U-604277, Annual Radiological Environmental Operating Report: Difference between revisions

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{{#Wiki_filter:Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604277 April 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRG Docket No. 50-461 Exelon Generation
{{#Wiki_filter:Exelon Generation Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604277 April 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62                                   '"-"
NRG Docket No. 50-461


==Subject:==
==Subject:==
Clinton Power'Station 2015 Annual Radiological Environmental Operating Report Exelon Generating Company, LLC (Exelon), Clinton Power Station is submitting the 2015 Annual Radiological Environmental Operating Report. This report is submitted in accordance with Technical Specification requirement 5.6.2, "Annual Radiological Environmental Operating Report," and covers the period from January 1, 2015 through December 31, 2015. This report provides the results of the Radiological Environmental Monitoring Program as specific in Section 3/4 and 6.1 of the Offsite Dose Calculation Manual. There are no regulatory commitments  
Clinton Power'Station 2015 Annual Radiological Environmental Operating Report Exelon Generating Company, LLC (Exelon), Clinton Power Station is submitting the 2015 Annual Radiological Environmental Operating Report. This report is submitted in accordance with Technical Specification requirement 5.6.2, "Annual Radiological Environmental Operating Report," and covers the period from January 1, 2015 through December 31, 2015.
*contained within this letter. Questions on this letter may be directed to Mr. Rick Bair, Chemistry Manager, at 217-937-3200.
This report provides the results of the Radiological Environmental Monitoring Program as specific in Section 3/4 and 6.1 of the Offsite Dose Calculation Manual.
Respectfully, Theodore R. Stone( tf'\ Site Vice President Clinton Power Station dra/bsz Attachments:
There are no regulatory commitments *contained within this letter.
Annual Radiological Environmental Operating Report cc: Regional Administrator-NRG Region Ill NRG Senior Resident Inspector  
Questions on this letter may be directed to Mr. Rick Bair, Chemistry Manager, at 217-937-3200.
-Clinton Power Station Office of Nuclear Facility Safety -Illinois Emergency Management Agency ' "-"
Respectfully,
Page 1of138 Intentionally left blank Page 2of138 Docket No: 50-461 POWER Annual Radiological Environmental Operating Report January 1 Through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services J:/ ExelonGeneration, Clinton Power Station Clinton, IL 61727 April 2016 Page 3of138 INTENTIONALLY LEFT BLANK Page 4of138 Table Of Contents I. Summary and Conclusions  
      ~
..............................................................................................
Theodore R. Stone( tf'\
1 II. Introduction  
Site Vice President Clinton Power Station dra/bsz Attachments:
....................................................................................................  
Annual Radiological Environmental Operating Report cc:       Regional Administrator- NRG Region Ill NRG Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Emergency Management Agency
-.................
 
3 A. Objectives of the REMP ......................................................................................
Page 1of138 Intentionally left blank Page 2of138
3 B. Implementation of the Objectives  
 
........................................................................
Docket No:     50-461 CL~NTON      POWER             STAT~ON Annual Radiological Environmental Operating Report January 1 Through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services
3 Ill. Program Description  
    *~
......................................................................................................
J:/ ExelonGeneration, Clinton Power Station Clinton, IL 61727 April 2016 Page 3of138
4 A. Sample Collection  
 
...............................................................................................
INTENTIONALLY LEFT BLANK Page 4of138
4 B. Sample Analysis .......................................................
 
: ..........................................
Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ....................................................................................................-................. 3 A. Objectives of the REMP ...................................................................................... 3 B. Implementation of the Objectives ........................................................................ 3 Ill. Program Description ...................................................................................................... 4 A. Sample Collection ............................................................................................... 4 B. Sample Analysis .......................................................:.......................................... 6 C. Data_ lnterpretati<;m ***'.****'._******~:***************************-**~*:*********************:*********************** 6
6 C. Data_ lnterpretati<;m 6 ------n_,-Pro-graih Exceptions-
    - ----n_,- Pro-graih Exceptions-........... .-.-.~ ...........-..-.......... :.. :.~.~~~-.-.:-:.-~:.-.... :............ .-:... .-.-.: ......... 8 E. Program Changes .............................................................._              ............................... 12 IV. Results and Discussion ............................................................................................... 12 A. Aquatic Environment ......................................................................................... 12
...........
: 1. Surface Water. ........................................................................................ 12
...........
: 2. Drinking Water ........................................................................................ 12
-. .-..........
: 3. Well Water ............................................................................................. 13
: ..
: 4. Fish ......................................................................................................... 13
.... : ............  
: 5. Sediment. ................................................................................................ 14 B. Atmospheric Environment ............... :***************************************************************** 14
.-: ... .-.-.: .........
: 1. Airborne .................................................................................................. 14
8 E. Program Changes ..............................................................
: a. Air Particulates ................................. :........................................*... 14
_ ...............................
: b. Airborne Iodine ............................................................................ 15
12 IV. Results and Discussion
: 2. Terrestrial ................................................................................................ 15
...............................................................................................
: a. Milk ............................................................................................... 15
12 A. Aquatic Environment
: b. Food Products ............................................................................. 16
.........................................................................................
: c. Grass ........................................................................................... 16 C. Ambient Gamma Radiation ............................................................................... 16 D. Land Use Survey ............................................................................................... 17 E. Errata Data ........................................................................................................ 17 F. Summary of Results - Inter-laboratory Comparison Program .......................... 18 V. References ................................................................................................................... 22 Page 5of138
12 1. Surface Water. ........................................................................................
 
12 2. Drinking Water ........................................................................................
Appendices Appendix A     Radiological Environmental Monitoring Report Summary Tables Table A-1     Radiological Environmental Monitoring Program Annual Summary for the Clinton Power Station, 2015 Appendix B   Location Designation, Distance & Direction, and Sample Collection &
12 3. Well Water .............................................................................................
Analytical Methods
13 4. Fish .........................................................................................................
__,_:Tables ..
13 5. Sediment.  
Table B-1   Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Table B-2   Radiological Environmental Monitoring Program - Summary of Sample Collection, Clinton Power Station, 2015 Figures Figure B-1  Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 Figure B-2  Environmental Sampling Locations Between One and Two Miles from the Clinton Power Station, 2015 Figure B-3  Environmental Sampling Locations Between-Two and Five Miles from the Clinton Power Station, 2015 Figure B-4   Environmental Sampling Locations Greater Than Five Miles from the Clinton Power Station, 2015 Appendix C   Data Tables and Figures - Primary Laboratory Tables Table C-1.1   Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
................................................................................................
Table C-1.2   Concentrations of Tritium in Surface Water Samples Coll~cted in the Vicinity of Clinton Power Station, 2015.
14 B. Atmospheric Environment
Table C-1.3   Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
...............
Table C-11.1  Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
:*****************************************************************
ii Page 6of138
14 1. Airborne ..................................................................................................
 
14 a. Air Particulates  
Table C-11.2    Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
.................................
Table C-11.3    Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
: ........................................  
Table C-11.4    Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
* ... 14 b. Airborne Iodine ............................................................................
Table C-111.1    Concentrations of Tritium in Well Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
15 2. Terrestrial  
Table C-111.2    Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
................................................................................................
Table C-IV.1    Concentrations of Gamma Emitters in Fish Samples Collected in the
15 a. Milk ...............................................................................................
* Vicinity of Clinton Power Station, 2015.
15 b. Food Products .............................................................................
------~-; *~*' ., -*   ,. - -        - - - - .. - - - *- - -                ~
16 c. Grass ...........................................................................................
                                                                                  - - .
16 C. Ambient Gamma Radiation  
                                                                -- ............ --..--  -        .    *- ~ - -
...............................................................................
Table C-V.1      Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Clinton Power Station, 2015.
16 D. Land Use Survey ...............................................................................................
Table C-Vl.1    Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.
17 E. Errata Data ........................................................................................................
Table C-Vl.2    Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.
17 F. Summary of Results -Inter-laboratory Comparison Program ..........................
Table C-Vl.3    Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Clinton Power Statio_n, 2015.
18 V. References  
Table C-Vll.1   Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Clinton Power Station, 2015.
...................................................................................................................
Table C-Vlll.1  Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.
22 Page 5of138 Appendix A Tables Table A-1 Appendix B __ ,_:Tables  
Table C-Vlll.Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.
.. Table B-1 Table B-2 Figures Figure B-1 Figure B-2 Figure B-3 Figure B-4 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-11.1 Appendices Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Clinton Power Station, 2015 Location Designation, Distance & Direction, and Sample Collection
Table C-IX.1     Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Clinton Power Station, 2015.
& Analytical Methods Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Radiological Environmental Monitoring Program -Summary of Sample Collection, Clinton Power Station, 2015 Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 Environmental Sampling Locations Between One and Two Miles from the Clinton Power Station, 2015 Environmental Sampling Locations Between-Two and Five Miles from the Clinton Power Station, 2015 Environmental Sampling Locations Greater Than Five Miles from the Clinton Power Station, 2015 Data Tables and Figures -Primary Laboratory Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Tritium in Surface Water Samples in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. ii Page 6of138 Table C-11.2 Table C-11.3 Table C-11.4 Table C-111.1 Table C-111.2 Table C-IV.1
Table C-IX.2    Concentrations of Gamma Emitters in Grass Samples Collected in the Vicinity of Clinton Power Station, 2015.
., -* ,. --Table C-V.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Tritium in Well Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Fish Samples Collected in the
Table C-X.1      Quarterly DLR Results for Clinton Power Station, 2015.
* Vicinity of Clinton Power Station, 2015. ------.. ---*-----............ --..--. -. *---Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vl.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vl.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vl.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Clinton Power Statio_n, 2015. Table C-Vll.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vlll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vlll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-IX.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-IX.2 Concentrations of Gamma Emitters in Grass Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-X.1 Quarterly DLR Results for Clinton Power Station, 2015. Table C-X.2 Mean Quarterly DLR Results for the Inner Ring, Outer Ring, Special Interest and Control Locations for Clinton Power Station, 2015. Table C-X.3 Summary of the Ambient Dosimetry Program for Clinton Power Station, 2015. iii Page 7of138 Figures Figure C-1 Figure C-2 Appendix D Tables Table D-1 TaQle Table D-3 Table D-4 Table D-5 Appendix E Appendix F Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of CPS, 2015. Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of CPS, 2015. Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, .2015 DOE's Mixed Alialyte Performance Evaluation Program (MAPEP) Teledyne Brown Engine-ering, 2015 * * -ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 ERA(a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 DOE's Mixed Analyte Performance Evaluation-Program (MAPEP) Teledyne Brown Engineering, 2015
Table C-X.2      Mean Quarterly DLR Results for the Inner Ring, Outer Ring, Special Interest and Control Locations for Clinton Power Station, 2015.
* Errata Data . Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 8of138 I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Clinton Power Station (CPS) by Exelon Generation Company, LLC (Exelon) covers the period January 1, 2015 through December 31, 2015. During that time period, 1,590 analyses were performed on 1,463 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of CPS had no adverse radiological impact on the environment.
Table C-X.3      Summary of the Ambient Dosimetry Program for Clinton Power Station, 2015.
iii Page 7of138
 
Figures Figure C-1 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of CPS, 2015.
Figure C-2 Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of CPS, 2015.
Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, .2015 TaQle D~2  DOE's Mixed Alialyte Performance Evaluation Program (MAPEP)
Teledyne Brown Engine-ering, 2015                          * -~- * -
Table D-3  ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 Table D-4  ERA(a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 Table D-5  DOE's Mixed Analyte Performance Evaluation- Program (MAPEP)
Teledyne Brown Engineering, 2015
* Appendix E Errata Data .
Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 8of138
 
I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Clinton Power Station (CPS) by Exelon Generation Company, LLC (Exelon) covers the period January 1, 2015 through December 31, 2015.
During that time period, 1,590 analyses were performed on 1,463 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of CPS had no adverse radiological impact on the environment.
There were zero (0) radioactive liquid releases from CPS during 2015. Releases of gaseous radioactive materials were accurately measured in plant effluents.
There were zero (0) radioactive liquid releases from CPS during 2015. Releases of gaseous radioactive materials were accurately measured in plant effluents.
There were no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite _dose received by.,a member. of the-public in :2015. due-to .the release .oL'---*-*-. gaseous effluents from CPS was 2.53 E-03 or 0.00253 mRem. Surface, drinking,_
There were no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite _dose received by.,a member. of the- public in :2015. due-to .the release .oL'---*-*- .
and well water samples were analyzed for concentrations of tritium and gamma emitting nuclides.
gaseous effluents from CPS was 2.53 E-03 or 0.00253 mRem.
Drinking water samples were also analyzed for concentrations of gross beta and 1-131. Naturally occurring K-40 was detected .at levels consistent with those detected in previous years. No fission or activation products were detected.
Surface, drinking,_ and well water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of gross beta and 1-131. Naturally occurring K-40 was detected .at levels consistent with those detected in previous years. No fission or activation products were detected. No tritium or gross beta activity was detected. and the required lower limit of detection (LLD) was met.
No tritium or gross beta activity was detected.
Fish and shoreline sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish or shoreline sediment samples.
and the required lower limit of detection (LLD) was met. Fish and shoreline sediment samples were analyzed for concentrations of gamma emitting nuclides.
Air particulate samples were analyzed for concentrations of gross. beta and gamma emitting nuclides. Cosmogenic Be-7 and naturally occurring K-40 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.
No fission or activation products were detected in fish or shoreline sediment samples. Air particulate samples were analyzed for concentrations of gross. beta and gamma emitting nuclides.
Iodine- 1-131 analyses were performed on weekly air samples. All results were less than the lower limit of detection for 1-131.
Cosmogenic Be-7 and naturally occurring K-40 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.
High sensitivity 1-131 analyses and gamma analyses were performed on cow milk samples. All results were below the required LLDs for 1-131.
Iodine-1-131 analyses were performed on weekly air samples. All results were less than the lower limit of detection for 1-131. High sensitivity 1-131 analyses and gamma analyses were performed on cow milk samples. All results were below the required LLDs for 1-131. Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found. Food product samples were analyzed for concentrations of gamma emitting nuclides.
Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.
Concentrations of cosmogenically produced Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.
Food product samples were analyzed for concentrations of gamma emitting nuclides. Concentrations of cosmogenically produced Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.
Grass samples were analyzed for concentrations of gamma emitting nuclides.
Grass samples were analyzed for concentrations of gamma emitting nuclides.
Concentrations of cosmogenically produced Be-7 and naturally occurring were consistent with those detected in previous years. No fission or activation Page 9of138 products were detected.
Concentrations of cosmogenically produced Be-7 and naturally occurring K~40 were consistent with those detected in previous years. No fission or activation Page 9of138
Environmental gamma radiation measurements were performed quarterly using Dosimeters of Legal Record (DLR). Levels detected were consistent with those observed in previous years. Page 10of138 II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois.
 
CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on February 15, 1987. The site encloses approximately 13, 730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated on approximately 150 acres. The cooling water discharge flume -which discharges to the eastern arm of the lake -occupies an additional 130 acres. Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa f.nn_a _Townships.
products were detected.
A Radiological Environmental Monitoring Program (REMP) for CPS was initiated in 1987. The preoperational period for most media covers the periods May 1980 through February 27, 1987 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TSE) and Landauer on samples collected during the period January 1, 2015 through December 31, 2015. A. Objectives of the REMP The objectives of the REMP are to: 1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
Environmental gamma radiation measurements were performed quarterly using Dosimeters of Legal Record (DLR). Levels detected were consistent with those observed in previous years.
Page 10of138
 
II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on February 15, 1987. The site encloses approximately 13, 730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated on approximately 150 acres. The cooling water discharge flume - which discharges to the eastern arm of the lake - occupies an additional 130 acres.
Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa f.nn_a _Townships.
A Radiological Environmental Monitoring Program (REMP) for CPS was initiated in 1987. The preoperational period for most media covers the periods May 1980 through February 27, 1987 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TSE) and Landauer on samples collected during the period January 1, 2015 through December 31, 2015.
A. Objectives of the REMP The objectives of the REMP are to:
: 1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
: 2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
: 2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
B. Implementation of the Objectives The implementation of the objectives is accomplished by: 1. Identifying significant exposure pathways.
B. Implementation of the Objectives The implementation of the objectives is accomplished by:
: 1. Identifying significant exposure pathways.
: 2. Establishing baseline radiological data of media within those pathways.
: 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. Page 11 of 138 Ill. Program Description A. Sample Collection This section describes the general collection methods used by Environmental Inc. (Midwest Labs) to obtain environmental samples for the CPS REMP in 2015. Sample locations and descriptions can be found in Tables B-1 and and Figures B-1 through B-4, Appendix B. The sampling methods used by Environmental Inc. (Midwest Labs) are listed in Table B-2. Aquatic Environment The aquatic environment was evaluated by performing radiological  
: 3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.
---------* analyses on samples of surface water, drinking water; well-water, fish, shoreline sediment.
Page 11 of 138
Two gallon water samples were collected monthly from composite samplers located at three surface water locations (CL-90, CL-91 and CL-99) and one drinking water location (CL-14). A monthly grab sample was obtained from one surface water location (CL-13). Quarterly samples were obtained from two well water locations (CL-70 and CL-12). All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection.
 
Fish samples comprising the flesh of largemouth bass, crappie, carp, bluegill and channel catfish, the species most commonly harvested from the lakes by sporting fishermen, were collected semiannually at two locations, CL-19 and CL-105. CL-105 was the control location, which is located about 50 miles upwind of the station. Shoreline sediment samples composed of recently deposited substrate were collected at two locations semiannually (CL-78 and CL-105 (control)).
Ill.       Program Description A. Sample Collection This section describes the general collection methods used by Environmental Inc. (Midwest Labs) to obtain environmental samples for the CPS REMP in 2015. Sample locations and descriptions can be found in Tables B-1 and B~2, and Figures B-1 through B-4, Appendix B. The sampling methods used by Environmental Inc. (Midwest Labs) are listed in Table B-2.
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, food produce and grass. Airborne iodine and particulate samples were collected and analyzed weekly at ten locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94). CL-11 was the control location, which is located 16 miles upwind of the station. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached.
Aquatic Environment The aquatic environment was evaluated by performing radiological
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 an independent laboratory for analysis. Page 12of138 Milk samples were collected biweekly at one location (CL-116) from May through October to coincide with the grazing season, and monthly from November through April. All samples were collected in new unused plastic bottles from the bulk tank at the dairy farm, preserved with sodium bisulfite and shipped promptly to the laboratory.
    -------- -
* analyses on samples of surface water, drinking water; well-water, fish, and---'-
shoreline sediment. Two gallon water samples were collected monthly from composite samplers located at three surface water locations (CL-90, CL-91 and CL-99) and one drinking water location (CL-14). A monthly grab sample was obtained from one surface water location (CL-13).
Quarterly samples were obtained from two well water locations (CL-70 and CL-12). All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of largemouth bass, crappie, carp, bluegill and channel catfish, the species most commonly harvested from the lakes by sporting fishermen, were collected semiannually at two locations, CL-19 and CL-105. CL-105 was the control location, which is located about 50 miles upwind of the station. Shoreline sediment samples composed of recently deposited substrate were collected at two locations semiannually (CL-78 and CL-105 (control)).
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, food produce and grass. Airborne iodine and particulate samples were collected and analyzed weekly at ten locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94). CL-11 was the control location, which is located 16 miles upwind of the station. 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 an independent laboratory for analysis.
Page 12of138
 
Milk samples were collected biweekly at one location (CL-116) from May through October to coincide with the grazing season, and monthly from November through April. All samples were collected in new unused plastic bottles from the bulk tank at the dairy farm, preserved with sodium bisulfite and shipped promptly to the laboratory.
Food products were collected once a month from June through September at four locations (CL-114, CL-115, CL-117 and CL-118). The control location was CL-114, which is located 12.5 miles upwind of the station. Various broadleaf vegetable samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Food products were collected once a month from June through September at four locations (CL-114, CL-115, CL-117 and CL-118). The control location was CL-114, which is located 12.5 miles upwind of the station. Various broadleaf vegetable samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Grass samples were collected biweekly at four locations (CL-1, CL-2, CL-8 and CL-116) from May through October. CL-116 was the control -
Grass samples were collected biweekly at four locations (CL-1, CL-2, CL-8 and CL-116) from May through October. CL-116 was the control
location, which is -located 14 miles WSW of the station. -Ail samples were collected in new unused plastic bags and sent to the laboratory for analysis.
- ------~ location, which is -located 14 miles WSW of the station. -Ail samples were --
Ambient Gamma Radiation Direct radiation measurements were made using DLRs. Each location consisted of 2 dosimeter sets. The DLRs were exchanged quarterly and sent to Landauer for analysis.
collected in new unused plastic bags and sent to the laboratory for analysis.
The DLR locations were placed around the CPS site as follows: An inner ring consisting of 16 locations (CL-1, CL-5, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42 CL-43, CL-44, CL-45, CL-46, CL-47, CL-48 and CL-63). An outer ring consisting of 16 locations (CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80 and CL-81). CL-58MM was installed as part of a volunteer comparison study extending to approximately 5 miles from the site. A special interest set consisting of seven locations (CL-37, CL-41, CL-49, CL-64, CL-65, CL-74 and CL-75) representing special interest areas. A supplemental set consisting of 14 locations (CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 and CL-114). CL-11 represents the control location for all environmental DLRs. The specific DLR locations were determined by the following criteria: Page13of138
Ambient Gamma Radiation Direct radiation measurements were made using DLRs. Each location consisted of 2 dosimeter sets. The DLRs were exchanged quarterly and sent to Landauer for analysis. The DLR locations were placed around the CPS site as follows:
: 1. The presence of relatively dense population;
An inner ring consisting of 16 locations (CL-1, CL-5, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42 CL-43, CL-44, CL-45, CL-46, CL-47, CL-48 and CL-63).
: 2. Site meteorological data taking into account distance and elevation for each of the sixteen-22 1 /2 degree meteorological sectors around the site, where estimated annual dose from CPS, if detected, would be most significant;
An outer ring consisting of 16 locations (CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80 and CL-81). CL-58MM was installed as part of a volunteer comparison study extending to approximately 5 miles from the site.
: 3. On hills free from local obstructions and within sight of the HVAC and VG stacks (where practical);
A special interest set consisting of seven locations (CL-37, CL-41, CL-49, CL-64, CL-65, CL-74 and CL-75) representing special interest areas.
: 4. And near the closest dwelling to the HVAC and VG stacks in the prevailing downwind direction.  
A supplemental set consisting of 14 locations (CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 and CL-114).
/ Each location has two DLRs in a vented PVC conduit located approximately three feet above ground-level.
CL-11 represents the control location for all environmental DLRs.
The DLRs were exchanged
The specific DLR locations were determined by the following criteria:
Page13of138
: 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 meteorological sectors around the site, where estimated annual dose from CPS, if detected, would be most significant;
: 3.     On hills free from local obstructions and within sight of the HVAC and VG stacks (where practical);
: 4.     And near the closest dwelling to the HVAC and VG stacks in the prevailing downwind direction.         /
Each location has two DLRs in a vented PVC conduit located approximately three feet above ground-level. The DLRs were exchanged
* quarterly and sent to Landauer for analysis.
* quarterly and sent to Landauer for analysis.
B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the CPS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-2. In order to achieve the stated objectives, the current program includes the following analyses:
B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the CPS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-2.
: 1. Concentrations of beta emitters in drinking water and air particulates.
In order to achieve the stated objectives, the current program includes the following analyses:
: 2. Concentrations of gamma emitters in surface, drinking and well water, air particulates, milk, fish, grass, sediment and vegetables.
: 1.     Concentrations of beta emitters in drinking water and air particulates.
: 3. Concentrations of tritium in surface, drinking and well water. 4. Concentrations of 1-131 in air, milk, drinking water and surface water. 5. Ambient gamma radiation levels at various off-site environs.
: 2.     Concentrations of gamma emitters in surface, drinking and well water, air particulates, milk, fish, grass, sediment and vegetables.
C. Data Interpretation The radiological and direct radiation data collected prior to CPS becoming operational was used as a baseline with which these operational data were compared.
: 3.     Concentrations of tritium in surface, drinking and well water.
For the purpose of this-report, CPS was considered Page 14of138 operational at initial criticality.
: 4.     Concentrations of 1-131 in air, milk, drinking water and surface water.
In addition, data were compared to previous years' operational data for consistency and trending.
: 5. Ambient gamma radiation levels at various off-site environs.
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" value. 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.
C. Data Interpretation The radiological and direct radiation data collected prior to CPS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this- report, CPS was considered Page 14of138
All analyses were designed to achieve the required CPS *detection capabilities for-environmental sample analysis.
 
: 2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity.
operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:
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 resulting in a negative number. A minimum detectable concentration (MDC) was reported in all cases where positive activity was not detected.
: 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" value. 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 CPS
Gamma spectroscopy results for each type of sample were grouped as follows: For surface water, well water, fish, sediment, and milk: 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
      *detection capabilities for-environmental sample analysis.
For drinking water, grass, and vegetation:
: 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 resulting in a negative number. A minimum detectable concentration (MDC) was reported in all cases where positive activity was not detected.
13 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
Gamma spectroscopy results for each type of sample were grouped as follows:
For air particulate:
For surface water, well water, fish, sediment, and milk: 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
9 nuclides, Co-60, Nb-95, Zr-95, Ru-103, Ru-106, Cs-134, Cs-137, Ce-141 and Ce-144, were reported.
For drinking water, grass, and vegetation: 13 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
The mean and deviation of the results were calculated.
For air particulate: 9 nuclides, Co-60, Nb-95, Zr-95, Ru-103, Ru-106, Cs-134, Cs-137, Ce-141 and Ce-144, were reported.
The standard de;,iation represents the variability of measured results for different samples rather than single analysis uncertainty. Page 15of138 D. Program Exceptions The exceptions (Issue Reports, IRs) described below are those that are considered  
The mean and ~tandard deviation of the results were calculated.
'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM. By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and within Radiological Assessment Branch Technical Position, Revision 1, November 1979, which states .... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, ------" -malfunction of automatic sampling equipment and other legitimate . *-*--.. --. -.*. --:.. ;-,----*----reasons" .... The below section addresses the reporting requirements found within Section 6.0_of the Station's ODCM. -Exceptions/Anomalies January 14, 2015, IR 02437296 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
The standard de;,iation represents the variability of measured results for different samples rather than single analysis uncertainty.
Page 15of138
 
D. Program Exceptions The exceptions (Issue Reports, IRs) described below are those that are considered 'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM. By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",
October 1978, and within Radiological Assessment Branch Technical Position, Revision 1, November 1979, which states .... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability,
--       - - --"                                 - malfunction of automatic sampling equipment and other legitimate reasons" .... The below section addresses the reporting requirements found within Section 6.0_of the Station's ODCM. -
  . *-*- - .. - - . - .*. - - :.. ;-,--- - *----
Exceptions/Anomalies January 14, 2015, IR 02437296 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 04, 2015, IR 02463282 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 04, 2015, IR 02463282 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 11, 2015, IR 02468075 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 11, 2015, IR 02468075 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
May 07, 2015, IR 02497332 While performing the ODCM weekly air sample collection and equipment verification activities on May 06, 2015, vendor Environmental Inc., Midwest Laboratories (EIML) discovered that the ODCM air samplers CL-2 and CL-3 had no power. In the absence of any severe storms or power outages, it was Page 16of138 indeterminate as to why there was no power. However, the minimum sample volume was reached. July 01, 2015, IR 02522637 At 1244 hours on 07/01/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its ground fault interrupter (GFI) 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis.
May 07, 2015, IR 02497332 While performing the ODCM weekly air sample collection and equipment verification activities on May 06, 2015, vendor Environmental Inc., Midwest Laboratories (EIML) discovered that the ODCM air samplers CL-2 and CL-3 had no power. In the absence of any severe storms or power outages, it was Page 16of138
A supplemental  
 
'grab' sample from the process stream was collected and added to the monthly collection container.
indeterminate as to why there was no power. However, the minimum sample volume was reached.
The GFI was reset and CL-90 was returned to service. July 15, 2015, IR 02528489 While performing the weekly inspection on 07/15/15 of ODCM Water Compositors, CL-99 was found not running with the GFI 'tripped' and the sample collection container tipped over inside of the Dog House enclosure.
July 01, 2015, IR 02522637 At 1244 hours on 07/01/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its ground fault interrupter (GFI) 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.
The last weekly inspection performed on July 08, 2015 revealed both as found and as left conditions as being satisfactory.
July 15, 2015, IR 02528489 While performing the weekly inspection on 07/15/15 of ODCM Water Compositors, CL-99 was found not running with the GFI
During this 7 day window, Murray and "'frettel, our fleetwide meteorological vendor, reported that Lincoln County had 4.5 inches, Bloomington haq 4.6 inches and DeWitt County had 4 inches of rain which all contributed to the North Fork Creek flooding.
      'tripped' and the sample collection container tipped over inside of the Dog House enclosure. The last weekly inspection performed on July 08, 2015 revealed both as found and as left conditions as being satisfactory. During this 7 day window, Murray and "'frettel, our fleetwide meteorological vendor, reported that Lincoln County had 4.5 inches, Bloomington haq 4.6 inches and DeWitt County had 4 inches of rain which all contributed to the North Fork Creek flooding. This flooding contributed to the 'as found' condition*
This flooding contributed to the 'as found' condition*
noted.
noted. August 19, 2015, IR 02543695 At 1046 hours on 08/19/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its GFI 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis.
August 19, 2015, IR 02543695 At 1046 hours on 08/19/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its GFI 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.
A supplemental  
August 21, 2015, IR 02545496 During the execution of Work Order #1614812-05 for the recently scheduled Potable Water Outage that commenced at 0325 hours, 08/21/15 the potable water was secured, drained and potable water pumps were placed in Manual OFF. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water samples Page 17of138
'grab' sample from the process stream was collected and added to the monthly collection container.
 
The GFI was reset and CL-90 was returned to service. August 21, 2015, IR 02545496 During the execution of Work Order #1614812-05 for the recently scheduled Potable Water Outage that commenced at 0325 hours, 08/21/15 the potable water was secured, drained and potable water pumps were placed in Manual OFF. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water samples Page 17of138 throughout the duration of the Potable Water Outage that was restored to service at 1800 hours on 08/22/15.
throughout the duration of the Potable Water Outage that was restored to service at 1800 hours on 08/22/15.
November 14, 2015, IR 02588060 During the execution of Clearance Order #129314 and energized Circuit 302 per WO 1863079-06 for the recently scheduled outage, potable water was secured at 0006 hours on 11/14/15.
November 14, 2015, IR 02588060 During the execution of Clearance Order #129314 and de-energized Circuit 302 per WO 1863079-06 for the recently scheduled outage, potable water was secured at 0006 hours on 11/14/15. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water sample throughout the duration of the Potable Water Outage that was restored to service at 2055 hours on 11 /14/15.
This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water sample throughout the duration of the Potable Water Outage that was restored to service at 2055 hours on 11 /14/15. November 18, 2015, IR 02589324 During the weekly checks of ODCM Water compositors on 11/15/15, at 12:35, CL-90 was found with its GFI 'tripped'.
November 18, 2015, IR 02589324 During the weekly checks of ODCM Water compositors on 11/15/15, at 12:35, CL-90 was found with its GFI 'tripped'. The breaker was reset but the GFI 'tripped' after the initial reset. There was standing water within the doghouse enclosure, which contributed to the GFI tripping both times.
The breaker was reset but the GFI 'tripped' after the initial reset. There was standing water within the doghouse enclosure, which contributed to the GFI tripping both times. Throughout 2015, the following IRs were generated to document Program exceptions that were entered into the corrective action program for trending purposes.
Throughout 2015, the following IRs were generated to document Program exceptions that were entered into the corrective action program for trending purposes.
Missed Samples May 13, 2015, IR 02500319 The ODCM air samplers CL-2 and CL-3 lost power on 05/06/15 (IR #02497332).
Missed Samples May 13, 2015, IR 02500319 The ODCM air samplers CL-2 and CL-3 lost power on 05/06/15 (IR
A portable generator was placed to supply power to CL-2 & CL-3 air monitoring stations.
      #02497332). A portable generator was placed to supply power to CL-2 & CL-3 air monitoring stations. The minimum sample volume was not reached for that sampling period.
The minimum sample volume was not reached for that sampling period. June 03, 2015, IR 02512981 While performing the weekly ODCM Surveillance on Wednesday, June 10, 2015 for the collection of particulate and iodine filters and cartridges, the sample collector noted that upon arrival at CL-7, the sample pump was not running. Instead of the typical run time of approximately 168 hours, the timer registered 2 hours and 6 minutes. The minimum volume was not reached for that sampling period. Page 18of138 June 13, 2015, IR 02515452 The ODCM air samplers CL-2 and CL-3 lost power some time on or before June 13, 2015 at 0230 hours when first observed by a Station Security Officer (IR #02514143).
June 03, 2015, IR 02512981 While performing the weekly ODCM Surveillance on Wednesday, June 10, 2015 for the collection of particulate and iodine filters and cartridges, the sample collector noted that upon arrival at CL-7, the sample pump was not running. Instead of the typical run time of approximately 168 hours, the timer registered 2 hours and 6 minutes. The minimum volume was not reached for that sampling period.
Both air sample stations now have back-up generator power, returning both sample stations to service. Minimum sample volume was not collected for that sampling period. July 29, 2015, IR 02534576 ---During the Weekly Sample Collection Surveillance it was discovered that the two (2) recently changed out Environmental DLRs for CL-51, placed there on June 25, 2015 as part of the 3rd . *** --* * --Quarter Exchange, were found-missing: -The adjacent farm culvert had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs, the PVC sample holder or the stanchion pole that it was connected to. August 20, 2015, IR 02546978 While performing the Weekly OCDM Surveillance on Wednesday, 08/26/15 for the collection of particulate filters and iodine cartridges, it was discovered that there was no electrical power to CL-8. Instead of the typical run time of approximately 168 hours, the timer registered 19 hours and 36 minutes. The minimum volume was not reached for that sample. September 24, 2015, IR 02560026 During the 4 1 h Quarter Exchange of Environmental DLRs, it was discovered the CL-46 dosimeters placed on 06/25/15 as part of the 3rd Quarter Exchange were found missing. The adjacent farm field had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs or the PVC sample holder, but the stanchion pole was found lying in the field. Program exceptions were reviewed to understand the causes of the exception and to return to ODCM sample compliance before the next sampling frequency period. The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation. Page 19of138 E. Program Changes There were no changes to the program in 2015. IV. Results and Discussion A. Aquatic Environment
Page 18of138
: 1. Surface Water Composite samples were taken hourly at three locations (CL-90, CL-91 and CL-99) on a monthly schedule and grab samples were taken monthly from one location (CL-13). The following analyses _ were performed.-
 
-----. --lodine-131 Monthly samples from location CL-90 were analyzed for 1-131 activity (Table C-1.1, Appendix C). No 1-131 was detected in any samples and the required LLD was met. Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.2, Appendix C). No tritium was detected in any samples and the required LLD was met. Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. 2. Drinking Water Monthly composite samples were taken hourly at one location (CL-14). The'following analyses were performed:
June 13, 2015, IR 02515452 The ODCM air samplers CL-2 and CL-3 lost power some time on or before June 13, 2015 at 0230 hours when first observed by a Station Security Officer (IR #02514143). Both air sample stations now have back-up generator power, returning both sample stations to service. Minimum sample volume was not collected for that sampling period.
Gross Beta Monthly samples were analyzed for concentrations of gross beta (Tables C-11.1, Appendix C). No Gross beta was detected in any of the samples. Page 20 of 138 .. .----"* *-*
July 29, 2015, IR 02534576
Tritium Monthly samples were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). No tritium was detected in any samples and the required LLD was met. lodine-131 Monthly samples from location CL-14 were analyzed for 1-131 activity (Table C-11.3, Appendix C). No 1-131 was detected in any samples and the required LLD was met. Gamma Spectrometry  
              -- - During the Weekly Sample Collection Surveillance it was discovered that the two (2) recently changed out Environmental DLRs for CL-51, placed there on June 25, 2015 as part of the 3rd .
* * *** ' Monthly samples Were ana.lyzed for gamma emitting nu elides (Table C-11.4, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. 3. Well Water Quarterly grab samples were collected at two locations (CL-7D and CL-12, consisting of CL-12R [a raw water sample from this well] and CL-12T [same well water, but after treatment and available for consumption]).
*** - ~-- - * * -- Quarter Exchange, were found-missing: -The adjacent farm field's-culvert had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs, the PVC sample holder or the stanchion pole that it was connected to.
The following analyses were performed:
August 20, 2015, IR 02546978 While performing the Weekly OCDM Surveillance on Wednesday, 08/26/15 for the collection of particulate filters and iodine cartridges, it was discovered that there was no electrical power to CL-8. Instead of the typical run time of approximately 168 hours, the timer registered 19 hours and 36 minutes. The minimum volume was not reached for that sample.
Tritium Samples from all locations were analyzed for tritium activity {Table C-111.1, Appendix C). No tritium was detected in any samples and the required LLD was met. Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. 4. Fish Fish samples comprised of carp, largemouth bass, bluegill, crappie and channel catfish were collected at two locations (CL-19 and CL-105) semiannually.
September 24, 2015, IR 02560026 1
The following analysis was performed: Page 21 of 138 Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. .5. Shoreline Sediment Aquatic shoreline sediment samples were collected at CL-78 and CL-105 semiannually.
During the 4 h Quarter Exchange of Environmental DLRs, it was discovered the CL-46 dosimeters placed on 06/25/15 as part of the 3rd Quarter Exchange were found missing. The adjacent farm field had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs or the PVC sample holder, but the stanchion pole was found lying in the field.
The following analysis was performed:
Program exceptions were reviewed to understand the causes of the exception and to return to ODCM sample compliance before the next sampling frequency period.
Gamma Spectrometry Shoreline  
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
*seaiment samples were analyzed for gamma emitting--*
Page 19of138
nuclides (Table C-V.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. B. Atmospheric Environment
 
: 1. Airborne a. Air Particulates Continuous air particulate samples were collected from 10 locations on a weekly basis. The 10 locations were separated into three groups: Group I represents locations within one mile of the CPS site boundary (CL-2, CL-3, CL-4, CL-6, CL-15 and CL-94); Group II represents the locations at an intermediate distance within one to five miles of CPS (CL-1, CL-7 and CL-8); and Group Ill represents the control location greater than five miles from CPS (CL-11). The following analyses were performed:
E. Program Changes There were no changes to the program in 2015.
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-Vl.1 and C-Vl.2 and Figure C-1, Appendix C). Detectable gross beta activity was observed at all locations.
IV. Results and Discussion A. Aquatic Environment
Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of CPS. The results from the On-Site locations (Group I) ranged from 7 to 43 E-3 pCi/m 3 with a mean of 19 E-3 Page 22 of 138
: 1. Surface Water Composite samples were taken hourly at three locations (CL-90, CL-91 and CL-99) on a monthly schedule and grab samples were taken monthly from one location (CL-13). The following analyses _
: b. pCi/m 3. The results from the Intermediate Distance location (Group II) ranged from 6 to 42 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Control locations (Group Ill) ranged from 7 to 36 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3. Comparison of the 2015 air particulate data with previous years' data indicate no measurable impact from the operation of CPS. In addition, a comparison of the weekly mean values for 2014 indicate no notable differences among the three groups. Gamma Spectrometry Weekly samples were composited quarterly and analyzed '*for gamma emitting nuclides (Table C-Vl.3, Appendix C). * -NcYplant produced*radionuclides were detected and all ----required LLDs were met. Airborne Iodine Continuous air samples were collected from 10 locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94) and analyzed weekly for 1-131 (Table C-Vll.1, Appendix C). All results were less than the MDC and the required LLD was met. 2. Terrestrial
were performed.- -                   ----. --                           .. .----"* *-*
: a. Milk Samples were collected from CL-116 biweekly May tnrough October to coincide with the grazing season, and monthly November through April. The following analyses were performed:
lodine-131 Monthly samples from location CL-90 were analyzed for 1-131 activity (Table C-1.1, Appendix C). No 1-131 was detected in any samples and the required LLD was met.
lodine-131 Milk samples were analyzed for concentrations of 1-131 (Table C-Vlll.1, Appendix C). lodine-131 was not detected in any of the samples. The required LLD was met. Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.2, Appendix C). Naturally occurring K-40 activity was found in all samples. Page 23 of 138 No plant produced radionuclides were detected and all required LLDs were met. b. Food Products Broad leaf vegetation samples were collected from four locations (CL-114, and CL-118) monthly June through September to coincide with the harvest season. The following analysis was performed:
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.2, Appendix C). No tritium was detected in any samples and the required LLD was met.
Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). No plant produced radionuclides were detected and all required----** *-0-LLDs were met. c. Grass Samples were collected from four locations (CL-1, CL-2, CL-8, and CL-116) biweekly May through October. The following analysis was performed:
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
: 2. Drinking Water Monthly composite samples were taken hourly at one location (CL-14). The'following analyses were performed:
Gross Beta Monthly samples were analyzed for concentrations of gross beta (Tables C-11.1, Appendix C). No Gross beta was detected in any of the samples.
Page 20 of 138
 
Tritium Monthly samples were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). No tritium was detected in any samples and the required LLD was met.
lodine-131 Monthly samples from location CL-14 were analyzed for 1-131 activity (Table C-11.3, Appendix C). No 1-131 was detected in any samples and the required LLD was met.
Gamma Spectrometry
* c~* * ***   ' Monthly samples Were ana.lyzed for gamma emitting nu elides (Table C-11.4, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
: 3. Well Water Quarterly grab samples were collected at two locations (CL-7D and CL-12, consisting of CL-12R [a raw water sample from this well]
and CL-12T [same well water, but after treatment and available for consumption]). The following analyses were performed:
Tritium Samples from all locations were analyzed for tritium activity {Table C-111.1, Appendix C). No tritium was detected in any samples and the required LLD was met.
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
: 4. Fish Fish samples comprised of carp, largemouth bass, bluegill, crappie and channel catfish were collected at two locations (CL-19 and CL-105) semiannually. The following analysis was performed:
Page 21 of 138
 
Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C).
No plant produced radionuclides were detected and all required LLDs were met.
  .5. Shoreline Sediment Aquatic shoreline sediment samples were collected at CL-78 and CL-105 semiannually. The following analysis was performed:
Gamma Spectrometry Shoreline *seaiment samples were analyzed for gamma emitting--*
nuclides (Table C-V.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
B. Atmospheric Environment
: 1. Airborne
: a. Air Particulates Continuous air particulate samples were collected from 10 locations on a weekly basis. The 10 locations were separated into three groups: Group I represents locations within one mile of the CPS site boundary (CL-2, CL-3, CL-4, CL-6, CL-15 and CL-94); Group II represents the locations at an intermediate distance within one to five miles of CPS (CL-1, CL-7 and CL-8); and Group Ill represents the control location greater than five miles from CPS (CL-11). The following analyses were performed:
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-Vl.1 and C-Vl.2 and Figure C-1, Appendix C).
Detectable gross beta activity was observed at all locations.
Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of CPS. The results from the On-Site locations (Group I) 3 ranged from 7 to 43 E-3 pCi/m with a mean of 19 E-3 Page 22 of 138
 
pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from 6 to 42 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3 . The results from the Control locations (Group Ill) ranged from 7 to 36 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3 . Comparison of the 2015 air particulate data with previous years' data indicate no measurable impact from the operation of CPS. In addition, a comparison of the weekly mean values for 2014 indicate no notable differences among the three groups.
Gamma Spectrometry Weekly samples were composited quarterly and analyzed
        '*for gamma emitting nuclides (Table C-Vl.3, Appendix C).
      * - NcYplant produced*radionuclides were detected and all --- -
required LLDs were met.
: b.      Airborne Iodine Continuous air samples were collected from 10 locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94) and analyzed weekly for 1-131 (Table C-Vll.1, Appendix C). All results were less than the MDC and the required LLD was met.
: 2. Terrestrial
: a.     Milk Samples were collected from CL-116 biweekly May tnrough October to coincide with the grazing season, and monthly November through April. The following analyses were performed:
lodine-131 Milk samples were analyzed for concentrations of 1-131 (Table C-Vlll.1, Appendix C). lodine-131 was not detected in any of the samples. The required LLD was met.
Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.2, Appendix C).
Naturally occurring K-40 activity was found in all samples.
Page 23 of 138
 
No plant produced radionuclides were detected and all required LLDs were met.
: b.           Food Products Broad leaf vegetation samples were collected from four locations (CL-114, CL~115, CL~117 and CL-118) monthly June through September to coincide with the harvest season. The following analysis was performed:
Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). No
              -~---***"  plant produced radionuclides were detected and all required- - -- ** *-0
                                                                                                  -
LLDs were met.
: c.           Grass Samples were collected from four locations (CL-1, CL-2, CL-8, and CL-116) biweekly May through October. The following analysis was performed:
Gamma Spectrometry Each grass sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.2, Appendix C). No plant produced radionuclides were detected and all required
Gamma Spectrometry Each grass sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.2, Appendix C). No plant produced radionuclides were detected and all required
* LLDs were met. C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing DLRs. Fifty-four DLR locations were established around the site. Results of DLR mea.surements are listed in Tables C-X.1 to C-X.3, Appendix C. A total of 214 OSLO measurements were made in 2015. The average dose from the inner ring was 23.4 mRem/quarter.
* LLDs were met.
The average dose from the outer ring was 23.8 mRem/quarter.
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing DLRs. Fifty-four DLR locations were established around the site. Results of DLR mea.surements are listed in Tables C-X.1 to C-X.3, Appendix C.
The average dose from the special interest group was 23.1 mRem/quarter.
A total of 214 OSLO measurements were made in 2015. The average dose from the inner ring was 23.4 mRem/quarter. The average dose from the outer ring was 23.8 mRem/quarter. The average dose from the special interest group was 23.1 mRem/quarter. The average dose from the supplemental group was 22.1 mRem/quarter. The quarterly measurements ranged from 17.3 to 28.0 mRem/quarter.
The average dose from the supplemental group was 22.1 mRem/quarter.
The inner ring and outer ring measurements compared well to the Control Station, CL-11, which ranged from 19.9 mRem/quarter to 23.6 Page 24 of 138
The quarterly measurements ranged from 17.3 to 28.0 mRem/quarter.
 
The inner ring and outer ring measurements compared well to the Control Station, CL-11, which ranged from 19.9 mRem/quarter to 23.6 Page 24 of 138 mRem/quarter with an average measurement of 21.9 mRem/quarter.
mRem/quarter with an average measurement of 21.9 mRem/quarter. A comparison of the Inner Ring and Outer Ring data to the Control Location data indicate that the ambient gamma radiation levels from all the locations were comparable. The historical ambient gamma radiation data from the control location were plotted along with similar data from the Inner and Outer Ring Locations (Figure C-2, Appendix C).
A comparison of the Inner Ring and Outer Ring data to the Control Location data indicate that the ambient gamma radiation levels from all the locations were comparable.
D. Land Use Survey A Land Use Survey conducted during the July through October 2015 growing season around the Clinton Power Station (CPS) was performed by Environmental Inc. (Midwest Labs) for Exelon to comply with Clinton's Offsite Dose Calculation Manual, section 8.0. The purpose of the survey was to document the nearest resident, milk producing animal and garden 2
The historical ambient gamma radiation data from the control location were plotted along with similar data from the Inner and Outer Ring Locations (Figure C-2, Appendix C). D. Land Use Survey E. A Land Use Survey conducted during the July through October 2015 growing season around the Clinton Power Station (CPS) was performed by Environmental Inc. (Midwest Labs) for Exelon to comply with Clinton's Offsite Dose Calculation Manual, section 8.0. The purpose of the survey was to document the nearest resident, milk producing animal and garden *of-greater than 538 m 2 in each of the sixteen 22 % degree sectors-around the site. The distance and direction of all locations from the CPS Station HVAC vent stack were positioned using Global Positioning System (GPS) technology.
  *of-greater than 538 m in each of the sixteen 22 % degree sectors-around the site. The distance and direction of all locations from the CPS Station HVAC vent stack were positioned using Global Positioning System (GPS) technology. There were no changes required to the CPS REMP as a result of the Land Use Survey. The results of this survey are summarized below.
There were no changes required to the CPS REMP as a result of the Land Use Survey. The results of this survey are summarized below. Distance in Kilometers from the CPS Station HVAC Vent Stack Sector Residence Garden Milk Animal (km) (km) (km) 1 N 1.5 1.5 1.5 2 NNE 1.5 1.5 >8 3 NE 2.1 3.5 >8 4 ENE 2.9 2.9 >8 5 E 1.7 1.7 >8 6 ESE 5.1 5.3 >8 7 SE 4.4 >8 >8 8 SSE 2.9 4.3 >8 9 s 4.8 4.8 6.6 10SSW 4.7 >8 5.5 11 SW 1.2 5.9 >8 12WSW 3.6 3.7 5.5 13W 2.0 3.2 >8 14WNW 2.6 2.6 >8 15NW 2.7 4.7 >8 16NNW 2.1 2.1 2.1 Errata Data There was no errata data for 2015. Page 25 of 138 F. Summary of Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of -air particulate, air iodine, milk, soil, vegetation and water matrices for 25 analytes (Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:
Distance in Kilometers from the CPS Station HVAC Vent Stack Sector       Residence         Garden       Milk Animal (km)             (km)           (km) 1 N               1.5             1.5             1.5 2 NNE             1.5             1.5             >8 3 NE             2.1             3.5             >8 4 ENE             2.9             2.9             >8 5 E               1.7             1.7             >8 6 ESE             5.1             5.3             >8 7 SE             4.4             >8             >8 8 SSE             2.9             4.3             >8 9 s               4.8             4.8             6.6 10SSW             4.7             >8             5.5 11 SW             1.2             5.9             >8 12WSW             3.6             3.7             5.5 13W               2.0             3.2             >8 14WNW             2.6             2.6             >8 15NW               2.7             4.7             >8 16NNW             2.1             2.1             2.1 E. Errata Data There was no errata data for 2015.
: 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TB E's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal -
Page 25 of 138
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 Acceptance Limits, as applicable.
F. Summary of     Results~  Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of
The acceptance limits are either determined by a regression equation speeific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
  -air particulate, air iodine, milk, soil, vegetation and water matrices for 25 analytes (Appendix D). The PE samples, supplied by Analytics Inc.,
3.* DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. The MAPEP defines three levels of performance:
Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:
Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/- 20% to +/- 30% of the reference value (i.e., 20% < bias< 30%). If the bias is greater than 30%, the results are deemed not acceptable.
: 1.     Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TB E's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal
For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria.
    - ----~--QC requirements,-which are based on-the DOE MAPEP criteria. -
Ten analyses (AP -Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water -Ni:-3, Sr-89, Sr-90, and U natural; Vegetation Page 26 of 138 Sr-90 samples) did not meet the specified acceptance criteria for the following reasons: -Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained 1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (acceptable with warning) was exceeded.
: 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 Perform~nce Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation speeific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the __
3.*     DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.
half .,.life (27. 7 :days) and the lowest.gamma energy_(320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations).
The MAPEP defines three levels of performance: Acceptable
This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable.
                  =                                        =
NCR 15-18 2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr .. 90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested st;imple utilized for analysis.
(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.
The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 -553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13 3. Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper acceptance range of 0.0202 Sq/sample.
For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria. Ten analyses (AP - Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water - Ni:-3, Sr-89, Sr-90, and U natural; Vegetation Page 26 of 138
Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered Page 27 of 138 acceptable.
 
MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233.
Sr-90 samples) did not meet the specified acceptance criteria for the following reasons:
Due to the extremely low activity, it was difficult to quantify the U-234/233.
        -     Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained
NCR 15-13 4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the. lower acceptance range of 0.53 Sq/sample.
: 1.           Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (acceptable with warning) was exceeded. The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the
The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard.
__ --*~ ----.~"""'- ~: ~- -~shortest half.,.life (27. 7:days) and the lowest.gamma energy_(320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations). This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable. NCR 15-18
The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency.
: 2.           Teledyne Brown Engineering's MAPEP March 2015 soil Sr.. 90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested st;imple utilized for analysis. The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -
When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and . --cannot escape to be-counted.--When the sample-media absorbs--the alpha particles this is known as self-absorption or attenuation.
1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 - 553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13
The calibration must include a similar configuration/media to correct for the attenuation.
: 3.           Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper acceptance range of 0.0202 Sq/sample. Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered Page 27 of 138
In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters. The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24 -1.53 Sq/sample.
 
Unlike the MAPEP samples, air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed.
acceptable. MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233. Due to the extremely low activity, it was difficult to quantify the U-234/233. NCR 15-13
NCR 15-13 5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21 6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample.
: 4.       Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the. lower acceptance range of 0.53 Sq/sample. The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and
In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for Page 28 of 138 the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.
  . - - cannot escape to be-counted.--When the sample-media absorbs- -
TBE will no longer analyze the air particulate through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21 7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the lower acceptance range of 0.91 Sq/sample.
the alpha particles this is known as self-absorption or attenuation.
In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incompl_ete removal of the isotope of interest for -the-laboratories analyi:ing-the:cross checks.' TBE suspects-thatthis maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.
The calibration must include a similar configuration/media to correct for the attenuation. In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters.
Results from previous performance evaluations were reviewed and shown to be acceptable.
The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24
NCR 15-21 8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively.
        - 1.53 Sq/sample. Unlike the MAPEP samples, air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed. NCR 15-13
The yields -were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09 10. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L. The technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the EIML laboratory, 90 of 94 analyses met the specified acceptance criteria.
: 5.       Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21
Four analyses (Water-Co-57, Fe-55; AP -Co-57; Soil -Sr-90) did not meet the specified acceptance criteria for the following reasons: 1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L. The reported value should have been 27.84, which would have Page 29 of 138 been evaluated as acceptable.
: 6.       Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for Page 28 of 138
A data entry error resulted in a non-acceptable result. 2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1,06 Sq/sample.
 
The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable.
the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity. TBE will no longer analyze the air particulate Sr~90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21
A data entry error resulted in a non-acceptable result. 3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed "-----:-c -low result.' -The reanalysis result of 352 Bq/kg fell within ":--acceptance criteria.
: 7.       Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the lower acceptance range of 0.91 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incompl_ete removal of the isotope of interest for
: 4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L. The known activity was below the routine laboratory detection limits for the available aliquot fraction.
      - the-laboratories analyi:ing-the:cross checks.' TBE suspects-thatthis maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.
Results from previous performance evaluations were reviewed and shown to be acceptable. NCR 15-21
: 8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively. The yields
      - were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09
: 10.     Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L.
The technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the EIML laboratory, 90 of 94 analyses met the specified acceptance criteria. Four analyses (Water- Co-57, Fe-55; AP - Co-57; Soil - Sr-90) did not meet the specified acceptance criteria for the following reasons:
: 1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L.
The reported value should have been 27.84, which would have Page 29 of 138
 
been evaluated as acceptable. A data entry error resulted in a non-acceptable result.
: 2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1,06 Sq/sample. The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.
: 3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed
      "-- - --   :-c - low result.' -The reanalysis result of 352 Bq/kg fell within ":- -
acceptance criteria.
: 4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L.
The known activity was below the routine laboratory detection limits for the available aliquot fraction.
V. References
V. References
: 1. American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," ANSI N545-1975. 2. Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).
: 1.         American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," ANSI N545-1975.
: 3. CPS 2014 Annual Radioactive Effluent Release Report. 4. "Environmental Radioactivity," M. Eisenbud, 1987 (E187). 5. "Natural Radon Exposure in the United States," Donald T. Oakley, U.S. Environmental Protection Agency. ORP/SID 72-1, June 1972. 6. Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960. 7. International Commission on Radiation Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, "Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977). Page 30 of 138
: 2.         Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).
: 3.         CPS 2014 Annual Radioactive Effluent Release Report.
: 4.         "Environmental Radioactivity," M. Eisenbud, 1987 (E187).
: 5.         "Natural Radon Exposure in the United States," Donald T. Oakley, U.S.
Environmental Protection Agency. ORP/SID 72-1, June 1972.
: 6.         Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960.
: 7.         International Commission on Radiation Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, "Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977).
Page 30 of 138
: 8. International Commission on Radiation Protection, Publication No. 39 (1984), "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".
: 8. International Commission on Radiation Protection, Publication No. 39 (1984), "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".
: 9. * "Radioactivity in the Environment:
: 9. * "Radioactivity in the Environment: Sources, Distribution and Surveillance," Ronald L. Kathren, 1984.
Sources, Distribution and Surveillance," Ronald L. Kathren, 1984. 10. National Council on Radiation Protection and Measurements, Report No. 22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52). 11. National Council on Radiation Protection and Measurements, Report No. 39, "Basic Radiation Protection Criteria," January 1971. --12. National Council on Radiation Protection and Measurements, Report No. 44, "Krypton-85 in the Atmosphere  
: 10. National Council on Radiation Protection and Measurements, Report No.
-Accumulation, Biological Significance, and Control Technology," July 1975. 13. National Council on Radiation Protection and Measurements, Report No. 91, "Recommendations on Limits for Exposure to Ionizing Radiation," June 1987. 14. National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," September 1987. 15. National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".
22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52).
: 16. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975. 17. United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry:
: 11. National Council on Radiation Protection and Measurements, Report No.
Environmental Applications, "Revision 1, July 1977. 18. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 OCFR Part 50, Appendix I, "Revision 1, October 1977. 19. United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979. 20. United States Nuclear Regulatory Commission, Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Page 31 of 138 Operations)  
39, "Basic Radiation Protection Criteria," January 1971.
-Effluent Streams and the Environment," Revision 1, February 1979. 21. Technical Specifications, Clinton Power Station, Unit No. 1, Docket No. 50-461, Office of Nuclear Reactor Regulation, 1986. Facility Operating License Number NPF-62. 22. . Clinton Power Station, Updated Safety Analysis Report. 23. Clinton-Power Station, Unit 1, Off-Site Dose Calculation Manual. Page 32 of 138
-- 12. National Council on Radiation Protection and Measurements, Report No.
.. -. -; ---._ : -:_ -.. APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT  
44, "Krypton-85 in the Atmosphere - Accumulation, Biological Significance, and Control Technology," July 1975.
: 13. National Council on Radiation Protection and Measurements, Report No.
91, "Recommendations on Limits for Exposure to Ionizing Radiation,"
June 1987.
: 14. National Council on Radiation Protection and Measurements, Report No.
93, "Ionizing Radiation Exposure of the Population of the United States,"
September 1987.
: 15. National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".
: 16. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.
: 17. United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, "Revision 1, July 1977.
: 18. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1OCFR Part 50, Appendix I, "Revision 1, October 1977.
: 19. United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program,"
Revision 1, November 1979.
: 20. United States Nuclear Regulatory Commission, Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Page 31 of 138
 
Operations) - Effluent Streams and the Environment," Revision 1, February 1979.
: 21. Technical Specifications, Clinton Power Station, Unit No. 1, Docket No.
50-461, Office of Nuclear Reactor Regulation, 1986. Facility Operating License Number NPF-62.
: 22. . Clinton Power Station, Updated Safety Analysis Report.
: 23. Clinton- Power Station, Unit 1, Off-Site Dose Calculation Manual.
Page 32 of 138
 
                                                                                  --
                      .. - . -; - - - ._ : -:_ - ..               - - .,, ,,...._-;- - --
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT  


==SUMMARY==
==SUMMARY==
Page 33 of 138 ----.,, ,,...._-;-
 
---
Page 33 of 138
Intentionally left blank Page 34 of 138 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
 
Intentionally left blank Page 34 of 138
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 j, INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M) i 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
CLINTON POWER STATION LOCATION OF FACILITY:
  . MEASUREMENT)                                                (LLD)                                                                  MEASUREMENTS SURFACE WATER            1-131                12                    <LLD       NA                                                     0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 j, INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF . MEASUREMENT)
H-3                  16          2000    <LLD         <LLD                                                   0 GAMMA                48 MN-54                              15      <LLD       <LLD                                                   0 C0-58                              15      <LLD         <LLD                                                   0 FE-59                              30      <LLD       <LLD                                                   0 C0-60                              15      <LLD         <LLD                                                   0 ZN-65                              30      <LLD         <LLD                                                   0 "U
SURF ACE WATER (PCI/LITER) "U Ill cc m (,.) U1 0 _,, (,.) ()'.) TYPES OF ANALYSIS PERFORMED 1-131 H-3 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 12 16 48 REQUIRED LOWER LIMIT OF DETECTION (LLD) 2000 15 15 30 15 30 15 LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE  
Ill cc m
<LLD NA <LLD <LLD <LLD <LLD  
(,.)
<LLD <LLD <LLD <LLD  
U1 0_,,                          NB-95                              15      <LLD         <LLD                                                   0
<LLD <LLD <LLD <LLD  
(,.)
<LLD <LLD i MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
()'.)
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015            i NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR CONTROL         LOCATION WITH IDGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 (UNITOF                  PERFORMED        PERFORMED  OF DETECTION RANGE       RANGE        RANGE        DISTANCE AND DIRECTION  REPORTED MEASUREMENT)                                              (LLD)                                                                  MEASUREMENTS SURFACE WATER            ZR-95                              30    <LLD         <LLD                                                   0 (PCI/LITER)
DEWITT COUNTY, IL THE CLINTON POWER STATION, 2015 i DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH IDGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
CS-134                              15    <LLD         <LLD                                                   0 CS-137                              18    <LLD         <LLD                                                   0 BA-140                              60    <LLD         <LLD                                                   0 LA-140                              15    <LLD         <LLD                                                   0 CE-144                              NA    <LLD         <LLD                                                   0 DRINKING WATER          GR-B                  12            4    <LLD         NA                                                     0 "U(PCI/LITER)
SURFACE WATER (PCI/LITER)
D.l (Q
DRINKING WATER "U(PCI/LITER)
CD VJ                          H-3                    4          2000    <LLD        NA                                                      0
D.l (Q CD VJ (j) 0 --" VJ CXl TYPES OF ANALYSIS PERFORMED ZR-95 CS-134 CS-137 BA-140 LA-140 CE-144 GR-B H-3 NUMBER OF ANALYSIS PERFORMED 12 4 REQUIRED LOWER LIMIT OF DETECTION (LLD) 30 15 18 60 15 NA 4 2000 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 
-
,. TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
(j) 0
-"
VJ CXl THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
                                                                                                          ,.
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NA.ME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NA.ME OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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             I-131                12                  <LLD        NA                                                      0 (PCJJLITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
GAMMA                12 MN-54                              15      <LLD        NA                                                      0 C0-58                              15    <LLD        NA                                                      0 FE-59                              30      <LLD        NA                                                      0 C0-60                              15      <LLD        NA,                                                    0 ZN-65                              30      <LLD        NA                                                      0 NB-95                              15      <LLD        NA                                                    0
DRINKING WATER (PCJJLITER) -u Dl (Q CD (.U ---i 0 -_,,. (.U Ol TYPES OF ANALYSIS PERFORMED I-131 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 NUMBER OF ANALYSIS PERFORMED 12 12 REQUIRED LOWER LIMIT OF DETECTION (LLD) 15 15 30 15 30 15 30 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE NA NA NA NA NA, NA NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMANNUAL  
-u Dl (Q
CD
(.U
-
---i 0
_,,.
(.U Ol ZR-95                             30     <LLD         NA                                                     0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
LOCATIONS LOCATION MEDIUM OR                 TYPES OF          NUMBER OF    REQU1RED  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           CS-134                              15      <LLD        NA                                                      0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
CS-137                             18      <LLD        NA                                                      0 BA-140                             60      <LLD        NA                                                      0 LA-140                             15      <LLD        NA                                                      0 CE-144                             NA      <LLD        NA                                                      0 WELL WATER              H-3                   12          2000    <LLD        NA                                                    0 (PCI/LITER)
DRINKING WATER (PCI/LITER)
GAMMA                 12 MN-54                               15      <LLD        NA                                                      0
WELL WATER (PCI/LITER)  
"'U Ill cc CD w
"'U Ill cc CD w OJ 0 -....>. w OJ TYPES OF ANALYSIS PERFORMED CS-134 CS-137 BA-140 LA-140 CE-144 H-3 GAMMA MN-54 C0-58 NUMBER OF ANALYSIS PERFORMED 12 12 REQU1RED LOWER LIMIT OF DETECTION (LLD) 15 18 60 15 NA 2000 15 15 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE NA NA NA NA NA NA NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
-
OJ 0                              C0-58                               15     <LLD         NA                                                     0
....>.
w OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 WELL WATER               FE-59                              30      <LLD        NA                                                      0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
C0-60                              15      <LLD        NA                                                      0 ZN-65                              30      <LLD        NA                                                      0
WELL WATER (PCI/LITER)  
)>
)> I C.11 "U m cc <D (,.) (.0 0 --+> (,.) CX> TYPES OF ANALYSIS PERFORMED FE-59 C0-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 NUMBER OF ANALYSIS PERFORMED REQUIRED LOWER LIMIT OF DETECTION (LLD) 30 15 30 15 30 15 18 60 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE NA NA NA NA NA NA NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
I C.11 NB-95                              15      <LLD        NA                                                      0 ZR-95                              30      <LLD        NA                                                      0 CS-134                              15      <LLD        NA                                                      0 CS-137                              18      <LLD        NA                                                      0 "U
m cc
<D
(,.)
(.0                          BA-140                              60      <LLD        NA                                                      0 0
--+>
(,.)
CX>
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION .                     DOCKET NUMBER:           50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION . DOCKET NUMBER: 50-461 LOCATION OF FACILITY:
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 (UNITOF                  PERFORMED        PERFORMED  OF DETECTION RANGE         RANGE       RANGE         DISTANCE AND DIRECTION   REPORTED j
DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
MEASUREMENT)                                              (LLD)                                                                  MEASUREMENTS
WELL WATER (PCI/LITER)
                                                                                                        "
FISH :P-(PCI/KG WET) O') "U Ill co CD .i:. 0 0 -n _,. w ()) TYPES OF ANALYSIS PERFORMED LA-140 CE-144 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 16 REQUIRED LOWER LIMIT OF DETECTION (LLD) 15 NA 130 130 260 130 260 NA LOCATIONS LOCATION MEAN(M) MEAN(M) MEAN(M) STATION# (F) (F) (F) NAME RANGE RANGE RANGE DISTANCE AND DIRECTION j " <LLD NA <LLD NA <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD " <LLD <LLD <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
WELL WATER              LA-140                              15    <LLD         NA                                                      0 (PCI/LITER)
CE-144                            NA       <LLD         NA                                                     0 FISH                    GAMMA                16
:P-(PCI/KG WET)              MN-54                              130      <LLD         <LLD                                                   0 O')
C0-58                              130      <LLD       <LLD                                                   0 FE-59                              260      <LLD         <LLD                                                   0 C0-60                              130    <LLD         <LLD                                                   0
                                                                                                        "
ZN-65                              260    <LLD         <LLD                                                   0 "U
Ill co CD
.i:.
0 0                            NB-95                              NA      <LLD         <LLD                                                   0
-n
_,.
w
())
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCA;noN WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 MEASURE.tvIBNT)                                            (LLD)                                                                  MEASUREMENTS FISH                    ZR-95                              NA      <LLD         <LLD                                                   0 (PCI/KG WET)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCA;noN WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASURE.tvIBNT)
CS-134                            130      <LLD         <LLD                                                   0 CS-137                            150      <LLD         <LLD                                                   0 BA-140                            NA      <LLD         <LLD                                                   0 LA-140                            NA      <LLD         <LLD                                                   0 CE-144                            NA      <LLD         <LLD                                                   0 SEDIMENT                GAMMA                  4 "1J(PCI/KG DRY)                MN-54                              NA      <LLD         <LLD               :i' I*                                   0 Dl
FISH (PCI/KG WET) SEDIMENT "1J(PCI/KG DRY) Dl (.Q m .j:>. ....>. 0 -....>. w 00 TYPES OF ANALYSIS PERFORMED ZR-95 CS-134 CS-137 BA-140 LA-140 CE-144 GAMMA MN-54 C0-58 NUMBER OF ANALYSIS PERFORMED 4 REQUIRED LOWER LIMIT OF DETECTION (LLD) NA 130 150 NA NA NA NA NA LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE :i' I* STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
(.Q m
.j:>.
-
....>.
0                              C0-58                              NA      <LLD        <LLD                                                  0
....>.
w 00 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH IDGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
LOCATIONS LOCATION            I 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 MEASUREJ\1ENT)                                            (LLD)                                                                  MEASUREMENTS SEDIMENT                FE-59                              NA      <LLD         <LLD                                                   0 (PCI/KG DRY)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH IDGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREJ\1ENT)
C0-60                              NA      <LLD         <LLD                                                   0 ZN-65                              NA      <LLD         <LLD                                                   0 NB-95                              NA      <LLD         <LLD                                                   0 ZR-95                              NA      <LLD         <LLD                                                   0 CS-134                            150    <LLD         <LLD                                                   0 CS-137                            180    <LLD         <LLD                                                   0
""CJ Q) cc CD N 0 ..... (;.) OJ SEDIMENT (PCI/KG DRY) TYPES OF ANALYSIS PERFORMED FE-59 C0-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 NUMBER OF ANALYSIS PERFORMED REQUIRED LOWER LIMIT OF DETECTION (LLD) NA NA NA NA NA 150 180 NA LOCATIONS LOCATION I MEAN(M) MEAN(M) MEAN(M) ' STATION# (F) (F) (F) NAME RANGE RANGE RANGE DISTANCE AND DIRECTION  
""CJ Q) cc CD
<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
~                            BA-140                            NA      <LLD         <LLD                                                   0 N
0
.....
(;.)
OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 :
CLINTON POWER STATION LOCATION OF FACILITY:
INDICATOR CONTROL        LOCATION WITH IDGHEST ANNUAL MEAN (M)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 : MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
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                LA-140                            NA       <LLD         <LLD                                                           0 (PCI/KG DRY)
SEDIMENT (PCI/KG DRY) AIR PARTICULATE
CE-144                            NA       <LLD         <LLD                                                           0 AIR PARTICULATE        GR-B                  514          JO      19          19          20            CL-3 INDICATOR                      0
:P-CE-3 PCI/CUMETER) c.o iJ Ill ca CD .i:.. w 0 __,, __. w OJ TYPES OF ANALYSIS PERFORMED LA-140 CE-144 GR-B GAMMA C0-60 NB-95 ZR-95 RU-103 RU-106 NUMBER OF ANALYSIS PERFORMED 514 40 INDICATOR LOCATIONS REQUIRED MEAN(M) LOWER LIMIT (F) OF DETECTION RANGE (LLD) NA <LLD NA <LLD JO 19 (462/462)
:P-CE-3 PCI/CUMETER)                                                       (462/462)   (52/52)     (50/50)       CLINTON'S SECONDARY ACCESS ROAD c.o                                                                        (6/43)     (7/36)       (9/43)       0.7 MILES NE OF SITE GAMMA                40 C0-60                              NA      <LLD        <LLD                                                            0 NB-95                              NA      <LLD        <LLD                                                          0 ZR-95                              NA      <LLD        <LLD                                                          0 RU-103                            NA      <LLD        <LLD                                                            0 iJ Ill ca CD
(6/43) NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD 19 (52/52) (7/36) <LLD <LLD <LLD <LLD <LLD* LOCATION WITH IDGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 20 (50/50) (9/43) STATION# NAME DISTANCE AND DIRECTION CL-3 INDICATOR NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 CLINTON'S SECONDARY ACCESS ROAD 0.7 MILES NE OF SITE 0 0 0 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
.i:..
w
__,,
0                             RU-106                            NA      <LLD        <LLD*                                                          0
__.
w OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 MEASURElv!ENT)                                             (LLD)                                                                  MEASUREMENTS AIR PARTICULATE         CS-134                              50      <LLD        <LLD                                                  0 (E-3 PCI/CU.METER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASURElv!ENT)
CS-137                              60      <LLD        <LLD                                                  0 CE-141                            NA      <LLD        <LLD                                                  0 CE-144                            NA      <LLD        <LLD                                                  0 AIR IODINE               GAMMA                514 (E-3 PCI/CUMETER)       I-131                              70      <LLD        <LLD                                                  0 MILK                     I-131                  19                  NA          <LLD                                                  0 (PCI/LITER)
AIR PARTICULATE (E-3 PCI/CU.METER)
GAMMA                 19 MN-54                             NA       NA           <LLD                                                   0 C0-58                              NA       NA           <LLD                                                   0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
AIR IODINE (E-3 PCI/CUMETER)
 
MILK (PCI/LITER)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
TYPES OF ANALYSIS PERFORMED CS-134 CS-137 CE-141 CE-144 GAMMA I-131 I-131 GAMMA MN-54 C0-58 NUMBER OF ANALYSIS PERFORMED 514 19 19 REQUIRED LOWER LIMIT OF DETECTION (LLD) 50 60 NA NA 70 NA NA LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD NA NA NA LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 '~
CLINTON POWER STATION LOCATION OF FACILITY:
INDICATOR CONTROL       LOCAfrION WITH HIGHEST ANNUAL MEAN (M)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCAfrION WITH HIGHEST ANNUAL MEAN (M) '' MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
LOCATIONS LOCATION            ''
MILK (PCIILITER) "U D> cc m C.11 0 --" (JJ 00 TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) FE-59 NA C0-60 NA ZN-65 NA NB-95 NA ZR-95 NA CS-134 _ 15 CS-137 18 BA-140 60 LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE NA <LLD NA <LLD NA <LLD .NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD MEAN(M) (F) RANGE i, ,. 1 1. STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING Tf,JE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ; NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
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 (UNITOF                  PERFORMED         PERFORMED   OF DETECTION RANGE        RANGE        RANGE          DISTANCE AND DIRECTION  REPORTED MEASUREMENT)                                                (LLD)                                   i,                              MEASUREMENTS
                                                                                                          ,.
MILK                    FE-59                             NA      NA           <LLD                                                    0 (PCIILITER)
C0-60                             NA      NA         <LLD                                                    0 ZN-65                             NA       NA          <LLD                                                    0 NB-95                             NA      .NA           <LLD                                                    0 ZR-95                             NA       NA          <LLD                                                    0 CS-134 _                           15     NA          <LLD                                                    0 CS-137                             18     NA          <LLD                                                    0 "U
D>
cc m
~                            BA-140                             60     NA           <LLD               1                                    0
-C.11 0
-"
(JJ 00 1.
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING Tf,JE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED
                                                                                                          ;
IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR     CONTROL     LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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                     LA-140                              15    NA          <LLD                                                    0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
CE-144                            NA      NA            <LLD                                                  0
MILK (PCI/LITER)  
)>VEGETATION                   GAMMA                48
)>VEGETATION (PCI/KG WET) N -u Dl cc CD (J) 0 -....>. w ()'.) TYPES OF ANALYSIS PERFORMED LA-140 CE-144 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 48 REQUIRED LOWER LIMIT OF DETECTION (LLD) 15 NA NA NA NA NA NA NA LOCATIONS MEAN(M) (F) RANGE NA NA <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
~ (PCI/KG WET)                 MN-54                             NA      <LLD        <LLD                                                    0 N
C0-58                             NA      <LLD          <LLD                                                  0 FE-59                             NA       <LLD         <LLD                                                   0 C0-60                              NA      <LLD         <LLD                                                   0 ZN-65                              NA      <LLD         <LLD                                                   0
-u Dl cc CD
~
-
(J) 0                              NB-95                              NA      <LLD         <LLD                                                   0
....>.
w
()'.)
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME.OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME.OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:            50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR CONTROL         LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 (UNITOF                 PERFORMED        PERFORMED  OF DETECTION RANGE        RANGE        RANGE        DISTANCE AND DIRECTION  REPORTED MEASUREMENT)                                               (LLD)                                                                  MEASUREMENTS VEGETATION             ZR-95                              NA      <LLD        <LLD                                                    0 (PCI/KG WET)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
I-131                              60    <LLD        <LLD                                                    0 CS-134                              60    <LLD        <LLD                                                    0
VEGETATION (PCI/KG WET) )> I _... (...) "'U Dl cc CD ::!'.JGRASS o (PCI/KG WET) -....>. (,,) OJ TYPES OF ANALYSIS PERFORMED ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 CE-144 GAMMA MN-54 NUMBER OF ANALYSIS PERFORMED 52 REQUIRED LOWER LIMIT OF DETECTION (LLD) NA 60 60 80 NA NA NA NA LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
)>
_...
I
(...)
CS-137                              80    <LLD        <LLD                                                    0 BA-140                            NA      <LLD        <LLD                                                    0 LA-140                            NA      <LLD        <LLD                                                    0 CE-144                            NA      <LLD        <LLD                                                    0
"'U Dl cc CD
::!'.JGRASS                   GAMMA                52
-
o (PCI/KG WET)
....>.
(,,)
OJ MN-54                               NA     <LLD         <LLD                                                   0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:            50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR CONTROL         LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
                                                                                                          !
GRASS (PCI/KG WET) )> I ...... ""'O Dl co CD Ol 0 --" (,.) Ol TYPES OF ANALYSIS PERFORMED C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 I-131 CS-134 NUMBER OF ANALYSIS PERFORMED REQUIRED LOWER LIMIT OF DETECTION (LLD) NA NA NA NA NA NA 60 60 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE ! STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
MEASUREMENT)                                              (LLD)                                                                  MEASUREMENTS GRASS                  C0-58                              NA      <LLD         <LLD                                                   0 (PCI/KG WET)
FE-59                              NA      <LLD         <LLD                                                   0 C0-60                              NA      <LLD         <LLD                                                   0
)>
......
I
~
ZN-65                              NA      <LLD         <LLD                                                   0 NB-95                              NA      <LLD         <LLD                                                   0 ZR-95                              NA      <LLD         <LLD                                                   0 I-131                              60      <LLD         <LLD                                                   0
""'O Dl co CD
~                            CS-134                              60      <LLD         <LLD                                                   0
-
Ol 0
-"
(,.)
Ol THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                      DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                            REPORTING PERIOD:        2015 '
CLINTON POWER STATION LOCATION OF FACILITY:
INDICATOR CONTROL        LOCATION WITH HIGHEST ANNUAL MEAN (M)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 ' INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
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 GRASS                  CS-137                              80      <LLD        <LLD                                                  0 (PCI/KG WET)
)> I ...... C.J1 -u Dl cc CD .!:>. <.O 0 -....>. w OJ GRASS (PCI/KG WET) DIRECT
BA-140                            NA      <LLD        <LLD                                                  0 LA-140                            NA      <LLD        <LLD                                                  0
)>
......
I C.J1 CE-144                            NA      <LLD        <LLD                                                  0 DIRECT RADIATION        DLR-QUARTERLY        214          NA      23.2        21.9        25.3          CL-51 INDICATOR              0 (MILLIREM/QTR.)                                                    (210/210)  (4/4)        (3/3)
(17.3/28.0) (19.9/23.6)  (24.3/26.3)  4.4MILESNW
-u Dl cc CD
.!:>.
-
<.O 0
....>.
w OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES


==SUMMARY==
==SUMMARY==
OF THE AMBIENT DOSIMETRY PROGRAM FOR CLINTON POWER STATION, 201S RESULTS IN UNITS OF MILLIREM/QUARTER  
OF THE AMBIENT DOSIMETRY PROGRAM FOR CLINTON POWER STATION, 201S RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATION LOCATION               SAMPLES PERIOD       PERIOD   PERIOD MEAN       PRE-OP MEAN ANALYZED MINIMUM MAXIMUM           +/-2 S.D.   +/- 2 S.D., ALL LOCATIONS INNER RING                 63     19.2       28.0   23.4 +/- 3.3 OUTER RING                 63     19.0       28.0   23.8 +/- 3.8         18.0 +/- 2.4 SPECIAL INTEREST           28     19.0       26.3   23.1 +/- 3.7 SUPPLEMENTAL               56     17.3       25.8   22.1 +/- 3.8 CONTROL                     4     19.9       23.6   21.9 +/- 3.0 INNER RING STATIONS - CL-01, CL-05, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42, CL-43, CL-44, CL-45, CL-46, CL-47, CL-48, CL-63 OUTER RING STATIONS - CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80, CL-81 SPECIAL INTEREST STATIONS - CL-37, CL-41, CL-49, CL-64, CL-65, CL-74, CL-75 SUPPLEMENTAL STATIONS - CL-02, CL-03, CL-04, CL-06, CL-07, CL-08, CL-114, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 CONTROL STATION - CL-11 C-24                                 Page 88 of 138
+/- 2 STANDARD DEVIATION LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN CONTROL 22.0 +/- 0.0 22.0 +/- 0.0 19.9 +/- 0.0 23.6 +/- 0.0 ANALYZED MINIMUM MAXIMUM +/-2 S.D. +/- 2 S.D., ALL LOCATIONS INNER RING 63 19.2 28.0 23.4  
 
+/- 3.3 OUTER RING 63 19.0 28.0 23.8 +/- 3.8 18.0 +/- 2.4 SPECIAL INTEREST 28 19.0 26.3 23.1 +/- 3.7 SUPPLEMENTAL 56 17.3 25.8 22.1 +/- 3.8 CONTROL 4 19.9 23.6 21.9  
FIGURE C-1 MEAN MONTHLY GROSS BETA CONCENTRATION IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CPS, 2015 0.052 0.047 0.042 0.037 M
+/- 3.0 INNER RING STATIONS -CL-01, CL-05, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42, CL-43, CL-44, CL-45, CL-46, CL-47, CL-48, CL-63 OUTER RING STATIONS -CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80, CL-81 SPECIAL INTEREST STATIONS -CL-37, CL-41, CL-49, CL-64, CL-65, CL-74, CL-75 SUPPLEMENTAL STATIONS -CL-02, CL-03, CL-04, CL-06, CL-07, CL-08, CL-114, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 CONTROL STATION -CL-11 C-24 Page 88 of 138 M E :::::: (.) c.. FIGURE C-1 M E AN MONTHLY GROSS BETA CONCENTRATION IN AIR PARTICULATE SA M PLES COLLECTED IN THE VICINITY OF CPS , 2015 0.052 0.0 4 7 0.042 0.037 0.032 0.027 0.022 0.017 0.012 0.007 0.002 -"-c,* c,* ts ts 0 v MONTH 1l!ll!!lll1ll PRE-OP (ALL SITES) _.,_2015 INDICATOR  
E
-+-2015 CONTROL C-25 Page 89 of 138 FIGURE C-2 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR) IN THE VIC I NITY OF CPS, 2015 50 45 40 35 E Q) 30 0::: E 25 20 15 10 QUARTER II PRE-OP 02015 indicator
::::::  0.032
* 2015 control C-26 Page 90 of 138 APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 91 of 138 Intentionally left blank Page 92 of 138 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF3) Identification Reported Known Ratio (c) MonthNear Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d) March 2015 E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 w E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A --* ---**--* ----. -E11184 AP Ce-141 pCi 107 85.0 1.26 w Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 Water Fe-55 pCi/L 1950 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 w Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143 125 1.14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 w Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1) Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A D-1 Page 93 of 138 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 2 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d) June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A -----, ,.. -:--. --.,,__ .. --.. ----" Zn-65 ... pCi/L *-392 353---.. 1.11 .-.A .. Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 *302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 -pCi/L __ 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A D-2 Page 94 of 138 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3) Identification Reported Known Ratio (c) MonthNear Number Matrix Nuclide Units Value (a) Value (b) TBE/Anal}'.tics Evaluation (d) December 2015 E11357 AP Ce-141 pCi 89.9 84.0 1.07 Cr-51 pCi 215 184 1.17 Cs-134 pCi 103 105 0.98 Cs-137 pCi 76.6 74.8 1.02 Co-58 pCi 76.2 71.9 1.06 Mn-54 pCi 91.4 94.4 0.97
(.)
* Fe-59 pCi 78.6 70.3 1.12 Zn-65 pCi 173 162 1.07 Co-60 pCi 138 139 0.99 E11422 AP Sr-89 pCi 98.0 96.9 1.01 Sr-90 pCi 10.0 14.0 0.71 E11356 Charcoal 1-131 pCi 74.9 75.2 1.00 E11358 Water Fe-55 pCi/L 2160 1710 1.26 E11353 Soil Ce-141 pCi/kg 252 222 1.14 Cr-51 pCi/kg 485 485 1.00 Cs-134 pCi/kg 319 277 1.15 Cs-137 pCi/kg 292 276 1.06 Co-58 pCi/kg 193 190 1.02 Mn-54 pCi/kg 258 250 1.03 Fe-59 pCi/kg 218 186 1.17 Zn-65 pCi/kg 457 429 1.07 Co-60 pCi/kg 381 368 1.04 (1) AP Cr-51 -Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable.
c..
NCR 15-18 (a) Teledyne Brown Engineering reported result. (b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) Ratio of Teledyne Brown Engineering to Analytics results. (d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1.20. W-Acceptable with 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. A A A A A A A A A A w A w A A A A A A A A A D-3 Page 95 of 138 TABLE D-2 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance Month/Year Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c) March 2015 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 -0.850 A Ni-63 Sq/L 2.5 (1) A Pu-238 Sq/L 0.0204 0.0089 (2) A Pu-239/240 Sq/L 0.9 0.8 0.582 -1.082 A 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314-582 A Sr-90 Sq/kg 286 653 487 -849 N (3) 15-RdF32 AP Sr-90 Sq/sample  
0.027 0.022 0.017 0.012 0.007 0.002
-0.0991 (1) A U-234/233 Sq/sample 0.0211 0.0155 0.0109 -0.0202 N (3) U-238 Sq/sample 0.095 0.099 0.069-0.129 A 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53 -3.01 N (3) Gr-S Sq/sample 0.7580 0.75 0.38 -.1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12 -9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 -11.93 w Co-57 Sq/sample  
              ~*  ~*  ~*  ~*
-0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 -7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample 0.999 1.08 0.76 -1.40 A Zn-65 Sq/sample  
            ")~  <l~ ~'if  ~  ~~
-0.108 (1) A September 2015 15-MaW33 Water Am-241 Sq/L 1.012 1.055 0. 739 -1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4) Pu-238 Sq/L 0.727 0.681 0.477 -0.885 A Pu-239/240 Sq/L 0.830 0.900 0.630-1.170 A 15-MaS33 Soil Ni-63 Sq/kg 635 682 477 -887 A Sr-90 Sq/kg 429 425 298 -553 A 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53 -2.83 N (4) U-234/233 Sq/sample 0.143 0.143 0.100-0.186 A U-238 Sq/sample 0.149 0.148 0.104-0.192 A 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 A Gr-S Sq/sample 1.34 1.56 0.78 -2.34 A 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06 -7.54 A Cs-137 Sq/sample 0.0002 (1) A Co-57 Sq/sample 8.01 6.62 4.63 -8.61 w Co-60 Sq/sample 4.97 4.56 3.19-5.93 A Mn-54 Sq/sample 8.33 7.68 5.38 -9.98 A Sr-90 Sq/sample 0.386 1.30 0.91 -1.69 N (4) (1) False positive test. Zn-65 Sq/sample 6.07 5.46 3.82-7.10 A (2) Sensitivity evaluation.
                                  -"-
(3) Soil Sr-90 -incomplete digestion of the sample resulted in low results; AP U-2341233  
ts~* ts~*    c,* ~* ~. ~* c,*
-extremely low activity was difficult to quantify AP Gr-A -the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21. (a) Teledyne Brown Engineering reported result. (b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) DOEIMAPEP evaluation:
                                                      ~ ~~ 0 v ~o ~<<;
A=acceptable, W=acceptable with warning, tvo1.94acceptable.
MONTH 1l!ll!!lll1ll PRE-OP (ALL SITES)
Page 96 of 138
_.,_ 2015 INDICATOR
--* TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 -71.2 Sr-90 pCi/L 28.0 41.9 30.8 -48.1 Ba-133 pCi/L 80.6 82.5 63.9 -90.8 Cs-134 pCi/L 71.7 75.7 61.8 -83.3 Cs-137 pCi/L 187 189 170 -210 Co-60 pCi/L 85.7 84.5 76.0 -95.3 Zn-65 pCi/L 197 203 183 -238 Gr-A pCi/L 26.1 42.6 22.1 -54.0 Gr-B pCi/L 28.8 32.9 21.3 -40.6 1-131 pCi/L 23.5 23.8 19.7 -28.3 U-Nat pCi/L 6.19 6.59 4.99 -7.83 H-3 pCi/L 3145 3280 2770 -3620 ---* ---November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 -42.5 Sr-90 pCi/L 29.3 31.1 22.7 -36.1 Ba-133 pCi/L 31.5 32.5 25.9 -36.7 Cs-134 pCi/L 59.65 62.3 50.6 -68.5 Cs-137 pCi/L 156 157 141 -175 Co-60 pCi/L 70.6 71.1 64.0 -80.7 Zn-65 pCi/L 145 126 113 -149 Gr-A pCi/L 38.2 51.6 26.9 -64.7 Gr-B pCi/L 42.0 36.6 24.1 -44.2 1-131 pCi/L 24.8 26.3 21.9-31.0 U-Nat pCi/L 146.90 56.2 45.7 -62.4 H-3 pCi/L 21100 21300 18700 -23400 ;;-(1) Yield on the high side of our acceptance range indicates possibility of calcium interference.
                              -+- 2015 CONTROL C-25                         Page 89 of 138
NCR 15-09 (2) Technician failed to dilute original sample. If di/ulted, the result would have been 57. 1, which tell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result. (b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) ERA evaluation:
 
A=acceptable.
FIGURE C-2 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR) IN THE VICINITY OF CPS, 2015 50 45 40 35 E
Reported result falls within the Warning Limits. NA=not acceptable.
Q) 0:::
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. Evaluation (c) N (1) N (1) A A A A A A A A A A A A A A A A A A A A N (2) A D-5 Page 97 of 138 TABLE D-4 ERA (a) STATISTICAL  
30 E
25 20 15 10 QUARTER II PRE-OP 02015 indicator
* 2015 control C-26                       Page 90 of 138
 
APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 91 of 138
 
Intentionally left blank Page 92 of 138
 
TABLE D-1               ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF3)
Identification                               Reported     Known         Ratio (c)
MonthNear             Number         Matrix   Nuclide       Units Value (a) Value (b)     TSE/Analytics Evaluation (d)
March 2015           E11181         Milk     Sr-89         pCi/L   88.9       97.2           0.91           A Sr-90         pCi/L   12.2       17.4           0.70           w E11182         Milk     1-131         pCi/L   61.3       65.1           0.94           A Ce-141         pCi/L   104         113           0.92           A Cr-51         pCi/L   265         276           0.96           A Cs-134         pCi/L   138         154           0.90           A Cs-137         pCi/L   205         207           0.99           A Co-58         pCi/L   178         183           0.97           A Mn-54         pCi/L   187         188           0.99           A Fe-59         pCi/L   182         177           1.03           A Zn-65         pCi/L   345         351           0.98           A Co-60         pCi/L   379         405           0.94           A
--* -- -**--* -- - -~ - .-
E11184         AP       Ce-141         pCi     107       85.0           1.26           w Cr-51           pCi   261         224           1.17           A Cs-134         pCi   74.6       77.0           0.97           A Cs-137         pCi   99.6         102           0.98           A Co-58           pCi   99.8         110           0.91           A Mn-54           pCi   99.2       96.9           1.02           A Fe-59           pCi     109         119           0.92           A Zn-65           pCi     188         183           1.03           A Co-60           pCi   200         201           1.00           A E11183         Charcoal 1-131           pCi   82.9       85.4           0.97           A E11185         Water     Fe-55         pCi/L   1950       1900           1.03           A June 2015             E11234         Milk     Sr-89         pCi/L   94.9       92.6           1.02           A Sr-90         pCi/L   14.3       12.7           1.13           A E11238         Milk     1-131         pCi/L   93.2       95.9           0.97           A Ce-141         pCi/L Not provided for this study Cr-51         pCi/L   349         276           1.26           w Cs-134         pCi/L   165         163           1.01           A Cs-137         pCi/L   143         125           1.14           A Co-58         pCi/L   82.0       68.4           1.20           A Mn-54         pCi/L   113         101           1.12           A Fe-59         pCi/L   184         151           1.22           w Zn-65         pCi/L   269         248           1.08           A Co-60         pCi/L   208         193           1.08           A E11237         AP       Ce-141         pCi Not provided for this study Cr-51           pCi   323         233           1.39         N (1)
Cs-134         pCi   139         138           1.01           A Cs-137         pCi   111         106           1.05           A Co-58           pCi   54.0       57.8           0.93           A Mn-54           pCi   96.8       84.9           1.14           A Fe-59           pCi   162         128           1.27           w Zn-65           pCi   198         210           0.94           A Co-60           pCi   178         163           1.09           A E11236         Charcoal 1-131           pCi   93.9         80           1.17           A D-1                                     Page 93 of 138
 
TABLE D-1                   ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 2 OF 3)
Identification                                                       Reported   Known     Ratio (c)
Month/Year               Number                         Matrix   Nuclide           Units   Value (a) Value (b) TSE/Analytics Evaluation (d)
June 2015                 E11238                         Water     Fe-55             pCi/L       1890     1790         1.06           A September 2015 E11289                                     Milk     Sr-89             pCi/L       95.7   99.1         0.97           A Sr-90             pCi/L       15.4     16.4       0.94           A E11290                         Milk     1-131             pCi/L       94.9   99.9         0.95           A Ce-141           pCi/L       228     213         1.07           A Cr-51             pCi/L       499     538         0.93           A Cs-134           pCi/L       208     212         0.98           A Cs-137           pCi/L       270     255         1.06           A Co-58             pCi/L       275     263         1.05           A Mn-54             pCi/L       320     290         1.10           A Fe-59             pCi/L       255     226         1.13           A
- - -- - , ,.. - :-- . --       .,,__ .. -- . -- - - ~ "           Zn-65 ...         pCi/L     *- 392     353---   .. 1.11         .-.A ..
Co-60             pCi/L       350     330         1.06           A E11292                         AP       Ce-141             pCi         104     85.1       1.22           w Cr-51             pCi         262     215         1.22           w Cs-134             pCi         86.1   84.6         1.02           A Cs-137             pCi         93     102         0.91           A Co-58             pCi         106     105         1.01           A Mn-54             pCi         117     116         1.01           A Fe-59             pCi         94.8     90.2       1.05           A Zn-65             pCi         160     141         1.13           A Co-60             pCi         146     132         1.11           A E11291                         Charcoal 1-131             pCi         85.9   81.7         1.05           A E11293                         Water     Fe-55             pCi/L       2090     1800         1.16           A E11294                         Soil     Ce-141           pCi/kg       209     222         0.94           A Cr-51           pCi/kg       463     560         0.83           A Cs-134           pCi/kg       231     221         1.05           A Cs-137           pCi/kg       311     344         0.90           A Co-58           pCi/kg       245     274         0.89           A Mn-54           pCi/kg       297     *302         0.98           A Fe-59           pCi/kg       248     235         1.06           A Zn-65           pCi/kg       347     368         0.94           A Co-60           pCi/kg       328     344         0.95           A December 2015             E11354                         Milk     Sr-89             pCi/L       96.2   86.8         1.11           A Sr-90         -   pCi/L __     14.8   12.5         1.18           A E11355                         Milk     1-131             pCi/L       95.1   91.2         1.04           A Ce-141           pCi/L       117     129         0.91           A Cr-51             pCi/L       265     281         0.94           A Cs-134           pCi/L       153     160         0.96           A Cs-137           pCi/L       119     115         1.03           A Co-58             pCi/L       107     110         0.97           A Mn-54             pCi/L       153     145         1.06           A Fe-59             pCi/L       117     108         1.08           A Zn-65             pCi/L       261     248         1.05           A Co-60             pCi/L       212     213         1.00           A D-2                                     Page 94 of 138
 
TABLE D-1                     ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3)
Identification                                                           Reported       Known           Ratio (c)
MonthNear                 Number                   Matrix           Nuclide             Units     Value (a)     Value (b)     TBE/Anal}'.tics Evaluation (d)
December 2015             E11357                   AP               Ce-141               pCi       89.9         84.0             1.07             A Cr-51                 pCi       215           184             1.17             A Cs-134               pCi         103           105             0.98             A Cs-137               pCi       76.6         74.8             1.02             A Co-58                 pCi       76.2         71.9             1.06             A Mn-54                 pCi       91.4         94.4             0.97             A
* Fe-59                 pCi       78.6         70.3             1.12             A Zn-65                 pCi         173           162             1.07             A Co-60                 pCi         138           139             0.99             A E11422                   AP               Sr-89                 pCi       98.0         96.9             1.01             A Sr-90                 pCi       10.0           14.0           0.71             w E11356                   Charcoal         1-131                 pCi       74.9         75.2             1.00             A E11358                   Water           Fe-55               pCi/L       2160         1710             1.26             w E11353                   Soil             Ce-141             pCi/kg       252           222             1.14             A Cr-51               pCi/kg       485           485             1.00             A Cs-134             pCi/kg       319           277             1.15             A Cs-137             pCi/kg       292           276             1.06             A Co-58               pCi/kg       193           190             1.02             A Mn-54               pCi/kg       258           250             1.03             A Fe-59               pCi/kg       218           186             1.17             A Zn-65               pCi/kg       457           429             1.07             A Co-60               pCi/kg       381           368             1.04             A (1) AP Cr Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable. NCR 15-18 (a) Teledyne Brown Engineering reported result.
(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) Ratio of Teledyne Brown Engineering to Analytics results.
(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1.20.
W-Acceptable with 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.
D-3                                                 Page 95 of 138
 
TABLE D-2                   DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)
Identification                                                         Reported       Known           Acceptance Month/Year               Number               Media           Nuclide*             Units     Value (a)     Value (b)             Range     Evaluation (c)
March 2015               15-MaW32             Water           Am-241               Sq/L         0.632         0.654         0.458 - 0.850       A Ni-63               Sq/L           2.5                               (1)           A Pu-238               Sq/L         0.0204       0.0089                 (2)           A Pu-239/240           Sq/L           0.9           0.8         0.582 - 1.082       A 15-MaS32             Soil             Ni-63               Sq/kg           392         448.0             314- 582         A Sr-90               Sq/kg           286           653             487 - 849       N (3) 15-RdF32             AP             Sr-90             Sq/sample -0.0991                                     (1)           A U-234/233         Sq/sample 0.0211               0.0155       0.0109 - 0.0202       N (3)
U-238           Sq/sample 0.095                 0.099         0.069- 0.129         A 15-GrF32             AP             Gr-A             Sq/sample         0.448         1.77           0.53 - 3.01     N (3)
Gr-S             Sq/sample       0.7580         0.75           0.38 -.1.13       A 15-RdV32             Vegetation Cs-134                 Sq/sample         8.08         7.32           5.12 - 9.52       A Cs-137           Sq/sample         11.6         9.18           6.43 - 11.93       w Co-57             Sq/sample -0.0096                                     (1)           A Co-60             Sq/sample         6.53         5.55           3.89 - 7.22       A Mn-54             Sq/sample 0.0058                                     (1)           A Sr-90             Sq/sample 0.999                 1.08           0.76 - 1.40       A Zn-65             Sq/sample -0.108                                     (1)           A September 2015 15-MaW33                       Water           Am-241               Sq/L         1.012         1.055         0. 739 - 1.372       A Ni-63                 Sq/L           11.8         8.55           5.99-11.12       N (4)
Pu-238               Sq/L         0.727         0.681         0.477 - 0.885       A Pu-239/240           Sq/L         0.830         0.900         0.630-1.170         A 15-MaS33             Soil           Ni-63               Sq/kg           635           682             477 - 887         A Sr-90               Sq/kg           429           425             298 - 553         A 15-RdF33             AP             Sr-90             Sq/sample         1.48         2.18             1.53 - 2.83     N (4)
U-234/233         Sq/sample         0.143         0.143         0.100- 0.186         A U-238             Sq/sample         0.149         0.148         0.104-0.192         A 15-GrF33             AP             Gr-A             Sq/sample         0.497         0.90           0.27 -1.53         A Gr-S             Sq/sample         1.34         1.56           0.78 - 2.34       A 15-RdV33             Vegetation Cs-134                 Sq/sample         6.10         5.80           4.06 - 7.54       A Cs-137           Sq/sample       0.0002                               (1)           A Co-57             Sq/sample         8.01         6.62             4.63 - 8.61       w Co-60             Sq/sample         4.97         4.56             3.19- 5.93         A Mn-54             Sq/sample         8.33         7.68             5.38 - 9.98       A Sr-90             Sq/sample         0.386         1.30           0.91 - 1.69     N (4)
(1) False positive test.                                       Zn-65             Sq/sample         6.07         5.46             3.82-7.10         A (2) Sensitivity evaluation.
(3) Soil Sr incomplete digestion of the sample resulted in low results; AP U-2341233 - extremely low activity was difficult to quantify AP Gr-A - the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21.
(a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, tvo1.94acceptable.
Page 96 of 138
 
TABLE D-3                       ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)
Identification                                                             Reported         Known         Acceptance Month/Year             Number                 Media             Nuclide             Units       Value (a)       Value (b)           Limits     Evaluation (c)
May 2015               RAD-101                 Water             Sr-89               pCi/L           45.2           63.2         51.1 - 71.2       N (1)
Sr-90               pCi/L           28.0           41.9         30.8 - 48.1       N (1)
Ba-133             pCi/L           80.6           82.5         63.9 - 90.8         A Cs-134               pCi/L           71.7           75.7         61.8 - 83.3         A Cs-137               pCi/L           187             189           170 - 210         A Co-60               pCi/L           85.7           84.5         76.0 - 95.3         A Zn-65               pCi/L           197           203             183 - 238         A Gr-A                 pCi/L           26.1           42.6         22.1 - 54.0         A Gr-B                 pCi/L           28.8           32.9         21.3 - 40.6         A 1-131               pCi/L           23.5           23.8           19.7 - 28.3       A U-Nat               pCi/L           6.19           6.59         4.99 - 7.83         A H-3                 pCi/L           3145           3280         2770 - 3620         A
--* --~- ---* -- -
November 2015         RAD-103                 Water             Sr-89               pCi/L           40.9           35.7         26.7 - 42.5         A Sr-90               pCi/L           29.3           31.1         22.7 - 36.1         A Ba-133               pCi/L           31.5           32.5         25.9 - 36.7         A Cs-134               pCi/L         59.65           62.3         50.6 - 68.5         A Cs-137               pCi/L           156             157           141 -175         A Co-60               pCi/L           70.6           71.1         64.0 - 80.7         A Zn-65               pCi/L           145             126           113 - 149         A Gr-A                 pCi/L           38.2           51.6         26.9 - 64.7         A Gr-B                 pCi/L           42.0           36.6         24.1 - 44.2         A 1-131               pCi/L           24.8           26.3         21.9- 31.0         A U-Nat               pCi/L         146.90           56.2         45.7 - 62.4       N (2)
H-3                 pCi/L         21100           21300       18700 - 23400         A
                                                                                                                                                            ;;-
(1) Yield on the high side of our acceptance range indicates possibility of calcium interference. NCR 15-09 (2) Technician failed to dilute original sample. If di/ulted, the result would have been 57. 1, which tell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.
D-5                                                     Page 97 of 138
 
3 TABLE D-4                       ERA (a) STATISTICAL  


==SUMMARY==
==SUMMARY==
PROFICIENCY TESTING PROGRAM 3 ENVIRONMENTAL, INC., 2015 (Page 1 of 1) Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result 0 Limits ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 -48.10 ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 -90.80 ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 -83.30 ERW-1448 04/06/15 Cs-137 -191.92 +/- 5.9 189 -170.00 -210.0 ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 -95.30 ERW-1448 04/06/15 Zn-65 -195.97 +/- 12.0 203 -183.00 -238.0 ERW-1450 04/06/15 Gr. Alpha 34.05 +/- 1.90 42.60 22.10 -54.00 ERW-1450 04/06/15 G. Beta 26.93 +/- 1.12 32.90 21.30 -40.60 ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19. 70 -28.30 ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 -3620 ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 -36.70 ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 -175.0 ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 -80.70 ERW-5531 10/05/15 Zn-65 -138.94 +/- 5.7 126 -113.00 -149.0 ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 -44.20 ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 -31.00 ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45.70 -62.40 ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 -23400.0
PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2015 (Page 1 of 1)
* 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.
Concentration (pCi/L)
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass *Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass as provided by ERA. Page 98 of 138 0-6 TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 1 of 2) Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 02/01/15 Ni-63 341 +/- 18 448 314 -582 Pass MAS0-975 02/01/15 Sr-90 523 +/- 12 653 457 -849 Pass MAS0-975 02/01/15 Cs-134 533 +/- 6 678 475 -881 Pass MAS0-975 02/01/15 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 02/01/15 Co-57 0.5 +/- 1 0.0 NA c Pass MAS0-975 02/01/15 Co-60 741 +/- 8 817 572 -1062 Pass MAS0-975 02/01/15 Mn-54 1, 153 +/- 9 1, 198 839 -1557 Pass MAS0-975 02/01/15 Zn-65 892 +/- 18 1064 745 -1383 Pass MAW-969 02/01/15 Am-241 0.650 +/- 0.078 0.654 0.458 -0.850 Pass MAW-969 02/01/15 Cs-134 21.09 +/- 0.25 23.5 16.5 -30.6 Pass MAW-969 02/01/15 Cs-137 19.63 +/- 0.34 19.1 13.4 -24.8 Pass MAW-969 d 02/01/15 Co-57 . --** 10.2 +/- 0.4 29.9 20.9 -38.9. Fail. MAW-969 02/01/15 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 02/01/15 H-3 569 +/- 13 563 394 -732 Pass MAW-969 02/01/15 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 02/01/15 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 02/01/15 Ni-63 2.9 +/- 3 0.00 NA c Pass MAW-969 02/01/15 Zn-65 16.54 +/- 0.85 18.3 12.8 -23.8 Pass MAW-969 02/01/15 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 02/01/15 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 02/01/15 Sr-90 9.40 +/- 1.30 9.48 6.64 -12.32 Pass MAW-950 02/01/15 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 02/01/15 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAAP-978 02/01/15 Cs-134 1.00 +/- 0.04 1.15 0.81 -1.50 Pass MAAP-978 02/01/15 Cs-137 0.004 +/- 0.023 0.00 NAC Pass MAAP-978 e 02/01/15 Co-57 0.04 +/- 0.04 1.51 1.06 -1.96 Fail MAAP-978 02/01/15 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 02/01/15 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978 02/01/15 Zn-65 0.83 +/- 0.10 0.83 0.58 -1.08 Pass MAAP-981 02/01/15 Sr-89 38.12 +/- 1.01 47.5 33.3 -61.8 Pass MAAP-981 02/01/15 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 02/01/15 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 02/01/15 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 02/01/15 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 02/01/15 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 02/01/15 Co-57 0.01 +/- 0.04 0.00 NAC Pass MAVE-972 02/01/15 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 02/01/15 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 02/01/15 Zn-65 0.09 +/- 0.12 0.00 NA c Pass Page 99 of 138 D-7 TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 2 of 2) Concentration a Known Lab Code b Date Analysis Laboratory result Activity MAS0-4903 08/01/15 Ni-63 556 +/- 18 682 MAS0-4903 f 08/01/15 Sr-90 231 +/- 7 425 MAS0-4903 f 08/01/15 Sr-90 352 +/- 10 425 MAS0-4903 08/01/15 Cs-134 833 +/- 10 1,010 MAS0-4903 08/01/15 Cs-137 808 +/- 11 809.00 MAS0-4903 08/01/15 Co-57 1,052 +/- 10 1, 180 MAS0-4903 08/01/15 Co-60 2 +/- 2 1.3 MAS0-4903 08/01/15 Mn-54 1,331 +/- 13 1,340 MAS0-4903 08/01/15 Zn-65 686 +/- 15 662 MAW-5007 08/01/15 Cs-134 16.7 +/- 0.4 23.1 MAW-5007 08/01/15 Cs-137 -0.36 +/- 0.13 0 MAW-5007 "08/01/15 21.8 +/- 0.4 20.8 MAW-5007 08/01/15 Co-60 17.3 +/- 0.3 17.1 MAW-5007 08/01/15 H-3 227.5 +/- 8.9 216 MAW-5007 g 08/01/15 Fe-55 4.2 +/- 14.1 13.1 MAW-5007 08/01/15 Mn-54 16.6 +/- 0.5 15.6 MAW-5007 08/01/15 Ni-63 9.1 +/- 2.6 8.55 MAW-5007 08/01/15 Zn-65 15.5 +/- 0.9 13.9 MAW-5007 08/01/15 Sr-90 4.80 +/- 0.50 4.80 MAW-5007 08/01/15 Gr. Alpha 0.41 +/- 0.04 0.43 MAW-5007 08/01/15 Gr. Beta 3.45 +/- 0.07 3.52 MAAP-4911 08/01/15 Sr-89 3.55 +/- 0.67 3.98 MAAP-4911 08/01/15 Sr-90 0.94 +/- 0.16 1.05 MAAP-4907 08/01/15 Gr. Alpha 0.30 +/- 0.04 0.90 MAAP-4907 08/01/15 Gr. Beta 1.85 +/- 0.09 1.56 MAVE-4901 08/01/15 Cs-134 5.56 +/- 0.16 5.80 MAVE-4901 08/01/15 Cs-137 -0.02 +/- 0.06 0.00 MAVE-4901 08/01/15 Co-57 7.74 +/- 0.18 6.62 MAVE-4901 08/01/15 Co-60 4.84 +/- 0.15 4.56 MAVE-4901 08/01/15 Mn-54 8.25 +/- 0.25 7.68 MAVE-4901 08/01/15 Zn-65 5.78 +/- 0.29 5.46 a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
Lab Code           Date           Analysis               Laboratory             ERA                     Control 0
Result b           Result                   Limits           Acceptance ERW-1444           04/06/15       Sr-89               59.71 +/- 5.44           63.20             51.10   - 71.20         Pass ERW-1444           04/06/15       Sr-90               43.41   +/- 2.43           41.90             30.80   - 48.10         Pass ERW-1448           04/06/15       Ba-133               77.75 +/- 4.69           82.50             69.30   - 90.80         Pass ERW-1448           04/06/15       Cs-134               68.82 +/- 3.08           75.70             61.80   - 83.30         Pass ERW-1448           04/06/15       Cs-137           -191.92   +/- 5.9             189           - 170.00   - 210.0         Pass ERW-1448           04/06/15       Co-60               85.05 +/- 4.59           84.50             76.00   - 95.30         Pass ERW-1448           04/06/15       Zn-65             -195.97   +/- 12.0           203           -183.00   - 238.0         Pass ERW-1450           04/06/15       Gr. Alpha           34.05 +/- 1.90           42.60             22.10   - 54.00         Pass ERW-1450           04/06/15       G. Beta             26.93 +/- 1.12           32.90             21.30   - 40.60         Pass ERW-1453           04/06/15       1-131               22.47 +/- 0.83           23.80             19. 70 - 28.30         Pass ERW-1456           04/06/15       Uranium               5.98 +/- 0.31           6.59               4.99 - 7.83         *Pass ERW-1461           04/06/15       H-3                 3,254 +/- 180           3280               2,770   - 3620           Pass ERW-5528           10/05/15       Sr-89               34.76 +/- 0.06           35.70             26.70   - 42.50         Pass ERW-5528           10/05/15       Sr-90               29.23 +/- 0.06           31.10             22.70   - 36.10         Pass ERW-5531           10/05/15       Ba-133               30.91 +/- 0.53           32.50             25.90   - 36.70         Pass ERW-5531           10/05/15       Cs-134               57.40 +/- 2.57           62.30             50.69   - 68.50         Pass ERW-5531           10/05/15       Cs-137           -163.12   +/- 4.8             157           -141.00   - 175.0         Pass ERW-5531           10/05/15       Co-60               73.41 +/- 1.72           71.10             64.00   - 80.70         Pass ERW-5531           10/05/15     Zn-65             -138.94   +/- 5.7             126           -113.00   - 149.0         Pass ERW-5534           10/05/15       Gr. Alpha           29.99 +/- 0.08           51.60             26.90   - 64.70         Pass ERW-5534           10/05/15       G. Beta             27.52 +/- 0.04           36.60             24.10   - 44.20         Pass ERW-5537           10/05/15       1-131               25.54 +/- 0.60           26.30             21.90   - 31.00         Pass ERW-5540           10/05/15       Uranium             53.30 +/- 0.55           56.20             45.70   - 62.40         Pass ERW-5543           10/05/15       H-3               21,260   +/- 351           21,300             18,700   - 23400.0       Pass
* 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.                                                                                           Page 98 of 138 0-6
 
TABLE D-5             DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
ENVIRONMENTAL, INC., 2015 (Page 1 of 2)
Concentration a Known             Control Lab Code b   Date       Analysis     Laboratory result         Activity         Limits c         Acceptance MAS0-975     02/01/15   Ni-63             341 +/- 18               448           314 - 582             Pass MAS0-975     02/01/15   Sr-90             523 +/- 12               653           457 - 849             Pass MAS0-975     02/01/15   Cs-134             533 +/-6                 678           475 - 881             Pass MAS0-975     02/01/15   Cs-137             0.8 +/- 2.5               0.0             NA c               Pass MAS0-975     02/01/15   Co-57               0.5 +/-1                 0.0             NA c               Pass MAS0-975     02/01/15   Co-60             741 +/-8                 817           572 - 1062             Pass MAS0-975     02/01/15   Mn-54           1, 153 +/-9               1, 198         839 - 1557             Pass MAS0-975     02/01/15   Zn-65             892 +/- 18             1064           745 - 1383             Pass MAW-969     02/01/15   Am-241         0.650   +/- 0.078           0.654       0.458 - 0.850           Pass MAW-969     02/01/15   Cs-134         21.09   +/- 0.25           23.5         16.5 - 30.6             Pass MAW-969     02/01/15   Cs-137         19.63   +/- 0.34             19.1         13.4 - 24.8             Pass MAW-969   d 02/01/15   Co-57     . --** 10.2 +/- 0.4             29.9         20.9 - 38.9.             Fail.
MAW-969     02/01/15   Co-60             0.02 +/- 0.05             0.00             NA c               Pass MAW-969     02/01/15   H-3               569 +/- 13               563           394 - 732             Pass MAW-969     02/01/15   Fe-55             6.00 +/- 6.60             6.88         4.82 - 8.94             Pass MAW-969     02/01/15   Mn-54             0.02 +/- 0.07             0.00             NA c               Pass MAW-969     02/01/15   Ni-63               2.9 +/-3                 0.00             NA c               Pass MAW-969     02/01/15   Zn-65           16.54   +/- 0.85             18.3         12.8 - 23.8             Pass MAW-969     02/01/15   Pu-238           0.02 +/- 0.03             0.01             NAe               Pass MAW-969     02/01/15   Pu-239/240       0.81 +/- 0.10             0.83         0.58 - 1.08           Pass MAW-969     02/01/15   Sr-90             9.40 +/- 1.30             9.48         6.64 - 12.32         Pass MAW-950     02/01/15   Gr. Alpha         0.66 +/- 0.05             1.07         0.32 - 1.81           Pass MAW-950     02/01/15   Gr. Beta         2.72 +/- 0.06             2.79         1.40 - 4.19           Pass MAAP-978     02/01/15   Cs-134           1.00 +/- 0.04             1.15         0.81 - 1.50             Pass MAAP-978     02/01/15   Cs-137         0.004   +/- 0.023           0.00             NAC                 Pass MAAP-978 e   02/01/15   Co-57             0.04 +/- 0.04             1.51         1.06 - 1.96             Fail MAAP-978     02/01/15   Co-60             0.01 +/- 0.02             0.00             NA c               Pass MAAP-978     02/01/15   Mn-54             1.11 +/- 0.08             1.02         0.71 - 1.33           Pass MAAP-978     02/01/15   Zn-65             0.83 +/- 0.10             0.83         0.58 - 1.08           Pass MAAP-981     02/01/15   Sr-89           38.12   +/- 1.01           47.5         33.3 - 61.8           Pass MAAP-981     02/01/15   Sr-90             1.22 +/- 0.13             1.06         0.74 - 1.38           Pass MAAP-984     02/01/15   Gr. Alpha         0.59 +/- 0.06             1.77         0.53 - 3.01           Pass MAAP-984     02/01/15   Gr. Beta         0.95 +/- 0.07             0.75         0.38 - 1.13           Pass MAVE-972     02/01/15   Cs-134           6.98 +/- 0.13             7.32         5.12 - 9.52             Pass MAVE-972     02/01/15   Cs-137           9.73 +/- 0.21             9.18         6.43 - 11.93           Pass MAVE-972     02/01/15   Co-57             0.01 +/- 0.04             0.00             NAC                 Pass MAVE-972     02/01/15   Co-60             3.89 +/- 0.20             5.55         3.89 - 7.22             Pass MAVE-972     02/01/15   Mn-54             0.04 +/- 0.07             0.00             NA c               Pass MAVE-972     02/01/15   Zn-65             0.09 +/- 0.12             0.00             NA c               Pass Page 99 of 138 D-7
 
TABLE D-5                     DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
ENVIRONMENTAL, INC., 2015 (Page 2 of 2)
Concentration a Known                 Control Lab Code   b       Date           Analysis           Laboratory result             Activity               Limits 0        Acceptance MAS0-4903           08/01/15       Ni-63                 556   +/- 18                   682               477 - 887            Pass MAS0-4903 f         08/01/15       Sr-90                 231   +/-7                     425               298 - 553              Fail MAS0-4903 f         08/01/15       Sr-90                 352   +/- 10                   425               298 - 553            Pass MAS0-4903           08/01/15       Cs-134                 833   +/- 10                 1,010             707 - 1313            Pass MAS0-4903           08/01/15       Cs-137                 808   +/- 11                 809.00             566 - 1052            Pass MAS0-4903           08/01/15       Co-57               1,052   +/- 10                 1, 180             826 - 1534            Pass 0
MAS0-4903           08/01/15       Co-60                     2 +/-2                     1.3                 NA                Pass MAS0-4903           08/01/15       Mn-54               1,331   +/- 13                 1,340             938 - 1742            Pass MAS0-4903           08/01/15       Zn-65                 686   +/- 15                   662               463 - 861            Pass MAW-5007           08/01/15       Cs-134               16.7   +/- 0.4                 23.1             16.2 - 30              Pass MAW-5007           08/01/15       Cs-137               -0.36   +/- 0.13                   0                  NA 0             Pass MAW-5007           "08/01/15       co~57                21.8   +/- 0.4                 20.8             14.6  -  27          Pass MAW-5007           08/01/15       Co-60                 17.3   +/- 0.3                 17.1               12  -  22.2        Pass MAW-5007           08/01/15       H-3                 227.5   +/- 8.9                 216               151  -  281          Pass MAW-5007 g         08/01/15       Fe-55                   4.2 +/- 14.1                 13.1               9.2  -  17            Fail MAW-5007           08/01/15       Mn-54                 16.6   +/- 0.5                 15.6             10.9  -  20.3        Pass MAW-5007           08/01/15       Ni-63                   9.1 +/- 2.6                 8.55             5.99  -  11.12        Pass MAW-5007           08/01/15       Zn-65                 15.5   +/- 0.9                 13.9               9.7  -  18.1        Pass MAW-5007           08/01/15       Sr-90                 4.80   +/- 0.50                 4.80             3.36  -  6.24          Pass MAW-5007             08/01/15       Gr. Alpha             0.41   +/- 0.04                 0.43             0.13  -  0.73          Pass MAW-5007             08/01/15       Gr. Beta             3.45   +/- 0.07                 3.52             1.76  -  5.28          Pass MAAP-4911           08/01/15       Sr-89                 3.55   +/- 0.67                 3.98             2.79  -  5.17        Pass MAAP-4911           08/01/15       Sr-90                 0.94   +/- 0.16                 1.05             0.74  -  1.37          Pass MAAP-4907           08/01/15       Gr. Alpha             0.30   +/- 0.04                 0.90             0.27  -  1.53          Pass MAAP-4907           08/01/15       Gr. Beta             1.85   +/- 0.09                 1.56             0.78  -  2.34          Pass MAVE-4901           08/01/15       Cs-134               5.56   +/- 0.16                 5.80             4.06 - 7.54            Pass MAVE-4901           08/01/15       Cs-137               -0.02   +/- 0.06                 0.00                 NA c              Pass MAVE-4901           08/01/15       Co-57                 7.74   +/- 0.18                 6.62             4.63  -  8.61          Pass MAVE-4901           08/01/15       Co-60                 4.84   +/- 0.15                 4.56             3.19  -  5.93          Pass MAVE-4901           08/01/15       Mn-54                 8.25   +/- 0.25                 7.68             5.38  -  9.98          Pass MAVE-4901           08/01/15       Zn-65                 5.78   +/- 0.29                 5.46             3.82  -  7.10        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).
b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).
Control Limits 0 477 -887 298 -553 298 -553 707 -1313 566 -1052 826 -1534 NA 0 938 -1742 463 -861 16.2 -30 NA 0 14.6 -27 12 -22.2 151 -281 9.2 -17 10.9 -20.3 5.99 -11.12 9.7 -18.1 3.36 -6.24 0.13 -0.73 1.76 -5.28 2.79 -5.17 0.74 -1.37 0.27 -1.53 0.78 -2.34 4.06 -7.54 NA c 4.63 -8.61 3.19 -5.93 5.38 -9.98 3.82 -7.10 0 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".
0 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.
MAPEP does not provide control limits. d Lab result was 27.84. Data entry_ error resulted in a non-acceptable result.
d Lab result was 27.84. Data entry_ error resulted in a non-acceptable result.
* Lab result was 1.58. Data entry error resulted in a non-acceptable result. f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.
* Lab result was 1.58. Data entry error resulted in a non-acceptable result.
Acceptance Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass g The known activity was below the routine laboratory detection limits for the available aliquot fraction.
f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.
Page 100 of 138 D-8 APPENDIX E ERRATA DATA *Page 101of138 Intentionally left blank Page 102of138 There is no errata data for 2015. Page 103of138 Intentionally left blank Page 1 04 of 138 APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR} Page 105of138 Intentionally left blank Page 106of138 Docket No: 50-461 l?OWIER. STATION Annual Radiological Groundwater Protection Program Report --------. -. . ----. ----------:----. -----<o-------.  
g The known activity was below the routine laboratory detection limits for the available aliquot fraction.             Page 100 of 138 D-8
---.__,,,_ ___ .--* ____ .,... -'> *-,,...------=--
 
-..__ *. ., January 1 through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services Clinton Power Station Clinton, IL 61727 April 2016 Page 107 of 138
APPENDIX E ERRATA DATA
* Intentionally left blank Page 108of138 Table Of Contents I. Summary and Conclusions
            *Page 101of138
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1 II. Introduction
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3 A Objectives of the RGPP ......................................................................................
There is no errata data for 2015.
3 8. Implementation of the Objectives
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3 C. Program Description
Intentionally left blank Page 1 04 of 138
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4 D. Characteristics of Tritium (H-3) ...........................................................................
APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR}
5 Ill. Program Description  
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5 A. Sample Analysis ....................................... , ..........................................................
Intentionally left blank Page 106of138
5 8. Data Interpretation  
 
........ -...... ........ -... :.: .................................................................  
Docket No:                50-461 Cl~NTON                      l?OWIER. STATION Annual Radiological Groundwater Protection Program Report
-. 6 _. __ :. -*-:. -:": .... --* _;;_----,. -.. :*::*::::  
- - - -- -- - -- - -    ------:-- -- . --~ - -- --<o----- --. . - .         . - -
.*:_:-.':-::*:*: .-:.:.  
                                                                *----...-----~-.**
.. *. ::-. ... ,:-_ ; = 1. Background Concentrations of Tritium ............................................
                                                                                          - ___ .-- .-* ____.,. .
: ........ 7 IV. Results and Discussion  
                                                                                    --- .__,,,_                  - '> *-,,...- - - - - -=-- --~-- - ~ ..__*. .,
.................................................................................................
January 1 through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services Clinton Power Station Clinton, IL 61727 April 2016 Page 107 of 138
9 A. Program Exceptions  
* Intentionally left blank Page 108of138
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9 8. Program Changes ...............................................................................................
Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 3 A Objectives of the RGPP ...................................................................................... 3
9 C. Groundwater Results ..........................................................................................
: 8. Implementation of the Objectives ........................................................................ 3 C. Program Description ........................................................................................... 4 D. Characteristics of Tritium (H-3) ........................................................................... 5 Ill. Program Description ...................................................................................................... 5 A. Sample Analysis ....................................... ,.......................................................... 5
9 D. Surface Water Results ...............................................................  
: 8. Data Interpretation ........-...... ~ ........-... :.: .................................................................-. 6
,, .....................
_.__ :. -*- :. -:": .... -- *_;;_----,. -t~:; sack9rduncfAil~i1ysis.~::-:~.: :~~-.. :*::*:::: .:'::.:.~.~--~:_:'.--'.*.-~_::::: :::~--.:-~ .*:_:-.':-::*:*: ~ .-:.:. '.~--~:.~:~..*. ::-. ::':~:::-*1 ~--...,:-_ ; =
11 E. Precipitation Water Results ...............................................................................
: 1. Background Concentrations of Tritium ............................................ :........ 7 IV. Results and Discussion ................................................................................................. 9 A. Program Exceptions ............................................................................................ 9
11 F. Recapture  
: 8. Program Changes ............................................................................................... 9 C. Groundwater Results .......................................................................................... 9 D. Surface Water Results ............................................................... ,, ..................... 11 E. Precipitation Water Results ............................................................................... 11 F. Recapture .......................................................................................................... 11 G. Summary of Results - Inter-laboratory Comparison Program .......................... 11 H. Errata Data .......................................................................................................... 11 I. Leaks, Spills, and Releases ......................................................................... ,...... 12 J. Trends ................................................, ................................................................ 12 K. Investigations ..................................................................................................... 12 L. Actions Taken ..................................................................................,.................. 12
..........................................................................................................
* Page 109of138
11 G. Summary of Results -Inter-laboratory Comparison Program ..........................
 
11 H. Errata Data ..........................................................................................................
Appendices Appendix A                           Location Designation of the Annual Radiological Groundwater Protection Program Report (ARGPPR)
11 I. Leaks, Spills, and Releases ......................................................................... , ...... 12 J. Trends ................................................ , ................................................................
* Tables
12 K. Investigations  
*Table A-1                          Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Figures Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Clinton Power Station,
.....................................................................................................
                                    ~015
12 L. Actions Taken .................................................................................. , ..................
    -.--.,,<-----~*--. _..,-.* __ : - ~ -- . , *-~--~-.-_:- : __ -. ,.. __ . . . . - _.,._ --*-- - -* ~--,....,,**---*  - .,,...,..,.__,........,c,.:-..:= _,--------- ....-- .,*-~-
12
Figure A-1                         Onsite Sampling Locations at Clinton Power Station Figure A-2                         Sampling Locations South of Clinton Power Station Figure A-3                         Sampling Locations East of Clinton Power Station Figure A-4                         Recapture Sampling Locations of Clinton Power Station Appendix B                         Data Tables of the Annual Radiological Groundwater Protection Program Report (ARGPPR)
* Page 109of138 Appendix A Tables *Table A-1 Figures Appendices Location Designation of the Annual Radiological Groundwater Protection Program Report (ARGPPR)
Tables Table 8-1.1                        Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.
* Radiological Groundwater Protection Program -Sampling Locations, Clinton Power Station, 2015 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Clinton Power Station,
Table 8-1.2                        Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.
_..,-.* __ : ---. ,
Table 8-1.3                        Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.
: __ -. , .. __ .... -_.,._ --*----*  
Table 8-11.1                        Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
-.,,...,..,.__,........,c,.:-..:=
Table    B~ll.2                    Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
_,---------
ii Page 110 of 138
.... --
 
Figure A-1 Figure A-2 Figure A-3 Figure A-4 Appendix B Tables Table 8-1.1 Table 8-1.2 Table 8-1.3 Table 8-11.1 Table Onsite Sampling Locations at Clinton Power Station Sampling Locations South of Clinton Power Station Sampling Locations East of Clinton Power Station Recapture Sampling Locations of Clinton Power Station Data Tables of the Annual Radiological Groundwater Protection Program Report (ARGPPR) Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. ii Page 110 of 138 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 Clinton Power Station (CPS). This evaluation involved numerous station personnel and contractor support personnel.
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 Clinton Power Station (CPS). This evaluation involved numerous station personnel and contractor support personnel. This report covers groundwater and surface water samples, collected outside of the Licensee required Off-Site Dose Calculation Manual (ODCM) requirements, both on and off station property in 2015. During that time period, 246 analyses were performed on 97 samples from 24 locations.
This report covers groundwater and surface water samples, collected outside of the Licensee required Off-Site Dose Calculation Manual (ODCM) requirements, both on and off station property in 2015. During that time period, 246 analyses were performed on 97 samples from 24 locations.
The monitoring was conducted in four phases.
The monitoring was conducted in four phases. In assessing all the data gathered for this report, it was concluded that the operation of CPS had no adverse radiological impact on the environment, and --the-re are no known-active-releases into the groundwater or surface water
In assessing all the data gathered for this report, it was concluded that the operation of CPS had no adverse radiological impact on the environment, and
__ -----CPS. No program changes occurred during the sampling year of 2015. 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 NUREG-1302 in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that the independent laboratory achieve a lower limit of detection 10 times lower than that required by the United States Environmental Protection Agency (USEPA) regulation.
  -- the-re are no known-active-releases into the groundwater or surface water at~, __ - -- - -
Strontium-89 was not detected in any samples. Strontium-90 was not detected in any samples. Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Background levels of tritium were detected at concentrations greater than the self-imposed LLD of 200 pCi/L in four of 17 groundwater monitoring locations.
CPS. No program changes occurred during the sampling year of 2015.
The tritium concentrations ranged from 176 +/- 106 pCi/L to 365 +/- 136 pCi/L. Tritium was not detected in any surface water. Precipitation samples were not analyzed during 2015. Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.
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 NUREG-1302 in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that the independent laboratory achieve a lower limit of detection 10 times lower than that required by the United States Environmental Protection Agency (USEPA) regulation.
Gross Beta (dissolved) was detected in 15 of 17 groundwater locations.
Strontium-89 was not detected in any samples. Strontium-90 was not detected in any samples.
The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations. Page 111 of 138 Hard-To-Detect analyses were performed on two groundwater locations.
Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Background levels of tritium were detected at concentrations greater than the self-imposed LLD of 200 pCi/L in four of 17 groundwater monitoring locations. The tritium concentrations ranged from 176 +/-
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 analyzed were not found at concentrations greater than their respective MDCs. Page 112of138 II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois.
106 pCi/L to 365 +/- 136 pCi/L. Tritium was not detected in any surface water.
CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on 15 February 1987. The site encloses approximately 13,730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated -on approximately 150 The cooling water discharge flume, which discharges to the eastern arm of the lake, occupies an additional 130 acres. Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13, 730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Ann_a Townships. --**-. __ ,,__,,, ___ -. ---This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015. A. Objectives of the Radiological Groundwater Protection Program (RGPP) The long-term objectives of the RGPP are as follows: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources. 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain knowledge of flow patterns on the surface and shallow subsurface.
Precipitation samples were not analyzed during 2015.
* 3. Perform routine water sampling and radiological analysis of water from selected locations.
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations. Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations.
: 4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner. 5. Regularly assess analytical results to identify adverse trends. 6. Take necessary corrective actions to protect groundwater resources.
Page 111 of 138
: 8. Implementation of the Objectives The objectives identified have been implemented at Clinton Power Station as discussed below: Page 113of138
 
: 1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public in station specific reports. 2. The Clinton Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
Hard-To-Detect analyses were performed on two 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 analyzed were not found at concentrations greater than their respective MDCs.
Page 112of138
 
II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on 15 February 1987. The site encloses approximately 13,730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated -on approximately 150 acres~ The cooling water discharge flume, which discharges to the eastern arm of the lake, occupies an additional 130 acres.
Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13, 730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Ann_a Townships.
                                                            **-. __ ,,__,,, ___ -. - - *~-- - - -
This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015.
A. Objectives of the Radiological Groundwater Protection Program (RGPP)
The long-term objectives of the RGPP are as follows:
: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
: 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain knowledge of flow patterns on the surface and shallow subsurface.                                                             *
: 3. Perform routine water sampling and radiological analysis of water from selected locations.
: 4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
: 5. Regularly assess analytical results to identify adverse trends.
: 6. Take necessary corrective actions to protect groundwater resources.
: 8. Implementation of the Objectives The objectives identified have been implemented at Clinton Power Station as discussed below:
Page 113of138
: 1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public in station specific reports.
: 2. The Clinton Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
: 3. Clinton Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
: 3. Clinton Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
: 4. Clinton Power Station has implemented new procedures to identify report rrew leaks,-spiils, o*r*otlier detections with potential*
: 4. Clinton Power Station has implemented new procedures to identify
radiological significance in a timely manner. 5. Clinton Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends. C. Program Description
        ~-and report rrew leaks,-spiils, o*r*otlier detections with potential*
: 1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1, A-2, A-3, and A-4 Appendix A. Groundwater, Surface Water and Precipitation Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Groundwater, surface water, and precipitation water are collected.
radiological significance in a timely manner.
Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures.
: 5. Clinton Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial by the contractor.
C. Program Description
Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to Page 114of138 hydrogeologic conditions.
: 1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1, A-2, A-3, and A-4 Appendix A.
D. Characteristics of Tritium (H-3) Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen.
Groundwater, Surface Water and Precipitation Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Groundwater, surface water, and precipitation water are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial revi~w by the contractor.
The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.
Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to Page 114of138
Tritiated water behaves the same as ordinary water in both the environment and the body. 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, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period. Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules.
hydrogeologic conditions.
Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless.
D.     Characteristics of Tritium (H-3)
Tritiated water behaves chemically and physically like tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.
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." The chemical properties of tritium are essentially those of ordinary hydrogen.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron).
Tritiated water behaves the same as ordinary water in both the environment and the body. 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
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 beta 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.
            * -clearance rate-characterized by*an effective biological half-life-of.about-14 *' - ; --
* Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Clinton Page 115 of 138 Power Station RGPP in 2015. In order to achieve the stated objectives, the current program includes the following analyses:
days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.
: 1. Concentrations of gamma emitters in groundwater and surface water. 2. Concentrations of strontium in groundwater.
Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. 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.
: 3. Concentrations of tritium in groundwater and surface water. 4. Concentrations of gross alpha and gross beta in groundwater.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). 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 beta 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.
5." ---; -Concentrations of-Am-241-in groundwater.  
Ill.
-6. Concentrations of Cm-242 and Cm-243/244 in groundwater.
* Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Clinton Page 115 of 138
: 7. Concentrations of Pu-238 and Pu-239/240 in groundwater.
 
: 8. Concentrations of U-234, U-235 and U-238 in groundwater.
Power Station RGPP in 2015.
: 9. Concentrations of Fe-55 in groundwater.
In order to achieve the stated objectives, the current program includes the following analyses:
: 10. Concentrations of Ni-63 in groundwater.
: 1.         Concentrations of gamma emitters in groundwater and surface water.
B. Data Interpretation The radiological data collected prior to Clinton Power Station becoming operational were used as a baseline with which these operational data were compared.
: 2.         Concentrations of strontium in groundwater.
For the purpose of this report, Clinton Power Station was considered operational at initial criticality.
: 3.         Concentrations of tritium in groundwater and surface water.
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) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.
: 4.         Concentrations of gross alpha and gross beta in groundwater.
: 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. Page116of138 Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence.
5." ---; - Concentrations of-Am-241-in groundwater. -
The convention is to report results with a 95% level of confidence.
: 6.         Concentrations of Cm-242 and Cm-243/244 in groundwater.
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) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated.
: 7.         Concentrations of Pu-238 and Pu-239/240 in groundwater.
Exelon reports the TPU by following the result with plus
: 8.         Concentrations of U-234, U-235 and U-238 in groundwater.
: 9.         Concentrations of Fe-55 in groundwater.
: 10.       Concentrations of Ni-63 in groundwater.
B. Data Interpretation The radiological data collected prior to Clinton Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Clinton Power Station 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) 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.
Page116of138
 
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) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus
* or minus+/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.
* or minus+/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.
Analytical uncertainties are reported at the 95% confidence level in --** -*this report for reporting consistency With the AREOR.--* Gamma spectroscopy results for each type of sample were grouped as follows: For groundwater and surface water 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.
Analytical uncertainties are reported at the 95% confidence level in
C. Background Analysis Pre-operational Radiological Environmental Monitoring Program operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, milk, and vegetation.
  -- **   -*this report for reporting consistency With the AREOR.-          .,~- -*
The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Clinton Power Nuclear Power Station, Illinois Power Company, Annual Report 1987, May 1988. The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater.
Gamma spectroscopy results for each type of sample were grouped as follows:
: 1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. a. Tritium Production Tritium is created in the environment from naturally occurring Page 117 of 138 processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and 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.
For groundwater and surface 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.
A major anthropogenic source of tritium and strontium-90  
C. Background Analysis Pre-operational Radiological Environmental Monitoring Program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, milk, and vegetation. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Clinton Power Nuclear Power Station, Illinois Power Company, Annual Report 1987, May 1988.
.. _;******comes from the former atmo*spheric*testing of-thermonuclear  
The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater.
* *
: 1.       Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.
* 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.
: a.     Tritium Production Tritium is created in the environment from naturally occurring Page 117 of 138
The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
 
: b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides.
processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and 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.
Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database.
A major anthropogenic source of tritium and strontium-90
GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006. RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline Jp until 1975, followed by. a gradual decline that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Page 118 of 138
.:.~.. _;******comes from the former atmo*spheric*testing of-thermonuclear * * *~*~'---
: c. Surface Water Data Tritium concentrations are routinely measured in Clinton Lake. According to the USEPA, surface water data typically has an uncertainty+/-
* 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.
70 to 100 pCi/L 95% confidence bound on each given measurement.
: b.           Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006.
Therefore, the typical background data provided may be subject to measurement uncertainty of approximately  
RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline Jp until 1975, followed by. a gradual decline sine~ that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above.
+/- 70 to 100 pCi/L. The radio-analytical laboratory is counting tritium results to an Exelon specified 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.
Page 118 of 138
: c. Surface Water Data Tritium concentrations are routinely measured in Clinton Lake.
According to the USEPA, surface water data typically has an uncertainty+/- 70 to 100 pCi/L 95% confidence bound on each given measurement. Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.
The radio-analytical laboratory is counting tritium results to an Exelon specified 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. Program Exceptions
IV. Results and Discussion A. Program Exceptions
: 1. Sample Anomalies There were no samples anomalies in 2015. 2. Missed Samples There were no missed samples in 2015. B. Program Changes There were no sampling program changes in 2015. C. Groundwater Results Groundwater Baseline samples were collected from off-site wells during four (4) phases at the station. Analytical results are discussed below. No anomalies were noted during the year. Page 119 of 138 Tritium Samples from 17 locations were analyzed for tritium activity (Table B-1.1 Appendix B). Tritium values ranged from below the Exelon imposed LLD of 200 pCi/I to 365 pCi/I. Strontium Strontium-89 was not detected in any of the 17 samples analyzed and the required LLD of 10 pCi/L was met. Strontium-90 was also not detected in any of the 17 samples analyzed and the required LLD of 1 pCi/L was met. (Table B-1.1 Appendix B). Gross Alpha and Gross Beta (dissolved and suspended)
: 1. Sample Anomalies There were no samples anomalies in 2015.
: 2. Missed Samples There were no missed samples in 2015.
B. Program Changes There were no sampling program changes in 2015.
C. Groundwater Results Groundwater Baseline samples were collected from off-site wells during four (4) phases at the station. Analytical results are discussed below. No anomalies were noted during the year.
Page 119 of 138
 
Tritium Samples from 17 locations were analyzed for tritium activity (Table B-1.1 Appendix B). Tritium values ranged from below the Exelon imposed LLD of 200 pCi/I to 365 pCi/I.
Strontium Strontium-89 was not detected in any of the 17 samples analyzed and the required LLD of 10 pCi/L was met. Strontium-90 was also not detected in any of the 17 samples analyzed and the required LLD of 1 pCi/L was met. (Table B-1.1 Appendix B).
Gross Alpha and Gross Beta (dissolved and suspended)
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed oh groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed oh groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.
Gross Beta (dissolved) was detected in 15 of 17 groundwater locations.
Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L.
The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B). Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-1.2, Appendix B). Hard-To-Detect Hard-To-Detect analyses were performed on two groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs. Occasionally, the isotopes of U-234 and U-238 are detected at low levels and indistinguishable from background (Table B-1.3 Appendix B). Page 120 of 138 D. Surface Water Results Surface Water Baseline samples were collected from on-site surface waters during four (4) phases at the station. Analytical results are discussed belo.w. No anomalies were noted during the year. Tritium Samples from seven locations were analyzed for tritium activity -(Table B-11.1 Appendix B). Tritium was not detected at concentrations greater than the LLD. --* * -. ---... '" *-*-*-*. --Strontium****-**  
Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B).
*-* . .--' ---' _,, .... *  
Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-1.2, Appendix B).
* -*--**--.* -*--Strontium was not analyzed in 2015 (Table B-11.1 Appendix B). Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-11.2, Appendix B). E. Precipitation Water Reirnlts Precipitation Water Precipitation water samples were not collected during 2015. F. Recapture Recapture samples were not required in 2015. G. Summary of Results -Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report. H. Errata Data The 2014 ARGPP incorrectly reported 607 analyses in the Summary and Conclusion section. The number of analyses in 2014 should have been , reported as 253 (IR 02635324). Page 121of138 I. Leaks, Spills, and Releases No leaks, spills or releases were identified during the year. J. Trends MW-CL-14S had a slight trend upward from <200 pCi/L to 241, 300 and 365 pCi/L respectively in 2015. However, the 1st Quarter of 2016 revealed MW-CL-14S has trended back to 218 pCi/L. Additionally, MW-CL-21S, after it too experienced a slight trend from 219 pCi/L to 287 pCi/L in 2015, has now had consecutive values of 189 pCi/L in the 4th Quarter of 2015 and 191 pCi/L from our 1st Quarter of 2016. All sampling well locations are currently indicating tritium levels that are less than the ODCM LLD of 2,000 pCi/I. All wells will continue to be sampled in accordance with the RGPP in 2016 .. K. Investigations Currently no investigations are on-going.
Hard-To-Detect Hard-To-Detect analyses were performed on two groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.
L. Actions Taken 1. Compensatory Actions There have been no station events requiring compensatory actions at the Clinton Power Station in 2015. 2. Installation of Monitoring Wells No new wells were installed during the 2015. 3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes. Page 122of138 APPENDIX A LOCATION DESIGNATION OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT {ARGPPR) Page 123of138 Intentionally left blank Page 124of138 TABLEA-1:
Occasionally, the isotopes of U-234 and U-238 are detected at low levels and indistinguishable from background (Table B-1.3 Appendix B).
Radiological Groundwater Protection Program -Sampling Locations, Clinton Power Station, 2015 Site B-3 MW-CL-1 MW-CL-2 MW-CL-121 MW-CL-131 MW-CL-13S MW-CL-14S MW-CL-151 MW-CL-15S MW-CL-16S MW-CL-17S MW-CL-181 MW-CL-18S MW-CL-19S MW-CL-20S MW-CL-21S MW-CL-22S Sewage Treatment Plant ----SW-CL-1 SW-CL-2 SW-CL-4 SW-CL-5 SW-CL-6 SW-CL-7 Site Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water A-1 Page 125of138 
Page 120 of 138
. ,, , *. , *. <l A-2 Page 126of138 c .Q ro U5 '--(]) 3 0 Cl. c 0 c ...... u 1-<( co (]) (f) *-co LL u 0 _J Cl) c Q_ E co (/) 2 *;n c 0
 
)> I (,.) ""CJ Q) <O CD N --.,J MW-1. 0 100 200 ---===--=:=::J Fee t
D.       Surface Water Results Surface Water Baseline samples were collected from on-site surface waters during four (4) phases at the station. Analytical results are discussed belo.w. No anomalies were noted during the year.
......  
Tritium Samples from seven locations were analyzed for tritium activity
...... CXl Figure A-2 Sampling Locations South of Clinton Pow er Station   
                              -   (Table B-11.1 Appendix B). Tritium was not detected at concentrations greater than the LLD.
"'O Dl (0 _.. N Ol 0 -_.. w Ol 0 1 00 200 Feet Sampling Loe f Figure A -3 a ions East of er inton Powe r Station
*-~ --* * -. ---... '" *-*-*-*. --Strontium****-** *- * . .- - ' -- -' _,,.... * *--------~~---,------ * - *-- **--.* -*--
--":-. -.
Strontium was not analyzed in 2015 (Table B-11.1 Appendix B).
* RG-15 Figure A-4 Recapture Sampling Locations of Clinton Power Station A-5
Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-11.2, Appendix B).
* RG-3 Page 129of138 Intentionally left blank Page 130of138 APPENDIX B DATA TABLES OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR) Page 131 of 138 Intentionally left blank Page 132of138 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) 8-3 02/09/15 < 157 8-3 05/26/15 < 194 8-3 08/17/15 < 180 < 5.2 < 0.6 1.2 +/- 0.8 < 1.1 3.2 +/- 1.0 < 1.6 8-3 11/02/15 < 196 MW-CL-1 02/09/15 < 156 MW-CL-1 05/26/15 < 195 MW-CL-1 08/17/15 < 179 -< 5.4 < 0.6 < 0.9 < 1.1 2.1 +/- 0.9 < 1.6 MW-CL-1 11/02/15 < 187 MW-CL-121 02/09/15 < 178 MW-CL-121 05/26/15 < 196 MW-CL-121 08/17/15 < 191 < 5.6 < 0.6 < 0.9 < 1.1 4.9 +/- 1.0 < 1.6 MW-CL-121 11/02/15 322 +/- 134 MW-CL-131 02/09/15 < 154 MW-CL-131 05/26/15 < 193 MW-CL-131 08/17/15 < 187 . < 4.0 < 0.6 < 0.7 < 1.1 3.2 +/- 1.1 < 1.6 MW-CL-131 11/02/15 < 187 MW-CL-13S 02/09/15 < 157 MW-CL-13S 05/26/15 < 193 MW-CL-13S 08/17/15 < 199 < 4.7 < 0.6 < 0.6 < 1.1 2.7 +/- 1.0 < 1.6 MW-CL-13S 11/02/15 220 +/- 128 MW-CL-14S 02/09/15 < 156 MW-CL-14S 07/22/15 241 +/- 128 MW-CL-14S 08/18/15 300 +/- 126 < 6.9 < 0.8 < 1.3 < 1.1 11.9 +/- 1.6 < 1.6 MW-CL-14S 11/03/15 365 +/- 136 MW-CL-151 02/09/15 < 156 MW-CL-151 05/26/15 < 193 MW-CL-151 08/17/15 < 174 < 5.7 < 0.7 < 0.7 < 0.5 1.9 +/- 1.0 < 1.7 MW-CL-151 11/02/15 < 193 MW-CL-15S 02/09/15 < 155 MW-CL-15S 05/26/15 < 193 MW-CL-15S 08/17/15 < 197 MW-CL-15S 09/29/15 < 5.2 < 0.6 < 0.9 < 0.8 < 0.9 < 1.6 MW-CL-15S 11/02/15 < 185 MW-CL-16S 02/09/15 < 186 MW-CL-16S 05/27/15 < 189 MW-CL-16S 08/18/15 <.180 MW-CL-16S 09/29/15 < 5.6 < 0.7 < 2.3 < 0.8 8.7 +/- 1.4 < 1.6 MW-CL-16S 11/03/15 < 188 MW-CL-17S 02/09/15 < 159 MW-CL-17S 05/27/15 < 194 MW-CL-17S 08/18/15 < 180 < 5.3 < 0.7 < 1.9 < 0.5 3.4 +/- 1.1 < 1.6 MW-CL-17S 11/03/15 < 188 MW-CL-181 02/09/15 < 154 MW-CL-181 05/27/15 < 194 MW-CL-181 08/18/15 < 198 < 5.5 < 0.6 < 1.2 < 0.5 4.2 +/- 1.1 < 1.6 MW-CL-181 11/03/15 < 186 B-1 Page 133of138 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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-CL-18S 02/09/15
E.       Precipitation Water Reirnlts Precipitation Water Precipitation water samples were not collected during 2015.
< 156 MW-CL-18S 05/27/15 < 193 MW-CL-18S 08/18/15 < 189 < 4.5 < 0.8 < 2.1 < 0.5 4.4 +/- 1.2 < 1.6 MW-CL-18S 11/03/15 < 188 MW-CL-19S 02/09/15
F.       Recapture Recapture samples were not required in 2015.
< 155 MW-CL-19S 05/26/15 < 194 MW-CL-19S 08/17/15 < 174 < 4.5 < 0.7 < 2.5 < 0.6 6.7 +/- 1.5 < 1.7 MW-CL-19S 11/02/15 < 190 MW-CL-2 02/09/15 < 154 MW-CL-2 05/26/15 < 195 . MW-CL-2 08/17/15 < 180 < 5.2 < 0.6 < 1.2 < 1.1 3.9 +/- 1.1 < 1.6 MW-CL-2 11/02/15 < 188 MW-CL-20S 02/09/15 < 154 MW-CL-20S 05/26/15
G.       Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.
< 198 MW-CL-20S 08/17/15 < 175 < 6.3 < 0.5 < 1.2 < 0.5 2.8 +/- 1.1 < 1.6 MW-CL-20S 11/02/15 < 188 MW-CL-21S 02/09/15 176 +/- 106 MW-CL-21S 05/26/15 219 +/- 130 MW-CL-21S 08/17/15 287 +/- 124 MW-CL-21S 09/29/15 < 197 < 5.3 < 0.8 < 1.8 < 0.8 < 1.5 < 1.6 MW-CL-21S 11/02/15 < 189 MW-CL-22S 02/09/15 < 179 MW-CL-22S 05/27/15 < 194 MW-CL-22S 08/18/15 < 180 MW-CL-22S 09/29/15 < 4.4 < 0.7 < 2.3 < 0.9 11.2 +/- 1.5 < 1.6 MW-CL-22S 11/03/15 < 192 B-2 Page 134of138 OJ I w "'U Ol cc CD _,.. w 01 0 -_,.. w c:o Table 8-1.2 SITE B-3 MW-CL-1 MW-CL-121 MW-CL-131 MW-CL-138 MW-CL-148 MW-CL-148 MW-CL-151 MW-CL-158 MW-CL-168
H.       Errata Data The 2014 ARGPP incorrectly reported 607 analyses in the Summary and Conclusion section. The number of analyses in 2014 should have been ,
reported as 253 (IR 02635324).
Page 121of138
 
I. Leaks, Spills, and Releases No leaks, spills or releases were identified during the year.
J. Trends MW-CL-14S had a slight trend upward from <200 pCi/L to 241, 300 and 365 pCi/L respectively in 2015. However, the 1st Quarter of 2016 revealed MW-CL-14S has trended back to 218 pCi/L. Additionally, MW-CL-21S, after it too experienced a slight trend from 219 pCi/L to 287 pCi/L in 2015, has now had consecutive values of 189 pCi/L in the 4th Quarter of 2015 and 191 pCi/L from our 1st Quarter of 2016. All sampling well locations are currently indicating tritium levels that are less than the ODCM LLD of 2,000 pCi/I. All wells will continue to be sampled in accordance with the RGPP in 2016..
K. Investigations Currently no investigations are on-going.
L. Actions Taken
: 1. Compensatory Actions There have been no station events requiring compensatory actions at the Clinton Power Station in 2015.
: 2. Installation of Monitoring Wells No new wells were installed during the 2015.
: 3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.
Page 122of138
 
APPENDIX A LOCATION DESIGNATION OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT
{ARGPPR)
Page 123of138
 
Intentionally left blank Page 124of138
 
TABLEA-1:       Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Site                           Site Type B-3                           Monitoring Well MW-CL-1                       Monitoring Well MW-CL-2                       Monitoring Well MW-CL-121                     Monitoring Well MW-CL-131                     Monitoring Well MW-CL-13S                     Monitoring Well MW-CL-14S                     Monitoring Well MW-CL-151                     Monitoring Well MW-CL-15S                     Monitoring Well MW-CL-16S                     Monitoring Well MW-CL-17S                     Monitoring Well MW-CL-181                     Monitoring Well MW-CL-18S                     Monitoring Well MW-CL-19S                     Monitoring Well MW-CL-20S                     Monitoring Well MW-CL-21S                     Monitoring Well MW-CL-22S                     Monitoring Well Sewage Treatment Plant - - - - Surface Water SW-CL-1                       Surface Water SW-CL-2                       Surface Water SW-CL-4                       Surface Water SW-CL-5                       Surface Water SW-CL-6                       Surface Water SW-CL-7                       Surface Water A-1                                        Page 125of138
 
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CXl Figure A- 2 Sampling Locations South of Clinton Power Station
 
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* RG-3 Figure A-4 Recapture Sampling Locations of Clinton Power Station A-5                             Page 129of138
 
Intentionally left blank Page 130of138


MW-CL-178 MW-CL-181 MW-CL-188 MW-CL-198 MW-CL-2 MW-CL-208 MW-CL-218 MW-CL-218 MW-CL-218 MW-CL-228 COLLECTION DATE 08/17/15 08/17/15 08/17/15 08/17/15 08/17/15 02/09/15 08/18/15 08/17/15 09/29/15 09/29/15 08/18/15 08/18/15 08/18/15 08/17/15 08/17/15 08/17/15 02/09/15 05/26/15 09/29/15 09/29/15 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER
APPENDIX B DATA TABLES OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)
+/- SIGMA Be-7 < 36 < 38 < 38 < 41 < 37 < 42 < 38 < 38 < 73 < 79 < 36 < 35 < 16 < 21 < 32 < 18 < 31 < 15 < 57 < 80 K-40 Mn-54 < 29 < 3 < 36 < 4 < 37 < 4 68 +/- 37 < 4 < 77 < 4 < 68 < 4 < 51 < 4 < 30 < 148 < 154 < 32 < 72 < 32 < 47 < 26 < 18 < 58 < 30 < 87 < 95 <4 < 6 < 11 <4 < 5 < 2 < 2 < 3 < 2 < 3 < 1 < 7 < 8 Co-58 <4 < 5 <4 < 4 <4 < 5 < 5 <4 < 8 < 9 <4 < 4 < 2 < 2 < 4 < 2 < 3 < 2 < 7 < 6 Fe-59 < 7 < 10 < 8 < 10 < 11 < 9 < 11 < 8 < 16 < 19 < 9 < 10 < 4 < 6 < 7 < 4 < 9 <4 < 19 < 23 Co-60 <4 <4 < 3 < 3 <4 <4 < 5 < 4 < 8 < 9 <4 < 4 < 2 < 2 < 3 < 2 < 3 < 2 < 7 < 7 Zn-65 < 6 < 8 < 7 < 8 < 8 < 9 < 9 < 8 < 11 < 19 < 9 < 6 < 3 < 5 < 6 < 3 < 7 < 3 < 14 < 20 Nb-95 <4 < 5 <4 <4 < 5 < 5 <4 < 5 < 11 < 5 <4 < 2 < 3 <4 < 2 < 4 < 2 < 9 < 9 Zr-95 < 6 < 8 < 7 < 7 < 8 < 8 < 9 < 7 < 11 < 17 < 8 < 5 < 3 <4 < 7 < 3 < 8 < 3 < 16 < 17 Cs-134 Cs-137 < 3 <4 <4 <4 <4 < 4 <4 < 3 < 6 < 7 < 3 < 3 < 1 < 2 < 3 < 2 < 3 < 1 < 8 < 9 < 4 < 4 <4
Page 131 of 138
<4 <4 <4 <4 < 3 < 8 < 12 <4 <4 < 2 < 2 <4 < 2 < 4 < 2 < 7 < 10 Ba-140 < 29 < 28 < 28 < 30 < 30 < 33 < 31 < 28 < 34 < 45 < 27 < 26 < 17 < 24 < 32 < 18 < 25 < 13 < 34 < 43 La-140 < 8 < 13 < 10 < 9 < 11 < 10 < 12 < 9 < 14 < 12 < 9 < 8 < 5 < 7 < 9 < 6 < 8 <4 < 12 < 9 
 
""C Dl cc CD _,, (,.) CJ) 0 -_,, (,.) OJ TABLE B-1.3 ,, " ,, 1;: CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015: I *' ! RESULTS IN UNITS OF PCl/LITER  
Intentionally left blank Page 132of138
+/- 2 SIGMA 1r SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 DATE THERE WERE NO HARD TO DETECTS ANALYZED IN 2015 :*. I I; " I* I J l Fe-55 Ni-63 TABLE B-11.1 SITE SW-CL-1 SW-CL-1 SW-CL-1 SW-CL-1 SW-CL-2 SW-CL-2 SW-CL-2 SW-CL-2 SW-CL-4 SW-CL-4 SW-Cl.-4 SW-CL-4 SW-CL-5 SW-CL-5 SW-CL-5 SW-CL-5 SW-CL-6 SW-CL-6 SW-CL-6 SW-CL-6 SW-CL-7 SW-CL-7 SW-CL-7 SW-CL-7 SEWAGE TREATMENT PLANT SEWAGE TREATMENT PLANT SEWAGE TREATMENT PLANT SEWAGE TREATMENT PLANT CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER
 
+/- 2 SIGMA COLLECTION DATE H-3 02/09/15 < 186 05/26/15 < 194 08/17/15 < 174 11/02/15 < 189 02/09/15 < 179 05/26/15 < 195 08/17/15 < 177 11/02/15 < 190 02/09/15 < 180 05/26/15 < 188 08/17/15 < 176 -*-----:-11/02/15 < 191 02/09/15 < 182 05/26/15 < 194 08/17/15 < 173 11/02/15 < 191 02/09/15 < 177 05/26/15 < 194 08/17/15 < 174 11/02/15 < 188 02/09/15 < 183 05/26/15 < 195 08/17/15 < 181 11/02/15 < 194 02/09/15 < 182 05/26/15 < 192 08/17/15 < 177 11/02/15 < 193 B-5 Page 137of138 OJ I Q') "U Dl ca CD Table 8-11.2 SITE COLLECTION DATE CL-SW-CL-1 08/17/15 CL-SW-CL-2 08/17/15 CL-SW-CL-4 08/17/15 CL-SW-CL-5 08/17/15 CL-SW-CL-6 08/17/15 CL-SW-CL-7 08/17/15 SEWAGE TREATMENT PLANT 08/17/15 CONCENTRATIONS OF GAMMA EMITTERS IN suRi;:AcE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER  
TABLE B-1.1          CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE        DATE          H-3          Sr-89      Sr-90  Gr-A (Dis) Gr-A (Sus)    Gr-8 (Dis) Gr-8 (Sus) 8-3        02/09/15    < 157 8-3        05/26/15   < 194 8-3        08/17/15   < 180        < 5.2      < 0.6  1.2  +/- 0.8  < 1.1          3.2 +/- 1.0  < 1.6 8-3        11/02/15   < 196 MW-CL-1    02/09/15   < 156 MW-CL-1    05/26/15   < 195 MW-CL-1    08/17/15   < 179 -      < 5.4      < 0.6    < 0.9      < 1.1          2.1 +/- 0.9  < 1.6 MW-CL-1    11/02/15   < 187 MW-CL-121  02/09/15   < 178 MW-CL-121  05/26/15   < 196 MW-CL-121  08/17/15   < 191        < 5.6      < 0.6    < 0.9      < 1.1          4.9 +/- 1.0  < 1.6 MW-CL-121  11/02/15      322 +/- 134 MW-CL-131  02/09/15    < 154 MW-CL-131  05/26/15    < 193 MW-CL-131  08/17/15    < 187 .      < 4.0      < 0.6    < 0.7      < 1.1          3.2 +/- 1.1  < 1.6 MW-CL-131  11/02/15   < 187 MW-CL-13S  02/09/15    < 157 MW-CL-13S  05/26/15    < 193 MW-CL-13S  08/17/15    < 199        < 4.7      < 0.6    < 0.6      < 1.1          2.7 +/- 1.0  < 1.6 MW-CL-13S  11/02/15      220 +/- 128 MW-CL-14S  02/09/15    < 156 MW-CL-14S  07/22/15      241 +/- 128 MW-CL-14S  08/18/15      300 +/- 126 < 6.9      < 0.8    < 1.3      < 1.1        11.9 +/- 1.6  < 1.6 MW-CL-14S  11/03/15      365 +/- 136 MW-CL-151  02/09/15    < 156 MW-CL-151  05/26/15    < 193 MW-CL-151  08/17/15    < 174        < 5.7      < 0.7    < 0.7     < 0.5         1.9 +/- 1.0  < 1.7 MW-CL-151  11/02/15    < 193 MW-CL-15S  02/09/15    < 155 MW-CL-15S  05/26/15    < 193 MW-CL-15S  08/17/15    < 197 MW-CL-15S  09/29/15                < 5.2     < 0.6    < 0.9      < 0.8      < 0.9          < 1.6 MW-CL-15S  11/02/15    < 185 MW-CL-16S  02/09/15    < 186 MW-CL-16S  05/27/15    < 189 MW-CL-16S  08/18/15    <.180 MW-CL-16S  09/29/15                < 5.6      < 0.7    < 2.3      < 0.8          8.7 +/- 1.4 < 1.6 MW-CL-16S  11/03/15    < 188 MW-CL-17S  02/09/15    < 159 MW-CL-17S  05/27/15    < 194 MW-CL-17S  08/18/15    < 180        < 5.3     < 0.7    < 1.9      < 0.5         3.4 +/- 1.1  < 1.6 MW-CL-17S  11/03/15    < 188 MW-CL-181  02/09/15    < 154 MW-CL-181  05/27/15    < 194 MW-CL-181  08/18/15    < 198        < 5.5      < 0.6    < 1.2     < 0.5          4.2 +/- 1.1  < 1.6 MW-CL-181  11/03/15    < 186 B-1                              Page 133of138
+/- SIGMA 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-14 < 21 < 18 < 2 < 2 < 5 < 2
 
<4 < 2 < 4 < 2 < 2 <
TABLE B-1.1          CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE        DATE          H-3         Sr-89      Sr-90 Gr-A (Dis) Gr-A (Sus)    Gr-B (Dis) Gr-B (Sus)
22 <7 < 17 40 + 26 < 1 < 2 <4 < 1 < 3 <2 < 3 < 1 < 2 <
MW-CL-18S  02/09/15    < 156 MW-CL-18S  05/27/15    < 193 MW-CL-18S  08/18/15    < 189        < 4.5     < 0.8    < 2.1      < 0.5         4.4 +/- 1.2 < 1.6 MW-CL-18S  11/03/15    < 188 MW-CL-19S  02/09/15    < 155 MW-CL-19S  05/26/15    < 194 MW-CL-19S  08/17/15    < 174        < 4.5      < 0.7   < 2.5      < 0.6          6.7 +/- 1.5 < 1.7 MW-CL-19S  11/02/15    < 190 MW-CL-2    02/09/15    < 154 MW-CL-2    05/26/15    < 195 .
17 < 5 < 16 < 12 < 1 <2 < 4 < 1 < 3 < 2 < 3 < 1 < 2 < 17 <4 < 18 < 47 < 1 < 2 <4 <2 <, 3 <2 < 4 < 2 < 2 <
MW-CL-2    08/17/15    < 180        < 5.2      < 0.6   < 1.2     < 1.1          3.9 +/- 1.1  < 1.6 MW-CL-2     11/02/15    < 188 MW-CL-20S  02/09/15    < 154 MW-CL-20S  05/26/15    < 198 MW-CL-20S  08/17/15    < 175        < 6.3      < 0.5    < 1.2     < 0.5          2.8 +/- 1.1  < 1.6 MW-CL-20S  11/02/15    < 188 MW-CL-21S  02/09/15      176 +/- 106 MW-CL-21S  05/26/15      219 +/- 130 MW-CL-21S  08/17/15      287 +/- 124 MW-CL-21S  09/29/15    < 197        < 5.3      < 0.8    < 1.8      < 0.8      < 1.5          < 1.6 MW-CL-21S  11/02/15    < 189 MW-CL-22S  02/09/15    < 179 MW-CL-22S  05/27/15    < 194 MW-CL-22S  08/18/15    < 180 MW-CL-22S  09/29/15                < 4.4      < 0.7    < 2.3      < 0.9         11.2 +/- 1.5  < 1.6 MW-CL-22S  11/03/15    < 192 B-2                            Page 134of138
21 < 6 < 18 65 + 31 < 2 < 2 < 5 < 2 < 3 < 2 < 4 < 1 <2 < 18 < 6 < 15 < 15 < 1 < 1 <4 < 2 < 3 < 2 < 3 < 1 < 1 <
 
16 < 6 < 17 < 17 <2 < 2 <4 < 2 <4 < 2 < 4 < 2 < 2 <
Table 8-1.2              CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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 B-3        08/17/15  < 36  < 29      < 3    <4    < 7    <4    < 6    <4    < 6    < 3    < 4    < 29  < 8 MW-CL-1     08/17/15  < 38  < 36      < 4    < 5    < 10  <4    < 8    < 5    < 8    <4    < 4    < 28  < 13 MW-CL-121  08/17/15  < 38  < 37      < 4    <4    < 8    < 3  < 7    <4    <  7    <4    <4    < 28  < 10 MW-CL-131  08/17/15  < 41      68 +/- 37 < 4    < 4    < 10  < 3  < 8    <4    <  7    <4    <4    < 30  < 9 MW-CL-138  08/17/15  < 37  < 77      < 4     <4     < 11  <4   < 8    ~4     <  8    <4    <4    < 30  < 11 MW-CL-148  02/09/15  < 42  < 68      < 4    < 5   < 9    <4    < 9    < 5   <  8    < 4    <4    < 33  < 10 MW-CL-148  08/18/15  < 38  < 51      < 4    < 5   < 11  < 5   < 9    < 5    <  9    <4    <4    < 31  < 12 MW-CL-151  08/17/15  < 38  < 30      <4      <4    < 8    < 4  < 8    <4    <  7    < 3    < 3    < 28  < 9 MW-CL-158  09/29/15  < 73  < 148      < 6    < 8    < 16  < 8  < 11  < 5    <  11  < 6    < 8    < 34  < 14 OJ I    MW-CL-168  09/29/15  < 79  < 154      < 11    < 9    < 19  < 9  < 19  < 11  < 17    < 7   < 12  < 45  < 12 w    MW-CL-178  08/18/15  < 36  < 32      <4      <4    < 9    <4    < 9    < 5    < 8    < 3    <4    < 27  < 9 MW-CL-181  08/18/15   < 35  < 72      < 5    < 4    < 10  < 4  < 6    <4    < 5    < 3    <4    < 26   < 8 MW-CL-188  08/18/15   < 16  < 32      < 2    < 2    < 4    < 2  < 3    < 2    < 3    < 1    < 2    < 17  < 5 MW-CL-198  08/17/15   < 21  < 47      < 2    < 2    < 6    < 2  < 5    < 3    <4      < 2    < 2    < 24  < 7 MW-CL-2    08/17/15   < 32  < 26      < 3    <4    < 7    < < 6    <4    <  7    < 3    <4    < 32  < 9 MW-CL-208  08/17/15   < 18  < 18      < 2    < 2    < 4    < 2  < 3    < 2    < 3    < 2    < 2    < 18  < 6 MW-CL-218  02/09/15   < 31  < 58      < 3    < 3    < 9    < 3  < 7    < 4    < 8    < 3    <4    < 25  < 8 MW-CL-218  05/26/15   < 15   < 30      < 1    < 2   <4    < 2  < 3    <2    < 3    < 1    < 2    < 13  <4 MW-CL-218  09/29/15   < 57  < 87      < 7    < 7    < 19  < 7  < 14  < 9    < 16    < 8    < 7    < 34  < 12 MW-CL-228  09/29/15   < 80  < 95      < 8    < 6    < 23  < 7  < 20  < 9    < 17   < 9    < 10  < 43  < 9
20 < 6 Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604277 April 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRG Docket No. 50-461 Exelon Generation
"'U Ol cc CD
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                                                                                        ,,
                                                                                          "
                                                                                          ,,
1;:
TABLE B-1.3            CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015:
I
                                                                                        *'
                                                                                          !
RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA                   1r 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 THERE WERE NO HARD TO DETECTS ANALYZED IN 2015
:*.
I I;
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Dl                                                                                      I cc                                                                                        J CD
_,,                                                                                    l
(,.)                                                                                    :~
-
CJ) 0
_,,
(,.)
OJ
 
TABLE B-11.1           CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE                  DATE        H-3 SW-CL-1                02/09/15  < 186 SW-CL-1               05/26/15  < 194 SW-CL-1                08/17/15  < 174 SW-CL-1               11/02/15  < 189 SW-CL-2               02/09/15  < 179 SW-CL-2               05/26/15  < 195 SW-CL-2               08/17/15  < 177 SW-CL-2               11/02/15  < 190 SW-CL-4                02/09/15  < 180 SW-CL-4                05/26/15  < 188 SW-Cl.-4               08/17/15   < 176
                                                              - *-----:-
SW-CL-4                11/02/15   < 191 SW-CL-5                02/09/15  < 182 SW-CL-5                05/26/15  < 194 SW-CL-5                08/17/15  < 173 SW-CL-5                11/02/15  < 191 SW-CL-6                02/09/15  < 177 SW-CL-6               05/26/15  < 194 SW-CL-6                08/17/15  < 174 SW-CL-6                11/02/15  < 188 SW-CL-7                02/09/15  < 183 SW-CL-7                05/26/15  < 195 SW-CL-7                08/17/15  < 181 SW-CL-7                11/02/15  < 194 SEWAGE TREATMENT PLANT 02/09/15  < 182 SEWAGE TREATMENT PLANT 05/26/15  < 192 SEWAGE TREATMENT PLANT 08/17/15  < 177 SEWAGE TREATMENT PLANT 11/02/15  < 193 B-5                              Page 137of138
 
Table 8-11.2                        CONCENTRATIONS OF GAMMA EMITTERS IN suRi;:AcE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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-14 DATE CL-SW-CL-1            08/17/15  < 21  < 18      < 2    < 2    < 5    < 2  <4    < 2  <4    <2    <2    < 22  <7 CL-SW-CL-2            08/17/15  < 17    40 + 26 < 1    < 2    <4      < 1  < 3  <2    <3    < 1    < 2    < 17  < 5 CL-SW-CL-4            08/17/15  < 16  < 12      < 1    <2      < 4    < 1  < 3  < 2  < 3  < 1    < 2    < 17  <4 CL-SW-CL-5            08/17/15  < 18  < 47      < 1    < 2    <4      <2    <, 3  <2    < 4  < 2    < 2    < 21  < 6 CL-SW-CL-6            08/17/15  < 18    65 + 31 < 2    < 2    < 5    < 2  <3    < 2  < 4  < 1    <2    < 18  < 6 CL-SW-CL-7            08/17/15  < 15  < 15      < 1    < 1    <4      < 2  < 3  < 2  < 3  < 1    < 1    < 16  < 6 SEWAGE TREATMENT PLANT 08/17/15  < 17  < 17      <2    < 2    <4      < 2  <4    < 2  < 4  < 2    <2    < 20  < 6 OJ I
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Exelon Generation Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604277 April 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62                                    '"-"
NRG Docket No. 50-461


==Subject:==
==Subject:==
Clinton Power'Station 2015 Annual Radiological Environmental Operating Report Exelon Generating Company, LLC (Exelon), Clinton Power Station is submitting the 2015 Annual Radiological Environmental Operating Report. This report is submitted in accordance with Technical Specification requirement 5.6.2, "Annual Radiological Environmental Operating Report," and covers the period from January 1, 2015 through December 31, 2015. This report provides the results of the Radiological Environmental Monitoring Program as specific in Section 3/4 and 6.1 of the Offsite Dose Calculation Manual. There are no regulatory commitments  
Clinton Power'Station 2015 Annual Radiological Environmental Operating Report Exelon Generating Company, LLC (Exelon), Clinton Power Station is submitting the 2015 Annual Radiological Environmental Operating Report. This report is submitted in accordance with Technical Specification requirement 5.6.2, "Annual Radiological Environmental Operating Report," and covers the period from January 1, 2015 through December 31, 2015.
*contained within this letter. Questions on this letter may be directed to Mr. Rick Bair, Chemistry Manager, at 217-937-3200.
This report provides the results of the Radiological Environmental Monitoring Program as specific in Section 3/4 and 6.1 of the Offsite Dose Calculation Manual.
Respectfully, Theodore R. Stone( tf'\ Site Vice President Clinton Power Station dra/bsz Attachments:
There are no regulatory commitments *contained within this letter.
Annual Radiological Environmental Operating Report cc: Regional Administrator-NRG Region Ill NRG Senior Resident Inspector  
Questions on this letter may be directed to Mr. Rick Bair, Chemistry Manager, at 217-937-3200.
-Clinton Power Station Office of Nuclear Facility Safety -Illinois Emergency Management Agency ' "-"
Respectfully,
Page 1of138 Intentionally left blank Page 2of138 Docket No: 50-461 POWER Annual Radiological Environmental Operating Report January 1 Through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services J:/ ExelonGeneration, Clinton Power Station Clinton, IL 61727 April 2016 Page 3of138 INTENTIONALLY LEFT BLANK Page 4of138 Table Of Contents I. Summary and Conclusions  
      ~
..............................................................................................
Theodore R. Stone( tf'\
1 II. Introduction  
Site Vice President Clinton Power Station dra/bsz Attachments:
....................................................................................................  
Annual Radiological Environmental Operating Report cc:       Regional Administrator- NRG Region Ill NRG Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Emergency Management Agency
-.................
 
3 A. Objectives of the REMP ......................................................................................
Page 1of138 Intentionally left blank Page 2of138
3 B. Implementation of the Objectives  
 
........................................................................
Docket No:     50-461 CL~NTON      POWER             STAT~ON Annual Radiological Environmental Operating Report January 1 Through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services
3 Ill. Program Description  
    *~
......................................................................................................
J:/ ExelonGeneration, Clinton Power Station Clinton, IL 61727 April 2016 Page 3of138
4 A. Sample Collection  
 
...............................................................................................
INTENTIONALLY LEFT BLANK Page 4of138
4 B. Sample Analysis .......................................................
 
: ..........................................
Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ....................................................................................................-................. 3 A. Objectives of the REMP ...................................................................................... 3 B. Implementation of the Objectives ........................................................................ 3 Ill. Program Description ...................................................................................................... 4 A. Sample Collection ............................................................................................... 4 B. Sample Analysis .......................................................:.......................................... 6 C. Data_ lnterpretati<;m ***'.****'._******~:***************************-**~*:*********************:*********************** 6
6 C. Data_ lnterpretati<;m 6 ------n_,-Pro-graih Exceptions-
    - ----n_,- Pro-graih Exceptions-........... .-.-.~ ...........-..-.......... :.. :.~.~~~-.-.:-:.-~:.-.... :............ .-:... .-.-.: ......... 8 E. Program Changes .............................................................._              ............................... 12 IV. Results and Discussion ............................................................................................... 12 A. Aquatic Environment ......................................................................................... 12
...........
: 1. Surface Water. ........................................................................................ 12
...........
: 2. Drinking Water ........................................................................................ 12
-. .-..........
: 3. Well Water ............................................................................................. 13
: ..
: 4. Fish ......................................................................................................... 13
.... : ............  
: 5. Sediment. ................................................................................................ 14 B. Atmospheric Environment ............... :***************************************************************** 14
.-: ... .-.-.: .........
: 1. Airborne .................................................................................................. 14
8 E. Program Changes ..............................................................
: a. Air Particulates ................................. :........................................*... 14
_ ...............................
: b. Airborne Iodine ............................................................................ 15
12 IV. Results and Discussion
: 2. Terrestrial ................................................................................................ 15
...............................................................................................
: a. Milk ............................................................................................... 15
12 A. Aquatic Environment
: b. Food Products ............................................................................. 16
.........................................................................................
: c. Grass ........................................................................................... 16 C. Ambient Gamma Radiation ............................................................................... 16 D. Land Use Survey ............................................................................................... 17 E. Errata Data ........................................................................................................ 17 F. Summary of Results - Inter-laboratory Comparison Program .......................... 18 V. References ................................................................................................................... 22 Page 5of138
12 1. Surface Water. ........................................................................................
 
12 2. Drinking Water ........................................................................................
Appendices Appendix A     Radiological Environmental Monitoring Report Summary Tables Table A-1     Radiological Environmental Monitoring Program Annual Summary for the Clinton Power Station, 2015 Appendix B   Location Designation, Distance & Direction, and Sample Collection &
12 3. Well Water .............................................................................................
Analytical Methods
13 4. Fish .........................................................................................................
__,_:Tables ..
13 5. Sediment.  
Table B-1   Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Table B-2   Radiological Environmental Monitoring Program - Summary of Sample Collection, Clinton Power Station, 2015 Figures Figure B-1  Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 Figure B-2  Environmental Sampling Locations Between One and Two Miles from the Clinton Power Station, 2015 Figure B-3  Environmental Sampling Locations Between-Two and Five Miles from the Clinton Power Station, 2015 Figure B-4   Environmental Sampling Locations Greater Than Five Miles from the Clinton Power Station, 2015 Appendix C   Data Tables and Figures - Primary Laboratory Tables Table C-1.1   Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
................................................................................................
Table C-1.2   Concentrations of Tritium in Surface Water Samples Coll~cted in the Vicinity of Clinton Power Station, 2015.
14 B. Atmospheric Environment
Table C-1.3   Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
...............
Table C-11.1  Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
:*****************************************************************
ii Page 6of138
14 1. Airborne ..................................................................................................
 
14 a. Air Particulates  
Table C-11.2    Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
.................................
Table C-11.3    Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
: ........................................  
Table C-11.4    Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
* ... 14 b. Airborne Iodine ............................................................................
Table C-111.1    Concentrations of Tritium in Well Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
15 2. Terrestrial  
Table C-111.2    Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
................................................................................................
Table C-IV.1    Concentrations of Gamma Emitters in Fish Samples Collected in the
15 a. Milk ...............................................................................................
* Vicinity of Clinton Power Station, 2015.
15 b. Food Products .............................................................................
------~-; *~*' ., -*   ,. - -        - - - - .. - - - *- - -                ~
16 c. Grass ...........................................................................................
                                                                                  - - .
16 C. Ambient Gamma Radiation  
                                                                -- ............ --..--  -        .    *- ~ - -
...............................................................................
Table C-V.1      Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Clinton Power Station, 2015.
16 D. Land Use Survey ...............................................................................................
Table C-Vl.1    Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.
17 E. Errata Data ........................................................................................................
Table C-Vl.2    Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.
17 F. Summary of Results -Inter-laboratory Comparison Program ..........................
Table C-Vl.3    Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Clinton Power Statio_n, 2015.
18 V. References  
Table C-Vll.1   Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Clinton Power Station, 2015.
...................................................................................................................
Table C-Vlll.1  Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.
22 Page 5of138 Appendix A Tables Table A-1 Appendix B __ ,_:Tables  
Table C-Vlll.Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.
.. Table B-1 Table B-2 Figures Figure B-1 Figure B-2 Figure B-3 Figure B-4 Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-11.1 Appendices Radiological Environmental Monitoring Report Summary Radiological Environmental Monitoring Program Annual Summary for the Clinton Power Station, 2015 Location Designation, Distance & Direction, and Sample Collection
Table C-IX.1     Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Clinton Power Station, 2015.
& Analytical Methods Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Radiological Environmental Monitoring Program -Summary of Sample Collection, Clinton Power Station, 2015 Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 Environmental Sampling Locations Between One and Two Miles from the Clinton Power Station, 2015 Environmental Sampling Locations Between-Two and Five Miles from the Clinton Power Station, 2015 Environmental Sampling Locations Greater Than Five Miles from the Clinton Power Station, 2015 Data Tables and Figures -Primary Laboratory Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Tritium in Surface Water Samples in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. ii Page 6of138 Table C-11.2 Table C-11.3 Table C-11.4 Table C-111.1 Table C-111.2 Table C-IV.1
Table C-IX.2    Concentrations of Gamma Emitters in Grass Samples Collected in the Vicinity of Clinton Power Station, 2015.
., -* ,. --Table C-V.1 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Tritium in Well Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Fish Samples Collected in the
Table C-X.1      Quarterly DLR Results for Clinton Power Station, 2015.
* Vicinity of Clinton Power Station, 2015. ------.. ---*-----............ --..--. -. *---Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vl.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vl.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vl.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Clinton Power Statio_n, 2015. Table C-Vll.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vlll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-Vlll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-IX.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-IX.2 Concentrations of Gamma Emitters in Grass Samples Collected in the Vicinity of Clinton Power Station, 2015. Table C-X.1 Quarterly DLR Results for Clinton Power Station, 2015. Table C-X.2 Mean Quarterly DLR Results for the Inner Ring, Outer Ring, Special Interest and Control Locations for Clinton Power Station, 2015. Table C-X.3 Summary of the Ambient Dosimetry Program for Clinton Power Station, 2015. iii Page 7of138 Figures Figure C-1 Figure C-2 Appendix D Tables Table D-1 TaQle Table D-3 Table D-4 Table D-5 Appendix E Appendix F Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of CPS, 2015. Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of CPS, 2015. Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, .2015 DOE's Mixed Alialyte Performance Evaluation Program (MAPEP) Teledyne Brown Engine-ering, 2015 * * -ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 ERA(a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 DOE's Mixed Analyte Performance Evaluation-Program (MAPEP) Teledyne Brown Engineering, 2015
Table C-X.2      Mean Quarterly DLR Results for the Inner Ring, Outer Ring, Special Interest and Control Locations for Clinton Power Station, 2015.
* Errata Data . Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 8of138 I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Clinton Power Station (CPS) by Exelon Generation Company, LLC (Exelon) covers the period January 1, 2015 through December 31, 2015. During that time period, 1,590 analyses were performed on 1,463 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of CPS had no adverse radiological impact on the environment.
Table C-X.3      Summary of the Ambient Dosimetry Program for Clinton Power Station, 2015.
iii Page 7of138
 
Figures Figure C-1 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of CPS, 2015.
Figure C-2 Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of CPS, 2015.
Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, .2015 TaQle D~2  DOE's Mixed Alialyte Performance Evaluation Program (MAPEP)
Teledyne Brown Engine-ering, 2015                          * -~- * -
Table D-3  ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 Table D-4  ERA(a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 Table D-5  DOE's Mixed Analyte Performance Evaluation- Program (MAPEP)
Teledyne Brown Engineering, 2015
* Appendix E Errata Data .
Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 8of138
 
I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Clinton Power Station (CPS) by Exelon Generation Company, LLC (Exelon) covers the period January 1, 2015 through December 31, 2015.
During that time period, 1,590 analyses were performed on 1,463 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of CPS had no adverse radiological impact on the environment.
There were zero (0) radioactive liquid releases from CPS during 2015. Releases of gaseous radioactive materials were accurately measured in plant effluents.
There were zero (0) radioactive liquid releases from CPS during 2015. Releases of gaseous radioactive materials were accurately measured in plant effluents.
There were no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite _dose received by.,a member. of the-public in :2015. due-to .the release .oL'---*-*-. gaseous effluents from CPS was 2.53 E-03 or 0.00253 mRem. Surface, drinking,_
There were no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite _dose received by.,a member. of the- public in :2015. due-to .the release .oL'---*-*- .
and well water samples were analyzed for concentrations of tritium and gamma emitting nuclides.
gaseous effluents from CPS was 2.53 E-03 or 0.00253 mRem.
Drinking water samples were also analyzed for concentrations of gross beta and 1-131. Naturally occurring K-40 was detected .at levels consistent with those detected in previous years. No fission or activation products were detected.
Surface, drinking,_ and well water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of gross beta and 1-131. Naturally occurring K-40 was detected .at levels consistent with those detected in previous years. No fission or activation products were detected. No tritium or gross beta activity was detected. and the required lower limit of detection (LLD) was met.
No tritium or gross beta activity was detected.
Fish and shoreline sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish or shoreline sediment samples.
and the required lower limit of detection (LLD) was met. Fish and shoreline sediment samples were analyzed for concentrations of gamma emitting nuclides.
Air particulate samples were analyzed for concentrations of gross. beta and gamma emitting nuclides. Cosmogenic Be-7 and naturally occurring K-40 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.
No fission or activation products were detected in fish or shoreline sediment samples. Air particulate samples were analyzed for concentrations of gross. beta and gamma emitting nuclides.
Iodine- 1-131 analyses were performed on weekly air samples. All results were less than the lower limit of detection for 1-131.
Cosmogenic Be-7 and naturally occurring K-40 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.
High sensitivity 1-131 analyses and gamma analyses were performed on cow milk samples. All results were below the required LLDs for 1-131.
Iodine-1-131 analyses were performed on weekly air samples. All results were less than the lower limit of detection for 1-131. High sensitivity 1-131 analyses and gamma analyses were performed on cow milk samples. All results were below the required LLDs for 1-131. Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found. Food product samples were analyzed for concentrations of gamma emitting nuclides.
Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.
Concentrations of cosmogenically produced Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.
Food product samples were analyzed for concentrations of gamma emitting nuclides. Concentrations of cosmogenically produced Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.
Grass samples were analyzed for concentrations of gamma emitting nuclides.
Grass samples were analyzed for concentrations of gamma emitting nuclides.
Concentrations of cosmogenically produced Be-7 and naturally occurring were consistent with those detected in previous years. No fission or activation Page 9of138 products were detected.
Concentrations of cosmogenically produced Be-7 and naturally occurring K~40 were consistent with those detected in previous years. No fission or activation Page 9of138
Environmental gamma radiation measurements were performed quarterly using Dosimeters of Legal Record (DLR). Levels detected were consistent with those observed in previous years. Page 10of138 II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois.
 
CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on February 15, 1987. The site encloses approximately 13, 730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated on approximately 150 acres. The cooling water discharge flume -which discharges to the eastern arm of the lake -occupies an additional 130 acres. Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa f.nn_a _Townships.
products were detected.
A Radiological Environmental Monitoring Program (REMP) for CPS was initiated in 1987. The preoperational period for most media covers the periods May 1980 through February 27, 1987 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TSE) and Landauer on samples collected during the period January 1, 2015 through December 31, 2015. A. Objectives of the REMP The objectives of the REMP are to: 1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
Environmental gamma radiation measurements were performed quarterly using Dosimeters of Legal Record (DLR). Levels detected were consistent with those observed in previous years.
Page 10of138
 
II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on February 15, 1987. The site encloses approximately 13, 730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated on approximately 150 acres. The cooling water discharge flume - which discharges to the eastern arm of the lake - occupies an additional 130 acres.
Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa f.nn_a _Townships.
A Radiological Environmental Monitoring Program (REMP) for CPS was initiated in 1987. The preoperational period for most media covers the periods May 1980 through February 27, 1987 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TSE) and Landauer on samples collected during the period January 1, 2015 through December 31, 2015.
A. Objectives of the REMP The objectives of the REMP are to:
: 1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
: 2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
: 2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
B. Implementation of the Objectives The implementation of the objectives is accomplished by: 1. Identifying significant exposure pathways.
B. Implementation of the Objectives The implementation of the objectives is accomplished by:
: 1. Identifying significant exposure pathways.
: 2. Establishing baseline radiological data of media within those pathways.
: 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. Page 11 of 138 Ill. Program Description A. Sample Collection This section describes the general collection methods used by Environmental Inc. (Midwest Labs) to obtain environmental samples for the CPS REMP in 2015. Sample locations and descriptions can be found in Tables B-1 and and Figures B-1 through B-4, Appendix B. The sampling methods used by Environmental Inc. (Midwest Labs) are listed in Table B-2. Aquatic Environment The aquatic environment was evaluated by performing radiological  
: 3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.
---------* analyses on samples of surface water, drinking water; well-water, fish, shoreline sediment.
Page 11 of 138
Two gallon water samples were collected monthly from composite samplers located at three surface water locations (CL-90, CL-91 and CL-99) and one drinking water location (CL-14). A monthly grab sample was obtained from one surface water location (CL-13). Quarterly samples were obtained from two well water locations (CL-70 and CL-12). All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection.
 
Fish samples comprising the flesh of largemouth bass, crappie, carp, bluegill and channel catfish, the species most commonly harvested from the lakes by sporting fishermen, were collected semiannually at two locations, CL-19 and CL-105. CL-105 was the control location, which is located about 50 miles upwind of the station. Shoreline sediment samples composed of recently deposited substrate were collected at two locations semiannually (CL-78 and CL-105 (control)).
Ill.       Program Description A. Sample Collection This section describes the general collection methods used by Environmental Inc. (Midwest Labs) to obtain environmental samples for the CPS REMP in 2015. Sample locations and descriptions can be found in Tables B-1 and B~2, and Figures B-1 through B-4, Appendix B. The sampling methods used by Environmental Inc. (Midwest Labs) are listed in Table B-2.
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, food produce and grass. Airborne iodine and particulate samples were collected and analyzed weekly at ten locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94). CL-11 was the control location, which is located 16 miles upwind of the station. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached.
Aquatic Environment The aquatic environment was evaluated by performing radiological
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 an independent laboratory for analysis. Page 12of138 Milk samples were collected biweekly at one location (CL-116) from May through October to coincide with the grazing season, and monthly from November through April. All samples were collected in new unused plastic bottles from the bulk tank at the dairy farm, preserved with sodium bisulfite and shipped promptly to the laboratory.
    -------- -
* analyses on samples of surface water, drinking water; well-water, fish, and---'-
shoreline sediment. Two gallon water samples were collected monthly from composite samplers located at three surface water locations (CL-90, CL-91 and CL-99) and one drinking water location (CL-14). A monthly grab sample was obtained from one surface water location (CL-13).
Quarterly samples were obtained from two well water locations (CL-70 and CL-12). All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of largemouth bass, crappie, carp, bluegill and channel catfish, the species most commonly harvested from the lakes by sporting fishermen, were collected semiannually at two locations, CL-19 and CL-105. CL-105 was the control location, which is located about 50 miles upwind of the station. Shoreline sediment samples composed of recently deposited substrate were collected at two locations semiannually (CL-78 and CL-105 (control)).
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, food produce and grass. Airborne iodine and particulate samples were collected and analyzed weekly at ten locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94). CL-11 was the control location, which is located 16 miles upwind of the station. 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 an independent laboratory for analysis.
Page 12of138
 
Milk samples were collected biweekly at one location (CL-116) from May through October to coincide with the grazing season, and monthly from November through April. All samples were collected in new unused plastic bottles from the bulk tank at the dairy farm, preserved with sodium bisulfite and shipped promptly to the laboratory.
Food products were collected once a month from June through September at four locations (CL-114, CL-115, CL-117 and CL-118). The control location was CL-114, which is located 12.5 miles upwind of the station. Various broadleaf vegetable samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Food products were collected once a month from June through September at four locations (CL-114, CL-115, CL-117 and CL-118). The control location was CL-114, which is located 12.5 miles upwind of the station. Various broadleaf vegetable samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Grass samples were collected biweekly at four locations (CL-1, CL-2, CL-8 and CL-116) from May through October. CL-116 was the control -
Grass samples were collected biweekly at four locations (CL-1, CL-2, CL-8 and CL-116) from May through October. CL-116 was the control
location, which is -located 14 miles WSW of the station. -Ail samples were collected in new unused plastic bags and sent to the laboratory for analysis.
- ------~ location, which is -located 14 miles WSW of the station. -Ail samples were --
Ambient Gamma Radiation Direct radiation measurements were made using DLRs. Each location consisted of 2 dosimeter sets. The DLRs were exchanged quarterly and sent to Landauer for analysis.
collected in new unused plastic bags and sent to the laboratory for analysis.
The DLR locations were placed around the CPS site as follows: An inner ring consisting of 16 locations (CL-1, CL-5, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42 CL-43, CL-44, CL-45, CL-46, CL-47, CL-48 and CL-63). An outer ring consisting of 16 locations (CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80 and CL-81). CL-58MM was installed as part of a volunteer comparison study extending to approximately 5 miles from the site. A special interest set consisting of seven locations (CL-37, CL-41, CL-49, CL-64, CL-65, CL-74 and CL-75) representing special interest areas. A supplemental set consisting of 14 locations (CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 and CL-114). CL-11 represents the control location for all environmental DLRs. The specific DLR locations were determined by the following criteria: Page13of138
Ambient Gamma Radiation Direct radiation measurements were made using DLRs. Each location consisted of 2 dosimeter sets. The DLRs were exchanged quarterly and sent to Landauer for analysis. The DLR locations were placed around the CPS site as follows:
: 1. The presence of relatively dense population;
An inner ring consisting of 16 locations (CL-1, CL-5, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42 CL-43, CL-44, CL-45, CL-46, CL-47, CL-48 and CL-63).
: 2. Site meteorological data taking into account distance and elevation for each of the sixteen-22 1 /2 degree meteorological sectors around the site, where estimated annual dose from CPS, if detected, would be most significant;
An outer ring consisting of 16 locations (CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80 and CL-81). CL-58MM was installed as part of a volunteer comparison study extending to approximately 5 miles from the site.
: 3. On hills free from local obstructions and within sight of the HVAC and VG stacks (where practical);
A special interest set consisting of seven locations (CL-37, CL-41, CL-49, CL-64, CL-65, CL-74 and CL-75) representing special interest areas.
: 4. And near the closest dwelling to the HVAC and VG stacks in the prevailing downwind direction.  
A supplemental set consisting of 14 locations (CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 and CL-114).
/ Each location has two DLRs in a vented PVC conduit located approximately three feet above ground-level.
CL-11 represents the control location for all environmental DLRs.
The DLRs were exchanged
The specific DLR locations were determined by the following criteria:
Page13of138
: 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 meteorological sectors around the site, where estimated annual dose from CPS, if detected, would be most significant;
: 3.     On hills free from local obstructions and within sight of the HVAC and VG stacks (where practical);
: 4.     And near the closest dwelling to the HVAC and VG stacks in the prevailing downwind direction.         /
Each location has two DLRs in a vented PVC conduit located approximately three feet above ground-level. The DLRs were exchanged
* quarterly and sent to Landauer for analysis.
* quarterly and sent to Landauer for analysis.
B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the CPS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-2. In order to achieve the stated objectives, the current program includes the following analyses:
B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the CPS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-2.
: 1. Concentrations of beta emitters in drinking water and air particulates.
In order to achieve the stated objectives, the current program includes the following analyses:
: 2. Concentrations of gamma emitters in surface, drinking and well water, air particulates, milk, fish, grass, sediment and vegetables.
: 1.     Concentrations of beta emitters in drinking water and air particulates.
: 3. Concentrations of tritium in surface, drinking and well water. 4. Concentrations of 1-131 in air, milk, drinking water and surface water. 5. Ambient gamma radiation levels at various off-site environs.
: 2.     Concentrations of gamma emitters in surface, drinking and well water, air particulates, milk, fish, grass, sediment and vegetables.
C. Data Interpretation The radiological and direct radiation data collected prior to CPS becoming operational was used as a baseline with which these operational data were compared.
: 3.     Concentrations of tritium in surface, drinking and well water.
For the purpose of this-report, CPS was considered Page 14of138 operational at initial criticality.
: 4.     Concentrations of 1-131 in air, milk, drinking water and surface water.
In addition, data were compared to previous years' operational data for consistency and trending.
: 5. Ambient gamma radiation levels at various off-site environs.
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" value. 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.
C. Data Interpretation The radiological and direct radiation data collected prior to CPS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this- report, CPS was considered Page 14of138
All analyses were designed to achieve the required CPS *detection capabilities for-environmental sample analysis.
 
: 2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity.
operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:
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 resulting in a negative number. A minimum detectable concentration (MDC) was reported in all cases where positive activity was not detected.
: 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" value. 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 CPS
Gamma spectroscopy results for each type of sample were grouped as follows: For surface water, well water, fish, sediment, and milk: 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
      *detection capabilities for-environmental sample analysis.
For drinking water, grass, and vegetation:
: 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 resulting in a negative number. A minimum detectable concentration (MDC) was reported in all cases where positive activity was not detected.
13 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
Gamma spectroscopy results for each type of sample were grouped as follows:
For air particulate:
For surface water, well water, fish, sediment, and milk: 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
9 nuclides, Co-60, Nb-95, Zr-95, Ru-103, Ru-106, Cs-134, Cs-137, Ce-141 and Ce-144, were reported.
For drinking water, grass, and vegetation: 13 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.
The mean and deviation of the results were calculated.
For air particulate: 9 nuclides, Co-60, Nb-95, Zr-95, Ru-103, Ru-106, Cs-134, Cs-137, Ce-141 and Ce-144, were reported.
The standard de;,iation represents the variability of measured results for different samples rather than single analysis uncertainty. Page 15of138 D. Program Exceptions The exceptions (Issue Reports, IRs) described below are those that are considered  
The mean and ~tandard deviation of the results were calculated.
'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM. By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and within Radiological Assessment Branch Technical Position, Revision 1, November 1979, which states .... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, ------" -malfunction of automatic sampling equipment and other legitimate . *-*--.. --. -.*. --:.. ;-,----*----reasons" .... The below section addresses the reporting requirements found within Section 6.0_of the Station's ODCM. -Exceptions/Anomalies January 14, 2015, IR 02437296 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
The standard de;,iation represents the variability of measured results for different samples rather than single analysis uncertainty.
Page 15of138
 
D. Program Exceptions The exceptions (Issue Reports, IRs) described below are those that are considered 'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM. By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",
October 1978, and within Radiological Assessment Branch Technical Position, Revision 1, November 1979, which states .... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability,
--       - - --"                                 - malfunction of automatic sampling equipment and other legitimate reasons" .... The below section addresses the reporting requirements found within Section 6.0_of the Station's ODCM. -
  . *-*- - .. - - . - .*. - - :.. ;-,--- - *----
Exceptions/Anomalies January 14, 2015, IR 02437296 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 04, 2015, IR 02463282 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 04, 2015, IR 02463282 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 11, 2015, IR 02468075 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
March 11, 2015, IR 02468075 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.
May 07, 2015, IR 02497332 While performing the ODCM weekly air sample collection and equipment verification activities on May 06, 2015, vendor Environmental Inc., Midwest Laboratories (EIML) discovered that the ODCM air samplers CL-2 and CL-3 had no power. In the absence of any severe storms or power outages, it was Page 16of138 indeterminate as to why there was no power. However, the minimum sample volume was reached. July 01, 2015, IR 02522637 At 1244 hours on 07/01/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its ground fault interrupter (GFI) 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis.
May 07, 2015, IR 02497332 While performing the ODCM weekly air sample collection and equipment verification activities on May 06, 2015, vendor Environmental Inc., Midwest Laboratories (EIML) discovered that the ODCM air samplers CL-2 and CL-3 had no power. In the absence of any severe storms or power outages, it was Page 16of138
A supplemental  
 
'grab' sample from the process stream was collected and added to the monthly collection container.
indeterminate as to why there was no power. However, the minimum sample volume was reached.
The GFI was reset and CL-90 was returned to service. July 15, 2015, IR 02528489 While performing the weekly inspection on 07/15/15 of ODCM Water Compositors, CL-99 was found not running with the GFI 'tripped' and the sample collection container tipped over inside of the Dog House enclosure.
July 01, 2015, IR 02522637 At 1244 hours on 07/01/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its ground fault interrupter (GFI) 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.
The last weekly inspection performed on July 08, 2015 revealed both as found and as left conditions as being satisfactory.
July 15, 2015, IR 02528489 While performing the weekly inspection on 07/15/15 of ODCM Water Compositors, CL-99 was found not running with the GFI
During this 7 day window, Murray and "'frettel, our fleetwide meteorological vendor, reported that Lincoln County had 4.5 inches, Bloomington haq 4.6 inches and DeWitt County had 4 inches of rain which all contributed to the North Fork Creek flooding.
      'tripped' and the sample collection container tipped over inside of the Dog House enclosure. The last weekly inspection performed on July 08, 2015 revealed both as found and as left conditions as being satisfactory. During this 7 day window, Murray and "'frettel, our fleetwide meteorological vendor, reported that Lincoln County had 4.5 inches, Bloomington haq 4.6 inches and DeWitt County had 4 inches of rain which all contributed to the North Fork Creek flooding. This flooding contributed to the 'as found' condition*
This flooding contributed to the 'as found' condition*
noted.
noted. August 19, 2015, IR 02543695 At 1046 hours on 08/19/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its GFI 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis.
August 19, 2015, IR 02543695 At 1046 hours on 08/19/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its GFI 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.
A supplemental  
August 21, 2015, IR 02545496 During the execution of Work Order #1614812-05 for the recently scheduled Potable Water Outage that commenced at 0325 hours, 08/21/15 the potable water was secured, drained and potable water pumps were placed in Manual OFF. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water samples Page 17of138
'grab' sample from the process stream was collected and added to the monthly collection container.
 
The GFI was reset and CL-90 was returned to service. August 21, 2015, IR 02545496 During the execution of Work Order #1614812-05 for the recently scheduled Potable Water Outage that commenced at 0325 hours, 08/21/15 the potable water was secured, drained and potable water pumps were placed in Manual OFF. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water samples Page 17of138 throughout the duration of the Potable Water Outage that was restored to service at 1800 hours on 08/22/15.
throughout the duration of the Potable Water Outage that was restored to service at 1800 hours on 08/22/15.
November 14, 2015, IR 02588060 During the execution of Clearance Order #129314 and energized Circuit 302 per WO 1863079-06 for the recently scheduled outage, potable water was secured at 0006 hours on 11/14/15.
November 14, 2015, IR 02588060 During the execution of Clearance Order #129314 and de-energized Circuit 302 per WO 1863079-06 for the recently scheduled outage, potable water was secured at 0006 hours on 11/14/15. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water sample throughout the duration of the Potable Water Outage that was restored to service at 2055 hours on 11 /14/15.
This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water sample throughout the duration of the Potable Water Outage that was restored to service at 2055 hours on 11 /14/15. November 18, 2015, IR 02589324 During the weekly checks of ODCM Water compositors on 11/15/15, at 12:35, CL-90 was found with its GFI 'tripped'.
November 18, 2015, IR 02589324 During the weekly checks of ODCM Water compositors on 11/15/15, at 12:35, CL-90 was found with its GFI 'tripped'. The breaker was reset but the GFI 'tripped' after the initial reset. There was standing water within the doghouse enclosure, which contributed to the GFI tripping both times.
The breaker was reset but the GFI 'tripped' after the initial reset. There was standing water within the doghouse enclosure, which contributed to the GFI tripping both times. Throughout 2015, the following IRs were generated to document Program exceptions that were entered into the corrective action program for trending purposes.
Throughout 2015, the following IRs were generated to document Program exceptions that were entered into the corrective action program for trending purposes.
Missed Samples May 13, 2015, IR 02500319 The ODCM air samplers CL-2 and CL-3 lost power on 05/06/15 (IR #02497332).
Missed Samples May 13, 2015, IR 02500319 The ODCM air samplers CL-2 and CL-3 lost power on 05/06/15 (IR
A portable generator was placed to supply power to CL-2 & CL-3 air monitoring stations.
      #02497332). A portable generator was placed to supply power to CL-2 & CL-3 air monitoring stations. The minimum sample volume was not reached for that sampling period.
The minimum sample volume was not reached for that sampling period. June 03, 2015, IR 02512981 While performing the weekly ODCM Surveillance on Wednesday, June 10, 2015 for the collection of particulate and iodine filters and cartridges, the sample collector noted that upon arrival at CL-7, the sample pump was not running. Instead of the typical run time of approximately 168 hours, the timer registered 2 hours and 6 minutes. The minimum volume was not reached for that sampling period. Page 18of138 June 13, 2015, IR 02515452 The ODCM air samplers CL-2 and CL-3 lost power some time on or before June 13, 2015 at 0230 hours when first observed by a Station Security Officer (IR #02514143).
June 03, 2015, IR 02512981 While performing the weekly ODCM Surveillance on Wednesday, June 10, 2015 for the collection of particulate and iodine filters and cartridges, the sample collector noted that upon arrival at CL-7, the sample pump was not running. Instead of the typical run time of approximately 168 hours, the timer registered 2 hours and 6 minutes. The minimum volume was not reached for that sampling period.
Both air sample stations now have back-up generator power, returning both sample stations to service. Minimum sample volume was not collected for that sampling period. July 29, 2015, IR 02534576 ---During the Weekly Sample Collection Surveillance it was discovered that the two (2) recently changed out Environmental DLRs for CL-51, placed there on June 25, 2015 as part of the 3rd . *** --* * --Quarter Exchange, were found-missing: -The adjacent farm culvert had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs, the PVC sample holder or the stanchion pole that it was connected to. August 20, 2015, IR 02546978 While performing the Weekly OCDM Surveillance on Wednesday, 08/26/15 for the collection of particulate filters and iodine cartridges, it was discovered that there was no electrical power to CL-8. Instead of the typical run time of approximately 168 hours, the timer registered 19 hours and 36 minutes. The minimum volume was not reached for that sample. September 24, 2015, IR 02560026 During the 4 1 h Quarter Exchange of Environmental DLRs, it was discovered the CL-46 dosimeters placed on 06/25/15 as part of the 3rd Quarter Exchange were found missing. The adjacent farm field had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs or the PVC sample holder, but the stanchion pole was found lying in the field. Program exceptions were reviewed to understand the causes of the exception and to return to ODCM sample compliance before the next sampling frequency period. The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation. Page 19of138 E. Program Changes There were no changes to the program in 2015. IV. Results and Discussion A. Aquatic Environment
Page 18of138
: 1. Surface Water Composite samples were taken hourly at three locations (CL-90, CL-91 and CL-99) on a monthly schedule and grab samples were taken monthly from one location (CL-13). The following analyses _ were performed.-
 
-----. --lodine-131 Monthly samples from location CL-90 were analyzed for 1-131 activity (Table C-1.1, Appendix C). No 1-131 was detected in any samples and the required LLD was met. Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.2, Appendix C). No tritium was detected in any samples and the required LLD was met. Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. 2. Drinking Water Monthly composite samples were taken hourly at one location (CL-14). The'following analyses were performed:
June 13, 2015, IR 02515452 The ODCM air samplers CL-2 and CL-3 lost power some time on or before June 13, 2015 at 0230 hours when first observed by a Station Security Officer (IR #02514143). Both air sample stations now have back-up generator power, returning both sample stations to service. Minimum sample volume was not collected for that sampling period.
Gross Beta Monthly samples were analyzed for concentrations of gross beta (Tables C-11.1, Appendix C). No Gross beta was detected in any of the samples. Page 20 of 138 .. .----"* *-*
July 29, 2015, IR 02534576
Tritium Monthly samples were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). No tritium was detected in any samples and the required LLD was met. lodine-131 Monthly samples from location CL-14 were analyzed for 1-131 activity (Table C-11.3, Appendix C). No 1-131 was detected in any samples and the required LLD was met. Gamma Spectrometry  
              -- - During the Weekly Sample Collection Surveillance it was discovered that the two (2) recently changed out Environmental DLRs for CL-51, placed there on June 25, 2015 as part of the 3rd .
* * *** ' Monthly samples Were ana.lyzed for gamma emitting nu elides (Table C-11.4, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. 3. Well Water Quarterly grab samples were collected at two locations (CL-7D and CL-12, consisting of CL-12R [a raw water sample from this well] and CL-12T [same well water, but after treatment and available for consumption]).
*** - ~-- - * * -- Quarter Exchange, were found-missing: -The adjacent farm field's-culvert had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs, the PVC sample holder or the stanchion pole that it was connected to.
The following analyses were performed:
August 20, 2015, IR 02546978 While performing the Weekly OCDM Surveillance on Wednesday, 08/26/15 for the collection of particulate filters and iodine cartridges, it was discovered that there was no electrical power to CL-8. Instead of the typical run time of approximately 168 hours, the timer registered 19 hours and 36 minutes. The minimum volume was not reached for that sample.
Tritium Samples from all locations were analyzed for tritium activity {Table C-111.1, Appendix C). No tritium was detected in any samples and the required LLD was met. Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. 4. Fish Fish samples comprised of carp, largemouth bass, bluegill, crappie and channel catfish were collected at two locations (CL-19 and CL-105) semiannually.
September 24, 2015, IR 02560026 1
The following analysis was performed: Page 21 of 138 Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. .5. Shoreline Sediment Aquatic shoreline sediment samples were collected at CL-78 and CL-105 semiannually.
During the 4 h Quarter Exchange of Environmental DLRs, it was discovered the CL-46 dosimeters placed on 06/25/15 as part of the 3rd Quarter Exchange were found missing. The adjacent farm field had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs or the PVC sample holder, but the stanchion pole was found lying in the field.
The following analysis was performed:
Program exceptions were reviewed to understand the causes of the exception and to return to ODCM sample compliance before the next sampling frequency period.
Gamma Spectrometry Shoreline  
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
*seaiment samples were analyzed for gamma emitting--*
Page 19of138
nuclides (Table C-V.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met. B. Atmospheric Environment
 
: 1. Airborne a. Air Particulates Continuous air particulate samples were collected from 10 locations on a weekly basis. The 10 locations were separated into three groups: Group I represents locations within one mile of the CPS site boundary (CL-2, CL-3, CL-4, CL-6, CL-15 and CL-94); Group II represents the locations at an intermediate distance within one to five miles of CPS (CL-1, CL-7 and CL-8); and Group Ill represents the control location greater than five miles from CPS (CL-11). The following analyses were performed:
E. Program Changes There were no changes to the program in 2015.
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-Vl.1 and C-Vl.2 and Figure C-1, Appendix C). Detectable gross beta activity was observed at all locations.
IV. Results and Discussion A. Aquatic Environment
Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of CPS. The results from the On-Site locations (Group I) ranged from 7 to 43 E-3 pCi/m 3 with a mean of 19 E-3 Page 22 of 138
: 1. Surface Water Composite samples were taken hourly at three locations (CL-90, CL-91 and CL-99) on a monthly schedule and grab samples were taken monthly from one location (CL-13). The following analyses _
: b. pCi/m 3. The results from the Intermediate Distance location (Group II) ranged from 6 to 42 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3. The results from the Control locations (Group Ill) ranged from 7 to 36 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3. Comparison of the 2015 air particulate data with previous years' data indicate no measurable impact from the operation of CPS. In addition, a comparison of the weekly mean values for 2014 indicate no notable differences among the three groups. Gamma Spectrometry Weekly samples were composited quarterly and analyzed '*for gamma emitting nuclides (Table C-Vl.3, Appendix C). * -NcYplant produced*radionuclides were detected and all ----required LLDs were met. Airborne Iodine Continuous air samples were collected from 10 locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94) and analyzed weekly for 1-131 (Table C-Vll.1, Appendix C). All results were less than the MDC and the required LLD was met. 2. Terrestrial
were performed.- -                   ----. --                           .. .----"* *-*
: a. Milk Samples were collected from CL-116 biweekly May tnrough October to coincide with the grazing season, and monthly November through April. The following analyses were performed:
lodine-131 Monthly samples from location CL-90 were analyzed for 1-131 activity (Table C-1.1, Appendix C). No 1-131 was detected in any samples and the required LLD was met.
lodine-131 Milk samples were analyzed for concentrations of 1-131 (Table C-Vlll.1, Appendix C). lodine-131 was not detected in any of the samples. The required LLD was met. Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.2, Appendix C). Naturally occurring K-40 activity was found in all samples. Page 23 of 138 No plant produced radionuclides were detected and all required LLDs were met. b. Food Products Broad leaf vegetation samples were collected from four locations (CL-114, and CL-118) monthly June through September to coincide with the harvest season. The following analysis was performed:
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.2, Appendix C). No tritium was detected in any samples and the required LLD was met.
Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). No plant produced radionuclides were detected and all required----** *-0-LLDs were met. c. Grass Samples were collected from four locations (CL-1, CL-2, CL-8, and CL-116) biweekly May through October. The following analysis was performed:
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
: 2. Drinking Water Monthly composite samples were taken hourly at one location (CL-14). The'following analyses were performed:
Gross Beta Monthly samples were analyzed for concentrations of gross beta (Tables C-11.1, Appendix C). No Gross beta was detected in any of the samples.
Page 20 of 138
 
Tritium Monthly samples were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). No tritium was detected in any samples and the required LLD was met.
lodine-131 Monthly samples from location CL-14 were analyzed for 1-131 activity (Table C-11.3, Appendix C). No 1-131 was detected in any samples and the required LLD was met.
Gamma Spectrometry
* c~* * ***   ' Monthly samples Were ana.lyzed for gamma emitting nu elides (Table C-11.4, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
: 3. Well Water Quarterly grab samples were collected at two locations (CL-7D and CL-12, consisting of CL-12R [a raw water sample from this well]
and CL-12T [same well water, but after treatment and available for consumption]). The following analyses were performed:
Tritium Samples from all locations were analyzed for tritium activity {Table C-111.1, Appendix C). No tritium was detected in any samples and the required LLD was met.
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
: 4. Fish Fish samples comprised of carp, largemouth bass, bluegill, crappie and channel catfish were collected at two locations (CL-19 and CL-105) semiannually. The following analysis was performed:
Page 21 of 138
 
Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C).
No plant produced radionuclides were detected and all required LLDs were met.
  .5. Shoreline Sediment Aquatic shoreline sediment samples were collected at CL-78 and CL-105 semiannually. The following analysis was performed:
Gamma Spectrometry Shoreline *seaiment samples were analyzed for gamma emitting--*
nuclides (Table C-V.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
B. Atmospheric Environment
: 1. Airborne
: a. Air Particulates Continuous air particulate samples were collected from 10 locations on a weekly basis. The 10 locations were separated into three groups: Group I represents locations within one mile of the CPS site boundary (CL-2, CL-3, CL-4, CL-6, CL-15 and CL-94); Group II represents the locations at an intermediate distance within one to five miles of CPS (CL-1, CL-7 and CL-8); and Group Ill represents the control location greater than five miles from CPS (CL-11). The following analyses were performed:
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-Vl.1 and C-Vl.2 and Figure C-1, Appendix C).
Detectable gross beta activity was observed at all locations.
Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of CPS. The results from the On-Site locations (Group I) 3 ranged from 7 to 43 E-3 pCi/m with a mean of 19 E-3 Page 22 of 138
 
pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from 6 to 42 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3 . The results from the Control locations (Group Ill) ranged from 7 to 36 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3 . Comparison of the 2015 air particulate data with previous years' data indicate no measurable impact from the operation of CPS. In addition, a comparison of the weekly mean values for 2014 indicate no notable differences among the three groups.
Gamma Spectrometry Weekly samples were composited quarterly and analyzed
        '*for gamma emitting nuclides (Table C-Vl.3, Appendix C).
      * - NcYplant produced*radionuclides were detected and all --- -
required LLDs were met.
: b.      Airborne Iodine Continuous air samples were collected from 10 locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94) and analyzed weekly for 1-131 (Table C-Vll.1, Appendix C). All results were less than the MDC and the required LLD was met.
: 2. Terrestrial
: a.     Milk Samples were collected from CL-116 biweekly May tnrough October to coincide with the grazing season, and monthly November through April. The following analyses were performed:
lodine-131 Milk samples were analyzed for concentrations of 1-131 (Table C-Vlll.1, Appendix C). lodine-131 was not detected in any of the samples. The required LLD was met.
Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.2, Appendix C).
Naturally occurring K-40 activity was found in all samples.
Page 23 of 138
 
No plant produced radionuclides were detected and all required LLDs were met.
: b.           Food Products Broad leaf vegetation samples were collected from four locations (CL-114, CL~115, CL~117 and CL-118) monthly June through September to coincide with the harvest season. The following analysis was performed:
Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). No
              -~---***"  plant produced radionuclides were detected and all required- - -- ** *-0
                                                                                                  -
LLDs were met.
: c.           Grass Samples were collected from four locations (CL-1, CL-2, CL-8, and CL-116) biweekly May through October. The following analysis was performed:
Gamma Spectrometry Each grass sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.2, Appendix C). No plant produced radionuclides were detected and all required
Gamma Spectrometry Each grass sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.2, Appendix C). No plant produced radionuclides were detected and all required
* LLDs were met. C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing DLRs. Fifty-four DLR locations were established around the site. Results of DLR mea.surements are listed in Tables C-X.1 to C-X.3, Appendix C. A total of 214 OSLO measurements were made in 2015. The average dose from the inner ring was 23.4 mRem/quarter.
* LLDs were met.
The average dose from the outer ring was 23.8 mRem/quarter.
C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing DLRs. Fifty-four DLR locations were established around the site. Results of DLR mea.surements are listed in Tables C-X.1 to C-X.3, Appendix C.
The average dose from the special interest group was 23.1 mRem/quarter.
A total of 214 OSLO measurements were made in 2015. The average dose from the inner ring was 23.4 mRem/quarter. The average dose from the outer ring was 23.8 mRem/quarter. The average dose from the special interest group was 23.1 mRem/quarter. The average dose from the supplemental group was 22.1 mRem/quarter. The quarterly measurements ranged from 17.3 to 28.0 mRem/quarter.
The average dose from the supplemental group was 22.1 mRem/quarter.
The inner ring and outer ring measurements compared well to the Control Station, CL-11, which ranged from 19.9 mRem/quarter to 23.6 Page 24 of 138
The quarterly measurements ranged from 17.3 to 28.0 mRem/quarter.
 
The inner ring and outer ring measurements compared well to the Control Station, CL-11, which ranged from 19.9 mRem/quarter to 23.6 Page 24 of 138 mRem/quarter with an average measurement of 21.9 mRem/quarter.
mRem/quarter with an average measurement of 21.9 mRem/quarter. A comparison of the Inner Ring and Outer Ring data to the Control Location data indicate that the ambient gamma radiation levels from all the locations were comparable. The historical ambient gamma radiation data from the control location were plotted along with similar data from the Inner and Outer Ring Locations (Figure C-2, Appendix C).
A comparison of the Inner Ring and Outer Ring data to the Control Location data indicate that the ambient gamma radiation levels from all the locations were comparable.
D. Land Use Survey A Land Use Survey conducted during the July through October 2015 growing season around the Clinton Power Station (CPS) was performed by Environmental Inc. (Midwest Labs) for Exelon to comply with Clinton's Offsite Dose Calculation Manual, section 8.0. The purpose of the survey was to document the nearest resident, milk producing animal and garden 2
The historical ambient gamma radiation data from the control location were plotted along with similar data from the Inner and Outer Ring Locations (Figure C-2, Appendix C). D. Land Use Survey E. A Land Use Survey conducted during the July through October 2015 growing season around the Clinton Power Station (CPS) was performed by Environmental Inc. (Midwest Labs) for Exelon to comply with Clinton's Offsite Dose Calculation Manual, section 8.0. The purpose of the survey was to document the nearest resident, milk producing animal and garden *of-greater than 538 m 2 in each of the sixteen 22 % degree sectors-around the site. The distance and direction of all locations from the CPS Station HVAC vent stack were positioned using Global Positioning System (GPS) technology.
  *of-greater than 538 m in each of the sixteen 22 % degree sectors-around the site. The distance and direction of all locations from the CPS Station HVAC vent stack were positioned using Global Positioning System (GPS) technology. There were no changes required to the CPS REMP as a result of the Land Use Survey. The results of this survey are summarized below.
There were no changes required to the CPS REMP as a result of the Land Use Survey. The results of this survey are summarized below. Distance in Kilometers from the CPS Station HVAC Vent Stack Sector Residence Garden Milk Animal (km) (km) (km) 1 N 1.5 1.5 1.5 2 NNE 1.5 1.5 >8 3 NE 2.1 3.5 >8 4 ENE 2.9 2.9 >8 5 E 1.7 1.7 >8 6 ESE 5.1 5.3 >8 7 SE 4.4 >8 >8 8 SSE 2.9 4.3 >8 9 s 4.8 4.8 6.6 10SSW 4.7 >8 5.5 11 SW 1.2 5.9 >8 12WSW 3.6 3.7 5.5 13W 2.0 3.2 >8 14WNW 2.6 2.6 >8 15NW 2.7 4.7 >8 16NNW 2.1 2.1 2.1 Errata Data There was no errata data for 2015. Page 25 of 138 F. Summary of Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of -air particulate, air iodine, milk, soil, vegetation and water matrices for 25 analytes (Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:
Distance in Kilometers from the CPS Station HVAC Vent Stack Sector       Residence         Garden       Milk Animal (km)             (km)           (km) 1 N               1.5             1.5             1.5 2 NNE             1.5             1.5             >8 3 NE             2.1             3.5             >8 4 ENE             2.9             2.9             >8 5 E               1.7             1.7             >8 6 ESE             5.1             5.3             >8 7 SE             4.4             >8             >8 8 SSE             2.9             4.3             >8 9 s               4.8             4.8             6.6 10SSW             4.7             >8             5.5 11 SW             1.2             5.9             >8 12WSW             3.6             3.7             5.5 13W               2.0             3.2             >8 14WNW             2.6             2.6             >8 15NW               2.7             4.7             >8 16NNW             2.1             2.1             2.1 E. Errata Data There was no errata data for 2015.
: 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TB E's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal -
Page 25 of 138
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 Acceptance Limits, as applicable.
F. Summary of     Results~  Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of
The acceptance limits are either determined by a regression equation speeific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
  -air particulate, air iodine, milk, soil, vegetation and water matrices for 25 analytes (Appendix D). The PE samples, supplied by Analytics Inc.,
3.* DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. The MAPEP defines three levels of performance:
Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria:
Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/- 20% to +/- 30% of the reference value (i.e., 20% < bias< 30%). If the bias is greater than 30%, the results are deemed not acceptable.
: 1.     Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TB E's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal
For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria.
    - ----~--QC requirements,-which are based on-the DOE MAPEP criteria. -
Ten analyses (AP -Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water -Ni:-3, Sr-89, Sr-90, and U natural; Vegetation Page 26 of 138 Sr-90 samples) did not meet the specified acceptance criteria for the following reasons: -Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained 1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (acceptable with warning) was exceeded.
: 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 Perform~nce Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation speeific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the __
3.*     DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.
half .,.life (27. 7 :days) and the lowest.gamma energy_(320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations).
The MAPEP defines three levels of performance: Acceptable
This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable.
                  =                                        =
NCR 15-18 2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr .. 90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested st;imple utilized for analysis.
(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.
The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 -553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13 3. Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper acceptance range of 0.0202 Sq/sample.
For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria. Ten analyses (AP - Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water - Ni:-3, Sr-89, Sr-90, and U natural; Vegetation Page 26 of 138
Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered Page 27 of 138 acceptable.
 
MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233.
Sr-90 samples) did not meet the specified acceptance criteria for the following reasons:
Due to the extremely low activity, it was difficult to quantify the U-234/233.
        -     Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained
NCR 15-13 4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the. lower acceptance range of 0.53 Sq/sample.
: 1.           Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (acceptable with warning) was exceeded. The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the
The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard.
__ --*~ ----.~"""'- ~: ~- -~shortest half.,.life (27. 7:days) and the lowest.gamma energy_(320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations). This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable. NCR 15-18
The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency.
: 2.           Teledyne Brown Engineering's MAPEP March 2015 soil Sr.. 90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested st;imple utilized for analysis. The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -
When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and . --cannot escape to be-counted.--When the sample-media absorbs--the alpha particles this is known as self-absorption or attenuation.
1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 - 553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13
The calibration must include a similar configuration/media to correct for the attenuation.
: 3.           Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper acceptance range of 0.0202 Sq/sample. Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered Page 27 of 138
In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters. The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24 -1.53 Sq/sample.
 
Unlike the MAPEP samples, air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed.
acceptable. MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233. Due to the extremely low activity, it was difficult to quantify the U-234/233. NCR 15-13
NCR 15-13 5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21 6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample.
: 4.       Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the. lower acceptance range of 0.53 Sq/sample. The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and
In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for Page 28 of 138 the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.
  . - - cannot escape to be-counted.--When the sample-media absorbs- -
TBE will no longer analyze the air particulate through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21 7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the lower acceptance range of 0.91 Sq/sample.
the alpha particles this is known as self-absorption or attenuation.
In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incompl_ete removal of the isotope of interest for -the-laboratories analyi:ing-the:cross checks.' TBE suspects-thatthis maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.
The calibration must include a similar configuration/media to correct for the attenuation. In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters.
Results from previous performance evaluations were reviewed and shown to be acceptable.
The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24
NCR 15-21 8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively.
        - 1.53 Sq/sample. Unlike the MAPEP samples, air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed. NCR 15-13
The yields -were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09 10. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L. The technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the EIML laboratory, 90 of 94 analyses met the specified acceptance criteria.
: 5.       Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21
Four analyses (Water-Co-57, Fe-55; AP -Co-57; Soil -Sr-90) did not meet the specified acceptance criteria for the following reasons: 1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L. The reported value should have been 27.84, which would have Page 29 of 138 been evaluated as acceptable.
: 6.       Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for Page 28 of 138
A data entry error resulted in a non-acceptable result. 2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1,06 Sq/sample.
 
The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable.
the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity. TBE will no longer analyze the air particulate Sr~90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21
A data entry error resulted in a non-acceptable result. 3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed "-----:-c -low result.' -The reanalysis result of 352 Bq/kg fell within ":--acceptance criteria.
: 7.       Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the lower acceptance range of 0.91 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incompl_ete removal of the isotope of interest for
: 4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L. The known activity was below the routine laboratory detection limits for the available aliquot fraction.
      - the-laboratories analyi:ing-the:cross checks.' TBE suspects-thatthis maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.
Results from previous performance evaluations were reviewed and shown to be acceptable. NCR 15-21
: 8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively. The yields
      - were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09
: 10.     Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L.
The technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the EIML laboratory, 90 of 94 analyses met the specified acceptance criteria. Four analyses (Water- Co-57, Fe-55; AP - Co-57; Soil - Sr-90) did not meet the specified acceptance criteria for the following reasons:
: 1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L.
The reported value should have been 27.84, which would have Page 29 of 138
 
been evaluated as acceptable. A data entry error resulted in a non-acceptable result.
: 2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1,06 Sq/sample. The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.
: 3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed
      "-- - --   :-c - low result.' -The reanalysis result of 352 Bq/kg fell within ":- -
acceptance criteria.
: 4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L.
The known activity was below the routine laboratory detection limits for the available aliquot fraction.
V. References
V. References
: 1. American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," ANSI N545-1975. 2. Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).
: 1.         American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," ANSI N545-1975.
: 3. CPS 2014 Annual Radioactive Effluent Release Report. 4. "Environmental Radioactivity," M. Eisenbud, 1987 (E187). 5. "Natural Radon Exposure in the United States," Donald T. Oakley, U.S. Environmental Protection Agency. ORP/SID 72-1, June 1972. 6. Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960. 7. International Commission on Radiation Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, "Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977). Page 30 of 138
: 2.         Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).
: 3.         CPS 2014 Annual Radioactive Effluent Release Report.
: 4.         "Environmental Radioactivity," M. Eisenbud, 1987 (E187).
: 5.         "Natural Radon Exposure in the United States," Donald T. Oakley, U.S.
Environmental Protection Agency. ORP/SID 72-1, June 1972.
: 6.         Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960.
: 7.         International Commission on Radiation Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, "Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977).
Page 30 of 138
: 8. International Commission on Radiation Protection, Publication No. 39 (1984), "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".
: 8. International Commission on Radiation Protection, Publication No. 39 (1984), "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".
: 9. * "Radioactivity in the Environment:
: 9. * "Radioactivity in the Environment: Sources, Distribution and Surveillance," Ronald L. Kathren, 1984.
Sources, Distribution and Surveillance," Ronald L. Kathren, 1984. 10. National Council on Radiation Protection and Measurements, Report No. 22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52). 11. National Council on Radiation Protection and Measurements, Report No. 39, "Basic Radiation Protection Criteria," January 1971. --12. National Council on Radiation Protection and Measurements, Report No. 44, "Krypton-85 in the Atmosphere  
: 10. National Council on Radiation Protection and Measurements, Report No.
-Accumulation, Biological Significance, and Control Technology," July 1975. 13. National Council on Radiation Protection and Measurements, Report No. 91, "Recommendations on Limits for Exposure to Ionizing Radiation," June 1987. 14. National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," September 1987. 15. National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".
22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52).
: 16. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975. 17. United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry:
: 11. National Council on Radiation Protection and Measurements, Report No.
Environmental Applications, "Revision 1, July 1977. 18. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 OCFR Part 50, Appendix I, "Revision 1, October 1977. 19. United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979. 20. United States Nuclear Regulatory Commission, Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Page 31 of 138 Operations)  
39, "Basic Radiation Protection Criteria," January 1971.
-Effluent Streams and the Environment," Revision 1, February 1979. 21. Technical Specifications, Clinton Power Station, Unit No. 1, Docket No. 50-461, Office of Nuclear Reactor Regulation, 1986. Facility Operating License Number NPF-62. 22. . Clinton Power Station, Updated Safety Analysis Report. 23. Clinton-Power Station, Unit 1, Off-Site Dose Calculation Manual. Page 32 of 138
-- 12. National Council on Radiation Protection and Measurements, Report No.
.. -. -; ---._ : -:_ -.. APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT  
44, "Krypton-85 in the Atmosphere - Accumulation, Biological Significance, and Control Technology," July 1975.
: 13. National Council on Radiation Protection and Measurements, Report No.
91, "Recommendations on Limits for Exposure to Ionizing Radiation,"
June 1987.
: 14. National Council on Radiation Protection and Measurements, Report No.
93, "Ionizing Radiation Exposure of the Population of the United States,"
September 1987.
: 15. National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".
: 16. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.
: 17. United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, "Revision 1, July 1977.
: 18. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1OCFR Part 50, Appendix I, "Revision 1, October 1977.
: 19. United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program,"
Revision 1, November 1979.
: 20. United States Nuclear Regulatory Commission, Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Page 31 of 138
 
Operations) - Effluent Streams and the Environment," Revision 1, February 1979.
: 21. Technical Specifications, Clinton Power Station, Unit No. 1, Docket No.
50-461, Office of Nuclear Reactor Regulation, 1986. Facility Operating License Number NPF-62.
: 22. . Clinton Power Station, Updated Safety Analysis Report.
: 23. Clinton- Power Station, Unit 1, Off-Site Dose Calculation Manual.
Page 32 of 138
 
                                                                                  --
                      .. - . -; - - - ._ : -:_ - ..               - - .,, ,,...._-;- - --
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT  


==SUMMARY==
==SUMMARY==
Page 33 of 138 ----.,, ,,...._-;-
 
---
Page 33 of 138
Intentionally left blank Page 34 of 138 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
 
Intentionally left blank Page 34 of 138
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 j, INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M) i 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
CLINTON POWER STATION LOCATION OF FACILITY:
  . MEASUREMENT)                                                (LLD)                                                                  MEASUREMENTS SURFACE WATER            1-131                12                    <LLD       NA                                                     0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 j, INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF . MEASUREMENT)
H-3                  16          2000    <LLD         <LLD                                                   0 GAMMA                48 MN-54                              15      <LLD       <LLD                                                   0 C0-58                              15      <LLD         <LLD                                                   0 FE-59                              30      <LLD       <LLD                                                   0 C0-60                              15      <LLD         <LLD                                                   0 ZN-65                              30      <LLD         <LLD                                                   0 "U
SURF ACE WATER (PCI/LITER) "U Ill cc m (,.) U1 0 _,, (,.) ()'.) TYPES OF ANALYSIS PERFORMED 1-131 H-3 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 12 16 48 REQUIRED LOWER LIMIT OF DETECTION (LLD) 2000 15 15 30 15 30 15 LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE  
Ill cc m
<LLD NA <LLD <LLD <LLD <LLD  
(,.)
<LLD <LLD <LLD <LLD  
U1 0_,,                          NB-95                              15      <LLD         <LLD                                                   0
<LLD <LLD <LLD <LLD  
(,.)
<LLD <LLD i MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
()'.)
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015            i NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR CONTROL         LOCATION WITH IDGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 (UNITOF                  PERFORMED        PERFORMED  OF DETECTION RANGE       RANGE        RANGE        DISTANCE AND DIRECTION  REPORTED MEASUREMENT)                                              (LLD)                                                                  MEASUREMENTS SURFACE WATER            ZR-95                              30    <LLD         <LLD                                                   0 (PCI/LITER)
DEWITT COUNTY, IL THE CLINTON POWER STATION, 2015 i DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH IDGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
CS-134                              15    <LLD         <LLD                                                   0 CS-137                              18    <LLD         <LLD                                                   0 BA-140                              60    <LLD         <LLD                                                   0 LA-140                              15    <LLD         <LLD                                                   0 CE-144                              NA    <LLD         <LLD                                                   0 DRINKING WATER          GR-B                  12            4    <LLD         NA                                                     0 "U(PCI/LITER)
SURFACE WATER (PCI/LITER)
D.l (Q
DRINKING WATER "U(PCI/LITER)
CD VJ                          H-3                    4          2000    <LLD        NA                                                      0
D.l (Q CD VJ (j) 0 --" VJ CXl TYPES OF ANALYSIS PERFORMED ZR-95 CS-134 CS-137 BA-140 LA-140 CE-144 GR-B H-3 NUMBER OF ANALYSIS PERFORMED 12 4 REQUIRED LOWER LIMIT OF DETECTION (LLD) 30 15 18 60 15 NA 4 2000 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 
-
,. TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
(j) 0
-"
VJ CXl THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
                                                                                                          ,.
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NA.ME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NA.ME OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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             I-131                12                  <LLD        NA                                                      0 (PCJJLITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
GAMMA                12 MN-54                              15      <LLD        NA                                                      0 C0-58                              15    <LLD        NA                                                      0 FE-59                              30      <LLD        NA                                                      0 C0-60                              15      <LLD        NA,                                                    0 ZN-65                              30      <LLD        NA                                                      0 NB-95                              15      <LLD        NA                                                    0
DRINKING WATER (PCJJLITER) -u Dl (Q CD (.U ---i 0 -_,,. (.U Ol TYPES OF ANALYSIS PERFORMED I-131 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 NUMBER OF ANALYSIS PERFORMED 12 12 REQUIRED LOWER LIMIT OF DETECTION (LLD) 15 15 30 15 30 15 30 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE NA NA NA NA NA, NA NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMANNUAL  
-u Dl (Q
CD
(.U
-
---i 0
_,,.
(.U Ol ZR-95                             30     <LLD         NA                                                     0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
LOCATIONS LOCATION MEDIUM OR                 TYPES OF          NUMBER OF    REQU1RED  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           CS-134                              15      <LLD        NA                                                      0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
CS-137                             18      <LLD        NA                                                      0 BA-140                             60      <LLD        NA                                                      0 LA-140                             15      <LLD        NA                                                      0 CE-144                             NA      <LLD        NA                                                      0 WELL WATER              H-3                   12          2000    <LLD        NA                                                    0 (PCI/LITER)
DRINKING WATER (PCI/LITER)
GAMMA                 12 MN-54                               15      <LLD        NA                                                      0
WELL WATER (PCI/LITER)  
"'U Ill cc CD w
"'U Ill cc CD w OJ 0 -....>. w OJ TYPES OF ANALYSIS PERFORMED CS-134 CS-137 BA-140 LA-140 CE-144 H-3 GAMMA MN-54 C0-58 NUMBER OF ANALYSIS PERFORMED 12 12 REQU1RED LOWER LIMIT OF DETECTION (LLD) 15 18 60 15 NA 2000 15 15 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE NA NA NA NA NA NA NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
-
OJ 0                              C0-58                               15     <LLD         NA                                                     0
....>.
w OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 WELL WATER               FE-59                              30      <LLD        NA                                                      0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
C0-60                              15      <LLD        NA                                                      0 ZN-65                              30      <LLD        NA                                                      0
WELL WATER (PCI/LITER)  
)>
)> I C.11 "U m cc <D (,.) (.0 0 --+> (,.) CX> TYPES OF ANALYSIS PERFORMED FE-59 C0-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 NUMBER OF ANALYSIS PERFORMED REQUIRED LOWER LIMIT OF DETECTION (LLD) 30 15 30 15 30 15 18 60 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE NA NA NA NA NA NA NA NA MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
I C.11 NB-95                              15      <LLD        NA                                                      0 ZR-95                              30      <LLD        NA                                                      0 CS-134                              15      <LLD        NA                                                      0 CS-137                              18      <LLD        NA                                                      0 "U
m cc
<D
(,.)
(.0                          BA-140                              60      <LLD        NA                                                      0 0
--+>
(,.)
CX>
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION .                     DOCKET NUMBER:           50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION . DOCKET NUMBER: 50-461 LOCATION OF FACILITY:
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 (UNITOF                  PERFORMED        PERFORMED  OF DETECTION RANGE         RANGE       RANGE         DISTANCE AND DIRECTION   REPORTED j
DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
MEASUREMENT)                                              (LLD)                                                                  MEASUREMENTS
WELL WATER (PCI/LITER)
                                                                                                        "
FISH :P-(PCI/KG WET) O') "U Ill co CD .i:. 0 0 -n _,. w ()) TYPES OF ANALYSIS PERFORMED LA-140 CE-144 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 16 REQUIRED LOWER LIMIT OF DETECTION (LLD) 15 NA 130 130 260 130 260 NA LOCATIONS LOCATION MEAN(M) MEAN(M) MEAN(M) STATION# (F) (F) (F) NAME RANGE RANGE RANGE DISTANCE AND DIRECTION j " <LLD NA <LLD NA <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD " <LLD <LLD <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
WELL WATER              LA-140                              15    <LLD         NA                                                      0 (PCI/LITER)
CE-144                            NA       <LLD         NA                                                     0 FISH                    GAMMA                16
:P-(PCI/KG WET)              MN-54                              130      <LLD         <LLD                                                   0 O')
C0-58                              130      <LLD       <LLD                                                   0 FE-59                              260      <LLD         <LLD                                                   0 C0-60                              130    <LLD         <LLD                                                   0
                                                                                                        "
ZN-65                              260    <LLD         <LLD                                                   0 "U
Ill co CD
.i:.
0 0                            NB-95                              NA      <LLD         <LLD                                                   0
-n
_,.
w
())
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCA;noN WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 MEASURE.tvIBNT)                                            (LLD)                                                                  MEASUREMENTS FISH                    ZR-95                              NA      <LLD         <LLD                                                   0 (PCI/KG WET)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCA;noN WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASURE.tvIBNT)
CS-134                            130      <LLD         <LLD                                                   0 CS-137                            150      <LLD         <LLD                                                   0 BA-140                            NA      <LLD         <LLD                                                   0 LA-140                            NA      <LLD         <LLD                                                   0 CE-144                            NA      <LLD         <LLD                                                   0 SEDIMENT                GAMMA                  4 "1J(PCI/KG DRY)                MN-54                              NA      <LLD         <LLD               :i' I*                                   0 Dl
FISH (PCI/KG WET) SEDIMENT "1J(PCI/KG DRY) Dl (.Q m .j:>. ....>. 0 -....>. w 00 TYPES OF ANALYSIS PERFORMED ZR-95 CS-134 CS-137 BA-140 LA-140 CE-144 GAMMA MN-54 C0-58 NUMBER OF ANALYSIS PERFORMED 4 REQUIRED LOWER LIMIT OF DETECTION (LLD) NA 130 150 NA NA NA NA NA LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE :i' I* STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
(.Q m
.j:>.
-
....>.
0                              C0-58                              NA      <LLD        <LLD                                                  0
....>.
w 00 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH IDGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
LOCATIONS LOCATION            I 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 MEASUREJ\1ENT)                                            (LLD)                                                                  MEASUREMENTS SEDIMENT                FE-59                              NA      <LLD         <LLD                                                   0 (PCI/KG DRY)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH IDGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREJ\1ENT)
C0-60                              NA      <LLD         <LLD                                                   0 ZN-65                              NA      <LLD         <LLD                                                   0 NB-95                              NA      <LLD         <LLD                                                   0 ZR-95                              NA      <LLD         <LLD                                                   0 CS-134                            150    <LLD         <LLD                                                   0 CS-137                            180    <LLD         <LLD                                                   0
""CJ Q) cc CD N 0 ..... (;.) OJ SEDIMENT (PCI/KG DRY) TYPES OF ANALYSIS PERFORMED FE-59 C0-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 NUMBER OF ANALYSIS PERFORMED REQUIRED LOWER LIMIT OF DETECTION (LLD) NA NA NA NA NA 150 180 NA LOCATIONS LOCATION I MEAN(M) MEAN(M) MEAN(M) ' STATION# (F) (F) (F) NAME RANGE RANGE RANGE DISTANCE AND DIRECTION  
""CJ Q) cc CD
<LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
~                            BA-140                            NA      <LLD         <LLD                                                   0 N
0
.....
(;.)
OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:       2015 :
CLINTON POWER STATION LOCATION OF FACILITY:
INDICATOR CONTROL        LOCATION WITH IDGHEST ANNUAL MEAN (M)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 : MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
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                LA-140                            NA       <LLD         <LLD                                                           0 (PCI/KG DRY)
SEDIMENT (PCI/KG DRY) AIR PARTICULATE
CE-144                            NA       <LLD         <LLD                                                           0 AIR PARTICULATE        GR-B                  514          JO      19          19          20            CL-3 INDICATOR                      0
:P-CE-3 PCI/CUMETER) c.o iJ Ill ca CD .i:.. w 0 __,, __. w OJ TYPES OF ANALYSIS PERFORMED LA-140 CE-144 GR-B GAMMA C0-60 NB-95 ZR-95 RU-103 RU-106 NUMBER OF ANALYSIS PERFORMED 514 40 INDICATOR LOCATIONS REQUIRED MEAN(M) LOWER LIMIT (F) OF DETECTION RANGE (LLD) NA <LLD NA <LLD JO 19 (462/462)
:P-CE-3 PCI/CUMETER)                                                       (462/462)   (52/52)     (50/50)       CLINTON'S SECONDARY ACCESS ROAD c.o                                                                        (6/43)     (7/36)       (9/43)       0.7 MILES NE OF SITE GAMMA                40 C0-60                              NA      <LLD        <LLD                                                            0 NB-95                              NA      <LLD        <LLD                                                          0 ZR-95                              NA      <LLD        <LLD                                                          0 RU-103                            NA      <LLD        <LLD                                                            0 iJ Ill ca CD
(6/43) NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD CONTROL LOCATION MEAN(M) (F) RANGE <LLD <LLD 19 (52/52) (7/36) <LLD <LLD <LLD <LLD <LLD* LOCATION WITH IDGHEST ANNUAL MEAN (M) MEAN(M) (F) RANGE 20 (50/50) (9/43) STATION# NAME DISTANCE AND DIRECTION CL-3 INDICATOR NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 CLINTON'S SECONDARY ACCESS ROAD 0.7 MILES NE OF SITE 0 0 0 0 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
.i:..
w
__,,
0                             RU-106                            NA      <LLD        <LLD*                                                          0
__.
w OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 INDICATOR CONTROL       LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 MEASURElv!ENT)                                             (LLD)                                                                  MEASUREMENTS AIR PARTICULATE         CS-134                              50      <LLD        <LLD                                                  0 (E-3 PCI/CU.METER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASURElv!ENT)
CS-137                              60      <LLD        <LLD                                                  0 CE-141                            NA      <LLD        <LLD                                                  0 CE-144                            NA      <LLD        <LLD                                                  0 AIR IODINE               GAMMA                514 (E-3 PCI/CUMETER)       I-131                              70      <LLD        <LLD                                                  0 MILK                     I-131                  19                  NA          <LLD                                                  0 (PCI/LITER)
AIR PARTICULATE (E-3 PCI/CU.METER)
GAMMA                 19 MN-54                             NA       NA           <LLD                                                   0 C0-58                              NA       NA           <LLD                                                   0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
AIR IODINE (E-3 PCI/CUMETER)
 
MILK (PCI/LITER)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
TYPES OF ANALYSIS PERFORMED CS-134 CS-137 CE-141 CE-144 GAMMA I-131 I-131 GAMMA MN-54 C0-58 NUMBER OF ANALYSIS PERFORMED 514 19 19 REQUIRED LOWER LIMIT OF DETECTION (LLD) 50 60 NA NA 70 NA NA LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD NA NA NA LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                             REPORTING PERIOD:       2015 '~
CLINTON POWER STATION LOCATION OF FACILITY:
INDICATOR CONTROL       LOCAfrION WITH HIGHEST ANNUAL MEAN (M)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCAfrION WITH HIGHEST ANNUAL MEAN (M) '' MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
LOCATIONS LOCATION            ''
MILK (PCIILITER) "U D> cc m C.11 0 --" (JJ 00 TYPES OF NUMBER OF REQUIRED ANALYSIS ANALYSIS LOWER LIMIT PERFORMED PERFORMED OF DETECTION (LLD) FE-59 NA C0-60 NA ZN-65 NA NB-95 NA ZR-95 NA CS-134 _ 15 CS-137 18 BA-140 60 LOCATIONS LOCATION MEAN(M) MEAN(M) (F) (F) RANGE RANGE NA <LLD NA <LLD NA <LLD .NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD MEAN(M) (F) RANGE i, ,. 1 1. STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING Tf,JE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ; NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
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 (UNITOF                  PERFORMED         PERFORMED   OF DETECTION RANGE        RANGE        RANGE          DISTANCE AND DIRECTION  REPORTED MEASUREMENT)                                                (LLD)                                   i,                              MEASUREMENTS
                                                                                                          ,.
MILK                    FE-59                             NA      NA           <LLD                                                    0 (PCIILITER)
C0-60                             NA      NA         <LLD                                                    0 ZN-65                             NA       NA          <LLD                                                    0 NB-95                             NA      .NA           <LLD                                                    0 ZR-95                             NA       NA          <LLD                                                    0 CS-134 _                           15     NA          <LLD                                                    0 CS-137                             18     NA          <LLD                                                    0 "U
D>
cc m
~                            BA-140                             60     NA           <LLD               1                                    0
-C.11 0
-"
(JJ 00 1.
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING Tf,JE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED
                                                                                                          ;
IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                       DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR     CONTROL     LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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                     LA-140                              15    NA          <LLD                                                    0 (PCI/LITER)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
CE-144                            NA      NA            <LLD                                                  0
MILK (PCI/LITER)  
)>VEGETATION                   GAMMA                48
)>VEGETATION (PCI/KG WET) N -u Dl cc CD (J) 0 -....>. w ()'.) TYPES OF ANALYSIS PERFORMED LA-140 CE-144 GAMMA MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 NUMBER OF ANALYSIS PERFORMED 48 REQUIRED LOWER LIMIT OF DETECTION (LLD) 15 NA NA NA NA NA NA NA LOCATIONS MEAN(M) (F) RANGE NA NA <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
~ (PCI/KG WET)                 MN-54                             NA      <LLD        <LLD                                                    0 N
C0-58                             NA      <LLD          <LLD                                                  0 FE-59                             NA       <LLD         <LLD                                                   0 C0-60                              NA      <LLD         <LLD                                                   0 ZN-65                              NA      <LLD         <LLD                                                   0
-u Dl cc CD
~
-
(J) 0                              NB-95                              NA      <LLD         <LLD                                                   0
....>.
w
()'.)
THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME.OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME.OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:            50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR CONTROL         LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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 (UNITOF                 PERFORMED        PERFORMED  OF DETECTION RANGE        RANGE        RANGE        DISTANCE AND DIRECTION  REPORTED MEASUREMENT)                                               (LLD)                                                                  MEASUREMENTS VEGETATION             ZR-95                              NA      <LLD        <LLD                                                    0 (PCI/KG WET)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNITOF MEASUREMENT)
I-131                              60    <LLD        <LLD                                                    0 CS-134                              60    <LLD        <LLD                                                    0
VEGETATION (PCI/KG WET) )> I _... (...) "'U Dl cc CD ::!'.JGRASS o (PCI/KG WET) -....>. (,,) OJ TYPES OF ANALYSIS PERFORMED ZR-95 I-131 CS-134 CS-137 BA-140 LA-140 CE-144 GAMMA MN-54 NUMBER OF ANALYSIS PERFORMED 52 REQUIRED LOWER LIMIT OF DETECTION (LLD) NA 60 60 80 NA NA NA NA LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
)>
_...
I
(...)
CS-137                              80    <LLD        <LLD                                                    0 BA-140                            NA      <LLD        <LLD                                                    0 LA-140                            NA      <LLD        <LLD                                                    0 CE-144                            NA      <LLD        <LLD                                                    0
"'U Dl cc CD
::!'.JGRASS                   GAMMA                52
-
o (PCI/KG WET)
....>.
(,,)
OJ MN-54                               NA     <LLD         <LLD                                                   0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                     DOCKET NUMBER:            50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                           REPORTING PERIOD:         2015 INDICATOR CONTROL         LOCATION WITH HIGHEST ANNUAL MEAN (M)
CLINTON POWER STATION LOCATION OF FACILITY:
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
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
                                                                                                          !
GRASS (PCI/KG WET) )> I ...... ""'O Dl co CD Ol 0 --" (,.) Ol TYPES OF ANALYSIS PERFORMED C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 I-131 CS-134 NUMBER OF ANALYSIS PERFORMED REQUIRED LOWER LIMIT OF DETECTION (LLD) NA NA NA NA NA NA 60 60 LOCATIONS MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD LOCATION MEAN(M) (F) RANGE <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD MEAN(M) (F) RANGE ! STATION# NAME DISTANCE AND DIRECTION THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 0 TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  
MEASUREMENT)                                              (LLD)                                                                  MEASUREMENTS GRASS                  C0-58                              NA      <LLD         <LLD                                                   0 (PCI/KG WET)
FE-59                              NA      <LLD         <LLD                                                   0 C0-60                              NA      <LLD         <LLD                                                   0
)>
......
I
~
ZN-65                              NA      <LLD         <LLD                                                   0 NB-95                              NA      <LLD         <LLD                                                   0 ZR-95                              NA      <LLD         <LLD                                                   0 I-131                              60      <LLD         <LLD                                                   0
""'O Dl co CD
~                            CS-134                              60      <LLD         <LLD                                                   0
-
Ol 0
-"
(,.)
Ol THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
 
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL  


==SUMMARY==
==SUMMARY==
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY:
FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION                      DOCKET NUMBER:          50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL                            REPORTING PERIOD:        2015 '
CLINTON POWER STATION LOCATION OF FACILITY:
INDICATOR CONTROL        LOCATION WITH HIGHEST ANNUAL MEAN (M)
DEWITT COUNTY, IL DOCKET NUMBER: REPORTING PERIOD: 50-461 2015 ' INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
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 GRASS                  CS-137                              80      <LLD        <LLD                                                  0 (PCI/KG WET)
)> I ...... C.J1 -u Dl cc CD .!:>. <.O 0 -....>. w OJ GRASS (PCI/KG WET) DIRECT
BA-140                            NA      <LLD        <LLD                                                  0 LA-140                            NA      <LLD        <LLD                                                  0
)>
......
I C.J1 CE-144                            NA      <LLD        <LLD                                                  0 DIRECT RADIATION        DLR-QUARTERLY        214          NA      23.2        21.9        25.3          CL-51 INDICATOR              0 (MILLIREM/QTR.)                                                    (210/210)  (4/4)        (3/3)
(17.3/28.0) (19.9/23.6)  (24.3/26.3)  4.4MILESNW
-u Dl cc CD
.!:>.
-
<.O 0
....>.
w OJ THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES


==SUMMARY==
==SUMMARY==
OF THE AMBIENT DOSIMETRY PROGRAM FOR CLINTON POWER STATION, 201S RESULTS IN UNITS OF MILLIREM/QUARTER  
OF THE AMBIENT DOSIMETRY PROGRAM FOR CLINTON POWER STATION, 201S RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATION LOCATION               SAMPLES PERIOD       PERIOD   PERIOD MEAN       PRE-OP MEAN ANALYZED MINIMUM MAXIMUM           +/-2 S.D.   +/- 2 S.D., ALL LOCATIONS INNER RING                 63     19.2       28.0   23.4 +/- 3.3 OUTER RING                 63     19.0       28.0   23.8 +/- 3.8         18.0 +/- 2.4 SPECIAL INTEREST           28     19.0       26.3   23.1 +/- 3.7 SUPPLEMENTAL               56     17.3       25.8   22.1 +/- 3.8 CONTROL                     4     19.9       23.6   21.9 +/- 3.0 INNER RING STATIONS - CL-01, CL-05, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42, CL-43, CL-44, CL-45, CL-46, CL-47, CL-48, CL-63 OUTER RING STATIONS - CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80, CL-81 SPECIAL INTEREST STATIONS - CL-37, CL-41, CL-49, CL-64, CL-65, CL-74, CL-75 SUPPLEMENTAL STATIONS - CL-02, CL-03, CL-04, CL-06, CL-07, CL-08, CL-114, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 CONTROL STATION - CL-11 C-24                                 Page 88 of 138
+/- 2 STANDARD DEVIATION LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN CONTROL 22.0 +/- 0.0 22.0 +/- 0.0 19.9 +/- 0.0 23.6 +/- 0.0 ANALYZED MINIMUM MAXIMUM +/-2 S.D. +/- 2 S.D., ALL LOCATIONS INNER RING 63 19.2 28.0 23.4  
 
+/- 3.3 OUTER RING 63 19.0 28.0 23.8 +/- 3.8 18.0 +/- 2.4 SPECIAL INTEREST 28 19.0 26.3 23.1 +/- 3.7 SUPPLEMENTAL 56 17.3 25.8 22.1 +/- 3.8 CONTROL 4 19.9 23.6 21.9  
FIGURE C-1 MEAN MONTHLY GROSS BETA CONCENTRATION IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CPS, 2015 0.052 0.047 0.042 0.037 M
+/- 3.0 INNER RING STATIONS -CL-01, CL-05, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42, CL-43, CL-44, CL-45, CL-46, CL-47, CL-48, CL-63 OUTER RING STATIONS -CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80, CL-81 SPECIAL INTEREST STATIONS -CL-37, CL-41, CL-49, CL-64, CL-65, CL-74, CL-75 SUPPLEMENTAL STATIONS -CL-02, CL-03, CL-04, CL-06, CL-07, CL-08, CL-114, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 CONTROL STATION -CL-11 C-24 Page 88 of 138 M E :::::: (.) c.. FIGURE C-1 M E AN MONTHLY GROSS BETA CONCENTRATION IN AIR PARTICULATE SA M PLES COLLECTED IN THE VICINITY OF CPS , 2015 0.052 0.0 4 7 0.042 0.037 0.032 0.027 0.022 0.017 0.012 0.007 0.002 -"-c,* c,* ts ts 0 v MONTH 1l!ll!!lll1ll PRE-OP (ALL SITES) _.,_2015 INDICATOR  
E
-+-2015 CONTROL C-25 Page 89 of 138 FIGURE C-2 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR) IN THE VIC I NITY OF CPS, 2015 50 45 40 35 E Q) 30 0::: E 25 20 15 10 QUARTER II PRE-OP 02015 indicator
::::::  0.032
* 2015 control C-26 Page 90 of 138 APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 91 of 138 Intentionally left blank Page 92 of 138 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF3) Identification Reported Known Ratio (c) MonthNear Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d) March 2015 E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 w E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A --* ---**--* ----. -E11184 AP Ce-141 pCi 107 85.0 1.26 w Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 Water Fe-55 pCi/L 1950 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 w Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143 125 1.14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 w Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1) Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A D-1 Page 93 of 138 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 2 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d) June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A -----, ,.. -:--. --.,,__ .. --.. ----" Zn-65 ... pCi/L *-392 353---.. 1.11 .-.A .. Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 *302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 -pCi/L __ 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A D-2 Page 94 of 138 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3) Identification Reported Known Ratio (c) MonthNear Number Matrix Nuclide Units Value (a) Value (b) TBE/Anal}'.tics Evaluation (d) December 2015 E11357 AP Ce-141 pCi 89.9 84.0 1.07 Cr-51 pCi 215 184 1.17 Cs-134 pCi 103 105 0.98 Cs-137 pCi 76.6 74.8 1.02 Co-58 pCi 76.2 71.9 1.06 Mn-54 pCi 91.4 94.4 0.97
(.)
* Fe-59 pCi 78.6 70.3 1.12 Zn-65 pCi 173 162 1.07 Co-60 pCi 138 139 0.99 E11422 AP Sr-89 pCi 98.0 96.9 1.01 Sr-90 pCi 10.0 14.0 0.71 E11356 Charcoal 1-131 pCi 74.9 75.2 1.00 E11358 Water Fe-55 pCi/L 2160 1710 1.26 E11353 Soil Ce-141 pCi/kg 252 222 1.14 Cr-51 pCi/kg 485 485 1.00 Cs-134 pCi/kg 319 277 1.15 Cs-137 pCi/kg 292 276 1.06 Co-58 pCi/kg 193 190 1.02 Mn-54 pCi/kg 258 250 1.03 Fe-59 pCi/kg 218 186 1.17 Zn-65 pCi/kg 457 429 1.07 Co-60 pCi/kg 381 368 1.04 (1) AP Cr-51 -Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable.
c..
NCR 15-18 (a) Teledyne Brown Engineering reported result. (b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) Ratio of Teledyne Brown Engineering to Analytics results. (d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1.20. W-Acceptable with 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. A A A A A A A A A A w A w A A A A A A A A A D-3 Page 95 of 138 TABLE D-2 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance Month/Year Number Media Nuclide* Units Value (a) Value (b) Range Evaluation (c) March 2015 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 -0.850 A Ni-63 Sq/L 2.5 (1) A Pu-238 Sq/L 0.0204 0.0089 (2) A Pu-239/240 Sq/L 0.9 0.8 0.582 -1.082 A 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314-582 A Sr-90 Sq/kg 286 653 487 -849 N (3) 15-RdF32 AP Sr-90 Sq/sample  
0.027 0.022 0.017 0.012 0.007 0.002
-0.0991 (1) A U-234/233 Sq/sample 0.0211 0.0155 0.0109 -0.0202 N (3) U-238 Sq/sample 0.095 0.099 0.069-0.129 A 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53 -3.01 N (3) Gr-S Sq/sample 0.7580 0.75 0.38 -.1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12 -9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 -11.93 w Co-57 Sq/sample  
              ~*  ~*  ~*  ~*
-0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 -7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample 0.999 1.08 0.76 -1.40 A Zn-65 Sq/sample  
            ")~  <l~ ~'if  ~  ~~
-0.108 (1) A September 2015 15-MaW33 Water Am-241 Sq/L 1.012 1.055 0. 739 -1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4) Pu-238 Sq/L 0.727 0.681 0.477 -0.885 A Pu-239/240 Sq/L 0.830 0.900 0.630-1.170 A 15-MaS33 Soil Ni-63 Sq/kg 635 682 477 -887 A Sr-90 Sq/kg 429 425 298 -553 A 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53 -2.83 N (4) U-234/233 Sq/sample 0.143 0.143 0.100-0.186 A U-238 Sq/sample 0.149 0.148 0.104-0.192 A 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 A Gr-S Sq/sample 1.34 1.56 0.78 -2.34 A 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06 -7.54 A Cs-137 Sq/sample 0.0002 (1) A Co-57 Sq/sample 8.01 6.62 4.63 -8.61 w Co-60 Sq/sample 4.97 4.56 3.19-5.93 A Mn-54 Sq/sample 8.33 7.68 5.38 -9.98 A Sr-90 Sq/sample 0.386 1.30 0.91 -1.69 N (4) (1) False positive test. Zn-65 Sq/sample 6.07 5.46 3.82-7.10 A (2) Sensitivity evaluation.
                                  -"-
(3) Soil Sr-90 -incomplete digestion of the sample resulted in low results; AP U-2341233  
ts~* ts~*    c,* ~* ~. ~* c,*
-extremely low activity was difficult to quantify AP Gr-A -the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21. (a) Teledyne Brown Engineering reported result. (b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) DOEIMAPEP evaluation:
                                                      ~ ~~ 0 v ~o ~<<;
A=acceptable, W=acceptable with warning, tvo1.94acceptable.
MONTH 1l!ll!!lll1ll PRE-OP (ALL SITES)
Page 96 of 138
_.,_ 2015 INDICATOR
--* TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1) Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Limits May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 -71.2 Sr-90 pCi/L 28.0 41.9 30.8 -48.1 Ba-133 pCi/L 80.6 82.5 63.9 -90.8 Cs-134 pCi/L 71.7 75.7 61.8 -83.3 Cs-137 pCi/L 187 189 170 -210 Co-60 pCi/L 85.7 84.5 76.0 -95.3 Zn-65 pCi/L 197 203 183 -238 Gr-A pCi/L 26.1 42.6 22.1 -54.0 Gr-B pCi/L 28.8 32.9 21.3 -40.6 1-131 pCi/L 23.5 23.8 19.7 -28.3 U-Nat pCi/L 6.19 6.59 4.99 -7.83 H-3 pCi/L 3145 3280 2770 -3620 ---* ---November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 -42.5 Sr-90 pCi/L 29.3 31.1 22.7 -36.1 Ba-133 pCi/L 31.5 32.5 25.9 -36.7 Cs-134 pCi/L 59.65 62.3 50.6 -68.5 Cs-137 pCi/L 156 157 141 -175 Co-60 pCi/L 70.6 71.1 64.0 -80.7 Zn-65 pCi/L 145 126 113 -149 Gr-A pCi/L 38.2 51.6 26.9 -64.7 Gr-B pCi/L 42.0 36.6 24.1 -44.2 1-131 pCi/L 24.8 26.3 21.9-31.0 U-Nat pCi/L 146.90 56.2 45.7 -62.4 H-3 pCi/L 21100 21300 18700 -23400 ;;-(1) Yield on the high side of our acceptance range indicates possibility of calcium interference.
                              -+- 2015 CONTROL C-25                         Page 89 of 138
NCR 15-09 (2) Technician failed to dilute original sample. If di/ulted, the result would have been 57. 1, which tell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result. (b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) ERA evaluation:
 
A=acceptable.
FIGURE C-2 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR) IN THE VICINITY OF CPS, 2015 50 45 40 35 E
Reported result falls within the Warning Limits. NA=not acceptable.
Q) 0:::
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. Evaluation (c) N (1) N (1) A A A A A A A A A A A A A A A A A A A A N (2) A D-5 Page 97 of 138 TABLE D-4 ERA (a) STATISTICAL  
30 E
25 20 15 10 QUARTER II PRE-OP 02015 indicator
* 2015 control C-26                       Page 90 of 138
 
APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 91 of 138
 
Intentionally left blank Page 92 of 138
 
TABLE D-1               ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF3)
Identification                               Reported     Known         Ratio (c)
MonthNear             Number         Matrix   Nuclide       Units Value (a) Value (b)     TSE/Analytics Evaluation (d)
March 2015           E11181         Milk     Sr-89         pCi/L   88.9       97.2           0.91           A Sr-90         pCi/L   12.2       17.4           0.70           w E11182         Milk     1-131         pCi/L   61.3       65.1           0.94           A Ce-141         pCi/L   104         113           0.92           A Cr-51         pCi/L   265         276           0.96           A Cs-134         pCi/L   138         154           0.90           A Cs-137         pCi/L   205         207           0.99           A Co-58         pCi/L   178         183           0.97           A Mn-54         pCi/L   187         188           0.99           A Fe-59         pCi/L   182         177           1.03           A Zn-65         pCi/L   345         351           0.98           A Co-60         pCi/L   379         405           0.94           A
--* -- -**--* -- - -~ - .-
E11184         AP       Ce-141         pCi     107       85.0           1.26           w Cr-51           pCi   261         224           1.17           A Cs-134         pCi   74.6       77.0           0.97           A Cs-137         pCi   99.6         102           0.98           A Co-58           pCi   99.8         110           0.91           A Mn-54           pCi   99.2       96.9           1.02           A Fe-59           pCi     109         119           0.92           A Zn-65           pCi     188         183           1.03           A Co-60           pCi   200         201           1.00           A E11183         Charcoal 1-131           pCi   82.9       85.4           0.97           A E11185         Water     Fe-55         pCi/L   1950       1900           1.03           A June 2015             E11234         Milk     Sr-89         pCi/L   94.9       92.6           1.02           A Sr-90         pCi/L   14.3       12.7           1.13           A E11238         Milk     1-131         pCi/L   93.2       95.9           0.97           A Ce-141         pCi/L Not provided for this study Cr-51         pCi/L   349         276           1.26           w Cs-134         pCi/L   165         163           1.01           A Cs-137         pCi/L   143         125           1.14           A Co-58         pCi/L   82.0       68.4           1.20           A Mn-54         pCi/L   113         101           1.12           A Fe-59         pCi/L   184         151           1.22           w Zn-65         pCi/L   269         248           1.08           A Co-60         pCi/L   208         193           1.08           A E11237         AP       Ce-141         pCi Not provided for this study Cr-51           pCi   323         233           1.39         N (1)
Cs-134         pCi   139         138           1.01           A Cs-137         pCi   111         106           1.05           A Co-58           pCi   54.0       57.8           0.93           A Mn-54           pCi   96.8       84.9           1.14           A Fe-59           pCi   162         128           1.27           w Zn-65           pCi   198         210           0.94           A Co-60           pCi   178         163           1.09           A E11236         Charcoal 1-131           pCi   93.9         80           1.17           A D-1                                     Page 93 of 138
 
TABLE D-1                   ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 2 OF 3)
Identification                                                       Reported   Known     Ratio (c)
Month/Year               Number                         Matrix   Nuclide           Units   Value (a) Value (b) TSE/Analytics Evaluation (d)
June 2015                 E11238                         Water     Fe-55             pCi/L       1890     1790         1.06           A September 2015 E11289                                     Milk     Sr-89             pCi/L       95.7   99.1         0.97           A Sr-90             pCi/L       15.4     16.4       0.94           A E11290                         Milk     1-131             pCi/L       94.9   99.9         0.95           A Ce-141           pCi/L       228     213         1.07           A Cr-51             pCi/L       499     538         0.93           A Cs-134           pCi/L       208     212         0.98           A Cs-137           pCi/L       270     255         1.06           A Co-58             pCi/L       275     263         1.05           A Mn-54             pCi/L       320     290         1.10           A Fe-59             pCi/L       255     226         1.13           A
- - -- - , ,.. - :-- . --       .,,__ .. -- . -- - - ~ "           Zn-65 ...         pCi/L     *- 392     353---   .. 1.11         .-.A ..
Co-60             pCi/L       350     330         1.06           A E11292                         AP       Ce-141             pCi         104     85.1       1.22           w Cr-51             pCi         262     215         1.22           w Cs-134             pCi         86.1   84.6         1.02           A Cs-137             pCi         93     102         0.91           A Co-58             pCi         106     105         1.01           A Mn-54             pCi         117     116         1.01           A Fe-59             pCi         94.8     90.2       1.05           A Zn-65             pCi         160     141         1.13           A Co-60             pCi         146     132         1.11           A E11291                         Charcoal 1-131             pCi         85.9   81.7         1.05           A E11293                         Water     Fe-55             pCi/L       2090     1800         1.16           A E11294                         Soil     Ce-141           pCi/kg       209     222         0.94           A Cr-51           pCi/kg       463     560         0.83           A Cs-134           pCi/kg       231     221         1.05           A Cs-137           pCi/kg       311     344         0.90           A Co-58           pCi/kg       245     274         0.89           A Mn-54           pCi/kg       297     *302         0.98           A Fe-59           pCi/kg       248     235         1.06           A Zn-65           pCi/kg       347     368         0.94           A Co-60           pCi/kg       328     344         0.95           A December 2015             E11354                         Milk     Sr-89             pCi/L       96.2   86.8         1.11           A Sr-90         -   pCi/L __     14.8   12.5         1.18           A E11355                         Milk     1-131             pCi/L       95.1   91.2         1.04           A Ce-141           pCi/L       117     129         0.91           A Cr-51             pCi/L       265     281         0.94           A Cs-134           pCi/L       153     160         0.96           A Cs-137           pCi/L       119     115         1.03           A Co-58             pCi/L       107     110         0.97           A Mn-54             pCi/L       153     145         1.06           A Fe-59             pCi/L       117     108         1.08           A Zn-65             pCi/L       261     248         1.05           A Co-60             pCi/L       212     213         1.00           A D-2                                     Page 94 of 138
 
TABLE D-1                     ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3)
Identification                                                           Reported       Known           Ratio (c)
MonthNear                 Number                   Matrix           Nuclide             Units     Value (a)     Value (b)     TBE/Anal}'.tics Evaluation (d)
December 2015             E11357                   AP               Ce-141               pCi       89.9         84.0             1.07             A Cr-51                 pCi       215           184             1.17             A Cs-134               pCi         103           105             0.98             A Cs-137               pCi       76.6         74.8             1.02             A Co-58                 pCi       76.2         71.9             1.06             A Mn-54                 pCi       91.4         94.4             0.97             A
* Fe-59                 pCi       78.6         70.3             1.12             A Zn-65                 pCi         173           162             1.07             A Co-60                 pCi         138           139             0.99             A E11422                   AP               Sr-89                 pCi       98.0         96.9             1.01             A Sr-90                 pCi       10.0           14.0           0.71             w E11356                   Charcoal         1-131                 pCi       74.9         75.2             1.00             A E11358                   Water           Fe-55               pCi/L       2160         1710             1.26             w E11353                   Soil             Ce-141             pCi/kg       252           222             1.14             A Cr-51               pCi/kg       485           485             1.00             A Cs-134             pCi/kg       319           277             1.15             A Cs-137             pCi/kg       292           276             1.06             A Co-58               pCi/kg       193           190             1.02             A Mn-54               pCi/kg       258           250             1.03             A Fe-59               pCi/kg       218           186             1.17             A Zn-65               pCi/kg       457           429             1.07             A Co-60               pCi/kg       381           368             1.04             A (1) AP Cr Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable. NCR 15-18 (a) Teledyne Brown Engineering reported result.
(b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) Ratio of Teledyne Brown Engineering to Analytics results.
(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1.20.
W-Acceptable with 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.
D-3                                                 Page 95 of 138
 
TABLE D-2                   DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)
Identification                                                         Reported       Known           Acceptance Month/Year               Number               Media           Nuclide*             Units     Value (a)     Value (b)             Range     Evaluation (c)
March 2015               15-MaW32             Water           Am-241               Sq/L         0.632         0.654         0.458 - 0.850       A Ni-63               Sq/L           2.5                               (1)           A Pu-238               Sq/L         0.0204       0.0089                 (2)           A Pu-239/240           Sq/L           0.9           0.8         0.582 - 1.082       A 15-MaS32             Soil             Ni-63               Sq/kg           392         448.0             314- 582         A Sr-90               Sq/kg           286           653             487 - 849       N (3) 15-RdF32             AP             Sr-90             Sq/sample -0.0991                                     (1)           A U-234/233         Sq/sample 0.0211               0.0155       0.0109 - 0.0202       N (3)
U-238           Sq/sample 0.095                 0.099         0.069- 0.129         A 15-GrF32             AP             Gr-A             Sq/sample         0.448         1.77           0.53 - 3.01     N (3)
Gr-S             Sq/sample       0.7580         0.75           0.38 -.1.13       A 15-RdV32             Vegetation Cs-134                 Sq/sample         8.08         7.32           5.12 - 9.52       A Cs-137           Sq/sample         11.6         9.18           6.43 - 11.93       w Co-57             Sq/sample -0.0096                                     (1)           A Co-60             Sq/sample         6.53         5.55           3.89 - 7.22       A Mn-54             Sq/sample 0.0058                                     (1)           A Sr-90             Sq/sample 0.999                 1.08           0.76 - 1.40       A Zn-65             Sq/sample -0.108                                     (1)           A September 2015 15-MaW33                       Water           Am-241               Sq/L         1.012         1.055         0. 739 - 1.372       A Ni-63                 Sq/L           11.8         8.55           5.99-11.12       N (4)
Pu-238               Sq/L         0.727         0.681         0.477 - 0.885       A Pu-239/240           Sq/L         0.830         0.900         0.630-1.170         A 15-MaS33             Soil           Ni-63               Sq/kg           635           682             477 - 887         A Sr-90               Sq/kg           429           425             298 - 553         A 15-RdF33             AP             Sr-90             Sq/sample         1.48         2.18             1.53 - 2.83     N (4)
U-234/233         Sq/sample         0.143         0.143         0.100- 0.186         A U-238             Sq/sample         0.149         0.148         0.104-0.192         A 15-GrF33             AP             Gr-A             Sq/sample         0.497         0.90           0.27 -1.53         A Gr-S             Sq/sample         1.34         1.56           0.78 - 2.34       A 15-RdV33             Vegetation Cs-134                 Sq/sample         6.10         5.80           4.06 - 7.54       A Cs-137           Sq/sample       0.0002                               (1)           A Co-57             Sq/sample         8.01         6.62             4.63 - 8.61       w Co-60             Sq/sample         4.97         4.56             3.19- 5.93         A Mn-54             Sq/sample         8.33         7.68             5.38 - 9.98       A Sr-90             Sq/sample         0.386         1.30           0.91 - 1.69     N (4)
(1) False positive test.                                       Zn-65             Sq/sample         6.07         5.46             3.82-7.10         A (2) Sensitivity evaluation.
(3) Soil Sr incomplete digestion of the sample resulted in low results; AP U-2341233 - extremely low activity was difficult to quantify AP Gr-A - the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21.
(a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, tvo1.94acceptable.
Page 96 of 138
 
TABLE D-3                       ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)
Identification                                                             Reported         Known         Acceptance Month/Year             Number                 Media             Nuclide             Units       Value (a)       Value (b)           Limits     Evaluation (c)
May 2015               RAD-101                 Water             Sr-89               pCi/L           45.2           63.2         51.1 - 71.2       N (1)
Sr-90               pCi/L           28.0           41.9         30.8 - 48.1       N (1)
Ba-133             pCi/L           80.6           82.5         63.9 - 90.8         A Cs-134               pCi/L           71.7           75.7         61.8 - 83.3         A Cs-137               pCi/L           187             189           170 - 210         A Co-60               pCi/L           85.7           84.5         76.0 - 95.3         A Zn-65               pCi/L           197           203             183 - 238         A Gr-A                 pCi/L           26.1           42.6         22.1 - 54.0         A Gr-B                 pCi/L           28.8           32.9         21.3 - 40.6         A 1-131               pCi/L           23.5           23.8           19.7 - 28.3       A U-Nat               pCi/L           6.19           6.59         4.99 - 7.83         A H-3                 pCi/L           3145           3280         2770 - 3620         A
--* --~- ---* -- -
November 2015         RAD-103                 Water             Sr-89               pCi/L           40.9           35.7         26.7 - 42.5         A Sr-90               pCi/L           29.3           31.1         22.7 - 36.1         A Ba-133               pCi/L           31.5           32.5         25.9 - 36.7         A Cs-134               pCi/L         59.65           62.3         50.6 - 68.5         A Cs-137               pCi/L           156             157           141 -175         A Co-60               pCi/L           70.6           71.1         64.0 - 80.7         A Zn-65               pCi/L           145             126           113 - 149         A Gr-A                 pCi/L           38.2           51.6         26.9 - 64.7         A Gr-B                 pCi/L           42.0           36.6         24.1 - 44.2         A 1-131               pCi/L           24.8           26.3         21.9- 31.0         A U-Nat               pCi/L         146.90           56.2         45.7 - 62.4       N (2)
H-3                 pCi/L         21100           21300       18700 - 23400         A
                                                                                                                                                            ;;-
(1) Yield on the high side of our acceptance range indicates possibility of calcium interference. NCR 15-09 (2) Technician failed to dilute original sample. If di/ulted, the result would have been 57. 1, which tell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.
D-5                                                     Page 97 of 138
 
3 TABLE D-4                       ERA (a) STATISTICAL  


==SUMMARY==
==SUMMARY==
PROFICIENCY TESTING PROGRAM 3 ENVIRONMENTAL, INC., 2015 (Page 1 of 1) Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result 0 Limits ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 -48.10 ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 -90.80 ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 -83.30 ERW-1448 04/06/15 Cs-137 -191.92 +/- 5.9 189 -170.00 -210.0 ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 -95.30 ERW-1448 04/06/15 Zn-65 -195.97 +/- 12.0 203 -183.00 -238.0 ERW-1450 04/06/15 Gr. Alpha 34.05 +/- 1.90 42.60 22.10 -54.00 ERW-1450 04/06/15 G. Beta 26.93 +/- 1.12 32.90 21.30 -40.60 ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19. 70 -28.30 ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 -3620 ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 -36.70 ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 -175.0 ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 -80.70 ERW-5531 10/05/15 Zn-65 -138.94 +/- 5.7 126 -113.00 -149.0 ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 -44.20 ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 -31.00 ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45.70 -62.40 ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 -23400.0
PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2015 (Page 1 of 1)
* 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.
Concentration (pCi/L)
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass *Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass as provided by ERA. Page 98 of 138 0-6 TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 1 of 2) Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 02/01/15 Ni-63 341 +/- 18 448 314 -582 Pass MAS0-975 02/01/15 Sr-90 523 +/- 12 653 457 -849 Pass MAS0-975 02/01/15 Cs-134 533 +/- 6 678 475 -881 Pass MAS0-975 02/01/15 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 02/01/15 Co-57 0.5 +/- 1 0.0 NA c Pass MAS0-975 02/01/15 Co-60 741 +/- 8 817 572 -1062 Pass MAS0-975 02/01/15 Mn-54 1, 153 +/- 9 1, 198 839 -1557 Pass MAS0-975 02/01/15 Zn-65 892 +/- 18 1064 745 -1383 Pass MAW-969 02/01/15 Am-241 0.650 +/- 0.078 0.654 0.458 -0.850 Pass MAW-969 02/01/15 Cs-134 21.09 +/- 0.25 23.5 16.5 -30.6 Pass MAW-969 02/01/15 Cs-137 19.63 +/- 0.34 19.1 13.4 -24.8 Pass MAW-969 d 02/01/15 Co-57 . --** 10.2 +/- 0.4 29.9 20.9 -38.9. Fail. MAW-969 02/01/15 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 02/01/15 H-3 569 +/- 13 563 394 -732 Pass MAW-969 02/01/15 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 02/01/15 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 02/01/15 Ni-63 2.9 +/- 3 0.00 NA c Pass MAW-969 02/01/15 Zn-65 16.54 +/- 0.85 18.3 12.8 -23.8 Pass MAW-969 02/01/15 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 02/01/15 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 02/01/15 Sr-90 9.40 +/- 1.30 9.48 6.64 -12.32 Pass MAW-950 02/01/15 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 02/01/15 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAAP-978 02/01/15 Cs-134 1.00 +/- 0.04 1.15 0.81 -1.50 Pass MAAP-978 02/01/15 Cs-137 0.004 +/- 0.023 0.00 NAC Pass MAAP-978 e 02/01/15 Co-57 0.04 +/- 0.04 1.51 1.06 -1.96 Fail MAAP-978 02/01/15 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 02/01/15 Mn-54 1.11 +/- 0.08 1.02 0.71 -1.33 Pass MAAP-978 02/01/15 Zn-65 0.83 +/- 0.10 0.83 0.58 -1.08 Pass MAAP-981 02/01/15 Sr-89 38.12 +/- 1.01 47.5 33.3 -61.8 Pass MAAP-981 02/01/15 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 02/01/15 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 02/01/15 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 02/01/15 Cs-134 6.98 +/- 0.13 7.32 5.12 -9.52 Pass MAVE-972 02/01/15 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 02/01/15 Co-57 0.01 +/- 0.04 0.00 NAC Pass MAVE-972 02/01/15 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 02/01/15 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 02/01/15 Zn-65 0.09 +/- 0.12 0.00 NA c Pass Page 99 of 138 D-7 TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) ENVIRONMENTAL, INC., 2015 (Page 2 of 2) Concentration a Known Lab Code b Date Analysis Laboratory result Activity MAS0-4903 08/01/15 Ni-63 556 +/- 18 682 MAS0-4903 f 08/01/15 Sr-90 231 +/- 7 425 MAS0-4903 f 08/01/15 Sr-90 352 +/- 10 425 MAS0-4903 08/01/15 Cs-134 833 +/- 10 1,010 MAS0-4903 08/01/15 Cs-137 808 +/- 11 809.00 MAS0-4903 08/01/15 Co-57 1,052 +/- 10 1, 180 MAS0-4903 08/01/15 Co-60 2 +/- 2 1.3 MAS0-4903 08/01/15 Mn-54 1,331 +/- 13 1,340 MAS0-4903 08/01/15 Zn-65 686 +/- 15 662 MAW-5007 08/01/15 Cs-134 16.7 +/- 0.4 23.1 MAW-5007 08/01/15 Cs-137 -0.36 +/- 0.13 0 MAW-5007 "08/01/15 21.8 +/- 0.4 20.8 MAW-5007 08/01/15 Co-60 17.3 +/- 0.3 17.1 MAW-5007 08/01/15 H-3 227.5 +/- 8.9 216 MAW-5007 g 08/01/15 Fe-55 4.2 +/- 14.1 13.1 MAW-5007 08/01/15 Mn-54 16.6 +/- 0.5 15.6 MAW-5007 08/01/15 Ni-63 9.1 +/- 2.6 8.55 MAW-5007 08/01/15 Zn-65 15.5 +/- 0.9 13.9 MAW-5007 08/01/15 Sr-90 4.80 +/- 0.50 4.80 MAW-5007 08/01/15 Gr. Alpha 0.41 +/- 0.04 0.43 MAW-5007 08/01/15 Gr. Beta 3.45 +/- 0.07 3.52 MAAP-4911 08/01/15 Sr-89 3.55 +/- 0.67 3.98 MAAP-4911 08/01/15 Sr-90 0.94 +/- 0.16 1.05 MAAP-4907 08/01/15 Gr. Alpha 0.30 +/- 0.04 0.90 MAAP-4907 08/01/15 Gr. Beta 1.85 +/- 0.09 1.56 MAVE-4901 08/01/15 Cs-134 5.56 +/- 0.16 5.80 MAVE-4901 08/01/15 Cs-137 -0.02 +/- 0.06 0.00 MAVE-4901 08/01/15 Co-57 7.74 +/- 0.18 6.62 MAVE-4901 08/01/15 Co-60 4.84 +/- 0.15 4.56 MAVE-4901 08/01/15 Mn-54 8.25 +/- 0.25 7.68 MAVE-4901 08/01/15 Zn-65 5.78 +/- 0.29 5.46 a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
Lab Code           Date           Analysis               Laboratory             ERA                     Control 0
Result b           Result                   Limits           Acceptance ERW-1444           04/06/15       Sr-89               59.71 +/- 5.44           63.20             51.10   - 71.20         Pass ERW-1444           04/06/15       Sr-90               43.41   +/- 2.43           41.90             30.80   - 48.10         Pass ERW-1448           04/06/15       Ba-133               77.75 +/- 4.69           82.50             69.30   - 90.80         Pass ERW-1448           04/06/15       Cs-134               68.82 +/- 3.08           75.70             61.80   - 83.30         Pass ERW-1448           04/06/15       Cs-137           -191.92   +/- 5.9             189           - 170.00   - 210.0         Pass ERW-1448           04/06/15       Co-60               85.05 +/- 4.59           84.50             76.00   - 95.30         Pass ERW-1448           04/06/15       Zn-65             -195.97   +/- 12.0           203           -183.00   - 238.0         Pass ERW-1450           04/06/15       Gr. Alpha           34.05 +/- 1.90           42.60             22.10   - 54.00         Pass ERW-1450           04/06/15       G. Beta             26.93 +/- 1.12           32.90             21.30   - 40.60         Pass ERW-1453           04/06/15       1-131               22.47 +/- 0.83           23.80             19. 70 - 28.30         Pass ERW-1456           04/06/15       Uranium               5.98 +/- 0.31           6.59               4.99 - 7.83         *Pass ERW-1461           04/06/15       H-3                 3,254 +/- 180           3280               2,770   - 3620           Pass ERW-5528           10/05/15       Sr-89               34.76 +/- 0.06           35.70             26.70   - 42.50         Pass ERW-5528           10/05/15       Sr-90               29.23 +/- 0.06           31.10             22.70   - 36.10         Pass ERW-5531           10/05/15       Ba-133               30.91 +/- 0.53           32.50             25.90   - 36.70         Pass ERW-5531           10/05/15       Cs-134               57.40 +/- 2.57           62.30             50.69   - 68.50         Pass ERW-5531           10/05/15       Cs-137           -163.12   +/- 4.8             157           -141.00   - 175.0         Pass ERW-5531           10/05/15       Co-60               73.41 +/- 1.72           71.10             64.00   - 80.70         Pass ERW-5531           10/05/15     Zn-65             -138.94   +/- 5.7             126           -113.00   - 149.0         Pass ERW-5534           10/05/15       Gr. Alpha           29.99 +/- 0.08           51.60             26.90   - 64.70         Pass ERW-5534           10/05/15       G. Beta             27.52 +/- 0.04           36.60             24.10   - 44.20         Pass ERW-5537           10/05/15       1-131               25.54 +/- 0.60           26.30             21.90   - 31.00         Pass ERW-5540           10/05/15       Uranium             53.30 +/- 0.55           56.20             45.70   - 62.40         Pass ERW-5543           10/05/15       H-3               21,260   +/- 351           21,300             18,700   - 23400.0       Pass
* 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.                                                                                           Page 98 of 138 0-6
 
TABLE D-5             DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
ENVIRONMENTAL, INC., 2015 (Page 1 of 2)
Concentration a Known             Control Lab Code b   Date       Analysis     Laboratory result         Activity         Limits c         Acceptance MAS0-975     02/01/15   Ni-63             341 +/- 18               448           314 - 582             Pass MAS0-975     02/01/15   Sr-90             523 +/- 12               653           457 - 849             Pass MAS0-975     02/01/15   Cs-134             533 +/-6                 678           475 - 881             Pass MAS0-975     02/01/15   Cs-137             0.8 +/- 2.5               0.0             NA c               Pass MAS0-975     02/01/15   Co-57               0.5 +/-1                 0.0             NA c               Pass MAS0-975     02/01/15   Co-60             741 +/-8                 817           572 - 1062             Pass MAS0-975     02/01/15   Mn-54           1, 153 +/-9               1, 198         839 - 1557             Pass MAS0-975     02/01/15   Zn-65             892 +/- 18             1064           745 - 1383             Pass MAW-969     02/01/15   Am-241         0.650   +/- 0.078           0.654       0.458 - 0.850           Pass MAW-969     02/01/15   Cs-134         21.09   +/- 0.25           23.5         16.5 - 30.6             Pass MAW-969     02/01/15   Cs-137         19.63   +/- 0.34             19.1         13.4 - 24.8             Pass MAW-969   d 02/01/15   Co-57     . --** 10.2 +/- 0.4             29.9         20.9 - 38.9.             Fail.
MAW-969     02/01/15   Co-60             0.02 +/- 0.05             0.00             NA c               Pass MAW-969     02/01/15   H-3               569 +/- 13               563           394 - 732             Pass MAW-969     02/01/15   Fe-55             6.00 +/- 6.60             6.88         4.82 - 8.94             Pass MAW-969     02/01/15   Mn-54             0.02 +/- 0.07             0.00             NA c               Pass MAW-969     02/01/15   Ni-63               2.9 +/-3                 0.00             NA c               Pass MAW-969     02/01/15   Zn-65           16.54   +/- 0.85             18.3         12.8 - 23.8             Pass MAW-969     02/01/15   Pu-238           0.02 +/- 0.03             0.01             NAe               Pass MAW-969     02/01/15   Pu-239/240       0.81 +/- 0.10             0.83         0.58 - 1.08           Pass MAW-969     02/01/15   Sr-90             9.40 +/- 1.30             9.48         6.64 - 12.32         Pass MAW-950     02/01/15   Gr. Alpha         0.66 +/- 0.05             1.07         0.32 - 1.81           Pass MAW-950     02/01/15   Gr. Beta         2.72 +/- 0.06             2.79         1.40 - 4.19           Pass MAAP-978     02/01/15   Cs-134           1.00 +/- 0.04             1.15         0.81 - 1.50             Pass MAAP-978     02/01/15   Cs-137         0.004   +/- 0.023           0.00             NAC                 Pass MAAP-978 e   02/01/15   Co-57             0.04 +/- 0.04             1.51         1.06 - 1.96             Fail MAAP-978     02/01/15   Co-60             0.01 +/- 0.02             0.00             NA c               Pass MAAP-978     02/01/15   Mn-54             1.11 +/- 0.08             1.02         0.71 - 1.33           Pass MAAP-978     02/01/15   Zn-65             0.83 +/- 0.10             0.83         0.58 - 1.08           Pass MAAP-981     02/01/15   Sr-89           38.12   +/- 1.01           47.5         33.3 - 61.8           Pass MAAP-981     02/01/15   Sr-90             1.22 +/- 0.13             1.06         0.74 - 1.38           Pass MAAP-984     02/01/15   Gr. Alpha         0.59 +/- 0.06             1.77         0.53 - 3.01           Pass MAAP-984     02/01/15   Gr. Beta         0.95 +/- 0.07             0.75         0.38 - 1.13           Pass MAVE-972     02/01/15   Cs-134           6.98 +/- 0.13             7.32         5.12 - 9.52             Pass MAVE-972     02/01/15   Cs-137           9.73 +/- 0.21             9.18         6.43 - 11.93           Pass MAVE-972     02/01/15   Co-57             0.01 +/- 0.04             0.00             NAC                 Pass MAVE-972     02/01/15   Co-60             3.89 +/- 0.20             5.55         3.89 - 7.22             Pass MAVE-972     02/01/15   Mn-54             0.04 +/- 0.07             0.00             NA c               Pass MAVE-972     02/01/15   Zn-65             0.09 +/- 0.12             0.00             NA c               Pass Page 99 of 138 D-7
 
TABLE D-5                     DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
ENVIRONMENTAL, INC., 2015 (Page 2 of 2)
Concentration a Known                 Control Lab Code   b       Date           Analysis           Laboratory result             Activity               Limits 0        Acceptance MAS0-4903           08/01/15       Ni-63                 556   +/- 18                   682               477 - 887            Pass MAS0-4903 f         08/01/15       Sr-90                 231   +/-7                     425               298 - 553              Fail MAS0-4903 f         08/01/15       Sr-90                 352   +/- 10                   425               298 - 553            Pass MAS0-4903           08/01/15       Cs-134                 833   +/- 10                 1,010             707 - 1313            Pass MAS0-4903           08/01/15       Cs-137                 808   +/- 11                 809.00             566 - 1052            Pass MAS0-4903           08/01/15       Co-57               1,052   +/- 10                 1, 180             826 - 1534            Pass 0
MAS0-4903           08/01/15       Co-60                     2 +/-2                     1.3                 NA                Pass MAS0-4903           08/01/15       Mn-54               1,331   +/- 13                 1,340             938 - 1742            Pass MAS0-4903           08/01/15       Zn-65                 686   +/- 15                   662               463 - 861            Pass MAW-5007           08/01/15       Cs-134               16.7   +/- 0.4                 23.1             16.2 - 30              Pass MAW-5007           08/01/15       Cs-137               -0.36   +/- 0.13                   0                  NA 0             Pass MAW-5007           "08/01/15       co~57                21.8   +/- 0.4                 20.8             14.6  -  27          Pass MAW-5007           08/01/15       Co-60                 17.3   +/- 0.3                 17.1               12  -  22.2        Pass MAW-5007           08/01/15       H-3                 227.5   +/- 8.9                 216               151  -  281          Pass MAW-5007 g         08/01/15       Fe-55                   4.2 +/- 14.1                 13.1               9.2  -  17            Fail MAW-5007           08/01/15       Mn-54                 16.6   +/- 0.5                 15.6             10.9  -  20.3        Pass MAW-5007           08/01/15       Ni-63                   9.1 +/- 2.6                 8.55             5.99  -  11.12        Pass MAW-5007           08/01/15       Zn-65                 15.5   +/- 0.9                 13.9               9.7  -  18.1        Pass MAW-5007           08/01/15       Sr-90                 4.80   +/- 0.50                 4.80             3.36  -  6.24          Pass MAW-5007             08/01/15       Gr. Alpha             0.41   +/- 0.04                 0.43             0.13  -  0.73          Pass MAW-5007             08/01/15       Gr. Beta             3.45   +/- 0.07                 3.52             1.76  -  5.28          Pass MAAP-4911           08/01/15       Sr-89                 3.55   +/- 0.67                 3.98             2.79  -  5.17        Pass MAAP-4911           08/01/15       Sr-90                 0.94   +/- 0.16                 1.05             0.74  -  1.37          Pass MAAP-4907           08/01/15       Gr. Alpha             0.30   +/- 0.04                 0.90             0.27  -  1.53          Pass MAAP-4907           08/01/15       Gr. Beta             1.85   +/- 0.09                 1.56             0.78  -  2.34          Pass MAVE-4901           08/01/15       Cs-134               5.56   +/- 0.16                 5.80             4.06 - 7.54            Pass MAVE-4901           08/01/15       Cs-137               -0.02   +/- 0.06                 0.00                 NA c              Pass MAVE-4901           08/01/15       Co-57                 7.74   +/- 0.18                 6.62             4.63  -  8.61          Pass MAVE-4901           08/01/15       Co-60                 4.84   +/- 0.15                 4.56             3.19  -  5.93          Pass MAVE-4901           08/01/15       Mn-54                 8.25   +/- 0.25                 7.68             5.38  -  9.98          Pass MAVE-4901           08/01/15       Zn-65                 5.78   +/- 0.29                 5.46             3.82  -  7.10        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).
b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).
Control Limits 0 477 -887 298 -553 298 -553 707 -1313 566 -1052 826 -1534 NA 0 938 -1742 463 -861 16.2 -30 NA 0 14.6 -27 12 -22.2 151 -281 9.2 -17 10.9 -20.3 5.99 -11.12 9.7 -18.1 3.36 -6.24 0.13 -0.73 1.76 -5.28 2.79 -5.17 0.74 -1.37 0.27 -1.53 0.78 -2.34 4.06 -7.54 NA c 4.63 -8.61 3.19 -5.93 5.38 -9.98 3.82 -7.10 0 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".
0 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.
MAPEP does not provide control limits. d Lab result was 27.84. Data entry_ error resulted in a non-acceptable result.
d Lab result was 27.84. Data entry_ error resulted in a non-acceptable result.
* Lab result was 1.58. Data entry error resulted in a non-acceptable result. f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.
* Lab result was 1.58. Data entry error resulted in a non-acceptable result.
Acceptance Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass g The known activity was below the routine laboratory detection limits for the available aliquot fraction.
f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.
Page 100 of 138 D-8 APPENDIX E ERRATA DATA *Page 101of138 Intentionally left blank Page 102of138 There is no errata data for 2015. Page 103of138 Intentionally left blank Page 1 04 of 138 APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR} Page 105of138 Intentionally left blank Page 106of138 Docket No: 50-461 l?OWIER. STATION Annual Radiological Groundwater Protection Program Report --------. -. . ----. ----------:----. -----<o-------.  
g The known activity was below the routine laboratory detection limits for the available aliquot fraction.             Page 100 of 138 D-8
---.__,,,_ ___ .--* ____ .,... -'> *-,,...------=--
 
-..__ *. ., January 1 through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services Clinton Power Station Clinton, IL 61727 April 2016 Page 107 of 138
APPENDIX E ERRATA DATA
* Intentionally left blank Page 108of138 Table Of Contents I. Summary and Conclusions
            *Page 101of138
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1 II. Introduction
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3 A Objectives of the RGPP ......................................................................................
There is no errata data for 2015.
3 8. Implementation of the Objectives
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3 C. Program Description
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4 D. Characteristics of Tritium (H-3) ...........................................................................
APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR}
5 Ill. Program Description  
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5 A. Sample Analysis ....................................... , ..........................................................
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5 8. Data Interpretation  
 
........ -...... ........ -... :.: .................................................................  
Docket No:                50-461 Cl~NTON                      l?OWIER. STATION Annual Radiological Groundwater Protection Program Report
-. 6 _. __ :. -*-:. -:": .... --* _;;_----,. -.. :*::*::::  
- - - -- -- - -- - -    ------:-- -- . --~ - -- --<o----- --. . - .         . - -
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                                                                *----...-----~-.**
.. *. ::-. ... ,:-_ ; = 1. Background Concentrations of Tritium ............................................
                                                                                          - ___ .-- .-* ____.,. .
: ........ 7 IV. Results and Discussion  
                                                                                    --- .__,,,_                  - '> *-,,...- - - - - -=-- --~-- - ~ ..__*. .,
.................................................................................................
January 1 through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services Clinton Power Station Clinton, IL 61727 April 2016 Page 107 of 138
9 A. Program Exceptions  
* Intentionally left blank Page 108of138
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9 8. Program Changes ...............................................................................................
Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 3 A Objectives of the RGPP ...................................................................................... 3
9 C. Groundwater Results ..........................................................................................
: 8. Implementation of the Objectives ........................................................................ 3 C. Program Description ........................................................................................... 4 D. Characteristics of Tritium (H-3) ........................................................................... 5 Ill. Program Description ...................................................................................................... 5 A. Sample Analysis ....................................... ,.......................................................... 5
9 D. Surface Water Results ...............................................................  
: 8. Data Interpretation ........-...... ~ ........-... :.: .................................................................-. 6
,, .....................
_.__ :. -*- :. -:": .... -- *_;;_----,. -t~:; sack9rduncfAil~i1ysis.~::-:~.: :~~-.. :*::*:::: .:'::.:.~.~--~:_:'.--'.*.-~_::::: :::~--.:-~ .*:_:-.':-::*:*: ~ .-:.:. '.~--~:.~:~..*. ::-. ::':~:::-*1 ~--...,:-_ ; =
11 E. Precipitation Water Results ...............................................................................
: 1. Background Concentrations of Tritium ............................................ :........ 7 IV. Results and Discussion ................................................................................................. 9 A. Program Exceptions ............................................................................................ 9
11 F. Recapture  
: 8. Program Changes ............................................................................................... 9 C. Groundwater Results .......................................................................................... 9 D. Surface Water Results ............................................................... ,, ..................... 11 E. Precipitation Water Results ............................................................................... 11 F. Recapture .......................................................................................................... 11 G. Summary of Results - Inter-laboratory Comparison Program .......................... 11 H. Errata Data .......................................................................................................... 11 I. Leaks, Spills, and Releases ......................................................................... ,...... 12 J. Trends ................................................, ................................................................ 12 K. Investigations ..................................................................................................... 12 L. Actions Taken ..................................................................................,.................. 12
..........................................................................................................
* Page 109of138
11 G. Summary of Results -Inter-laboratory Comparison Program ..........................
 
11 H. Errata Data ..........................................................................................................
Appendices Appendix A                           Location Designation of the Annual Radiological Groundwater Protection Program Report (ARGPPR)
11 I. Leaks, Spills, and Releases ......................................................................... , ...... 12 J. Trends ................................................ , ................................................................
* Tables
12 K. Investigations  
*Table A-1                          Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Figures Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Clinton Power Station,
.....................................................................................................
                                    ~015
12 L. Actions Taken .................................................................................. , ..................
    -.--.,,<-----~*--. _..,-.* __ : - ~ -- . , *-~--~-.-_:- : __ -. ,.. __ . . . . - _.,._ --*-- - -* ~--,....,,**---*  - .,,...,..,.__,........,c,.:-..:= _,--------- ....-- .,*-~-
12
Figure A-1                         Onsite Sampling Locations at Clinton Power Station Figure A-2                         Sampling Locations South of Clinton Power Station Figure A-3                         Sampling Locations East of Clinton Power Station Figure A-4                         Recapture Sampling Locations of Clinton Power Station Appendix B                         Data Tables of the Annual Radiological Groundwater Protection Program Report (ARGPPR)
* Page 109of138 Appendix A Tables *Table A-1 Figures Appendices Location Designation of the Annual Radiological Groundwater Protection Program Report (ARGPPR)
Tables Table 8-1.1                        Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.
* Radiological Groundwater Protection Program -Sampling Locations, Clinton Power Station, 2015 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Clinton Power Station,
Table 8-1.2                        Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.
_..,-.* __ : ---. ,
Table 8-1.3                        Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.
: __ -. , .. __ .... -_.,._ --*----*  
Table 8-11.1                        Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
-.,,...,..,.__,........,c,.:-..:=
Table    B~ll.2                    Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.
_,---------
ii Page 110 of 138
.... --
 
Figure A-1 Figure A-2 Figure A-3 Figure A-4 Appendix B Tables Table 8-1.1 Table 8-1.2 Table 8-1.3 Table 8-11.1 Table Onsite Sampling Locations at Clinton Power Station Sampling Locations South of Clinton Power Station Sampling Locations East of Clinton Power Station Recapture Sampling Locations of Clinton Power Station Data Tables of the Annual Radiological Groundwater Protection Program Report (ARGPPR) Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015. ii Page 110 of 138 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 Clinton Power Station (CPS). This evaluation involved numerous station personnel and contractor support personnel.
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 Clinton Power Station (CPS). This evaluation involved numerous station personnel and contractor support personnel. This report covers groundwater and surface water samples, collected outside of the Licensee required Off-Site Dose Calculation Manual (ODCM) requirements, both on and off station property in 2015. During that time period, 246 analyses were performed on 97 samples from 24 locations.
This report covers groundwater and surface water samples, collected outside of the Licensee required Off-Site Dose Calculation Manual (ODCM) requirements, both on and off station property in 2015. During that time period, 246 analyses were performed on 97 samples from 24 locations.
The monitoring was conducted in four phases.
The monitoring was conducted in four phases. In assessing all the data gathered for this report, it was concluded that the operation of CPS had no adverse radiological impact on the environment, and --the-re are no known-active-releases into the groundwater or surface water
In assessing all the data gathered for this report, it was concluded that the operation of CPS had no adverse radiological impact on the environment, and
__ -----CPS. No program changes occurred during the sampling year of 2015. 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 NUREG-1302 in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that the independent laboratory achieve a lower limit of detection 10 times lower than that required by the United States Environmental Protection Agency (USEPA) regulation.
  -- the-re are no known-active-releases into the groundwater or surface water at~, __ - -- - -
Strontium-89 was not detected in any samples. Strontium-90 was not detected in any samples. Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Background levels of tritium were detected at concentrations greater than the self-imposed LLD of 200 pCi/L in four of 17 groundwater monitoring locations.
CPS. No program changes occurred during the sampling year of 2015.
The tritium concentrations ranged from 176 +/- 106 pCi/L to 365 +/- 136 pCi/L. Tritium was not detected in any surface water. Precipitation samples were not analyzed during 2015. Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.
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 NUREG-1302 in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that the independent laboratory achieve a lower limit of detection 10 times lower than that required by the United States Environmental Protection Agency (USEPA) regulation.
Gross Beta (dissolved) was detected in 15 of 17 groundwater locations.
Strontium-89 was not detected in any samples. Strontium-90 was not detected in any samples.
The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations. Page 111 of 138 Hard-To-Detect analyses were performed on two groundwater locations.
Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Background levels of tritium were detected at concentrations greater than the self-imposed LLD of 200 pCi/L in four of 17 groundwater monitoring locations. The tritium concentrations ranged from 176 +/-
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 analyzed were not found at concentrations greater than their respective MDCs. Page 112of138 II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois.
106 pCi/L to 365 +/- 136 pCi/L. Tritium was not detected in any surface water.
CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on 15 February 1987. The site encloses approximately 13,730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated -on approximately 150 The cooling water discharge flume, which discharges to the eastern arm of the lake, occupies an additional 130 acres. Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13, 730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Ann_a Townships. --**-. __ ,,__,,, ___ -. ---This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015. A. Objectives of the Radiological Groundwater Protection Program (RGPP) The long-term objectives of the RGPP are as follows: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources. 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain knowledge of flow patterns on the surface and shallow subsurface.
Precipitation samples were not analyzed during 2015.
* 3. Perform routine water sampling and radiological analysis of water from selected locations.
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations. Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations.
: 4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner. 5. Regularly assess analytical results to identify adverse trends. 6. Take necessary corrective actions to protect groundwater resources.
Page 111 of 138
: 8. Implementation of the Objectives The objectives identified have been implemented at Clinton Power Station as discussed below: Page 113of138
 
: 1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public in station specific reports. 2. The Clinton Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
Hard-To-Detect analyses were performed on two 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 analyzed were not found at concentrations greater than their respective MDCs.
Page 112of138
 
II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on 15 February 1987. The site encloses approximately 13,730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated -on approximately 150 acres~ The cooling water discharge flume, which discharges to the eastern arm of the lake, occupies an additional 130 acres.
Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13, 730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Ann_a Townships.
                                                            **-. __ ,,__,,, ___ -. - - *~-- - - -
This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015.
A. Objectives of the Radiological Groundwater Protection Program (RGPP)
The long-term objectives of the RGPP are as follows:
: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
: 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain knowledge of flow patterns on the surface and shallow subsurface.                                                             *
: 3. Perform routine water sampling and radiological analysis of water from selected locations.
: 4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
: 5. Regularly assess analytical results to identify adverse trends.
: 6. Take necessary corrective actions to protect groundwater resources.
: 8. Implementation of the Objectives The objectives identified have been implemented at Clinton Power Station as discussed below:
Page 113of138
: 1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public in station specific reports.
: 2. The Clinton Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
: 3. Clinton Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
: 3. Clinton Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
: 4. Clinton Power Station has implemented new procedures to identify report rrew leaks,-spiils, o*r*otlier detections with potential*
: 4. Clinton Power Station has implemented new procedures to identify
radiological significance in a timely manner. 5. Clinton Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends. C. Program Description
        ~-and report rrew leaks,-spiils, o*r*otlier detections with potential*
: 1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1, A-2, A-3, and A-4 Appendix A. Groundwater, Surface Water and Precipitation Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Groundwater, surface water, and precipitation water are collected.
radiological significance in a timely manner.
Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures.
: 5. Clinton Power Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial by the contractor.
C. Program Description
Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to Page 114of138 hydrogeologic conditions.
: 1. Sample Collection Sample locations can be found in Table A-1 and Figures A-1, A-2, A-3, and A-4 Appendix A.
D. Characteristics of Tritium (H-3) Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen.
Groundwater, Surface Water and Precipitation Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Groundwater, surface water, and precipitation water are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial revi~w by the contractor.
The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.
Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to Page 114of138
Tritiated water behaves the same as ordinary water in both the environment and the body. 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, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period. Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules.
hydrogeologic conditions.
Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless.
D.     Characteristics of Tritium (H-3)
Tritiated water behaves chemically and physically like tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.
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." The chemical properties of tritium are essentially those of ordinary hydrogen.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron).
Tritiated water behaves the same as ordinary water in both the environment and the body. 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
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 beta 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.
            * -clearance rate-characterized by*an effective biological half-life-of.about-14 *' - ; --
* Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Clinton Page 115 of 138 Power Station RGPP in 2015. In order to achieve the stated objectives, the current program includes the following analyses:
days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.
: 1. Concentrations of gamma emitters in groundwater and surface water. 2. Concentrations of strontium in groundwater.
Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. 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.
: 3. Concentrations of tritium in groundwater and surface water. 4. Concentrations of gross alpha and gross beta in groundwater.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). 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 beta 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.
5." ---; -Concentrations of-Am-241-in groundwater.  
Ill.
-6. Concentrations of Cm-242 and Cm-243/244 in groundwater.
* Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Clinton Page 115 of 138
: 7. Concentrations of Pu-238 and Pu-239/240 in groundwater.
 
: 8. Concentrations of U-234, U-235 and U-238 in groundwater.
Power Station RGPP in 2015.
: 9. Concentrations of Fe-55 in groundwater.
In order to achieve the stated objectives, the current program includes the following analyses:
: 10. Concentrations of Ni-63 in groundwater.
: 1.         Concentrations of gamma emitters in groundwater and surface water.
B. Data Interpretation The radiological data collected prior to Clinton Power Station becoming operational were used as a baseline with which these operational data were compared.
: 2.         Concentrations of strontium in groundwater.
For the purpose of this report, Clinton Power Station was considered operational at initial criticality.
: 3.         Concentrations of tritium in groundwater and surface water.
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) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.
: 4.         Concentrations of gross alpha and gross beta in groundwater.
: 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. Page116of138 Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence.
5." ---; - Concentrations of-Am-241-in groundwater. -
The convention is to report results with a 95% level of confidence.
: 6.         Concentrations of Cm-242 and Cm-243/244 in groundwater.
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) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated.
: 7.         Concentrations of Pu-238 and Pu-239/240 in groundwater.
Exelon reports the TPU by following the result with plus
: 8.         Concentrations of U-234, U-235 and U-238 in groundwater.
: 9.         Concentrations of Fe-55 in groundwater.
: 10.       Concentrations of Ni-63 in groundwater.
B. Data Interpretation The radiological data collected prior to Clinton Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Clinton Power Station 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) 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.
Page116of138
 
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) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus
* or minus+/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.
* or minus+/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.
Analytical uncertainties are reported at the 95% confidence level in --** -*this report for reporting consistency With the AREOR.--* Gamma spectroscopy results for each type of sample were grouped as follows: For groundwater and surface water 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.
Analytical uncertainties are reported at the 95% confidence level in
C. Background Analysis Pre-operational Radiological Environmental Monitoring Program operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, milk, and vegetation.
  -- **   -*this report for reporting consistency With the AREOR.-          .,~- -*
The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Clinton Power Nuclear Power Station, Illinois Power Company, Annual Report 1987, May 1988. The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater.
Gamma spectroscopy results for each type of sample were grouped as follows:
: 1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. a. Tritium Production Tritium is created in the environment from naturally occurring Page 117 of 138 processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and 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.
For groundwater and surface 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.
A major anthropogenic source of tritium and strontium-90  
C. Background Analysis Pre-operational Radiological Environmental Monitoring Program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, milk, and vegetation. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Clinton Power Nuclear Power Station, Illinois Power Company, Annual Report 1987, May 1988.
.. _;******comes from the former atmo*spheric*testing of-thermonuclear  
The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater.
* *
: 1.       Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.
* 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.
: a.     Tritium Production Tritium is created in the environment from naturally occurring Page 117 of 138
The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
 
: b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides.
processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and 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.
Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database.
A major anthropogenic source of tritium and strontium-90
GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006. RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline Jp until 1975, followed by. a gradual decline that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Page 118 of 138
.:.~.. _;******comes from the former atmo*spheric*testing of-thermonuclear * * *~*~'---
: c. Surface Water Data Tritium concentrations are routinely measured in Clinton Lake. According to the USEPA, surface water data typically has an uncertainty+/-
* 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.
70 to 100 pCi/L 95% confidence bound on each given measurement.
: b.           Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006.
Therefore, the typical background data provided may be subject to measurement uncertainty of approximately  
RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline Jp until 1975, followed by. a gradual decline sine~ that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above.
+/- 70 to 100 pCi/L. The radio-analytical laboratory is counting tritium results to an Exelon specified 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.
Page 118 of 138
: c. Surface Water Data Tritium concentrations are routinely measured in Clinton Lake.
According to the USEPA, surface water data typically has an uncertainty+/- 70 to 100 pCi/L 95% confidence bound on each given measurement. Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.
The radio-analytical laboratory is counting tritium results to an Exelon specified 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. Program Exceptions
IV. Results and Discussion A. Program Exceptions
: 1. Sample Anomalies There were no samples anomalies in 2015. 2. Missed Samples There were no missed samples in 2015. B. Program Changes There were no sampling program changes in 2015. C. Groundwater Results Groundwater Baseline samples were collected from off-site wells during four (4) phases at the station. Analytical results are discussed below. No anomalies were noted during the year. Page 119 of 138 Tritium Samples from 17 locations were analyzed for tritium activity (Table B-1.1 Appendix B). Tritium values ranged from below the Exelon imposed LLD of 200 pCi/I to 365 pCi/I. Strontium Strontium-89 was not detected in any of the 17 samples analyzed and the required LLD of 10 pCi/L was met. Strontium-90 was also not detected in any of the 17 samples analyzed and the required LLD of 1 pCi/L was met. (Table B-1.1 Appendix B). Gross Alpha and Gross Beta (dissolved and suspended)
: 1. Sample Anomalies There were no samples anomalies in 2015.
: 2. Missed Samples There were no missed samples in 2015.
B. Program Changes There were no sampling program changes in 2015.
C. Groundwater Results Groundwater Baseline samples were collected from off-site wells during four (4) phases at the station. Analytical results are discussed below. No anomalies were noted during the year.
Page 119 of 138
 
Tritium Samples from 17 locations were analyzed for tritium activity (Table B-1.1 Appendix B). Tritium values ranged from below the Exelon imposed LLD of 200 pCi/I to 365 pCi/I.
Strontium Strontium-89 was not detected in any of the 17 samples analyzed and the required LLD of 10 pCi/L was met. Strontium-90 was also not detected in any of the 17 samples analyzed and the required LLD of 1 pCi/L was met. (Table B-1.1 Appendix B).
Gross Alpha and Gross Beta (dissolved and suspended)
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed oh groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.
Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed oh groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.
Gross Beta (dissolved) was detected in 15 of 17 groundwater locations.
Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L.
The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B). Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-1.2, Appendix B). Hard-To-Detect Hard-To-Detect analyses were performed on two groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs. Occasionally, the isotopes of U-234 and U-238 are detected at low levels and indistinguishable from background (Table B-1.3 Appendix B). Page 120 of 138 D. Surface Water Results Surface Water Baseline samples were collected from on-site surface waters during four (4) phases at the station. Analytical results are discussed belo.w. No anomalies were noted during the year. Tritium Samples from seven locations were analyzed for tritium activity -(Table B-11.1 Appendix B). Tritium was not detected at concentrations greater than the LLD. --* * -. ---... '" *-*-*-*. --Strontium****-**  
Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B).
*-* . .--' ---' _,, .... *  
Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-1.2, Appendix B).
* -*--**--.* -*--Strontium was not analyzed in 2015 (Table B-11.1 Appendix B). Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-11.2, Appendix B). E. Precipitation Water Reirnlts Precipitation Water Precipitation water samples were not collected during 2015. F. Recapture Recapture samples were not required in 2015. G. Summary of Results -Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report. H. Errata Data The 2014 ARGPP incorrectly reported 607 analyses in the Summary and Conclusion section. The number of analyses in 2014 should have been , reported as 253 (IR 02635324). Page 121of138 I. Leaks, Spills, and Releases No leaks, spills or releases were identified during the year. J. Trends MW-CL-14S had a slight trend upward from <200 pCi/L to 241, 300 and 365 pCi/L respectively in 2015. However, the 1st Quarter of 2016 revealed MW-CL-14S has trended back to 218 pCi/L. Additionally, MW-CL-21S, after it too experienced a slight trend from 219 pCi/L to 287 pCi/L in 2015, has now had consecutive values of 189 pCi/L in the 4th Quarter of 2015 and 191 pCi/L from our 1st Quarter of 2016. All sampling well locations are currently indicating tritium levels that are less than the ODCM LLD of 2,000 pCi/I. All wells will continue to be sampled in accordance with the RGPP in 2016 .. K. Investigations Currently no investigations are on-going.
Hard-To-Detect Hard-To-Detect analyses were performed on two groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.
L. Actions Taken 1. Compensatory Actions There have been no station events requiring compensatory actions at the Clinton Power Station in 2015. 2. Installation of Monitoring Wells No new wells were installed during the 2015. 3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes. Page 122of138 APPENDIX A LOCATION DESIGNATION OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT {ARGPPR) Page 123of138 Intentionally left blank Page 124of138 TABLEA-1:
Occasionally, the isotopes of U-234 and U-238 are detected at low levels and indistinguishable from background (Table B-1.3 Appendix B).
Radiological Groundwater Protection Program -Sampling Locations, Clinton Power Station, 2015 Site B-3 MW-CL-1 MW-CL-2 MW-CL-121 MW-CL-131 MW-CL-13S MW-CL-14S MW-CL-151 MW-CL-15S MW-CL-16S MW-CL-17S MW-CL-181 MW-CL-18S MW-CL-19S MW-CL-20S MW-CL-21S MW-CL-22S Sewage Treatment Plant ----SW-CL-1 SW-CL-2 SW-CL-4 SW-CL-5 SW-CL-6 SW-CL-7 Site Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water A-1 Page 125of138 
Page 120 of 138
. ,, , *. , *. <l A-2 Page 126of138 c .Q ro U5 '--(]) 3 0 Cl. c 0 c ...... u 1-<( co (]) (f) *-co LL u 0 _J Cl) c Q_ E co (/) 2 *;n c 0
 
)> I (,.) ""CJ Q) <O CD N --.,J MW-1. 0 100 200 ---===--=:=::J Fee t
D.       Surface Water Results Surface Water Baseline samples were collected from on-site surface waters during four (4) phases at the station. Analytical results are discussed belo.w. No anomalies were noted during the year.
......  
Tritium Samples from seven locations were analyzed for tritium activity
...... CXl Figure A-2 Sampling Locations South of Clinton Pow er Station   
                              -   (Table B-11.1 Appendix B). Tritium was not detected at concentrations greater than the LLD.
"'O Dl (0 _.. N Ol 0 -_.. w Ol 0 1 00 200 Feet Sampling Loe f Figure A -3 a ions East of er inton Powe r Station
*-~ --* * -. ---... '" *-*-*-*. --Strontium****-** *- * . .- - ' -- -' _,,.... * *--------~~---,------ * - *-- **--.* -*--
--":-. -.
Strontium was not analyzed in 2015 (Table B-11.1 Appendix B).
* RG-15 Figure A-4 Recapture Sampling Locations of Clinton Power Station A-5
Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-11.2, Appendix B).
* RG-3 Page 129of138 Intentionally left blank Page 130of138 APPENDIX B DATA TABLES OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR) Page 131 of 138 Intentionally left blank Page 132of138 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) 8-3 02/09/15 < 157 8-3 05/26/15 < 194 8-3 08/17/15 < 180 < 5.2 < 0.6 1.2 +/- 0.8 < 1.1 3.2 +/- 1.0 < 1.6 8-3 11/02/15 < 196 MW-CL-1 02/09/15 < 156 MW-CL-1 05/26/15 < 195 MW-CL-1 08/17/15 < 179 -< 5.4 < 0.6 < 0.9 < 1.1 2.1 +/- 0.9 < 1.6 MW-CL-1 11/02/15 < 187 MW-CL-121 02/09/15 < 178 MW-CL-121 05/26/15 < 196 MW-CL-121 08/17/15 < 191 < 5.6 < 0.6 < 0.9 < 1.1 4.9 +/- 1.0 < 1.6 MW-CL-121 11/02/15 322 +/- 134 MW-CL-131 02/09/15 < 154 MW-CL-131 05/26/15 < 193 MW-CL-131 08/17/15 < 187 . < 4.0 < 0.6 < 0.7 < 1.1 3.2 +/- 1.1 < 1.6 MW-CL-131 11/02/15 < 187 MW-CL-13S 02/09/15 < 157 MW-CL-13S 05/26/15 < 193 MW-CL-13S 08/17/15 < 199 < 4.7 < 0.6 < 0.6 < 1.1 2.7 +/- 1.0 < 1.6 MW-CL-13S 11/02/15 220 +/- 128 MW-CL-14S 02/09/15 < 156 MW-CL-14S 07/22/15 241 +/- 128 MW-CL-14S 08/18/15 300 +/- 126 < 6.9 < 0.8 < 1.3 < 1.1 11.9 +/- 1.6 < 1.6 MW-CL-14S 11/03/15 365 +/- 136 MW-CL-151 02/09/15 < 156 MW-CL-151 05/26/15 < 193 MW-CL-151 08/17/15 < 174 < 5.7 < 0.7 < 0.7 < 0.5 1.9 +/- 1.0 < 1.7 MW-CL-151 11/02/15 < 193 MW-CL-15S 02/09/15 < 155 MW-CL-15S 05/26/15 < 193 MW-CL-15S 08/17/15 < 197 MW-CL-15S 09/29/15 < 5.2 < 0.6 < 0.9 < 0.8 < 0.9 < 1.6 MW-CL-15S 11/02/15 < 185 MW-CL-16S 02/09/15 < 186 MW-CL-16S 05/27/15 < 189 MW-CL-16S 08/18/15 <.180 MW-CL-16S 09/29/15 < 5.6 < 0.7 < 2.3 < 0.8 8.7 +/- 1.4 < 1.6 MW-CL-16S 11/03/15 < 188 MW-CL-17S 02/09/15 < 159 MW-CL-17S 05/27/15 < 194 MW-CL-17S 08/18/15 < 180 < 5.3 < 0.7 < 1.9 < 0.5 3.4 +/- 1.1 < 1.6 MW-CL-17S 11/03/15 < 188 MW-CL-181 02/09/15 < 154 MW-CL-181 05/27/15 < 194 MW-CL-181 08/18/15 < 198 < 5.5 < 0.6 < 1.2 < 0.5 4.2 +/- 1.1 < 1.6 MW-CL-181 11/03/15 < 186 B-1 Page 133of138 TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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-CL-18S 02/09/15  
E.       Precipitation Water Reirnlts Precipitation Water Precipitation water samples were not collected during 2015.
< 156 MW-CL-18S 05/27/15 < 193 MW-CL-18S 08/18/15 < 189 < 4.5 < 0.8 < 2.1 < 0.5 4.4 +/- 1.2 < 1.6 MW-CL-18S 11/03/15 < 188 MW-CL-19S 02/09/15  
F.       Recapture Recapture samples were not required in 2015.
< 155 MW-CL-19S 05/26/15 < 194 MW-CL-19S 08/17/15 < 174 < 4.5 < 0.7 < 2.5 < 0.6 6.7 +/- 1.5 < 1.7 MW-CL-19S 11/02/15 < 190 MW-CL-2 02/09/15 < 154 MW-CL-2 05/26/15 < 195 . MW-CL-2 08/17/15 < 180 < 5.2 < 0.6 < 1.2 < 1.1 3.9 +/- 1.1 < 1.6 MW-CL-2 11/02/15 < 188 MW-CL-20S 02/09/15 < 154 MW-CL-20S 05/26/15  
G.       Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.
< 198 MW-CL-20S 08/17/15 < 175 < 6.3 < 0.5 < 1.2 < 0.5 2.8 +/- 1.1 < 1.6 MW-CL-20S 11/02/15 < 188 MW-CL-21S 02/09/15 176 +/- 106 MW-CL-21S 05/26/15 219 +/- 130 MW-CL-21S 08/17/15 287 +/- 124 MW-CL-21S 09/29/15 < 197 < 5.3 < 0.8 < 1.8 < 0.8 < 1.5 < 1.6 MW-CL-21S 11/02/15 < 189 MW-CL-22S 02/09/15 < 179 MW-CL-22S 05/27/15 < 194 MW-CL-22S 08/18/15 < 180 MW-CL-22S 09/29/15 < 4.4 < 0.7 < 2.3 < 0.9 11.2 +/- 1.5 < 1.6 MW-CL-22S 11/03/15 < 192 B-2 Page 134of138 OJ I w "'U Ol cc CD _,.. w 01 0 -_,.. w c:o Table 8-1.2 SITE B-3 MW-CL-1 MW-CL-121 MW-CL-131 MW-CL-138 MW-CL-148 MW-CL-148 MW-CL-151 MW-CL-158 MW-CL-168  
H.       Errata Data The 2014 ARGPP incorrectly reported 607 analyses in the Summary and Conclusion section. The number of analyses in 2014 should have been ,
reported as 253 (IR 02635324).
Page 121of138
 
I. Leaks, Spills, and Releases No leaks, spills or releases were identified during the year.
J. Trends MW-CL-14S had a slight trend upward from <200 pCi/L to 241, 300 and 365 pCi/L respectively in 2015. However, the 1st Quarter of 2016 revealed MW-CL-14S has trended back to 218 pCi/L. Additionally, MW-CL-21S, after it too experienced a slight trend from 219 pCi/L to 287 pCi/L in 2015, has now had consecutive values of 189 pCi/L in the 4th Quarter of 2015 and 191 pCi/L from our 1st Quarter of 2016. All sampling well locations are currently indicating tritium levels that are less than the ODCM LLD of 2,000 pCi/I. All wells will continue to be sampled in accordance with the RGPP in 2016..
K. Investigations Currently no investigations are on-going.
L. Actions Taken
: 1. Compensatory Actions There have been no station events requiring compensatory actions at the Clinton Power Station in 2015.
: 2. Installation of Monitoring Wells No new wells were installed during the 2015.
: 3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.
Page 122of138
 
APPENDIX A LOCATION DESIGNATION OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT
{ARGPPR)
Page 123of138
 
Intentionally left blank Page 124of138
 
TABLEA-1:       Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Site                           Site Type B-3                           Monitoring Well MW-CL-1                       Monitoring Well MW-CL-2                       Monitoring Well MW-CL-121                     Monitoring Well MW-CL-131                     Monitoring Well MW-CL-13S                     Monitoring Well MW-CL-14S                     Monitoring Well MW-CL-151                     Monitoring Well MW-CL-15S                     Monitoring Well MW-CL-16S                     Monitoring Well MW-CL-17S                     Monitoring Well MW-CL-181                     Monitoring Well MW-CL-18S                     Monitoring Well MW-CL-19S                     Monitoring Well MW-CL-20S                     Monitoring Well MW-CL-21S                     Monitoring Well MW-CL-22S                     Monitoring Well Sewage Treatment Plant - - - - Surface Water SW-CL-1                       Surface Water SW-CL-2                       Surface Water SW-CL-4                       Surface Water SW-CL-5                       Surface Water SW-CL-6                       Surface Water SW-CL-7                       Surface Water A-1                                        Page 125of138
 
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CXl Figure A- 2 Sampling Locations South of Clinton Power Station
 
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* RG-3 Figure A-4 Recapture Sampling Locations of Clinton Power Station A-5                             Page 129of138
 
Intentionally left blank Page 130of138
 
APPENDIX B DATA TABLES OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)
Page 131 of 138
 
Intentionally left blank Page 132of138
 
TABLE B-1.1         CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE       DATE         H-3         Sr-89     Sr-90 Gr-A (Dis) Gr-A (Sus)     Gr-8 (Dis) Gr-8 (Sus) 8-3         02/09/15   < 157 8-3         05/26/15   < 194 8-3         08/17/15   < 180       < 5.2     < 0.6   1.2 +/- 0.8   < 1.1         3.2 +/- 1.0 < 1.6 8-3         11/02/15   < 196 MW-CL-1     02/09/15   < 156 MW-CL-1     05/26/15   < 195 MW-CL-1     08/17/15   < 179 -     < 5.4     < 0.6     < 0.9     < 1.1         2.1 +/- 0.9 < 1.6 MW-CL-1     11/02/15   < 187 MW-CL-121   02/09/15   < 178 MW-CL-121   05/26/15   < 196 MW-CL-121   08/17/15   < 191       < 5.6     < 0.6     < 0.9     < 1.1         4.9 +/- 1.0 < 1.6 MW-CL-121   11/02/15       322 +/- 134 MW-CL-131   02/09/15   < 154 MW-CL-131   05/26/15   < 193 MW-CL-131   08/17/15   < 187 .     < 4.0     < 0.6     < 0.7     < 1.1         3.2 +/- 1.1 < 1.6 MW-CL-131   11/02/15   < 187 MW-CL-13S   02/09/15   < 157 MW-CL-13S   05/26/15   < 193 MW-CL-13S   08/17/15   < 199       < 4.7     < 0.6     < 0.6     < 1.1         2.7 +/- 1.0 < 1.6 MW-CL-13S   11/02/15       220 +/- 128 MW-CL-14S   02/09/15   < 156 MW-CL-14S   07/22/15       241 +/- 128 MW-CL-14S   08/18/15       300 +/- 126 < 6.9     < 0.8     < 1.3     < 1.1         11.9 +/- 1.6 < 1.6 MW-CL-14S   11/03/15       365 +/- 136 MW-CL-151   02/09/15   < 156 MW-CL-151   05/26/15   < 193 MW-CL-151   08/17/15   < 174       < 5.7     < 0.7     < 0.7     < 0.5         1.9 +/- 1.0 < 1.7 MW-CL-151   11/02/15   < 193 MW-CL-15S   02/09/15   < 155 MW-CL-15S   05/26/15   < 193 MW-CL-15S   08/17/15   < 197 MW-CL-15S   09/29/15                 < 5.2     < 0.6     < 0.9     < 0.8     < 0.9         < 1.6 MW-CL-15S   11/02/15   < 185 MW-CL-16S   02/09/15   < 186 MW-CL-16S   05/27/15   < 189 MW-CL-16S   08/18/15   <.180 MW-CL-16S   09/29/15                 < 5.6     < 0.7     < 2.3     < 0.8         8.7 +/- 1.4 < 1.6 MW-CL-16S   11/03/15   < 188 MW-CL-17S   02/09/15   < 159 MW-CL-17S   05/27/15   < 194 MW-CL-17S   08/18/15   < 180       < 5.3     < 0.7     < 1.9     < 0.5         3.4 +/- 1.1 < 1.6 MW-CL-17S   11/03/15   < 188 MW-CL-181   02/09/15   < 154 MW-CL-181   05/27/15   < 194 MW-CL-181   08/18/15   < 198       < 5.5     < 0.6     < 1.2     < 0.5         4.2 +/- 1.1 < 1.6 MW-CL-181   11/03/15   < 186 B-1                             Page 133of138
 
TABLE B-1.1         CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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-CL-18S   02/09/15   < 156 MW-CL-18S   05/27/15   < 193 MW-CL-18S   08/18/15   < 189       < 4.5     < 0.8   < 2.1     < 0.5         4.4 +/- 1.2 < 1.6 MW-CL-18S   11/03/15   < 188 MW-CL-19S   02/09/15   < 155 MW-CL-19S   05/26/15   < 194 MW-CL-19S   08/17/15   < 174       < 4.5     < 0.7   < 2.5     < 0.6         6.7 +/- 1.5 < 1.7 MW-CL-19S   11/02/15   < 190 MW-CL-2     02/09/15   < 154 MW-CL-2     05/26/15   < 195 .
MW-CL-2     08/17/15   < 180       < 5.2     < 0.6   < 1.2     < 1.1         3.9 +/- 1.1 < 1.6 MW-CL-2     11/02/15   < 188 MW-CL-20S   02/09/15   < 154 MW-CL-20S   05/26/15   < 198 MW-CL-20S   08/17/15   < 175       < 6.3     < 0.5   < 1.2     < 0.5         2.8 +/- 1.1 < 1.6 MW-CL-20S   11/02/15   < 188 MW-CL-21S   02/09/15       176 +/- 106 MW-CL-21S   05/26/15       219 +/- 130 MW-CL-21S   08/17/15       287 +/- 124 MW-CL-21S   09/29/15   < 197       < 5.3     < 0.8   < 1.8     < 0.8     < 1.5         < 1.6 MW-CL-21S   11/02/15   < 189 MW-CL-22S   02/09/15   < 179 MW-CL-22S   05/27/15   < 194 MW-CL-22S   08/18/15   < 180 MW-CL-22S   09/29/15                 < 4.4     < 0.7   < 2.3     < 0.9         11.2 +/- 1.5 < 1.6 MW-CL-22S   11/03/15   < 192 B-2                             Page 134of138
 
Table 8-1.2              CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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 B-3        08/17/15  < 36  < 29      < 3    <4    < 7    <4    < 6    <4    < 6    < 3    < 4    < 29  < 8 MW-CL-1    08/17/15  < 38  < 36      < 4    < 5    < 10  <4    < 8    < 5    < 8    <4    < 4    < 28  < 13 MW-CL-121  08/17/15  < 38  < 37      < 4    <4    < 8    < 3  < 7    <4    <  7    <4    <4    < 28  < 10 MW-CL-131  08/17/15  < 41      68 +/- 37 < 4    < 4    < 10  < 3  < 8    <4    <  7    <4    <4    < 30  < 9 MW-CL-138  08/17/15  < 37  < 77      < 4    <4    < 11  <4    < 8    ~4    <  8    <4    <4    < 30  < 11 MW-CL-148  02/09/15  < 42  < 68      < 4    < 5    < 9    <4    < 9    < 5    <  8    < 4    <4    < 33  < 10 MW-CL-148  08/18/15  < 38  < 51      < 4    < 5    < 11  < 5  < 9    < 5    <  9    <4    <4    < 31  < 12 MW-CL-151  08/17/15  < 38  < 30      <4      <4    < 8    < 4  < 8    <4    <  7    < 3    < 3    < 28  < 9 MW-CL-158  09/29/15  < 73  < 148      < 6    < 8    < 16  < 8  < 11  < 5    <  11  < 6    < 8    < 34  < 14 OJ I    MW-CL-168   09/29/15  < 79  < 154      < 11    < 9    < 19  < 9  < 19  < 11  < 17    < 7    < 12  < 45  < 12 w    MW-CL-178  08/18/15  < 36  < 32      <4      <4    < 9    <4    < 9    < 5    < 8    < 3    <4    < 27  < 9 MW-CL-181  08/18/15  < 35  < 72      < 5    < 4    < 10  < 4  < 6    <4    < 5    < 3    <4    < 26  < 8 MW-CL-188  08/18/15  < 16  < 32      < 2    < 2    < 4    < 2  < 3    < 2    < 3    < 1    < 2    < 17  < 5 MW-CL-198  08/17/15  < 21  < 47      < 2    < 2    < 6    < 2  < 5    < 3    <4      < 2    < 2    < 24  < 7 MW-CL-2    08/17/15  < 32  < 26      < 3    <4    < 7    < 3  < 6    <4    <  7    < 3    <4    < 32  < 9 MW-CL-208  08/17/15  < 18  < 18      < 2    < 2    < 4    < 2  < 3    < 2    < 3    < 2    < 2    < 18  < 6 MW-CL-218  02/09/15  < 31  < 58      < 3    < 3    < 9    < 3  < 7    < 4    < 8    < 3    <4    < 25  < 8 MW-CL-218  05/26/15  < 15  < 30      < 1    < 2    <4    < 2  < 3    <2    < 3    < 1    < 2    < 13  <4 MW-CL-218  09/29/15  < 57  < 87      < 7    < 7    < 19  < 7  < 14  < 9    < 16    < 8    < 7    < 34  < 12 MW-CL-228  09/29/15  < 80  < 95      < 8    < 6    < 23  < 7  < 20  < 9    < 17    < 9    < 10  < 43  < 9
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                                                                                          "
                                                                                          ,,
1;:
TABLE B-1.3            CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015:
I
                                                                                        *'
                                                                                          !
RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA                    1r 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 THERE WERE NO HARD TO DETECTS ANALYZED IN 2015
:*.
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TABLE B-11.1          CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE                  DATE        H-3 SW-CL-1                02/09/15  < 186 SW-CL-1                05/26/15  < 194 SW-CL-1                08/17/15  < 174 SW-CL-1                11/02/15  < 189 SW-CL-2                02/09/15  < 179 SW-CL-2                05/26/15  < 195 SW-CL-2                08/17/15  < 177 SW-CL-2                11/02/15  < 190 SW-CL-4                02/09/15  < 180 SW-CL-4                05/26/15  < 188 SW-Cl.-4              08/17/15  < 176
                                                              - *-----:-
SW-CL-4                11/02/15  < 191 SW-CL-5                02/09/15  < 182 SW-CL-5                05/26/15  < 194 SW-CL-5                08/17/15  < 173 SW-CL-5                11/02/15  < 191 SW-CL-6                02/09/15  < 177 SW-CL-6                05/26/15  < 194 SW-CL-6                08/17/15  < 174 SW-CL-6                11/02/15  < 188 SW-CL-7                02/09/15  < 183 SW-CL-7                05/26/15  < 195 SW-CL-7                08/17/15  < 181 SW-CL-7                11/02/15  < 194 SEWAGE TREATMENT PLANT 02/09/15  < 182 SEWAGE TREATMENT PLANT 05/26/15  < 192 SEWAGE TREATMENT PLANT 08/17/15  < 177 SEWAGE TREATMENT PLANT 11/02/15  < 193 B-5                              Page 137of138


MW-CL-178 MW-CL-181 MW-CL-188 MW-CL-198 MW-CL-2 MW-CL-208 MW-CL-218 MW-CL-218 MW-CL-218 MW-CL-228 COLLECTION DATE 08/17/15 08/17/15 08/17/15 08/17/15 08/17/15 02/09/15 08/18/15 08/17/15 09/29/15 09/29/15 08/18/15 08/18/15 08/18/15 08/17/15 08/17/15 08/17/15 02/09/15 05/26/15 09/29/15 09/29/15 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER  
Table 8-11.2                       CONCENTRATIONS OF GAMMA EMITTERS IN suRi;:AcE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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-14 DATE CL-SW-CL-1             08/17/15   < 21   < 18     < 2   < 2     < 5     < 2   <4   < 2   <4   <2     <2     < 22   <7 CL-SW-CL-2            08/17/15  < 17     40 + 26 < 1   < 2     <4     < 1   < 3   <2   <3   < 1   < 2   < 17   < 5 CL-SW-CL-4            08/17/15  < 16   < 12     < 1   <2     < 4     < 1   < 3   < 2   < 3   < 1   < 2   < 17   <4 CL-SW-CL-5            08/17/15  < 18   < 47     < 1   < 2     <4     <2   <, 3 <2   < 4   < 2   < 2   < 21   < 6 CL-SW-CL-6            08/17/15  < 18     65 + 31 < 2   < 2     < 5     < 2   <3   < 2   < 4   < 1   <2     < 18   < 6 CL-SW-CL-7            08/17/15  < 15   < 15     < 1   < 1     <4     < 2   < 3   < 2   < 3   < 1   < 1   < 16   < 6 SEWAGE TREATMENT PLANT 08/17/15  < 17   < 17     <2     < 2     <4     < 2   <4   < 2   < 4   < 2   <2     < 20   < 6 OJ I
+/- SIGMA Be-7 < 36 < 38 < 38 < 41 < 37 < 42 < 38 < 38 < 73 < 79 < 36 < 35 < 16 < 21 < 32 < 18 < 31 < 15 < 57 < 80 K-40 Mn-54 < 29 < 3 < 36 < 4 < 37 < 4 68 +/- 37 < 4 < 77 < 4 < 68 < 4 < 51 < 4 < 30 < 148 < 154 < 32 < 72 < 32 < 47 < 26 < 18 < 58 < 30 < 87 < 95 <4 < 6 < 11 <4 < 5 < 2 < 2 < 3 < 2 < 3 < 1 < 7 < 8 Co-58 <4 < 5 <4 < 4 <4 < 5 < 5 <4 < 8 < 9 <4 < 4 < 2 < 2 < 4 < 2 < 3 < 2 < 7 < 6 Fe-59 < 7 < 10 < 8 < 10 < 11 < 9 < 11 < 8 < 16 < 19 < 9 < 10 < 4 < 6 < 7 < 4 < 9 <4 < 19 < 23 Co-60 <4 <4 < 3 < 3 <4 <4 < 5 < 4 < 8 < 9 <4 < 4 < 2 < 2 < 3 < 2 < 3 < 2 < 7 < 7 Zn-65 < 6 < 8 < 7 < 8 < 8 < 9 < 9 < 8 < 11 < 19 < 9 < 6 < 3 < 5 < 6 < 3 < 7 < 3 < 14 < 20 Nb-95 <4 < 5 <4 <4 < 5 < 5 <4 < 5 < 11 < 5 <4 < 2 < 3 <4 < 2 < 4 < 2 < 9 < 9 Zr-95 < 6 < 8 < 7 < 7 < 8 < 8 < 9 < 7 < 11 < 17 < 8 < 5 < 3 <4 < 7 < 3 < 8 < 3 < 16 < 17 Cs-134 Cs-137 < 3 <4 <4 <4 <4 < 4 <4 < 3 < 6 < 7 < 3 < 3 < 1 < 2 < 3 < 2 < 3 < 1 < 8 < 9 < 4 < 4 <4
Q')
<4 <4 <4 <4 < 3 < 8 < 12 <4 <4 < 2 < 2 <4 < 2 < 4 < 2 < 7 < 10 Ba-140 < 29 < 28 < 28 < 30 < 30 < 33 < 31 < 28 < 34 < 45 < 27 < 26 < 17 < 24 < 32 < 18 < 25 < 13 < 34 < 43 La-140 < 8 < 13 < 10 < 9 < 11 < 10 < 12 < 9 < 14 < 12 < 9 < 8 < 5 < 7 < 9 < 6 < 8 <4 < 12 < 9 
"U Dl ca CD}}
""C Dl cc CD _,, (,.) CJ) 0 -_,, (,.) OJ TABLE B-1.3 ,, " ,, 1;: CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015: I *' ! RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA 1r SITE COLLECTION Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 DATE THERE WERE NO HARD TO DETECTS ANALYZED IN 2015 :*. I I; " I* I J l Fe-55 Ni-63 TABLE B-11.1 SITE SW-CL-1 SW-CL-1 SW-CL-1 SW-CL-1 SW-CL-2 SW-CL-2 SW-CL-2 SW-CL-2 SW-CL-4 SW-CL-4 SW-Cl.-4 SW-CL-4 SW-CL-5 SW-CL-5 SW-CL-5 SW-CL-5 SW-CL-6 SW-CL-6 SW-CL-6 SW-CL-6 SW-CL-7 SW-CL-7 SW-CL-7 SW-CL-7 SEWAGE TREATMENT PLANT SEWAGE TREATMENT PLANT SEWAGE TREATMENT PLANT SEWAGE TREATMENT PLANT CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- 2 SIGMA COLLECTION DATE H-3 02/09/15 < 186 05/26/15 < 194 08/17/15 < 174 11/02/15 < 189 02/09/15 < 179 05/26/15 < 195 08/17/15 < 177 11/02/15 < 190 02/09/15 < 180 05/26/15 < 188 08/17/15 < 176 -*-----:-11/02/15 < 191 02/09/15 < 182 05/26/15 < 194 08/17/15 < 173 11/02/15 < 191 02/09/15 < 177 05/26/15 < 194 08/17/15 < 174 11/02/15 < 188 02/09/15 < 183 05/26/15 < 195 08/17/15 < 181 11/02/15 < 194 02/09/15 < 182 05/26/15 < 192 08/17/15 < 177 11/02/15 < 193 B-5 Page 137of138 OJ I Q') "U Dl ca CD Table 8-11.2 SITE COLLECTION DATE CL-SW-CL-1 08/17/15 CL-SW-CL-2 08/17/15 CL-SW-CL-4 08/17/15 CL-SW-CL-5 08/17/15 CL-SW-CL-6 08/17/15 CL-SW-CL-7 08/17/15 SEWAGE TREATMENT PLANT 08/17/15 CONCENTRATIONS OF GAMMA EMITTERS IN suRi;:AcE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER
+/- SIGMA 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-14 < 21 < 18 < 2 < 2 < 5 < 2  
<4 < 2 < 4 < 2 < 2 <
22 <7 < 17 40 + 26 < 1 < 2 <4 < 1 < 3 <2 < 3 < 1 < 2 <
17 < 5 < 16 < 12 < 1 <2 < 4 < 1 < 3 < 2 < 3 < 1 < 2 < 17 <4 < 18 < 47 < 1 < 2 <4 <2 <, 3 <2 < 4 < 2 < 2 <
21 < 6 < 18 65 + 31 < 2 < 2 < 5 < 2 < 3 < 2 < 4 < 1 <2 < 18 < 6 < 15 < 15 < 1 < 1 <4 < 2 < 3 < 2 < 3 < 1 < 1 <
16 < 6 < 17 < 17 <2 < 2 <4 < 2 <4 < 2 < 4 < 2 < 2 <
20 < 6}}

Revision as of 20:42, 30 October 2019

Annual Radiological Environmental Operating Report
ML16125A370
Person / Time
Site: Clinton Constellation icon.png
Issue date: 04/29/2016
From: Stoner T
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
U-604277
Download: ML16125A370 (139)


Text

Exelon Generation Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604277 April 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 '"-"

NRG Docket No. 50-461

Subject:

Clinton Power'Station 2015 Annual Radiological Environmental Operating Report Exelon Generating Company, LLC (Exelon), Clinton Power Station is submitting the 2015 Annual Radiological Environmental Operating Report. This report is submitted in accordance with Technical Specification requirement 5.6.2, "Annual Radiological Environmental Operating Report," and covers the period from January 1, 2015 through December 31, 2015.

This report provides the results of the Radiological Environmental Monitoring Program as specific in Section 3/4 and 6.1 of the Offsite Dose Calculation Manual.

There are no regulatory commitments *contained within this letter.

Questions on this letter may be directed to Mr. Rick Bair, Chemistry Manager, at 217-937-3200.

Respectfully,

~

Theodore R. Stone( tf'\

Site Vice President Clinton Power Station dra/bsz Attachments:

Annual Radiological Environmental Operating Report cc: Regional Administrator- NRG Region Ill NRG Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Emergency Management Agency

Page 1of138 Intentionally left blank Page 2of138

Docket No: 50-461 CL~NTON POWER STAT~ON Annual Radiological Environmental Operating Report January 1 Through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services

  • ~

J:/ ExelonGeneration, Clinton Power Station Clinton, IL 61727 April 2016 Page 3of138

INTENTIONALLY LEFT BLANK Page 4of138

Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ....................................................................................................-................. 3 A. Objectives of the REMP ...................................................................................... 3 B. Implementation of the Objectives ........................................................................ 3 Ill. Program Description ...................................................................................................... 4 A. Sample Collection ............................................................................................... 4 B. Sample Analysis .......................................................:.......................................... 6 C. Data_ lnterpretati<;m ***'.****'._******~:***************************-**~*:*********************:*********************** 6

- ----n_,- Pro-graih Exceptions-........... .-.-.~ ...........-..-.......... :.. :.~.~~~-.-.:-:.-~:.-.... :............ .-:... .-.-.: ......... 8 E. Program Changes .............................................................._ ............................... 12 IV. Results and Discussion ............................................................................................... 12 A. Aquatic Environment ......................................................................................... 12

1. Surface Water. ........................................................................................ 12
2. Drinking Water ........................................................................................ 12
3. Well Water ............................................................................................. 13
4. Fish ......................................................................................................... 13
5. Sediment. ................................................................................................ 14 B. Atmospheric Environment ............... :***************************************************************** 14
1. Airborne .................................................................................................. 14
a. Air Particulates ................................. :........................................*... 14
b. Airborne Iodine ............................................................................ 15
2. Terrestrial ................................................................................................ 15
a. Milk ............................................................................................... 15
b. Food Products ............................................................................. 16
c. Grass ........................................................................................... 16 C. Ambient Gamma Radiation ............................................................................... 16 D. Land Use Survey ............................................................................................... 17 E. Errata Data ........................................................................................................ 17 F. Summary of Results - Inter-laboratory Comparison Program .......................... 18 V. References ................................................................................................................... 22 Page 5of138

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Clinton Power Station, 2015 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods

__,_:Tables ..

Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection, Clinton Power Station, 2015 Figures Figure B-1 Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 Figure B-2 Environmental Sampling Locations Between One and Two Miles from the Clinton Power Station, 2015 Figure B-3 Environmental Sampling Locations Between-Two and Five Miles from the Clinton Power Station, 2015 Figure B-4 Environmental Sampling Locations Greater Than Five Miles from the Clinton Power Station, 2015 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-1.2 Concentrations of Tritium in Surface Water Samples Coll~cted in the Vicinity of Clinton Power Station, 2015.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-11.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

ii Page 6of138

Table C-11.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-11.3 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-111.1 Concentrations of Tritium in Well Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-111.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-IV.1 Concentrations of Gamma Emitters in Fish Samples Collected in the

  • Vicinity of Clinton Power Station, 2015.

~-; *~*' ., -* ,. - - - - - - .. - - - *- - - ~

- - .

-- ............ --..-- - . *- ~ - -

Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vl.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vl.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vl.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Clinton Power Statio_n, 2015.

Table C-Vll.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vlll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vlll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-IX.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-IX.2 Concentrations of Gamma Emitters in Grass Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-X.1 Quarterly DLR Results for Clinton Power Station, 2015.

Table C-X.2 Mean Quarterly DLR Results for the Inner Ring, Outer Ring, Special Interest and Control Locations for Clinton Power Station, 2015.

Table C-X.3 Summary of the Ambient Dosimetry Program for Clinton Power Station, 2015.

iii Page 7of138

Figures Figure C-1 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of CPS, 2015.

Figure C-2 Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of CPS, 2015.

Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, .2015 TaQle D~2 DOE's Mixed Alialyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engine-ering, 2015 * -~- * -

Table D-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 Table D-4 ERA(a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 Table D-5 DOE's Mixed Analyte Performance Evaluation- Program (MAPEP)

Teledyne Brown Engineering, 2015

  • Appendix E Errata Data .

Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 8of138

I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Clinton Power Station (CPS) by Exelon Generation Company, LLC (Exelon) covers the period January 1, 2015 through December 31, 2015.

During that time period, 1,590 analyses were performed on 1,463 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of CPS had no adverse radiological impact on the environment.

There were zero (0) radioactive liquid releases from CPS during 2015. Releases of gaseous radioactive materials were accurately measured in plant effluents.

There were no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite _dose received by.,a member. of the- public in :2015. due-to .the release .oL'---*-*- .

gaseous effluents from CPS was 2.53 E-03 or 0.00253 mRem.

Surface, drinking,_ and well water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of gross beta and 1-131. Naturally occurring K-40 was detected .at levels consistent with those detected in previous years. No fission or activation products were detected. No tritium or gross beta activity was detected. and the required lower limit of detection (LLD) was met.

Fish and shoreline sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish or shoreline sediment samples.

Air particulate samples were analyzed for concentrations of gross. beta and gamma emitting nuclides. Cosmogenic Be-7 and naturally occurring K-40 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.

Iodine- 1-131 analyses were performed on weekly air samples. All results were less than the lower limit of detection for 1-131.

High sensitivity 1-131 analyses and gamma analyses were performed on cow milk samples. All results were below the required LLDs for 1-131.

Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.

Food product samples were analyzed for concentrations of gamma emitting nuclides. Concentrations of cosmogenically produced Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.

Grass samples were analyzed for concentrations of gamma emitting nuclides.

Concentrations of cosmogenically produced Be-7 and naturally occurring K~40 were consistent with those detected in previous years. No fission or activation Page 9of138

products were detected.

Environmental gamma radiation measurements were performed quarterly using Dosimeters of Legal Record (DLR). Levels detected were consistent with those observed in previous years.

Page 10of138

II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on February 15, 1987. The site encloses approximately 13, 730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated on approximately 150 acres. The cooling water discharge flume - which discharges to the eastern arm of the lake - occupies an additional 130 acres.

Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa f.nn_a _Townships.

A Radiological Environmental Monitoring Program (REMP) for CPS was initiated in 1987. The preoperational period for most media covers the periods May 1980 through February 27, 1987 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TSE) and Landauer on samples collected during the period January 1, 2015 through December 31, 2015.

A. Objectives of the REMP The objectives of the REMP are to:

1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

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

1. Identifying significant exposure pathways.
2. Establishing baseline radiological data of media within those pathways.
3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

Page 11 of 138

Ill. Program Description A. Sample Collection This section describes the general collection methods used by Environmental Inc. (Midwest Labs) to obtain environmental samples for the CPS REMP in 2015. Sample locations and descriptions can be found in Tables B-1 and B~2, and Figures B-1 through B-4, Appendix B. The sampling methods used by Environmental Inc. (Midwest Labs) are listed in Table B-2.

Aquatic Environment The aquatic environment was evaluated by performing radiological


-

  • analyses on samples of surface water, drinking water; well-water, fish, and---'-

shoreline sediment. Two gallon water samples were collected monthly from composite samplers located at three surface water locations (CL-90, CL-91 and CL-99) and one drinking water location (CL-14). A monthly grab sample was obtained from one surface water location (CL-13).

Quarterly samples were obtained from two well water locations (CL-70 and CL-12). All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of largemouth bass, crappie, carp, bluegill and channel catfish, the species most commonly harvested from the lakes by sporting fishermen, were collected semiannually at two locations, CL-19 and CL-105. CL-105 was the control location, which is located about 50 miles upwind of the station. Shoreline sediment samples composed of recently deposited substrate were collected at two locations semiannually (CL-78 and CL-105 (control)).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, food produce and grass. Airborne iodine and particulate samples were collected and analyzed weekly at ten locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94). CL-11 was the control location, which is located 16 miles upwind of the station. 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 an independent laboratory for analysis.

Page 12of138

Milk samples were collected biweekly at one location (CL-116) from May through October to coincide with the grazing season, and monthly from November through April. All samples were collected in new unused plastic bottles from the bulk tank at the dairy farm, preserved with sodium bisulfite and shipped promptly to the laboratory.

Food products were collected once a month from June through September at four locations (CL-114, CL-115, CL-117 and CL-118). The control location was CL-114, which is located 12.5 miles upwind of the station. Various broadleaf vegetable samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Grass samples were collected biweekly at four locations (CL-1, CL-2, CL-8 and CL-116) from May through October. CL-116 was the control

- ------~ location, which is -located 14 miles WSW of the station. -Ail samples were --

collected in new unused plastic bags and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct radiation measurements were made using DLRs. Each location consisted of 2 dosimeter sets. The DLRs were exchanged quarterly and sent to Landauer for analysis. The DLR locations were placed around the CPS site as follows:

An inner ring consisting of 16 locations (CL-1, CL-5, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42 CL-43, CL-44, CL-45, CL-46, CL-47, CL-48 and CL-63).

An outer ring consisting of 16 locations (CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80 and CL-81). CL-58MM was installed as part of a volunteer comparison study extending to approximately 5 miles from the site.

A special interest set consisting of seven locations (CL-37, CL-41, CL-49, CL-64, CL-65, CL-74 and CL-75) representing special interest areas.

A supplemental set consisting of 14 locations (CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 and CL-114).

CL-11 represents the control location for all environmental DLRs.

The specific DLR locations were determined by the following criteria:

Page13of138

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 meteorological sectors around the site, where estimated annual dose from CPS, if detected, would be most significant;
3. On hills free from local obstructions and within sight of the HVAC and VG stacks (where practical);
4. And near the closest dwelling to the HVAC and VG stacks in the prevailing downwind direction. /

Each location has two DLRs in a vented PVC conduit located approximately three feet above ground-level. The DLRs were exchanged

  • quarterly and sent to Landauer for analysis.

B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the CPS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-2.

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

1. Concentrations of beta emitters in drinking water and air particulates.
2. Concentrations of gamma emitters in surface, drinking and well water, air particulates, milk, fish, grass, sediment and vegetables.
3. Concentrations of tritium in surface, drinking and well water.
4. Concentrations of 1-131 in air, milk, drinking water and surface water.
5. Ambient gamma radiation levels at various off-site environs.

C. Data Interpretation The radiological and direct radiation data collected prior to CPS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this- report, CPS was considered Page 14of138

operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. 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" value. 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 CPS
  • detection capabilities for-environmental sample analysis.
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 resulting in a negative number. A minimum detectable concentration (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 water, well water, fish, sediment, and milk: 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.

For drinking water, grass, and vegetation: 13 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.

For air particulate: 9 nuclides, Co-60, Nb-95, Zr-95, Ru-103, Ru-106, Cs-134, Cs-137, Ce-141 and Ce-144, were reported.

The mean and ~tandard deviation of the results were calculated.

The standard de;,iation represents the variability of measured results for different samples rather than single analysis uncertainty.

Page 15of138

D. Program Exceptions The exceptions (Issue Reports, IRs) described below are those that are considered 'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM. By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",

October 1978, and within Radiological Assessment Branch Technical Position, Revision 1, November 1979, which states .... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability,

-- - - --" - malfunction of automatic sampling equipment and other legitimate reasons" .... The below section addresses the reporting requirements found within Section 6.0_of the Station's ODCM. -

. *-*- - .. - - . - .*. - - :.. ;-,--- - *----

Exceptions/Anomalies January 14, 2015, IR 02437296 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.

March 04, 2015, IR 02463282 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.

March 11, 2015, IR 02468075 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.

May 07, 2015, IR 02497332 While performing the ODCM weekly air sample collection and equipment verification activities on May 06, 2015, vendor Environmental Inc., Midwest Laboratories (EIML) discovered that the ODCM air samplers CL-2 and CL-3 had no power. In the absence of any severe storms or power outages, it was Page 16of138

indeterminate as to why there was no power. However, the minimum sample volume was reached.

July 01, 2015, IR 02522637 At 1244 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.73342e-4 months <br /> on 07/01/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its ground fault interrupter (GFI) 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.

July 15, 2015, IR 02528489 While performing the weekly inspection on 07/15/15 of ODCM Water Compositors, CL-99 was found not running with the GFI

'tripped' and the sample collection container tipped over inside of the Dog House enclosure. The last weekly inspection performed on July 08, 2015 revealed both as found and as left conditions as being satisfactory. During this 7 day window, Murray and "'frettel, our fleetwide meteorological vendor, reported that Lincoln County had 4.5 inches, Bloomington haq 4.6 inches and DeWitt County had 4 inches of rain which all contributed to the North Fork Creek flooding. This flooding contributed to the 'as found' condition*

noted.

August 19, 2015, IR 02543695 At 1046 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98003e-4 months <br /> on 08/19/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its GFI 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.

August 21, 2015, IR 02545496 During the execution of Work Order #1614812-05 for the recently scheduled Potable Water Outage that commenced at 0325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br />, 08/21/15 the potable water was secured, drained and potable water pumps were placed in Manual OFF. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water samples Page 17of138

throughout the duration of the Potable Water Outage that was restored to service at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on 08/22/15.

November 14, 2015, IR 02588060 During the execution of Clearance Order #129314 and de-energized Circuit 302 per WO 1863079-06 for the recently scheduled outage, potable water was secured at 0006 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on 11/14/15. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water sample throughout the duration of the Potable Water Outage that was restored to service at 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br /> on 11 /14/15.

November 18, 2015, IR 02589324 During the weekly checks of ODCM Water compositors on 11/15/15, at 12:35, CL-90 was found with its GFI 'tripped'. The breaker was reset but the GFI 'tripped' after the initial reset. There was standing water within the doghouse enclosure, which contributed to the GFI tripping both times.

Throughout 2015, the following IRs were generated to document Program exceptions that were entered into the corrective action program for trending purposes.

Missed Samples May 13, 2015, IR 02500319 The ODCM air samplers CL-2 and CL-3 lost power on 05/06/15 (IR

  1. 02497332). A portable generator was placed to supply power to CL-2 & CL-3 air monitoring stations. The minimum sample volume was not reached for that sampling period.

June 03, 2015, IR 02512981 While performing the weekly ODCM Surveillance on Wednesday, June 10, 2015 for the collection of particulate and iodine filters and cartridges, the sample collector noted that upon arrival at CL-7, the sample pump was not running. Instead of the typical run time of approximately 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, the timer registered 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 minutes. The minimum volume was not reached for that sampling period.

Page 18of138

June 13, 2015, IR 02515452 The ODCM air samplers CL-2 and CL-3 lost power some time on or before June 13, 2015 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> when first observed by a Station Security Officer (IR #02514143). Both air sample stations now have back-up generator power, returning both sample stations to service. Minimum sample volume was not collected for that sampling period.

July 29, 2015, IR 02534576

-- - During the Weekly Sample Collection Surveillance it was discovered that the two (2) recently changed out Environmental DLRs for CL-51, placed there on June 25, 2015 as part of the 3rd .

      • - ~-- - * * -- Quarter Exchange, were found-missing: -The adjacent farm field's-culvert had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs, the PVC sample holder or the stanchion pole that it was connected to.

August 20, 2015, IR 02546978 While performing the Weekly OCDM Surveillance on Wednesday, 08/26/15 for the collection of particulate filters and iodine cartridges, it was discovered that there was no electrical power to CL-8. Instead of the typical run time of approximately 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, the timer registered 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> and 36 minutes. The minimum volume was not reached for that sample.

September 24, 2015, IR 02560026 1

During the 4 h Quarter Exchange of Environmental DLRs, it was discovered the CL-46 dosimeters placed on 06/25/15 as part of the 3rd Quarter Exchange were found missing. The adjacent farm field had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs or the PVC sample holder, but the stanchion pole was found lying in the field.

Program exceptions were reviewed to understand the causes of the exception and to return to ODCM sample compliance before the next sampling frequency period.

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

Page 19of138

E. Program Changes There were no changes to the program in 2015.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Composite samples were taken hourly at three locations (CL-90, CL-91 and CL-99) on a monthly schedule and grab samples were taken monthly from one location (CL-13). The following analyses _

were performed.- - ----. -- .. .----"* *-*

lodine-131 Monthly samples from location CL-90 were analyzed for 1-131 activity (Table C-1.1, Appendix C). No 1-131 was detected in any samples and the required LLD was met.

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.2, Appendix C). No tritium was detected in any samples and the required LLD was met.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.

2. Drinking Water Monthly composite samples were taken hourly at one location (CL-14). The'following analyses were performed:

Gross Beta Monthly samples were analyzed for concentrations of gross beta (Tables C-11.1, Appendix C). No Gross beta was detected in any of the samples.

Page 20 of 138

Tritium Monthly samples were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). No tritium was detected in any samples and the required LLD was met.

lodine-131 Monthly samples from location CL-14 were analyzed for 1-131 activity (Table C-11.3, Appendix C). No 1-131 was detected in any samples and the required LLD was met.

Gamma Spectrometry

  • c~* * *** ' Monthly samples Were ana.lyzed for gamma emitting nu elides (Table C-11.4, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
3. Well Water Quarterly grab samples were collected at two locations (CL-7D and CL-12, consisting of CL-12R [a raw water sample from this well]

and CL-12T [same well water, but after treatment and available for consumption]). The following analyses were performed:

Tritium Samples from all locations were analyzed for tritium activity {Table C-111.1, Appendix C). No tritium was detected in any samples and the required LLD was met.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.

4. Fish Fish samples comprised of carp, largemouth bass, bluegill, crappie and channel catfish were collected at two locations (CL-19 and CL-105) semiannually. The following analysis was performed:

Page 21 of 138

Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C).

No plant produced radionuclides were detected and all required LLDs were met.

.5. Shoreline Sediment Aquatic shoreline sediment samples were collected at CL-78 and CL-105 semiannually. The following analysis was performed:

Gamma Spectrometry Shoreline *seaiment samples were analyzed for gamma emitting--*

nuclides (Table C-V.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.

B. Atmospheric Environment

1. Airborne
a. Air Particulates Continuous air particulate samples were collected from 10 locations on a weekly basis. The 10 locations were separated into three groups: Group I represents locations within one mile of the CPS site boundary (CL-2, CL-3, CL-4, CL-6, CL-15 and CL-94); Group II represents the locations at an intermediate distance within one to five miles of CPS (CL-1, CL-7 and CL-8); and Group Ill represents the control location greater than five miles from CPS (CL-11). The following analyses were performed:

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

Detectable gross beta activity was observed at all locations.

Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of CPS. The results from the On-Site locations (Group I) 3 ranged from 7 to 43 E-3 pCi/m with a mean of 19 E-3 Page 22 of 138

pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from 6 to 42 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3 . The results from the Control locations (Group Ill) ranged from 7 to 36 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3 . Comparison of the 2015 air particulate data with previous years' data indicate no measurable impact from the operation of CPS. In addition, a comparison of the weekly mean values for 2014 indicate no notable differences among the three groups.

Gamma Spectrometry Weekly samples were composited quarterly and analyzed

'*for gamma emitting nuclides (Table C-Vl.3, Appendix C).

  • - NcYplant produced*radionuclides were detected and all --- -

required LLDs were met.

b. Airborne Iodine Continuous air samples were collected from 10 locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94) and analyzed weekly for 1-131 (Table C-Vll.1, Appendix C). All results were less than the MDC and the required LLD was met.
2. Terrestrial
a. Milk Samples were collected from CL-116 biweekly May tnrough October to coincide with the grazing season, and monthly November through April. The following analyses were performed:

lodine-131 Milk samples were analyzed for concentrations of 1-131 (Table C-Vlll.1, Appendix C). lodine-131 was not detected in any of the samples. The required LLD was met.

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.2, Appendix C).

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

Page 23 of 138

No plant produced radionuclides were detected and all required LLDs were met.

b. Food Products Broad leaf vegetation samples were collected from four locations (CL-114, CL~115, CL~117 and CL-118) monthly June through September to coincide with the harvest season. The following analysis was performed:

Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). No

-~---***" plant produced radionuclides were detected and all required- - -- ** *-0

-

LLDs were met.

c. Grass Samples were collected from four locations (CL-1, CL-2, CL-8, and CL-116) biweekly May through October. The following analysis was performed:

Gamma Spectrometry Each grass sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.2, Appendix C). No plant produced radionuclides were detected and all required

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing DLRs. Fifty-four DLR locations were established around the site. Results of DLR mea.surements are listed in Tables C-X.1 to C-X.3, Appendix C.

A total of 214 OSLO measurements were made in 2015. The average dose from the inner ring was 23.4 mRem/quarter. The average dose from the outer ring was 23.8 mRem/quarter. The average dose from the special interest group was 23.1 mRem/quarter. The average dose from the supplemental group was 22.1 mRem/quarter. The quarterly measurements ranged from 17.3 to 28.0 mRem/quarter.

The inner ring and outer ring measurements compared well to the Control Station, CL-11, which ranged from 19.9 mRem/quarter to 23.6 Page 24 of 138

mRem/quarter with an average measurement of 21.9 mRem/quarter. A comparison of the Inner Ring and Outer Ring data to the Control Location data indicate that the ambient gamma radiation levels from all the locations were comparable. The historical ambient gamma radiation data from the control location were plotted along with similar data from the Inner and Outer Ring Locations (Figure C-2, Appendix C).

D. Land Use Survey A Land Use Survey conducted during the July through October 2015 growing season around the Clinton Power Station (CPS) was performed by Environmental Inc. (Midwest Labs) for Exelon to comply with Clinton's Offsite Dose Calculation Manual, section 8.0. The purpose of the survey was to document the nearest resident, milk producing animal and garden 2

  • of-greater than 538 m in each of the sixteen 22 % degree sectors-around the site. The distance and direction of all locations from the CPS Station HVAC vent stack were positioned using Global Positioning System (GPS) technology. There were no changes required to the CPS REMP as a result of the Land Use Survey. The results of this survey are summarized below.

Distance in Kilometers from the CPS Station HVAC Vent Stack Sector Residence Garden Milk Animal (km) (km) (km) 1 N 1.5 1.5 1.5 2 NNE 1.5 1.5 >8 3 NE 2.1 3.5 >8 4 ENE 2.9 2.9 >8 5 E 1.7 1.7 >8 6 ESE 5.1 5.3 >8 7 SE 4.4 >8 >8 8 SSE 2.9 4.3 >8 9 s 4.8 4.8 6.6 10SSW 4.7 >8 5.5 11 SW 1.2 5.9 >8 12WSW 3.6 3.7 5.5 13W 2.0 3.2 >8 14WNW 2.6 2.6 >8 15NW 2.7 4.7 >8 16NNW 2.1 2.1 2.1 E. Errata Data There was no errata data for 2015.

Page 25 of 138

F. Summary of Results~ Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of

-air particulate, air iodine, milk, soil, vegetation and water matrices for 25 analytes (Appendix D). The PE samples, supplied by Analytics Inc.,

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

1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TB E'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 Perform~nce Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation speeific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

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

The MAPEP defines three levels of performance: Acceptable

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

For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria. Ten analyses (AP - Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water - Ni:-3, Sr-89, Sr-90, and U natural; Vegetation Page 26 of 138

Sr-90 samples) did not meet the specified acceptance criteria for the following reasons:

- Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained

1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (acceptable with warning) was exceeded. The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the

__ --*~ ----.~"""'- ~: ~- -~shortest half.,.life (27. 7:days) and the lowest.gamma energy_(320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations). This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable. NCR 15-18

2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr.. 90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested st;imple utilized for analysis. The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -

1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 - 553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13

3. Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper acceptance range of 0.0202 Sq/sample. Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered Page 27 of 138

acceptable. MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233. Due to the extremely low activity, it was difficult to quantify the U-234/233. NCR 15-13

4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the. lower acceptance range of 0.53 Sq/sample. The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and

. - - cannot escape to be-counted.--When the sample-media absorbs- -

the alpha particles this is known as self-absorption or attenuation.

The calibration must include a similar configuration/media to correct for the attenuation. In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters.

The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24

- 1.53 Sq/sample. Unlike the MAPEP samples, air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed. NCR 15-13

5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21
6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for Page 28 of 138

the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity. TBE will no longer analyze the air particulate Sr~90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21

7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the lower acceptance range of 0.91 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incompl_ete removal of the isotope of interest for

- the-laboratories analyi:ing-the:cross checks.' TBE suspects-thatthis maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.

Results from previous performance evaluations were reviewed and shown to be acceptable. NCR 15-21

8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively. The yields

- were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09

10. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L.

The technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the EIML laboratory, 90 of 94 analyses met the specified acceptance criteria. Four analyses (Water- Co-57, Fe-55; AP - Co-57; Soil - Sr-90) did not meet the specified acceptance criteria for the following reasons:

1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L.

The reported value should have been 27.84, which would have Page 29 of 138

been evaluated as acceptable. A data entry error resulted in a non-acceptable result.

2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1,06 Sq/sample. The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.
3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed

"-- - --  :-c - low result.' -The reanalysis result of 352 Bq/kg fell within ":- -

acceptance criteria.

4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L.

The known activity was below the routine laboratory detection limits for the available aliquot fraction.

V. References

1. American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," ANSI N545-1975.
2. Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).
3. CPS 2014 Annual Radioactive Effluent Release Report.
4. "Environmental Radioactivity," M. Eisenbud, 1987 (E187).
5. "Natural Radon Exposure in the United States," Donald T. Oakley, U.S.

Environmental Protection Agency. ORP/SID 72-1, June 1972.

6. Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960.
7. International Commission on Radiation Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, "Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977).

Page 30 of 138

8. International Commission on Radiation Protection, Publication No. 39 (1984), "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".
9. * "Radioactivity in the Environment: Sources, Distribution and Surveillance," Ronald L. Kathren, 1984.
10. National Council on Radiation Protection and Measurements, Report No.

22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52).

11. National Council on Radiation Protection and Measurements, Report No.

39, "Basic Radiation Protection Criteria," January 1971.

-- 12. National Council on Radiation Protection and Measurements, Report No.

44, "Krypton-85 in the Atmosphere - Accumulation, Biological Significance, and Control Technology," July 1975.

13. National Council on Radiation Protection and Measurements, Report No.

91, "Recommendations on Limits for Exposure to Ionizing Radiation,"

June 1987.

14. National Council on Radiation Protection and Measurements, Report No.

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

September 1987.

15. National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".
16. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.
17. United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, "Revision 1, July 1977.
18. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1OCFR Part 50, Appendix I, "Revision 1, October 1977.
19. United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program,"

Revision 1, November 1979.

20. United States Nuclear Regulatory Commission, Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Page 31 of 138

Operations) - Effluent Streams and the Environment," Revision 1, February 1979.

21. Technical Specifications, Clinton Power Station, Unit No. 1, Docket No.

50-461, Office of Nuclear Reactor Regulation, 1986. Facility Operating License Number NPF-62.

22. . Clinton Power Station, Updated Safety Analysis Report.
23. Clinton- Power Station, Unit 1, Off-Site Dose Calculation Manual.

Page 32 of 138

--

.. - . -; - - - ._ : -:_ - .. - - .,, ,,...._-;- - --

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Page 33 of 138

Intentionally left blank Page 34 of 138

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 j, INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) i 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 1-131 12 <LLD NA 0 (PCI/LITER)

H-3 16 2000 <LLD <LLD 0 GAMMA 48 MN-54 15 <LLD <LLD 0 C0-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 C0-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 "U

Ill cc m

(,.)

U1 0_,, NB-95 15 <LLD <LLD 0

(,.)

()'.)

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 i NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH IDGHEST 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZR-95 30 <LLD <LLD 0 (PCI/LITER)

CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 CE-144 NA <LLD <LLD 0 DRINKING WATER GR-B 12 4 <LLD NA 0 "U(PCI/LITER)

D.l (Q

CD VJ H-3 4 2000 <LLD NA 0

-

(j) 0

-"

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

,.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NA.ME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 I-131 12 <LLD NA 0 (PCJJLITER)

GAMMA 12 MN-54 15 <LLD NA 0 C0-58 15 <LLD NA 0 FE-59 30 <LLD NA 0 C0-60 15 <LLD NA, 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0

-u Dl (Q

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(.U Ol ZR-95 30 <LLD NA 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQU1RED 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 CS-134 15 <LLD NA 0 (PCI/LITER)

CS-137 18 <LLD NA 0 BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 CE-144 NA <LLD NA 0 WELL WATER H-3 12 2000 <LLD NA 0 (PCI/LITER)

GAMMA 12 MN-54 15 <LLD NA 0

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-

OJ 0 C0-58 15 <LLD NA 0

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 WELL WATER FE-59 30 <LLD NA 0 (PCI/LITER)

C0-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0

)>

I C.11 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 "U

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION . DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED j

MEASUREMENT) (LLD) MEASUREMENTS

"

WELL WATER LA-140 15 <LLD NA 0 (PCI/LITER)

CE-144 NA <LLD NA 0 FISH GAMMA 16

P-(PCI/KG WET) MN-54 130 <LLD <LLD 0 O')

C0-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 C0-60 130 <LLD <LLD 0

"

ZN-65 260 <LLD <LLD 0 "U

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCA;noN 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 MEASURE.tvIBNT) (LLD) MEASUREMENTS FISH ZR-95 NA <LLD <LLD 0 (PCI/KG WET)

CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 CE-144 NA <LLD <LLD 0 SEDIMENT GAMMA 4 "1J(PCI/KG DRY) MN-54 NA <LLD <LLD :i' I* 0 Dl

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0 C0-58 NA <LLD <LLD 0

....>.

w 00 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH IDGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION I 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 MEASUREJ\1ENT) (LLD) MEASUREMENTS SEDIMENT FE-59 NA <LLD <LLD 0 (PCI/KG DRY)

C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 CS-134 150 <LLD <LLD 0 CS-137 180 <LLD <LLD 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 :

INDICATOR CONTROL LOCATION WITH IDGHEST 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 LA-140 NA <LLD <LLD 0 (PCI/KG DRY)

CE-144 NA <LLD <LLD 0 AIR PARTICULATE GR-B 514 JO 19 19 20 CL-3 INDICATOR 0

P-CE-3 PCI/CUMETER) (462/462) (52/52) (50/50) CLINTON'S SECONDARY ACCESS ROAD c.o (6/43) (7/36) (9/43) 0.7 MILES NE OF SITE GAMMA 40 C0-60 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 RU-103 NA <LLD <LLD 0 iJ Ill ca CD

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 MEASURElv!ENT) (LLD) MEASUREMENTS AIR PARTICULATE CS-134 50 <LLD <LLD 0 (E-3 PCI/CU.METER)

CS-137 60 <LLD <LLD 0 CE-141 NA <LLD <LLD 0 CE-144 NA <LLD <LLD 0 AIR IODINE GAMMA 514 (E-3 PCI/CUMETER) I-131 70 <LLD <LLD 0 MILK I-131 19 NA <LLD 0 (PCI/LITER)

GAMMA 19 MN-54 NA NA <LLD 0 C0-58 NA NA <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 '~

INDICATOR CONTROL LOCAfrION 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) i, MEASUREMENTS

,.

MILK FE-59 NA NA <LLD 0 (PCIILITER)

C0-60 NA NA <LLD 0 ZN-65 NA NA <LLD 0 NB-95 NA .NA <LLD 0 ZR-95 NA NA <LLD 0 CS-134 _ 15 NA <LLD 0 CS-137 18 NA <LLD 0 "U

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~ BA-140 60 NA <LLD 1 0

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IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 LA-140 15 NA <LLD 0 (PCI/LITER)

CE-144 NA NA <LLD 0

)>VEGETATION GAMMA 48

~ (PCI/KG WET) MN-54 NA <LLD <LLD 0 N

C0-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME.OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION ZR-95 NA <LLD <LLD 0 (PCI/KG WET)

I-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0

)>

_...

I

(...)

CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 CE-144 NA <LLD <LLD 0

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-

o (PCI/KG WET)

....>.

(,,)

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 GRASS C0-58 NA <LLD <LLD 0 (PCI/KG WET)

FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0

)>

......

I

~

ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 I-131 60 <LLD <LLD 0

""'O Dl co CD

~ CS-134 60 <LLD <LLD 0

-

Ol 0

-"

(,.)

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

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 '

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 GRASS CS-137 80 <LLD <LLD 0 (PCI/KG WET)

BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0

)>

......

I C.J1 CE-144 NA <LLD <LLD 0 DIRECT RADIATION DLR-QUARTERLY 214 NA 23.2 21.9 25.3 CL-51 INDICATOR 0 (MILLIREM/QTR.) (210/210) (4/4) (3/3)

(17.3/28.0) (19.9/23.6) (24.3/26.3) 4.4MILESNW

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Intentionally left blank Page 50 of 138

APPENDIX 8 LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS Page 51 of 138

Intentionally left blank Page 52 of 138

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Location Location Description Distance & Direction From Site A. Surface Water Cl-13 Salt Creek Bridge on Rt. 10 (indicator) 3.6 miles SW CL-90 Discharge Flume (indicator) 0.4 miles SE CL-91 Parnell Boat Access (control) 6.1 miles ENE CL-99 North Fork Access (control) 3.5 miles NNE B. Drinking (Potable) Water CL-14 Station Plant Service Bldg (indicator) Onsite C. Well Water CL-7D Mascoutin Recreation Area (indicator) 2.3 miles ESE CL-12T DeWitt Pump House (indicator) 1.6 miles E CL-12R DeWitt Pump House (indicator) 1.6 miles E D. Milk - bi-weekly I monthly CL-116 Dement Dairy (control) 14 miles WSW E. Air Particulates I Air Iodine CL-1 Camp Quest 1.8 miles W CL-2 Clinton's Main Access Road 0.7 miles NNE CL-3 Clinton's Secondary Access Road 0.7 miles NE CL-4 Residence Near Recreation Area 0.8miles SW CL-6 Clinton's Recreation Area 0.7milesWSW CL-7 Mascoutin Recreation Area 2.3 miles SE CL-8 DeWitt Cemetery 2.2 miles E CL-11 Illinois Power Substation (control) 16 miles S CL-15 Rt. 900N Residence 0.9 miles N CL-94 Old Clinton Road 0.6 miles E F. Fish CL-19 End of Discharge Flume (indicator) 3.4 miles E CL-105 Lake Shelbyville (control) 50 miles S G. Shoreline Sediment CL-7B Clinton Lake (indicator) 2.1 miles SE CL-105 Lake Shelbyville (control) 50 miles S H. Food Products CL-114 Cisco (Control) 12.5 miles SSE CL-115 Site's Secondary Access Road 0.7 miles NE CL-117 Residence North of Site 0.9 miles N CL-118 Site's Main Access Road 0.7 miles NNE I. Grass CL-1 Camp Quest 1.8 miles W CL-2 Clinton's Main Access Road 0.7 miles NNE CL-8 DeWitt Cemetery 2.2 miles E CL-116 Pasture in Rural Kenney (control) 14 miles WSW B-1 Page 53 of 138

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Location Location Description Distance & Direction From Site J. Environmental Dosimetrv - DLR Inner Ring CL-1 1.8 miles W CL-5 0.7 miles NNE CL-22 0.6 miles NE CL-23 0.5 miles ENE CL-24 0.5 miles E CL-34 0.8 miles WNW CL-35 0.7miles NW CL-36 0.6 miles N CL-42 2.8 miles ESE CL-43 2.8 miles SE CL-44 2.3 miles SSE CL-45 2.8 miles S CL-46 2.8 miles SSW CL-47 3.3milesSW CL-48 2.3milesWSW CL-63 1.3 miles NNW Outer Ring CL-51 4.4 miles NW CL-52 4.3 miles NNW CL-53 4.3 miles E CL-54 4.6 miles ESE CL-55 4.1 miles SE CL-56 4.1 miles SSE CL-57 4.6 miles S CL-58 4.3 miles SSW CL-60 4.5 miles SW CL-61 4.5 miles WSW CL-76 4.6 miles N CL-77 4.5 miles NNE CL-78 4.8 miles NE CL-79 4.5 miles ENE CL-80 4.1 miles W CL-81 4.5milesWNW B-2 Page 54 of 138

TABLE B-1: RadiOlogical Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Location Location Description Distance & Direction From Site J. Environmental Dosimetrv- DLR (cont.)

Special Interest CL-37 3.4 miles N CL-41 2.4 miles E CL-49 3.5 milesW CL-64 2.1 miles WNW CL-65 2.6 miles ENE CL-74 1.9 miles W CL-75 0.9 miles N Supplemental CL-2 0.7 miles NNE CL-3 0.7 miles NE CL-4 0.8 miles SW CL-6 0.8 miles WSW CL-7 2.3 miles SE CL-8 2.2 miles E CL-15 0.9 miles N CL-33 11.7 miles SW CL-84 0.6 miles E CL-90 0.4 miles SE CL-91 6.1 miles ENE CL-97 10.3 miles SW CL-99 3.5 miles NNE CL-114 12.5 miles SE CL-11 16 miles S B-3 Page 55 of 138

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Clinton Power Station, 2015 Sample Analysis Sampling Method Analytical Procedure Number Medium Surface Gamma Monthly composite TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous water compositor. Env. Inc., SPM-1 Samplino Procedure Manual Surface Tritium Quarterly composite TSE, TBE-2011 Tritium analysis in drinking water by liquid Water from a continuous scintillation water compositor.

Env. Inc., SPM-1 Sampling Procedure Manual Surface 1-131 Monthly composite TSE, TBE-2012 Radioiodine in various matrices Water from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Drinking Gross Beta Monthly composite TSE, TBE-2008 Gross Alpha and/or gross beta activity in Water from a continuous various matrices water compositor.

Env. Inc., SPM-1 Samplino Procedure Manual Drinking Gamma Monthly composite TSE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Drinking Tritium Quarterly composite TSE, TBE-2011 Tritium analysis in drinking water by liquid Water from a continuous scintillation water compositor.

Env. Inc., SPM-1 Sampling Procedure Manual Drinking 1-131 Quarterly composite TBE, TBE-2031 Radioactive Iodine in Drinking Water Water from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Well Water Gamma Quarterly composite TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Well Water Tritium Quarterly composite TSE, TBE-2011 Tritium analysis in drinking water by liquid from a continuous scintillation water compositor.

Env. Inc., SPM-1 Samplino Procedure Manual Fish Gamma Semi-annual samples TBE-2007 Gamma emitting radioisotope analysis Spectroscopy collected via electroshocking or other techniaues Env. Inc., SPM-1 Samolino Procedure Manual Air Gross Beta One-week composite of TBE, TBE-2008 Gross Alpha and/or gross beta activity in Particulates continuous air various matrices sampling through glass fiber filter paper Env. Inc., SPM-1 Sampling Procedure Manual Air Gamma Quarterly composite of TSE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy each station Env. Inc., SPM-1 Samolinq Procedure Manual Air Iodine Gamma One-week composite of TSE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy continuous air sampling through Env. Inc., SPM-1 Sampling Procedure Manual charcoal filter Milk 1-131 Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices when cows are on pasture. Monthly all other times Env. Inc., SPM-1 Samolino Procedure Manual Milk Gamma Bi-weekly grab sample TBE-2007 Gamma emitting radioisotope analysis Spectroscopy when cows are on pasture. Monthly all other times Env. Inc., SPM-1 Samolina Procedure Manual B-4 Page 56 of 138

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Clinton Power Station, 2015 Sample Analysis Sampling Method Analytical Procedure Number Medium Food Gross Beta Monthly grab June TBE, TBE-2008 Gross Alpha and/or gross beta activity in Products through September various matrices Env. Inc., SPM-1 Samolinq Procedure Manual Food Gamma Spectroscopy Monthly grab June TBE, TBE-2007 Gamma emitting radioisotopes analysis Products through September Env. Inc., SPM-1 Samolinq Procedure Manual Grass Gamma Spectroscopy Biweekly May through TBE, TBE-2007 Gamma emitting radioisotopes analysis October Env. Inc., SPM-1 Samolinq Procedure Manual DLR Optically Stimulated Quarterly DLRs Landauer Incorporated Luminescence com prised of two Dosimetry Al20 3:C Landauer Incorporated elements.

B-5 Page 57 of 138

l I N

I 15 Figure B-1 Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 B-6 Page 58 of 138

Figure 8-2 Environmental Sampling Locations Between One and Two Miles of the Clinton Power Station, 2015 B-7 Page 59 of 138

  • Figure B-3 Environmental Sampling Locations between Two and Five Miles from the Clinton Power Station ,

2015 B-8 Page 60 of 138

Figure B-4 Environmental Sampling Locations Greater Than Five Miles of the Clinton Pov.er Station, 2015 B-9 Page 61 of 138

Intentionally left blank Page 62 of 138

APPENDIX C DATA TABLES AND FIGURES -

PRIMARY LABORATORY Page 63 of 138

Intentionally left blank Pag~ 64 of 138

Table C-1.1 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-90 PERIOD 12/31/14 - 01/28/15 < 0.6 01/28/15 - 02/25/15 < 0.3 02/25/15 - 03/25/15 < 0.7 03/25/15 - 04/29/15 < 0.4 04/29/15 - 05/27/15 < 0.2 05/27/15 - 06/24/15 < 0.9 06/24/15 - 07/29/15 < 0.3 07/29/15 - 08/26/15 < 0.8 08/26/15 - 09/30/15 < 0.6 09/30/15 - 10/28/15 < 0. 7 10/28/15 - 11/25/15 < 0.8 11/25/15 - 12/30/15 < 0.6 MEAN Table C-1.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-90 CL-13 CL-91 CL-99 PERIOD 01/28/15 - 03/25/15 < 196 < 196 < 199 < 198 (1) 04/29/15 - 06/24/15 < 192 < 188 < 189 < 191 07/29/15 - 09/30/15 < 195 < 198 < 197 < 196 10/28/15 - 12/30/15 < 188 < 187 < 188 < 189 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 Page 65 of 138

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-13 01/28/15 - 01/28/15 < 6 < 6 < 12 < 6 < 12 < 6 < 11 < 6 < 6 < 26 < 9 < 36 02/25/15 - 02/25/15 <4 <4 < 8 <4 <7 < 5 < 7 <4 <4 < 21 < 5 < 33 03/25/15 - 03/25/15 < 3 <4 < 8 < 3 < 7 < 3 < 6 < 3 < 3 < 27 < 8 < 28 04/29/15 - 04/29/15 < 7 < 7 < 12 < 6 < 13 < 8 < 15 < 6 < 7 < 28 < 6 < 50 05/27/15 - 05/27/15 < 7 < 8 < 15 < 7 < 19 < 10 < 15 < 8 < 9 < 38 < 10 < 43 06/24/15 - 06/24/15 < 6 < 9 < 17 < 6 < 8 < 10 < 13 < 8 < 7 < 34 < 11 < 60 07/29/15 - 07/29/15 < 7 < 6 < 14 < 7 < 13 < 7 < 11 < 5 < 6 < 29 < 11 < 52 08/26/15 - 08/26/15 < 5 <7 < 16 < 8 < 18 < 6 < 11 < 7 < 8 < 32 < 10 < 59 09/30/15 - 09/30/15 < 7 < 6 < 13 < 8 < 12 <8 < 12 < 7 < 8 < 31 < 12 < 49 10/28/15 - 10/28/15 < 6 < 7 < 14 < 8 < 9 < 6 < 9 < 5 < 6 < 27 < 7 < 43 11/25/15 - 11/25/15 < 5 < 5 < 12 < 5 < 5 < 5 < 8 <4 < 5 < 24 <4 < 37 12/30/15 - 12/30/15 < 5 < 6 < 10 < 4 < 12 < 5 < 10 I <4 < 6 < 25 < 13 < 44 MEAN

()

I CL-90 12/31/14 - 01/28/15 < 5 < 5 < 10 < 6 < 12 < 5 < 9 < 5 < 5 < 30 < 10 < 40 N

01/28/15 - 02/25/15 <4 <4 < 7 <4 < 6 <4 < 6 < 3 <4 < 18 < 5 < 30 02/25/15 - 03/25/15 <4 < 5 < 9 < 5 < 8 <4 < 7 < 4 <4 < 28 < 12 < 31 03/25/15 - 04/29/15 < 7 <7 < 17 < 6 < 18 < 9 < 13 < 8 < 8 < 31 < 11 < 51 04/29/15 - 05/27/15 < 6 < 8 < 16 < 7 < 14 < 8 < 12 < 7 < 8 < 39 < 14 < 55 05/27/15 - 06/24/15 < 7 < 6 < 13 < 7 < 17 < 7 < 12 < 7 < 8 < 39 < 9 < 53 06/24/15 - 07/29/15 < 6 < 5 < 10 < 5 < 12 < 6 < 10 < 6 < 6 < 24 < 9 < 44 07/29/15 - 08/26/15 < 3 < 3 < 7 <4 < 5 <4 < 6 < 3 < 4 < 18 < 6 < 30 08/26/15 - 09/30/15 < 6 < 8 < 9 < 7 < 11 < 6 < 8 < 5 < 5 < 27 < 12 < 46 09/30/15 - 10/28/15 < 5 < 7 < 12 < 6 < 13 < 6 < 11 < 6 < 6 < 36 < 5 < 49 10/28/15 - 11/25/15 < 6 < 5 < 12 < 6 < 12 < 6 < 10 < 5 < 5 < 34 < 11 < 47 11/25/15 - 12/30/15 < 5 < 6 < 14 < 7 < 12 < 6 < 12 < 6 < 7 < 35 < 11 < 44 MEAN "U

OJ ca CD O'J O'J

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0

__,. THE MEAN AND lWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES w

OJ

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-91 12/31/14 - 01/28/15 < 6 < 5 < 12 <4 < 12 <7 < 8 < 5 < 6 < 28 < 11 < 45 01/28/15 - 02/25/15 < 6 < 7 < 13 < 8 < 12 < 5 < 7 < 6 < 6 < 32 <7 < 58 02/25/15 - 03/25/15 < 3 < 3 < 7 < 3 < 6 < 3 < 5 < 3 < 3 < 25 < 6 < 30 03/25/15 - 04/29/15 <6 <6 < 13 <7 < 14 < 8 < 16 < 7 < 9 < 41 < 9 < 63 04/29/15 - 05/27/15 < 6 < 7 < 10 < 5 < 12 < 6 < 8 < 5 < 6 < 24 < 8 < 41 05/27/15 - 06/24/15 < 5 < 7 < 13 <5 < 13 < 6 < 12 < 6 < 7 < 29 < 12 < 51 06/24/15 - 07/29/15 <4 <4 < 8 <4 < 8 < 5 < 8 <4 < 4 < 18 < 5 < 34 07/29/15 - 08/26/15 < 5 < 3 < 7 <4 < 11 < 5 < 9 < 5 < 5 < 23 < 8 < 38 08/26/15 - 09/30/15 < 7 < 7 < 18 < 7 < 18 < 8 < 14 < 8 < 8 < 41 < 11 < 69 09/30/15 - 10/28/15 < 6 < 8 < 12 < 8 < 12 < 6 < 12 < 6 < 8 < 30 < 14 < 41 10/28/15 - 11/25/15 < 5 < 5 < 9 <4 < 11 < 6 < 8 < 5 < 5 < 28 < 8 < 43 11/25/15 - 12/30/15 < 6 < 6 < 16 < 6 < 14 < 8 < 13 < 5 < 7 < 31 < 12 < 39 MEAN

()

I

(...) CL-99 12/31/14 - 01/28/15 < 3 < 4 < 9 < 5 < 8 < 5 < 7 < 5 < 5 < 24 < 9 < 37 01/28/15 - 02/25/15 < 6 < 6 < 9 < 5 < 10 < 6 < 9 < 5 < 6 < 28 < 9 < 45 02/25/15 - 03/25/15 < 3 < 3 < 6 < 3 < 6 < 3 < 6 <4 < 4 < 26 < 4 < 35 03/25/15 - 04/29/15 < 9 < 8 < 19 < 11 < 18 < 9 < 12 < 9 < # < 45 < 13 < 52 04/29/15 - 05/27/15 < 5 < 7 < 15 < 6 < 14 < 6 < 7 < 6 < 6 < 31 <7 < 47 05/27/15 - 06/24/15 < 6 < 6 < 13 < 8 < 17 < 9 < 15 < 8 < 8 < 31 < 14 < 41 06/24/15 - 07/29/15 < 4 < 3 < 8 < 3 < 8 <4 < 6 <4 <4 < 20 < 7 < 30 07/29/15 - 08/26/15 < 6 < 5 < 12 < 5 < 14 < 5 < 10 < 5 < 7 < 28 < 8 < 43 08/26/15 - 09/30/15 < 6 < 8 < 16 < 8 < 17 < 10 < 12 < 7 < 7 < 36 < 13 < 67 09/30/15 - 10/28/15 < 6 < 6 < 11 < 6 < 15 < 7 < 12 < 7 < 7 < 33 < 10 < 55 10/28/15 - 11/25/15 < 6 <7 < 14 < 8 < 14 <6 < 12 < 6 < 8 < 35 < 10 < 39 11/25/15 - 12/30/15 < 7 < 7 < 18 < 10 < 16 < 9 < 12 < 9 < 8 < 41 < 11 < 69 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-11.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-14 PERIOD 12/31/14 - 01/28/15 < 1.4 01/28/15 - 02/25/15 < 1.5 02/25/15 - 03/25/15 < 1.5 03/25/15 - 04/29/15 < 1.6 04/29/15 - 05/27/15 < 1.3 05/27/15 - 06/24/15 < 1.5 06/24/15 - 07/29/15 < 1.4 07/29/15 - 08/26/15 < 1.6 08/26/15 - 09/30/15 < 1.5 09/30/15 - 10/28/15 < 1.5 10/28/15 - 11 /25/15 < 1.5 11/25/15 - 12/30/15 < 1.5 MEAN Table C-11.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-14 PERIOD 12/31/14 - 03/25/15 < 199 03/25/15 - 06/24/15 < 187 06/24/15 - 09/30/15 < 199 09/30/15 - 12/30/15 < 187 MEAN Table C-11.3 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-14 PERIOD 12/31/14 - 01/28/15 < 0.3 01/28/15 - 02/25/15 < 0.4 02/25/15 - 03/25/15 < 0.3 03/25/15 - 04/29/15 < 0.4 04/29/15 - 05/27/15 < 0.3 05/27/15 - 06/24/15 < 0.4 06/24/15 - 07/29/15 < 0.4 07/29/15 - 08/26/15 < 0.9 08/26/15 - 09/30/15 < 0.7 09/30/15 - 10/28/15 < 0.6 10/28/15 - 11 /25/15 < 0.7 11 /25/15 - 12/30/15 < 0.6 MEAN C-4 Page 68 of 138

Table C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-14 12/31/14 - 01/28/15 < 4 <5 < 11 <4 < 8 < 4 < 9 <4 < 4 < 18 < 6 < 37 01/28/15 - 02/25/15 < 6 < 5 < 13 < 6 < 10 < 7 < 11 I < 5 < 6 < 27 < 7 < 48 02/25/15 - 03/25/15 < 3 <4 < 8 <4 < 7 <4 < 8 < 3 <4 < 23 < 7 < 31 03/25/15 - 04/29/15 < 8 < 8 < 18 <8 < 21 < 10 < 14 < 8 <8 < 33 < 12 < 61 04/29/15 - 05/27/15 < 5 < 6 < 9 < 6 < 9 <7 < 12 < 6 < 6 < 32 < 6 < 52 05/27/15 - 06/24/15 < 9 < 7 < 18 < 8 < 15 < 8 < 15 < 8 < 10 < 41 < 5 < 67 06/24/15 - 07/29/15 < 5 < 5 < 11 < 5 < 11 < 4 < 8 <4 < 6 < 27 < 8 < 41 07/29/15 - 08/26/15 < 7 < 8 < 15 <7 < 13 <7 < 12 < 6 < 8 < 33 < 11 < 59 08/26/15 - 09/30/15 < 5 < 5 < 14 <5 < 13 < 7 < 12 <6 < 5 < 30 < 10 < 44 09/30/15 - 10/28/15 < 5 < 6 < 11 < 6 < 11 <5 < 8 < 6 < 5 < 28 < 7 < 46 10/28/15 - 11/25/15 <4 < 4 < 9 <4 < 9 < 5 < 8 <4 < 5 < 21 < 7 < 34 11/25/15 - 12/30/15 <4 < 8 < 16 <4 < 10 < 9 < 12 < 6 < 8 < 43 < 12 < 51 MEAN

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Table C-111.1 CONCENTRATIONS OF TRITIUM IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-12R CL-12T CL-70 PERIOD 03/25/15 - 03/25/15 < 182 < 181 < 180 06/24/15 - 06/24/15 < 164 < 164 < 160 09/30/15 - 09/30/15 < 185 < 187 < 186 12/30/15 - 12/30/15 < 196 < 196 < 192 MEAN C-6 Page 70 of 138

Table C-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION; 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-12R 03/25/15 < 5 <6 < 10 < 5 < 10 < 5 < 10 < 5 < 6 < 39 < 13 < 38 06/24/15 < 9 <7 < 12 < 7 < 17 < 9 < 13 < 5 < 6 < 32 < 12 < 62 09/30/15 < 8 <4 < 17 <4 < 14 < 5 < 11 ,, < 6 < 7 < 36 < 10 < 54 12/30/15 <4 < 7 < 15 <6 < 12 < 8 < 10 < 5 < 7 < 32 < 10 < 49 MEAN CL-12T 03/25/15 < 5 < 5 < 10 <4 < 9 < 5 < 8 < 5 < 5 < 32 < 8 < 37 06/24/15 < 10 < 9 < 17 < 10 < 20 < 10 < 15- < 8 < 9 < 46 < 13 < 80 09/30/15 < 5 *< 8 < 14 < 6 < 13 < 9 < 14 < 7 < 7 < 38 < 8 < 47 12/30/15 < 8 < 6 < 15 <5 < 17 < 8 < ~5 < 6 < 8 < 43 < 8 < 57 MEAN

() CL-70 03/25/15 <4 <4 < 9 < 3 < 6 <4 < 8 < 3 <4 < 23 <7 < 30 I

06/24/15 < 7 < 9 < 17 < 7 < 20 < 9 < 20 < 8 < 9 < 36 < 13 < 51

""" 09/30/15 12/30/15

< 7

< 6

< 8

< 5

<

<

18 10

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5 5

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12 12

< 8

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14 .['

9

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7 5

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MEAN j:

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Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 '

RESULTS IN UNITS OF PCl/KG WET+/- 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 Ce-144 PERIOD CL-105 Bluegill 04/23/15 < 51 < 53 < 109 < 48 < 99 < 56 < 104 < 50 < 70 < 519 < 178 < 385 Carp 04/23/15 < 63 < 71 < 105 < 60 < 159 < 57 < 126 < 52 < 60 < 500 < 153 < 312 Channel Catfish 04/23/15 < 44 < 41 < 118 < 41 < 94 < 56 < 96 < 41 < 53 < 386 < 124 < 273 Largemouth Bass 04/23/15 < 102 < 98 < 228 < 83 < 205 < 115 < 188 < 91 < 87 < 841 < 194 < 524 bluegill 10/05/15 < 39 < 38 < 73 < 40 < 82 < 37 < 61 < 34 < 36 < 186 < 52 < 189 carp 10/05/15 < 46 < 50 < 97 < 49 < 98 < 49 < 79 < 47 < 46 < 237 < 74 < 200 crappie 10/05/15 < 63 < 55 < 112 < 65 < 160 < 70 < 88 < 61 < 55 < 295 < 72 < 323 largemouth bass 10/05/15 < 70 < 65 < 136 < 62 < 117 < 71 < 93 < 39 < 65 < 243 < 46 < 381 MEAN CL-19 Bluegill 04/23/15 < 73 < 85 < 217 < 101 < 163 < 87 < 155 < 79 < 79 < 802 < 142 < 499 Carp 04/23/15 < 74 < 86 < 174 < 76 < 146 < 76 < 180 < 67 < 70 < 657 < 225 < 421

() Channel Catfish 04/23/15 < 57 < 75 < 163 < 74 < 163 < 78 < 140 < 67 < 60 < 500 < 181 < 354 I Largemouth Bass 04/23/15 < 63 < 74 < 159 < 61 < 123 < 75 < 122 < 70 < 51 < 564 < 107 < 410 O:>

bluegill 10/05/15 < 56 < 82 < 156 < 61 < 132 < 75 < 120 < 83 < 62 < 389 < 130 < 392 carp 10/05/15 < 69 < 50 < 117 < 63 < 144 < 29 < 122 < 64 < 74 < 431 < 101 < 404 channel catfish 10/05/15 < 66 < 78 < 144 < 77 < 97 < 90 < 123 < 70 < 83 < 408 < 83 < 332 largemouth bass 10/05/15 < 88 < 83 < 177 < 84 < 190 < 92 < 136 < 74 < 90 < 476 < 124 < 510 MEAN

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THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES w

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Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG DRY+/- 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 Ce-144 PERIOD CL-078 04/23/15 < 40 < 49 < 135 < 40 < 99 < 55 < 89 . < 33 < 41 < 761 < 171 < 241 10/05/15 < 69 < 63 < 140 < 80 < 108 < 68 < 136 < 60 < 72 < 336 < 69 < 322 MEAN CL-105 04/23/15 < 44 < 49 < 123 < 45 < 106 < 59 < 101 < 38 < 44 < 748 < 198 < 312 10/05/15 < 76 < 92 < 217 < 121 < 173 < 62 < 153 < 84 < 80 < 417 < 93 < 400

.

MEAN '*

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c.v CXl THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

.,.

Table C-Vl.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION. 2015 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA COLLECTION GROUP I PERIOD CL-2 CL-3 CL-4 CL-6 CL-15 CL-94 12/31/14 - 01/07/15 20 +/- 4 20 +/- 5 21 +/- 5 21 +/- 5 21 +/- 5 18 +/- 4 01/07/15 - 01/14/15 19 +/- 4 20 +/- 4 20 +/- 4 18 +/- 4 20 +/- 4 16 +/- 4 01/14/15 - 01/21/15 26 +/- 5 31 +/- 5 23 +/- 5 30 +/- 5 26 +/- 5 28 +/- 5 01/21/15 - 01/28/15 13 +/- 4 14 +/- 4 14 +/- 4 11 +/- 4 14 +/- 4 14 +/- 4 01/28/15 - 02/04/15 19 +/- 4 17 +/- 4 17 +/- 4 18 +/- 4 18 +/- 4 20 +/- 5 02/04/15 - 02/11/15 29 +/- 5 28 +/- 5 31 +/- 5 25 +/- 5 27 +/- 5 24 +/- 5 02/11 /15 - 02/18/15 23 +/- 4 24 +/- 5 23 +/- 4 24 +/- 5 22 +/- 4 27 +/- 5 02/18/15 - 02/25/15 35 +/- 5 43 +/- 6 41 +/- 5 40 +/- 6 37 +/- 5 37 +/- 5 02/25/15 - 03/04/15 23 +/- 5 23 +/- 5 24 +/- 5 22 +/- 5 14 +/- 4 16 +/- 4 03/04/15 - 03/11/15 18 +/- 4 17 +/- 4 15 +/- 4 17 +/- 4 19 +/- 4 14 +/- 4 03/11/15 - 03/18/15 16 +/- 4 13 +/- 4 12 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 03/18/15 - 03/25/15 15 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 16 +/- 4 03/25/15 - 04/01/15 14 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 17 +/- 4

_04/01/15 - 04/08/15 9 +/-_4 - JJ +/- 4 _10 +/- 4 13 +/- 4 11 +/- 4 13 +/- 4 04/08/15 - 04/15/15 17 +/- 4 18 +/- 4 13 +/- 4 16 +/- 4 16 +/- 4 17 +/- 4 04/15/15 - 04/22/15 13 +/- 4 16 +/- 4 19 +/- 4 16 +/- 4 17 +/- 4 18 +/- 4 04/22/15 - 04/29/15 9+/-3 11+/-4 15 +/- 4 13 +/- 4 12 +/- 4 12 +/- 4 04/29/15 - 05/06/15 16 +/- 4 14 +/- 4 15 +/- 4 17 +/- 4 17 +/- 4 18 +/- 4 05/06/15 - 05/13/15 9 +/- 6 (1) < 9 (1) 12 +/- 4 7 +/-4 9 +/-4 9 +/-4 05/13/15 - 05/20/15 11+/-4 9+/-4 7 +/-4 9 +/-4 8+/-4 9+/-4 05/20/15 - 05/27/15 30 +/- 8 32 +/- 8 18 +/- 4 17 +/- 4 16 +/- 4 18 +/- 4 05/27/15 - 06/03/15 13 +/- 4 12 +/- 4 14 +/- 4 13 +/- 4 12 +/- 4 9 +/-4 06/03/15 - 06/10/15 16 +/- 4 16 +/- 4 20 +/- 4 22 +/- 4 18 +/- 4 17 +/- 4 06/10/15 - 06/17/15 < 23 (1) < 20 (1) 13 +/- 4 14 +/- 4 15 +/- 4 14 +/- 4 06/17/15 - 06/24/15 11+/-4 13+/-4 13 +/- 4 12 +/- 4 11 +/- 4 11 +/- 4 06/24/15 - 07/01/15 13+/-4 11+/-4 10 +/- 4 8+/-4 10 +/- 4 11 +/- 4 07/01/15 - 07/08/15 13 +/- 4 12 +/- 4 12 +/- 4 14 +/- 4 12 +/- 4 15 +/- 4 07/08/15 - 07/15/15 10+/-3 9+/-4 8 +/- 3 14 +/- 4 10 +/- 4 14 +/- 4 07/15/15 - 07/22/15 16 +/- 5 14 +/- 4 13 +/- 4 16 +/- 4 12 +/- 4 20 +/- 4 07/22/15 - 07/29/15 18 +/- 4 24 +/- 5 17 +/- 4 22 +/- 5 21 +/- 5 17 +/- 4 07/29/15 - 08/05/15 20 +/- 4 18 +/- 4 21 +/- 4 20 +/- 4 20 +/- 4 20 +/- 4 08/05/15 - 08/12/15 21 +/- 4 24 +/- 4 20 +/- 4 21 +/- 4 23 +/- 4 23 +/- 4 08/12/15 - 08/19/15 29 +/- 5 29 +/- 5 29 +/- 5 29 +/- 5 26 +/- 5 21 +/- 5 08/19/15 - 08/26/15 17 +/- 4 17 +/- 4 16 +/- 4 13 +/- 4 18 +/- 4 17 +/- 4 08/26/15 - 09/02/15 36 +/- 5 31 +/- 5 31 +/- 5 34 +/- 5 33 +/- 5 39 +/- 5 09/02/15 - 09/09/15 35 +/- 5 35 +/- 5 36 +/- 5 33 +/- 5 28 +/- 5 39 +/- 5 09/09/15 - 09/16/15 15 +/- 4 13 +/- 4 15 +/- 4 17 +/- 4 15 +/- 4 16 +/- 4 09/16/15 - 09/23/15 19 +/- 5 20 +/- 5 24 +/- 5 17 +/- 4 18 +/- 4 21 +/- 5 09/23/15 - 09/30/15 30 +/- 5 25 +/- 5 24 +/- 5 24 +/- 5 27 +/- 5 26 +/- 5 09/30/15 - 10/07/15 12 +/- 4 9 +/-4 11 +/- 4 13 +/- 4 13 +/- 4 12 +/- 4 10/07/15 - 10/14/15 22 +/- 5 21 +/- 5 21 +/- 5 27 +/- 5 21 +/- 5 25 +/- 5 10/14/15 - 10/21/15 16 +/- 4 18 +/- 4 21 +/- 4 20 +/- 4 14 +/- 4 19 +/- 4 10/21/15 - 10/28/15 17 +/- 4 21 +/- 4 20 +/- 4 21 +/- 4 19 +/- 4 20 +/- 4 10/28/15 - 11 /04/15 19 +/- 5 14 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 19 +/- 5 11 /04/15 - 11 /11 /15 25 +/- 5 27 +/- 5 20 +/- 4 24 +/- 5 18 +/- 4 21 +/- 4 11/11/15 - 11/18/15 27 +/- 5 23 +/- 4 26 +/- 5 26 +/- 5 27 +/- 5 24 +/- 4 11/18/15 - 11/25/15 17 +/- 4 16 +/- 4 19 +/- 4 18 +/- 4 16 +/- 4 15 +/- 4 11/25/15 - 12/02/15 16 +/- 4 16 +/- 4 17 +/- 4 18 +/- 4 19 +/- 4 15 +/- 4 12/02/15 - 12/09/15 34 +/- 5 33 +/- 5 37 +/- 6 37 +/- 5 35 +/- 5 33 +/- 5 12/09/15 - 12/16/15 17 +/- 5 18 +/- 5 20 +/- 5 20 +/- 5 18 +/- 5 20 +/- 5 12/16/15 - 12/23/15 22 +/- 5 28 +/- 5 19 +/- 4 25 +/- 5 24 +/- 5 20 +/- 4 12/23/15 - 12/30/15 15 +/- 4 16 +/- 4 18 +/- 4 22 +/- 4 18 +/- 4 17 +/- 4 MEAN 19 +/- 14 20 +/- 15 19 +/- 14 19 +/- 14 18 +/- 13 19 +/- 14 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-10 Page 74of138

Table C-Vl.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION. 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP II GROUP Ill PERIOD CL-1 CL-7 CL-8 CL-11 12/31/14 - 01/07/15 26 +/- 5 W+/- 4 22 +/- 5 17 +/- 4 01/07/15 - 01/14/15 19 +/- 4 17 +/- 4 19 +/- 4 19 +/- 4 01/14/15 - 01/21/15 28 +/- 5 25 +/- 5 25 +/- 5 28 +/- 5 01/21/15 - 01/28/15 13 +/- 4 9 .+/- 4 15 +/- 4 11 +/- 4 01/28/15 - 02/04/15 13 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 02/04/15 - 02/11/15 26 +/- 5 26 +/- 5 25 +/- 5 27 +/- 5 02/11/15 - 02/18/15 23 +/- 5 22 +/- 4 21 +/- 4 23 +/- 4 02/18/15 - 02/25/15 39 +/- 5 39 +/- 5 42 +/- 6 36 +/- 5 02/25/15 - 03/04/15 20 +/- 5 20 +/- 5 20 +/- 5 17 +/- 4 03/04/15 - 03/11/15 15 +/- 4 15 +/- 4 18 +/- 4 20 +/- 4 03/11/15 - 03/18/15 16 +/- 4 13 +/- 4 15 +/- 4 13 +/- 4 03/18/15 - 03/25/15 16 +/- 4 17 +/- 4 19 +/- 4 18 +/- 4 03/25/15 - 04/01/15 14 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 0<!/01/15 - 04/08/15 12 +/- 4. 11 +/- 4 11 +/- 4 11 +/- 4 04/08/15 - 04/15/15 17 +/- 4 17 +/- 4 15 +/- 4 15 +/- 4 04/15/15 - 04/22/15 19 +/- 4 14 +/- 4 20 +/- 4 17 +/- 4 04/22/15 - 04/29/15 12 +/- 4 10 +/- 4 12 +/- 4 12 +/- 4 04/29/15 - 05/06/15 16 +/- 4 17 +/- 4 19 +/- 4 17 +/- 4 05/06/15 - 05/13/15 11 +/- 4 8 +/- 4 9 +/-4 8+/-4 05/13/15 - 05/20/15 9+/-4 8 +/- 4 10 +/- 4 7 +/- 4 05/20/15 - 05/27/15 14 +/- 4 13 +/- 4 18 +/- 4 17 +/- 4 05/27/15 - 06/03/15 12 +/- 4 9 +/- 4 8 +/-4 13 +/- 4 06/03/15 - 06/10/15 16 +/- 4 (1) 19 +/- 4 18 +/- 4 06/10/15 - 06/17/15 13 +/- 4 12 +/- 4 16 +/- 4 14 +/- 4 06/17/15 - 06/24/15 13 +/- 4 11 +/- 4 12 +/- 4 15 +/- 4 06/24/15 - 07/01/15 10 +/- 4 10 +/- 4 12 +/- 4 13 +/- 4 07/01/15 - 07/08/15 10 +/- 4 11 +/- 4 13 +/- 4 11 +/- 4 07/08/15 - 07/15/15 10 +/- 4 8 +/- 3 10 +/- 4 9 +/- 3 07/15/15 - 07/22/15 12 +/- 4 15 +/- 4 15 +/- 4 17 +/- 4 07/22/15 - 07/29/15 22 +/- 5 19 +/- 4 20 +/- 4 20 +/- 4 07/29/15 - 08/05/15 21 +/- 4 19 +/- 4 19 +/- 4 16 +/- 4 08/05/15 - 08/12/15 19 +/- 4 22 +/- 4 25 +/- 4 19 +/- 4 08/12/15 - 08/19/15 28 +/- 5 26 +/- 5 29 +/- 5 28 +/- 5 08/19/15 - 08/26/15 14 +/- 4 14 +/- 4 < 37 (1) 18 +/- 4 08/26/15 - 09/02/15 33 +/- 5 28 +/- 5 37 +/- 7 34 +/- 5 09/02/15 - 09/09/15 35 +/- 5 32 +/- 5 38 +/- 5 34 +/- 5 09/09/15 - 09/16/15 17 +/- 4 11 +/- 4 16 +/- 4 18 +/- 4 09/16/15 - 09/23/15 18 +/- 4 17 +/- 4 21 +/- 5 20 +/- 5 09/23/15 - 09/30/15 25 +/- 5 24 +/- 5 22 +/- 4 25 +/- 5 09/30/15 - 10/07/15 15 +/- 4 14 +/- 4 14 +/- 4 11 +/- 4 10/07/15 - 10/14/15 22 +/- 5 27 +/- 5 22 +/- 5 23 +/- 5 10/14/15 - 10/21/15 17 +/- 4 15 +/- 4 20 +/- 4 18 +/- 4 10/21/15 - 10/28/15 20 +/- 4 6 +/- 3 21 +/- 4 19 +/- 4 10/28/15 - 11/04/15 22 +/- 5 20 +/- 5 14 +/- 4 24 +/- 5 11/04/15 - 11/11/15 22 +/- 4 24 +/- 4 22 +/- 4 23 +/- 4 11/11/15 - 11/18/15 21 +/- 4 21 +/- 4 22 +/- 4 20 +/- 4 11/18/15 - 11/25/15 15 +/- 4 16 +/- 4 14 +/- 4 16 +/- 4 11/25/15 - 12/02/15 17 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 12/02/15 - 12/09/15 36 +/- 5 35 +/- 5 30 +/- 5 32 +/- 5 12/09/15 - 12/16/15 17 +/- 5 15 +/- 4 17 +/- 5 19 +/- 5 12/16/15 - 12/23/15 26 +/- 5 24 +/- 5 21 +/- 5 23 +/- 5 12/23/15 - 12/30/15 17 +/- 4 17 +/- 4 19 +/- 4 17 +/- 4 MEAN 19 +/- 14 17 +/- 14 19 +/- 14 19 +/- 13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11 Page 75 of 138

Table C-Vl.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - INTERMEDIATE DISTANCE LOCATIONS GROUP Ill - CONTROL LOCATIONS COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/-

PERIOD 2SD PERIOD 2SD PERIOD 2SD 12/31/14 - 01/28/15 11 31 20 +/- 11 12/31/14 - 01/28/15 9 28 19 +/- 11 I

12/31/14 - 01/28/15 11 28 19 +/- 14 01 /28/15 - 02/25/15 17 I 43 27 +/- 16 01 /28/15 - 02/25/15 13 42 26 +/- !9 01/28/15 - 02/25/15 16 36 26 +/- 17 02/25/15 - 04/01/15 12 24 16 +/- 6 02/25/15 - 04/01 /15 13 20 17 +/- 5 02/25/15 - 04/01/15 13 20 16 +/- 5 04/01 /15 - 04/29/15 9 19 14 +/- 6 04/01/15 - 04/29/15 10 20 14 +/- 7 04/01/15 - 04/29/15 11 17 14 +/- 6 04/29/15 - 06/03/15 7 32 14 +/- 12 04/29/15 - 06/03/15 8 19 12 +/- 8 04/29/15 - 06/03/15 7 17 12 +/- 9 06/03/15 - 07/01/15 8 22 14 +/- 7 06/03/15 - 07/01/15 10 19 13 +/- 6 06/03/15 - 07/01/15 13 18 15 +/- 4 07/01 /15 - 07129/15 8 24 15 +/- 8 07/01/15 - 07/29/15 . 8 22 14 +/- 9 07/01/15 - 07/29/15 9 20 14 +/- 10 07/29/15 - 09/02/15 13 39 24 +/- 13 07/29/15 - 09/02/15 14 37 24 +/- 14 07/29/15 - 09/02/15 16 34 23 +/- 15 09/02/15 - 09/30/15 13 39 24 +/- 15 09/02/15 - 09/30/15 11 38 23 +/- 16 09/02/15 - 09/30/15 18 34 24 +/- 14 09/30/15 - 10/28/15 9 27 18 +/- 9 09/30/15 - 10/28/15 6 27 18 +/- 11 09/30/15 - 10/28/15 11 23 18 +/- 10 10/28/15 - 12/02/15 14 27 20 +/- 8 10/28/15 - 12/02/15 14 24 19 +/- 7 10/28/15 - 12/02/15 16 24 20 +/- 8 12/02/15 - 12/30/15 15 37 24 +/- 15 12/02/15 - 12/30/15 15 36 23 +/- 15 12/02/15 - 12/30/15 17 32 23 +/- 13

()

I 12/31/14 - 12/30/15 7 43 19 +/- 14 12/31/14 - 12/30/15 6 42 18 +/- 14 12/31/14 - 12/30/15 7 36 19 +/- 13

-"

N i*

I

"O Dl co CD

""-.!

-

())

0

_,..

(J.)

co

I*

Table C-Vl.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTl,CULATE " SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA

'

SITE COLLECTION Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-13'7* Ce-141 Ce-144 PERIOD :1.

CL-1 12/31/14 - 04/01/15 <2 <6 < 8 < 7 < 32 < 4 <3 ~; < 9 < 13 04/01/15 - 07/01/15 < 3 <4 < 7 <5 < 23 < 3 < 2 'i' <7 < 12 07/01/15 - 09/30/15 < 3 <3 < 5 < 3 < 21 < 2 <2 .<5 < 10

  • 09/30/15 - 12/30/15 < 5 <4 < 9 < 5 < 34 <4 <4 < 6 < 14

MEAN - "'

CL-11 12/31/14 - 04/01/15 <3 < 3 < 6 < 6 < 18 <3 <2 < 7 < 12 04/01/15 - 07/01/15 <2 < 5 < 9 < 8 < 32 < 4 <4 < 10 < 17 07/01/15 - 09/30/15 < 2 <3 < 6 <4 < 21 < 2 < 2 *. < 5 < 9 09/30/15 - 12/30/15 < 5 <4 < 8 <5 < 36 <4 <4 ~' .

!  !

< 6 < 15 MEAN

() CL-15 12/31/14 - 04/01/15 < 6 < 9 < 10 < 8 < 46 < 4 < 5 *i: < 12 < 15

......

I 04/01/15 - 07/01/15 < 3 < 2 < 6 <4 < 18 < 3 < 3 '.

" < 5 < 11 VJ 07/01/15 < 3 < 5 < 16

- 09/30/15 < 3 < 7 < 25 < 3 < 3 < 8 09/30/15 - 12/30/15 <2 < 3 < 5 < 3 < 25 < 2 <2 < 5 < 12

i~

MEAN - ".

CL-2 12/31/14 - 04/01/15 < 5 < 3 < 6 <4 < 17 < 3 <2 < 8 < 13 04/01/15 - 07/01/15 < 2 < 3 <4 <4 < 16 < 3 <2 ; < 6 < 11 07/01/15 - 09/30/15 < 3 < 3 <5 <4 < 23 < 3 < 3 '< 6 < 11 09/30/15 - 12/30/15 < 3 < 3 <5 < 4 < 26 < 2 <3 *

('

I'

<4 < 11 MEAN

i CL-3 12/3.1/14 - 04/01/15 < 8 < 9 < 15 < 10 < 37 <5 < 5 < 12 < 17 04/01/15 - 07/01/15 < 3 <4 < 8 < 6 < 21 <3 < 3 < 7 < 12

"'C 07/01/15 - 09/30/15 < 3 <4 < 6 <4 < 25 < 3 < 3 < 5 < 10 Dl (C 09/30/15 - 12/30/15 <4 <4 < 6 < 5 < 21 <4 < 3 . < 6 < 16

\*

CD *::

---1 !1

-

-

---1 MEAN !I*

0

_,,,

c,j 'io CXl :r THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

,,'*

.r

"

Table C-Vl.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATiON, 2015 l'

.r RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA i'

,,

SITE COLLECTION Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 PERIOD CL-4 12/31/14 - 04/01/15 <5 <4 < 10 < 7 < 24 < 3 < 3 < 9 < 17

04/01/15 07/01/15 < 3 <4 <6 < 5 < 23 < 2 < 2 ,, < 6 < 10 07/01/15 - 09/30/15 <2 <4 < 6 < 3 < 18 <2 < 2. < 5 < 10 09/30/15 - 12/30/15 <2 <2 <4 < 3 < 18 <2 < 2 <4 < 8 MEAN  ;

CL-6 12/31/14 04/01/15 < 3 < 6 < 13 < 10 < 42 < 5 < 5 < 15 < 23

,.

04/01/15 - 07/01/15 < 3 <4 <4 <4 < 21 < 3 < 2 ,,,.. < 7 < 10 07/01/15 - 09/30/15 <4 <6 < 8 < 5 < 33 <4 <4 < 6 < 10

  • ).

09/30/15 12/30/15 <2 < 3 <3 <3 < 20 <2 < 2 <4 < 9

  • .

.;i MEAN - ,,

"*

() CL-7 12/31/14 - 04/01/15 <4 <4 < 8 <6 < 26 < 3 <3 ,, < 6 < 14

....

~

I 04/01/15 - 07/01/15 <4 <6 < 11 < 9 < 37 <4 <4

.!*

< 10 < 14 07/01/15 - 09/30/15 < 3 <4 < 6 <4 < 24 < 3 <2 < 7 < 15 09/30/15 - 12/30/15 < 3 < 3 < 6 < 3 ' <' 19 < 3 <2 < 5 < 10 MEAN - J'..

I*!

1*

CL-8 12/31/14 - 04/01/15 < 4 < 5 < 9 < 7 < 21 <3 < 3 < 10 < 16 04/01/15 - 07/01/15 < 3 <4 < 7 < 5 < 25 < 3 < 2 < 7 < 13 07/01/15 - 09/30/15 < 3 <6 < 11 < 6 < 38 <4 < 3 < 10 < 23 09/30/15 - 12/30/15 < 3 < 3 <4 < 3' < 21 <2 < 2 < 5 < 12 MEAN CL-94 12/31/14 - 04/01/15 < 3 <5 < 8 < 7 < 29 <4 < 3 *, < 10 < 14 04/01/15 - 07/01/15 < 2 < 2 < 4 < 3 < 17 < 1 < 1 <4 < 7

"

-a 07/01/15 - 09/30/15 < 2 < 2 < 5 <3 < 20 <2 < 2 < 6 < 10 ru 09/30/15 - 12/30/15 < .2 <2 < 5 <4 < 25 <2 < 3 "" <4 < 12 cc CD

-.J

-

co 0

......

w co MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES "

,,fl

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP I PERIOD CL-2 CL-3 CL-4 CL-6 CL-15 CL-94 12/31/14 - 01/07/15 < 38 < 38 < 37 < 38 < 43 < 43 01/07/15 - 01/14/15 < 60 < 60 < 60 < 62 < 63 < 64 01/14/15 - 01/21/15 < 40 < 41 < 40 < 40 < 16 < 37 01/21/15 - 01/28/15 < 33 < 33 < 34 < 33 < 60 < 33 01 /28/15 - 02/04/15 < 41 < 44 < 42 < 43 < 52 < 52 02/04/15 - 02/11 /15 < 38 < 39 < 39 < 39 < 32 < 18 02/11/15 - 02/18/15 < 69 < 69 < 68 < 69 < 66 < 65 02/18/15 - 02/25/15 < 54 < 54 < 54 < 55 < 45 < 45 02/25/15 - 03/04/15 < 23 < 24 < 23 < 23 < 22 < 22 03/04/15 - 03/11/15 < 58 < 61 < 59 < 61 < 44 < 44 03/11/15 - 03/18/15 < 19 < 47 < 47 < 47 < 34 < 44 03/18/15 - 03/25/15 < 39 < 40 < 39 < 40 < 52 < 52 03/25/15 - 04/01/15 < 44 < 17 < 45 < 45 < 37 < 36 04/01/15 - 04/08/15 < 53 < 56 < 54 < 54 < 56 < 56 04/08/15 - 04/15/15 < 64 < 64 < 64 < .60 < 26 < 25

. 04/15/15 - 04/22/15 < 58 .. < 59 <"58 < *58- ** < 63 < 62 04/22/15 - 04/29/15 < 41 < 44 < 42 < 23 < 20 < 44 04/29/15 - 05/06/15 <44 <45 < 42 < 42 < 53 < 52 05/06/15 - 05/13/15 < 33.~ (1) < 31 (1) < 48 < 47 < 48 < 47 05/13/15 - 05/20/15 < 64 < 65 < 62 < 63 < 36 < 37 05/20/15 - 05/27/15 < 46 < 46 < 25 < 20 < 28 < 27 05/27/15 - 06/03/15 < 66 < 69 < 67 < 66 < 68 < 68 06/03/15 - 06/10/15 < 69 < 68 < 67 < 40 < 66 < 65 06/10/15 - 06/17/15 < 88 (1) < 77 (1) < 38 < 15 < 40 < 18 06/17/15 - 06/24/15 < 58 < 60 < 58 < 23 < 64 < 64 06/24/15 - 07/01/15 < 19 < 55 < 52 < 52 < 44 < 44 07/01/15 - 07/08/15 < 61 < 26 < 64 < 62 < 23 < 59 07/08/15 - 07/15/15 < 53 < 56 < 56 < 56 < 47 < 46 07/15/15 - 07/22/15 < 35 < 61 < 59 < 59 < 61 < 58 07/22/15 - 07/29/15 < 30 < 31 < 12 < 31 < 37 < 37 07/29/15 - 08/05/15 < 26 < 63 < 64 < 63 < 53 < 53 08/05/15 - 08/12/15 < 47 < 50 < 20 < 50 < 34 < 33 08/12/15 - 08/19/15 < 31 < 32 < 31 < 12 < 37 < 39 08/19/15 - 08/26/15 < 45 < 45 < 18 < 45 < 49 < 46 08/26/15 - 09/02/15 < 24 < 59 < 58 < 58 < 38 < 39 09/02/15 - 09/09/15 < 34 < 35 < 34 < 44 < 34 < 34 09/09/15 - 09/16/15 < 37 < 37 < 37 < 49 < 42 < 41 09/16/15 - 09/23/15 < 44 < 46 < 43 < 44 < 52 < 54 09/23/15 - 09/30/15 < 43 < 44 < 43 < 43 < 56 < 56 09/30/15 - 10/07/15 < 62 < 63 < 62 < 24 < 59 < 61 10/07/15 - 10/14/15 < 63 < 63 < 61 < 63 < 54 < 55 10/14/15 - 10/21/15 < 64 < 67 < 67 < 28 < 15 < 39 10/21/15 - 10/28/15 < 30 < 31 < 30 < 30 < 49 < 48 10/28/15 - 11/04/15 < 63 < 64 < 62 < 64 < 40 < 41 11/04/15 - 11/11/15 < 68 < 69 < 69 < 69 < 55 < 55 11/11/15 - 11/18/15 < 45 < 47 < 47 < 48 < 51 < 49 11/18/15 - 11/25/15 < 67 < 68 < 67 < 65 < 65 < 65 11/25/15 - 12/02/15 < 36 < 35 < 35 < 35 < 39 < 38 12/02/15 - 12/09/15 < 55 < 54 < 54 < 37 < 14 < 37 12/09/15 - 12/16/15 < 59 < 59 < 59 < 55 < 23 < 56 12/16/15 - 12/23/15 < 54 < 54 < 54 < 53 < 55 < 54 12/23/15 - 12/30/15 < 49 < 48 < 47 < 46 < 47 < 45 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15 Page 79 of 138

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP II I GROUP Ill PERIOD CL-1 CL-7 CL-8 CL-11 12/31/14 - 01/07/15 < 15 < 18 < 44 < 43 01/07/15 - 01/14/15 < 34 < 34 < 65 < 63 01/14/15 - 01/21/15 < 15 < 37 < 37 < 37 01/21/15 - 01/28/15 < 18 < 60 < 60 < 60 01/28/15 - 02/04/15 < 23 < 27 < 51 < 50 02/04/15 - 02/11/15 < 16 < 32 < 32 < 32 02/11/15 - 02/18/15 < 27 < 27 < 66 < 66 02/18/15 - 02/25/15 < 24 < 16 < 47 < 45 02/25/15 - 03/04/15 < 10 < 8 < 22 < 22 03/04/15 - 03/11 /15 < 22 < 18 < 43 < 43 03/11/15 - 03/18/15 < 47 < 56 < 35 < 36 03/18/15 - 03/25/15 < 17 < 27 < 51 < 51 03/25/15 - 04/01/15 < 44 < 20 < 36 < 35 04/01/15 - 04/08/15 < 21 < 24 < 57 < 56 04/08/15 - 04/15/15 < 64 < 60 < 58 < 60 04/15/15 - 04/22/15 "< 25 < 22 < 65 --- < 63 04/22/15 - 04/29/15 < 43 < 45 < 44 < 44 04/29/15 - 05/06/15 < 44 < 42 < 42 < 53 05/06/15 - 05/13/15 < 48 < 19 < 47 < 47 05/13/15 - 05/20/15 < 63 < 60 < 37 < 37 05/20/15 - 05/27/15 < 25 < 20 < 8 < 20 05/27/15 - 06/03/15 < 68 < 67 < 67 < 67 06/03/15 - 06/10/15 < 69 (1) < 15 < 25 06/10/15 - 06/17/15 < 39 < 43 < 41 < 44 06/17/15 - 06/24/15 < 60 < 27 < 64 < 62 06/24/15 - 07/01/15 < 51 < 24 < 44 < 44 07/01/15 - 07/08/15 < 65 < 59 < 58 < 60 07/08/15 - 07/15/15 < 23 < 16 < 46 < 45 07/15/15 - 07/22/15 < 59 < 60 < 30 < 59 07/22/15 - 07/29/15 < 31 < 37 < 36 < 15 07/29/15 - 08/05/15 < 63 < 54 < 52 < 23 08/05/15 - 08/12/15 < 51 < 13 < 34 < 34 08/12/15 - 08/19/15 < 31 < 16 < 37 < 37 08/19/15 - 08/26/15 < 46 < 47 < 170 (1) < 48 08/26/15 - 09/02/15 < 58 < 15 < 54 < 37 09/02/15 - 09/09/15 < 35 < 44 < 42 < 33 09/09/15 - 09/16/15 < 38 < 48 < 49 < 42 09/16/15 - 09/23/15 < 17 < 23 < 53 < 53 09/23/15 - 09/30/15 < 17 < 24 < 55 < 55 09/30/15 - 10/07/15 < 61 < 24 < 60 < 59 10/07/15 - 10/14/15 < 25 < 22 < 54 < 54 10/14/15 - 10/21/15 < 66 < 39 < 39 < 39 10/21/15 - 10/28/15 < 12 < 50 < 20 < 48 10/28/15 - 11/04/15 < 27 < 20 < 43 < 41 11/04/15 - 11/11/15 < 27 < 21 < 55 < 55 11/11/15 - 11/18/15 < 26 < 20 < 50 < 50 11/18/15 - 11/25/15 < 29 < 33 < 64 < 64 11/25/15 - 12/02/15 < 14 < 40 < 15 < 38 12/02/15 - 12/09/15 < 54 < 21 < 36 < 36 12/09/15 - 12/16/15 < 58 < 22 < 56 < 56 12/16/15 - 12/23/15 < 21 < 23 < 54 < 55 12/23/15 - 12/30/15 < 19 < 44 < 46 < 18 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16 Page 80 of 138

Table C-Vlll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA CONTROL FARM COLLECTION CL-116 PERIOD 01/28/15 < 0.3 02/25/15 <: 0.3 03/25/15 < 0.6 04/29/15 < 0.1 OS/13/15 < 0.9 05/27/15 < 0.5 06/10/15 < 0.9 06/24/15 < 0.5 07/08/15 < 0.8 07/22/15 < 0.4 08/05/15 < 0.6 08/19/15 < 0.7

. *-*- -- 09/02/15 - -. -< 0.8_- ___ - -" .. .,...- *-- ----~- ---- >.

--

09/16/15 < 0.6 09/30/15 < 0.8 10/14/15 < 0.6 10/28/15 < 0.6 11/25/15 < 0.9 12/30/15 < 1.0 MEAN C-17 Page 81 of 138

Table C-Vlll.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Ce-144

"'

PERIOD CL-116 01/28/15 1295 +/- 138 < 6 < 6 < 15 < 7 < 13 < 6 .< 9 < 5 < 6 < 30 < 8 < 34 02/25/15 1426 +/- 167 < 6 < 7 < 14 < 7 < 20 < 7 < 11 < 6 < 6 < 28 < 10 < 45 03/25/15 1007 +/- 141 < 5 < 5 < 15 < 6 < 12 < 6 '< 9 < 5 < 6 < 28 < 8 < 35 04/29/15 05/13/15 1345 1277

+/- 149

+/- 123

< 5

< 8

< 6

< 8

< 16

< 19

< 7

< 8

< 12

< 21

< 5

< 9

> 11

< 16

< 5

< 9

< 6

< 9

< 27

< 47

< 9

< 11

< 41

< 65 05/27/15 1203 +/- 205 < 11 < 7 < 18 < 9 < 19 < 9 < 17 < 9 < 9 < 36 < 11 < 47 06/10/15 1282 +/- 211 < 9 < 8 < 26 < 7 < 23 < 9  ; < 13 < 7 < 8 < 56 < 9 < 64 06/24/15 1378 +/- 197 < 9 < 9 < 20 < 11 < 21 < 10 i < 17 < 9 < 10 < 42 < 15 < 48 07/08/15 1344 +/- 168 < 6 < 6 < 18 < 9 < 17 < 6 < 9 < 5 < 7 < 28 < 5 < 42 07/22/15 1242 +/- 158 < 6 < 7 < 18 < 8 < 18 < 6  : < 13 < 7 < 8 < 32 < 9 < 44 08/05/15 1464 +/- 217 < 9 < 10 < 16 < 9 < 23 < 9 ', < 18 < 9 < 10 < 40 < 13 < 48 08/19/15 1025 +/- 195 < 9 < 8 < 14 < 10 < 23 < 9 < 17 < 9 < 10 < 35 < 10 < 68

() 09/02/15 1490 +/- 233 < 11 < 7 < 22 < 8 < 21 < 10 < 16 < 9 < 9 < 42 < 11 < 79 I

...... 09/16/15 1158 +/- 170 < 7 < 8 < 20 < 8 < 19 < 9 < 16 < 8 < 8 < 37 < 10 < 68 co 09/30/15 1187 +/- 211 < 9 < 9 < 19 < 9 < 21 < 10 < 18 < 9 < 10 < 46 < 13 < 56 10/14/15 1107 +/- 174 < 7 < 8 < 20 < 9 < 22 < 8 < 14 < 8 < 8 < 33 < 10 < 49 10/28/15 1159 +/- 141 < 7 < 6 < 12 < 6 < 18 < 5 < 11 < 7 < 6 < 25 < 9 < 48 11/25/15 1296 +/- 157 < 7 < 7 < 17 < 7 < 21 < 8 < 11 < 7 < 8 < 35 < 12 < 49 12/30/15 1445 +/- 180 < 8 < 7 < 15 < 8 < 16 < 9 < 15 < 7 < 8 < 36 < 10 < 61 MEAN 1270 +/- 282 "U

[l) cc CD OJ

-

N 0

....>.

(,,)

OJ

Table C-IX.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-114 06/24/15 Cabbage < 6 < 6 < 15 < 6 < 13 < 6 < 10 .< 18 < 6 < 6 < 41 < 11 < 37 06/24/15 Lettuce < 16 < 20 < 38 < 19 < 39 < 18 < 31 < 60 < 15 < 17 < 109 < 15 < 117 06/24/15 Swiss Chard < 18 < 18 < 42 < 17 < 39 < 20 < 32 < 59 < 17 < 19 < 125 < 43 < 86 07/29/15 Cabbage < 9 < 11 < 23 < 9 < 19 < 11 < 17 < 60 < 9 < 10 < 101 < 22 < 68 07/29/15 Lettuce <6 <7 < 18 < 6 < 15 <7 < 13 < 36 < 6 <6 < 60 < 16 < 40 07/29/15 Swiss Chard < 11 < 13 < 33 < 12 < 29 < 13 < 23 < 59 < 10 < 11 < 113 < 35 < 52 08/26/15 Cabbage < 31 < 33 < 80 < 37 < 75 < 30 < 47 1< 50 < 30 < 37 < 170 < 49 < 166 08/26/15 Lettuce < 18 < 26 < 49 < 25 < 47 < 24 < 43 :1 < 49 < 22 < 26 < 120 < 27 < 173 08/26/15 Swiss Chard < 42 < 37 < 86 < 39 < 82 < 43 < 57 '< 59 < 34 < 26 < 167 < 49 < 228 09/30/15 Cabbage < 23 < 24 < 54 < 20 < 51 < 20 < 40 < 46 < 22 < 23 < 105 < 36 < 149 09/30/15 Kale < 23 < 26 < 61 < 23 < 59 < 25 < 42  :< 50 < 24 < 27 < 123 < 24 < 179 09/30/15 Swiss Chard < 27 < 39 < 107 < 40 < 101 < 41 < 59 < 59 < 34 < 38 < 156 < 44 < 244 MEAN CL-115 06/24/15 Cabbage < 14 < 14 < 33 < 15 < 27 < 16 < 22 .< 49 < 15 < 14 < 99 < 30 < 86 06/24/15 Lettuce < 16 < 18 < 36 < 18 < 36 < 19 < 29 < 51 < 13 < 17 < 109 < 26 < 91

() 06/24/15 Swiss Chard < 14 < 17 < 31 < 17 < 34 < 16 < 30 < 54 < 14 < 16 < 107 < 27 < 105

......

I 07/29/15 Cabbage < 8 < 8 < 21 < 7 < 18 < 10 < 15 .< 57 < 8 < 8 < 90 < 23 < 57 CD 07/29/15 Lettuce < 6 < 7 < 17 < 6 < 15 < 7 < 12 .< 34 < 5 < 6 < 62 < 15 < 37 07/29/15 Swiss Chard <7 < 8 < 18 < 7 < 16 < 8 < 13 < 39 < 6 < 7 < 67 < 20 < 47 08/26/15 Cabbage < 34 < 34 < 78 < 34 < 94 < 33 < 65 < 59 < 34 < 35 < 193 < 49 < 236 08/26/15 Lettuce < 26 < 26 < 68 < 34 < 68 < 31 < 46 .< 46 < 22 < 28 < 116 < 32 < 160 08/26/15 Swiss Chard < 30 < 35 < 80 < 31 < 81 < 38 < 52 '< 60 < 30 < 36 < 169 < 47 < 252 09/30/15 Cabbage < 29 < 19 < 65 < 26 < 57 < 28 < 47 "< 45 < 21 < 26 < 140 < 40 < 153 09/30/15 Kale < 20* < 32 < 67 < 29 < 65 < 27 < 48 < 55 < 27 < 25 < 132 < 44 < 204 09/30/15 Swiss Chard < 21 < 25 < 59 < 28 < 38 < 23 < 50 < 42 < 24 < 20 < 124 < 13 < 143 MEAN i

'..

"

'

"'U Ill cc CD

())

-

w 0

-"

w

())

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

Table C-IX.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-117 06/24/15 Cabbage < 13 < 11 < 26 < 11 < 29 < 14 < 22 < 39 < 11 < 12 < 86 < 21 < 77 06/24/15 Lettuce < 12 < 16 <"34 < 13 < 34 < 16 < 28 .1.< 37 < 13 < 14 < 101 < 26 < 68 06/24/15 Swiss Chard < 15 < 19 < 39 < 17 < 36 < 18 < 32 '< 51 < 16 < 17 < 117 < 39 < 93 07/29/15 Cabbage < 10 < 12 < 26 < 10 < 23 < 12 < 20  :< 55 < 9 < 10 < 96 < 29 < 57 07/29/15 Lettuce <4 < 5 < 12 < 4 < 10 < 5 <9 < 27 <4 < 4 < 43 < 13 < 25 07/29/15 Swiss Chard < 6 < 7 < 16 < 6 < 14 < 7 < 12 < 39 < 6 < 6 < 65 < 17 < 40 08/26/15 Cabbage < 32 < 33 < 67 < 26 < 68 < 33 < 59 < 56 < 29 < 29 < 170 < 52 < 209 08/26/15 Lettuce < 33 < 31 < 81 < 37 < 80 < 39 < 63 < 51 < 39 < 32 < 160 < 30 < 219 08/26/15 Swiss Chard < 24 < 23 < 46 < 18 < 39 < 29 < 37 < 43 < 20 < 25 < 116 < 32 < 178 09/30/15 Cabbage < 27 < 24 < 54 < 26 < 48 < 27 < 49 < 41 < 21 < 24 < 108 < 23 < 142 09/30/15 Kale < 24 < 23 < 51 < 23 < 51 < 26 < 39 < 41 < 23 < 20 < 104 < 25 < 154 09/30/15 Swiss Chard < 31 < 29 < 75 < 32 < 81 < 34 < 60 < 58 < 26 < 30 < 145 < 51 < 212 MEAN CL-118 06/24/15 Cabbage < 17 < 20 < 36 < 18 < 39 < 20 < 32 < 60 < 17 < 20 < 130 < 35 < 86 06/24/15 Lettuce < 15 < 17 < 37 < 16 < 35 < 16 < 34 < 44 < 14 < 16 < 100 < 36 < 89

() 06/24/15 Swiss Chard < 15 < 19 < 38 < 18 < 27 < 16 < 33 < 51 < 13 < 15 < 110 < 38 < 97 I

N 07/29/15 Cabbage < 8 < 9 < 22 < 8 < 19 < 10 < 16 < 54 < 7 <8 < 91 < 22 < 57 0 07/29/15 Lettuce < 6 < 6 < 17 < 6 < 15 <7 < 12 < 39 < 5 < 6 < 64 < 16 < 37 07/29/15 Swiss Chard < 8 < 8 < 25 < 9 < 22 < 11 < 18 < 55 < 7 < 9 < 92 < 22 < 55 08/26/15 Cabbage < 18 < 21 < 53 < 22 < 56 < 23 < 41 < 37 < 22 < 19 < 123 < 26 < 133 08/26/15 Lettuce < 40 < 33 < 77 < 33 < 87 < 43 < 53 < 59 < 37 < 38 < 173 < 30 < 196 08/26/15 Swiss Chard < 25 < 23 < 65 < 35 < 71 < 31 < 49 < 42 < 21 < 31 < 115 < 28 < 168 09/30/15 Cabbage < 23 < 22 < 54 < 28 < 49 < 24 < 44 < 44 < 22 < 26 < 108 < 34 < 152 09/30/15 Kale < 26 < 22 < 55 < 27 < 49 < 26 < 43 . < 42 < 21 < 25 < 110 < 25 < 143 09/30/15 Swiss Chard < 27 < 21 < 73 < 33 < 75 < 32 < 65 . < 56 < 29 < 34 < 150 < 40 < 213 MEAN

""O Ol cc CD Ol

.j:>.

-0

.......

(,.)

Ol THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-IX.2 CONCENTRATIONS OF GAMMA EMITTERS IN GRASS SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-01 05/13/15 < 13 < 15 < 34 < 15 < 32 < 15 < 23 < 43 < 12 < 14 < 81 < 24 < 82 05/27/15 < 16 < 17 < 37 < 20 < 37 < 17 < 31 < 35 < 15 < 16 < 90 < 26 < 104 06/10/15 < 29 < 29 < 64 < 24 < 72 < 29 < 41 < 44 < 24 < 28 < 129 < 42 < 127 06/24/15 < 10 < 12 < 26 < 9 < 24 < 11 < 21 < 53 < 10 < 11 < 93 < 23 < 86 07/08/15 < 13 < 13 < 30 < 14 < 33 < 13 < 24 < 23 < 12 < 14 < 58 < 17 < 93 07/22/15 . < 15 < 14 < 29 < 14 < 34 < 16 < 22 < 26 < 12 < 15 < 73 < 15 < 103 08/05/15 < 11 < 13 < 30 < 12 < 27 < 13 < 23 < 49 < 10 < 12 < 91 < 29 < 71 08/19/15 < 35 < 29 < 64 < 26 < 70 < 27 < 52 < 39 < 28 < 29 < 144 < 20 < 163 09/02/15 < 38 < 38 < 66 < 34 < 73 < 36 < 59 < 59 < 31 < 32 < 159 < 51 < 174 09/16/15 < 22 < 24 < 45 < 22 < 48 < 22 < 35 < 41 < 21 < 22 < 102 < 26 < 155 09/30/15 < 25 < 27 < 61 < 29 < 70 < 30 < 52 < 55 < 27 < 30 < 139 < 37 < 212 10/14/15 < 28 < 28 < 69 < 36 < 72 < 29 < 48 < 50 < 24 < 30 < 129 < 41 < 184 10/28/15 < 17 < 15 < 45 < 17 < 52 < 20 < 33 < 42 < 17 < 23 < 113 < 26 < 148 0

N

...... MEAN CL-02 05/13/15 < 15 < 16 < 37 < 12 < 33 < 16 < 29 < 51 < 14 < 16 < 107 < 25 < 109 05/27/15 < 14 < 15 < 33 < 14 < 37 < 13 < 25 < 29 < 12 < 15 < 78 < 20 < 75 06/10/15 < 31 < 29 < 64 < 24 < 66 < 30 < 57 < 55 < 24 < 33 < 125 < 31 < 170 06/24/15 < 6 < 7 < 15 < 6 < 15 < 7 < 12 < 27 < 5 < 6 < 54 < 13 < 44 07/08/15 < 15 < 14 < 35 < 18 < 28 < 15 < 26 < 25 < 11 < 15 < 64 < 19 < 90 07/22/15 < 27 < 28 < 57 < 25 < 58 < 31 < 50 < 49 < 25 < 30 < 142 < 31 < 197 08/05/15 < 14 < 14 < 37 < 14 < 33 < 15 < 26 < 55 < 13 < 14 < 114 < 25 < 95 08/19/15 < 31 < 20 < 57 < 29 < 63 < 28 < 46 < 39 < 24 < 29 < 122 < 21 < 171 09/02/15 < 30 < 31 < 55 < 24 < 62 < 31 < 40 < 54 < 28 < 31 < 150 < 50 < 172 09/16/15 < 31 < 34 < 73 < 36 < 85 < 35 < 68 < 54 < 32 < 33 < 162 < 34 < 228 09/30/15 < 32 < 25 < 76 < 33 < 62 < 31 < 51 <-56 < 21 < 33 < 157 < 35 < 208 "U 10/14/15 < 18 < 17 < 40 < 16 < 45 < 20 < 29 < 29 < 17 < 19 < 86 < 20 < 107 Ill ca 10/28/15 < 20 < 24 < 51 < 30 < 49 < 25 < 40 < 35 < 22 < 28 < 118 < 32 < 129 CD CXl CTI MEAN a

--"

(,.)

CXl

Table C-IX.2 CONCENTRATIONS OF GAMMA EMITTERS IN GRASS SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-08 05/13/15 < 17 < 16 < 41 < 14 < 39 < 18 < 33 < 59 < 14 < 17 < 117 < 31 < 103 05/27/15 < 18 < 15 < 42 < 19 < 44 < 18 < 35 < 37 < 17 < 19 < 91 < 33 < 108 06/10/15 < 29 < 30 < 71 < 32 < 80 < 32 < 61 < 57 < 32 < 34 < 140 < 33 < 177 06/24/15 < 8 < 9 < 21 < 7 < 19 < 9 < 16 < 37 < 8 < 8 < 68 < 19 < 57 07/08/15 < 16 < 17 < 31 < 18 < 33 < 15 < 26 < 28 < 14 < 16 < 76 < 15 < 115 07/22/15 < 22 < 28 < 50 < 28 < 58 < 21 < 34 < 42 < 21 < 26 < 114 < 33 < 152 08/05/15 < 12 < 13 < 32 < 12 < 28 < 14 < 25 < 51 < 11 < 11 < 99 < 25 < 81 08/19/15 < 27 < 28 < 64 < 23 < 63 < 30 < 49 < 46 < 27 < 30 < 133 < 37 < 177 09/02/15 < 30 < 25 < 70 < 31 < 66 < 22 < 40 < 46 < 27 < 29 < 128 < 30 < 162 09/16/15 < 26 < 27 < 49 < 26 < 59 < 27 < 45 < 41 < 27 < 27 < 120 < 25 < 171 09/30/15 < 29 < 30 < 81 < 36 < 83 < 40 < 57 < 59 < 35 < 34 < 164 < 51 < 209

() 10/14/15 < 18 < 17 < 37 < 19 < 39 < 20 < 32 < 31 < 18 < 18 < 85 < 24 < 127 I

10/28/15 < 23 < 25 < 51 < 18 < 61 < 24 < 41 < 40 < 24 < 23 < 116 < 32 < 164 N

N MEAN CL-116 05/13/15 < 9 < 9 < 26 < 9 < 22 < 10 < 17 < 33 < 9 < 10 < 70 < 20 < 69 05/27/15 < 9 < 10 < 21 < 12 < 20 < 9 < 18 < 15 < 9 < 8 < 50 < 13 < 54 06/10/15 < 25 < 27 < 61 < 31 < 50 < 29 < 49 < 49 < 26 < 28 < 145 < 32 < 211 06/24/15 < 10 < 10 < 27 < 9 < 23 < 11 < 19 < 43 < 9 < 10 < 81 < 21 < 62 07/08/15 < 16 < 13 < 34 < 15 < 29 < 18 < 26 < 29 < 15 < 16 < 76 < 21 < 109 07/22/15 < 30 < 20 < 57 < 28 < 62 < 25 < 43 < 42 < 23 < 30 < 115 < 28 < 142 08/05/15 < 13 < 14 < 32 < 13 < 30 < 15 < 26 < 60 < 12 < 14 < 114 < 25 < 101 08/19/15 < 35 < 29 < 71 < 36 < 83 < 30 < 57 < 60 < 30 < 33 < 152 < 46 < 195 09/02/15 < 27 < 29 < 68 < 27 < 85 < 29 < 61 < 54 < 27 < 29 < 126 < 45 < 166 09/16/15 < 25 < 22 < 48 < 23 < 55 < 30 < 43 < 40 < 19 < 28 < 117 < 32 < 214

"'U 09/30/15 < 34 < 30 < 42 < 29 < 62 < 26 < 54 < 52 < 29 < 28 < 153 < 44 < 220 Ql cc 10/14/15 < 32 < 30 < 79 < 34 < 73 < 31 < 62 < 58 < 33 < 29 < 157 < 39 < 246 CD CXl 10/28/15 < 22 < 21 < 49 < 14 < 47 < 22 < 35 < 39 < 20 < 23 < 99 < 18 < 162 (j)

-0

....>.

(,J CXl MEAN

Table C-X.1 QUARTERLY DLR RESULTS FOR CLINTON POWER STATION, 2015 RESULTS IN UNITS OF MILLI REM/QUARTER+/- 2 STANDARD DEVIATIONS STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +/-2S.D.

CL-01 22.7 +/- 3.1 23.0 20.9 22.2 24.6 CL-02 23.6 +/- 3.6 24.7 23.1 21.3 25.3 CL-03 23.7 +/- 3.5 24.4 22.9 21.8 25.8 CL-04 22.5 +/- 2.8 22.9 21.8 21.0 24.2 CL-05 23.9 +/- 3.1 24.6 22.4 22.8 25.7 CL-06 20.9 +/- 2.9 21.4 20.1 19.4 22.7 CL-07 22.2 +/- 1.9 22.8 21.5 21.2 23.2 CL-08 22.9.+/- 4.0 24.3 21.3 21.1 24.9 CL-11 21.9 +/- 3.0 22.0 22.0 19.9 23.6 CL-15 20.7 +/- 2.9 21.0 19.8 19.4 22.6 CL-22 23.3 +/- 3.3 23.7 22.7 21.5 25.4 CL-23 24.2 +/- 2.1 24.5 23.7 23.0 25.4 CL-24 24.3 +/- 2.3 25.2 23.4 23.1 25.3 CL-33 24.1 +/- 2.5 23.6 24.2 22.8 25.7 CL-34 25.1 +/- 2.8 24.3 25.0 23.9 27.1 CL-35 22.2 +/- 3.0 23.8 20.7 21.1 23.1 CL-36 23.4 +/- 3.7 24.2 *22.3 21.4 25.5 CL-37 21.7 +/- 2.5 22.7 20.1 21.2 22.6 CL-41 24.5 +/- 2.2 24.5 23.8 23.5 26.0 CL-42 23.0 +/- 2.9 23.1 22.3 21.6 25.0 CL-43 23.8 +/- 2.4 24.5 23.3 22.4 25.1 CL-44 23.4 +/- 2.3 23.9 22.9 22.0 24.6 CL-45 24.4 +/- 5.2 24.4 23.2 21.9 28.0 CL-46 23.3 +/- 2.8 24.2 21.7 (1) 24.1 CL-47 23.9 +/- 3.8 23.6 23.6 21.8 26.4 CL-48 22.7 +/- 3.2 22.6 21.9 21.4 25.0 CL-49 23.8 +/- 3.7 24.1 22.6 22.3 26.3 CL-51 25.3 +/- 2.0 25.4 24.3 (1) 26.3 CL-52 24.7 +/- 5.5 25.7 23.1 21.9 28.0 CL-53 22.0 +/- 2.9 21.6 21.6 20.8 24.1 CL-54 24.2 +/- 4.0 25.4 22.7 22.4 26.4 CL-55 23.9 +/- 4.1 24.0 23.1 21.9 26.7 CL-56 24.3 +/- 3.6 24.4 23.9 22.2 26.6 CL-57 25.0 +/- 1.1 24.5 25.0 24.7 25.8 CL-58 24.2 +/- 3.7 25.2 23.6 21.9 26.1 CL-60 24.2 +/- 3.2 24.2 24.5 22.1 26.0 CL-61 23.9 +/- 3.9 24.0 22.8 22.2 26.6 CL-63 21.5 +/- 3.8 21.8 21.0 19.2 23.8 CL-64 23.1 +/- 3.2 23.0 22.6 21.4 25.2 CL-65 24.3 +/- 3.4 25.2 22.8 23.0 26.3 CL-74 21.5 +/- 3.9 22.6 20.8 19.0 23.4 CL-75 23.3 +/- 3.6 23.6 22.2 21.6 25.6 CL-76 24.5 +/- 3.4 24.8 23.7 22.7 26.7 CL-77 22.4 +/- 3.4 23.4 20.9 21.0 24.2 CL-78 22.1 +/- 4.3 23.8 22.1 19.0 23.3 CL-79 24.0 +/- 4.5 24.6 22.9 21.6 26.8 CL-80 23.4 +/- 3.3 23.6 22.5 21.9 25.7 CL-81 23.7 +/- 4.6 24.5 23.0 20.9 26.3 CL-84 23.0 +/- 2.2 22.9 22.8 21.9 24.5 CL-90 20.1 +/- 2.8 21.2 19.2 18.6 21.3 CL-91 21.3 +/- 2.9 22.6 20.1 20.0 22.5 CL-97 23.0 +/- 2.1 22.7 23.1 21.9 24.4 CL-99 19.3 +/- 2.8 20.2 19.1 17.3 20.4 CL-114 22.3 +/- 2.1 23.2 21.4 21.4 23.3 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-23 Page 87 of 138

TABLE C-X.2 MEAN QUARTLY DLR RESULTS FOR THE INNER RING, OUTER RING, SPECIAL INTEREST, SUPPLEMENTAL AND CONTROL LOCATIONS FOR CLINTON POWER STATION, 2015 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING OUTER RING SPECIAL INTEREST SUPPLEMENTAL CONTROL PERIOD +/-2 S.D.

JAN-MAR 23.8 +/- 1.7 24.3 +/- 2.0 23.7 +/- 2.0 22.7 +/- 2.7 22.0 +/- 0.0 APR-JUN 22.6 +/- 2.3 23.1 +/- 2.1 22.1 +/- 2.5 21.5 +/- 3.2 22.0 +/- 0.0 JUL-SEP 22.0 +/- 2.2 21.8 +/- 2.4 21.7 +/- 2.9 20.7 +/- 3.0 19.9 +/- 0.0 OCT-DEC 25.3 +/- 2.4 26.0 +/- 2.4 25.1 +/- 3.0 23.6 +/- 3.3 23.6 +/- 0.0 TABLE C-X.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR CLINTON POWER STATION, 201S RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATION LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN ANALYZED MINIMUM MAXIMUM +/-2 S.D. +/- 2 S.D., ALL LOCATIONS INNER RING 63 19.2 28.0 23.4 +/- 3.3 OUTER RING 63 19.0 28.0 23.8 +/- 3.8 18.0 +/- 2.4 SPECIAL INTEREST 28 19.0 26.3 23.1 +/- 3.7 SUPPLEMENTAL 56 17.3 25.8 22.1 +/- 3.8 CONTROL 4 19.9 23.6 21.9 +/- 3.0 INNER RING STATIONS - CL-01, CL-05, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42, CL-43, CL-44, CL-45, CL-46, CL-47, CL-48, CL-63 OUTER RING STATIONS - CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80, CL-81 SPECIAL INTEREST STATIONS - CL-37, CL-41, CL-49, CL-64, CL-65, CL-74, CL-75 SUPPLEMENTAL STATIONS - CL-02, CL-03, CL-04, CL-06, CL-07, CL-08, CL-114, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 CONTROL STATION - CL-11 C-24 Page 88 of 138

FIGURE C-1 MEAN MONTHLY GROSS BETA CONCENTRATION IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CPS, 2015 0.052 0.047 0.042 0.037 M

E

0.032

(.)

c..

0.027 0.022 0.017 0.012 0.007 0.002

~* ~* ~* ~*

")~ <l~ ~'if ~ ~~

-"-

ts~* ts~* c,* ~* ~. ~* c,*

~ ~~ 0 v ~o ~<<;

MONTH 1l!ll!!lll1ll PRE-OP (ALL SITES)

_.,_ 2015 INDICATOR

-+- 2015 CONTROL C-25 Page 89 of 138

FIGURE C-2 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR) IN THE VICINITY OF CPS, 2015 50 45 40 35 E

Q) 0:::

30 E

25 20 15 10 QUARTER II PRE-OP 02015 indicator

  • 2015 control C-26 Page 90 of 138

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 91 of 138

Intentionally left blank Page 92 of 138

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF3)

Identification Reported Known Ratio (c)

MonthNear Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d)

March 2015 E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 w E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A

--* -- -**--* -- - -~ - .-

E11184 AP Ce-141 pCi 107 85.0 1.26 w Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 Water Fe-55 pCi/L 1950 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 w Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143 125 1.14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 w Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1)

Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A D-1 Page 93 of 138

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d)

June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A

- - -- - , ,.. - :-- . -- .,,__ .. -- . -- - - ~ " Zn-65 ... pCi/L *- 392 353--- .. 1.11 .-.A ..

Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 *302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 - pCi/L __ 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A D-2 Page 94 of 138

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3)

Identification Reported Known Ratio (c)

MonthNear Number Matrix Nuclide Units Value (a) Value (b) TBE/Anal}'.tics Evaluation (d)

December 2015 E11357 AP Ce-141 pCi 89.9 84.0 1.07 A Cr-51 pCi 215 184 1.17 A Cs-134 pCi 103 105 0.98 A Cs-137 pCi 76.6 74.8 1.02 A Co-58 pCi 76.2 71.9 1.06 A Mn-54 pCi 91.4 94.4 0.97 A

  • Fe-59 pCi 78.6 70.3 1.12 A Zn-65 pCi 173 162 1.07 A Co-60 pCi 138 139 0.99 A E11422 AP Sr-89 pCi 98.0 96.9 1.01 A Sr-90 pCi 10.0 14.0 0.71 w E11356 Charcoal 1-131 pCi 74.9 75.2 1.00 A E11358 Water Fe-55 pCi/L 2160 1710 1.26 w E11353 Soil Ce-141 pCi/kg 252 222 1.14 A Cr-51 pCi/kg 485 485 1.00 A Cs-134 pCi/kg 319 277 1.15 A Cs-137 pCi/kg 292 276 1.06 A Co-58 pCi/kg 193 190 1.02 A Mn-54 pCi/kg 258 250 1.03 A Fe-59 pCi/kg 218 186 1.17 A Zn-65 pCi/kg 457 429 1.07 A Co-60 pCi/kg 381 368 1.04 A (1) AP Cr Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable. NCR 15-18 (a) Teledyne Brown Engineering reported result.

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

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

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1.20.

W-Acceptable with 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.

D-3 Page 95 of 138

TABLE D-2 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

March 2015 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 - 0.850 A Ni-63 Sq/L 2.5 (1) A Pu-238 Sq/L 0.0204 0.0089 (2) A Pu-239/240 Sq/L 0.9 0.8 0.582 - 1.082 A 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314- 582 A Sr-90 Sq/kg 286 653 487 - 849 N (3) 15-RdF32 AP Sr-90 Sq/sample -0.0991 (1) A U-234/233 Sq/sample 0.0211 0.0155 0.0109 - 0.0202 N (3)

U-238 Sq/sample 0.095 0.099 0.069- 0.129 A 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53 - 3.01 N (3)

Gr-S Sq/sample 0.7580 0.75 0.38 -.1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12 - 9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 - 11.93 w Co-57 Sq/sample -0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 - 7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample 0.999 1.08 0.76 - 1.40 A Zn-65 Sq/sample -0.108 (1) A September 2015 15-MaW33 Water Am-241 Sq/L 1.012 1.055 0. 739 - 1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4)

Pu-238 Sq/L 0.727 0.681 0.477 - 0.885 A Pu-239/240 Sq/L 0.830 0.900 0.630-1.170 A 15-MaS33 Soil Ni-63 Sq/kg 635 682 477 - 887 A Sr-90 Sq/kg 429 425 298 - 553 A 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53 - 2.83 N (4)

U-234/233 Sq/sample 0.143 0.143 0.100- 0.186 A U-238 Sq/sample 0.149 0.148 0.104-0.192 A 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 A Gr-S Sq/sample 1.34 1.56 0.78 - 2.34 A 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06 - 7.54 A Cs-137 Sq/sample 0.0002 (1) A Co-57 Sq/sample 8.01 6.62 4.63 - 8.61 w Co-60 Sq/sample 4.97 4.56 3.19- 5.93 A Mn-54 Sq/sample 8.33 7.68 5.38 - 9.98 A Sr-90 Sq/sample 0.386 1.30 0.91 - 1.69 N (4)

(1) False positive test. Zn-65 Sq/sample 6.07 5.46 3.82-7.10 A (2) Sensitivity evaluation.

(3) Soil Sr incomplete digestion of the sample resulted in low results; AP U-2341233 - extremely low activity was difficult to quantify AP Gr-A - the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21.

(a) Teledyne Brown Engineering reported result.

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

(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, tvo1.94acceptable.

Page 96 of 138

TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 - 71.2 N (1)

Sr-90 pCi/L 28.0 41.9 30.8 - 48.1 N (1)

Ba-133 pCi/L 80.6 82.5 63.9 - 90.8 A Cs-134 pCi/L 71.7 75.7 61.8 - 83.3 A Cs-137 pCi/L 187 189 170 - 210 A Co-60 pCi/L 85.7 84.5 76.0 - 95.3 A Zn-65 pCi/L 197 203 183 - 238 A Gr-A pCi/L 26.1 42.6 22.1 - 54.0 A Gr-B pCi/L 28.8 32.9 21.3 - 40.6 A 1-131 pCi/L 23.5 23.8 19.7 - 28.3 A U-Nat pCi/L 6.19 6.59 4.99 - 7.83 A H-3 pCi/L 3145 3280 2770 - 3620 A

--* --~- ---* -- -

November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 - 42.5 A Sr-90 pCi/L 29.3 31.1 22.7 - 36.1 A Ba-133 pCi/L 31.5 32.5 25.9 - 36.7 A Cs-134 pCi/L 59.65 62.3 50.6 - 68.5 A Cs-137 pCi/L 156 157 141 -175 A Co-60 pCi/L 70.6 71.1 64.0 - 80.7 A Zn-65 pCi/L 145 126 113 - 149 A Gr-A pCi/L 38.2 51.6 26.9 - 64.7 A Gr-B pCi/L 42.0 36.6 24.1 - 44.2 A 1-131 pCi/L 24.8 26.3 21.9- 31.0 A U-Nat pCi/L 146.90 56.2 45.7 - 62.4 N (2)

H-3 pCi/L 21100 21300 18700 - 23400 A

-

(1) Yield on the high side of our acceptance range indicates possibility of calcium interference. NCR 15-09 (2) Technician failed to dilute original sample. If di/ulted, the result would have been 57. 1, which tell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result.

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

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

D-5 Page 97 of 138

3 TABLE D-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2015 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control 0

Result b Result Limits Acceptance ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 - 71.20 Pass ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 04/06/15 Cs-137 -191.92 +/- 5.9 189 - 170.00 - 210.0 Pass ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 - 95.30 Pass ERW-1448 04/06/15 Zn-65 -195.97 +/- 12.0 203 -183.00 - 238.0 Pass ERW-1450 04/06/15 Gr. Alpha 34.05 +/- 1.90 42.60 22.10 - 54.00 Pass ERW-1450 04/06/15 G. Beta 26.93 +/- 1.12 32.90 21.30 - 40.60 Pass ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19. 70 - 28.30 Pass ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 - 7.83 *Pass ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 - 3620 Pass ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26.70 - 42.50 Pass ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 - 36.10 Pass ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 - 175.0 Pass ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/05/15 Zn-65 -138.94 +/- 5.7 126 -113.00 - 149.0 Pass ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 - 31.00 Pass ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 - 23400.0 Pass

  • 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. Page 98 of 138 0-6

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

ENVIRONMENTAL, INC., 2015 (Page 1 of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 02/01/15 Ni-63 341 +/- 18 448 314 - 582 Pass MAS0-975 02/01/15 Sr-90 523 +/- 12 653 457 - 849 Pass MAS0-975 02/01/15 Cs-134 533 +/-6 678 475 - 881 Pass MAS0-975 02/01/15 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 02/01/15 Co-57 0.5 +/-1 0.0 NA c Pass MAS0-975 02/01/15 Co-60 741 +/-8 817 572 - 1062 Pass MAS0-975 02/01/15 Mn-54 1, 153 +/-9 1, 198 839 - 1557 Pass MAS0-975 02/01/15 Zn-65 892 +/- 18 1064 745 - 1383 Pass MAW-969 02/01/15 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 02/01/15 Cs-134 21.09 +/- 0.25 23.5 16.5 - 30.6 Pass MAW-969 02/01/15 Cs-137 19.63 +/- 0.34 19.1 13.4 - 24.8 Pass MAW-969 d 02/01/15 Co-57 . --** 10.2 +/- 0.4 29.9 20.9 - 38.9. Fail.

MAW-969 02/01/15 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 02/01/15 H-3 569 +/- 13 563 394 - 732 Pass MAW-969 02/01/15 Fe-55 6.00 +/- 6.60 6.88 4.82 - 8.94 Pass MAW-969 02/01/15 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 02/01/15 Ni-63 2.9 +/-3 0.00 NA c Pass MAW-969 02/01/15 Zn-65 16.54 +/- 0.85 18.3 12.8 - 23.8 Pass MAW-969 02/01/15 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 02/01/15 Pu-239/240 0.81 +/- 0.10 0.83 0.58 - 1.08 Pass MAW-969 02/01/15 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 02/01/15 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 02/01/15 Gr. Beta 2.72 +/- 0.06 2.79 1.40 - 4.19 Pass MAAP-978 02/01/15 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 02/01/15 Cs-137 0.004 +/- 0.023 0.00 NAC Pass MAAP-978 e 02/01/15 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fail MAAP-978 02/01/15 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 02/01/15 Mn-54 1.11 +/- 0.08 1.02 0.71 - 1.33 Pass MAAP-978 02/01/15 Zn-65 0.83 +/- 0.10 0.83 0.58 - 1.08 Pass MAAP-981 02/01/15 Sr-89 38.12 +/- 1.01 47.5 33.3 - 61.8 Pass MAAP-981 02/01/15 Sr-90 1.22 +/- 0.13 1.06 0.74 - 1.38 Pass MAAP-984 02/01/15 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 02/01/15 Gr. Beta 0.95 +/- 0.07 0.75 0.38 - 1.13 Pass MAVE-972 02/01/15 Cs-134 6.98 +/- 0.13 7.32 5.12 - 9.52 Pass MAVE-972 02/01/15 Cs-137 9.73 +/- 0.21 9.18 6.43 - 11.93 Pass MAVE-972 02/01/15 Co-57 0.01 +/- 0.04 0.00 NAC Pass MAVE-972 02/01/15 Co-60 3.89 +/- 0.20 5.55 3.89 - 7.22 Pass MAVE-972 02/01/15 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 02/01/15 Zn-65 0.09 +/- 0.12 0.00 NA c Pass Page 99 of 138 D-7

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

ENVIRONMENTAL, INC., 2015 (Page 2 of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits 0 Acceptance MAS0-4903 08/01/15 Ni-63 556 +/- 18 682 477 - 887 Pass MAS0-4903 f 08/01/15 Sr-90 231 +/-7 425 298 - 553 Fail MAS0-4903 f 08/01/15 Sr-90 352 +/- 10 425 298 - 553 Pass MAS0-4903 08/01/15 Cs-134 833 +/- 10 1,010 707 - 1313 Pass MAS0-4903 08/01/15 Cs-137 808 +/- 11 809.00 566 - 1052 Pass MAS0-4903 08/01/15 Co-57 1,052 +/- 10 1, 180 826 - 1534 Pass 0

MAS0-4903 08/01/15 Co-60 2 +/-2 1.3 NA Pass MAS0-4903 08/01/15 Mn-54 1,331 +/- 13 1,340 938 - 1742 Pass MAS0-4903 08/01/15 Zn-65 686 +/- 15 662 463 - 861 Pass MAW-5007 08/01/15 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30 Pass MAW-5007 08/01/15 Cs-137 -0.36 +/- 0.13 0 NA 0 Pass MAW-5007 "08/01/15 co~57 21.8 +/- 0.4 20.8 14.6 - 27 Pass MAW-5007 08/01/15 Co-60 17.3 +/- 0.3 17.1 12 - 22.2 Pass MAW-5007 08/01/15 H-3 227.5 +/- 8.9 216 151 - 281 Pass MAW-5007 g 08/01/15 Fe-55 4.2 +/- 14.1 13.1 9.2 - 17 Fail MAW-5007 08/01/15 Mn-54 16.6 +/- 0.5 15.6 10.9 - 20.3 Pass MAW-5007 08/01/15 Ni-63 9.1 +/- 2.6 8.55 5.99 - 11.12 Pass MAW-5007 08/01/15 Zn-65 15.5 +/- 0.9 13.9 9.7 - 18.1 Pass MAW-5007 08/01/15 Sr-90 4.80 +/- 0.50 4.80 3.36 - 6.24 Pass MAW-5007 08/01/15 Gr. Alpha 0.41 +/- 0.04 0.43 0.13 - 0.73 Pass MAW-5007 08/01/15 Gr. Beta 3.45 +/- 0.07 3.52 1.76 - 5.28 Pass MAAP-4911 08/01/15 Sr-89 3.55 +/- 0.67 3.98 2.79 - 5.17 Pass MAAP-4911 08/01/15 Sr-90 0.94 +/- 0.16 1.05 0.74 - 1.37 Pass MAAP-4907 08/01/15 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 - 1.53 Pass MAAP-4907 08/01/15 Gr. Beta 1.85 +/- 0.09 1.56 0.78 - 2.34 Pass MAVE-4901 08/01/15 Cs-134 5.56 +/- 0.16 5.80 4.06 - 7.54 Pass MAVE-4901 08/01/15 Cs-137 -0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 08/01/15 Co-57 7.74 +/- 0.18 6.62 4.63 - 8.61 Pass MAVE-4901 08/01/15 Co-60 4.84 +/- 0.15 4.56 3.19 - 5.93 Pass MAVE-4901 08/01/15 Mn-54 8.25 +/- 0.25 7.68 5.38 - 9.98 Pass MAVE-4901 08/01/15 Zn-65 5.78 +/- 0.29 5.46 3.82 - 7.10 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).

0 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.

d Lab result was 27.84. Data entry_ error resulted in a non-acceptable result.

  • Lab result was 1.58. Data entry error resulted in a non-acceptable result.

f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

g The known activity was below the routine laboratory detection limits for the available aliquot fraction. Page 100 of 138 D-8

APPENDIX E ERRATA DATA

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There is no errata data for 2015.

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APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR}

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Docket No: 50-461 Cl~NTON l?OWIER. STATION Annual Radiological Groundwater Protection Program Report

- - - -- -- - -- - - ------:-- -- . --~ - -- --<o----- --. . - . . - -

  • ----...-----~-.**

- ___ .-- .-* ____.,. .

--- .__,,,_ - '> *-,,...- - - - - -=-- --~-- - ~ ..__*. .,

January 1 through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services Clinton Power Station Clinton, IL 61727 April 2016 Page 107 of 138

  • Intentionally left blank Page 108of138

Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 3 A Objectives of the RGPP ...................................................................................... 3

8. Implementation of the Objectives ........................................................................ 3 C. Program Description ........................................................................................... 4 D. Characteristics of Tritium (H-3) ........................................................................... 5 Ill. Program Description ...................................................................................................... 5 A. Sample Analysis ....................................... ,.......................................................... 5
8. Data Interpretation ........-...... ~ ........-... :.: .................................................................-. 6

_.__ :. -*- :. -:": .... -- *_;;_----,. -t~:; sack9rduncfAil~i1ysis.~::-:~.: :~~-.. :*::*:::: .:'::.:.~.~--~:_:'.--'.*.-~_::::: :::~--.:-~ .*:_:-.':-::*:*: ~ .-:.:. '.~--~:.~:~..*. ::-. ::':~:::-*1 ~--...,:-_ ; =

1. Background Concentrations of Tritium ............................................ :........ 7 IV. Results and Discussion ................................................................................................. 9 A. Program Exceptions ............................................................................................ 9
8. Program Changes ............................................................................................... 9 C. Groundwater Results .......................................................................................... 9 D. Surface Water Results ............................................................... ,, ..................... 11 E. Precipitation Water Results ............................................................................... 11 F. Recapture .......................................................................................................... 11 G. Summary of Results - Inter-laboratory Comparison Program .......................... 11 H. Errata Data .......................................................................................................... 11 I. Leaks, Spills, and Releases ......................................................................... ,...... 12 J. Trends ................................................, ................................................................ 12 K. Investigations ..................................................................................................... 12 L. Actions Taken ..................................................................................,.................. 12
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Appendices Appendix A Location Designation of the Annual Radiological Groundwater Protection Program Report (ARGPPR)

  • Tables
  • Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Figures Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Clinton Power Station,

~015

-.--.,,<-----~*--. _..,-.* __ : - ~ -- . , *-~--~-.-_:- : __ -. ,.. __ . . . . - _.,._ --*-- - -* ~--,....,,**---* - .,,...,..,.__,........,c,.:-..:= _,--------- ....-- .,*-~-

Figure A-1 Onsite Sampling Locations at Clinton Power Station Figure A-2 Sampling Locations South of Clinton Power Station Figure A-3 Sampling Locations East of Clinton Power Station Figure A-4 Recapture Sampling Locations of Clinton Power Station Appendix B Data Tables of the Annual Radiological Groundwater Protection Program Report (ARGPPR)

Tables Table 8-1.1 Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table 8-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table 8-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table 8-11.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table B~ll.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

ii Page 110 of 138

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 Clinton Power Station (CPS). This evaluation involved numerous station personnel and contractor support personnel. This report covers groundwater and surface water samples, collected outside of the Licensee required Off-Site Dose Calculation Manual (ODCM) requirements, both on and off station property in 2015. During that time period, 246 analyses were performed on 97 samples from 24 locations.

The monitoring was conducted in four phases.

In assessing all the data gathered for this report, it was concluded that the operation of CPS had no adverse radiological impact on the environment, and

-- the-re are no known-active-releases into the groundwater or surface water at~, __ - -- - -

CPS. No program changes occurred during the sampling year of 2015.

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 NUREG-1302 in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that the independent laboratory achieve a lower limit of detection 10 times lower than that required by the United States Environmental Protection Agency (USEPA) regulation.

Strontium-89 was not detected in any samples. Strontium-90 was not detected in any samples.

Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Background levels of tritium were detected at concentrations greater than the self-imposed LLD of 200 pCi/L in four of 17 groundwater monitoring locations. The tritium concentrations ranged from 176 +/-

106 pCi/L to 365 +/- 136 pCi/L. Tritium was not detected in any surface water.

Precipitation samples were not analyzed during 2015.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations. Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations.

Page 111 of 138

Hard-To-Detect analyses were performed on two 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 analyzed were not found at concentrations greater than their respective MDCs.

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II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on 15 February 1987. The site encloses approximately 13,730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated -on approximately 150 acres~ The cooling water discharge flume, which discharges to the eastern arm of the lake, occupies an additional 130 acres.

Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13, 730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Ann_a Townships.

    • -. __ ,,__,,, ___ -. - - *~-- - - -

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015.

A. Objectives of the Radiological Groundwater Protection Program (RGPP)

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

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
2. Understand the local hydrogeologic regime in the vicinity of the station and maintain knowledge of flow patterns on the surface and shallow subsurface. *
3. Perform routine water sampling and radiological analysis of water from selected locations.
4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
5. Regularly assess analytical results to identify adverse trends.
6. Take necessary corrective actions to protect groundwater resources.
8. Implementation of the Objectives The objectives identified have been implemented at Clinton Power Station as discussed below:

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1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public in station specific reports.
2. The Clinton Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
3. Clinton Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
4. Clinton Power Station has implemented new procedures to identify

~-and report rrew leaks,-spiils, o*r*otlier detections with potential*

radiological significance in a timely manner.

5. Clinton Power 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, A-2, A-3, and A-4 Appendix A.

Groundwater, Surface Water and Precipitation Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Groundwater, surface water, and precipitation water are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial revi~w by the contractor.

Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to Page 114of138

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." The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the environment and the body. 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, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. 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 has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). 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 beta 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 to analyze the environmental samples for radioactivity for the Clinton Page 115 of 138

Power Station RGPP in 2015.

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

1. Concentrations of gamma emitters in groundwater and surface water.
2. Concentrations of strontium in groundwater.
3. Concentrations of tritium in groundwater and surface water.
4. Concentrations of gross alpha and gross beta in groundwater.

5." ---; - Concentrations of-Am-241-in groundwater. -

6. Concentrations of Cm-242 and Cm-243/244 in groundwater.
7. Concentrations of Pu-238 and Pu-239/240 in groundwater.
8. Concentrations of U-234, U-235 and U-238 in groundwater.
9. Concentrations of Fe-55 in groundwater.
10. Concentrations of Ni-63 in groundwater.

B. Data Interpretation The radiological data collected prior to Clinton Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Clinton Power Station 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) 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.

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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) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus

  • or minus+/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

Analytical uncertainties are reported at the 95% confidence level in

-- ** -*this report for reporting consistency With the AREOR.- .,~- -*

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

For groundwater and surface water 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.

C. Background Analysis Pre-operational Radiological Environmental Monitoring Program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, milk, and vegetation. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Clinton Power Nuclear Power Station, Illinois Power Company, Annual Report 1987, May 1988.

The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater.

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.
a. Tritium Production Tritium is created in the environment from naturally occurring Page 117 of 138

processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and 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 atmo*spheric*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.
b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006.

RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline Jp until 1975, followed by. a gradual decline sine~ that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above.

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c. Surface Water Data Tritium concentrations are routinely measured in Clinton Lake.

According to the USEPA, surface water data typically has an uncertainty+/- 70 to 100 pCi/L 95% confidence bound on each given measurement. Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.

The radio-analytical laboratory is counting tritium results to an Exelon specified 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. Program Exceptions

1. Sample Anomalies There were no samples anomalies in 2015.
2. Missed Samples There were no missed samples in 2015.

B. Program Changes There were no sampling program changes in 2015.

C. Groundwater Results Groundwater Baseline samples were collected from off-site wells during four (4) phases at the station. Analytical results are discussed below. No anomalies were noted during the year.

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Tritium Samples from 17 locations were analyzed for tritium activity (Table B-1.1 Appendix B). Tritium values ranged from below the Exelon imposed LLD of 200 pCi/I to 365 pCi/I.

Strontium Strontium-89 was not detected in any of the 17 samples analyzed and the required LLD of 10 pCi/L was met. Strontium-90 was also not detected in any of the 17 samples analyzed and the required LLD of 1 pCi/L was met. (Table B-1.1 Appendix B).

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed oh groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.

Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L.

Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B).

Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-1.2, Appendix B).

Hard-To-Detect Hard-To-Detect analyses were performed on two groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

Occasionally, the isotopes of U-234 and U-238 are detected at low levels and indistinguishable from background (Table B-1.3 Appendix B).

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D. Surface Water Results Surface Water Baseline samples were collected from on-site surface waters during four (4) phases at the station. Analytical results are discussed belo.w. No anomalies were noted during the year.

Tritium Samples from seven locations were analyzed for tritium activity

- (Table B-11.1 Appendix B). Tritium was not detected at concentrations greater than the LLD.

  • -~ --* * -. ---... '" *-*-*-*. --Strontium****-** *- * . .- - ' -- -' _,,.... * *--------~~---,------ * - *-- **--.* -*--

Strontium was not analyzed in 2015 (Table B-11.1 Appendix B).

Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-11.2, Appendix B).

E. Precipitation Water Reirnlts Precipitation Water Precipitation water samples were not collected during 2015.

F. Recapture Recapture samples were not required in 2015.

G. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.

H. Errata Data The 2014 ARGPP incorrectly reported 607 analyses in the Summary and Conclusion section. The number of analyses in 2014 should have been ,

reported as 253 (IR 02635324).

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I. Leaks, Spills, and Releases No leaks, spills or releases were identified during the year.

J. Trends MW-CL-14S had a slight trend upward from <200 pCi/L to 241, 300 and 365 pCi/L respectively in 2015. However, the 1st Quarter of 2016 revealed MW-CL-14S has trended back to 218 pCi/L. Additionally, MW-CL-21S, after it too experienced a slight trend from 219 pCi/L to 287 pCi/L in 2015, has now had consecutive values of 189 pCi/L in the 4th Quarter of 2015 and 191 pCi/L from our 1st Quarter of 2016. All sampling well locations are currently indicating tritium levels that are less than the ODCM LLD of 2,000 pCi/I. All wells will continue to be sampled in accordance with the RGPP in 2016..

K. Investigations Currently no investigations are on-going.

L. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Clinton Power Station in 2015.
2. Installation of Monitoring Wells No new wells were installed during the 2015.
3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.

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APPENDIX A LOCATION DESIGNATION OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT

{ARGPPR)

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TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Site Site Type B-3 Monitoring Well MW-CL-1 Monitoring Well MW-CL-2 Monitoring Well MW-CL-121 Monitoring Well MW-CL-131 Monitoring Well MW-CL-13S Monitoring Well MW-CL-14S Monitoring Well MW-CL-151 Monitoring Well MW-CL-15S Monitoring Well MW-CL-16S Monitoring Well MW-CL-17S Monitoring Well MW-CL-181 Monitoring Well MW-CL-18S Monitoring Well MW-CL-19S Monitoring Well MW-CL-20S Monitoring Well MW-CL-21S Monitoring Well MW-CL-22S Monitoring Well Sewage Treatment Plant - - - - Surface Water SW-CL-1 Surface Water SW-CL-2 Surface Water SW-CL-4 Surface Water SW-CL-5 Surface Water SW-CL-6 Surface Water SW-CL-7 Surface Water A-1 Page 125of138

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APPENDIX B DATA TABLES OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) 8-3 02/09/15 < 157 8-3 05/26/15 < 194 8-3 08/17/15 < 180 < 5.2 < 0.6 1.2 +/- 0.8 < 1.1 3.2 +/- 1.0 < 1.6 8-3 11/02/15 < 196 MW-CL-1 02/09/15 < 156 MW-CL-1 05/26/15 < 195 MW-CL-1 08/17/15 < 179 - < 5.4 < 0.6 < 0.9 < 1.1 2.1 +/- 0.9 < 1.6 MW-CL-1 11/02/15 < 187 MW-CL-121 02/09/15 < 178 MW-CL-121 05/26/15 < 196 MW-CL-121 08/17/15 < 191 < 5.6 < 0.6 < 0.9 < 1.1 4.9 +/- 1.0 < 1.6 MW-CL-121 11/02/15 322 +/- 134 MW-CL-131 02/09/15 < 154 MW-CL-131 05/26/15 < 193 MW-CL-131 08/17/15 < 187 . < 4.0 < 0.6 < 0.7 < 1.1 3.2 +/- 1.1 < 1.6 MW-CL-131 11/02/15 < 187 MW-CL-13S 02/09/15 < 157 MW-CL-13S 05/26/15 < 193 MW-CL-13S 08/17/15 < 199 < 4.7 < 0.6 < 0.6 < 1.1 2.7 +/- 1.0 < 1.6 MW-CL-13S 11/02/15 220 +/- 128 MW-CL-14S 02/09/15 < 156 MW-CL-14S 07/22/15 241 +/- 128 MW-CL-14S 08/18/15 300 +/- 126 < 6.9 < 0.8 < 1.3 < 1.1 11.9 +/- 1.6 < 1.6 MW-CL-14S 11/03/15 365 +/- 136 MW-CL-151 02/09/15 < 156 MW-CL-151 05/26/15 < 193 MW-CL-151 08/17/15 < 174 < 5.7 < 0.7 < 0.7 < 0.5 1.9 +/- 1.0 < 1.7 MW-CL-151 11/02/15 < 193 MW-CL-15S 02/09/15 < 155 MW-CL-15S 05/26/15 < 193 MW-CL-15S 08/17/15 < 197 MW-CL-15S 09/29/15 < 5.2 < 0.6 < 0.9 < 0.8 < 0.9 < 1.6 MW-CL-15S 11/02/15 < 185 MW-CL-16S 02/09/15 < 186 MW-CL-16S 05/27/15 < 189 MW-CL-16S 08/18/15 <.180 MW-CL-16S 09/29/15 < 5.6 < 0.7 < 2.3 < 0.8 8.7 +/- 1.4 < 1.6 MW-CL-16S 11/03/15 < 188 MW-CL-17S 02/09/15 < 159 MW-CL-17S 05/27/15 < 194 MW-CL-17S 08/18/15 < 180 < 5.3 < 0.7 < 1.9 < 0.5 3.4 +/- 1.1 < 1.6 MW-CL-17S 11/03/15 < 188 MW-CL-181 02/09/15 < 154 MW-CL-181 05/27/15 < 194 MW-CL-181 08/18/15 < 198 < 5.5 < 0.6 < 1.2 < 0.5 4.2 +/- 1.1 < 1.6 MW-CL-181 11/03/15 < 186 B-1 Page 133of138

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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-CL-18S 02/09/15 < 156 MW-CL-18S 05/27/15 < 193 MW-CL-18S 08/18/15 < 189 < 4.5 < 0.8 < 2.1 < 0.5 4.4 +/- 1.2 < 1.6 MW-CL-18S 11/03/15 < 188 MW-CL-19S 02/09/15 < 155 MW-CL-19S 05/26/15 < 194 MW-CL-19S 08/17/15 < 174 < 4.5 < 0.7 < 2.5 < 0.6 6.7 +/- 1.5 < 1.7 MW-CL-19S 11/02/15 < 190 MW-CL-2 02/09/15 < 154 MW-CL-2 05/26/15 < 195 .

MW-CL-2 08/17/15 < 180 < 5.2 < 0.6 < 1.2 < 1.1 3.9 +/- 1.1 < 1.6 MW-CL-2 11/02/15 < 188 MW-CL-20S 02/09/15 < 154 MW-CL-20S 05/26/15 < 198 MW-CL-20S 08/17/15 < 175 < 6.3 < 0.5 < 1.2 < 0.5 2.8 +/- 1.1 < 1.6 MW-CL-20S 11/02/15 < 188 MW-CL-21S 02/09/15 176 +/- 106 MW-CL-21S 05/26/15 219 +/- 130 MW-CL-21S 08/17/15 287 +/- 124 MW-CL-21S 09/29/15 < 197 < 5.3 < 0.8 < 1.8 < 0.8 < 1.5 < 1.6 MW-CL-21S 11/02/15 < 189 MW-CL-22S 02/09/15 < 179 MW-CL-22S 05/27/15 < 194 MW-CL-22S 08/18/15 < 180 MW-CL-22S 09/29/15 < 4.4 < 0.7 < 2.3 < 0.9 11.2 +/- 1.5 < 1.6 MW-CL-22S 11/03/15 < 192 B-2 Page 134of138

Table 8-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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 B-3 08/17/15 < 36 < 29 < 3 <4 < 7 <4 < 6 <4 < 6 < 3 < 4 < 29 < 8 MW-CL-1 08/17/15 < 38 < 36 < 4 < 5 < 10 <4 < 8 < 5 < 8 <4 < 4 < 28 < 13 MW-CL-121 08/17/15 < 38 < 37 < 4 <4 < 8 < 3 < 7 <4 < 7 <4 <4 < 28 < 10 MW-CL-131 08/17/15 < 41 68 +/- 37 < 4 < 4 < 10 < 3 < 8 <4 < 7 <4 <4 < 30 < 9 MW-CL-138 08/17/15 < 37 < 77 < 4 <4 < 11 <4 < 8 ~4 < 8 <4 <4 < 30 < 11 MW-CL-148 02/09/15 < 42 < 68 < 4 < 5 < 9 <4 < 9 < 5 < 8 < 4 <4 < 33 < 10 MW-CL-148 08/18/15 < 38 < 51 < 4 < 5 < 11 < 5 < 9 < 5 < 9 <4 <4 < 31 < 12 MW-CL-151 08/17/15 < 38 < 30 <4 <4 < 8 < 4 < 8 <4 < 7 < 3 < 3 < 28 < 9 MW-CL-158 09/29/15 < 73 < 148 < 6 < 8 < 16 < 8 < 11 < 5 < 11 < 6 < 8 < 34 < 14 OJ I MW-CL-168 09/29/15 < 79 < 154 < 11 < 9 < 19 < 9 < 19 < 11 < 17 < 7 < 12 < 45 < 12 w MW-CL-178 08/18/15 < 36 < 32 <4 <4 < 9 <4 < 9 < 5 < 8 < 3 <4 < 27 < 9 MW-CL-181 08/18/15 < 35 < 72 < 5 < 4 < 10 < 4 < 6 <4 < 5 < 3 <4 < 26 < 8 MW-CL-188 08/18/15 < 16 < 32 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 17 < 5 MW-CL-198 08/17/15 < 21 < 47 < 2 < 2 < 6 < 2 < 5 < 3 <4 < 2 < 2 < 24 < 7 MW-CL-2 08/17/15 < 32 < 26 < 3 <4 < 7 < 3 < 6 <4 < 7 < 3 <4 < 32 < 9 MW-CL-208 08/17/15 < 18 < 18 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 18 < 6 MW-CL-218 02/09/15 < 31 < 58 < 3 < 3 < 9 < 3 < 7 < 4 < 8 < 3 <4 < 25 < 8 MW-CL-218 05/26/15 < 15 < 30 < 1 < 2 <4 < 2 < 3 <2 < 3 < 1 < 2 < 13 <4 MW-CL-218 09/29/15 < 57 < 87 < 7 < 7 < 19 < 7 < 14 < 9 < 16 < 8 < 7 < 34 < 12 MW-CL-228 09/29/15 < 80 < 95 < 8 < 6 < 23 < 7 < 20 < 9 < 17 < 9 < 10 < 43 < 9

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RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA 1r 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 THERE WERE NO HARD TO DETECTS ANALYZED IN 2015

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SW-CL-4 11/02/15 < 191 SW-CL-5 02/09/15 < 182 SW-CL-5 05/26/15 < 194 SW-CL-5 08/17/15 < 173 SW-CL-5 11/02/15 < 191 SW-CL-6 02/09/15 < 177 SW-CL-6 05/26/15 < 194 SW-CL-6 08/17/15 < 174 SW-CL-6 11/02/15 < 188 SW-CL-7 02/09/15 < 183 SW-CL-7 05/26/15 < 195 SW-CL-7 08/17/15 < 181 SW-CL-7 11/02/15 < 194 SEWAGE TREATMENT PLANT 02/09/15 < 182 SEWAGE TREATMENT PLANT 05/26/15 < 192 SEWAGE TREATMENT PLANT 08/17/15 < 177 SEWAGE TREATMENT PLANT 11/02/15 < 193 B-5 Page 137of138

Table 8-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN suRi;:AcE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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-14 DATE CL-SW-CL-1 08/17/15 < 21 < 18 < 2 < 2 < 5 < 2 <4 < 2 <4 <2 <2 < 22 <7 CL-SW-CL-2 08/17/15 < 17 40 + 26 < 1 < 2 <4 < 1 < 3 <2 <3 < 1 < 2 < 17 < 5 CL-SW-CL-4 08/17/15 < 16 < 12 < 1 <2 < 4 < 1 < 3 < 2 < 3 < 1 < 2 < 17 <4 CL-SW-CL-5 08/17/15 < 18 < 47 < 1 < 2 <4 <2 <, 3 <2 < 4 < 2 < 2 < 21 < 6 CL-SW-CL-6 08/17/15 < 18 65 + 31 < 2 < 2 < 5 < 2 <3 < 2 < 4 < 1 <2 < 18 < 6 CL-SW-CL-7 08/17/15 < 15 < 15 < 1 < 1 <4 < 2 < 3 < 2 < 3 < 1 < 1 < 16 < 6 SEWAGE TREATMENT PLANT 08/17/15 < 17 < 17 <2 < 2 <4 < 2 <4 < 2 < 4 < 2 <2 < 20 < 6 OJ I

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Exelon Generation Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604277 April 29, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 '"-"

NRG Docket No. 50-461

Subject:

Clinton Power'Station 2015 Annual Radiological Environmental Operating Report Exelon Generating Company, LLC (Exelon), Clinton Power Station is submitting the 2015 Annual Radiological Environmental Operating Report. This report is submitted in accordance with Technical Specification requirement 5.6.2, "Annual Radiological Environmental Operating Report," and covers the period from January 1, 2015 through December 31, 2015.

This report provides the results of the Radiological Environmental Monitoring Program as specific in Section 3/4 and 6.1 of the Offsite Dose Calculation Manual.

There are no regulatory commitments *contained within this letter.

Questions on this letter may be directed to Mr. Rick Bair, Chemistry Manager, at 217-937-3200.

Respectfully,

~

Theodore R. Stone( tf'\

Site Vice President Clinton Power Station dra/bsz Attachments:

Annual Radiological Environmental Operating Report cc: Regional Administrator- NRG Region Ill NRG Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Emergency Management Agency

Page 1of138 Intentionally left blank Page 2of138

Docket No: 50-461 CL~NTON POWER STAT~ON Annual Radiological Environmental Operating Report January 1 Through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services

  • ~

J:/ ExelonGeneration, Clinton Power Station Clinton, IL 61727 April 2016 Page 3of138

INTENTIONALLY LEFT BLANK Page 4of138

Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ....................................................................................................-................. 3 A. Objectives of the REMP ...................................................................................... 3 B. Implementation of the Objectives ........................................................................ 3 Ill. Program Description ...................................................................................................... 4 A. Sample Collection ............................................................................................... 4 B. Sample Analysis .......................................................:.......................................... 6 C. Data_ lnterpretati<;m ***'.****'._******~:***************************-**~*:*********************:*********************** 6

- ----n_,- Pro-graih Exceptions-........... .-.-.~ ...........-..-.......... :.. :.~.~~~-.-.:-:.-~:.-.... :............ .-:... .-.-.: ......... 8 E. Program Changes .............................................................._ ............................... 12 IV. Results and Discussion ............................................................................................... 12 A. Aquatic Environment ......................................................................................... 12

1. Surface Water. ........................................................................................ 12
2. Drinking Water ........................................................................................ 12
3. Well Water ............................................................................................. 13
4. Fish ......................................................................................................... 13
5. Sediment. ................................................................................................ 14 B. Atmospheric Environment ............... :***************************************************************** 14
1. Airborne .................................................................................................. 14
a. Air Particulates ................................. :........................................*... 14
b. Airborne Iodine ............................................................................ 15
2. Terrestrial ................................................................................................ 15
a. Milk ............................................................................................... 15
b. Food Products ............................................................................. 16
c. Grass ........................................................................................... 16 C. Ambient Gamma Radiation ............................................................................... 16 D. Land Use Survey ............................................................................................... 17 E. Errata Data ........................................................................................................ 17 F. Summary of Results - Inter-laboratory Comparison Program .......................... 18 V. References ................................................................................................................... 22 Page 5of138

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Clinton Power Station, 2015 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods

__,_:Tables ..

Table B-1 Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Table B-2 Radiological Environmental Monitoring Program - Summary of Sample Collection, Clinton Power Station, 2015 Figures Figure B-1 Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 Figure B-2 Environmental Sampling Locations Between One and Two Miles from the Clinton Power Station, 2015 Figure B-3 Environmental Sampling Locations Between-Two and Five Miles from the Clinton Power Station, 2015 Figure B-4 Environmental Sampling Locations Greater Than Five Miles from the Clinton Power Station, 2015 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-1.1 Concentrations of 1-131 in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-1.2 Concentrations of Tritium in Surface Water Samples Coll~cted in the Vicinity of Clinton Power Station, 2015.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-11.1 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

ii Page 6of138

Table C-11.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-11.3 Concentrations of 1-131 in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-11.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-111.1 Concentrations of Tritium in Well Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-111.2 Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-IV.1 Concentrations of Gamma Emitters in Fish Samples Collected in the

  • Vicinity of Clinton Power Station, 2015.

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Table C-V.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vl.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vl.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vl.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Clinton Power Statio_n, 2015.

Table C-Vll.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vlll.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-Vlll.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-IX.1 Concentrations of Gamma Emitters in Vegetation Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-IX.2 Concentrations of Gamma Emitters in Grass Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table C-X.1 Quarterly DLR Results for Clinton Power Station, 2015.

Table C-X.2 Mean Quarterly DLR Results for the Inner Ring, Outer Ring, Special Interest and Control Locations for Clinton Power Station, 2015.

Table C-X.3 Summary of the Ambient Dosimetry Program for Clinton Power Station, 2015.

iii Page 7of138

Figures Figure C-1 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of CPS, 2015.

Figure C-2 Mean Quarterly Ambient Gamma Radiation Levels (DLR) in the Vicinity of CPS, 2015.

Appendix D Inter-Laboratory Comparison Program Tables Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, .2015 TaQle D~2 DOE's Mixed Alialyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engine-ering, 2015 * -~- * -

Table D-3 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2015 Table D-4 ERA(a) Statistical Summary Proficiency Testing Program Environmental, Inc., 2015 Table D-5 DOE's Mixed Analyte Performance Evaluation- Program (MAPEP)

Teledyne Brown Engineering, 2015

  • Appendix E Errata Data .

Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) iv Page 8of138

I. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP) conducted for the Clinton Power Station (CPS) by Exelon Generation Company, LLC (Exelon) covers the period January 1, 2015 through December 31, 2015.

During that time period, 1,590 analyses were performed on 1,463 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of CPS had no adverse radiological impact on the environment.

There were zero (0) radioactive liquid releases from CPS during 2015. Releases of gaseous radioactive materials were accurately measured in plant effluents.

There were no gaseous effluent releases that approached the limits specified in the CPS Offsite Dose Calculation Manual (ODCM). The highest calculated offsite _dose received by.,a member. of the- public in :2015. due-to .the release .oL'---*-*- .

gaseous effluents from CPS was 2.53 E-03 or 0.00253 mRem.

Surface, drinking,_ and well water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of gross beta and 1-131. Naturally occurring K-40 was detected .at levels consistent with those detected in previous years. No fission or activation products were detected. No tritium or gross beta activity was detected. and the required lower limit of detection (LLD) was met.

Fish and shoreline sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected in fish or shoreline sediment samples.

Air particulate samples were analyzed for concentrations of gross. beta and gamma emitting nuclides. Cosmogenic Be-7 and naturally occurring K-40 were detected at levels consistent with those detected in previous years. No fission or activation products were detected.

Iodine- 1-131 analyses were performed on weekly air samples. All results were less than the lower limit of detection for 1-131.

High sensitivity 1-131 analyses and gamma analyses were performed on cow milk samples. All results were below the required LLDs for 1-131.

Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.

Food product samples were analyzed for concentrations of gamma emitting nuclides. Concentrations of cosmogenically produced Be-7 and naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were detected.

Grass samples were analyzed for concentrations of gamma emitting nuclides.

Concentrations of cosmogenically produced Be-7 and naturally occurring K~40 were consistent with those detected in previous years. No fission or activation Page 9of138

products were detected.

Environmental gamma radiation measurements were performed quarterly using Dosimeters of Legal Record (DLR). Levels detected were consistent with those observed in previous years.

Page 10of138

II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on February 15, 1987. The site encloses approximately 13, 730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated on approximately 150 acres. The cooling water discharge flume - which discharges to the eastern arm of the lake - occupies an additional 130 acres.

Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13,730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa f.nn_a _Townships.

A Radiological Environmental Monitoring Program (REMP) for CPS was initiated in 1987. The preoperational period for most media covers the periods May 1980 through February 27, 1987 and was summarized in a separate report. This report covers those analyses performed by Teledyne Brown Engineering (TSE) and Landauer on samples collected during the period January 1, 2015 through December 31, 2015.

A. Objectives of the REMP The objectives of the REMP are to:

1. Provide data on measurable levels of radiation and radioactive materials in the site environs.
2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

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

1. Identifying significant exposure pathways.
2. Establishing baseline radiological data of media within those pathways.
3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

Page 11 of 138

Ill. Program Description A. Sample Collection This section describes the general collection methods used by Environmental Inc. (Midwest Labs) to obtain environmental samples for the CPS REMP in 2015. Sample locations and descriptions can be found in Tables B-1 and B~2, and Figures B-1 through B-4, Appendix B. The sampling methods used by Environmental Inc. (Midwest Labs) are listed in Table B-2.

Aquatic Environment The aquatic environment was evaluated by performing radiological


-

  • analyses on samples of surface water, drinking water; well-water, fish, and---'-

shoreline sediment. Two gallon water samples were collected monthly from composite samplers located at three surface water locations (CL-90, CL-91 and CL-99) and one drinking water location (CL-14). A monthly grab sample was obtained from one surface water location (CL-13).

Quarterly samples were obtained from two well water locations (CL-70 and CL-12). All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of largemouth bass, crappie, carp, bluegill and channel catfish, the species most commonly harvested from the lakes by sporting fishermen, were collected semiannually at two locations, CL-19 and CL-105. CL-105 was the control location, which is located about 50 miles upwind of the station. Shoreline sediment samples composed of recently deposited substrate were collected at two locations semiannually (CL-78 and CL-105 (control)).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, milk, food produce and grass. Airborne iodine and particulate samples were collected and analyzed weekly at ten locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94). CL-11 was the control location, which is located 16 miles upwind of the station. 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 an independent laboratory for analysis.

Page 12of138

Milk samples were collected biweekly at one location (CL-116) from May through October to coincide with the grazing season, and monthly from November through April. All samples were collected in new unused plastic bottles from the bulk tank at the dairy farm, preserved with sodium bisulfite and shipped promptly to the laboratory.

Food products were collected once a month from June through September at four locations (CL-114, CL-115, CL-117 and CL-118). The control location was CL-114, which is located 12.5 miles upwind of the station. Various broadleaf vegetable samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.

Grass samples were collected biweekly at four locations (CL-1, CL-2, CL-8 and CL-116) from May through October. CL-116 was the control

- ------~ location, which is -located 14 miles WSW of the station. -Ail samples were --

collected in new unused plastic bags and sent to the laboratory for analysis.

Ambient Gamma Radiation Direct radiation measurements were made using DLRs. Each location consisted of 2 dosimeter sets. The DLRs were exchanged quarterly and sent to Landauer for analysis. The DLR locations were placed around the CPS site as follows:

An inner ring consisting of 16 locations (CL-1, CL-5, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42 CL-43, CL-44, CL-45, CL-46, CL-47, CL-48 and CL-63).

An outer ring consisting of 16 locations (CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80 and CL-81). CL-58MM was installed as part of a volunteer comparison study extending to approximately 5 miles from the site.

A special interest set consisting of seven locations (CL-37, CL-41, CL-49, CL-64, CL-65, CL-74 and CL-75) representing special interest areas.

A supplemental set consisting of 14 locations (CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 and CL-114).

CL-11 represents the control location for all environmental DLRs.

The specific DLR locations were determined by the following criteria:

Page13of138

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 meteorological sectors around the site, where estimated annual dose from CPS, if detected, would be most significant;
3. On hills free from local obstructions and within sight of the HVAC and VG stacks (where practical);
4. And near the closest dwelling to the HVAC and VG stacks in the prevailing downwind direction. /

Each location has two DLRs in a vented PVC conduit located approximately three feet above ground-level. The DLRs were exchanged

  • quarterly and sent to Landauer for analysis.

B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the CPS REMP in 2015. The analytical procedures used by the laboratories are listed in Table 8-2.

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

1. Concentrations of beta emitters in drinking water and air particulates.
2. Concentrations of gamma emitters in surface, drinking and well water, air particulates, milk, fish, grass, sediment and vegetables.
3. Concentrations of tritium in surface, drinking and well water.
4. Concentrations of 1-131 in air, milk, drinking water and surface water.
5. Ambient gamma radiation levels at various off-site environs.

C. Data Interpretation The radiological and direct radiation data collected prior to CPS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this- report, CPS was considered Page 14of138

operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. 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" value. 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 CPS
  • detection capabilities for-environmental sample analysis.
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 resulting in a negative number. A minimum detectable concentration (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 water, well water, fish, sediment, and milk: 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.

For drinking water, grass, and vegetation: 13 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140, La-140 and Ce-144 were reported.

For air particulate: 9 nuclides, Co-60, Nb-95, Zr-95, Ru-103, Ru-106, Cs-134, Cs-137, Ce-141 and Ce-144, were reported.

The mean and ~tandard deviation of the results were calculated.

The standard de;,iation represents the variability of measured results for different samples rather than single analysis uncertainty.

Page 15of138

D. Program Exceptions The exceptions (Issue Reports, IRs) described below are those that are considered 'deviations' from the Radiological Environmental Monitoring Program as required by the Station's ODCM. By definition, 'deviations' are permitted as delineated within NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",

October 1978, and within Radiological Assessment Branch Technical Position, Revision 1, November 1979, which states .... "Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability,

-- - - --" - malfunction of automatic sampling equipment and other legitimate reasons" .... The below section addresses the reporting requirements found within Section 6.0_of the Station's ODCM. -

. *-*- - .. - - . - .*. - - :.. ;-,--- - *----

Exceptions/Anomalies January 14, 2015, IR 02437296 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.

March 04, 2015, IR 02463282 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.

March 11, 2015, IR 02468075 While performing the ODCM weekly inspection the upstream non-ODCM Water Compositor Sampler, CL-99, was found not running. North Fork Creek was found to be at a low level and frozen due to below zero temperatures.

May 07, 2015, IR 02497332 While performing the ODCM weekly air sample collection and equipment verification activities on May 06, 2015, vendor Environmental Inc., Midwest Laboratories (EIML) discovered that the ODCM air samplers CL-2 and CL-3 had no power. In the absence of any severe storms or power outages, it was Page 16of138

indeterminate as to why there was no power. However, the minimum sample volume was reached.

July 01, 2015, IR 02522637 At 1244 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.73342e-4 months <br /> on 07/01/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its ground fault interrupter (GFI) 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.

July 15, 2015, IR 02528489 While performing the weekly inspection on 07/15/15 of ODCM Water Compositors, CL-99 was found not running with the GFI

'tripped' and the sample collection container tipped over inside of the Dog House enclosure. The last weekly inspection performed on July 08, 2015 revealed both as found and as left conditions as being satisfactory. During this 7 day window, Murray and "'frettel, our fleetwide meteorological vendor, reported that Lincoln County had 4.5 inches, Bloomington haq 4.6 inches and DeWitt County had 4 inches of rain which all contributed to the North Fork Creek flooding. This flooding contributed to the 'as found' condition*

noted.

August 19, 2015, IR 02543695 At 1046 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98003e-4 months <br /> on 08/19/15 while performing weekly checks of ODCM Water Compositors, CL-90 was found with its GFI 'tripped' and observed to have less than the weekly composite sample collection volume for the monthly analysis. A supplemental 'grab' sample from the process stream was collected and added to the monthly collection container. The GFI was reset and CL-90 was returned to service.

August 21, 2015, IR 02545496 During the execution of Work Order #1614812-05 for the recently scheduled Potable Water Outage that commenced at 0325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br />, 08/21/15 the potable water was secured, drained and potable water pumps were placed in Manual OFF. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water samples Page 17of138

throughout the duration of the Potable Water Outage that was restored to service at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on 08/22/15.

November 14, 2015, IR 02588060 During the execution of Clearance Order #129314 and de-energized Circuit 302 per WO 1863079-06 for the recently scheduled outage, potable water was secured at 0006 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on 11/14/15. This prevented ODCM Water Compositor CL-14 from obtaining hourly composite water sample throughout the duration of the Potable Water Outage that was restored to service at 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br /> on 11 /14/15.

November 18, 2015, IR 02589324 During the weekly checks of ODCM Water compositors on 11/15/15, at 12:35, CL-90 was found with its GFI 'tripped'. The breaker was reset but the GFI 'tripped' after the initial reset. There was standing water within the doghouse enclosure, which contributed to the GFI tripping both times.

Throughout 2015, the following IRs were generated to document Program exceptions that were entered into the corrective action program for trending purposes.

Missed Samples May 13, 2015, IR 02500319 The ODCM air samplers CL-2 and CL-3 lost power on 05/06/15 (IR

  1. 02497332). A portable generator was placed to supply power to CL-2 & CL-3 air monitoring stations. The minimum sample volume was not reached for that sampling period.

June 03, 2015, IR 02512981 While performing the weekly ODCM Surveillance on Wednesday, June 10, 2015 for the collection of particulate and iodine filters and cartridges, the sample collector noted that upon arrival at CL-7, the sample pump was not running. Instead of the typical run time of approximately 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, the timer registered 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 minutes. The minimum volume was not reached for that sampling period.

Page 18of138

June 13, 2015, IR 02515452 The ODCM air samplers CL-2 and CL-3 lost power some time on or before June 13, 2015 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> when first observed by a Station Security Officer (IR #02514143). Both air sample stations now have back-up generator power, returning both sample stations to service. Minimum sample volume was not collected for that sampling period.

July 29, 2015, IR 02534576

-- - During the Weekly Sample Collection Surveillance it was discovered that the two (2) recently changed out Environmental DLRs for CL-51, placed there on June 25, 2015 as part of the 3rd .

      • - ~-- - * * -- Quarter Exchange, were found-missing: -The adjacent farm field's-culvert had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs, the PVC sample holder or the stanchion pole that it was connected to.

August 20, 2015, IR 02546978 While performing the Weekly OCDM Surveillance on Wednesday, 08/26/15 for the collection of particulate filters and iodine cartridges, it was discovered that there was no electrical power to CL-8. Instead of the typical run time of approximately 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, the timer registered 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> and 36 minutes. The minimum volume was not reached for that sample.

September 24, 2015, IR 02560026 1

During the 4 h Quarter Exchange of Environmental DLRs, it was discovered the CL-46 dosimeters placed on 06/25/15 as part of the 3rd Quarter Exchange were found missing. The adjacent farm field had appeared to be recently mowed. A search was conducted of the surrounding area. There was no sign of the DLRs or the PVC sample holder, but the stanchion pole was found lying in the field.

Program exceptions were reviewed to understand the causes of the exception and to return to ODCM sample compliance before the next sampling frequency period.

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

Page 19of138

E. Program Changes There were no changes to the program in 2015.

IV. Results and Discussion A. Aquatic Environment

1. Surface Water Composite samples were taken hourly at three locations (CL-90, CL-91 and CL-99) on a monthly schedule and grab samples were taken monthly from one location (CL-13). The following analyses _

were performed.- - ----. -- .. .----"* *-*

lodine-131 Monthly samples from location CL-90 were analyzed for 1-131 activity (Table C-1.1, Appendix C). No 1-131 was detected in any samples and the required LLD was met.

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.2, Appendix C). No tritium was detected in any samples and the required LLD was met.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.

2. Drinking Water Monthly composite samples were taken hourly at one location (CL-14). The'following analyses were performed:

Gross Beta Monthly samples were analyzed for concentrations of gross beta (Tables C-11.1, Appendix C). No Gross beta was detected in any of the samples.

Page 20 of 138

Tritium Monthly samples were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). No tritium was detected in any samples and the required LLD was met.

lodine-131 Monthly samples from location CL-14 were analyzed for 1-131 activity (Table C-11.3, Appendix C). No 1-131 was detected in any samples and the required LLD was met.

Gamma Spectrometry

  • c~* * *** ' Monthly samples Were ana.lyzed for gamma emitting nu elides (Table C-11.4, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.
3. Well Water Quarterly grab samples were collected at two locations (CL-7D and CL-12, consisting of CL-12R [a raw water sample from this well]

and CL-12T [same well water, but after treatment and available for consumption]). The following analyses were performed:

Tritium Samples from all locations were analyzed for tritium activity {Table C-111.1, Appendix C). No tritium was detected in any samples and the required LLD was met.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-111.2, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.

4. Fish Fish samples comprised of carp, largemouth bass, bluegill, crappie and channel catfish were collected at two locations (CL-19 and CL-105) semiannually. The following analysis was performed:

Page 21 of 138

Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C).

No plant produced radionuclides were detected and all required LLDs were met.

.5. Shoreline Sediment Aquatic shoreline sediment samples were collected at CL-78 and CL-105 semiannually. The following analysis was performed:

Gamma Spectrometry Shoreline *seaiment samples were analyzed for gamma emitting--*

nuclides (Table C-V.1, Appendix C). No plant produced radionuclides were detected and all required LLDs were met.

B. Atmospheric Environment

1. Airborne
a. Air Particulates Continuous air particulate samples were collected from 10 locations on a weekly basis. The 10 locations were separated into three groups: Group I represents locations within one mile of the CPS site boundary (CL-2, CL-3, CL-4, CL-6, CL-15 and CL-94); Group II represents the locations at an intermediate distance within one to five miles of CPS (CL-1, CL-7 and CL-8); and Group Ill represents the control location greater than five miles from CPS (CL-11). The following analyses were performed:

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

Detectable gross beta activity was observed at all locations.

Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of CPS. The results from the On-Site locations (Group I) 3 ranged from 7 to 43 E-3 pCi/m with a mean of 19 E-3 Page 22 of 138

pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from 6 to 42 E-3 pCi/m 3 with a mean of 18 E-3 pCi/m 3 . The results from the Control locations (Group Ill) ranged from 7 to 36 E-3 pCi/m 3 with a mean of 19 E-3 pCi/m 3 . Comparison of the 2015 air particulate data with previous years' data indicate no measurable impact from the operation of CPS. In addition, a comparison of the weekly mean values for 2014 indicate no notable differences among the three groups.

Gamma Spectrometry Weekly samples were composited quarterly and analyzed

'*for gamma emitting nuclides (Table C-Vl.3, Appendix C).

  • - NcYplant produced*radionuclides were detected and all --- -

required LLDs were met.

b. Airborne Iodine Continuous air samples were collected from 10 locations (CL-1, CL-2, CL-3, CL-4, CL-6, CL-7, CL-8, CL-11, CL-15 and CL-94) and analyzed weekly for 1-131 (Table C-Vll.1, Appendix C). All results were less than the MDC and the required LLD was met.
2. Terrestrial
a. Milk Samples were collected from CL-116 biweekly May tnrough October to coincide with the grazing season, and monthly November through April. The following analyses were performed:

lodine-131 Milk samples were analyzed for concentrations of 1-131 (Table C-Vlll.1, Appendix C). lodine-131 was not detected in any of the samples. The required LLD was met.

Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-Vlll.2, Appendix C).

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

Page 23 of 138

No plant produced radionuclides were detected and all required LLDs were met.

b. Food Products Broad leaf vegetation samples were collected from four locations (CL-114, CL~115, CL~117 and CL-118) monthly June through September to coincide with the harvest season. The following analysis was performed:

Gamma Spectrometry Each food product sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.1, Appendix C). No

-~---***" plant produced radionuclides were detected and all required- - -- ** *-0

-

LLDs were met.

c. Grass Samples were collected from four locations (CL-1, CL-2, CL-8, and CL-116) biweekly May through October. The following analysis was performed:

Gamma Spectrometry Each grass sample was analyzed for concentrations of gamma emitting nuclides (Table C-IX.2, Appendix C). No plant produced radionuclides were detected and all required

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing DLRs. Fifty-four DLR locations were established around the site. Results of DLR mea.surements are listed in Tables C-X.1 to C-X.3, Appendix C.

A total of 214 OSLO measurements were made in 2015. The average dose from the inner ring was 23.4 mRem/quarter. The average dose from the outer ring was 23.8 mRem/quarter. The average dose from the special interest group was 23.1 mRem/quarter. The average dose from the supplemental group was 22.1 mRem/quarter. The quarterly measurements ranged from 17.3 to 28.0 mRem/quarter.

The inner ring and outer ring measurements compared well to the Control Station, CL-11, which ranged from 19.9 mRem/quarter to 23.6 Page 24 of 138

mRem/quarter with an average measurement of 21.9 mRem/quarter. A comparison of the Inner Ring and Outer Ring data to the Control Location data indicate that the ambient gamma radiation levels from all the locations were comparable. The historical ambient gamma radiation data from the control location were plotted along with similar data from the Inner and Outer Ring Locations (Figure C-2, Appendix C).

D. Land Use Survey A Land Use Survey conducted during the July through October 2015 growing season around the Clinton Power Station (CPS) was performed by Environmental Inc. (Midwest Labs) for Exelon to comply with Clinton's Offsite Dose Calculation Manual, section 8.0. The purpose of the survey was to document the nearest resident, milk producing animal and garden 2

  • of-greater than 538 m in each of the sixteen 22 % degree sectors-around the site. The distance and direction of all locations from the CPS Station HVAC vent stack were positioned using Global Positioning System (GPS) technology. There were no changes required to the CPS REMP as a result of the Land Use Survey. The results of this survey are summarized below.

Distance in Kilometers from the CPS Station HVAC Vent Stack Sector Residence Garden Milk Animal (km) (km) (km) 1 N 1.5 1.5 1.5 2 NNE 1.5 1.5 >8 3 NE 2.1 3.5 >8 4 ENE 2.9 2.9 >8 5 E 1.7 1.7 >8 6 ESE 5.1 5.3 >8 7 SE 4.4 >8 >8 8 SSE 2.9 4.3 >8 9 s 4.8 4.8 6.6 10SSW 4.7 >8 5.5 11 SW 1.2 5.9 >8 12WSW 3.6 3.7 5.5 13W 2.0 3.2 >8 14WNW 2.6 2.6 >8 15NW 2.7 4.7 >8 16NNW 2.1 2.1 2.1 E. Errata Data There was no errata data for 2015.

Page 25 of 138

F. Summary of Results~ Inter-Laboratory Comparison Program The primary laboratory analyzed Performance Evaluation (PE) samples of

-air particulate, air iodine, milk, soil, vegetation and water matrices for 25 analytes (Appendix D). The PE samples, supplied by Analytics Inc.,

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

1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TB E'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 Perform~nce Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation speeific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.

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

The MAPEP defines three levels of performance: Acceptable

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

For the TBE laboratory, 129 out of 139 analyses performed met the specified acceptance criteria. Ten analyses (AP - Cr-51, U-234/233, Gr A, Sr-90; Soil Sr-90; Water - Ni:-3, Sr-89, Sr-90, and U natural; Vegetation Page 26 of 138

Sr-90 samples) did not meet the specified acceptance criteria for the following reasons:

- Note: The Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP) samples are created to mimic conditions found at DOE sites which do not resemble typical environmental samples obtained

1. Teledyne Brown Engineering's Analytics' June 2015 air particulate Cr-51 result of 323 +/- 45.5 pCi was higher than the known value of 233 pCi with a ratio of 1.39. The upper ratio of 1.30 (acceptable with warning) was exceeded. The air particulate sample is counted at a distance above the surface of the detector to avoid detector summing which could alter the results. Chromium-51 has the

__ --*~ ----.~"""'- ~: ~- -~shortest half.,.life (27. 7:days) and the lowest.gamma energy_(320.08 keV) of this mixed nuclide sample. Additionally, Cr-51 has only one gamma energy and also has a low intensity (9.38 gamma photons produced per 100 disintegrations). This geometry produces a larger error for the Cr-51 and other gamma emitters as any distance from the detector decreases the counting rate and the probability of accurately detecting the nuclide energy. Taking into consideration the uncertainty, the activity of Cr-51 overlaps with the known value at a ratio of 1.19, which would statistically be considered acceptable. NCR 15-18

2. Teledyne Brown Engineering's MAPEP March 2015 soil Sr.. 90 result of 286 Total Bq/kg was lower than the known value of 653 Bq/kg, exceeding the lower acceptance range of 487 Bq/kg. The failure was due to incomplete digestion of the sample. Incomplete digestion of samples causes some of the sample to be left behind and is not present in the digested st;imple utilized for analysis. The procedure has been updated to include a more robust digestion using stirring during the heating phase. The MAPEP September 2014 soil Sr-90 series prior to this study was evaluated as acceptable with a result of 694 and an acceptance range of 601 -

1115 Bq/kg. The MAPEP September 2015 series soil Sr-90 after this study was evaluated as acceptable with a result of 429 and an acceptance range of 298 - 553 Bq/kg. We feel the issue is specific to the March 2015 MAPEP sample. NCR 15-13

3. Teledyne Brown Engineering's MAPEP March 2015 air particulate U-234/233 result of 0.0211 +/- 0.0120 Sq/sample was higher than the known value of 0.0155 Sq/sample, exceeding the upper acceptance range of 0.0202 Sq/sample. Although evaluated as a failure, taking into consideration the uncertainty, TBE's result would overlap with the known value, which is statistically considered Page 27 of 138

acceptable. MAPEP spiked the sample with significantly more U-238 activity (a found to known ratio of 0.96) than the normal U-234/233. Due to the extremely low activity, it was difficult to quantify the U-234/233. NCR 15-13

4. Teledyne Brown Engineering's MAPEP March 2015 air particulate gross alpha result of 0.448 Sq/sample was lower than the known value of 1. 77 Sq/sample, exceeding the. lower acceptance range of 0.53 Sq/sample. The instrument efficiency used for gross alpha is determined using a non-attenuated alpha standard. The MAPEP filter has the alphas embedded in the filter, requiring an attenuated efficiency. When samples contain alpha particles that are embedded in the sample media, due to the size of the alpha particle, some of the alpha particles are absorbed by the media and

. - - cannot escape to be-counted.--When the sample-media absorbs- -

the alpha particles this is known as self-absorption or attenuation.

The calibration must include a similar configuration/media to correct for the attenuation. In order to correct the low bias, TBE will create an attenuated efficiency for MAPEP air particulate filters.

The MAPEP September series air particulate gross alpha result of 0.47 Sq/sample was evaluated as acceptable with a range of 0.24

- 1.53 Sq/sample. Unlike the MAPEP samples, air particulate Gross alpha analyses for power plants are not evaluated as a direct count sample. Power plant air particulate filters for gross alpha go through an acid digestion process prior to counting and the digested material is analyzed. NCR 15-13

5. Teledyne Brown Engineering's MAPEP September water Ni-63 result of 11.8 +/- 10.8 Bq/l was higher than the known value of 8.55 Bq/l, exceeding the upper acceptance range of 11.12 Bq/L. The Ni-63 half-life is approximately 100 years. Nickel-63 is considered to be a "soft" or low energy beta emitter, which means that the beta energy is very low. The maximum beta energy for Ni-63 is approximately 65 keV, much lower than other more common nuclides such as Co-60 (maximum beta energy of 1549 keV). The original sample was run with a 10 ml aliquot which was not sufficient for the low level of Ni-63 in the sample. The rerun aliquot of 30 ml produced an acceptable result of 8.81 Bq/L. NCR 15-21
6. Teledyne Brown Engineering's MAPEP September air particulate Sr-90 result of 1.48 Sq/sample was lower than the known value of 2.18 Sq/sample, exceeding the lower acceptance range of 1.53 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incomplete removal of the isotope of interest for Page 28 of 138

the laboratories analyzing the cross checks. TBE suspects that this may be the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity. TBE will no longer analyze the air particulate Sr~90 through MAPEP but will participate in the Analytics cross check program to perform both Sr-89 and Sr-90 in the air particulate matrix. NCR 15-21

7. Teledyne Brown Engineering's MAPEP September vegetation Sr-90 result of 0.386 Sq/sample was lower than the known value of 1.30 Sq/sample, exceeding the lower acceptance range of 0.91 Sq/sample. In the past, MAPEP has added substances (unusual compounds found in DOE complexes) to various matrices that have resulted in incompl_ete removal of the isotope of interest for

- the-laboratories analyi:ing-the:cross checks.' TBE suspects-thatthis maybe the cause of this error. Many compounds, if not properly accounted for or removed in the sample matrix, can cause interferences to either indicate lower activity or higher activity.

Results from previous performance evaluations were reviewed and shown to be acceptable. NCR 15-21

8. & 9.Teledyne Brown Engineering's ERA May water Sr-89/90 results of 45.2 and 28.0 pCi/L, respectively were lower than the known values of 63.2 and 41.9 pCi/L, respectively, exceeding the lower acceptance limits of 51.1 and 30.8 pCi/L, respectively. The yields

- were on the high side of the TBE acceptance range, which indicates the present of excess calcium contributed to the yield, resulting in low results. NCR 15-09

10. Teledyne Brown Engineering's ERA November water Uranium natural result of 146.9 pCi/L was higher than the known value of 56.2 pCi/L, exceeding the upper acceptance limit of 62.4 pCi/L.

The technician failed to dilute the original sample, but used the entire 12 ml sample. When the results were recalculated without the dilution and using the 12 ml aliquot, the result of 57 .16 agreed with the assigned value of 56.2. NCR 15-19 For the EIML laboratory, 90 of 94 analyses met the specified acceptance criteria. Four analyses (Water- Co-57, Fe-55; AP - Co-57; Soil - Sr-90) did not meet the specified acceptance criteria for the following reasons:

1. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 water Co-57 result of 10.2 Bq/L was lower than the known value of 29.9 Bq/L, exceeding the lower control limit of 20.9 Bq/L.

The reported value should have been 27.84, which would have Page 29 of 138

been evaluated as acceptable. A data entry error resulted in a non-acceptable result.

2. The Environmental Inc., Midwest Laboratory's MAPEP February 2015 AP Co-57 result of 0.04 Sq/sample was lower than the known value of 1.51 Bq/ sample, exceeding the lower control limit of 1,06 Sq/sample. The reported value should have been 1.58 Sq/sample, which would have been evaluated as acceptable. A data entry error resulted in a non-acceptable result.
3. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 soil Sr-90 result of 231 Bq/kg was lower than the known value of 425 Bq/kg, exceeding the lower control limit of 298 Bq/kg. The incomplete separation of calcium from strontium caused a failed

"-- - --  :-c - low result.' -The reanalysis result of 352 Bq/kg fell within ":- -

acceptance criteria.

4. The Environmental Inc., Midwest Laboratory's MAPEP August 2015 water Fe-55 result of 4.2 Bq/L was lower than the known value of 13.1 Bq/L, exceeding the lower control limit of 9.2 Bq/L.

The known activity was below the routine laboratory detection limits for the available aliquot fraction.

V. References

1. American National Standards Institute, Inc., "Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry," ANSI N545-1975.
2. Code of Federal Regulations, Title 10, Part 20 (Nuclear Regulatory Commission).
3. CPS 2014 Annual Radioactive Effluent Release Report.
4. "Environmental Radioactivity," M. Eisenbud, 1987 (E187).
5. "Natural Radon Exposure in the United States," Donald T. Oakley, U.S.

Environmental Protection Agency. ORP/SID 72-1, June 1972.

6. Federal Radiation Council Report No. 1, "Background Material for the Development of Radiation Protection Standards," May 13, 1960.
7. International Commission on Radiation Protection, Publication 2, "Report of Committee II on Permissible Dose for Internal Radiation," (1959) with 1962 Supplement issued in ICRP Publication 6; Publication 9, "Recommendations on Radiation Exposure," (1965); ICRP Publication 7 (1965), amplifying specific recommendations of Publication 26 (1977).

Page 30 of 138

8. International Commission on Radiation Protection, Publication No. 39 (1984), "Principles of Limiting Exposure to the Public to Natural Sources of Radiation".
9. * "Radioactivity in the Environment: Sources, Distribution and Surveillance," Ronald L. Kathren, 1984.
10. National Council on Radiation Protection and Measurements, Report No.

22, "Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure," (Published as National Bureau of Standards Handbook 69, issued June 1959, superseding Handbook 52).

11. National Council on Radiation Protection and Measurements, Report No.

39, "Basic Radiation Protection Criteria," January 1971.

-- 12. National Council on Radiation Protection and Measurements, Report No.

44, "Krypton-85 in the Atmosphere - Accumulation, Biological Significance, and Control Technology," July 1975.

13. National Council on Radiation Protection and Measurements, Report No.

91, "Recommendations on Limits for Exposure to Ionizing Radiation,"

June 1987.

14. National Council on Radiation Protection and Measurements, Report No.

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

September 1987.

15. National Research Council, 1990, Committee on Biological Effects of Ionizing Radiation (BEIR V), Board on Radiation Effects Research on Life Sciences, "The Effects of Exposure to Low Levels of Ionizing Radiation".
16. United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.
17. United States Nuclear Regulatory Commission, Regulatory Guide 4.13, "Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications, "Revision 1, July 1977.
18. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1OCFR Part 50, Appendix I, "Revision 1, October 1977.
19. United States Nuclear Regulatory Commission Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program,"

Revision 1, November 1979.

20. United States Nuclear Regulatory Commission, Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Norm Page 31 of 138

Operations) - Effluent Streams and the Environment," Revision 1, February 1979.

21. Technical Specifications, Clinton Power Station, Unit No. 1, Docket No.

50-461, Office of Nuclear Reactor Regulation, 1986. Facility Operating License Number NPF-62.

22. . Clinton Power Station, Updated Safety Analysis Report.
23. Clinton- Power Station, Unit 1, Off-Site Dose Calculation Manual.

Page 32 of 138

--

.. - . -; - - - ._ : -:_ - .. - - .,, ,,...._-;- - --

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

Page 33 of 138

Intentionally left blank Page 34 of 138

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 j, INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) i 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 1-131 12 <LLD NA 0 (PCI/LITER)

H-3 16 2000 <LLD <LLD 0 GAMMA 48 MN-54 15 <LLD <LLD 0 C0-58 15 <LLD <LLD 0 FE-59 30 <LLD <LLD 0 C0-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 "U

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 i NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH IDGHEST 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER ZR-95 30 <LLD <LLD 0 (PCI/LITER)

CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 CE-144 NA <LLD <LLD 0 DRINKING WATER GR-B 12 4 <LLD NA 0 "U(PCI/LITER)

D.l (Q

CD VJ H-3 4 2000 <LLD NA 0

-

(j) 0

-"

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

,.

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NA.ME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 I-131 12 <LLD NA 0 (PCJJLITER)

GAMMA 12 MN-54 15 <LLD NA 0 C0-58 15 <LLD NA 0 FE-59 30 <LLD NA 0 C0-60 15 <LLD NA, 0 ZN-65 30 <LLD NA 0 NB-95 15 <LLD NA 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQU1RED 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 CS-134 15 <LLD NA 0 (PCI/LITER)

CS-137 18 <LLD NA 0 BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 CE-144 NA <LLD NA 0 WELL WATER H-3 12 2000 <LLD NA 0 (PCI/LITER)

GAMMA 12 MN-54 15 <LLD NA 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 WELL WATER FE-59 30 <LLD NA 0 (PCI/LITER)

C0-60 15 <LLD NA 0 ZN-65 30 <LLD NA 0

)>

I C.11 NB-95 15 <LLD NA 0 ZR-95 30 <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA 0 "U

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION . DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED j

MEASUREMENT) (LLD) MEASUREMENTS

"

WELL WATER LA-140 15 <LLD NA 0 (PCI/LITER)

CE-144 NA <LLD NA 0 FISH GAMMA 16

P-(PCI/KG WET) MN-54 130 <LLD <LLD 0 O')

C0-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 C0-60 130 <LLD <LLD 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCA;noN 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 MEASURE.tvIBNT) (LLD) MEASUREMENTS FISH ZR-95 NA <LLD <LLD 0 (PCI/KG WET)

CS-134 130 <LLD <LLD 0 CS-137 150 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 CE-144 NA <LLD <LLD 0 SEDIMENT GAMMA 4 "1J(PCI/KG DRY) MN-54 NA <LLD <LLD :i' I* 0 Dl

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 INDICATOR CONTROL LOCATION WITH IDGHEST ANNUAL MEAN (M)

LOCATIONS LOCATION I 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 MEASUREJ\1ENT) (LLD) MEASUREMENTS SEDIMENT FE-59 NA <LLD <LLD 0 (PCI/KG DRY)

C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 CS-134 150 <LLD <LLD 0 CS-137 180 <LLD <LLD 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 :

INDICATOR CONTROL LOCATION WITH IDGHEST 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 LA-140 NA <LLD <LLD 0 (PCI/KG DRY)

CE-144 NA <LLD <LLD 0 AIR PARTICULATE GR-B 514 JO 19 19 20 CL-3 INDICATOR 0

P-CE-3 PCI/CUMETER) (462/462) (52/52) (50/50) CLINTON'S SECONDARY ACCESS ROAD c.o (6/43) (7/36) (9/43) 0.7 MILES NE OF SITE GAMMA 40 C0-60 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 RU-103 NA <LLD <LLD 0 iJ Ill ca CD

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 MEASURElv!ENT) (LLD) MEASUREMENTS AIR PARTICULATE CS-134 50 <LLD <LLD 0 (E-3 PCI/CU.METER)

CS-137 60 <LLD <LLD 0 CE-141 NA <LLD <LLD 0 CE-144 NA <LLD <LLD 0 AIR IODINE GAMMA 514 (E-3 PCI/CUMETER) I-131 70 <LLD <LLD 0 MILK I-131 19 NA <LLD 0 (PCI/LITER)

GAMMA 19 MN-54 NA NA <LLD 0 C0-58 NA NA <LLD 0 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 '~

INDICATOR CONTROL LOCAfrION 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) i, MEASUREMENTS

,.

MILK FE-59 NA NA <LLD 0 (PCIILITER)

C0-60 NA NA <LLD 0 ZN-65 NA NA <LLD 0 NB-95 NA .NA <LLD 0 ZR-95 NA NA <LLD 0 CS-134 _ 15 NA <LLD 0 CS-137 18 NA <LLD 0 "U

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IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 LA-140 15 NA <LLD 0 (PCI/LITER)

CE-144 NA NA <LLD 0

)>VEGETATION GAMMA 48

~ (PCI/KG WET) MN-54 NA <LLD <LLD 0 N

C0-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0 ZN-65 NA <LLD <LLD 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME.OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 (UNITOF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION ZR-95 NA <LLD <LLD 0 (PCI/KG WET)

I-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0

)>

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CS-137 80 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 CE-144 NA <LLD <LLD 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 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 GRASS C0-58 NA <LLD <LLD 0 (PCI/KG WET)

FE-59 NA <LLD <LLD 0 C0-60 NA <LLD <LLD 0

)>

......

I

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ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD <LLD 0 ZR-95 NA <LLD <LLD 0 I-131 60 <LLD <LLD 0

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TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE CLINTON POWER STATION, 2015 NAME OF FACILITY: CLINTON POWER STATION DOCKET NUMBER: 50-461 LOCATION OF FACILITY: DEWITT COUNTY, IL REPORTING PERIOD: 2015 '

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 GRASS CS-137 80 <LLD <LLD 0 (PCI/KG WET)

BA-140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0

)>

......

I C.J1 CE-144 NA <LLD <LLD 0 DIRECT RADIATION DLR-QUARTERLY 214 NA 23.2 21.9 25.3 CL-51 INDICATOR 0 (MILLIREM/QTR.) (210/210) (4/4) (3/3)

(17.3/28.0) (19.9/23.6) (24.3/26.3) 4.4MILESNW

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Intentionally left blank Page 50 of 138

APPENDIX 8 LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS Page 51 of 138

Intentionally left blank Page 52 of 138

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Location Location Description Distance & Direction From Site A. Surface Water Cl-13 Salt Creek Bridge on Rt. 10 (indicator) 3.6 miles SW CL-90 Discharge Flume (indicator) 0.4 miles SE CL-91 Parnell Boat Access (control) 6.1 miles ENE CL-99 North Fork Access (control) 3.5 miles NNE B. Drinking (Potable) Water CL-14 Station Plant Service Bldg (indicator) Onsite C. Well Water CL-7D Mascoutin Recreation Area (indicator) 2.3 miles ESE CL-12T DeWitt Pump House (indicator) 1.6 miles E CL-12R DeWitt Pump House (indicator) 1.6 miles E D. Milk - bi-weekly I monthly CL-116 Dement Dairy (control) 14 miles WSW E. Air Particulates I Air Iodine CL-1 Camp Quest 1.8 miles W CL-2 Clinton's Main Access Road 0.7 miles NNE CL-3 Clinton's Secondary Access Road 0.7 miles NE CL-4 Residence Near Recreation Area 0.8miles SW CL-6 Clinton's Recreation Area 0.7milesWSW CL-7 Mascoutin Recreation Area 2.3 miles SE CL-8 DeWitt Cemetery 2.2 miles E CL-11 Illinois Power Substation (control) 16 miles S CL-15 Rt. 900N Residence 0.9 miles N CL-94 Old Clinton Road 0.6 miles E F. Fish CL-19 End of Discharge Flume (indicator) 3.4 miles E CL-105 Lake Shelbyville (control) 50 miles S G. Shoreline Sediment CL-7B Clinton Lake (indicator) 2.1 miles SE CL-105 Lake Shelbyville (control) 50 miles S H. Food Products CL-114 Cisco (Control) 12.5 miles SSE CL-115 Site's Secondary Access Road 0.7 miles NE CL-117 Residence North of Site 0.9 miles N CL-118 Site's Main Access Road 0.7 miles NNE I. Grass CL-1 Camp Quest 1.8 miles W CL-2 Clinton's Main Access Road 0.7 miles NNE CL-8 DeWitt Cemetery 2.2 miles E CL-116 Pasture in Rural Kenney (control) 14 miles WSW B-1 Page 53 of 138

TABLE B-1: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Location Location Description Distance & Direction From Site J. Environmental Dosimetrv - DLR Inner Ring CL-1 1.8 miles W CL-5 0.7 miles NNE CL-22 0.6 miles NE CL-23 0.5 miles ENE CL-24 0.5 miles E CL-34 0.8 miles WNW CL-35 0.7miles NW CL-36 0.6 miles N CL-42 2.8 miles ESE CL-43 2.8 miles SE CL-44 2.3 miles SSE CL-45 2.8 miles S CL-46 2.8 miles SSW CL-47 3.3milesSW CL-48 2.3milesWSW CL-63 1.3 miles NNW Outer Ring CL-51 4.4 miles NW CL-52 4.3 miles NNW CL-53 4.3 miles E CL-54 4.6 miles ESE CL-55 4.1 miles SE CL-56 4.1 miles SSE CL-57 4.6 miles S CL-58 4.3 miles SSW CL-60 4.5 miles SW CL-61 4.5 miles WSW CL-76 4.6 miles N CL-77 4.5 miles NNE CL-78 4.8 miles NE CL-79 4.5 miles ENE CL-80 4.1 miles W CL-81 4.5milesWNW B-2 Page 54 of 138

TABLE B-1: RadiOlogical Environmental Monitoring Program - Sampling Locations, Distance and Direction, Clinton Power Station, 2015 Location Location Description Distance & Direction From Site J. Environmental Dosimetrv- DLR (cont.)

Special Interest CL-37 3.4 miles N CL-41 2.4 miles E CL-49 3.5 milesW CL-64 2.1 miles WNW CL-65 2.6 miles ENE CL-74 1.9 miles W CL-75 0.9 miles N Supplemental CL-2 0.7 miles NNE CL-3 0.7 miles NE CL-4 0.8 miles SW CL-6 0.8 miles WSW CL-7 2.3 miles SE CL-8 2.2 miles E CL-15 0.9 miles N CL-33 11.7 miles SW CL-84 0.6 miles E CL-90 0.4 miles SE CL-91 6.1 miles ENE CL-97 10.3 miles SW CL-99 3.5 miles NNE CL-114 12.5 miles SE CL-11 16 miles S B-3 Page 55 of 138

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Clinton Power Station, 2015 Sample Analysis Sampling Method Analytical Procedure Number Medium Surface Gamma Monthly composite TBE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous water compositor. Env. Inc., SPM-1 Samplino Procedure Manual Surface Tritium Quarterly composite TSE, TBE-2011 Tritium analysis in drinking water by liquid Water from a continuous scintillation water compositor.

Env. Inc., SPM-1 Sampling Procedure Manual Surface 1-131 Monthly composite TSE, TBE-2012 Radioiodine in various matrices Water from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Drinking Gross Beta Monthly composite TSE, TBE-2008 Gross Alpha and/or gross beta activity in Water from a continuous various matrices water compositor.

Env. Inc., SPM-1 Samplino Procedure Manual Drinking Gamma Monthly composite TSE, TBE-2007 Gamma emitting radioisotope analysis Water Spectroscopy from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Drinking Tritium Quarterly composite TSE, TBE-2011 Tritium analysis in drinking water by liquid Water from a continuous scintillation water compositor.

Env. Inc., SPM-1 Sampling Procedure Manual Drinking 1-131 Quarterly composite TBE, TBE-2031 Radioactive Iodine in Drinking Water Water from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Well Water Gamma Quarterly composite TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous water compositor. Env. Inc., SPM-1 Sampling Procedure Manual Well Water Tritium Quarterly composite TSE, TBE-2011 Tritium analysis in drinking water by liquid from a continuous scintillation water compositor.

Env. Inc., SPM-1 Samplino Procedure Manual Fish Gamma Semi-annual samples TBE-2007 Gamma emitting radioisotope analysis Spectroscopy collected via electroshocking or other techniaues Env. Inc., SPM-1 Samolino Procedure Manual Air Gross Beta One-week composite of TBE, TBE-2008 Gross Alpha and/or gross beta activity in Particulates continuous air various matrices sampling through glass fiber filter paper Env. Inc., SPM-1 Sampling Procedure Manual Air Gamma Quarterly composite of TSE, TBE-2007 Gamma emitting radioisotope analysis Particulates Spectroscopy each station Env. Inc., SPM-1 Samolinq Procedure Manual Air Iodine Gamma One-week composite of TSE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy continuous air sampling through Env. Inc., SPM-1 Sampling Procedure Manual charcoal filter Milk 1-131 Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices when cows are on pasture. Monthly all other times Env. Inc., SPM-1 Samolino Procedure Manual Milk Gamma Bi-weekly grab sample TBE-2007 Gamma emitting radioisotope analysis Spectroscopy when cows are on pasture. Monthly all other times Env. Inc., SPM-1 Samolina Procedure Manual B-4 Page 56 of 138

TABLE B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Clinton Power Station, 2015 Sample Analysis Sampling Method Analytical Procedure Number Medium Food Gross Beta Monthly grab June TBE, TBE-2008 Gross Alpha and/or gross beta activity in Products through September various matrices Env. Inc., SPM-1 Samolinq Procedure Manual Food Gamma Spectroscopy Monthly grab June TBE, TBE-2007 Gamma emitting radioisotopes analysis Products through September Env. Inc., SPM-1 Samolinq Procedure Manual Grass Gamma Spectroscopy Biweekly May through TBE, TBE-2007 Gamma emitting radioisotopes analysis October Env. Inc., SPM-1 Samolinq Procedure Manual DLR Optically Stimulated Quarterly DLRs Landauer Incorporated Luminescence com prised of two Dosimetry Al20 3:C Landauer Incorporated elements.

B-5 Page 57 of 138

l I N

I 15 Figure B-1 Environmental Sampling Locations Within One Mile of the Clinton Power Station, 2015 B-6 Page 58 of 138

Figure 8-2 Environmental Sampling Locations Between One and Two Miles of the Clinton Power Station, 2015 B-7 Page 59 of 138

  • Figure B-3 Environmental Sampling Locations between Two and Five Miles from the Clinton Power Station ,

2015 B-8 Page 60 of 138

Figure B-4 Environmental Sampling Locations Greater Than Five Miles of the Clinton Pov.er Station, 2015 B-9 Page 61 of 138

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APPENDIX C DATA TABLES AND FIGURES -

PRIMARY LABORATORY Page 63 of 138

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Table C-1.1 CONCENTRATIONS OF 1-131 IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-90 PERIOD 12/31/14 - 01/28/15 < 0.6 01/28/15 - 02/25/15 < 0.3 02/25/15 - 03/25/15 < 0.7 03/25/15 - 04/29/15 < 0.4 04/29/15 - 05/27/15 < 0.2 05/27/15 - 06/24/15 < 0.9 06/24/15 - 07/29/15 < 0.3 07/29/15 - 08/26/15 < 0.8 08/26/15 - 09/30/15 < 0.6 09/30/15 - 10/28/15 < 0. 7 10/28/15 - 11/25/15 < 0.8 11/25/15 - 12/30/15 < 0.6 MEAN Table C-1.2 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-90 CL-13 CL-91 CL-99 PERIOD 01/28/15 - 03/25/15 < 196 < 196 < 199 < 198 (1) 04/29/15 - 06/24/15 < 192 < 188 < 189 < 191 07/29/15 - 09/30/15 < 195 < 198 < 197 < 196 10/28/15 - 12/30/15 < 188 < 187 < 188 < 189 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1 Page 65 of 138

Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-13 01/28/15 - 01/28/15 < 6 < 6 < 12 < 6 < 12 < 6 < 11 < 6 < 6 < 26 < 9 < 36 02/25/15 - 02/25/15 <4 <4 < 8 <4 <7 < 5 < 7 <4 <4 < 21 < 5 < 33 03/25/15 - 03/25/15 < 3 <4 < 8 < 3 < 7 < 3 < 6 < 3 < 3 < 27 < 8 < 28 04/29/15 - 04/29/15 < 7 < 7 < 12 < 6 < 13 < 8 < 15 < 6 < 7 < 28 < 6 < 50 05/27/15 - 05/27/15 < 7 < 8 < 15 < 7 < 19 < 10 < 15 < 8 < 9 < 38 < 10 < 43 06/24/15 - 06/24/15 < 6 < 9 < 17 < 6 < 8 < 10 < 13 < 8 < 7 < 34 < 11 < 60 07/29/15 - 07/29/15 < 7 < 6 < 14 < 7 < 13 < 7 < 11 < 5 < 6 < 29 < 11 < 52 08/26/15 - 08/26/15 < 5 <7 < 16 < 8 < 18 < 6 < 11 < 7 < 8 < 32 < 10 < 59 09/30/15 - 09/30/15 < 7 < 6 < 13 < 8 < 12 <8 < 12 < 7 < 8 < 31 < 12 < 49 10/28/15 - 10/28/15 < 6 < 7 < 14 < 8 < 9 < 6 < 9 < 5 < 6 < 27 < 7 < 43 11/25/15 - 11/25/15 < 5 < 5 < 12 < 5 < 5 < 5 < 8 <4 < 5 < 24 <4 < 37 12/30/15 - 12/30/15 < 5 < 6 < 10 < 4 < 12 < 5 < 10 I <4 < 6 < 25 < 13 < 44 MEAN

()

I CL-90 12/31/14 - 01/28/15 < 5 < 5 < 10 < 6 < 12 < 5 < 9 < 5 < 5 < 30 < 10 < 40 N

01/28/15 - 02/25/15 <4 <4 < 7 <4 < 6 <4 < 6 < 3 <4 < 18 < 5 < 30 02/25/15 - 03/25/15 <4 < 5 < 9 < 5 < 8 <4 < 7 < 4 <4 < 28 < 12 < 31 03/25/15 - 04/29/15 < 7 <7 < 17 < 6 < 18 < 9 < 13 < 8 < 8 < 31 < 11 < 51 04/29/15 - 05/27/15 < 6 < 8 < 16 < 7 < 14 < 8 < 12 < 7 < 8 < 39 < 14 < 55 05/27/15 - 06/24/15 < 7 < 6 < 13 < 7 < 17 < 7 < 12 < 7 < 8 < 39 < 9 < 53 06/24/15 - 07/29/15 < 6 < 5 < 10 < 5 < 12 < 6 < 10 < 6 < 6 < 24 < 9 < 44 07/29/15 - 08/26/15 < 3 < 3 < 7 <4 < 5 <4 < 6 < 3 < 4 < 18 < 6 < 30 08/26/15 - 09/30/15 < 6 < 8 < 9 < 7 < 11 < 6 < 8 < 5 < 5 < 27 < 12 < 46 09/30/15 - 10/28/15 < 5 < 7 < 12 < 6 < 13 < 6 < 11 < 6 < 6 < 36 < 5 < 49 10/28/15 - 11/25/15 < 6 < 5 < 12 < 6 < 12 < 6 < 10 < 5 < 5 < 34 < 11 < 47 11/25/15 - 12/30/15 < 5 < 6 < 14 < 7 < 12 < 6 < 12 < 6 < 7 < 35 < 11 < 44 MEAN "U

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__,. THE MEAN AND lWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES w

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Table C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-91 12/31/14 - 01/28/15 < 6 < 5 < 12 <4 < 12 <7 < 8 < 5 < 6 < 28 < 11 < 45 01/28/15 - 02/25/15 < 6 < 7 < 13 < 8 < 12 < 5 < 7 < 6 < 6 < 32 <7 < 58 02/25/15 - 03/25/15 < 3 < 3 < 7 < 3 < 6 < 3 < 5 < 3 < 3 < 25 < 6 < 30 03/25/15 - 04/29/15 <6 <6 < 13 <7 < 14 < 8 < 16 < 7 < 9 < 41 < 9 < 63 04/29/15 - 05/27/15 < 6 < 7 < 10 < 5 < 12 < 6 < 8 < 5 < 6 < 24 < 8 < 41 05/27/15 - 06/24/15 < 5 < 7 < 13 <5 < 13 < 6 < 12 < 6 < 7 < 29 < 12 < 51 06/24/15 - 07/29/15 <4 <4 < 8 <4 < 8 < 5 < 8 <4 < 4 < 18 < 5 < 34 07/29/15 - 08/26/15 < 5 < 3 < 7 <4 < 11 < 5 < 9 < 5 < 5 < 23 < 8 < 38 08/26/15 - 09/30/15 < 7 < 7 < 18 < 7 < 18 < 8 < 14 < 8 < 8 < 41 < 11 < 69 09/30/15 - 10/28/15 < 6 < 8 < 12 < 8 < 12 < 6 < 12 < 6 < 8 < 30 < 14 < 41 10/28/15 - 11/25/15 < 5 < 5 < 9 <4 < 11 < 6 < 8 < 5 < 5 < 28 < 8 < 43 11/25/15 - 12/30/15 < 6 < 6 < 16 < 6 < 14 < 8 < 13 < 5 < 7 < 31 < 12 < 39 MEAN

()

I

(...) CL-99 12/31/14 - 01/28/15 < 3 < 4 < 9 < 5 < 8 < 5 < 7 < 5 < 5 < 24 < 9 < 37 01/28/15 - 02/25/15 < 6 < 6 < 9 < 5 < 10 < 6 < 9 < 5 < 6 < 28 < 9 < 45 02/25/15 - 03/25/15 < 3 < 3 < 6 < 3 < 6 < 3 < 6 <4 < 4 < 26 < 4 < 35 03/25/15 - 04/29/15 < 9 < 8 < 19 < 11 < 18 < 9 < 12 < 9 < # < 45 < 13 < 52 04/29/15 - 05/27/15 < 5 < 7 < 15 < 6 < 14 < 6 < 7 < 6 < 6 < 31 <7 < 47 05/27/15 - 06/24/15 < 6 < 6 < 13 < 8 < 17 < 9 < 15 < 8 < 8 < 31 < 14 < 41 06/24/15 - 07/29/15 < 4 < 3 < 8 < 3 < 8 <4 < 6 <4 <4 < 20 < 7 < 30 07/29/15 - 08/26/15 < 6 < 5 < 12 < 5 < 14 < 5 < 10 < 5 < 7 < 28 < 8 < 43 08/26/15 - 09/30/15 < 6 < 8 < 16 < 8 < 17 < 10 < 12 < 7 < 7 < 36 < 13 < 67 09/30/15 - 10/28/15 < 6 < 6 < 11 < 6 < 15 < 7 < 12 < 7 < 7 < 33 < 10 < 55 10/28/15 - 11/25/15 < 6 <7 < 14 < 8 < 14 <6 < 12 < 6 < 8 < 35 < 10 < 39 11/25/15 - 12/30/15 < 7 < 7 < 18 < 10 < 16 < 9 < 12 < 9 < 8 < 41 < 11 < 69 MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-11.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-14 PERIOD 12/31/14 - 01/28/15 < 1.4 01/28/15 - 02/25/15 < 1.5 02/25/15 - 03/25/15 < 1.5 03/25/15 - 04/29/15 < 1.6 04/29/15 - 05/27/15 < 1.3 05/27/15 - 06/24/15 < 1.5 06/24/15 - 07/29/15 < 1.4 07/29/15 - 08/26/15 < 1.6 08/26/15 - 09/30/15 < 1.5 09/30/15 - 10/28/15 < 1.5 10/28/15 - 11 /25/15 < 1.5 11/25/15 - 12/30/15 < 1.5 MEAN Table C-11.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-14 PERIOD 12/31/14 - 03/25/15 < 199 03/25/15 - 06/24/15 < 187 06/24/15 - 09/30/15 < 199 09/30/15 - 12/30/15 < 187 MEAN Table C-11.3 CONCENTRATIONS OF 1-131 IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-14 PERIOD 12/31/14 - 01/28/15 < 0.3 01/28/15 - 02/25/15 < 0.4 02/25/15 - 03/25/15 < 0.3 03/25/15 - 04/29/15 < 0.4 04/29/15 - 05/27/15 < 0.3 05/27/15 - 06/24/15 < 0.4 06/24/15 - 07/29/15 < 0.4 07/29/15 - 08/26/15 < 0.9 08/26/15 - 09/30/15 < 0.7 09/30/15 - 10/28/15 < 0.6 10/28/15 - 11 /25/15 < 0.7 11 /25/15 - 12/30/15 < 0.6 MEAN C-4 Page 68 of 138

Table C-11.4 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-14 12/31/14 - 01/28/15 < 4 <5 < 11 <4 < 8 < 4 < 9 <4 < 4 < 18 < 6 < 37 01/28/15 - 02/25/15 < 6 < 5 < 13 < 6 < 10 < 7 < 11 I < 5 < 6 < 27 < 7 < 48 02/25/15 - 03/25/15 < 3 <4 < 8 <4 < 7 <4 < 8 < 3 <4 < 23 < 7 < 31 03/25/15 - 04/29/15 < 8 < 8 < 18 <8 < 21 < 10 < 14 < 8 <8 < 33 < 12 < 61 04/29/15 - 05/27/15 < 5 < 6 < 9 < 6 < 9 <7 < 12 < 6 < 6 < 32 < 6 < 52 05/27/15 - 06/24/15 < 9 < 7 < 18 < 8 < 15 < 8 < 15 < 8 < 10 < 41 < 5 < 67 06/24/15 - 07/29/15 < 5 < 5 < 11 < 5 < 11 < 4 < 8 <4 < 6 < 27 < 8 < 41 07/29/15 - 08/26/15 < 7 < 8 < 15 <7 < 13 <7 < 12 < 6 < 8 < 33 < 11 < 59 08/26/15 - 09/30/15 < 5 < 5 < 14 <5 < 13 < 7 < 12 <6 < 5 < 30 < 10 < 44 09/30/15 - 10/28/15 < 5 < 6 < 11 < 6 < 11 <5 < 8 < 6 < 5 < 28 < 7 < 46 10/28/15 - 11/25/15 <4 < 4 < 9 <4 < 9 < 5 < 8 <4 < 5 < 21 < 7 < 34 11/25/15 - 12/30/15 <4 < 8 < 16 <4 < 10 < 9 < 12 < 6 < 8 < 43 < 12 < 51 MEAN

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Table C-111.1 CONCENTRATIONS OF TRITIUM IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION CL-12R CL-12T CL-70 PERIOD 03/25/15 - 03/25/15 < 182 < 181 < 180 06/24/15 - 06/24/15 < 164 < 164 < 160 09/30/15 - 09/30/15 < 185 < 187 < 186 12/30/15 - 12/30/15 < 196 < 196 < 192 MEAN C-6 Page 70 of 138

Table C-111.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION; 2015 RESULTS IN UNITS OF PCl/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 Ce-144 PERIOD CL-12R 03/25/15 < 5 <6 < 10 < 5 < 10 < 5 < 10 < 5 < 6 < 39 < 13 < 38 06/24/15 < 9 <7 < 12 < 7 < 17 < 9 < 13 < 5 < 6 < 32 < 12 < 62 09/30/15 < 8 <4 < 17 <4 < 14 < 5 < 11 ,, < 6 < 7 < 36 < 10 < 54 12/30/15 <4 < 7 < 15 <6 < 12 < 8 < 10 < 5 < 7 < 32 < 10 < 49 MEAN CL-12T 03/25/15 < 5 < 5 < 10 <4 < 9 < 5 < 8 < 5 < 5 < 32 < 8 < 37 06/24/15 < 10 < 9 < 17 < 10 < 20 < 10 < 15- < 8 < 9 < 46 < 13 < 80 09/30/15 < 5 *< 8 < 14 < 6 < 13 < 9 < 14 < 7 < 7 < 38 < 8 < 47 12/30/15 < 8 < 6 < 15 <5 < 17 < 8 < ~5 < 6 < 8 < 43 < 8 < 57 MEAN

() CL-70 03/25/15 <4 <4 < 9 < 3 < 6 <4 < 8 < 3 <4 < 23 <7 < 30 I

06/24/15 < 7 < 9 < 17 < 7 < 20 < 9 < 20 < 8 < 9 < 36 < 13 < 51

""" 09/30/15 12/30/15

< 7

< 6

< 8

< 5

<

<

18 10

<

<

5 5

<

<

12 12

< 8

<6

<

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9

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7 5

<6

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< 12

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<

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Table C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 '

RESULTS IN UNITS OF PCl/KG WET+/- 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 Ce-144 PERIOD CL-105 Bluegill 04/23/15 < 51 < 53 < 109 < 48 < 99 < 56 < 104 < 50 < 70 < 519 < 178 < 385 Carp 04/23/15 < 63 < 71 < 105 < 60 < 159 < 57 < 126 < 52 < 60 < 500 < 153 < 312 Channel Catfish 04/23/15 < 44 < 41 < 118 < 41 < 94 < 56 < 96 < 41 < 53 < 386 < 124 < 273 Largemouth Bass 04/23/15 < 102 < 98 < 228 < 83 < 205 < 115 < 188 < 91 < 87 < 841 < 194 < 524 bluegill 10/05/15 < 39 < 38 < 73 < 40 < 82 < 37 < 61 < 34 < 36 < 186 < 52 < 189 carp 10/05/15 < 46 < 50 < 97 < 49 < 98 < 49 < 79 < 47 < 46 < 237 < 74 < 200 crappie 10/05/15 < 63 < 55 < 112 < 65 < 160 < 70 < 88 < 61 < 55 < 295 < 72 < 323 largemouth bass 10/05/15 < 70 < 65 < 136 < 62 < 117 < 71 < 93 < 39 < 65 < 243 < 46 < 381 MEAN CL-19 Bluegill 04/23/15 < 73 < 85 < 217 < 101 < 163 < 87 < 155 < 79 < 79 < 802 < 142 < 499 Carp 04/23/15 < 74 < 86 < 174 < 76 < 146 < 76 < 180 < 67 < 70 < 657 < 225 < 421

() Channel Catfish 04/23/15 < 57 < 75 < 163 < 74 < 163 < 78 < 140 < 67 < 60 < 500 < 181 < 354 I Largemouth Bass 04/23/15 < 63 < 74 < 159 < 61 < 123 < 75 < 122 < 70 < 51 < 564 < 107 < 410 O:>

bluegill 10/05/15 < 56 < 82 < 156 < 61 < 132 < 75 < 120 < 83 < 62 < 389 < 130 < 392 carp 10/05/15 < 69 < 50 < 117 < 63 < 144 < 29 < 122 < 64 < 74 < 431 < 101 < 404 channel catfish 10/05/15 < 66 < 78 < 144 < 77 < 97 < 90 < 123 < 70 < 83 < 408 < 83 < 332 largemouth bass 10/05/15 < 88 < 83 < 177 < 84 < 190 < 92 < 136 < 74 < 90 < 476 < 124 < 510 MEAN

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THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES w

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Table C-V.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG DRY+/- 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 Ce-144 PERIOD CL-078 04/23/15 < 40 < 49 < 135 < 40 < 99 < 55 < 89 . < 33 < 41 < 761 < 171 < 241 10/05/15 < 69 < 63 < 140 < 80 < 108 < 68 < 136 < 60 < 72 < 336 < 69 < 322 MEAN CL-105 04/23/15 < 44 < 49 < 123 < 45 < 106 < 59 < 101 < 38 < 44 < 748 < 198 < 312 10/05/15 < 76 < 92 < 217 < 121 < 173 < 62 < 153 < 84 < 80 < 417 < 93 < 400

.

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c.v CXl THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

.,.

Table C-Vl.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION. 2015 RESULTS IN UNITS OF E-3 PCl/CU METER +/- 2 SIGMA COLLECTION GROUP I PERIOD CL-2 CL-3 CL-4 CL-6 CL-15 CL-94 12/31/14 - 01/07/15 20 +/- 4 20 +/- 5 21 +/- 5 21 +/- 5 21 +/- 5 18 +/- 4 01/07/15 - 01/14/15 19 +/- 4 20 +/- 4 20 +/- 4 18 +/- 4 20 +/- 4 16 +/- 4 01/14/15 - 01/21/15 26 +/- 5 31 +/- 5 23 +/- 5 30 +/- 5 26 +/- 5 28 +/- 5 01/21/15 - 01/28/15 13 +/- 4 14 +/- 4 14 +/- 4 11 +/- 4 14 +/- 4 14 +/- 4 01/28/15 - 02/04/15 19 +/- 4 17 +/- 4 17 +/- 4 18 +/- 4 18 +/- 4 20 +/- 5 02/04/15 - 02/11/15 29 +/- 5 28 +/- 5 31 +/- 5 25 +/- 5 27 +/- 5 24 +/- 5 02/11 /15 - 02/18/15 23 +/- 4 24 +/- 5 23 +/- 4 24 +/- 5 22 +/- 4 27 +/- 5 02/18/15 - 02/25/15 35 +/- 5 43 +/- 6 41 +/- 5 40 +/- 6 37 +/- 5 37 +/- 5 02/25/15 - 03/04/15 23 +/- 5 23 +/- 5 24 +/- 5 22 +/- 5 14 +/- 4 16 +/- 4 03/04/15 - 03/11/15 18 +/- 4 17 +/- 4 15 +/- 4 17 +/- 4 19 +/- 4 14 +/- 4 03/11/15 - 03/18/15 16 +/- 4 13 +/- 4 12 +/- 4 15 +/- 4 15 +/- 4 15 +/- 4 03/18/15 - 03/25/15 15 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 16 +/- 4 03/25/15 - 04/01/15 14 +/- 4 15 +/- 4 15 +/- 4 14 +/- 4 14 +/- 4 17 +/- 4

_04/01/15 - 04/08/15 9 +/-_4 - JJ +/- 4 _10 +/- 4 13 +/- 4 11 +/- 4 13 +/- 4 04/08/15 - 04/15/15 17 +/- 4 18 +/- 4 13 +/- 4 16 +/- 4 16 +/- 4 17 +/- 4 04/15/15 - 04/22/15 13 +/- 4 16 +/- 4 19 +/- 4 16 +/- 4 17 +/- 4 18 +/- 4 04/22/15 - 04/29/15 9+/-3 11+/-4 15 +/- 4 13 +/- 4 12 +/- 4 12 +/- 4 04/29/15 - 05/06/15 16 +/- 4 14 +/- 4 15 +/- 4 17 +/- 4 17 +/- 4 18 +/- 4 05/06/15 - 05/13/15 9 +/- 6 (1) < 9 (1) 12 +/- 4 7 +/-4 9 +/-4 9 +/-4 05/13/15 - 05/20/15 11+/-4 9+/-4 7 +/-4 9 +/-4 8+/-4 9+/-4 05/20/15 - 05/27/15 30 +/- 8 32 +/- 8 18 +/- 4 17 +/- 4 16 +/- 4 18 +/- 4 05/27/15 - 06/03/15 13 +/- 4 12 +/- 4 14 +/- 4 13 +/- 4 12 +/- 4 9 +/-4 06/03/15 - 06/10/15 16 +/- 4 16 +/- 4 20 +/- 4 22 +/- 4 18 +/- 4 17 +/- 4 06/10/15 - 06/17/15 < 23 (1) < 20 (1) 13 +/- 4 14 +/- 4 15 +/- 4 14 +/- 4 06/17/15 - 06/24/15 11+/-4 13+/-4 13 +/- 4 12 +/- 4 11 +/- 4 11 +/- 4 06/24/15 - 07/01/15 13+/-4 11+/-4 10 +/- 4 8+/-4 10 +/- 4 11 +/- 4 07/01/15 - 07/08/15 13 +/- 4 12 +/- 4 12 +/- 4 14 +/- 4 12 +/- 4 15 +/- 4 07/08/15 - 07/15/15 10+/-3 9+/-4 8 +/- 3 14 +/- 4 10 +/- 4 14 +/- 4 07/15/15 - 07/22/15 16 +/- 5 14 +/- 4 13 +/- 4 16 +/- 4 12 +/- 4 20 +/- 4 07/22/15 - 07/29/15 18 +/- 4 24 +/- 5 17 +/- 4 22 +/- 5 21 +/- 5 17 +/- 4 07/29/15 - 08/05/15 20 +/- 4 18 +/- 4 21 +/- 4 20 +/- 4 20 +/- 4 20 +/- 4 08/05/15 - 08/12/15 21 +/- 4 24 +/- 4 20 +/- 4 21 +/- 4 23 +/- 4 23 +/- 4 08/12/15 - 08/19/15 29 +/- 5 29 +/- 5 29 +/- 5 29 +/- 5 26 +/- 5 21 +/- 5 08/19/15 - 08/26/15 17 +/- 4 17 +/- 4 16 +/- 4 13 +/- 4 18 +/- 4 17 +/- 4 08/26/15 - 09/02/15 36 +/- 5 31 +/- 5 31 +/- 5 34 +/- 5 33 +/- 5 39 +/- 5 09/02/15 - 09/09/15 35 +/- 5 35 +/- 5 36 +/- 5 33 +/- 5 28 +/- 5 39 +/- 5 09/09/15 - 09/16/15 15 +/- 4 13 +/- 4 15 +/- 4 17 +/- 4 15 +/- 4 16 +/- 4 09/16/15 - 09/23/15 19 +/- 5 20 +/- 5 24 +/- 5 17 +/- 4 18 +/- 4 21 +/- 5 09/23/15 - 09/30/15 30 +/- 5 25 +/- 5 24 +/- 5 24 +/- 5 27 +/- 5 26 +/- 5 09/30/15 - 10/07/15 12 +/- 4 9 +/-4 11 +/- 4 13 +/- 4 13 +/- 4 12 +/- 4 10/07/15 - 10/14/15 22 +/- 5 21 +/- 5 21 +/- 5 27 +/- 5 21 +/- 5 25 +/- 5 10/14/15 - 10/21/15 16 +/- 4 18 +/- 4 21 +/- 4 20 +/- 4 14 +/- 4 19 +/- 4 10/21/15 - 10/28/15 17 +/- 4 21 +/- 4 20 +/- 4 21 +/- 4 19 +/- 4 20 +/- 4 10/28/15 - 11 /04/15 19 +/- 5 14 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 19 +/- 5 11 /04/15 - 11 /11 /15 25 +/- 5 27 +/- 5 20 +/- 4 24 +/- 5 18 +/- 4 21 +/- 4 11/11/15 - 11/18/15 27 +/- 5 23 +/- 4 26 +/- 5 26 +/- 5 27 +/- 5 24 +/- 4 11/18/15 - 11/25/15 17 +/- 4 16 +/- 4 19 +/- 4 18 +/- 4 16 +/- 4 15 +/- 4 11/25/15 - 12/02/15 16 +/- 4 16 +/- 4 17 +/- 4 18 +/- 4 19 +/- 4 15 +/- 4 12/02/15 - 12/09/15 34 +/- 5 33 +/- 5 37 +/- 6 37 +/- 5 35 +/- 5 33 +/- 5 12/09/15 - 12/16/15 17 +/- 5 18 +/- 5 20 +/- 5 20 +/- 5 18 +/- 5 20 +/- 5 12/16/15 - 12/23/15 22 +/- 5 28 +/- 5 19 +/- 4 25 +/- 5 24 +/- 5 20 +/- 4 12/23/15 - 12/30/15 15 +/- 4 16 +/- 4 18 +/- 4 22 +/- 4 18 +/- 4 17 +/- 4 MEAN 19 +/- 14 20 +/- 15 19 +/- 14 19 +/- 14 18 +/- 13 19 +/- 14 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-10 Page 74of138

Table C-Vl.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION. 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP II GROUP Ill PERIOD CL-1 CL-7 CL-8 CL-11 12/31/14 - 01/07/15 26 +/- 5 W+/- 4 22 +/- 5 17 +/- 4 01/07/15 - 01/14/15 19 +/- 4 17 +/- 4 19 +/- 4 19 +/- 4 01/14/15 - 01/21/15 28 +/- 5 25 +/- 5 25 +/- 5 28 +/- 5 01/21/15 - 01/28/15 13 +/- 4 9 .+/- 4 15 +/- 4 11 +/- 4 01/28/15 - 02/04/15 13 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 02/04/15 - 02/11/15 26 +/- 5 26 +/- 5 25 +/- 5 27 +/- 5 02/11/15 - 02/18/15 23 +/- 5 22 +/- 4 21 +/- 4 23 +/- 4 02/18/15 - 02/25/15 39 +/- 5 39 +/- 5 42 +/- 6 36 +/- 5 02/25/15 - 03/04/15 20 +/- 5 20 +/- 5 20 +/- 5 17 +/- 4 03/04/15 - 03/11/15 15 +/- 4 15 +/- 4 18 +/- 4 20 +/- 4 03/11/15 - 03/18/15 16 +/- 4 13 +/- 4 15 +/- 4 13 +/- 4 03/18/15 - 03/25/15 16 +/- 4 17 +/- 4 19 +/- 4 18 +/- 4 03/25/15 - 04/01/15 14 +/- 4 15 +/- 4 16 +/- 4 14 +/- 4 0<!/01/15 - 04/08/15 12 +/- 4. 11 +/- 4 11 +/- 4 11 +/- 4 04/08/15 - 04/15/15 17 +/- 4 17 +/- 4 15 +/- 4 15 +/- 4 04/15/15 - 04/22/15 19 +/- 4 14 +/- 4 20 +/- 4 17 +/- 4 04/22/15 - 04/29/15 12 +/- 4 10 +/- 4 12 +/- 4 12 +/- 4 04/29/15 - 05/06/15 16 +/- 4 17 +/- 4 19 +/- 4 17 +/- 4 05/06/15 - 05/13/15 11 +/- 4 8 +/- 4 9 +/-4 8+/-4 05/13/15 - 05/20/15 9+/-4 8 +/- 4 10 +/- 4 7 +/- 4 05/20/15 - 05/27/15 14 +/- 4 13 +/- 4 18 +/- 4 17 +/- 4 05/27/15 - 06/03/15 12 +/- 4 9 +/- 4 8 +/-4 13 +/- 4 06/03/15 - 06/10/15 16 +/- 4 (1) 19 +/- 4 18 +/- 4 06/10/15 - 06/17/15 13 +/- 4 12 +/- 4 16 +/- 4 14 +/- 4 06/17/15 - 06/24/15 13 +/- 4 11 +/- 4 12 +/- 4 15 +/- 4 06/24/15 - 07/01/15 10 +/- 4 10 +/- 4 12 +/- 4 13 +/- 4 07/01/15 - 07/08/15 10 +/- 4 11 +/- 4 13 +/- 4 11 +/- 4 07/08/15 - 07/15/15 10 +/- 4 8 +/- 3 10 +/- 4 9 +/- 3 07/15/15 - 07/22/15 12 +/- 4 15 +/- 4 15 +/- 4 17 +/- 4 07/22/15 - 07/29/15 22 +/- 5 19 +/- 4 20 +/- 4 20 +/- 4 07/29/15 - 08/05/15 21 +/- 4 19 +/- 4 19 +/- 4 16 +/- 4 08/05/15 - 08/12/15 19 +/- 4 22 +/- 4 25 +/- 4 19 +/- 4 08/12/15 - 08/19/15 28 +/- 5 26 +/- 5 29 +/- 5 28 +/- 5 08/19/15 - 08/26/15 14 +/- 4 14 +/- 4 < 37 (1) 18 +/- 4 08/26/15 - 09/02/15 33 +/- 5 28 +/- 5 37 +/- 7 34 +/- 5 09/02/15 - 09/09/15 35 +/- 5 32 +/- 5 38 +/- 5 34 +/- 5 09/09/15 - 09/16/15 17 +/- 4 11 +/- 4 16 +/- 4 18 +/- 4 09/16/15 - 09/23/15 18 +/- 4 17 +/- 4 21 +/- 5 20 +/- 5 09/23/15 - 09/30/15 25 +/- 5 24 +/- 5 22 +/- 4 25 +/- 5 09/30/15 - 10/07/15 15 +/- 4 14 +/- 4 14 +/- 4 11 +/- 4 10/07/15 - 10/14/15 22 +/- 5 27 +/- 5 22 +/- 5 23 +/- 5 10/14/15 - 10/21/15 17 +/- 4 15 +/- 4 20 +/- 4 18 +/- 4 10/21/15 - 10/28/15 20 +/- 4 6 +/- 3 21 +/- 4 19 +/- 4 10/28/15 - 11/04/15 22 +/- 5 20 +/- 5 14 +/- 4 24 +/- 5 11/04/15 - 11/11/15 22 +/- 4 24 +/- 4 22 +/- 4 23 +/- 4 11/11/15 - 11/18/15 21 +/- 4 21 +/- 4 22 +/- 4 20 +/- 4 11/18/15 - 11/25/15 15 +/- 4 16 +/- 4 14 +/- 4 16 +/- 4 11/25/15 - 12/02/15 17 +/- 4 17 +/- 4 16 +/- 4 17 +/- 4 12/02/15 - 12/09/15 36 +/- 5 35 +/- 5 30 +/- 5 32 +/- 5 12/09/15 - 12/16/15 17 +/- 5 15 +/- 4 17 +/- 5 19 +/- 5 12/16/15 - 12/23/15 26 +/- 5 24 +/- 5 21 +/- 5 23 +/- 5 12/23/15 - 12/30/15 17 +/- 4 17 +/- 4 19 +/- 4 17 +/- 4 MEAN 19 +/- 14 17 +/- 14 19 +/- 14 19 +/- 13 THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11 Page 75 of 138

Table C-Vl.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - INTERMEDIATE DISTANCE LOCATIONS GROUP Ill - CONTROL LOCATIONS COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/-

PERIOD 2SD PERIOD 2SD PERIOD 2SD 12/31/14 - 01/28/15 11 31 20 +/- 11 12/31/14 - 01/28/15 9 28 19 +/- 11 I

12/31/14 - 01/28/15 11 28 19 +/- 14 01 /28/15 - 02/25/15 17 I 43 27 +/- 16 01 /28/15 - 02/25/15 13 42 26 +/- !9 01/28/15 - 02/25/15 16 36 26 +/- 17 02/25/15 - 04/01/15 12 24 16 +/- 6 02/25/15 - 04/01 /15 13 20 17 +/- 5 02/25/15 - 04/01/15 13 20 16 +/- 5 04/01 /15 - 04/29/15 9 19 14 +/- 6 04/01/15 - 04/29/15 10 20 14 +/- 7 04/01/15 - 04/29/15 11 17 14 +/- 6 04/29/15 - 06/03/15 7 32 14 +/- 12 04/29/15 - 06/03/15 8 19 12 +/- 8 04/29/15 - 06/03/15 7 17 12 +/- 9 06/03/15 - 07/01/15 8 22 14 +/- 7 06/03/15 - 07/01/15 10 19 13 +/- 6 06/03/15 - 07/01/15 13 18 15 +/- 4 07/01 /15 - 07129/15 8 24 15 +/- 8 07/01/15 - 07/29/15 . 8 22 14 +/- 9 07/01/15 - 07/29/15 9 20 14 +/- 10 07/29/15 - 09/02/15 13 39 24 +/- 13 07/29/15 - 09/02/15 14 37 24 +/- 14 07/29/15 - 09/02/15 16 34 23 +/- 15 09/02/15 - 09/30/15 13 39 24 +/- 15 09/02/15 - 09/30/15 11 38 23 +/- 16 09/02/15 - 09/30/15 18 34 24 +/- 14 09/30/15 - 10/28/15 9 27 18 +/- 9 09/30/15 - 10/28/15 6 27 18 +/- 11 09/30/15 - 10/28/15 11 23 18 +/- 10 10/28/15 - 12/02/15 14 27 20 +/- 8 10/28/15 - 12/02/15 14 24 19 +/- 7 10/28/15 - 12/02/15 16 24 20 +/- 8 12/02/15 - 12/30/15 15 37 24 +/- 15 12/02/15 - 12/30/15 15 36 23 +/- 15 12/02/15 - 12/30/15 17 32 23 +/- 13

()

I 12/31/14 - 12/30/15 7 43 19 +/- 14 12/31/14 - 12/30/15 6 42 18 +/- 14 12/31/14 - 12/30/15 7 36 19 +/- 13

-"

N i*

I

"O Dl co CD

""-.!

-

())

0

_,..

(J.)

co

I*

Table C-Vl.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTl,CULATE " SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA

'

SITE COLLECTION Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-13'7* Ce-141 Ce-144 PERIOD :1.

CL-1 12/31/14 - 04/01/15 <2 <6 < 8 < 7 < 32 < 4 <3 ~; < 9 < 13 04/01/15 - 07/01/15 < 3 <4 < 7 <5 < 23 < 3 < 2 'i' <7 < 12 07/01/15 - 09/30/15 < 3 <3 < 5 < 3 < 21 < 2 <2 .<5 < 10

  • 09/30/15 - 12/30/15 < 5 <4 < 9 < 5 < 34 <4 <4 < 6 < 14

MEAN - "'

CL-11 12/31/14 - 04/01/15 <3 < 3 < 6 < 6 < 18 <3 <2 < 7 < 12 04/01/15 - 07/01/15 <2 < 5 < 9 < 8 < 32 < 4 <4 < 10 < 17 07/01/15 - 09/30/15 < 2 <3 < 6 <4 < 21 < 2 < 2 *. < 5 < 9 09/30/15 - 12/30/15 < 5 <4 < 8 <5 < 36 <4 <4 ~' .

!  !

< 6 < 15 MEAN

() CL-15 12/31/14 - 04/01/15 < 6 < 9 < 10 < 8 < 46 < 4 < 5 *i: < 12 < 15

......

I 04/01/15 - 07/01/15 < 3 < 2 < 6 <4 < 18 < 3 < 3 '.

" < 5 < 11 VJ 07/01/15 < 3 < 5 < 16

- 09/30/15 < 3 < 7 < 25 < 3 < 3 < 8 09/30/15 - 12/30/15 <2 < 3 < 5 < 3 < 25 < 2 <2 < 5 < 12

i~

MEAN - ".

CL-2 12/31/14 - 04/01/15 < 5 < 3 < 6 <4 < 17 < 3 <2 < 8 < 13 04/01/15 - 07/01/15 < 2 < 3 <4 <4 < 16 < 3 <2 ; < 6 < 11 07/01/15 - 09/30/15 < 3 < 3 <5 <4 < 23 < 3 < 3 '< 6 < 11 09/30/15 - 12/30/15 < 3 < 3 <5 < 4 < 26 < 2 <3 *

('

I'

<4 < 11 MEAN

i CL-3 12/3.1/14 - 04/01/15 < 8 < 9 < 15 < 10 < 37 <5 < 5 < 12 < 17 04/01/15 - 07/01/15 < 3 <4 < 8 < 6 < 21 <3 < 3 < 7 < 12

"'C 07/01/15 - 09/30/15 < 3 <4 < 6 <4 < 25 < 3 < 3 < 5 < 10 Dl (C 09/30/15 - 12/30/15 <4 <4 < 6 < 5 < 21 <4 < 3 . < 6 < 16

\*

CD *::

---1 !1

-

-

---1 MEAN !I*

0

_,,,

c,j 'io CXl :r THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

,,'*

.r

"

Table C-Vl.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATiON, 2015 l'

.r RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA i'

,,

SITE COLLECTION Co-60 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 PERIOD CL-4 12/31/14 - 04/01/15 <5 <4 < 10 < 7 < 24 < 3 < 3 < 9 < 17

04/01/15 07/01/15 < 3 <4 <6 < 5 < 23 < 2 < 2 ,, < 6 < 10 07/01/15 - 09/30/15 <2 <4 < 6 < 3 < 18 <2 < 2. < 5 < 10 09/30/15 - 12/30/15 <2 <2 <4 < 3 < 18 <2 < 2 <4 < 8 MEAN  ;

CL-6 12/31/14 04/01/15 < 3 < 6 < 13 < 10 < 42 < 5 < 5 < 15 < 23

,.

04/01/15 - 07/01/15 < 3 <4 <4 <4 < 21 < 3 < 2 ,,,.. < 7 < 10 07/01/15 - 09/30/15 <4 <6 < 8 < 5 < 33 <4 <4 < 6 < 10

  • ).

09/30/15 12/30/15 <2 < 3 <3 <3 < 20 <2 < 2 <4 < 9

  • .

.;i MEAN - ,,

"*

() CL-7 12/31/14 - 04/01/15 <4 <4 < 8 <6 < 26 < 3 <3 ,, < 6 < 14

....

~

I 04/01/15 - 07/01/15 <4 <6 < 11 < 9 < 37 <4 <4

.!*

< 10 < 14 07/01/15 - 09/30/15 < 3 <4 < 6 <4 < 24 < 3 <2 < 7 < 15 09/30/15 - 12/30/15 < 3 < 3 < 6 < 3 ' <' 19 < 3 <2 < 5 < 10 MEAN - J'..

I*!

1*

CL-8 12/31/14 - 04/01/15 < 4 < 5 < 9 < 7 < 21 <3 < 3 < 10 < 16 04/01/15 - 07/01/15 < 3 <4 < 7 < 5 < 25 < 3 < 2 < 7 < 13 07/01/15 - 09/30/15 < 3 <6 < 11 < 6 < 38 <4 < 3 < 10 < 23 09/30/15 - 12/30/15 < 3 < 3 <4 < 3' < 21 <2 < 2 < 5 < 12 MEAN CL-94 12/31/14 - 04/01/15 < 3 <5 < 8 < 7 < 29 <4 < 3 *, < 10 < 14 04/01/15 - 07/01/15 < 2 < 2 < 4 < 3 < 17 < 1 < 1 <4 < 7

"

-a 07/01/15 - 09/30/15 < 2 < 2 < 5 <3 < 20 <2 < 2 < 6 < 10 ru 09/30/15 - 12/30/15 < .2 <2 < 5 <4 < 25 <2 < 3 "" <4 < 12 cc CD

-.J

-

co 0

......

w co MEAN THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES "

,,fl

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP I PERIOD CL-2 CL-3 CL-4 CL-6 CL-15 CL-94 12/31/14 - 01/07/15 < 38 < 38 < 37 < 38 < 43 < 43 01/07/15 - 01/14/15 < 60 < 60 < 60 < 62 < 63 < 64 01/14/15 - 01/21/15 < 40 < 41 < 40 < 40 < 16 < 37 01/21/15 - 01/28/15 < 33 < 33 < 34 < 33 < 60 < 33 01 /28/15 - 02/04/15 < 41 < 44 < 42 < 43 < 52 < 52 02/04/15 - 02/11 /15 < 38 < 39 < 39 < 39 < 32 < 18 02/11/15 - 02/18/15 < 69 < 69 < 68 < 69 < 66 < 65 02/18/15 - 02/25/15 < 54 < 54 < 54 < 55 < 45 < 45 02/25/15 - 03/04/15 < 23 < 24 < 23 < 23 < 22 < 22 03/04/15 - 03/11/15 < 58 < 61 < 59 < 61 < 44 < 44 03/11/15 - 03/18/15 < 19 < 47 < 47 < 47 < 34 < 44 03/18/15 - 03/25/15 < 39 < 40 < 39 < 40 < 52 < 52 03/25/15 - 04/01/15 < 44 < 17 < 45 < 45 < 37 < 36 04/01/15 - 04/08/15 < 53 < 56 < 54 < 54 < 56 < 56 04/08/15 - 04/15/15 < 64 < 64 < 64 < .60 < 26 < 25

. 04/15/15 - 04/22/15 < 58 .. < 59 <"58 < *58- ** < 63 < 62 04/22/15 - 04/29/15 < 41 < 44 < 42 < 23 < 20 < 44 04/29/15 - 05/06/15 <44 <45 < 42 < 42 < 53 < 52 05/06/15 - 05/13/15 < 33.~ (1) < 31 (1) < 48 < 47 < 48 < 47 05/13/15 - 05/20/15 < 64 < 65 < 62 < 63 < 36 < 37 05/20/15 - 05/27/15 < 46 < 46 < 25 < 20 < 28 < 27 05/27/15 - 06/03/15 < 66 < 69 < 67 < 66 < 68 < 68 06/03/15 - 06/10/15 < 69 < 68 < 67 < 40 < 66 < 65 06/10/15 - 06/17/15 < 88 (1) < 77 (1) < 38 < 15 < 40 < 18 06/17/15 - 06/24/15 < 58 < 60 < 58 < 23 < 64 < 64 06/24/15 - 07/01/15 < 19 < 55 < 52 < 52 < 44 < 44 07/01/15 - 07/08/15 < 61 < 26 < 64 < 62 < 23 < 59 07/08/15 - 07/15/15 < 53 < 56 < 56 < 56 < 47 < 46 07/15/15 - 07/22/15 < 35 < 61 < 59 < 59 < 61 < 58 07/22/15 - 07/29/15 < 30 < 31 < 12 < 31 < 37 < 37 07/29/15 - 08/05/15 < 26 < 63 < 64 < 63 < 53 < 53 08/05/15 - 08/12/15 < 47 < 50 < 20 < 50 < 34 < 33 08/12/15 - 08/19/15 < 31 < 32 < 31 < 12 < 37 < 39 08/19/15 - 08/26/15 < 45 < 45 < 18 < 45 < 49 < 46 08/26/15 - 09/02/15 < 24 < 59 < 58 < 58 < 38 < 39 09/02/15 - 09/09/15 < 34 < 35 < 34 < 44 < 34 < 34 09/09/15 - 09/16/15 < 37 < 37 < 37 < 49 < 42 < 41 09/16/15 - 09/23/15 < 44 < 46 < 43 < 44 < 52 < 54 09/23/15 - 09/30/15 < 43 < 44 < 43 < 43 < 56 < 56 09/30/15 - 10/07/15 < 62 < 63 < 62 < 24 < 59 < 61 10/07/15 - 10/14/15 < 63 < 63 < 61 < 63 < 54 < 55 10/14/15 - 10/21/15 < 64 < 67 < 67 < 28 < 15 < 39 10/21/15 - 10/28/15 < 30 < 31 < 30 < 30 < 49 < 48 10/28/15 - 11/04/15 < 63 < 64 < 62 < 64 < 40 < 41 11/04/15 - 11/11/15 < 68 < 69 < 69 < 69 < 55 < 55 11/11/15 - 11/18/15 < 45 < 47 < 47 < 48 < 51 < 49 11/18/15 - 11/25/15 < 67 < 68 < 67 < 65 < 65 < 65 11/25/15 - 12/02/15 < 36 < 35 < 35 < 35 < 39 < 38 12/02/15 - 12/09/15 < 55 < 54 < 54 < 37 < 14 < 37 12/09/15 - 12/16/15 < 59 < 59 < 59 < 55 < 23 < 56 12/16/15 - 12/23/15 < 54 < 54 < 54 < 53 < 55 < 54 12/23/15 - 12/30/15 < 49 < 48 < 47 < 46 < 47 < 45 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-15 Page 79 of 138

Table C-Vll.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF E-3 PCl/CU METER+/- 2 SIGMA COLLECTION GROUP II I GROUP Ill PERIOD CL-1 CL-7 CL-8 CL-11 12/31/14 - 01/07/15 < 15 < 18 < 44 < 43 01/07/15 - 01/14/15 < 34 < 34 < 65 < 63 01/14/15 - 01/21/15 < 15 < 37 < 37 < 37 01/21/15 - 01/28/15 < 18 < 60 < 60 < 60 01/28/15 - 02/04/15 < 23 < 27 < 51 < 50 02/04/15 - 02/11/15 < 16 < 32 < 32 < 32 02/11/15 - 02/18/15 < 27 < 27 < 66 < 66 02/18/15 - 02/25/15 < 24 < 16 < 47 < 45 02/25/15 - 03/04/15 < 10 < 8 < 22 < 22 03/04/15 - 03/11 /15 < 22 < 18 < 43 < 43 03/11/15 - 03/18/15 < 47 < 56 < 35 < 36 03/18/15 - 03/25/15 < 17 < 27 < 51 < 51 03/25/15 - 04/01/15 < 44 < 20 < 36 < 35 04/01/15 - 04/08/15 < 21 < 24 < 57 < 56 04/08/15 - 04/15/15 < 64 < 60 < 58 < 60 04/15/15 - 04/22/15 "< 25 < 22 < 65 --- < 63 04/22/15 - 04/29/15 < 43 < 45 < 44 < 44 04/29/15 - 05/06/15 < 44 < 42 < 42 < 53 05/06/15 - 05/13/15 < 48 < 19 < 47 < 47 05/13/15 - 05/20/15 < 63 < 60 < 37 < 37 05/20/15 - 05/27/15 < 25 < 20 < 8 < 20 05/27/15 - 06/03/15 < 68 < 67 < 67 < 67 06/03/15 - 06/10/15 < 69 (1) < 15 < 25 06/10/15 - 06/17/15 < 39 < 43 < 41 < 44 06/17/15 - 06/24/15 < 60 < 27 < 64 < 62 06/24/15 - 07/01/15 < 51 < 24 < 44 < 44 07/01/15 - 07/08/15 < 65 < 59 < 58 < 60 07/08/15 - 07/15/15 < 23 < 16 < 46 < 45 07/15/15 - 07/22/15 < 59 < 60 < 30 < 59 07/22/15 - 07/29/15 < 31 < 37 < 36 < 15 07/29/15 - 08/05/15 < 63 < 54 < 52 < 23 08/05/15 - 08/12/15 < 51 < 13 < 34 < 34 08/12/15 - 08/19/15 < 31 < 16 < 37 < 37 08/19/15 - 08/26/15 < 46 < 47 < 170 (1) < 48 08/26/15 - 09/02/15 < 58 < 15 < 54 < 37 09/02/15 - 09/09/15 < 35 < 44 < 42 < 33 09/09/15 - 09/16/15 < 38 < 48 < 49 < 42 09/16/15 - 09/23/15 < 17 < 23 < 53 < 53 09/23/15 - 09/30/15 < 17 < 24 < 55 < 55 09/30/15 - 10/07/15 < 61 < 24 < 60 < 59 10/07/15 - 10/14/15 < 25 < 22 < 54 < 54 10/14/15 - 10/21/15 < 66 < 39 < 39 < 39 10/21/15 - 10/28/15 < 12 < 50 < 20 < 48 10/28/15 - 11/04/15 < 27 < 20 < 43 < 41 11/04/15 - 11/11/15 < 27 < 21 < 55 < 55 11/11/15 - 11/18/15 < 26 < 20 < 50 < 50 11/18/15 - 11/25/15 < 29 < 33 < 64 < 64 11/25/15 - 12/02/15 < 14 < 40 < 15 < 38 12/02/15 - 12/09/15 < 54 < 21 < 36 < 36 12/09/15 - 12/16/15 < 58 < 22 < 56 < 56 12/16/15 - 12/23/15 < 21 < 23 < 54 < 55 12/23/15 - 12/30/15 < 19 < 44 < 46 < 18 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16 Page 80 of 138

Table C-Vlll.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA CONTROL FARM COLLECTION CL-116 PERIOD 01/28/15 < 0.3 02/25/15 <: 0.3 03/25/15 < 0.6 04/29/15 < 0.1 OS/13/15 < 0.9 05/27/15 < 0.5 06/10/15 < 0.9 06/24/15 < 0.5 07/08/15 < 0.8 07/22/15 < 0.4 08/05/15 < 0.6 08/19/15 < 0.7

. *-*- -- 09/02/15 - -. -< 0.8_- ___ - -" .. .,...- *-- ----~- ---- >.

--

09/16/15 < 0.6 09/30/15 < 0.8 10/14/15 < 0.6 10/28/15 < 0.6 11/25/15 < 0.9 12/30/15 < 1.0 MEAN C-17 Page 81 of 138

Table C-Vlll.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA SITE COLLECTION K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Ce-144

"'

PERIOD CL-116 01/28/15 1295 +/- 138 < 6 < 6 < 15 < 7 < 13 < 6 .< 9 < 5 < 6 < 30 < 8 < 34 02/25/15 1426 +/- 167 < 6 < 7 < 14 < 7 < 20 < 7 < 11 < 6 < 6 < 28 < 10 < 45 03/25/15 1007 +/- 141 < 5 < 5 < 15 < 6 < 12 < 6 '< 9 < 5 < 6 < 28 < 8 < 35 04/29/15 05/13/15 1345 1277

+/- 149

+/- 123

< 5

< 8

< 6

< 8

< 16

< 19

< 7

< 8

< 12

< 21

< 5

< 9

> 11

< 16

< 5

< 9

< 6

< 9

< 27

< 47

< 9

< 11

< 41

< 65 05/27/15 1203 +/- 205 < 11 < 7 < 18 < 9 < 19 < 9 < 17 < 9 < 9 < 36 < 11 < 47 06/10/15 1282 +/- 211 < 9 < 8 < 26 < 7 < 23 < 9  ; < 13 < 7 < 8 < 56 < 9 < 64 06/24/15 1378 +/- 197 < 9 < 9 < 20 < 11 < 21 < 10 i < 17 < 9 < 10 < 42 < 15 < 48 07/08/15 1344 +/- 168 < 6 < 6 < 18 < 9 < 17 < 6 < 9 < 5 < 7 < 28 < 5 < 42 07/22/15 1242 +/- 158 < 6 < 7 < 18 < 8 < 18 < 6  : < 13 < 7 < 8 < 32 < 9 < 44 08/05/15 1464 +/- 217 < 9 < 10 < 16 < 9 < 23 < 9 ', < 18 < 9 < 10 < 40 < 13 < 48 08/19/15 1025 +/- 195 < 9 < 8 < 14 < 10 < 23 < 9 < 17 < 9 < 10 < 35 < 10 < 68

() 09/02/15 1490 +/- 233 < 11 < 7 < 22 < 8 < 21 < 10 < 16 < 9 < 9 < 42 < 11 < 79 I

...... 09/16/15 1158 +/- 170 < 7 < 8 < 20 < 8 < 19 < 9 < 16 < 8 < 8 < 37 < 10 < 68 co 09/30/15 1187 +/- 211 < 9 < 9 < 19 < 9 < 21 < 10 < 18 < 9 < 10 < 46 < 13 < 56 10/14/15 1107 +/- 174 < 7 < 8 < 20 < 9 < 22 < 8 < 14 < 8 < 8 < 33 < 10 < 49 10/28/15 1159 +/- 141 < 7 < 6 < 12 < 6 < 18 < 5 < 11 < 7 < 6 < 25 < 9 < 48 11/25/15 1296 +/- 157 < 7 < 7 < 17 < 7 < 21 < 8 < 11 < 7 < 8 < 35 < 12 < 49 12/30/15 1445 +/- 180 < 8 < 7 < 15 < 8 < 16 < 9 < 15 < 7 < 8 < 36 < 10 < 61 MEAN 1270 +/- 282 "U

[l) cc CD OJ

-

N 0

....>.

(,,)

OJ

Table C-IX.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-114 06/24/15 Cabbage < 6 < 6 < 15 < 6 < 13 < 6 < 10 .< 18 < 6 < 6 < 41 < 11 < 37 06/24/15 Lettuce < 16 < 20 < 38 < 19 < 39 < 18 < 31 < 60 < 15 < 17 < 109 < 15 < 117 06/24/15 Swiss Chard < 18 < 18 < 42 < 17 < 39 < 20 < 32 < 59 < 17 < 19 < 125 < 43 < 86 07/29/15 Cabbage < 9 < 11 < 23 < 9 < 19 < 11 < 17 < 60 < 9 < 10 < 101 < 22 < 68 07/29/15 Lettuce <6 <7 < 18 < 6 < 15 <7 < 13 < 36 < 6 <6 < 60 < 16 < 40 07/29/15 Swiss Chard < 11 < 13 < 33 < 12 < 29 < 13 < 23 < 59 < 10 < 11 < 113 < 35 < 52 08/26/15 Cabbage < 31 < 33 < 80 < 37 < 75 < 30 < 47 1< 50 < 30 < 37 < 170 < 49 < 166 08/26/15 Lettuce < 18 < 26 < 49 < 25 < 47 < 24 < 43 :1 < 49 < 22 < 26 < 120 < 27 < 173 08/26/15 Swiss Chard < 42 < 37 < 86 < 39 < 82 < 43 < 57 '< 59 < 34 < 26 < 167 < 49 < 228 09/30/15 Cabbage < 23 < 24 < 54 < 20 < 51 < 20 < 40 < 46 < 22 < 23 < 105 < 36 < 149 09/30/15 Kale < 23 < 26 < 61 < 23 < 59 < 25 < 42  :< 50 < 24 < 27 < 123 < 24 < 179 09/30/15 Swiss Chard < 27 < 39 < 107 < 40 < 101 < 41 < 59 < 59 < 34 < 38 < 156 < 44 < 244 MEAN CL-115 06/24/15 Cabbage < 14 < 14 < 33 < 15 < 27 < 16 < 22 .< 49 < 15 < 14 < 99 < 30 < 86 06/24/15 Lettuce < 16 < 18 < 36 < 18 < 36 < 19 < 29 < 51 < 13 < 17 < 109 < 26 < 91

() 06/24/15 Swiss Chard < 14 < 17 < 31 < 17 < 34 < 16 < 30 < 54 < 14 < 16 < 107 < 27 < 105

......

I 07/29/15 Cabbage < 8 < 8 < 21 < 7 < 18 < 10 < 15 .< 57 < 8 < 8 < 90 < 23 < 57 CD 07/29/15 Lettuce < 6 < 7 < 17 < 6 < 15 < 7 < 12 .< 34 < 5 < 6 < 62 < 15 < 37 07/29/15 Swiss Chard <7 < 8 < 18 < 7 < 16 < 8 < 13 < 39 < 6 < 7 < 67 < 20 < 47 08/26/15 Cabbage < 34 < 34 < 78 < 34 < 94 < 33 < 65 < 59 < 34 < 35 < 193 < 49 < 236 08/26/15 Lettuce < 26 < 26 < 68 < 34 < 68 < 31 < 46 .< 46 < 22 < 28 < 116 < 32 < 160 08/26/15 Swiss Chard < 30 < 35 < 80 < 31 < 81 < 38 < 52 '< 60 < 30 < 36 < 169 < 47 < 252 09/30/15 Cabbage < 29 < 19 < 65 < 26 < 57 < 28 < 47 "< 45 < 21 < 26 < 140 < 40 < 153 09/30/15 Kale < 20* < 32 < 67 < 29 < 65 < 27 < 48 < 55 < 27 < 25 < 132 < 44 < 204 09/30/15 Swiss Chard < 21 < 25 < 59 < 28 < 38 < 23 < 50 < 42 < 24 < 20 < 124 < 13 < 143 MEAN i

'..

"

'

"'U Ill cc CD

())

-

w 0

-"

w

())

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

Table C-IX.1 CONCENTRATIONS OF GAMMA EMITTERS IN VEGETATION SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-117 06/24/15 Cabbage < 13 < 11 < 26 < 11 < 29 < 14 < 22 < 39 < 11 < 12 < 86 < 21 < 77 06/24/15 Lettuce < 12 < 16 <"34 < 13 < 34 < 16 < 28 .1.< 37 < 13 < 14 < 101 < 26 < 68 06/24/15 Swiss Chard < 15 < 19 < 39 < 17 < 36 < 18 < 32 '< 51 < 16 < 17 < 117 < 39 < 93 07/29/15 Cabbage < 10 < 12 < 26 < 10 < 23 < 12 < 20  :< 55 < 9 < 10 < 96 < 29 < 57 07/29/15 Lettuce <4 < 5 < 12 < 4 < 10 < 5 <9 < 27 <4 < 4 < 43 < 13 < 25 07/29/15 Swiss Chard < 6 < 7 < 16 < 6 < 14 < 7 < 12 < 39 < 6 < 6 < 65 < 17 < 40 08/26/15 Cabbage < 32 < 33 < 67 < 26 < 68 < 33 < 59 < 56 < 29 < 29 < 170 < 52 < 209 08/26/15 Lettuce < 33 < 31 < 81 < 37 < 80 < 39 < 63 < 51 < 39 < 32 < 160 < 30 < 219 08/26/15 Swiss Chard < 24 < 23 < 46 < 18 < 39 < 29 < 37 < 43 < 20 < 25 < 116 < 32 < 178 09/30/15 Cabbage < 27 < 24 < 54 < 26 < 48 < 27 < 49 < 41 < 21 < 24 < 108 < 23 < 142 09/30/15 Kale < 24 < 23 < 51 < 23 < 51 < 26 < 39 < 41 < 23 < 20 < 104 < 25 < 154 09/30/15 Swiss Chard < 31 < 29 < 75 < 32 < 81 < 34 < 60 < 58 < 26 < 30 < 145 < 51 < 212 MEAN CL-118 06/24/15 Cabbage < 17 < 20 < 36 < 18 < 39 < 20 < 32 < 60 < 17 < 20 < 130 < 35 < 86 06/24/15 Lettuce < 15 < 17 < 37 < 16 < 35 < 16 < 34 < 44 < 14 < 16 < 100 < 36 < 89

() 06/24/15 Swiss Chard < 15 < 19 < 38 < 18 < 27 < 16 < 33 < 51 < 13 < 15 < 110 < 38 < 97 I

N 07/29/15 Cabbage < 8 < 9 < 22 < 8 < 19 < 10 < 16 < 54 < 7 <8 < 91 < 22 < 57 0 07/29/15 Lettuce < 6 < 6 < 17 < 6 < 15 <7 < 12 < 39 < 5 < 6 < 64 < 16 < 37 07/29/15 Swiss Chard < 8 < 8 < 25 < 9 < 22 < 11 < 18 < 55 < 7 < 9 < 92 < 22 < 55 08/26/15 Cabbage < 18 < 21 < 53 < 22 < 56 < 23 < 41 < 37 < 22 < 19 < 123 < 26 < 133 08/26/15 Lettuce < 40 < 33 < 77 < 33 < 87 < 43 < 53 < 59 < 37 < 38 < 173 < 30 < 196 08/26/15 Swiss Chard < 25 < 23 < 65 < 35 < 71 < 31 < 49 < 42 < 21 < 31 < 115 < 28 < 168 09/30/15 Cabbage < 23 < 22 < 54 < 28 < 49 < 24 < 44 < 44 < 22 < 26 < 108 < 34 < 152 09/30/15 Kale < 26 < 22 < 55 < 27 < 49 < 26 < 43 . < 42 < 21 < 25 < 110 < 25 < 143 09/30/15 Swiss Chard < 27 < 21 < 73 < 33 < 75 < 32 < 65 . < 56 < 29 < 34 < 150 < 40 < 213 MEAN

""O Ol cc CD Ol

.j:>.

-0

.......

(,.)

Ol THE MEAN AND TWO STANDARD DEVIATION ARE CALCULATED USING THE POSITIVE VALUES

Table C-IX.2 CONCENTRATIONS OF GAMMA EMITTERS IN GRASS SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-01 05/13/15 < 13 < 15 < 34 < 15 < 32 < 15 < 23 < 43 < 12 < 14 < 81 < 24 < 82 05/27/15 < 16 < 17 < 37 < 20 < 37 < 17 < 31 < 35 < 15 < 16 < 90 < 26 < 104 06/10/15 < 29 < 29 < 64 < 24 < 72 < 29 < 41 < 44 < 24 < 28 < 129 < 42 < 127 06/24/15 < 10 < 12 < 26 < 9 < 24 < 11 < 21 < 53 < 10 < 11 < 93 < 23 < 86 07/08/15 < 13 < 13 < 30 < 14 < 33 < 13 < 24 < 23 < 12 < 14 < 58 < 17 < 93 07/22/15 . < 15 < 14 < 29 < 14 < 34 < 16 < 22 < 26 < 12 < 15 < 73 < 15 < 103 08/05/15 < 11 < 13 < 30 < 12 < 27 < 13 < 23 < 49 < 10 < 12 < 91 < 29 < 71 08/19/15 < 35 < 29 < 64 < 26 < 70 < 27 < 52 < 39 < 28 < 29 < 144 < 20 < 163 09/02/15 < 38 < 38 < 66 < 34 < 73 < 36 < 59 < 59 < 31 < 32 < 159 < 51 < 174 09/16/15 < 22 < 24 < 45 < 22 < 48 < 22 < 35 < 41 < 21 < 22 < 102 < 26 < 155 09/30/15 < 25 < 27 < 61 < 29 < 70 < 30 < 52 < 55 < 27 < 30 < 139 < 37 < 212 10/14/15 < 28 < 28 < 69 < 36 < 72 < 29 < 48 < 50 < 24 < 30 < 129 < 41 < 184 10/28/15 < 17 < 15 < 45 < 17 < 52 < 20 < 33 < 42 < 17 < 23 < 113 < 26 < 148 0

N

...... MEAN CL-02 05/13/15 < 15 < 16 < 37 < 12 < 33 < 16 < 29 < 51 < 14 < 16 < 107 < 25 < 109 05/27/15 < 14 < 15 < 33 < 14 < 37 < 13 < 25 < 29 < 12 < 15 < 78 < 20 < 75 06/10/15 < 31 < 29 < 64 < 24 < 66 < 30 < 57 < 55 < 24 < 33 < 125 < 31 < 170 06/24/15 < 6 < 7 < 15 < 6 < 15 < 7 < 12 < 27 < 5 < 6 < 54 < 13 < 44 07/08/15 < 15 < 14 < 35 < 18 < 28 < 15 < 26 < 25 < 11 < 15 < 64 < 19 < 90 07/22/15 < 27 < 28 < 57 < 25 < 58 < 31 < 50 < 49 < 25 < 30 < 142 < 31 < 197 08/05/15 < 14 < 14 < 37 < 14 < 33 < 15 < 26 < 55 < 13 < 14 < 114 < 25 < 95 08/19/15 < 31 < 20 < 57 < 29 < 63 < 28 < 46 < 39 < 24 < 29 < 122 < 21 < 171 09/02/15 < 30 < 31 < 55 < 24 < 62 < 31 < 40 < 54 < 28 < 31 < 150 < 50 < 172 09/16/15 < 31 < 34 < 73 < 36 < 85 < 35 < 68 < 54 < 32 < 33 < 162 < 34 < 228 09/30/15 < 32 < 25 < 76 < 33 < 62 < 31 < 51 <-56 < 21 < 33 < 157 < 35 < 208 "U 10/14/15 < 18 < 17 < 40 < 16 < 45 < 20 < 29 < 29 < 17 < 19 < 86 < 20 < 107 Ill ca 10/28/15 < 20 < 24 < 51 < 30 < 49 < 25 < 40 < 35 < 22 < 28 < 118 < 32 < 129 CD CXl CTI MEAN a

--"

(,.)

CXl

Table C-IX.2 CONCENTRATIONS OF GAMMA EMITTERS IN GRASS SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/KG WET+/- 2 SIGMA SITE COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-144 PERIOD CL-08 05/13/15 < 17 < 16 < 41 < 14 < 39 < 18 < 33 < 59 < 14 < 17 < 117 < 31 < 103 05/27/15 < 18 < 15 < 42 < 19 < 44 < 18 < 35 < 37 < 17 < 19 < 91 < 33 < 108 06/10/15 < 29 < 30 < 71 < 32 < 80 < 32 < 61 < 57 < 32 < 34 < 140 < 33 < 177 06/24/15 < 8 < 9 < 21 < 7 < 19 < 9 < 16 < 37 < 8 < 8 < 68 < 19 < 57 07/08/15 < 16 < 17 < 31 < 18 < 33 < 15 < 26 < 28 < 14 < 16 < 76 < 15 < 115 07/22/15 < 22 < 28 < 50 < 28 < 58 < 21 < 34 < 42 < 21 < 26 < 114 < 33 < 152 08/05/15 < 12 < 13 < 32 < 12 < 28 < 14 < 25 < 51 < 11 < 11 < 99 < 25 < 81 08/19/15 < 27 < 28 < 64 < 23 < 63 < 30 < 49 < 46 < 27 < 30 < 133 < 37 < 177 09/02/15 < 30 < 25 < 70 < 31 < 66 < 22 < 40 < 46 < 27 < 29 < 128 < 30 < 162 09/16/15 < 26 < 27 < 49 < 26 < 59 < 27 < 45 < 41 < 27 < 27 < 120 < 25 < 171 09/30/15 < 29 < 30 < 81 < 36 < 83 < 40 < 57 < 59 < 35 < 34 < 164 < 51 < 209

() 10/14/15 < 18 < 17 < 37 < 19 < 39 < 20 < 32 < 31 < 18 < 18 < 85 < 24 < 127 I

10/28/15 < 23 < 25 < 51 < 18 < 61 < 24 < 41 < 40 < 24 < 23 < 116 < 32 < 164 N

N MEAN CL-116 05/13/15 < 9 < 9 < 26 < 9 < 22 < 10 < 17 < 33 < 9 < 10 < 70 < 20 < 69 05/27/15 < 9 < 10 < 21 < 12 < 20 < 9 < 18 < 15 < 9 < 8 < 50 < 13 < 54 06/10/15 < 25 < 27 < 61 < 31 < 50 < 29 < 49 < 49 < 26 < 28 < 145 < 32 < 211 06/24/15 < 10 < 10 < 27 < 9 < 23 < 11 < 19 < 43 < 9 < 10 < 81 < 21 < 62 07/08/15 < 16 < 13 < 34 < 15 < 29 < 18 < 26 < 29 < 15 < 16 < 76 < 21 < 109 07/22/15 < 30 < 20 < 57 < 28 < 62 < 25 < 43 < 42 < 23 < 30 < 115 < 28 < 142 08/05/15 < 13 < 14 < 32 < 13 < 30 < 15 < 26 < 60 < 12 < 14 < 114 < 25 < 101 08/19/15 < 35 < 29 < 71 < 36 < 83 < 30 < 57 < 60 < 30 < 33 < 152 < 46 < 195 09/02/15 < 27 < 29 < 68 < 27 < 85 < 29 < 61 < 54 < 27 < 29 < 126 < 45 < 166 09/16/15 < 25 < 22 < 48 < 23 < 55 < 30 < 43 < 40 < 19 < 28 < 117 < 32 < 214

"'U 09/30/15 < 34 < 30 < 42 < 29 < 62 < 26 < 54 < 52 < 29 < 28 < 153 < 44 < 220 Ql cc 10/14/15 < 32 < 30 < 79 < 34 < 73 < 31 < 62 < 58 < 33 < 29 < 157 < 39 < 246 CD CXl 10/28/15 < 22 < 21 < 49 < 14 < 47 < 22 < 35 < 39 < 20 < 23 < 99 < 18 < 162 (j)

-0

....>.

(,J CXl MEAN

Table C-X.1 QUARTERLY DLR RESULTS FOR CLINTON POWER STATION, 2015 RESULTS IN UNITS OF MILLI REM/QUARTER+/- 2 STANDARD DEVIATIONS STATION MEAN JAN-MAR APR-JUN JUL-SEP OCT-DEC CODE +/-2S.D.

CL-01 22.7 +/- 3.1 23.0 20.9 22.2 24.6 CL-02 23.6 +/- 3.6 24.7 23.1 21.3 25.3 CL-03 23.7 +/- 3.5 24.4 22.9 21.8 25.8 CL-04 22.5 +/- 2.8 22.9 21.8 21.0 24.2 CL-05 23.9 +/- 3.1 24.6 22.4 22.8 25.7 CL-06 20.9 +/- 2.9 21.4 20.1 19.4 22.7 CL-07 22.2 +/- 1.9 22.8 21.5 21.2 23.2 CL-08 22.9.+/- 4.0 24.3 21.3 21.1 24.9 CL-11 21.9 +/- 3.0 22.0 22.0 19.9 23.6 CL-15 20.7 +/- 2.9 21.0 19.8 19.4 22.6 CL-22 23.3 +/- 3.3 23.7 22.7 21.5 25.4 CL-23 24.2 +/- 2.1 24.5 23.7 23.0 25.4 CL-24 24.3 +/- 2.3 25.2 23.4 23.1 25.3 CL-33 24.1 +/- 2.5 23.6 24.2 22.8 25.7 CL-34 25.1 +/- 2.8 24.3 25.0 23.9 27.1 CL-35 22.2 +/- 3.0 23.8 20.7 21.1 23.1 CL-36 23.4 +/- 3.7 24.2 *22.3 21.4 25.5 CL-37 21.7 +/- 2.5 22.7 20.1 21.2 22.6 CL-41 24.5 +/- 2.2 24.5 23.8 23.5 26.0 CL-42 23.0 +/- 2.9 23.1 22.3 21.6 25.0 CL-43 23.8 +/- 2.4 24.5 23.3 22.4 25.1 CL-44 23.4 +/- 2.3 23.9 22.9 22.0 24.6 CL-45 24.4 +/- 5.2 24.4 23.2 21.9 28.0 CL-46 23.3 +/- 2.8 24.2 21.7 (1) 24.1 CL-47 23.9 +/- 3.8 23.6 23.6 21.8 26.4 CL-48 22.7 +/- 3.2 22.6 21.9 21.4 25.0 CL-49 23.8 +/- 3.7 24.1 22.6 22.3 26.3 CL-51 25.3 +/- 2.0 25.4 24.3 (1) 26.3 CL-52 24.7 +/- 5.5 25.7 23.1 21.9 28.0 CL-53 22.0 +/- 2.9 21.6 21.6 20.8 24.1 CL-54 24.2 +/- 4.0 25.4 22.7 22.4 26.4 CL-55 23.9 +/- 4.1 24.0 23.1 21.9 26.7 CL-56 24.3 +/- 3.6 24.4 23.9 22.2 26.6 CL-57 25.0 +/- 1.1 24.5 25.0 24.7 25.8 CL-58 24.2 +/- 3.7 25.2 23.6 21.9 26.1 CL-60 24.2 +/- 3.2 24.2 24.5 22.1 26.0 CL-61 23.9 +/- 3.9 24.0 22.8 22.2 26.6 CL-63 21.5 +/- 3.8 21.8 21.0 19.2 23.8 CL-64 23.1 +/- 3.2 23.0 22.6 21.4 25.2 CL-65 24.3 +/- 3.4 25.2 22.8 23.0 26.3 CL-74 21.5 +/- 3.9 22.6 20.8 19.0 23.4 CL-75 23.3 +/- 3.6 23.6 22.2 21.6 25.6 CL-76 24.5 +/- 3.4 24.8 23.7 22.7 26.7 CL-77 22.4 +/- 3.4 23.4 20.9 21.0 24.2 CL-78 22.1 +/- 4.3 23.8 22.1 19.0 23.3 CL-79 24.0 +/- 4.5 24.6 22.9 21.6 26.8 CL-80 23.4 +/- 3.3 23.6 22.5 21.9 25.7 CL-81 23.7 +/- 4.6 24.5 23.0 20.9 26.3 CL-84 23.0 +/- 2.2 22.9 22.8 21.9 24.5 CL-90 20.1 +/- 2.8 21.2 19.2 18.6 21.3 CL-91 21.3 +/- 2.9 22.6 20.1 20.0 22.5 CL-97 23.0 +/- 2.1 22.7 23.1 21.9 24.4 CL-99 19.3 +/- 2.8 20.2 19.1 17.3 20.4 CL-114 22.3 +/- 2.1 23.2 21.4 21.4 23.3 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-23 Page 87 of 138

TABLE C-X.2 MEAN QUARTLY DLR RESULTS FOR THE INNER RING, OUTER RING, SPECIAL INTEREST, SUPPLEMENTAL AND CONTROL LOCATIONS FOR CLINTON POWER STATION, 2015 RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION INNER RING OUTER RING SPECIAL INTEREST SUPPLEMENTAL CONTROL PERIOD +/-2 S.D.

JAN-MAR 23.8 +/- 1.7 24.3 +/- 2.0 23.7 +/- 2.0 22.7 +/- 2.7 22.0 +/- 0.0 APR-JUN 22.6 +/- 2.3 23.1 +/- 2.1 22.1 +/- 2.5 21.5 +/- 3.2 22.0 +/- 0.0 JUL-SEP 22.0 +/- 2.2 21.8 +/- 2.4 21.7 +/- 2.9 20.7 +/- 3.0 19.9 +/- 0.0 OCT-DEC 25.3 +/- 2.4 26.0 +/- 2.4 25.1 +/- 3.0 23.6 +/- 3.3 23.6 +/- 0.0 TABLE C-X.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR CLINTON POWER STATION, 201S RESULTS IN UNITS OF MILLIREM/QUARTER +/- 2 STANDARD DEVIATION LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN PRE-OP MEAN ANALYZED MINIMUM MAXIMUM +/-2 S.D. +/- 2 S.D., ALL LOCATIONS INNER RING 63 19.2 28.0 23.4 +/- 3.3 OUTER RING 63 19.0 28.0 23.8 +/- 3.8 18.0 +/- 2.4 SPECIAL INTEREST 28 19.0 26.3 23.1 +/- 3.7 SUPPLEMENTAL 56 17.3 25.8 22.1 +/- 3.8 CONTROL 4 19.9 23.6 21.9 +/- 3.0 INNER RING STATIONS - CL-01, CL-05, CL-22, CL-23, CL-24, CL-34, CL-35, CL-36, CL-42, CL-43, CL-44, CL-45, CL-46, CL-47, CL-48, CL-63 OUTER RING STATIONS - CL-51, CL-52, CL-53, CL-54, CL-55, CL-56, CL-57, CL-58, CL-60, CL-61, CL-76, CL-77, CL-78, CL-79, CL-80, CL-81 SPECIAL INTEREST STATIONS - CL-37, CL-41, CL-49, CL-64, CL-65, CL-74, CL-75 SUPPLEMENTAL STATIONS - CL-02, CL-03, CL-04, CL-06, CL-07, CL-08, CL-114, CL-15, CL-33, CL-84, CL-90, CL-91, CL-97, CL-99 CONTROL STATION - CL-11 C-24 Page 88 of 138

FIGURE C-1 MEAN MONTHLY GROSS BETA CONCENTRATION IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF CPS, 2015 0.052 0.047 0.042 0.037 M

E

0.032

(.)

c..

0.027 0.022 0.017 0.012 0.007 0.002

~* ~* ~* ~*

")~ <l~ ~'if ~ ~~

-"-

ts~* ts~* c,* ~* ~. ~* c,*

~ ~~ 0 v ~o ~<<;

MONTH 1l!ll!!lll1ll PRE-OP (ALL SITES)

_.,_ 2015 INDICATOR

-+- 2015 CONTROL C-25 Page 89 of 138

FIGURE C-2 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (DLR) IN THE VICINITY OF CPS, 2015 50 45 40 35 E

Q) 0:::

30 E

25 20 15 10 QUARTER II PRE-OP 02015 indicator

  • 2015 control C-26 Page 90 of 138

APPENDIX D INTER-LABORATORY COMPARISON PROGRAM Page 91 of 138

Intentionally left blank Page 92 of 138

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF3)

Identification Reported Known Ratio (c)

MonthNear Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d)

March 2015 E11181 Milk Sr-89 pCi/L 88.9 97.2 0.91 A Sr-90 pCi/L 12.2 17.4 0.70 w E11182 Milk 1-131 pCi/L 61.3 65.1 0.94 A Ce-141 pCi/L 104 113 0.92 A Cr-51 pCi/L 265 276 0.96 A Cs-134 pCi/L 138 154 0.90 A Cs-137 pCi/L 205 207 0.99 A Co-58 pCi/L 178 183 0.97 A Mn-54 pCi/L 187 188 0.99 A Fe-59 pCi/L 182 177 1.03 A Zn-65 pCi/L 345 351 0.98 A Co-60 pCi/L 379 405 0.94 A

--* -- -**--* -- - -~ - .-

E11184 AP Ce-141 pCi 107 85.0 1.26 w Cr-51 pCi 261 224 1.17 A Cs-134 pCi 74.6 77.0 0.97 A Cs-137 pCi 99.6 102 0.98 A Co-58 pCi 99.8 110 0.91 A Mn-54 pCi 99.2 96.9 1.02 A Fe-59 pCi 109 119 0.92 A Zn-65 pCi 188 183 1.03 A Co-60 pCi 200 201 1.00 A E11183 Charcoal 1-131 pCi 82.9 85.4 0.97 A E11185 Water Fe-55 pCi/L 1950 1900 1.03 A June 2015 E11234 Milk Sr-89 pCi/L 94.9 92.6 1.02 A Sr-90 pCi/L 14.3 12.7 1.13 A E11238 Milk 1-131 pCi/L 93.2 95.9 0.97 A Ce-141 pCi/L Not provided for this study Cr-51 pCi/L 349 276 1.26 w Cs-134 pCi/L 165 163 1.01 A Cs-137 pCi/L 143 125 1.14 A Co-58 pCi/L 82.0 68.4 1.20 A Mn-54 pCi/L 113 101 1.12 A Fe-59 pCi/L 184 151 1.22 w Zn-65 pCi/L 269 248 1.08 A Co-60 pCi/L 208 193 1.08 A E11237 AP Ce-141 pCi Not provided for this study Cr-51 pCi 323 233 1.39 N (1)

Cs-134 pCi 139 138 1.01 A Cs-137 pCi 111 106 1.05 A Co-58 pCi 54.0 57.8 0.93 A Mn-54 pCi 96.8 84.9 1.14 A Fe-59 pCi 162 128 1.27 w Zn-65 pCi 198 210 0.94 A Co-60 pCi 178 163 1.09 A E11236 Charcoal 1-131 pCi 93.9 80 1.17 A D-1 Page 93 of 138

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TSE/Analytics Evaluation (d)

June 2015 E11238 Water Fe-55 pCi/L 1890 1790 1.06 A September 2015 E11289 Milk Sr-89 pCi/L 95.7 99.1 0.97 A Sr-90 pCi/L 15.4 16.4 0.94 A E11290 Milk 1-131 pCi/L 94.9 99.9 0.95 A Ce-141 pCi/L 228 213 1.07 A Cr-51 pCi/L 499 538 0.93 A Cs-134 pCi/L 208 212 0.98 A Cs-137 pCi/L 270 255 1.06 A Co-58 pCi/L 275 263 1.05 A Mn-54 pCi/L 320 290 1.10 A Fe-59 pCi/L 255 226 1.13 A

- - -- - , ,.. - :-- . -- .,,__ .. -- . -- - - ~ " Zn-65 ... pCi/L *- 392 353--- .. 1.11 .-.A ..

Co-60 pCi/L 350 330 1.06 A E11292 AP Ce-141 pCi 104 85.1 1.22 w Cr-51 pCi 262 215 1.22 w Cs-134 pCi 86.1 84.6 1.02 A Cs-137 pCi 93 102 0.91 A Co-58 pCi 106 105 1.01 A Mn-54 pCi 117 116 1.01 A Fe-59 pCi 94.8 90.2 1.05 A Zn-65 pCi 160 141 1.13 A Co-60 pCi 146 132 1.11 A E11291 Charcoal 1-131 pCi 85.9 81.7 1.05 A E11293 Water Fe-55 pCi/L 2090 1800 1.16 A E11294 Soil Ce-141 pCi/kg 209 222 0.94 A Cr-51 pCi/kg 463 560 0.83 A Cs-134 pCi/kg 231 221 1.05 A Cs-137 pCi/kg 311 344 0.90 A Co-58 pCi/kg 245 274 0.89 A Mn-54 pCi/kg 297 *302 0.98 A Fe-59 pCi/kg 248 235 1.06 A Zn-65 pCi/kg 347 368 0.94 A Co-60 pCi/kg 328 344 0.95 A December 2015 E11354 Milk Sr-89 pCi/L 96.2 86.8 1.11 A Sr-90 - pCi/L __ 14.8 12.5 1.18 A E11355 Milk 1-131 pCi/L 95.1 91.2 1.04 A Ce-141 pCi/L 117 129 0.91 A Cr-51 pCi/L 265 281 0.94 A Cs-134 pCi/L 153 160 0.96 A Cs-137 pCi/L 119 115 1.03 A Co-58 pCi/L 107 110 0.97 A Mn-54 pCi/L 153 145 1.06 A Fe-59 pCi/L 117 108 1.08 A Zn-65 pCi/L 261 248 1.05 A Co-60 pCi/L 212 213 1.00 A D-2 Page 94 of 138

TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE3 OF 3)

Identification Reported Known Ratio (c)

MonthNear Number Matrix Nuclide Units Value (a) Value (b) TBE/Anal}'.tics Evaluation (d)

December 2015 E11357 AP Ce-141 pCi 89.9 84.0 1.07 A Cr-51 pCi 215 184 1.17 A Cs-134 pCi 103 105 0.98 A Cs-137 pCi 76.6 74.8 1.02 A Co-58 pCi 76.2 71.9 1.06 A Mn-54 pCi 91.4 94.4 0.97 A

  • Fe-59 pCi 78.6 70.3 1.12 A Zn-65 pCi 173 162 1.07 A Co-60 pCi 138 139 0.99 A E11422 AP Sr-89 pCi 98.0 96.9 1.01 A Sr-90 pCi 10.0 14.0 0.71 w E11356 Charcoal 1-131 pCi 74.9 75.2 1.00 A E11358 Water Fe-55 pCi/L 2160 1710 1.26 w E11353 Soil Ce-141 pCi/kg 252 222 1.14 A Cr-51 pCi/kg 485 485 1.00 A Cs-134 pCi/kg 319 277 1.15 A Cs-137 pCi/kg 292 276 1.06 A Co-58 pCi/kg 193 190 1.02 A Mn-54 pCi/kg 258 250 1.03 A Fe-59 pCi/kg 218 186 1.17 A Zn-65 pCi/kg 457 429 1.07 A Co-60 pCi/kg 381 368 1.04 A (1) AP Cr Cr-51 has the shortest half-life and the weakest gamma energy of the mixed nuclide sample, which produces a large error. Taking into account the error, the lowest value would be 119% of the reference value, which would be considered acceptable. NCR 15-18 (a) Teledyne Brown Engineering reported result.

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

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

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable, reported result falls within ratio limits of 0. 80-1.20.

W-Acceptable with 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.

D-3 Page 95 of 138

TABLE D-2 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)

TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

March 2015 15-MaW32 Water Am-241 Sq/L 0.632 0.654 0.458 - 0.850 A Ni-63 Sq/L 2.5 (1) A Pu-238 Sq/L 0.0204 0.0089 (2) A Pu-239/240 Sq/L 0.9 0.8 0.582 - 1.082 A 15-MaS32 Soil Ni-63 Sq/kg 392 448.0 314- 582 A Sr-90 Sq/kg 286 653 487 - 849 N (3) 15-RdF32 AP Sr-90 Sq/sample -0.0991 (1) A U-234/233 Sq/sample 0.0211 0.0155 0.0109 - 0.0202 N (3)

U-238 Sq/sample 0.095 0.099 0.069- 0.129 A 15-GrF32 AP Gr-A Sq/sample 0.448 1.77 0.53 - 3.01 N (3)

Gr-S Sq/sample 0.7580 0.75 0.38 -.1.13 A 15-RdV32 Vegetation Cs-134 Sq/sample 8.08 7.32 5.12 - 9.52 A Cs-137 Sq/sample 11.6 9.18 6.43 - 11.93 w Co-57 Sq/sample -0.0096 (1) A Co-60 Sq/sample 6.53 5.55 3.89 - 7.22 A Mn-54 Sq/sample 0.0058 (1) A Sr-90 Sq/sample 0.999 1.08 0.76 - 1.40 A Zn-65 Sq/sample -0.108 (1) A September 2015 15-MaW33 Water Am-241 Sq/L 1.012 1.055 0. 739 - 1.372 A Ni-63 Sq/L 11.8 8.55 5.99-11.12 N (4)

Pu-238 Sq/L 0.727 0.681 0.477 - 0.885 A Pu-239/240 Sq/L 0.830 0.900 0.630-1.170 A 15-MaS33 Soil Ni-63 Sq/kg 635 682 477 - 887 A Sr-90 Sq/kg 429 425 298 - 553 A 15-RdF33 AP Sr-90 Sq/sample 1.48 2.18 1.53 - 2.83 N (4)

U-234/233 Sq/sample 0.143 0.143 0.100- 0.186 A U-238 Sq/sample 0.149 0.148 0.104-0.192 A 15-GrF33 AP Gr-A Sq/sample 0.497 0.90 0.27 -1.53 A Gr-S Sq/sample 1.34 1.56 0.78 - 2.34 A 15-RdV33 Vegetation Cs-134 Sq/sample 6.10 5.80 4.06 - 7.54 A Cs-137 Sq/sample 0.0002 (1) A Co-57 Sq/sample 8.01 6.62 4.63 - 8.61 w Co-60 Sq/sample 4.97 4.56 3.19- 5.93 A Mn-54 Sq/sample 8.33 7.68 5.38 - 9.98 A Sr-90 Sq/sample 0.386 1.30 0.91 - 1.69 N (4)

(1) False positive test. Zn-65 Sq/sample 6.07 5.46 3.82-7.10 A (2) Sensitivity evaluation.

(3) Soil Sr incomplete digestion of the sample resulted in low results; AP U-2341233 - extremely low activity was difficult to quantify AP Gr-A - the MAPEP filter has the activity embedded in the filter. To corrected the low bias, TBE will create an attenuated efficiency for MAPEP samples. NCR 15-13 (4) Water Ni-63 extremely low activity was difficult to quantify; AP & Vegetation Sr-90 was lost during separation, possible from substance added by MAPEP NCR 15-21.

(a) Teledyne Brown Engineering reported result.

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

(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, tvo1.94acceptable.

Page 96 of 138

TABLE D-3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2015 (PAGE 1OF1)

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

May 2015 RAD-101 Water Sr-89 pCi/L 45.2 63.2 51.1 - 71.2 N (1)

Sr-90 pCi/L 28.0 41.9 30.8 - 48.1 N (1)

Ba-133 pCi/L 80.6 82.5 63.9 - 90.8 A Cs-134 pCi/L 71.7 75.7 61.8 - 83.3 A Cs-137 pCi/L 187 189 170 - 210 A Co-60 pCi/L 85.7 84.5 76.0 - 95.3 A Zn-65 pCi/L 197 203 183 - 238 A Gr-A pCi/L 26.1 42.6 22.1 - 54.0 A Gr-B pCi/L 28.8 32.9 21.3 - 40.6 A 1-131 pCi/L 23.5 23.8 19.7 - 28.3 A U-Nat pCi/L 6.19 6.59 4.99 - 7.83 A H-3 pCi/L 3145 3280 2770 - 3620 A

--* --~- ---* -- -

November 2015 RAD-103 Water Sr-89 pCi/L 40.9 35.7 26.7 - 42.5 A Sr-90 pCi/L 29.3 31.1 22.7 - 36.1 A Ba-133 pCi/L 31.5 32.5 25.9 - 36.7 A Cs-134 pCi/L 59.65 62.3 50.6 - 68.5 A Cs-137 pCi/L 156 157 141 -175 A Co-60 pCi/L 70.6 71.1 64.0 - 80.7 A Zn-65 pCi/L 145 126 113 - 149 A Gr-A pCi/L 38.2 51.6 26.9 - 64.7 A Gr-B pCi/L 42.0 36.6 24.1 - 44.2 A 1-131 pCi/L 24.8 26.3 21.9- 31.0 A U-Nat pCi/L 146.90 56.2 45.7 - 62.4 N (2)

H-3 pCi/L 21100 21300 18700 - 23400 A

-

(1) Yield on the high side of our acceptance range indicates possibility of calcium interference. NCR 15-09 (2) Technician failed to dilute original sample. If di/ulted, the result would have been 57. 1, which tell within the acceptance limits. NCR 15-19 (a) Teledyne Brown Engineering reported result.

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

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

D-5 Page 97 of 138

3 TABLE D-4 ERA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2015 (Page 1 of 1)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control 0

Result b Result Limits Acceptance ERW-1444 04/06/15 Sr-89 59.71 +/- 5.44 63.20 51.10 - 71.20 Pass ERW-1444 04/06/15 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 04/06/15 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 04/06/15 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 04/06/15 Cs-137 -191.92 +/- 5.9 189 - 170.00 - 210.0 Pass ERW-1448 04/06/15 Co-60 85.05 +/- 4.59 84.50 76.00 - 95.30 Pass ERW-1448 04/06/15 Zn-65 -195.97 +/- 12.0 203 -183.00 - 238.0 Pass ERW-1450 04/06/15 Gr. Alpha 34.05 +/- 1.90 42.60 22.10 - 54.00 Pass ERW-1450 04/06/15 G. Beta 26.93 +/- 1.12 32.90 21.30 - 40.60 Pass ERW-1453 04/06/15 1-131 22.47 +/- 0.83 23.80 19. 70 - 28.30 Pass ERW-1456 04/06/15 Uranium 5.98 +/- 0.31 6.59 4.99 - 7.83 *Pass ERW-1461 04/06/15 H-3 3,254 +/- 180 3280 2,770 - 3620 Pass ERW-5528 10/05/15 Sr-89 34.76 +/- 0.06 35.70 26.70 - 42.50 Pass ERW-5528 10/05/15 Sr-90 29.23 +/- 0.06 31.10 22.70 - 36.10 Pass ERW-5531 10/05/15 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/05/15 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/05/15 Cs-137 -163.12 +/- 4.8 157 -141.00 - 175.0 Pass ERW-5531 10/05/15 Co-60 73.41 +/- 1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/05/15 Zn-65 -138.94 +/- 5.7 126 -113.00 - 149.0 Pass ERW-5534 10/05/15 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/05/15 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537 10/05/15 1-131 25.54 +/- 0.60 26.30 21.90 - 31.00 Pass ERW-5540 10/05/15 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/05/15 H-3 21,260 +/- 351 21,300 18,700 - 23400.0 Pass

  • 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. Page 98 of 138 0-6

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

ENVIRONMENTAL, INC., 2015 (Page 1 of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 02/01/15 Ni-63 341 +/- 18 448 314 - 582 Pass MAS0-975 02/01/15 Sr-90 523 +/- 12 653 457 - 849 Pass MAS0-975 02/01/15 Cs-134 533 +/-6 678 475 - 881 Pass MAS0-975 02/01/15 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 02/01/15 Co-57 0.5 +/-1 0.0 NA c Pass MAS0-975 02/01/15 Co-60 741 +/-8 817 572 - 1062 Pass MAS0-975 02/01/15 Mn-54 1, 153 +/-9 1, 198 839 - 1557 Pass MAS0-975 02/01/15 Zn-65 892 +/- 18 1064 745 - 1383 Pass MAW-969 02/01/15 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 02/01/15 Cs-134 21.09 +/- 0.25 23.5 16.5 - 30.6 Pass MAW-969 02/01/15 Cs-137 19.63 +/- 0.34 19.1 13.4 - 24.8 Pass MAW-969 d 02/01/15 Co-57 . --** 10.2 +/- 0.4 29.9 20.9 - 38.9. Fail.

MAW-969 02/01/15 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 02/01/15 H-3 569 +/- 13 563 394 - 732 Pass MAW-969 02/01/15 Fe-55 6.00 +/- 6.60 6.88 4.82 - 8.94 Pass MAW-969 02/01/15 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 02/01/15 Ni-63 2.9 +/-3 0.00 NA c Pass MAW-969 02/01/15 Zn-65 16.54 +/- 0.85 18.3 12.8 - 23.8 Pass MAW-969 02/01/15 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 02/01/15 Pu-239/240 0.81 +/- 0.10 0.83 0.58 - 1.08 Pass MAW-969 02/01/15 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 02/01/15 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 02/01/15 Gr. Beta 2.72 +/- 0.06 2.79 1.40 - 4.19 Pass MAAP-978 02/01/15 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 02/01/15 Cs-137 0.004 +/- 0.023 0.00 NAC Pass MAAP-978 e 02/01/15 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fail MAAP-978 02/01/15 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 02/01/15 Mn-54 1.11 +/- 0.08 1.02 0.71 - 1.33 Pass MAAP-978 02/01/15 Zn-65 0.83 +/- 0.10 0.83 0.58 - 1.08 Pass MAAP-981 02/01/15 Sr-89 38.12 +/- 1.01 47.5 33.3 - 61.8 Pass MAAP-981 02/01/15 Sr-90 1.22 +/- 0.13 1.06 0.74 - 1.38 Pass MAAP-984 02/01/15 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 02/01/15 Gr. Beta 0.95 +/- 0.07 0.75 0.38 - 1.13 Pass MAVE-972 02/01/15 Cs-134 6.98 +/- 0.13 7.32 5.12 - 9.52 Pass MAVE-972 02/01/15 Cs-137 9.73 +/- 0.21 9.18 6.43 - 11.93 Pass MAVE-972 02/01/15 Co-57 0.01 +/- 0.04 0.00 NAC Pass MAVE-972 02/01/15 Co-60 3.89 +/- 0.20 5.55 3.89 - 7.22 Pass MAVE-972 02/01/15 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 02/01/15 Zn-65 0.09 +/- 0.12 0.00 NA c Pass Page 99 of 138 D-7

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

ENVIRONMENTAL, INC., 2015 (Page 2 of 2)

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits 0 Acceptance MAS0-4903 08/01/15 Ni-63 556 +/- 18 682 477 - 887 Pass MAS0-4903 f 08/01/15 Sr-90 231 +/-7 425 298 - 553 Fail MAS0-4903 f 08/01/15 Sr-90 352 +/- 10 425 298 - 553 Pass MAS0-4903 08/01/15 Cs-134 833 +/- 10 1,010 707 - 1313 Pass MAS0-4903 08/01/15 Cs-137 808 +/- 11 809.00 566 - 1052 Pass MAS0-4903 08/01/15 Co-57 1,052 +/- 10 1, 180 826 - 1534 Pass 0

MAS0-4903 08/01/15 Co-60 2 +/-2 1.3 NA Pass MAS0-4903 08/01/15 Mn-54 1,331 +/- 13 1,340 938 - 1742 Pass MAS0-4903 08/01/15 Zn-65 686 +/- 15 662 463 - 861 Pass MAW-5007 08/01/15 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30 Pass MAW-5007 08/01/15 Cs-137 -0.36 +/- 0.13 0 NA 0 Pass MAW-5007 "08/01/15 co~57 21.8 +/- 0.4 20.8 14.6 - 27 Pass MAW-5007 08/01/15 Co-60 17.3 +/- 0.3 17.1 12 - 22.2 Pass MAW-5007 08/01/15 H-3 227.5 +/- 8.9 216 151 - 281 Pass MAW-5007 g 08/01/15 Fe-55 4.2 +/- 14.1 13.1 9.2 - 17 Fail MAW-5007 08/01/15 Mn-54 16.6 +/- 0.5 15.6 10.9 - 20.3 Pass MAW-5007 08/01/15 Ni-63 9.1 +/- 2.6 8.55 5.99 - 11.12 Pass MAW-5007 08/01/15 Zn-65 15.5 +/- 0.9 13.9 9.7 - 18.1 Pass MAW-5007 08/01/15 Sr-90 4.80 +/- 0.50 4.80 3.36 - 6.24 Pass MAW-5007 08/01/15 Gr. Alpha 0.41 +/- 0.04 0.43 0.13 - 0.73 Pass MAW-5007 08/01/15 Gr. Beta 3.45 +/- 0.07 3.52 1.76 - 5.28 Pass MAAP-4911 08/01/15 Sr-89 3.55 +/- 0.67 3.98 2.79 - 5.17 Pass MAAP-4911 08/01/15 Sr-90 0.94 +/- 0.16 1.05 0.74 - 1.37 Pass MAAP-4907 08/01/15 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 - 1.53 Pass MAAP-4907 08/01/15 Gr. Beta 1.85 +/- 0.09 1.56 0.78 - 2.34 Pass MAVE-4901 08/01/15 Cs-134 5.56 +/- 0.16 5.80 4.06 - 7.54 Pass MAVE-4901 08/01/15 Cs-137 -0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 08/01/15 Co-57 7.74 +/- 0.18 6.62 4.63 - 8.61 Pass MAVE-4901 08/01/15 Co-60 4.84 +/- 0.15 4.56 3.19 - 5.93 Pass MAVE-4901 08/01/15 Mn-54 8.25 +/- 0.25 7.68 5.38 - 9.98 Pass MAVE-4901 08/01/15 Zn-65 5.78 +/- 0.29 5.46 3.82 - 7.10 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).

0 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.

d Lab result was 27.84. Data entry_ error resulted in a non-acceptable result.

  • Lab result was 1.58. Data entry error resulted in a non-acceptable result.

f The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

g The known activity was below the routine laboratory detection limits for the available aliquot fraction. Page 100 of 138 D-8

APPENDIX E ERRATA DATA

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There is no errata data for 2015.

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APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR}

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Docket No: 50-461 Cl~NTON l?OWIER. STATION Annual Radiological Groundwater Protection Program Report

- - - -- -- - -- - - ------:-- -- . --~ - -- --<o----- --. . - . . - -

  • ----...-----~-.**

- ___ .-- .-* ____.,. .

--- .__,,,_ - '> *-,,...- - - - - -=-- --~-- - ~ ..__*. .,

January 1 through December 31, 2015 Prepared By Teledyne Brown Engineering Environmental Services Clinton Power Station Clinton, IL 61727 April 2016 Page 107 of 138

  • Intentionally left blank Page 108of138

Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 3 A Objectives of the RGPP ...................................................................................... 3

8. Implementation of the Objectives ........................................................................ 3 C. Program Description ........................................................................................... 4 D. Characteristics of Tritium (H-3) ........................................................................... 5 Ill. Program Description ...................................................................................................... 5 A. Sample Analysis ....................................... ,.......................................................... 5
8. Data Interpretation ........-...... ~ ........-... :.: .................................................................-. 6

_.__ :. -*- :. -:": .... -- *_;;_----,. -t~:; sack9rduncfAil~i1ysis.~::-:~.: :~~-.. :*::*:::: .:'::.:.~.~--~:_:'.--'.*.-~_::::: :::~--.:-~ .*:_:-.':-::*:*: ~ .-:.:. '.~--~:.~:~..*. ::-. ::':~:::-*1 ~--...,:-_ ; =

1. Background Concentrations of Tritium ............................................ :........ 7 IV. Results and Discussion ................................................................................................. 9 A. Program Exceptions ............................................................................................ 9
8. Program Changes ............................................................................................... 9 C. Groundwater Results .......................................................................................... 9 D. Surface Water Results ............................................................... ,, ..................... 11 E. Precipitation Water Results ............................................................................... 11 F. Recapture .......................................................................................................... 11 G. Summary of Results - Inter-laboratory Comparison Program .......................... 11 H. Errata Data .......................................................................................................... 11 I. Leaks, Spills, and Releases ......................................................................... ,...... 12 J. Trends ................................................, ................................................................ 12 K. Investigations ..................................................................................................... 12 L. Actions Taken ..................................................................................,.................. 12
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Appendices Appendix A Location Designation of the Annual Radiological Groundwater Protection Program Report (ARGPPR)

  • Tables
  • Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Figures Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Clinton Power Station,

~015

-.--.,,<-----~*--. _..,-.* __ : - ~ -- . , *-~--~-.-_:- : __ -. ,.. __ . . . . - _.,._ --*-- - -* ~--,....,,**---* - .,,...,..,.__,........,c,.:-..:= _,--------- ....-- .,*-~-

Figure A-1 Onsite Sampling Locations at Clinton Power Station Figure A-2 Sampling Locations South of Clinton Power Station Figure A-3 Sampling Locations East of Clinton Power Station Figure A-4 Recapture Sampling Locations of Clinton Power Station Appendix B Data Tables of the Annual Radiological Groundwater Protection Program Report (ARGPPR)

Tables Table 8-1.1 Concentrations of Tritium, Strontium, Gross Alpha, and Gross Beta in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table 8-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table 8-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table 8-11.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

Table B~ll.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Clinton Power Station, 2015.

ii Page 110 of 138

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 Clinton Power Station (CPS). This evaluation involved numerous station personnel and contractor support personnel. This report covers groundwater and surface water samples, collected outside of the Licensee required Off-Site Dose Calculation Manual (ODCM) requirements, both on and off station property in 2015. During that time period, 246 analyses were performed on 97 samples from 24 locations.

The monitoring was conducted in four phases.

In assessing all the data gathered for this report, it was concluded that the operation of CPS had no adverse radiological impact on the environment, and

-- the-re are no known-active-releases into the groundwater or surface water at~, __ - -- - -

CPS. No program changes occurred during the sampling year of 2015.

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 NUREG-1302 in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that the independent laboratory achieve a lower limit of detection 10 times lower than that required by the United States Environmental Protection Agency (USEPA) regulation.

Strontium-89 was not detected in any samples. Strontium-90 was not detected in any samples.

Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Background levels of tritium were detected at concentrations greater than the self-imposed LLD of 200 pCi/L in four of 17 groundwater monitoring locations. The tritium concentrations ranged from 176 +/-

106 pCi/L to 365 +/- 136 pCi/L. Tritium was not detected in any surface water.

Precipitation samples were not analyzed during 2015.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations. Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L. Gross Beta (suspended) was not detected at any of the groundwater locations.

Page 111 of 138

Hard-To-Detect analyses were performed on two 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 analyzed were not found at concentrations greater than their respective MDCs.

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II. Introduction The Clinton Power Station (CPS), consisting of one approximately 1, 140 MW gross electrical power output boiling water reactor is located in Harp Township, DeWitt County, Illinois. CPS is owned and operated by Exelon and became operational in 1987. Unit No. 1 went critical on 15 February 1987. The site encloses approximately 13,730 acres. This includes the 4,895 acre, man-made cooling lake and about 452 acres of property not owned by Exelon. The plant is situated -on approximately 150 acres~ The cooling water discharge flume, which discharges to the eastern arm of the lake, occupies an additional 130 acres.

Although the nuclear reactor, supporting equipment and associated electrical generation and distribution equipment lie in Harp Township, portions of the aforementioned 13, 730 acre plot reside within Wilson, Rutledge, DeWitt, Creek, Nixon and Santa Ann_a Townships.

    • -. __ ,,__,,, ___ -. - - *~-- - - -

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2015.

A. Objectives of the Radiological Groundwater Protection Program (RGPP)

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

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
2. Understand the local hydrogeologic regime in the vicinity of the station and maintain knowledge of flow patterns on the surface and shallow subsurface. *
3. Perform routine water sampling and radiological analysis of water from selected locations.
4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
5. Regularly assess analytical results to identify adverse trends.
6. Take necessary corrective actions to protect groundwater resources.
8. Implementation of the Objectives The objectives identified have been implemented at Clinton Power Station as discussed below:

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1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Connestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public in station specific reports.
2. The Clinton Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
3. Clinton Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.
4. Clinton Power Station has implemented new procedures to identify

~-and report rrew leaks,-spiils, o*r*otlier detections with potential*

radiological significance in a timely manner.

5. Clinton Power 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, A-2, A-3, and A-4 Appendix A.

Groundwater, Surface Water and Precipitation Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Groundwater, surface water, and precipitation water are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial revi~w by the contractor.

Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to Page 114of138

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." The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the environment and the body. 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, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. 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 has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). 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 beta 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 to analyze the environmental samples for radioactivity for the Clinton Page 115 of 138

Power Station RGPP in 2015.

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

1. Concentrations of gamma emitters in groundwater and surface water.
2. Concentrations of strontium in groundwater.
3. Concentrations of tritium in groundwater and surface water.
4. Concentrations of gross alpha and gross beta in groundwater.

5." ---; - Concentrations of-Am-241-in groundwater. -

6. Concentrations of Cm-242 and Cm-243/244 in groundwater.
7. Concentrations of Pu-238 and Pu-239/240 in groundwater.
8. Concentrations of U-234, U-235 and U-238 in groundwater.
9. Concentrations of Fe-55 in groundwater.
10. Concentrations of Ni-63 in groundwater.

B. Data Interpretation The radiological data collected prior to Clinton Power Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Clinton Power Station 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) 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.

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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) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus

  • or minus+/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

Analytical uncertainties are reported at the 95% confidence level in

-- ** -*this report for reporting consistency With the AREOR.- .,~- -*

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

For groundwater and surface water 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.

C. Background Analysis Pre-operational Radiological Environmental Monitoring Program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, milk, and vegetation. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Clinton Power Nuclear Power Station, Illinois Power Company, Annual Report 1987, May 1988.

The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater.

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.
a. Tritium Production Tritium is created in the environment from naturally occurring Page 117 of 138

processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and 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 atmo*spheric*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.
b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide from 1960 to 2006.

RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline Jp until 1975, followed by. a gradual decline sine~ that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above.

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c. Surface Water Data Tritium concentrations are routinely measured in Clinton Lake.

According to the USEPA, surface water data typically has an uncertainty+/- 70 to 100 pCi/L 95% confidence bound on each given measurement. Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.

The radio-analytical laboratory is counting tritium results to an Exelon specified 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. Program Exceptions

1. Sample Anomalies There were no samples anomalies in 2015.
2. Missed Samples There were no missed samples in 2015.

B. Program Changes There were no sampling program changes in 2015.

C. Groundwater Results Groundwater Baseline samples were collected from off-site wells during four (4) phases at the station. Analytical results are discussed below. No anomalies were noted during the year.

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Tritium Samples from 17 locations were analyzed for tritium activity (Table B-1.1 Appendix B). Tritium values ranged from below the Exelon imposed LLD of 200 pCi/I to 365 pCi/I.

Strontium Strontium-89 was not detected in any of the 17 samples analyzed and the required LLD of 10 pCi/L was met. Strontium-90 was also not detected in any of the 17 samples analyzed and the required LLD of 1 pCi/L was met. (Table B-1.1 Appendix B).

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed oh groundwater samples during the third quarter of sampling in 2015. Naturally occurring Gross Alpha (dissolved) was detected in one of 17 groundwater locations at a concentration of 1.2 +/- 0.8 pCi/L. Gross Alpha (suspended) was not detected at any of the groundwater locations.

Gross Beta (dissolved) was detected in 15 of 17 groundwater locations. The concentrations ranged from 1.9 to 11.9 pCi/L.

Gross Beta (suspended) was not detected at any of the groundwater locations (Table B-1.1 Appendix B).

Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-1.2, Appendix B).

Hard-To-Detect Hard-To-Detect analyses were performed on two groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, and U-238. All hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

Occasionally, the isotopes of U-234 and U-238 are detected at low levels and indistinguishable from background (Table B-1.3 Appendix B).

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D. Surface Water Results Surface Water Baseline samples were collected from on-site surface waters during four (4) phases at the station. Analytical results are discussed belo.w. No anomalies were noted during the year.

Tritium Samples from seven locations were analyzed for tritium activity

- (Table B-11.1 Appendix B). Tritium was not detected at concentrations greater than the LLD.

  • -~ --* * -. ---... '" *-*-*-*. --Strontium****-** *- * . .- - ' -- -' _,,.... * *--------~~---,------ * - *-- **--.* -*--

Strontium was not analyzed in 2015 (Table B-11.1 Appendix B).

Gamma Emitters Naturally occurring K-40 was detected and no plant produced radionuclides were detected (Table B-11.2, Appendix B).

E. Precipitation Water Reirnlts Precipitation Water Precipitation water samples were not collected during 2015.

F. Recapture Recapture samples were not required in 2015.

G. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.

H. Errata Data The 2014 ARGPP incorrectly reported 607 analyses in the Summary and Conclusion section. The number of analyses in 2014 should have been ,

reported as 253 (IR 02635324).

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I. Leaks, Spills, and Releases No leaks, spills or releases were identified during the year.

J. Trends MW-CL-14S had a slight trend upward from <200 pCi/L to 241, 300 and 365 pCi/L respectively in 2015. However, the 1st Quarter of 2016 revealed MW-CL-14S has trended back to 218 pCi/L. Additionally, MW-CL-21S, after it too experienced a slight trend from 219 pCi/L to 287 pCi/L in 2015, has now had consecutive values of 189 pCi/L in the 4th Quarter of 2015 and 191 pCi/L from our 1st Quarter of 2016. All sampling well locations are currently indicating tritium levels that are less than the ODCM LLD of 2,000 pCi/I. All wells will continue to be sampled in accordance with the RGPP in 2016..

K. Investigations Currently no investigations are on-going.

L. Actions Taken

1. Compensatory Actions There have been no station events requiring compensatory actions at the Clinton Power Station in 2015.
2. Installation of Monitoring Wells No new wells were installed during the 2015.
3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.

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APPENDIX A LOCATION DESIGNATION OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT

{ARGPPR)

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TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Clinton Power Station, 2015 Site Site Type B-3 Monitoring Well MW-CL-1 Monitoring Well MW-CL-2 Monitoring Well MW-CL-121 Monitoring Well MW-CL-131 Monitoring Well MW-CL-13S Monitoring Well MW-CL-14S Monitoring Well MW-CL-151 Monitoring Well MW-CL-15S Monitoring Well MW-CL-16S Monitoring Well MW-CL-17S Monitoring Well MW-CL-181 Monitoring Well MW-CL-18S Monitoring Well MW-CL-19S Monitoring Well MW-CL-20S Monitoring Well MW-CL-21S Monitoring Well MW-CL-22S Monitoring Well Sewage Treatment Plant - - - - Surface Water SW-CL-1 Surface Water SW-CL-2 Surface Water SW-CL-4 Surface Water SW-CL-5 Surface Water SW-CL-6 Surface Water SW-CL-7 Surface Water A-1 Page 125of138

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APPENDIX B DATA TABLES OF THE ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus) 8-3 02/09/15 < 157 8-3 05/26/15 < 194 8-3 08/17/15 < 180 < 5.2 < 0.6 1.2 +/- 0.8 < 1.1 3.2 +/- 1.0 < 1.6 8-3 11/02/15 < 196 MW-CL-1 02/09/15 < 156 MW-CL-1 05/26/15 < 195 MW-CL-1 08/17/15 < 179 - < 5.4 < 0.6 < 0.9 < 1.1 2.1 +/- 0.9 < 1.6 MW-CL-1 11/02/15 < 187 MW-CL-121 02/09/15 < 178 MW-CL-121 05/26/15 < 196 MW-CL-121 08/17/15 < 191 < 5.6 < 0.6 < 0.9 < 1.1 4.9 +/- 1.0 < 1.6 MW-CL-121 11/02/15 322 +/- 134 MW-CL-131 02/09/15 < 154 MW-CL-131 05/26/15 < 193 MW-CL-131 08/17/15 < 187 . < 4.0 < 0.6 < 0.7 < 1.1 3.2 +/- 1.1 < 1.6 MW-CL-131 11/02/15 < 187 MW-CL-13S 02/09/15 < 157 MW-CL-13S 05/26/15 < 193 MW-CL-13S 08/17/15 < 199 < 4.7 < 0.6 < 0.6 < 1.1 2.7 +/- 1.0 < 1.6 MW-CL-13S 11/02/15 220 +/- 128 MW-CL-14S 02/09/15 < 156 MW-CL-14S 07/22/15 241 +/- 128 MW-CL-14S 08/18/15 300 +/- 126 < 6.9 < 0.8 < 1.3 < 1.1 11.9 +/- 1.6 < 1.6 MW-CL-14S 11/03/15 365 +/- 136 MW-CL-151 02/09/15 < 156 MW-CL-151 05/26/15 < 193 MW-CL-151 08/17/15 < 174 < 5.7 < 0.7 < 0.7 < 0.5 1.9 +/- 1.0 < 1.7 MW-CL-151 11/02/15 < 193 MW-CL-15S 02/09/15 < 155 MW-CL-15S 05/26/15 < 193 MW-CL-15S 08/17/15 < 197 MW-CL-15S 09/29/15 < 5.2 < 0.6 < 0.9 < 0.8 < 0.9 < 1.6 MW-CL-15S 11/02/15 < 185 MW-CL-16S 02/09/15 < 186 MW-CL-16S 05/27/15 < 189 MW-CL-16S 08/18/15 <.180 MW-CL-16S 09/29/15 < 5.6 < 0.7 < 2.3 < 0.8 8.7 +/- 1.4 < 1.6 MW-CL-16S 11/03/15 < 188 MW-CL-17S 02/09/15 < 159 MW-CL-17S 05/27/15 < 194 MW-CL-17S 08/18/15 < 180 < 5.3 < 0.7 < 1.9 < 0.5 3.4 +/- 1.1 < 1.6 MW-CL-17S 11/03/15 < 188 MW-CL-181 02/09/15 < 154 MW-CL-181 05/27/15 < 194 MW-CL-181 08/18/15 < 198 < 5.5 < 0.6 < 1.2 < 0.5 4.2 +/- 1.1 < 1.6 MW-CL-181 11/03/15 < 186 B-1 Page 133of138

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/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-CL-18S 02/09/15 < 156 MW-CL-18S 05/27/15 < 193 MW-CL-18S 08/18/15 < 189 < 4.5 < 0.8 < 2.1 < 0.5 4.4 +/- 1.2 < 1.6 MW-CL-18S 11/03/15 < 188 MW-CL-19S 02/09/15 < 155 MW-CL-19S 05/26/15 < 194 MW-CL-19S 08/17/15 < 174 < 4.5 < 0.7 < 2.5 < 0.6 6.7 +/- 1.5 < 1.7 MW-CL-19S 11/02/15 < 190 MW-CL-2 02/09/15 < 154 MW-CL-2 05/26/15 < 195 .

MW-CL-2 08/17/15 < 180 < 5.2 < 0.6 < 1.2 < 1.1 3.9 +/- 1.1 < 1.6 MW-CL-2 11/02/15 < 188 MW-CL-20S 02/09/15 < 154 MW-CL-20S 05/26/15 < 198 MW-CL-20S 08/17/15 < 175 < 6.3 < 0.5 < 1.2 < 0.5 2.8 +/- 1.1 < 1.6 MW-CL-20S 11/02/15 < 188 MW-CL-21S 02/09/15 176 +/- 106 MW-CL-21S 05/26/15 219 +/- 130 MW-CL-21S 08/17/15 287 +/- 124 MW-CL-21S 09/29/15 < 197 < 5.3 < 0.8 < 1.8 < 0.8 < 1.5 < 1.6 MW-CL-21S 11/02/15 < 189 MW-CL-22S 02/09/15 < 179 MW-CL-22S 05/27/15 < 194 MW-CL-22S 08/18/15 < 180 MW-CL-22S 09/29/15 < 4.4 < 0.7 < 2.3 < 0.9 11.2 +/- 1.5 < 1.6 MW-CL-22S 11/03/15 < 192 B-2 Page 134of138

Table 8-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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 B-3 08/17/15 < 36 < 29 < 3 <4 < 7 <4 < 6 <4 < 6 < 3 < 4 < 29 < 8 MW-CL-1 08/17/15 < 38 < 36 < 4 < 5 < 10 <4 < 8 < 5 < 8 <4 < 4 < 28 < 13 MW-CL-121 08/17/15 < 38 < 37 < 4 <4 < 8 < 3 < 7 <4 < 7 <4 <4 < 28 < 10 MW-CL-131 08/17/15 < 41 68 +/- 37 < 4 < 4 < 10 < 3 < 8 <4 < 7 <4 <4 < 30 < 9 MW-CL-138 08/17/15 < 37 < 77 < 4 <4 < 11 <4 < 8 ~4 < 8 <4 <4 < 30 < 11 MW-CL-148 02/09/15 < 42 < 68 < 4 < 5 < 9 <4 < 9 < 5 < 8 < 4 <4 < 33 < 10 MW-CL-148 08/18/15 < 38 < 51 < 4 < 5 < 11 < 5 < 9 < 5 < 9 <4 <4 < 31 < 12 MW-CL-151 08/17/15 < 38 < 30 <4 <4 < 8 < 4 < 8 <4 < 7 < 3 < 3 < 28 < 9 MW-CL-158 09/29/15 < 73 < 148 < 6 < 8 < 16 < 8 < 11 < 5 < 11 < 6 < 8 < 34 < 14 OJ I MW-CL-168 09/29/15 < 79 < 154 < 11 < 9 < 19 < 9 < 19 < 11 < 17 < 7 < 12 < 45 < 12 w MW-CL-178 08/18/15 < 36 < 32 <4 <4 < 9 <4 < 9 < 5 < 8 < 3 <4 < 27 < 9 MW-CL-181 08/18/15 < 35 < 72 < 5 < 4 < 10 < 4 < 6 <4 < 5 < 3 <4 < 26 < 8 MW-CL-188 08/18/15 < 16 < 32 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 1 < 2 < 17 < 5 MW-CL-198 08/17/15 < 21 < 47 < 2 < 2 < 6 < 2 < 5 < 3 <4 < 2 < 2 < 24 < 7 MW-CL-2 08/17/15 < 32 < 26 < 3 <4 < 7 < 3 < 6 <4 < 7 < 3 <4 < 32 < 9 MW-CL-208 08/17/15 < 18 < 18 < 2 < 2 < 4 < 2 < 3 < 2 < 3 < 2 < 2 < 18 < 6 MW-CL-218 02/09/15 < 31 < 58 < 3 < 3 < 9 < 3 < 7 < 4 < 8 < 3 <4 < 25 < 8 MW-CL-218 05/26/15 < 15 < 30 < 1 < 2 <4 < 2 < 3 <2 < 3 < 1 < 2 < 13 <4 MW-CL-218 09/29/15 < 57 < 87 < 7 < 7 < 19 < 7 < 14 < 9 < 16 < 8 < 7 < 34 < 12 MW-CL-228 09/29/15 < 80 < 95 < 8 < 6 < 23 < 7 < 20 < 9 < 17 < 9 < 10 < 43 < 9

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RESULTS IN UNITS OF PCl/LITER +/- 2 SIGMA 1r 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 THERE WERE NO HARD TO DETECTS ANALYZED IN 2015

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SW-CL-4 11/02/15 < 191 SW-CL-5 02/09/15 < 182 SW-CL-5 05/26/15 < 194 SW-CL-5 08/17/15 < 173 SW-CL-5 11/02/15 < 191 SW-CL-6 02/09/15 < 177 SW-CL-6 05/26/15 < 194 SW-CL-6 08/17/15 < 174 SW-CL-6 11/02/15 < 188 SW-CL-7 02/09/15 < 183 SW-CL-7 05/26/15 < 195 SW-CL-7 08/17/15 < 181 SW-CL-7 11/02/15 < 194 SEWAGE TREATMENT PLANT 02/09/15 < 182 SEWAGE TREATMENT PLANT 05/26/15 < 192 SEWAGE TREATMENT PLANT 08/17/15 < 177 SEWAGE TREATMENT PLANT 11/02/15 < 193 B-5 Page 137of138

Table 8-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN suRi;:AcE WATER SAMPLES COLLECTED IN THE VICINITY OF CLINTON POWER STATION, 2015 RESULTS IN UNITS OF PCl/LITER +/- 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-14 DATE CL-SW-CL-1 08/17/15 < 21 < 18 < 2 < 2 < 5 < 2 <4 < 2 <4 <2 <2 < 22 <7 CL-SW-CL-2 08/17/15 < 17 40 + 26 < 1 < 2 <4 < 1 < 3 <2 <3 < 1 < 2 < 17 < 5 CL-SW-CL-4 08/17/15 < 16 < 12 < 1 <2 < 4 < 1 < 3 < 2 < 3 < 1 < 2 < 17 <4 CL-SW-CL-5 08/17/15 < 18 < 47 < 1 < 2 <4 <2 <, 3 <2 < 4 < 2 < 2 < 21 < 6 CL-SW-CL-6 08/17/15 < 18 65 + 31 < 2 < 2 < 5 < 2 <3 < 2 < 4 < 1 <2 < 18 < 6 CL-SW-CL-7 08/17/15 < 15 < 15 < 1 < 1 <4 < 2 < 3 < 2 < 3 < 1 < 1 < 16 < 6 SEWAGE TREATMENT PLANT 08/17/15 < 17 < 17 <2 < 2 <4 < 2 <4 < 2 < 4 < 2 <2 < 20 < 6 OJ I

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