from both locations were analyzed for Sr-90 (Table C-IV.1, Appendix C). No strontium activity was detected. The highest MDC was calculated at <3.7 pCi/kg wet for Sr-90.
Gamma Spectrometrv The edible portions of fish samples from both locations were analyzed for gamma emitting nuclides (Table C-IV.2, Appendix C).
Naturally occurring K-40 was found in all fish samples and ranged from 2,411 to 3,869 pCi/kg wet and was consistent with levels detected in previous years. No fission or activation products were detected.
- 7. Sediment Aquatic sediment samples were collected at three locations (A1-3, J2-1 and K1-3) semiannually. Of these locations two (J2-1 and KI-3) could be affected by TMINS' effluent releases. The following analysis was performed:
Gamma Spectrometrv Sediment samples from all locations were analyzed for gamma emitting nuclides (Table C-V.1, Appendix C). Potassium-40 was found in all sediment samples and ranged from 8,369 to 17,610 pCi/kg dry. No other fission or activation products were detected.
Cesium-1 37 is occasionally found in sediment at very low levels (just above LLD) and is not distinguishable from background levels (Figure C-5, Appendix C).
B. Atmospheric Environment
- 1. Airborne Particulates
- a. Air Particulates Continuous air particulate samples were collected from seven locations on a weekly basis. Six locations (A3-1, E1-2, F1-3, G2-1, H3-1 and M2-1) were indicator stations located in the highest D/Q sectors and the nearest communities to TMI. One sample (Q15-1) represents the control location at a remote distance from TMINS. The following analyses were performed:
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-VI.1 and C-VI.2, Appendix C).
Detectable gross beta activity was observed at all locations.
Comparison of results aid in determining the effects, if any, resulting from the operation of TMINS. The results from the closest to the site boundary locations (Group I) ranged from 8 to 32 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3 . The results from the intermediate offsite locations (Group II) ranged from 6 to 38 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . The results from the Control location (Group Ill) ranged from 9 to 31 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . Comparison of the 2014 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 2014 indicate no notable differences between indicator and control stations (Figure C-7, Appendix C).
Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-VI.3, Appendix C).
Naturally occurring Be-7 due to cosmic ray activity was detected in 26 samples. These concentrations ranged from 37 to 102 E-3 pCi/m3. All other nuclides were less than the MDC.
- b. Airborne Iodine Continuous air samples were collected from seven (A3-1, E1-2, F1-3, G2-1, H3-1, M2-1 and Q15-1) locations and analyzed weekly for 1-131 (Table C-VII.1, Appendix C). All results were less than the MDC for 1-131.
- 2. Terrestrial
- a. Milk Samples were collected from five locations (K1 5-3, E2-2, F4-1 G2-1 and P4-1) biweekly March through November and monthly December through February. The following analyses were performed:
Iodine-1 31 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VIII.1, Appendix C). The K15-3 sample collected on 07/23/14 initially showed activity for 1-131. The sample was recounted two days later and again the next day. Both recounts showed an increase in activity. These results are not congruent with normal 1-131 decay. A gamma scan was then performed and K-40 was detected. The non-decaying activity was attributed to this naturally occurring isotope. No 1-131 analysis result is available for this sample. All other results were less than the MDC.
Strontium Milk samples from all locations were composited quarterly and analyzed for Sr-89 and Sr-90 (Table C-VIII.2, Appendix C). No Sr-89 or Sr-90 activity was detected. Occasionally Sr-90 is detected and is consistent with those detected in the pre-operational years (Figure C-8, Appendix C).
Gamma Spectrometry Milk samples from all locations were analyzed for concentrations of gamma emitting nuclides (Table C-VIII.3, Appendix C).
Naturally occurring K-40 activity was found in all samples.
The concentrations ranged from 636 to 1,517 pCi/l. All other nuclides were less than the MDC.
- b. Food Products Food products were collected monthly at three locations (B10-2, E1-2 and H1-2), in lieu of milk sampling and annually from the four food product groups at two locations (B10-2, E1-2 and H1-2). B10-2 was the control location for both annual and monthly sampling. The following analyses were performed:
Strontium Twenty-six of 32 food product samples were analyzed for concentrations of Sr-90 (Table C-IX.1, Appendix C).
Strontium-90 activity was detected in 11 of 26 samples. The concentrations ranged from 2 to 18 pCi/kg wet.
Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C).
Naturally occurring Be-7 due to cosmic ray activity was detected in 14 of 32 samples. These concentrations ranged from 353 to 2,515 pCi/I. Naturally occurring K-40 activity was found in all samples. The concentrations ranged from 1,672 to 8,693 pCi/I. All other nuclides were less than the MDC.
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Optically Stimulated Luminescence Dosimeter (OSLD). Ninety OSLD locations were established around the site. Results of OSLD measurements are listed in Tables C-X.1 to C-X.3, Appendix C All of the OSLD measurements were below 40 mR/quarter, with a range of 16.2 to 37.4 mR/standard quarter. A comparison of the Site Boundary and Indicator data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 averaged higher than indicator stations. Locations D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1 and R15-1 have a historical high bias, but tracked with the data from all three groups this bias is most likely due to radon and other naturally occurring nuclides, e.g. K-40, emanating from the ground.
D. Land Use Survey A Land Use Survey conducted in the July through November 2014 growing season around the Three Mile Island Nuclear Station (TMINS) was performed by Normandeau Associates, RMC Environmental Services Division for Exelon to comply with Sections 8.2 of the Plant's Offsite Dose Calculation Manual (ODCM). The purpose of the survey was to document the nearest resident, milk-producing animal and garden of greater than 500 ft2 in each of the sixteen 22 /2 degree sectors around the site. For 2014, a meat census was also performed. The results of these surveys are summarized below.
Distance in Miles from the TMINS Reactor Buildings Sector Residence Garden Milk Farm Meat Animal Miles Miles Miles Miles 1 N 1.1 1.9 2.1 2.1 2 NNE 0.7 1.2 - 2.4 3 NE 0.5 0.7 4.2 2.4 4 ENE 0.5 0.5 4.5 1.1 5 E 0.4 0.5 1.1 1.1 6 ESE 1.1 1.2 3.2 1.1 7 SE 0.7 1.6 1.4 1.4 8 SSE 0.7 0.8 - 1.8 9 S 2.3 2.7 3.3 10 SSW 0.6 2.5 4.9, 14.4 4.9 11 SW 0.5 1.0 -
12 WSW 0.5 1.3 13 W 0.7 1.4 - -
14 WNW 0.4 1.7 3.7 2.4 15 NW 0.4 1.2 - -
16 NNW 1.1 2.4 -
E. Radiological Impact of TMINS Operations An assessment of potential radiological impact indicated that radiation doses to the public from 2014 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of radiation. The 2014 whole body dose potentially received by an assumed maximum exposed individual from TMI-1 and TMI-2 liquid and airborne effluents was conservatively calculated to be 0.12 mrem. This dose is equivalent to 0.04% of the dose that an individual living in the TMI area receives each year from natural background radiation.
- 1. Determination of Radiation Doses to the Public Dose assessments can be performed by using either effluent data and an environmental transport model or environmental sample data. To the extent possible, doses to the public are based on the direct measurement of dose rates from external sources and the measurement of radionuclide concentrations in environmental media which may contribute to an internal dose of radiation. Optically Stimulated Luminescent Dosimetry (OSLDs) positioned in the environment around TMINS provide measurements to determine external radiation doses to humans. Samples of air, water and food products are used to determine internal doses.
The quantity of radioactive materials released during normal operations are typically too small to be measured once distributed in the offsite environment. Therefore, the potential offsite doses are more effectively calculated for TMINS operations using a computerized model that predicts concentrations of radioactive materials in the environment and subsequent radiation doses based on measured effluents.
Doses are calculated using a model that incorporates the guidelines and methodology set forth by the USNRC in Regulatory Guide 1.109 and NUREG 0133. Due to the conservative assumptions that are used in the model, the calculated doses are generally higher than the doses based on actual environmental sample concentrations.
Therefore, the model predicts doses that are higher than actual doses received by people. The type and amount of radioactivity released from TMINS is calculated using measurements from effluent sample analyses.
Airborne releases are diluted and carried away from the site by atmospheric diffusion, which continuously acts to disperse radioactivity. Variables that affect atmospheric dispersion include wind speed, temperature at different elevations, terrain, and shift in wind direction. A weather station on the north end of TMI is linked to a data logger that records the meteorological data.
Computer models also are used to predict the downstream dilution and travel times for liquid releases into the Susquehanna River.
Actual monthly Susquehanna River flows are obtained from the USGS Stream gauging station 01570500 located at Harrisburg, PA.
The human exposure pathways also are included in the model and are depicted in Figure 1. The exposure pathways that are considered for the discharge of TMINS liquid effluents are consumption of drinking water and fish. The exposure pathways considered for the discharge of TMINS airborne effluents are plume exposure, inhalation, cow milk consumption, fruit and vegetable consumption, and meat consumption.
When determining the dose to humans, it is necessary to consider all applicable pathways and all exposed tissues, summing the dose from each to provide the total dose for each organ as well as the whole body from a given radionuclide. Dose calculations involve determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides taken into the body, the metabolism of the radionuclide in the body must be known along with the physical characteristics of the nuclide such as energies, types of radiations emitted and half-life. The dose assessment model also contains dose conversion factors for the radionuclides for each of four age groups (adults, teenagers, children and infants) and eight organs (total body, thyroid, liver, skin, kidney, lung, bone and GI tract).
- 2. Result of Dose Calculations The maximum hypothetical doses due to 2014 TMI-1 and TMI-2 liquid and airborne effluents are summarized in Tables 1 and 2.
Table 1 compares the calculated maximum hypothetical individual doses to the USNRC 10 CFR 50 App. I guidelines. This table also compares the calculated doses (to an individual of the public) from effluents and direct radiation to USEPA 40 CFR 190 dose limits.
Table 2 presents the maximum hypothetical whole body doses to an individual. As shown in Table 1, the doses calculated for 2014 operations at TMINS were well below the Federal dose limits (USEPA 40 CFR 190) and the guidelines of USNRC 10 CFR 50 App. I. This conclusion was supported by radionuclide concentrations detected in actual environmental samples.
Doses from natural background radiation provide a baseline for assessing the potential public health significance of radioactive effluents. Natural background radiation from cosmic, terrestrial and natural radionuclides in the human body (not including radon),
averages about 81 mrem/yr (Ref. 5). Additionally, the average individual living in the United States receives an annual dose of about 2,760 mrem to the lung from natural radon gas. This lung dose is considered to be equivalent to a whole (or total) body dose of 230 mrem (Ref. 5). Therefore, the average person in the United States receives a whole body dose of about 311 mrem/yr from natural background radiation sources.
As shown on Table 2, the maximum hypothetical whole body dose received by an individual from 2014 TMI-1 and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.12 mrem. This dose is equivalent to 0.04% percent of the dose that an individual living in the TMI area receives each year from natural background radiation (311 mrem).
The low doses calculated for 2014 TMINS operations were the result of efforts to maintain releases "as low as reasonably achievable" (ALARA).
In conclusion, radioactive materials related to 2014 TMINS operations were detected in environmental samples, but the measured concentrations were low and consistent with measured effluents. The environmental sample results verified that the doses received by the public from TMINS effluents in 2014 were well below applicable dose limits and only a small fraction of the doses received from natural background radiation. Additionally, the results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels.
Therefore, based on the results of the radiological environmental monitoring program (REMP) and the doses calculated from measured effluents, TMINS operations in 2014 did not have any adverse effects on the health of the public or on the environment.
TABLE 1 Calculated Maximum Hypothetical Doses to an Individual from 2014 TMI-1 and TMI-2 Liquid and Airborne Effluents Maximum Hypothetical Doses To An Individual USNRC 10 CFR 50 APP. I Calculated Dose Guidelines (mrem/yr)
(mrem/yr) TMI-1 TMI-2 From Radionuclides 3 total body, or 4.57E-3 3.87E-4 In Liquid Releases 10 any organ 4.63E-3 6.15E-4 From Radionuclides In 5 total body, or 1.85E-4 0*
Airborne Releases (Noble Gases) 15 skin 2.72E-4 0*
From Radionuclides In Airborne 15 any organ I.IOE-1 5.63E-5 Releases (Iodines, Tritium and Particulates)
- No noble gases were released from TMI-2.
USEPA Calculated Dose 40 CFR 190 (mrem/yr)
Limits TMI-1 and TMI-2 (mrem/yr) Combined**
Total from Site 75 thyroid 0.69 25 total body 0.77 or other organs
- *This sums together TMI-1 and TMI-2 maximum doses regardless of age group for different pathways.
The combined doses include those due to radioactive effluents and direct radiation from TMINS. The direct radiation dose is calculated from environmental dosimeter data. For this calculation, exposure is assumed to be equal to dose.
The direct radiation dose from 2014 TMINS operations was 0.65 mrem. This dose was based on a maximum net fence-line exposure rate and a shoreline/fence-line occupancy factor of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> (Regulatory Guide 1.109). The combination of the maximum organ dose from TMI-I and TMI-2 effluents (0.12 mrem) and the dose from direct radiation (0.65 mrem) yielded a maximum hypothetical dose of 0.77 mrem.
- 24 -
TABLE 2 Calculated Whole Body Doses to the Maximum Individual I From 2014 TMI-1 and TMI-2 Liquid and Airborne Effluents Calculated Maximum Individual Whole Body Dose (mrem/yr)
TMI-I TMI-2 From Radionuclides In Liquid Releases 4.57E-3 3.87E-4 From Radionuclides in Airborne Releases 1.85E-4 0*
(Noble Gases)
From Radionuclides In Airborne 3.03E-2 5.63E-5 Releases (lodines, Tritium and Particulates)
- No noble gases were released from TMI-2.
Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations: 0.12 mrem/yr Individual Whole Body Dose Due to Natural Background Radiation (1) 311 mrem/yr (1) NCRP 160-(2009)
Figure 1 Exposure Pathways For Radlonuclides Routinely Released From TMINS I
I PREDOMINANT RADIONUCLIDES!
NOBLE GASES (Xe,Kr)
ACTIVATION PRODUCTS.(Co-60, Mn.54)
Plume exposure Shoreline exposure RADIOIODINES (1-131, 1-133)
Inhalation and consumption of milk, RADIOCESIUMS (Cs-134, Cs-137) water, fruits, and vegetables Shoreline exposure and consumption of milk, meat, fish, water, fruits, and vegetables RADIOSTRONTIUMS (Sr-89, Sr-90)
Consumption of milk, meat. TR(TIUM (H-3) fruits, and vegetables Inhalation and consumption of water, milk, fruits, and vegetables I
F. Errata Data There is no errata data for 2014.
G. Summary of Results - Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:
- 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
- 2. ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
- 3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.
The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.
In reviewing our environmental inter-laboratory crosscheck programs, we identified 1) duplication of efforts on some matrices and isotopes and 2) that we are performing crosscheck samples on some matrices and isotopes that we do not perform for clients.
Since the DOE MAPEP is designed to evaluate the ability of analytical facilities to cprrectly analyze for radiological constituents representative of those at DOE sites, the needed changes were made to the MAPEP program. Therefore, the following isotopes were removed from the MAPEP program:
Soil - gamma - will be provided by Analytics twice per year, starting in 2015. For 2014, one soil gamma is provided by MAPEP, the 2 nasoil gamma is provided by Analytics.
AP - gamma - is currently provided by Analytics.
Water - gamma, H-3, Sr-90, uranium, gross alpha and gross beta currently provided by ERA.
MAPEP evaluates non-reported (NR) analyses as failed if they were reported in the previous series.
For the TBE laboratory, 163 out of 169 analyses performed met the specified acceptance criteria. Six analyses (Ni-63, K-40 and 1-131 in water, and two Sr-90s and one Gross Alpha in AP samples) did not meet the specified acceptance criteria for the following reasons:
- 1. Teledyne Brown Engineering's MAPEP March 2014 Ni-63 in water result of 32.7 +/- 1.69 Bq/L was overlooked when reporting the data but would have passed the acceptance range of 23.9 - 44.2 Bq/L. NCR 14-04
- 2. Teledyne Brown Engineering's MAPEP March 2014 K-40 in water result of 1.63 +/- 2.49 Bq/L was overlooked when reporting the data but would have passed the false positive test. NCR 14-04
- 3. Teledyne Brown Engineering's ERA November 2014 1-131 in water result of 15.8 pCi/L was lower than the known value of 20.3 pCi/L, failing below the lower acceptance limit of 16.8.
The result was evaluated as failed with a found to known ratio of 0.778. No cause could be found for the slightly low result. All ERA 1-131 evaluations since 2004 have been acceptable. NCR 14-08
- 4. Teledyne Brown Engineering's MAPEP March 2014 Sr-90 in AP result of 0.822 Bq/sample was lower than the known value of 1.18 Bq/sample, failing below the lower acceptance limit of 0.83 Bq/sample. The rerun result was still low, but fell within the lower acceptance range of 0.836. The rerun result was statistically the same number as the original result. No cause could be found for the slightly low results.
NCR 14-04
- 5. Teledyne Brown Engineering's MAPEP September 2014 Sr-90 in AP result of 0.310 Bq/sample was lower than the known value of 0.703 Bq/shmple. The gravimetric yield of 117% was very high (we normally see yields of 60% to 70
%) and could account for the low activity. NCR 14-09
- 6. Teledyne Brown Engineering's MAPEP September 2014 Gr-Alpha in AP result of 0.153 Bq/sample was lower than the known value of 0.53 Bq/sample. The AP sample was counted on the wrong side. The AP was flipped over and recounted with acceptable results. NCR 14-09 For the EIML laboratory, 85 of 90 analyses met the specified acceptance criteria. Five analyses (Water - Pu-238, Pu-239, Fe-55; AP - Co-57; Soil, Cs134) did not meet the specified acceptance criteria for the following reasons:
- 1. Environmental Inc., Midwest Laboratory's MAPEP February 2014 water Pu-238 result of 1.28 Bq/L was higher than the known value of 0.83 Bq/L, exceeding the upper control limit of 1.08 Bq/L. The high bias on the plutonium was traced to contamination from a newly purchased standard. The result of the reanalysis with the new tracer was 0.68, which fell within the acceptance criteria.
- 2. Environmental Inc., Midwest Laboratory's MAPEP February 2014 water Pu-239/240 result of 0.91 Bq/L was higher than the known value of 0.68 Bq/L, exceeding the upper control limit of 0.88 Bq/L. The high bias on the plutonium was traced to contamination from a newly purchased standard.
The result of reanalysis with the new tracer was 0.66 Bq/L, which fell within the acceptance criteria.
- 3. Environmental Inc., Midwest Laboratory's MAPEP February 2014 AP Co-57 result of 1.60 +/- 0.05 Bq/total sample failed the false positive test. Interference from the Eu-1 52 resulted in the misidentification of Co-57.
- 4. Environmental Inc., Midwest Laboratory's MAPEP February 2014 soil Cs-134 result of 6.10 +/- 1.80 Bq/kg failed the false positive test. Long sample counting time lead to interference from naturally occurring Bi-214 in the sample matrix with a close spectral energy.
- 5. Environmental Inc., Midwest Laboratory's MAPEP August 2014 water Fe-55 result of 55.10 +/- 14.80 Bq/L was higher than the known value of 31.50 Bq/L, exceeding the upper control limit of 41.00 Bq/L. The result of the reanalysis of tFe-55 was 32.63 +/- 16.30 Bq/L, which fell within thp acceptance criteria.
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.
V. References
- 1. Three Mile Island Nuclear Station, Unit 1, Technical Specifications, DPR 50.
- 2. Three Mile Island Nuclear Station, Unit 2, PDMS Technical Specifications, DPR 73.
- 3. Radiation Management Corporation. "Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1, 1974 - June 5, 1974." RMC-TR-75-17, January 1975.
- 4. Exelon. "Three Mile Island Nuclear Station Offsite Dose Calculation Manual (ODCM)."
- 5. National Council of Radiation Protection and Measurements Report No.
160. "Ionizing Radiation Exposure of the Population of the United States."
2009.
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
Intentionally left blank TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER H-3 24 2000 935 <LLD 935 J1-2 INDICATOR 0 (PCI/LITER) (4/12) (4/12) WEST SHORE; TMI (291/2280) (291/2280) 0.5 MILES S OF SITE 1-131 12 I NA <LLD 0 GAMMA 24 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0 ZR-95 30 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER CS-134 15 <LLD <LLD (PCI/LITER)
CS-137 18 <LLD <LLD BA-140 60 <LLD <LLD
>)
LA-140 15 <LLD <LLD 0 DRINKING WATER GR-B 36 3.1 2.1 3.1 G 15-2 INDICATOR 0 (PCI/LITER) (16/24) (6/12) (11/12) WRIGHTS WATER SUPPLY (2.3/4.2) (1.9/2.3) (2.3/4.2) 13.3 MILES SE OF SITE 1-131 36 I <LLD <LLD H-3 36 2000 <LLD <LLD 0 GAMMA 36 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER FE-59 30 <LLD <LLD 0 (PCI/LITER)
CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0 ZR-95 30 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA- 140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER GR-B 12 4 5.3 NA 5.3 KI-I INDICATOR 0 (PCI/LITER) (12/12) (12/12) MAIN STATION LIQ. DISCHARGE (2.8/7.0) (2.8/7.0) ONSITE 1-131 12 I <LLD NA H-3 12 2000 11593 NA 11593 KI-I INDICATOR 0 (4/12) (4/12) MAIN STATION LIQ. DISCHARGE (2300/27000) (2300/27000) ONSITE SR-89 5 <LLD NA SR-90 2 2 <LLD NA 0 GAMMA 12 MN-54 15 <LLD NA 0 CO-58 15 <LLD NA FE-59 30 <LLD NA CO-60 15 <LLD NA 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS EFFLUENT WATER ZN-65 30 <LLD NA 0 (PCI/LITER)
NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 BA-140 60 <LLD NA 0 LA- 140 15 <LLD NA 0 BOTTOM FEEDER SR-90 10 <LLD <LLD 0 (PCVKG WET)
GAMMA 4 K-40 NA 3451 3188 3451 INDB INDICATOR 0 (2/2) (2/2) (2/2) YORK HAVEN DAM (3032/3869) (2512/3864) (3032/3869) DOWNSTREAM OF DISCHARGE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER MN-54 130 <LLD <LLD 0 (PCI/KG WET)
CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 PREDATOR SR-90 10 <LLD <LLD 0 (PCI/KG WET)
GAMMA 4 K-40 NA 3119 2809 3119 INDP INDICATOR 0 (2/2) (2/2) (2/2) YORK HAVEN DAM (2434/3804 (2411/3206) (2434/3804) DOWNSTREAM OF DISCHARGE THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014
. NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS PREDATOR MN-54 130 <LLD <LLD 0 (PCI/KG WET)
CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 SEDIMENT GAMMA 7 (PCI/KG DRY) K-40 NA 12573 13155 17610 EDCB INDICATOR 0 (5/5) (2/2) (1/1) STORM WATER BASIN (8369/17610) (11700/14610) 0.2 MILES SE OF SITE MN-54 NA <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT CO-58 NA <LLD <LLD 0 (PCI/KG DRY)
CO-60 NA <LLD <LLD 0 CS-134 150 <LLD <LLD 0 00 CS-137 180 <LLD <LLD 0 AIR PARTICULATE GR-B 360 10 17 17 18 A3-1 INDICATOR 0 (E-3 PCI/CU.METER) (305/308) (50/52) (51/51) MIDDLETOWN (6/38) (9/31 ) (8/35) 2.6 MILES N OF SITE GAMMA 28 BE-7 NA 68 63 82 A3-1 INDICATOR 0 (22/24) (4/4) (4/4) MIDDLETOWN (37/102) (49/95) (68/95) 2.6 MILES N OF SITE MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE NB-95 NA <LLD <LLD 0 (E-3 PCI/CU.METER)
ZR-95 NA <LLD <LLD 0 CS-134 50 <LLD <LLD CS-137 60 <LLD <LLD 0 AIR IODINE GAMMA 360 (PCI/CU.M) 1-131 70 <LLD <LLD 0 MILK 1-131I 114 I <LLD <LLD 0 (PCI/LITER)
SR-89 20 5 <LLD <LLD SR-90 20 2 <LLD <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK GAMMA 115 (PCI/LITER) K-40 NA 1265 1251 1371 F4-1 INDICATOR (92/92) (23/23) (23/23) TURNPIKE ROAD FARM (636/1517) (1028/1448) (1049/1517) 3.0 MILES ESE OF SITE CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0
,0 BA-140 60 <LLD <LLD LA-140 15 <LLD <LLD 0 VEGETATION SR-90 26 10 7 12 12 B 10-2 CONTROL 0 (PCI/KG WET) (8/13) (3/13) (3/13) MILTON HERSHEY SCHOOL (2/13) (4/18) (4/18) 10.1 MILES NNE OF SITE GAMMA 32 BE-7 NA 859 1431 1431 B 10-2 CONTROL (8/16) (6/16) (6/16) MILTON HERSHEY SCHOOL (353/1944) (795/2515) (795/2515) 10. 1 MILES NNE OF SITE K-40 NA 4244 4257 4531 HI-2 INDICATOR 0 (16/16) (16/16) (12/12) RED HILL MARKET, ALONG ROUTE 441 (2680/6885) (1672/8693) (2738/6885) 1.0 MILES SSE OF SITE 1-131 60 <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE THREE MILE ISLAND NUCLEAR STATION, 2014 NAME OF FACILITY: THREE MILE ISLAND NUCLEAR STATION DOCKET NUMBER: 50-289 & 50-320 2014 LOCATION OF FACILITY: MIDDLETOWN COUNTY PA REPORTING PERIOD:
INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION CS-134 60 <LLD <LLD 0 (PCI/KG WET)
CS-137 80 <LLD <LLD 0 DIRECT RADIATION OSLD-QUARTERLY 359 NA 22.1 23.6 35.6 F1-2 INDICATOR 0 (MILLI-ROENTGEN/STD.MO.) (315/315) (44/44) (4/4) REACTOR BUILDING ON TOP OF DYKE MIDWAY (16.2/37.4) (19.1/31.8) (32.8/37.4) 0.5 MILES ESE OF SITE C,.
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUE FRACTION OF DETECTABLE MEASUREMENT AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESIS (F)
Intentionally left blank APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS
Intentionally left blank TABLE B-i: Location Designation and Identification System for the Three Mile Island Nuclear Station XYY-Z- General code for identification of locations, where:
X - Angular Sector of Sampling Location. The compass is divided into 16 sectors of 22 1/2 degrees each with center at Three Mile Island's Units 1 and 2 off-gas vents. Sector A is centered due North, and others are alphabetical in a clockwise direction.
YY - Radial Zone of Sampling Location in miles.
Z - Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.
B-i
TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Sample Station Map Distance Medium Code Number (miles) Azimuth Description AQS Al -3 0.5 3590 N of site off north tip of TMI in Susquehanna River ID A1-4 0.3 60 N of Reactor Building on W fence adjacent to North Weather Station, TMI APAIID A3-1 2.7 3570 N of site at Mill Street Substation SW A3-2 2.7 3560 N of site at Swatara Creek, Middletown ID A5-1 4.4 30 N of site on Vine Street Exit off Route 283 ID A9-3 8.0 2o N of site at Duke Street Pumping Station, Hummelstown ID Bi-1 0.6 250 NNE of site on light pole in middle of North Bridge, TMI ID B1-2 0.4 230 NNE of Reactor Building on top of dike, TMI ID B2-1 1.9 170 NNE of site on Sunset Dr. (off Hillsdale Rd.)
ID B5-1 4.9 190 NNE of site at intersection of School House and Miller Roads ID B10-1 9.2 210 NNE of site at intersection of West Areba Avenue and Mill Street, Hershey FP B10-2 10 310 NNE of site at Milton Hershey School, Hershey ID C1-1 0.7 370 NE of site along Route 441 N ID Cl-2 0.3 50' NE of Reactor Building on top of dike, TMI ID C2-1 1.5 440 NE of site at Middletown Junction ID C5-1 4.7 430 NE of site on Kennedy Lane ID C8-1 7.1 480 NE of site at Schenk's Church on School House Road AQF Control - All locations where finfish are collected above Dock St.
Dam, Harrisburg ID D1-1 0.2 76' ENE of Reactor Building on top of dike, TMI ID D1-2 0.5 67' ENE of site off Route 441 along lane between garden center and residence ID D2-2 1.6 740 ENE of site along Hillsdale Rd. (S of Zion Rd.)
ID D6-1 5.2 660 ENE of site off Beagle Road ID D15-1 10.8 640 ENE of site along Route 241, Lawn AP, Al, ID, FP E1-2 0.4 970 E of site at TMI Visitor's Center ID E1-4 0.2 970 E of Reactor Building on top of dike, TMI M E2-2 1.1 960 E of site at farm on Pecks Road ID E2-3 2.0 970 E of site along Hillsdale Rd. (N of Creek Rd.)
ID E5-1 4.7 820 E of site at intersection of North Market Street (Route 230) and Zeager Road ID E7-1 6.7 880 E of site along Hummelstown Street, Elizabethtown ID F1-1 0.5 1170 ESE of site near entrance to 500 kV Substation ID F1-2 0.2 1120 ESE of Reactor Building on top of dike midway within ISWSF, TMI AP, Al F1-3 0.6 1120 ESE of site in 500 kV Substation ID F1-4 0.2 1220 ESE of Reactor Building on top of dike, TMI ID F2-1 1.3 1190 ESE of site along Engle Road M F4-1 3.2 1040 ESE of site at farm on Turnpike Road ID F5-1 4.7 109° ESE of site along Amosite Road ID F10-1 9.4 1120 ESE of site along Donegal Springs Road, Donegal Springs ID F25-1 3 22 1060 ESE of site at intersection of Steel Way and Loop Roads, Lancaster ID G1-2 1 0.7 1450 SE of site along Route 441 S ID G1 -3 1 0.2 1300 SE of Reactor Building on top of dike, TMI ID G1-5 0.3 143' SE of Reactor Building on top of dike, TMI ID G1-6 0.3 1390 SE of Reactor Building on top of dike, TMI Al, AP, M G2-1 2 1.4 1260 SE of site at farm on Becker Road ID G2-4 2 1.7 1380 SE of site on Becker Road ID G5-1 2 4.8 1310 SE of site at intersection of Bainbridge and Risser Roads ID G10-1 3 9.7 1280 SE of site at farm along Engles Tollgate Road, Marietta ID G15-1 3 14.4 1260 SE of site at Columbia Water Treatment Plant DW G15-2 3 13.3 1290 SE of site at Wrightsville Water Treatment Plant DW G15-3 3 15.7 1240 SE of site at Lancaster Water Treatment Plant B-2
TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Sample Station Map Distance Medium Code Number (miles) Azimuth Description ID H1-1 0.5 1670 SSE of site, TMI FP H1-2 1.0 151
- SSE of site along Route 441, Red Hill Market AP, Al, ID H3-1 2 2.2 1600 SSE of site in Falmouth-Collins Substation ID H5-1 2 4.1 1580 SSE of site by Guard Shack at Brunner Island Steam Electric Station 0
ID H8-1 3 7.4 163 SSE of site along Saginaw Road, Starview ID H15-1 3 13.2 157* SSE of site at intersection of Orchard and Stonewood Roads, Wilshire Hills AQF Indicator - - All locations where finfish are collected downstream of the TMINS liquid discharge outfall ID J1-1 0.8 176° S of site, TMI SW J1-2 0.5 1880 S of site downstream of the TMINS liquid discharge outfall in Susquehanna River ID J1-3 0.3 1890 S of Reactor Building just S of SOB, TMI AQS J2-1 2 1.4 1790 S of site in Susquehanna River just upstream of the York Haven Dam ID J3-1 2 2.7 1790 S of site at York Haven/Cly ID J5-1 2 4.9 181 ° S of site along Canal Road, Conewago Heights ID J7-1 3 6.5 176° S of site off of Maple Street, Manchester ID J15-1 3 12.6 1830 S of site in Met-Ed York Load Dispatch Station EW K1-1 0.2 2100 On site at RML-7 Main Station Discharge Building AQS K1 -3 0.2 2120 SSW of site downstream of the TMINS liquid discharge outfall in the Susquehanna River ID K1-4 0.2 2090 SSW of Reactor Building on top of dike behind Warehouse 2, TMI ID K2-1 2 1.2 2000 SSW of site on S Shelley Island ID K3-1 2 2.0 2060 SSW of site along Rt. 262, N of Cly ID K5-1 2 4.9 2020 SSW of site along Conewago Creek Road, Strinestown ID K8-1 3 7.5 196' SSW of site at intersection of Coppenhaffer Road and Route 295, Zions View ID K15-1 3 12.8 2030 SSW of site behind McDonald's and next to child care center, Weiglestown M K15-3 3 14.4 2050 SSW of site at farm along S Salem Church Rd, Dover ID 1-1i 0.1 2360 SW of site on top of dike W of Mech. Draft Cooling Tower, TMI ID L1-2 0.5 221 SW of site on Beech Island ID L2-1 2 1.8 2240 SW of site along Route 262 ID L5-1 2 4.1 2280 SW of site at intersection of Stevens and Wilson Roads ID L8-1 3 8.0 2250 SW of site along Rohlers Church Rd., Andersontown ID L15-1 3 11.8 2260 SW of site on W side of Route 74, rear of church, Mt.
Royal ID M1-1 0.1 2500 WSW of Reactor Building on SE comer of U-2 Screenhouse fence, TMI ID M1-2 0.4 2520 WSW of site on E side of Shelley Island, Lot #157 AP, Al, ID M2-1 2 1.3 2560 WSW of site along Route 262 and adjacent to Fishing Creek, Goldsboro ID M5-1 2 4.3 2490 WSW of site at intersection of Lewisberry and Roxberry Roads, Newberrytown 3
ID M9-1 8.7 2430 WSW of site along Alpine Road, Maytown ID N1-1 1 0.7 2740 W of site on W side of Shelley Island, between lots #13 and #14 ID N1-3 0.1 2740 W of Reactor Building on fence adjacent to Screenhouse entrance gate, TMI ID N2-1 2 1.2 261 W of site at Goldsboro Marina ID N5-1 2 5.0 2680 W of site off of Old York Road along Robin Hood Drive ID N8-1 3 7.7 2620 W of site along Route 382, 1/2 mile north of Lewisberry ID N15-2 3 10.4 2750 W of site at intersection of Lisburn Road and Main Street, Lisburn ID P1-1 0.4 3030 WNW of site on Shelley Island B-3
TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Sample Station Map Distance Medium Code Number (miles) Azimuth Description ID P1-2 0.1 2920 WNW of Reactor Building on fence N of Unit 1 Screenhouse, TMI ID P2-1 2.0 2830 WNW of site along Route 262 M P4-1 3.7 295° WNW of site at farm on Valley Road ID P5-1 5.0 284U WNW of site at intersection of Valley Road (Route 262) and Beinhower Road ID P8-1 8.0 2920 WNW of site along Evergreen Road, Reesers Summit ID Q1-1 0.5 3170 NW of site on E side of Shelley Island ID Q1-2 0.2 321' NW of Reactor Building on fence W of Warehouse 1, TMI ID Q2-1 1.9 3100 NW of site along access road along river ID Q5-1 5.0 3170 NW of site along Lumber Street, Highspire SW, DW, ID Q9-1 8.5 3100 NW of site at the Steelton Water Company AP, Al, ID Q15-1 13.4 309* NW of site behind West Fairview Fire Dept. Social Hall (abandoned)
ID R1-1 0.2 3350 NNW of Reactor Building along W fence, TMI ID R1-2 0.7 3340 NNW of site on central Henry Island ID R3-1 2.6 3410 NNW of site at Crawford Station, Middletown ID R5-1 4.9 3390 NNW of site at intersection of Spring Garden Drive and Route 441 ID R9-1 8.0 3410 NNW of site at intersection of Derry and 66th Streets, Rutherford Heights ID R15-1 11.2 3320 NNW of site at intersection of Route 22 and Colonial Road, Colonial Park IDENTIFICATION KEY ID = Immersion Dose (OSLD) EW = Effluent Water SW = Surface Water DW = Drinking Water Al =Air Iodine M = Milk (Cow)
AP = Air Particulate AQF = Finfish FP = Food Products (Green Leafy AQS = Aquatic Sediment Vegetation, Fruits, Vegetables)
B-4
TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor. Nuclear Station)
Env. Inc., T-02 Determination of tritium in water (direct method)
Surface lodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion exchange Drinking Gross Beta Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in Water from a continuous radiological analysis (Three Mile Island various matrices water compositor. Nuclear Station)
Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)
Drinking Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor. Nuclear Station)
Env. Inc., T-02 Determination of tritium in water (direct method)
Drinking Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by an ion exchange Effluent Iodine-131 Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices Water from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by an ion exchanae Effluent Gross Beta Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2008 Gross alpha and/or gross beta activity in Water from a continuous radiological analysis (Three Mile Island various matrices water compositor. Nuclear Station)
Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)
TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Effluent Gamma Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous radiological analysis (Three Mile Island water compositor. Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Effluent Tritium Monthly composite ER-TMI-06 Collection of water samples for 2 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water from a continuous radiological analysis (Three Mile Island scintillation water compositor. Nuclear Station)
Env. Inc., T-02 Determination of tritium in water (direct method)
Effluent Strontium- Semi-annual TBE, TBE-2023 Compositing of samples 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange Water 89/90 composite from monthly samples.
Storm Gamma Quarterly composite ER-TMI-06 Collection of water samples for 1 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy of monthly grab radiological analysis (Three Mile Island samples Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Storm Tritium Quarterly composite ER-TMI-06 Collection of water samples for 1 gallon TBE, TBE-2010 Tritium and carbon-14 analysis by liquid Water of monthly grab radiological analysis (Three Mile Island scintillation samples Nuclear Station)
Env. Inc., T-02 Determination of tritium in water (direct method)
Fish Gamma Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by other techniques gamma spectroscopy Fish Strontium-90 Semi-annual samples ER-TMI-13 Collection of fish samples for 1000 grams (wet) TBE, TBE-2019 Radiostrontium analysis by ion exchange collected via radiological analysis (Three Mile Island electroshocking or Nuclear Station) Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in other techniques Ashed Samples
TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Sediment Gamma Semi-annual grab ER-TMI-03 Collection of sediment samples for 500 grams (dry) TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Gross Beta One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2008 Gross alpha and/or gross beta activity in Particulates composite of iodine samples for radiological analysis (Three (approximately various matrices continuous air Mile Island Nuclear Station) 280 cubic sampling through meters weekly) Env. Inc., AP-02 Determination of gross alpha and/or gross glass fiber filter beta in air particulate filters paper Air Gamma Quarterly composite TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy of each station (approximately Env. Inc., AP-03 Procedure for compositing air 3600 cubic Env. Inc., GS-01 Determination of gamma emitters by particulate filters for gamma spectroscopic meters) gamma spectroscopy analysis Air Iodine Gamma One-week ER-TMI-14 Collection of air particulate and air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy composite of iodine samples for radiological analysis (Three (approximately continuous air Mile Island Nuclear Station) 280 cubic Env. Inc., 1-131-02 Determination of 1-131 in charcoal sampling through meters weekly) canisters by gamma spectroscopy (batch method) charcoal filter Milk 1-131 Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various" matrices sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion Monthly all other exchange times Milk Strontium- Quarterly composite ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 of Bi-weekly and radiological analysis (Three Mile Island Nuclear monthly grab Station) Enc. Inc., SR-07, Determination of Sr-89 and Sr-90 in Milk samples (Ion Exchange Batch Method)
TBE, TBE-2023 Compositing of samples Milk Gamma Bi-weekly grab ER-TMI-01 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy sample when cows radiological analysis (Three Mile Island Nuclear are on pasture. Station) Env. Inc., GS-01 Determination of gamma emitters by Monthly all other gamma spectroscopy times Vegetation Gamma Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy
TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Three Mile Island Nuclear Station, 2014 Sample Analysis Sampling Collection Procedure Number Sample Size Analytical Procedure Number Medium Method Vegetation Strontium- Monthly and annual ER-TMI-04 Collection of vegetation samples for 1000 grams TBE, TBE-2019 Radiostrontium analysis by ion exchange 89/90 grab sample radiological analysis (Three Mile Island Nuclear Station) Env. Inc., SR-05, Determination of Sr-89 and Sr-90 in Ashed Samples OSLD Optically Quarterly OSLDs ER-TMI-02 Collection of OSLD samples for 2 badges with 3 Landauer Incorporated Stimulated comprised of two radiological analysis (Three Mile Island Nuclear dosimeters Luminescence A120 3:C Landauer Station)
Dosimetry Incorporated elements.
- o
& t"i b s*mP a**3g..j &aih,94402, amg Figure B-I Environmental sampling Locations Within One Mile of the Three Mile Island Nuclear Station, 2014 B-9
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I Intentionally left blank
APPENDIX C DATA TABLES AND FIGURES -
PRIMARY LABORATORY
Intentionally left blank Table C-1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION J1-2 Q9-1 PERIOD 12/31/13 - 01/28/14 (1) < 193 < 188 01/28/14 - 02/25/14 (1) < 160 < 161 02/25/14 - 04/01/14 (1) < 166 < 167 04/01/14 - 04/29/14 291 +/- 133 < 185 04/29/14 - 06/03/14 700 +/- 157 < 190 06/03/14 - 07/01/14 467 +/- 131 < 171 07/01/14 - 07/29/14 2280 +/- 277 < 164 07/29/14 - 09/02/14 < 188 < 192 09/02/14 - 09/30/14 < 180 < 184 09/30/14 - 10/28/14 < 166 < 167 10/28/14 - 12/02/14 < 184 < 189 12/02/14 - 12/30/14 < 168 < 170 MEAN 935 +/- 1825 -
Table C-I.2 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION A3-2 PERIOD 01/06/14 - 01/21/14 (1) < 0.6 02/04/14 - 02/25/14 < 0.8 03/05/14 - 04/01/14 < 0.7 04/08/14 - 04/29/14 < 0.6 05/06/14 - 06/03/14 < 0.7 06/10/14 - 07/01/14 < 0.7 07/08/14 - 07/29/14 < 0.7 08/05/14 - 09/02/14 < 0.7 09/09/14 - 09/30/14 < 0.7 10/07/14 - 10/28/14 < 0.6 11/04/14 - 12/02/14 < 0.6 12/09/14 - 12/30/14 < 0.4 MEAN -
THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1
Table C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD J1-2 12/31/13 - 01/28/14 (1) <5 <6 < 12 <5 < 12 <6 < 10 <6 <6 < 32 <9 01/28/14 - 02/25/14 (1) <5 <5 < 10 <5 < 10 <5 < 10 <5 <6 < 28 <9 02/25/14 - 04/01/14 (1) <4 <4 <9 <4 <9 <4 <7 <3 <4 < 27 <7 04/01/14 - 04/29/14 <2 <2 <4 <2 <3 <2 <3 <2 <2 < 12 <3 04/29/14 - 06/03/14 <6 <6 < 12 <5 <9 <6 < 12 <6 <6 < 29 < 10 06/03/14 - 07/01/14 <5 <4 < 10 <4 < 11 <5 <9 <5 <6 < 25 <9 07/01/14 - 07/29/14 <3 <3 <6 <3 <6 <3 <5 <3 <3 < 16 <5 07/29/14 - 09/02/14 <5 <5 < 15 <6 < 11 <7 <9 <5 <7 < 33 <6 09/02/14 - 09/30/14 <4 <4 <9 <4 <9 <4 <6 <4 <5 < 26 <9 09/30/14 - 10/28/14 <5 <4 <8 <6 < 11 <5 <9 <4 <5 < 25 <8 10/28114 - 12/02/14 <3 <4 <7 <4 <7 <4 <6 <3 <3 < 19 <6 12/02/14 - 12/30/14 <6 <6 < 14 <5 < 10 <6 < 10 <6 <6 < 30 < 11 MEAN Q9-1 12/31/13 - 01/28/14 <6 <6 < 10 <5 < 12 <6 <9 <5 <7 < 30 <11 01/28/14 - 02/25/14 <5 <6 < 11 <5 < 10 <6 <10 <6 <6 < 27 <8 02/25/14 - 04/01/14 <5 <4 <9 <4 <8 <5 <8 <5 <5 < 30 <8 04/01/14 - 04/29/14 <2 <2 <4 <2 <3 <2 <3 <2 <2 < 12 <4 04/29/14 - 06/03/14 <5 <6 < 16 <7 <13 <6 <9 <6 <7 < 27 < 12 06/03/14 - 07/01/14 <4 <4 <7 <4 <8 <4 <7 <4 <4 < 23 <6 07/01/14 - 07/29/14 <4 <4 <8 <4 <6 <4 <6 <6 <6 < 30 <3 07/29/14 - 09/02/14 <5 <4 <8 <4 <8 <6 <9 <5 <5 < 26 <7 09/02/14 - 09/30/14 <5 <6 < 11 <6 < 11 <7 < 11 <5 <5 < 35 < 11 09/30/14 - 10/28/14 <5 <5 < 12 <4 < 10 <5 <8 <5 <5 < 21 <8 10/28/14 - 12/02/14 <3 <4 <7 <4 <6 <3 <7 <3 <3 < 18 <7 12/02/14 - 12/30/14 <6 <7 < 14 <5 <14 <7 < 12 <6 <8 < 36 <7 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION
Table C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/31/13 - 01/28/14 (1) 3.9 +/- 1.6 2.4 +/- 1.4 2.0 +/- 1.3 01/28/14 - 02/25/14 2.3 +/- 1.4 3.8 +/- 1.6 < 1.9 02/25/14 - 04/01/14 2.7 +/- 1.5 < 2.1 2.0 +/- 1.4 04/01/14 - 04/29/14 2.6 +/- 1.4 < 1.8 1.9 + 1.2 04/29114 - 06/03114 2.9 +/- 1.5 < 2.0 < 1.9 06/03/14 - 07/01/14 2.8 +/- 1.5 < 2.2 < 2.1 (1) 07/01/14 - 07/29/14 (1) < 2.2 < 2.2 < 2.1 07/29/14 - 09/02/14 (1) 2.9 +/- 1.5 3.3 +/- 1.5 < 1.9 09/02/14 - 09/30/14 3.5 +/- 1.5 3.1 +/- 1.6 2.3 + 1.6 09/30/14 - 10/28/14 2.9 +/- 1.6 < 2.3 < 2.2 10/28/14 - 12/02/14 3.4 +/- 1.6 < 2.2 2.3 +/- 1.5 12/02/14 - 12/30/14 4.2 +/- 1.5 2.4 +/- 1.3 2.1 + 1.3 MEAN 3.1 +/- 1.2 3.0 +/- 1.2 2.1 + 0.3 Table C-II.2 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 1Z/31/1 - U1/Zd/14 (1) < U.8 < u.8 < 0.8 01/28/14 - 02/25/14 < 0.7 < 0.8 < 0.9 02/25/14 - 04/01/14 < 0.8 < 1.0 < 0.8 04/01/14 - 04/29/14 < 0.5 < 0.7 < 0.6 04/29/14 - 06/03/14 < 0.7 < 0.7 < 0.6 06/03/14 - 07/01/14 < 0.7 < 0.8 < 0.7 (1) 07/01114 - 07/29/14 (1) < 0.6 < 0.5 < 0.6 07/29/14 - 09/02/14 (1) < 0.8 < 0.8 < 0.8 09/02/14 - 09/30/14 < 0.6 < 0.6 < 0.6 09/30/14 - 10/28/14 < 0.5 < 0.7 < 0.6 10128/14 - 12/02/14 < 0.8 < 0.5 < 0.6 12/02/14 - 12/30/14 < 0.4 < 0.6 < 0.5 MEAN - -
Table C-11.3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA COLLECTION G15-2 G15-3 Q9-1 PERIOD 12/31/13 - 01/28/14 (1) < 193 < 179 < 19u 01128/14 - 02/25/14 < 166 < 162 < 164 02/25/14 - 04/01/14 < 170 < 175 < 169 04/01/14 - 04/29/14 < 186 < 191 < 186 04/29/14 - 06/03/14 < 191 < 190 < 189 06103/14 - 07/01/14 < 173 < 169 < 173 (1) 07101/14 - 07/29/14 (1) < 171 < 168 < 164 07/29/14 - 09/02/14 (1) < 191 < 192 < 193 09102/14 - 09/30/14 < 182 < 183 < 185 09/30/14 - 10/28/14 < 165 < 165 < 171 10/28/14 - 12/02/14 < 188 < 186 < 185 12/02/14 - 12/30/14 < 168 < 165 < 166 MEAN - -
THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-3
Table C-Ih.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD G15-2 12/31/13 - 01/28/14 (1) < 5 <7 < 13 <6 < 11 <5 < 10 <6 <6 < 35 < 11 01/28/14 - 02/25/14 <5 <7 < 11 <6 < 12 <7 < 10 <6 <6 < 26 <9 02/25/14 - 04/01/14 <4 <3 <9 <4 <7 <4 <6 <3 <4 < 26 <7 04101114 - 04/29/14 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 15 <4 04/29/14 - 06103/14 <4 <3 <8 <5 <8 <4 <9 <4 <4 < 21 <6 06/03/14 - 07/01/14 <4 <5 < 11 <5 <9 <5 <9 <5 <4 < 27 <9 07/01/14 - 07/29/14 (1) < 4 <3 <8 <4 <6 <4 <6 <4 <4 < 17 <5 07/29/14 - 09/02/14 (1) < 4 <4 <7 <4 <9 <4 <7 <4 <4 < 17 <6 09/02/14 - 09/30/14 <5 <6 <9 <4 < 11 <5 <6 <4 <5 < 25 <6 09130t14 - 10/28114 <6 <6 < 13 <6 < 12 <7 < 10 <5 <6 < 28 < 10 10/28/14 - 12/02/14 <6 <7 < 12 <7 < 11 <6 < 11 <6 <6 < 34 < 11 12/02/14 - 12/30/14 <5 <5 < 13 <3 < 11 <6 <8 <6 <6 < 27 <6 MEAN G15-3 12/31/13 - 01/28/14 <7 <8 < 16 <9 < 15 <7 < 15 <6 <7 < 38 <8 01/28/14 - 02/25/14 <5 <5 < 12 <7 < 14 <6 < 12 <6 <6 < 31 < 12 02/25/14 - 04101114 <3 <4 <6 <4 <6 <3 <6 <3 <3 < 25 <8 04/01/14 - 04/29/14 <2 <2 <4 <2 <4 <2 <3 <2 <2 < 13 <4 04/29/14 - 06103/14 <6 <6 < 12 <6 < 16 <7 < 12 <5 <6 < 31 <9 06/03/14 - 07/01/14 <6 <5 < 13 <5 < 10 <5 <9 <6 <7 < 31 < 14 07/01/14 - 07/29/14 <5 <5 <9 <4 < 10 <5 <8 <4 <5 < 19 <7 07/29/14 - 09/02/14 <5 <6 < 12 <5 < 13 <5 < 10 <6 <6 < 21 <8 09/02114 - 09/30/14 <6 <6 < 11 <7 < 10 <6 < 10 <5 <6 < 35 <9 09130/14 - 10128/14 <7 <7 < 14 <8 < 18 <7 < 11 <6 <7 < 29 < 10 10/28/14 - 12/02/14 <7 <7 < 15 <8 < 14 <7 < 12 <6 <6 < 34 < 14 12/02/14 - 12/30/14 <4 <4 < 10 <5 <9 <5 <8 <4 <5 < 24 <8 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION
Table C-II.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q9-1 12/31/13 - 01/28/14 <5 <5 < 10 <7 < 10 <5 < 11 <5 <6 < 34 <9 01/28/14 - 02/25/14 <5 <5 <11 <4 < 10 <5 < 10 <5 <6 < 23 <5 02/25/14 - 04/01/14 <4 <4 < 10 <5 <7 <4 <9 <4 <4 < 29 <9 04/01/14 - 04/29/14 <2 <2 <5 <2 <5 <2 <4 <2 <2 < 15 <6 04/29/14 - 06/03/14 <6 <5 <9 <6 < 10 <5 < 10 <6 <6 < 28 <5 06/03/14 - 07/01/14 (1) < 6 <6 < 12 <6 <9 <5 < 10 <6 <7 < 34 <9 07/01/14 - 07/29/14 <5 <5 <9 <5 <10 <6 <9 <5 <5 < 27 <6 07/29/14 - 09/02/14 <6 <6 < 13 <7 < 13 <7 < 12 <7 <7 < 34 < 10 09/02/14 - 09/30/14 <5 <5 < 15 <6 < 10 <7 < 12 <6 <7 < 34 < 14 09/30/14 - 10/28/14 <6 <4 < 12 <6 < 12 <6 < 11 <6 <7 < 33 <9 10/28/14 - 12/02/14 <5 <4 < 11 <5 < 10 <5 <8 <5 <5 < 31 <7 12/02/14 - 12/30/14 <8 <8 < 15 <9 < 21 <9 < 12 <7 <7 < 41 <5 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION
Table C-III.1 CONCENTRATIONS OF GROSS BETA, IODINE-131, TRITIUM, AND STRONTIUM IN EFFLUENT WATER SAMPLES FOR STATION KI-1 COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION GR-B 1-131 H-3 SR-89 SR-90 PERIOD K1-1 12/31/13 - 01/28 /14 5.7 +/- 1.6 < 0.8 < 187 12/31/13 - 07/01/14 < 4.4 < 0.9 01/28/14 - 02/25 /14 6.5 +/- 1.8 < 0.8 < 160 02/25114 - 04101 /14 3.6 +/- 1.5 < 0.8 < 167 04/01/14 - 04/29 /14 2.8 +/- 1.4 < 0.6 2300 +/- 282 04/29/14 - 06/03 /14 3.4 +/- 1.6 < 0.7 9780 +/- 1020 06/03/14 - 07/01 /14 4.6 +/- 1.9 < 0.7 7290 +/- 775 07/01/14 - 07/29 /14 7.0 +/- 2.1 < 0.5 27000 +/- 2740 07/01/14 - 12/30 /14 < 4.6 < 0.7 07/29/14 - 09/02/14 5.9 +/- 2.0 < 0.7 < 197 09/02/14 - 09/30 /14 6.4 +/-2.1 < 0.5 < 182 09/30/14 - 10/28 /14 6.2 +2.1 < 0.5 < 167 10/28/14 - 12/02 /14 6.3 +/- 2.1 < 0.6 < 186 12/02/14 - 12/30 /14 5.6 +/- 1.6 < 0.5 < 188 MEAN 5.3 +/- 2.8 - 11593 +/- 21464 -
THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-6
Table C-III.2 CONCENTRATIONS OF GAMMA EMITTERS IN EFFLUENT WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD K1-1 12/31/13 01/28/14 <5 <5 < 13 <6 < 12 <5 9 <5 <8 < 24 <10 01/28/14 02/25/14 <4 <5 <9 <4 <8 <5 7 <6 <5 < 24 <8 02/25/14 04/01/14 <4 <4 < 10 <4 <8 <4 7 <4 <4 < 31 <7 04/01/14 04/29/14 <2 <2 <4 <2 <3 <2 3 <2 <2 < 13 <3 04/29/14 06/03/14 <5 <5 < 15 <8 < 11 <6 10 <5 <5 < 33 <8 06/03/14 07/01/14 <3 <3 <7 <3 <6 <3 5 <3 <3 < 18 <7 07/01/14 07/29/14 <3 <3 <7 <3 <6 <3 5 <3 <3 < 15 <5 07/29/14 09/02/14 <4 <4 <9 <4 <9 <7 9 <6 <6 < 22 <9 09/02/14 09/30/14 <5 <6 < 10 <3 < 11 <5 9 <4 <5 < 29 <8 09/30/14 10/28/14 <5 <6 < 11 <5 < 12 <6 8 <6 <6 < 28 <6 10/28/14 12/02/14 <5 <5 < 10 <4 <9 <5 10 <4 <6 < 32 <9 12/02/14 12/30/14 <6 <7 < 13 <6 < 10 <7 11 <6 <7 < 32 <1 MEAN
Table C-IV.1 CONCENTRATIONS OF STRONTIUM IN PREDATOR AND BOTTOM FEEDER (FISH)
SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Sr-90 PERIOD INDP PREDATOR 06/13/14 < 2.1 09124/14 < 2.3 MEAN INDB BOTTOM FEEDER 06/13/14 < 2.5 09/24/14 < 1.4 MEAN BKGP PREDATOR 06/19/14 < 1.7 09/30/14 < 2.3 MEAN BKGB BOTTOM FEEDER 06/19/14 < 1.9 09/30/14 < 3.7 MEAN C-8
Table C-IV.2 CONCENTRATIONS OF GAMMA EMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH) SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 PERIOD BKGB BOTTOM FEEDER 06/19/14 2512 +/- 875 < 51 < 78 < 133 < 60 < 101 < 62 < 78 09/30/14 3864 +/- 997 < 61 < 61 < 140 < 67 < 130 < 55 < 67 MEAN 3188 +/- 1912 -
BKGP PREDATOR 06/19/14 2411 +/- 758 < 65 < 67 < 140 < 60 < 123 < 72 < 75 09/30/14 3206 +/- 1103 < 77 < 88 < 174 < 97 < 143 < 75 < 76 MEAN 2809 +/- 1124 INDB BOTTOM FEEDER 06/13/14 3032 +/- 763 < 49 < 48 < 120 < 69 < 129 < 48 < 59 09/24/14 3869 +/- 954 < 68 < 60 < 168 < 57 < 148 < 59 < 69 MEAN 3451 +/- 1184 - - - - - -
INDP PREDATOR 06/13/14 3804 +/- 1259 < 81 < 80 < 152 < 75 < 202 < 86
- 98 09/24/14 2434 +/- 1075 < 68 < 91 < 196 < 67 < 152 < 84 < 79 MEAN 3119 +/- 1937 C-9
Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Co-60 Cs-134 Cs-1 37 PERIOD A1-3 06/13/14 14610 +/- 1576 < 83 < 78 < 85 < 83 < 103 10/31/14 11700 +/- 1544 < 87 < 99 < 93 < 94 < 98 MEAN 13155 +/- 4115 - - - - -
EDCB 10/31/14 17610 +/- 1344 < 43 < 45 < 40 < 42 < 69 MEAN J2-1 06/13/14 16770 +/- 1773 < 102 < 98 < 79 < 81 < 110 10/31/14 11150 +/- 1510 < 93 < 97 < 81 < 113 < 111 MEAN 13960 +/- 7948 K1-3 06/13/14 8369 +/- 1161 < 77 < 67 < 72 < 73 < 81 10/31/14 8965 +/- 1349 < 86 < 92 < 71 < 75 < 88 MEAN 8667 +/- 843 C-I0
Table C-VI.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION. 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I IGROUP 11 GROUP III PERIOD E1-2 F1-3 A3-1 G2-1 1-3-1 M2-1 Q15-1 01/02/14 -01/09/14 17 +/- 5 16 +/-5 16 +/-5 16 +/- 5 14 +/-5 16+/-:t5 15 +/-5 01/09/14 -01/15/14 18 +/-6 20 +/-6 27 +/-6 20 +/-6 19 +/-6 26+/-i6 23 +/-6 01/15/14 -01/23/14 18 +/-5 22 +/-5 20 +/-5 19 +/-5 21 +/-5 21+/-i5 23 +/-5 01/23/14-01/30/14 10 +/-5 12 +/-5 15 +/-5 14 +/-5 14 +/-5 9 +/-5 12 +/-5 01/30/14 -02/06/14 12 +/- 5 22 +/-5 23 +/-5 17 +/- 5 22 +/-6 22 +/- 5 14+/-5 02/06/14-02/12/14 32 +/-7 (1) 31 +/-7 30 +/-7 37 +/-7 38 +/-7 23+/-i6 31+/-7 02/12/14 -02/20/14 26 +/- 6 20 +/-5 26 +/-5 22 +/- 5 25 +/-5 27 +/- 5 19+/-5 02/20/14 -02/27/14 13 +/- 6 14 +/-5 15 +/-5 16 +/- 5 17 +/-5 16 +/- 5 16+/-5 02/27/14-03/06/14 32 +/-6 23 +/-6 35 +/-6 29 +/-6 29 +/-6 27 +/-6 27+/-6 03/06/14-03/12/14 25 +/-6 19 +/-6 22 +/-6 19 +/-6 25 +/-6 (1) 24+/- 6 03/12/14 -03/20/14 12 +/- 4 11 +/- 4 10 +/- 4 12 +/- 4 14 +/- 5 12 +/- 5 10 +/- 4 03/20/14 -03/27/14 20 +/- 5 16 +/-5 18 +/-5 19 +/- 5 16 +/-5 16+/-i5 22+/- 5 03/27/14 -04/03/14 13 +/- 5 11 +/- 5 17 +/- 5 15 +/- 5 11 +/- 5 8 +/- 5 9 +/-5 04/03/14 -04/10/14 18 +/-4 14 +/-5 21 +/-4 19 +/-4 17 +/-4 17 +/-4 21+/- 4 04/10/14 -04/17/14 14 +/- 5 15 +/-5 17 +/-5 14 +/- 5 15 +/-5 18 t 5 15 +/-5 04/17/14 -04/23/14 19 +/- 6 16 +/-6 15 +/-6 13 +/- 6 12 +/-6 15 +/- 6 17+/- 6 04/23/14-05/01/14 10 +/-4 9 +/-4 12 +/-4 9 +/-4 13 +/-5 6+/-:t4 13+/- 4 05/01/14 -05/07/14 11 +/- 6 8 +/- 6 10 +/- 6 < 8 9 +/-6 < 8 < 8 05/07/14 -05/15/14 16 +/- 5 10 +/-4 13 +/-5 17 +/- 5 16+/-5 (1) 15 +/-5 15+/- 5 05/15/14 -05/22/14 17 +/- 5 17 +/-5 17 +/-5 20 +/- 5 21+/-5 18 +/-5 20+/- 5 05/22/14 -05/29/14 11 +/- 5 8 +/- 4 14 +/- 5 12 +/- 5 12 +/-5 13 +/- 5 13 +/- 5 05/29/14-06/05/14 8 +/-5 8 +/-5 8 +/-5 9 +/-5 11+/-5 <7 <7 06/05/14 -06/11/14 12 +/- 5 10 +/- 5 (1) 13 +/- 6 11 +/-5 9 +/- 5 10 +/- 5 06/11/14 -06/19/14 20 +/- 5 14 +/- 4 18 +/- 5 16 +/- 4 16 +/- 4 13 +/- 4 15 +/- 4 06/19/14 -06/25/14 17 +/- 6 12 +/-5 17 +/-5 13 +/- 5 19 +/-6 17 +/-6 20+/- 6 06/25/14 -07/03/14 9 +/- 4 (1) 14 +/-5 18 +/- 5 14 +/-5 14 +/- 5 16+/- 5 07/03/14 -07/10/14 10 +/- 5 22 +/- 6 (1) 17 +/- 5 18 +/- 5 11 +/- 5 20 +/- 5 20 +/- 5 07/10/14 -07/17/14 16 +/- 5 11 +/- 5 20 +/- 5 15 +/- 5 14 +/- 5 18 +/- 5 15 +/- 5 07/17/14 -07/24/14 17 +/- 5 18 +/-5 19 +/-5 17 +/- 5 16 +/-5 15 +/-5 14+/- 5 07/24/14 -07/31/14 9 +/- 5 12 +/- 5 12 +/- 5 14 +/- 5 10 +/- 5 12 +/- 5 11 +/- 5 07/31/14 -08/07/14 17 +/- 5 15 +/-5 19 +/-5 17 +/- 5 19 +/-5 19 +/- 5 16 +/-5 08/07/14 -08/14/14 17 +/- 5 12 +/-5 17 +/-5 15 +/- 5 17 +/-5 19 +/-5 15+/- 5 08/14/14 -08/21/14 16 +/- 5 13 +/-5 13 +/-5 17 +/- 5 16 +/-5 16 +/-5 18+/- 5 08/21/14 -08/28/14 17 +/- 5 21 +/-5 21 +/-7 (1) 14 +/- 5 18 +/-5 18 +/-5 16+/- 5 08/28/14-09/04/14 9 +/-5 20 +/-6 20 +/-6 12 +/-5 15 +/-5 14 +/-5 15+/- 5 09/04/14 -09/10/14 17 +/- 6 19 +/-6 23 +/-6 17 +/- 6 16 +/-6 15 +/- 6 16+/- 6 09/10/14 -09/18/14 10 +/- 4 12 +/-4 17 +/-5 15 +/- 5 15 +/-5 15 +/- 5 17+/- 5 09/18/14 -09/25/14 17 +/- 5 24 +/-5 20 +/-5 20 +/- 5 23 +/-5 24 +/-6 20+/- 5 09/25/14-10/02/14 24 +/-6 20 +/-5 24 +/-6 26 +/-6 19 +/-5 20 +/-5 24+/- 6 10/02/14 -10/09/14 18 +/- 5 13 +/-5 19 +/-5 19 +/- 5 18 +/-5 16 +/- 5 17+/- 5 10/09/14 -10/16/14 21 +/- 5 21 +/-5 19 +/-5 20 +/- 5 20 +/-5 20 +/-5 18 +/-5 10/16/14 -10/23/14 12 +/- 5 10 +/- 5 14 +/- 5 13 +/- 5 15 +/- 5 11 +/- 5 14 +/- 5 10/23/14 -10/30/14 16 +/- 5 16 +/-5 19 +/-6 17 +/- 5 20 +/-6 19 +/-6 20+/- 6 10/30/14 -11/06/14 15 +/- 5 16 +/- 5 13 +/- 5 15 +/- 5 13 +/- 5 16 +/- 5 14 +/- 5 11/06/14 -11/13/14 19 +/- 5 17 +/- 5 18 +/- 5 18 +/- 5 17 +/- 5 20 +/- 5 20 +/- 5 11/13/14 -11/20/14 17 +/- 5 19 +/- 5 15 +/- 5 19 +/- 5 18 +/- 5 16 +/- 5 16 +/- 5 11/20/14 -11/26/14 26 +/- 6 22 +/- 6 22 +/- 6 28 +/- 7 26 +/- 6 25 +/- 9 (1) 21 +/- 6 11/26/14 -12/04/14 18 +/- 5 16 +/- 4 17 +/- 5 18 +/- 5 21 +/- 5 (1) 21 +/- 5 12/04/14 -12/11/14 19 +/- 6 14 +/- 5 14 +/- 5 15 +/- 5 14 +/- 5 17 +/- 5 13 +/- 5 12/11/14 -12/17/14 25 +/- 6 19 +/- 6 21 +/- 6 19 +/- 6 20 +/- 6 17 +/- 6 21 +/- 6 12/17/14 -12/24/14 8 +/- 4 11 +/- 4 14 +/- 5 14 +/- 5 12 +/- 5 16 +/- 5 17 +/- 5 12/24/14 -01/01/15 19 +/- 5 16 +/-4 20 +/-5 17 +/- 5 17 +/-5 14 +/-4 19+/- 5 MEAN 16 +/- 11 16 +/- 10 18 +/- 10 17 +/- 10 17 +/- 11 17 +/- 9 17 +/- 9 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-1Il
Table C-VI.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - CLOSEST TO THE SITE BOUNDARY GROUP II - INTERMEDIATE OFFSITE GROUP III - CONTROL LOCATIONS COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/-
PERIOD 2SD PERIOD 2SD PERIOD 2SD 011/0114 U1/1U/14 1U 32 11 +7 U1/U0I14 - U1/30/14 27 18 +/-1 01102/14 01/30/14 12 23 +/- 11 01/30/14 02/27/14 12 32 21 +/- 16 01/30114 02/27/14 15 38 24 +/- 14 01130/14 02/27/14 14 31 20 +/- 15 02127/14 04/03/14 11 32 18 +/- 14 02/27/14 04/03/14 8 35 19 +/- 15 02/27/14 04/03/14 9 27 18 +/- 17 04/03/14 05/01/14 9 19 14 +/- 7 04(03/14 05(01(14 6 21 15 +/- 7 04(03/14 05/01(14 13 21 16 +/- 7 05101/14 05129t14 8 17 12 +/- 8 05/01/14 05129/14 9 21 15-+/- 7 05107/14 05t29114 13 20 16 +/- 8 05/29/14 07/03/14 8 20 12 +/- 8 05/29/14 07/03/14 8 19 14 7 06/05/14 07/03/14 10 20 15 +/- 9 07/03/14 07/31/14 9 22 14 +/- 9 07/03/14 07/31/14 10 20 15 6 07/03/14 07/31/14 11 20 15 +/- 8 07/31/14 09/04/14 9 21 16 +/- 8 07/31/14 09104114 12 21 17 5 07/31/14 09/04/14 15 18 16 +/- 2 09/04/14 10/02/14 10 24 18 +/- 10 09/04/14 10/02/14 15 26 19 7 09/04/14 10/02/14 16 24 19 +/- 8 10/02/14 10/30/14 10 21 16 +/- 8 10/02/14 10/30/14 11 20 17 +/-5 10/02/14 10/30/14 14 20 17 +/- 5 10/30/14 12/04/14 15 26 18 +/- 7 10/30/14 12/04/14 13 28 19 +/- 9 10/30/14 12/04/14 14 21 18 +/- 6 12/04/14 01/01/15 8 25 16 +/- 11 12/04/14 01/01115 12 21 16 +/- 6 12104/14 01/01/15 13 21 18 +/- 7 I',J 01/02/14 - 01/0'1115 8 32 16 +/- 10 01/02/14 - 01101/15 6 38 17 +/- 10 01102/14 - 01/01/15 9 31 17 +/- 9
Table C-VI.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED INTHE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION Be-7 Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 PERIOD A3-1 01/02/14 - 04/03/14 68+/-38 <4 <4 <4 <4 <8 <4 <4 04/03/14 - 07/03/14 87+/-31 <4 <5 <4 <6 <10 <4 <4 07/03/14 - 10/02/14 79+/-27 <3 <4 <3 <4 <8 <3 <3 10/02/14 - 01/01/15 95 +/- 23 <3 < 3 < 3 <3 <6 <3 <4 MEAN 82 +/- 23 E1-2 01/02/14 - 04/03/14 57 +/- 20 < 3 < 3 < 3 <3 <5 <3 <3 04/03/14 - 07/03/14 73 +/- 26 < 3 < 3 <2 <3 <6 <3 <2 07/03/14 - 10/02/14 50+/-33 <3 <4 <4 <5 <8 <2 <3 10/02/14 - 01/01/15 <46 <4 <6 <5 <5 <8 <4 <3 MEAN 60 +/- 24 - - -
F1-3 01/02/14 - 04/03/14 69 +/- 30 <3 < 4 < 2 <4 <9 <4 <4 04/03/14 - 07/03/14 50+/-17 <2 <3 <3 <3 <5 <2 <2 07/04/14 - 10/02/14 60+/-39 <4 <6 <4 <6 <10 <4 <4 10/02/14 - 01/01/15 46+/-16 <1 <3 <2 <2 <4 <2 <2 MEAN 56 +/- 21 -
G2-1 01/02/14 - 04/03/14 99+/-37 <7 <9 <5 <8 <16 <6 <8 04/03/14 - 07/03/14 62+/-21 <2 <3 <2 <3 <5 <2 <3 07/03/14 - 10/02/14 <61 <4 <6 <4 <7 <12 <5 <3 10/02/14 - 01/01/15 44+/-21 <2 <3 <3 <3 <5 <2 <2 MEAN 68 +/- 56 H3-1 01/02/14 - 04/03/14 69+/-20 <3 <4 <2 <3 <6 <2 <3 04/03/14 - 07/03/14 69+/-25 <3 <4 <2 <4 <6 <2 <2 07/03/14 - 10/02/14 94+/-29 <3 <4 <3 <3 <5 <2 <2 10/02/14 - 01/01/15 37+/-20 <2 <3 <2 <4 <6 <2 <3 MEAN 67 +/- 47 M2-1 01/02/14 - 04/03/14 63+/-22 <3 <5 <3 <5 <8 <3 <3 04/03/14 - 07/03/14 54+/-23 <2 <3 <2 <3 <6 <3 <2 07/03/14 - 10/02/14 70+/-22 <2 <3 <1 <3 <6 <2 <2 10/02/14 - 01/01/15 102+/-22 <3 <4 <3 <4 <7 <3 <3 MEAN 72 +/- 42 Q15-1 01/02/14 - 04/03/14 55+/-26 <4 <4 <5 <5 <10 <4 <4 04/03/14 - 07/03/14 95+/-29 <3 <3 <3 <4 <6 <2 <3 07/03/14 - 10/02/14 49+/-28 <4 <5 <2 <4 <6 <2 <3 10/02/14 - 01/01/15 53+/-29 <4 <5 <4 <5 <7 <4 <3 MEAN 63 +/- 43 C-13
Table C-VII.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I I GROUP 11 IGROUP III PERIOD El -2 Fl -3 A3-1 G2-1 1-3-1 M2-1 Q15-1 U 01/02114 - 01109/14 < 55 < 53
- 51
- 54
- 56
- 52 < 53 01/09/14 - 01/15/14 < 65 <64
- 56 < 64
- 67
- 56 < 57 01/15114 - 01/23/14 < 60 <58
- 53
- 59 < 56 < 54 < 54 01/23/14 - 01/30/14
- 53 < 51
- 69
- 52 < 54
- 69 < 69 01130/14 - 02/06/14
- 61 <59
- 56
- 60
- 62
- 57 < 58 02/06/14 - 02/12/14
- 62 (1) <60
- 58
- 26
- 63
- 58 < 59 02/12/14 - 02/20/14
- 61 < 44
- 62
- 45 < 46
- 63 < 63 02/20/14 - 02/27/14
- 56 <c49
- 48
- 51
- 18
- 49 < 49 02/27/14 - 03/06/14
- 65
- 64 < 48
- 65
- 67
- 48 < 50 03/06/14 - 03/12/14
- 57
- 55 < 41
- 56
- 43 (1) < 42 03/12/14 - 03/20/14 < 43 *<43 < 46 < 43
- 49
- 53 < 20 03/20/14 - 03/27/14
- 61
- 58
- 16
- 59 < 46 < 44 < 45 03/27/14 - 04/03/14
- 68
- 66
- 64
- 67
- 69
- 65 < 65 04/03/14 - 04/10/14 < 54
- 22
- 55 < 54
- 55 <53 < 54 04/10/14 - 04/17/14
- 57 <55
- 57
- 56
- 58 <57 < 57 04/17/14 - 04/23/14
- 53
- 52
- 51
- 52
- 54
- 51 < 52 04/23/14 - 05/01/14
- 25
- 63
- 61 < 64
- 66
- 62 < 62 05101/14 - 05/07/14 *<67
- 66 < 66
- 66
- 69
- 67 < 67 05/07/14 - 05/15/14
- 60
- 58
- 56
- 37
- 50 (1)
- 56 < 57 05/15/14 - 05/22/14
- 68
- 66
- 61
- 67
- 29
- 61 < 62 05/22/14 - 05/29/14
- 23
- 22
- 23
- 23
- 23 < 24 < 24 05/29/14 - 06/05/14
- 28
- 27
- 26
- 29
- 27 < 11 < 26 06/05/14 - 06/11/14 < 41 < 40 (1)
- 42
- 42
- 41 < 41 06/11/14 - 06/19/14
- 33
- 33
- 48 ., 34 < 34
- 38 < 37 06/19/14 - 06/25/14
- 69
- 68
- 61 < 70
- 68
- 61 < 59 06/25/14 - 07/03/14
- 23 (1)
- 23 <- 24 < 24 < 24 < 24 07/03/14 - 07/10/14
- 51
- 56 (1) < 48 < 52
- 49
- 48 < 48 07/10/14 - 07/17/14
- 41
- 41
- 39 < 43 < 42
- 39 < 39 07/17/14 - 07/24/14
- 27
- 27
- 27 < 28
- 28
- 28 < 27 07/24/14 - 07/31/14
- 19
- 54
- 62 < 56
- 55
- 63 < 62 07/31/14 - 08/07/14
- 25
- 25
- 25 < 26
- 26 < 26 < 25 08/07/14 - 08/14/14
- 30
- 29
- 29 < 12
- 30
- 29 < 29 08/14/14 - 08/21/14
- 57
- 56
- 56 < 59
- 58
- 57 < 57 08/21/14 - 08/28/14
- 60
- 59
- 63 (1) < 61
- 23
- 39 < 39 08/28/14 - 09/04/14
- 59
- 58
- 67 < 61
- 60
- 61 < 60 09/04/14 -09/10/14
- 53
- 52
- 53 < 54
- 53
- 53 < 53 09/10/14 -09/18/14 < 64
- 63
- 67 < 66
- 65
- 28 < 67 09/18/14 -09/25/14
- 67
- 66
- 59 < 68
- 67
- 61 < 60 09/25/14 -10/02/14
- 66
- 65
- 60 < 68
- 66
- 60 < 60 10/02/14 -10/09/14
- 59
- 58
- 58 < 60
- 59
- 55 < 54 10/09/14 -10/16/14
- 38
- 37
- 38 < 39
- 38
- 39 < 38 10/16/14 -10/23/14
- 30
- 12
- 30 < 31
- 31
- 30 < 30 10/23/14 -10/30/14
- 40
- 39 < 41 < 41 < 40 < 42 < 41 10/30/14 -11/06/14
- 69
- 68 < 64 < 65
- 70 < 65 < 64 11/06/14 -11/13/14
- 25
- 25
- 28 < 26
- 26
- 28 < 28 11/13/14 -11/20/14 < 68 < 67
- 19 < 38 < 69
- 19 < 19 11/20/14 -11/26/14
- 67
- 65 < 43 < 68
- 67
- 68 (1) < 43 11/26/14 -12/04/14
- 67
- 68
- 67 < 69
- 70 (1) < 67 12/04/14 -12/11/14
- 57
- 56 < 43 < 59
- 58
- 42 < 43 12/11/14 -12/17/14
- 66
- 65
- 68 < 68
- 67
- 69 < 69 12/17/14 -12/24/14
- 67
- 66
- 61 < 69
- 68
- 63 < 61 12/24/14 -01/01/15
- 31
- 31
- 38 < 32
- 39
- 15 < 38 MEAN--
(1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-14
Table C-VIII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDICATOR FARM COLLECTION TM-M-K15-3 I TM-M-E2-2 TM-M-F4-1 TM-M-G2-1 TM-M-P4-1 PERIOD 01/08/14 < 0.8 < 0.6 < 0.6 < 0.7 < 0.8 02/05/14 < 0.8 < 0.7 < 0.8 < 0.7 < 0.6 03/05/14 < 0.8 < 0.9 < 0.7 < 0.9 < 0.7 03/19/14 < 0.8 < 0.8 < 0.5 < 0.7 < 0.8 04/02/14 < 0.6 < 0.8 < 0.6 < 0.9 < 0.9 04/16/14 < 0.7 < 0.6 < 0.6 < 0.8 < 0.6 04/30/14 < 0.7 < 0.7 < 0.8 < 0.9 < 0.7 05/14/14 < 0.6 < 0.9 < 0.6 < 0.7 < 0.7 05/28/14 < 0.6 < 0.7 < 0.7 < 0.9 < 0.8 06/11/14 < 0.6 < 0.6 < 0.7 < 0.7 < 0.6 06/25/14 < 0.6 < 0.6 < 0.5 < 0.6 < 0.6 07/09/14 < 0.6 < 0.6 < 0.6 < 0.7 < 0.6 07/23/14 (1) < 0.4 < 0.5 < 0.4 < 0.5 08/06/14 < 0.6 < 0.6 < 0.6 < 0.6 < 0.7 08/20/14 < 0.7 < 0.9 < 0.7 < 0.9 < 0.8 09/03/14 < 0.9 < 0.7 < 0.6 < 0.7 < 0.7 09/17/14 < 0.5 < 0.6 < 0.5 < 0.5 < 0.6 10/01/14 < 0.5 < 0.6 < 0.5 < 0.7 < 0.5 10/15/14 < 0.8 < 0.5 < 0.6 < 0.7 < 0.7 10/29/14 < 0.8 < 0.7 < 0.8 < 0.7 < 0.6 11/12/14 < 0.3 < 0.8 < 0.9 < 0.4 < 0.6 11/25/14 < 0.6 < 0.7 < 0.7 < 0.6 < 0.7 12/10/14 0.7 < 0.8 0.6 <'0.8
< < < 0.6 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-15
Table C-VIII.2 CONCENTRATIONS OF STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA CONTROL FARM I INDICATOR FARM COLLECTION SR-89 K15-3 I P4-1 I E2-2 I F4-1 I G2-1 PERIOD SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 SR-89 SR-90 01/08/14 - 03/19/14 < 3.6 < 0.6 < 4.7 < 0.7 < 3.8 < 0.6 < 3.9 < 0.8 < 4.9 < 0.8 04/02/14 - 06/25/14 < 3.8 < 0.6 < 4.6 < 0.3 <4.3 < 0.4 < 4.0 < 0.6 < 3.4 < 0.6 07/09/14 - 09/17/14 < 3.2 < 0.9 < 3.5 < 1.0 < 1.7 < 0.5 < 3.2 < 0.8 < 2.4 < 0.6 10/01/14 - 12/10/14 < 2.8 < 0.9 < 2.6 < 0.7 < 3.5 < 1.0 < 2.8 < 1.0 < 2.9
- 0.9 MEAN 0~~
Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-1 37 Ba-140 La-140 PERIOD L--
01/08/14 11b +/- lbl <6 <7 < 37t < 10 02/05/14 1294 +/- 160 <6 <6 < 44 < 12 03/05/14 1442 +/- 170 < 6 <7 < 38 <8 03/19/14 1171 +/- 106 <5 <5 < 21 <6 04/02/14 1409 +/- 166 <7 <8 < 37 < 12 04/16/14 1309 +/- 145 <6 <6 < 34 < 10 04/30/14 1260 +/- 131 <5 <6 < 36 < 13 05/14/14 1347 +/- 168 <7 <8 < 24 <5 05/28/14 1302 +/- 147 <7 <8 < 32 < 10 06/11/14 1473 +/- 151 <6 <7 < 34 <7 06/25/14 1258 +/- 134 <6 <7 < 26 <8 07/09/14 1511 +/- 203 <7 < 10 < 43 < 11 07/23/14 1347 +/- 126 <5 <6 < 24 <6 08/06/14 1343 +/- 183 <6 <8 < 38 <6 08/20/14 1292 +/- 128 <5 <5 < 22 <8 09/03/14 1300 +/- 163 <8 <8 < 59 < 10 09/17/14 1156 +/- 153 <5 <6 < 28 <8 10/01/14 1388 +/- 125 <4 <6 < 27 <8 10/15/14 1191 +/- 111 <4 <4 < 45 < 12 10/29/14 1411 +/- 169 <7 <7 < 42 < 13 11/12/14 1292 +/- 182 <6 <7 < 38 < 10 11/25/14 1340 +/- 173 <6 <9 < 43 < 14 12/10/14 1325 +/- 113 <5 <5 < 24 <7 MEAN 1319 +/- 189 F4-1 01/08/14 1049 +/- 157 <8 <9 < 42 < 13 02/05/14 1348 +/- 139 <5 <6 < 33 < 12 03/05/14 1443 +/- 178 <5 <7 < 36 < 11 03/19/14 1335 +/- 93 <4 <4 < 20 <6 04/02/14 1500 +/- 172 <5 <5 < 26 <5 04/16/14 1333 +/- 135 <6 <6 < 28 <7 04/30/14 1306 +/- 141 <6 <6 < 41 < 12 05/14/14 1322 +/- 132 <5 <6 < 23 <6 05/28/14 1382 +/- 175 <8 <8 < 43 < 12 06/11/14 1343 +/- 128 <7 <7 < 37 <9 06/25/14 1224 +/- 159 <5 <7 < 31 <6 07/09/14 1478 +/- 174 <7 <8 < 31 < 10 07/23/14 1259 +/- 118 <4 <4
- 23 <6 08/06/14 1341 +/- 169 <7 <7 < 36 <9 08/20/14 1456 +/- 148 <4 <6 < 22 <7 09/03/14 1318 +/- 156 <6 <8 < 49 < 11 09/17/14 1468 +/- 156 <4 <6 < 25 <3 10/01/14 1507 +/- 208 <8 <7 < 43 < 11 10/15/14 1473 +/- 130 <5 <5 < 46 < 14 10/29/14 1517 +/- 138 <8 <8 < 46 < 11 11/12/14 1263 +/- 158 <7 <7 < 33 <8 11/25/14 1483 +/- 176 <6 <8 < 40 < 10 12/10/14 1396 +/- 114 <4 <5 < 22 <6 MEAN 1371 +/- 225 C-17
Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-1 40 PFRIflfl PERIOD G2-1 01/08/14 1090 +/- 158 <5 <7 < 38 < 12 02/05/14 1195 +/- 118 <6 <7 < 43 < 11 03/05/14 985 +/- 105 <5 <6
- 30 <7 03/19/14 1218 +/- 115 <4 <5 < 24 <6 04/02/14 1127 +/- 149 <7 <7 < 43 < 14 04/16/14 971 +/- 135 <6 <8 < 39 < 11 04/30/14 915 +/- 130 <6 <6 < 42 < 15 05/14/14 770 +/- 139 <8 <8 < 40 < 12 05/28/14 1240 +/- 150 <7 <8 < 37 < 12 06/11/14 963 +/- 103 <5 <6 < 28 < 10 06/25/14 802 +/- 131 <8 <9 < 35 <9 07/09/14 1296 +/- 215 <7 <8 < 37 < 14 07/23/14 957 +/- 133 <5 <6 < 32 <9 08/06/14 636 +/- 161 <8 <7 < 42 < 14 08/20/14 1072 +/- 184 <7 <8 < 29 < 12 09/03/14 1289 +/- 169 <6 <8 < 51 < 15 09/17/14 851 +/- 143 <7 <8 < 33 <9 10/01/14 907 +/- 171 <9 <9 < 44 < 13 10/15/14 1126 +/- 110 <4 <6 < 44 < 15 10/29/14 756 +/- 120 <5 <5 < 43 < 12 11/12/14 824 +/- 150 < 12 < 10 < 51 < 12 11/25/14 973 +/- 133 <5 <7 < 33 <8 12/10/14 1133 +/- 142 <7 <7 < 35 <11 MEAN 1004 +/- 366 K15-3 01/08/14 1293 +/- 164 <6 <8 < 42 < 14 02/05/14 1332 +/- 122 <5 <6 < 39 <9 3/5/2014 1101 +/- 166 <7 <7 < 43 < 10 03/19/14 1028 +/- 105 <4 <5 < 22 <8
+/- 188 <7 <8 < 37 <11 4/2/2014 1392 04/16/14 1448 +/- 130 <6 <6 < 31 <7 04/30/14 1295 +/- 136 <4 <5 < 34 < 11 05/14/14 1292 +/- 172 <5 <8 < 30 <5 05/28/14 1384 +/- 182 <7 <8 < 34 <9 06/11/14 1254 +/- 129 <5 <6 < 26 <8 06125/14 1060 +/- 139 <6 <7 < 31 <7 07/09/14 1222 +/- 171 <6 <6 < 34 <9 07/23/14 1244 +/- 118 <4 <4 < 19 <5 08/06/14 1282 +/- 156 <6 <7 < 28 <12 08/20/14 1275 +/- 151 <5 <6 < 26 <8 09/03/14 1333 +/- 148 <5 <6 < 42 < 15 09/17/14 1231 +/- 140 <6 <7 < 29 <8 10/01/14 1068 +/- 183 <8 < 10 < 48
- 13 10/15/14 1369 +/- 116 <4 <5 < 44 < 14 10/29/14 1174 +/- 132 <6 <6 < 41 <11 11/12/14 1335 +/- 194 <7 <9 < 42 <11 11/25/14 1077 +/- 157 <6 <6 < 35 < 10 12/10/14 1275 +/- 108 <4 <4 < 22 <6 MEAN 1251 +/- 233 C-18
Table C-VIII.3 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 Ba-140 La-140 PERIOD P4-1 01/08/14 1318 +/- 123 <5 <6 < 30 < 10 02/05/14 1339 +/- 171 <6 <6 <41 < 12 03/05/14 1290 +/- 133 <5 <6 < 26 <7 03/19/14 1465 +/- 107 <4 <5 < 19 <6 04/02/14 1487 +/- 124 <5 <5 < 23 <7 04/16/14 1390 +/- 105 <4 <4 < 19 <5 04/30/14 1378 +/- 140 <5 <5 < 38 <13 05/14/14 1430 +/- 124 <5 <5 < 20 <6 05/28/14 1482 +/- 155 <5 <6 < 26 <8 06/11/14 1388 +/- 116 <4 <4 < 18 <6 06/25/14 1363 +/- 181 <7 <7 < 27 < 10 07/09/14 1219 +/- 183 <8 <9 < 36 <8 07/23/14 1467 +/- 128 <4 <5 < 23 <6 08/06/14 1438 +/- 184 <7 <8 < 35 < 12 08/20/14 1398 +/- 182 <7 <7 < 27 <5 09/03/14 1350 +/- 136 <5 <4 < 34 <7 09/17/14 1206 +/- 118 <4 <5
- 16 <6 10/01/14 1117 +/- 184 <7 <6 < 34 < 10 10/15/14 1188 +/- 121 <5 <5 < 47 < 15 10/29/14 1366 +/- 162 <6 <7 < 42 < 15 11/12/14 1450 +/- 177 < 11 <9 < 50 < 14 11/25/14 1492 +/- 168 <7 <8 < 38 < 15 12/10/14 1411 +/- 167 <3 <2 < 16 <4 MEAN 1367 +/- 206 C-19
Table C-IX.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION SR-90 Be-7 K-40 1-131 Cs-134 Cs-137 PERIOD B10-2 Broccoli Leaves 06/30/14 <3 < 244 3697 +/- 616 < 55 < 26 < 29 Cabbage & Leaves 06/30/14 <3 < 185 4292 +/- 458 < 44 < 19 < 24 Cauliflower Leaves 06/30/14 <4 < 282 5720 +/- 608 < 58 < 23 < 29 Cabbage 07/23114 <2 < 186 2865 +/- 409 < 36 < 20 < 20 Cabbage 07/30/14 <4 < 218 2559 +/- 529 < 49
- 22
- 21 Sunflower Leaves 07/30/14 14 + 3 1595 +/- 268 6073 +/- 550 <41 < 19 < 22 Sweet Corn Leaves 07/30/14 <3 1096 +/- 229 3642 +/- 398 < 39 < 20 < 22 Sweet Corn 08/04/14 < 133 2449 +/- 376 < 18 < 15 <16 Tomatoes 08/04/14 < 95 1672 +/- 258 < 16 < 10 <11 Cabbage 08/27/14 18 + 3 < 162 2450 +/- 335 < 59 < 14 < 19 Neck Pumpkin Leaves 08/27/14 <2 2515 +/- 224 5745 +/- 416 < 52 < 12 < 16 Sunflower Leaves 08/27/14 <3 1088 +/- 190 8693 +/- 438 < 58 < 14
- 16 Cabbage 09/24/14 <2 < 108 2744 +/- 217 < 51 < 10 < 11 Neck Pumpkin Leaves 09/24/14 <2 1497 +/- 90 5150 +/- 174 < 44 <7 <8 Sunflower Leaves 09/24/14 4+/-3 795 +/- 84 6838 +/- 214 < 30 <5 <6 Sweet Potatoes 10/08/14 < 176 3518 +/- 460 < 37 < 21 < 21 MEAN 12 +/- 14 1431 +/- 1214 4257 +/- 3877 -
E1-2 Cabbage 07/23/14 <1 122 2680 +/- 279
- 22 < 12 < 14 Sweet Corn 08/04/14 179 2976 +/- 368 < 30 < 22 < 23 Tomatoes 08/04/14 148 3008 +/- 363 < 24 < 18 < 18 Sweet Potatoes 10/08/14 171 4872 +/- 546 < 32 < 19 < 21 MEAN 3384 +/- 2006 -
H1i-2 Eggplant Leaves 06/30/14 < 4 403 +/- 201 6885 +/- 497 < 37 < 19 < 19 Squash Leaves 06/30/14 8 +/-2 353 +/- 196 4753 +/- 579 < 51 < 23 < 22 Zucchini Leaves 06/30/14 4 +/-2 < 278 5055 +/- 591
- 46 < 20
- 24 Eggplant Leaves 07/30/14 <3 940 +/- 230 4196 +/- 533 < 50 < 22
- 27 Squash Leaves 07/30/14 8 +/-2 1944 +/- 270 5062 +/- 504 < 51 < 20 < 24 Zucchini Leaves 07/30/14 10 +/-2 1055 +/- 178 4452 +/- 379 < 29 < 15
- 14 Cucumber Leaves 08/27/14 < 2 1129 +/- 207 2970 +/- 322 < 58 < 14
- 15 Squash Leaves 08/27/14 13 +/- 3 488 +/- 131 2900 +/- 270 < 47 < 11
- 12 Zucchini Leaves 08/27/14 10 +/-2 563 +/- 139 4499 +/- 375 < 59 < 14
- 14 Broccoli Leaves 09/24/14 4 +/-1 < 108 3979 +/- 241 < 52 < 10 < 10 Cauliflower Leaves 09/24/14 < 2 < 110 2738 +/- 205 < 50 < 10 < 10 Turnip Greens 09/24/14 2 +/-1 < 82 6877 +/- 240 < 43 <8 <9 MEAN 7 +/-7 859 +/- 1065 4531 +/- 2723 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES C-20
Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREM/QUARTER STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE +/- 2 S.D.
A1-4 18.7 +/- 3.4 16.2 18.8 19.9 19.8 A3-1 18.6 +/- 2.6 16.8 18.7 19.7 19.4 A5-1 23.3 +/- 5.2 20.9 23.0 (1) 26.1 A9-3 19.8 +/- 3.6 17.6 19.6 20.3 21.9 B1-1 19.7 +/- 2.8 18.0 19.2 20.7 20.9 B1-2 19.2 +/- 3.0 17.1 19.3 20.5 20.1 B2-1 19.0 +/- 2.6 17.5 18.5 20.6 19.3 B5-1 22.4 +/- 4.0 19.6 22.4 24.1 23.5 Cl-i 22.1 +/- 3.2 19.9 21.9 23.3 23.2 C1-2 19.8 +/- 2.9 18.4 18.7 21.3 20.8 C2-1 20.9 +/- 3.8 18.9 20.2 23.4 21.3 C5-1 23.0 +/- 3.4 20.7 22.8 24.5 24.2 C8-1 22.5 +/- 3.9 19.7 22.7 23.7 24.0 D1-1 21.8 +/- 2.8 20.3 21.3 23.6 21.9 D1-2 20.8 +/- 3.6 18.4 20.7 22.5 21.8 02-2 25.2 +/- 5.1 21.8 24.8 26.9 27.3 D6-1 24.1 +/- 5.7 20.6 23.1 26.9 26.0 E1-2 20.5 +/- 3.0 18.8 20.1 22.3 21.0 E1-4 27.9 +/- 1.4 27.1 27.6 28.5 28.4 E2-3 23.7 +/- 4.2 20.9 23.4 25.6 25.0 E5-1 22.9 +/- 4.3 19.9 22.7 24.2 24.7 (1)
E7-1 22.6 +/- 3.6 20.2 22.2 24.2 23.8 F1-1 21.8 +/- 3.1 19.9 21.2 22.9 23.1 F1-2 35.6 +/- 4.2 37.0 35.3 37.4 32.8 F1-4 35.3 +/- 4.6 37.1 35.4 36.6 32.0 F2-1 23.9 +/- 4.1 21.2 24.0 26.1 24.3 F5-1 25.3 +/- 5.2 21.6 25.6 27.5 26.5 G1-2 22.3 +/- 3.1 20.1 22.2 23.4 23.5 G1-3 28.0 +/- 3.1 28.4 27.6 29.9 26.2 G1-5 21.7 +/- 3.2 20.1 20.9 23.8 22.1 G1-6 23.6 +/- 2.7 23.2 21.8 24.7 24.5 G2-4 25.9 +/- 5.2 22.6 25.4 28.6 27.1 G5-1 21.7 +/- 3.3 19.8 20.9 23.7 22.3 H1-1 21.5 +/- 2.9 19.6 21.2 22.4 22.8 H3-1 18.2 +/- 1.8 17.0 18.2 18.5 19.1 H5-1 18.0 +/- 2.6 16.5 17.6 19.5 18.5 H8-1 32.6 +/- 7.8 27.7 31.7 36.8 34.4 J1-1 19.5 +/- 3.6 17.2 18.9 20.8 21.0 J1-3 18.0 +/- 2.1 16.9 17.4 19.1 18.7 J3-1 21.5 +/- 4.4 18.7 21.0 22.8 23.7 J5-1 23.5 +/- 6.1 20.0 22.1 25.9 26.2 J7-1 25.5 +/- 5.0 22.4 24.6 27.2 27.8 K1 -4 19.7 +/- 2.9 18.3 18.7 21.2 20.7 K2-1 23.6 +/- 4.3 20.7 23.2 25.1 25.4 K3-1 19.6 +/- 3.9 17.6 18.4 21.9 20.4 K5-1 23.2 +/- 4.7 20.2 23.0 23.8 25.8 K8-1 23.0 +/- 3.8 20.5 22.6 24.7 24.3 L1-1 20.4 +/- 3.0 18.4 20.3 21.7 21.2 (1) SEE PROGRAM EXCEPTIONS SECTION FOR INFORMATION C-21
Table C-X.1 QUARTERLY OSLD RESULTS FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREM/QUARTER STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE +/- 2 S.D.
L1-2 19.9 +/- 2.5 18.4 19.4 21.1 20.7 L2-1 21.8 +/- 2.8 19.9 21.5 22.8 22.9 L5-1 20.4 +/- 2.4 18.9 20.0 21.4 21.3 L8-1 22.0 +/- 4.7 18.8 21.7 24.1 23.4 MI-i 18.1 +/- 2.3 16.5 18.1 19.2 18.5 M1-2 21.3 +/- 4.9 18.5 20.2 23.7 23.0 M2-1 19.3 +/- 3.2 17.5 18.7 21.3 19.6 M5-1 21.3 +/- 3.5 19.0 21.0 22.8 22.6 M9-1 26.0 +/- 4.8 23.1 25.1 28.6 27.2 N1-1 20.8 +/- 4.2 18.3 19.9 22.9 22.1 N1-3 20.5 +/- 3.0 19.0 19.8 22.4 21.0 N2-1 22.3 +/- 4.4 19.7 21.3 23.5 24.7 N5-1 18.7 +/- 3.6 16.5 18.3 20.8 19.1 N8-1 22.7 +/- 3.0 20.8 22.5 24.1 23.7 P1-i 20.5 +/- 3.2 18.3 20.6 21.7 21.7 P1-2 19.0 +/- 2.4 17.7 18.5 20.4 19.6 P2-1 25.2 +/- 5.0 21.9 25.0 26.3 27.7 P5-1 22.4 +/- 4.4 19.6 21.9 24.8 23.3 P8-1 19.1 +/- 3.7 16.8 18.7 21.0 20.1 Q1-1 20.9 +/- 3.6 18.8 20.1 22.3 22.4 Q1-2 17.7 +/- 2.4 16.2 17.3 18.5 18.8 Q2-1 19.4 +/- 4.0 16.8 19.0 21.4 20.5 Q5-1 20.2 +/- 2.8 18.6 19.6 21.4 21.3 Q9-1 20.9 +/- 4.3 17.9 20.8 22.3 22.7 R1-1 18.5 +/- 2.4 16.9 18.4 19.9 18.8 R1-2 19.2 +/- 2.7 17.6 18.7 20.6 20.0 R3-1 24.3 +/- 4.2 21.3 24.3 25.8 25.7 R5-1 22.9 +/- 4.5 19.6 23.2 24.4 24.3 R9-1 23.2 +/- 2.6 21.5 23.3 24.5 23.6 B10-1 21.3 +/- 2.8 19.2 21.8 22.2 22.2 D15-1 21.8 +/- 3.9 19.5 21.1 24.0 22.7 F10-1 25.4 +/- 5.0 22.4 24.5 27.8 27.1 F25-1 23.1 +/- 3.2 20.9 23.2 23.6 24.7 G10-1 29.5 +/- 5.9 25.2 30.2 30.8 31.8 G15-1 26.1 +/- 2.0 24.7 27.0 26.7 26.0 H15-1 22.4 +/- 4.0 19.7 22.5 24.4 23.3 J15-1 24.8 +/- 4.3 22.4 23.7 26.9 26.4 K15-1 21.0 +/- 2.9 19.7 19.9 22.7 21.9 L15-1 21.7 +/- 4.2 19.1 21.3 24.1 22.4 N15-2 23.7 +/- 4.2 21.1 23.1 25.7 25.1 Q15-1 23.8 +/- 4.6 21.0 23.0 25.5 25.9 R15-1 21.3 +/- 2.1 19.9 21.1 22.4 21.6 C-22
TABLE C-X.2 MEAN QUARTERLY OSLD RESULTS FOR THE SITE BOUNDARY, INDICATOR AND CONTROL LOCATIONS FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA I I COLLECTION SITE BOUNDARY INDICATOR CONTROL PERIOD +/-2 S.D.
JAN-MAR 21.3 +/- 13.0 19.5 +/- 4.0 21.2 +/- 4.2 APR-JUN 21.9 +/- 11.1 21.6 +/- 5.0 23.3 +/- 5.9 JUL-SEP 23.7 +/- 11.1 23.6 +/- 5.8 25.2 +/- 4.8 OCT-DEC 22.5 +/- 8.7 23.3 +/- 5.7 24.7 +/- 5.8 TABLE C-X.3
SUMMARY
OF THE AMBIENT DOSIMETRY PROGRAM FOR THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF MILLIREMQUARTER LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/- 2 S.D.
SITE BOUNDARY 76 16.2 37.4 22.4 +/- 11.0 INDICATOR 239 16.5 36.8 22.0 + 6.1 CONTROL 44 19.1 31.8 23.6 +/- 5.9 SITE BOUNDARY STATIONS - AI-4, B1-2, Cl-2, Di-1, E1-4, F1-2, FI-4, G1-3, G1-5, G1-6, H1-1, J1-3, K1-4, LI-1, Mi-1, N1-3, P1-2, Q1-2, Ri-i INDICATOR STATIONS - A3-1, A5-1, A9-3, Bi-1, B10-1, B2-1, B5-1, Cl-1, C2-1, C5-1, C8-1, D1-2, D2-2, D6-1, Ei-2, E2-3, E5-1, E7-1, Fi-1, F10-1, F2-1, F5-1, G1-2, G2-4, G5-1, H3-1, H5-1, H8-1, Ji-1, J3-1, J5-1, J7-1, K2-1, K3-1, K5-1, K8-1, Li-2, L2-1, L5-1, L8-1, M1-2, M2-1, M5-1, M9-1, Ni-i, N2-1, N5-1, N8-1, Pi-1, P2-1, P5-1, P8-1, Qi-i, Q2-1, Q5-1, Q9-1, R1-2, R3-1, R5-1, R9-1 CONTROL STATIONS - D15-1, F25-1, G10-1, G15-1, H15-1, J15-1, K15-1, L15-1, N15-2, Q15-1, R15-1 C-23
FIGURE C-1 Monthly Tritium Concentrations in Surface Water and Effluent Water Three Mile Island Nuclear Station, 2014 0 Station J1-2 (Downstream of Discharge) U Station Q9-1 (Control) 1_
10000 -
..h.
10000- ...........................................
1000-i...................... o...... .. o............. .................................................
100-10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec n'.
Month E Station K1-1 (TMINS Liquid Discharge) 1000000 100000-10000-1000-o 100-
- a. 10 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month
FIGURE C-2 Mean Quarterly Tritium Concentrations in Surface Water Three Mile Island Nuclear Station, 1974 - 2014
- Indicator Samples - Control Samples 12000 II 11000 10000 9000 8000 7000 t'j LAh
- 0. 6000 cn 0) 5000 U
0 C-)
0~ 4000 3000 2000 1000 0
-1000 LO (0C r'-
1- w- a '( N 0 D f- w MCD 0 y- " Loco M 1-CD m D cD N 0m L~*
DO I- wO) MD 0 - - NC*- I r-f-r- I-C wO CD~~~~~
DC D
D D
DC CD ~~
g CO SDC CD M
C' MMMCD CD C" D 0a NDN CD a O~
C' CD aD a 00-aD aD a a CND N(N N~N N N N N " N(N (N Year
FIGURE C-3 Mean Monthly Gross Beta Concentrations in Drinking Water Three Mile Island Nuclear Station, 2014 El Indicator Samples E] Control Samples 10 9
8 7 --
FIGURE C-4 Mean Monthly Tritium Concentrations in Drinking Water and Effluent Water Three Mile Island Nuclear Station, 2014 NOTE: The mean values are calculated using both the MDCs and EJ Indicator Samples M Control Samples the positive values.
500 NOTE: USEPA Drinking Water Limit for Tritium: 20,000 pCi/L
"* 400 .. . . . .. . ..
a:D
- 0) 300 200 C.) 300 -- -; -t - - - - ---
o 200 -- - -::
-- -s~ -. -~E~. - - - :::
(L 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month
-. 1 N Station K1-1 (TMIINS Liquid Discharge) 1000000 a) 100000-I...
a) a- 10000-0) a)
0 0
U
- 15:
1000-100-10-I--/- 1---
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 - 2014 Indicator Samples -,,- Control Samples 900 -]"
Significant Event 800 Chemobyl - ----- April 1986 . .........
700 - . .. . .... . .... - - - - -
E A-0 42300 - - - -
a.\
200 .. . . . .
100 -_ !
0 Year
FIGURE C-6 Mean Quarterly Gross Beta Concentrations in Air Particulates Three Mile Island Nuclear Station, 1972 - 2014 Indicator - Control 0.4 TMI-1 Critical June 1974 March 1972 June 1973 0.35 TMI-2 Critical March 1978 June 1974 September 1 TMI-2 Accident March 1979 September 1976 November 1 TMI-2 RB Purge June 1980 September 1977 March 1978 e 0.3 (D
0.25 U
k)
~30.
0~
C.,
0.2 4.
8 0.15 Q.6 0.1 0.05 0
1--.
M ~~
r- -
1- N-f,
~ 0- ~0ý 9 ~ C O0r-W CO If LO W CO COw r-CO w)
W
~
w)
M~.
w) M)
- N (n
M M
VU' M M M CD oI-M 0DZ 0 CD 0 M a0 CD f CO Wf 0 0CDC 0 0ý 0)0 )0 )0 )0 )0 )0 ) )0 )0 0))0 0))0 )0 )0 ) 0 D n0 0 03 0D 0 0 a 0 0' 0 0 0 0 0D Year-
FIGURE C-7 Mean Weekly Gross Beta Concentrations in Air Particulates-Three Mile Island Nuclear Station, 2007 - 2014 0.100
-- Indicator -- Control 0 .0 90 . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. .. . . . .
0.080
$ 0.070
.2 0.060 16 0.05 0 -- .. - -- .--.-- -- - .-- . . -. -- --- .-.- --. . . - -- --.-. ----.- ----
8 oo 0.020 0.010 - -
0.0001 0 0 ;a a il a i:4 0 ~0 /;z ay -
4 / 0Year Nz N iN F4Mo*
Month IDay / Year Ihe high value on I1/24/2U09 was caused by an airborne release on 11/21/2009
FIGURE C-8 Mean Quarterly Strontium-90 Concentrations in Cow Milk Three Mile Island Nuclear Station, 1979 - 2014
- Indicator Samples - Control Samples in Significant Events Maior Atm. Nuclear Weapon Tests
_ TMI-2 Accident March 1979 December 1978 October 1980 9-TMI-2 RB Purge June 1980 Chemobyl April 1986 8-7-
L..
6-5 0.
0 4 0
F,)
3 A-~ --A 2
AA*r\
1+
0 i11111 Iit i I 1111 t It ll ti ii 1 k:1 a) I- 0M4
) GoN 0)
CD'M C) D C.) C. CD U-) 8-001 0) 8)
0) iM 0Z; t%
04* ' ~ ~ U
-! T-R R 11 NR R 8 N N N N N N N N N N Year
I Intentionally left blank
APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY
Intentionally left blank The following section presents the results of data analysis performed by the QC laboratory, Environmental Inc. Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and the QC laboratory. Comparison of the results for most media were within expected ranges. Q D-1
I Intentionally left blank D-2
TABLE D-I.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 12/31/13 - 01/28/ 14 < 1.2 01/28/14 - 02/25/ 14 1.6 +/- 0.7 02/25/14 - 04/01/ 14 < 1.3 04/01/14 - 04/29/ 14 < 1.8 04/29/14 - 06/03/ 14 < 0.8 06/03/14 - 07/01/ 14 < 1.3 07/01/14 - 07/29/ 14 < 0.9 07/29/14 - 09/02/ 14 1.8 +/- 0.9 09/02/14 - 09/30/ 14 2.2 +/- 0.8 09/30/14 - 10/28/ 14 1.3 +/- 0.6 10/28/14 - 12/02/ 14 3.5 +/- 1.1 12/02/14 - 12/30/ 14 1.5 +/- 0.7 MEAN 2.0 +/- 1.6 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-1Q PERIOD 12/31/13 01/28/14 147 01/28/14 02/25/14 146 02/25/14 04/01/14 148 04/01/14 04/29/14 145 04/29/14 06/03/14 142 06/03/14 07/01/14 134 07/01/14 07/29/14 131 07/29/14 09/02/14 177 09/02/14 09/30/14 149 09/30/14 10/28/14 169 10/28/14 12/02/14 169 12/02/14 12/30/14 175 MEAN TABLE D-I.3 CONCENTRATIONS OF IODINE-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION Q9-10 PERIOD 1213113 - 0112814 < 0.2 01/28/14 - 02/25/14 < 0.3 02/25/14 - 04/01/14 < 0.3 04/01/14 - 04/29/14 < 0.3 04/29/14 - 06/03/14 < 0.2 06/03/14 - 07/01/14 < 0.4 07/01/14 - 07/29/14 < 0.3 07/29/14 - 09/02/14 < 0.2 09/02/14 - 09/30/14 < 0.3 09/30/14 - 10/28/14 < 0.3 10/28/14 - 12/02/14
- 0.3 12/02/14 - 12/30/14 < 0.2 MEAN THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES D-3
TABLE D-I.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q9-1Q 12/31/13 - 01/28/14 < 3 <4 < 3 < 3 <4 < 3 <4 <2 <2 <8 <2 01/28/14 - 02/25/14 <2 <5 <2 <2 <5 <4 <2 <2 <3
- 15 <3 02/25/14 - 04/01/14 <2 <2 <3 <1 <3 <3 <3 <3 <2 < 16 <3 04101/14 - 04/29/14 <3 <3 <3 <2 <3 <5 <3 <2 <3 < 13 <3 04/29/14 - 06/03/14 <4 <4 <3 <2 <5 <4 <5 <4 <3 <15 <2 06/03/14 - 07/01/14 <3 <7 <3 <4 <4 <7 <4 <3 <4 <17 <5 07/01/14 - 07/29/14 <3 <6 <4 <2 <5 <5 <2 <2 <4 < 27 <7 07/29/14 - 09/02/14 <2 <4 <2 <2 <2 <5 <3 <2 <2 < 23 <5 09/02/14 - 09/30/14 <3 <6 <5 <3 <6 <6 <4 <3 <3 < 14 <2 09/30/14 - 10/28/14 <2 <2 <2 <3 <3 <5 <3 <2 <2 < 20 <5 10/28/14 - 12/02/14 <3 <6 <3 <2 <3 <5 <4 <4 <4 < 12 <4 12/02/14 - 12/30/14 <3 <3 <3 <3 <3 <4 <2 <2 <3 < 15 <2
TABLE D-1I.1 CONCENTRATIONS OF STRONTIUM AND GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION Sr-89 Sr-90 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 PERIOD INDP 09/24/14 < 10 < 7 3210 +/- 380 < 13 < 14 < 22 < 17 < 18 < 10 < 14
TABLE D-III.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 Cs-134 Cs-137 PERIOD J2-1 10/31/14 9443 +/- 631 < 18 < 26 A1-3 10/31/14 9891 +/- 652 <21 < 24 MEAN 9667 +/- 634 D-6
TABLE D-IV.1 CONCENTRATIONS OF GAMMA EMITTERS AND STRONTIUM IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA SITE COLLECTION K-40 1-131 Cs-134 Cs-1 37 Sr-89 Sr-90 PERIOD PERIOD H1-2Q 07/30/14 4580 +/- 340 < 22 < 10 <9 <15 8+/-5 B10-2Q 07/23/14 2720 +/- 320 < 12 < 11 <10 <3 2+/-1 MEAN 3650 +/- 2630 D-7
TABLE D-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE AND 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION El-2Q El -20 PERIOD GROSS BETA 1-13 1 01/09/14 O1/U9/14 25 -+/--5 < 1I E1-2Q 1-131 01/09114 01/15/14 30 +/- 5
- 13 01/15/14 01/23/14 29 +/- 4
- 14 01/23/14 01/30/14 24 +/- 4
- 19 01/30/14 02/06/14 26 +/- 4 < 17 02/06/14 02/12/14 (1) (1) 02/12/14 02120/14 27 +4 < 17 02/20/14 02/27/14 20 +5
- 21 02127/14 03/06/14 37 +5
- 25 03/06/14 03/12/14 28 +5 < 18 03/12/14 03/20/14 20 +4 < 25 03/20/14 03/27/14 24 +5 < 25 03/27/14 04/03/14 17+/- 4
- 15 04/03/14 04/10/14 17 +/-4 < 19 04/10/14 04/17/14 21 +4
- 16 04/17/14 04/23/14 26 +/-5
- 21 04/23/14 05/01/14 14+/- 3 < 10 05/01/14 05/07/14 17 5 < 11 05/07114 05/15/14 21 +/- 4
- 20 05/15/14 05/22/14 25 +/- 4
- 20 05/22/14 05/29/14 24 +/- 4
- 24 05/29/14 06/05/14 15 +/- 4 < 26 06/05/14 06/11/14 16 +/- 5 < 17 06/11/14 06/19/14 17 +/- 4 < 14 06/19/14 06/25/14 16 +/- 5 < 19 06/25/14 07/03/14 21 +/- 4
- 27 07/03/14 07/10/14 24 +/- 5
- 23 07/10/14 07/17/14 25 +/- 4 < 25 07/17/14 07/24/14 (1) (1) 07/24/14 07/31/14 19 +/- 5
- 21 07131/14 08/07/14 24 +/- 5
- 28 08/07/14 08/14/14 21 +/- 5 < 25 08/14/14 08/21/14 25 +/- 5 < 25 08/21/14 08/28/14 26 +/- 4 < 33 08/28/14 09/04/14 25 +/- 4 < 18 09104/14 09/10/14 23 +/- 5 < 18 09/10/14 09/18/14 21 +/- 4 < 25 09/18/14 09/25/14 30 +/- 5 < 33 09/25/14 10/02/14 31 +/- 5 < 14 10/02/14 10/09/14 23 +/- 4 < 23 10/09/14 10/16/14 24 +/- 4
- 24 10/16/14 10/23/14 11+/- 4 < 14 10/23/14 10/30/14 28 +/-4 < 12 10/30/14 11/06/14 20 +4 < 19 11/06/14 11/13/14 22 +/-4 < 24 11/13/14 11/20/14 24 +/-4 < 30 11/20/14 11/26/14 33 +/-6
- 31 11126114 12/04/14 22 +4
- 19 12/04/14 12/11/14 25 +/-4 < 14 12/11/14 12/17/14 27 +/-5 < 18 12/17/14 12/24/14 15+/- 4 < 27 12/24/14 01/01/15 21 +4 < 18 MEAN 23 +/- 10 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION D-8
TABLE D-V.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA SITE COLLECTION Be-7 Cs-1 34 Cs-1 37 PERIOD E1-2Q 01/02/14 - 04/03/14 80 +/- 16 < 0.9 < 0.7 04/03/14 - 07/03/14 93 +/- 18 < 0.5 < 0.6 07/03/14 - 10/02/14 87 +/- 19
- 1.3 < 1.1 10/02/14 - 01/01/15 62 +/- 16 < 1.0 < 0.9 MEAN 81 +/- 27 D-9
TABLE D-VI.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION, GAMMA EMITTERS, AND STRONTIUM IN MILK SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION 1-131 K-40 Cs-1 34 Cs-1 37 Ba-140 La-140 Sr-89 Sr-90 DATE G2-1Q 01/08/14 < 0.3 1403 +/- 103 <3 <3 < 22 <5 02/05114 < 0.3 976 +/- 103 <6 <4 < 21 <5 03/05/14 < 0.4 863 +/- 94 <5 <2 < 19 <4 03/19/14 < 0.5 1042 +/- 96 <4 <4 < 18 <5 < 0.5 0.5 +/- 0.3 04/02/14 < 0.3 978 +/- 95 <4 <4 < 21 <4 04/16/14 < 0.3 757 +/- 147 < 11 <4 < 17 <9 04/30/14 < 0.3 1032 +/- 96 <4 <3 < 19 <3 05/14/14 < 0.5 1082 +/- 102 <3 <3 < 26 <4 05/28/14 < 0.3 997 +/- 115 <6 <6 < 17 <3 06111/14 < 0.4 899 +/- 80 <3 <2 < 14 <4 < 1.0 < 0.5 06125/14 < 0.4 1023 +/- 88 <3 <3
- 20 <5 07/09/14 < 0.2 1468 +/- 106 <3 <3 < 26 <3 07/23/14 < 0.3 1013 +/- 88 <4 <3 < 34 <3 08/06/14 < 0.2 763 +/- 79 <3 <3 <41 <7 08/20/14 < 0.3 1267 +/- 107 <3 <3
- 31 <3 09/03/14 < 0.4 1314 +/- 125 <2 <3 < 16 <2 09/17/14 < 0.3 1001 +/- 143 <6 <4 < 25 <6 < 0.7 < 0.6 10/01/14 < 0.4 1230 +/- 123 <5 <5 < 23 <2 10/15/14 < 0.4 1191 +/- 76 <2 <2 < 25 <6 10/29/14 < 0.3 759 +/- 87 <3 <3 < 22 <4 11/12/14 < 0.4 799 +/- 64 <3 <4 < 24 <7 11/25/14 < 0.2 910 +/- 94 <3 <4 < 27 <2 12/10/14 < 0.3 988 +/- 91 <3 <5 < 23 <3 < 0.8 < 0.5 MEAN 1033 +/- 408 D-10
FIGURE D-1 MONTHLY GROSS BETA CONCENTRATIONS IN 6
DRINKING WATER SAMPLES COLLECTED FROM TMINS LOCATION Q9-1Q, 2014 i 0c________.
QC-LAB
________ l_
S....................................................................................--a- PRIM A RY - LA B 4
4.. 3 2
1 0
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH
FIGURE D-2 WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM TMINS LOCATION E1-2Q, 2014 60 50
- (D40 E
30 I"J C.)
C.)
LW20 10 0
1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.
APPENDIX E INTER-LABORATORY COMPARISON PROGRAM
Intentionally left blank TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
March 2014 E10854 Milk Sr-89 pCi/L 95.1 91.7 1.04 A Sr-90 pCi/L 10.9 15.1 0.72 W E10855 Milk 1-131 pCi/L 96.6 98.5 0.98 A Ce-141 pCi/L 112 119 0.94 A Cr-51 pCi/L 449 491 0.91 A Cs-1 34 pCi/L 186 210 0.89 A Cs-137 pCi/L 250 253 0.99 A Co-58 pCi/L 248 268 0.93 A Mn-54 pCi/L 292 297 0.98 A Fe-59 pCi/L 230 219 1.05 A Zn-65 pCi/L 312 323 0.97 A Co-60 pCi/L 321 337 0.95 A E10857 AP Ce-141 pCi 53.0 53.9 0.98 A Cr-51 pCi 232 223 1.04 A Cs-134 pCi 100 95.3 1.05 A Cs-1 37 pCi 122 115 1.06 A Co-58 pCi 122 121 1.01 A Mn-54 pCi 135 135 1.00 A Fe-59 pCi 111 99.3 1.12 A Zn-65 pCi 140 147 0.95 A Co-60 pCi 187 153 1.22 W E10856 Charcoal 1-131 pCi 74.1 76.4 0.97 A E10858 Water Fe-55 pCi/L 2090 1760 1.19 A June 2014 E10913 Milk Sr-89 pCi/L 85.9 91.3 0.94 Sr-90 pCi/L 13.8 14.5 0.95 E10914 Milk 1-131 pCi/L 86.5 90.9 0.95 Ce-141 pCi/L 111 124 0.90 Cr-51 pCi/L 255 253 1.01 Cs-134 pCi/L 147 162 0.91 Cs-137 pCi/L 123 120 1.03 Co-58 pCi/L 105 112 0.94 Mn-54 pCi/L 155 156 0.99 Fe-59 pCi/L 106 102 1.04 Zn-65 pCi/L 251 252 1.00 Co-60 pCi/L 218 224 0.97 E10916 AP Ce-141 pCi 95.1 92.6 1.03 Cr-51 pCi 215 190 1.13 Cs-1 34 pCi 122 122 1.00 Cs-1 37 pCi 95.1 89.8 1.06 Co-58 pCi 88.7 84.1 1.05 Mn-54 pCi 115 116 0.99 Fe-59 pCi 72.6 76.7 0.95 Zn-65 pCi 193 189 1.02 Co-60 pCi 179 168 1.07 E10915 Charcoal 1-131 pCi 85.6 85.2 1.00 E10917 Water Fe-55 pCi/L 1680 1810 0.93 A E-1
TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
September2014 E10946 Milk Sr-89 pCi/L 90.7 96.9 0.94 Sr-90 pCi/L 14.0 16.4 0.85 E10947 Milk 1-131 pCi/L 92.0 97.6 0.94 Ce-141 pCi/L 117 126 0.93 Cr-51 pCi/L 281 288 0.98 Cs-134 pCi/L 141 158 0.89 Cs-1 37 pCi/L 186 193 0.96 Co-58 pCi/L 137 143 0.96 Mn-54 pCi/L 138 142 0.97 Fe-59 pCi/L 162 158 1.03 Zn-65 pCi/L 75.2 73.0 1.03 Co-60 pCi/L 286 297 0.96 E10949 AP Ce-141 pCi 97.8 82.1 1.19 Cr-51 pCi 212 188 1.13 Cs-134 pCi 106 103 1.03 Cs-137 pCi 131 126 1.04 Co-58 pCi 85.7 93.0 0.92 Mn-54 pCi 92.8 92.3 1.01 Fe-59 pCi 113 103 1.10 Zn-65 pCi 53.2 47.5 1.12 Co-60 pCi 202 193 1.05 E10948 Charcoal 1-131 pCi 83.9 89.8 0.93 E10950 Water Fe-55 pCi/L 2010 1720 1.17 A E10951 Soil Ce-141 pCi/g 0.208 0.186 1.12 A Cr-51 pCi/g 0.398 0.425 0.94 A Cs-1 34 pCi/g 0.216 0.233 0.93 A Cs-137 pCi/g 0.398 0.365 1.09 A Co-58 pCi/g 0.197 0.211 0.93 A Mn-54 pCi/g 0.242 0.209 1.16 A Fe-59 pCi/g 0.238 0.233 1.02 A Zn-65 pCi/g 0.117 0.108 1.08 A Co-60 pCi/g 0.447 0.438 1.02 A December 2014 El1078 Milk Sr-89 pCi/L 85.7 95.7 0.90 A Sr-90 pCi/L 12.9 15.6 0.83 A El1079 Milk 1-131 pCi/L 85.9 95.1 0.90 A Ce-141 pCi/L 205 219 0.94 A Cr-51 pCi/L 402 406 0.99 A Cs-134 pCi/L 156 164 0.95 A Cs-137 pCi/L 194 198 0.98 A Co-58 pCi/L 122 130 0.94 A Mn-54 pCi/L 220 225 0.98 A Fe-59 pCi/L 183 175 1.05 A Zn-65 pCi/L 287 297 0.97 A Co-60 pCi/L 224 235 0.95 A E-2
TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 3 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)
December 2014 El1081 AP Ce-141 pCi 96.4 102 0.95 A Cr-51 pCi 171 190 0.90 A Cs-134 pCi 73.1 76.9 0.95 A Cs-137 pCi 99.0 92.6 1.07 A Co-58 pCi 57.5 60.8 0.95 A Mn-54 pCi 107 105 1.02 A Fe-59 pCi 74.2 81.6 0.91 A Zn-65 pCi 144 139 1.04 A Co-60 pCi 114 110 1.04 A El1080 Charcoal 1-131 pCi 93.5 98.2 0.95 A E11082 Water Fe-55 pCi/L 1760 1970 0.89 A (a) Teledyne Brown Engineering reported result.
(b) The Analytics known value is equal to 100% of the parameterpresent in the standardas determinedby gravimetricand/or volumetric measurements made during standardpreparation.
(c) Ratio of Teledyne Brown Engineering to Analytics results.
(d) Analytics evaluation based on TBE internalQC limits: A= Acceptable, reportedresult falls within ratiolimits of 0.80-1.20.
W-Acceptable with warning, reported result falls within 0. 70-0.80 or 1.20-1.30. N = Not Acceptable, reported result falls outside the ratio limits of < 0. 70 and > 1.30.
E-3
TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 1)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits Evaluation (c)
May 2014 RAD-97 Water Sr-89 pCi/L 38.25 36.7 27.5 - 43.6 A Sr-90 pCi/L 24.65 26.5 19.2 - 30.9 A Ba-1 33 pCi/L 89.1 87.9 74.0 - 96.7 A Cs-134 pCi/L 45.55 44.3 35.5 -48.7 A Cs-137 pCi/L 91.15 89.1 80.2- 101 A Co-60 pCi/L 65.10 64.2 57.8 - 73.1 A Zn-65 pCi/L 244 235 212-275 A Gr-A pCi/L 45.65 61.0 31.9 - 75.8 A Gr-B pCi/L 27.95 33.0 21.4-40.7 A 1-131 pCi/L 23.75 25.7 21.3-30.3 A U-Nat pCi/L 9.61 10.2 7.95-11.8 A H-3 pCi/L 8435 8770 7610-9650 A MRAD-20 Filter Gr-A pCi/filter 28.0 46.0 15.4-71.4 A November 2014 RAD-99 Water Sr-89 pCiIL 30.4 31.4 22.8 - 38.1 A Sr-90 pCi/L 18.6 21.8 15.6-25.7 A Ba-133 pCi/L 46.8 49.1 40.3 - 54.5 A Cs-134 pCi/L 88.0 89.8 73.7- 98.8 A Cs-137 pCi/L 99.0 98.8 88.9-111 A Co-60 pCi/L 92.5 92.1 82.9- 104 A Zn-65 pCi/L 325 310 279 - 362 A Gr-A pCi/L 29.9 37.6 19.4-48.1 A Gr-B pCi/L 27.5 27.4 17.3-35.3 A 1-131 pCi/L 15.8 20.3 16.8-24.4 N (1)
U-Nat pCi/L 5.74 5.80 4.34 - 6.96 A H-3 pCi/L 6255 6880 5940 - 7570 A MRAD-21 Filter Gr-A pCi/filter 27.3 36.9 12.4 - 57.3 A (1) The Iodine-131 was evaluatedas failed with a ratio of 0. 778. No cause could be found for the slighly low activity. TBE would evaluate this as acceptablle with warning. A rerun was not possible due to 1-131 decay. All ERA /odine-131 evaluations since 2004 have been acceptable. NCR 14-08 (a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.
(c) ERA evaluation:A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.
E-4
TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2014 (PAGE 1 OF 2)
Identification Reported Known Acceptance MonthNear Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c)
March 2014 14-MaW30 Water Am-241 Bq/L 0.764 0.720 0.504 - 0.936 A Cs-134 Bq/L 20.7 23.1 16.2-300 A Cs-137 Bq/L 28.0 28.9 20.2 - 37.6 A Co-57 Bq/L 26.5 27.5 19.3 - 35.8 A Co-60 Bq/L 15.6 16.0 11.2-20.8 A H-3** Bq/L NR 321 225 -417 N (3)
Mn-54 Bq/L 13.5 13.9 9.7- 18.1 A Ni-63 Bq/L NR 34.0 23.8 - 44.2 N (3)
Pu-238 Bq/L 0.911 0.828 0.580 - 1.076 Pu-239/240 Bq/L 0.751 0.676 0.473 - 0.879 K-40 Bq/L NR (1) N (3)
Sr-90** Bq/L NR 8.51 5.96- 11.06 N (3)
U-234/233** Bq/L NR 0.225 0.158 - 0.293 N (3)
U-238** Bq/L NR 1.45 1.02-1.89 N (3)
Zn-65 Bq/L -0.201 (1) A 14-MaS30 Soil Cs-134 Bq/kg 2.02 (1) A Cs-137 Bq/kg 1300 1238 867 - 1609 A Co-57 Bq/kg 1069 966 676- 1256 A Co-60 Bq/kg 1.32 1.22 (2) A Mn-54 Bq/kg 1510 1430 1001 - 1859 A K-40 Bq/kg 669 622 435 - 809 A Sr-90 Bq/kg 4.14 (1) A Zn-65 Bq/kg 763 695 487 - 904 A 14-RdF30 AP Cs-134** Bq/sample NR 1.91 1.34-2.48 N (3)
Cs-137** Bq/sample NR 1.76 1.23-2.29 N (3)
Co-57** Bq/sample NR (1) N (3)
Co-60** Bq/sample NR 1.39 0.97 - 1.81 N (3)
Mn-54** Bq/sample NR (1) N (3)
Sr-90 Bq/sample 0.8220 1.18 0.83-1.53 N (3)
Zn-65** Bq/sample NR (1) N (3) 14-GrF30 AP Gr-A Bq/sample 0.606 1.77 0.53-3.01 A Gr-B Bq/sample 0.7507 0.77 0.39- 1.16 A 14-RdV30 Vegetation Cs-134 Bq/sample 5.96 6.04 4.23 - 7.85 A Cs-1 37 Bq/sample 5.06 4.74 3.32-6.16 A Co-57 Bq/sample 11.8 10.1 7.1 - 13.1 A Co-60 Bq/sample 7.34 6.93 4.85 - 9.01 A Mn-54 Bq/sample 8.95 8.62 6.03- 11.21 A Sr-90 Bq/sample 1.23 1.46 1.02-1.90 A Zn-65 Bq/sample 8.91 7.86 5.50- 10.22 A E-5
TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2014 (PAGE 2 OF 2)
Identification Reported Known Acceptance Month/Year Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c)
September 2014 14-MaW31 Water Am-241 Bq/L 0.705 0.88 0.62- 1.14 A Cs-134*** Bq/L NR (1) N (4)
Cs-137*** Bq/L NR 18.4 12.9(- 23.9 N (4)
Co-57*** Bq/L NR 24.7 17.3-32.1 N (4)
Co-60*** Bq/L NR 12.4 8.7-16.1 N (4)
Mn-54*** Bq/L NR 14.0 9.8 - 18.2 N (4)
Ni-63 Bq/L 24.07 24.6 17.2-32.0 A Pu-238 Bq/L 0.591 0.618 0.433 - 0.803 A Pu-2391240 Bq/L 0.0153 0.0048 (2) A K-40*** Bq/L NR 161 113-209 N (4)
Zn-65*** Bq/L NR 10.9 7.6- 14.2 N (4) 14-MaS31 Soil Cs-i 34*~* Bq/kg NR 622 435-809 N (4)
Cs-i 37*** Bq/kg NR (1) N (4)
Co-57*** Bq/kg NR 1116 781-1451 N (4)
Co-60~** Bq/kg NR 779 545-1013 N (4)
Mn-54*** Bq/kg NR 1009 706-1312 N (4)
K-40*** Bq/kg NR 824 577-1071 N (4)
Sr-90 Bq/kg 694 858 601-1115 A Zn-65*** Bq/kg NR 541 379-703 N (4) 14-RdF31 AP Sr-90 Bq/sample 0.310 0.703 0.492 - 0.914 N (4) 14-GrF31 AP Gr-A Bq/sample 0.153 0.53 0.16-0.90 N (4)
Gr-B Bq/sample 0.977 1.06 0.53- 1.59 A September 2014 14-RdV31 Vegetation Cs-134 Bq/sample 7.31 7.38 5.17-9.59 A Cs-137 Bq/sample 8.93 8.14 5.70 - 10.58 A Co-57 Bq/sample 10.8 9.2 6.4- 12.0 A Co-60 Bq/sample 6.31 6.11 4.28 - 7.94 A Mn-54 Bq/sample 7.76 7.10 4.97 - 9.23 A Sr-90 Bq/sample 0.738 0.85 0.60-1.11 A Zn-65 Bq/sample 7.16 6.42 4.49 - 8.35 A
- The MAPEP cross check isotope list has been reduced due to duplication of effort or analysis not being performed for clients.
These nuclides are no longer part of the TBE cross check program due to duplication of effort or analysis not being performed for clients. MAPEP evaluates non-reported analyses as failed ifthey were reported in the previous series.
All future gamma cross check samples for these isotopes will be provided by Analytics.
(I) False positive test.
(2) Sensitivity evaluation.
(3) Water, Ni-63 overlooked when reporting, but the result of 32. 7 +- 1.69 would have passed the acceptance criteria. NCR 14-04 Water, the non-detected K-40 was overlooked when reporting, but would have passed the false positive test. NCR 14-04 AP, Sr-S0 rerun was within the low range of the acceptqancecriteria. The originaland rerun results were statistically the same. No cause could be identified for the slightly low Sr-90 activity. NCR 14-04 For non reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-04 (4) AP, Sr-90 gravimetric yield was very high at 117%. Could indicatelargerthan normal amounts of calcium in the AP. A second fuming HNO 3 separationwould be requiredto remove the excess calcium. NCR 14-09 AP, Gr-Alpha was counted on the wrong side. When flipped over and recounted the results were acceptable. NCR 14-09 Fornon reported (NR) analyses, MAPEP evaluates as failed if they were reported in the previous series. NCR 14-09 (a) Teledyne Brown Engineering reported result.
(b) The MAPEPknown value is equal to 100% of the parameterpresent in the standardas determined by gravimetric and/or volumetric measurementsmade during standardpreparation.
(c) DO__MAPEPevaluation:A=acceptable, W=acceptablewith warning, N=not acceptable.
E-6
TABLE E-4 ERA (a) STATISTICAL
SUMMARY
PROFICIENCY TESTING PROGRAMa ENVIRONMENTAL, INC., 2014 (Page 1 of 1)
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1384 04/07/14 Sr-89 40.29 +/- 5.76 36.70 27.50 - 43.60 Pass ERW-1 384 04/07/14 Sr-90 24.08 +/- 2.35 26.50 19.20 - 30.90 Pass ERW-1385 04/07/14 Ba-133 78.23 +/- 3.93 87.90 74.00 - 96.70 Pass ERW-1385 04/07/14 Co-60 62.75 +/- 3.53 64.20 57.80 - 73.10 Pass ERW-1385 04/07/14 Cs-134 44.97 +/- 3.99 44.30 35.50 - 48.70 Pass ERW-1385 04/07/14 Cs-137 88.54 +/- 4.93 89.10 80.20 - 101.00 Pass ERW-1385 04/07/14 Zn-65 249.1 +/- 10.44 235.0 212.0 - 275.0 Pass ERW-1388 04/07/14 Gr. Alpha 56.70 +/- 2.47 61.00 31.90 - 75.80 Pass ERW-1388 04/07/14 Gr. Beta 32.10 +/- 1.20 33.00 21.40 - 40.70 Pass ERW-1391 04/07/14 1-131 25.52 +/- 1.12 25.70 21.30 - 30.30 Pass ERW-1394 04/07/14 Uranium 10.76 +/- 0.74 10.20 7.95 - 11.80 Pass ERW-1397 04/07/14 H-3 8982 +/- 279 8770 7610 - 9650 Pass ERW-5382 10/06/14 Sr-89 29.40 +/- 5.32 31.40 22.80 - 38.10 Pass ERW-5382 10/06/14 Sr-90 19.19 +/- 1.85 21.80 15.60 - 25.70 Pass ERW-5385 10/06/14 Ba-133 43.54 +/- 4.54 49.10 40.30 - 54.50 Pass ERW-5385 10/06/14 Cs-134 81.95 +/- 7.49 89.80 73.70 - 98.80 Pass ERW-5385 10/06/14 Cs-137 95.76 +/- 5.50 98.80 88.90 - 111.00 Pass ERW-5385 10/06/14 Co-60 90.25 +/- 2.77 92.10 82.90 - 104.00 Pass ERW-5385 10/06/14 Zn-65 327.4 +/- 23.3 310.00 279.0 - 362.0 Pass ERW-5388 10/06/14 Gr. Alpha 30.88 +/- 8.05 37.60 19.40 - 46.10 Pass ERW-5388 10/06/14 G. Beta 20.47 +/- 4.75 27.40 17.30 - 35.30 Pass ERW-5392 10/06/14 1-131 19.58 +/- 2.35 20.30 16.80 - 24.40 Pass ERW-5394 10/06/14 Uranium 5.51 +/- 0.37 5.80 4.34 - 6.96 Pass ERW-5397 10/06/14 H-3 6876 +/- 383 6880 5940 - 7570 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
E-7
TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
ENVIRONMENTAL, INC., 2014 (Page 1 of 2)
Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-1 140 02/01/14 Gr. Alpha 0.77 +/- 0.06 0.85 0.26 - 1.44 Pass MAW-1 140 02/01/14 Gr. Beta 4.31 +/- 0.08 4.19 2.10 - 6.29 Pass MAW-i 184 02/01/14 Fe-55 0.40 +/- 3.20 0.00 -0.01 - 2.00 Pass MAW-1184 02/01/14 H-3 345.10 +/- 10.60 321.00 225.00 - 417.00 Pass MAW-1184 02/01/14 Ni-63 32.40 +/- 3.20 34.00 23.80 - 44.20 Pass MAW-i 184 02/01/14 Pu-238 1.28 +/- 0.12 0.83 0.58 - 1.08 Fail (1)
MAW-i 184 02/01/14 Pu-239/240 0.91 +/- 0.10 0.68 0.47 - 0.88 Fail (1)
MAW-i 184 02/01/14 Sr-90 7.00 +/- 0.70 8.51 5.96 - 11.06 Pass MAW-1184 02/01/14 U-233/234 0.20 +/- 0.07 0.23 0.16 - 0.29 Pass MAW-1184 02/01/14 U-238 1.25 +/- 0.18 1.45 1.02 - 1.89 Pass MAW-i 184 02/01/14 Co-57 27.86 +/- 0.38 27.50 19.30 - 35.80 Pass MAW-1184 02/01/14 Co-60 15.99 +/- 0.27 16.00 11.20 - 20.80 Pass MAW-i 184 02/01/14 Cs-1 34 21.85 +/- 0.54 23.10 16.20 - 30.00 Pass MAW-i 184 02/01/14 Cs-137 28.74 +/- 0.49 28.90 20.20 - 37.60 Pass MAW-i 184 02/01114 K-40 1.80 +/- 2.00 0.00 0.00 - 10.00 Pass MAW-1184 02/01/14 Mn-54 14.06 +/- 0.40 13.90 9.70 - 18.10 Pass MAW-1 184 02/01/14 Zn-65 0.00 +/- 0.19 0.00 -0.01 - 0.00 Pass MAVE-1 148 02/01/14 Co-57 11.63 +/- 0.19 10.10 7.10 - 13.10 Pass MAVE-1 148 02/01/14 Co-60 7.28 +/- 0.18 6.93 4.85 - 9.01 Pass MAVE-1 148 02/01/14 Cs-1 34 6.29 +/- 0.29 6.04 4.23 - 7.85 Pass MAVE-1 148 02/01/14 Cs-1 37 5.18 +/- 0.20 4.74 3.32 - 6.16 Pass MAVE-1 148 02/01/14 Mn-54 9.22 +/- 0.26 8.62 6.03 - 11.21 Pass MAVE-1 148 02/01/14 Zn-65 8.59 +/- 0.40 7.86 5.50 - 10.22 Pass MAAP-1 151 02/01/14 Co-57 1.60 +/- 0.05 0.00 NA Fail (2)
MAAP-1 151 02/01/14 Co-60 1.38 +/- 0.08 1.39 0.97 - 1.81 Pass MAAP-1 151 02/01/14 Cs-1 34 1.75 +/- 0.11 1.91 1.34 - 2.48 Pass MAAP-1151 02/01/14 Cs-1 37 1.81 +/- 0.10 1.76 1.23 - 2.29 Pass MAAP-1151 02/01/14 Mn-54 0.01 +/- 0.03 0.00 NA Pass MAAP- 1151 02/01/14 Zn-65 -0.24 +/- 0.09 0.00 -0.50 - 1.00 Pass MAAP-1151 02/01/14 Sr-90 1.11 +/- 0.14 1.18 0.83 - 1.53 Pass MAAP-1 154 02/01/14 Gr. Alpha 0.56 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-1 154 02/01/14 Gr. Beta 0.98 +/- 0.06 0.77 0.39 - 1.16 Pass MASO-1 146 02/01/14 Ni-63 4.80 +/- 15.30 0.00 NA Pass MASO-1 146 02/01/14 Co-57 1064.50 +/- 3.60 966.00 676.00 - 1256.00 Pass MASO-1 146 02/01/14 Co-60 1.70 +/- 0.50 1.22 (3) Pass MASO-1 146 02/01/14 Cs-134 6.10 +/- 1.80 0.00 NA Fail (4)
MASO-1 146 02/01/14 Cs-137 1364.30 +/- 5.30 1238.00 867.00 - 1609.00 Pass MASO-1 146 02/01/14 K-40 728.90 +/- 15.90 622.00 435.00 - 809.00 Pass MASO-1 146 02/01/14 Mn-54 1588.00 +/- 6.00 1430.00 1001.00 - 1859.00 Pass MASO-1 146 02/01/14 Zn-65 763.50 +/- 6.80 695.00 487.00 - 904.00 Pass MASO-1 146 02/01/14 Sr-90 1.23 +/- 1.37 0.00 NA Pass E-8
TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
ENVIRONMENTAL, INC., 2014 (Page 2 of 2)
Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MASO-4439 08/01/14 Ni-63 771.62 +/- 23.29 980.00 686.00 - 1274.00 Pass MASO-4439 08/01/14 Sr-90 778.34 +/- 17.82 858.00 601.00 - 1115.00 Pass MASO-4439 08/01/14 Cs-1 34 520.60 +/- 7.09 622.00 435.00 - 809.00 Pass MASO-4439 08/01/14 Co-57 1135.00 +/- 7.40 1116.00 781.00 - 1451.00 Pass MASO-4439 08/01/14 Co-60 768.20 +/- 7.70 779.00 545.00 - 1013.00 Pass MASO-4439 08/01/14 Mn-54 1050.70 +/- 12.60 1009.00 706.00 - 1312.00 Pass MASO-4439 08/01/14 Zn-65 407.89 +/- 15.03 541.00 379.00 - 703.00 Pass MAW-4431 08/01/14 Am-241 0.79 +/- 0.08 0.88 0.62 - 1.14 Pass MAW-4431 08/01/14 Cs-1 37 18.62 +/- 0.54 18.40 12.90 - 23.90 Pass MAW-4431 08/01/14 Co-57 24.85 +/- 0.42 24.70 17.30 - 32.10 Pass MAW-4431 08/01/14 Co-60 12.27 +/- 0.38 12.40 8.70 - 16.10 Pass MAW-4431 08/01/14 H-3 207.20 +/- 10.60 208.00 146.00 - 270.00 Pass MAW-4431 08/01/14 Fe-55 55.10 +/- 14.80 31.50 22.10 - 41.00 Fail (5)
MAW-4431 08/01/14 Mn-54 14.36 +/- 0.53 14.00 9.80 - 18.20 Pass MAW-4431 08/01/14 Zn-65 11.46 +/- 0.78 10.90 7.60 - 14.20 Pass MAW-4493 08/01/14 Gr. Alpha 0.93 +/- 0.07 1.40 0.42 - 2.38 Pass MAW-4493 08/01/14 Gr. Beta 6.31 +/- 1.35 6.50 3.25 - 9.75 Pass MAAP-4433 08/01/14 Sr-90 0.74 +/- 0.10 0.70 0.49 - 0.91 Pass MAAP-4444 08/01/14 Sr-89 7.82 +/- 0.52 9.40 6.60 - 12.20 Pass MAAP-4444 08/01/14 Sr-90 0.76 +/- 0.10 0.76 0.53 - 0.99 Pass MAVE-4436 08/01/14 Cs-1 34 7.49 +/- 0.18 7.38 5.17 - 9.59 Pass MAVE-4436 08/01/14 Co-57 11.20 +/- 0.19 9.20 6.40 - 12.00 Pass MAVE-4436 08/01/14 Co-60 6.84 +/- 0.17 6.11 4.28 - 7.94 Pass MAVE-4436 08/01/14 Mn-54 8.11 +/- 0.26 7.11 4.97 - 9.23 Pass MAVE-4436 08/01/14 Zn-65 7.76 +/- 0.43 6.42 4.49 - 8.35 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).
c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
(1) The high bias on the plutonium crosscheck samples was traced to contamination from a newly purchased standard.
The results of reanalysis with replacement tracer purchased from NIST:
MAW-1184 Pu-238 0.68 +/- 0.10 Bq / L MAW-1 184 Pu-239/240 0.66 +/- 0.10 Bq / L (2) Interference from Eu-1 52 resulted in misidentification of Co-57.
(3) Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.
(4) False positive test. Long sample counting time lead to interference from naturally occuring Bi-214 in sample matrix with a close spectral energy.
(5) Result of reanalysis Fe-55 32.63 +/- 16.30 Bq/L E-9
Intentionally left blank APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)
Intentionally left blank Docket No: 50-289 50-320 THREE MILE ISLAND NUCLEAR STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report (ARGPPR) 1 January Through 31 December 2014 Prepared By Teledyne Brown Engineering Environmental Services om-r ExelonGeneration, Three Mile Island Nuclear Station Middletown, PA 17057 April 2015
Intentionally left blank Table Of Contents I. Sum m ary and Conclusions .............................................................................................. 1
- 11. Introduction .. 9 - - ** 3 II.Inroucio .................... ...... ***............. ....... 3 A. O bjectives of the RGPP ................................................................................. 3 B. Im plem entation of the Objectives .................................................................... 4 C. Program Description ..................................................................................... 4 D. Characteristics of Tritium (H-3) ...................................................................... 5 Ill. Program Description ................................................................................................. 6 A. Sam ple Analysis ............................................................................................. 6 B. Data Interpretation .......................................................................................... 7 IV. Results and Discussion ............................................................................................ 8 A. Groundwater Results ...................................................................................... 8 B. Surface W ater Results ................................................................................... 9 C. Storm W ater Results .................................................................................... 10 D. Precipitation W ater Results ........................................................................... 11 E. Leaks, Spills, and Releases .......................................................................... 11 F. Actions Taken ............................................................................................... 12
Appendices Appendix A Location Designation I Tables I Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Three Mile Island Nuclear Station, 2014 Figures Figure A-1 Sampling Locations at the Three Mile Island Nuclear Station, 2014 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
Table B-1.2 Concentrations of Gamma E'mitters in Groundwater Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2014.
Table B-11.1 Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table B-111.1 Concentrations of Tritium in Storm Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
Table B-Ill.2 Concentrations of Gamma Emitters in Storm Water Samples Collected in the Vicinity of Three Mile Island Nuclear Station, 2014.
Table B-IV.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
ii
Appendix C Data Tables Tables Table C-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, three Mile Island Nuclear Station, 2014.
Table C-1.2 Concentrations of Gamma Emitters in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
Table C-1.3 Concentrations of Hard-To-Detects in Groundwater Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Generating Station, 2014.
Table C-I1.1 Concentrations of Tritium in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
Table C-11.2 Concentrations of Gamma Emitters in Surface Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
Table C-I11.1 Concentrations of Tritium in Precipitation Water Split Samples Collected as Part of the Radiological Groundwater Protection Program, Three Mile Island Nuclear Station, 2014.
iii
I. Summary and Conclusions In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Three Mile Island Nuclear Station. At Three Mile Island Nuclear, 31 new permarent groundwater monitoring wells were installed in 2006. The results for all TMI wells are included in this report. This report covers groundwater, surface water, storm water and precipitation samples collected from the environment, both on and off station property in 2014. During that time period 694 analyses were performed on 258 samples from 68 locations.
In assessing all the data gathered for this report, it was concluded that the operation of Three Mile Island Nuclear Station had no adverse radiological impact on the environment.
Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater, surface water, storm water and precipitation samples. In the case of tritium, Exelon specified that its laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.
Strontium-89 and strontium-90 were not detected at a concentration greater than their respective LLD of 10 and 1 picoCurie per liter (pCi/L) in the groundwater samples tested.
Tritium was not detected in any groundwater, surface water, storm water or precipitation water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 30 of 60 groundwater monitoring locations. The groundwater tritium concentrations ranged from 184 +/- 115 pCi/L to 17,700 + 1,810 pCi/L. Tritium that was detected in groundwater at the Station is believed to be the result of a potential leak, historical releases, the recapture of gaseous tritium releases via rainwater and/or background from external sources greater than 200 pCi/L. Tritium was detected in three of four precipitation water locations. The concentration ranged from 246
+/- 83 to 2,470 + 299 pCi/L. Tritium was not detected at any surface water location. Tritium was detected in two storm water samples. The concentrations ranged from 289 +/- 118 to 312 +/- 114 pCi/L.
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2014. Gross Alpha (dissolved) was not detected at any of the groundwater locations. Gross Alpha (suspended) was detected at four of 39 groundwater locations. The concentrations ranged from 3.2 to 4.3 pCi/L. Gross Beta (dissolved) was detected at 38 of 39 groundwater locations. The concentrations ranged from 1.2 to 13.7 pCi/L. Gross Beta (suspended) was detected at six of 39 groundwater locations. The concentrations ranged from 1.9 and 8.2 pCi/L.
Hard-To-Detect analyses were performed on a select group of groundwater locations. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.
II. Introduction The Three Mile Island Nuclear Station (TMINS) established a revised and more comprehensive groundwater monitoring program in 2006 as part of an Exelon Nuclear fleetwide assessment.
Conestoga Rovers & Associates (CRA) performed the initial assessment. CRA prepared a Hydrogeologic Investigation Report (HIR) for Exelon to determine whether groundwater at and near TMINS has been adversely impacted by any releases of radionuclides. The CRA report documents the results of the May 2006 Hydrogeologic Investigation Work Plan. CRA assessed groundwater quality at the Station and identified locations designated as Areas for Further Evaluation. The results and conclusions of this Phase 1 study were made available to state and federal regulators, as well as the public on an Exelon web site for station specific reports.
As a result of the Phase 1 study, the Radiological Groundwater Protection Program (RGPP) was revised to a long term monitoring program. This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on well water, surface water, precipitation water and storm water samples collected in 2014. TMINS groundwater movement is into the Susquehanna River which surrounds the station on all sides.
This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2014.
A. Objective of the RGPP The long-term objectives of the Radiological Groundwater Protection Program (RGPP) are as follows:
- 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
- 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.
- 3. Perform routine water sampling and radiological analysis of water from selected locations.
- 4. Notify stakeholders in a timely manner for new leaks, spills, or other detections with potential radiological significance.
- 5. Regularly assess analytical results to identify adverse trends.
- 6. Take necessary corrective actions to protect groundwater resources.
B. Implementation of the Objectives The objectives identified have been implemented at Three Mile Island Nuclear Station as discussed below:
- 1. Three Mile Island Nuclear Station continues to sample and monitor the groundwater at the station in accordance with station procedures.
Sample frequencies and locations are adjusted based on monitoring results and investigations.
- 2. The Three Mile Island Nuclear Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
- 3. Three Mile Island Nuclear Station will continue to perform routine sampling and radiological analysis of water from selected locations.
- 4. Three Mile Island Nuclear Station has implemented procedures to identify and report leaks, spills, or other detections with potential radiological significance in a timely manner.
- 5. Three Mile Island Nuclear Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
C. Program Description
- 1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1 and A-2, Appendix A.
Groundwater, Surface Water, Storm Water, and Precipitation Samples of water are collected, managed, transported and analyzed in accordance with approved procedures. Groundwater, surface water, storm water and precipitation are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures.
Contractor and/or station personnel are trained in the collection, preservation management and shipment of samples, as well as in documentation of sampling events. For split samples, collectors will periodically collect samples that are sent to Midwest Labs to confirm that TBE is producing comparable data. Analytical laboratories are subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits.
Station personnel review and evaluate all analytical data deliverables as data are received.
Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.
D. Characteristics of Tritium (H-3)
Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.
Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. This "cosmogenic" tritium combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.
A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
The chemical properties of tritium are essentially those of ordinary hydrogen. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body.
Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, all tritium is essentially cleared.
Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.
Tritium has a radiological half-life of approximately 12.3 years. It decays spontaneously to helium-3 (He-3). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides, because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.
Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the Three Mile Island Nuclear Station RGPP in 2014.
In order to achieve the stated objectives, the current program includes the following analyses:
- 1. Concentrations of gamma emitters in groundwater, surface water and storm water.
- 2. Concentrations of strontium in groundwater.
- 3. Concentrations of tritium in groundwater, surface water, precipitation water and storm water.
- 4. Concentrations of Am-241 in groundwater.
- 5. Concentrations of Cm-242 and Cm-243/244 in groundwater.
- 6. Concentrations of Pu-238 and PU-239/240 in groundwater.
- 8. Concentrations of Fe-55 in groundwater.
- 9. Concentrations of Ni-63 in groundwater.
- 10. Concentrations of Gross Alpha and Gross Beta (Dissolved and Suspended) in groundwater.
B. Data Interpretation
- 1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.
- 2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.
Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error).
Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.
Gamma spectroscopy results for each type of sample were grouped as follows:
For groundwater, surface water, and storm water 13 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140 and La-140 were reported.
The radio-analytical laboratory is counting tritium results to an LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 - 240 pCi/L or 140 +/- 100 pCi/L.
Clearly, these sample results cannot be distinguished as different from background at this concentration.
IV. Results and Discussion A. Groundwater Results Samples were collected from on and off-site wells in accordance with the station radiological groundwater protection program.
Analytical results and anomalies are discussed below.
Tritium Samples from 60 locations were analyzed for tritium activity. Tritium values ranged from the detection limit to 17,700 pCi/L (Table B-I.1, Appendix B).
Tritium Split Samples Tritium values ranged from 186 to 8,916 pCi/L (Table C-1.1, Appendix C).
Strontium Strontium-89 and strontium-90 were not detected above their required detection limit of 10 and 1.0 pCi/L, respectively (Table B-1.1, Appendix B).
Strontium Split Samples Strontium-89 and Strontium-90 were not detected above the required detection limit (Table C-1.1, Appendix C).
Gross Alpha and Gross Beta (dissolved and suspended)
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2014. Gross Alpha (dissolved) was not detected at any of the 39 groundwater locations. Gross Alpha (suspended) was detected at four of 39 groundwater locations. The concentrations ranged from 3.2 to 4.3 pCi/L. Gross Beta (dissolved) was detected at 38 of 39 groundwater locations. The concentrations ranged from 1.2 to 13.7 pCi/L. Gross Beta (suspended) was detected at six of 39 groundwater locations. The concentrations were 1.9 and 8.2 pCi/L (Table B-1.1, Appendix B).
Gross Alpha and Gross Beta Split Samples Two split samples were analyzed for Gross Alpha and Gross Beta in 2014. Gross Alpha was not detected at either groundwater location. Gross beta was detected in both samples analyzed. The concentrations ranged from 2.7 to 3.5 pCi/L (Table C-1.1, Appendix C).
Gamma Emitters Potassium-40 was detected in four of 78 samples with concentrations ranging from 53 pCi/L to 119 pCi/L. No other gamma-emitting nuclides were detected (Table B-1.2, Appendix B).
Gamma Emitters Split Samples Five locations were analyzed for gamma-emitting nuclides in 2014.
No gamma-emitting nuclides were detected in any split samples (Table C-1.2, Appendix C).
Hard-To-Detect Hard-To-Detect analyses were performed on a select group of groundwater locations. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235 and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs (Table B-1.3, Appendix B).
Hard-To-Detect Split Samples Hard to detects were not analyzed on any split samples in 2014 (Table C-1.3, Appendix C).
B. Surface Water Results Samples were collected from surface water locations in accordance with the station radiological groundwater protection program.
Analytical results and anomalies are discussed below.
Tritium Three locations were analyzed for tritium in 2014. Tritium was not detected above the required detection limit of 200 pCi/L in any of the 13 samples analyzed (Table B-11.1, Appendix B).
Tritium Split Samples One location was analyzed for tritium in 2014. Tritium was not detected above the required detection limit (Table C-I1.1, Appendix C).
Strontium Surface water samples were not analyzed for Sr-90 in 2014 (Table B-II.1, Appendix B).
Gamma Emitters Three locations were analyzed for gamma-emitting nuclides in 2014. None of the four samples detected gamma-emitting nuclides (Table B-1I.2, Appendix B).
Gamma Emitters Split Samples One location was analyzed for gamma-emitting nuclides in 2014.
No gamma emitting nuclides were detected (Table C-11.2, Appendix C).
C. Storm Water Results Samples were collected from storm water locations in accordance with the station radiological groundwater protection program.
Analytical results and anomalies are discussed below.
Tritium One location was analyzed for tritium. Tritium was detected in two of samples above the required detection limit of 200 pCi/L. The concentration ranged from 289 to 312 pCi/L (Table B-Ill.1, Appendix B).
Gamma Emitters Samples from one location were analyzed for gamma-emitting nuclides. No gamma emitting nuclides were detected (Table B-Ill.2, Appendix B).
D. Precipitation Water Results Samples were collected at four locations. The following analyses were performed:
Tritium Samples from five locations were analyzed for tritium activity. Tritium activity was detected at three of four locations. The concentrations ranged from 246 to 2,470 pCi/L (Table B-IV.1, Appendix B).
Tritium Split Samples Samples from one location were analyzed for tritium activity. Tritium activity was detected in three of four samples. The concentrations ranged from 246 to 2,350 pCi/L (Table C-111.1, Appendix C).
Gamma Emitters Precipitation water was not analyzed for Gamma Emitters in 2014.
Gamma Emitters Split Samples No gamma-emitting nuclides were analyzed in 2014.
E. Leaks, Spills, and Releases A potential leak was identified at TMI in 2012 due to elevated MS-22 tritium concentration readings. TMI continues to monitor MS-22 and surrounding wells, in addition to tritium plumes from previous years, and reports the activity and dose to the public in the ARERR. The elevated MS-22 well tritium concentrations were voluntarily reported under the reporting requirements for the NEI Groundwater Protection Initiative (GPI) as implemented in Exelon's Reportability procedure LS-AA-1 120, RAD 1.34 ( IR 1385497/1515261)
As reported previously a number of potential sources were mitigated in 2013. The Borated Water Storage Tank (BWST) tunnel sump was cleaned and repaired. An active input to the BWST tunnel sump (packing leak-off of a BWST isolation valve) was corrected. A tank leak on CST B and a leaking buried pipe flange were repaired, and BS-T-1 & 2 and ancillary piping were drained and emptied.
In June 2014 an inspection of the BWST external connections revealed that a 24 inch flange was found coated in boron deposits indicating leakage. The flange was cleaned and the boron deposits removed. The repair of the flange is scheduled during TMI's refueling outage in the Fall of 2015. In December 2014, a follow-up inspection showed additional boron deposits. In January 2015, an enclosure with a catch containment was installed to help in preventing the small amounts of leakage from migrating to the environment.
F. Actions Taken
- 1. Compensatory Actions In 2013, TMI installed eight new wells to help isolate and investigate the area of the leak. TMI has an extensive groundwater monitoring program with over 50 monitoring wells. No monitoring wells outside the investigation area have seen elevated tritium concentrations. TMI continues to monitor the BWST area wells closely. The leakage has been mitigated by preventing rain/snow from entering the area of concern and by placement of a catch containment for any moisture that might accumulate. The containment is inspected regularly, and the permanent flange repair is scheduled during TMI's next refueling outage in Fall 2015.
Intentionally left blank APPENDIX A LOCATION DESIGNATION & DISTANCE
Intentionally left blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2014 Site Site Type
- 3 Monitoring Well 48N Monitoring Well 48S Production Potable Well E1-2 Monitoring Well, Offsite EDCB Storm Water GP-12 Monitoring Well GP-6 Monitoring Well GP-8 Monitoring Well GP-9 Monitoring Well MS-1 Monitoring Well MS-19 Monitoring Well MS-2 Monitoring Well MS-20 Monitoring Well MS-21 Monitoring Well MS-22 Monitoring Well MS-3 Monitoring Well MS-4 Monitoring Well MS-5 Monitoring Well MS-6 Monitoring Well MS-7 Monitoring Well MS-8 Monitoring Well MW-1 Monitoring Well MW-2 Monitoring Well MW-3 Monitoring Well MW-4 Monitoring Well N2-1 Monitoring Well, Offsite NW-A Production Well NW-B Production Well NW-C Production Well NW-CW Clearwell OS-13B Monitoring Well OS-14 Monitoring Well OS-16 Monitoring Well OS-17 Monitoring Well OS-18 Monitoring Well OSF Production Potable Well RW-1 Monitoring Well RW-2 Monitoring Well SW-E-1 Surface Water SW-E-2 Surface Water SW-E-3 Surface Water MW-TMI-9S* Monitoring Well MW-TMI-1 0D Monitoring Well MW-TMI-101 Monitoring Well MW-TMI-10S Monitoring Well MW-TM- 11 S* Monitoring Well MW-TMI-12S Monitoring Well MW-TMI-131 Monitoring Well MW-TMI-13S Monitoring Well MW-TMI-14D Monitoring Well MW-TMI-141 Monitoring Well MW-TMI-14S Monitoring Well MW-TMI-16D Monitoring Well MW-TMI-161 Monitoring Well MW-TMI-17D Monitoring Well MW-TMI-171 Monitoring Well MW-TMI-18D Monitoring Well MW-TMI-19D Monitoring Well MW-TM -191 Monitoring Well MW-TMI-1D Monitoring Well MW-TMI-20D** Monitoring Well A-I
TABLE A-I: Radiological Groundwater Protection Program - Sampling Locations and Distance, Three Mile Island Nuclear Station, 2014 Site Site Type MW-TMI-201** Monitoring Well MW-TMI-21 D** Monitoring Well MW-TMI-21 I** Monitoring Well MW-TMI-21S** Monitoring Well MW-TMI-22D** Monitoring Well MW-TMI-221** Monitoring Well MW-TMI-22S** Monitoring Well MW-TMI-2D Monitoring Well MW-TMI-31 Monitoring Well MW-TMI-41 Monitoring Well MW-TMI-4S Monitoring Well MW-TMI-5D Monitoring Well MW-TMI-6D Monitoring Well MW-TMI-61 Monitoring Well MW-TMI-7S Monitoring Well MW-TMI-8S Monitoring Well MW-TMI-91 Monitoring Well MW-TMI-9S Monitoring Well TRAINING CENTER Offsite Monitoring Well TM-PR-ESE Precipitation Water TM-PR-MS-1 Precipitation Water TM-PR-MS-2 Precipitation Water TM-PR-MS-20 Precipitation Water TM-PR-MS-22 Precipitation Water TM-PR-MS-4 Precipitation Water TM-PR-NW-B Precipitation Water
- NO WATER PRESENT TO SAMPLE
- NEW WELLS INSTALLED 2014 A-2
Figure A - 1 Sampling Locations at the Three Mile Island Nuclear Station, 2014 A-3
I Intentionally left blank
APPENDIX B DATA TABLES
Intentionally left blank TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA
£1 COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B3 (Sus) 3 U1/ZU/14 < 16V 3 04/23/14 < 167 < 4.7 < 0.6 < 0.5 < 0.9 1.6 +/- 0.8 < 1.6 3 07/10/14 200 +/- 114 3 10/28/14 195 +/- 114 48S 10/28/14 196 +/- 114 48S 01/20/14 < 181 48S 04/24/14 Original 192 +/- 116 < 4.8 < 0.7 < 1.3 < 0.7 3.9 +/- 1.1 < 1.4 48S 04/24/14 Recount 196 +/- 122 48S 07/10/14
- 184 48S 07/10/14 < 184 MS-i 10/28/14 < 166 MS-1 01/21/14 < 184 MS-1 04/22/14 < 159 < 4.4 < 0.6 < 5.1 < 0.6 6.7 +/- 1.6 < 1.3 MS-1 07/09/14 < 183 MS-19 10/28/14 < 173 MS-19 01/21/14 < 181 MS-19 04/22/14 < 169 < 5.2 < 0.7 < 0.9 3.9 +/- 1.5 3.4 +/- 0.9 6.2 +/- 1.5 MS-19 07/09/14 < 183 MS-2 10/28/14 < 174 MS-2 01/21/14 312 +/- 116 MS-2 04/23/14 Original 718 +/- 141
- 5.8 < 0.8 < 0.8 < 0.9 4.0 + 1.1 < 1.6 MS-2 04/23/14 Recount 808 +/- 163 MS-2 04/23/14 Original 798 +/- 153 < 6.9 < 0.5 < 0.9 < 0.7 5.2 +/- 1.1 < 1.4 MS-2 04/23/14 Recount 659 +/- 150 MS-2 07/10/14 513 +/- 129 MS-20 10/29/14 522 +/- 125 MS-20 01/20/14 491 +/- 141 MS-20 01/20/14 418 +/- 138 MS-20 04/21/14 630 +/- 133 < 4.9 < 0.7 < 1.2 < 0.6 6.4 +/- 1.2 < 1.3 MS-20 07/09/14 630 +/- 137 MS-20 10/27/14. Original 2650 +/- 319 MS-20 10/27/14 Recount 2670 +/- 312 MS-20 10/27/14 Reanaly, sis 2500 +/- 296 MS-21 12/16/14 298 +/- 120 MS-21 01/20/14 < 163 MS-21 04/23/14 240 +/- 115 < 4.1 < 0.8 < 0.4 < 0.9 1.7 + 0.7 < 1.6 MS-21 07/09/14 < 165 MS-22 10/27/14 < 168 MS-22 01/20/14 2460 +/- 292 MS-22 02/10/14 1930 +/- 244 MS-22 03/07/14 1990 +/- 249 MS-22 04/23/14 4790 +/- 524 S
MS-22 04/23/14 < 6.9 < 0.6 < 0.8 < 0.7 7.7 + 1.1 < 1.4 MS-22 05/19/14 3180 +/- 364 < 4.9 < 0.5 < 2.7 < 0.6 9.2 +/- 1.9 < 2.8 MS-22 06/17/14 Original 5380 +/- 578 MS-22 06/17/14 Recount 5040 +/- 553 S
MS-22 06/17/14 Reanalyssis 5140 +/- 558 MS-22 07/09/14 9850 +/- 1030 MS-22 10/27/14 Original 12900 +/- 1330 MS-22 10/27/14 Recount 14300 +/- 1470 S
MS-22 10/27/14 Reanalyssis 13400 +/- 1380 MS-3 12/16/14 2700 +/- 320 MS-3 01/21/14 < 184 04/23/14 Original 437 +/- 129 < 8.5 < 0.6 < 0.8 < 0.9 5.5 +/- 1.1 < 1.6 MS-3 04/23/14 Recount 360 +/- 140 MS-3 07/10/14 376 :1 124 MS-3 10/29/14 251 +/-1 118 MS-4 04/23/14 251 + 117 B-1
TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)
MS-5 01/21/14 < 183 MS-5 04/23/14
- 167 < 3.3 < 0.7 < 0.6 < 0.9 5.0 +/- 1.1 < 1.6 MS-5 07/10/14 Original 336 +/- 133 MS-5 07/10/14 Recount 190 +/- 107 MS-5 07/10/14 Reanalysis 244 +/- 111 MS-5 10/29/14 < 167 MS-7 01/21/14 < 190 MS-7 04/22/14 < 160 < 3.1 < 0.6 <0.9 4.0 +/- 1.7 3.4 +/- 1.4 5.2 +/- 1.9 MS-7 07109114 < 184 MS-7 07109/14 < 192 MS-7 10/29/14 < 175 MS-8 01/21/14 < 183 MS-8 01/21/14 < 190 MS-8 04/23/14 276 +/- 120 < 3.8 < 0.5 <0.7 < 0.9 4.3+/- 0.9 < 1.6 MS-8 07/10/14 281 +/- 117 MS-8 10/29/14 < 171 MS-8 10/29/14 < 172 MW-1 04/24/14 < 191 MW-2 04/24/14 < 191 MW-TMI -10D 01120114 197 +/- 111 MW-TMI-10D 04/22/14 218 +/- 113 MW-TMI-10D 04/22/14 226 +/- 114 MW-TMI-10D 10128/14 < 171 MW-TMI-101 01/20/14 903 +/- 146 MW-TMI-101 04/22/14 741 +/- 138
- 4.8 < 0.6 <1.2 < 0.6 5.2 +/-1.1 < 1.3 MW-TMI-101 07/09/14 733 +/- 155 MW-TMI-1 01 10/28/14 705 +/- 138 MW-TMI-10S 01120/14 741 +/- 140 MW-TMI-10S 01/20/14 643 +/- 148 MW-TMI-10S 04/22/14 741 +/- 142
- 4.1 < 0.7 <0.7
- 0.9 4.5 +/-1.1 < 1.6 MW-TMI-10S 07/09/14 1710 +/- 225 MW-TMI-10S 07/09/14 1630 +/- 216 MW-TM I-10S 10/28/14 1570 +/- 214 MW-TMI-12S 01/21/14 < 189 MW-TMI-12S 04/23/14 < 170 < 3.5 < 0.5 <0.9
- 0.9 9.4 +/-1.4 < 1.6 MW-TMI-1 2S 07/10/14 < 161 MW-TMI-12S 10/28/14 < 169 MW-TMI-131 01/20/14 348 +/- 135 MW-TMI-131 04/22/14 382 +/- 121 MW-TMI-1 31 07/09/14 212 +/- 123 MW-TMI-131 10/28/14
- 170 MW-TMI-131 10/28/14 < 171 MW-TMI-13S 01/20/14 223 +/- 128 MW-TMI-13S 04/22/14 < 150 < 5.5 < 0.7 <0.8 < 0.6 3.4 +/-0.8 < 1.3 MW-TMI-14D 01/22114 293 +/- 128 MW-TMI-14D 04/22/14 226 +/- 111 MW-TMI-14D 07/09/14 274 +/- 131 MW-TMI-14D 10/28/14 184 +/- 115 MW-TMI-141 01/21/14
- 180 MW-TMI-141 01/21/14
- 190 MW-TMI-141 04/22/14 207 +/- 113 MW-TMI-14S 01/21/14
- 179 MW-TMI-14S 04/22/14
- 161 < 5.4 < 0.8 <0.7 < 0.6 1.2 +/-0.7 1.9 +/- 1.0 MW-TMI-16D 01/21114 905 +/- 165 MW-TMI-16D 04/22114 620 +/- 121 MW-TMI-160 10/29/14 634 +/- 136 MW-TMI-161 01/21/14
- 180 MW-TMI-161 04/22/14 Original 224 +/- 108 B-2
TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)
MW-TMI-161 04/22/14 Recount 211 +/- 124 MW-TMI-171 04/24/14 < 179 MW-TMI-18D 04/24/14 273 +/- 128 MW-TMI-18D 04/24/14 331 +/- 133 MW-TMI-191 04/22/14 < 167 MW-TMI-1 D 04/24/14 190 +/- 114 MW-TMI-20D 01/20/14 287 +/- 118 MW-TMI-20D 04/22/14 303 +/- 119 < 5.3 < 0.6 < 2.3 < 0.6 5.9 +/- 1.3 < 1.3 MW-TMI-201 01/20/14 407 +/- 124 MW-TMI-201 04/22/14 611 +/- 124 < 6.0 < 0.7 < 7.6 < 1.2 34.0 +/- 3.4 < 2.3 MW-TMI-21D 01/20/14 3120 +/- 359 MW-TMI-21 D 02/10/14 2760 +/- 323 MW-TMI-21 D 03/07/14 2810 +/- 331 MW-TMI-21 D 04/21/14 3450 +/- 395 MW-TMI-21 D 05/19/14 4010 +/- 447 < 5.1 < 0.5 < 0.9 < 0.6 1.5 +/- 0.9 < 2.8 MW-TMI-21 D 06/17/14 3740 +/- 412 MW-TMI-21 D 07/09/14 3660 +/- 403 MW-TMI-21 D 10/27/14 3960 +/- 440 MW-TMI-21 D 12/16/14 3480 +/- 397 MW-TMI-21 I 01/20/14 Original 3480 +/- 396 MW-TMI-21 I 01/20/14 Recount 3930 +/- 439 MW-TMI-211 02/10/14 2980 +/- 344 MW-TMI-21 I 03/07/14 2090 +/- 259 MW-TMI-21 I 04/21/14 Original 5250 +/- 574 MW-TMI-21 I 04/21/14 Recount 5130 +/- 563 S
MW-TMI-21 I 04/21/14 Reanalys is 4630 +/- 510 MW-TMI-21 I 05/19/14 5660 +/- 607 < 3.8 < 0.5 < 2.5 < 1.1 4.1 +/- 1.4 < 2.5 MW-TMI-21 I 06/17/14 3250 +/- 368 MW-TMI-21 I 07/09/14 3510 +/- 389 MW-TMI-21 I 07/09/14 3130 +/- 350 MW-TMI-21 I 10/27/14 Original 10400 +/- 1080 MW-TMI-21 I 10/27/14 Recount 11300 +/- 1170 S
MW-TMI-21 I 10/27/14 Reanalys 'is 10500 +/- 1090 MW-TMI-21 I 12/16/14 5720 +/- 618 MW-TMI-21S 01/20/14 Original 454 +/- 130 MW-TMI-21S 01/20/14 Recount 546 +/- 147 MW-TMI-21S 02/10/14 359 +/- 115 MW-TMI-21S 03/07/14 502 +/- 136 MW-TMI-21S 04/21/14 594 +/- 155 MW-TMI-21 S 05/19/14 326 +/- 134 < 3.8 < 0.5 < 2.6 < 1.1 7.3 +/- 1.6 <2.5 MW-TMI-21 S 06/17/14 489 +/- 147 MW-TMI-21 S 07/09/14 502 +/- 132 MW-TMI-21 S 10/27/14 Original 4020 +/- 444 MW-TMI-21S 10/27/14 Recount 4900 +/- 534 MW-TMI-21S 10/27/14 Reanalys 'is 4650 +/- 511 MW-TMI-21S 12/16114 923 +/- 154 MW-TMI-22D 01/20/14 4690 +/- 515 MW-TMI-22D 02/10/14 4470 +/- 492 MW-TMI-22D 03/11/14 4430 +/- 490 MW-TMI-22D 04/21/14 5280 +/- 576 MW-TMI-22D 05/19/14 6630 +/- 705 < 4.0 < 0.4 < 2.4 < 1.1 2.3 +/- 1.3 < 2.5 MW-TMI-22D 06/17/14 5410 +/- 581 MW-TMI-22D 07/09/14 5680 +/- 602 MW-TMI-22D 10/27/14 4100 +/- 453 MW-TMI-22D 12/16/14 4130 +/- 461 MW-TMI-221 01/20/14 7890 +/- 834 MW-TMI-221 02/10/14 7490 +/- 789 MW-TMI-221 03/11/14 8430 +/- 887 B-3
TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)
MW-TMI-221 04/21/14 9230 +/- 968 MW-TMI-221 05/19/14 9430 +/- 985 < 5.4 < 0.5 < 1.6 < 1.1 4.4 +/- 1.1 < 2.5 MW-TMI-221 06/17/14 8400 +/- 878 MW-TMI-221 07/09/14 8590 +/- 893 MW-TMI-221 10/27/14 7540 +/- 794 MW-TMI-221 12/16/14 8890 +/- 932 MW-TMI-22S 01/20/14 3210 +/- 369 MW-TMI-22S 02/10/14 Original 5100 +/- 553 MW-TMI-22S 02/10/14 Recount 5860 +/- 631 MW-TMI-22S 03/11/14 Original 7740 +/- 819 MW-TMI-22S 03/11/14 Reanalys is 7030 +/- 755 MW-TMI-22S 04/21/14 8660 +/- 904 < 8.2 < 0.9 < 0.6 < 0.7 7.2 +/- 0.9 < 1.4 MW-TMI-22S 04/21/14 8380 +/- 883 MW-TMI-22S 05/19/14 7440 +/- 787 < 3.6 < 0.4 < 2.4 < 1.1 8.2 +/- 1.5 <2.5 MW-TMI-22S 06/17/14 Original 17200 +/- 1760 MW-TMI-22S 06/17/14 Recount 17200 +/- 1760 MW-TMI-22S 06/17/14 Reanalys is 17700 +/- 1810 MW-TMI-22S 07/09/14 12900 +/- 1320 MW-TMI-22S 10/27/14 12300 +/- 1270 MW-TMI-22S 12/16/14 3780 +/- 427 MW-TMI-2D 01/22/14 < 161 MW-TMI-2D 04/24/14 412 +/- 137 < 5.0 < 0.7 < 0.4 < 0.8 13.7 +/- 1.0 2.2 +/- 1.1 MW-TMI-2D 04/24/14 Original 319 +/- 134 MW-TMI-31 01/22/14 Recount 309 +/- 132 MW-TMI-31 04/24/14 290 +/- 126 < 6.2 < 0.9 < 1.8 4.3 +/- 1.4 6.0 +/- 1.3 8.2 +/- 1.6 MW-TMI-31 07/10/14 272 +/- 127 MW-TMI-31 10/29/14 193 +/- 113 MW-TMI-31 10/29/14 241 +/- 117 MW-TMI-41 04/22/14 < 165 MW-TMI-41 04/22/14 < 180 MW-TMI-4S 04/22/14 < 158 MW-TMI-6D 01/21/14
- 189 MW-TMI-6D 04/22/14 < 165 < 5.0 < 0.6 < 1.0 < 0.6 1.9 +/- 0.9 < 1.3 MW-TMI-61 01/21/14 < 187 MW-TMI-61 04/22/14 < 165 < 3.6 < 0.7 < 0.5 3.2 +/- 1.6 < 1.6 4.4 +/- 1.8 MW-TMI-7S 04/24/14 < 186 MW-TMI-8S 04/24/14 Original 281 +/- 131 MW-TMI-8S 04/24/14 Recount 224 +/- 129 MW-TMI-91 04/24/14 Original 248 +/- 130 MW-TMI-91 04/24/14 Recount 241 +/- 133 MW-TMI-9S 04/24/14 < 186 N2-1 04/25/14 < 175 NW-A 02/20/14 588 +/- 133 NW-A 04/25/14 723 +/- 145 < 6.5 < 0.7 < 0.8 < 0.7 2.2 +/- 0.9 < 1.4 NW-A 07/08/14 663 +/- 152 NW-A 10/28/14 850 +/- 149 NW-B 02/20/14 261 +/- 121 NW-B 04/25/14 337 +/- 136 < 5.9 < 0.5 < 0.7
- 0.7 2.6 +/- 0.9 < 1.4 NW-B 07/08/14 < 185 NW-B 10/28/14 185 +/- 109 NW-C 02/20/14 897 +/- 154 NW-C 04/25/14 1020 +/- 166 < 4.6 < 0.5 < 0.7 < 0.7 1.5 +/- 0.8 < 1.4 NW-C 07/08/14 1260 +/- 183 NW-C 10/28/14 820 +/- 146 NW-CW 01/24/14 403 +/- 132 NW-CW 04/24/14 Original 579 +/- 139 < 2.8 < 0.5 < 0.7 < 0.7 2.5 +/- 0.9 < 1.4 NW-CW 04/24/14 Recount 474 +/- 140 NW-CW 07/08/14 494 +/- 143 B-4
TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)
NW-CW 10/28/14 447 +/- 128 OS-14 01/21/14 < 180 OS-14 04/23/14 < 170 < 8.3 < 0.5 < 1.0 < 0.9 9.3 +/- 1.3 < 1.6 OS-14 07/10/14 < 167 OS-14 10/29/14 < 170 OS-16 01/21/14 443 +/- 125 OS-16 04/23/14 651 +/- 139 < 4.5 < 0.7 < 0.6 < 0.9 5.9 +/- 0.9 < 1.6 OS-16 07/10/14 445 +/- 125 OS-16 10/29/14 463 +/- 124 OS-18 01/21/14 < 186 OS-18 04122/14 Original 347 +/- 113 < 6.2 < 0.7 < 1.4
- 0.6 6.6 +/- 1.2 < 1.3 OS-18 04/22/14 Recount 327 +/- 129 OSF 01/20/14 494 +/- 141 OSF 04/24/14 258 +/- 108 < 6.6 < 0.5 < 1.8 < 0.7 6.1 +/- 1.3 < 1.4 OSF 07/10/14 294 +/- 131 OSF 10/28/14 220 +/- 116 RW-1 01/20/14 < 163 RW-1 04/24/14 < 181 < 3.4 < 0.6 < 1.1
- 0.7 8.5 +/- 1.3 < 1.4 RW-1 07/10/14 < 163 RW-1 10/28/14 < 170 RW-2 01/21/14 < 186 RW-2 01/21/14 < 162 RW-2 04/23/14 < 168 < 4.4 < 0.6 < 0.8 < 0.9 11.5 +/- 1.4 < 1.6 TRAINING CENTEF 04/23/14 < 168 B-5
TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE 3 04/23/14 < 41 < 72 <4 <4 < 10 <5 <8 <-5 <9 <4 < 5 < 3i < lU 48S 04/24/14 < 37 < 72 <3 <4 <8 <4 <8 <4 <6 <4 <3 < 24 <8 MS-1 04/22/14 < 44 < 43 <5 <5 < 10 <5 <8 <5 <9 <5 <5 < 32 < 10 MS-19 04/22/14 < 35 < 74 <4 <3 <5 <4 <6 <4 <6 <4 <3 < 27 <5 MS-2 04/23/14 < 42 107 +/- 49 < 5 <5 < 11 <4 <9 <5 <9 <5 <5 < 27 < 12 MS-2 04/23/14 < 35 < 32 <3 <4 <8 <3 <6 <4 <6 <3 <4 < 29 <8 MS-20 04121/14 < 32 < 34 <3 <4 <7 <3 <6 <4 <6 <3 <4 < 26 <7 MS-21 04/23/14 < 32 < 65 <4 <4 <8 <4 <7 <5 <8 <4 <4 < 24 <8 MS-22 04/23/14 < 39 < 83 <4 <4 <9 <4 <8 <5 <8 <4 <4 < 32 <8 MS-22 05/19/14 < 20 < 33 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 21 <8 MS-3 01/21/14 < 32 < 27 <4 <4 <8 <3 <6 <4 <6 <3 <4 < 27 <6 MS-3 04/23/14 < 39 < 36 <4 <4 <8 <4 <8 <5 <7 <4 <5 < 30 <7 MS-3 07/10/14 < 45 < 47 <4 <5 < 10 <4 <9 <5 <8 <4 <5 < 27 <8 MS-3 10/29/14 < 58 < 135 <6 <7 < 11 <6 < 15 <7 < 16 <6 <8 < 31 < 10 MS-4 04/23/14 <41 < 44 <4 <4 <9 <4 <8 <4 <8 <4 <4 < 27 <9 MS-5 01/21/14 < 46 < 86 <4 <5 < 11 <5 <9 <5 < 10 <4 <5 < 34 < 12 MS-5 04/23/14 < 45 < 80 <5 <4 <9 <5 <7 <5 <9 <4 <4 < 30 < 12 MS-5 07/10/14 < 39 < 69 <4 <5 <8 <4 <8 <5 <9 <4 <5 < 25 <9 MS-5 10/29/14 < 50 < 112 <5 <6 < 13 <5 < 11 <6 < 10 <6 <6 < 27 <9 MS-7 04/22/14 < 41 < 83 <4 <5 <9 <5 <9 <5 <8 <4 <4 < 29 <9 MS-8 01/21/14 < 35 < 71 <4 <4 <8 <3 <8 <4 <7 <4 < 3 < 27 <8 MS-8 01/21/14 < 37 < 32 <4 <4 <9 <4 <7 <4 <8 <4 <4 < 26 < 10 MS-8 04/23114 < 42 119 +/- 51 <4 <5 <9 <4 < 10 <5 <8 <5 <5 < 31 <9 MS-8 07110114 < 37 < 82 <4 <4 <9 <4 <8 <4 <8 <4 <4 < 22 <7 MS-8 10/29/14 < 56 < 102 <8 <5 < 17 <9 < 15 <8 < 11 <5 <8 < 29 < 14 MS-8 10/29/14 < 56 < 97 <6 <5 < 14 <6 < 15 <7 < 12 <6 <7 < 31 < 11 MW-i 04/24/14 < 41 < 85 <4 <5 < 10 <4 <8 <5 <7 <4 <5 < 31 <9 MW-2 04/24/14 < 40 < 34 <4 <4 <8 <3 <6 <4 <7 <4 <4 < 26 <6 MW-TMI-10D 10/28/14 < 43 < 55 <5 <5 < 10 <3 < 10 <5 <8 <5 <4 < 27 <7 MW-TMI-101 04/22/14 < 39 < 80 <4 <4 < 10 <4 <8 <5 <8 <4 <4 < 29 < 10 MW-TMI-10S 04/22/14 < 43 < 42 <4 <4 < 12 <5 <9 <4 <9 <4 <4 < 30 <9 MW-TMI-12S 04/23/14 < 43 < 35 <5 <5 < 10 <4 <8 <5 <9 <5 <5 < 30 <9 MW-TMI-1 3S 04/22/14 < 43 < 45 <5 <5 < 10 <5 < 10 <5 <8 <4 <5 < 32 < 11 MW-TMI-14S 04/22/14 < 43 < 46 <4 <5 < 10 <5 <7 <4 <9 <4 <4 < 33 <9 MW-TMI-16D 10/29/14 < 70 < 70 <8 <7 < 15 < 17 <7 < 12 <8 <8 < 41 < 10 MW-TMI-171 04/24/14 < 44 < 93 <4 <5 < 13 <5 < 10 <5 < 11 <4 <5 < 31 < 11 MW-TMI-1 8D 04/24/14 < 38 < 37 <4 <5 <B <4 <8 <4 <8 <4 <4 < 28 <9 MW-TMI -18D 04/24/14 < 44 < 39 <4 <3 <8 <3 <8 <4 <7 <4 <4 < 25 < 10 MW-TMI-191 04/22/14 < 32 < 24 <4 <4 <5 <3 <8 <4 <6 <3 <4 < 22 <5 MW-TMI-1D 04/24/14 < 40 < 93 <4 <4 < 10 <6 <9 <5 <8 <4 <4 < 28 <8 MW-TMI-20D 04/22114 < 40 < 77 <4 <5 <9 <5 <9 <4 <8 <4 <4 < 28 < 11 MW-TMI-201 04/22/14 <41 < 74 <4 <5 <9 <5 <7 <5 <8 <4 <4 < 29 < 10
TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE MW-TMI-21 D 05/19/14 < 23 <17 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 22 MW-TMI-21 I 05/19/14 < 18 <14 <2 <2 <4 <2 <4 <2 <4 <2 <2 < 19 MW-TMI-21 S 05/19/14 < 21 <22 <2 <2 <6 <2 <5 <3 <4 <2 <2 < 21 MW-TMI-22D 05/19/14
- 21 <45 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 22 MW-TMI-221 05/19/14 < 21 <17 <2 <2 <5 <2 <4 <2 <4 <2 <2 < 22 MW-TMI-22S 04/21/14 < 30 < 39 <4 <3 <8 <4 <7 <4 <6 <3 <3 < 26 MW-TMI-22S 05/19/14 <18 <32 <2 <2 <5 <2 <4 <2 <4 <2 <2 <19 MW-TMI-2D 04/24/14 < 44 < 112 < 4 <5 <7 <4 <9 <5 <9 <4 <5
- 30 MW-TMI-31 04/24/14 < 41 < 89 <4 <4 <8 <4 <8 <4 <8 <4 <4 < 29 MW-TMI-41 04/22/14 < 44 96 55 < 5 <5 < 10 <5 <10 <6 <9 <5 <5 < 32 MW-TMI-41 04/22/14 < 39 <63 <4 <4 <9 <3 <7 <4 <7 <3 <4 < 31 MW-TMI-4S 04/22/14 < 45 < 35 <4 <4 <9 <4 <9 <4 <8 <4 <4 < 30 MW-TMI-6D 04/22/14 < 42 < 36 <4 <4 < 10 <5 <8 <5 <7 <4 <4 < 32 MW-TMI-61 04/22/14 < 40 <25 <5 <4 <8 <4 <9 <5 <8 <4 <6
- 30 MW-TMI-7S 04/24/14 < 49 <36 <4 <4 < 11 <5 <7 <4 <9 <5 <5 < 35
,4 MW-TMI-8S 04/24/14 < 39 <48 <4 <5 < 10 <5 <9 <5 <7 <4 <4 < 27 MW-TMI-91 04/24/14 < 42 <86 <4 <6 <9 <4 < 11 <5 <7 <4 <5 < 28 MW-TMI-9S 04/24/14 < 45 <91 <4 <5 < 10 <5 < 10 <5 <9 <4 <4 < 32 N2-1 04/25/14 < 16 <32 < 2 <2 <4 <2 <3 <2 <3 <1 <2 < 13 NW-A 04/25/14 < 42 <92 <5 <5 < 10 <4 < 10 <5 <9 <5 <5 < 33 NW-B 04/25/14 < 43 < 76 <4 <5 < 11 <4 <11 <5 <8 <4 <4 < 28 NW-C 04/25/14 < 49 <49 < 5 <5 < 10 <4 <9 <5 <8 <4 <5 < 36 NW-CW 04/24/14 < 45 <50 <5 <5 < 12 <5 < 10 <5 <9 <5 <5 < 32 OS-14 01/21/14 < 35 <60 < 3 <4 <7 <4 <7 <4 <6 <3 <4 < 27 OS-14 04/23/14 < 41 <41 <4 <5 < 10 <5 <9 <5 < 10 <4 <5 < 33 OS-14 07/10/14 < 34 <51 <3 <3 <5 <3 <5 <4 <5 <3 <3 < 19 OS-14 10/29/14 < 80 < 165 < 7 <8 < 18 <9 < 15 <8 < 15 <6 <8 < 41 OS-16 01/21/14 < 39 <42 <4 <4 <9 <4 <9 <5 <8 <4 <4 < 31 OS-16 04/23/14 < 37 <46 <4 <5 <9 <4 <8 <4 <8 <4 <4 < 28 OS-16 07/10/14 < 48 <56 < 5 <6 < 13 <6 < 10 <6 < 10 <5 <5 < 32 OS-16 10/29/14 < 58 <65 <6 <7 < 15 <6 < 10 <7 < 13 <6 <6 < 29 OS-18 04/22/14 < 45 <110 <4 <5 <9 <4 <8 <5 <7 <4 <5 < 32 OSF 04/24/14 < 44 <46 <4 <4 <11 <4 <9 <5 <9 <4 <5 < 29 RW-1 04/24/14 < 39 53 + 35 < 4 <4 <9 <4 <8 <4 <8 <4 <4 < 26 RW-2 04/23/14 < 43 < 34 <4 <5 <7 <4 <7 <4 <7 <4 <4 < 28 TRAINING CENTER 04/23/14 < 44 < 86 <4 <5 < 11 <5 <9 <6 <9 <5 <5 < 31
TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 DATE MW-TMI-101 04/22114 < 0.04 < 0.04 < 0.05 < 0.03 < 0.02 < 0.04 < 0.02 < 0.04 < 140
- 4.8 MW-TMI-10S 04/22/14 < 0.10 < 0.02 < 0.03 < 0.02 < 0.03 < 0.08 < 0.14 < 0.18 < 94
- 4.8 80
TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 U
SW-E-1 01/20/14 < 181 SW-E-1 04/24/14 < 179 SW-E-1 07/10/14 < 176 SW-E-1 10/28/14 < 170 SW-E-2 01/22/14 < 181 SW-E-2 04/23/14 < 165 SW-E-2 07/10/14 < 181 SW-E-2 10/28/14 < 172 SW-E-3 01/22/14 < 182 SW-E-3 04/23/14 < 156 SW-E-3 04/23/14 < 170 SW-E-3 07/10/14 < 182 SW-E-3 10/28/14 < 170 B-9
TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE SW-E-1 04/24114 < 41 < 46 <4 <5 <12 <4 <9 <5 <7 <3 <4 <28 <8 L586 SW-E-2 04/23/14 < 36 < 32 <3 <3 <8 <4 <8 <4 <7 <4 <3 <27 <7 L586 SW-E-3 04/23/14 < 51 < 95. <5 <6 <12 <4 <10 <6 <8 <5 <5 <38 <10 L586 SW-E-3 04/23/14 < 40 < 102 <4 <4 <10 <4 <7 <4 <7 <4 <4 <31 <7 L586 0
TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN STORM WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM PROGRAM - THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 EUDB 02/04/14 289 +/- 118 EDCB 04/29/14
- 176 EDCB 07/29/14 < 157 EDCB 10/28/14 312 +/- 114 B-Il
TABLE B-I11.2 CONCENTRATIONS OF GAMMA EMITTERS IN STORM WATER SAMPLES COLLECTED IN THE VICINITY OF THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 DATE EDCB 02/04/14 < 19 < 45 <2 <2 <4 <2 <4 <2 <4 <2 <2 <14 <5 EDCB 04/29/14 < 48 < 108 <6 <5 < 10 <6 < 12 <6 <10 <5 <5 <29 <9 EDCB 07/29/14 <41 <40 <5 <5 <8 <4 <8 <5 <9 <4 <5 <26 <6 EDCB 10/28/14 <43 <69 <4 <5 <9 <6 <9 <5 <7 <4 <5 <23 <8
,=J
TABLE B-IV.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 U
TM-PR-ESE 03/10/14 Original 2140 +/- 256 TM-PR-ESE 03/10/14 Recount 2180 +/- 273 TM-PR-ESE 03/10/14 Reanalysis 2470 +/- 299 TM-PR-ESE 05/10/14 182 TM-PR-ESE 08108/14 194 TM-PR-ESE 10/08/14 Original 741 +/- 153 TM-PR-ESE 10/08/14 Recount 721 +/- 152 TM-PR-ESE 10/08/14 Reanalysis 502 +/- 145 TM-PR-MS-1 03/10/14 191 TM-PR-MS-1 05/10/14 188 TM-PR-MS-1 08/08/14 194 TM-PR-MS-1 10/08/14 177 TM-PR-MS-2 03/10/14 Original 2210 +/- 272 TM-PR-MS-2 03/10/14 Recount 2200 +/- 275 TM-PR-MS-2 03/10/14 Reanalysis 2070 +/- 260 TM-PR-MS-2 05/10/14 191 TM-PR-MS-2 08/08/14 196 TM-PR-MS-2 10/08/14 Original 459 :1 135 TM-PR-MS-2 10/08/14 Recount 357 +/- 131 TM-PR-MS-2 10/08/14 Reanalysis 300 + 132 TM-PR-MS-4 03/10/14 Original 1060 + 173 TM-PR-MS-4 03/10/14 Recount 1010 +/- 175 TM-PR-MS-4 03/10/14 Reanalysis 838 + 163 TM-PR-MS-4 05/10/14 187 TM-PR-MS-4 08/08/14 194 TM-PR-MS-4 10/08/14 Original 318 +/- 128 TM-PR-MS-4 10/08/14 Recount 324 +/- 131 TM-PR-MS-4 10/08/14 Reanalysis 353 +/- 144 B-13
Intentionally left blank APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY
Intentionally left blank TABLE C-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A Gr-B 3 10/28/14 431 +/- 110 48S 07/10/14
- 136 MS-2 04/23/14 860 +/- 110 < 0.5 < 0.4 < 1.4 2.7 +/- 0.7 MS-20 01/20/14 568 +/- 101 MS-7 07/09/14 186 +/- 76 MS-8 01/21/14 295 +/- 90 MW-TM I-10)D 04/22/14 293 +/- 87 MW-TMI-1OS 01/20/14 795 +/- 110 MW-TMI-10S 07/09/14 1695 +/- 133 MW-TMI-1 31 10/28/14 284 +/- 102 MW-TMI-141 01/20/14 < 144 MW-TMI-18D 04/24114 305 +/- 88 MW-TMI-21 I 07/09/14 3540 +/- 182 MW-TMI-22S 04/21/14 8916 +/- 278 < 0.7 < 0.6 < 0.9 3.5 +/- 0.7 MW-TMI-31 10/29/14 404 +/- 109 MW-TMI-41 04/22/14 186 +/- 82 RW-2 01/21/14 < 144 C-I
TABLE C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD MS-2 04/23/14 < 32 < 73 <4 <5 <2 <2 <5 <4 <3 <2 <4 < 16 <5 MS-8 01/21/14 < 43 < ## <4 <4 <2 <3 <8 <7 <6 <3 <3 < 16 <2 MW-TMI-18D 04/24/14 < 30 < 35 <2 <3 <2 <3 <7 <4 <2 <4 <3 < 16 <3 MW-TMI-22S 04/21/14 < 34 < 53 <2 <4 <1 <2 <3 <3 <4 <3 <3 < 15 <4 MW-TMI-41 04/22/14 < 28 < 63 <2 <6 <3 <2 <5 <5 <3 <3 <2 < 13 <3 n-
TABLE C-1.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-233/234 U-235 U-238 Fe-55 Ni-63 PERIOD NONE FOR 2014
TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SW-E-3 04/23/14 < 146 C-4
TABLE C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE COLLECTION Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD SW-E-3 04/23/14 < 32 < 65 <3 <4 <2 <3 <3 <4 <2 <3 <2 <17 <3
TABLE C-II1.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SPLIT SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, THREE MILE ISLAND NUCLEAR STATION, 2014 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 TM-PR-MS-2Q 03/31/14 2350 +/- 158 TM-PR-MS-2Q 06/06/14 246 +/- 83 TM-PR-MS-2Q 08/29/14 < 177 TM-PR-MS-2Q 11/07/14 599 +/- 111 C-6